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| {{#Wiki_filter:FENOC 5501 North State Route 2 RtEnepW ANucar Operating Company Oak Harbor Ohio 43449 Lew W eMs 419-321-7599 Chief Operating Officer Fax: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial 1-1335 December 19, 2003 Mr. James E. Dyer, Administrator United States Nuclear Regulatory Commission, Region III 801 Warrenville Road Lisle, IL 605324351 | | {{#Wiki_filter:}} |
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| ==Subject:==
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| Submittal of Revisions 7, 8, 9, and 10 of the Nuclear Operating Business Practice, Restart Readiness Review Extended Plant Outage (DBBP-VP-0002)
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| ==Dear Mr. Dyer:==
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| On September 13, 2003 (Serial 1-1327), the FirstEnergy Nuclear Operating Company (FENOC) submitted Revision 6 of the nuclear operating business practice DBBP-VP-0002, Restart Readiness Review Extended Plant Outage. This business practice provides the review process to ensure Davis-Besse's materiel condition; programs and processes; and organization, including the organization's safety culture, are ready for plant restart and safe, reliable operation.
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| This Davis-Besse Business Practice was subsequently revised to enhance and refine the Restart Readiness Review process. This letter submits Revisions 7, 8, 9, and 10 to nuclear operating business practice DBBP-VP-0002, Restart Readiness Review Extended Plant Outage, included as Enclosures 1, 2, and 3 to this letter. Revision 10, dated December 1, 2003, supercedes all previous revisions in their entirety.
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| It should be noted that FirstEnergy Nuclear Operating Company may periodically update this document in the future. If you have any questions or require further information, please contact Mr. Kevin L. Ostrowski, Manager - Regulatory Affairs, at (419) 321-8450.
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| Sincerely yours, LJS Attachment/Enclosures cc: USNRC Document Control Desk DB-1 Senior NRC/NRR Project Manager DB-I Senior NRC Resident Inspector Utility Radiological Safety Board
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| Docket Number 50-346 License Number NPF-3 Serial Number 1-1335 Attachment Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station (DBNPS) in this document. Any other actions discussed in the submittal represent intended or planned actions by the DBNPS. They are described only for information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs (419-321-8450) at the DBNPS of any questions regarding this document or associated regulatory commitments.
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| COMMITMENTS DUE DATE None N/A
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| Docket Number 50-346 License Number NPF-3 Serial Number 1-1335 Enclosure I Revision 7 of the Nuclear Operating Business Practice Restart Readiness Review Extended Plant Outage (DBBP-VP-0002)
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| (86 pages to follow)
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| NUCLEAR OPERATING BUSINESS PRACTICE NumDBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 1 of 86 RESTART READINESS REVIEW EXTENDED PLANT OUTAGE Approved: " . ' Af/'/
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| - , of ~e0 ,-
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| Vice President, Approved:
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| Chief Operatin cificer Effective Date NOV I M
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| NUCLEAR OPERATING BUSINESS PRACTICE DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 2 of 86 TABLE OF CONTENTS Page 1.0 PURPOSE ............ 3 2.0 APPLICABILITY ............ 3 3.0 RESPONSIBILITY..........................................................................................3 4.0 DETAILS ............ 4 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS ..................... 7 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX .......................................... 9 ATTACHMENT 3: RESTART READINESS REVIEW FOR PLANT SHUTDOWN .......................................... 12 ATTACHMENT 4: PLANT INSPECTION DOCUMENTATION SHEET .................. 13 ATTACHMENT 5: OPERATIONAL READINESS AFFIRMATION FORM .............. 14 ATTACHMENT 6: CORE CONFIGURATION AFFIRMATION FORM .................... 15 ATTACHMENT 7: REACTOR STARTUP AFFIRMATION FORM .......................... 16 ATTACHMENT 8 SYSTEM ENGINEER/PROGRAM OWNER READINESS AFFIRMATION FORM .......................................... 17 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE .................................. 18 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA ................. 21 ATTACHMENT 10: SAFETY CULTURE ASSESSMENT CRITERIA MATRIX ........ 59 7
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| ATTACHMENT 11: SAFETY CULTURE ATTRIBUTE ASSESSMENT MATRIX... 60
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| NUCLEAR OPERATING BUSINESS PRACTICE Number
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| ____________________________________DBBP-VP-0002 Titbe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 3 of 86 1.0 PURPOSE The purpose of this Business Practice is to provide assurance that the Davis-Besse Nuclear Power Station is ready to restart following the extended plant outage. The framework detailed here establishes a review process for areas not addressed by the Restart Test Plan and DB startup procedures to ensure that Davis-Besse's materiel condition, programs and processes, and organization, including the organization's safety culture are ready for plant restart and safe, reliable operation.
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| 2.0 APPLICABILITY This Business Practice applies to the first plant startup following the extended plant outage which began on February 16, 2002. It also applies to subsequent startups from this same outage and therefore shall be re-performed if the startup is halted resulting in an entry into a lower mode.
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| Adherence to this Business Practice is mandatory.
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| 3.0 RESPONSIBILITY The Vice President-Nuclear is responsible for initiating the Restart Readiness Review Process.
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| Each Section Manager and 0350 Restart List Responsible Individual is responsible for the accuracy and adequacy of the reviews performed, actions taken and action plans developed during the review process.
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| The Section Managers of Plant Engineering and Operations and the Director-Work Management (Maintenance) are responsible for ensuring plant walk-down inspections are conducted prior to power ascension.
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| The Manager-Operations is responsible for affirming: 1) the Operations Section has completed a review of operational readiness and is ready to support the safe and reliable startup and operation of the plant through the next operating cycle; 2) that the plant is in a condition of materiel readiness to support safe and reliable startup and operation and the operating crews are prepared and ready to startup and operate the plant in a safe and reliable manner through the next operating cycle.
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| The Supervisor-DB Reactor Engineering is responsible for 1) following movement of fuel in the reactor core, changes to reactivity control components in the reactor core and/or changes to nuclear instrumentation in the reactor core, verifying that the reactor core is configured to support safe and reliable operation through the cycle.
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| This affirmation is required prior to installation of the reactor head; 2) prior to reactor startup, verifying that the required conditions exist to support a safe startup and power ascension.
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| NUCLEAR OPERATING BUSINESS PRACTICE Num DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 4 of 86 Each Director is responsible for the final review of the assessment and action plans developed during the review process by the sections in his department.
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| The Chief Operating Officer is responsible for final approval prior to plant restart.
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| 4.0 DETAILS
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| : 1. The review process shall be initiated early enough to ensure it is completed prior to entry into Modes 6, 4 and 2. The review shall be completed by the milestone date as determined by the responsible Shift Outage Director. All Sections and 0350 Checklist Responsible Individuals, shall submit restart readiness reviews by the milestone dates; not all items have to be complete, provided bullet (4) in Step 3 is appropriately addressed.
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| : 2. The process consists of the review and assessment of the specified Restart Readiness Review Indicators. The matrix on Attachment 2 designates the minimum indicators from Attachment I that are applicable to each Section and/or 0350 Checklist Item. Each Section and 0350 Checklist Responsible Individual, shall address applicable indicators and should participate in the review and assessment of any indicator for which meaningful input can be provided.
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| : 3. The methodology for the review process consists of the following steps:
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| * Monitor plant system/component work activity progress during the outage
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| * Monitor emergent work/issues during the outage for shutdown concerns
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| * Monitor personnel and administrative issues during the outage for restart concerns
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| * Assess Restart Readiness Review Indicators as identified on Attachment 1, as applicable per Attachment 2.
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| * Assess Safety Culture as identified on Attachment 9, Page 18
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| * Identify items to be complete prior to the designated Mode (6, 4 or 2) that have not been completed as of the Shift Outage Director milestone date.
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| Ensure a reference is associated with each incomplete item that addresses completion of that item before needed in that mode.
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| : 4. Results of the individual indicator assessments, including the status of action plans to support plant restart, will be indicated on Attachment 1, and acknowledged by the signature of the Section Manager or 0350 Checklist Responsible Individual. Indicator assessments should be marked as Final (all conditions are acceptable to support plant restart) or Preliminary (one or more indicators are not currently complete or acceptable and action plans will support plant restart when complete). Details on incomplete items and the status of action plans to eliminate them shall be attached.
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| : 5. The signed original Restart Readiness Review Indicators (Attachment 1) should be provided to the Restart Action Process Administrator at the end of the Readiness meetings for inclusion in the Mode Readiness notebook
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| : 6. Restart Readiness Review Indicators shall be reviewed by the Senior Leadership Team and approved by the Vice President-Nuclear or Chief Operating Officer, as provided on Attachment 3.
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| : 7. Completed Attachments 1 and 3 shall be included with the documentation package assembled in accordance with this Business Practice.
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| : 8. Walk down inspections shall be completed prior to power ascension as described in this document and in accordance with EN-DP-01 503, System Walkdowns or Plant Engineering Policy PE-02, System Walkdown Checklist. Results of walkdown inspections shall be documented in Attachment 4 and submitted to the on-shift Engineering Manager.
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| : 9. The Shift Manager of each crew should:
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| : a. Conduct reasonable and appropriate activities to accomplish the objective of attaining, demonstrating and affirming operational readiness. The Shift Manager should consider the following to support the affirmation of operating crew readiness:
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| -adequacy of staffing levels, personnel experience and qualification levels.
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| -assure Operations personnel believe the Station can be operated safely by eliciting any outstanding safety concerns from shift personnel and ensuring that the concerns are resolved.
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| -completion of appropriate personnel refresher training of shift personnel, including training on plant, procedures and process changes.
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| -completion of training of shift personnel on the startup and power ascension plan. This training shall include discussion on the expected behavior and characteristics of the core for this startup.
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| : b. Affirm to the best of their knowledge and judgment that the plant is in a condition of materiel readiness to support safe and reliable startup and operation. The Shift Manager should consider the following:
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| -adequacy of the materiel condition of the plant, including the current status of operator work-arounds, to support safe and reliable restart and operation during the next operating cycle.
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| -all outage-related temporary fire suppression systems removed and fire protection requirements or commitments ready to support startup.
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 6 of 86
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| -temporary modifications, temporary power feeds, removed/MCCs restored, installed temporary power feeds, if applicable, reviewed to ensure they will not affect safety or operations.
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| : c. Complete Attachment 5.
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| : 10. The Supervisor-DB Reactor Engineering shall, following movement of fuel, changes to reactivity control components and/or changes to nuclear instrumentation in the reactor core, verify that the reactor core is configured to support safe and reliable operation through the cycle. This affirmation is required prior to installation of the reactor head. Attachment 6, Core Configuration Affirmation Form, details the required review areas and documents the affirmation.
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| : 11. The Supervisor-DB Reactor Engineering, shall, prior to a reactor startup, verify that the required conditions exist to support a safe startup and power ascension.
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| Attachment 7, Reactor Startup Affirmation Form, details the required review areas and documents that affirmation.
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| : 12. Each System Engineer and 0350 Program Owner shall complete Attachment 8, System Engineer/Program Owner Readiness Affirmation Form. The System Engineer forms shall be part of the Plant Engineering Manager's presentation for restart readiness. The 0350 Program Owners form will be used as part of their readiness discussion. Selected systems (System Engineers) will be identified by the Manager-Operations, Manager-Plant Engineering and Plant Manager to be discussed during the Restart Readiness Review Meetings.
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED iPLANT OUTAGE 07 Page 7 of 86 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS Page 1 of 2 Plant Section or 0350 Checklist Item Acceptable Mode to Support Restart?
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| Yes/No/NA 1 All assigned outage work activities are complete to support plant restart and operations. This includes a reconfirmation that previous dispositions of nonconforming conditions or Preventive Maintenance deferrals continue to provide a justification for continued operation. (Attachment 2, Column a) 2 Outstanding Operability Evaluations, CR corrective actions and new CRs generated during the shutdown have been evaluated for operability concerns are either closed or determined to have no impact on operability. (Attachment 2, Column b) 3 Regulatory and internal commitments have been evaluated for operability concerns or restart restraints and are either closed or determined to have no impact on operability. (Attachment 2, Column c) 4 Housekeeping walkdowns utilizing the guidelines of NG-DB-00215, Material Readiness and Housekeeping Inspection Program are complete. (Attachment 2, Column d) 5 The Power Ascension Schedule has been reviewed for accuracy and adequacy ensuring: (Attachment 2, Column e)
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| * Post maintenance retest and special testing are identified and scheduled correctly with instructions in place.
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| * Planned walkdowns are scheduled appropriately 6 Personnel, materials and special test equipment necessary to support power ascension retest and walkdown activities have been identified and availability is ensured during power ascension. (Attachment 2, Column f) 7 Contingency plans are established for immediate response to plan and repair steam leaks or high-risk test failures. (Attachment 2, Column g) 8 Standing orders have been reviewed for continued applicability and system status sheets completed as required by DB-OP-0691 1, Pre-Startup Checklist. (Attachment 2, Column h) 9 System walkdowns have been performed by Plant Engineering and Maintenance, as directed by Operations, to ensure system readiness for restart.
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| 10 Operating Experience reports have been reviewed to ensure no potential operability concerns.
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| 11 Procedure alterations/PCRs are ready for mode change or restart.
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| 12 Work around and burdens identified prior to or during shutdown and not corrected have been confirmed acceptable. (Attachment 2, Column i)
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| NUCLEAR OPERATING BUSINESS PRACTICE Number
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| _____________________________________DBBP-VP-0002 itle: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 8 of 86 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS (Continued)
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| Page 2 of 2 Plant Section or 0350 Checklist Item_ Acceptable to Support Mode Restart?
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| Yes/No/NA 13 All Management and Human Performance Improvement Plan items required for restart are complete. (Attachment 2, Column j) 14 All 0350 Discovery Action Plan milestones identified as required for restart are complete. (Attachment 2, Column k) 15 All 0350 Implementation Action Plan milestones identified as required for restart are complete. (Attachment 2, Column I) 16 All Section Corrective Action Program Improvement Plan activities required for restart have been validated as ready to support restart. (Attachment 2, Column ii) 17 All Condition Reports and corrective actions, work orders, modifications (including EWRs and ECRs) categorized as 0350 are completed. (Attachment 2, Columns m, n, o) 18 All Condition Reports and corrective actions, work orders, and modifications (including EWRs and ECRs) designated as required for restart by the Restart Station Review Board are complete. (Attachment 2, Columns q, r, s) 19 Any required for restart Condition Report or corrective action, work order or modification (including EWRs and ECRs), which cannot be completed prior to restart, has a written exemption from the RSRB. (Attachment 2, Column u) 20 All pending allegations have been reviewed and determined not to affect the restart of the plant. (Attachment 2, Column v) 21 Integrated Restart Report per NG-VP-001 00 signed by the SLT. (Attachment 2, 7 Column w)
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| Check one Preliminary: I have reviewed the assessment of the Restart Readiness Review Indicators as indicated above and confirm that the attached plans will support plant restart when complete.
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| Final: I have reviewed the assessment of the Restart Readiness Review Indicators as indicated above and concur that the current conditions support plant restart.
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| Section Manager or 0350 Checklist Individual (
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| (Please Print Your Name)
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| Signature: Date.
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| Section Manager or 0350 Checklist Individual ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision. Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 9 of 86 Page 1 of 3 a) C 0-C 0 .be Ca 0 C D C:
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| co E ~ ~ 2 CE wE L
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| E ~ ~ .e 0 a)
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| !~~~~~~~~~~~~b °n 0 M't ~~
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| 00U a) 0 CD 0 <r > <
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| 2____
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| Plant I Operations X X xX X X X X X X X RP X X X X X X X X X Chemistry X X X X X X X X Outage Management X X X X X X X and Work Control II FIN X X X X X X Mechanical X X X X X X X E&C X X XX X X Maint. Serv. X X X X X X Training X X X X 7
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| Safety X X X _ X Engineering Plant Engineering X X X X X X X X X Design Engineering X X X X X X Project Management X X X X X X RRT XX X X Reactor Engineering X X X X X X X Support Services Regulatory Affairs X X X X X X X X 7 (includes Emer. Prep.) _
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| Quality Services X x - X X Security X X X 7
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| Other Sections QAIQC X X X X _ X Supply Chain = X X = X X Client Services X X Business Services X X Human Resources X _ _ X X
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| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page IO of 86 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 2 of 3 0350 CHECKLIST ITEM RESTART READINESS REVIEW INDICATOR MATRIX o
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| B o -o C
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| ca r E9 ~0 0 owM
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| > E0 ~~ 0 'a ° ~s ~ jn oes tn E r L LOL LOW 0 LOCD0 .0) CV....
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| 0350 Checklist Item____
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| : 1. Adequacy of Root Cause Determinations- X X X X S. Loehlein, M. Roder, D. Gudger, J. Powers, D. Eshelman, F. von Ahn, L. Myers*
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| : 2. Adequacy of Safety Significant Structures, X X X X X Systems and Components-D. Baker, A.
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| Stallard, T. Chambers, R. Hovland, J.
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| O'Neill*
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| : 3. Adequacy of Safety Significant Programs--A. X X X McAllister, L. Dohrmann, S. Loehlein, C.
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| Daft, J. Grabnar, R.Farrell, D. Schreiner, R.
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| Perry, K. Ostrowski* 7
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| : 4. Adequacy of Organizational Effectiveness X X X X X and Human Performance- M. Bezilla, J.
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| Powers*
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| : 5. Readiness for Restart-C. Price, F. VonAhn, X X R. Hovland, R. Schrauder, A. Stallard, J.
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| Hirsch*
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| : 6. Licensing Issue Resolution-J. Powers, K. X X Ostrowski*
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| : 7. Confirmatory Action Letter Resolution--L. X Myers, C. Price K. Ostrowski* III _ I
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| * Or an approved designated alternate ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX
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| NUCLEAR OPERATING BUSINESS PRACTICE Number-.
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| _____________________________________DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 11 of 86 Page 3 of 3 REQUIRED FOR RESTART READINESS REVIEW INDICATOR MATRIX 10beco 0 = C JO E E S E z X E ' X 0 i a). , 0 Restart Station Review X X X X Quality Services ____X Employee Concerns X Program ___
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| Station Review Board X (Plant Operating Review Committee)__ _ _ __ _ _ _ _ _ _ _ _ _
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| Company Nuclear Review X Board _ _ _ _ _ __ _ _
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| Restart Overview Panel __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ X
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED IPLANT OUTAGE 1 07 Page 12 of 86 ATTACHMENT 3: RESTART READINESS REVIEW FOR PLANT STARTUP Restart/Mode Change Recommended By:
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| Mode_
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| Plant Manager-Davis-Besse Nuclear Power Station Date Director-Davis-Besse Nuclear Engineering Date Director-Davis-Besse Work Management Date Director-Davis-Besse Support Services Date Director-Davis-Besse Restart Date 7
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| RESTART IMODE CHANGE APPROVAL:
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| Vice President-Nuclear Date Chief Operating Officer Date
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| NUCLEAR OPERATING BUSINESS PRACTICE Number.
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| DBBP-VP-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 13 of 86 ATTACHMENT 4: PLANT INSPECTIONIWALKDOWN DOCUMENTATION SHEET Page 1 of 1 Mode_
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| ASSET LABEL:
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| Or AREA INSPECTED:
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| NOUN NAME:
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| LOCATION:
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| DESCRIPTION:
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| MAINTENANCE TAG/WORK ORDER #:
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| CONDITION REPORT INITIATED (#)-
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| MODE RESTRAINT: (es __No SUBMITTED BY: DATE/TIME I (please print your name)
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| SIGNATURE:
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| ATTACHMENT 5: OPERATIONAL READINESS AFFIRMATION FORM
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 14 of 86 Shift Designator:
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| Shift Manager:
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| (Please Print)
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| Mode_
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| Review Summary:
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| The Shift Manager should initial each item below to affirm that he/she and the operating crew have completed the required actions:
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| Shift staffing levels, including personnel experience and qualification levels, are adequate.
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| Operations personnel believe the station can be operated safely. All safety concerns have been identified and addressed.
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| Appropriate refresher training of shift personnel, including training on plant, procedure and process changes, has been completed.
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| Appropriate training of shift personnel on the startup and power ascension plan, have been completed, including discussions on core behavior and characteristics for this startup.
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| The materiel condition of the plant, including the current status of operator work-arounds, is adequate to support safe and reliable restart and operation.
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| Affirmation:
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| Based upon an evaluation of the considerations set forth in Details, 4.0, and to the best of my knowledge and judgment, the plant is in a condition of materiel readiness to support the safe and reliable startup and power operation through the next operating cycle and the operating crew is ready to startup and operate the plant in a safe and reliable manner.
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| Shift Manager:
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| Print/Signature/Date Reviews and Approvals:
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| Manager-Operations:
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| Print/Signature/Date Remarks: (Attach a continuation sheet if applicable)
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| NUCLEAR OPERATING BUSINESS PRACTICE Number DBB P-VP-0002
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| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 07 Page 15 of 86 ATTACHMENT 6: CORE CONFIGURATION AFFIRMATION FORM Mode_
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| Review Summary:
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| The Supervisor-DB Reactor Engineering, should initial each item below to affirm that the required conditions exist following movement of fuel in the reactor core, changes to reactivity control components and/or changes to nuclear instrumentation in the reactor core. This affirmation is required prior to installation of the reactor head.
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| All new fuel assemblies loaded into the reactor core were inspected, as required, to ensure that the manufacturing and design specifications were met.
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| All irradiated fuel assemblies present in the reactor core were inspected, as required, and dispositioned as acceptable for operation through the cycle.
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| No fuel assemblies in the reactor core are known leaking assemblies.
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| A 10CFR50.59 Reload Safety Evaluation governing reactor core operation has been approved by the Plant Operating Review Committee (PORC)
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| The reactor core loading has been verified.
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| All reactivity control components in the reactor core will meet their design functions.
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| All nuclear instrumentation in the reactor core will meet their design functions.
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| Affirmation:
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| Based on my knowledge and judgment, the required conditions exist and the reactor core is configured to support safe and reliable operation through the cycle.
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| Supervisor-DB Reactor Engineering Print/Signature/Date Remarks: (Attach a continuation sheet if appropriate)
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| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tifie: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 16 of 86 ATTACHMENT 7: REACTOR STARTUP AFFIRMATION FORM Mode_
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| Review Summary:
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| The Supervisor-DB Reactor Engineering should initial each item below to affirm that the required conditions exist prior to reactor startup.
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| Estimated Critical Conditions have been prepared and independently verified.
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| Preparations are complete for any necessary Low Power Physics Testing (i.e. equipment, procedures, calculations, training)
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| Personnel are available, as required, to support reactor startup and power ascension to 100%.
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| Required training has been completed for Nuclear Fuels personnel.
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| Reactivity plans are available, as required, to support reactor startup and power ascension to 100%. These plans include expectations for reactor behavior with emphasis on any behavior that is different from recent plant operation.
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| The Core Monitoring System is operable.
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| All reactivity control systems will meet their design functions.
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| Sufficient nuclear instrumentation is available to safely startup and operate the reactor core.
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| There are no outstanding reactivity management issues impacting the safe operation of the reactor core.
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| Affirmation:
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| Based on my knowledge andjudgment, the required conditions exist and the reactor core is ready to support a safe startup and power ascension.
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| Supervisor-DB Reactor Engineering Print/Signature/Date Remarks: (Attach a continuation sheet if appropriate)
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| ____ ____ ____ ____ ____D B B P-V P-0002
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| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 17 of 86 ATTACHMENT 8: SYSTEM ENGINEER/PROGRAM OWNER READINESS AFFIRMATION FORM Mode_
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| : 1. Name of System/Program:
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| : 2. The status of the system/program is (For systems, a brief description of the physical status of the system including System Health status and Maintenance Rule status. For programs, a brief status of the program):
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| : 3. System/Program is ready for Mode : Yes or No
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| : 4. The system/program is ready for Mode because: (if not ready, skip to #5)
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| : 5. The system/program is not ready for Mode because:
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| and the following actions are in place to address these issues:
| |
| The system/program will be ready for Mode by: (Date)
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| : 6. Items in abnormal status or configuration (workarounds, temporary modifications, Control Room deficiencies) identified and not corrected have been reviewed and determined to be acceptable: Yes_ or No_ (Attach a list of the above items)
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| : 7. Housekeeping issues associated with this system/program have been addressed for Mode : Yes_ or No (Attach a list of those not resolved)
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| : 8. I have the following concerns about my system and its readiness for Mode :
| |
| Briefly identify concerns. (The Restart Readiness Review process will not resolve these concerns at the meeting. They should be scheduled for presentation to the Plant Support Center if there is a concern relative to this mode change.)
| |
| : 9. Open CRs, CAs, Work Orders or Engineering modifications required for Mode (Attach a list).
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| Name: Extension:
| |
| (Please Print)
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| Signature: Date:-
| |
| Date:____________
| |
| Signature:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 18 of 86 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 1 of 3 ASSESSMENT OF SAFETY CULTURE Assessment Summary:
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| Improving safety culture isa long-term activity that is monitored by Davis-Besse senior management. For Restart Readiness, it is important to show an improving safety culture with no critical areas of weakness that management evaluates as a restart concern. The individual criteria that make up the Commitment Areas may be green, white, yellow or red. Some of the Commitment Areas may be white (Policy or Corporate Commitment Area, Plant Management Commitment Area or Individual Commitment Area) however restart will not be approved if any of the three are red, or yellow without restart corrective actions being completed.
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| Remedial actions will be taken for any red criteria. Condition Reports will be written for all red and yellow criteria at the site and/or section level, with corrective actions to identify an existing or new plan for improvement. Corrective Actions may take credit for ongoing activities. Red criteria corrective actions will be formally presented to the Senior Leadership Team. If a Condition Report iswritten at the site level for a red or yellow Commitment Area or criteria, it will encompass any red or yellow section Commitment Area or criteria and that section need not write a 7 separate Condition Report. Ifthere is no site wide red or yellow Commitment Area or criteria then the Section Manager will write a Condition Report for the red or yellow Commitment Area or criteria.
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| The threshold for rating the attributes that comprise each criteria are provided in Appendix A. These thresholds are guidelines. Management may consider other factors and adjust the ratings accordingly. Management judgment is a key factor that cannot be removed or quantified. The purpose of the collegial group review isto challenge, seek alternative input, and facilitate dialogue and to determine final criteria and Commitment color rating If other factors are considered, they shall be documented in an attachment to the Rating sheet. The ratings are based on convergent assessment such as: performance indicators, management observations, demonstrated performance during critical plant conditions surveys and interviews, training and feedback from independent safety culture reviews and Nuclear Quality Assurance Assessments. Each criterion will be assessed using information from the attribute reviews performed. An overall assessment of each attribute and criterion will be performed and documented explaining any that are rated as red or yellow and identifying the corrective actions needed prior to restart.
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| The ratings for an individual attribute will reflect recent activities or the most recent assessment data. If no applicable activities or assessments have been conducted within the past 12 months (i.e., there is no information applicable to the review period), the attribute shall be marked NA", (Not Applicable). If both objective and subjective data are available, differences in data will be evaluated and decisions on use of data made.
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| Safety Culture Commitment Area/Criteria Ratings:
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| Green: all major criteria/attributes are acceptable with a few minor criteria deviations White: all major criteria/attributes are acceptable with a few criteria requiring management attention 7 Yellow: all major criteria/attributes are acceptable with several criteria requiring prompt management action Red: several major criteria/attributes do not meet acceptable standards and require immediate management action
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 19 of 86 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 2 of 3 Each Section Manager will provide a Rating sheet (ATTACHMENT 9, Page -20,) with the Final Restart Readiness Criteria. For any individual attribute where only site-wide numbers are available (e.g. 4Cs surveys, ECP etc.), or for any individual attribute not applicable to a section (e.g. operator work-arounds for other than Operations), the Manager will NA that attribute on his backup sheets and that attribute will not be used as part of the site-wide tally for the criteria. For any attribute where "surveys and/or interviews' are used as the basis for the rating, these surveys must be written but may be anonymous. Interview results will also be documented as to results although they may also be anonymous. The results for surveys or interviews will be maintained until after restart.
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| Documentation for Attachment 9 may be in the form of a tally for these survey or interview results.
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| At the final Restart Readiness Review meeting for any mode, a site-wide Rating sheet will be prepared by the management team using the individual section ratings as a guideline. The final Rating sheet will be signed by the Vice President-Nuclear and maintained with the other Restart Readiness documentation, including Attachment 11.
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| Preliminarily, determination of the Commitment Area/criteria color will be based on an average of the ratings of the associated criteria/attributes. Considerations include:
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| Greater than one red attribute or criteria means the criteria or Commitment Area can be no better than yellow. If more than two or more than 113 (whichever is 7 greater) of the attributes or criteria are red, the indicator or Commitment Area shall be red.
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| For the overall plant ratings for Commitment Areas/criteria, management will consider whether the problems taken collectively indicate a more significant concern than indicated by the averages. For example, one section may perform more activities related to safety with respect to a certain criteria than other sections, and management may adjust the color to give greater weight to that section in determining the final color rating. Similarly, if percentages or averages alone indicate a positive rating but there were several associated safety-significant events or conditions, management may provide a more negative color rating to reflect those events or conditions.
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| If such an adjustment is made, it shall be documented. Generally, if all sections have similar rating, the overall rating for the plant will be the same as the ratings for the individual sections. During group review, senior management will seek to verify that the entire Restart Readiness Review team not only concurs, but also aligns behind the assessment.
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| At the completion of the Safety Culture Assessment, an evaluation of the significance of the overall assessment ratings for criteria to focus on the process and organization will be completed using Attachment 10 at the end of the document. A final report will then be prepared which documents how each Commitment Area, criteria and attribute was assessed and its final color rating. The report will also document any red or yellow area, criteria or attribute, corrective actions needed for restart and explain why restart isacceptable with the current condition.
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| Attachments 10 and II will be included as part of that report.
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| NUCLEAR OPERATING BUSINESS PRP-ACTICE Number
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| _____________________________________DBBP-VP-0002 Titfe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 20 of 86 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 3 of 3 Rating Safety Culture Mode_
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| item Color
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| : 1. Policy or Corporate Commitment Area
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| : a. Policies on Safety Culture and Safety Conscious Work Environment clearly state that safety is a core value and are understood by the organization
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| : b. Management values are clearly reflected in the Business Plan and are understood by the organization
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| : c. Resources are available or can be obtained to ensure safe, reliable operations
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| : d. Self-Assessment is a tool used to monitor, assess and improve our performance
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| : e. Independent Oversight is a tool used to validate acceptable performance and identify areas for improvement or corrective action
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| : 2. Plant Management Commitment Area
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| : a. There is a visible commitment to safety: nuclear, industrial, radiological and environmental
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| : b. Goals and roles are clear and teamwork is reinforced
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| : c. Ownership and accountability is evident
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| : d. Training and Qualification are valued
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| : e. Commitment to continuous improvement is evident
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| : f. Cross-functional work management and communication
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| : g. Creating an environment of engagement and commitment
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| : 3. Individual Commitment Area
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| : a. Drive for excellence-nuclear assets of people and plant are continuously improved to enhance margins of safety
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| : b. Questioning attitude-challenges are welcomed
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| : c. Rigorous work control and prudent approach-performing activities in a quality manner is the standard
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| : d. Open communications-associates are comfortable in voicing opinions, issues and concerns
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| : e. Nuclear Professionalism-persistence and urgency in identification and resolution of problems is prevalent I have reviewed the Rating of Safety Culture as indicated above and concur that the current conditions support readiness for mode change.
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| Section Manager (Please Print Your Name)
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| Signature: Date_ _
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| Section Manager Adjustments to ratings from the standard criteria should be documented and attached to this page.
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 21 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 1 of 39
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| : 1. POLICY COMMITMENT AREA la. CRITERIA RELATED TO STATEMENT OF SAFETY POLICY Policies on Safety Culture and Safety Conscious Work Environment clearly state that safety is a core value and are understood by the organization ATTRIBUTE RED YELLOW WHITE GREEN Policy statement Policy statement is Policy statement is Policy statement is Policy statement is on Safety Culture* issued but it is not issued but only issued and is issued and is reinforced by occasionally reinforced frequently reinforced continuously reinforced FENOC by FENOC by FENOC by FENOC management management. management. management. 7 Policy statement Policy statement is Policy statement is Policy statement is Policy statement is on Safety issued but it is not issued but only issued and is issued and it is a strong Conscious Work reinforced by occasionally reinforced frequently reinforced statement of safety Environment FENOC by FENOC by FENOC conscious work (SCWE)* management. management. management. environment and often reinforced by FENOC management Making employees Policy statements Policy statements Policy statements are Policy statements are aware of policy simply issued as distributed separately communicated by at communicated to statements* part of FENOC to employees in least two employees and (Explain why white Business Plan. memo. means.(e.g., hard emphasized regularly in is acceptable ff there copy distribution, meetings and face to is no face to face newsletters, group face communication.
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| communication) meetings, training, stand down).
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| Employee Surveys/interviews Surveys/interviews Surveys/interviews Surveys/interviews understanding of indicate less than indicate that 70-80% of indicate that 80-90% indicate that more than policies' 70% of employees the employees of employees 90% of employees understand the understand the understand the understand the policies policies. policies and consider policies and consider and consider safety a safety a FE value. safety a FE value. FE value and the normal way to do business.
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| Worker Surveys/interviews Surveys/interviews Surveys/interviews Surveys/interviews understanding of indicate that less indicate that between indicate that between indicate that more than responsibility to than 85% of workers 85-90% of workers 90-95% of workers 95% of workers raise safety understand their understand their understand their understand their concerns' responsibility to responsibility to raise responsibility to raise responsibility to raise raise nuclear safety nuclear safety or nuclear safety or nuclear safety or quality or quality concerns. quality concerns. quality concerns. concerns.
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| * Site wide assessment only. Data provided from Edventures survey results
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| ** Site wide assessment only. Data provided from Edventures survey results and 4Cs.
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| NUCLEAR OPERATING BUSINESS PRACTICE Number: D P-0002
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| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 07 Page 22 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 2 of 39
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| : 1. POLICY COMMITMENT AREA lb. CRITERIA RELATED TO MANAGEMENT VALUES Management values are clearly reflected in the Business Plan and are understood by the organization ATTRIBUTE RED YELLOW WHITE GREEN Corporate vafues* There is no There isa There is a corporate There is a corporate corporate level corporate level level statement of level statement of statement of statement of commitment to commitment to safety.
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| safety values. commitment to safety. FirstEnergy FirstEnergy FirstEnergy safety. management meets management meets management FirstEnergy occasionally with frequently with plant does not management plant personnel to personnel to express its express its meets express its safety safety values.
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| safety values to infrequently with values.
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| plant personnel. plant personnel to express its safety values.
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| Statement of There is no The statement of The statement of The statement of mission, vision, statement of Mission, Vision, Mission, Vision, and Mission, Vision, and and values** Mission, Vision, and Values Values places greater Values emphasizes and Values and places weight on weight on safety than safety first, then allows employees safety and often on production/profits consideration of believe focus is employees and most employees production and profits on production believe the agree that the and over 90% of and profits. overriding focus overriding priority is employees agree based is safety on safety on surveys.
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| FENOC Business Business Plan Business Plan Business Plan Business Plan contains Plan* contains no contains few contains Strategic Strategic Objective Strategic Strategic Objective Measures Measures on safety Objective Objective on safety with and all are being fully Measures on Measures on implementation plans. implemented.
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| safety. safety but no implementation plans 7
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| *Site wide assessment only. Data provided by Senior Management
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| ** Site wide assessment only. Data provided from Edventures survey results
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| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
| |
| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 23 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 3 of 39
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| : 1. POLICY COMMITMENT AREA 1c. CRITERIA RELATED TO RESOURCES Resources are available or can be obtained to ensure safe, reliable operations ATTRIBUTE RED YELLOW WHITE GREEN Adequacy of More than five More than three Three or less All management management supervisor or above supervisor or supervisor or above positions are filled with resources* positions are not above positions positions are not filled ANSI qualified FENOC filled with ANSI are not filled with with ANSI qualified individuals.
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| qualified FENOC ANSI qualified FENOC individuals.
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| individuals. FENOC individuals.
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| Adequacy of More than four Three or four One or two sections Each section has a full personnel sections do not have sections do not do not have sufficient complement of resources*# sufficient personnel have sufficient personnel to perform personnel (minus to perform their personnel to their assigned normal attrition) to assigned perform their responsibilities perform its assigned responsibilities assigned without contractor responsibilities.
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| without contractor responsibilities support support without contractor 7 support Adequacy of Risk significant The majority of All risk significant Sufficient funding exists funding' activities, to improve identified risk identified to perform more than nuclear safety, as significant improvements to just risk significant defined by the improvements to nuclear safety, as improvements, as Senior Leadership nuclear safety, as identified by the PRC identified by the PRC in Team and Project identified by the for the plant, plant, programs and Review Committee PRC for the plant, programs, or other other activities to (PRC) are not being programs, or activities, are funded improve nuclear safety.
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| funded in a timely other activities, in a timely manner.
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| manner and funding are funded in a was requested and timely manner.
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| rejected by FENOC Executive Management.
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| * Site wide assessment only. Data provided by Human Resources
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| *#Significance evaluation regarding resources will be discussed depending on contractor support by section. Color identified for site after section discussion
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| **Site wide assessment only. Data provided by the chairman of the PRC
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| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| ____________________________________DBBP-VP-0002
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| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 24 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 4 of 39
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| : 1. POLICY COMMITMENT AREA 1c. CRITERIA RELATED TO RESOURCES (continued)
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| Resources are available or can be obtained to ensure safe, reliable operations Adequacy of tools, More than 25 % Between 20- Between 10-20% of Less than 10% of material and of scheduled 25% of scheduled scheduled tasks scheduled tasks PMs, equipment to tasks (PMs, tasks (PMs, Work (PMs, Work Orders, Work Orders, ECRs complete site Work Orders, Orders, ECRs ECRs and projects) and projects) are not 7 tasks* ECRs and and projects) are are not being being completed by the projects) are not not being completed by the site site in a timely manner being completed completed by the in a timely manner due to lack of tools, by the site in a site in a timely due to lack of tools, material or equipment.
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| timely manner manner due to material or due to lack of lack of tools, equipment.
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| tools, material or material or equipment. equipment.
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| Adequacy of tools, More than 25% Between 20-25% Between 10-20% of Less than 10% of key material and of key scheduled of key scheduled key scheduled tasks scheduled tasks are not equipment to tasks are not tasks are not are not being being completed by the complete Section being completed being completed completed by the section in a timely tasks by the section in by the section in section in a timely manner due to lack of a timely manner a timely manner manner due to lack of tools, material or due to lack of due to lack of tools, material or equipment.
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| tools, material or tools, material or equipment.
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| equipment. equipment.
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| *Site wide assessment only. Data provided by Outage Management and Work Control
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
| |
| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 25 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 5 of 39
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| : 1. POLICY COMMITMENT AREA 1d. CRITERIA RELATED TO SELF-ASSESSMENT Self-Assessment is a toot used to monitor, assess and improe our performance ATTRIBUTE RED YELLOW WHITE GREEN Use of Nuclear Less than 70% of Between 70-80% of Between 80-90% of More than 90% of the Quality the sections have the sections have the sections have sections have used Assurance to used NQA input used NQA input to used NQA input to NQA to supplement the supplement the to supplement the supplement the supplement the self- self-assessment 7 self- self-assessment self-assessment assessment process process as defined in assessment process as defined process as defined as defined in NOBP- NOBP-LP-2004 process in NOBP-LP- 2004 in NOBP-LP-2004 LP-2004 Self- Less than 60% of Between 60-75% of Between 75-90% of More than 90% of assessments in sections (< 14) sections (15-17) sections (17-20) sections (> have accordance have scheduled have scheduled have scheduled any scheduled any self-with NOBP-LP- any self- any self- self-assessments for assessments for 1St &
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| 2004, FENOC assessments for assessments for 1 5t st 1 & 2 nd quarter 2 nd quarter 2004.
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| Ongoing Seff- Is & 2nd quarter &2nd quarter 2004. 2004.
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| Assessment 2004.
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| Guideline*
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| Section Performance Section performance Section performance Section performance Performance indicators related to indicators exist for indicators exist for indicators exist and are Indicators safety and quality important activities important activities appropriate and are being exist for the section affecting quality and affecting quality and regularly updated for safety but less than safety and 75-89% of important activities 75% of goals are met goals are met affecting safety and quality, with more than 90% of goals met.
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| Personnel The performance The performance The performance The performance Performance appraisal program appraisal program appraisal program appraisal program Appraisals** does not include includes includes assessments includes assessments of assessments of assessments of of safety or quality of safety and quality of safety or quality of safety or quality of performance but some performance and the performance. performance but most appraisals have not appraisals are being employee appraisals been performed in performed in timely have not been timely manner and manner and all employees performed. some employees do have a current appraisal.
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| not have a current appraisal.
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| *Site wide assessment only. Data provided by Quality Services "Site wide assessment only. Data provided by Human Resources 17
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| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tite Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 26 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 6 of 39
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| : 1. POLICY COMMITMENT AREA le. CRITERIA RELATED TO INDEPENDENT OVERSIGHT Oversight is a tool used to show acceptable performance and identify areas for improvement and corrective actions.
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| ATTRIBUTE RED YELLOW WHITE GREEN Nuclear The Nuclear The Nuclear The Nuclear The Nuclear Committee Committee of Committee of the Committee Committee has safety has safety performance Board of Board has little occasionally discusses performance as a part as a part of the agenda Directors* focus on safety safety performance as of the agenda every every meeting and performance in the atopic in the agenda. meeting requests additional agenda. presentations relative to specific issues to monitor performance Company The CNRB has a The CNRB agenda The CNRB agenda The CNRB agenda has Nuclear Review safety has a safety has a safety a safety discussion Board (CNRB)+ performance discussion and discussion at every every meeting and is assessment monitors safety meeting and reviews proactive in providing 7 discussion on the performance presentations on safety focus actions for agenda. safety focus issues FENOC Nuclear Quality NQA is not Some NQA audits or NQA audits or NQA is regularly Assurance performing audits assessments were assessments were performing audits and (NQA)** or assessments of performed when performed when assessments of important safety required and a number required, for important important safety activities and not of areas of concern safety activities and activities and identifying finding areas of were identified for some Significant key issues for concern causing important safety Conditions Adverse to improvement that are Significant activities causing Quality were noted below the Significant Conditions Significant Conditions Condition Adverse to Adverse to Quality Adverse to Quality Quality threshold.
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| Learning from Personnel in the Personnel inthe Personnel in the Personnel in the section the experience section do not section seldom section occasionally routinely participate in of the industry participate in participate in industry participate in industry industry committees, industry committees, visit other committees, visit other visit other sites or host committees, visit sites or host personnel sites or host personnel personnel from other other sites or host from other sites from other sites sites personnel from other sites
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| *Site wide assessment only. Data provided by Senior Management
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| +Site wide assessment only. Data provided by NQA Manager or VP Oversight
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| **This item is assessed by NQA only.
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| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number NUCLEAR_____________3_____i_________________E DBBP-VP-0002 TiUe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 27 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 7 of 39
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| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Management There isa There is a management There isa There is a management observations management observation program management observation program performed as observation program and 65-75% of observation program and more than 90% are scheduled with and less than 65% management and 76-90% are performed as proper of the observations observations are performed as scheduled and less coaching* are performed as performed as scheduled and less than 5% rated as scheduled and scheduled and greater than 10% rated as overall unsat.
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| >90% indicate no than 10% were rated overall unsat.
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| coaching required. overall unsat.
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| Management Most management Between 50-74% of the Between 75-89% of More than 90% of the observations observations are not management the management management are self self-critical. observations performed observations observations performed critical* are self-critical and performed are self- are self-critical and actions implemented. critical and actions actions implemented.
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| implemented.
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| Management No method has been One method has been Two means have Multiple means have emphasis on used in the last used in the last month been used in the last been used by safety to month to provide to provide emphasis on month to provide management in the last employees; emphasis on safety safety to employees in emphasis on safety to month to provide face questioning to employees in the the section (e.g., town employees in the to face emphasis on attitude section (e.g., town hall, 4Cs or All Hands section and at least safety to employees in hall, 4Cs, or All meetings, standdowns, one was face to face the section (e.g., town Hands meetings, newsletters, and (e.g., town hall, 4Cs hall, 4Cs or All Hands standdowns, training). or All Hands meetings, standdowns, newsletters, and meetings, newsletters, and training). standdowns, training).
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| newsletters, and training).
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| *Site wide assessment only. Data provided by Management Observation Program
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| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| ____ ____ ____ ____ ____D B B P-V P-0002
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| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 28 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 8 of 39
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| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY (continued)
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| There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Leadership in Leadership in Leadership in Action Leadership in Action Leadership in Action* Action includes includes discussions on includes discussions Action includes discussions on safety culture. on safety culture.
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| * discussions on safety culture.
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| * And And safety culture.
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| * And Employee feedback Employee feedback And Employee feedback indicates it was indicates it was very Employee indicates it was not effective effective. feedback indicates effective. And And it was very And ~An Adeffective Leadership in Action Leadership in Action And Leadership in training has been training has been Action training has available and available and Leadership in been available and scheduled for more scheduled for more Action training has 7 scheduled for less than 75% of than 80% of been available and than 75% of supervisors and above supervisors and scheduled for supervisors and within 12 months of above within 12 more than 85% of above within 12 new appointment.* months of new supervisors and months of new appointment.* above within 12 appointment.* months of new appointment.*
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| Problem solving* A problem solving In more than 5 cases, In all but one case, The problem process exists but the problem solving the problem solving solving process, there is no use of process NOP-EN-3001 process, NOP-EN- NOP-EN-3001 has the document in the has not been properly 3001 has been been properly section and CRs implemented in the properly implemented implemented in the were written to section for applicable in the section for section for document the conditions and CRs applicable conditions applicable failure to use the were written in the during the previous conditions during process during the previous quarter. quarter. the previous previous quarter. quarter.
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| *Site wide assessment only. Data provided by Human Resources 7
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| **Site wide assessment only. Data provided by Plant Engineering Manager APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA
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| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
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| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 29 of 86 Page 9 of 39
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| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY (continued)
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| There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Decision A Safety significant A Safety significant The majority of safety Safety significant making Condition Adverse to Condition Adverse to significant decisions decisions were made in Quality Condition Quality Condition were made in the the section with Report indicates that Report indicates that section with adequate required information, decisions were decisions are made in information, management oversight, made in the section the section with minimal management involvement and peer in isolation without information, oversight, checking during the adequate management oversight, involvement and peer past six months as information, involvement and peer checking during the indicated by no SCAQs.
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| management checking during the quarter as indicated oversight, past two months. by no SCAQs.
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| involvement and peer checking during the past month.
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| Improvements There have been There have been some There have been Significant in safety minimal improvements made in obvious improvements have margin* improvements made safety margin. . improvements made been made in safety in safety margin . in safety margin. margin.).
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| Plant activities A significant plant Less than 2 Condition Significant plant Significant plant receive proper event, associated Adverse to Quality CRs activities associated activities associated management with the section, associated with the with the section had a with the section had a attention and occurred during the section were written management plan management plan with safety focus previous quarter and due to lack of with a management a management sponsor a lack of a management attention sponsor and and management (Reference management or lack of safety focus management oversight scheduled for NG-DB-00800) attention or safety during the previous oversight scheduled the duration of the focus was indicated quarter. for the duration of the activity and no CAQ and an SCAQ activity and only one events occurred during written. CAQ event occurred the previous quarter.
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| indicating a lack of management attention during the previous quarter.
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| *Site wide assessment only. Data provided by Design Engineering Manager
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| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
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| 'ite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 30 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 10 of 39
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| : 2. MANAGERS' COMMITMENT AREA 2.b CRITERIA RELATED TO ROLES AND TEAMWORK Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Understanding Station surveys Station surveys Station surveys and/or Station surveys that safety is and/or interviews and/or interviews, interviews show that 80- and/or interviews highest priority* show that less show that 70-80% 90% of employees, show that more than than 70% of of employees, understand that safety is 90% of employees in 7
| |
| employees understand that the highest priority. that safety is the understand that safety is the highest highest priority.
| |
| safety is the priority.
| |
| highest priority.
| |
| Program Five of the 61 All 61 Phase I All 61 Phase 1 All 61 Phase 1 ownership' Phase 1 programs programs in the programs in the program programs in the in the program program review review have assigned program review have review do not have have assigned owners. With several assigned owners. In assigned owners owners and more exceptions, program general, program and five CRs were than three CRs owners are owners are written against were written on implementing their implementing their different programs different programs assigned responsibilities assigned in the past quarter. in the past quarter. and less than 3 CRs responsibilities and were written on different no CRs were written programs in the past against programs in quarter. the last quarter.
