IR 05000266/2017008: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(3 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML17170A097
| number = ML17039B018
| issue date = 06/16/2017
| issue date = 02/08/2017
| title = NRC Temporary Instruction 2515/191, Mitigation Strategies, Spent Fuel Pool Instrumentation and Emergency Preparedness Inspection Report 05000266/2017008; 05000301/2017008
| title = Information Request to Support Upcoming Temporary Instruction 2515/191 Inspection at Point Beach Nuclear Plant, Units 1 and 2 - Inspection Report 05000266/2017008; 05000301/2017008
| author name = Stone A
| author name = Stone A
| author affiliation = NRC/RGN-III/DRP/TSS
| author affiliation = NRC/RGN-III/DRP/TSS
Line 8: Line 8:
| addressee affiliation = NextEra Energy Point Beach, LLC
| addressee affiliation = NextEra Energy Point Beach, LLC
| docket = 05000266, 05000301
| docket = 05000266, 05000301
| license number = NPF-024, NPF-027
| license number = DPR-024, DPR-027
| contact person =  
| contact person =  
| document report number = IR 2017008
| document report number = IR 2017008
| document type = Inspection Report, Letter
| document type = Inspection Plan, Letter
| page count = 15
| page count = 5
}}
}}


Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 June 16, 2017 Mr. Robert Coffey Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516 SUBJECT: POINT BEACH NUCLEAR POWER PLANT-NRC TEMPORARY INSTRUCTION 2515/191, MITIGATION STRATEGIES, SPENT FUEL POOL INSTRUMENTATION AND EMERGENCY PREPAREDNESS INSPECTION REPORT 05000266/2017008; 05000301/2017008
{{#Wiki_filter:February 8, 2017
 
==SUBJECT:==
INFORMATION REQUEST TO SUPPORT UPCOMING TEMPORARY INSTRUCTION 2515/191 INSPECTION AT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2INSPECTION REPORT 05000266/2017008; 05000301/2017008


==Dear Mr. Coffey:==
==Dear Mr. Coffey:==
On May 12, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed Temporary Instruction (TI) 2515/191, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans" inspection at your Point Beach Nuclear Power Plant, Units 1 and 2. On May 12, 2017, the NRC inspection team discussed the results of this inspection with you and other members of your staff. The enclosed report represents the results of this inspection.
This letter is to request information to support our inspection of the Implementation of Mitigating Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communications/Staffing/Multi-Unit Dose Assessment Plans beginning May 8, 2017, at your Point Beach Nuclear Plant, Units 1 and 2. This inspection will be performed in accordance with the U.S. Nuclear Regulatory Commission (NRC) Temporary Instruction 2515/191.


The inspection examined activities conducted un der your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commission's rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station
In order to minimize the impact that the inspection has on the site and to ensure a productive inspection, we have enclosed a list of documents requested for the inspection. Please provide this information prior to April 21, 2017. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection. Insofar as possible, this information should be provided electronically to the lead inspector.


personnel.
The lead inspector for this inspection is Dr. Stuart Sheldon. We understand that our primary contact for this inspection is Ms. Lori Christensen of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at (630) 829-9727 or via e-mail at Stuart.Sheldon@nrc.gov.


The NRC inspectors did not identify any findings or violations of more than minor significance during this inspection. This letter, its enclosure, and your response, (if any), will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding."
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150 0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number. In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter, its enclosure, and your response, (if any), will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal, privacy or proprietary information so that it can be made available to the Public without redaction.


Sincerely,
Sincerely,
/RA/
/RA/  
Ann Marie Stone, Team Leader Technical Support Staff  
 
Ann Marie Stone, Team Lead Technical Support Staff Division of Reactor Projects
 
Docket Nos: 50-266; 50-301 License Nos: DPR-24; DPR-27
 
Enclosure:
Requested for Information to Support Temporary Instruction 2515/191 IR 05000266/2017008; 05000301/2017008 cc: Distribution via LISTSERV
 
Enclosure REQUESTED INFORMATION TO SUPPORT TEMPORARY INSTRUCTION 2515/191 INSPECTION REPORT 05000266/2017008; 05000301/2017008


Division of Reactor Projects Docket Nos. 50-266; 50-301 License Nos. NPF-24, NPF-27
Please provide the following information on a compact disc or another form of electronic media, if possible. For requested lists please provide the information, if possible, in a sortable Excel spreadsheet format. For the purposes of this document request, FLEX will mean any item, SSC, procedure, calculation or document that was part of the implementation of Mitigating Strategies, or Spent Fuel Pool Instrumentation (SFPLI) orders and emergency preparedness communications/staffing and multi-unit dose assessment.


