ML15033A430
| ML15033A430 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/03/2015 |
| From: | Michael Brown Japan Lessons-Learned Division |
| To: | James Shea Tennessee Valley Authority |
| Brown M, NRR/JLD, 415-1924 | |
| References | |
| EA-12-049, EA-12-051, TAC MF0794, TAC MF0795, TAC MF0864, TAC MF0865 | |
| Download: ML15033A430 (18) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 3, 2015 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street LP 3D-C Chattanooga, TN 37402
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REPORT FOR THE ONSITE AUDIT REGARDING IMPLEMENTATION OF MITIGATING STRATEGIES AND RELIABLE SPENT FUEL INSTRUMENTATION RELATED TO ORDERS EA-12-049 AND EA-12-051 (TAC NOS. MF0864, MF0865, MF0794, AND MF0795)
Dear Mr. Shea:
On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events" and Order EA-12-051, "Order to Modify Licenses With Regard To Reliable Spent Fuel Pool Instrumentation," (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12054A736 and ML12054A679, respectively). The orders require holders of operating reactor licenses and construction permits issued under Title 10 of the Code of Federal Regulations Part 50 to submit for review, Overall Integrated Plans (OIPs) including descriptions of how compliance with the requirements of of each order will be achieved.
By letter dated February 28, 2013 (ADAMS Accession No. ML13063A183), Tennessee Valley Authority (TVA. the licensee) submitted its OIP for Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah) in response to Order EA-12-049. By letters dated August 28, 2013, February 28, 2014, and August 28, 2014 (ADAMS Accession Nos. ML13247A286, ML14064A295, and ML14247A644, respectively), TVA submitted its first three six-month updates to the OIP. By letter dated August 28, 2013 (ADAMS Accession No. ML13234A503),
the NRC notified all licensees and construction permit holders that the staff is conducting audits of their responses to Order EA-12-049 in accordance with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195). This audit process led to the issuance of the Sequoyah interim staff evaluation (ISE) (ADAMS Accession No. ML14002A109) and continues with in-office and onsite portions of this audit By letter dated February 28, 2013 (ADAMS Accession No. ML13063A011 ), the licensee submitted its 01 P for Sequoyah in response to Order EA-12-051. By letter dated July 17, 2013 (ADAMS Accession No. ML13198A354), the NRC staff sent a request for additional information (RAI) to the licensee. By letters dated August 16, 2013, August 28, 2013, February 28, 2014, and August 28, 2014 (ADAMS Accession Nos. ML13235A007, ML13247A291, ML14064A181, and ML14248A478. respectively), the licensee submitted its RAI responses and first three six-month updates to the OIP.
J. Shea The NRC staff's review led to the issuance of the Sequoyah ISE and RAI dated November 21, 2013 (ADAMS Accession.No .. ML13312A415). By letter dated March 26, 2014 (ADAMS Accession No. ML14083A620), the NRC notified all .licensees and construction permit holders that the staff is conducting iri-:office and. onsite audits of. th~ir responses tQ Order EA-12-051 in accordance with NRC NRR Office Instruction UC-~ 11,_as discussed above.
The ongoing audit process, to include the in-office and onsite portions, allows the staff to assess whether it has enough information to make a safety evaluation of the Integrated Plans. The audit allows the staff to review open and confirmatory items from the mitigation strategies ISE, RAI responses from the spent fuel pool instrumentation ISE, the licensee's integrated plans, and other audit questions. Additionally, the staff gains a better understanding of submitted and updated information, audit information provided on ePortals, and preliminary Overall Program Documents/Final Integrated Plans while identifying additional information necessary for the licensee to supplement its plan and address staff potential concerns.
In support of the ongoing audit of the licensee's OIPs as supplemented, the NRC staff conducted an onsite audit at Sequoyah from December 1-5, 2014, per the audit plan dated November 6, 2014 (ADAMS Accession No. ML14302A197). The purpose of the onsite portion of the audit was to provide the NRC staff the opportunity to continue the audit review and gain key insights most easily obtained at the plant as to whether the licensee is on the correct path for compliance with the Mitigation Strategies and SFPI orders. The onsite activities included detailed analysis and calculation discussion, walk-throughs of strategies and equipment laydown, visualization of portable equipment storage and deployment, review of staging and deployment of offsite equipment, and review of installation details for SFPI equipment.