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| Ownership of More than 5% of 5% of SCAQ Less than 5% of SCAQ Less than 5 of corrective SCAQ remedial remedial or remedial or preventive preventiverestart actions and preventive preventive restart restart required d at restart required required corrective corrective actions and required corrective Does not include corrective actions actions and 10% of 10% of CAQ remedial 10%of aQ emedal CRs or CAs linked and more than CAQ remedial and and preventive restart and of CAQ remedial to P3 activities. 10% of CAQ preventive restart required corrective an preventive resta remedial and required corrective actions for the section, required corrective preventive restart actions for the have received 2 have received less required corrective section, have extensions for the than 2 extensions f actions for the received more than previous quarter. the previous quarter section have 2 extensions for the required more previous quarter.
| |
| than 4 extensions for the previous quarter.
| |
| *Site wide assessment only. Data provided from Edventures survey results
| |
| **Site wide assessment only. Data provided by Plant Engineering Manager.
| |
| | |
| APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 11 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2b. CRITERIA RELATED TO ROLES AND TEAMWORK (continued)
| |
| Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Ownership of The quality of The quality of The quality of The quality of engineering engineering engineering engineering engineering products as products as products as products as products as measured by the EAB is measured by the measured by the measured by the measured by the 1.0 or less.
| |
| Engineering EAB is greater EAB is between EAB is between 2.0 Assessment Board than 3.0. 3.0 and 2.1. and 1.1.
| |
| (EAB)*
| |
| Effectiveness of The individual The individual The individual error The individual error rate supervision of error rate is>0. error rate is <.45- rate is<.35->.26 is<0.26 individual errors individuals' 45 individual >.36 individual individual errors per per 10,000 hours 7 errors per errors per 10,000 10,000 hours worked.
| |
| 10,000 hours hours worked. worked.
| |
| worked.
| |
| Intra-department As a Manager, I As a Manager, I As a Manager, I As a Manager, I believe teamwork and believe there is believe there is believe alignment is alignment and teamwork alignment ((Some no alignment minimal improving and are obvious among unit supervisors and little alignment and teamwork can be managers in all activities will input to this teamwork some teamwork seen in some key of my department.
| |
| attribute, such as, among my among my activities among my Reactor Department's Department's Department's Engineering and managers. managers. managers.
| |
| RRT.)
| |
| Expectations There are More than 90% More than 95% of There are statements of '7 statements of of sections have sections have expectations for all expectations for statements of statements of sections and managers less than 90% expectations and expectations and all are reinforcing them and of sections and most employees employees meet employees understand employees are not familiar them. and implement them.
| |
| routinely ignore with them.
| |
| them.
| |
| *Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| *Site wide assessment only. Data provided by Human Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW ETENDED PLANT OUTAGE 1 07 Page 32 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 12 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2b. CRITERIA RELATED TO ROLES AND TEAMWORK (continued)
| |
| Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Trust, openness 4Cs surveys 4Cs surveys 4Cs surveys show 4Cs surveys show more and focused show less than show 50-70% of 70-90% of than 90% of employees commitment' 50% of employees feel employees feel that feel that work groups employees feel that work groups work groups display display high levels of that work groups display high high levels of trust, trust, openness and display high levels of trust, openness and commitment.
| |
| levels of trust, openness and commitment.
| |
| openness and commitment.
| |
| commitment.
| |
| Clear goals and No clear goals Goals and Goals and priorities Employees are clear priorities and priorities priorities exist for exist for the section about goals and have been the section but and most employees priorities for the section established for are not understand and own as well as how their role 7 the section adequately them. contributes to achieving understood and them.
| |
| owned by some employees.
| |
| Input and No employee Only managers Managers and Employees are involvement input and and supervisors supervisors appropriately involved in involvement are involved in occasionally request setting department goals occurs in the the setting of input/involvement and establishing work setting of department goals from employees in priorities.
| |
| department and establishing the setting of goals and work priorities. department goals establishing and establishing work priorities. work priorities.
| |
| Site wide assessment only. Data provided by Chief Operating Officer
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002 Tide: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 33 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 13 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY Ownership and accountability is evident ATTRIBUTE RED YELLOW WHITE GREEN Performance Less than 70% of Between 70-80% Between 80-90% of More than 90% of reviews in performance of performance performance reviews performance reviews for accordance with reviews for the reviews for the for the section were the section were FENOC section were section were completed for the completed for the review Performance completed for the completed for the review period period Management review period review period Process*
| |
| Development Less than 70% of Between 70-80% Between 80-90% of More than 90% of plans* managers and of managers and managers and managers and supervisors have supervisors have supervisors have supervisors have development development development plans development plans plans submitted plans submitted submitted to HR submitted to HR to HR to HR Restart There is no A restart A restart readiness A restart readiness Readiness restart readiness readiness review review process review process exists Reviews' review process. process exists exists and is and is implemented but implemented with efficiently and with implementation is the majority of participation by poor as shown by Managers and the Managers and the lack of Manager Senior Leadership Senior Leadership Team participation. Team participation.
| |
| Worker Surveys and/or Surveys and/or Surveys and/or Surveys and/or understanding of interviews interviews interviews indicate interviews indicate that their responsibility indicate that less indicate that that between 90- more than 95% of to raise safety than 80% of between 80-90% 95% of workers workers understand their concerns# workers of workers understand their responsibility to raise understand their understand their responsibility to nuclear safety or quality responsibility to responsibility to raise nuclear safety concerns.
| |
| raise nuclear raise nuclear or quality concerns.
| |
| safety or quality safety or quality concerns. concerns.
| |
| *Site wide assessment only. Data provided by Human Resources
| |
| **Site wide assessment only. Data provided through discussion at the Restart Readiness Review meeting
| |
| # Site wide assessment only. Data provided from Edventures survey results
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 34 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 14 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY(continued)
| |
| Ownership and accountability is evident Willingness to Surveys show Surveys show Surveys show that Surveys show that more raise safety that less than that between 85- between 90-95% of than 95% of personnel concems* 85% of personnel 90% of personnel personnel are willing are willing to raise safety are willing to are willing to to raise safety concerns through their raise safety raise safety concerns through supervisor, a CR or concerns through concerns through their supervisor, a ECP.
| |
| their supervisor, a their supervisor, a CR or ECP.
| |
| CR or ECP. CR or ECP.
| |
| SRO reviews for Less than 90% Between 90-95% Between 95-98 % More than 98% were Operability are were completed were completed were completed completed within 24 performed in a within 24 hours. within 24 hours. within 24 hours. hours.
| |
| timely manner for the identified period of this review' System Less than 80% Between 80-90% Between 90-95% of More than 95% of the assessments+ of restart required of the restart the restart required restart required 7 improvements in required improvements in improvements in safety safety have been improvements in safety have been have been implemented implemented at safety have been implemented at this at this time this time. implemented at time.
| |
| this time.
| |
| *Site wide assessment only. Data provided by 4Cs program and /or Employee Concems Program "t his item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Plant Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDEDl PLANT OUTAGE 07 Page 35 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 15 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY (continued)
| |
| Ownership and accountability is evident NQA field NQA field NQA field NQA field NQA field assessments assessments** assessments assessments assessments show show that managers and show that show that that managers and supervisors are managers and managers and supervisors are generally effective.
| |
| supervisors are supervisors are generally effective, generally generally with a few ineffective. effective, with exceptions.
| |
| several noteworthy exceptions.
| |
| Management Less than 80% Between 80-85% Between 85-95% of More than 95% of observations of management of management management management leading to participating in participating in participating in the participating in the coaching+ the Management the Management Management Management 7 Observation Observation Observation Observation Program Program, have Program, have Program, have have performed a performed a performed a performed a coaching session in the coaching coaching session coaching session in last month.
| |
| session in the inthe last month. the last month.
| |
| last month.
| |
| Timeliness of Less than 50% Between 50% Between 75% and More than 90% of my corrective actions of my section's and 74% of my 89% of my section's section's corrective corrective section's corrective actions actions designated as Does not include actions corrective actions designated as required for restart, are CRs or CAs linked to designated as designated as required for restart, complete at this time P3 activities required for required for are complete at this restart are restart are time complete at this complete at this time time This item assessed by NQA only
| |
| +Site wide assessment only. Data pvided by Management Observation Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE _ 07 Page 36 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 16 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2d. CRITERIA RELATED TO TRAINING AND QUALIFICATION Training and Qualification are valued ATTRIBUTE RED YELLOW WHITE GREEN Restart training+ Most required Between 75-90% Between 90-99% of 100% of required 7 restart training is of required restart required restart restart training is (Explain why not complete. training is training is complete. complete.
| |
| acceptable if less complete.
| |
| than green) initial Operator Individuals in Individuals in training* initial license initial license class are class are Individuals in initial Individuals in initial maintaining a maintaining a license class are license class are class average of class average of maintaining a class maintaining a class 82% or less 83-87% average of 88-94% average of more than 94%
| |
| Requalification Less than 70% of Between 70-84% Between 85-95% of More than 95% of the training licensed of the licensed the licensed licensed operators have operators have operators have operators have passed their (Explain why passed their passed their passed their requalification training.
| |
| acceptable if less requalification requalification requalification than green) training. training. training.
| |
| *This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Nuclear Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _____________________________________DBB P-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 37 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 17 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2d. CRITERIA RELATED TO TRAINING AND QUALIFICATION (continued)
| |
| Training and Qualification are valued Operability Less than 50% of Between 50-74% Between 75-90% of More than 90% of determination applicable of applicable applicable operators applicable operators training operators and operators and and engineers have and engineers have (Explain why engineers have engineers have received training on received training on acceptable if less received training received training operability operability than green) on operability on operability determinations. determinations.
| |
| determinations. determinations. 7 Training on Less than 80% Between 80-89% Between 90-97% of More than 97%
| |
| SCWE of managers, of managers, managers, managers, supervisors, supervisors, and supervisors, and supervisors, and and operators have (Explain why operators have operators have operators have received training on acceptable if less received training received training received training on SCWE.
| |
| than green) on SCWE. on SCWE. SCWE.
| |
| Training on Less than 70 % Between 70-80% Between 80-90% of More than 90% of decision making of applicable of applicable applicable personnel applicable personnel process" personnel have personnel have have received have received training received training received training training on the on the decision making on the decision on the decision decision making process.
| |
| making process. making process. process.
| |
| Training on Less than 80% Between 80-89% Between 90-95% of More than 97% of standards and of personnel in of personnel in in the section personnel in the expectations the section have the section have personnel have section, have received (Explain why received training received training received training on training on standards acceptable if less on standards and on standards and standards and and expectations.
| |
| than green) expectations. expectations. expectations.
| |
| Continuing Less than 70% of Between 70-80% Between 80-90%of More than 90% of training identified scheduled of scheduled scheduled training scheduled training by Curriculum training identified training identified identified by the CRC identified by the CRC is Review by the CRC is by the CRC is is completed in a completed in a timely Committee completed in a completed in a timely manner. manner.
| |
| (CRC) timely manner. timely manner.
| |
| *This item assessed by Operations and Engineering only "Site wide assessment only. Data provided by Nuclear Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 38 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 18 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN improvements in Most requisitions About 50% of open About 75% of open At least 85% of open management for management requisitions for requisitions for requisitions for staffing* positions (all exempt management (all management management positions employees) have exempt employees) positions (all exempt (all exempt employees) not been filled in the positions have employees) have have been filled in the past month. been filled in the been filled in the past month.
| |
| past month. past month.
| |
| Corrective Action There are no The CARB has The CARB has been The CARB has been Review Board directors on the been enhanced enhanced with enhanced with director-(CARB)+ CARB. with director-level director-level level personnel.
| |
| personnel. personnel.
| |
| The backlog of The backlog of documents awaiting The backlog of The backlog of documents awaiting CARB review is documents awaiting documents awaiting CARB review is less more than four CARB review is CARB review is less than one week.
| |
| weeks. less than four than two weeks.
| |
| weeks.
| |
| Engineering The backlog of The backlog of The backlog of The backlog of Assessment documents awaiting documents awaiting documents awaiting documents awaiting EAB Board (EAB)++ EAB review is EAB review is less EAB review is less review is less than one greater than four than four weeks. than two weeks. week.
| |
| weeks.
| |
| *Site wide assessment only. Data provided by Human Resources 7
| |
| +Site wide assessment only. Data provided by Performance Improvement
| |
| ++Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tifie: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 07 Page 39 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 19 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT(continued)
| |
| Cnmmitment tn cntiniini irnvmynt i evident ATTRIBUTE RED YELLOW WHITE GREEN Benchmarking Less than 60% (< Between 60-75% Between 75-90% of More than 90% of against industry 14) of sections (15-17) of sections ( 17-20) sections (>20) have 7 standards@ have scheduled sections have have scheduled any scheduled any any benchmarking scheduled any benchmarking in benchmarking in in accordance bench-marking in accordance with accordance with with NOBP-LP- accor-dance with NOBP-LP-2002 or NOBP-LP-2002 or NG-2002 or NG-EN- NOBP -LP-2002 NG-EN-00386 for 1 EN-00386 for 1V & 2 nd 00386 for 1 & 2 nd or NG-EN-00386 $ 2nd quarter 2004. quarter 2004.
| |
| quarter 2004. for I" quarter 2004.
| |
| Management A management A management A management A management observations observation observation observation program observation program program has been program has has been established. has been established.
| |
| established. Less been established. More than 80% of More than 90% of than 70% of More than 70% of management management management management observations are observations are observations are observations are performed as performed as performed as performed as scheduled and most scheduled and contain scheduled, and scheduled, and are considered quality information.
| |
| observations are observations are acceptable.
| |
| weak. weak.
| |
| Temporary There are more There are 11 or There are 8 or less There are 5 or less modifications+# than 11 temporary less temporary temporary temporary modifications. modifications. modifications. modifications.
| |
| Number of There are more There are 2 There is 1 operator There are no operator Operator work- than 2 operator operator workarounds. workarounds.
| |
| arounds*# workarounds. workarounds.
| |
| Number of There are more There are 4 There are 1-3 Control There are no Control Control Room than 4 Control Control Room Room deficiencies. Room deficiencies.
| |
| deficiencies'# Room deficiencies.
| |
| deficiencies.
| |
| @ Site wide assessment only. Data provided by Quality Services or Industry Relations
| |
| *This item assessed by Operations only
| |
| 'Site wide assessment only. Data provided by Management Observation program
| |
| +Site wide assessment only. Data provided by Plant Engineering
| |
| #Significance evaluation will be discussed during the Restart Readiness Review Safety Culture 7 Assessment and the outcome of this discussion may affect any or all of the attribute ratings. Explain why acceptable if less than green
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 40 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 20 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT (continued)
| |
| Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Training on Less than 80% of Between 80-89% Between 90-97% of More than 97% of SCWE* managers, of managers, managers, managers, supervisors supervisors and supervisors and supervisors and and operators have operators have operators have operators have received training on received training received training received training on SCWE. 7 on SCWE. on SCWE. SCWE.
| |
| Licensed Individuals in Individuals In Individuals in initial Individuals in initial operator initial license initial license license class are license class are pipeline* class are class are maintaining a class maintaining a class maintaining a maintaining a average of 88-94% average of more than class average of class average of 94%.
| |
| 82% or less 83-87%
| |
| *Site wide assessment only. Data provided by Nuclear Training
| |
| **This item assessed by Operations only.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 41 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 21 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT (continued)
| |
| Commitment to continuous improvement is evident SAFETY CONSCIOUS WORK ENVIRONMENT (SCWE)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Use of More than 4 CRs Between 4-2 CRs Less than 2 CRs No CRs issued within SCWERT* issued within the issued within the issued within the past the past year related to past year related past year related year related to failure failure to properly to failure to to failure to to properly conduct conduct SCWERT 7 properly conduct properly conduct SCWERT review of review of Davis-Besse SCWERT review SCWERT review Davis-Besse work work disciplinary of Davis-Besse of Davis-Besse disciplinary actions actions prior to the work disciplinary work disciplinary prior to the action. action.
| |
| actions prior to actions prior to the action. the action.
| |
| Effectiveness of There are more There are 5 NRC There are 4 NRC There are 2 or fewer SCWERT in than 5 NRC allegations or allegations or ECP NRC allegations or avoiding allegations or ECP concerns of concerns of ECP concerns of discrimination ECP concerns of discrimination discrimination discrimination claims* discrimination submitted within submitted within the submitted within the submitted within the past year past year past year the past year Effectiveness in There is more There is one There are no There are no avoiding NRC or than one substantiated substantiated NRC or substantiated NRC or ECP substantiated NRC or ECP ECP discrimination ECP discrimination substantiated NRC or ECP discrimination claims within the past claims within the past 2 discrimination discrimination claim within the year. years.
| |
| claims* claim within the past year past year
| |
| *Site wide assessment only. Data provided by Employee Concems Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 42 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 22 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2f. CRITERIA RELATED TO COMMITMENT TO CROSS-FUNCTIONAL WORK MANAGEMENT AND COMMUNICATION Commitment to cross functional work management and communication is evident ATTRIBUTE RED YELLOW WHITE GREEN Cross-functional No cross-functional Some cross- Cross-functional Cross-functional teamwork* teamwork is evident functional teamwork frequently teams among sections among sections teamwork among occurs among are constantly sections exists but sections, enabling formingtreforming work issub- efficient and effective around the best way to optimized. workflow. get work done.
| |
| Department Many process Some process Minimal process Department interfaces interfaces breakdowns occur breakdowns occur breakdowns and are seamless; work within the within the rework occur within flows efficiently Department with Department with the Department with between departments extensive amounts frequent amounts effective and efficient throughout the entire of rework needed. of rework needed. resolution of emergent organization.
| |
| issues.
| |
| Performance to Less than 70% of Between 70-80% Between 80 -90% of More than 90% of schedule" work iscompleted of work is work iscompleted on work is completed on on time, as completed on time, as scheduled, time, as scheduled, scheduled, causing time, as with minimal within current resource major scheduled, with adjustments to capacity.
| |
| consequences to major adjustments resource capacity overall site to resource required to improve performance. capacity required performance.
| |
| to improve performance.
| |
| Interdepartmental Information that Information that Information that Information that communication impacts impacts impacts downstream impacts downstream downstream downstream implementation is implementation is implementation is implementation is frequently shared on a communicated as not shared, causing inconsistently timely basis, enabling soon as it's known, significant negative shared, which departments to enabling departments consequences to keeps other proactively plan and to work proactively on other departments. departments in a respond. a consistent basis.
| |
| reactive mode.
| |
| * Site wide assessment only. Data provided from Edventures survey results.
| |
| **Site wide assessment only. Data provided by Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 43 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 23 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2f. CRITERIA RELATED TO COMMITMENT TO CROSS-FUNCTIONAL WORK MANAGEMENT AND COMMUNICATION (continued)
| |
| Commitment to cross functional work management and communication is evident Interdepartmental Problem solving Cross-functional Cross-functional Cross-functional problem solving and decision sections, sections, sections, and decision making occurs in Departments or Departments or Departments or making isolation; non- stakeholders are stakeholders are stakeholders are involvement of seldom involved frequently involved consistently involved other Departments when problems when problems are when problems are or stakeholders. are being solved being solved and being solved and and decisions are decisions are made. decisions are made.
| |
| made.
| |
| Systemic learning Things are broken Discrete problems Attention isfocused Streamlining and down, focus is on are fixed within the on learning and improving systems the pieces and section with discovering and process is discrete problems minimal fundamental constant to resolve are fixed within the understanding of solutions to long-standing and/or section with no interdependencies resolving long- complex problems understanding of standing and/or within the section interdependencies. complex problems within the section Incorporating Industry operating There is less than There is full Operating Experience industry experience is not full utilization and utilization and is consistently and Operating consistently fully minimal compliance with the fully utilized in every Experience* utilized to enhance compliance to our Operating department and is site performance. Operating Experience Program well-integrated into Experience everyday activities to Program enhance plant performance.
| |
| *Site wide assessment only. Data provided by Operating Experience Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 44 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 24 of 39 2.MANAGERS' COMMITMENT AREA 2g. CRITERIA RELATED TO COMMITMENT TO CREATING AN ENVIRONMENT OF ENGAGEMENT AND COMMITMENT An environment of engagement and commitment is evident ATTRIBUTE RED YELLOW WHITE GREEN FENOC values, FENOC values, FENOC values, FENOC values, basic Most exempt basic principles basic principles and basic principles principles and personnel in the and leadership leadership and leadership leadership strategies section have strategies strategies are not strategies are are frequently internalized and are used by exempt inconsistently demonstrated by some living the FENOC personnel within demonstrated by exempt personnel values, basic the section some exempt within the section principles and personnel within leadership strategies the section as demonstrated in 7 their day to day actions.
| |
| Quality of Employee Employee Employees Concerns Employee Concerns management and Concerns Program, Concerns Program, Quality Program, Quality employee Quality Assessment Program, Quality Assessment and 4Cs Assessment and 4Cs relationships* and 4Cs survey Assessment and survey data indicates survey data indicate data indicates that 4Cs survey data that more than 80% of more than 90% of (Explain why employees openly Indicates that employees will bring employees raise acceptable if not express fear of more than 70% concerns to issues directly with green) retaliation and will of employees management. management, work not raise safety will bring safety collaboratively to concerns with concerns to resolves issues and management. management. reflect favorable improvement.
| |
| Organizational Section Section Section management Section management commitment and management management frequently supports consistently supports shared success focuses on what is occasionally doing what is in the doing what is in the criteria in the best Interest supports what is best interest of the best interest for the of their section at in the best whole organization whole organization the expense of interest of their rather than what is in rather than what is in what is in the best section without the best interest of the best interest for interest of the consideration to their section. their section.
| |
| whole organization. what is in the best interest of the whole organization.
| |
| *Site wide assessment only. Data provided by ECP, NQA and 4Cs
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 45 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 25 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2g. CRITERIA RELATED TO COMMITMENT TO CREATING AN ENVIRONMENT OF ENGAGEMENT AND COMMITMENT (continued)
| |
| An environment of engagement and commitment is evident Performance Less than 70% of Between 70-80% Between 80-90% of More than 90% of reviews in performance of performance performance reviews performance reviews accordance with reviews for the reviews for the for the section were for the section were FENOC section were section were completed for the completed for the 7 Performance completed for the completed for the review period per. review period per the Management review period per review period per. the FENOC FENOC Performance process* the FENOC the FENOC Performance Management process Performance Performance Management Management Management process process process FENOC Less than 70% of Between 70-80% Between 80-90% of More than 90% of Performance managers and of managers and managers and managers and Management supervisors have supervisors have supervisors have supervisors have Process development plans development plans development plans development plans Development submitted to HR submitted to HR submitted to HR submitted to HR Plans*
| |
| *Site wide assessment only. Data provided by Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 46 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 26 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3a. CRITERIA RELATED TO DRIVE FOR EXCELLENCE Nuclear assets of people and plant are continuously improved to enhance margins of safety ATTRIBUTE RED YELLOW WHITE GREEN Maintenance Rule There are more There are 2-3 There is one Red There are zero Red (a)(1) Systems* than 3 Red Red (a)(1) (a)(1) system. (a)(1) systems and all 7 (a)(1) systems. systems. Maintenance Rule (a)(1) systems are in monitoring status Number of There are more There are 2 There is 1 operator There are no operator Operator than 2 operator operator workarounds. workarounds.
| |
| workarounds**# workarounds. workarounds.
| |
| Number of Control There are more There are 4 There are 1-3 There are no Control Room than 4 Control Control Room Control Room Room deficiencies.
| |
| deficiencies**# Room deficiencies. deficiencies.
| |
| deficiencies.
| |
| Number of There are more There are 11 or There are 8 or less There are 5 or less temporary than 11 less temporary temporary temporary modifications.
| |
| modifications+# temporary modifications. modifications.
| |
| modifications.
| |
| Individual Error The individual The individual The individual error The individual error rate Rate++ error rate is error rate is 0.31 rate is 0.29 <.35- is <0.26 individual errors 17
| |
| > 0.45 individual <.45->.36 >.26 individual errors per 10,000 hours errors per individual errors per 10,000 hours worked.
| |
| 10,000 hours per 10,000 hours worked.
| |
| worked. worked.
| |
| *Site wide assessment only. Data provided by Plant Engineering "This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Plant Engineering
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| ++Site wide assessment only. Data provided by Human Performance
| |
| #Significance evaluation will be discussed during the Restart Readiness Review Safety Culture Assessment and the outcome of this discussion may affect any or all of the attribute ratings. Explain why acceptable if less than green.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D BBP-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 47 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 27 of 39
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| : 3. INDIVIDUALS' COMMITMENT AREA 3a. CRITERIA RELATED TO DRIVE FOR EXCELLENCE (continued)
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| Nuclear assets of people and plant are continuously improved to enhance margins of safety Percent of Less than 80% of 80% or more of the 90% or more of the 95% or more of the CRs self-identified the CRs originated CRs originated are CRs originated are originated are self-Condition are self-identified. self-identified. self-identified. identified.
| |
| Reports (CRs)*
| |
| Number of Less than 80% of At least 80-90% of At least 90% of SCAQ All SCAQ evaluations open SCAQ evaluations SCAQ evaluations evaluations and 80- and 90% of CAQ Condition and less than 70% and 70-80% of 90% of CAQ evaluations were Report of CAQ evaluations CAQ evaluations evaluations were completed on schedule evaluations* were completed on were completed on completed on for the previous quarter.
| |
| schedule for the schedule for the schedule for the previous quarter. previous quarter. previous quarter.
| |
| Engineering The quality of The quality of The quality of The quality of Assessment engineering engineering engineering products engineering products as Board (EAB) products as products as as measured by the measured by the EAB is index' measured by the measured by the EAB is 2.0 or less. 1.0 or less.
| |
| EAB is greater than EAB is 3.0 or less.
| |
| 3.0.
| |
| Performance More than one One significant Major plant evolutions Major plant evolutions during major significant event has event has occurred have been performed have been performed 7 plant occurred during a during a plant in the past month with successfully in the past evolutions+ plant evolution in the evolution in the some less than month as planned past month past month significant challenges without any challenges or transients.
| |
| Addressing Less than 70% of Between 70-80% of Between 80-90% of More than 90% of Operating operating operating operating experience operating experience Experience experience reports experience reports reports applicable to reports applicable to the applicable to the applicable to the the section are section are completed section are section are completed on time on time.
| |
| completed on time completed on time Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Significant is defined by INPO as an event which caused or had the potential to cause an appreciable reduction in plant safety or reliability, excessive radiation exposure, the discharge of radioactivity offsite or serious han to individuals. The significance of a particular event (including the discovery of a serious deficiency, lies in the actual or potential consequences of the event or in the likelihood that it is a precursor to a more serious event.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| *Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| +Site wide assessment only. Data provided by Operations
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 48 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 28 of 39
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| : 3. INDIVIDUALS' COMMITMENT AREA 3b. CRITERIA RELATED TO QUESTONING ATTITUDE Challenges are welcomed ATTRIBUTE RED YELLOW WHITE GREEN Quality of pre-job Management Management Management Management briefs* observations and QA observations and observations and QA observations and field observations QA field field observations QA field show that most pre-job observations show show that, with some observations show briefs are not that most pre-job exceptions, pre-job that pre-job briefs in acceptable. briefs are briefs are acceptable. general are acceptable. acceptable.
| |
| Percent of CRs Less than 13% of Between 13-15% Between 15-17% of More than 17% of per person per individuals wrote CRs of individuals individuals wrote CRs individuals wrote group during the past 30 wrote CRs during during the past 30 CRs during the past days. the past 30 days. days. month.
| |
| Number of The number of The number of The number of The number of programmatic programmatic CRs programmatic CRs programmatic CRs programmatic CRs CRs' indicates that indicates that most indicates that a large indicates that individuals in general individuals are majority of individuals individuals in are reluctant to write willing to write are willing to write general are willing CRs on programmatic CRs on CRs on programmatic to write CRs on and management programmatic and and management programmatic and issues. management issues. management issues. issues.
| |
| Program and >0.50 program and <0.50-.>.37 <0.37->.27 program <0.27 program process error process errors per program and and process errors and process errors rate+ 10,000 hours worked. process errors per per 10,000 hours per 10,000 hours 10,000 hours worked. worked.
| |
| worked.
| |
| Raising Management Management Management Management problems* observations, CAP and observations, CAP observations, CAP observations, CAP NQA field observations and NQA field and NQA field and NQA field 7 show that most observations show observations show observations show individuals are not individuals that a large majority that most raising problems generally are of individuals are individuals are encountered in the raising problems raising problems raising problems field. encountered in the encountered in the encountered in the field. field. field.
| |
| *Site wide assessment only. Data provided by Management Observation Program and NQA.
| |
| *Site wide assessment only. Data provided by Performance Improvement.
| |
| +Site wide assessment only. Data provided by Human Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ___________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 49 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 29 of 39
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| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Event Free Clock* The event free The event free The event free The event free clock is clock is less clock is between 20 clock is 30 to 39 greater than 40 days on than 20 days on and 30 days on days on average. average.
| |
| average. average.
| |
| Industrial safety There are 11 or There are between There are 4 to 7 There are no more than performance' more OSHA 8 and 10 OSHA OSHA recordables 3 OSHA recordables per recordables per recordables per per year. year.
| |
| year. year.
| |
| Individual error The individual The individual error The individual The individual error rate rate* error rate is rate is <0.<.45->.36 error rate is is <0.26 individual errors
| |
| >0.45 individual individual errors per <0.<.36->.26 per 10,000 hours 7 errors per 10,000 hours individual errors worked.
| |
| 10,000 hours worked. per 10,000 hours worked, worked.
| |
| Program and >0.50 program <0.50->.37 <..37->.27 <0.27 program and process error rate* and process program and program and process errors per errors per process errors per process errors per 10,000 hours worked.
| |
| 10,000 hours 10,000 hours 10,000 hours worked. worked. worked.
| |
| Significant human There are more There are fewer There are fewer There were no performance than 3 significant than 3 significant than 2 significant significant human errors resulting in human human human performance errors per plant transients* performance performance errors performance year resulting in plant errors per year per year resulting in errors per year transients.
| |
| resulting in plant plant transients. resulting in plant transients. transients.
| |
| Backlog of Priority There are more There are less There are less There are less than100 procedure change than 200 open than 200 open than 150 open open Priority PCRs.
| |
| requests (PCRs)+ Priority PCRs. Priority PCRs. Priority PCRs. 7 Operational transient Isdefined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| *Site wide assessment only. Data provided by Human Performance "Site wide assessment only. Data provided by Industrial Safety
| |
| +Site wide assessment only. Data provided by Quality Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 50 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 30 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH (continued)
| |
| Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Deficiency rate for Deficiency rate The deficiency The deficiency rate The deficiency rate for QC holds* for QC hold rate for QC hold for QC holds point is QC hold points is less points is more points is less than less than 15 %. than 7 %.
| |
| than 25%. 25%.
| |
| Rework rated Rework rate is The rework rate The rework rate is The rework rate is more than 3%. is 2.5-3.0%. 2.1-2.5%. <2.0%.
| |
| Ratio of completed Less than 50% More than 50% of More than 75% of More than 90% of to scheduled of scheduled scheduled work scheduled work scheduled work orders works orders per work orders are orders are orders are are completed.
| |
| week+ completed. completed. completed.
| |
| Number of late Less than 50% More than 50% of More than 75% of More than 90% of preventive of scheduled scheduled PMs scheduled PM are scheduled PMs are 7 maintenance (PM) PMs are are completed on completed on time. completed on time.
| |
| activities+ completed on time.
| |
| time Backlog of There are more There are There are between There are less than 134 corrective than 230 CM between 229 and 149 and 134 CM CM activities maintenance (CM) activities 150 CM activities activities outstanding.
| |
| activities+ outstanding. outstanding. outstanding.
| |
| Number of There are more There are 2-3 There is one Red There are zero Red Maintenance Rule than 3 Red Red (a)(1) (a)(1) systems. (a)(1) systems. All 7 (a)(1) systems++ (a)(1) systems. systems. Maintenance Rule (a)(1) systems will be in monitoring
| |
| *This item assessed by QC only. The Deficiency Rate for QC relates to rejectable or unsatisfactory inspection attributes identified in the field by the QC Inspector during the implementation of the Order (work order). The established QC hold points are embedded within the Order as either a specific Step in the work sequence or on a standalone document such as a Weld Traveler.
| |
| **This item assessed by Maintenance only
| |
| +Site wide assessment only. Data provided by Outage Management and Work Control
| |
| ++Site wide assessment only. Data provided by Plant Engineering. Explain why acceptable if not green. l 7
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 51 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 31 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH (continued)
| |
| Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Performance One significant Major plant Major plant Major plant evolutions during major plant event has evolutions have evolutions have have been performed evolutions @ occurred during a been performed been performed with successfully as plant evolution in with some some transients but planned. There are no the past month or transients or one no significant events transients or significant there are three or significant event during major plant events during major more transients during major plant evolutions prior to plant evolutions prior during major evolutions prior to restart. to restart.
| |
| plant evolutions restart. 17 prior to restart.
| |
| Use of procedures Management Management Management Management and work orders* observations and observations and observations and observations and NQA NQA field NQA field NQA field field observations observations observations show observations show show that the vast show that most that individuals that many majority of individuals individuals are generally are individuals are using are using procedures not using using procedures procedures or work or work orders.
| |
| procedures or or work orders. orders.
| |
| work orders.
| |
| Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Significant is defined by INPO as an event that caused or had the potential to cause an appreciable reduction in plant safety or reliability, excessive radiation exposure, the discharge of radioactivity offsite or serious harm to individuals. The significance of a particular event (including the discovery of a serious deficiency, lies in the actual or potential consequences of the event or in the likelihood that it is a precursor to a more serious event.
| |
| @ Site wide assessment only. Data provided by Operations
| |
| *Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED
| |
| ,PLANT OUTAGE 07 Page 52 of 86, APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 32 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS Associates are comfortable in voicing opinions, issues and concerns ATTRIBUTE RED YELLOW WHITE GREEN Number of CRs per Less than 13% of Between 13-15% of Between 15-17% of More than 17% of person per group* individuals wrote CRs individuals wrote CRs individuals wrote individuals wrote during the past 30 during the past 30 CRs during the past CRs during the past days. days. 30 days. 30 days.
| |
| Worker confidence in Surveys and/or Surveys and/or Surveys and/or Surveys and/or raising safety interviews indicate interviews indicate interviews indicate interviews indicate concerns** that less than 80% of that between 80-90% that between 90- that more than 95%
| |
| workers believe they of workers believe 95% of workers of workers believe Explain why can raise nuclear they can raise believe they can they can raise acceptable if not safety or quality nuclear safety or raise nuclear safety nuclear safety or green) concerns without fear quality concerns or quality concerns quality concerns of retaliation. without fear of without fear of without fear of retaliation. retaliation. retaliation.
| |
| Feedback from 4Cs Feedback from the Feedback from the Feedback from the Feedback from the meetings+ 4Cs meetings 4Cs meetings 4Cs meetings 4Cs meetings indicates that most indicates that more indicates that more indicates that more individuals are not than 70% of than 80% of than 90% of willing to raise individuals are willing individuals are individuals are concerns to to raise concerns to willing to raise willing to raise management. management. concerns to concerns to management. management.
| |
| Keep Improving Each month's total Each month's total Each month's total Each months total Performance (KIP) Safe behavior is 59% Safe behavior is 60% Safe behavior is Safe behavior is program++ or less. to 69%. 70% to 79%. 80% or higher.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| +Site wide assessment only. Data provided by Chief Operating Officer
| |
| ++Site wide assessment only. Data provided by Industrial Safety "Site wide assessment only. Data provided by Employee Concems Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 53 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 33 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| Associates are comfortable in voicing opinions, issues and concerns ATTRIBUTE RED YELLOW WHITE GREEN Pre-job briefings@ Management Management Management Management observations observations and observations and QA observations and QA and QA field QA field field observations field observations show observations observations show that, with some that pre-job briefs in show that most show that most exceptions, pre-job general are acceptable.
| |
| pre-job briefs pre-job briefs are briefs are acceptable.
| |
| are not acceptable.
| |
| acceptable.
| |
| Intra-department No formal Infrequent Formal Formal communication information sharing communication information communication structures exist and are structures exist sharing exists structures exist and consistently used to for sharing among the are occasionally used share information information sections of the to share information among the sections of among the department. among the sections the department.
| |
| sections of the of the department.
| |
| department.
| |
| Quality of 4Cs surveys 4Cs surveys 4Cs surveys indicate 4Cs surveys indicate communication* indicate that indicate that more that more than 70% that more than 70% of more than 50% than 50% of of employees believe employees believe that of employees employees that communication communication from believe that the believe that from their Managers their Managers isgood.
| |
| communication communication isfair.
| |
| from their from their Managers is Managers isfair poor cSite wide assessment only. Data provided by Management Observation Program and NQA
| |
| *Site wide assessment only. Data provided by Chief Operating Officer
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 54 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 34 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| SAFETY CONSCIOUS WORK ENVIRONMENT (SCWE)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Employee Surveys and/or Surveys and/or Surveys and/or Surveys and/or awareness of interviews indicate that interviews indicate that interviews indicate interviews indicate SCWE policy" less than 80% of 80-90% of employees that 90-95% of that more than 95%
| |
| employees in the in the section are aware employees in the of employees in the (Explain why section are aware of of policy and consider it section are aware of section are aware of acceptable if not policy. a FE value. policy and consider it policy and consider it green) an FE value. an FE value and the normal way to do business.
| |
| Training on Less than 80% of Between 80-89% of Between 90-97% of More than 97% of SCWE *managers, supervisors, managers, supervisors, managers, managers, and operators have and operators have supervisors, and supervisors, and (Explain why received training on received training on operators have operators have acceptable if not SCWE. SCWE. received training on received training on green) SCWE. SCWE.
| |
| NQA nterviews+ NQA interviews indicate NQA interviews indicate NQA interviews NQA interviews 7 that less than 85% of that between 85-90% of indicate that between indicate that more (Explain why individuals are willing to individuals are willing to 90-95% of individuals than 95% of acceptable if not raise concerns to their raise concerns to their are willing to raise individuals are willing green) supervisors or ECP. supervisors or ECP. concerns to their to raise concerns to supervisors or ECP. their supervisors or ECP.
| |
| Worker Surveys and/or Surveys and/or Surveys and/or Surveys and/or confidence in interviews indicate that interviews indicate that interviews indicate interviews indicate raising safety less than 80% of between 80-90% of that between 90-95% that more than 95%
| |
| concerns workers in the section workers in the section of workers in the of workers in the believe they can raise believe they can raise section believe they section believe they (Explain why nuclear safety or quality nuclear safety or quality can raise nuclear can raise nuclear acceptable if not concerns without fear of concerns without fear of safety or quality safety or quality green) retaliation. retaliation. concerns without fear concerns without fear of retaliation. of retaliation.
| |
| *Site wide assessment only. Data provided by Nuclear Training
| |
| **Site wide assessment only. Data provided by Employee Concems Program
| |
| +Site wide assessment only. Data provided by NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 55 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 35 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| EMPLOYEE CONCERNS PROGRAM (ECP)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Ratio of concerns There are more There are more There are at least 4 There are at least 8 submitted to ECP NRC allegations ECP concerns times more ECP times more ECP vs. NRC than ECP than NRC concerns than NRC concerns than NRC allegations based concerns. allegations. allegations or there allegations or there are on three month are no NRC no NRC allegations or rolling average* allegations. ECP concerns.
| |
| Satisfaction of Less than 70% of Between 70-80 % Between 80-90% of More than 90% of employees using employees that of employees that employees that use employees that use the the ECP* use the ECP use the ECP the ECP report being ECP report being report being report being satisfied with the satisfied with the satisfied with the satisfied with the process. process.
| |
| process. process.
| |
| Complaints of There are more There are 2 There is 1 complaint There are zero breach of than 2 complaints complaints this this year. complaints this year.
| |
| confidentiality of this year. year.
| |
| ECP*
| |
| Management Employee Employee Employee surveys Employee surveys support for ECP* surveys indicate surveys indicate indicate between 80- indicate more than 90% 7 less than 70% of between 70-80% 90% of individuals of individuals believe (Explain why individuals of individuals believe management management supports acceptable if not believe believe supports ECP. ECP.
| |
| green) management management supports ECP. supports ECP.
| |
| *Site wide assessment only. Data provided by Employee Concems Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 07 Page 56 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 36 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM Persistence and urgency in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Development Less than 70% of Between 70-80 % Between 80-90% of More than 90% of Plans per applicable of applicable applicable employees applicable employees in FENOC employees in the employees in the in the section have the section have 7 Performance section have section have completed completed development Management completed completed development plans. plans.
| |
| process development development plans. plans.
| |
| Training Training Training Training attendance Training attendance is attendances attendance is less attendance is is between 91-98%. greater than 98%.
| |
| than 85%. between 85-90%.
| |
| Rework rate+ The rework rate is The rework rate The rework rate is The rework rate is more than 3%. is 2.5-3.0%. 2.1-2.5%. <2.0%.
| |
| Results of EAB The quality of The quality of The quality of The quality of assessments++ engineering engineering engineering products engineering products as products as products as as measure by the measured by the EAB measured by the measured by the EAB is 2.0 or less is 1.0 or less.
| |
| EAB is greater EAB is 3.0 or than 3.0. less.
| |
| Training Overall Training Overall Training Overall Training Overall Training performance performance score performance performance score performance score score per less than 60% score between between 80-90% greater than 90%
| |
| NOBP-TR- 60-80%.
| |
| 1501#
| |
| Radiation There are more There are 1-3 There is I radiation There are no radiation Protection than 3 radiation radiation protection event in protection events in the 7 events @ protection events protection events the last quarter. last quarter.
| |
| in the last quarter. in the last quarter.
| |
| *Site wide assessment only. Data provided by Nuclear Training
| |
| +This item assessed by Maintenance only
| |
| ++This item assessed by Engineering only. Data provided by Director-Nuclear Engineering
| |
| #This item assessed by Nuclear Training only.
| |
| @Site wide assessment only. Data provided by Radiation Protection. An RP event is defined as any radiological event that would be included in the NRC Performance Indicator for Radiation Safety Comerstone.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ _____ _____ ____ _____ ____D BB P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 57 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 37 of 39 3.INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence and urgency in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Procedure Management Management Management Management compliance' observations and observations and observations and observations and NQA NQA field NQA field NQA field field observations show observations show observations observations show that the vast majority of 7 that most show that that many individuals individuals are individuals are not individuals are complying with complying with complying with generally are procedures. procedures.
| |
| procedures. complying with procedures.
| |
| Personal Few employees in Employees in the Employees in the Employees at all levels initiative the section section work hard section do what it in the section take routinely express to do what's takes to get the job personal initiative to why work can't be expected. done. invent methods to done or improved. achieve higher quality and greater efficiency.
| |
| Ownership Employees in the Employees in the Employees in the Most employees in the section don't section are section follow through section regularly follow through on inconsistent in and do what is asked volunteer to own/lead assigned following through of them and do what project, develop plans, commitments and to meet quality is defined within their coordinate efforts and seldom volunteer and timing of job description. see work through to for ownership. assigned completion.
| |
| commitments.
| |
| 7
| |
| **Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| _____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 58 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 38 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Implementation Implementation Implementation of Implementation of The CAP improvements of CAP of the CAP the CAP the CAP designated for restart 7 improvements* improvements improvements improvements for are completed and designated for designated for restart is completed associated training is (Explain why restart has not restart is started but the associated completed.
| |
| acceptable ifnot started. but none are training is not green) completed. completed.
| |
| Root cause The root cause The root cause The root cause The root cause evaluation evaluation evaluation evaluation approval evaluation approval rate quality* approval rate as approval rate as rate as determined as determined by the determined by determined by the by the CARB is CARB is 90% or greater.
| |
| the CARB is less CARB is between between 75-90%.
| |
| than 50%. 50-74%.
| |
| CR category The CR category The CR category The CR category The CR category accuracy* accuracy rate is accuracy rate is accuracy rate is accuracy rate is 90% or 7 less than 70% or between 70-80%. between 80-90%. greater.
| |
| (Explain why greater.
| |
| acceptable if not green)
| |
| CR self- Less than 80% of 80% or more of 90% or more of the 95% or more of the CRs identification the CRs the CRs originated CRs originated are originated are self-rate* originated are are self-identified. self-identified. identified.
| |
| self-identified.
| |
| Employee Employee Employee surveys Employee surveys Employee surveys survey+ surveys indicate indicate that indicate that indicate that less than 7 that more than between 10-5% of between 5-2% of 2% of individuals are not (Explain why 10 % of individuals are not individuals are not willing to use the CAP.
| |
| acceptable if not individuals are willing to use the willing to use the green) not willing to use CAP. CAP.
| |
| the CAP.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| +Site wide assessment only. Data provided by Employee Concerns Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| _____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 59 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 39 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN NQA interviews* NQA interviews NQA interviews NQA interviews NQA interviews indicate that indicate that indicate that between - indicate that less than more than 10% between 10-5% of 5-2% of individuals are 2 % of individuals are of individuals are individuals are not not willing to use the not willing to use the not willing to use willing to use the CAP. CAP.
| |
| the CAP. CAP.
| |
| Timeliness of Less than 50% of Between 50-74% Between 75-89%of More than 90% of corrective actions corrective actions of corrective corrective actions for corrective actions for 7 for section CRs actions for section section CRs are section CRs are Does not include are completed on CRs are completed on completed on CRs or CAs linked schedule without completed on schedule without schedule without to P3 activities extensions. schedule without extensions. extensions.
| |
| extensions.
| |
| *Site wide assessment only. Data provided by NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberB
| |
| __________ ______ DBBP-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 60 of 86 7
| |
| ATTACHMENT 10: SAFETY CULTURE ASSESSMENT CRITERIA MATRIX
| |
| &.S _ el; U Chemistry =__=_=_== = ==_=====
| |
| M°gnmtNt0~Vork _ _ _ __ _ _
| |
| Maintenance =_== = = = =
| |
| OAIQC~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~C Engneering = _ _ _= _ _ _ _ = _ = --
| |
| Project =__ _=____=__=_-=__
| |
| Plant Opeorti s_
| |
| RMeanagaemEent = = == = = = = = = == _= _
| |
| = = = =
| |
| Services ___________=__=_____
| |
| Affairs_
| |
| Quality Serv ces _ _ _ _ _ _ _ _ _ __ _ _ __ _ _
| |
| Other Serctions = = = = = = = = =
| |
| Client Services = == = = =
| |
| Husminss_ _ _ _ _ _ _-_ _ _ _ _ _-_ _ _
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Num DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 61 of 86 ATTACHMENT 11: SAFETY CULTURE ATTRIBUTE ASSESSMENT MATRIX
| |
| : 1. Policy Commitment Area:
| |
| la. Criteria Related to Statement of Safety Policy Item Color Policy statement on Safety Culture Policy statement on SCWE Making employees aware of policy statements l 7 Employee understanding of policies I Worker understanding of responsibility to raise safety concerns l Total for a Color:
| |
| lb. Criteria Related to Management Values Item Color Corporate values Statement of mission, vision and values FENOC Business Plan Total for lb Color:
| |
| Ic. Criteria Related to Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ___ ___ D BBP-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 62 of 86 Item Color 7
| |
| Adequacy of management resources Adequacy of personnel resources Adequacy of funding Adequacy of tools, material and equipment to complete site tasks Adequacy of tools, material and equipment to complete Section tasks Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Total for 1c Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 63 of 86 Id. Criteria Related to Self-Assessment 7 Item Color Use of NQA to supplement the self assessment process Self assessments in accordance with NOBP-LP-2004 Section Performance Indicators Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Personnel Performance Appraisals Total for Id Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 64 of 86 le. Criteria Related to Independent Oversight 7
| |
| Item Color Nuclear Committee of the Board of Directors Company Nuclear Review Board l Nuclear Quality Assurance Learning from the experience of the Industry Total for le Color:
| |
| Total for 1 Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I - 07 Page 65 of 86
| |
| : 2. Managers' Commitment Area 2a. Criteria Related to Commitment to Safety Item Color Management observations performed as scheduled with coaching Management observations are self critical 7
| |
| Management emphasis on safety to employees Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Leadership in Action
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 07 Page 66 of 86 Item Color Problem Solving Decision making Operations Radiation Protection Chemistry 7 Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Improvement in safety margin Plant activities receive proper management attention and safety focus Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| _____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 67 of 86 Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance 7
| |
| Supply Chain Client Services Business Services Human Resources Total for 2a Color:
| |
| 2b. Criteria Related to Roles and Teamwork Item Color Understanding that safety is highest priority Program Ownership Ownership of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 68 of 86 Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Item Color Ownership of Engineering products as measured by EAB 7
| |
| Effectiveness of supervision of Individuals Intra-department teamwork and alignment Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ________________________________ DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 69 of 86 Business Services Human Resources Item Color Expectations Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance 7
| |
| Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Trust, openness and focused commitment Clear goals and priorities Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 70 of 86 Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services 7
| |
| Business Services Human Resources Item Color Input and involvement Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002 Tife Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 71 of 86 Total for 2b Color:
| |
| 2c. Criteria Related to Ownership and Accountability Item Color Performance Reviews in accordance with FENOC Performance 7 Management Process Development plans Readiness Reviews Worker understanding of responsibility to raise safety concerns l Willingness to raise safety concerns l SRO reviews for Operability are performed in timely manner System assessments NQA field assessments Management observations leading to coaching Timeliness of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 72 of 86 Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering 7
| |
| Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Total for 2c Color:
| |
| 2d. Criteria Related to Training and Qualification Item Color Restart training Initial Operator training Requalification training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.,
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 73 of 86 Item Color Operability determination training Operations Engineering Training on SCWE Training on decision making process Training on standards and expectations Operations Radiation Protection Chemistry Outage Management and Work Control 7 Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Continuing training identified by Curriculum Review Committee Total for 2d Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B BP-V P-0002 Tife: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page74of86 2e. Criteria Related to Commitment to Continuous Improvement Item Color Improvements in management staffing Corrective Action Review Board Engineering Assessment Board Benchmarking against industry standards 7
| |
| Management observations Temporary modifications Number of operator work arounds Number of Control Room deficiencies Training on SCWE Licensed operator pipeline Use of SCWERT Effectiveness of SCWERT in avoiding discrimination claims Effectiveness in avoiding NRC or ECP substantiated discrimination claims Total for 2e Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 75 of 86 2f. Criteria Related to Commitment to Cross-Functional Work Management and Communication Item Color Cross functional teamwork Department interfaces Operations Radiation Protection Chemistry 7 Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Performance to schedule Interdepartmental communication Item Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 76 of 86 Interdepartmental problem solving and decision making i Operations
| |
| _.._.........___I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
| |
| Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety 7 Plant Engineering Design Engineering Project Management Rapid Response Team
| |
| _..~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
| |
| Reactor Engineering
| |
| _._~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
| |
| Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Systemic learning Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 77 of 86 Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources IIncorporating industry Operating Experience I I Total for 2f IColor: I 2g. Criteria Related to Commitment to Creating an Environment of 7 Engagement and Commitment Item Color FENOC values, basic principles and leadership strategies Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 78 of 86 Business Services Human Resources Item Color Quality of management and employee relationships Organizational commitment and shared success criteria Operations Radiation Protection Chemistry Outage Management and Work Control 7 Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Performance reviews in accordance with FENOC Performance Management Process FENOC Performance Management Process Development plans Total for 2g Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 79 of 86 Total for 2 Color:
| |
| : 3. Individuals' Commitment Area 3a. Criteria Related to Drive for Excellence Item Color 7
| |
| Maintenance Rule (a)(1) systems Number of Operator workarounds Number of Control Room deficiencies Number of temporary modifications Individual Error Rate Percent of self-identified Condition Reports Number of open Condition Report evaluations Engineering Assessment Board index Performance during major plant evolutions Addressing Operating Experience Total for 3a Color:
| |
| 3b. Criteria Related to Questioning Attitude
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| .__ ___ DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 80 of 86 Item Color Quality of pre-job briefs Percent of CRs per person per group l Number of programmatic CRs 7
| |
| Program and process error rate Raising problems Total for 3b Color:
| |
| 3c. Criteria Related to Rigorous work Control and Prudent Approach Item IColor I Event Free Clock I I I Industrial Safety Performance I I Individual Error Rate 0 I IProgram and process error rate I I Significant human performance errors result in plant transients I l I Backlog of Priority Procedure Change Requests I I
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 81 of 86 Deficiency rate for QC holds (QC only)
| |
| Rework Rate (Maintenance)
| |
| Ratio of completed to scheduled work orders per week Number of late preventive maintenance activities 7 Backlog of corrective maintenance activities Number of Maintenance Rule (a)(1) systems Performance during major plant evolutions Use of procedures and work orders Total for 3c Color:
| |
| 3d. Criteria Related to Open Communications Item Color Number of CRs per person per group l Worker confidence in raising safety concerns Feedback from 4Cs meetings Keep Improving Performance program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ____________________________________DBB P-VP-DO 02 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 82 of 86 Pre-job briefings Intra-department information sharing Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance 7 Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Item Color Quality of Communication Employee awareness of SCWE policy Training on SCWE NQA interviews Worker confidence in raising safety concerns
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ___________________________________DBB P-VP-0 002 Tige: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 07 Page 83 of 86 Ratio of concerns submitted to ECP vs. NRC allegations 7
| |
| Satisfaction of employees using ECP Complaints of breach of confidentiality in ECP Management support for ECP Total for 3d Color 3e. Criteria Related to Nuclear Professionalism Item Color FENOC Performance Management Process development plans Training attendance Item Color Rework Rate (Maintenance)
| |
| Results of EAB assessments Training performance score per NOBP-TR-1501 Radiation Protection Events Procedure Compliance Personal initiative Operations Radiation Protection
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tife: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 84 of 86 Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Item [Color Ownership Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002 tle: Revision: Page RESTART READINESS REVIEW EXTENDED IPLANT OUTAGE 07 Page 85 of 86 Client Services Business Services Human Resources Implementation of CAP Improvements Root cause evaluation quality CR category accuracy CR self identification rate Employee Survey NQA interviews Item Color Timeliness of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 07 Page 86 of 86 7 Supply Chain Client Services Business Services Human Resources Total for 3e IColor:
| |
| i Total for 3 l Color:
| |
| | |
| Docket Number 50-346 License Number NPF-3 Serial Number 1-1335 Revision 8 of the Nuclear Operating Business Practice Restart Readiness Review Extended Plant Outage (DBBP-VP-0002)
| |
| (86 pages to follow)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 Tifie: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 1 of 86 RESTART READINESS REVIEW EXTENDED PLANT OUTAGE Approved:
| |
| Vice Presiden Approves Effective Date NOV 13 ;1O3
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 2 of 86 TABLE OF CONTENTS Page 1.0 PURPOSE ............ 3 2.0 APPLICABILITY ............. 3 3.0 RESPONSIBILITY ............. 3 4.0 DETAILS ............. 4 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS ..................... 7 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX ......................................... 9 ATTACHMENT 3: RESTART READINESS REVIEW FOR PLANT SHUTDOWN ......................................... 12 ATTACHMENT 4: PLANT INSPECTION DOCUMENTATION SHEET .................. 13 I ATTACHMENT 5: OPERATIONAL READINESS AFFIRMATION FORM .............. 14 ATTACHMENT 6: CORE CONFIGURATION AFFIRMATION FORM .................... 15 ATTACHMENT 7: REACTOR STARTUP AFFIRMATION FORM .......................... 16 ATTACHMENT 8 SYSTEM ENGINEER/PROGRAM OWNER READINESS AFFIRMATION FORM ......................................... 17 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE .................................. 18 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA ................. 21 ATTACHMENT 10: SAFETY CULTURE ASSESSMENT CRITERIA MATRIX ........ 59 ATTACHMENT 11: SAFETY CULTURE ATTRIBUTE ASSESSMENT MATRIX... 60
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ___________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 3 of 86 1.0 PURPOSE The purpose of this Business Practice is to provide assurance that the Davis-Besse Nuclear Power Station is ready to restart following the extended plant outage. The framework detailed here establishes a review process for areas not addressed by the Restart Test Plan and DB startup procedures to ensure that Davis-Besse's materiel condition, programs and processes, and organization, including the organization's safety culture are ready for plant restart and safe, reliable operation.