Enclosure: IR 05000266/2017008; 05000301/2017008 cc: Distribution via LISTSERV
1. A current copy of the FIP and any documentation to or from the NRC related to the FIP.


=SUMMARY=
Please include any changes to the FIP since submittal to the NRC.
Inspection Report 05000266/2017008; 05000301/2017008, 05/08/2017 - 05/12/2017,  Point Beach Nuclear Power Plant Units 1 and 2; Temporary Instruction 2515/191


Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans. This inspection was performed by a resident inspector and three U.S. Nuclear Regulatory Commission (NRC) regional inspectors. No findings of significance or violations of NRC requirements were identified during this inspection. The significance of inspection findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter 0609, "Significance Determination Process," dated April 29, 2015. Cross-cutting aspects are determined using Inspection Manual Chapter (IMC) 0310, "Aspects Within the Cross-Cutting Areas," dated December 4, 2014. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," dated July 2016.
2. A listing of any changes to the FIP since issuance of the NRC Safety Evaluation Report.


===NRC-Identified and Self-Revealing Findings===
3. A copy of your communications and staffing assessments for responding to a beyond design basis external event.


None.
4. A listing of CAP items related to implementation of FLEX, maintenance of the FLEX program and equipment, modifications related to FLEX, and training related to FLEX.


3
5. A current copy of the SAFER response plan.


=REPORT DETAILS=
6. A copy of any audits related to your preparation for this inspection as well as any related to the implementation or maintenance of FLEX.


==OTHER ACTIVITIES==
7. A current copy of administrative procedure(s) for the CAP, modification program, maintenance of FLEX equipment program, operations procedure writing and implementing, and top-level documents for the work control programs, and work scheduling programs. If FLEX related procedures such as FSGs or the Final Integrated Plan (FIP) are maintained under a different process please include copies of those procedures. Include procedures for configuration control of FLEX documents.
{{a|4OA5}}
==4OA5 Other Activities (TI 2515/191) The objective of Temporary Instruction (TI) 2515/191, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency==


Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans," is to verify the licensee has adequately implemented the mitigation strategies as described in the licensee's Final Integrated Plan Revision 0 (ADAMS Accession No. ML15350A085), and the NRC's safety evaluation (ADAMS Accession No. ML16241A000) and to verify the licensee installed reliable water-level measurement instrumentation in their spent fuel pool. The purpose of this TI was also to verify the licensee had implemented Emergency Preparedness (EP) enhancements as described in their site-specific submittals and NRC safety assessments, including multi-unit dose assessment capability and enhancements to ensure staffing is sufficient and communications can be maintained during such an event. The inspection also verifies plans for complying with NRC Orders EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for  Beyond-Design-Basis External Events (ADAMS Accession No. ML12054A736) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation (ADAMS Accession No. ML12054A679) are in place and are being implemented by the licensee. Additionally, the inspection verified implementation of staffing and communications information provided in response to the March 12, 2012, request for information letter and multiunit dose assessment information provided per COMSECY-13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons Learned, dated March 27, 2013, (ADAMS Accession No. ML12339A262). The inspectors discussed the plans and strategies with plant staff, reviewed documentation, and where appropriate, performed plant walk downs to verify the strategies could be implemented as stated in the licensee's submittals and the NRC  staff prepared safety evaluation. For most strategies, this included verification that the strategy was feasible, procedures and/or guidance had been developed, training had been provided to plant staff, and required equipment had been identified and staged.
8. A current copy of the Emergency Operating Procedures, Abnormal Operating Procedures, Off-Normal Procedures and Flex Support Guidelines. Please have available the annunciator response procedures. Also include Station Blackout related procedures if they are separate from the above.


Specific details of the team's inspection activities are described in the following sections. This inspection closes TI 191 for the Point Beach facility.
9. A current copy of your outage planning procedures including forced outage planning procedures related to FLEX implementation. For example, procedures for implementation of FLEX in shutdown modes.


===.1 Mitigation Strategies for Beyond-Design Basis External Events===
10. FLEX related training documents, aids, and records, including presentations and videos.


