IR 05000298/2018010: Difference between revisions

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{{Adams
{{Adams
| number = ML18128A074
| number = ML18023A110
| issue date = 05/08/2018
| issue date = 01/23/2018
| title = Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans - Inspection Report 05000298/2018010
| title = CNS - Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans (05000298/2018010) and Request
| author name = Kozal J
| author name = Kozal J
| author affiliation = NRC/RGN-IV/DRP/RPB-C
| author affiliation = NRC/RGN-IV/DRP/RPB-C
Line 9: Line 9:
| docket = 05000298
| docket = 05000298
| license number = DPR-046
| license number = DPR-046
| contact person = Kozal J
| contact person = Miller G
| document report number = IR 2018010
| document report number = IR 2018010
| document type = Inspection Report, Letter
| document type = Inspection Plan, Letter
| page count = 14
| page count = 7
}}
}}


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=Text=
=Text=
{{#Wiki_filter:May 8, 2018 Mr. John Dent, Jr.
{{#Wiki_filter:January 23, 2018


Vice President-Nuclear and CNO Nebraska Public Power District Cooper Nuclear Station 72676 648A Avenue P.O. Box 98 Brownville, NE 68321 SUBJECT: COOPER NUCLEAR STATION - INSPECTION OF THE IMPLEMENTATION OF MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/
==SUBJECT:==
STAFFING/MULTI-UNIT DOSE ASSESSMENT PLANS - INSPECTION REPORT 05000298/2018010
COOPER NUCLEAR STATION - NOTIFICATION OF NRC INSPECTION OF THE IMPLEMENTATION OF MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/ STAFFING/MULTI-UNIT DOSE ASSESSMENT PLANS (05000298/2018010) AND REQUEST FOR INFORMATION


==Dear Mr. Dent:==
==Dear Mr. Dent:==
On March 15, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed the onsite portion of this inspection at your Cooper Nuclear Station. On April 16, 2018, the NRC inspectors discussed the results of this inspection with Mr. J. Kalamaja, General Manager of Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
staff will conduct a mitigation strategies for beyond-design-basis external events, spent fuel pool instrumentation, and emergency preparedness enhancements inspection at the Cooper Nuclear Station, from March 12-16, 2018. The inspection will consist of two reactor inspectors from the NRCs Region IV office, one reactor inspector from the NRCs Region III office, plus one of the assigned Resident Inspectors at the Cooper Nuclear Station for one week. The inspection will be conducted in accordance with the NRCs Temporary Instruction 2515/191, Inspection of the Implementation of Mitigating Strategies and Spent Fuel Pool Instrumentation Orders, and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans.


The inspection examined activities conducted under 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, and Multi-Unit Dose Assessment Plans, your compliance with the Commissions 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 personnel.
Experience has shown that this inspection is resource intensive both for the NRC inspectors and licensee staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection activity. Please note that the documents are requested to be provided by February 23, 2018.


NRC inspectors documented one finding of very low safety significance (Green) in this report.
During the onsite inspection, inspectors will verify that plans for complying with NRC Orders EA-12-049 and EA-12-051 are in place and are being implemented. Inspectors will also verify the establishment of staffing and communications plans provided in response to the March 12, 2012, request for information letter, and multi-unit 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. These plans and information were provided in the site specific submittals, which were subsequently reviewed by the NRC staff for understanding and documented in the NRCs plant safety evaluations (SEs) and safety assessments. Therefore, appropriate personnel knowledgeable of the stations FLEX strategies, spent fuel pool instrumentation, and emergency preparedness enhancements should be available to support the inspectors at the site during the inspection. We have discussed the schedule for this inspection activity with your staff and understand that our regulatory contact for this inspection will be Brenda Kirkpatrick of your licensing organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Michael H. Stafford, by telephone at 402-825-3371 or by e-mail at Michael.Stafford@nrc.gov.


The finding did not involve a violation of NRC requirements.
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.


If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC resident inspector at the Cooper Nuclear Station. Jr. 2 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.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


Sincerely,
Sincerely,
/RA/
/RA/  
Jason W. Kozal, Chief Project Branch C Division of Reactor Projects Docket: 50-298 License: DPR-46 Enclosure:
Inspection Report 05000298/2018010 w/Attachment:
Documents Reviewed


U.S. NUCLEAR REGULATORY COMMISSION
Jason W. Kozal, Branch Chief Project Branch C Division of Reactor Projects


==Inspection Report==
Dockets: 50-298 Licenses: DPR-46  
Docket Number: 05000298 License Number: DPR-46 Report Number: 05000298/2018010 Enterprise Identifier: I-2018-010-0017 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: Brownville, Nebraska Inspection Dates: March 12, 2018 to April 16, 2018 Inspectors: M. Stafford, Resident Inspector - Cooper (Team Leader)
R. Alexander, Sr. Project Engineer - Region IV J. Mateychick, Sr. Reactor Inspector - Region IV S. Sheldon, Project Engineer - Region III Approved By: Jason Kozal Chief, Project Branch C Division of Reactor Projects


Enclosure
Enclosure:
FLEX Strategies, Spent Fuel Pool Instrumentation, & EP Enhancements Inspection Request for Information
 
Enclosure Request for Information FLEX Strategies, Spent Fuel Pool Instrumentation, & EP Enhancements Inspection Cooper Nuclear Station
 
Inspection Report:
05000298/2018010
 
Inspection Dates:
 
March 12 - 16, 2018
 
Inspection Procedure:
Temporary Instruction 2515/191, Inspection of the Implementation of Mitigating Strategies and Spent Fuel Pool Instrumentation Orders, and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans
 
Inspectors:
 
Michael H. Stafford, Team Lead, CNS Resident Inspector
 
Ryan D. Alexander, Sr. Project Engineer, Region IV
 
John M. Mateychick, Sr. Reactor Inspector, Region IV


=SUMMARY=
Stuart N. Sheldon, Project Engineer, Region III
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a Temporary Instruction 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/
Staffing/Multi-Unit Dose Assessment Plans at Cooper Nuclear Station in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-revealed findings, violations, and additional items are summarized in the table below.


List of Findings and Violations Failure to Maintain Satellite Phones in Locations That Provide Reasonable Assurance They Will Remain Available Following All Beyond Design Basis External Events Cornerstone      Significance                                      Cross-cutting Report Aspect          Section Emergency        Green                                            H.3 -          TI 2515/191 Preparedness FIN 05000298/2018010-01                                Change Closed                                            Management The NRC inspection team identified a Green finding related to the licensees failure to maintain the station satellite phones in locations that would provide reasonable assurance the phones would remain available following all beyond design basis external events.
Information Requested for the In-Office Preparation Week


=INSPECTION SCOPES=
The following information should be sent to the Region IV office in hard copy or electronic format (use of the Certrec IMS information portal is preferred), to the attention of Ryan Alexander, by February 23, 2018. Additionally, a copy of any material sent to the Region IV office should also be delivered to the resident inspectors office at Cooper Nuclear Station. The inspectors will select specific items from the information requested below and then request from your staff additional documents needed during the onsite inspection week. Also, we request that you categorize the documents in your response with the numbered list below. Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the lead inspector, and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the lead inspector as soon as possible.


Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
TI 2515/191 - Appendix A A. Provide current revision of the FLEX Final Integrated Plan (i.e., current FLEX Program Document), including any revisions since January 2017 submission to the NRC.


==OTHER ACTIVITIES==
B. Provide the FLEX Strategy Basis Document.
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 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 Inspectors verified 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 (Agencywide Documents Access and Management System (ADAMS) Accession No.


ML12056A045) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation (ADAMS 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 (ADAMS No. ML12053A340) 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 No.
C. Provide each operating, off-normal, abnormal, and/or emergency procedures where entry into one or more FLEX Support Guideline(s) are initiated.