The enclosed audit report provides a summary of the activities for the onsite audit portion.
Additionally, this report contains an attachment listing all open audit items currently under NRC staff review.
J. Shea If you have any questions, please contact me at 301-415-1924 or by e-mail at Tony.Brown@nrc.gov.
Sincerely, Tony Bro n, Project Manager Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
Audit report cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 AUDIT REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO ORDERS EA-12-049 AND EA-12-051 MODIFYING LICENSES WITH REGARD TO REQUIREMENTS FOR MITIGATION STRATEGIES FOR BEYOND-DESIGN-BASIS EXTERNAL EVENTS AND RELIABLE SPENT FUEL POOL INSTRUMENTATION TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 and 50-328 BACKGROUND AND AUDIT BASIS On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events" and Order EA-12-051, "Order to Modify Licenses With Regard To Reliable Spent Fuel Pool Instrumentation," (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML12054A736 and ML12054A679, respectively). Order EA-12-049 directs licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool (SFP) cooling capabilities in the event of a beyond-design-basis external event (BDBEE). Order EA-12-051 requires, in part, that all operating reactor sites have a reliable means of remotely monitoring wide-range SFP levels to support effective prioritization of event mitigation and recovery actions in the event of a BDBEE. The orders require holders of operating reactor licenses and construction permits issued under Title 10 of the Code of Federal Regulations Part 50 to submit for review, Overall Integrated Plans (OIPs) including descriptions of how compliance with the requirements of Attachment 2 of each order will be achieved.
By letter dated February 28, 2013, (ADAMS Accession No. ML13063A183), Tennessee Valley Authority (TVA, the licensee) submitted its OIP for Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah) in response to Order EA-12-049. By letters dated August 28, 2013, February 28, 2014, and August 28, 2014 (ADAMS Accession Nos. ML13247A286, ML14064A295, and ML14247A644, respectively), TVA submitted its first three six-month updates to the OIP. By letter dated August 28, 2013 (ADAMS Accession No. ML13234A503),
the NRC notified all licensees and construction permit holders that the staff is conducting audits of their responses to Order EA-12-049 in accordance with NRC Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits" (ADAMS Accession No. ML082900195). This audit process led to the issuance of the Sequoyah interim staff evaluation Enclosure
(ISE) (ADAMS Accession No. ML14002A109) and continues with in-office and onsite portions of this audit.
By letter dated February 28, 2013 (AQAMS Accessio~ No. ML13063A011 ), the licensee submitted its OIP for Sequoyah in response to Order EA-12-051. By letter dated July 17, 2013 (ADAMS Accession No. ML13198A354), the NRC staff sent a request for additional information (RAI) to the licensee. By letters dated August 16, 2013, August 28, 2013, February 28, 2014, and August 28, 2014 (ADAMS Accession Nos. ML13235A007, ML13247A291, ML14064A181, and ML14248A478, respectively), the licensee submitted its RAI responses and first three six-month updates to the OIP. The NRC staff's review led to the issuance of the Sequoyah ISE and RAI dated November 21, 2013 (ADAMS Accession No. ML13312A415). By letter dated March 26, 2014 (ADAMS Accession No. ML14083A620), the NRC notified all licensees and construction permit holders that the staff is conducting in-office and onsite audits of their responses to Order EA-12-051 in accordance with NRC NRR Office Instruction LIC-111, as discussed above.
The ongoing audit process, to include the in-office and onsite portions, allows the staff to assess whether it has enough information to make a safety evaluation of the Integrated Plans. The audit allows the staff to review open and confirmatory items from the mitigation strategies ISE, RAI responses from the spent fuel pool instrumentation (SFPI) ISE, the licensee's integrated plans, and other audit questions. Additionally, the staff gains a better understanding of submitted and updated information, audit information provided on ePortals, and preliminary Overall Program Documents(OPDs)/Final Integrated Plans (FIPs) while identifying additional information necessary for the licensee to supplement its plan and address staff potential concerns.