| |
| 2.0 APPLICABILITY This Business Practice applies to the first plant startup following the extended plant outage which began on February 16, 2002. It also applies to subsequent startups from this same outage and therefore shall be re-performed if the startup is halted resulting in an entry into a lower mode.
| |
| Adherence to this Business Practice is mandatory.
| |
| 3.0 RESPONSIBILITY The Vice President-Nuclear is responsible for initiating the Restart Readiness Review Process.
| |
| Each Section Manager and 0350 Restart List Responsible Individual is responsible for the accuracy and adequacy of the reviews performed, actions taken and action plans developed during the review process.
| |
| The Section Managers of Plant Engineering and Operations and the Director-Work Management (Maintenance) are responsible for ensuring plant walk-down inspections are conducted prior to power ascension.
| |
| The Manager-Operations is responsible for affirming: 1) the Operations Section has completed a review of operational readiness and is ready to support the safe and reliable startup and operation of the plant through the next operating cycle; 2) that the plant is in a condition of materiel readiness to support safe and reliable startup and operation and the operating crews are prepared and ready to startup and operate the plant in a safe and reliable manner through the next operating cycle.
| |
| The Supervisor-DB Reactor Engineering is responsible for: 1) following movement of fuel in the reactor core, changes to reactivity control components in the reactor core and/or changes to nuclear instrumentation in the reactor core, verifying that the reactor core is configured to support safe and reliable operation through the cycle.
| |
| This affirmation is required prior to installation of the reactor head; 2) prior to reactor startup, verifying that the required conditions exist to support a safe startup and power ascension.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| .DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 4 of 86 Each Director is responsible for the final review of the assessment and action plans developed during the review process by the sections in his department.
| |
| The Chief Operating Officer is responsible for final approval prior to plant restart.
| |
| 4.0 DETAILS
| |
| : 1. The review process shall be initiated early enough to ensure it is completed prior to entry into Modes 6, 4 and 2. The review shall be completed by the milestone date as determined by the responsible Shift Outage Director. All Sections and 0350 Checklist Responsible Individuals, shall submit restart readiness reviews by the milestone dates; not all items have to be complete, provided bullet (4) in Step 3 is appropriately addressed.
| |
| : 2. The process consists of the review and assessment of the specified Restart Readiness Review Indicators. The matrix on Attachment 2 designates the minimum indicators from Attachment 1 that are applicable to each Section and/or 0350 Checklist Item. Each Section and 0350 Checklist Responsible Individual, shall address applicable indicators and should participate in the review and assessment of any indicator for which meaningful input can be provided.
| |
| : 3. The methodology for the review process consists of the following steps:
| |
| * Monitor plant system/component work activity progress during the outage
| |
| * Monitor emergent work/issues during the outage for shutdown concerns
| |
| * Monitor personnel and administrative issues during the outage for restart concerns
| |
| * Assess Restart Readiness Review Indicators as identified on Attachment 1, as applicable per Attachment 2.
| |
| * Assess Safety Culture as identified on Attachment 9, Page 18
| |
| * Identify items to be complete prior to the designated Mode (6, 4 or 2) that have not been completed as of the Shift Outage Director milestone date.
| |
| Ensure a reference is associated with each incomplete item that addresses completion of that item before needed in that mode.
| |
| : 4. Results of the individual indicator assessments, including the status of action plans to support plant restart, will be indicated on Attachment 1, and acknowledged by the signature of the Section Manager or 0350 Checklist Responsible Individual. Indicator assessments should be marked as Final (all conditions are acceptable to support plant restart) or Preliminary (one or more indicators are not currently complete or acceptable and action plans will support plant restart when complete). Details on incomplete items and the status of action plans to eliminate them shall be attached.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 5 of 86
| |
| : 5. The signed original Restart Readiness Review Indicators (Attachment 1) should be provided to the Restart Action Process Administrator at the end of the Readiness meetings for inclusion in the Mode Readiness notebook
| |
| : 6. Restart Readiness Review Indicators shall be reviewed by the Senior Leadership Team and approved by the Vice President-Nuclear or Chief Operating Officer, as provided on Attachment 3.
| |
| : 7. Completed Attachments 1 and 3 shall be included with the documentation package assembled in accordance with this Business Practice.
| |
| : 8. Walk down inspections shall be completed prior to power ascension as described in this document and in accordance with EN-DP-01 503, System Walkdowns or Plant Engineering Policy PE-02, System Walkdown Checklist. Results of walkdown inspections shall be documented in Attachment 4 and submitted to the on-shift Engineering Manager.
| |
| : 9. The Shift Manager of each crew should:
| |
| : a. Conduct reasonable and appropriate activities to accomplish the objective of attaining, demonstrating and affirming operational readiness. The Shift Manager should consider the following to support the affirmation of operating crew readiness:
| |
| -adequacy of staffing levels, personnel experience and qualification levels.
| |
| -assure Operations personnel believe the Station can be operated safely by eliciting any outstanding safety concerns from shift personnel and ensuring that the concerns are resolved.
| |
| -completion of appropriate personnel refresher training of shift personnel, including training on plant, procedures and process changes.
| |
| -completion of training of shift personnel on the startup and power ascension plan. This training shall include discussion on the expected behavior and characteristics of the core for this startup.
| |
| : b. Affirm to the best of their knowledge and judgment that the plant is in a condition of materiel readiness to support safe and reliable startup and operation. The Shift Manager should consider the following:
| |
| -adequacy of the materiel condition of the plant, including the current status of operator work-arounds, to support safe and reliable restart and operation during the next operating cycle.
| |
| -all outage-related temporary fire suppression systems removed and fire protection requirements or commitments ready to support startup.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 6 of 86
| |
| -temporary modifications, temporary power feeds, removed/MCCs restored, installed temporary power feeds, if applicable, reviewed to ensure they will not affect safety or operations.
| |
| : c. Complete Attachment 5.
| |
| : 10. The Supervisor-DB Reactor Engineering shall, following movement of fuel, changes to reactivity control components and/or changes to nuclear instrumentation in the reactor core, verify that the reactor core is configured to support safe and reliable operation through the cycle. This affirmation is required prior to installation of the reactor head. Attachment 6, Core Configuration Affirmation Form, details the required review areas and documents the affirmation.
| |
| : 11. The Supervisor-DB Reactor Engineering, shall, prior to a reactor startup, verify that the required conditions exist to support a safe startup and power ascension.
| |
| Attachment 7, Reactor Startup Affirmation Form, details the required review areas and documents that affirmation.
| |
| : 12. Each System Engineer and 0350 Program Owner shall complete Attachment 8, System Engineer/Program Owner Readiness Affirmation Form. The System Engineer forms shall be part of the Plant Engineering Manager's presentation for restart readiness. The 0350 Program Owner's form will be used as part of their readiness discussion. Selected systems (System Engineers) will be identified by the Manager-Operations, Manager-Plant Engineering and Plant Manager to be discussed during the Restart Readiness Review Meetings.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumbeDBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 7 of 86 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS Page 1 of 2 Plant Section or 0350 Checklist Item Acceptable Mode_ to Support Restart?
| |
| Yes/No/NA 1 All assigned outage work activities are complete to support plant restart and operations. This includes a reconfirmation that previous dispositions of nonconforming conditions or Preventive Maintenance deferrals continue to provide a justification for continued operation. (Attachment 2, Column a) 2 Outstanding Operability Evaluations, CR corrective actions and new CRs generated during the shutdown have been evaluated for operability concerns are either closed or determined to have no impact on operability. (Attachment 2, Column b) 3 Regulatory and internal commitments have been evaluated for operability concerns or restart restraints and are either closed or determined to have no impact on operability. (Attachment 2, Column c) 4 Housekeeping walkdowns utilizing the guidelines of NG-DB-00215, Material Readiness and Housekeeping Inspection Program are complete. (Attachment 2, Column d) 5 The Power Ascension Schedule has been reviewed for accuracy and adequacy ensuring: (Attachment 2, Column e)
| |
| * Post maintenance retest and special testing are identified and scheduled correctly with instructions in place.
| |
| * Planned walkdowns are scheduled appropriately 6 Personnel, materials and special test equipment necessary to support power ascension retest and walkdown activities have been identified and availability is ensured during power ascension. (Attachment 2, Column f) 7 Contingency plans are established for immediate response to plan and repair steam leaks or high-risk test failures. (Attachment 2, Column g) 8 Standing orders have been reviewed for continued applicability and system status sheets completed as required by DB-OP-0691 1, Pre-Startup Checklist. (Attachment 2, Column h) 9 System walkdowns have been performed by Plant Engineering and Maintenance, as directed by Operations, to ensure system readiness for restart.
| |
| 10 Operating Experience reports have been reviewed to ensure no potential operability concerns.
| |
| 11 Procedure alterations/PCRs are ready for mode change or restart.
| |
| 12 Work around and burdens identified prior to or during shutdown and not corrected have been confirmed acceptable. (Attachment 2, Column i)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| .___________________________________________ DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 8 of 86 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS (Continued)
| |
| Page 2 of 2 Plant Section or 0350 Checklist Item_ Acceptable to Support Mode Restart?
| |
| Yes/No/NA 13 All Management and Human Performance Improvement Plan items required for restart are complete. (Attachment 2, Column j) 14 All 0350 Discovery Action Plan milestones identified as required for restart are complete. (Attachment 2, Column k) 15 All 0350 Implementation Action Plan milestones identified as required for restart are complete. (Attachment 2, Column I) 16 All Section Corrective Action Program Improvement Plan activities required for restart have been validated as ready to support restart. (Attachment 2, Column ii) 17 All Condition Reports and corrective actions, work orders, modifications (including EWRs and ECRs) categorized as 0350 are completed. (Attachment 2, Columns m, n, o) 18 All Condition Reports and corrective actions, work orders, and modifications (including EWRs and ECRs) designated as required for restart by the Restart Station Review Board are complete. (Attachment 2, Columns q, r, s) 19 Any required for restart Condition Report or corrective action, work order or modification (including EWRs and ECRs), which cannot be completed prior to restart, has a written exemption from the RSRB. (Attachment 2, Column u) 20 All pending allegations have been reviewed and determined not to affect the restart of the plant. (Attachment 2, Column v) 21 Integrated Restart Report per NG-VP-00100 signed by the SLT. (Attachment 2, Column w)
| |
| Check one Preliminary: I have reviewed the assessment of the Restart Readiness Review Indicators as indicated above and confirm that the attached plans will support plant restart when complete.
| |
| Final: I have reviewed the assessment of the Restart Readiness Review Indicators as indicated above and concur that the current conditions support plant restart.
| |
| Section Manager or 0350 Checklist Individual (Please Print Your Name)
| |
| Signature: Date Section Manager or 0350 Checklist Individual
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| _____ ____ _____ ____D B B P-VP-0002 Tifte: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 9 of 86 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 1 of 3 o ilu E0 oC ) } D C- >U E w a) a.) w t5 a u
| |
| o~
| |
| 0 -
| |
| E I2 0
| |
| 50 'COD e ro0 0C-a L 4 2U)a 00
| |
| ( UO vD a)
| |
| >< co 2 v
| |
| °EŽ
| |
| .0 L) CO0U x 0) co :
| |
| co. C.. . a__ Co_
| |
| Plant Opraios_
| |
| Operations X x
| |
| X x
| |
| X x x WxX x X___XX_
| |
| x x x RP_ xXXX x X X _X X _ ___XX Chemistry X X X X X X X X Outage Management X X X X X X X and Work Control FIN X X X X -. X X Mechanical X X X X X X X E&C X X X X X X X Maint. Serv. X X X X X X Training X X X X Safety X X X X Engineering _________
| |
| Plant Engineering X X X X X X X = = X X Design Engineering X X X X X X Project Management X X X X X X RRT XX _ X X Reactor Engineering X X IX x x x x Support Services _I___
| |
| Regulatory Affairs X X X X X X X X (includes Emer. Prep.) _
| |
| Quality Services X X_ X l X Security X X x Other Sections QA/QC X X X X X Supply Chain X X X X Client Services X __ X Business Services - - Xi - X Human Resources - - - X - X X
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _____________________________________DBBP-VP-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 10 of 86 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 2 of 3 0350 CHECKLIST ITEM RESTART READINESS REVIEW INDICATOR MATRIX
| |
| .0
| |
| _ Cal O) ._ 0 0 Ou t CC C X )
| |
| oE U2V_ U 2 Sc CMO E 0E° 0350 Checklist Item
| |
| : 1. Adequacy of Root Cause Determinations- X X X X S. Loehlein, M. Roder, D. Gudger, J. Powers, D. Eshelman, F. von Ahn, L. Myers* _ _
| |
| : 2. Adequacy of Safety Significant Structures, X X X X X Systems and Components-D. Baker, A.
| |
| Stallard, T. Chambers, R. Hovland, J.
| |
| O'Neill*
| |
| : 3. Adequacy of Safety Significant Programs--A. X X X McAllister, L. Dohrmann, S. Loehlein, C.
| |
| Daft, J. Grabnar, R.Farrell, D. Schreiner, R.
| |
| Perry, K. Ostrowski*
| |
| : 4. Adequacy of Organizational Effectiveness X X X X X and Human Performance- M. Bezilla, J.
| |
| Powers* _ _ _
| |
| : 5. Readiness for Restart-C. Price, F. VonAhn, X X R. Hovland, R. Schrauder, A. Stallard, J.
| |
| Hirsch*
| |
| : 6. Licensing Issue Resolution-J. Powers, K. X X Ostrowski* _
| |
| : 7. Confirmatory Action Letter Resolution--L. X Myers, C. Price K. Ostrowski_
| |
| * Or an approved designated alternate
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002 rite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 11 of 86 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 3 of 3 REQUIRED FOR RESTART READINESS REVIEW INDICATOR MATRIX t
| |
| S0 U) sz00JW- .0 .
| |
| is 2 I-eWCh 1~Jo U
| |
| C
| |
| \ O i E~~~~~
| |
| FE"0~~~~~~~
| |
| 0 ,0 5: 0 cC i003 0
| |
| . W.C ..
| |
| Restart Station Review X X X x Board Quality Services X Employee Concerns x Program .
| |
| Station Review Board x (Plant Operating Review Committee)
| |
| Company Nuclear Review x Board .
| |
| Restart Overview Panel x
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| _________________________________________ DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 12 of 86 ATTACHMENT 3: RESTART READINESS REVIEW FOR PLANT STARTUP Restart/Mode Chance Recommended By:
| |
| Mode_
| |
| Plant Manager-Davis-Besse Nuclear Power Station Date Director-Davis-Besse Nuclear Engineering Date Director-Davis-Besse Work Management Date Director-Davis-Besse Support Services Date Director-Davis-Besse Restart Date RESTART /MODE CHANGE APPROVAL:
| |
| Vice President-Nuclear Date OprtnffcrDt ChiefChie Operating Officer Date
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision *: Page
| |
| . RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 13 of 86 ATTACHMENT 4: PLANT INSPECTION/WALKDOWN DOCUMENTATION SHEET Page 1 of 1 Mode_
| |
| ASSET LABEL:
| |
| Or AREA INSPECTED:_
| |
| NOUN NAME:
| |
| LOCATION:
| |
| DESCRIPTION:
| |
| MAINTENANCE TAG/WORK ORDER #:
| |
| CONDITION REPORT INITIATED (#)_
| |
| MODE RESTRAINT: Yes No SUBMITTED BY: DATEITIME /
| |
| (please print your name)
| |
| SIGNATURE:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| .___________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 14 of 86 ATTACHMENT 5: OPERATIONAL READINESS AFFIRMATION FORM Shift Designator:
| |
| Shift Manager:
| |
| (Please Print)
| |
| Mode_
| |
| Review Summary:
| |
| The Shift Manager should initial each item below to affirm that he/she and the operating crew have completed the required actions:
| |
| Shift staffing levels, including personnel experience and qualification levels, are adequate.
| |
| Operations personnel believe the station can be operated safely. All safety concerns have been identified and addressed.
| |
| Appropriate refresher training of shift personnel, including training on plant, procedure and process changes, has been completed.
| |
| Appropriate training of shift personnel on the startup and power ascension plan, have been completed, including discussions on core behavior and characteristics for this startup.
| |
| The materiel condition of the plant, including the current status of operator work-arounds, is adequate to support safe and reliable restart and operation.
| |
| Affirmation:
| |
| Based upon an evaluation of the considerations set forth in Details, 4.0, and to the best of my knowledge and judgment, the plant is in a condition of materiel readiness to support the safe and reliable startup and power operation through the next operating cycle and the operating crew is ready to startup and operate the plant in a safe and reliable manner.
| |
| Shift Manager:
| |
| PrintlSignature/Date Reviews and Approvals:
| |
| Manager-Operations:
| |
| Print/Sianature/Date l Remarks: (Attach a continuation sheet if applicable)
| |
| | |
| RESTART READINESS REVIEW EXTENDED PLANT OUTAGE ATTACHMENT 6: CORE CONFIGURATION AFFIRMATION FORM Mode__
| |
| Review Summary:
| |
| The Supervisor-DB Reactor Engineering, should initial each item below to affirm that the required conditions exist following movement of fuel in the reactor core, changes to reactivity control components and/or changes to nuclear instrumentation in the reactor core. This affirmation is required prior to installation of the reactor head.
| |
| All new fuel assemblies loaded into the reactor core were inspected, as required, to ensure that the manufacturing and design specifications were met.
| |
| All irradiated fuel assemblies present in the reactor core were inspected, as required, and dispositioned as acceptable for operation through the cycle.
| |
| No fuel assemblies in the reactor core are known leaking assemblies.
| |
| A 10CFR50.59 Reload Safety Evaluation governing reactor core operation has been approved by the Plant Operating Review Committee (PORC)
| |
| The reactor core loading has been verified.
| |
| All reactivity control components in the reactor core will meet their design functions.
| |
| All nuclear instrumentation in the reactor core will meet their design functions.
| |
| Affirmation:
| |
| Based on my knowledge and judgment, the required conditions exist and the reactor core is configured to support safe and reliable operation through the cycle.
| |
| Supervisor-DB Reactor Engineering Print/Signature/Date Remarks: (Attach a continuation sheet if appropriate)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE __ _ 08 Page 16 of 86 ATTACHMENT 7: REACTOR STARTUP AFFIRMATION FORM Mode_
| |
| Review Summary:
| |
| The Supervisor-DB Reactor Engineering should initial each item below to affirm that the required conditions exist prior to reactor startup.
| |
| Estimated Critical Conditions have been prepared and independently verified.
| |
| Preparations are complete for any necessary Low Power Physics Testing (i.e. equipment, procedures, calculations, training)
| |
| Personnel are available, as required, to support reactor startup and power ascension to 100%.
| |
| Required training has been completed for Nuclear Fuels personnel.
| |
| Reactivity plans are available, as required, to support reactor startup and power ascension to 100%. These plans include expectations for reactor behavior with emphasis on any behavior that is different from recent plant operation.
| |
| The Core Monitoring System is operable.
| |
| All reactivity control systems will meet their design functions.
| |
| Sufficient nuclear instrumentation is available to safely startup and operate the reactor core.
| |
| There are no outstanding reactivity management issues impacting the safe operation of the reactor core.
| |
| Affirmation:
| |
| Based on my knowledge and judgment, the required conditions exist and the reactor core is ready to support a safe startup and power ascension.
| |
| Supervisor-DB Reactor Engineering Print/Signature/Date Remarks: (Attach a continuation sheet if appropriate)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Nuer:DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 08 Page 17 of 86 ATTACHMENT 8: SYSTEM ENGINEER/PROGRAM OWNER READINESS AFFIRMATION FORM Mode_
| |
| : 1. Name of System/Program:
| |
| : 2. The status of the system/program is (For systems, a brief description of the physical status of the system including System Health status and Maintenance Rule status. For programs, a brief status of the program):
| |
| : 3. System/Program is ready for Mode : Yes_ or No
| |
| : 4. The system/program is ready for Mode because: (if not ready, skip to #5)
| |
| : 5. The system/program is not ready for Mode _ because:
| |
| and the following actions are in place to address these issues:
| |
| The system/program will be ready for Mode - by: _(Date)
| |
| : 6. Items in abnormal status or configuration (workarounds, temporary modifications, Control Room deficiencies) identified and not corrected have been reviewed and determined to be acceptable: Yes_ or No (Attach a list of the above items)
| |
| : 7. Housekeeping issues associated with this system/program have been addressed for Mode : Yes_ or No (Attach a list of those not resolved)
| |
| : 8. I have the following concerns about my system and its readiness for Mode :
| |
| Briefly identify concerns. (The Restart Readiness Review process will not resolve these concerns at the meeting. They should be scheduled for presentation to the Plant Support Center if there is a concern relative to this mode change.)
| |
| : 9. Open CRs, CAs, Work Orders or Engineering modifications required for Mode (Attach a list).
| |
| Name: Extension:
| |
| (Please Print)
| |
| Signature: Signature: Date:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| | |
| ==Title:==
| |
| Revson: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 18 of 86 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 1 of 3 ASSESSMENT OF SAFETY CULTURE Assessment Summary:
| |
| Improving safety culture isa long-term activity that is monitored by Davis-Besse senior management. For Restart Readiness, it is important to show an improving safety culture with no critical areas of weakness that management evaluates as a restart concern. The individual criteria that make up the Commitment Areas may be green, white, yellow or red. Some of the Commitment Areas may be white (Policy or Corporate Commitment Area, Plant Management Commitment Area or Individual Commitment Area) however restart will not be approved if any of the three are red, or yellow without restart corrective actions being completed.
| |
| Remedial actions will be taken for any red criteria. Condition Reports will be written for all red and yellow criteria at the site and/or section level, with corrective actions to identify an existing or new plan for improvement. Corrective Actions may take credit for ongoing activities. Red criteria corrective actions will be formally presented to the Senior Leadership Team. If a Condition Report iswritten at the site level for a red or yellow Commitment Area or criteria, it will encompass any red or yellow section Commitment Area or criteria and that section need not write a separate Condition Report. Ifthere is no site wide red or yellow Commitment Area or criteria then the Section Manager will write a Condition Report for the red or yellow Commitment Area or criteria.
| |
| The threshold for rating the attributes that comprise each criteria are provided in Appendix A. These thresholds are guidelines. Management may consider other factors and adjust the ratings accordingly. Management judgment is a key factor that cannot be removed or quantified. The purpose of the collegial group review is to challenge, seek alternative input, and facilitate dialogue and to determine final criteria and Commitment color rating Ifother factors are considered, they shall be documented in an attachment to the Rating sheet. The ratings are based on convergent assessment such as: performance indicators, management observations, demonstrated performance during critical plant conditions surveys and interviews, training and feedback from independent safety culture reviews and Nuclear Quality Assurance Assessments. Each criterion will be assessed using information from the attribute reviews performed. An overall assessment of each attribute and criterion will be performed and documented explaining any that are rated as red or yellow and identifying the corrective actions needed prior to restart.
| |
| The ratings for an individual attribute will reflect recent activities or the most recent assessment data. If no applicable activities or assessments have been conducted within the past 12 months (i.e., there is no information applicable to the review period), the attribute shall be marked NA', (Not Applicable). If both objective and subjective data are available, differences in data will be evaluated and decisions on use of data made.
| |
| Safety Culture Commitment Area/Criteria Ratings:
| |
| Green: all major criteria/attributes are acceptable with afew minor criteria deviations White: all major criteria/attributes are acceptable with a few criteria requiring management attention Yellow: all major criterialattributes are acceptable with several criteria requiring prompt management action Red: several major criteria/attributes do not meet acceptable standards and require immediate management action
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 19 of 86 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 2 of 3 Each Section Manager will provide a Rating sheet (ATTACHMENT 9, Page -20,) with the Final Restart Readiness Criteria. For any individual attribute where only site-wide numbers are available (e.g. 4Cs surveys, ECP etc.), or for any individual attribute not applicable to a section (e.g. operator work-arounds for other than Operations), the Manager will NA that attribute on his backup sheets and that attribute will not be used as part of the site-wide tally for the criteria. For any attribute where surveys and/or interviews" are used as the basis for the rating, these surveys must be written but may be anonymous. Interview results will also be documented as to results although they may also be anonymous. The results for surveys or interviews will be maintained until after restart.
| |
| Documentation for Attachment 9 may be in the form of a tally for these survey or interview results.
| |
| At the final Restart Readiness Review meeting for any mode, a site-wide Rating sheet will be prepared by the management team using the individual section ratings as a guideline. The final Rating sheet will be signed by the Vice President-Nuclear and maintained with the other Restart Readiness documentation, including Attachment 11.
| |
| Preliminarily, determination of the Commitment Area/criteria color will be based on an average of the ratings of the associated criteria/attributes. Considerations include:
| |
| Greater than one red attribute or criteria means the criteria or Commitment Area can be no better than yellow. If more than two or more than 1/3 (whichever is greater) of the attributes or criteria are red, the indicator or Commitment Area shall be red.
| |
| For the overall plant ratings for Commitment Areas/criteria, management will consider whether the problems taken collectively indicate a more significant concern than indicated by the averages. For example, one section may perform more activities related to safety with respect to a certain criteria than other sections, and management may adjust the color to give greater weight to that section in determining the final color rating. Similarly, if percentages or averages alone indicate a positive rating but there were several associated safety-significant events or conditions, management may provide a more negative color rating to reflect those events or conditions.
| |
| If such an adjustment is made, it shall be documented. Generally, if all sections have similar rating, the overall rating for the plant will be the same as the ratings for the individual sections. During group review, senior management will seek to verify that the entire Restart Readiness Review team not only concurs, but also aligns behind the assessment.
| |
| At the completion of the Safety Culture Assessment, an evaluation of the significance of the overall assessment ratings for criteria to focus on the process and organization will be completed using Attachment 10 at the end of the document. A final report will then be prepared which documents how each Commitment Area, criteria and attribute was assessed and its final color rating. The report will also document any red or yellow area, criteria or attribute, corrective actions needed for restart and explain why restart is acceptable with the current condition.
| |
| Attachments 10 and 11 will be included as part of that report.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ._____ ______ __________ ______ _____D B B P-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 20 of 86 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 3 of 3 Rating Safety Culture Mode_
| |
| Item Color
| |
| : 1. Policy or Corporate Commitment Area
| |
| : a. Policies on Safety Culture and Safety Conscious Work Environment clearly state that safety isa core value and are understood by the organization
| |
| : b. Management values are clearly reflected in the Business Plan and are understood by the organization
| |
| : c. Resources are available or can be obtained to ensure safe, reliable operations
| |
| : d. Self-Assessment isa tool used to monitor, assess and improve our performance
| |
| : e. Independent Oversight is a tool used to validate acceptable performance and identify areas for improvement or corrective action
| |
| : 2. Plant Management Commitment Area
| |
| : a. There isa visible commitment to safety: nuclear, industrial, radiological and environmental
| |
| : b. Goals and roles are clear and teamwork is reinforced
| |
| : c. Ownership and accountability isevident
| |
| : d. Training and Qualification are valued
| |
| : e. Commitment to continuous improvement is evident
| |
| : f. Cross-functional work management and communication
| |
| : g. Creating an environment of engagement and commitment
| |
| : 3. Individual Commitment Area
| |
| : a. Drive for excellence-nuclear assets of people and plant are continuously improved to enhance margins of safety
| |
| : b. Questioning attitude-challenges are welcomed
| |
| : c. Rigorous work control and prudent approach-performing activities in a quality manner is the standard
| |
| : d. Open communications-associates are comfortable in voicing opinions, issues and concerns
| |
| : e. Nuclear Professionalism-persistence and urgency in identification and resolution of problems is prevalent I have reviewed the Rating of Safety Culture as indicated above and concur that the current conditions 1 Itsupport readiness for mode change. I Section Manager (Please Print Your Name)
| |
| Signature: Date_ _
| |
| Section Manager Adjustments to ratings from the standard criteria should be documented and attached to this page.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW ETENDED PLANT OUTAGE 1 08 Page 21 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 1 of 39 1.POLICY COMMITMENT AREA la. CRITERIA RELATED TO STATEMENT OF SAFETY POLICY Policies on Safety Culture and Safety Conscious Work Environment clearly state that safety is a core value and are understood by the organization ATTRIBUTE RED YELLOW WHITE GREEN Policy statement Policy statement is Policy statement is Policy statement is Policy statement is on Safety Culture* issued but it is not issued but only issued and is issued and is reinforced by occasionally reinforced frequently reinforced continuously reinforced FENOC by FENOC by FENOC by FENOC management management. management. management.
| |
| Policy statement Policy statement is Policy statement is Policy statement is Policy statement is on Safety issued but it is not issued but only issued and is issued and it is a strong Conscious Work reinforced by occasionally reinforced frequently reinforced statement of safety Environment FENOC by FENOC by FENOC conscious work (SC WE)* management. management. management. environment and often reinforced by FENOC management Making employees Policy statements Policy statements Policy statements are Policy statements are aware of policy simply issued as distributed separately communicated by at communicated to statements* part of FENOC to employees in least two employees and (Explain why white Business Plan. memo. means.(e.g., hard emphasized regularly in is acceptable if there copy distribution, meetings and face to is no face to face newsletters, group face communication.
| |
| communication) meetings, training, stand down).
| |
| Employee Surveys/interviews Surveys/interviews Surveys/interviews Surveys/interviews understanding of indicate less than Indicate that 70-80% of indicate that 80-90% indicate that more than policies" 70% of employees the employees of employees 90% of employees understand the understand the understand the understand the policies policies, policies and consider policies and consider and consider safety a safety a FE value. safety a FE value. FE value and the normal way to do business.
| |
| Worker Surveys/interviews Surveys/interviews Surveys/interviews Surveysinterviews understanding of indicate that less indicate that between indicate that between indicate that more than responsibilty to than 85% of workers 85-90% of workers 90-95% of workers 95% of workers raise safety understand their understand their understand their understand their concerns** responsibility to responsibility to raise responsibility to raise responsibility to raise raise nuclear safety nuclear safety or nuclear safety or nuclear safety or quality or quality concerns. quality concerns. quality concerns. concerns.
| |
| Site wide assessment only. Data provided from Edventures survey results
| |
| ** Site wide assessment only. Data provided from Edventures survey results and 4Cs.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 08 Page 22 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 2 of 39
| |
| : 1. POLICY COMMITMENT AREA lb. CRITERIA RELATED TO MANAGEMENT VALUES Management values are clearly reflected in the Business Plan and are understood by the organization ATTRIBUTE RED YELLOW WHITE GREEN Corporate values* There is no There is a There is a corporate There is a corporate corporate level corporate level level statement of level statement of statement of statement of commitment to commitment to safety.
| |
| safety values. commitment to safety. FirstEnergy FirstEnergy FirstEnergy safety. management meets management meets management FirstEnergy occasionally with frequently with plant does not management plant personnel to personnel to express its express its meets express its safety safety values.
| |
| safety values to infrequently with values.
| |
| plant personnel. plant personnel to express its safety values.
| |
| Statement of There is no The statement of The statement of The statement of mission, vision, statement of Mission, Vision, Mission, Vision, and Mission, Vision, and and values' Mission, Vision, and Values Values places greater Values emphasizes and Values and places weight on weight on safety than safety first, then allows employees safety and often on production/profits consideration of believe focus is employees and most employees production and profits on production believe the agree that the and over 90% of and profits. overriding focus overriding priority is employees agree based Is safety on safety on surveys.
| |
| FENOC Business Business Plan Business Plan Business Plan Business Plan contains Plan* contains no contains few contains Strategic Strategic Objective Strategic Strategic Objective Measures Measures on safety Objective Objective on safety with and all are being fully Measures on Measures on implementation plans. implemented.
| |
| safety. safety but no implementation plans
| |
| *Site wide assessment only. Data provided by Senior Management
| |
| ** Site wide assessment only. Data provided from Edventures survey results
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| _____________________________________DBB P-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 23 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 3 of 39
| |
| : 1. POLICY COMMITMENT AREA lc. CRITERIA RELATED TO RESOURCES Resources are available or can be obtained to ensure safe, reliable operations ATTRIBUTE RED YELLOW WHITE GREEN Adequacy of More than five More than three Three or less All management management supervisor or above supervisor or supervisor or above positions are filled with resources* positions are not above positions positions are not filled ANSI qualified FENOC filled with ANSI are not filled with with ANSI qualified individuals.
| |
| qualified FENOC ANSI qualified FENOC individuals.
| |
| individuals. FENOC individuals.
| |
| Adequacy of More than four Three or four One or two sections Each section has a full personnel sections do not have sections do not do not have sufficient complement of resources*# sufficient personnel have sufficient personnel to perform personnel (minus to perform their personnel to their assigned normal attrition) to assigned perform their responsibilities perform ts assigned responsibilities assigned without contractor responsibilities.
| |
| without contractor responsibilities support support without contractor support Adequacy of Risk significant The majority of All risk significant Sufficient funding exists funding* activities, to improve identified risk identified to perform more than nuclear safety, as significant improvements to just risk significant defined by the improvements to nuclear safety, as improvements, as Senior Leadership nuclear safety, as identified by the PRC identified by the PRC in Team and Project identified by the for the plant, plant, programs and Review Committee PRC for the plant, programs, or other other activities to (PRC) are not being programs, or activities, are funded improve nuclear safety.
| |
| funded in a timely other activities, in a timely manner.
| |
| manner and funding are funded in a was requested and timely manner.
| |
| rejected by FENOC Executive Management.
| |
| * Site wide assessment only. Data provided by Human Resources
| |
| *#Significance evaluation regarding resources will be discussed depending on contractor support by section. Color identified for site after section discussion
| |
| *Site wide assessment only. Data provided by the chairman of the PRC
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberDBBP-VP-0002 Tifle: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 24 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 4 of 39
| |
| : 1. POLICY COMMITMENT AREA 1c. CRITERIA RELATED TO RESOURCES (continued)
| |
| Resources are available or can be obtained to ensure safe, reliable operations Adequacy of tools, More than 25 % Between 20- Between 10-20% of Less than 10% of material and of scheduled 25% of scheduled scheduled tasks scheduled tasks PMs, equipment to tasks (PMs, tasks (PMs, Work (PMs, Work Orders, Work Orders, ECRs complete site Work Orders, Orders, ECRs ECRs and projects) and projects) are not tasks* ECRs and and projects) are are not being being completed by the projects) are not not being completed by the site site in a timely manner being completed completed by the in a timely manner due to lack of tools, by the site in a site in a timely due to lack of tools, material or equipment.
| |
| timely manner manner due to material or due to lack of lack of tools, equipment.
| |
| tools, material or material or equipment. equipment.
| |
| Adequacy of tools, More than 25% Between 20-25% Between 10-20% of Less than 10% of key material and of key scheduled of key scheduled key scheduled tasks scheduled tasks are not equipment to tasks are not tasks are not are not being being completed by the complete Section being completed being completed completed by the section in a timely tasks by the section in by the section in section in a timely manner due to lack of a timely manner a timely manner manner due to lack of tools, material or due to lack of due to lack of tools, material or equipment.
| |
| tools, material or tools, material or equipment.
| |
| equipment. equipment.
| |
| *Site wide assessment only. Data provided by Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 25 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 5 of 39
| |
| : 1. POLICY COMMITMENT AREA Id. CRITERIA RELATED TO SELF-ASSESSMENT Self-Assessment is a tool used to monitor, assess and improve our erformance ATTRIBUTE RED YELLOW WHITE GREEN Use of Nuclear Less than 70% of Between 70-80% of Between 80-90% of More than 90% of the Quality the sections have the sections have the sections have sections have used Assurance to used NQA input used NQA input to used NQA input to NQA to supplement the supplement the to supplement the supplement the supplement the self- self-assessment self- self-assessment self-assessment assessment process process as defined in assessment process as defined process as defined as defined in NOBP- NOBP-LP-2004 process in NOBP-LP- 2004 in NOBP-LP-2004 LP-2004 Self- Less than 60% of Between 60-75% of Between 75-90% of More than 90% of assessments in sections (< 14) sections (15-17) sections (17-20) sections (>20) have accordance have planned have planned have planned planned ongoing self- 8 with NOBP-LP- ongoing self- ongoing self- ongoing self- assessments for 1 t &
| |
| 2004, FENOC assessments for assessments for 5 assessments for 1 2nt quarter 2004.
| |
| Ongoing Self- 11 & 21 quarter &2ndquarter 2004. & 2nd quarter 2004.
| |
| Assessment 2004.
| |
| Guideline*
| |
| Section Performance Section performance Section performance Section performance Performance indicators related to indicators exist for indicators exist for indicators exist and are Indicators safety and quality important activities important activities appropriate and are being exist for the section affecting quality and affecting quality and regularly updated for safety but less than safety and 75-89% of important activities 75% of goals are met goals are met affecting safety and quality, with more than 90% of goals met.
| |
| Personnel The performance The performance The performance The performance Performance appraisal program appraisal program appraisal program appraisal program Appraisals" does not include includes includes assessments includes assessments of assessments of assessments of of safety or quality of safety and quality of safety or quality of safety or quality of performance but some performance and the performance. performance but most appraisals have not appraisals are being employee appraisals been performed in performed in timely have not been timely manner and manner and all employees performed. some employees do have a current appraisal.
| |
| not have a current appraisal.
| |
| *Site wide assessment only. Data provided by Quality Services "Site wide assessment only. Data provided by Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE j 08 Page 26 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 6 of 39
| |
| : 1. POLICY COMMITMENT AREA le. CRITERIA RELATED TO INDEPENDENT OVERSIGHT Oversight is a tool used to show acceptable performance and identify areas for improvement and corrective actions.
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Nuclear The Nuclear The Nuclear The Nuclear The Nuclear Committee Committee of Committee of the Committee Committee has safety has safety performance Board of Board has little occasionally discusses performance as a part as a part of the agenda Directors* focus on safety safety performance as of the agenda every every meeting and performance in the a topic in the agenda. meeting requests additional agenda. presentations relative to specific issues to monitor performance Company The CNRB has a The CNRB agenda The CNRB agenda The CNRB agenda has Nuclear Review safety has a safety has a safety a safety discussion Board (CNRB)+ performance discussion and discussion at every every meeting and is assessment monitors safety meeting and reviews proactive in providing discussion on the performance presentations on safety focus actions for agenda. safety focus issues FENOC Nuclear Quality NQA isnot Some NQA audits or NQA audits or NQA is regularly Assurance performing audits assessments were assessments were performing audits and (NQA)** or assessments of performed when performed when assessments of important safety required and a number required, for important important safety activities and not of areas of concern safety activities and activities and identifying finding areas of were identified for some Significant key issues for concern causing important safety Conditions Adverse to improvement that are Significant activities causing Quality were noted below the Significant Conditions Significant Conditions Condition Adverse to Adverse to Quality Adverse to Quality Quality threshold.
| |
| Learning from Personnel in the Personnel in the Personnel in the Personnel in the section the experience section do not section seldom section occasionally routinely participate in of the industry participate in participate in industry participate in industry industry committees, industry committees, visit other committees, visit other visit other sites or host committees, visit sites or host personnel sites or host personnel personnel from other other sites or host from other sites from other sites sites personnel from other sites
| |
| *Site wide assessment only. Data provided by Senior Management
| |
| +Slte wide assessment only. Data provided by NQA Manager or VP Oversight
| |
| **This item is assessed by NQA only.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 27 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 7 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Management There is a There is a management There is a There is a management observations management observation program management observation program performed as observation program and 65-75% of observation program and more than 90% are scheduled with and less than 65% management and 76-90% are performed as proper of the observations observations are performed as scheduled and less coaching* are performed as performed as scheduled and less than 5% rated as scheduled and scheduled and greater than 10% rated as overall unsat.
| |
| >90% indicate no than 10% were rated overall unsat.
| |
| coaching required. overall unsat.
| |
| Management Most management Between 50-74% of the Between 75-89% of More than 90% of the observations observations are not management the management management are self self-critical. observations performed observations observations performed critical* are self-criticai and performed are self- are self-critical and actions implemented. critical and actions actions implemented.
| |
| implemented.
| |
| Management No method has been One method has been Two means have Multiple means have emphasis on used in the last used in the last month been used in the last been used by safety to month to provide to provide emphasis on month to provide management in the last employees; emphasis on safety safety to employees in emphasis on safety to month to provide face questioning to employees in the the section (e.g., town employees in the to face emphasis on attitude section (e.g., town hall, 4Cs or All Hands section and at least safety to employees in hall, 4Cs, or All meetings, standdowns, one was face to face the section (e.g., town Hands meetings, newsletters, and (e.g., town hall, 4Cs hall, 4Cs or All Hands standdowns, training). or All Hands meetings, standdowns, newsletters, and meetings, newsletters, and training). standdowns, training).
| |
| newsletters, and training).
| |
| *Site wide assessment only. Data provided by Management Observation Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-VP-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 28 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 8 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY (continued)
| |
| There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Leadership in Leadership in Leadership in Action Leadership in Action Leadership in Action* Action includes includes discussions on includes discussions Action includes discussions on safety culture.
| |
| * on safety culture. discussions on safety culture. ^ And And safety culture.
| |
| And Employee feedback Employee feedback And Employee feedback indicates it was indicates it was very Employee indicates it was not effective effective. feedback indicates effective. And And it was very And~ ~ ndArdeffective And Leadership in Action Leadership in Action And Leadership in training has been training has been Action training has available and available and Leadership in been available and scheduled for more scheduled for more Action training has scheduled for less than 75% of than 80% of been available and than 75% of supervisors and above supervisors and scheduled for supervisors and within 12 months of above within 12 more than 85% of above within 12 new appointment.* months of new supervisors and months of new appointment.* above within 12 appointment.* months of new appointment.*
| |
| Problem solving" A problem solving In more than 5 cases, In all but one case, The problem process exists but the problem solving the problem solving solving process, there is no use of process NOP-EN-3001 process, NOP-EN- NOP-EN-3001 has the document in the has not been properly 3001 has been been properly section and CRs implemented in the properly implemented implemented in the were written to section for applicable in the section for section for document the conditions and CRs applicable conditions applicable failure to use the were written in the during the previous conditions during process during the previous quarter. quarter. the previous previous quarter. quarter.
| |
| *Sitewide assessment only. Data provided by Human Resources
| |
| **Site wide assessment only. Data provided by Plant Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 29 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 9 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY (continued)
| |
| There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Decision A Safety significant A Safety significant The majority of safety Safety significant making Condition Adverse to Condition Adverse to significant decisions decisions were made in Quality Condition Quality Condition were made inthe the section with Report indicates that Report indicates that section with adequate required information, decisions were decisions are made in information, management oversight, made in the section the section with minimal management involvement and peer in isolation without information, oversight, checking during the adequate management oversight, involvement and peer past six months as information, involvement and peer checking during the indicated by no SCAQs.
| |
| management checking during the quarter as indicated oversight, past two months. by no SCAQs.
| |
| involvement and peer checking during the past month.
| |
| Improvements There have been There have been some There have been Significant in safety minimal improvements made in obvious improvements have margin* improvements made safety margin. . improvements made been made in safety in safety margin . in safety margin. margin.).
| |
| Plant activities A significant plant Less than 2 Condition Significant plant Significant plant receive proper event, associated Adverse to Quality CRs activities associated activities associated management with the section, associated with the with the section had a with the section had a aftention and occurred during the section were written management plan management plan with safety focus previous quarter and due to lack of with a management a management sponsor a lack of a management attention sponsor and and management (Reference management or lack of safety focus management oversight scheduled for NG-DB-00800) attention or safety during the previous oversight scheduled the duration of the focus was indicated quarter. for the duration of the activity and no CAQ and an SCAQ activity and only one events occurred during written. CAQ event occurred the previous quarter.
| |
| indicating a lack of management attention during the previous quarter.
| |
| *Site wide assessment only. Data provided by Design Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE VNumber
| |
| _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ D B B P -V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 30 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 10 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2.b CRITERIA RELATED TO ROLES AND TEAMWORK Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Understanding Station surveys Station surveys Station surveys and/or Station surveys that safety is and/or interviews and/or interviews, interviews show that 80- and/or interviews highest priority* show that less show that 70-80% 90% of employees, show that more than than 70% of of employees, understand that safety is 90% of employees in employees understand that the highest priority. that safety is the understand that safety is the highest highest priority.
| |
| safety is the priority.
| |
| highest priority.
| |
| Program Five of the 61 All 61 Phase 1 All 61 Phase 1 All 61 Phase 1 ownership Phase I programs programs in the programs in the program programs in the in the program program review review have assigned program review have review do not have have assigned owners. With several assigned owners. In assigned owners owners and more exceptions, program general, program and five CRs were than three CRs owners are owners are written against were written on implementing their implementing their different programs different programs assigned responsibilities assigned in the past quarter. in the past quarter. and less than 3 CRs responsibilities and were written on different no CRs were written programs in the past against programs in quarter. the last quarter.
| |
| Ownership of More than 5% of 5%of SCAQ Less than 5%of SCAQ Less than 5% of corrective SCAQ remedial remedial or remedial or preventive SCAQ remedial and actions and preventive preventive restart restart required preventive restart restart required required corrective corrective actions and required corrective Does not include corrective actions actions and 10% of 10% of CAQ remedial actions and less than CRs or CAs linked and more than CAQ remedial and and preventive restart 1 0 of CAQ remedial to P3 activities. 10% of CAQ preventive restart required corrective requpredective remedial and required corrective actions for the section, required corrective preventive restart actions for the have received 2 actions for the section required corrective section, have extensions for the than 2 extensions for actions for the received more than previous quarter. the previous quarter.
| |
| section have 2 extensions for the required more previous quarter.
| |
| than 4 extensions for the previous quarter.
| |
| *Site wide assessment only. Data provided from Edventures survey results
| |
| **Site wide assessment only. Data provided by Plant Engineering Manager.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Title. Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 31 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 11 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2b. CRITERIA RELATED TO ROLES AND TEAMWORK (continued)
| |
| Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Ownership of The quality of The quality of The quality of The quality of engineering engineering engineering engineering engineering products as products as products as products as products as measured by the EAB is measured by the measured by the measured by the measured by the 1.0 or less.
| |
| Engineering EAB is greater EAB is between EAB is between 2.0 Assessment Board than 3.0. 3.0 and 2.1. and 1.1.
| |
| (EAB)*
| |
| Effectiveness of The individual The individual The individual error The individual error rate supervision of error rate is >0. error rate is <.45- rate is<.35->.26 is<0.26 individual errors individuals" 45 Individual >.36 individual individual errors per per 10,000 hours errors per errors per 10,000 10,000 hours worked.
| |
| 10,000 hours hours worked. worked.
| |
| worked.
| |
| Intra-department As a Manager, I As a Manager, I As a Manager, I As a Manager, I believe teamwork and believe there is believe there is believe alignment is alignment and teamwork alignment ((Some no alignment minimal improving and are obvious among unit supervisors and little alignment and teamwork can be managers in all activities will input to this teamwork some teamwork seen in some key of my department.
| |
| attribute, such as, among my among my activities among my Reactor Department's Department's Department's Engineering and managers. managers. managers.
| |
| RRT.)
| |
| Expectations There are More than 90% More than 95% of There are statements of statements of of sections have sections have expectations for all expectations for statements of statements of sections and managers less than 90% expectations and expectations and all are reinforcing them and of sections and most employees employees meet employees understand employees are not familiar them. and implement them.
| |
| routinely ignore with them.
| |
| them.
| |
| *Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| *Site wide assessment only. Data provided by Human Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Numer
| |
| __ __ __ __ _ __ __ __ __ _DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page
| |
| - RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 32 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 12 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2b. CRITERIA RELATED TO ROLES AND TEAMWORK (continued)
| |
| Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Trust, openness 4Cs surveys 4Cs surveys 4Cs surveys show 4Cs surveys show more and focused show less than show 50-70% of 70-90% of than 90% of employees commitments 50% of employees feel employees feel that feel that work groups employees feel that work groups work groups display display high levels of that work groups display high high levels of trust, trust, openness and display high levels of trust, openness and commitment.
| |
| levels of trust, openness and commitment.
| |
| openness and commitment.
| |
| commitment.
| |
| Clear goals and No clear goals Goals and Goals and priorities Employees are clear priorities and priorities priorities exist for exist for the section about goals and have been the section but and most employees priorities for the section established for are not understand and own as well as how their role the section adequately them. contributes to achieving understood and them.
| |
| owned by some employees.
| |
| Input and No employee Only managers Managers and Employees are involvement input and and supervisors supervisors appropriately involved in involvement are involved in occasionally request setting department goals occurs in the the setting of input/involvement and establishing work setting of department goals from employees in priorities.
| |
| department and establishing the setting of goals and work priorities. department goals establishing and establishing work priorities. work priorities.
| |
| Site wide assessment only. Data provided by Chief Operating Officer
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED l PLANT OUTAGE I 08 Page 33 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 13 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY Ownerhip and accountability is evident ATTRIBUTE RED YELLOW WHITE GREEN Performance Less than 70% of Between 70-80% Between 80-90% of More than 90% of reviews in performance of performance performance reviews performance reviews for accordance with reviews for the reviews for the for the section were the section were FENOC section were section were completed for the completed for the review Performance completed for the completed for the review period period Management review period review period Process*
| |
| Development Less than 70% of Between 7040% Between 80-90% of More than 90% of plans* managers and of managers and managers and managers and supervisors have supervisors have supervisors have supervisors have development development development plans development plans plans submitted plans submitted submitted to HR submitted to HR to HR to HR Restart There is no A restart A restart readiness A restart readiness Readiness restart readiness readiness review review process review process exists Reviews' review process. process exists exists and is and is implemented but implemented with efficiently and with implementation is the majority of participation by poor as shown by Managers and the Managers and the lack of Manager Senior Leadership Senior Leadership Team participation. Team participation.
| |
| Worker Surveys and/or Surveys and/or Surveys and/or Surveys and/or understanding of interviews interviews interviews indicate interviews indicate that their responsibility indicate that less indicate that that between 90- more than 95% of to raise safety than 80% of between 80-90% 95% of workers workers understand their concerns# workers of workers understand their responsibility to raise understand their understand their responsibility to nuclear safety or quality responsibility to responsibility to raise nuclear safety concerns.
| |
| raise nuclear raise nuclear or quality concerns.
| |
| safety or quality safety or quality concerns. concerns.
| |
| *Sitewide assessment only. Data provided by Human Resources "Site wide assessment only. Data provided through discussion at the Restart Readiness Review meeting
| |
| # Site wide assessment only. Data provided from Edventures survey results
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ____ ____ ____ ____ ____D BB P-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 34 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 14 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY(continued)
| |
| Ownership and accountability is evident Willingness to Surveys show Surveys show Surveys show that Surveys show that more raise safety that less than that between 85- between 90-95% of than 95% of personnel concems* 85% of personnel 90% of personnel personnel are willing are willing to raise safety are willing to are willing to to raise safety concerns through their raise safety raise safety concerns through supervisor, a CR or concerns through concerns through their supervisor, a ECP.
| |
| their supervisor, a their supervisor, a CR or ECP.
| |
| CR or ECP. CR or ECP.
| |
| SRO reviews for Less than 90% Between 90-95% Between 95-98 % More than 98% were Operability are were completed were completed were completed completed within 24 performed in a within 24 hours. within 24 hours. within 24 hours. hours.
| |
| timely manner for the identified period of this review' System Less than 80% Between 80-90% Between 90-95% of More than 95% of the assessments+ of restart required of the restart the restart required restart required improvements in required improvements in improvements in safety safety have been improvements in safety have been have been implemented implemented at safety have been implemented at this at this time this time. implemented at time.
| |
| this time.
| |
| *Site wide assessment only. Data provided by 4Cs program and or Employee Concerns Program "This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Plant Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Mile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I 08 Page 35 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 15 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY (continued)
| |
| Ownership and accountability is evident NQA field NQA field NQA field NQA field NQA field assessments assessments assessments assessments assessments show show that managers and show that show that that managers and supervisors are managers and managers and supervisors are generally effective.