ML12339A262).
D. Provide a list and copies of every FLEX Support Guideline (FSG) or equivalent procedure which you developed or revised to implement your mitigating strategies.
: (1) Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the Diverse and Flexible Coping Strategies (FLEX) as described in the plant specific submittals [including the Final Integrated Plan (ADAMS Accession No. ML17017A166)] and the associated safety evaluation (ADAMS No. ML17226A032) and determined that the licensee is in compliance with NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. The inspectors verified the licensee satisfactorily:
a) developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX strategies for postulated external events; b) integrated their FSGs into their existing plant procedures such that entry into and departure from the FSGs were clear when using existing plant procedures; c) protected FLEX equipment from site-specific hazards; d) developed and implemented adequate testing and maintenance of FLEX equipment to ensure their availability and capability; e) trained their staff to assure personnel proficiency in the mitigation of beyond-design basis events; and f)  developed the means to ensure the necessary off-site FLEX equipment would be available from off-site locations.
: (2) Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals [including the Final Integrated Plan (ADAMS Accession No.


ML17017A166)] and the associated safety evaluation (ADAMS No. ML17226A032) and determined that the licensee is in compliance with NRC Order NRC Order EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation.
E. Provide a list of key pieces of equipment that directly perform a FLEX mitigation strategy for core cooling, containment, and/or spent fuel pool cooling.


The inspectors verified the licensee satisfactorily :
F. Provide a listing/summaries of plant modifications completed related to the FLEX program.
a) installed the spent fuel pool (SFP) instrumentation sensors, cabling and power supplies to provide physical and electrical separation as described in the plant specific submittals and safety evaluation; b) installed the SFP instrumentation display in the location, environmental conditions and accessibility as described in the plant specific submittals; c) trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation; and d) developed and issued procedures for maintenance, testing and use of the reliable SFP instrumentation.
: (3) The inspectors reviewed information provided in the licensees multi-unit dose submittal and in response to the NRCs March 12, 2012, request for information letter (ADAMS No. ML12053A340), and verified that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3 in response to a large scale natural emergency event that results in an extended loss of all ac power to all site units and impedes access to the site. The inspectors verified the following:
a) the licensee satisfactorily implemented required staffing changes to support an extend loss of all AC power (ELAP)/loss of ultimate heat sink (LUHS) scenario; b) EP communications equipment and facilities are sufficient for dealing with an ELAP/LUHS scenario; and c) the licensee implemented multi-unit/-source dose assessment capabilities (including releases from spent fuel pools) using the licensees site-specific dose assessment software and approach.


The inspectors verified that non-compliances with requirements and standards identified during the inspection were entered into the licensee's corrective action program as appropriate.
G. Provide a listing of calculations, evaluations, and 50.59 reviews related to the FLEX program and modifications.


==INSPECTION RESULTS==
H. Applicable site specific hazards for the Cooper Nuclear Station:
Failure to Maintain Satellite Phones in Locations That Provide Reasonable Assurance They Will Remain Available Following All Beyond Design Basis External Events Cornerstone            Significance                            Cross-cutting    Report Aspect            Section Emergency              Green                                  H.3 - Change      TI 2515/191 Preparedness            FIN 05000298/2018010-01                Management Closed The NRC inspection team identified a Green finding related to the licensees failure to maintain the station satellite phones in locations that would provide reasonable assurance the phones would remain available following all beyond design basis external events.
1) Provide documents which show the locations and configuration of structure(s) which store FLEX equipment.


=====Description:=====
2) Seismic (a) Provide the travel route(s) for FLEX equipment from storage location(s) to their location(s) of use, AND evaluation(s) which demonstrate that for the potential for soil liquefaction is not of a concern for these travel route(s).
The Cooper Nuclear Station FLEX Program Document, Revision 1, Section 5.2.27, Support Functions - Communications, states, in part: NEI 12-01 provides required emergency communications capabilities during an Extended Loss of AC Power (ELAP)Satellite phones are credited for off-site communicationDocking stations and remote antennas have been installed to allow use of the satellite phones from inside buildings.


NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities, Revision 0, Section 4.5, Equipment Location Requirements, states: to be assumed operable, a piece of on-site communications equipment should be in a location, and maintained in a manner, that maximizes survivability following a beyond design basis external eventEquipment should be stored, or otherwise available, in locations that can be readily accessed when neededThe above guidance applies to equipment at the point of use as well as any supporting infrastructure components. Such components may include portable power sources, and radio system repeaters and antennas.
(b) Seismic concerns for water source(s)
(1) If the FLEX water sources are seismically robust, then provide the assessment that shows that they are.


Initially, when the licensee implemented their plans to resolve issues associated with communications during a beyond design basis external event (BDBEE), they had handheld satellite phones located in the control room and the technical support center (TSC), which required the users to relocate outdoors to acquire a usable signal. These locations are rated to withstand all BDBEE, and would therefore meet the requirements of NEI 12-01. However, in an effort to enhance the communications methods, the licensee pursued plans to provide a means for personnel to be able to communicate with satellite phones from inside buildings.
(2) If the FLEX water sources are not seismically robust, then provide:
(a) an assessment of alternate water sources, and (b) the procedure(s) which describe when and how to access those sources.


These enhancements involved providing external antennas, relocating the existing satellite phones to docking stations in a structure attached to the elevated release point (ERP shack)and in a communications room (PBX room), and routing wires to control room and TSC desk phones. These enhancements are mentioned in general in a letter from the licensee to the NRC, NLS2013028, dated 2/21/13, Response to NRC Technical Issues for Resolution Regarding Licensee Communication Submittals Associated with Near-Term Task Force Recommendation 9.3.
3) External Flooding (a) Provide description of where FLEX equipment is stored relative to protection from flood waters in accordance with site flood analysis.


In moving the physical location of the satellite phones from the control room and TSC, the licensee failed to ensure that the new locations were suitable to withstand all BDBEE. The ERP shack is not rated for tornado wind loading, and the phones relocated from the control room may not survive this external event. Additionally, the external antennas located on the elevated release point and the meteorological tower would not be able to withstand the elevated wind speeds during a tornado or other high wind event.
(1) If any FLEX equipment is stored below flood level, then (i) on an event timeline, show when that equipment will be needed; and (ii) provide the procedure(s) used to retrieve and deploy that equipment.


The team determined that, by implementing this enhancement to communications systems, the licensee placed their satellite phone equipment in locations that are vulnerable to BDBEE.
(b) Provide your plans/procedures to support successful FLEX equipment deployment for flooding/ponding from localized intense precipitation (which persist over a long time period).


This does not meet the requirements of NEI 12-01 and therefore does not meet the requirements of the FLEX Program Document.
(c) If credited in the strategy, provide plans/procedures for storage and deployment of temporary flood barriers, including timeline of deployment strategy.


Corrective Action(s): In response to the teams questions, the licensee documented the concerns in the corrective action program. Additionally, the licensee is in the process of procuring three additional satellite phones to stage in the control room, thereby restoring compliance with NEI 12-01.
4) Severe storms with high winds (a) Provide evaluation/evidence as to how FLEX equipment is stored relative to protection from severe storms with high winds (including tornadic):  
(1) In a structure that meets the plants design basis for high wind hazards (e.g.,
existing safety-related structure); OR


Corrective Action Reference(s): CR-CNS-2018-01499
(2) In a structure that meets the design requirements as described in ASCE 7-10, Minimum Design Loads for Buildings and Other Structures, given the limiting tornado wind speeds from Regulatory Guide 1.76, and/or design-basis hurricane wind speeds.


=====Performance Assessment:=====
(b) Provide pathways via which you plan to move FLEX equipment from onsite storage areas to final deployment locations.
Performance Deficiency: That the station failed to maintain the satellite phones in locations that provide reasonable assurance the phones will remain available following all beyond design basis external events is a performance deficiency. Specifically, by moving the satellite phones from locations where the phones were protected from beyond design basis external events to locations where the phones were not protected was contrary to NEI 12-01, Revision 0, Section 4.5. The ERP shack is not rated for tornado wind loading and therefore the phones relocated from the control room may not survive this external event. Additionally, the antennas may not survive high wind speeds.