In support of the ongoing audit of the licensee's OIPs, as supplemented, the NRC staff conducted an onsite audit at Sequoyah from December 1-5, 2014, per the audit plan dated November 6, 2014 (ADAMS Accession No. ML14302A197). The purpose of the onsite portion of the audit was to provide the NRC staff the opportunity to continue the audit review and gain key insights most easily obtained at the plant as to whether the licensee is on the correct path for compliance with the Mitigation Strategies and SFPI orders. The onsite activities included detailed analysis and calculation discussion, walk-throughs of strategies and equipment laydown, visualization of portable equipment storage and deployment, review of staging and deployment of offsite equipment, and review of installation details for SFPI equipment.
Following the licensee's declarations of order compliance, the NRC staff will evaluate the OIPs, as supplemented; the resulting site-specific OPDs/FIPs; and, as appropriate, other licensee submittals based on the requirements in the orders. For Order EA-12-049, the staff will make a safety determination using the Nuclear Energy Institute (NEI) developed guidance document NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" issued in August 2012 (ADAMS Accession No. ML12242A378), as endorsed, by NRC Japan Lessons-Learned Directorate (JLD) interim staff guidance (ISG) JLD-ISG-2012-01 "Compliance with Order EA-12-049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events"' (ADAMS Accession No. ML12229A174).
For Order EA-12-051, the staff will make a safety determination using the NEI developed guidance document NEI 12-02, Revision 1, "Industry Guidance for Compliance with NRC Order EA-12-051, 'To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation"'
(ADAMS Accession No. ML12240A307), as endorsed, with exceptions and clarifications, by NRC ISG JLD-ISG-2012-03, "Compliance with Order EA-12-051, 'Reliable Spent Fuel Pool Instrumentation"' (ADAMS Accession No. ML12221A339) as providing one acceptable means of meeting the order requirements. Should the licensee propose an alternative strategy for compliance, additional staff review will be required to evaluate the alternative strategy in reference to the applicable order.
AUDIT ACTIVITIES The onsite audit was conducted at the Sequoyah facility from December 1, 2014, through December 5, 2014. The NRC audit team staff was as follows:
Title Team Member Organization Team Lead/Project Manager Tony Brown NRR/JLD Technical Support - Balance of Plant Garry Armstrong NRR/JLD Technical Support - Reactor Systems Joshua Miller NRR/JLD Technical Suooort - Electrical Prem Sahav NRR/JLD Technical Support - l&C Stephen Wyman NRR/JLD The NRC staff executed the onsite portion of the audit per the three part approach discussed in the November 6, 2014, plan, to include conducting a tabletop discussion of the site's integrated mitigating strategies (MS) compliance program, a review of specific technical review items, and discussion of specific program topics. Activities that were planned to support the above included detailed analysis and calculation discussions, walk-throughs of strategies and equipment laydown, visualization of portable equipment storage and deployment, staging and deployment of offsite equipment, and physical sizing and placement of SFPI equipment.
AUDIT
SUMMARY
1.0 Entrance Meeting (December 1. 2014)
At the audit entrance meeting, the NRC staff audit team introduced itself followed by introductions from the licensee's staff. The NRC audit team provided a brief overview of the audit's objectives and anticipated schedule.
2.0 Integrated Mitigating Strategies Compliance Program Overview Per the audit plan and as an introduction to the site's program, the licensee provided a presentation to the NRC audit team describing the site's strategies to meet the NRC orders.
The licensee reviewed its strategy to maintain core cooling, containment, and SFP cooling in the event of a BDBEE, and the plant modifications being done in order to implement the strategies.
Also reviewed was the design and location of the storage facilities for the FLEX equipment, the interface with the National Strategic Alliance for FLEX Emergency Response (SAFER)
Response Center including staging areas, the spent fuel pool level indication modification, the modifications planned to enhance emergency communications, preventative maintenance plans for the FLEX equipment, procedural enhancements such as development of FLEX support guidelines, and operator training.
for the FLEX equipment, procedural enhancements such as development of FLEX support guidelines, and operator training.
