ML11308B386

Independent Spent Fuel Storage Installation Restart Readiness Determination Plan - Completed Activities Long-Term Action Plan to Be Completed After Unit Restart

ML11308B386
Person / Time
Site:	North Anna
Issue date:	11/03/2011
From:	Price A Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
11-520C
Download: ML11308B386 (15)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 3, 2011 10 CFR 100, Appendix A U.S. Nuclear Regulatory Commission Serial No.:

11-520C Attention: Document Control Desk NL&OS/GDM RO Washington, DC 20555 Docket Nos.:

50-338/339 72-16/72-56 License Nos.:

NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION RESTART READINESS DETERMINATION PLAN - COMPLETED ACTIVITIES LONG-TERM ACTION PLAN TO BE COMPLETED AFTER UNIT RESTART By letter dated September 17, 2011 (Serial No.11-520), Virginia Electric and Power Company (Dominion) submitted a summary report of the response of North Anna Power Station to the August 23, 2011 Central Virginia earthquake as well as a Restart Readiness Determination Plan that would demonstrate no functional damage had occurred to station structures, systems and components necessary to perform required safety functions and that operation of North Anna Units 1 and 2 could resume.

Subsequent to the initial submittal, Dominion provided additional information, status updates and responses to NRC requests for additional information, which included several ongoing activities as part of the Restart Readiness Determination Plan.

As indicated in Attachment 1, these activities are now complete, with the exception of activities that can only be completed during unit restart (i.e., surveillance tests). The activities that will be completed during unit restart are identified in Attachment 2.

In addition, a compilation of long-term programmatic actions that Dominion has committed to perform to address the August 23, 2011 earthquake is provided in. The compilation includes the scheduled completion dates for the actions, as well as the associated letters that contain the commitments. These long term actions will be completed following the restart of North Anna Units 1 and 2.

Serial Number 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 2 of 3 If you have any questions or require additional information, please contact Mr. Gary D.

Miller at (804) 273-2771.

Sincerely, J.

an rice Vi Pr sident-Nuclear Engineering Attachments:

1. Restart Readiness Determination Plan - Completed Activities

2. Surveillance Tests to be Performed During Unit 1 and Unit 2 Startup

3. Long-Term Commitments Contained in Dominion Correspondence Associated with the August 23, 2011 Earthquake There are no new commitments contained in this letter.

COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. Alan Price who is Vice President - Nuclear Engineering, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this 3 day of 1

'Y 2YI2XY, 2011.

My Commission Expires:

1 j'3 J2l GIF44r Lynn Rutherford NOTARY PUBUC Notary Public Cm§smonwealth of Virginia w

Reg. # 310847 M* gommt1eo Expies 4V/2Ois

Serial Number 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 3 of 3 cc:

Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station M. Khanna Branch Chief - Mechanical and Civil Engineering Branch U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E-3 11555 Rockville Pike Rockville, MD 20852-2738 R. E. Martin NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 P. G. Boyle NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 J. B. Davis NRC Senior Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop EBB-E3-D2M 11555 Rockville Pike Rockville, MD 20852-2738 J. E. Reasor, Jr.

Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.

Glen Allen, Virginia 23060

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Restart Readiness Determination Plan - Completed Activities Virginia Electric and Power Company (Dominion)

North Anna Power Station Units 1 and 2

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 1 of 4 Restart Readiness Determination Plan - Completed Activities Actions Identified in Previous Dominion Docketed Letters Completed Actions identified in Previous Letters Letter No.

Status Emergency Core Cooling System (ECCS) Pump Room Emergency Air Conditioning System 11-566 Completed (PREACS) Train A filter (1-HV-FL-3A) in-place test is scheduled to be performed prior to either unit Page 1 Satisfactorily entering Mode 4.

Perform measurement of the Control Room Envelope pressure relative to the external areas.11-566 Completed Page 2 Satisfactorily The following testing will be performed prior to Unit 1 and 2 startup to ensure operability of the electrical systems:

" Functional testing of undervoltage circuitry, including testing which interrupts normal emergency bus power sources, which verifies bus load shed, Emergency Diesel Generator (EDG) start and 11-566 Completed load, and proper load sequencing.

Page 4 Satisfactorily

" Engineered Safety Features Actuation System (ESFAS) functional testing which initiates the ESFAS and verifies the required equipment actuates.