Screening: The inspectors determined the performance deficiency was more than minor because it adversely affected the facilities and equipment attribute of the Emergency Preparedness Cornerstone and its objective to ensure that the licensee is capable of implementing adequate measures to protect the health and safety of the public in the event of a radiological emergency. Specifically, by moving the satellite phones to locations that are not rated for all beyond design basis external events, the licensee would not be able to contact any offsite organizations.
(1) Show how you designated and evaluated those pathways for post-storm accessibility for staging and connecting FLEX equipment.


Significance: The team assessed the significance of the finding using Inspection Manual Chapter (IMC) 0609, Appendix O, Significance Determination Process for Mitigating Strategies and Spent Fuel Pool Instrumentation (Orders EA-12-049 and EA-12-051), dated October 7, 2016. The team determined that the performance deficiency did not
5) Snow, Ice, and Extreme Cold For each key piece of equipment described in Item E (above) that directly performs or implements a FLEX mitigation strategy:  
: (1) impact the spent fuel pool instrumentation order (EA-12-051);
: (2) did not involve a failure of FLEX equipment for 72 hours or more that would result in a complete loss of one or more of the FLEX functions;
: (3) did not involve deficient procedures or training that would result in a complete loss of one or more of the FLEX functions;
: (4) did not have a product of the exposure time and external even initiating event frequency greater than 1E-6; and
: (5) did not involve significant programmatic issues which reduced the effectiveness of the Mitigating Strategies. Therefore, the finding was determined to be of very low safety significance (Green).


Cross-cutting Aspect: The finding had a human performance cross-cutting aspect associated with change management, in that the licensee failed to fully evaluate implementing the enhancement to move the satellite phones from the control room and TSC to the ERP shack an the PBX room [H.3].
(a) Provide procedures/documents demonstrating how the FLEX equipment is maintained at a temperature within a range to ensure that it will function when called upon.


=====Enforcement:=====
(b) Proved procedures/documents demonstrating how the FLEX equipment can be moved from the storage location to its deployment location during extreme snowfall and ice storms.
Inspectors did not identify a violation of regulatory requirements associated with this finding.


==EXIT MEETINGS AND DEBRIEFS==
6) Extreme high temperatures For each key piece of equipment described in Item E (above) that directly performs or implements a FLEX mitigation strategy:
The inspectors verified no proprietary information was retained or documented in this report.
(a) Provide procedures/documents which describes the high-temperature limit of the range within which the equipment will function.
* On March 15, 2018, the inspection team presented the on-site inspection results in a management debrief to Mr. J. Kalamaja, General Manager of Plant Operations, and other members of the site staff.
* On April 16, 2018, the lead inspector presented the final inspection results in an exit meeting to Mr. J. Kalamaja, General Manager of Plant Operations, and other members of the site staff.


=DOCUMENTS REVIEWED=
(b) Provide procedures/documents which describe how the equipment is maintained below that limit in its storage location.


Other Activities - TI 2515/191
I. Provide the station-specific FLEX strategies time validation study(ies).
Procedures/Instructions
Number              Title                                              Revision
0-CNS-OU-108        Shutdown Safety Management Program                4
0.50.5              Outage Shutdown Safety                            37
2.4FPC              Fuel Pool Cooling Trouble                          34
5.1FLOOD            Emergency Operations Procedure: Flood              22
7.0.11              Maintenance Procedure: Flood Control Barriers      30
14.41.1.1            FPC-LIT-1 Testing                                  4
EOF08                Position Instruction Manual: Logistics Coordinator 30
FSG 5.10FLEX        FLEX Support Guidelines (FSGs)                    2
FSG 5.10FLEX.01 125 VDC Div 1 FLEX Operations                          1
FSG 5.10FLEX.02 125 VDC Div 2 FLEX Operations                          1
FSG 5.10FLEX.03 250 VDC Div 1 FLEX Operations                          1
FSG 5.10FLEX.04 250 VDC Div 2 FLEX Operations                          1
FSG 5.10FLEX.05 Reliable Hardened Containment Vent Battery              1
Charger Tie-in
FSG 5.10FLEX.06 Fuel Pool Level Instrument Electrical Tie-In            1
FSG 5.10FLEX.07 4160 F Bus Tie-in with Off-Site Generator            2
FSG 5.10FLEX.08 4160 G Bus Tie-in with Off-Site Generator            2
FSG 5.10FLEX.09 Hotwell to ECST FLEX Operations                        1
FSG 5.10FLEX.10 ECST Makeup from North Well                            2
FSG 5.10FLEX.11 Spent Fuel Pool Supply FLEX Operations                  2
FSG 5.10FLEX.12 Reactor Building Reliable Air FLEX Operations          1
FSG 5.10FLEX.13 REC SW FLEX Supply                                      1
FSG 5.10FLEX.14 RHR Div 1 Shutdown Cooling FLEX Operations              1
FSG 5.10FLEX.15 RHR Div 2 Shutdown Cooling FLEX Operations              1
FSG 5.10FLEX.16 Residual Heat Removal Service Water (RHRSW)            2
Div 1 FLEX Operations
FSG 5.10FLEX.17 Residual Heat Removal Service Water (RHRSW)            2
Div 2 FLEX Operations
FSG 5.10FLEX.18 Alternate Reactor Building Ventilation FLEX            1
Operations
FSG 5.10FLEX.19 Alternate Ventilation FLEX Operations                  1
FSG 5.10FLEX.20 Debris Removal in Support of FLEX Operations            1
FSG 5.10FLEX.21 Shutdown Injection FLEX Operations                      1
FSG 5.10FLEX.22 Communications and Lighting Equipment FLEX              1
Power
FSG 5.10FLEX.23 Reactor Equipment Cooling FLEX Operations              1
FSG 5.10FLEX.24 Control Building Temporary Heating FLEX                1
Operations
FSG 5.10FLEX.25    Alternate RPV Injection thru RHR SW Riser or RHR-  1
B B.5.B Connection
FSG 5.10FLEX.26    RHR Suppression Pool Cooling Div 1 FLEX            1
Operations
FSG 5.10FLEX.27    RHR Suppression Pool Cooling Div 2 FLEX            1
Operations
FSG 5.10FLEX.28    Vital Instrumentation FLEX Operations              1
FSG 5.10FLEX.29    Alternate Reactor Vessel Injection from Missouri  1
River
FSG 5.10FLEX.30    Hardened Containment Vent System FLEX              5
Operations
FSG 5.10FLEX.31    FLEX Equipment Refueling Operations                1
5.3SBO            Station Blackout                                  43
5.7.17            CNS Dose Assessment                                49
5.7.17.1          Dose Assessment (Manual)                          3
6.FPC.701          FPC Level Transmitter Functional Test              0
OI 25              Operations Routine Duties                          70
Security          Access Control Devices                            50
Procedure 2.8
Site Services      Station Security                                  59
Procedure 1.1
FLEX Final Integrated Plan                        1
FLEX Program Document                              1
Preventative Maintenance Activities
Number          Title                                                Revision
5067082          SAMG Diesel Generator Testing                        9/27/2016
5155721          Perform Vendor FLEX Maintenance Activities (1 year  5/23/2017
Operational Inspections)
5164463          Perform Vendor FLEX Equipment Maintenance (6        11/06/2017
month)
5194852          Spent Fuel Pool Primary LI Signal PCRS              12/29/2017
Drawings
Number          Title                                                Revision
453010422        Emergency Condensate Storage Tanks                  AB/02
R110827          Cooper Nuclear Strategy Topography Survey            8/23/2012
Other Documents/Reports
Number          Title                                                Revision
EC 6036621      Install Remote Satellite Units                      0
EE 01-057        Class I Restrained Seismic Design Basis of Class IIS 0
Piping
EE 01-147        Summary of Main Steam Isolation Valve (MSIV)        2
Leakage Pathway to the Condenser Seismic
Qualification
ER 2016-002      FLEX Portable Equipment Deployment Path              0
Liquefaction Evaluation
Number          Title                                                Revision
INT0350113      FLEX Modifications                                  1
INT0350114      FLEX Strategy                                        1
INT0350116      FLEX Strategy Walkdown                              0
Lesson Plan    Level Measurement & Devices                          8
IAC202-00-00
LO#2018-0092    2018 CNS TI-2515/191 Mitigating Strategies (SFP/EP)
Inspection Assessment
MEC 500-01-01  MEC OSC Emergency Response Overview                  2
ML17226A032    Cooper Nuclear Station Safety Evaluation Regarding  9/20/2017
Implementation of Mitigating Strategies and Reliable
Spent Fuel Pool Instrumentation Related to Orders
EA-12-049 and EA-12-051 (CAC Nos. MF0971 and
MF0972)
MP              FLEX Equipment Maintenance Plans for FLEX Air        {Not Dated}
800000050260    Compressors; 175 kW, 60 kW, and 6 kW Diesel
Generators; and FLEX Godwin Pumps
NEDC 09-102    Internal Flooding - HELB, MELB, and Feedwater Line  2
Break
NEDC 14-001    Storage Facility Structural Calculation              1
NEDC 14-027    Review of ERIN Calculation C122140001-11622,        0
MAAP Analysis to Support Cooper FLEX Strategy
NEI 12-01      Guideline for Assessing Beyond Design Basis          0
Accident Response Staffing and Communications
Capabilities
NEI 12-06      Diverse and Flexible Coping Strategies (FLEX)        2
Implementation Guidelines
NLS2013028      Response to NRC Technical Issues for Resolution      2/21/13
Regarding Licensee Communication Submittals
Associated with Near-Term Task Force
Recommendation 9.3
NSRC-005        SAFER Response Plan for Cooper Nuclear Station      9/15/2015
PM Notification Maintenance Plan 800000050260 Revision              10/25/2017
11417703
Purchase Order  Preventive Maintenance Program                      3/06/17
4500200470
Technical      Beyond Design Basis Components                      11/06/16
Requirements
Manual Section
3.12
Cooper Nuclear Station NEI 12-01 Phase 2 Staffing    4/21/2016
Assessment
FLEX Validation Document
NANTeL Generic Basic FLEX, ERO0010102/ILT-
251/NAN-56252
NANTeL Generic Advanced FLEX, ERO0010103/ILT-
253/NAN-56254
Corrective Action Program Documents (CR-CNS-)
2016-02845                    2016-02869      2017-01463  2017-02565
2017-02568                    2017-02799      2017-02801  2017-03089
2017-03777                    2017-05033      2017-05285  2017-06372
2018-01166                    2018-01243      2018-01442* 2018-01443*
2018-01450*                    2018-01451*    2018-01457* 2018-01458*
2018-01463*                    2018-01469*    2018-01475* 2018-01494*
2018-01496*                    2018-01499*    2018-01500* 2018-01509*
2018-01511*                    2018-02294*
* - Initiated as a result of this inspection