3.0 Onsite Audit Technical Discussion Topics Based on the audit plan, and with a particular emphasis on the Part 2 "Specific Technical Review Items," the NRC staff technical reviewers conducted interviews with licensee technical staff, site walk-downs, and detailed document review for the items listed in the plan. Results of these technical reviews and any additional review items needed from the licensee are documented in the audit item status table in Attachment 3, as discussed in the Conclusion section below.
3.1 Reactor Systems Technical Discussions and Walk-Downs NRC staff met with licensee staff to discuss the amount of leakage from the reactor coolant pump (RCP) seals, the timing of the injection of borated water into the reactor coolant system (RCS), and the availability of borated water sources. NRC staff reviewed the boration calculations and flow calculations along with applicable procedures. NRC staff determined that the amount of leakage from the RCP seals needed to be finalized, and that would affect the other parameters.
3.2 Electrical Technical Discussions and Walk-Downs
- a. NRC staff reviewed the calculations on extending battery life based on load shedding, and walked down the battery rooms to evaluate strategies for hydrogen and temperature control. NRC staff also walked down panels used for load shedding to evaluate feasibility and timing.
- b. NRC staff walked down connection points and locations for FLEX electrical generators. In order to provide electrical power, the licensee will pre-stage two 225kva diesel generators on the roof of the auxiliary building along with two 3MW diesel generators staged in an additional diesel generator building. This is an alternative approach to NEI 12-06, Rev. 0. All pre-staged locations are protected from external events. The staff reviewed the licensee's load and sizing calculations for the FLEX generators and found them acceptable. The staff also walked down the storage locations for the FLEX diesel generators (DGs).
3.3 SFPI Technical Discussions and Walk-Downs NRC staff walked down instrument, transmitter, electronics, and display locations for the SFP level instrumentation, along with the associated cable runs. No concerns were identified during the walkdown. NRC staff also reviewed the associated calibration, maintenance and test procedures for the SFP level instrumentation.
3.4 Other Technical Discussion Areas and Walk-Downs
- a. NRC staff met with licensee staff to discuss the required robust source of water for the turbine-driven auxiliary feedwater (TDAFW) pump. The licensee indicated that the condensate storage tank (CST) will be reinforced to shield from tornado missiles and provide additional seismic support in order to provide the initial source of steam generator (SG) makeup through the TDAFW pumps. The FLEX pumps can be aligned to the CST in the event that the TDAFW pumps are unavailable. Other sources of water will be provided to makeup to the CST based on prioritization, which includes: primary water storage tanks, demineralized water storage tanks, essential raw cooling water (ERCW) in robust piping, and Tennessee River. The staff conducted a walkdown of the locations of the water sources to be used as well as the connection points inside the auxiliary building. The staff also reviewed the procedures for providing makeup to the SGs, as well as alternate methods as needed.
- b. NRC staff toured the designated location of the FLEX equipment storage building (FESS) and reviewed the building plans and noted that it will be a robust building (as defined in NEI 12-06). The staff noted the building is not located above the design-basis flood levels, but the licensee has sufficient time during a flooding event to move all of the FLEX equipment to higher elevations.
- c. NRC staff walked down the FLEX strategies for core cooling, RCS inventory, and SFP inventory functions. This included the point of deployment for the portable FLEX pumps, hose routing and deployment connection points (primary and alternate).
- d. NRC staff reviewed the strategy that will be implemented by the licensee to refuel the portable diesel-powered FLEX equipment. The NRC staff reviewed the instructions for refueling the equipment as well as the equipment needed to perform the refueling. The NRC staff noted that the licensee had not developed any guidance for maintaining adequate fuel quality and the licensee initiated actions to ensure adequate guidance is developed.
- e. The licensee's cooldown strategy relies on operation of the SG atmospheric relief valves (ARVs). The licensee indicated that nitrogen bottles will be used to provide motive force for the ARVs and that one bottle will be used for each ARV and will be sufficient to cool down the plant. Additionally, no electrical power will be required to operate the valves locally. The staff observed these mechanisms during the walkdown in the auxiliary building and also reviewed the site procedures for operation of the ARVs.