" EDG functional testing per SR 3.8.1.2, SR 3.8.1.3, SR 3.8.1.6, SR 3.8.1.7, SR 3.8.1.9, SR 3.8.1.12, SR 3.8.1.15, and SR 3.8.1.17.

Switchyard is being inspected and repairs made as necessary.11-566 Completed Page 4 Satisfactorily Repair component cooling 1-(CC)-TV-102A, 1-Main Steam (MS)-TV-101A and 1-MS-TV-101 B prior to 11-566 Completed restart.

Page 9 Satisfactorily Adjust 1-CC-TV-104B prior to startup.11-566 Completed Page 9 Satisfactorily Perform Unit 2 valve stroke time testing prior to Unit 2 restart.11-566 Completed Page 9 Satisfactorily Complete Appendix J testing for Units 1 and 2 prior to restart:

11-566 Completed (Equipment Hatch, Personnel and Escape Hatch, Containment Purge Valves.

Page 10 Satisfactorily Perform performance discharge testing on the Unit 2 "H" train batteries (2-1, 2-11, and 2H EDG)11-566 Completed Page 15 Satisfactorily Perform calibration of the Unit 2 Reactor Trip System and ESFAS instrumentation.11-566 Completed Page 23 Satisfactorily Perform calibration for Unit 2 Technical Specifications (TS) support and Balance of Plant 11-566 Completed instrumentation.

Page 23 Satisfactorily

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 2 of 4 Completed Actions identified in Previous Letters Letter No.

Status Complete repairs to walls with cracks as required.11-566 Completed Page 28 Satisfactorily Complete repairs to the main transformer deluge system.11-566 Completed Page 28 Satisfactorily Provide detailed Unit 2 steam generator (S/G) inspection results to the NRC.11-566 Completed Page 31 Satisfactorily Perform functional testing on 5 additional snubbers due to low fluid levels.11-566 Completed

_Page 36 Satisfactorily The following Technical Specifications (TS) surveillances will be completed prior to unit restart:

11-566A Completed SR 3.8.1.2, 3.8.1.3, 3.8.1.6, 3.8.1.7, 3.8.1.9, 3.8.1.12, 3.8.1.15, 3.8.1.17.

Page 2 Satisfactorily Work towards identifying the source of the foreign materials and address any generic issues.

11-566A Completed Page 11 Satisfactorily Repair the snubber with the bent attachment lug and functionally test the snubber that was removed 11-566A Completed from service.

Page 12 Satisfactorily Functional testing of additional twelve small bore snubbers and two large bore snubbers on Unit 1 will 11-566A Completed be completed prior to entering Mode 4 on Unit 1.

Page 13 Satisfactorily Before reactor startup, set the high power trip setpoints for the power range nuclear instrumentation 11-566B Completed conservatively low until such time that core analysis can confirm proper response of the detectors.

Page 5 Satisfactorily Continue to consider post restart Condition Reports for potential earthquake damage.

11-566B Ongoing Page 8 Ongoing Provide the NRC additional justification for not performing re-evaluation of pipe support structural 11-577 Completed analyses.

Page 9 Satisfactorily 11-577 Completed Perform system walkdowns for Unit 1 and Unit 2 in accordance with ER-AA-SYS-1 002.

11 Co rly Page 11 Satisfactorily 11-577 Completed Complete inspection of equipment to ensure integrity of off-site power.

Page 16 Satisfactorily Provide the Unit 2 NDE results in correspondence to the NRC.11-577 Completed Page 19 Satisfactorily Complete Appendix J testing prior to restart - Equipment Hatch, Personnel & Escape Hatches,11-577 Completed Containment Purge Valves.

Page 22 Satisfactorily

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 3 of 4 Completed Actions identified in Previous Letters Letter No.

Status Perform a visual examination of the sump strainer gaps.11-520 Completed Encl.8, Page 2 Satisfactorily Perform RCCA drag testing prior to Unit 2 core onload.

11-520A Completed Satisfactorily Complete the RCE on the Unit 2H Emergency Diesel Generator Coolant Leak.

11-520A Completed Satisfactorily Perform a 20% sample inspection of Unit 2 steam generators.

11-520A Completed Satisfactorily Completed Complete tests and inspections delineated in Response to RAI-8 (fuel and RVI components).