| |
| supervisors are supervisors are generally effective, generally generally with afew ineffective. effective, with exceptions.
| |
| several noteworthy exceptions.
| |
| Management Less than 80% Between 80-85% Between 85-95% of More than 95% of observations of management of management management management leading to participating in participating in participating in the participating in the coaching+ the Management the Management Management Management Observation Observation Observation Observation Program Program, have Program, have Program, have have performed a performed a performed a performed a coaching session in the coaching coaching session coaching session in last month.
| |
| session In the in the last month. the last month.
| |
| last month.
| |
| Timeliness of Less than 50% Between 50% Between 75% and More than 90% of my corrective actions of my section's and 74% of my 89% of my section's section's corrective corrective section's corrective actions actions designated as Does not include actions corrective actions designated as required for restart, are CRs or CAs linked to designated as designated as required for restart, complete at this time P3 activities required for required for are complete at this restart are restart are time complete at this complete at this time time This Item assessed by NQA only
| |
| +Site wide assessment only. Data provided by Management Observation Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Trite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 36 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 16 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2d. CRITERIA RELATED TO TRAINING AND QUALIFICATION Training and Qualificaton are valued ATTRIBUTE RED YELLOW WHITE GREEN Restart training+ Most required Between 75-90% Between 90-99% of 100% of required restart training is of required restart required restart restart training is (Explain why not complete. training is training is complete. complete.
| |
| acceptable if less complete.
| |
| than green)
| |
| Initial Operator Individuals in Individuals in training- initial license initial license class are class are Individuals in initial Individuals in initial maintaining a maintaining a license class are license class are class average of class average of maintaining a class maintaining a class 82% or less 83-87% average of 88-94% average of more than 94%
| |
| Requalification Less than 70% of Between 70-84% Between 85-95% of More than 95% of the training- licensed of the licensed the licensed licensed operators have operators have operators have operators have passed their (Explain why passed their passed their passed their requalification training.
| |
| acceptable if less requalification requalification requalification than green) training. training. training,
| |
| -This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Nuclear Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number W_________________________________________ _ A D B B P-V P-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 37 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 17 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2d. CRITERIA RELATED TO TRAINING AND QUALIFICATION (continued)
| |
| Training and Qualification are valued Operability Less than 50% of Between 50-74% Between 75-90% of More than 90% of determination applicable of applicable applicable operators applicable operators training* operators and operators and and engineers have and engineers have (Explain why engineers have engineers have received training on received training on acceptable ff less received training received training operability operability than green) on operability on operability determinations. determinations.
| |
| determinations. determinations.
| |
| Training on Less than 80% Between 8-89% Between 90-97% of More than 97%
| |
| SCWE of managers, of managers, managers, managers, supervisors, supervisors, and supervisors, and supervisors, and and operators have (Explain why operators have operators have operators have received training on acceptable if less received training received training received training on SCWE.
| |
| than green) on SCWE. on SCWE. SCWE.
| |
| Training on Less than 70 % Between 70-80% Between 80-90% of More than 90% of decision making of applicable of applicable applicable personnel applicable personnel process" personnel have personnel have have received have received training received training received training training on the on the decision making on the decision on the decision decision making process.
| |
| making process. making process. process.
| |
| Training on Less than 80% Between 80-89% Between 90-95% of More than 97% of standards and of personnel in of personnel in in the section personnel in the expectations the section have the section have personnel have section, have received (Explain why received training received training received training on training on standards acceptable if less on standards and on standards and standards and and expectations.
| |
| than green) expectations. expectations. expectations.
| |
| Continuing Less than 70% of Between 70-80% Between 80-90%of More than 90% of training identified scheduled of scheduled scheduled training scheduled training by Curriculum training identified training identified identified by the CRC identified by the CRC is Review by the CRC is by the CRC is is completed in a completed in a timely Committee completed in a completed in a timely manner. manner.
| |
| (CRC)* timely manner. timely manner.
| |
| *This Item assessed by Operations and Engineering only
| |
| *Site wide assessment only. Data provided by Nuclear Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| __ __ _DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 38 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 18 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Improvements in Most requisitions About 50% of open About 75% of open At least 85% of open management for management requisitions for requisitions for requisitions for staffing* positions (all exempt management (all management management positions employees) have exempt employees) positions (all exempt (all exempt employees) not been filled in the positions have employees) have have been filled in the past month. been filled in the been filled in the past month.
| |
| past month. past month.
| |
| Corrective Action There are no The CARB has The CARB has been The CARB has been Review Board directors on the been enhanced enhanced with enhanced with director-(CARB)+ CARB. with director-level director-level level personnel.
| |
| personnel. personnel.
| |
| The backlog of The backlog of documents awaiting The backlog of The backlog of documents awaiting CARB review is documents awaiting documents awaiting CARB review is less more than four CARB review is CARB review is less than one week.
| |
| weeks. less than four than two weeks.
| |
| weeks.
| |
| Engineering The backlog of The backlog of The backlog of The backlog of Assessment documents awaiting documents awaiting documents awaiting documents awaiting EAB Board (EAB)++ EAB review is EAB review is less EAB review is less review is less than one greater than four than four weeks. than two weeks. week.
| |
| weeks.
| |
| Site wide assessment only. Data provided by Human Resources
| |
| +Site wide assessment only. Data provided by Performance Improvement
| |
| ++Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NuiberD
| |
| ____ ____ ____ ____ ____D BB P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 39 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 19 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT(continued)
| |
| Commitment to continuous improement is evident ATTRIBUTE RED YELLOW WHITE GREEN Benchmarking Less than 60% (< Between 60-75% Between 75-90% of More than 90% of against industry 14) of sections (15-17) of sections ( 17-20) sections (>20) have standards@ have scheduled sections have have scheduled any scheduled any any benchmarking scheduled any benchmarking in benchmarking in in accordance bench-marking in accordance with accordance with with NOBP-LP- accor-dance with NOBP-LP-2002 or NOBP-LP-2002 or NG-2002 or NG-EN- NOBP -P-2002 NG-EN-00386 for 1" EN-00386 for t & nd 2 00386 for 1" 2nd or NG-EN-00386 $ 2' quarter 2004. quarter 2004.
| |
| quarter 2004. for 1'' quarter 2004.
| |
| Management A management A management A management A management observations" observation observation observation program observation program program has been program has has been established. has been established.
| |
| established. Less been established. More than 80% of More than 90% of than 70% of More than 70% of management management management management observations are observations are observations are observations are performed as performed as performed as performed as scheduled and most scheduled and contain scheduled, and scheduled, and are considered quality information.
| |
| observations are observations are acceptable.
| |
| weak. weak.
| |
| Temporary There are more There are 11 or There are 8 or less There are 5 or less modificatons+# than 11 temporary less temporary temporary temporary modifications. modifications. modifications. modifications.
| |
| Number of There are more There are 2 There is1 operator There are no operator Operator work- than 2 operator operator workarounds. workarounds.
| |
| arounds*# workarounds. workarounds.
| |
| Number of There are more There are 4 There are 1-3 Control There are no Control Control Room than 4 Control Control Room Room deficiencies. Room deficiencies.
| |
| deficiencies*# Room deficiencies.
| |
| deficiencies.
| |
| @Site wide assessment only. Data provided by Quality Services or Industry Relations
| |
| *This item assessed by Operations only
| |
| **Site wide assessment only. Data provided by Management Observation program
| |
| +Site wide assessment only. Data provided by Plant Engineering
| |
| #Significance evaluation will be discussed during the Restart Readiness Review Safety Culture Assessment and the outcome of this discussion may affect any or all of the attribute ratings. Explain why acceptable if less than green
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 40 of 86 APPENDIX A: ASSESSMiENT OF SAFETY CULTURE CRITERIA Page 20 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT (continued)
| |
| Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Training on Less than 80% of Between 80-89% Between 90-97% of More than 97% of SCVE* managers, of managers, managers, managers, supervisors supervisors and supervisors and supervisors and and operators have operators have operators have operators have received training on received training received training received training on SCWE.
| |
| on SCWE. on SCWE. SCWE.
| |
| Licensed Individuals in Individuals in Individuals in initial Individuals in initial operator initial license initial license license class are license class are pipeline class are class are maintaining a class maintaining a class maintaining a maintaining a average of 88-94% average of more than class average of class average of 94%.
| |
| 82% or less 83-87%
| |
| *Site wide assessment only. Data provided by Nuclear Training "This item assessed by Operations only.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| _ __ __ _ . DBBP-VP-0002 Mtle: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE A 08 Page 41 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 21 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT (continued)
| |
| Commitment to continuous improvement is evident SAFETY CONSCIOUS WORK ENVIRONMENT (SCWE)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Use of More than 4 CRs Between 4-2 CRs Less than 2 CRs No CRs issued within SCWERT issued within the issued within the issued within the past the past year related to past year related past year related year related to failure failure to properly to failure to to failure to to properly conduct conduct SCWERT properly conduct properly conduct SCWERT review of review of Davis-Besse SCWERT review SCWERT review Davis-Besse work work disciplinary of Davis-Besse of Davis-Besse disciplinary actions actions prior to the work disciplinary work disciplinary prior to the action. action.
| |
| actions prior to actions prior to the action. the action.
| |
| Effectiveness of There are more There are 5 NRC There are 4 NRC There are 2 or fewer SCWERT in than 5 NRC allegations or allegations or ECP NRC allegations or avoiding allegations or ECP concerns of concerns of ECP concerns of discrimination ECP concerns of discrimination discrimination discrimination claims* discrimination submitted within submitted within the submitted within the submitted within the past year past year past year the past year Effectiveness in There is more There is one There are no There are no avoiding NRC or than one substantiated substantiated NRC or substantiated NRC or ECP substantiated NRC or ECP ECP discrimination ECP discrimination substantiated NRCor ECP discrimination claims within the past claims within the past 2 discrimination discrimination claim within the year. years.
| |
| claims* claim within the past year past year Site wide assessment only. Data provided by Employee Concems Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number0
| |
| ___ __ __ __ ___ __ __ __ _ _DBBP-VP-0002 Mile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 42 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 22 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2f. CRITERIA RELATED TO COMMITMENT TO CROSS-FUNCTIONAL WORK MANAGEMENT AND COMMUNICATION Commitment to cross functional work management and communication is evident ATTRIBUTE RED YELLOW WHITE GREEN Cross-functional No cross-functional Some cross- Cross-functional Cross-functional teamwork* teamwork is evident functional teamwork frequently teams among sections among sections teamwork among occurs among are constantly sections exists but sections, enabling forming/reforming work is sub- efficient and effective around the best way to optimized. workflow. get work done.
| |
| Department Many process Some process Minimal process Department interfaces interfaces breakdowns occur breakdowns occur breakdowns and are seamless; work within the within the rework occur within flows efficiently Department with Department with the Department with between departments extensive amounts frequent amounts effective and efficient throughout the entire of rework needed. of rework needed. resolution of emergent organization.
| |
| issues.
| |
| Performance to Less than 70% of Between 70-80% Between 80 -90% of More than 90% of schedule' work is completed of work is work is completed on work is completed on on time, as completed on time, as scheduled, time, as scheduled, scheduled, causing time, as with minimal within current resource major scheduled, with adjustments to capacity.
| |
| consequences to major adjustments resource capacity overall site to resource required to improve performance. capacity required performance.
| |
| to improve performance.
| |
| Interdepartmental Information that Information that Information that Information that communication impacts impacts impacts downstream impacts downstream downstream downstream implementation is implementation is implementation is implementation is frequently shared on a communicated as not shared, causing inconsistently timely basis, enabling soon as it's known, significant negative shared, which departments to enabling departments consequences to keeps other proactively plan and to work proactively on other departments. departments in a respond. a consistent basis.
| |
| reactive mode.
| |
| Site wide assessment only. Data provided from Edventures survey results.
| |
| *Site wide assessment only. Data provided by Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 43 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 23 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2f. CRITERIA RELATED TO COMMITMENT TO CROSS-FUNCTIONAL WORK MANAGEMENT AND COMMUNICATION (continued)
| |
| Commitment to cross functional work management and communication is evident interdepartmental Problem solving Cross-functional Cross-functional Cross-functional problem solving and decision sections, sections, sections, and decision making occurs in Departments or Departments or Departments or making isolation; non- stakeholders are stakeholders are stakeholders are involvement of seldom involved frequently involved consistently involved other Departments when problems when problems are when problems are or stakeholders. are being solved being solved and being solved and and decisions are decisions are made. decisions are made.
| |
| made.
| |
| Systemic learning Things are broken Discrete problems Attention isfocused Streamlining and down, focus Is on are fixed within the on learning and improving systems the pieces and section with discovering and process is discrete problems minimal fundamental constant to resolve are fixed within the understanding of solutions to long-standing and/or section with no interdependencies resolving long- complex problems understanding of standing and/or within the section interdependencies. complex problems within the section Incorporating Industry operating There is less than There isfull Operating Experience industry experience is not full utilization and utilization and is consistently and Operating consistently fully minimal compliance with the fully utilized in every Experience* utilized to enhance compliance to our Operating department and is site performance. Operating Experience Program well-integrated into Experience everyday activities to Program enhance plant performance.
| |
| *Site wide assessment only. Data provided by Operating Experience Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 08 Page 44 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 24 of 39 2.MANAGERS' COMMITMENT AREA 2g. CRITERIA RELATED TO COMMITMENT TO CREATING AN ENVIRONMENT OF ENGAGEMENT AND COMMITMENT An environment of engagement and commitment is evident ATTRIBUTE RED YELLOW WHITE GREEN FENOC values, FENOC values, FENOC values, FENOC values, basic Most exempt basic principles basic principles and basic principles principles and personnel in the and leadership leadership and leadership leadership strategies section have strategies strategies are not strategies are are frequently internalized and are used by exempt inconsistently demonstrated by some living the FENOC personnel within demonstrated by exempt personnel values, basic the section some exempt within the section principles and personnel within leadership strategies the section as demonstrated in their day to day actions.
| |
| Quality of Employee Employee Employees Concerns Employee Concerns management and Concerns Program, Concerns Program, Quality Program, Quality employee Quality Assessment Program, Quality Assessment and 4Cs Assessment and 4Cs relationships* and 4Cs survey Assessment and survey data indicates survey data indicate data indicates that 4Cs survey data that more than 80% of more than 90% of (Explain why employees openly indicates that employees will bring employees raise acceptable if not express fear of more than 70% concerns to issues directly with green) retaliation and will of employees management. management, work not raise safety will bring safety collaboratively to concerns with concerns to resolves issues and management. management. reflect favorable improvement.
| |
| Organizational Section Section Section management Section management commitment and management management frequently supports consistently supports shared success focuses on what is occasionally doing what is in the doing what is in the criteria in the best interest supports what is best interest of the best interest for the of their section at in the best whole organization whole organization the expense of interest of their rather than what is in rather than what is in what is in the best section without the best interest of the best interest for interest of the consideration to their section. their section.
| |
| whole organization. what is in the best interest of the whole organization.
| |
| *Site wide assessment only. Data provided by ECP, NQA and 4Cs
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 45 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 25 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2g. CRITERIA RELATED TO COMMITMENT TO CREATING AN ENVIRONMENT OF ENGAGEMENT AND COMMITMENT (continued)
| |
| An environment of engagement and commitment is evident Performance Less than 70% of Between 70-80% Between 80-90% of More than 90% of reviews in performance of performance performance reviews performance reviews accordance with reviews for the reviews for the for the section were for the section were FENOC section were section were completed for the completed for the Performance completed for the completed for the review period per. review period per the Management review period per review period per. the FENOC FENOC Performance process* the FENOC the FENOC Performance Management process Performance Performance Management Management Management process process process FENOC Less than 70% of Between 70-80% Between 80-90% of More than 90% of Performance managers and of managers and managers and managers and Management supervisors have supervisors have supervisors have supervisors have Process development plans development plans development plans development plans Development submitted to HR submitted to HR submitted to HR submitted to HR Plans*
| |
| *Site wide assessment only. Data provided by Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Num DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 46 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 26 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3a. CRITERIA RELATED TO DRIVE FOR EXCELLENCE Nuclear assets of people and plant are continuously improved to enhance margins of safety ATTRIBUTE RED YELLOW WHITE GREEN Maintenance Rule There are more There are 2-3 There is one Red There are zero Red (a)(1) Systems* than 3 Red Red (a)(1) (a)(1) system. (a)(1) systems and all (a)(1) systems. systems. Maintenance Rule (a)(1) systems are in monitoring status Number of There are more There are 2 There is 1 operator There are no operator Operator than 2 operator operator workarounds. workarounds.
| |
| workarounds*# workarounds. workarounds.
| |
| Number of Control There are more There are 4 There are 1-3 There are no Control Room than 4 Control Control Room Control Room Room deficiencies.
| |
| deficiencies Room deficiencies. deficiencies.
| |
| deficiencies.
| |
| Number of There are more There are 11 or There are 8 or less There are 5 or less temporary than 11 less temporary temporary temporary modifications.
| |
| modifications+# temporary modifications. modifications.
| |
| modifications Individual Error The individual The individual The individual error The individual error rate Rate++ error rate is error rate is 0.31 rate is 0.29 < is <0.26 individual errors
| |
| > 0.45 individual <.45->.36 >.26 individual errors per 10,000 hours errors per individual errors per 10,000 hours worked.
| |
| 10,000 hours per 10,000 hours worked.
| |
| worked. worked.
| |
| Site wide assessment only. Data provided by Plant Engineering "This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Plant Engineering
| |
| ++Site wide assessment only. Data provided by Human Performance
| |
| #Significance evaluation will be discussed during the Restart Readiness Review Safety Culture Assessment and the outcome of this discussion may affect any or all of the attribute ratings. Explain why acceptable If less than green.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 47 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 27 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3a. CRITERIA RELATED TO DRIVE FOR EXCELLENCE (continued)
| |
| Nuclear assets of people and plant are continuously improved to enhance margins of safety Percent of Less than 80% of 80% or more of the 90% or more of the 95% or more of the CRs seff-identified the CRs originated CRs originated are CRs originated are originated are self-Condition are self-identified. self-identified. self-identified. identified.
| |
| Reports (CRs)*
| |
| Number of Less than 80% of At least 80-90% of At least 90% of SCAQ All SCAQ evaluations open SCAQ evaluations SCAQ evaluations evaluations and 80- and 90% of CAQ Condition and less than 70% and 70-80% of 90% of CAQ evaluations were Report of CAQ evaluations CAQ evaluations evaluations were completed on schedule evaluations* were completed on were completed on completed on for the previous quarter.
| |
| schedule for the schedule for the schedule for the previous quarter. previous quarter. previous quarter.
| |
| Engineering The quality of The quality of The quality of The quality of Assessment engineering engineering engineering products engineering products as Board (EAB) products as products as as measured by the measured by the EAB is index' measured by the measured by the EAB is 2.0 or less. 1.0 or less.
| |
| EAB is greater than EAB is 3.0 or less.
| |
| 3.0.
| |
| Performance More than one One significant Major plant evolutions Major plant evolutions during major significant event has event has occurred have been performed have been performed plant occurred during a during a plant in the past month with successfully in the past evolutions+ plant evolution in the evolution in the some less than month as planned past month past month significant challenges without any challenges or transients.
| |
| Addressing Less than 70% of Between 70-80% of Between 80-90% of More than 90% of Operating operating operating operating experience operating experience Experience experience reports experience reports reports applicable to reports applicable to the applicable to the applicable to the the section are section are completed section are section are completed on time on time.
| |
| completed on time completed on time Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Significant is defined by INPO as an event which caused or had the potential to cause an appreciable reduction in plant safety or reliability, excessive radiation exposure, the discharge of radioactivity offsite or serious harm to individuals. The significance of a particular event (including the discovery of a serious deficiency, lies in the actual or potential consequences of the event or in the likelihood that it is a precursor to a more serious event.
| |
| *Site wide assessment only. Data provided by Performance Improvement Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| +Site wide assessment only. Data provided by Operations
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number B
| |
| _____ ________ _____ ____ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revislon: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 48 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 28 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3b. CRITERIA RELATED TO QUESTONING ATTITUDE Challenges are welcomed ATTRIBUTE RED YELLOW WHITE GREEN Quality of prejob Management Management Management Management briefs* observations and OA observations and observations and OA observations and field observations CA field field observations OA field show that most pre-job observations show show that, with some observations show briefs are not that most pre-job exceptions, pre-job that pre-job briefs in acceptable. briefs are briefs are acceptable. general are acceptable. acceptable.
| |
| Percent of CRs Less than 13% of Between 13-15% Between 15-17% of More than 17% of per person per individuals wrote CRs of individuals individuals wrote CRs individuals wrote group during the past 30 wrote CRs during during the past 30 CRs during the past days. the past 30 days. days. month.
| |
| Number of The number of The number of The number of The number of programmatic programmatic CRs programmatic CRs programmatic CRs programmatic CRs CRs* indicates that indicates that most indicates that a large indicates that individuals in general individuals are majority of individuals individuals in are reluctant to write willing to write are willing to write general are willing CRs on programmatic CRs on CRs on programmatic to write CRs on and management programmatic and and management programmatic and issues. management issues. management issues. issues.
| |
| Program and >0.50 program and <0.50-.>.37 c0.37->.27 program <0.27 program process error process errors per program and and process errors and process errors rate+ 10,000 hours worked. process errors per per 10,000 hours per 10,000 hours 10,000 hours worked. worked.
| |
| worked.
| |
| Raising Management Management Management Management problems observations, CAP and observations, CAP observations, CAP observations, CAP NQA field observations and NQA field and NQA field and NQA field show that most observations show observations show observations show individuals are not individuals that a large majority that most raising problems generally are of individuals are individuals are encountered in the raising problems raising problems raising problems field. encountered in the encountered in the encountered In the field. field. field.
| |
| *Site wide assessment only. Data provided by Management Observation Program and NQA.
| |
| **Site wide assessment only. Data provided by Performance Improvement.
| |
| +Site wide assessment only. Data provided by Human Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 49 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 29 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Event Free Clock* The event free The event free The event free The event free clock is clock is less clock is between 20 clock is 30 to 39 greater than 40 days on than 20 days on and 30 days on days on average. average.
| |
| average. average.
| |
| Industrial safety There are 11 or There are between There are 4 to 7 There are no more than performance more OSHA 8 and 10 OSHA OSHA recordables 3 OSHA recordables per recordables per recordables per per year. year.
| |
| year. year.
| |
| Individual error The individual The individual error The individual The individual error rate rate error rate is rate is <0..45->.36 error rate is is <0.26 individual errors
| |
| >0.45 individual individual errors per <O.<.36->.26 per 10,000 hours errors per 10,000 hours individual errors worked.
| |
| 10,000 hours worked. per 10,000 hours worked. worked.
| |
| Program and >0.50 program <0.50->.37 <..37->.27 <0.27 program and process error rate* and process program and program and process errors per errors per process errors per process errors per 10,000 hours worked.
| |
| 10,000 hours 10,000 hours 10,000 hours worked. worked. worked.
| |
| Significant human There are more There are fewer There are fewer There were no performance than 3 significant than 3 significant than 2 significant significant human errors resulting in human human human performance errors per plant transients* performance performance errors performance year resulting in plant errors per year per year resulting in errors per year transients.
| |
| resulting in plant plant transients. resulting in plant transients. transients.
| |
| Backlog of Priority There are more There are less There are less There are less than 100 procedure change than 200 open than 200 open than 150 open open Priority PCRs.
| |
| requests (PCRs)+ Priority PCRs. Priority PCRs. Priority PCRs.
| |
| Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| *Site wide assessment only. Data provided by Human Performance Site wide assessment only. Data provided by Industrial Safety
| |
| +Site wide assessment only. Data provided by Quality Services
| |
| | |
| APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 30 of 39
| |
| : 3. INDIVIDUALS COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH (continued)
| |
| Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Deficiency rate for Deficiency rate The deficiency The deficiency rate The deficiency rate for QC holds for QC hold rate for QC hold for QC holds point is QC hold points is less points is more points is less than less than 15 %. than 7 %.
| |
| than 25%. 25%.
| |
| Rework rate' Rework rate is The rework rate The rework rate is The rework rate is more than 3%. is 2.5-3.0%. 2.1-2.5%. <2.0%.
| |
| Ratio of completed Less than 50% More than 50% of More than 75% of More than 90% of to scheduled of scheduled scheduled work scheduled work scheduled work orders works orders per work orders are orders are orders are are completed.
| |
| week+ completed. completed. completed.
| |
| Number of late Less than 50% More than 50% of More than 75% of More than 90% of preventive of scheduled scheduled PMs scheduled PM are scheduled PMs are maintenance (PM) PMs are are completed on completed on time. completed on time.
| |
| activities+ completed on time.
| |
| time Backlog of There are more There are There are between There are less than 134 corrective than 230 CM between 229 and 149 and 134 CM CM activities maintenance (CM) activities 150 CM activities activities outstanding.
| |
| activities+ outstanding. outstanding. outstanding.
| |
| Number of There are more There are 2-3 There is one Red There are zero Red Maintenance Rule than 3 Red Red (a)(1) (a)(1) systems. (a)(1) systems. All (a)(1) systems++ (a)(1) systems. systems. Maintenance Rule (a)(1) systems will be in monitoring
| |
| 'This Item assessed by QC only. The Deficiency Rate for QC relates to rejectable or unsatisfactory inspection attributes identified in the field by the QC Inspector during the implementation of the Order (work order). The established QC hold points are embedded within the Order as either a specific Step in the work sequence or on a standalone document such as a Weld Traveler.
| |
| "This item assessed by Maintenance only
| |
| +Site wide assessment only. Data provided by Outage Management and Work Control
| |
| ++Site wide assessment only. Data provided by Plant Engineering. Explain why acceptable if not green.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002 rite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE _ 08 Page 51 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 31 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH (continued)
| |
| Performing activities ina quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Performance One significant Major plant Major plant Major plant evolutions during major plant event has evolutions have evolutions have have been performed evolutions @ occurred during a been performed been performed with successfully as plant evolution in with some some transients but planned. There are no the past month or transients or one no significant events transients or significant there are three or significant event during major plant events during major more transients during major plant evolutions prior to plant evolutions prior during major evolutions prior to restart. to restart.
| |
| plant evolutions restart.
| |
| prior to restart.
| |
| Use of procedures Management Management Management Management and work orders* observations and observations and observations and observations and NQA NQA field NQA field NQA field field observations observations observations show observations show show that the vast show that most that individuals that many majority of individuals individuals are generally are individuals are using are using procedures not using using procedures procedures or work or work orders.
| |
| procedures or or work orders. orders.
| |
| work orders.
| |
| Operational transient isdefined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Significant is defined by INPO as an event that caused or had the potential to cause an appreciable reduction in plant safety or reliability, excessive radiation exposure, the discharge of radioactivity offsIte or serious harm to individuals. The significance of a particular event (Including the discovery of a serious deficiency, lies in the actual or potential consequences of the event or inthe likelihood that it is a precursor to a more serious event.
| |
| @ Site wide assessment only. Data provided by Operations
| |
| *Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE _ 08 Page 52 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 32 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS Associates are comfortable in voicing opinions, issues and concerns ATTRIBUTE RED YELLOW WHITE GREEN Number of CRs per Less than 13% of Between 13-15% of Between 15-17% of More than 17% of person per group individuals wrote CRs individuals wrote CRs individuals wrote individuals wrote during the past 30 during the past 30 CRs during the past CRs during the past days. days. 30 days. 30 days.
| |
| Worker confidence in Surveys and/or Surveys and/or Surveys and/or Surveys and/or raising safety interviews indicate interviews indicate interviews indicate interviews indicate concems** that less than 80% of that between 80-90% that between 90- that more than 95%
| |
| workers believe they of workers believe 95% of workers of workers believe Explain why can raise nuclear they can raise believe they can they can raise acceptable if not safety or quality nuclear safety or raise nuclear safety nuclear safety or green) concerns without fear quality concerns or quality concerns quality concerns of retaliation. without fear of without fear of without fear of retaliation. retaliation. retaliation.
| |
| Feedback from 4Cs Feedback from the Feedback from the Feedback from the Feedback from the meetings+ 4Cs meetings 4Cs meetings 4Cs meetings 4Cs meetings indicates that most indicates that more indicates that more indicates that more individuals are not than 70% of than 80% of than 90% of willing to raise individuals are willing individuals are individuals are concerns to to raise concerns to willing to raise willing to raise management. management. concerns to concerns to management. management.
| |
| Keep Improving Each month's total Each month's total Each month's total Each months total Performance (KIP) Safe behavior is 59% Safe behavior is 60% Safe behavior is Safe behavior is program++ or less. to 69%. 70% to 79%. 80% or higher.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| +Site wide assessment only. Data provided by Chief Operating Officer
| |
| ++Site wide assessment only. Data provided by Industrial Safety "Site wide assessment only. Data provided by Employee Concems Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumPber
| |
| _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .D_ B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 53 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 33 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| Associates are comfortable in voicing opinions, issues and concerns ATTRIBUTE RED YELLOW WHITE GREEN Pre-job briefings@ Management Management Management Management observations observations and observations and QA observations and QA and QA field QA field field observations field observations show observations observations show that, with some that pre-job briefs in show that most show that most exceptions, pre-job general are acceptable.
| |
| pre-job briefs pre-job briefs are briefs are acceptable.
| |
| are not acceptable.
| |
| acceptable.
| |
| Intra-department No formal Infrequent Formal Formal communication information sharing communication information communication structures exist and are structures exist sharing exists structures exist and consistently used to for sharing among the are occasionally used share information information sections of the to share information among the sections of among the department. among the sections the department.
| |
| sections of the of the department.
| |
| department.
| |
| Quality of 4Cs surveys 4Cs surveys 4Cs surveys indicate 4Cs surveys indicate communication* indicate that indicate that more that more than 70% that more than 70% of more than 50% than 50% of of employees believe employees believe that of employees employees that communication communication from believe that the believe that from their Managers their Managers isgood.
| |
| communication communication isfair.
| |
| from their from their Managers is Managers is fair poor
| |
| @Sfte wide assessment only. Data provided by Management Observation Program and NQA
| |
| *Site wide assessment only. Data provided by Chief Operating Officer
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 54 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 34 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| SAFETY CONSCIOUS WORK ENVIRONMENT (SCWE)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Employee Surveys and/or Surveys and/or Surveys and/or Surveys and/or awareness of interviews indicate that interviews indicate that interviews indicate interviews indicate SCVVE policy less than 80% of 80-90% of employees that 90-95% of that more than 95%
| |
| employees in the in the section are aware employees in the of employees in the (Explain why section are aware of of policy and consider it section are aware of section are aware of acceptable if not policy. a FE value. policy and consider it policy and consider it green) an FE value. an FE value and the normal way to do business.
| |
| Training on Less than 80% of Between 80-89% of Between 90-97% of More than 97% of SCWE managers, supervisors, managers, supervisors, managers, managers, and operators have and operators have supervisors, and supervisors, and (Explain why received training on received training on operators have operators have acceptable if not SCWE. SCWE. received training on received training on green) SCWE. SCWE.
| |
| NQA nterviews+ NQA interviews indicate NQA interviews indicate NQA interviews NQA interviews that less than 85% of that between 85-90% of indicate that between indicate that more (Explain why individuals are willing to individuals are willing to 90-95% of individuals than 95% of acceptable if not raise concerns to their raise concerns to their are willing to raise individuals are willing green) supervisors or ECP. supervisors or ECP. concerns to their to raise concerns to supervisors or ECP. their supervisors or ECP.
| |
| Worker Surveys and/or Surveys and/or Surveys and/or Surveys and/or confidence in interviews indicate that interviews indicate that interviews indicate interviews indicate raising safety less than 80% of between 80-90% of that between 90-95% that more than 95%
| |
| concerns' workers in the section workers in the section of workers in the of workers in the believe they can raise believe they can raise section believe they section believe they (Explain why nuclear safety or quality nuclear safety or quality can raise nuclear can raise nuclear acceptable if not concerns without fear of concerns without fear of safety or quality safety or quality green) retaliation. retaliation. concerns without fear concerns without fear of retaliation. of retaliation.
| |
| *Site wide assessment only. Data provided by Nuclear Training
| |
| **Site wide assessment only. Data provided by Employee Concerns Program
| |
| +Site wide assessment only. Data provided by NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| _____ ____ ____ _____ ____ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 55 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 35 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| EMPLOYEE CONCERNS PROGRAM (ECP)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Ratio of concerns There are more There are more There are at least 4 There are at least 8 submitted to ECP NRC allegations ECP concerns times more ECP times more ECP vs. NRC than ECP than NRC concerns than NRC concerns than NRC allegations based concerns. allegations. allegations or there allegations or there are on three month are no NRC no NRC allegations or rolling average* allegations. ECP concerns.
| |
| Satisfaction of Less than 70% of Between 70-80 % Between 80-90% of More than 90% of employees using employees that of employees that employees that use employees that use the the ECP* use the ECP use the ECP the ECP report being ECP report being report being report being satisfied with the satisfied with the satisfied with the satisfied with the process. process.
| |
| process. process.
| |
| Complaints of There are more There are 2 There is 1 complaint There are zero breach of than 2 complaints complaints this this year. complaints this year.
| |
| confidentiality of this year. year.
| |
| ECP*
| |
| Management Employee Employee Employee surveys Employee surveys support for ECP surveys indicate surveys indicate indicate between 80- indicate more than 90%
| |
| less than 70% of between 70-80% 90% of individuals of individuals believe (Explain why individuals of individuals believe management management supports acceptable if not believe believe supports ECP. ECP.
| |
| green) management management supports ECP. supports ECP.
| |
| *Site wide assessment only. Data provided by Employee Concems Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 56 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 36 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM Persistence and urgency in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Development Less than 70% of Between 70-80 % Between 80-90% of More than 90% of Plans per applicable of applicable applicable employees applicable employees in FENOC employees in the employees in the in the section have the section have Performance section have section have completed completed development Management completed completed development plans. plans.
| |
| process development development plans. plans.
| |
| Training Training Training Training attendance Training attendance is attendance" attendance is less attendance is is between 91-98%. greater than 98%.
| |
| than 85%. between 85-90%.
| |
| Rework rate+ The rework rate is The rework rate The rework rate is The rework rate is more than 3%. is 2.5-3.0%. 2.1-2.5%. <2.0%.
| |
| Results of EAB The quality of The quality of The quality of The quality of assessments++ engineering engineering engineering products engineering products as products as products as as measure by the measured by the EAB measured by the measured by the EAB is 2.0 or less is 1.0 or less.
| |
| EAB is greater EAB is 3.0 or than 3.0. less.
| |
| Training Overall Training Overall Training Overall Training Overall Training performance performance score performance performance score performance score score per less than 60% score between between 80-90% greater than 90%
| |
| NOFP-TR- 60-80%.
| |
| 1501#
| |
| Radiation There are more There are 1-3 There is 1 radiation There are no radiation Protection than 3 radiation radiation protection event in protection events in the events @ protection events protection events the last quarter. last quarter.
| |
| in the last quarter. in the last quarter.
| |
| *Site wide assessment only. Data provided by Nuclear Training
| |
| +This item assessed by Maintenance only
| |
| ++This item assessed by Engineering only. Data provided by Director-Nuclear Engineering
| |
| #This item assessed by Nuclear Training only.
| |
| @Sfte wide assessment only. Data provided by Radiation Protection. An RP event is defined as any radiological event that would be included in the NRC Performance Indicator for Radiation Safety Cornerstone.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ _____DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 57 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 37 of 39 3.INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence and urgency in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Procedure Management Management Management Management compliances observations and observations and observations and observations and NQA NQA field NQA field NQA field field observations show observations show observations observations show that the vast majority of that most show that that many individuals individuals are individuals are not individuals are complying with complying with complying with generally are procedures. procedures.
| |
| procedures. complying with procedures.
| |
| Personal Few employees in Employees in the Employees in the Employees at all levels initiative the section section work hard section do what it in the section take routinely express to do what's takes to get the job personal initiative to why work can't be expected. done. invent methods to done or improved. achieve higher quality and greater efficiency.
| |
| Ownership Employees in the Employees in the Employees in the Most employees in the section don't section are section follow through section regularly follow through on inconsistent in and do what is asked volunteer to own/lead assigned following through of them and do what project, develop plans, commitments and to meet quality is defined within their coordinate efforts and seldom volunteer and timing of job description. see work through to for ownership. assigned completion.
| |
| commitments.
| |
| **Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ___ __ ___ ___ __ ___ __ ___ __ ____ _ _ _ DBB P-VP-0002 Tife: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 58 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 38 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Implementation Implementation Implementation of Implementation of The CAP improvements of CAP of the CAP the CAP the CAP designated for restart improvements* improvements improvements improvements for are completed and designated for designated for restart is completed associated training is (Explain why restart has not restart is started but the associated completed.
| |
| acceptable if not started. but none are training is not green) completed. completed.
| |
| Root cause The root cause The root cause The root cause The root cause evaluation evaluation evaluation evaluation approval evaluation approval rate quality* approval rate as approval rate as rate as determined as determined by the determined by determined by the by the CARB is CARB is 90% or greater.
| |
| the CARB is less CARB is between between 75-90%.
| |
| than 50%. 50-74%.
| |
| CR category The CR category The CR category The CR category The CR category accuracy* accuracy rate is accuracy rate is accuracy rate is accuracy rate is 90% or less than 70% or between 70-80%. between 80-90%. greater.
| |
| (Explain why greater.
| |
| acceptable if not green)
| |
| CR self- Less than 80% of 80% or more of 90% or more of the 95% or more of the CRs identification the CRs the CRs originated CRs originated are originated are self-rate* originated are are self-identified. self-identified. identified.
| |
| self-identified.
| |
| Employee Employee Employee surveys Employee surveys Employee surveys survey+. surveys indicate indicate that indicate that indicate that less than that more than between 10-5% of between 5-2% of 2% of individuals are not (Explain why 10 % of individuals are not individuals are not willing to use the CAP.
| |
| acceptable if not individuals are willing to use the willing to use the green) not willing to use CAP. CAP.
| |
| the CAP.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| +Site wide assessment only. Data provided by Employee Concerns Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 TIe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 59 of 86 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 39 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN NQA interviews* NQA interviews NQA interviews NQA interviews NQA interviews indicate that indicate that indicate that between - indicate that less than more than 10% between 10-5% of 5-2% of individuals are 2 % of individuals are of individuals are individuals are not not willing to use the not willing to use the not willing to use willing to use the CAP. CAP.
| |
| the CAP. CAP.
| |
| Timeliness of Less than 50% of Between 50-74% Between 75-89%of More than 90% of corrective actions corrective actions of corrective corrective actions for corrective actions for for section CRs actions for section section CRs are section CRs are Does not include are completed on CRs are completed on completed on CRs or CAs linked schedule without completed on schedule without schedule without to P3 activities extensions. schedule without extensions. extensions.
| |
| extensions.
| |
| *Site wide assessment only. Data provided by NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE _ 08 Page 60 of 86 ATTACHMENT 10: SAFETY CULTURE ASSESSMENT CRITERIA MATRIX 0 C0 X : e0 X U M Site wide Plant Operations _=_=
| |
| RP Chemistry __ -
| |
| Outage MgmtP/Work Control Maintenance Training Safety_ == = == == = == === = =
| |
| Engineering ___
| |
| Plant Engineering Design Project Management RRT Reactor Eng.
| |
| Support Services Regulatory Affairs Quality Services _ _
| |
| Security Other Sections __ __
| |
| QA/QC__.
| |
| Supply Chain Client Services Business Services___
| |
| Human Resources
| |
| | |
| ATTACHMENT 11: SAFETY CULTURE ATTRIBUTE ASSESSMENT MATRIX
| |
| : 1. Policy Commitment Area:
| |
| la. Criteria Related to Statement of Safety Policy Item Color Policy statement on Safety Culture Policy statement on SCWE T Making employees aware of policy statements l Employee understanding of policies Worker understanding of responsibility to raise safety concerns Total for a Color:
| |
| lb. Criteria Related to Management Values I Item I Color I Corporate values I Statement of mission, vision and values l j FENOC Business Plan l .{
| |
| Total for lb I Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberDBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 62 of 86 1c. Criteria Related to Resources Item Color Adequacy of management resources Adequacy of personnel resources Adequacy of funding Adequacy of tools, material and equipment to complete site tasks Adequacy of tools, material and equipment to complete Section tasks Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Total for Ic Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:DBBP-VP-0002 Titie: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 63 of 86 1d. Criteria Related to Self-Assessment Item Color Use of NQA to supplement the self assessment process Self assessments in accordance with NOBP-LP-2004 Section Performance Indicators Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Personnel Performance Appraisals l Total for 1d Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberDBBP-VP-0002 Mtle: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 64 of 86 le. Criteria Related to Independent Oversight Item Color Nuclear Committee of the Board of Directors Company Nuclear Review Board Nuclear Quality Assurance Learning from the experience of the industry Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training ___
| |
| Safety 8 Plant Engineering Design Engineering _
| |
| Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Total for le Color:
| |
| Total for I Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| _____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 65 of 86
| |
| : 2. Managers' Commitment Area 2a. CriteriaRelated to Commitment to Safety Item Color Management observations performed as scheduled with coaching Management observations are self critical Management emphasis on safety to employees Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Leadership In Action
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _____ __________ _____ _____ _____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 66 of 86 Item Color Problem Solving Decision making Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Improvement in safety margin Plant activities receive proper management attention and safety focus Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 67 of 86 I Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Total for 2a Color:
| |
| 2b. Criteria Related to Roles and Teamwork Item IColor Understanding that safety Is highest priority l Program Ownership Ownership of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ _________ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 68 of 86 Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Item Color Ownership of Engineering products as measured by EAB Effectiveness of supervision of individuals Intra-department teamwork and alignment Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberDBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 69 of 86 Business Services Human Resources Item Color Expectations Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Trust, openness and focused commitment Clear goals and priorities Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety _ _ _
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| __ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ __ DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 70 of 86 Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Item Color Input and involvement Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumbeDBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 71 of 86 Total for 2b Color:
| |
| 2c. Criteria Related to Ownership and Accountability Item Color Performance Reviews in accordance with FENOC Performance Management Process Development plans Readiness Reviews Worker understanding of responsibility to raise safety concerns Willingness to raise safety concerns SRO reviews for Operability are performed in timely manner System assessments NQA field assessments Management observations leading to coaching Timeliness of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberDBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 72 of 86 Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Total for 2c Color:
| |
| 2d. Criteria Related to Training and Qualification Item Color Restart training Initial Operator training Requalification training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberDBBP-VP-0002 Tife: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 73 of 86 Item Color Operability determination training Operations Engineering Training on SCWE Training on decision making process Training on standards and expectations Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Continuing training identified by Curriculum Review Committee Total for 2d Color:
| |
| | |
| TMfle:
| |
| RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 2e. Criteria Related to Commitment to Continuous Improvement Item Color Improvements in management staffing Corrective Action Review Board Engineering Assessment Board Benchmarking against industry standards Management observations Temporary modifications Number of operator work arounds Number of Control Room deficiencies Training on SCWE Licensed operator pipeline Use of SCWERT Effectiveness of SCWERT in avoiding discrimination claims Effectiveness in avoiding NRC or ECP substantiated discrimination claims Total for 2e Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Numnber
| |
| ___________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 75 of 86 2f. CriteriaRelated to Commitment to Cross-FunctionalWork Management and Communication Item Color Cross functional teamwork Department interfaces Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Performance to schedule Interdepartmental communication
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D BB P-V P-0002 rite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 76 of 86 Item Color Interdepartmental problem solving and decision making Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Systemic learning Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| .________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 77 of 86 Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources IIncorporating industry Operating Experience l 7 ITotal for 2f l Color: I 2g. Criteria Related to Commitment to Creating an Environment of Engagement and Commitment Item Color FENOC values, basic principles and leadership strategies Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 78 of 86 Business Services Human Resources Item Color Quality of management and employee relationships Organizational commitment and shared success criteria Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Performance reviews in accordance with FENOC Performnance
| |
| _Management Process FENOC Performance Management Process Development plans Total for 2g Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 rite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 79 of 86 Total for 2 Color:
| |
| : 3. Individuals' Commitment Area 3a. Criteria Related to Drive for Excellence Item Color Maintenance Rule (a)(1) systems Number of Operator workarounds Number of Control Room deficiencies Number of temporary modifications Individual Error Rate Percent of self-identified Condition Reports Number of open Condition Report evaluations Engineering Assessment Board index Performance during major plant evolutions Addressing Operating Experience Total for 3a Color:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number -V0
| |
| ___________________________________DBB P-VP0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 80 of 86 3b. Criteria Related to Questioning Attitude Item Color Quality of pre-job briefs Percent of CRs per person per group -
| |
| Number of programmatic CRs Program and process error rate Raising problems Total for 3b Color:
| |
| 3c. Criteria Related to Rigorous work Control and Prudent Approach Item Color Event Free Clock I I I Industrial Safety Performance I Individual Error Rate I Program and process error rate ISignificant human performance errors result in plant transients
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| I ____________________________________________ D BBP-V P-0002 TiMe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 81 of 86 Backlog of Priority Procedure Change Requests Deficiency rate for QC holds (QC only)
| |
| Rework Rate (Maintenance)
| |
| Ratio of completed to scheduled work orders per week Number of late preventive maintenance activities Backlog of corrective maintenance activities Number of Maintenance Rule (a)(1) systems Performance during major plant evolutions Use of procedures and work orders Total for 3c IColor:
| |
| 3d. Criteria Related to Open Communications IItem IColor INumber of CRs per person per group I IWorker confidence in raising safety concerns I IFeedback from 4Cs meetings
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________DBBP-VP-0002 Tife: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE _ 08 Page 82 of 86, Keep Improving Performance program Pre-job briefings Intra-department information sharing Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Item Color Quality of Communication Employee awareness of SCWE policy Training on SCWE NQA interviews
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 83 of 86 Worker confidence in raising safety concerns Ratio of concerns submitted to ECP vs. NRC allegations Satisfaction of employees using ECP Complaints of breach of confidentiality in ECP Management support for ECP Total for 3d Color 3e. Criteria Related to Nuclear Professionalism Item Color FENOC Performance Management Process development plans Training attendance Item Color Rework Rate (Maintenance)
| |
| Results of EAB assessments Training performance score per NOBP-TR-1501 Radiation Protection Events Procedure Compliance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tifte: Revision: Page
| |
| - RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 84 of 86 Personal initiative Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Item Color Ownership Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B BP-V P-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 08 Page 85 of 86 Security 1-Quality Assurance
| |
| +/-
| |
| Supply Chain
| |
| +
| |
| Client Services
| |
| +
| |
| Business Services Human Resources _ _ _
| |
| Item Color Implementation of CAP Improvements Root cause evaluation quality CR category accuracy CR self Identification rate l Employee Survey NQA interviews Timeliness of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:DBBP-VP-0002 Tffle: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE _ 08 Page 86 of 86 Regulatory Affairs Security Quality Assurance Supply Chain Client Services Business Services Human Resources Total for 3e I I Color:
| |
| Total for 3 Color:
| |
| | |
| Docket Number 50-346 License Number NPF-3 Serial Number 1-1335 Revision 9 of the Nuclear Operating Business Practice Restart Readiness Review Extended Plant Outage (DBBP-VP-0002)
| |
| (89 pages to follow)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _ _ _ _ _ _ -D _ B B P -V P -0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE _ 09 Page 1 of 89 RESTART READINESS REVIEW EXTENDED PLANT OUTAGE Approved: V/ 1W1 Vice President Approved: 1/ k0Xf < ,OM)N Effective Date N 15 am
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| | |
| NUCLEAR OPERATING BUSINESS PRACTICE DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 2 of 89 TABLE OF CONTENTS Page 1.0 PURPOSE ............. 3 2.0 APPLICABILITY ............ 3 3.0 RESPONSIBILITY ............. 3 4.0 DETAILS ............. 4 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS ..................... 7 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX .......................................... 9 ATTACHMENT 3: RESTART READINESS REVIEW FOR PLANT SHUTDOWN ......................................... 12 ATTACHMENT 4: PLANT INSPECTION DOCUMENTATION SHEET .................. 13 ATTACHMENT 5: OPERATIONAL READINESS AFFIRMATION FORM .............. 14 ATTACHMENT 6: CORE CONFIGURATION AFFIRMATION FORM ................... 15 ATTACHMENT 7: REACTOR STARTUP AFFIRMATION FORM ......................... 16 ATTACHMENT 8 SYSTEM ENGINEER/PROGRAM OWNER READINESS AFFIRMATION FORM ......................................... 17 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE .................................. 18 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA ................21 ATTACHMENT 10: SAFETY CULTURE ASSESSMENT CRITERIA MATRIX ........ 60 ATTACHMENT 11: SAFETY CULTURE ATTRIBUTE ASSESSMENT MATRIX... 61 ATTACHMENT 12: PROGRAM OWNERSHIP LIST ........................................ 62
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page3 of 89 1.0 PURPOSE The purpose of this Business Practice is to provide assurance that the Davis-Besse Nuclear Power Station is ready to restart following the extended plant outage. The framework detailed here establishes a review process for areas not addressed by the Restart Test Plan and DB startup procedures to ensure that Davis-Besse's materiel condition, programs and processes, and organization, including the organization's safety culture are ready for plant restart and safe, reliable operation.
| |
| 2.0 APPLICABILITY This Business Practice applies to the first plant startup following the extended plant outage which began on February 16, 2002. It also applies to subsequent startups from this same outage and therefore shall be re-performed if the startup is halted resulting in an entry into a lower mode.
| |
| Adherence to this Business Practice is mandatory.
| |
| 3.0 RESPONSIBILITY The Vice President-Nuclear is responsible for initiating the Restart Readiness Review Process.
| |
| Each Section Manager and 0350 Restart List Responsible Individual is responsible for the accuracy and adequacy of the reviews performed, actions taken and action plans developed during the review process.
| |
| The Section Managers of Plant Engineering and Operations and the Director-Work Management (Maintenance) are responsible for ensuring plant walk-down inspections are conducted prior to power ascension.
| |
| The Manager-Operations is responsible for affirming: 1) the Operations Section has completed a review of operational readiness and is ready to support the safe and reliable startup and operation of the plant through the next operating cycle; 2) that the plant is in a condition of materiel readiness to support safe and reliable startup and operation and the operating crews are prepared and ready to startup and operate the plant in a safe and reliable manner through the next operating cycle.
| |
| The Supervisor-DB Reactor Engineering is responsible for: 1) following movement of fuel in the reactor core, changes to reactivity control components in the reactor core and/or changes to nuclear instrumentation in the reactor core, verifying that the reactor core is configured to support safe and reliable operation through the cycle.
| |
| This affirmation is required prior to installation of the reactor head; 2) prior to reactor startup, verifying that the required conditions exist to support a safe startup and power ascension.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _ __ DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 4 of 89 Each Director is responsible for the final review of the assessment and action plans developed during the review process by the sections in his department.
| |
| The Chief Operating Officer is responsible for final approval prior to plant restart.
| |
| 4.0 DETAILS
| |
| : 1. The review process shall be initiated early enough to ensure it is completed prior to entry into Modes 6, 4 and 2. The review shall be completed by the milestone date as determined by the responsible Shift Outage Director. All Sections and 0350 Checklist Responsible Individuals, shall submit restart readiness reviews by the milestone dates; not all items have to be complete, provided bullet (4) in Step 3 is appropriately addressed.
| |
| : 2. The process consists of the review and assessment of the specified Restart Readiness Review Indicators. The matrix on Attachment 2 designates the minimum indicators from Attachment 1 that are applicable to each Section and/or 0350 Checklist Item. Each Section and 0350 Checklist Responsible Individual, shall address applicable indicators and should participate in the review and assessment of any indicator for which meaningful input can be provided.
| |
| : 3. The methodology for the review process consists of the following steps:
| |
| * Monitor plant system/component work activity progress during the outage
| |
| * Monitor emergent work/issues during the outage for shutdown concerns
| |
| * Monitor personnel and administrative issues during the outage for restart concerns
| |
| * Assess Restart Readiness Review Indicators as identified on Attachment 1, as applicable per Attachment 2.
| |
| * Assess Safety Culture as identified on Attachment 9, Page 18
| |
| * Identify items to be complete prior to the designated Mode (6, 4 or 2) that have not been completed as of the Shift Outage Director milestone date.