4.0 Exit Meeting (December 5. 2014)
The NRC staff audit team conducted an exit meeting with licensee staff following the closure of onsite audit activities. The NRC staff highlighted items reviewed and noted that the results of the onsite audit trip will be documented in this report. The NRC staff also discussed the remaining open items with the licensee and information needed for closure. The open items are listed in Attachment 3 of this report.
CONCLUSION The NRC staff completed all three parts of the November 6, 2014, onsite audit plan. Each audit item listed in Part 2 of the plan was reviewed by NRC staff members while on site. In addition to the list of NRC and licensee onsite audit staff participants in Attachment 1, Attachment 2 provides a list of documents reviewed during the onsite audit portion.
In support of the continuing audit process, as the licensee proceeds towards orders compliance for this site, Attachment 3 provides the status of all open audit review items that the NRC staff is evaluating in anticipation of issuance of a combined safety evaluation for both the Mitigation Strategies and Spent Fuel Pool Level Instrumentation orders. The five sources for the audit items referenced below are as follows:
- a. Interim Staff Evaluation (ISE) Open Items (Ols) and Confirmatory Items (Cls)
- b. Audit Questions (AQs)
- c. Licensee-identified Overall Integrated Plan (OIP) Open Items (Ols}
- d. Spent Fuel Pool Level Instrumentation (SFPLI) Requests for Additional Information (RAls)
- e. Additional Safety Evaluation (SE) needed information The attachments provide audit information as follows:
- a. Attachment 1: List of NRC staff and licensee staff audit participants
- b. Attachment 2: List of documents reviewed during the onsite audit
- c. Attachment 3: MS/SFPI SE Audit Items currently under NRC staff review (licensee input needed as noted)
While this report notes the completion of the onsite portion of the audit per the audit plan dated November 6, 2014, the ongoing audit process continues as per the letters dated August 28, 2013, and March 26, 2014, to all licensees and construction permit holders for both orders.
Additionally, while Attachment 3 provides a list of currently open items, the status and progress of the NRC staff's review may change based on licensee plan changes, resolution of generic issues, and other NRC staff concerns not previously documented. Changes in the NRC staff review will be communicated in the ongoing audit process.
Attachments:
- 1. NRC and Licensee Staff Onsite Audit Participants
- 2. Onsite Audit Documents Reviewed
- 3. MS/SFPI Audit Items currently under NRC staff review
Onsite Audit Participants NRC Staff:
Tony Brown NRR/JLD/JOMB NRR/JLD/JERB Garry Armstrong NRR/JLD/JCBB NRR/JLD/JERB Joshua Miller NRR/JLD/JERB Sequoyah and TVA Staff:
John Holcomb NPG Project Manager, SQN Fukushima Team Kevin Casey Corporate LicensinQ Brian Flynn Principal Project Manager, Fukushima Behrouz Ahmadi Fukushima Senior Project Manager Mike Sedlacik Fukushima Engineering Manager Jesse Alexander Fukushima Project Lenard Bush Fukushima Project Phil Hitchcock Fukushima Project Ron Gladney Fukushima Project Paul Parashak Operations Procedures Charles Price Maintenance Procedures Neil Gannon Corporate Fukushima Project Director Dennis Jones Corporate EP Manager Attachment 1
Documents Reviewed
- SQN-DC-V-48.0, "FLEX Response System," Rev. 4
- AOP-N.02, "Tornado Watch/Warning," Rev. 30
- AOP-N.03, "External Flooding," Rev. 53
- Design Change Notice 23096
- Design Change Notice 23414
- Service Request 963905
- Service Request 938927
- Service Request 981252
- Service Request 981262
- Problem Evaluation Report 939667
- FSl-1, "Long Term RCS Inventory Control," Rev. OOOOC
- FSl-2, "Alternate AFW Suction Source," Rev. 0000
- FSl-3, "Alternate Low Pressure Feedwater," Rev. 0000
- FSl-5.01, "Initial Assessment and FLEX Equipment Deployment," Rev. OOOOB