11-544A Satisfactorily The Operability Determination previously prepared for the fuel rod bow concern will be reviewed.11-520 Completed Encl 4, Page 4 Satisfactorily Perform containment inspections to identify and remove debris that may have resulted from the 11-520 Completed earthquake, as required.

Encl 7, Page 2 Satisfactorily A final containment cleanliness inspection (North Anna Operating Procedure %-OP-1 B, ("Containment 11 -520A Completed Checklist") is performed as normal station practice prior to Mode 4 entry.

Att. 1, Satisfactorily Page 19 The completion status for the Unit 2 surveillance and functional testing will be provided in a 11-520A Completed subsequent update.

Att. 1, Page 23 Satisfactorily 11-520A Completed Provide an update on the completion of the surveillance and functional testing in an update letter.

Page23 Corly Page 23 Satisfactorily

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 4 of 4 REQUIRED FOR MODE 2 Action To Be Completed Letter No.

Status Perform hot rod drop testing for Unit 1 and 2.11-520 Page 8 Assigned Perform 1/2-PT-46.21 - VT-2 system walkdowns.11-577 Page 9 Assigned Complete Unit 1 and 2 Surveillance Periodic Tests as determined by the Seismic Event Review Team.

11-520A Page 23 In-progress 1 1-566C&D Test Unit 1 and 2 Turbine Driven AFW Pump when steam is available.

Pages 31/6 Assigned DURING MODE 1 Action To Be Completed Letter No.

Status Hold reactor power for Unit 1 and Unit 2 at less than or equal to 30% power to perform core flux 11-566B mapping. Hold power at less than or equal to 75% and 96% power to validate proper core response Assigned and adjust nuclear instrumentation as necessary.

Page 5

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Surveillance Tests to be Performed During Unit I and 2 Startup Virginia Electric and Power Company (Dominion)

North Anna Power Station Units 1 and 2

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 1 of 3 Surveillance Tests to be Performed During Unit 1 and Unit 2 Startup Unit I - Surveillance Tests Just Prior to Mode 4 Install Solid State fuses and perform the "A" and "B" Train Solid State Surveillances (1 -PT-36. 1A and 1 -PT-36.1 B)

Prior to Mode 3

• Verify Boron Injection Tank-Boron Concentration (1-PT-58.2)

Prior to Mode 2

" Rod Control System Check-Out (RCS > 350'F) - IPM - RCS-G-001B

" Hot Rod Drops (RCS > 500°F) PT-17.2

" Rod Operability Test (performed with Hot Rod Drops PT-17.1)

" SI Accumulator MOV Breaker Verification (RCS > 2000 psig) 1-PT-56.2

" RCP Seal Injection flow Verification (RCS > 2215 psig) 1-PT-52.1

" RTD Cross Calibration (RCS at 547*F) PT-121

" VT-2 of ISI class 1, 2, and 3 Piping Inside Containment - Leak Check (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold at 2235 psig prior to walkdown) PT-46.21 Turbine Driven Auxiliary Feedwater Pump Test (within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after S/G Pressure achieves 1005 psig) PT-71.1Q Intersystem LOCA Leak Check-1-PT-61.4 Prior to exceeding 30%

" Turbine Valve Freedom Test and Turbine Overspeed Test (approximately 12%

Power) PT-34.3 and 1-PT-34.5 Calorimetric Heat Balance (within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after > 15% power) PT-24.1 Flux Map and Hot-Channel Factor Verification and NIS verifications Primary-to-Secondary Leakage Checks (within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after > 25% reactor power)

Prior to exceedinq 50%

Axial Flux Difference Verification PT-20.1 Quadrant Power Tilt Ratio Verification PT-20.3 Prior to exceeding 75%

Power Range NIS Verifications After achieving full power

" RCS Flow Verification PT-27 FW Ultrasonic Flow verification PT-32.4.9 and 1-PT-34.2.10

" Verification of Turbine First Stage Pressure Indication PT-34.5.1 Turbine-Generator Oil Pump Verification 1-PT-34.6 Flux Map and Hot Channel Factor Verification and NIS Verifications

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 2 of 3 Unit 2 - Surveillance Tests (Identical to Unit 1 - additional surveillances identified with an asterisk)

Just Prior to Mode 4 Install Solid State fuses and perform the "A" and "B" Train Solid State Surveillances (2-PT-36.1A and 2-PT-36.1B)