| |
| Ensure a reference is associated with each incomplete item that addresses completion of that item before needed in that mode.
| |
| : 4. Results of the individual indicator assessments, including the status of action plans to support plant restart, will be indicated on Attachment 1, and acknowledged by the signature of the Section Manager or 0350 Checklist Responsible Individual. Indicator assessments should be marked as Final (all conditions are acceptable to support plant restart) or Preliminary (one or more indicators are not currently complete or acceptable and action plans will support
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 5 of 89 plant restart when complete). Details on incomplete items and the status of action plans to eliminate them shall be attached.
| |
| : 5. The signed original Restart Readiness Review Indicators (Attachment 1) should be provided to the Restart Action Process Administrator at the end of the Readiness meetings for inclusion in the Mode Readiness notebook
| |
| : 6. Restart Readiness Review Indicators shall be reviewed by the Senior Leadership Team and approved by the Vice President-Nuclear or Chief Operating Officer, as provided on Attachment 3.
| |
| : 7. Completed Attachments 1 and 3 shall be included with the documentation package assembled in accordance with this Business Practice.
| |
| : 8. Walk down inspections shall be completed prior to power ascension as described in this document and in accordance with EN-DP-01 503, System Walkdowns or Plant Engineering Policy PE-02, System Walkdown Checklist. Results of walkdown inspections shall be documented in Attachment 4 and submitted to the on-shift Engineering Manager.
| |
| : 9. The Shift Manager of each crew should:
| |
| : a. Conduct reasonable and appropriate activities to accomplish the objective of attaining, demonstrating and affirming operational readiness. The Shift Manager should consider the following to support the affirmation of operating crew readiness:
| |
| -adequacy of staffing levels, personnel experience and qualification levels.
| |
| -assure Operations personnel believe the Station can be operated safely by eliciting any outstanding safety concerns from shift personnel and ensuring that the concerns are resolved.
| |
| -completion of appropriate personnel refresher training of shift personnel, including training on plant, procedures and process changes.
| |
| -completion of training of shift personnel on the startup and power ascension plan. This training shall include discussion on the expected behavior and characteristics of the core for this startup.
| |
| : b. Affirm to the best of their knowledge and judgment that the plant is in a condition of materiel readiness to support safe and reliable startup and operation. The Shift Manager should consider the following:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page6 of 89
| |
| -adequacy of the materiel condition of the plant, including the current status of operator work-arounds, to support safe and reliable restart and operation during the next operating cycle.
| |
| -all outage-related temporary fire suppression systems removed and fire protection requirements or commitments ready to support startup.
| |
| -temporary modifications, temporary power feeds, removed/MCCs restored, installed temporary power feeds, if applicable, reviewed to ensure they will not affect safety or operations.
| |
| : c. Complete Attachment 5.
| |
| : 10. The Supervisor-DB Reactor Engineering shall, following movement of fuel, changes to reactivity control components and/or changes to nuclear instrumentation in the reactor core, verify that the reactor core is configured to support safe and reliable operation through the cycle. This affirmation is required prior to installation of the reactor head. Attachment 6, Core Configuration Affirmation Form, details the required review areas and documents the affirmation.
| |
| : 11. The Supervisor-DB Reactor Engineering, shall, prior to a reactor startup, verify that the required conditions exist to support a safe startup and power ascension.
| |
| Attachment 7, Reactor Startup Affirmation Form, details the required review areas and documents that affirmation.
| |
| : 12. Each System Engineer and 0350 Program Owner shall complete Attachment 8, System Engineer/Program Owner Readiness Affirmation Form. The System Engineer forms shall be part of the Plant Engineering Manager's presentation for restart readiness. The 0350 Program Owner's form will be used as part of their readiness discussion. Selected systems (System Engineers) will be identified by the Manager-Operations, Manager-Plant Engineering and Plant Manager to be discussed during the Restart Readiness Review Meetings.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 7 of 89 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS Page 1 of 2 Plant Section or 0350 Checklist Item Acceptable Mode to Support Restart?
| |
| Yes/No/NA 1 All assigned outage work activities are complete to support plant restart and operations. This includes a reconfirmation that previous dispositions of nonconforming conditions or Preventive Maintenance deferrals continue to provide a justification for continued operation. (Attachment 2, Column a) 2 Outstanding Operability Evaluations, CR corrective actions and new CRs generated during the shutdown have been evaluated for operability concerns are either closed or determined to have no impact on operability. (Attachment 2, Column b) 3 Regulatory and internal commitments have been evaluated for operability concerns or restart restraints and are either closed or determined to have no impact on operability. (Attachment 2, Column c) 4 Housekeeping walkdowns utilizing the guidelines of NG-DB-00215, Material Readiness and Housekeeping Inspection Program are complete. (Attachment 2, Column d) 5 The Power Ascension Schedule has been reviewed for accuracy and adequacy ensuring: (Attachment 2, Column e)
| |
| * Post maintenance retest and special testing are identified and scheduled correctly with instructions in place.
| |
| * Planned walkdowns are scheduled appropriately 6 Personnel, materials and special test equipment necessary to support power ascension retest and walkdown activities have been identified and availability is ensured during power ascension. (Attachment 2, Column f) 7 Contingency plans are established for immediate response to plan and repair steam leaks or high-risk test failures. (Attachment 2, Column g) 8 Standing orders have been reviewed for continued applicability and system status sheets completed as required by DB-OP-0691 1, Pre-Startup Checklist. (Attachment 2, Column h) 9 System walkdowns have been performed by Plant Engineering and Maintenance, as directed by Operations, to ensure system readiness for restart.
| |
| 10 Operating Experience reports have been reviewed to ensure no potential operability concems.
| |
| 11 Procedure alterations/PCRs are ready for mode change or restart.
| |
| 12 Work around and burdens identified prior to or during shutdown and not corrected have been confirmed acceptable. (Attachment 2, Column i)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| .________________________ _ . DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 8 of 89 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS (Continued)
| |
| Page 2 of 2 Plant Section or 0350 Checklist Item Acceptable to Support Mode Restart?
| |
| Yes/No/NA 13 All Management and Human Performance Improvement Plan items required for restart are complete. (Attachment 2, Column j) 14 All 0350 Discovery Action Plan milestones identified as required for restart are complete. (Attachment 2, Column k) 15 All 0350 Implementation Action Plan milestones identified as required for restart are complete. (Attachment 2, Column I) 16 All Section Corrective Action Program Improvement Plan activities required for restart have been validated as ready to support restart. (Attachment 2, Column ii) 17 All Condition Reports and corrective actions, work orders, modifications (including EWRs and ECRs) categorized as 0350 are completed. (Attachment 2, Columns m, n, o) 18 All Condition Reports and corrective actions, work orders, and modifications (including EWRs and ECRs) designated as required for restart by the Restart Station Review Board are complete. (Attachment 2, Columns q, r, s) 19 Any required for restart Condition Report or corrective action, work order or modification (including EWRs and ECRs), which cannot be completed prior to restart, has a written exemption from the RSRB. (Attachment 2, Column u) 20 All pending allegations have been reviewed and determined not to affect the restart of the plant. (Attachment 2, Column v) 21 Integrated Restart Report per NG-VP-00100 signed by the SLT. (Attachment 2, Column w)
| |
| Check one Preliminary: I have reviewed the assessment of the Restart Readiness Review Indicators as indicated above and confirm that the attached plans will support plant restart when complete.
| |
| Final: I have reviewed the assessment of the Restart Readiness Review Indicators as indicated above and concur that the current conditions support plant restart.
| |
| Section Manager or 0350 Checklist Individual . . .
| |
| (Please Print Your Name)
| |
| Signature: Date Section Manager or 0350 Checklist Individual
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 9 of 89 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 1 of 3
| |
| : 0) _0 _* _ _
| |
| : o. CA C a) 4)) () O r- <<) U) )
| |
| D a 0 w . 20Ž E co O EC I coo ) _ E 0 .. .
| |
| Plant =__ =____ =__=_=_=
| |
| Operations X X XX X X X X X X X RP X X XX X X X X X Chemistry X X X X X X X X Outage Management X X X X X X X and Work Control _ _
| |
| FIN XXX X X _ X X Mechanical X X __X -_ X X X E&C X X X X X XX Maint. Serv. X X X X X X Training = X s X =- X X Safety= X =_ X_ X X =
| |
| Engineering__
| |
| PlantEngineerin X X X X X X X X X Design Engineering X X X -X X X Proiect Management X X X X X X RRT X X --- X __ ___ X Reactor Engineering X X X X X X X Support Services .___ _ _
| |
| Regulatory Affairs X X X X X X X X (includes Emer. Prep.) ____
| |
| Quality Services X - X - -X X Security =n = = = X XX Other Sections entX___ __
| |
| QA/QC- X X X - X __ _ _ _ X Supply Chain _ X X __ X X Client Services X X Business Services ._ X _X Human Resources _ X X X
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 10 of 89 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 2 of 3 0350 CHECKLIST ITEM RESTART READINESS REVIEW INDICATOR MATRIX C
| |
| 0 Dco> ,XMA ~0 -o C 0 C L)~~
| |
| LDC BE 0~ 00 0 0350 Checklist Item ____MaC
| |
| : 1. Adequacy of Root Cause Determinations- X X X X S. Loehlein, M. Roder, D. Gudger, J. Powers, D. Eshelman, F. von Ahn, L. Myers* __ __
| |
| : 2. Adequacy of Safety Significant Structures, X X X X X Systems and Components-D. Baker, A.
| |
| Stallard, T. Chambers, R. Hovland, J.
| |
| O'Neill*
| |
| : 3. Adequacy of Safety Significant Programs-A. X X X McAllister, L. Dohrmann, S. Loehlein, C.
| |
| Daft, J. Grabnar, R.Farrell, D. Schreiner, R.
| |
| Perry, K. Ostrowski*
| |
| : 4. Adequacy of Organizational Effectiveness X X X X X and Human Performance- M. Bezilla, J.
| |
| Powers*
| |
| : 5. Readiness for Restart-C. Price, F. VonAhn, X X R. Hovland, R. Schrauder, A. Stallard, J.
| |
| Hirsch*
| |
| : 6. Licensing Issue Resolution-J. Powers, K. X X Ostrowski*
| |
| : 7. Confirmatory Action Letter Resolution-L. X Myers, C. Price K. Ostrowski*
| |
| * Or an approved designated alternate
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002 TiUe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 11 of 89 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 3 of 3 REQUIRED FOR RESTART READINESS REVIEW INDICATOR MATRIX
| |
| 'u e.2 C, i X c lw] o 4 U) o EE rv32~-
| |
| i<
| |
| BEB S C MI0 o a. u ~ C 0~~~~~~~~~~~~~~~~~~~~~~~~
| |
| Restart Station~ Review Employee ~ ~ ~ X~ ~ X~~ X U Cocen X X B o a rd _ _ _ _ _ _ _ _ _ _ _ _
| |
| Quality Services __ _ _ _ _ _ X _ _ _ _ _ _ _ _
| |
| Employee Concerns X Program Station Review Board X (Plant Operating Review Committee)
| |
| Company Nuclear Review X Board Restart Overview Panel X
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page12 of 89 ATTACHMENT 3: RESTART READINESS REVIEW FOR PLANT STARTUP Restart/Mode Chance Recommended B:
| |
| Mode_
| |
| Plant Manager-Davis-Besse Nuclear Power Station Date Director-Davis-Besse Nuclear Engineering Date Director-Davis-Besse Work Management Date Director-Davis-Besse Support Services Date Director-Davis-Besse Restart Date RESTART /MODE CHANGE APPROVAL:
| |
| Vice President-Nuclear Date Chief Operating Officer Date
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ___ ___ ___ _ D BBP-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 13 of 89 ATTACHMENT 4: PLANT INSPECTIONIWALKDOWN DOCUMENTATION SHEET Page 1 of 1 Mode_
| |
| ASSET LABEL:
| |
| Or AREA INSPECTED:_
| |
| NOUN NAME:
| |
| LOCATION:
| |
| DESCRIPTION:
| |
| MAINTENANCE TAG/WORK ORDER #:
| |
| CONDITION REPORT INITIATED (#)
| |
| MODE RESTRAINT: res No SUBMITTED BY: DATE/TIME I (please print your name)
| |
| SIGNATURE:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 14 of 89 ATTACHMENT 5: OPERATIONAL READINESS AFFIRMATION FORM Shift Designator:
| |
| Shift Manager:
| |
| (Please Print)
| |
| Mode Review Summary:
| |
| The Shift Manager should initial each item below to affirm that he/she and the operating crew have completed the required actions:
| |
| Shift staffing levels, including personnel experience and qualification levels, are adequate.
| |
| Operations personnel believe the station can be operated safely. All safety concerns have been identified and addressed.
| |
| Appropriate refresher training of shift personnel, including training on plant, procedure and process changes, has been completed.
| |
| Appropriate training of shift personnel on the startup and power ascension plan, have been completed, including discussions on core behavior and characteristics for this startup.
| |
| The materiel condition of the plant, including the current status of operator work-arounds, is adequate to support safe and reliable restart and operation.
| |
| Affirmation:
| |
| Based upon an evaluation of the considerations set forth in Details, 4.0, and to the best of my knowledge andjudgment, the plant is in a condition of materiel readiness to support the safe and reliable startup and power operation through the next operating cycle and the operating crew is ready to startup and operate the plant in a safe and reliable manner.
| |
| Shift Manager:
| |
| Print/Signature/Date Reviews and Aporovals:
| |
| Manager-Operations:
| |
| Print/Sianature/Date
| |
| - -- - - V -- - - --
| |
| l Remarks: (Attach a continuation sheet if applicable)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page15 of 89 ATTACHMENT 6: CORE CONFIGURATION AFFIRMATION FORM Mode_
| |
| Review Summary:
| |
| The Supervisor-DB Reactor Engineering, should initial each item below to affirm that the required conditions exist following movement of fuel in the reactor core, changes to reactivity control components and/or changes to nuclear instrumentation in the reactor core. This affirmation is required prior to installation of the reactor head.
| |
| All new fuel assemblies loaded into the reactor core were inspected, as required, to ensure that the manufacturing and design specifications were met.
| |
| All irradiated fuel assemblies present in the reactor core were inspected, as required, and dispositioned as acceptable for operation through the cycle.
| |
| No fuel assemblies in the reactor core are known leaking assemblies.
| |
| A 10CFR50.59 Reload Safety Evaluation governing reactor core operation has been approved by the Plant Operating Review Committee (PORC)
| |
| The reactor core loading has been verified.
| |
| All reactivity control components in the reactor core will meet their design functions.
| |
| All nuclear instrumentation in the reactor core will meet their design functions.
| |
| Affirmation:
| |
| Based on my knowledge and judgment, the required conditions exist and the reactor core is configured to support safe and reliable operation through the cycle.
| |
| Supervisor-DB Reactor Engineering Print/Signature/Date l Remarks: (Attach a continuation sheet if appropriate)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBB P-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 16 of 89 ATTACHMENT 7: REACTOR STARTUP AFFIRMATION FORM Mode Review Summary:
| |
| The Supervisor-DB Reactor Engineering should initial each item below to affirm that the required conditions exist prior to reactor startup.
| |
| Estimated Critical Conditions have been prepared and independently verified.
| |
| Preparations are complete for any necessary Low Power Physics Testing (i.e. equipment, procedures, calculations, training)
| |
| Personnel are available, as required, to support reactor startup and power ascension to 100%.
| |
| Required training has been completed for Nuclear Fuels personnel.
| |
| Reactivity plans are available, as required, to support reactor startup and power ascension to 100%. These plans include expectations for reactor behavior with emphasis on any behavior that is different from recent plant operation.
| |
| The Core Monitoring System is operable.
| |
| All reactivity control systems will meet their design functions.
| |
| Sufficient nuclear instrumentation is available to safely startup and operate the reactor core.
| |
| There are no outstanding reactivity management issues impacting the safe operation of the reactor core.
| |
| Affirmation:
| |
| Based on my knowledge and judgment, the required conditions exist and the reactor core is ready to support a safe startup and power ascension.
| |
| Supervisor-DB Reactor Engineering Print/Signature/Date Remarks: (Attach a continuation sheet if appropriate)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tide: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 17 of 89 ATTACHMENT 8: SYSTEM ENGINEER/PROGRAM OWNER READINESS AFFIRMATION FORM Mode_
| |
| : 1. Name of System/Program:
| |
| : 2. The status of the system/program is (For systems, a brief description of the physical status of the system including System Health status and Maintenance Rule status. For programs, a brief status of the program):
| |
| : 3. System/Program is ready for Mode Yes_ or No_
| |
| : 4. The system/program is ready for Mode because: (if not ready, skip to #5)
| |
| : 5. The system/program is not ready for Mode because:
| |
| and the following actions are in place to address these issues:
| |
| The system/program will be ready for Mode by: (Date)
| |
| : 6. Items in abnormal status or configuration (workarounds, temporary modifications, Control Room deficiencies) identified and not corrected have been reviewed and determined to be acceptable: Yes_ or No_ (Attach a list of the above items)
| |
| : 7. Housekeeping issues associated with this system/program have been addressed for Mode : Yes_ or No (Attach a list of those not resolved)
| |
| : 8. I have the following concerns about my system and its readiness for Mode :
| |
| Briefly identify concerns. (The Restart Readiness Review process will not resolve these concerns at the meeting. They should be scheduled for presentation to the Plant Support Center if there is a concern relative to this mode change.)
| |
| : 9. Open CRs, CAs, Work Orders or Engineering modifications required for Mode (Attach a list).
| |
| Name: Extension:
| |
| (Please Print)
| |
| Signature: Date:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tilte: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page18 of 89 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 1 of 3 ASSESSMENT OF SAFETY CULTURE Assessment Summary:
| |
| Improving safety culture is a long-term activity that ismonitored by Davis-Besse senior management. For Restart Readiness, it is important to show an improving safety culture with no critical areas of weakness that management evaluates as a restart concern. The individual criteria that make up the Commitment Areas may be green, white, yellow or red. Some of the Commitment Areas may be white (Policy or Corporate Commitment Area, Plant Management Commitment Area or Individual Commitment Area) however restart will not be approved if any of the three are red, or yellow without restart corrective actions being completed.
| |
| Remedial actions will be taken for any red criteria. Condition Reports will be written for all red and yellow criteria at the site and/or section level, with corrective actions to identify an existing or new plan for improvement. Corrective Actions may take credit for ongoing activities. Red criteria corrective actions will be formally presented to the Senior Leadership Team. If a Condition Report is written at the site level for a red or yellow Commitment Area or criteria, it will encompass any red or yellow section Commitment Area or criteria and that section need not write a separate Condition Report. If there isno site wide red or yellow Commitment Area or criteria then the Section Manager will write a Condition Report for the red or yellow Commitment Area or criteria.
| |
| The threshold for rating the attributes that comprise each criteria are provided in Appendix A. These thresholds are guidelines. Management may consider other factors and adjust the ratings accordingly. Management judgment isa key factor that cannot be removed or quantified. The purpose of the collegial group review is to challenge, seek alternative input, and facilitate dialogue and to determine final criteria and Commitment color rating Ifother factors are considered, they shall be documented in an attachment to the Rating sheet. The ratings are based on convergent assessment such as: performance indicators, management observations, demonstrated performance during critical plant conditions surveys and interviews, training and feedback from independent safety culture reviews and Nuclear Quality Assurance Assessments. Each criterion will be assessed using information from the attribute reviews performed. An overall assessment of each attribute and criterion will be performed and documented explaining any that are rated as red or yellow and identifying the corrective actions needed prior to restart.
| |
| The ratings for an individual attribute will reflect recent activities or the most recent assessment data. If no applicable activities or assessments have been conducted within the past 12 months (i.e., there isno information applicable to the review period), the attribute shall be marked NA", (Not Applicable). If both objective and subjective data are available, differences in data will be evaluated and decisions on use of data made.
| |
| Safety Culture Commitment Area/Criteria Ratings:
| |
| Green: all major criteria/attributes are acceptable with a few minor criteria deviations White: all major criteria/attributes are acceptable with a few criteria requiring management attention Yellow: all major criteria/attributes are acceptable with several criteria requiring prompt management action Red: several major criteria/attributes do not meet acceptable standards and require immediate management action
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 19 of 89 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 2 of 3 Each Section Manager will provide a Rating sheet (ATTACHMENT 9, Page -20,) with the Final Restart Readiness Criteria. For any individual attribute where only site-wide numbers are available (e.g. 4Cs surveys, ECP etc.), or for any individual attribute not applicable to a section (e.g. operator work-arounds for other than Operations), the Manager will NA that attribute on his backup sheets and that attribute will not be used as part of the site-wide tally for the criteria. For any attribute where "surveys andlor interviews" are used as the basis for the rating, these surveys must be written but may be anonymous. Interview results will also be documented as to results although they may also be anonymous. The results for surveys or interviews will be maintained until after restart.
| |
| Documentation for Attachment 9 may be in the form of a tally for these survey or interview results.
| |
| At the final Restart Readiness Review meeting for any mode, a site-wide Rating sheet will be prepared by the management team using the individual section ratings as a guideline. The final Rating sheet will be signed by the Vice President-Nuclear and maintained with the other Restart Readiness documentation, including Attachment 11.
| |
| Preliminarily, determination of the Commitment Area/criteria color will be based on an average of the ratings of the associated criteria/attributes. Considerations include:
| |
| Greater than one red attribute or criteria means the criteria or Commitment Area can be no better than yellow. If more than two or more than 1/3 (whichever is greater) of the attributes or criteria are red, the indicator or Commitment Area shall be red.
| |
| For the overall plant ratings for Commitment Areas/criteria, management will consider whether the problems taken collectively indicate a more significant concern than indicated by the averages. For example, one section may perform more activities related to safety with respect to a certain criteria than other sections, and management may adjust the color to give greater weight to that section in determining the final color rating. Similarly, if percentages or averages alone indicate a positive rating but there were several associated safety-significant events or conditions, management may provide a more negative color rating to reflect those events or conditions.
| |
| If such an adjustment is made, it shall be documented. Generally, if all sections have similar rating, the overall rating for the plant will be the same as the ratings for the individual sections. During group review, senior management will seek to verify that the entire Restart Readiness Review team not only concurs, but also aligns behind the assessment.
| |
| At the completion of the Safety Culture Assessment, an evaluation of the significance of the overall assessment ratings for criteria to focus on the process and organization will be completed using Attachment 10 at the end of the document. A final report will then be prepared which documents how each Commitment Area, criteria and attribute was assessed and its final color rating. The report will also document any red or yellow area, criteria or attribute, corrective actions needed for restart and explain why restart is acceptable with the current condition.
| |
| Attachments 10 and 11 will be included as part of that report.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 20 of 89 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 3 of 3 Rating Safety Culture Mode_
| |
| Item Color
| |
| : 1. Policy or Corporate Commitment Area
| |
| : a. Policies on Safety Culture and Safety Conscious Work Environment clearly state that safety is a core value and are understood by the organization
| |
| : b. Management values are clearly reflected in the Business Plan and are understood by the organization
| |
| : c. Resources are available or can be obtained to ensure safe, reliable operations
| |
| : d. Self-Assessment is a tool used to monitor, assess and improve our performance
| |
| : e. Independent Oversight is a tool used to validate acceptable performance and identify areas for improvement or corrective action
| |
| : 2. Plant Management Commitment Area
| |
| : a. There is a visible commitment to safety: nuclear, industrial, radiological and environmental
| |
| : b. Goals and roles are clear and teamwork is reinforced
| |
| : c. Ownership and accountability is evident
| |
| : d. Training and Qualification are valued
| |
| : e. Commitment to continuous improvement is evident
| |
| : f. Cross-functional work management and communication
| |
| : g. Creating an environment of engagement and commitment
| |
| : 3. Individual Commitment Area
| |
| : a. Drive for excellence-nuclear assets of people and plant are continuously improved to enhance margins of safety
| |
| : b. Questioning attitude-challenges are welcomed
| |
| : c. Rigorous work control and prudent approach-performing activities in a quality manner is the standard
| |
| : d. Open communications-associates are comfortable in voicing opinions, issues and concerns
| |
| : e. Nuclear Professionalism-persistence and urgency in identification and resolution of problems is prevalent I have reviewed the Rating of Safety Culture as indicated above and concur that the current conditions support readiness for mode change.
| |
| Section Manager (Please Print Your Name)
| |
| Signature: _ Date_
| |
| Section Manager Adjustments to ratings from the standard criteria should be documented and attached to this page.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberD
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 21 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 1 of 39
| |
| : 1. POLICY COMMITMENT AREA Ia. CRITERIA RELATED TO STATEMENT OF SAFETY POLICY Policies on Safety Culture and Safety Conscious Work Environment clearly state that safety is a core value and are understood by the organization ATTRIBUTE RED YELLOW WHITE GREEN Policy statement Policy statement is Policy statement is Policy statement is Policy statement is on Safety Culture* issued but it is not issued but only issued and is issued and is reinforced by occasionally reinforced frequently reinforced continuously reinforced FENOC by FENOC by FENOC by FENOC management management. management. management.
| |
| Policy statement Policy statement is Policy statement is Policy statement is Policy statement is on Safety issued but it is not issued but only issued and is issued and it isa strong Conscious Work reinforced by occasionally reinforced frequently reinforced statement of safety Environment FENOC by FENOC by FENOC conscious work (SCWE)* management. management. management. environment and often reinforced by FENOC management Making employees Policy statements Policy statements Policy statements are Policy statements are aware of policy simply issued as distributed separately communicated by at communicated to statements* part of FENOC to employees in least two employees and (Explain why white Business Plan. memo. means.(e.g., hard emphasized regularly in isacceptable if there copy distribution, meetings and face to is no face to face newsletters, group face communication.
| |
| communication) meetings, training, stand down).
| |
| Employee Surveys/interviews Surveys/interviews Surveyslinterviews Surveys/interviews understanding of indicate less than indicate that 70-80% of indicate that 80-90% indicate that more than policies** 70% of employees the employees of employees 90% of employees understand the understand the understand the understand the policies policies. policies and consider policies and consider and consider safety a safety a FE value. safety a FE value. FE value and the normal way to do business.
| |
| Worker Surveys/interviews Surveys/interviews Surveys/interviews Surveys/interviews understanding of indicate that less indicate that between indicate that between indicate that more than responsibility to than 85% of workers 85-90% of workers 90-95% of workers 95% of workers raise safety understand their understand their understand their understand their concerns* responsibility to raise responsibility to raise responsibility to raise responsibility to raise nuclear safety or nuclear safety or nuclear safety or nuclear safety or quality quality concerns. quality concerns. quality concerns. concerns.
| |
| * Site wide assessment only. Data provided from Edventures survey results
| |
| ** Site wide assessment only. Data provided from Edventures survey results and 4Cs.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 22 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 2 of 39
| |
| : 1. POLICY COMMITMENT AREA I b. CRITERIA RELATED TO MANAGEMENT VALUES Manaaement values are clearly reflected in the Business Plan and are understood by the organization ATTRIBUTE RED YELLOW WHITE GREEN Corporate values* There is no There is a There is a corporate There is a corporate corporate level corporate level level statement of level statement of statement of statement of commitment to commitment to safety.
| |
| safety values. commitment to safety. FirstEnergy FirstEnergy FirstEnergy safety. management meets management meets management FirstEnergy occasionally with frequently with plant does not management plant personnel to personnel to express its express its meets express its safety safety values.
| |
| safety values to infrequently with values.
| |
| plant personnel. plant personnel to express its safety values.
| |
| Statement of There is no The statement of The statement of The statement of mission, vision, statement of Mission, Vision, Mission, Vision, and Mission, Vision, and and values** Mission, Vision, and Values Values places greater Values emphasizes and Values and places weight on weight on safety than safety first, then allows employees safety and often on production/profits consideration of believe focus is employees and most employees production and profits on production believe the agree that the and over 90% of and profits. overriding focus overriding priority is employees agree based is safety on safety on surveys.
| |
| FENOC Business Business Plan Business Plan Business Plan Business Plan contains Plan* contains no contains few contains Strategic Strategic Objective Strategic Strategic Objective Measures Measures on safety and Objective Objective on safety with all are being fully Measures on Measures on implementation plans. implemented.
| |
| safety. safety but no implementation plans
| |
| *Site wide assessment only. Data provided by Senior Management
| |
| ** Site wide assessment only. Data provided from Edventures survey results
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 23 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 3 of 39
| |
| : 1. POLICY COMMITMENT AREA Ic. CRITERIA RELATED TO RESOURCES Resources are available or can be obtained to ensure safe, reliable operations ATTRIBUTE RED YELLOW WHITE GREEN Adequacy of More than five More than three Three or less All management management supervisor or above supervisor or supervisor or above positions are filled with resources* positions are not above positions positions are not filled ANSI qualified FENOC filled with ANSI are not filled with with ANSI qualified individuals.
| |
| qualified FENOC ANSI qualified FENOC individuals.
| |
| individuals. FENOC individuals.
| |
| Adequacy of More than four Three or four One or two sections Each section has a full personnel sections do not have sections do not do not have sufficient complement of resources*# sufficient personnel have sufficient personnel to perform personnel (minus to perform their personnel to their assigned normal attrition) to assigned perform their responsibilities perform its assigned responsibilities assigned without contractor responsibilities.
| |
| without contractor responsibilities support support without contractor support Adequacy of Risk significant The majority of All risk significant Sufficient funding exists funding activities, to improve identified risk identified to perform more than nuclear safety, as significant improvements to just risk significant defined by the improvements to nuclear safety, as improvements, as Senior Leadership nuclear safety, as identified by the PRC identified by the PRC in Team and Project identified by the for the plant, plant, programs and Review Committee PRC for the plant, programs, or other other activities to (PRC) are not being programs, or activities, are funded improve nuclear safety.
| |
| funded in a timely other activities, in a timely manner.
| |
| manner and funding are funded in a was requested and timely manner.
| |
| rejected by FENOC Executive Management.
| |
| * Site wide assessment only. Data provided by Human Resources
| |
| *#Significance evaluation regarding resources will be discussed depending on contractor support by section. Color identified for site after section discussion
| |
| **Site wide assessment only. Data provided by the chairman of the PRC
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ __ _D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 24 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 4 of 39
| |
| : 1. POLICY COMMITMENT AREA 1c. CRITERIA RELATED TO RESOURCES (continued)
| |
| Resources are available or can be obtained to ensure safe, reliable operations Adequacy of tools, More than 25 % Between 20- Between 10-20% of Less than 10% of material and of scheduled 25% of scheduled scheduled tasks scheduled tasks PMs, equipment to tasks (PMs, tasks (PMs, Work (PMs, Work Orders, Work Orders, ECRs complete site Work Orders, Orders, ECRs ECRs and projects) and projects) are not tasks* ECRs and and projects) are are not being being completed by the projects) are not not being completed by the site site in a timely manner being completed completed by the in a timely manner due to ack of tools, by the site in a site in a timely due to lack of tools, material or equipment.
| |
| timely manner manner due to material or due to ack of lack of tools, equipment.
| |
| tools, material or material or equipment. equipment.
| |
| Adequacy of tools, More than 25% Between 20-25% Between 10-20% of Less than 10% of key material and of key scheduled of key scheduled key scheduled tasks scheduled tasks are not equipment to tasks are not tasks are not are not being being completed by the complete Section being completed being completed completed by the section in a timely tasks by the section in by the section in section in a timely manner due to lack of a timely manner a timely manner manner due to lack of tools, material or due to lack of due to lack of tools, material or equipment.
| |
| tools, material or tools, material or equipment.
| |
| equipment. equipment.
| |
| *Site wide assessment only. Data provided by Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 25 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 5 of 39
| |
| : 1. POLICY COMMITMENT AREA 1d. CRITERIA RELATED TO SELF-ASSESSMENT Self-Assessment is a tool used to monitor, assess and improve our performance ATTRIBUTE RED YELLOW WHITE GREEN Use of Nuclear Less than 70% of Between 70-80% of Between 80-90% of More than 90% of the Quality the sections have the sections have the sections have sections have used Assurance to used NQA input used NQA input to used NQA input to NQA to supplement supplement the to supplement the supplement the supplement the self- the self-assessment self- self-assessment self-assessment assessment process process as defined in assessment process as defined process as defined as defined in NOBP- NOBP-LP-2004 process in NOBP-LP- 2004 in NOBP-LP-2004 LP-2004 Self- Less than 60% of Between 60-75% of Between 75-90% of More than 90% of assessments in sections (< 14) sections (15-17) sections (17-20) sections (>20) have accordance have planned have planned have planned planned ongoing self-with NOBP-LP- ongoing self- ongoing self- ongoing self- assessments for 1S &
| |
| 2004, FENOC assessments for assessments for Ist assessments for I t 2'd quarter 2004.
| |
| Ongoing Self- At & 2rd quarter & 2nd quarter 2004. & 2x quarter 2004.
| |
| Assessment 2004.
| |
| Guideline*
| |
| Section Performance Section performance Section performance Section performance Performance indicators related to indicators exist for indicators exist for indicators exist and are Indicators safety and quality important activities important activities appropriate and are being exist for the section affecting quality and affecting quality and regularly updated for safety but less than safety and 75-89% of important activities 75% of goals are met goals are met affecting safety and quality, with more than 90% of goals met.
| |
| Personnel The performance The performance The performance The performance Performance appraisal program appraisal program appraisal program appraisal program Appraisals** does not include includes includes assessments includes assessments of assessments of assessments of of safety or quality of safety and quality of safety or quality of safety or quality of performance but some performance and the performance. performance but most appraisals have not appraisals are being employee appraisals been performed in performed in timely have not been timely manner and manner and all performed. some employees do employees have a current not have a current appraisal.
| |
| appraisal.
| |
| *Site wide assessment only. Data provided by Quality Services
| |
| **Site wide assessment only. Data provided by Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 26 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 6 of 39
| |
| : 1. POLICY COMMITMENT AREA le. CRITERIA RELATED TO INDEPENDENT OVERSIGHT Oversight is a tool used to show acceptable performance and identify areas for improvement and corrective actions.
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Nuclear The Nuclear The Nuclear The Nuclear The Nuclear Committee Committee of Committee of the Committee Committee has safety has safety performance Board of Board has little occasionally discusses performance as a part as a part of the agenda Directors* focus on safety safety performance as of the agenda every every meeting and performance in the a topic inthe agenda. meeting requests additional agenda. presentations relative to specific issues to monitor performance Company The CNRB has a The CNRB agenda The CNRB agenda The CNRB agenda has Nuclear Review safety has a safety has a safety a safety discussion Board (CNRB)+ performance discussion and discussion at every every meeting and is assessment monitors safety meeting and reviews proactive in providing discussion on the performance presentations on safety focus actions for agenda. safety focus issues FENOC Nuclear Quality NQA is not Some NQA audits or NQA audits or NQA is regularly Assurance performing audits assessments were assessments were performing audits and (NQA)** or assessments of performed when performed when assessments of important safety required and a number required, for important important safety activities and not of areas of concern safety activities and activities and identifying finding areas of were identified for some Significant key issues for concern causing important safety Conditions Adverse to improvement that are Significant activities causing Quality were noted below the Significant Conditions Significant Conditions Condition Adverse to Adverse to Quality Adverse to Quality Quality threshold.
| |
| Leaming from Personnel in the Personnel in the Personnel in the Personnel in the section the experience section do not section seldom section occasionally routinely participate in of the industry participate in participate in industry participate in industry industry committees, industry committees, visit other committees, visit other visit other sites or host committees, visit sites or host personnel sites or host personnel personnel from other other sites or host from other sites from other sites sites personnel from other sites
| |
| *Site wide assessment only. Data provided by Senior Management
| |
| +Site wide assessment only. Data provided by NQA Manager or VP Oversight
| |
| **This item is assessed by NQA only.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 27 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 7 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Management There is a There is a management There is a There is a management observations management observation program management observation program pedformed as observation program and 65-75% of observation program and more than 90% are scheduled with and less than 65% management and 76-90% are performed as proper of the observations observations are performed as scheduled and less coaching* are performed as performed as scheduled and less than 5% rated as scheduled and scheduled and greater than 10% rated as overall unsat.
| |
| >90% indicate no than 10% were rated overall unsat.
| |
| coaching required. overall unsat.
| |
| Management Most management Between 50-74% of the Between 75-89% of More than 90% of the observations observations are not management the management management are self self-critical. observations performed observations observations performed critical* are self-critical and performed are self- are self-critical and actions implemented. critical and actions actions implemented.
| |
| implemented.
| |
| Management No method has been One method has been Two means have Multiple means have emphasis on used in the last used in the last month been used in the last been used by safety to month to provide to provide emphasis on month to provide management in the last employees; emphasis on safety safety to employees in emphasis on safety to month to provide face questioning to employees in the the section (e.g., town employees in the to face emphasis on attitude section (e.g., town hall, 4Cs or All Hands section and at least safety to employees in hall, 4Cs, or All meetings, standdowns, one was face to face the section (e.g., town Hands meetings, newsletters, and (e.g., town hall, 4Cs hall, 4Cs or All Hands standdowns, training). or All Hands meetings, standdowns, newsletters, and meetings, newsletters, and training). standdowns, training).
| |
| newsletters, and training).
| |
| *Site wide assessment only. Data provided by Management Observation Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 28 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 8 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY (continued)
| |
| There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Leadership in Leadership in Leadership in Action Leadership in Action Leadership in Action* Action includes includes discussions on includes discussions Action includes discussions on safety culture.
| |
| * on safety culture.
| |
| * discussions on safety culture.
| |
| * And And safety culture.
| |
| * And Employee feedback Employee feedback And Employee feedback indicates it was indicates it was very Employee indicates it was not effective effective. feedback indicates effective. it was very And And effective And Leadership in Action Leadership in Action And Leadership in training has been training has been Action training has available and available and Leadership in been available and scheduled for more scheduled for more Action training has scheduled for less than 75% of than 80% of been available and than 75% of supervisors and above supervisors and scheduled for supervisors and within 12 months of above within 12 more than 85% of above within 12 new appointment.* months of new supervisors and months of new appointment.* above within 12 appointment.* months of new appointment.*
| |
| Problem solving** A problem solving In more than 5 cases, In all but one case, The problem process exists but the problem solving the problem solving solving process, there Is no use of process NOP-EN-3001 process, NOP-EN- NOP-EN-3001 has the document in the has not been properly 3001 has been been properly section and CRs implemented in the properly implemented implemented in were written to section for applicable in the section for the section for document the conditions and CRs applicable conditions applicable failure to use the were written in the during the previous conditions during process during the previous quarter. quarter. the previous previous quarter. quarter.
| |
| *Site wide assessment only. Data provided by Human Resources
| |
| **Site wide assessment only. Data provided by Plant Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 29 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 9 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY (continued)
| |
| Ther re is a visible commitment to safety: nuclear. industrial. radioloaical and environmental ATTRIBUTE RED YELLOW WHITE GREEN Decision A Safety significant A Safety significant The majority of safety Safety significant making Condition Adverse to Condition Adverse to significant decisions decisions were made in Quality Condition Quality Condition were made in the the section with Report indicates that Report indicates that section with adequate required information, decisions were decisions are made in information, management oversight, made in the section the section with minimal management involvement and peer in isolation without information, oversight, checking during the adequate management oversight, involvement and peer past six months as information, involvement and peer checking during the indicated by no SCAQs.
| |
| management checking during the quarter as indicated oversight, past two months. by no SCAQs.
| |
| involvement and peer checking during the past month.
| |
| Improvements There have been There have been some There have been Significant in safety minimal improvements made in obvious improvements have margin* improvements made safety margin. improvements made been made in safety in safety margin. in safety margin. margin.
| |
| Plant activities A significant plant Two Condition Adverse Significant plant Significant plant receive proper event, associated to Quality CRs activities associated activities associated management with the section, associated with the with the section had a with the section had a attention and occurred during the section were written management plan management plan with safety focus previous quarter and due to lack of with a management a management sponsor a lack of a management attention sponsor and and management (Reference management or lack of safety focus management oversight scheduled for NG-DB-00800) attention or safety during the previous oversight scheduled the duration of the focus was indicated quarter. for the duration of the activity and no CAQ and an SCAQ activity and only one events occurred during written. CAQ event occurred the previous quarter.
| |
| indicating a lack of management attention during the previous quarter.
| |
| *Site wide assessment only. Data provided by Design Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tide: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 30 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 10 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2.b CRITERIA RELATED TO ROLES AND TEAMWORK Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Understanding Station surveys Station surveys Station surveys and/or Station surveys that safety is and/or interviews and/or interviews, interviews show that 80- and/or interviews highest priority* show that less show that 70-80% 90% of employees, show that more than than 70% of of employees, understand that safety is 90% of employees in employees understand that the highest priority. that safety is the understand that safety is the highest highest priority.
| |
| safety isthe priority.
| |
| highest priority.
| |
| Program Five or more of the All identified All identified programs All identified ownership** identified programs have have assigned owners. programs have programs in the assigned owners With several exceptions, assigned owners. In program review do and 3-4 SCAQI program owners are general, program not have assigned CAQs were written implementing their owners are 9 owners and > five on different assigned responsibilities implementing their SCAQ/CAQs were programs in the and 1-2 SCAQ/CAQs assigned written against past quarter. were written on different responsibilities and different programs programs in the past no SCAQQ/CAQs in the past quarter. quarter. were written against programs in the last quarter.
| |
| Ownership of More than 5% of 5% of SCAQ Less than 5% of SCAQ Less than 5% of corrective SCAQ remedial remedial or remedial or preventive SCAQ remedial and actions and preventive preventive restart restart required preventive restart restart required required corrective corrective actions and required corrective Does not include corrective actions actions and 10% of 10% of CAQ remedial and actions less than CRs or CAs linked and more than CAQ remedial and and preventive restart 10% of CAQ remedial to P3 activities. 10% of CAQ preventive restart required corrective and preventive restart remedial and required corrective actions for the section, required corrective preventive restart actions for the have received 2 actions for the section required corrective section, have extensions for the have received less actions for the received more than previous quarter. the previous quarter.
| |
| section have 2 extensions for the required more previous quarter.
| |
| than 4 extensions for the previous quarter.
| |
| *Site wide assessment only. Data provided from Edventures survey results
| |
| **Site wide assessment only. Data provided by Plant Engineering Manager. See Attachment 12 for identified programs.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Me: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 31 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 11 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2b. CRITERIA RELATED TO ROLES AND TEAMWORK (continued)
| |
| Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Ownership of The quality of The quality of The quality of The quality of engineering engineering engineering engineering engineering products as products as products as products as products as measured by the EAB is measured by the measured by the measured by the measured by the 1.0 or less.
| |
| Engineering EAB isgreater EAB is between EAB is between 2.0 Assessment Board than 3.0. 3.0 and 2.1. and 1.1.
| |
| (EAB)*
| |
| Effectiveness of The individual The individual The individual error The individual error rate supervision of error rate is >0. error rate is <.45- rate is<.35->.26 is<0.26 individual errors individuals" 45 individual >.36 individual individual errors per per 10,000 hours errors per errors per 10,000 10,000 hours worked.
| |
| 10,000 hours hours worked. worked.
| |
| worked.
| |
| Intra-department As a Manager, I As a Manager, I As a Manager, I As a Manager, I believe teamwork and believe there is believe there is believe alignment is alignment and teamwork alignment ((Some no alignment minimal improving and are obvious among unit supervisors and little alignment and teamwork can be managers in all activities will input to this teamwork some teamwork seen in some key of my department.
| |
| attribute, such as, among my among my activities among my Reactor Department's Department's Department's Engineering and managers. managers. managers.
| |
| RRT.)
| |
| Expectations Four or more Three sections One or two sections All sections have sections do not do not have do not have statements of have statements statements of statements of expectations and 9 of expectations. expectations. For expectations. For managers are For those those that do, those that do, most reinforcing them and sections that do, most employees employees employees understand employees implement them. implement them. and routinely implement frequently do not them.
| |
| implement them.
| |
| *Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| **Site wide assessment only. Data provided by Human Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 32 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 12 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2b. CRITERIA RELATED TO ROLES AND TEAMWORK (continued)
| |
| Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Trust, openness 4Cs surveys 4Cs surveys 4Cs surveys show 4Cs surveys show more and focused show less than show 50-70% of 70-90% of than 90% of employees commitment" 50% of employees feel employees feel that feel that work groups employees feel that work groups work groups display display high levels of that work groups display high high levels of trust, trust, openness and display high levels of trust, openness and commitment.
| |
| levels of trust, openness and commitment.
| |
| openness and commitment.
| |
| commitment.
| |
| Clear goals and No clear goals Goals and Goals and priorities Employees are clear priorities and priorities priorities exist for exist for the section about goals and have been the section but and most employees priorities for the section established for are not understand and own as well as how their role the section adequately them. contributes to achieving understood and them.
| |
| owned by some employees.
| |
| Input and No employee Only managers Managers and Employees are involvement input and and supervisors supervisors appropriately involved in involvement are involved in occasionally request setting section goals and occurs in the the setting of inputlinvolvement establishing work setting of section section goals and from employees in priorities.
| |
| goals and establishing work the setting of section establishing priorities. goals and work priorities. establishing work priorities.
| |
| ** Site wide assessment only. Data provided by Chief Operating Officer
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tibe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 33 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 13 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY Ownership and accountability is evident ATTRIBUTE RED YELLOW WHITE GREEN Performance Less than 70% of Between 70-80% Between 80-90% of More than 90% of reviews in performance of performance performance reviews performance reviews for accordance with reviews for the reviews for the for the section were the section were FENOC section were section were completed for the completed for the review Performance completed for the completed for the review period period Management review period review period Process*
| |
| Development Less than 70% of Between 70-80% Between 80-90% of More than 90% of plans* managers and of managers and managers and managers and supervisors have supervisors have supervisors have supervisors have development development development plans development plans plans submitted plans submitted submitted to HR submitted to HR to HR to HR Restart There is no A restart A restart readiness A restart readiness Readiness restart readiness readiness review review process review process exists Reviews** review process. process exists exists and is and is implemented but implemented with efficiently and with implementation is the majority of participation by poor as shown by Managers and the Managers and the lack of Manager Senior Leadership Senior Leadership Team participation. Team participation.
| |
| Worker Surveys and/or Surveys and/or Surveys and/or Surveys and/or understanding of interviews interviews interviews indicate interviews indicate that their responsibility indicate that less indicate that that between 90- more than 95% of to raise safety than 80% of between 80-90% 95% of workers workers understand their concerns# workers of workers understand their responsibility to raise understand their understand their responsibility to raise nuclear safety or quality responsibility to responsibility to nuclear safety or concerns.
| |
| raise nuclear raise nuclear quality concerns.
| |
| safety or quality safety or quality concerns. concerns.
| |
| *Site wide assessment only. Data provided by Human Resources
| |
| **Site wide assessment only. Data provided through discussion at the Restart Readiness Review meeting
| |
| # Site wide assessment only. Data provided from Edventures survey results
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 34 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 14 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY(continued)
| |
| Ownership and accountability is evident Willingness to Surveys show Surveys show Surveys show that Surveys show that more raise safety that less than that between 85- between 90-95% of than 95% of personnel concerns* 85% of personnel 90% of personnel personnel are willing are willing to raise safety are willing to are willing to to raise safety concerns through their raise safety raise safety concerns through supervisor, a CR or concerns through concerns through their supervisor, a ECP.
| |
| their supervisor, a their supervisor, a CR or ECP.
| |
| CR or ECP. CR or ECP.
| |
| SRO reviews for Less than 90% Between 90-95% Between 95-98 % More than 98% were Operability are were completed were completed were completed completed within 24 performed in a within 24 hours. within 24 hours. within 24 hours. hours.
| |
| timely manner for the identified period of this review**
| |
| System Less than 80% Between 80-90% Between 90-95% of More than 95% of the assessments+ of restart required of the restart the restart required restart required improvements in required improvements in improvements in safety safety have been improvements in safety have been have been implemented implemented at safety have been implemented at this at this time this time. implemented at time.
| |
| this time.
| |
| *Site wide assessment only. Data provided by 4Cs program and /or Employee Concerns Program
| |
| **This Item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Plant Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number Tite: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 35 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 15 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY (continued)
| |
| Ownership and accountability is evident NQA field NQA field NQA field NQA field NQA field assessments assessments** assessments assessments assessments show show that managers and show that show that that managers and supervisors are managers and managers and supervisors are generally effective.
| |
| supervisors are supervisors are generally effective, generally generally with a few ineffective. effective, with exceptions.
| |
| several noteworthy exceptions.
| |
| Management Less than 80% Between 80-85% Between 85-95% of More than 95% of observations of management of management management management leading to participating in participating in participating in the participating in the coaching+ the Management the Management Management Management Observation Observation Observation Observation Program Program, have Program, have Program, have have performed a performed a performed a performed a coaching session in the coaching coaching session coaching session in last month.
| |
| session in the in the last month. the last month.
| |
| last month.
| |
| Timeliness of Less than 50% Between 50% Between 75% and More than 90% of my corrective actions of my section's and 74% of my 90% of my section's section's corrective 19 corrective section's corrective actions actions designated as Does not include actions corrective actions designated as required for restart, are CRs or CAs linked to designated as designated as required for restart, complete at this time P3 activities required for required for are complete at this restart are restart are time complete at this complete at this time time
| |
| ** This item assessed by NQA only
| |
| +Site wide assessment only. Data provided by Management Observation Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tite: Revsion: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 36 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 16 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2d. CRITERIA RELATED TO TRAINING AND QUALIFICATION Training and Qualification are valued ATTRIBUTE RED YELLOW WHITE GREEN Restart training+ Most required Between 75-90% Between 90-99% of 100% of required restart training is of required restart required restart restart training is (Explain why not complete. training is training is complete. complete.
| |
| acceptable if less complete.
| |
| than green)
| |
| Initial Operator Individuals in Individuals in Individuals in initial Individuals in initial training** initial license initial license license class are license class are class are class are maintaining a class maintaining a class maintaining a maintaining a average of 88-94% average of more than class average of class average of 94%
| |
| 82% or less 83-87%
| |
| Requalification Less than 70% of Between 70-84% Between 85-95% of More than 95% of the training** licensed of the licensed the licensed licensed operators have operators have operators have operators have passed their (Explain why passed their passed their passed their requalification training.
| |
| acceptable if less requalification requalification requalification than green) training. training. training.
| |
| "This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Nuclear Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 37 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 17 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2d. CRITERIA RELATED TO TRAINING AND QUALIFICATION (continued)
| |
| Training and Qualification are valued Operability Less than 50% of Between 50-74% Between 75-90% of More than 90% of determination applicable of applicable applicable operators applicable operators training* operators and operators and and engineers have and engineers have (Explain why engineers have engineers have received training on received training on acceptable if less received training received training operability operability than green) on operability on operability determinations. determinations.
| |
| determinations. determinations.
| |
| Training on Less than 80% Between 80-89% Between 90-97% of More than 97%
| |
| SCWE of managers, of managers, managers, managers, supervisors, supervisors, and supervisors, and supervisors, and and operators have (Explain why operators have operators have operators have received training on acceptable if less received training received training received training on SCWE.
| |
| than green) on SCWE. on SCWE. SCWE.
| |
| Training on Less than 70 % Between 70-80% Between 80-90% of More than 90% of decision making of applicable of applicable applicable personnel applicable personnel process* personnel have personnel have have received training have received training received training received training on the decision on the decision making on the decision on the decision making process. process.
| |
| making process. making process.
| |
| Training on Less than 80% Between 8049% Between 90-95% of More than 97% of standards and of personnel in of personnel in in the section personnel in the expectations the section have the section have personnel have section, have received (Explain why received training received training received training on training on standards acceptable if less on standards and on standards and standards and and expectations.
| |
| than green) expectations. expectations. expectations.
| |
| Continuing Less than 70% of Between 70-80% Between 80-90%of More than 90% of training identified scheduled of scheduled scheduled training scheduled training by Curriculum training identified training identified identified by the CRC identified by the CRC is Review by the CRC is by the CRC is is completed in a completed in a timely Committee completed in a completed in a timely manner. manner.
| |
| (CRC)** timely manner. timely manner.
| |
| *This item assessed by Operations and Engineering only
| |
| **Site wide assessment only. Data provided by Nuclear Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 38 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 18 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Improvements in Most requisitions About 50% of open About 75% of open At least 85% of open management for management requisitions for requisitions for requisitions for staffing* positions (all management (all management management positions exempt employees) exempt employees) positions (all exempt (all exempt employees) have not been filled positions have employees) have have been filled in the in the past month. been filled in the been filled inthe past month.