- FSl-5.03, "6.9kV and 480V Shutdown Board Initial FLEX Alignment," Rev. OOOOC
- FSl-5.04, "6900V FLEX D/G Plant Equipment Loading," Rev. 0000
- FSl-6, "Alternate CST Makeup," Rev. 0000
- FSl-7, "Loss of Vital Instrumentation or Control Power," Rev. 0000
- FSl-8, "Alternate RCS Boration," Rev. 0000
- FSl-9, "Low Decay Heat Temperature Control," Rev. OOOOD
- FSl-10, "Cold Leg Accumulator Isolation," Rev. 0000
- FSl-11, "Alternate SFP Makeup and Cooling," Rev. OOOOE
- FSl-12, "Alternate Containment Cooling," Rev. OOOOA
- FSl-13, "Transition from FLEX Support Instructions," Rev. OOOOC
Rev. O
- GENSTP3-001, "Upper Boundary Temperature for Mild Environments Related to Environmental Qualification of Electrical Equipment," Rev. 00
- SQN-CPS-057, "Vital Control Power System Loading Channel I and Continuous Loading Evaluation of Protective Devices in the 120V AC Vital Instrument Power Boards," Rev. 084
- SQN-CPS-058, "Vital Control Power System Loading Channel II and Continuous Loading Evaluation of Protective Devices in the 120V AC Vital Instrument Power Boards," Rev. 097
- SQN-CPS-059, "Vital Control Power System Loading Channel Ill and Continuous Loading Evaluation of Protective Devices in the 120V AC Vital Instrument Power Boards," Rev. 074
- SQN-CPS-063, "Hydrogen Generation, Vital Batteries," Rev. 0 Attachment 2
- EDQ0009992013000086, "Technical Justification for Extended Station Blackout Diesel Generators," Rev. 001
- EDN0003602014000120, "6900V 3MW Flex Diesel Generator A and B Electrical Cable System Analysis," Rev. 000
- EDQ0009992014000102, "FLEX Analysis for 125VDC Vital Batteries," Rev. 000
- ECA-0.0, "Loss of All AC Power," Rev. 26
- EA-250-1 , "Load Shed of Vital Loads After Station Blackout," Rev. 16
- O-Ml-FMl-360-023.0, "FLEX Portable Diesel Equipment Refueling" Rev. 0000
- CN-SEE-11-13-9, "Determination of the Time to Boil in the Sequoyah Units 1 & 2 Spent Fuel Pool after an Earthquake," Rev. O
- CN-SEE-11-13-37, "Sequoyah Unit 1 and Unit 2 Reactor Coolant System FLEX Evaluation with Standard Reactor Coolant Pump Seals," Rev. 0
- DAR-FSE-13-3, "FLEX Mechanical Conceptual Design Report for the Sequoyah Unit 1 and 2 Nuclear Plant," Rev. 0-A
- DAR-SEE-11-13-6, "Evaluation of Alternate Coolant Sources for Responding to a Postulated Extended Loss of All AC Power at Sequoyah Nuclear Power Plant," Rev. 0
- MDQ0026970001A, "High Pressure Fire Protection Supply to the Steam Generators for Flood Mode Operation," Rev. 003
- MDQ0003602013000088, "Maximum Temperature for 225 KVA DG Enclosures,"
Rev. 000
- NDQ0000782014000106, "Beyond Design Basis Dose Evaluation for Spent Fuel Pool Level Instrumentation," Rev. 001
- "Sequoyah Nuclear Plants Units 1 & 2 - Spent Fuel Pool Instrumentation Test and Qualification Summary"
- SAFER Response Plan for Sequoyah Nuclear Plant, Draft, 11/7/2014
- CDQ000020080083, "SON Stage I and II Warning Time Assessment," Rev. O
- AMEC Project 3050140254, "Report of Geotechnical Exploration - Deployment Paths Analysis and Condensate Storage Tanks TVA Sequoyah Nuclear Plant," October 15, 2014
- RvM-SOP-10.05.06, "Nuclear Notifications and Flood Warning Procedure," Rev. 0001
- TR-FSE-13-13, "Sequoyah FLEX Integrated Plan," Rev. O
- "Sequoyah Nuclear Plant Units 1 and 2 FLEX Overall Integrated Plan," Draft, Rev. 4B
- O-Ml-FMl-360-005.0, "FLEX-Align Flex High Pressure Pumps From BATS to Unit 1 or Unit 2 RCS Using Why Connection," Rev. 0
- 03D53EPMNQL021993, "Analysis to Support Changing TDAFW LCVs Actuator and Sizing Criteria of the Air Cylinder (for the TDAFW LCVs and MSS ARV's)," Rev. 10
Mitigation Strategies/Spent Fuel Pool Instrumentation Safety Evaluation Audit Items:
Audit Items Currently Under NRC Staff Review, Requiring Licensee Input As Noted Audit Item Item Description Licensee Input Needed Reference Core Sub Criticality - Complete the reanalysis to support the revised core boration coping strategy of providing The licensee provided a calculation showing the boration early in the ELAP [extended loss of alternating boration needed to remain subcritical at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ISE 01 3.2.1.8.A current power] event including the deployment The licensee is updating the calculation to ensure considerations and the rate of boration as it affects sizing that boration is not needed before 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the high pressure (HP) FLEX pump is to be completed. remain subcritical. Will review when available.
Open Item #4 in the 8/28/14 6-month update Containment Functions - Containment evaluations for states that Westinghouse Calculation LTR-Phases 1, 2 and 3 have not been done. Complete the ISENG-14-2, Rev 0, has been completed which ISE 01 3.2.3.A results of the evaluations needed to confirm that demonstrates that containment functions will be containment functions are maintained during the course maintained throughout all Phases of the ELAP.
of the ELAP event. This calculation should be added to the ePortal for staff review.
Off-Site Resources - Confirm the licensee's Reviewed draft SAFER playbook. The required ISE Cl 3.4.A arrangements for off-site resources address the guidance equipment is identified. The NRC staff requests of Guidelines 2 throuQh 10 in NEI 12-06, Section 12.2. to review this document once it is finalized.
A thorough analysis of the makeup flow rate The licensee indicated that the evaluation for SFP requirements and other equipment characteristics will be cooling actions will be completed by February OIP 01 #7 finalized during the detailed design phase of 2015. The staff will review the evaluation when FLEX. it's made available in the office to close this item.
Attachment 3
Audit Item Item Description Licensee Input Needed Reference Containment temperature instrumentation is only Open Item #1 O in the 8/28/14 6-month update available until flood waters enter the technical support states that this issue is "Started", but not yet OIP 01 #10 center (TSC) inverter or station battery rooms. A method closed. Once the licensee completes the to monitor containment temperature, post-flood, will be development of their plan, it should be submitted developed. to the staff for review.
An evaluation of the impact of FLEX response actions on The licensee indicated that the evaluation for design basis flood mode preparations will be performed. flood preparations will be completed by February OIP 01 #13 This evaluation will include the potential for extended 2015. The staff will review the flood evaluation preparation time for FLEX. Changes which affect the when it's made available in the office to close this lnteqrated Plan will be included in the six month update. item.
Perform an alternate cooling source evaluation. The The staff reviewed the evaluation provided and purpose of this analysis is to examine options to utilize OIP 01 #14 requests additional information regarding alternate water sources to provide continuous sources of additional analyses of existing sludge levels.
water to maintain key safety functions.
The licensee indicated that Westinghouse is Perform conceptual hydraulic performance analyses. The completing the hydraulic analysis and will be OIP 01 #15 purpose of this analysis is to conservatively evaluate available by February 2015. The staff will review hydraulic performance of FLEX systems. the hydraulic analysis when it's made available in the office to close this item.
The NRC staff requests that the licensee Perform an RCS makeup analysis. The purpose of this demonstrate that the required SI pump injection OIP 01 #18 analysis is to define FLEX RCS inventory and shutdown time, considering RCS shrinkage and RCP seal margin for Sequoyah. leakage, will not result in pump room heatup beyond the operating capability of the pumps.