ML18128A074
J. Provide the relevant station procedure(s)/guideline(s) which describe the testing and maintenance program for FLEX equipment. As applicable, provide a listing of the model work orders established to conduct period testing and maintenance activities for FLEX equipment.
SUNSI Review            Non-Sensitive            Publicly Available    Keyword:
By: MHS2/rdr              Sensitive                Non-Publicly Available NRC-002
OFFICE      RI:DRP/C/CNS SPE:DRP/A SRI:DRS/EB2 RIII:DRP/PE BC:DRP/C
NAME            MStafford RAlexander    JMateychick  SSheldon        JKozal
SIGNATURE        /RA-E/      /RA/          /RA/      /RA-E/          /RA/
DATE            4/19/18    4/19/18        4/20/18    4/19/18        5/8/18


May 8, 2018
NOTE - A sample of records for completed maintenance/testing activities will be requested for review during the onsite inspection week.
Mr. John Dent, Jr.
 
Vice President-Nuclear and CNO
K. Provide documents/procedures which describe the programmatic controls in place to ensure that if equipment and applicable connections are unavailable (e.g., due to maintenance, non-functionality), then compensatory measures are implemented in accordance with guidance outlined NEI 12-06.
Nebraska Public Power District
 
Cooper Nuclear Station
L. Provide the station-specific National SAFER Center Playbook M. Relative to personnel training on FLEX strategies, provide:
2676 648A Avenue
1) FLEX training bases document(s)
P.O. Box 98
2) Lesson plans/training documents for site emergency response leaders responsible for the implementation of FLEX strategies.
Brownville, NE 68321
 
SUBJECT:        COOPER NUCLEAR STATION - INSPECTION OF THE IMPLEMENTATION OF
NOTE - Records for staff completing this training may be requested for review during the onsite inspection week.
MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION
 
ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/
3) Lesson plans/training documents for site personnel responsible for the execution of mitigating strategies for BDBEEs (i.e., operators, craft personnel, security, radiation protection, etc.).
STAFFING/MULTI-UNIT DOSE ASSESSMENT PLANS - INSPECTION
NOTE - Records for staff completing this training may be requested for review during the onsite inspection week.
REPORT 05000298/2018010
 
Dear Mr. Dent:
N. A current copy of administrative procedure(s) for the CAP, modification program, operations procedure writing and implementation, and top-level documents for the work control and work scheduling programs. (If FLEX related procedures such as FSGs or the FIP are maintained under a different process, please include copies of those procedures.)
On March 15, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed the onsite
 
portion of this inspection at your Cooper Nuclear Station. On April 16, 2018, the NRC
O. A current copy of the U/FSAR, Technical Specifications, and Technical Specification Bases documents.
inspectors discussed the results of this inspection with Mr.  
 
: [[contact::J. Kalamaja]], General Manager of
P. Listing of corrective action program document summaries generated related to FLEX equipment, strategies, procedures, and/or training.
Plant Operations, and other members of your staff. The results of this inspection are
 
documented in the enclosed report.
NOTE - Complete corrective action program documents for a selection of those included in the summary will be requested for review during the onsite inspection week.
The inspection examined activities conducted under your license as they relate to the
 
implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049
Q. A copy of any audits/self-assessments related to your preparation for this inspection, as well as any related to the implementation or maintenance of the FLEX program.
and EA-12-051) and Emergency Preparedness Communication, Staffing, and Multi-Unit Dose
 
Assessment Plans, your compliance with the Commissions rules and regulations, and with the
TI 2515/191 - Appendix B R. Provide the procedures implemented for maintenance, testing, calibration, and use of the primary and backup Spent Fuel Pool (SFP) instrumentation channels.
conditions of your operating license. Within these areas, the inspection involved examination of
 
selected procedures and records, observation of activities, and interviews with station
S. Provide lesson plans/training documents which describe the training program that address the use, maintenance, calibration, surveillance, and the use of alternate power to the primary and backup SFP instrument channels.
personnel.
 
NRC inspectors documented one finding of very low safety significance (Green) in this report.
TI 2515/191 - Appendix C T. Communications:
The finding did not involve a violation of NRC requirements.
1) Provide documents which show that the communications system(s), technologies, equipment and power supplies would be available from the beginning of the event and operate during an ELAP.
If you disagree with a cross-cutting aspect assignment or a finding not associated with a
 
regulatory requirement in this report, you should provide a response within 30 days of the date
2) Provide the procedures and/or guidance used to implement the communication capabilities.
of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory
 
Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the
3) Provide documents which show that you have added any new communications equipment, portable power supplies and/or systems have been added to ongoing testing and preventative maintenance programs.
Regional Administrator, Region IV; and the NRC resident inspector at the Cooper Nuclear
 
Station.
U. Staffing:
J. Dent Jr.                                      2
1) Provide documents which show that onsite and augmented staff will be available to implement the strategies in response to a large scale natural event that results an ELAP and impedes access to the site, and that functions/tasks have been appropriately staffed.
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
2) Provide documents which show that the site access methods (e.g., roadways, navigable bodies of water and dockage, airlift, etc.) expected to be available following the event and available to the Emergency Response Organization (ERO) [as described in the Phase 1 and 2 staffing assessments and NRC safety assessment].
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
3) Provide documents which show the testing, training, and drills/exercises performed by the station to demonstrate the EROs ability to utilize the communications systems and/or equipment.
Withholding.
 