====a. Inspection Scope====
Include training on SFPLI maintenance and operations. (Ref. NEI 12-06 Section 11.6)  
The inspectors examined the licensee's established guidelines and implementing procedures for the beyond-design basis mitigation strategies. The inspectors assessed how the licensee coordinated and documented the interface/transition between existing off-normal and emergency operating procedures with the newly developed mitigation strategies. The inspectors selected a number of mitigation strategies and conducted plant walk downs with licensed operators and responsible plant staff to assess:  the adequacy and completeness of the procedures; familiarity of operators with the procedure objectives and specific guidance; staging and compatibility of equipment; 4 and the practicality of the operator actions prescribed by the procedures, consistent with the postulated scenarios. The inspectors verified a preventive maintenance program had been established for  the Diverse and Flexible Coping Strategies (FLEX) portable equipment and periodic equipment inventories were in place and being conducted. Additionally, the inspectors examined the introductory and planned periodic/refresher training provided to the Operations staff most likely to be tasked with implementation of the FLEX mitigation strategies. The inspectors also reviewed the introductory and planned periodic training provided to the Emergency Response Organization personnel. Documents reviewed are listed in the attachment. b. Assessment Based on samples selected for review, the inspectors verified the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittal(s) and the associated safety evaluation and determined the licensee  is generally in compliance with NRC Order EA-12-049. The inspectors verified the licensee satisfactorily:
* developed and issued FLEX Support Guidelines (FSG) to implement the FLEX strategies for postulated external events;
* integrated their FSGs into their existing plant procedures such that entry into and departure from the FSGs were clear when using existing plant procedures;
* protected FLEX equipment from site-specific hazards;
* developed and implemented adequate testing and maintenance of FLEX equipment to ensure their availability and capability;
* trained their staff to assure personnel proficiency in the mitigation of  beyond-design basis events; and
* developed the means to ensure the necessary off-site FLEX equipment would be available from off-site locations. The inspectors verified non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program as appropriate.


===.2 Spent Fuel Pool Instrumentation===
11. A listing of plant modifications related to FLEX along with a copies of the spent fuel pool instrumentation modification, and EP communications modifications.


====a. Inspection Scope====
12. A listing of calculations, evaluations, and 50.59 reviews related to FLEX.
The inspectors examined the licensee's newly installed spent fuel pool instrumentation. Specifically, the inspectors verified the sensors were installed as described in the plant specific submittals and the associated safety evaluation and that the cabling for the power supplies and the indications for each channel are physically and electrically separated. Additionally, environmental conditions and accessibility of the instruments were evaluated. Documents reviewed are listed in the attachment. b. Assessment Based on samples selected for review, the inspectors determined the licensee satisfactorily installed and established control of the spent fuel pool (SFP)instrumentation as described in the plant specific submittal(s) and the associated safety 5 evaluation and determined the licensee is generally in compliance with NRC  Order EA-12-051. The inspectors verified the licensee satisfactorily:
* installed the SFP instrumentation sensors, cabling and power supplies to provide physical and electrical separation as described in the plant specific submittal(s)and safety evaluation;
* installed the SFP instrumentation display in the location, environmental conditions and accessibility as described in the plant specific submittal(s); and
* trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation. The inspectors verified non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.


====c. Findings====
13. A copy of the current FLEX strategy basis document.
No findings were identified.


===.3 Staffing and Communication Request for Information===
(Ref. NEI 12-06 Section 11.8)


====a. Inspection Scope====
14. A copy of the FLEX strategies time validation study.
Through discussions with plant staff, review of documentation and plant walk downs,  the inspectors verified the licensee has implemented required changes to staffing, communications equipment and facilities to support a multi-unit extended loss of AC power (ELAP) scenario as described in the licensee's staffing assessment and the  NRC safety assessment. The inspectors also verified the licensee has implemented  multi-unit dose assessment (including releases from spent fuel pools) capability using the licensee's site-specific dose assessment software and approach as described in the licensee's multi-unit dose assessment submittal. Documents reviewed are listed in the


attachment. b. Assessment The inspectors reviewed information provided in the licensee's multi-unit dose submittal and in response to the NRC's March 12, 2012, request for information letter and verified that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3 response to a large scale natural emergency event that results in an ELAP to all site units and impedes access to the site. The inspectors verified the following:
15. A copy of the haul path liquefaction analysis. (Ref. NEI 12-06 Section 5.3.2.1)  
* the licensee satisfactorily implemented required staffing change(s) to support a  multi-unit ELAP scenario;
* EP communications equipment and facilities are sufficient for dealing with a  multi-unit ELAP scenario; and
* the licensee implemented multi-unit dose assessment capabilities (including releases from spent fuel pools) using the licensee's site-specific dose assessment software and approach.