| |
| past month. past month.
| |
| CorrectiveAction There are no The CARB has The CARB has been The CARB has been Review Board directors on the been enhanced enhanced with enhanced with director-(CARB)+ CARB. with director-level director-level level personnel.
| |
| personnel. personnel.
| |
| The backlog of The backlog of documents awaiting The backlog of The backlog of documents awaiting CARB review is documents awaiting documents awaiting CARB review is less more than four CARB review is CARB review is less than one week.
| |
| weeks. less than four than two weeks.
| |
| weeks.
| |
| Engineering The backlog of The backlog of The backlog of The backlog of Assessment documents awaiting documents awaiting documents awaiting documents awaiting EAB Board (EAB)++ EAB review is EAB review is less EAB review is less review is less than one greater than four than four weeks. than two weeks. week.
| |
| weeks.
| |
| *Site wide assessment only. Data provided by Human Resources
| |
| +Site wide assessment only. Data provided by Performance Improvement
| |
| ++Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 39 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 19 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT(continued)
| |
| Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Benchmarking Less than 60% (< Between 60-75% Between 75-90% of More than 90% of against industry 14) of sections (15-17) of sections ( 17-20) sections (>20) have standards@ have scheduled sections have have scheduled any scheduled any any benchmarking scheduled any benchmarking in benchmarking in inaccordance bench-marking in accordance with accordance with NOBP-with NOBP-LP- accor-dance with NOBP-LP-2002 or LP-2002 or NG-EN-2002 or NG-EN- NOBP -LP-2002 NG-EN-00386 for 1 00386 for 15' & 2"d 00386 for 1 & 2nd or NG-EN-00386 $ 2n quarter 2004. quarter 2004.
| |
| quarter 2004. for I t quarter 2004.
| |
| Management A management A management A management A management observations* observation observation observation program observation program program has been program has has been established. has been established.
| |
| established. Less been established. More than 80% of More than 90% of than 70% of More than 70% of management management management management observations are observations are observations are observations are performed as performed as performed as performed as scheduled and most scheduled and contain scheduled, and scheduled, and are considered quality information.
| |
| observations are observations are acceptable.
| |
| weak. weak.
| |
| Temporary There are more There are 11 or There are 8 or less There are 5 or less modifications+# than 11 temporary less temporary temporary temporary modifications. modifications. modifications. modifications.
| |
| Number of There are more There are 2 There is 1operator There are no operator Operator work- than 2 operator operator workarounds. workarounds.
| |
| arounds*# workarounds. workarounds.
| |
| Number of There are more There are 4 There are 1-3 Control There are no Control Control Room than 4 Control Control Room Room deficiencies. Room deficiencies.
| |
| deficiencies*# Room deficiencies.
| |
| deficiencies.
| |
| @ Site wide assessment only. Data provided by Quality Services
| |
| *This item assessed by Operations only
| |
| *Site wide assessment only. Data provided by Management Observation program 19
| |
| +Site wide assessment only. Data provided by Plant Engineering
| |
| #Significance evaluation will be discussed during the Restart Readiness Review Safety Culture Assessment and the outcome of this discussion may affect any or all of the attribute ratings. Explain why acceptable if less than green
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 40 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 20 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT (continued)
| |
| Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Training on Less than 80% of Between 80-89% Between 90-97% of More than 97% of SCWE* managers, of managers, managers, managers, supervisors supervisors and supervisors and supervisors and and operators have operators have operators have operators have received training on received training received training received training on SCWE.
| |
| on SCWE. on SCWE. SCWE.
| |
| Licensed Individuals in Individuals in Individuals in initial Individuals in initial operator initial license initial license license class are license class are pipeline** class are class are maintaining a class maintaining a class maintaining a maintaining a average of 88-94% average of more than class average of class average of 94%.
| |
| 82% or less 83-87%
| |
| *Site wide assessment only. Data provided by Nuclear Training
| |
| **This item assessed by Operations only.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 41 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 21 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT (continued)
| |
| Commitment to continuous improvement is evident SAFETY CONSCIOUS WORK ENVIRONMENT (SCWE)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Use of More than 4 CRs Between 4-2 CRs Less than 2 CRs No CRs issued within SCWERP issued within the issued within the issued within the past the past year related to past year related past year related year related to failure failure to properly to failure to to failure to to properly conduct conduct SCWERT properly conduct properly conduct SCWERT review of review of Davis-Besse SCWERT review SCWERT review Davis-Besse work work disciplinary of Davis-Besse of Davis-Besse disciplinary actions actions prior to the work disciplinary work disciplinary prior to the action. action.
| |
| actions prior to actions prior to the action. the action.
| |
| Effectiveness of There are more There are 5 NRC There are 4 NRC There are 2 or fewer SCWERTin than 5 NRC allegations or allegations or ECP NRC allegations or avoiding allegations or ECP concerns of concerns of ECP concerns of discrimination ECP concerns of discrimination discrimination discrimination claims* discrimination submitted within submitted within the submitted within the submitted within the past year past year past year the past year Effectiveness in There is more There is one There are no There are no avoiding NRC or than one substantiated substantiated NRC or substantiated NRC or ECP substantiated NRC or ECP ECP discrimination ECP discrimination substantiated NRC or ECP discrimination claims within the past claims within the past 2 discrimination discrimination claim within the year. years.
| |
| claims* claim within the past year past year
| |
| *Site wide assessment only. Data provided by Employee Concerns Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 42 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 22 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2f. CRITERIA RELATED TO COMMITMENT TO CROSS-FUNCTIONAL WORK MANAGEMENT AND COMMUNICATION Commitment to cross functional work management and communication is evident ATTRIBUTE RED YELLOW WHITE GREEN Cross-functional No cross-functional Some cross- Cross-functional Cross-functional teamwork* teamwork is evident functional teamwork frequently teams among sections among sections teamwork among occurs among are constantly sections exists but sections, enabling forming/reforming work is sub- efficient and effective around the best way to optimized. workflow. get work done.
| |
| Department Many process Some process Minimal process Department interfaces interfaces breakdowns occur breakdowns occur breakdowns and are seamless; work within the within the rework occur within the flows efficiently Department with Department with Department with between departments extensive amounts frequent amounts effective and efficient throughout the entire of rework needed. of rework needed. resolution of emergent organization.
| |
| issues.
| |
| Performance to Less than 70% of Between 70-80% Between 80 -90% of More than 90% of schedule* work is completed of work is work is completed on work is completed on on time, as completed on time, as scheduled, time, as scheduled, scheduled, causing time, as with minimal within current resource major scheduled, with adjustments to capacity.
| |
| consequences to major adjustments resource capacity overall site to resource required to improve performance. capacity required performance.
| |
| to improve performance.
| |
| Interdepartmental Information that Information that Information that Information that communication# impacts impacts impacts downstream impacts downstream downstream downstream implementation is implementation is implementation is implementation is frequently shared on a communicated as not shared, causing inconsistently timely basis, enabling soon as it's known, significant negative shared, which departments to enabling departments 9 consequences to keeps other proactively plan and to work proactively on other departments. departments in a respond. a consistent basis.
| |
| reactive mode.
| |
| * Site wide assessment only. Data provided from Edventures survey results.
| |
| **Site wide assessment only. Data provided by Outage Management and Work Control
| |
| #Site wide assessment only. Data provided by Edventures and 4Cs
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 43 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 23 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2f. CRITERIA RELATED TO COMMITMENT TO CROSS-FUNCTIONAL WORK MANAGEMENT AND COMMUNICATION (continued)
| |
| Commitment to cross functional work management and communication is evident Interdepartmental Problem solving Cross-functional Cross-functional Cross-functional problem solving and decision sections, sections, sections, and decision making occurs in Departments or Departments or Departments or making isolation; non- stakeholders are stakeholders are stakeholders are involvement of seldom involved frequently involved consistently involved other Departments when problems when problems are when problems are or stakeholders. are being solved being solved and being solved and and decisions are decisions are made. decisions are made.
| |
| made.
| |
| Systemic learning Things are broken Discrete problems Attention isfocused Streamlining and down, focus is on are fixed within the on learning and improving systems the pieces and section with discovering and process is discrete problems minimal fundamental constant to resolve are fixed within the understanding of solutions to resolving long-standing and/or section with no interdependencies long-standing and/or complex problems understanding of complex problems within the section interdependencies. within the section Incorporating Industry operating There is less than There isfull Operating Experience industry experience is not full utilization and utilization and is consistently and Operating consistently fully minimal compliance with the fully utilized in every Experience* utilized to enhance compliance to our Operating department and is site performance. Operating Experience Program well-integrated into Experience everyday activities to Program enhance plant performance.
| |
| *Site wide assessment only. Data provided by Operating Experience Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 44 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 24 of 39 2.MANAGERS' COMMITMENT AREA 2g. CRITERIA RELATED TO COMMITMENT TO CREATING AN ENVIRONMENT OF ENGAGEMENT AND COMMITMENT An environment of engagement and commitment is evident ATTRIBUTE RED YELLOW WHITE GREEN FENOC values, FENOC values, FENOC values, FENOC values, basic Most exempt basic principles basic principles and basic principles principles and personnel in the and leadership leadership and leadership leadership strategies section have strategies strategies are not strategies are are frequently internalized and are used by exempt inconsistently demonstrated by some living the FENOC personnel within the demonstrated by exempt personnel values, basic section some exempt within the section principles and personnel within leadership strategies the section as demonstrated in their day to day actions.
| |
| Quality of Employee Employee Employees Concems Employee Concerns management and Concerns Program, Concerns Program, Quality Program, Quality employee Quality Assessment Program, Quality Assessment and 4Cs Assessment and 4Cs relationships* and 4Cs survey Assessment and survey data indicates survey data indicate data indicates that 4Cs survey data that more than 80% of more than 90% of (Explain why employees openly indicates that employees will bring employees raise acceptable if not express fear of more than 70% concerns to issues directly with green) retaliation and will of employees management. management, work not raise safety will bring safety collaboratively to concerns with concerns to resolves issues and management. management. reflect favorable improvement.
| |
| Organizational Section Section Section management Section management commitment and management management frequently supports consistently supports shared success focuses on what is occasionally doing what is in the doing what is in the criteria in the best interest supports what is best interest of the best interest for the of their section at in the best whole organization whole organization the expense of interest of their rather than what is in rather than what is In what is in the best section without the best interest of the best interest for interest of the consideration to their section. their section.
| |
| whole organization. what is in the best interest of the whole organization.
| |
| *Sfte wide assessment only. Data provided by ECP, NQA and 4Cs
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 45 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 25 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2g. CRITERIA RELATED TO COMMITMENT TO CREATING AN ENVIRONMENT OF ENGAGEMENT AND COMMITMENT (continued)
| |
| An environment of engagement and commitment is evident Performance Less than 70% of Between 70-80% Between 80-90% of More than 90% of reviews in performance of performance performance reviews performance reviews accordance with reviews for the reviews for the for the section were for the section were FENOC section were section were completed for the completed for the Performance completed for the completed for the review period per. review period per the Management review period per review period per. the FENOC FENOC Performance process* the FENOC the FENOC Performance Management process Performance Performance Management Management Management process process process FENOC Less than 70% of Between 70-80% Between 80-90% of More than 90% of Performance managers and of managers and managers and managers and Management supervisors have supervisors have supervisors have supervisors have Process development plans development plans development plans development plans Development submitted to HR submitted to HR submitted to HR submitted to HR Plans*
| |
| *Site wide assessment only. Data provided by Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number-.
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 46 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 26 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3a. CRITERIA RELATED TO DRIVE FOR EXCELLENCE Nuclear assets of people and plant are continuously improved to enhance margins of safety ATTRIBUTE RED YELLOW WHITE GREEN Maintenance Rule There are more There are 2-3 There is one Red There are zero Red (a)(1) Systems* than 3 Red Red (a)(1) (a)(1) system. (a)(1) systems and all (a)(1) systems. systems. Maintenance Rule (a)(1) systems are in monitoring status Number of There are more There are 2 There is 1 operator There are no operator Operator than 2 operator operator workarounds. workarounds.
| |
| workarounds**# workarounds. workarounds.
| |
| Number of Control There are more There are 4 There are 1-3 There are no Control Room than 4 Control Control Room Control Room Room deficiencies.
| |
| deficiencies**# Room deficiencies. deficiencies.
| |
| deficiencies.
| |
| Number of There are more There are 11 or There are 8 or less There are 5 or less temporary than 11 less temporary temporary temporary modifications.
| |
| modifications+# temporary modifications. modifications.
| |
| modifications.
| |
| Individual Error The individual The individual The individual error The individual error rate Rate++ error rate is error rate is 0.31 rate is 0.29 <.35- is <0.26 individual errors
| |
| > 0.45 individual <.45->.36 >.26 individual errors per 10,000 hours errors per individual errors per 10.000 hours worked.
| |
| 10,000 hours per 10,000 hours worked.
| |
| worked. worked.
| |
| *Site wide assessment only. Data provided by Plant Engineering "This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Plant Engineering
| |
| ++Site wide assessment only. Data provided by Human Performance
| |
| #Significance evaluation will be discussed during the Restart Readiness Review Safety Culture Assessment and the outcome of this discussion may affect any or all of the attribute ratings. Explain why acceptable if less than green.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 47 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 27 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3a. CRITERIA RELATED TO DRIVE FOR EXCELLENCE (continued)
| |
| Nuclear assets of people and plant are continuously improved to enhance margins of safety Percent of Less than 80% of 80% or more of the 90% or more of the 95% or more of the CRs self-identified the CRs originated CRs originated are CRs originated are originated are self-Condition are self-identified. self-identified. self-identified. identified.
| |
| Reports (CRs)*
| |
| Number of Less than 80% of At least 80-90% of At least 90% of SCAQ All SCAQ evaluations open SCAQ evaluations SCAQ evaluations evaluations and 80- and 90% of CAQ Condition and less than 70% and 70-80% of 90% of CAQ evaluations were Report of CAQ evaluations CAQ evaluations evaluations were completed on schedule evaluations* were completed on were completed on completed on for the previous quarter.
| |
| schedule for the schedule for the schedule for the previous quarter. previous quarter. previous quarter.
| |
| Engineering The quality of The quality of The quality of The quality of Assessment engineering engineering engineering products engineering products as Board (EAB) products as products as as measured by the measured by the EAB is index** measured by the measured by the EAB is 2.0 or less. 1.0 or less.
| |
| EAB is greater than EAB is 3.0 or less.
| |
| 3.0.
| |
| Performance More than one One significant Major plant evolutions Major plant evolutions during major significant event has event has occurred have been performed have been performed plant occurred during a during a plant in the past month with successfully in the past evolutions+ plant evolution in the evolution in the past some less than month as planned past month month significant challenges without any challenges or transients.
| |
| Addressing Less than 70% of Between 70-80% of Between 80-90% of More than 90% of Operating operating operating operating experience operating experience Experience experience reports experience reports reports applicable to reports applicable to the applicable to the applicable to the the section are section are completed section are section are completed on time on time.
| |
| completed on time completed on time Operational transient isdefined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Significant isdefined by INPO as an event which caused or had the potential to cause an appreciable reduction in plant safety or reliability, excessive radiation exposure, the discharge of radioactivity offsite or serious harm to individuals. The significance of a particular event (including the discovery of a serious deficiency, lies in the actual or potential consequences of the event or in the likelihood that it is a precursor to a more serious event.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| **Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| +Site wide assessment only. Data provided by Operations
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 48 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 28 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3b. CRITERIA RELATED TO QUESTONING ATTITUDE Challenges are welcomed ATTRIBUTE RED YELLOW WHITE GREEN Quality of pre-job Management Management Management Management briefs* observations and QA observations and observations and QA observations and field observations QA field field observations QA field show that most pre-job observations show show that, with some observations show briefs are not that most pre-job exceptions, pre-job that pre-job briefs in acceptable. briefs are briefs are acceptable. general are acceptable. acceptable.
| |
| Percent of CRs Less than 13% of Between 13-15% Between 15-17% of More than 17% of per person per individuals wrote CRs of individuals individuals wrote CRs individuals wrote group during the past 30 wrote CRs during during the past 30 CRs during the past days. the past 30 days. days. month.
| |
| Number of The number of The number of The number of The number of programmatic programmatic CRs programmatic CRs programmatic CRs programmatic CRs CRs** indicates that indicates that most indicates that a large indicates that individuals in general individuals are majority of individuals individuals in are reluctant to write willing to write CRs are willing to write general are willing CRs on programmatic on programmatic CRs on to write CRs on and management and management programmatic and programmatic and issues. issues. management issues. management issues.
| |
| Program and >0.50 program and <0.50-.>.37 <0.37->.27 program <0.27 program process error process errors per program and and process errors and process errors rate+ 10,000 hours worked. process errors per per 10,000 hours per 10,000 hours 10,000 hours worked. worked.
| |
| worked.
| |
| Raising Management Management Management Management problems* observations, CAP and observations, CAP observations, CAP observations, CAP NQA field observations and NQA field and NQA field and NQA field show that most observations show observations show observations show individuals are not individuals that a large majority that most raising problems generally are of individuals are individuals are encountered in the raising problems raising problems raising problems field. encountered in the encountered inthe encountered in the field. field. field.
| |
| *Site wide assessment only. Data provided by Management Observation Program and NQA.
| |
| **Site wide assessment only. Data provided by Performance Improvement.
| |
| +Site wide assessment only. Data provided by Human Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 49 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 29 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Event Free Clock* The event free The event free The event free The event free clock is clock is less clock is between 20 clock is 30 to 39 greater than 40 days on than 20 days on and 30 days on days on average. average.
| |
| average. average.
| |
| industrial safety There are 11 or There are between There are 4 to 7 There are no more than pefformance** more OSHA 8 and 10 OSHA OSHA recordables 3 OSHA recordables per recordables per recordables per per year. year.
| |
| year. year.
| |
| Individual error The individual The individual error The individual The individual error rate rate* error rate is rate is <0.<.45->.36 error rate is is <0.26 individual errors
| |
| >0.45 individual individual errors per <0.<.36->.26 per 10,000 hours errors per 10,000 hours individual errors worked.
| |
| 10,000 hours worked. per 10,000 hours worked. worked.
| |
| Program and >0.50 program <0.50->.37 <..37->.27 <0.27 program and process error rate* and process program and program and process errors per errors per process errors per process errors per 10,000 hours worked.
| |
| 10,000 hours 10,000 hours 10,000 hours worked. worked. worked.
| |
| Significant human There are more There are fewer There are fewer There were no performance than 3 significant than 3 significant than 2 significant significant human errors resulting in human human human performance errors per plant transients performance performance errors performance year resulting in plant errors per year per year resulting in errors per year transients.
| |
| resulting in plant plant transients. resulting in plant transients. transients.
| |
| Backlog of Priority There are more There are less There are less There are less than100 procedure change than 200 open than 200 open than 150 open open Priority PCRs.
| |
| requests (PCRs)+ Priority PCRs. Priority PCRs. Priority PCRs.
| |
| Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| *Site wide assessment only. Data provided by Human Performance
| |
| **Site wide assessment only. Data provided by Industrial Safety
| |
| +Site wide assessment only. Data provided by Quality Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 50 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 30 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH (continued)
| |
| Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Deficiency rate for Deficiency rate The deficiency The deficiency rate The deficiency rate for QC holds* for QC hold rate for QC hold for QC holds point is QC hold points is less points is more points is less than less than 15 %. than 7 %.
| |
| than 25%. 25%.
| |
| Rework rate Rework rate is The rework rate The rework rate is The rework rate is more than 3%. is 2.5-3.0%. 2.1-2.5%. <2.0%.
| |
| Ratio of completed Less than 50% More than 50% of More than 75% of More than 90% of to scheduled of scheduled scheduled work scheduled work scheduled work orders works orders per work orders are orders are orders are are completed.
| |
| week+ completed. completed. completed.
| |
| Number of late Less than 50% More than 50% of More than 75% of More than 90% of preventive of scheduled scheduled PMs scheduled PM are scheduled PMs are maintenance (PM) PMs are are completed on completed on time. completed on time.
| |
| activities+ completed on time.
| |
| time Backlog of There are more There are There are between There are less than 134 corrective than 230 CM between 229 and 149 and 134 CM CM activities maintenance (CM) activities 150 CM activities activities outstanding.
| |
| activities+ outstanding. outstanding. outstanding.
| |
| Number of There are more There are 2-3 There isone Red There are zero Red Maintenance Rule than 3 Red Red (a)(1) (a)(1) systems. (a)(1) systems. All (a)(1) systems++ (a)(1) systems. systems. Maintenance Rule (a)(1) systems will be in monitoring
| |
| *This item assessed by QC only. The Deficiency Rate for QC relates to rejectable or unsatisfactory inspection attributes identified in the field by the QC Inspector during the Implementation of the Order (work order). The established QC hold points are embedded within the Order as either a specific Step in the work sequence or on a standalone document such as a Weld Traveler.
| |
| *This item assessed by Maintenance only
| |
| +Site wide assessment only. Data provided by Outage Management and Work Control
| |
| ++Site wide assessment only. Data provided by Plant Engineering. Explain why acceptable if not green.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 51 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 31 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH (continued)
| |
| Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Performance One significant Major plant Major plant Major plant evolutions during major plant event has evolutions have evolutions have have been performed evolutions @ occurred during a been performed been performed with successfully as plant evolution in with some some transients but planned. There are no the past month or transients or one no significant events transients or there are three or significant event during major plant significant events more transients during major plant evolutions prior to during major plant during major evolutions prior to restart. evolutions prior to plant evolutions restart. restart.
| |
| prior to restart.
| |
| Use of procedures Management Management Management Management and work orders* observations and observations and observations and observations and NQA NQA field NQA field NQA field field observations observations observations show observations show show that the vast show that most that individuals that many majority of individuals individuals are generally are using individuals are using are using procedures not using procedures or procedures or work or work orders.
| |
| procedures or work orders. orders.
| |
| work orders.
| |
| Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Significant is defined by INPO as an event that caused or had the potential to cause an appreciable reduction in plant safety or reliability, excessive radiation exposure, the discharge of radioactivity offsite or serious harm to individuals. The significance of a particular event (including the discovery of a serious deficiency, lies in the actual or potential consequences of the event or in the likelihood that it is a precursor to a more serious event.
| |
| @ Site wide assessment only. Data provided by Operations
| |
| *Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 52 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 32 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS Associates are comfortable in voicing opinions, issues and concerns ATTRIBUTE RED YELLOW WHITE GREEN Number of CRs per Less than 13% of Between 13-15% of . Between 15-17% of More than 17% of person per group* individuals wrote CRs individuals wrote CRs individuals wrote individuals wrote during the past 30 during the past 30 CRs during the past CRs during the past days. days. 30 days. 30 days.
| |
| Worker confidence in Surveys and/or Surveys and/or Surveys and/or Surveys and/or raising safety interviews indicate interviews indicate interviews indicate interviews indicate concems** that less than 80% of that between 80-90% that between 90- that more than 95%
| |
| workers believe they of workers believe 95% of workers of workers believe Explain why can raise nuclear they can raise nuclear believe they can they can raise acceptable ff not safety or quality safety or quality raise nuclear safety nuclear safety or green) concerns without fear concerns without fear or quality concerns quality concerns of retaliation. of retaliation. without fear of without fear of retaliation. retaliation.
| |
| Feedback from 4Cs Feedback from the Feedback from the Feedback from the Feedback from the meetings+ 4Cs meetings 4Cs meetings 4Cs meetings 4Cs meetings indicates that most indicates that more indicates that more indicates that more individuals are not than 70% of than 80% of than 90% of willing to raise individuals are willing individuals are individuals are concerns to to raise concerns to willing to raise willing to raise management. management. concerns to concerns to management. management.
| |
| Keep Improving Each month's total Each month's total Each month's total Each months total Performance (KIP) Safe behavior Is 59% Safe behavior is 60% Safe behavior is Safe behavior is program++ or less. to 69%. 70% to 79%. 80% or higher.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| +Site wide assessment only. Data provided by Chief Operating Officer
| |
| ++Site wide assessment only. Data provided by Industrial Safety
| |
| **Site wide assessment only. Data provided by Employee Concems Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ________________________________________ D BBP-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 53 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 33 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| Associates are comfortable in voicing opinions, issues and concerns ATTRIBUTE RED YELLOW WHITE GREEN Pre-job briefings@ Management Management Management Management observations observations and observations and QA observations and QA and QA field QA field field observations field observations show observations observations show that, with some that pre-job briefs in show that most show that most exceptions, pre-job general are acceptable.
| |
| pre-job briefs pre-job briefs are briefs are acceptable.
| |
| are not acceptable.
| |
| acceptable.
| |
| Intra-department No formal Infrequent Formal Formal communication information sharing communication information communication structures exist and are structures exist sharing exists structures exist and consistently used to for sharing among the are occasionally used share information information sections of the to share information among the sections of among the department. among the sections the department.
| |
| sections of the of the department.
| |
| department.
| |
| Quality of 4Cs surveys 4Cs surveys 4Cs surveys indicate 4Cs surveys indicate communication* indicate that indicate that more that more than 70% that more than 70% of more than 50% than 50% of of employees believe employees believe that of employees employees that communication communication from believe that the believe that from their Managers their Managers isgood.
| |
| communication communication isfair.
| |
| from their from their Managers is Managers is fair poor OSite wde assessment only. Data provided by Management Observation Program and NQA
| |
| *Site wide assessment only. Data provided by Chief Operating Officer
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ _________ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 54 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 34 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| SAFETY CONSCIOUS WORK ENVIRONMENT (SCWE)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Employee Surveys and/or Surveys and/or Surveys and/or Surveys and/or awareness of interviews indicate that interviews indicate that interviews indicate interviews indicate SCWE policy** less than 80% of 80-90% of employees that 90-95% of that more than 95%
| |
| employees in the in the section are aware employees in the of employees in the (Explain why section are aware of of policy and consider it section are aware of section are aware of acceptable if not policy. a FE value. policy and consider it policy and consider it green) an FE value. an FE value and the normal way to do business.
| |
| Training on Less than 80% of Between 80-89% of Between 90-97% of More than 97% of SCWE managers, supervisors, managers, supervisors, managers, managers, and operators have and operators have supervisors, and supervisors, and (Explain why received training on received training on operators have operators have acceptable if not SCWE. SCWE. received training on received training on green) SCWE. SCWE.
| |
| NQA interviews+ NQA interviews indicate NQA interviews indicate NQA interviews NQA interviews that less than 85% of that between 85-90% of indicate that between indicate that more (Explain why individuals are willing to individuals are willing to 90-95% of individuals than 95% of acceptable if not raise concerns to their raise concerns to their are willing to raise individuals are willing green) supervisors or ECP. supervisors or ECP. concerns to their to raise concerns to supervisors or ECP. their supervisors or ECP.
| |
| Worker Surveys and/or Surveys and/or Surveys and/or Surveys and/or confidence in interviews indicate that interviews indicate that interviews indicate interviews indicate raising safety less than 80% of between 80-90% of that between 90-95% that more than 95%
| |
| concerns** workers in the section workers in the section of workers in the of workers in the believe they can raise believe they can raise section believe they section believe they (Explain why nuclear safety or quality nuclear safety or quality can raise nuclear can raise nuclear acceptable if not concerns without fear of concerns without fear of safety or quality safety or quality green) retaliation. retaliation. concerns without fear concerns without fear of retaliation. of retaliation.
| |
| *Site wide assessment only. Data provided by Nuclear Training
| |
| **Site wide assessment only. Data provided by Employee Concerns Program
| |
| +Site wide assessment only. Data provided by NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 55 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 35 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| EMPLOYEE CONCERNS PROGRAM (ECP)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Ratio of concerns There are more There are more There are at least 4 There are at least 8 submitted to ECP NRC allegations ECP concerns times more ECP times more ECP vs. NRC than ECP than NRC concerns than NRC concerns than NRC allegations based concerns. allegations. allegations or there allegations or there are on three month are no NRC no NRC allegations or rolling average* allegations. ECP concerns.
| |
| Satisfaction of Less than 70% of Between 70-80 % Between 80-90% of More than 90% of employees using employees that of employees that employees that use employees that use the the ECP* use the ECP use the ECP the ECP report being ECP report being report being report being satisfied with the satisfied with the satisfied with the satisfied with the process. process.
| |
| process. process.
| |
| Complaints of There are more There are 2 There is 1 complaint There are zero breach of than 2 complaints complaints this this year. complaints this year.
| |
| confidentiality of this year. year.
| |
| ECP*
| |
| Management Employee Employee Employee surveys Employee surveys support for ECP* surveys indicate surveys indicate indicate between 80- indicate more than 90%
| |
| less than 70% of between 70-80% 90% of individuals of individuals believe (Explain why individuals of individuals believe management management supports acceptable if not believe believe supports ECP. ECP.
| |
| green) management management supports ECP. supports ECP.
| |
| Site wide assessment only. Data provided by Employee Concerns Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Me: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 56 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 36 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM Persistence and urgency in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Development Less than 70% of Between 70-80 % Between 80-90% of More than 90% of Plans per applicable of applicable applicable employees applicable employees in FENOC employees in the employees in the in the section have the section have Performance section have section have completed completed development Management completed completed development plans. plans.
| |
| process development development plans. plans.
| |
| Training Training Training Training attendance Training attendance Is attendance** attendance is less attendance is is between 91-98%. greater than 98%.
| |
| than 85%. between 85-90%.
| |
| Rework rate+ The rework rate is The rework rate The rework rate is The rework rate is more than 3%. is 2.5-3.0%. 2.1-2.5%. <2.0%.
| |
| Results of EAB The quality of The quality of The quality of The quality of assessments++ engineering engineering engineering products engineering products as products as products as as measure by the measured by the EAB measured by the measured by the EAB is 2.0 or less is 1.0 or less.
| |
| EAB is greater EAB is 3.0 or than 3.0. less.
| |
| Training Overall Training Overall Training Overall Training Overall Training performance performance score performance performance score performance score score per less than 60% score between between 80-90% greater than 90%
| |
| NOBP-TR- 60-80%.
| |
| 1501#
| |
| Radiation There are more There are 1-3 There is radiation There are no radiation Protection than 3 radiation radiation protection event in protection events in the events @ protection events protection events the last quarter. last quarter.
| |
| in the last quarter. in the last quarter.
| |
| **Site wide assessment only. Data provided by Nuclear Training
| |
| +This item assessed by Maintenance only
| |
| ++This item assessed by Engineering only. Data provided by Director-Nuclear Engineering
| |
| #This item assessed by Nuclear Training only.
| |
| @Site wide assessment only. Data provided by Radiation Protection. An RP event is defined as any radiological event that would be included in the NRC Performance Indicator for Radiation Safety Cornerstone.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 57 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 37 of 39 3.INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence and urgency in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Procedure Management Management Management Management compliance** observations and observations and observations and observations and NQA NQA field NQA field NQA field field observations show observations show observations observations show that the vast majority of that most show that that many individuals individuals are individuals are not individuals are complying with complying with complying with generally are procedures. procedures.
| |
| procedures. complying with procedures.
| |
| Personal Few employees in Employees in the Employees in the Employees at all levels initiative the section section work hard section do what it in the section take routinely express to do what's takes to get the job personal initiative to why work can't be expected. done. invent methods to done or improved. achieve higher quality and greater efficiency.
| |
| Ownership Employees in the Employees in the Employees in the Most employees in the section don't section are section follow through section regularly follow through on inconsistent in and do what is asked volunteer to own/lead assigned following through of them and do what project, develop plans, commitments and to meet quality is defined within their coordinate efforts and seldom volunteer and timing of job description. see work through to for ownership. assigned completion.
| |
| commitments.
| |
| **Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 58 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 38 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Implementation Implementation Implementation of Implementation of The CAP improvements of CAP of the CAP the CAP the CAP designated for restart improvements* improvements improvements improvements for are completed and designated for designated for restart is completed associated training is (Explain why restart has not restart is started but the associated completed.
| |
| acceptable if not started. but none are training is not green) completed. completed.
| |
| Root cause The root cause The root cause The root cause The root cause evaluation evaluation evaluation evaluation approval evaluation approval rate quality* approval rate as approval rate as rate as determined as determined by the determined by determined by the by the CARB is CARB is 90% or greater.
| |
| the CARB is less CARB is between between 75-90%.
| |
| than 50%. 50-74%.
| |
| CR category The CR category The CR category The CR category The CR category accuracy* accuracy rate is accuracy rate is accuracy rate is accuracy rate is 90% or less than 70% or between 70-80%. between 80-90%. greater.
| |
| (Explain why greater.
| |
| acceptable if not green)
| |
| CR self- Less than 80% of 80% or more of 90% or more of the 95% or more of the CRs identfication the CRs the CRs originated CRs originated are originated are self-rate* originated are are self-identified. self-identified. identified.
| |
| self-identified.
| |
| Employee Employee Employee surveys Employee surveys Employee surveys survey+ surveys indicate indicate that indicate that indicate that less than that more than between 10-5% of between 5-2% of 2% of individuals are not (Explain why 10 % of individuals are not individuals are not willing to use the CAP.
| |
| acceptable if not individuals are willing to use the willing to use the green) not willing to use CAP. CAP.
| |
| the CAP.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| +Site wide assessment only. Data provided by Employee Concems Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 59 of 89 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 39 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN NQA interviews* NQA interviews NQA interviews NQA interviews NQA interviews indicate that indicate that indicate that between - indicate that less than more than 10% between 10-5% of 5-2% of individuals are 2 % of individuals are of Individuals are individuals are not not willing to use the not willing to use the not willing to use willing to use the CAP. CAP.
| |
| the CAP. CAP.
| |
| Timeliness of Less than 50% of Between 50-74% Between 75-89%of More than 90% of corrective actions corrective actions of corrective corrective actions for corrective actions for for section CRs actions for section section CRs are section CRs are Does not include are completed on CRs are completed on completed on CRs or CAs linked schedule without completed on schedule without schedule without to P3 activities extensions. schedule without extensions. extensions.
| |
| extensions.
| |
| *Site wide assessment only. Data provided by NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 ile: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 60 of 89 ATTACHMENT 10: SAFETY CULTURE ASSESSMENT CRITERIA MATRIX 0~-- .0 ~0) 0 ~ .0 ~) ~ 0 co .0 u D0
| |
| - - j r r4 14 r1 rf r14 e' ci n Site wide Plant Operations RP Chemistry Outage MgmtlWork Control Maintenance = -__ _
| |
| Training Safety_ __._
| |
| Engineering Plant Enaineerina Design Engineering Project Management RRT Reactor Eng.
| |
| Support Services Regulatory Affairs Quality Services Security Other Sections QAIQC Supply Chain Client Services Business Services Human Resources __._
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 61 of 89 ATTACHMENT 11: SAFETY CULTURE ATTRIBUTE ASSESSMENT MATRIX
| |
| : 1. Policy Commitment Area:
| |
| la. Criteria Related to Statement of Safety Policy Item Color Policy statement on Safety Culture Policy statement on SCWE Making employees aware of policy statements Employee understanding of policies Worker understanding of responsibility to raise safety concerns Total for a-] Color:s lb. Criteria Related to Management Values Item Color Corporate values Statement of mission, vision and values FENOC Business Plan for Total 1b-Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 62 of 89 1c. Criteria Related to Resources Item Color Adequacy of management resources Adequacy of personnel resources Adequacy of funding Adequacy of tools, material and equipment to complete site tasks Adequacy of tools, material and equipment to complete Section tasks Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources lTotal for c lColor:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 63 of 89 1d. Criteria Related to Self-Assessment Item Color Use of NQA to supplement the self assessment process Self assessments in accordance with NOBP-LP-2004 Section Performance Indicators Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP I9 Supply Chain Client Services Business Services Human Resources Personnel Performance Appraisals ITotal for 1d IColor
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 64 of 89 le. Criteria Related to Independent Oversight Item Color Nuclear Committee of the Board of Directors Company Nuclear Review Board Nuclear Quality Assurance Learning from the experience of the industry Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain 19 Client Services Business Services Human Resources lTotal for e -T ~coIo r ITotal for 1 I Colors
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 65 of 89
| |
| : 2. Managers' Commitment Area 2a. CriteriaRelated to Commitment to Safety Item Color Management observations performed as scheduled with coaching Management observations are self critical Management emphasis on safety to employees Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP 9
| |
| Supply Chain Client Services Business Services Human Resources Leadership in Action
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 66 of 89 Item Color Problem Solving Decision making Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain 9
| |
| Client Services Business Services Human Resources Improvement in safety margin Plant activities receive proper management attention and safety focus Operations Radiation Protection Chemistry Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 67 of 89 Maintenance I
| |
| Training Safety Plant Engineering Design Engineering Project Management I
| |
| Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP 9 Supply Chain Client Services Business Services Human Resources Total for 2a lColor:
| |
| 2b. Criteria Related to Roles and Teamwork Item Color Understanding that safety is highest priority Program Ownership Ownership of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 68 of 89 Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP 19 Supply Chain Client Services Business Services Human Resources Item Color Ownership of Engineering products as measured by EAB Effectiveness of supervision of individuals Intra-department teamwork and alignment Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 69 of 89 Quality Assurance ECP I9 Supply Chain Client Services Business Services Human Resources Item Color Expectations Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Trust, openness and focused commitment Clear goals and priorities Operations
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberDBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 70 of 89 Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security 19 Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Item Color Input and involvement Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 71 of 89 Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Total for 2b IColors 2c. Criteria Related to Ownership and Accountability Item Color Performance Reviews in accordance with FENOC Performance Management Process Development plans Readiness Reviews Worker understanding of responsibility to raise safety concerns Willingness to raise safety concerns SRO reviews for Operability are performed in timely manner System assessments
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 1 09 Page 72 of 89 NQA field assessments Management observations leading to coaching Timeliness of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP 9 Supply Chain Client Services Business Services Human Resources Total for 2a Colors 2d. Criteria Related to Training and Qualification Item Color Restart training Initial Operator training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number.
| |
| ____ _________ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 73 of 89 Item Color Requalification training Operability determination training Operations Engineering Training on SCWE Training on decision making process Training on standards and expectations Operations Radiation Protection Chemistry __
| |
| Outage Management and Work Control Maintenance Training Safety _____
| |
| Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP19 Supply Chain Client Services Business Services Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 74 of 89 Continuing training identified by Curriculum Review Committee Total for 2d IColorl 2e. Criteria Related to Commitment to Continuous Improvement Item l Color Improvements in management staffing Corrective Action Review Board Engineering Assessment Board Benchmarking against Industry standards Management observations Temporary modifications Number of operator work arounds Number of Control Room deficiencies Training on SCWE Licensed operator pipeline Use of SCWERT
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 75 of 89 I Effectiveness of SCWERT in avoiding discrimination claims I l Effectiveness in avoiding NRC or ECP substantiated discrimination claims I[Total for 2e IColor: I 2f. Criteria Related to Commitment to Cross-Functional Work Management and Communication Item Color Cross functional teamwork Department interfaces Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 Tifle: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 76 of 89 Item Color Performance to schedule Interdepartmental communication Interdepartmental problem solving and decision making Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain 9 Client Services Business Services Human Resources Systemic learning Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 77 of 89 Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security D Quality Assurance ECP I
| |
| Supply Chain Client Services Business Services Human Resources Incorporating industry Operating Experience Total for 2f lColor\
| |
| 2g. Criteria Related to Commitment to Creating an Environment of Engagement and Commitment Item Color FENOC values, basic principles and leadership strategies Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Numberl DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 78 of 89 Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP 19 Supply Chain Client Services Business Services Human Resources Item Color Quality of management and employee relationships Organizational commitment and shared success criteria Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 o Page 79 of 89 Performance reviews in accordance with FENOC Performance Management Process FENOC Performance Management Process Development plans Total for 2 _ Color:
| |
| Total for 2 Color:
| |
| : 3. Individuals' Commitment Area 3a. Criteria Related to Drive for Excellence Item Color Maintenance Rule (a)(1) systems Number of Operator workarounds Number of Control Room deficiencies Number of temporary modifications Individual Error Rate Percent of self-identified Condition Reports Number of open Condition Report evaluations
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number-DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 80 of 89 Engineering Assessment Board index Performance during major plant evolutions Addressing Operating Experience Total fo7alcolor:]
| |
| 3b. Criteria Related to Questioning Attitude Item Color Quality of pre-job briefs Percent of CRs per person per group Number of programmatic CRs Program and process error rate Raising problems ITotal r 3b IColor:
| |
| 3c. Criteria Related to Rigorous work Control and Prudent Approach Item Color I Event Free Clock I I
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 81 of 89 Industrial Safety Performance Individual Error Rate Program and process error rate Significant human performance errors result in plant transients Backlog of Priority Procedure Change Requests Deficiency rate for QC holds (QC only)
| |
| Rework Rate (Maintenance)
| |
| Ratio of completed to scheduled work orders per week Number of late preventive maintenance activities l Backlog of corrective maintenance activities Number of Maintenance Rule (a)(1) systems Performance during major plant evolutions Use of procedures and work orders Total for 3c Colors
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number0
| |
| ____________________________________DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 82 of 89 3d. Criteria Related to Open Communications Item Color Number of CRs per person per group Worker confidence in raising safety concerns Feedback from 4Cs meetings Keep Improving Performance program Pre-job briefings Intra-department information sharing Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 83 of 89 Item Color Quality of Communication Employee awareness of SCWE policy Training on SCWE NQA interviews Worker confidence In raising safety concerns Ratio of concerns submitted to ECP vs. NRC allegations Satisfaction of employees using ECP Complaints of breach of confidentiality in ECP Management support for ECP
| |
| {Total for 3d - Color[
| |
| 3e. Criteria Related to Nuclear Professionalism Item I Color FENOC Performance Management Process development plans Training attendance l Item Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ _________ _____ ____ ____D BB P-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 84 of 89 Rework Rate (Maintenance)
| |
| Results of EAB assessments Training performance score per NOBP-TR-1501 Radiation Protection Events Procedure Compliance Personal initiative Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP 9
| |
| Supply Chain Client Services Business Services Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 85 of 89 Item Color Ownership Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security l Quality Assurance ECP l 9 Supply Chain Client Services Business Services Human Resources Implementation of CAP Improvements Root cause evaluation quality CR category accuracy CR self identification rate Employee Survey NQA interviews
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page I RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 86 of 89 Item Color Timeliness of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP 19 Supply Chain Client Services Business Services Human Resources lTotal for 3e lColor ItTotal for 3 lColors
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Numbers DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Reision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 87 of 89 ATTACHMENT 11: PROGRAM OWNERSHIP LIST Page 1 of 3 Phase I Programs (Taken from NG-EN-00386, Rev. 0. Attachment 1) 65 total 10CFR50.59 Program Air Operated Valve (AOV) Reliability Program 9
| |
| Appendix R and Safe Shutdown Program ASME Section Xl Repair, Replacement, and Modification Program Auxiliary Chemistry Control Program Breaker Reliability Program Calculation Control Program Check Valve Reliability Program Chemistry Measuring & Test Equipment Program Commercial Grade Dedication Program Commitment Management Program (TERMS)
| |
| Configuration Management Program Containment Leakage Rate Test Program (Appendix J)
| |
| Control of Work Controlled Materials Program Core Design & Reload Analysis Program Corrosion-Erosion Monitoring and Analysis Program (CEMAP)
| |
| Engineered Spare Parts List Program Environmental Qualification (EQ) Program Equipment Modemization Program Fire Protection Program Foreign Material Exclusion Program Fuel Reliability Program Heat Exchanger Monitoring Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number: -0
| |
| ____ ____ ____ ____ ____D BBP-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 88 of 89 ATTACHMENT 11: PROGRAM OWNERSHIP LIST Page 2 of 3 Hydraulic Snubber Program 9 Infrared Thermography Program Inservice Test Program Leak Reduction Program Locked Valve Program Lubrication Monitoring and Analysis Program Maintenance Rule Program Material Receipt Inspection Program Measuring & Test Equipment Program Meteorological Monitoring Program Motor Operated Valve (MOV) Reliability Program Motor Reliability Program On-line Risk Management Program Operability Determination Program Post Accident Sampling Program Predictive Maintenance Program Preventive Maintenance Program Primary Water Chemistry Monitoring & Control Program Procurement Program Quality Classification Control Program Radioactive Effluent Controls Program Radioactive Materials Program Reactivity Management Program Safety Tagging Program Secondary Water Chemistry Monitoring & Control Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| ____ _________ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 09 Page 89 of 89 ATTACHMENT 11: PROGRAM OWNERSHIP LIST Page 3 of 3 Service Water System Reliability Program 9 Severe Accident Management Program Shelf Life Evaluation Program Shutdown Risk Management Program Software Control Program Steam Generator Program Management Temporary Leak Sealing Temporary Modification Process Test Control Program Thermal Performance Monitoring Program Transient Counting Valve Packing Program Vendor Manual Control Program Ventilation Filter Testing Program Vibration Analysis Program Welding Implementation & Qualification Program Phase 2 Programs (taken from the Davis-Besse IMC 0350 Restart List)
| |
| Corrective Action Program Operating Experience Program Boric Acid Corrosion Control Program Reactor Coolant System Unidentified Leakage Monitoring Program In-Service Inspection Program Modification Control Program
| |
| | |
| Docket Number 50-346 License Number NPF-3 Serial Number 1-1335 Revision 10 of the Nuclear Operating Business Practice Restart Readiness Review Extended Plant Outage (DBBP-VP-0002)
| |
| (94 pages to follow)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE D VNumber:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 1 of94 RESTART READINESS REVIEW EXTENDED PLANT OUTAGE Approved:
| |
| Vice President Approved: C itO Offic )
| |
| Chief Operating Officer Effective Date DEC 2003
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 TiUe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 2 of 94 TABLE OF CONTENTS Page 1.0 PURPOSE....................................................................................................................3 2.0 APPLICABILITY ........................................................................................................ 3 3.0 RESPONSIBILITY......................................................................................................3 4.0 DETAILS.....................................................................................................................4 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS ............ ............... 7 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX..............................................................................................9 ATTACHMENT 3: RESTART READINESS REVIEW FOR PLANT STARTUP ........... 12 ATTACHMENT 3A: RESTART READINESS RECOMMENDATION, SRB .................... 13 10 ATTACHMENT 3B: RESTART READINESS RECOMMENDATION, CNRB ... 14 ATTACHMENT 3C: RESTART READINESS RECOMMENDATION, ROP .. 15 ATTACHMENT 4: PLANT INSPECTION DOCUMENTATION SHEET ....................... 16 ATTACHMENT 5: OPERATIONAL READINESS AFFIRMATION FORM .................... 17 ATTACHMENT 5A OPERATIONAL READINESS AFFIRMATION FORM (PART 2).. 18 ATTACHMENT 5B OPERATIONAL OVERSIGHT MGR. AFFIRMATION FORM ........ 19 ATTACHMENT 6: CORE CONFIGURATION AFFIRMATION FORM .......................... 20 ATTACHMENT 7: REACTOR STARTUP AFFIRMATION FORM ................................. 21 ATTACHMENT 8 SYSTEM ENGINEER/PROGRAM OWNER READINESS AFFIRM ATION FORM ................................................................. 22 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE ............................................ 23 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA ......................... 26 ATTACHMENT 10: SAFETY CULTURE ASSESSMENT CRITERIA MATRIX .............. 65 ATTACHMENT 1: SAFETY CULTURE ATTRIBUTE ASSESSMENT MATRIX ........ 66 ATTACHMENT 12: PROGRAM OWNERSHIP LIST ....................................................... 92
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| ____ ___ ____ ____ ____ ____ ___ ____ ____ ___D B B P-V P-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 3 of 94 1.0 PURPOSE The purpose of this Business Practice is to provide assurance that the Davis-Besse Nuclear Power Station is ready to restart following the extended plant outage. The framework detailed here establishes a review process for areas not addressed by the Restart Test Plan and DB startup procedures to ensure that Davis-Besse's materiel condition, programs and processes, and organization, including the organization's safety culture are ready for plant restart and safe, reliable operation.
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| 2.0 APPLICABILITY This Business Practice applies to the first plant startup following the extended plant outage which began on February 16, 2002. It also applies to subsequent startups from this same outage and therefore shall be re-performed if the startup is halted resulting in an entry into a lower mode.
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| Adherence to this Business Practice is mandatory.
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| 3.0 RESPONSIBILITY The Vice President-Nuclear is responsible for initiating the Restart Readiness Review Process.
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| Each Section Manager and 0350 Restart List Responsible Individual is responsible for the accuracy and adequacy of the reviews performed, actions taken and action plans developed during the review process.
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| The Section Managers of Plant Engineering and Operations and the Director-Work Management (Maintenance) are responsible for ensuring plant walk-down inspections are conducted prior to power ascension.
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| The Manager-Operations is responsible for affirming: 1) the Operations Section has completed a review of operational readiness and is ready to support the safe and reliable startup and operation of the plant through the next operating cycle; 2) that the plant is in a condition of materiel readiness to support safe and reliable startup and operation and the operating crews are prepared and ready to startup and operate the plant in a safe and reliable manner through the next operating cycle.
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| The Supervisor-DB Reactor Engineering is responsible for: 1) following movement of fuel in the reactor core, changes to reactivity control components in the reactor core and/or changes to nuclear instrumentation in the reactor core, verifying that the reactor core is configured to support safe and reliable operation through the cycle. This affirmation is required prior to installation of the reactor head; 2) prior to reactor startup, verifying that the required conditions exist to support a safe startup and power ascension.
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002 rite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 4 of 94 Each Director is responsible for the final review of the assessment and action plans developed during the review process by the sections in his department.
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| The Chief Operating Officer is responsible for final approval prior to plant restart.
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| 4.0 DETAILS
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| : 1. The review process shall be initiated early enough to ensure it is completed prior to entry into Modes 6, 4 and 2. The review shall be completed by the milestone date as determined by the responsible Shift Outage Director. All Sections and 0350 Checklist Responsible Individuals, shall submit restart readiness reviews by the milestone dates; not all items have to be complete, provided bullet (4) in Step 3 is appropriately addressed.
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| : 2. The process consists of the review and assessment of the specified Restart Readiness Review Indicators. The matrix on Attachment 2 designates the minimum indicators from Attachment I that are applicable to each Section and/or 0350 Checklist Item. Each Section and 0350 Checklist Responsible Individual, shall address applicable indicators and should participate in the review and assessment of any indicator for which meaningful input can be provided.
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| : 3. The methodology for the review process consists of the following steps:
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| * Monitor plant system/component work activity progress during the outage
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| * Monitor emergent work/issues during the outage for shutdown concerns
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| * Monitor personnel and administrative issues during the outage for restart concerns
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| * Assess Restart Readiness Review Indicators as identified on Attachment , as applicable per Attachment 2.
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| * Assess Safety Culture as identified on Attachment 9 10
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| * Identify items to be complete prior to the designated Mode (6, 4 or 2) that have not been completed as of the Shift Outage Director milestone date. Ensure a reference is associated with each incomplete item that addresses completion of that item before needed in that mode.
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| : 4. Results of the individual indicator assessments, including the status of action plans to support plant restart, will be indicated on Attachment 1, and acknowledged by the signature of the Section Manager or 0350 Checklist Responsible Individual. Indicator assessments should be marked as Final (all conditions are acceptable to support plant restart) or Preliminary (one or more indicators are not currently complete or acceptable and action plans will support plant restart when complete). Details on incomplete items and the status of action plans to eliminate them shall be attached.
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 5 of 94
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| : 5. The signed original Restart Readiness Review Indicators (Attachment 1) should be provided to the Restart Action Process Administrator at the end of the Readiness meetings for inclusion in the Mode Readiness notebook
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| : 6. Restart Readiness Review Indicators shall be reviewed by the Senior Leadership Team and approved by the Vice President-Nuclear or Chief Operating Officer, as provided on Attachment 3.
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| : 7. Completed Attachments I and 3 shall be included with the documentation package assembled in accordance with this Business Practice.
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| : 8. Walk down inspections shall be completed prior to power ascension as described in this document and in accordance with EN-DP-01503, System Walkdowns or Plant Engineering Policy PE-02, System Walkdown Checklist. Results of walkdown inspections shall be documented in Attachment 4 and submitted to the on-shift Engineering Manager.