Sincerely,
V. Provide documents and procedures which show that your dose assessment process/program is capable of analyzing concurrent radiological releases from all on-site significant sources, including releases from spent fuel pools (i.e., multi-unit/multi-source dose assessment capability).
                                                /RA/
 
Jason
Lead Inspector Contact Information:  
: [[contact::W. Kozal]], Chief
 
Project Branch C
Michael H. Stafford, Resident Inspector Mailing Address:
Division of Reactor Projects
402-825-3371 U.S. NRC, Region IV Michael.Stafford@nrc.gov Attn: Ryan Alexander, DRP
Docket: 50-298
 
License: DPR-46
1600 East Lamar Blvd.
Enclosure:
 
Inspection Report 05000298/2018010
Arlington, TX 76011-4511
w/Attachment:
 
Documents Reviewed
ML18023A110 SUNSI Review By: MHS/rdr ADAMS:
U.S. NUCLEAR REGULATORY COMMISSION
Yes No Sensitive Non-Sensitive Non-Publicly Available Publicly Available Keyword NRC-002 OFFICE DRP/RPBC C:DRP/RPBC
Inspection Report
 
Docket Number:        05000298
NAME MStafford JKozal
License Number:        DPR-46
Report Number:        05000298/2018010
Enterprise Identifier: I-2018-010-0017
Licensee:              Nebraska Public Power District
Facility:              Cooper Nuclear Station
Location:             Brownville, Nebraska
Inspection Dates:      March 12, 2018 to April 16, 2018
Inspectors:           
: [[contact::M. Stafford]], Resident Inspector - Cooper (Team Leader)
: [[contact::R. Alexander]], Sr. Project Engineer - Region IV
: [[contact::J. Mateychick]], Sr. Reactor Inspector - Region IV
: [[contact::S. Sheldon]], Project Engineer - Region III
Approved By:           Jason Kozal
Chief, Project Branch C
Division of Reactor Projects