6 The inspectors verified non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
16. A copy of performance verification tests for FLEX equipment.
{{a|4OA6}}
==4OA6 Management Meeting==


===.1 Exit Meeting Summary On May 12, 2017, the inspectors presented the inspection results to Mr. R. Coffey===
(Ref. NEI 12-06 Section 11.5.1)
and other members of the licensee's staff. The licensee acknowledged the issues presented. The inspectors confirmed none of the potential report input discussed was considered proprietary. ATTACHMENT: 


=SUPPLEMENTAL INFORMATION=
17. A listing of Preventive Maintenance (PM) tasks for FLEX equipment, SFPLI, and EP communications equipment installed for FLEX response. Include a copy of the most recent PMs (work orders) for this equipment. (Ref. NEI 12-06 Section 11.5.2)


==KEY POINTS OF CONTACT==
18. Current copies of SFPLI maintenance procedures.


Licensee
19. Documents and procedures related to your multi-unit dose assessment capability.
: [[contact::R. Craven]], Plant General Manager
: [[contact::J. Wilson]], Operations Director
: [[contact::B. Woyak]], Licensing Manager
: [[contact::B. Fromm]], Projects Site Manager
: [[contact::D. Shepherd]], Design Engineering Manager
: [[contact::E. Schmidt]], Programs Engineering Manager
: [[contact::R. Seizert]], Emergency Preparedness Manager
: [[contact::R. Welty]], Radiation Protection Manager
: [[contact::D. Peterson]], Training Manager
: [[contact::E. Schultz]], Operations Assistant Manager
: [[contact::M. Holzmann]], Operations Assistant Manager
: [[contact::M. Wilcox]], Online Manager
: [[contact::L. Christensen]], Licensing Project Manager
: [[contact::C. Gerbers]], Projects Engineering Supervisor
: [[contact::S. Manthei]], Licensing Senior Engineer
: [[contact::K. Hilliker]], Emergency Preparedness Coordinator
: [[contact::A. Guenther]], Programs Engineering Senior Engineer
: [[contact::B. Griffin]], Senior Communications Specialist


U.S. Nuclear Regulatory Commission
20. A copy of the UFSAR, Technical Specifications and TS bases documents.
: [[contact::T. Hartman]], Senior Resident Inspector


==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED==
OTHER:


===Opened and Closed===
On the first day of the inspection, please provide the inspection team an overview briefing of your FIP and overall strategy.


None.
On the first day of the inspection, please provide a copy of any procedures revised after your response to this request for information.


==LIST OF DOCUMENTS REVIEWED==
In addition, the inspectors will require computer access to the corrective action program (CAP)
The following is a partial list of documents reviewed during the inspection.
database while on site.
: Inclusion on this list does not imply the NRC inspector reviewed the documents in their entirety, but rather that
}}
}}

Latest revision as of 14:44, 9 January 2025

Information Request to Support Upcoming Temporary Instruction 2515/191 Inspection at Point Beach Nuclear Plant, Units 1 and 2 - Inspection Report 05000266/2017008; 05000301/2017008
ML17039B018
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 02/08/2017
From: Ann Marie Stone
NRC/RGN-III/DRP/TSS
To: Coffey R
Point Beach
References
IR 2017008
Download: ML17039B018 (5)


Text

February 8, 2017

SUBJECT:

INFORMATION REQUEST TO SUPPORT UPCOMING TEMPORARY INSTRUCTION 2515/191 INSPECTION AT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2INSPECTION REPORT 05000266/2017008; 05000301/2017008

Dear Mr. Coffey:

This letter is to request information to support our inspection of the Implementation of Mitigating Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communications/Staffing/Multi-Unit Dose Assessment Plans beginning May 8, 2017, at your Point Beach Nuclear Plant, Units 1 and 2. This inspection will be performed in accordance with the U.S. Nuclear Regulatory Commission (NRC) Temporary Instruction 2515/191.