The purpose of this analysis is to summarize the Perform a timing and deployment evaluation. The FLEX timeline for Sequoyah, identify time purpose of this analysis is to summarize the FLEX constraints and provide for the safety function OIP 01 #20 timeline for Sequoyah, identify time constraints and needs. The draft OIP states this evaluation has provide for the safety function needs. been started. The NRC staff requests to review this evaluation once it is finalized.
Audit Item Item Description Licensee Input Needed Reference The purpose of this report is to summarize the Develop a programmatic control report. The purpose of need to implement programmatic control of the OIP 01 #21 this report is to summarize the need to implement FLEX program. The NRC staff requests to review programmatic control of the FLEX program.
this document once it is finalized.
During site audit on 12/4/14, the licensee staff Further analysis will be performed to determine the stated that the SQN Staffing study table top required timeline for implementing the 6.9 KV FLEX DGs confirmed starting of the 6.9kV FLEX DGs within OIP 01 #24 as an alternate power source for the loads supplied by 5 hrs as defined in the Sequence Of Events the 480v FLEX DGs. (SOE) document. Provide a copy of SOE document on ePortal.
(Westinghouse Standard RCP Seals: NSAL-14-1) On February 10, 2014, Westinghouse issued Nuclear Safety Advisory Letter (NSAL)-14-1, which informed licensees of plants with standard Westinghouse RCP seals that 21 No additional input from the licensee is needed at SE#3 gpm may not be a conservative leakage rate for ELAP this time. Further review of the information analysis. This value had been previously used in the provided is required by the NRC staff.
ELAP analysis referenced by many Westinghouse PWRs, including the generic reference analysis in WCAP-17601-P.
Audit Item Item Description Licensee Input Needed Reference Please provide adequate justification for the seal leakage rates calculated according to the Westinghouse seal leakage model that was revised following the issuance of NSAL-14-1. The justification should include a discussion of the following factors:
- a. benchmarking of the seal leakage model against relevant data from tests or operating events, Pressurized-Water Reactor Owners Group
- b. discussion of the impact on the seal leakage rate due (PWROG) is still developing and validating that to fluid temperatures greater than 550°F resulting in leakage rates in PWROG-series reports are valid.
SE#4 increased deflection at the seal interface, More generic effort may be necessary to support
- c. clarification whether the second-stage reactor coolant issue resolution.
pump seal would remain closed under ELAP conditions predicted by the revised seal leakage model and a technical basis to support the determination, and,
- d. justification that the interpolation scheme used to compute the integrated leakage from the reactor coolant pump seals from a limited number of computer simulations (e.Q., three) is realistic or conservative.
Audit Item Item Description Licensee Input Needed Reference The NRC staff understands that Westinghouse has recently recalculated seal leakoff line pressures under loss of seal cooling events based on a revised seal leakage model and additional design-specific information for certain plants.
- a. Please clarify whether the piping and all components (e.g., flow elements, flanges, valves, etc.) in your seal leakoff line are capable of withstanding the pressure predicted during an ELAP event according to the revised seal leakage model. Staff has remaining questions regarding
- b. Please clarify whether operator actions are credited adequacy of PWROG method for computing with isolating low-pressure portions of the seal leakoff maximum pressures in PWROG-series reports.
SE#5 line, and if so, please explain how these actions will be The licensee is requested to provide justification executed under ELAP conditions. that the seal leak off line can withstand the
- c. If overpressurization of piping or components could pressures that are predicted by the PWROG work occur under ELAP conditions, please discuss any to be seen in the event.
planned modifications to the seal leakoff piping and component design and the associated completion timeline.
- d. Alternately, please identify the seal leakoff piping or components that would be susceptible to overpressurization under ELAP conditions, clarify their locations, and provide justification that the seal leakage rate would remain in an acceptable range if the affected piping or components were to rupture.
J. Shea If you have any questions, please contact me at 301-415-1924 or by e-mail at Tony.Brown@nrc.gov.
Sincerely, IRA/
Tony Brown, Project Manager Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
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