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| : 9. The Shift Manager of each crew shall:
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| 10
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| : a. Conduct reasonable and appropriate activities to accomplish the objective of attaining, demonstrating and affirming operational readiness. The Shift Manager should consider the following to support the affirmation of operating crew readiness:
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| -adequacy of staffing levels, personnel experience and qualification levels.
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| -assure Operations personnel believe the Station can be operated safely by eliciting any outstanding safety concerns from shift personnel and ensuring that the concerns are resolved.
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| -completion of appropriate personnel refresher training of shift personnel, including training on plant, procedures and process changes.
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| -completion of training of shift personnel on the startup and power ascension plan. This training shall include discussion on the expected behavior and characteristics of the core for this startup.
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| : b. Affirm to the best of their knowledge and judgment that the plant is in a condition of materiel readiness to support safe and reliable startup and operation. The Shift Manager should consider the following:
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| -adequacy of the materiel condition of the plant, including the current status of operator work-arounds, to support safe and reliable restart and operation during the next operating cycle.
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| -all outage-related temporary fire suppression systems removed and fire protection requirements or commitments ready to support startup.
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 6 of 94
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| -temporary modifications, temporary power feeds, removed/MCCs restored, installed temporary power feeds, if applicable, reviewed to ensure they will not affect safety or operations.
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| : c. Complete Attachment 5.
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| : 10. The Supervisor-DB Reactor Engineering shall, following movement of fuel, changes to reactivity control components and/or changes to nuclear instrumentation in the reactor core, verify that the reactor core is configured to support safe and reliable operation through the cycle. This affirmation is required prior to installation of the reactor head.
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| Attachment 6, Core Configuration Affirmation Form, details the required review areas and documents the affirmation.
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| : 11. The Supervisor-DB Reactor Engineering, shall, prior to a reactor startup, verify that the required conditions exist to support a safe startup and power ascension. Attachment 7, Reactor Startup Affirmation Form, details the required review areas and documents that affirmation.
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| : 12. Each System Engineer and 0350 Program Owner shall complete Attachment 8, System Engineer/Program Owner Readiness Affirmation Form. The System Engineer forms shall be part of the Plant Engineering Manager's presentation for restart readiness. The 0350 Program Owner's form will be used as part of their readiness discussion. Selected systems (System Engineers) will be identified by the Manager-Operations, Manager-Plant Engineering and Plant Manager to be discussed during the Restart Readiness Review Meetings.
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| : 13. The Manager-Operations, shall complete Attachment 5A, Operational Readiness Affirmation Form, Part 2. This affirmation, by the Manager-Operations, affirms that the Operations Improvement Action Plan restart required actions are complete; the Integrated 10 Restart Test Plan is ready to support heatup and startup; and the Work Management Philosophy for the first and second quarters of 2004 is issued and disseminated to the DB management team.
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| : 14. The Operations Oversight Manager shall complete Attachment SB, Operations Oversight Managers Affirnation. This affirmation, by the Operations Oversight Manager, affirms that the Operational Oversight Managers have assessed operational effectiveness prior to startup and that procedure quality is acceptable, Operations adherence to procedures is acceptable and operational activities are conducted in an industry accepted manner.
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| i NUCLEAR OPERATING BUSINESS PRACTICE Number: BP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 7 of 94 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS Page I of 2 Plant Section or 0350 Checklist Item Acceptable to Mode Support Restart?
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| Yes/No/NA I All assigned outage work activities are complete to support plant restart and operations.
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| This includes a reconfirmation that previous dispositions of nonconforming conditions or Preventive Maintenance deferrals continue to provide a justification for continued operation.
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| (Attachment 2. Column a) 2 Outstanding Operability Evaluations, CR corrective actions and new CRs generated during the shutdown have been evaluated for operability concerns are either closed or determined to have no impact on operability. (Attachment 2, Column b) 3 Regulatory and internal commitments have been evaluated for operability concerns or restart restraints and are either closed or determined to have no impact on operability. (Attachment 2, Column c) 4 Housekeeping walkdowns utilizing the guidelines of NG-DB-00215, Material Readiness and Housekeeping Inspection Program are complete. Managers must attach detailed written 10 documentation from their walkdown area (Attachment 2, Column d) 5 The Power Ascension Schedule has been reviewed for accuracy and adequacy ensuring:
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| (Attachment 2. Column e)
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| * Post maintenance retest and special testing are identified and scheduled correctly with instructions in place.
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| * Planned walkdowns are scheduled appropriately 6 Personnel, materials and special test equipment necessary to support power ascension retest and walkdown activities have been identified and availability is ensured during power ascension. (Attachment 2, Column f) 7 Contingency plans are established for immediate response to plan and repair steam leaks or high-risk test failures. (Attachment 2, Column g) 8 Standing orders have been reviewed for continued applicability and system status sheets completed as required by DB-OP-0691 1, Pre-Startup Checklist. (Attachment 2, Column h) 9 System walkdowns have been performed by Plant Engineering and Maintenance, as directed by Operations, to ensure system readiness for restart.
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| 10 Operating Experience reports have been reviewed to ensure no potential operability concerns.
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| 11 Procedure alterations/PCRs arc ready for mode change or restart.
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| 12 Work around and burdens identified prior to or during shutdown and not corrected have been confirmed acceptable. (Attachment 2, Column i)
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 8 of 94 ATTACHMENT 1: RESTART READINESS REVIEW INDICATORS (Continued)
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| Page 2 of 2 Plant Section or 0350 Checklist Item_ Acceptable to Support Mode Restart?
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| Yes/No/NA 13 All Management and Human Performance Improvement Plan items required for restart are complete. (Attachment 2, Column j) 14 All 0350 Discovery Action Plan milestones identified as required for restart are complete.
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| (Attachment 2, Column k) 15 All 0350 Implementation Action Plan milestones identified as required for restart are complete. (Attachment 2, Column 1) 16 All Section Corrective Action Program Improvement Plan activities required for restart have been validated as ready to support restart. (Attachment 2, Column ii) 17 All Condition Reports and corrective actions, work orders, modifications (including EWRs and ECRs) categorized as 0350 are completed. (Attachment 2, Columns m, n, o) 18 All Condition Reports and corrective actions, work orders, and modifications (including EWRs and ECRs) designated as required for restart by the Restart Station Review Board are complete. (Attachment 2, Columns q, r, s) 19 Any required for restart Condition Report or corrective action, work order or modification (including EWRs and ECRs), which cannot be completed prior to restart, has a written exemption from the RSRB. (Attachment 2, Column u) 20 All pending allegations have been reviewed and determined not to affect the restart of the plant. (Attachment 2, Column v) 21 Integrated Restart Report per NG-VP-00100 signed by the SLT. (Attachment 2, Column w)
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| Check one Preliminary: I have reviewed the assessment of the Restart Readiness Review Indicators as indicated above and confirm that the attached plans will support plant restart when complete, Final: I have reviewed the assessment of the Restart Readiness Review Indicators as indicated above and concur that the current conditions support plant restart.
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| Section Manager or 0350 Checklist Individual (Please Print Your Name)
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| Signature: Date_
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| Section Manager or 0350 Checklist Individual
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| _.D_ _ _ __ __ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ B B P-V P-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 9 of 94 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 1 of 3 u~~ 0 .2 r. -
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| U^ ..
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| o W
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| ~~~~
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| .~~~ U; I-0j U l
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| W A ~ W0V L j o; U O
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| - U F z o U z *2 , O4i Plant _ _
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| Operations X X X X X X X X X X X RP X X X X X X X X X Chemistry X X X X X X X X Outage Management and X X X X X X X X Work Control _ _
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| FIN X X X X X X Mechanical X X X X X X X E&C X X X X X X X 10 Maint. Serv. X X X X X X Training X X X X X Safety = X X X = x Engineering ___
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| Plant Engineering X X X X X X X X X Design Engineering X X X X X X X Project Management X X X X X X x RRT X X X X - X Reactor Engineering X X X X X X X X Support Services Regulatory Affairs X X X X X X X X (includes Emer. Prep.)
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| Quality Services X X X x Security X _ X X Other Sections ___
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| QA/QC X X X X - x Supply Chain X X X X Client Services X x Business Services X _ X Human Resources X ___ X X
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002 Tifie: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 10 of 94 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 2 of 3 0350 CHECKLIST ITEM RESTART READINESS REVIEW INDICATOR MATRIX 0~~~~~
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| U~~~~~~~~~U 0
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| 0 -~~~
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| Xe °i g: E vi t E .V 0350 Checklist Item I __
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| : 1. Adequacy of Root Cause Determinations- X X X x S. Loehlein, M. Roder, D. Gudger, J. Powers, D.
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| Eshelman, F. von Ahn, L. Myers*
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| : 2. Adequacy of Safety Significant Structures, X X X X X Systems and Components--D. Baker, A. Stallard, T. Chambers, R. Hovland, J. O'Neill*
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| : 3. Adequacy of Safety Significant Programs--A. X X X McAllister, L. Dohrmann, S. Loehlein, C. Daft,
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| : 1. Grabnar, R.Farrcll, D. Schreiner, R. Perry, K.
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| Ostrowski*
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| : 4. Adequacy of Organizational Effectiveness and X X X X x Human Performance- M. Bezilla, J. Powers*
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| : 5. Readiness for Restart-C. Price, F. VonAhn, R. X X Hovland, R. Schrauder, A. Stallard, J. Hirsch*
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| : 6. Licensing Issue Resolution--J. Powers, K. X X Ostrowski* _
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| : 7. Confirmatory Action Letter Resolution--L.
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| Myers, C. Price K. Ostrowski* T X
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| * Or an approved designated alternate
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| NUCLEAR OPERATING BUSINESS PRACTICE Number DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 11 of 94 ATTACHMENT 2: PLANT RESTART READINESS REVIEW INDICATOR MATRIX Page 3 of 3 REQUIRED FOR RESTART READINESS REVIEW INDICATOR MATRIX
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| . I..
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| t~~~~~~~~~
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| U I- 0 J3 U~~~~~~~~~~~~~~~~~~~~~~~~~~~~~(
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| CA Cj~~~~~~~~~~~~~~~~~~~C 0 MI') e-t e as Restart Station Review Board X X X X Quality Services X Employee Concerns Program _ _ X Station Review Board (Plant X Operating Review Committee)
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| Company Nuclear Review X Board Restart Overview Panel X
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 12 of 94 ATTACHMENT 3: RESTART READINESS REVIEW FOR PLANT STARTUP Restart/Mode Change Recommended By:
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| Mode_
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| Plant Manager-Davis-Besse Nuclear Power Station Date Director-Davis-Besse Nuclear Engineering Date Director-Davis-Besse Work Management Date Director-Davis-Besse Support Services Date Director-Davis-Besse Restart Date RESTART /MODE CHANGE APPROVAL:
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| c Vice President-Nuclear Date Date Chief Operating Officer Date
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 13 of 94 ATTACHMENT 3A: RESTART READINESS RECOMMENDATION.
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| STATION REVIEW BOARD 10 The Station Review Board has performed its functions during 13RFO as prescribed in DB-DP-00022, Station Review Board. The SRB is responsible to perform in-depth reviews to identify nuclcar safety concerns and to carry out the duties defined in the aforementioned procedure. Reviews include, but are not limited to, plant administrative procedures and changes; proposed procedures and changes to procedures and equipment or proposed tests or experiments determined to involved a OCFR50.59 evaluation; proposed changes to Technical Specifications or the Operating License; all written IOCFR50.59 evaluations, and changes to plans related to the Davis-Besse Operating License.
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| Based upon the results of its meetings, reviews and assessments, the SRB believes that Davis-Besse has taken proper actions to ensure that the plant, is ready for safe and reliable operation, and that the plant can be operated in conformance with applicable requirements.
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| SRB Chairman Date
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| I NUCLEAR OPERATING BUSINESS PRACTICE Number:DBBP-VP0002 Tile: Reiin Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 14 of 94 ATTACHMENT 3B: RESTART READINESS RECOMMENDATION COMPANY NUCLEAR REVIEW BOARD CNRB has assessed plant activities throughout RFO 13. The scope of the assessments included the planning, discovery, and implementation of the Return to Service Building Blocks. These assessments 10 have included documentation reviews, meetings with plant management, and assessment of NQA activities.
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| Based upon the results of its assessments, the CNRB concludes that FENOC has taken sufficient actions to ensure that the plant, programs, and organization are ready to support safe and reliable operation of Davis-Besse, and that there is reasonable assurance that the plant can be operated in conformance with applicable requirements and without endangering the public health and safety.
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| CNRB Chairman Date
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| NUCLEAR OPERATING BUSINESS PRACTICE Number. DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 15 of 94 ATTACHMENT 3C: RESTART READINESS RECOMMENDATION, RESTART OVERVIEW PANEL The Charter for the Davis-Besse Restart Overview Panel requires the ROP to make a recommendation 10 for the return to service of Davis-Besse.
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| The ROP has overviewed plant activities since it was created in mid-2002. The ROP has primarily focussed on assessing the planning, discovery, and implementation of the Return to Service Building Blocks. These assessments have included documentation reviews, interviews of plant personnel, observations of plant activities, and monthly meetings with plant management.
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| Based upon the results of its assessments, the ROP concludes that FENOC has taken sufficient actions to ensure that the plant, programs, and organization are ready to support safe and reliable operation of Davis-Besse, and that there is reasonable assurance that the plant can be operated in conformance with applicable requirements and without endangering the public health and safety.
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| ROP Chairman Date
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 16 of 94 ATTACHMENT 4: PLANT INSPECTION/WALKDOWN DOCUMENTATION SHEET Page I of I Mode_
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| ASSET LABEL:
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| Or AREA INSPECTED:
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| NOUN NAME:
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| LOCATION:
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| DESCRIPTION:
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| MAINTENANCE TAG/WORK ORDER #:
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| CONDITION REPORT INITIATED (#)_
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| MODE RESTRAINT: Yes No SUBMITTED BY: DATEDTIME I (please print your name)
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| SIGNATURE:
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 17 of 94 ATTACHMENT 5: OPERATIONAL READINESS AFFIRMATION FORM Shift Designator:
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| Shift Manager:
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| (Please Print)
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| Mode_
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| Review Summary:
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| Thie Shift Managershould initial each item below to affirm that he/she and the operatingcrew have completed the required actions:
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| Shift staffing levels, including personnel experience and qualification levels, are adequate.
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| Operations personnel believe the station can be operated safely. All safety concerns have been identified and addressed.
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| Appropriate refresher training of shift personnel, including training on plant, procedure and process changes, has been completed.
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| Appropriate training of shift personnel on the startup and power ascension plan, have been completed, including discussions on core behavior and characteristics for this startup.
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| The materiel condition of the plant, including the current status of operator work-arounds, is adequate to support safe and reliable restart and operation.
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| Affirmation:
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| Based upon an evaluation of the considerationssetforth in Details, 4.0, and to the best of my knowledge and judgment, the plant is in a condition of materiel readiness to support the safe and reliable startup and power operation through the next operatingcycle and the operating crew is ready to startupand operate the plant in a safe and reliable manner.
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| Shift Manager:
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| Print/Signature/Date Reviews and Approvals:
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| Manager-Operations:
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| Print/Signature/Date Of -* l Remarks: (Attach a continuation sheet if applicable)
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision; Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 18 of 94 ATTACHMENT 5A: OPERATIONAL READINESS AFFIRMATION FORM (Part 2)
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| Review Summary: 10 The Manager-Operationsshould initial each item below to affirm that the requiredactions have been completed The Operations Improvement Action Plan restart required actions are complete.
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| The Integrated Restart Test Plan has been reviewed, approved and is ready to support plant heatup and restart.
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| The Work Management Philosophy for first quarter of 2004 is issued and has been disseminated to the DB Management Team Affirmation:
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| Based on ny knowledge andjudgment. the above actions are complete and the Operatorsare ready to Jheatup, startup and operate the plant in a safe and reliable manner.
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| Manager-Operations:
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| Print/Signature/Date Remarks: (Attach a continuation sheet if applicable)
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| DBBP-VP-0002
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| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 19 of 94 ATTACHMENT SB: OPERATIONS OVERSIGHT MANAGER AFFIRMATION FORM Review Summary:
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| The Operations Oversight Manager should initialeach item below to affirn that the requiredactions have been completed 10 The Operational Oversight Managers have observed Operations crews at the simulator, in pre-job briefs, shift turnover, plant evolutions, non-licensed operator rounds, plant tours and post job briefs.
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| The Operational Oversight Managers have monitored Operations ownership and monitored shift turnover meetings to ensure safety related activities receive the attention warranted by their significance.
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| The Operational Oversight Managers have observed Operations crews relative to procedure use and adherence and it is in accordance with management expectations.
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| The Operational Oversight Managers have assessed Operations personnel Leadership in Action characteristics of Nuclear Professionalism and Nuclear Safety .
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| Affirmation:
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| In mv opinion, and based on ny observations of training,integratedprocedure enhancements and on shift behaviors. as well as reportsfron the OperationalOversight Managers,I believe the DB Operatorsare readv to restart the unit and return the plant to safe and reliableoperation.
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| Operational Oversight Manager:
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| Print/Signature/Date Remarks: (Attach a continuation sheet if applicable)
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| NUCLEAR OPERATING BUSINESS PRACTICE Number:
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| __ __ DBBP-VP-0002
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| | |
| ==Title:==
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| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 20 of 94 ATTACHMENT 6: CORE CONFIGURATION AFFIRMATION FORM Mode_
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| Review Summary:
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| The Supervisor-DB Reactor Engineering, should initial each item below to affirm that the required conditions exist following movement offuel in te reactor core, changes to reactivity control components and/or changes to nuclear instrumentation in the reactor core. This affirmation is requiredpriorto installationof the reactorhead.
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| All new fuel assemblies loaded into the reactor core were inspected, as required, to ensure that the manufacturing and design specifications were met.
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| All irradiated fuel assemblies present in the reactor core were inspected, as required, and dispositioned as acceptable for operation through the cycle.
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| No fuel assemblies in the reactor core are known leaking assemblies.
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| A I0CFR50.59 Reload Safety Evaluation governing reactor core operation has been approved by the Plant Operating Review Committee (PORC)
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| The reactor core loading has been verified.
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| All reactivity control components in the reactor core will meet their design functions.
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| All nuclear instrumentation in the reactor core will meet their design functions.
| |
| Affirmation:
| |
| Based on my knowledge andjudgment, the requiredconditions exist and the reactorcore is configured to support safe and reliableoperation through the cycle.
| |
| Supervisor-DB Reactor Engineering Print/Signature/Date Remarks: (Attach a continuation sheet if appropriate)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number: I
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 21 of 94 ATTACHMENT 7: REACTOR STARTUP AFFIRMATION FORM Mode_
| |
| Review Summary:
| |
| The Supervisor-DB Reactor Engineeringshould initial each item below to affirm that the required conditions exist priorto reactorstartup.
| |
| Estimated Critical Conditions have been prepared and independently verified.
| |
| Preparations are complete for any necessary Low Power Physics Testing (i.e. equipment, procedures, calculations, training)
| |
| Personnel are available, as required, to support reactor startup and power ascension to 100%.
| |
| Required training has been completed for Nuclear Fuels personnel.
| |
| Reactivity plans are available, as required, to support reactor startup and power ascension to 100%. These plans include expectations for reactor behavior with emphasis on any behavior that is different from recent plant operation.
| |
| The Core Monitoring System is operable.
| |
| All reactivity control systems will meet their design functions.
| |
| Sufficient nuclear instrumentation is available to safely startup and operate the reactor core.
| |
| There are no outstanding reactivity management issues impacting the safe operation of the reactor core.
| |
| Affirnation:
| |
| Based on my knowledge andjudgment, the required conditions exist and the reactorcore is read to support a safe startup andpower ascension.
| |
| Supervisor-DB Reactor Engineering Print/Signature/Date Remarks: (Attach a continuation sheet if appropriate)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number
| |
| _____ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 22 of 94 ATTACHMENT 8: SYSTEM ENGINEER/PROGRAM OWNER READINESS AFFIRMATION FORM Mode
| |
| : 1. Name of System/Program:
| |
| : 2. The status of the system/program is (For systems, a brief description of the physical status of the system including System Health status and Maintenance Rule status. For programs, a brief status of the program):
| |
| : 3. System/Program is ready for Mode Yes_ or No
| |
| : 4. The system/program is ready for Mode because: (if not ready, skip to #5)
| |
| : 5. The system/program is not ready for Mode because:
| |
| and the following actions are in place to address these issues:
| |
| The system/program will be ready for Mode _ by: (Date)
| |
| : 6. Items in abnormal status or configuration (workarounds, temporary modifications, Control Room deficiencies) identified and not corrected have been reviewed and determined to be acceptable:
| |
| Yes or No (Attach a list of the above items)
| |
| : 7. Housekeeping issues associated with this system/program have been addressed for Mode :
| |
| Yes or No (Attach a list of those not resolved)
| |
| : 8. I have the following concerns about my system and its readiness for Mode :
| |
| Briefly identify concerns. (The Restart Readiness Review process will not resolve these concerns at the meeting. They should be schediuledforpresentation to the Plant Support Center if there is a concern relative to this mode change.)
| |
| : 9. Open CRs, CAs, Work Orders or Engineering modifications required for Mode (Attach a list).
| |
| Name: Extension:
| |
| (Please Print)
| |
| Signature: Date:
| |
| | |
| I NUCLEAR OPERATING BUSINESS PRACTICE Number:DBBP-VP-0002 TUe Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 23 of 94 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 1 of 3 ASSESSMENT OF SAFETY CULTURE Assessment Summary:
| |
| Improving safety culture is a long-term activity that is monitored by Davis-Besse senior management. For Restart Readiness, it is important to show an improving safety culture with no critical areas of weakness that management evaluates as a restart concern. The individual criteria that make up the Commitment Areas may be green, white, yellow or red. Some of the Commitment Areas may be white (Policy or Corporate Commitment Area, Plant Management Commitment Area or Individual Commitment Area) however restart will not be approved if any of the three are red, or yellow without restart corrective actions being completed.
| |
| Remedial actions will be taken for any red criteria. Condition Reports will be written for all red and yellow criteria at the site and/or section level, with corrective actions to identify an existing or new plan for improvement. Corrective Actions may take credit for ongoing activities. Red criteria corrective actions will be formally presented to the Senior Leadership Team. If a Condition Report is written at the site level for a red or yellow Commitment Area or criteria, it will encompass any red or yellow section Commitment Area or criteria and that section need not write a separate Condition Report. If there is no site wide red or yellow Commitment Area or criteria then the Section Manager will write a Condition Report for the red or yellow Commitment Area or criteria.
| |
| The threshold for rating the attributes that comprise each criteria are provided in Appendix A. These thresholds are guidelines. Management may consider other factors and adjust the ratings accordingly. Management judgment is a key factor that cannot be removed or quantified. The purpose of the collegial group review Is to challenge, seek alternative input, and facilitate dialogue and to determine final criteria and Commitment color rating If other factors are considered, they shall be documented in an attachment to the Rating sheet. The ratings are based on convergent assessment such as: performance indicators, management observations, demonstrated performance during critical plant conditions surveys and interviews, training and feedback from independent safety culture reviews and Nuclear Quality Assurance Assessments. Each criterion will be assessed using information from the attribute reviews performed. An overall assessment of each attribute and criterion will be performed and documented explaining any that are rated as red or yellow and identifying the corrective actions needed prior to restart.
| |
| The ratings for an individual attribute will reflect recent activities or the most recent assessment data. If no applicable activities or assessments have been conducted within the past 12 months (i.e., there is no information applicable to the review period), the attribute shall be marked "NA", (Not Applicable). If both objective and subjective data are available, differences in data will be evaluated and decisions on use of data made.
| |
| Safety Culture Commitment Area/Criteria Ratings:
| |
| Green: all major criteria/attributes are acceptable with a few minor criteria deviations White: all major criteria/attributes are acceptable with a few criteria requiring management attention Yellow: all major criteria/attributes are acceptable with several criteria requiring prompt management action Red: several major criteria/attributes do not meet acceptable standards and require immediate management action
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 24 of 94 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 2 of 3 Each Section Manager will provide a Rating sheet (ATTACHMENT 9, Page -20,) with the Final Restart Readiness Criteria. For any individual attribute where only site-wide numbers are available (e.g. 4Cs surveys, ECP etc.), or for any individual attribute not applicable to a section (e.g. operator work-arounds for other than Operations), the Manager will NA that attribute on his backup sheets and that attribute will not be used as part of the site-wide tally for the criteria. For any attribute where surveys and/or interviews" are used as the basis for the rating, these surveys must be written but may be anonymous. Interview results will also be documented as to results although they may also be anonymous. The results for surveys or interviews will be maintained until after restart.
| |
| Documentation for Attachment 9 may be in the form of a tally for these survey or interview results.
| |
| At the final Restart Readiness Review meeting for any mode, a site-wide Rating sheet will be prepared by the management team using the individual section ratings as a guideline. The final Rating sheet will be signed by the Vice President-Nuclear and maintained with the other Restart Readiness documentation, including Attachment 11.
| |
| Preliminarily, determination of the Commitment Area/criteria color will be based on an average of the ratings of the associated criteria/attributes. Considerations include:
| |
| Greater than one red attribute or criteria means the criteria or Commitment Area can be no better than yellow. If more than two or more than 1/3 (whichever is greater) of the attributes or criteria are red, the indicator or Commitment Area shall be red.
| |
| For the overall plant ratings for Commitment Areas/criteria, management will consider whether the problems taken collectively indicate a more significant concern than indicated by the averages. For example, one section may perform more activities related to safety with respect to a certain criteria than other sections, and management may adjust the color to give greater weight to that section in determining the final color rating. Similarly, if percentages or averages alone indicate a positive rating but there were several associated safety-significant events or conditions, management may provide a more negative color rating to reflect those events or conditions.
| |
| If such an adjustment is made, it shall be documented. Generally, if all sections have similar rating, the overall rating for the plant will be the same as the ratings for the individual sections. During group review, senior management will seek to verify that the entire Restart Readiness Review team not only concurs, but also aligns behind the assessment.
| |
| At the completion of the Safety Culture Assessment, an evaluation of the significance of the overall assessment ratings for criteria to focus on the process and organization will be completed using Attachment 10 at the end of the document. A final report will then be prepared which documents how each Commitment Area, criteria and attribute was assessed and its final color rating. The report will also document any red or yellow area, criteria or attribute, corrective actions needed for restart and explain why restart is acceptable with the current condition.
| |
| Attachments 10 and 11 will be included as part of that report.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| .__ __ DBBP-VP-0002 Tide: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 25 of 94 ATTACHMENT 9: ASSESSMENT OF SAFETY CULTURE Page 3 of 3 Rating Safety Culture Mode_
| |
| Item Color
| |
| : 1. Policy or Corporate Commitment Area
| |
| : a. Policies on Safety Culture and Safety Conscious Work Environment clearly state that safety is a core value and are understood by the organization
| |
| : b. Management values are clearly reflected in the Business Plan and are understood by the organization
| |
| : c. Resources are available or can be obtained to ensure safe, reliable operations
| |
| : d. Self-Assessment is a tool used to monitor, assess and improve our performance
| |
| : e. Independent Oversight is a tool used to validate acceptable performance and identify areas for improvement or corrective action
| |
| : 2. Plant Management Commitment Area
| |
| : a. There is a visible commitment to safety: nuclear, industrial, radiological and environmental
| |
| : b. Goals and roles are clear and teamwork is reinforced
| |
| : c. Ownership and accountability is evident
| |
| : d. Training and Qualification are valued
| |
| : e. Commitment to continuous improvement is evident
| |
| : f. Cross-functional work management and communication
| |
| : g. Creating an environment of engagement and commitment
| |
| : 3. Individual Commitment Area
| |
| : a. Drive for excellence-nuclear assets of people and plant are continuously improved to enhance margins of safety
| |
| : b. Questioning attitude-challenges are welcomed
| |
| : c. Rigorous work control and prudent approach-performing activities in a quality manner is the standard
| |
| : d. Open communications-associates are comfortable in voicing opinions, issues and concerns
| |
| : e. Nuclear Professionalism-persistence and urgency in identification and resolution of problems is prevalent I have reviewed the Rating of Safety Culture as indicated above and concur that the current conditions l I I support readiness for mode change. l Section Manager (Please Print Your Name)
| |
| Signature: Date_
| |
| Section Manager Adjustments to ratings from the standard criteria should be documented and attached to this page.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Title Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 26 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 1 of 39
| |
| : 1. POLICY COMMITMENT AREA Ia. CRITERIA RELATED TO STATEMENT OF SAFETY POLICY Policies on Safety Culture and Safety Conscious Work Environment clearly state that safety is a core value and are understood by the organization ATTRIBUTE RED YELLOW WHITE GREEN Policy statement Policy statement is Policy statement is Policy statement is Policy statement is on Safety Culture* issued but it is not issued but only issued and is issued and is reinforced by occasionally reinforced frequently reinforced continuously reinforced FENOC by FENOC by FENOC by FENOC management management. management. management.
| |
| Policy statement Policy statement is Policy statement is Policy statement is Policy statement is on Safety issued but it is not issued but only issued and is issued and it is a strong Conscious Work reinforced by occasionally reinforced frequently reinforced statement of safety Environment FENOC by FENOC by FENOC conscious work (SCWE)' management. management. management. environment and often reinforced by FENOC management Making employees Policy statements Policy statements Policy statements are Policy statements are aware of policy simply issued as distributed separately communicated by at communicated to statements' part of FENOC to employees in least two employees and (Explain why white Business Plan. memo. means.(e.g., hard emphasized regularly in is acceptable if there copy distribution, meetings and face to is no face to face newsletters, group face communication.
| |
| communication) meetings, training, stand down).
| |
| Employee Surveys/interviews Surveys/interviews Surveys/interviews Surveys/interviews understanding of indicate less than indicate that 70-80% of indicate that 80-90% indicate that more than policies" 70% of employees the employees of employees 90% of employees understand the understand the understand the understand the policies policies. policies and consider policies and consider and consider safety a safety a FE value. safety a FE value. FE value and the normal way to do business.
| |
| Worker Surveys/interviews Surveys/interviews Surveys/interviews Surveys/interviews understanding of indicate that less indicate that between indicate that between indicate that more than responsibility to than 85% of workers 85-90% of workers 90-95% of workers 95% of workers raise safety understand their understand their understand their understand their concerns** responsibility to raise responsibility to raise responsibility to raise responsibility to raise nuclear safety or nuclear safety or nuclear safety or nuclear safety or quality quality concerns. quality concerns. quality concerns. concerns.
| |
| * Site wide assessment only. Data provided from Edventures survey results
| |
| ** Site wide assessment only. Data provided from Edventures survey results and 4Cs.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number: -
| |
| DBBP-VP-0002 I
| |
| | |
| ==Title:==
| |
| Revision: I Page RESTART READINESS REVIEW EXTENDED IPLANT OUTAGE 10 Page 27 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 2 of 39
| |
| : 1. POLICY COMMITMENT AREA lb. CRITERIA RELATED TO MANAGEMENT VALUES Management values are clearly reflected in the Business Plan and are understood by the organization ATTRIBUTE RED YELLOW WHITE GREEN Corporate values* There is no There is a There is a corporate There is a corporate corporate level corporate level level statement of level statement of statement of statement of commitment to commitment to safety.
| |
| safety values. commitment to safety. FirstEnergy FirstEnergy FirstEnergy safety. management meets management meets management FirstEnergy occasionally with frequently with plant does not management plant personnel to personnel to express its express its meets express its safety safety values.
| |
| safety values to infrequently with values.
| |
| plant personnel. plant personnel to express its safety values.
| |
| Statement of There is no The statement of The statement of The statement of mission, vision, statement of Mission, Vision, Mission, Vision, and Mission, Vision, and and values** Mission, Vision, and Values Values places greater Values emphasizes and Values and places weight on weight on safety than safety first, then allows employees safety and often on production/profits consideration of believe focus is employees and most employees production and profits on production believe the agree that the and over 90% of and profits. overriding focus overriding priority is employees agree based is safety on safety on surveys.
| |
| FENOC Business Business Plan Business Plan Business Plan Business Plan contains Plan* contains no contains few contains Strategic Strategic Objective Strategic Strategic Objective Measures Measures on safety and Objective Objective on safety with all are being fully Measures on Measures on implementation plans. implemented.
| |
| safety. safety but no implementation plans
| |
| *Site wide assessment only. Data provided by Senior Management
| |
| ** Site wide assessment only. Data provided from Edventures survey results
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number: I
| |
| ____ ____ ____ ____ ____D B B P-V P-.0002 Ttle Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 28 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 3 of 39
| |
| : 1. POLICY COMMITMENT AREA 1c. CRITERIA RELATED TO RESOURCES Resources are available or can be obtained to ensure safe, reliable operations ATTRIBUTE RED YELLOW WHITE GREEN Adequacy of More than five More than three Three or less All management management supervisor or above supervisor or supervisor or above positions are filled with resources* positions are not above positions positions are not filled ANSI qualified FENOC filled with ANSI are not filled with with ANSI qualified individuals.
| |
| qualified FENOC ANSI qualified FENOC individuals.
| |
| individuals. FENOC individuals.
| |
| Adequacy of More than four Three or four One or two sections Each section has a full personnel sections do not have sections do not do not have sufficient complement of resources'# sufficient personnel have sufficient personnel to perform personnel (minus to perform their personnel to their assigned normal attrition) to assigned perform their responsibilities perform its assigned responsibilities assigned without contractor responsibilities.
| |
| without contractor responsibilities support support without contractor support Adequacy of Risk significant The majority of All risk significant Sufficient funding exists funding** activities, to improve identified risk identified to perform more than nuclear safety, as significant improvements to just risk significant defined by the improvements to nuclear safety, as improvements, as Senior Leadership nuclear safety, as identified by the PRC identified by the PRC in Team and Project identified by the for the plant, plant, programs and Review Committee PRC for the plant, programs, or other other activities to (PRC) are not being programs, or activities, are funded improve nuclear safety.
| |
| funded in a timely other activities, in a timely manner.
| |
| manner and funding are funded in a was requested and timely manner.
| |
| rejected by FENOC Executive Management.
| |
| * Site wide assessment only. Data provided by Human Resources
| |
| #Significance evaluation regarding resources will be discussed depending on contractor support by section. Color identified for site after section discussion
| |
| *Site wide assessment only. Data provided by the chairman of the PRC
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 29 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 4 of 39
| |
| : 1. POLICY COMMITMENT AREA Ic. CRITERIA RELATED TO RESOURCES (continued)
| |
| Resources are available or can be obtained to ensure safe, reliable operations Adequacy of tools, More than 25 % Between 20- Between 10-20% of Less than 10% of material and of scheduled 25% of scheduled scheduled tasks scheduled tasks PMs, equipment to tasks (PMs, tasks (PMs, Work (PMs, Work Orders, Work Orders, ECRs complete site Work Orders, Orders, ECRs ECRs and projects) and projects) are not tasks* ECRs and and projects) are are not being being completed by the projects) are not not being completed by the site site in a timely manner being completed completed by the in a timely manner due to lack of tools, by the site in a site in a timely due to lack of tools, material or equipment.
| |
| timely manner manner due to material or due to lack of lack of tools, equipment.
| |
| tools, material or material or equipment. equipment.
| |
| Adequacy of tools, More than 25% Between 20-25% Between 10-20% of Less than 10% of key material and of key scheduled of key scheduled key scheduled tasks scheduled tasks are not equipment to tasks are not tasks are not are not being being completed by the complete Section being completed being completed completed by the section in a timely tasks by the section in by the section in section in a timely manner due to lack of a timely manner a timely manner manner due to lack of tools, material or due to lack of due to lack of tools, material or equipment.
| |
| tools, material or tools, material or equipment.
| |
| equipment. equipment.
| |
| Site wide assessment only. Data provided by Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| Title Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 30 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 5 of 39
| |
| : 1. POLICY COMMITMENT AREA Id. CRITERIA RELATED TO SELF-ASSESSMENT Self-Assessment is a tool used to monitor, assess and improve our performance ATTRIBUTE RED YELLOW WHITE GREEN Use of Nuclear Less than 70% of Between 70-80% of Between 80-90% of More than 90% of the Quality the sections have the sections have the sections have sections have used Assurance to used NQA input used NQA input to used NQA input to NQA to supplement supplement the to supplement the supplement the supplement the self- the self-assessment self- self-assessment self-assessment assessment process process as defined in assessment process as defined process as defined as defined in NOBP- NOBP-LP-2004 process in NOBP-LP- 2004 in NOBP-LP-2004 LP-2004 Self- Less than 60% of Between 60-75% of Between 75-90% of More than 90% of assessments in sections < 14) sections (15-17) sections (17-20) sections (>20) have accordance have planned have planned have planned planned ongoing self-with NOBP-LP- ongoing self- ongoing self- ongoing self- assessments for 15 &
| |
| 2004, FENOC assessments for assessments for 1 assessments for 15 2nd quarter 2004.
| |
| Ongoing Self- 15' & 2' quarter & 2nd quarter 2004. & 2rd quarter 2004.
| |
| Assessment 2004.
| |
| Guideline*
| |
| Section Performance Section performance Section performance Section performance Performance indicators related to indicators exist for indicators exist for indicators exist and are Indicators safety and quality important activities important activities appropriate and are being exist for the section affecting quality and affecting quality and regularly updated for safety but less than safety and 75-89% of important activities 75% of goals are met goals are met affecting safety and quality, with more than 90% of goals met.
| |
| Personnel The performance The performance The performance The performance Performance appraisal program appraisal program appraisal program appraisal program Appraisals" does not include includes includes assessments includes assessments of assessments of assessments of of safety or quality of safety and quality of safety or quality of safety or quality of performance but some performance and the performance. performance but most appraisals have not appraisals are being employee appraisals been performed in performed in timely have not been timely manner and manner and all performed. some employees do employees have a current I not have a current appraisal.
| |
| appraisal.
| |
| 'Site wide assessment only. Data provided by Quality Services
| |
| *Site wide assessment only. Data provided by Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Title Revison: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page31of94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 6 of 39
| |
| : 1. POLICY COMMITMENT AREA le. CRITERIA RELATED TO INDEPENDENT OVERSIGHT Oversight is a tool used to show acceptable performance and identify areas for improvement and corrective actions.
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Nuclear The Nuclear The Nuclear The Nuclear The Nuclear Committee Committee of Committee of the Committee Committee has safety has safety performance Board of Board has little occasionally discusses performance as a part as a part of the agenda Directors focus on safety safety performance as of the agenda every every meeting and performance in the a topic in the agenda. meeting requests additional agenda. presentations relative to specific issues to monitor performance Company The CNRB has a The CNRB agenda The CNRB agenda The CNRB agenda has Nuclear Review safety has a safety has a safety a safety discussion Board (CNRB)+ performance discussion and discussion at every every meeting and is assessment monitors safety meeting and reviews proactive in providing discussion on the performance presentations on safety focus actions for agenda. safety focus issues FENOC Nuclear Quality NQA is not Some NQA audits or NQA audits or NQA is regularly Assurance performing audits assessments were assessments were performing audits and (NQA)** or assessments of performed when performed when assessments of important safety required and a number required, for important important safety activities and not of areas of concern safety activities and activities and identifying finding areas of were identified for some Significant key issues for concern causing Important safety Conditions Adverse to improvement that are Significant activities causing Quality were noted below the Significant Conditions Significant Conditions Condition Adverse to Adverse to Quality Adverse to Quality Quality threshold.
| |
| Learning from Personnel in the Personnel in the Personnel in the Personnel in the section the experience section do not section seldom section occasionally routinely participate in of the industry participate in participate in industry participate in industry industry committees, industry committees, visit other committees, visit other visit other sites or host committees, visit sites or host personnel sites or host personnel personnel from other other sites or host from other sites from other sites sites personnel from other sites
| |
| *Site wide assessment only. Data provided by Senior Management
| |
| +Site wide assessment only. Data provided by NQA Manager or VP Oversight
| |
| **This item is assessed by NQA only.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 32 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 7 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Management There is a There is a management There is a There is a management observations management observation program management observation program performed as observation program and 65-75% of observation program and more than 90% are scheduled with and less than 65% management and 76-90% are performed as proper of the observations observations are performed as scheduled and less coaching* are performed as performed as scheduled and less than 5% rated as scheduled and scheduled and greater than 10% rated as overall unsat.
| |
| >90% indicate no than 10% were rated overall unsat, coaching required. overall unsat.
| |
| Management Most management Between 50-74% of the Between 75-89% of More than 90% of the observations observations are not management the management management are self self-critical. observations performed observations observations performed critical* are self-critical and performed are self- are self-critical and actions implemented. critical and actions actions Implemented.
| |
| implemented.
| |
| Management No method has been One method has been Two means have Multiple means have emphasis on used in the last used in the last month been used in the last been used by safety to month to provide to provide emphasis on month to provide management in the last employees; emphasis on safety safety to employees in emphasis on safety to month to provide face questioning to employees in the the section (e.g., town employees in the to face emphasis on attitude section (e.g., town hall, 4Cs or All Hands section and at least safety to employees in hall, 4Cs, or All meetings, standdowns, one was face to face the section (e.g., town Hands meetings, newsletters, and (e.g., town hall, 4Cs hall, 4Cs or All Hands standdowns, training). or All Hands meetings, standdowns, newsletters, and meetings, newsletters, and training). standdowns, training).
| |
| newsletters, and training).
| |
| *Site wide assessment only. Data provided by Management Observation Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 I Page 33 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 8 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY (continued)
| |
| There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Leadership in Leadership in Leadership in Action Leadership in Action Leadership in Action* Action includes includes discussions on includes discussions Action includes discussions on safety culture.
| |
| * on safety culture. ' discussions on safety culture.
| |
| * And And safety culture.
| |
| And Employee feedback Employee feedback And Employee feedback indicates it was indicates it was very Employee indicates it was not effective effective. feedback indicates effective. it was very And And effective And Leadership in Action Leadership in Action And Leadership in training has been training has been Action training has available and available and Leadership in been available and scheduled for more scheduled for more Action training has scheduled for less than 75% of than 80% of been available and than 75% of supervisors and above supervisors and scheduled for supervisors and within 12 months of above within 12 more than 85% of above within 12 new appointment.* months of new supervisors and months of new appointment.* above within 12 appointment.* months of new appointment.*
| |
| Problem solving- A problem solving in more than 5 cases, In all but one case, The problem process exists but the problem solving the problem solving solving process, there is no use of process NOP-EN-3001 process, NOP-EN- NOP-EN-3001 has the document in the has not been properly 3001 has been been properly section and CRs implemented in the property implemented implemented in were written to section for applicable in the section for the section for document the conditions and CRs applicable conditions applicable failure to use the were written in the during the previous conditions during process during the previous quarter. quarter. the previous previous quarter. quarter.
| |
| Site wide assessment only. Data provided by Human Resources
| |
| **Site wide assessment only. Data provided by Plant Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| I____ DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I 10 l Page 34 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 9 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2a. CRITERIA RELATED TO COMMITMENT TO SAFETY (continued)
| |
| There is a visible commitment to safety: nuclear, industrial, radiological and environmental ATTRIBUTE RED YELLOW WHITE GREEN Decision A Safety significant A Safety significant The majority of safety Safety significant making Condition Adverse to Condition Adverse to significant decisions decisions were made in Quality Condition Quality Condition were made in the the section with Report indicates that Report indicates that section with adequate required information, decisions were decisions are made in information, management oversight, made in the section the section with minimal management involvement and peer in isolation without information, oversight, checking during the adequate management oversight, involvement and peer past six months as information, involvement and peer checking during the indicated by no SCAQs.
| |
| management checking during the quarter as indicated oversight, past two months. by no SCAQs.
| |
| involvement and peer checking during the past month.
| |
| Improvements There have been There have been some There have been Significant in safety minimal improvements made in obvious improvements have margin* improvements made safety margin. improvements made been made in safety in safety margin. in safety margin. margin.
| |
| Plant activities A significant plant Two Condition Adverse Significant plant Significant plant receive proper event, associated to Quality CRs activities associated activities associated management with the section, associated with the with the section had a with the section had a attention and occurred during the section were written management plan management plan with safety focus previous quarter and due to lack of with a management a management sponsor a lack of a management attention sponsor and and management (Reference management or lack of safety focus management oversight scheduled for NG-DB-00800) attention or safety during the previous oversight scheduled the duration of the focus was indicated quarter. for the duration of the activity and no CAQ and an SCAQ activity and only one events occurred during written. CAQ event occurred the previous quarter.
| |
| indicating a lack of management attention during the previous quarter.
| |
| 'Site wide assessment only. Data provided by Design Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ______________ __ DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 35 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 10 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2.b CRITERIA RELATED TO ROLES AND TEAMWORK Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Understanding Station surveys Station surveys Station surveys and/or Station surveys that safety is and/or interviews and/or interviews, interviews show that 80- and/or interviews highest priority* show that less show that 70-80% 90% of employees, show that more than than 70% of of employees, understand that safety is 90% of employees 10 employees understand that the highest priority. believe that safety is understand that safety is the highest the highest priority.
| |
| safety is the priority.
| |
| highest priority.
| |
| Program Five or more of the All identified All identified programs All identified ownership" identified programs have have assigned owners. programs have programs in the assigned owners With several exceptions, assigned owners. In program review do and 3-4 SCAQ/ program owners are general, program not have assigned CAQs were written implementing their owners are owners and > five on different assigned responsibilities implementing their SCAQICAQs were programs in the and 1-2 SCAQ/CAQs assigned written against past quarter. were written on different responsibilities and different programs programs in the past no SCAQQICAQs in the past quarter. quarter. were written against programs in the last quarter.
| |
| Ownership of More than 5% of 5% of SCAQ Less than 5% of SCAQ Less than 5m of corrective SCAQ remedial remedial or remedial or preventive SCAQ remedial and actions and preventive preventive restart restart required preventive restart restart required required corrective corrective actions and required corrective Does not include corrective actions actions and 10% of 10% of CAQ remedial a0iof andthan less CRs or CAs linked and more than CAQ remedial and and preventive restart an% of CA remedial to P3 activities. 10% of CAQ preventive restart required corrective and preventive restart remedial and required corrective actions for the section, required corrective preventive restart actions for the have received 2 actions for the section required corrective section, have extensions for the have received less actions for the received more than previous quarter. than 2 extensions for section have 2 extensions for the the previous quarter.
| |
| required more previous quarter.
| |
| than 4 extensions for the previous quarter.
| |
| *Site wide assessment only. Data provided from Edventures survey results "Site wide assessment only. Data provided by Plant Engineering Manager. See Attachment 12 for identified programs.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 36 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 11 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2b. CRITERIA RELATED TO ROLES AND TEAMWORK (continued)
| |
| Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Ownership of The quality of The quality of The quality of The quality of engineering engineering engineering engineering engineering products as products as products as products as products as measured by the EAB is measured by the measured by the measured by the measured by the 1.0 or less.
| |
| Engineering EAB is greater EAB is between EAB is between 2.0 Assessment Board than 3.0. 3.0 and 2.1. and 1.1.
| |
| (EAB)-
| |
| Effectiveness of The individual The individual The individual error The individual error rate supervision of error rate is >0. error rate is <.45- rate is<.35->.26 is<0.26 individual errors individuals" 45 individual >.36 individual individual errors per per 10,000 hours errors per errors per 10,000 10,000 hours worked.
| |
| 10,000 hours hours worked. worked.
| |
| worked.
| |
| Intra-department As a Manager, I As a Manager, I As a Manager, I As a Manager, I believe teamwork and believe there is believe there is believe alignment is alignment and teamwork alignment ((Some no alignment minimal improving and are obvious among unit supervisors and little alignment and teamwork can be managers in all activities will input to this teamwork some teamwork seen in some key of my department.
| |
| attribute, such as, among my among my activities among my Reactor Department's Department's Department's Engineering and managers. managers. managers.
| |
| RRT.)
| |
| Expectations Four or more Three sections One or two sections All sections have sections do not do not have do not have statements of have statements statements of statements of expectations and of expectations. expectations. For expectations. For managers are For those those that do, those that do, most reinforcing them and sections that do, most employees employees employees understand employees implement them. implement them. and routinely implement frequently do not Xthem.
| |
| implement them. I
| |
| 'Site wide assessment only. Data provided by Director-Nuclear Engineering "Site wide assessment only. Data provided by Human Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 37 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 12 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2b. CRITERIA RELATED TO ROLES AND TEAMWORK (continued)
| |
| Goals and roles are clear and teamwork is reinforced ATTRIBUTE RED YELLOW WHITE GREEN Trust, openness 4Cs surveys 4Cs surveys 4Cs surveys show 4Cs surveys show more and focused show less than show 50-70% of 70-90% of than 90% of employees commitment** 50% of employees feel employees feel that feel that work groups employees feel that work groups work groups display display high levels of that work groups display high high levels of trust, trust, openness and display high levels of trust, openness and commitment.
| |
| levels of trust, openness and commitment.
| |
| openness and commitment.
| |
| commitment.
| |
| Clear goals and No clear goals Goals and Goals and priorities Employees are clear priorities and priorities priorities exist for exist for the section about goals and have been the section but and most employees priorities for the section established for are not understand and own as well as how their role the section adequately them. contributes to achieving understood and them.
| |
| owned by some employees.
| |
| Input and No employee Only managers Managers and Employees are involvement input and and supervisors supervisors appropriately involved in involvement are involved in occasionally request setting section goals and occurs in the the setting of input/involvement establishing work setting of section section goals and from employees in priorities.
| |
| goals and establishing work the setting of section establishing priorities. goals and work priorities. establishing work priorities.
| |
| - Site wide assessment only. Data provided by Chief Operating Officer
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 38 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 13 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY Ownership and accountability is evident ATTRIBUTE RED YELLOW WHITE GREEN Performance Less than 70% of Between 70-80% Between 80-90% of More than 90% of reviews in performance of performance performance reviews performance reviews for accordance with reviews for the reviews for the for the section were the section were FENOC section were section were completed for the completed for the review Performance completed for the completed for the review period period Management review period review period Process Development Less than 70% of Between 70-80% Between 80-90% of More than 90% of plans' managers and of managers and managers and managers and supervisors have supervisors have supervisors have supervisors have development development development plans development plans plans submitted plans submitted submitted to HR submitted to HR to HR to HR Restart There is no A restart A restart readiness A restart readiness Readiness restart readiness readiness review review process review process exists Reviews* review process. process exists exists and is and is implemented but implemented with efficiently and with implementation is the majority of participation by poor as shown by Managers and the Managers and the lack of Manager Senior Leadership Senior Leadership Team participation. Team participation.
| |
| Worker Surveys and/or Surveys and/or Surveys and/or Surveys and/or understanding of interviews interviews interviews indicate interviews indicate that their responsibility indicate that less indicate that that between 90- more than 95% of to raise safety than 80% of between 80-90% 95% of workers workers understand their concerns# workers of workers understand their responsibility to raise understand their understand their responsibility to raise nuclear safety or quality responsibility to responsibility to nuclear safety or concerns.
| |
| raise nuclear raise nuclear quality concerns.
| |
| safety or quality safety or quality concerns. concerns.
| |
| 'Site wide assessment only. Data provided by Human Resources "Site wide assessment only. Data provided through discussion at the Restart Readiness Review meeting
| |
| # Site wide assessment only. Data provided from Edventures survey results
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I 10 Page 39 of 94, APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 14 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY(continued)
| |
| Ownership and accountability is evident IWillingness to Surveys show Surveys show Surveys show that Surveys show that more raise safety that less than that between 85- between 90-95% of than 95% of personnel concerns t 85% of personnel 90% of personnel personnel are willing are willing to raise safety are willing to are willing to to raise safety concerns through their raise safety raise safety concerns through supervisor, a CR or concerns through concerns through their supervisor, a ECP.
| |
| their supervisor, a their supervisor, a CR or ECP.
| |
| CR or ECP. CR or ECP.
| |
| SRO reviews for Less than 90% Between 90-95% Between 95-98 % More than 98% were Operability are were completed were completed were completed completed within 24 performed in a within 24 hours. within 24 hours. within 24 hours. hours, timely manner for the identified period of this review**
| |
| System Less than 80% Between 80-90% Between 90-95% of More than 95% of the assessments+ of restart required of the restart the restart required restart required improvements in required improvements in improvements in safety safety have been improvements in safety have been have been implemented implemented at safety have been implemented at this at this time this time. implemented at time.