In order to minimize the impact that the inspection has on the site and to ensure a productive inspection, we have enclosed a list of documents requested for the inspection. Please provide this information prior to April 21, 2017. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection. Insofar as possible, this information should be provided electronically to the lead inspector.

The lead inspector for this inspection is Dr. Stuart Sheldon. We understand that our primary contact for this inspection is Ms. Lori Christensen of your organization. If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at (630) 829-9727 or via e-mail at Stuart.Sheldon@nrc.gov.

This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150 0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number. In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter, its enclosure, and your response, (if any), will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal, privacy or proprietary information so that it can be made available to the Public without redaction.

Sincerely,

/RA/

Ann Marie Stone, Team Lead Technical Support Staff Division of Reactor Projects

Docket Nos: 50-266; 50-301 License Nos: DPR-24; DPR-27

Enclosure:

Requested for Information to Support Temporary Instruction 2515/191 IR 05000266/2017008; 05000301/2017008 cc: Distribution via LISTSERV

Enclosure REQUESTED INFORMATION TO SUPPORT TEMPORARY INSTRUCTION 2515/191 INSPECTION REPORT 05000266/2017008; 05000301/2017008

Please provide the following information on a compact disc or another form of electronic media, if possible. For requested lists please provide the information, if possible, in a sortable Excel spreadsheet format. For the purposes of this document request, FLEX will mean any item, SSC, procedure, calculation or document that was part of the implementation of Mitigating Strategies, or Spent Fuel Pool Instrumentation (SFPLI) orders and emergency preparedness communications/staffing and multi-unit dose assessment.

1. A current copy of the FIP and any documentation to or from the NRC related to the FIP.

Please include any changes to the FIP since submittal to the NRC.

2. A listing of any changes to the FIP since issuance of the NRC Safety Evaluation Report.

3. A copy of your communications and staffing assessments for responding to a beyond design basis external event.

4. A listing of CAP items related to implementation of FLEX, maintenance of the FLEX program and equipment, modifications related to FLEX, and training related to FLEX.

5. A current copy of the SAFER response plan.

6. A copy of any audits related to your preparation for this inspection as well as any related to the implementation or maintenance of FLEX.

7. A current copy of administrative procedure(s) for the CAP, modification program, maintenance of FLEX equipment program, operations procedure writing and implementing, and top-level documents for the work control programs, and work scheduling programs. If FLEX related procedures such as FSGs or the Final Integrated Plan (FIP) are maintained under a different process please include copies of those procedures. Include procedures for configuration control of FLEX documents.

8. A current copy of the Emergency Operating Procedures, Abnormal Operating Procedures, Off-Normal Procedures and Flex Support Guidelines. Please have available the annunciator response procedures. Also include Station Blackout related procedures if they are separate from the above.

9. A current copy of your outage planning procedures including forced outage planning procedures related to FLEX implementation. For example, procedures for implementation of FLEX in shutdown modes.

10. FLEX related training documents, aids, and records, including presentations and videos.

Include training on SFPLI maintenance and operations. (Ref. NEI 12-06 Section 11.6)

11. A listing of plant modifications related to FLEX along with a copies of the spent fuel pool instrumentation modification, and EP communications modifications.

12. A listing of calculations, evaluations, and 50.59 reviews related to FLEX.

13. A copy of the current FLEX strategy basis document.

(Ref. NEI 12-06 Section 11.8)

14. A copy of the FLEX strategies time validation study.

15. A copy of the haul path liquefaction analysis. (Ref. NEI 12-06 Section 5.3.2.1)

16. A copy of performance verification tests for FLEX equipment.

(Ref. NEI 12-06 Section 11.5.1)

17. A listing of Preventive Maintenance (PM) tasks for FLEX equipment, SFPLI, and EP communications equipment installed for FLEX response. Include a copy of the most recent PMs (work orders) for this equipment. (Ref. NEI 12-06 Section 11.5.2)

18. Current copies of SFPLI maintenance procedures.

19. Documents and procedures related to your multi-unit dose assessment capability.

20. A copy of the UFSAR, Technical Specifications and TS bases documents.

OTHER:

On the first day of the inspection, please provide the inspection team an overview briefing of your FIP and overall strategy.

On the first day of the inspection, please provide a copy of any procedures revised after your response to this request for information.

In addition, the inspectors will require computer access to the corrective action program (CAP)

database while on site.