SUMMARY
SIGNATURE
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance
/RA/  
by conducting a Temporary Instruction 2515/191, Implementation of Mitigation Strategies and
/RA/  
Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/
Staffing/Multi-Unit Dose Assessment Plans at Cooper Nuclear Station in accordance with the
Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for
overseeing the safe operation of commercial nuclear power reactors. Refer to
https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-
revealed findings, violations, and additional items are summarized in the table below.
List of Findings and Violations
Failure to Maintain Satellite Phones in Locations That Provide Reasonable Assurance They
Will Remain Available Following All Beyond Design Basis External Events
Cornerstone      Significance                                      Cross-cutting Report
Aspect          Section
Emergency        Green                                            H.3 -          TI 2515/191
Preparedness FIN 05000298/2018010-01                                Change
Closed                                            Management
The NRC inspection team identified a Green finding related to the licensees failure to maintain
the station satellite phones in locations that would provide reasonable assurance the phones
would remain available following all beyond design basis external events.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors reviewed selected procedures and records,
observed activities, and interviewed personnel to assess licensee performance and compliance
with Commission rules and regulations, license conditions, site procedures, and standards.
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
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
Inspectors verified 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
(Agencywide Documents Access and Management System (ADAMS) Accession No.
ML12056A045) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel
Pool Instrumentation (ADAMS 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 (ADAMS No. ML12053A340) 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 No.
ML12339A262).
    (1) Based on samples selected for review, the inspectors verified that the licensee
satisfactorily implemented appropriate elements of the Diverse and Flexible Coping
Strategies (FLEX) as described in the plant specific submittals [including the Final
Integrated Plan (ADAMS Accession No. ML17017A166)] and the associated safety
evaluation (ADAMS No. ML17226A032) and determined that the licensee is in
compliance with NRC Order EA-12-049, Order Modifying Licenses with Regard to
Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. The
inspectors verified the licensee satisfactorily:
a) developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX
strategies for postulated external events;
b) integrated their FSGs into their existing plant procedures such that entry into and
departure from the FSGs were clear when using existing plant procedures;
c) protected FLEX equipment from site-specific hazards;
d) developed and implemented adequate testing and maintenance of FLEX equipment
to ensure their availability and capability;
e) trained their staff to assure personnel proficiency in the mitigation of
beyond-design basis events; and
f)  developed the means to ensure the necessary off-site FLEX equipment would be
available from off-site locations.
    (2) Based on samples selected for review, the inspectors verified that the licensee
satisfactorily implemented appropriate elements of the FLEX strategy as described in the
plant specific submittals [including the Final Integrated Plan (ADAMS Accession No.
ML17017A166)] and the associated safety evaluation (ADAMS No. ML17226A032) and
determined that the licensee is in compliance with NRC Order NRC Order EA-12-051,
Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation.
The inspectors verified the licensee satisfactorily :
a) installed the spent fuel pool (SFP) instrumentation sensors, cabling and power
supplies to provide physical and electrical separation as described in the plant
specific submittals and safety evaluation;
b) installed the SFP instrumentation display in the location, environmental conditions
and accessibility as described in the plant specific submittals;
c) trained their staff to assure personnel proficiency with the maintenance, testing, and
use of the SFP instrumentation; and
d) developed and issued procedures for maintenance, testing and use of the reliable
SFP instrumentation.
    (3) The inspectors reviewed information provided in the licensees multi-unit dose submittal
and in response to the NRCs March 12, 2012, request for information letter (ADAMS
No. ML12053A340), and verified that the licensee satisfactorily implemented
enhancements pertaining to Near-Term Task Force Recommendation 9.3 in response to
a large scale natural emergency event that results in an extended loss of all ac power to
all site units and impedes access to the site. The inspectors verified the following:
a) the licensee satisfactorily implemented required staffing changes to support an
extend loss of all AC power (ELAP)/loss of ultimate heat sink (LUHS) scenario;
b) EP communications equipment and facilities are sufficient for dealing with an
ELAP/LUHS scenario; and
c) the licensee implemented multi-unit/-source dose assessment capabilities (including
releases from spent fuel pools) using the licensees site-specific dose assessment
software and approach.
The inspectors verified that non-compliances with requirements and standards identified during
the inspection were entered into the licensee's corrective action program as appropriate.
INSPECTION RESULTS
Failure to Maintain Satellite Phones in Locations That Provide Reasonable Assurance They
Will Remain Available Following All Beyond Design Basis External Events
Cornerstone            Significance                            Cross-cutting    Report
Aspect            Section
Emergency              Green                                  H.3 - Change      TI 2515/191
Preparedness            FIN 05000298/2018010-01                Management
Closed
The NRC inspection team identified a Green finding related to the licensees failure to
maintain the station satellite phones in locations that would provide reasonable assurance the
phones would remain available following all beyond design basis external events.
Description: The Cooper Nuclear Station FLEX Program Document, Revision 1, Section
5.2.27, Support Functions - Communications, states, in part: NEI 12-01 provides required
emergency communications capabilities during an Extended Loss of AC Power
(ELAP)Satellite phones are credited for off-site communicationDocking stations and
remote antennas have been installed to allow use of the satellite phones from inside
buildings.
NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and
Communications Capabilities, Revision 0, Section 4.5, Equipment Location Requirements,
states: to be assumed operable, a piece of on-site communications equipment should be in a
location, and maintained in a manner, that maximizes survivability following a beyond design
basis external eventEquipment should be stored, or otherwise available, in locations that
can be readily accessed when neededThe above guidance applies to equipment at the
point of use as well as any supporting infrastructure components. Such components may
include portable power sources, and radio system repeaters and antennas.
Initially, when the licensee implemented their plans to resolve issues associated with
communications during a beyond design basis external event (BDBEE), they had handheld
satellite phones located in the control room and the technical support center (TSC), which
required the users to relocate outdoors to acquire a usable signal. These locations are rated
to withstand all BDBEE, and would therefore meet the requirements of NEI 12-01. However,
in an effort to enhance the communications methods, the licensee pursued plans to provide a
means for personnel to be able to communicate with satellite phones from inside buildings.
These enhancements involved providing external antennas, relocating the existing satellite
phones to docking stations in a structure attached to the elevated release point (ERP shack)
and in a communications room (PBX room), and routing wires to control room and TSC desk
phones. These enhancements are mentioned in general in a letter from the licensee to the
NRC, NLS2013028, dated 2/21/13, Response to NRC Technical Issues for Resolution
Regarding Licensee Communication Submittals Associated with Near-Term Task Force
Recommendation 9.3.
In moving the physical location of the satellite phones from the control room and TSC, the
licensee failed to ensure that the new locations were suitable to withstand all BDBEE. The
ERP shack is not rated for tornado wind loading, and the phones relocated from the control
room may not survive this external event. Additionally, the external antennas located on the
elevated release point and the meteorological tower would not be able to withstand the
elevated wind speeds during a tornado or other high wind event.
The team determined that, by implementing this enhancement to communications systems,
the licensee placed their satellite phone equipment in locations that are vulnerable to BDBEE.
This does not meet the requirements of NEI 12-01 and therefore does not meet the
requirements of the FLEX Program Document.
Corrective Action(s): In response to the teams questions, the licensee documented the
concerns in the corrective action program. Additionally, the licensee is in the process of
procuring three additional satellite phones to stage in the control room, thereby restoring
compliance with NEI 12-01.
Corrective Action Reference(s): CR-CNS-2018-01499
Performance Assessment:
Performance Deficiency: That the station failed to maintain the satellite phones in locations
that provide reasonable assurance the phones will remain available following all beyond
design basis external events is a performance deficiency. Specifically, by moving the satellite
phones from locations where the phones were protected from beyond design basis external
events to locations where the phones were not protected was contrary to NEI 12-01,
Revision 0, Section 4.5. The ERP shack is not rated for tornado wind loading and therefore
the phones relocated from the control room may not survive this external event. Additionally,
the antennas may not survive high wind speeds.
Screening: The inspectors determined the performance deficiency was more than minor
because it adversely affected the facilities and equipment attribute of the Emergency
Preparedness Cornerstone and its objective to ensure that the licensee is capable of
implementing adequate measures to protect the health and safety of the public in the event of
a radiological emergency. Specifically, by moving the satellite phones to locations that are
not rated for all beyond design basis external events, the licensee would not be able to
contact any offsite organizations.
Significance: The team assessed the significance of the finding using Inspection Manual
Chapter (IMC) 0609, Appendix O, Significance Determination Process for Mitigating
Strategies and Spent Fuel Pool Instrumentation (Orders EA-12-049 and EA-12-051), dated
October 7, 2016. The team determined that the performance deficiency did not (1) impact the
spent fuel pool instrumentation order (EA-12-051); (2) did not involve a failure of FLEX
equipment for 72 hours or more that would result in a complete loss of one or more of the
FLEX functions; (3) did not involve deficient procedures or training that would result in a
complete loss of one or more of the FLEX functions; (4) did not have a product of the
exposure time and external even initiating event frequency greater than 1E-6; and (5) did not
involve significant programmatic issues which reduced the effectiveness of the Mitigating
Strategies. Therefore, the finding was determined to be of very low safety significance
(Green).
Cross-cutting Aspect: The finding had a human performance cross-cutting aspect associated
with change management, in that the licensee failed to fully evaluate implementing the
enhancement to move the satellite phones from the control room and TSC to the ERP shack
an the PBX room [H.3].
Enforcement: Inspectors did not identify a violation of regulatory requirements associated
with this finding.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
*  On March 15, 2018, the inspection team presented the on-site inspection results in a
management debrief to Mr.
: [[contact::J. Kalamaja]], General Manager of Plant Operations, and other
members of the site staff.
*  On April 16, 2018, the lead inspector presented the final inspection results in an exit meeting
to Mr.
: [[contact::J. Kalamaja]], General Manager of Plant Operations, and other members of the site
staff.
DOCUMENTS REVIEWED
Other Activities - TI 2515/191
Procedures/Instructions
Number              Title                                              Revision
0-CNS-OU-108        Shutdown Safety Management Program                4
0.50.5              Outage Shutdown Safety                            37
2.4FPC              Fuel Pool Cooling Trouble                          34
5.1FLOOD            Emergency Operations Procedure: Flood              22
7.0.11              Maintenance Procedure: Flood Control Barriers      30
14.41.1.1            FPC-LIT-1 Testing                                  4
EOF08                Position Instruction Manual: Logistics Coordinator 30
FSG 5.10FLEX        FLEX Support Guidelines (FSGs)                    2
FSG 5.10FLEX.01 125 VDC Div 1 FLEX Operations                          1
FSG 5.10FLEX.02 125 VDC Div 2 FLEX Operations                          1
FSG 5.10FLEX.03 250 VDC Div 1 FLEX Operations                          1
FSG 5.10FLEX.04 250 VDC Div 2 FLEX Operations                          1
FSG 5.10FLEX.05 Reliable Hardened Containment Vent Battery              1
Charger Tie-in
FSG 5.10FLEX.06 Fuel Pool Level Instrument Electrical Tie-In            1
FSG 5.10FLEX.07 4160 F Bus Tie-in with Off-Site Generator            2
FSG 5.10FLEX.08 4160 G Bus Tie-in with Off-Site Generator            2
FSG 5.10FLEX.09 Hotwell to ECST FLEX Operations                        1
FSG 5.10FLEX.10 ECST Makeup from North Well                            2
FSG 5.10FLEX.11 Spent Fuel Pool Supply FLEX Operations                  2
FSG 5.10FLEX.12 Reactor Building Reliable Air FLEX Operations          1
FSG 5.10FLEX.13 REC SW FLEX Supply                                      1
FSG 5.10FLEX.14 RHR Div 1 Shutdown Cooling FLEX Operations              1
FSG 5.10FLEX.15 RHR Div 2 Shutdown Cooling FLEX Operations              1
FSG 5.10FLEX.16 Residual Heat Removal Service Water (RHRSW)            2
Div 1 FLEX Operations
FSG 5.10FLEX.17 Residual Heat Removal Service Water (RHRSW)            2
Div 2 FLEX Operations
FSG 5.10FLEX.18 Alternate Reactor Building Ventilation FLEX            1
Operations
FSG 5.10FLEX.19 Alternate Ventilation FLEX Operations                  1
FSG 5.10FLEX.20 Debris Removal in Support of FLEX Operations            1
FSG 5.10FLEX.21 Shutdown Injection FLEX Operations                      1
FSG 5.10FLEX.22 Communications and Lighting Equipment FLEX              1
Power
FSG 5.10FLEX.23 Reactor Equipment Cooling FLEX Operations              1
FSG 5.10FLEX.24 Control Building Temporary Heating FLEX                1
Operations
FSG 5.10FLEX.25    Alternate RPV Injection thru RHR SW Riser or RHR-  1
B B.5.B Connection
FSG 5.10FLEX.26    RHR Suppression Pool Cooling Div 1 FLEX            1
Operations
FSG 5.10FLEX.27    RHR Suppression Pool Cooling Div 2 FLEX            1
Operations
FSG 5.10FLEX.28    Vital Instrumentation FLEX Operations              1
FSG 5.10FLEX.29    Alternate Reactor Vessel Injection from Missouri  1
River
FSG 5.10FLEX.30    Hardened Containment Vent System FLEX              5
Operations
FSG 5.10FLEX.31    FLEX Equipment Refueling Operations                1
5.3SBO            Station Blackout                                  43
5.7.17            CNS Dose Assessment                                49
5.7.17.1          Dose Assessment (Manual)                          3
6.FPC.701          FPC Level Transmitter Functional Test              0
OI 25              Operations Routine Duties                          70
Security          Access Control Devices                            50
Procedure 2.8
Site Services      Station Security                                  59
Procedure 1.1
FLEX Final Integrated Plan                        1
FLEX Program Document                              1
Preventative Maintenance Activities
Number          Title                                                Revision
5067082          SAMG Diesel Generator Testing                        9/27/2016
5155721          Perform Vendor FLEX Maintenance Activities (1 year  5/23/2017
Operational Inspections)
5164463          Perform Vendor FLEX Equipment Maintenance (6        11/06/2017
month)
5194852          Spent Fuel Pool Primary LI Signal PCRS              12/29/2017
Drawings
Number          Title                                                Revision
453010422        Emergency Condensate Storage Tanks                  AB/02
R110827          Cooper Nuclear Strategy Topography Survey            8/23/2012
Other Documents/Reports
Number          Title                                                Revision
EC 6036621      Install Remote Satellite Units                      0
EE 01-057        Class I Restrained Seismic Design Basis of Class IIS 0
Piping
EE 01-147        Summary of Main Steam Isolation Valve (MSIV)        2
Leakage Pathway to the Condenser Seismic
Qualification
ER 2016-002      FLEX Portable Equipment Deployment Path              0
Liquefaction Evaluation
Number          Title                                                Revision
INT0350113      FLEX Modifications                                  1
INT0350114      FLEX Strategy                                        1
INT0350116      FLEX Strategy Walkdown                              0
Lesson Plan    Level Measurement & Devices                          8
IAC202-00-00
LO#2018-0092    2018 CNS TI-2515/191 Mitigating Strategies (SFP/EP)
Inspection Assessment
MEC 500-01-01  MEC OSC Emergency Response Overview                  2
ML17226A032    Cooper Nuclear Station Safety Evaluation Regarding  9/20/2017
Implementation of Mitigating Strategies and Reliable
Spent Fuel Pool Instrumentation Related to Orders
EA-12-049 and EA-12-051 (CAC Nos. MF0971 and
MF0972)
MP              FLEX Equipment Maintenance Plans for FLEX Air        {Not Dated}
800000050260    Compressors; 175 kW, 60 kW, and 6 kW Diesel
Generators; and FLEX Godwin Pumps
NEDC 09-102    Internal Flooding - HELB, MELB, and Feedwater Line  2
Break
NEDC 14-001    Storage Facility Structural Calculation              1
NEDC 14-027    Review of ERIN Calculation C122140001-11622,        0
MAAP Analysis to Support Cooper FLEX Strategy
NEI 12-01      Guideline for Assessing Beyond Design Basis          0
Accident Response Staffing and Communications
Capabilities
NEI 12-06      Diverse and Flexible Coping Strategies (FLEX)        2
Implementation Guidelines
NLS2013028      Response to NRC Technical Issues for Resolution      2/21/13
Regarding Licensee Communication Submittals
Associated with Near-Term Task Force
Recommendation 9.3
NSRC-005        SAFER Response Plan for Cooper Nuclear Station      9/15/2015
PM Notification Maintenance Plan 800000050260 Revision              10/25/2017
11417703
Purchase Order  Preventive Maintenance Program                      3/06/17
4500200470
Technical      Beyond Design Basis Components                      11/06/16
Requirements
Manual Section
3.12
Cooper Nuclear Station NEI 12-01 Phase 2 Staffing    4/21/2016
Assessment
FLEX Validation Document
NANTeL Generic Basic FLEX, ERO0010102/ILT-
251/NAN-56252
NANTeL Generic Advanced FLEX, ERO0010103/ILT-
253/NAN-56254
Corrective Action Program Documents (CR-CNS-)
2016-02845                    2016-02869      2017-01463  2017-02565
2017-02568                    2017-02799      2017-02801  2017-03089
2017-03777                    2017-05033      2017-05285  2017-06372
2018-01166                    2018-01243      2018-01442* 2018-01443*
2018-01450*                    2018-01451*    2018-01457* 2018-01458*
2018-01463*                    2018-01469*    2018-01475* 2018-01494*
2018-01496*                    2018-01499*    2018-01500* 2018-01509*
2018-01511*                    2018-02294*
* - Initiated as a result of this inspection