| |
| this time.
| |
| 'Site wide assessment only. Data provided by 4Cs program and /or Employee Concerns Program
| |
| "~This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Plant Engineering Manager
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 40 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 15 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2c. CRITERIA RELATED TO OWNERSHIP AND ACCOUNTABILITY (continued)
| |
| Ownership and accountability is evident NQA field NQA field NQA field NQA field NQA field assessments assessments' assessments assessments assessments show show that managers and show that show that that managers and supervisors are managers and managers and supervisors are generally effective.
| |
| supervisors are supervisors are generally effective, generally generally with a few ineffective. effective, with exceptions.
| |
| several noteworthy exceptions.
| |
| Management Less than 80% Between 80-85% Between 85-95% of More than 95% of observations of management of management management management leading to participating in participating in participating in the participating in the coaching+ the Management the Management Management Management Observation Observation Observation Observation Program Program, have Program, have Program, have have performed a performed a performed a performed a coaching session in the coaching coaching session coaching session in last month.
| |
| session in the in the last month. the last month.
| |
| last month.
| |
| Timeliness of Less than 50% Between 50% Between 75% and More than 90% of my corrective actions of my section's and 74% of my 90% of my section's section's corrective corrective section's corrective actions actions designated as Does not include actions corrective actions designated as required for restart, are CRs or CAs linked to designated as designated as required for restart, complete at this time P3 activities required for required for are complete at this restart are restart are time complete at this complete at this time time
| |
| - This item assessed by NQA only
| |
| +Site wide assessment only. Data provided by Management Observation Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 41 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 16 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2d. CRITERIA RELATED TO TRAINING AND QUALIFICATION Training and Qualification are valued IATTRIBUTE RED YELLOW WHITE GREEN Restart training+ Most required Between 75-90% Between 90-99% of 100% of required restart training is of required restart required restart restart training is (Explain why not complete. training is training is complete. complete.
| |
| acceptable if less complete.
| |
| than green)
| |
| Initial Operator Individuals in Individuals in Individuals in initial Individuals in initial training* initial license initial license license class are license class are class are class are maintaining a class maintaining a class maintaining a maintaining a average of 88-94% average of more than class average of class average of 94%
| |
| 82% or less 83-87%
| |
| Requalification Less than 70% of Between 70-84% Between 85-95% of More than 95% of the training** licensed of the licensed the licensed licensed operators have operators have operators have operators have passed their (Explain why passed their passed their passed their requalification training.
| |
| acceptable if less requalification requalification requalification than green) training. training, training.
| |
| "This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Nuclear Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tide Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 42 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 17 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2d. CRITERIA RELATED TO TRAINING AND QUALIFICATION (continued)
| |
| Training and Qualification are valued Operability Less than 50% of Between 50-74% Between 75-90% of More than 90% of determination applicable of applicable applicable operators applicable operators training* operators and operators and and engineers have and engineers have (Explain why engineers have engineers have received training on received training on acceptable if less received training received training operability operability than green) on operability on operability determinations. determinations.
| |
| determinations. determinations.
| |
| Training on Less than 80% Between 80-89% Between 90-97% of More than 97%
| |
| SCWE of managers, of managers, managers, managers, supervisors, supervisors, and supervisors, and supervisors, and and operators have (Explain why operators have operators have operators have received training on acceptable if less received training received training received training on SCWE.
| |
| than green) on SCWE. on SCWE. SCWE.
| |
| Training on Less than 70 % Between 70-80% Between 80-90% of More than 90% of decision making of applicable of applicable applicable personnel applicable personnel process` personnel have personnel have have received training have received training received training received training on the decision on the decision making on the decision on the decision making process. process.
| |
| making process. making process.
| |
| Training on Less than 80% Between 80-89% Between 90-95% of More than 97% of standards and of personnel in of personnel in in the section personnel in the expectations the section have the section have personnel have section, have received (Explain why received training received training received training on training on standards acceptable if less on standards and on standards and standards and and expectations.
| |
| than green) expectations. expectations. expectations.
| |
| Continuing Less than 70% of Between 70-80% Between 80-90%of More than 90% of training identified scheduled of scheduled scheduled training scheduled training by Curriculum training identified training identified identified by the CRC identified by the CRC is Review by the CRC is by the CRC is is completed in a completed in a timely Committee completed in a completed in a timely manner. manner.
| |
| (CRC) timely manner. timely manner.
| |
| *This item assessed by Operations and Engineering only
| |
| "*Site wide assessment only. Data provided by Nuclear Training
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE TNumber:
| |
| ___________________________________IDBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 43 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 18 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Improvements in Most requisitions About 50% of open About 75% of open At least 85% of open management for management requisitions for requisitions for requisitions for staffing* positions (all management (all management management positions exempt employees) exempt employees) positions (all exempt (all exempt employees) have not been filled positions have employees) have have been filled in the in the past month. been filled in the been filled in the past month.
| |
| past month. past month.
| |
| Corrective Action There are no The CARB has The CARB has been The CARB has been Review Board directors on the been enhanced enhanced with enhanced with director-(CARB)+ CARB. with director-level director-level level personnel.
| |
| personnel. personnel.
| |
| The backlog of The backlog of documents awaiting The backlog of The backlog of documents awaiting CARB review is documents awaiting documents awaiting CARB review is less more than four CARB review is CARB review is less than one week.
| |
| weeks. less than four than two weeks.
| |
| weeks.
| |
| Engineering The backlog of The backlog of The backlog of The backlog of Assessment documents awaiting documents awaiting documents awaiting documents awaiting EAB Board (EAB)++ EAB review is EAB review is less EAB review is less review is less than one greater than four than four weeks. than two weeks. week.
| |
| weeks. I I Site wide assessment only. Data provided by Human Resources
| |
| +Site wide assessment only. Data provided by Performance Improvement
| |
| ++Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-.0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 44 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 19 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT(continued)
| |
| Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Benchmarking Less than 60% (< Between 60-75% Between 75-90% of More than 90% of against industry 14) of sections (15-17) of sections ( 17-20) sections (>20) have standards@ have scheduled sections have have scheduled any scheduled any any benchmarking scheduled any benchmarking in benchmarking in in accordance bench-marking in accordance with accordance with NOBP-with NOBP-LP- accor-dance with NOBP-LP-2002 or LP-2002 or NG-EN-2002 or NG-EN- NOBP -LP-2002 NG-EN-00386 for 15' 00386 for 1 & 2'4 00386 for I & 2n or NG-EN-00386 $ 2'd quarter 2004. quarter 2004.
| |
| quarter 2004. for 1' quarter 2004.
| |
| Management A management A management A management A management observations.. observation observation observation program observation program program has been program has has been established. has been established.
| |
| established. Less been established. More than 80% of More than 90% of than 70% of More than 70% of management management management management observations are observations are observations are observations are performed as performed as performed as performed as scheduled and most scheduled and contain scheduled, and scheduled, and are considered quality information.
| |
| observations are observations are acceptable.
| |
| weak. weak.
| |
| Temporary There are more There are 11 or There are 8 or less There are 5 or less moditications+# than 11 temporary less temporary temporary temporary modifications. modifications. modifications. modifications.
| |
| Number of There are more There are 2 There is 1 operator There are no operator Operator work- than 2 operator operator workarounds. workarounds.
| |
| arounds*# workarounds. workarounds.
| |
| Number of There are more There are 4 There are 1-3 Control There are no Control Control Room than 4 Control Control Room Room deficiencies. Room deficiencies.
| |
| deficiencies*# Room deficiencies.
| |
| deficiencies.
| |
| @ Site wide assessment only. Data provided by Quality Services
| |
| *This item assessed by Operations only
| |
| **Site wide assessment only. Data provided by Management Observation program
| |
| +Site wide assessment only. Data provided by Plant Engineering
| |
| #Significance evaluation will be discussed during the Restart Readiness Review Safety Culture Assessment and the outcome of this discussion may affect any or all of the attribute ratings. Explain why acceptable if less than green
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:BBPVP 2
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED I PLANT OUTAGE 10 I Page 45 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 20 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT (continued)
| |
| Commitment to continuous improvement is evident ATTRIBUTE RED YELLOW WHITE GREEN Training on Less than 80% of Between 80-89% Between 90-97% of More than 97% of SCWE* managers, of managers, managers, managers, supervisors supervisors and supervisors and supervisors and and operators have operators have operators have operators have received training on received training received training received training on SCWE.
| |
| on SCWE. on SCWE. SCWE.
| |
| Licensed Individuals in Individuals in Individuals in initial Individuals in initial operator initial license initial license license class are license class are pipeline" class are class are maintaining a class maintaining a class maintaining a maintaining a average of 88-94% average of more than class average of class average of 94%.
| |
| 82% or less 83-87%
| |
| *Site wide assessment only. Data provided by Nuclear Training "This item assessed by Operations only.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 TiUe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 46 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 21 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2e. CRITERIA RELATED TO COMMITMENT TO CONTINUOUS IMPROVEMENT (continued)
| |
| Commitment to continuous improvement is evident SAFETY CONSCIOUS WORK ENVIRONMENT (SCWE)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Use of More than 4 CRs Between 4-2 CRs Less than 2 CRs No CRs issued within SCWERT* issued within the issued within the issued within the past the past year related to past year related past year related year related to failure failure to properly to failure to to failure to to properly conduct conduct SCWERT properly conduct properly conduct SCWERT review of review of Davis-Besse SCWERT review SCWERT review Davis-Besse work work disciplinary of Davis-Besse of Davis-Besse disciplinary actions actions prior to the work disciplinary work disciplinary prior to the action. action.
| |
| actions prior to actions prior to the action. the action.
| |
| Effectiveness of There are more There are 5 NRC There are 4 NRC There are 2 or fewer SCWERT in than 5 NRC allegations or allegations or ECP NRC allegations or avoiding allegations or ECP concerns of concerns of ECP concerns of discrimination ECP concerns of discrimination discrimination discrimination claims* discrimination submitted within submitted within the submitted within the submitted within the past year past year past year the past year Effectiveness in There is more There is one There are no There are no avoiding NRC or than one substantiated substantiated NRC or substantiated NRC or ECP substantiated NRC or ECP ECP discrimination ECP discrimination substantiated NRC or ECP discrimination claims within the past claims within the past 2 discrimination discrimination claim within the year. years.
| |
| claims claim within the past year past year Site wide assessment only. Data provided by Employee Concerns Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 47 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 22 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2f. CRITERIA RELATED TO COMMITMENT TO CROSS-FUNCTIONAL WORK MANAGEMENT AND COMMUNICATION Commitment to cross functional work management and communication is evident ATTRIBUTE RED YELLOW WHITE GREEN Cross-functional No cross-functional Some cross- Cross-functional Cross-functional teamwork* teamwork is evident functional teamwork frequently teams among sections among sections teamwork among occurs among are constantly sections exists but sections, enabling forming/reforming work is sub- efficient and effective around the best way to optimized. workflow. get work done.
| |
| Department Many process Some process Minimal process Department interfaces interfaces breakdowns occur breakdowns occur breakdowns and are seamless; work within the within the rework occur within the flows efficiently Department with Department with Department with between departments extensive amounts frequent amounts effective and efficient throughout the entire of rework needed. of rework needed. resolution of emergent organization.
| |
| issues.
| |
| Performance to Less than 70% of Between 70-80% Between 80 -90% of More than 90% of schedule" work is completed of work is work is completed on work is completed on on time, as completed on time, as scheduled, time, as scheduled, scheduled, causing time, as with minimal within current resource major scheduled, with adjustments to capacity.
| |
| consequences to major adjustments resource capacity overall site to resource required to improve performance. capacity required performance.
| |
| to improve performance.
| |
| Interdepartmental Information that Information that Information that Information that communication# impacts impacts impacts downstream impacts downstream downstream downstream implementation is implementation is implementation is implementation Is frequently shared on a communicated as not shared, causing inconsistently timely basis, enabling soon as it's known, significant negative shared, which departments to enabling departments consequences to keeps other proactively plan and to work proactively on other departments. departments in a respond. a consistent basis.
| |
| reactive mode.
| |
| ' Site wide assessment only. Data provided from Edventures survey results.
| |
| -Site wide assessment only. Data provided by Outage Management and Work Control
| |
| #Site wide assessment only. Data provided by Edventures and 4Cs
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 48 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 23 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2f. CRITERIA RELATED TO COMMITMENT TO CROSS-FUNCTIONAL WORK MANAGEMENT AND COMMUNICATION (continued)
| |
| Commitment to cross functional work management and communication is evident Interdepartmental Problem solving Cross-functional Cross-functional Cross-functional problem solving and decision sections, sections, sections, and decision making occurs in Departments or Departments or Departments or making isolation; non- stakeholders are stakeholders are stakeholders are involvement of seldom involved frequently involved consistently involved other Departments when problems when problems are when problems are or stakeholders. are being solved being solved and being solved and and decisions are decisions are made. decisions are made.
| |
| made.
| |
| Systemic learning Things are broken Discrete problems Attention is focused Streamlining and down, focus is on are fixed within the on learning and improving systems the pieces and section with discovering and process is discrete problems minimal fundamental constant to resolve are fixed within the understanding of solutions to resolving long-standing and/or section with no interdependencies long-standing and/or complex problems understanding of complex problems within the section interdependencies. within the section Incorporating Industry operating There is less than There is full Operating Experience industry experience is not full utilization and utilization and is consistently and Operating consistently fully minimal compliance with the fully utilized in every Experience* utilized to enhance compliance to our Operating department and is site performance. Operating Experience Program well-integrated into Experience everyday activities to Program enhance plant performance.
| |
| Site wide assessment only. Data provided by Operating Experience Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 49 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 24 of 39 2.MANAGERS' COMMITMENT AREA 2g. CRITERIA RELATED TO COMMITMENT TO CREATING AN ENVIRONMENT OF ENGAGEMENT AND COMMITMENT An environment of engagement and commitment is evident ATTRIBUTE RED YELLOW WHITE GREEN FENOC values, FENOC values, FENOC values, FENOC values, basic Most exempt basic principles basic principles and basic principles principles and personnel in the and leadership leadership and leadership leadership strategies section have strategies strategies are not strategies are are frequently internalized and are used by exempt inconsistently demonstrated by some living the FENOC personnel within the demonstrated by exempt personnel values, basic section some exempt within the section principles and personnel within leadership strategies the section as demonstrated in their day to day actions.
| |
| Quality of Employee Employee Employees Concerns Employee Concerns management and Concerns Program, Concems Program, Quality Program, Quality employee Quality Assessment Program, Quality Assessment and 4Cs Assessment and 4Cs relationships' and 4Cs survey Assessment and survey data indicates survey data indicate data indicates that 4Cs survey data that more than 80% of more than 90% of (Explain why employees openly indicates that employees will bring employees raise acceptable if not express fear of more than 70% concerns to issues directly with green) retaliation and will of employees management. management, work not raise safety will bring safety collaboratively to concerns with concerns to resolves issues and management. management. reflect favorable improvement.
| |
| Organizational Section Section Section management Section management commitment and management management frequently supports consistently supports shared success focuses on what is occasionally doing what is in the doing what is in the criteria in the best interest supports what is best interest of the best interest for the of their section at in the best whole organization whole organization the expense of interest of their rather than what is in rather than what is in what is in the best section without the best interest of the best interest for interest of the consideration to their section. their section.
| |
| whole organization. what is in the best interest of the whole organization.
| |
| 'Site wide assessment only. Data provided by ECP, NQA and 4Cs
| |
| | |
| I NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Title Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 50 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 25 of 39
| |
| : 2. MANAGERS' COMMITMENT AREA 2g. CRITERIA RELATED TO COMMITMENT TO CREATING AN ENVIRONMENT OF ENGAGEMENT AND COMMITMENT (continued)
| |
| An environment of engagement and commitment is evident Performance Less than 70% of Between 70-80% Between 80-90% of More than 90% of reviews in performance of performance performance reviews performance reviews accordance with reviews for the reviews for the for the section were for the section were FENOC section were section were completed for the completed for the Performance completed for the completed for the review period per. review period per the Management review period per review period per. the FENOC FENOC Performance process* the FENOC the FENOC Performance Management process Performance Performance Management Management Management process process process FENOC Less than 70% of Between 70-80% Between 80-90% of More than 90% of Performance managers and of managers and managers and managers and Management supervisors have supervisors have supervisors have supervisors have Process development plans development plans development plans development plans Development submitted to HR submitted to HR submitted to HR submitted to HR Plans*
| |
| 'Site wide assessment only. Data provided by Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 51 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 26 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3a. CRITERIA RELATED TO DRIVE FOR EXCELLENCE Nuclear assets of people and plant are continuously improved to enhance margins of safety ATTRIBUTE RED YELLOW WHITE GREEN Maintenance Rule There are more There are 2-3 There is one Red There are zero Red (a)(1) Systems* than 3 Red Red (a)(1) (a)(1) system. (a)(1) systems and all (a)(1) systems. systems. Maintenance Rule (a)(1) systems are in monitoring status Number of There are more There are 2 There is 1 operator There are no operator Operator than 2 operator operator workarounds. workarounds.
| |
| workarounds
| |
| * workarounds. workarounds.
| |
| Number of Control There are more There are 4 There are 1-3 There are no Control Room than 4 Control Control Room Control Room Room deficiencies.
| |
| deficiencies**# Room deficiencies. deficiencies.
| |
| deficiencies.
| |
| Number of There are more There are 11 or There are 8 or less There are 5 or less temporary than 11 less temporary temporary temporary modifications.
| |
| modifications+# temporary modifications. modifications.
| |
| modifications.
| |
| Individual Error The individual The individual The individual error The individual error rate Rate++ error rate is error rate is 0.31 rate is 0.29 <.35- is <0.26 individual errors
| |
| > 0.45 individual <.45->.36 >.26 individual errors per 10,000 hours errors per individual errors per 10,000 hours worked.
| |
| 10.000 hours per 10,000 hours worked.
| |
| worked. worked.
| |
| 'Site wide assessment only. Data provided by Plant Engineering "This item assessed by Operations only
| |
| +Site wide assessment only. Data provided by Plant Engineering
| |
| ++Site wide assessment only. Data provided by Human Performance
| |
| #Significance evaluation will be discussed during the Restart Readiness Review Safety Culture Assessment and the outcome of this discussion may affect any or all of the attribute ratings. Explain why acceptable if less than green.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| < ~~~~~DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 52 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 27 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3a. CRITERIA RELATED TO DRIVE FOR EXCELLENCE (continued)
| |
| Nuclear assets of people and plant are continuously improved to enhance margins of safety Percent of Less than 80% of 80% or more of the 90% or more of the 95% or more of the CRs self-identified the CRs originated CRs originated are CRs originated are originated are self-Condition are self-identified. self-identified. self-identified. identified.
| |
| Reports (CRs)
| |
| * Number of Less than 80% of At least 80-90% of At least 90% of SCAQ All SCAQ evaluations open SCAQ evaluations SCAQ evaluations evaluations and 80- and 90% of CAQ Condition and less than 70% and 70-80% of 90% of CAQ evaluations were Report of CAQ evaluations CAQ evaluations evaluations were completed on schedule evaluations* were completed on were completed on completed on for the previous quarter.
| |
| schedule for the schedule for the schedule for the previous quarter. previous quarter. previous quarter.
| |
| Engineering The quality of The quality of The quality of The quality of Assessment engineering engineering engineering products engineering products as Board (EAB) products as products as as measured by the measured by the EAB is index" measured by the measured by the EAB is 2.0 or less. 1.0 or less.
| |
| EAB is greater than EAB is 3.0 or less.
| |
| 3.0.
| |
| Performance More than one One significant Major plant evolutions Major plant evolutions during major significant event has event has occurred have been performed have been performed plant occurred during a during a plant in the past month with successfully in the past evolutions+ plant evolution in the evolution in the past some less than month as planned past month month significant challenges without any challenges or transients.
| |
| Addressing Less than 70% of Between 70-80% of Between 80-90% of More than 90% of Operating operating operating operating experience operating experience Experience* experience reports experience reports reports applicable to reports applicable to the 10 applicable to the applicable to the the section are section are completed section are section are completed on time on time.
| |
| completed on time completed on time Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Significant is defined by INPO as an event which caused or had the potential to cause an appreciable reduction in plant safety or reliability, excessive radiation exposure, the discharge of radioactivity offsite or serious harm to individuals. The significance of a particular event (including the discovery of a serious deficiency, lies in the actual or potential consequences of the event or in the likelihood that it is a precursor to a more serious event.
| |
| 'Site wide assessment only. Data provided by Performance Improvement "Site wide assessment only. Data provided by Director-Nuclear Engineering
| |
| +Site wide assessment only. Data provided by Operations
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _____________________,DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 53 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 28 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3b. CRITERIA RELATED TO QUESTONING ATTITUDE Challenges are welcomed ATTRIBUTE RED YELLOW WHITE GREEN Quality of pre-job Management Management Management Management briefs* observations and QA observations and observations and QA observations and field observations QA field field observations QA field show that most pre-job observations show show that, with some observations show briefs are not that most pre-job exceptions, pre-job that pre-job briefs in acceptable. briefs are briefs are acceptable. general are acceptable. acceptable.
| |
| Percent of CRs Less than 13% of Between 13-15% Between 15-17% of More than 17% of per person per individuals wrote CRs of individuals individuals wrote CRs individuals wrote group" during the past 30 wrote CRs during during the past 30 CRs during the past days. the past 30 days. days. month.
| |
| Number of The number of The number of The number of The number of programmatic programmatic CRs programmatic CRs programmatic CRs programmatic CRs CRs indicates that indicates that most indicates that a large indicates that individuals in general individuals are majority of individuals individuals in are reluctant to write willing to write CRs are willing to write general are willing CRs on programmatic on programmatic CRs on to write CRs on and management and management programmatic and programmatic and issues. issues. management issues. management issues.
| |
| Program and >0.50 program and <0.50-.>.37 <0.37->.27 program <0.27 program process error process errors per program and and process errors and process errors rate+ 10,000 hours worked. process errors per per 10,000 hours per 10,000 hours 10,000 hours worked. worked.
| |
| worked.
| |
| Raising Management Management Management Management problems* observations, CAP and observations, CAP observations, CAP observations, CAP NQA field observations and NQA field and NQA field and NQA field show that most observations show observations show observations show individuals are not individuals that a large majority that most raising problems generally are of individuals are individuals are encountered in the raising problems raising problems raising problems field. encountered in the encountered in the encountered in the field. field. field.
| |
| 'Site wide assessment only. Data provided by Management Observation Program and NQA.
| |
| "Site wide assessment only. Data provided by Performance Improvement.
| |
| +Site wide assessment only. Data provided by Human Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 54 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 29 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Event Free Clock The event free The event free The event free The event free clock is clock is less clock is between 20 clock is 30 to 39 greater than 40 days on than 20 days on and 30 days on days on average. average.
| |
| average. average.
| |
| Industrial safety There are 11 or There are between There are 4 to 7 There are no more than performance** more OSHA 8 and 10 OSHA OSHA recordables 3 OSHA recordables per recordables per recordables per per year. year.
| |
| year. year.
| |
| Individual error The individual The individual error The individual The individual error rate rate error rate is rate is <0.<.45->.36 error rate is is <0.26 individual errors
| |
| >0.45 Individual individual errors per <0.<.36->.26 per 10,000 hours errors per 10,000 hours individual errors worked.
| |
| 10,000 hours worked. per 10,000 hours worked. worked.
| |
| Program and >0.50 program <0.50->.37 <..37->.27 <0.27 program and process error rate and process program and program and process errors per errors per process errors per process errors per 10,000 hours worked.
| |
| 10,000 hours 10,000 hours 10,000 hours worked. worked. worked.
| |
| Significant human There are more There are fewer There are fewer There were no performance than 3 significant than 3 significant than 2 significant significant human errors resulting in human human human performance errors per plant transients* performance performance errors performance year resulting in plant errors per year per year resulting in errors per year transients.
| |
| resulting in plant plant transients. resulting in plant transients. transients.
| |
| Backlog of Priority There are more There are less There are less There are less than100 procedure change than 200 open than 200 open than 150 open open Priority PCRs.
| |
| requests (PCRs)+ Priority PCRs. Priority PCRs. Priority PCRs.
| |
| Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Site wide assessment only. Data provided by Human Performance "Site wide assessment only. Data provided by Industrial Safety
| |
| +Site wide assessment only. Data provided by Quality Services
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 55 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 30 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH (continued)
| |
| Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Deficiency rate for Deficiency rate The deficiency The deficiency rate The deficiency rate for QC holds for QC hold rate for QC hold for QC holds point is QC hold points is less points is more points is less than less than 15 %. than 7 %.
| |
| than 25%. 25%.
| |
| Rework rate Rework rate is The rework rate The rework rate is The rework rate is more than 3%. is 2.5-3.0%. 2.1-2.5%. <2.0%.
| |
| Ratio of completed Less than 50% More than 50% of More than 75% of More than 90% of to scheduled of scheduled scheduled work scheduled work scheduled work orders works orders per work orders are orders are orders are are completed.
| |
| week+ completed. completed. completed.
| |
| Number of late Less than 50% More than 50% of More than 75% of More than 90% of preventive of scheduled scheduled PMs scheduled PM are scheduled PMs are maintenance (PM) PMs are are completed on completed on time. completed on time.
| |
| activities+ completed on time.
| |
| time Backlog of There are more There are There are between There are less than 134 corrective than 230 CM between 229 and 149 and 134 CM CM activities maintenance (CM) activities 150 CM activities activities outstanding.
| |
| activities+ outstanding. outstanding. outstanding.
| |
| Number of There are more There are 2-3 There is one Red There are zero Red Maintenance Rule than 3 Red Red (a)(1) (a)(1) systems. (a)(1) systems. All (a)(1) systems++ (a)(1) systems. systems. Maintenance Rule (a)(1) systems will be in monitoring This item assessed by QC only. The Deficiency Rate for QC relates to rejectable or unsatisfactory inspection attributes identified in the field by the QC Inspector during the implementation of the Order (work order). The established QC hold points are embedded within the Order as either a specific Step in the work sequence or on a standalone document such as a Weld Traveler.
| |
| -This item assessed by Maintenance only
| |
| +Site wide assessment only. Data provided by Outage Management and Work Control
| |
| ++Site wide assessment only. Data provided by Plant Engineering. Explain why acceptable if not green.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 56 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 31 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3c. CRITERIA RELATED TO RIGOROUS WORK CONTROL AND PRUDENT APPROACH (continued)
| |
| Performing activities in a quality manner is the standard ATTRIBUTE RED YELLOW WHITE GREEN Performance One significant Major plant Major plant Major plant evolutions during major plant event has evolutions have evolutions have have been performed evolutions @ occurred during a been performed been performed with successfully as plant evolution in with some some transients but planned. There are no the past month or transients or one no significant events transients or there are three or significant event during major plant significant events more transients during major plant evolutions prior to during major plant during major evolutions prior to restart. evolutions prior to plant evolutions restart. restart.
| |
| prior to restart.
| |
| Use of procedures Management Management Management Management and work orders* observations and observations and observations and observations and NQA NQA field NQA field NQA field field observations observations observations show observations show show that the vast show that most that individuals that many majority of individuals individuals are generally are using individuals are using are using procedures not using procedures or procedures or work or work orders.
| |
| procedures or work orders. orders.
| |
| work orders.
| |
| Operational transient is defined by INPO as a plant transient that occurs (reactor critical or while shutdown) and results in significant changes in primary or secondary plant parameters or results in significant changes in mechanical or electrical lineups.
| |
| Significant is defined by INPO as an event that caused or had the potential to cause an appreciable reduction in plant safety or reliability, excessive radiation exposure, the discharge of radioactivity offsite or serious harm to individuals. The significance of a particular event (including the discovery of a serious deficiency, lies in the actual or potential consequences of the event or in the likelihood that it is a precursor to a more serious event.
| |
| @ Site wide assessment only. Data provided by Operations Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| | |
| IV NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| l ~~~~~~~~~~~~~DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 57 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 32 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS Associates are comfortable in voicing opinions, issues and concerns ATTRIBUTE RED YELLOW WHITE GREEN Number of CRs per Less than 13% of Between 13-15% of Between 15-17% of More than 17% of person per group* individuals wrote CRs individuals wrote CRs individuals wrote individuals wrote during the past 30 during the past 30 CRs during the past CRs during the past days. days. 30 days. 30 days.
| |
| [Worker confidence in Surveys and/or Surveys and/or Surveys and/or Surveys and/or raising safety interviews indicate interviews indicate interviews indicate interviews indicate concerns** that less than 80% of that between 80-90% that between 90- that more than 95%
| |
| workers believe they of workers believe 95% of workers of workers believe Explain why can raise nuclear they can raise nuclear believe they can they can raise acceptable if not safety or quality safety or quality raise nuclear safety nuclear safety or green) concerns without fear concerns without fear or quality concerns quality concerns of retaliation. of retaliation. without fear of without fear of retaliation. retaliation.
| |
| Feedback from 4Cs Feedback from the Feedback from the Feedback from the Feedback from the meetings+ 4Cs meetings 4Cs meetings 4Cs meetings 4Cs meetings indicates that most indicates that more indicates that more indicates that more individuals are not than 70% of than 80% of than 90% of willing to raise individuals are willing individuals are individuals are concerns to to raise concerns to willing to raise willing to raise management. management. concerns to concerns to management. management.
| |
| Keep Improving Each month's total Each month's total Each month's total Each months total Performance (KIP) Safe behavior is 59% Safe behavior is 60% Safe behavior is Safe behavior is program++ or less. to 69%. 70% to 79%. 80% or higher.
| |
| *Site wide assessment only. Data provided by Performance Improvement
| |
| +Site wide assessment only. Data provided by Chief Operating Officer
| |
| ++Site wide assessment only. Data provided by Industrial Safety
| |
| *Site wide assessment only. Data provided by Employee Concerns Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B BP-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 58 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 33 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| Associates are comfortable in voicing opinions, issues and concerns ATTRIBUTE RED YELLOW. WHITE GREEN Pre-job briefings@ Management Management Management Management observations observations and observations and QA observations and QA and QA field QA field field observations field observations show observations observations show that, with some that pre-job briefs in show that most show that most exceptions, pre-job general are acceptable.
| |
| pre-job briefs pre-job briefs are briefs are acceptable.
| |
| are not acceptable.
| |
| acceptable.
| |
| Intra-department No formal Infrequent Formal Formal communication information sharing communication information communication structures exist and are structures exist sharing exists structures exist and consistently used to for sharing among the are occasionally used share information information sections of the to share information among the sections of among the department. among the sections the department, sections of the of the department.
| |
| department.
| |
| Quality of 4Cs surveys 4Cs surveys 4Cs surveys indicate 4Cs surveys indicate communication* indicate that indicate that more that more than 70% that more than 70% of more than 50% than 50% of of employees believe employees believe that of employees employees that communication communication from believe that the believe that from their Managers their Managers is good.
| |
| communication communication is fair, from their from their Managers is Managers is fair poor
| |
| @Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| 'Site wide assessment only. Data provided by Chief Operating Officer
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002 Tite Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 59 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 34 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| SAFETY CONSCIOUS WORK ENVIRONMENT (SCWE)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Employee Surveys and/or Surveys and/or Surveys and/or Surveys and/or awareness of interviews indicate that interviews indicate that interviews indicate interviews indicate SCWE policy* less than 80% of 80-90% of employees that 90-95% of that more than 95%
| |
| employees in the in the section are aware employees in the of employees in the (Explain why section are aware of of policy and consider it section are aware of section are aware of acceptable if not policy. a FE value. policy and consider it policy and consider it green) an FE value. an FE value and the normal way to do business.
| |
| Training on Less than 80% of Between 80-89% of Between 90-97% of More than 97% of SCWE* managers, supervisors, managers, supervisors, managers, managers, and operators have and operators have supervisors, and supervisors, and (Explain why received training on received training on operators have operators have acceptable if not SCWE. SCWE. received training on received training on green) SCWE. SCWE.
| |
| NQA interviews+ NQA interviews indicate NQA interviews indicate NQA interviews NQA interviews that less than 85% of that between 85-90% of indicate that between indicate that more (Explain why individuals are willing to individuals are willing to 90-95% of individuals than 95% of acceptable if not raise concerns to their raise concerns to their are willing to raise individuals are willing green) supervisors or ECP. supervisors or ECP. concerns to their to raise concerns to supervisors or ECP. their supervisors or ECP.
| |
| I Worker Surveys and/or Surveys and/or Surveys and/or Surveys and/or confidence in interviews indicate that interviews indicate that interviews indicate interviews indicate raising safety less than 80% of between 80-90% of that between 90-95% that more than 95%
| |
| concerns workers in the section workers in the section of workers in the of workers in the believe they can raise believe they can raise section believe they section believe they (Explain why nuclear safety or quality nuclear safety or quality can raise nuclear can raise nuclear acceptable if not concerns without fear of concerns without fear of safety or quality safety or quality green) retaliation. retaliation. concerns without fear concerns without fear of retaliation. of retaliation.
| |
| Site wide assessment only. Data provided by Nuclear Training Site wide assessment only. Data provided by Employee Concerns Program
| |
| +Site wide assessment only. Data provided by NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 60 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 35 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3d. CRITERIA RELATED TO OPEN COMMUNICATIONS (continued)
| |
| EMPLOYEE CONCERNS PROGRAM (ECP)
| |
| ATTRIBUTE RED YELLOW WHITE GREEN Ratio of concerns There are more There are more There are at least 4 There are at least 8 submitted to ECP NRC allegations ECP concerns times more ECP times more ECP vs. NRC than ECP than NRC concerns than NRC concerns than NRC allegations based concerns. allegations, allegations or there allegations or there are on three month are no NRC no NRC allegations or rolling average* allegations. ECP concerns.
| |
| Satisfaction of Less than 70% of Between 70-80 % Between 80-90% of More than 90% of employees using employees that of employees that employees that use employees that use the the ECP* use the ECP use the ECP the ECP report being ECP report being report being report being satisfied with the satisfied with the satisfied with the satisfied with the process. process.
| |
| process. process.
| |
| Complaints of There are more There are 2 There is 1 complaint There are zero breach of than 2 complaints complaints this this year. complaints this year.
| |
| confidentiality of this year. year.
| |
| ECP*
| |
| Management Employee Employee Employee surveys Employee surveys support for ECP* surveys indicate surveys indicate indicate between 80- indicate more than 90%
| |
| less than 70% of between 70-80% 90% of individuals of individuals believe (Explain why individuals of individuals believe management management supports acceptable if not believe believe supports ECP. ECP.
| |
| green) management management supports ECP. supports ECP.
| |
| Site wide assessment only. Data provided by Employee Concerns Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D BB P-V P-0002 Title Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 61 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 36 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM Persistence and urgency in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Development Less than 70% of Between 70-80 % Between 80-90% of More than 90% of Plans per applicable of applicable applicable employees applicable employees in FENOC employees in the employees in the in the section have the section have Performance section have section have completed completed development Management completed completed development plans. plans.
| |
| process development development plans. plans.
| |
| Training Training Training Training attendance Training attendance is attendance" attendance is less attendance is is between 91-98%. greater than 98%.
| |
| than 85%. between 85-90%.
| |
| Rework rate+ The rework rate is The rework rate The rework rate is The rework rate is more than 3%. is 2.5-3.0%. 2.1-2.5%. <2.0%.
| |
| Results of EAB The quality of The quality of The quality of The quality of assessments++ engineering engineering engineering products engineering products as products as products as as measure by the measured by the EAB measured by the measured by the EAB is 2.0 or less is 1.0 or less.
| |
| EAB is greater EAB is 3.0 or than 3.0. less.
| |
| Training Overall Training Overall Training Overall Training Overall Training performance performance score performance performance score performance score score per less than 60% score between between 80-90% greater than 90%
| |
| NOBP-TR- 60-80%.
| |
| 1501#
| |
| Radiation There are more There are 1-3 There is 1 radiation There are no radiation Protection than 3 radiation radiation protection event in protection events in the events @ protection events protection events the last quarter. last quarter.
| |
| in the last quarter. in the last quarter.
| |
| *.Site wide assessment only. Data provided by Nuclear Training
| |
| +This item assessed by Maintenance only
| |
| ++This item assessed by Engineering only. Data provided by Director-Nuclear Engineering
| |
| #This item assessed by Nuclear Training only.
| |
| @Site wide assessment only. Data provided by Radiation Protection. An RP event is defined as any radiological event that would be included in the NRC Performance Indicator for Radiation Safety Cornerstone.
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| | |
| ==Title:==
| |
| Revison: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I 10 Page 62 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 37 of 39 3.INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence and urgency in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Procedure Management Management Management Management compliance- observations and observations and observations and observations and NQA NQA field NQA field NQA field field observations show observations show observations observations show that the vast majority of that most show that that many individuals individuals are individuals are not individuals are complying with complying with complying with generally are procedures. procedures.
| |
| procedures. complying with procedures.
| |
| Personal Few employees in Employees in the Employees in the Employees at all levels initiative the secton section work hard section do what it in the section take routinely express to do what's takes to get the job personal initiative to why work can't be expected. done. invent methods to done or improved. achieve higher quality and greater efficiency.
| |
| Ownership Employees in the Employees in the Employees in the Most employees in the section don't section are section follow through section regularly follow through on inconsistent in and do what is asked volunteer to own/lead assigned following through of them and do what project, develop plans, commitments and to meet quality is defined within their coordinate efforts and seldom volunteer and timing of job description. see work through to for ownership. assigned completion.
| |
| _ _ _ _ _____ commitments. I
| |
| **Site wide assessment only. Data provided by Management Observation Program and NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ _________ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 63 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 38 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN Implementation Implementation Implementation of Implementation of The CAP improvements of CAP of the CAP the CAP the CAP designated for restart improvements* improvements improvements improvements for are completed and designated for designated for restart is completed associated training is (Explain why restart has not restart Is started but the associated completed.
| |
| acceptable if not started. but none are training is not green) completed. completed.
| |
| Root cause The root cause The root cause The root cause The root cause evaluation evaluation evaluation evaluation approval evaluation approval rate quality* approval rate as approval rate as rate as determined as determined by the determined by determined by the by the CARB is CARB is 90% or greater.
| |
| the CARB is less CARB is between between 75-90%.
| |
| than 50%. 50-74%.
| |
| CR category The CR category The CR category The CR category The CR category accuracy- accuracy rate is accuracy rate is accuracy rate is accuracy rate is 90% or less than 70% or between 70-80%. between 80-90%. greater.
| |
| (Explain why greater.
| |
| acceptable if not green)
| |
| CR self- Less than 80% of 80% or more of 90% or more of the 95% or more of the CRs identification the CRs the CRs originated CRs originated are originated are self-rate' originated are are self-identified. self-identified. identified.
| |
| self-identified.
| |
| Employee Employee Employee surveys Employee surveys Employee surveys survey+ surveys indicate indicate that indicate that indicate that less than that more than between 10-5% of between 5-2% of 2% of individuals are not (Explain why 10 % of individuals are not individuals are not willing to use the CAP.
| |
| acceptable if not individuals are willing to use the willing to use the green) not willing to use CAP. CAP.
| |
| the CAP.
| |
| 'Site wide assessment only. Data provided by Performance Improvement
| |
| +Site wide assessment only. Data provided by Employee Concerns Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| I Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 64 of 94 APPENDIX A: ASSESSMENT OF SAFETY CULTURE CRITERIA Page 39 of 39
| |
| : 3. INDIVIDUALS' COMMITMENT AREA 3e. CRITERIA RELATED TO NUCLEAR PROFESSIONALISM (continued)
| |
| Persistence in identification and resolution of problems is prevalent ATTRIBUTE RED YELLOW WHITE GREEN NQA interviews* NQA interviews NQA interviews NQA interviews NQA interviews indicate that indicate that indicate that between - indicate that less than more than 10% between 10-5% of 5-2% of individuals are 2 % of individuals are of individuals are individuals are not not willing to use the not willing to use the not willing to use willing to use the CAP. CAP.
| |
| the CAP. CAP.
| |
| Timeliness of Less than 50% of Between 50-74% Between 75-89%of More than 90% of corrective actions corrective actions of corrective corrective actions for corrective actions for for section CRs actions for section section CRs are section CRs are Does not include are completed on CRs are completed on completed on CRs or CAs linked schedule without completed on schedule without schedule without to P3 activities extensions. schedule without extensions. extensions.
| |
| extensions.
| |
| *Site wide assessment only. Data provided by NQA
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ _________ _____ ____ ____D B B P-V P-0002 Titie: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 65 of 94 ATTACHMENT 10: SAFETY CULTURE ASSESSMENT CRITERIA MATRIX U-Site wide Plant Operations RP Chemistry Outage MgmtN~ork Control Maintenance Training - _ - - - -
| |
| Safety Engineering - _ _ - - =
| |
| Plant Enaineerina Design Enaineerina Project Manaaement _ - - _ -
| |
| RRT Reactor Eng.
| |
| Support Services Regulatory Affairs Quality Services Security Other Sections QA/QC ECP Supply Chain
| |
| [0 Client Services - _ - -- _ _
| |
| Business Services ___
| |
| Human Resources _
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I 10 Page 66 of 94 ATTACHMENT 11: SAFETY CULTURE ATTRIBUTE ASSESSMENT MATRIX
| |
| : 1. Policy Commitment Area:
| |
| la. Criteria Related to Statement of Safety Policy Item Color Policy statement on Safety Culture Policy statement on SCWE Making employees aware of policy statements Employee understanding of policies Worker understanding of responsibility to raise safety concerns Total for a lColors lb. Criteria Related to Management Values Item Color Corporate values Statement of mission, vision and values FENOC Business Plan
| |
| ]Total for 1lb - Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 67 of 94 1c. Criteria Related to Resources Item Color Adequacy of management resources Adequacy of personnel resources Adequacy of funding Adequacy of tools, material and equipment to complete site tasks Adequacy of tools, material and equipment to complete Section tasks Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Total for c itColor T
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE .10 I Page 68 of 94 1d. Criteria Related to Self-Assessment Item Color Use of NQA to supplement the self assessment process Self assessments in accordance with NOBP-LP-2Q04 Section Performance Indicators Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Personnel Performance Appraisals ITotal for 1Id itColor
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ______DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 69 of 94 le. Criteria Related to Independent Oversight Item Color Nuclear Committee of the Board of Directors Company Nuclear Review Board Nuclear Quality Assurance Learning from the experience of the industry Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Total for 1e l color: ]
| |
| ITotal for 1 IColor:
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberB
| |
| | |
| ==Title:==
| |
| Revlslon: P age RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I 10 Page 70 of 94
| |
| : 2. Managers' Commitment Area 2a. Criteria Related to Commitment to Safety Item Color Management observations performed as scheduled with coaching l Management observations are self critical Management emphasis on safety to employees Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Leadership in Action
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 71 of 94 Item Color Problem Solving Decision making Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Improvement in safety margin Plant activities receive proper management attention and safety focus Operations Radiation Protection Chemistry Outage Management and Work Control
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 72 of 94 Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team 4-Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources
| |
| [Total for 2a lColor:
| |
| 2b. Criteria Related to Roles and Teamwork Item Color Understanding that safety is highest priority Program Ownership Ownership of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE NumberDBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 73 of 94 Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP 4
| |
| Supply Chain Client Services Business Services Human Resources I l Item Color Ownership of Engineering products as measured by EAB Effectiveness of supervision of Individuals Intra-department teamwork and alignment Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| Title Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I 10 Page 74 of 94 Quality Assurance
| |
| +
| |
| ECP Supply Chain Client Services Business Services Human Resources Item Color Expectations Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Trust, openness and focused commitment Clear goals and priorities Operations
| |
| | |
| I NUCLEAR OPERATING BUSINESS PRACTICE Number:BBP-VP-0002 Title Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page75of94 Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services I-Business Services Human Resources Item Color Input and Involvement Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs
| |
| | |
| I NUCLEAR OPERATING BUSINESS PRACTICE Numer:DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 76 of 94 Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Total for 2b Color:
| |
| 2c. Criteria Related to Ownership and Accountability Item Color Performance Reviews in accordance with FENOC Performance Management Process Development plans Readiness Reviews Worker understanding of responsibility to raise safety concerns Willingness to raise safety concerns SRO reviews for Operability are performed in timely manner System assessments NQA field assessments
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ___ ____ ____ ____ ____ ___ ____ ____ ___D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 77 of 94 Management observations leading to coaching Timeliness of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources ITotal fr2c IColor:I 2d. Criteria Related to Training and Qualification Item Color IRestart training __l Initial Operator training Item Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number: I
| |
| ________ ____ ___ ___ ____ ____ ___ ____ ___D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 78 of 94 Requalification training Operability determination training Operations Engineering Training on SCWE Training on decision making process Training on standards and expectations Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 79 of 94 Continuing training identified by Curriculum Review Committee I
| |
| { Totalfor 2d IColor 2e. CriteriaRelated to Commitment to Continuous Improvement Item l Color Improvements n management staffing Corrective Action Review Board Engineering Assessment Board Benchmarking against industry standards Management observations Temporary modifications Number of operator work arounds Number of Control Room deficiencies Training on SCWE Licensed operator pipeline Use of SCWERT Effectiveness of SCWERT In avoiding discrimination claims
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:DBP-VP002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 80 of 94 Effectiveness in avoiding NRC or ECP substantiated discrimination claims I Total for 2e IColor: It 2f. Criteria Related to Commitment to Cross-Functional Work Management and Communication Item Color Cross functional teamwork Department interfaces Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Item Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 81 of 94 Performance to schedule Interdepartmental communication Interdepartmental problem solving and decision making Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Systemic learning Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| _____________________ .DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 82 of 94 Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Incorporating Industry Operating Experience ITotal for 2f Colors 2g. Criteria Related to Commitment to Creating an Environment of Engagement and Commitment Item Color FENOC values, basic principles and leadership strategies Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services
| |
| | |
| i NUCLEAR OPERATING BUSINESS PRACTICE Number: I
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 83 of 94 Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Item Color Quality of management and employee relationships Organizational commitment and shared success criteria Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Performance reviews in accordance with FENOC Performance Management Process
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 Tite: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE _ 10 Page 84 of 94 FENOC Performance Management Process Development plans II
| |
| >Total for 2I Color:
| |
| IVTotal for 2 Color: I
| |
| : 3. Individuals' Commitment Area 3a. Criteria Related to Drive for Excellence Item l olor Maintenance Rule (a)(1) systems Number of Operator workarounds Number of Control Room deficiencies Number of temporary modifications Individual Error Rate Percent of self-identified Condition Reports Number of open Condition Report evaluations Engineering Assessment Board index
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: lPage RESTART READINESS REVIEW EXTENDED P PLANT OUTAGE 10 I Page 85 of 94 Performance during major plant evolutions Addressing Operating Experience lTotal fr3a Tcolor:I 3b. Criteria Related to Questioning Attitude Item Color Quality of pre-job briefs Percent of CRs per person per group Number of programmatic CRs Program and process error rate Raising problems
| |
| [Total for 3b Color:
| |
| 3c. Criteria Related to Rigorous work Control and Prudent Approach Item I Color IEvent Free Clock I IIndustrial Safety Performance
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 86 of 94 Individual Error Rate Program and process error rate Significant human performance errors result in plant transients Backlog of Priority Procedure Change Requests Deficiency rate for QC holds (QC only)
| |
| Rework Rate (Maintenance)
| |
| Ratio of completed to scheduled work orders per week Number of late preventive maintenance activities Backlog of corrective maintenance activities Number of Maintenance Rule (a)(1) systems Performance during major plant evolutions Use of procedures and work orders ITotal for 3c ]Colors 3d. Criteria Related to Open Communications Item I Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ ____ ____ ____ ____D BB P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 87 of 94 Number of CRs per person per group LWorker confidence in raising safety concerns Feedback from 4Cs meetings Keep Improving Performance program Pre-job briefings Intra-department information sharing Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Item Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number: DBBP-VP-0002 TiUe: Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 88 of 94 Quality of Communication Employee awareness of SCWE policy Training on SCWE NQA interviews Worker confidence In raising safety concerns Ratio of concerns submitted to ECP vs. NRC allegations Satisfaction of employees using ECP Complaints of breach of confidentiality in ECP Management support for ECP Total for 3d ColorI 3e. Criteria Related to Nuclear Professionalism Item Color FENOC Performance Management Process development plans Training attendance Item Color Rework Rate (Maintenance)
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ _________ _____ ____ ____D B B P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 89 of 94 Results of EAB assessments Training performance score per NOBP-TR-1 501 Radiation Protection Events Procedure Compliance Personal initiative Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety:
| |
| Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Item Color Ownership Operations
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 90 of 94 Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain-Client Services Business Services Human Resources Implementation of CAP Improvements Root cause evaluation quality CR category accuracy CR self identification rate Employee Survey NQA interviews Item Color
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002 TiUe: Revision: age RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 91 of 94 Timeliness of corrective actions Operations Radiation Protection Chemistry Outage Management and Work Control Maintenance Training Safety Plant Engineering Design Engineering Project Management Rapid Response Team Reactor Engineering Quality Services Regulatory Affairs Security Quality Assurance ECP Supply Chain Client Services Business Services Human Resources Total for 3e }Color }
| |
| [Total for 3 lColori
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| DBBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE I 10 Page 92 of 94 ATTACHMENT 11: PROGRAM OWNERSHIP LIST Page of 3 Phase I Programs (Taken from NG-EN-00386, Rev. 0. Attachment 1) 65 total 10CFR50.59 Program Air Operated Valve (AOV) Reliability Program Appendix R and Safe Shutdown Program ASME Section Xl Repair, Replacement, and Modification Program Auxiliary Chemistry Control Program Breaker Reliability Program Calculation Control Program Check Valve Reliability Program Chemistry Measuring & Test Equipment Program Commercial Grade Dedication Program Commitment Management Program (TERMS)
| |
| Configuration Management Program Containment Leakage Rate Test Program (Appendix J)
| |
| Control of Work Controlled Materials Program Core Design & Reload Analysis Program Corrosion-Erosion Monitoring and Analysis Program (CEMAP)
| |
| Engineered Spare Parts List Program Environmental Qualification (EQ) Program Equipment Modernization Program Fire Protection Program Foreign Material Exclusion Program Fuel Reliability Program Heat Exchanger Monitoring Program
| |
| | |
| I NUCLEAR OPERATING BUSINESS PRACTICE Number:
| |
| ____ _____ ____ ____D BB P-V P-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 93 of 94 ATTACHMENT 11: PROGRAM OWNERSHIP LIST Page 2 of 3 Hydraulic Snubber Program Infrared Thermography Program Inservice Test Program Leak Reduction Program Locked Valve Program Lubrication Monitoring and Analysis Program Maintenance Rule Program Material Receipt Inspection Program Measuring & Test Equipment Program Meteorological Monitoring Program Motor Operated Valve (MOV) Reliability Program Motor Reliability Program On-line Risk Management Program Operability Determination Program Post Accident Sampling Program Predictive Maintenance Program Preventive Maintenance Program Primary Water Chemistry Monitoring & Control Program Procurement Program Quality Classification Control Program Radioactive Effluent Controls Program Radioactive Materials Program Reactivity Management Program Safety Tagging Program Secondary Water Chemistry Monitoring & Control Program
| |
| | |
| NUCLEAR OPERATING BUSINESS PRACTICE Number:DBP-VP-0002
| |
| | |
| ==Title:==
| |
| Revision: Page RESTART READINESS REVIEW EXTENDED PLANT OUTAGE 10 Page 94 of 94 ATTACHMENT 11: PROGRAM OWNERSHIP LIST Page 3 of 3 Service Water System Reliability Program Severe Accident Management Program Shelf Life Evaluation Program Shutdown Risk Management Program Software Control Program Steam Generator Program Management Temporary Leak Sealing Temporary Modification Process Test Control Program Thermal Performance Monitoring Program Transient Counting Valve Packing Program Vendor Manual Control Program Ventilation Filter Testing Program Vibration Analysis Program Welding Implementation & Qualification Program Phase 2 Programs taken from the Davis-Besse IMC 0350 Restart List)
| |
| Corrective Action Program Operating Experience Program Boric Acid Corrosion Control Program Reactor Coolant System Unidentified Leakage Monitoring Program In-Service Inspection Program Modification Control Program}}
| |