ML18128A074
DATE 01/23/2018 01/23/18
SUNSI Review            Non-Sensitive            Publicly Available    Keyword:
By: MHS2/rdr              Sensitive                Non-Publicly Available NRC-002
OFFICE      RI:DRP/C/CNS SPE:DRP/A SRI:DRS/EB2 RIII:DRP/PE BC:DRP/C
NAME            MStafford RAlexander    JMateychick  SSheldon        JKozal
SIGNATURE        /RA-E/      /RA/          /RA/      /RA-E/          /RA/
DATE             4/19/18    4/19/18        4/20/18    4/19/18        5/8/18
}}
}}

Latest revision as of 04:43, 7 January 2025

CNS - Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans (05000298/2018010) and Request
ML18023A110
Person / Time
Site: Cooper Entergy icon.png
Issue date: 01/23/2018
From: Jason Kozal
NRC/RGN-IV/DRP/RPB-C
To: Dent J
Nebraska Public Power District (NPPD)
Miller G
References
IR 2018010
Download: ML18023A110 (7)


Text

January 23, 2018

SUBJECT:

COOPER NUCLEAR STATION - NOTIFICATION OF NRC INSPECTION OF THE IMPLEMENTATION OF MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/ STAFFING/MULTI-UNIT DOSE ASSESSMENT PLANS (05000298/2018010) AND REQUEST FOR INFORMATION

Dear Mr. Dent:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

staff will conduct a mitigation strategies for beyond-design-basis external events, spent fuel pool instrumentation, and emergency preparedness enhancements inspection at the Cooper Nuclear Station, from March 12-16, 2018. The inspection will consist of two reactor inspectors from the NRCs Region IV office, one reactor inspector from the NRCs Region III office, plus one of the assigned Resident Inspectors at the Cooper Nuclear Station for one week. The inspection will be conducted in accordance with the NRCs Temporary Instruction 2515/191, Inspection of the Implementation of Mitigating Strategies and Spent Fuel Pool Instrumentation Orders, and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans.

Experience has shown that this inspection is resource intensive both for the NRC inspectors and licensee staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection activity. Please note that the documents are requested to be provided by February 23, 2018.

During the onsite inspection, inspectors will verify that plans for complying with NRC Orders EA-12-049 and EA-12-051 are in place and are being implemented. Inspectors will also verify the establishment of staffing and communications plans provided in response to the March 12, 2012, request for information letter, and multi-unit 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. These plans and information were provided in the site specific submittals, which were subsequently reviewed by the NRC staff for understanding and documented in the NRCs plant safety evaluations (SEs) and safety assessments. Therefore, appropriate personnel knowledgeable of the stations FLEX strategies, spent fuel pool instrumentation, and emergency preparedness enhancements should be available to support the inspectors at the site during the inspection. We have discussed the schedule for this inspection activity with your staff and understand that our regulatory contact for this inspection will be Brenda Kirkpatrick of your licensing organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Michael H. Stafford, by telephone at 402-825-3371 or by e-mail at Michael.Stafford@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 NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Jason W. Kozal, Branch Chief Project Branch C Division of Reactor Projects

Dockets: 50-298 Licenses: DPR-46

Enclosure:

FLEX Strategies, Spent Fuel Pool Instrumentation, & EP Enhancements Inspection Request for Information

Enclosure Request for Information FLEX Strategies, Spent Fuel Pool Instrumentation, & EP Enhancements Inspection Cooper Nuclear Station

Inspection Report:

05000298/2018010

Inspection Dates:

March 12 - 16, 2018

Inspection Procedure:

Temporary Instruction 2515/191, Inspection of the Implementation of Mitigating Strategies and Spent Fuel Pool Instrumentation Orders, and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans

Inspectors:

Michael H. Stafford, Team Lead, CNS Resident Inspector

Ryan D. Alexander, Sr. Project Engineer, Region IV

John M. Mateychick, Sr. Reactor Inspector, Region IV

Stuart N. Sheldon, Project Engineer, Region III

Information Requested for the In-Office Preparation Week

The following information should be sent to the Region IV office in hard copy or electronic format (use of the Certrec IMS information portal is preferred), to the attention of Ryan Alexander, by February 23, 2018. Additionally, a copy of any material sent to the Region IV office should also be delivered to the resident inspectors office at Cooper Nuclear Station. The inspectors will select specific items from the information requested below and then request from your staff additional documents needed during the onsite inspection week. Also, we request that you categorize the documents in your response with the numbered list below. Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the lead inspector, and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the lead inspector as soon as possible.

TI 2515/191 - Appendix A A. Provide current revision of the FLEX Final Integrated Plan (i.e., current FLEX Program Document), including any revisions since January 2017 submission to the NRC.

B. Provide the FLEX Strategy Basis Document.

C. Provide each operating, off-normal, abnormal, and/or emergency procedures where entry into one or more FLEX Support Guideline(s) are initiated.

D. Provide a list and copies of every FLEX Support Guideline (FSG) or equivalent procedure which you developed or revised to implement your mitigating strategies.

E. Provide a list of key pieces of equipment that directly perform a FLEX mitigation strategy for core cooling, containment, and/or spent fuel pool cooling.

F. Provide a listing/summaries of plant modifications completed related to the FLEX program.

G. Provide a listing of calculations, evaluations, and 50.59 reviews related to the FLEX program and modifications.

H. Applicable site specific hazards for the Cooper Nuclear Station:

1) Provide documents which show the locations and configuration of structure(s) which store FLEX equipment.

2) Seismic (a) Provide the travel route(s) for FLEX equipment from storage location(s) to their location(s) of use, AND evaluation(s) which demonstrate that for the potential for soil liquefaction is not of a concern for these travel route(s).

(b) Seismic concerns for water source(s)

(1) If the FLEX water sources are seismically robust, then provide the assessment that shows that they are.

(2) If the FLEX water sources are not seismically robust, then provide:

(a) an assessment of alternate water sources, and (b) the procedure(s) which describe when and how to access those sources.

3) External Flooding (a) Provide description of where FLEX equipment is stored relative to protection from flood waters in accordance with site flood analysis.

(1) If any FLEX equipment is stored below flood level, then (i) on an event timeline, show when that equipment will be needed; and (ii) provide the procedure(s) used to retrieve and deploy that equipment.

(b) Provide your plans/procedures to support successful FLEX equipment deployment for flooding/ponding from localized intense precipitation (which persist over a long time period).

(c) If credited in the strategy, provide plans/procedures for storage and deployment of temporary flood barriers, including timeline of deployment strategy.

4) Severe storms with high winds (a) Provide evaluation/evidence as to how FLEX equipment is stored relative to protection from severe storms with high winds (including tornadic):

(1) In a structure that meets the plants design basis for high wind hazards (e.g.,

existing safety-related structure); OR

(2) In a structure that meets the design requirements as described in ASCE 7-10, Minimum Design Loads for Buildings and Other Structures, given the limiting tornado wind speeds from Regulatory Guide 1.76, and/or design-basis hurricane wind speeds.

(b) Provide pathways via which you plan to move FLEX equipment from onsite storage areas to final deployment locations.

(1) Show how you designated and evaluated those pathways for post-storm accessibility for staging and connecting FLEX equipment.

5) Snow, Ice, and Extreme Cold For each key piece of equipment described in Item E (above) that directly performs or implements a FLEX mitigation strategy:

(a) Provide procedures/documents demonstrating how the FLEX equipment is maintained at a temperature within a range to ensure that it will function when called upon.

(b) Proved procedures/documents demonstrating how the FLEX equipment can be moved from the storage location to its deployment location during extreme snowfall and ice storms.

6) Extreme high temperatures For each key piece of equipment described in Item E (above) that directly performs or implements a FLEX mitigation strategy:

(a) Provide procedures/documents which describes the high-temperature limit of the range within which the equipment will function.

(b) Provide procedures/documents which describe how the equipment is maintained below that limit in its storage location.

I. Provide the station-specific FLEX strategies time validation study(ies).

J. Provide the relevant station procedure(s)/guideline(s) which describe the testing and maintenance program for FLEX equipment. As applicable, provide a listing of the model work orders established to conduct period testing and maintenance activities for FLEX equipment.

NOTE - A sample of records for completed maintenance/testing activities will be requested for review during the onsite inspection week.

K. Provide documents/procedures which describe the programmatic controls in place to ensure that if equipment and applicable connections are unavailable (e.g., due to maintenance, non-functionality), then compensatory measures are implemented in accordance with guidance outlined NEI 12-06.

L. Provide the station-specific National SAFER Center Playbook M. Relative to personnel training on FLEX strategies, provide:

1) FLEX training bases document(s)

2) Lesson plans/training documents for site emergency response leaders responsible for the implementation of FLEX strategies.

NOTE - Records for staff completing this training may be requested for review during the onsite inspection week.

3) Lesson plans/training documents for site personnel responsible for the execution of mitigating strategies for BDBEEs (i.e., operators, craft personnel, security, radiation protection, etc.).

NOTE - Records for staff completing this training may be requested for review during the onsite inspection week.

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

O. A current copy of the U/FSAR, Technical Specifications, and Technical Specification Bases documents.

P. Listing of corrective action program document summaries generated related to FLEX equipment, strategies, procedures, and/or training.

NOTE - Complete corrective action program documents for a selection of those included in the summary will be requested for review during the onsite inspection week.

Q. A copy of any audits/self-assessments related to your preparation for this inspection, as well as any related to the implementation or maintenance of the FLEX program.

TI 2515/191 - Appendix B R. Provide the procedures implemented for maintenance, testing, calibration, and use of the primary and backup Spent Fuel Pool (SFP) instrumentation channels.

S. Provide lesson plans/training documents which describe the training program that address the use, maintenance, calibration, surveillance, and the use of alternate power to the primary and backup SFP instrument channels.

TI 2515/191 - Appendix C T. Communications:

1) Provide documents which show that the communications system(s), technologies, equipment and power supplies would be available from the beginning of the event and operate during an ELAP.

2) Provide the procedures and/or guidance used to implement the communication capabilities.

3) Provide documents which show that you have added any new communications equipment, portable power supplies and/or systems have been added to ongoing testing and preventative maintenance programs.

U. Staffing:

1) Provide documents which show that onsite and augmented staff will be available to implement the strategies in response to a large scale natural event that results an ELAP and impedes access to the site, and that functions/tasks have been appropriately staffed.

2) Provide documents which show that the site access methods (e.g., roadways, navigable bodies of water and dockage, airlift, etc.) expected to be available following the event and available to the Emergency Response Organization (ERO) [as described in the Phase 1 and 2 staffing assessments and NRC safety assessment].

3) Provide documents which show the testing, training, and drills/exercises performed by the station to demonstrate the EROs ability to utilize the communications systems and/or equipment.

V. Provide documents and procedures which show that your dose assessment process/program is capable of analyzing concurrent radiological releases from all on-site significant sources, including releases from spent fuel pools (i.e., multi-unit/multi-source dose assessment capability).

Lead Inspector Contact Information:

Michael H. Stafford, Resident Inspector Mailing Address:

402-825-3371 U.S. NRC, Region IV Michael.Stafford@nrc.gov Attn: Ryan Alexander, DRP

1600 East Lamar Blvd.

Arlington, TX 76011-4511

ML18023A110 SUNSI Review By: MHS/rdr ADAMS:

Yes No Sensitive Non-Sensitive Non-Publicly Available Publicly Available Keyword NRC-002 OFFICE DRP/RPBC C:DRP/RPBC

NAME MStafford JKozal

SIGNATURE

/RA/

/RA/

DATE 01/23/2018 01/23/18