Prior to Mode 3 e Verify Boron Injection Tank - Boron Concentration (2-PT-58.2)

Prior to Mode 2

" Rod Control System Check-Out (RCS > 350F) - IPM - RCS-G-001B Hot Rod Drops (RCS > 500F) PT-17.2

" Rod Operability Test (performed with Hot Rod Drops PT-1 7.1)

" SI Accumulator MOV Breaker Verification (RCS > 2000 psig) 2-PT-56.2

" RCP Seal Injection Flow Verification (RCS > 2215 psig) 2-PT-52.1

" RTD Cross Calibration (RCS at 547) PT-121

• VT-2 of ISI class 1, 2, and 3 Piping Inside Containment - Leak Check (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold at 2235 psig prior to walkdown) PT-46.21

" Steam Driven Auxiliary Feedwater Pump Test (within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after S/G Pressure achieves 1005 psig) PT-71.1Q Intersystem LOCA Leak Check PT-61.4

• *Accumulator System Pressure Test (SI Accumulators > 600 psig) PT-307SI

• *MS Piping in MSVH (Class 2 and 3) System Pressure Test (MS Piping > 800 psig)- 2-PT-302MS

" *RHR Valve Leakage Check PT-61.5 Prior to Mode 1

• *Startup Physics Testing PT-94.0 Prior to exceeding 30%

" Turbine Valve Freedom Test and Turbine Overspeed Test (approximately 12% Power) PT-34.3 and 2-PT-34.5

• Calorimetric Heat Balance (within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after > 15% power) PT-24.1

" Flux Map and Hot Channel Factor Verification and NIS Verifications Primary-to-Secondary Leakage Checks (within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after > 25% reactor power)

Prior to exceeding 50%

" Axial Flux Difference Verification PT-20.1

" Quadrant Power Tilt Ratio Verification PT-20.3

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 3 of 3 Prior to exceeding 75%

NIS Verifications

• Flux Map and Hot Channel Factor Verification After achieving full power

" RCS Flow Verification PT-27

" FW Ultrasonic Flow Verification PT-32.4.9 and 2-PT-34.2.10

" Verification of Turbine First Stage Pressure indication PT-34.5.1

" Turbine-Generator Oil Pump Verification 2-PT-34.6

" Flux Map and Hot Channel Factor Verification and NIS Verifications

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Long-Term Commitments Contained in Dominion Correspondence Associated with the August 23, 2011 Earthquake Virginia Electric and Power Company

, (Dominion)

North Anna Power Station Units I and 2

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 1 of 2 Long-Term Commitments Contained in Dominion Correspondence Associated with the August 23, 2011 Earthquake North Anna Power Station Units 1 and 2 Item Dominion Letter Commitment Scheduled No.

Date/Serial No.

Completion Date As a long term action, Dominion plans to perform 10/18/11 sampling analysis of ASME Class 1, 2 and 3 piping (Serial No. 11-577A) systems in accordance with EPRI NP-6695, Section April 30, 2013 6.3.

As a long term action, in accordance with the 2

10/18/11 guidance in EPRI NP-6695, Dominion plans to April 30, 2013 (Serial No. 11-577A) perform a sampling analysis of equipment located in the Auxiliary Building.

3 10/18/11 Same as Item 6.d below (Serial No. 11-577A) 4 10/28/11 Dominion will provide an update regarding any March 31, 2012 (Serial No. 11-577B) special ground motion effects.

Dominion will implement a long term plan to address 10/28/11 the impact of the August 23, 2011 earthquake for 5

(Serial No. 11-577B) margin management on procurement of new and December 31,2011 replacement equipment and the design change process.

Dominion will revise the North Anna Updated Final Safety Analysis Report to document:

a. The recorded August 23, 2011 seismic April 30, 2012 event.

b. A summary of the evaluation and results of the seismic analysis of the recorded event April 30, 2013 completed per RG. 1.1.67/EPRI NP-6695.

10/28/111 6

(Serial No. 11-577B)

c.

Design controls on seismic margin April 30, 2012 management.

April_30,_2012

d.

Incorporation of Regulatory Guide (RG) 1.166, "Pre-Earthquake Planning and December 31, 2012 Immediate Nuclear Power Plant Operator (subject to receipt of Post-Earthquake Actions," and RG 1.167, seismic monitoring "Restart of a Nuclear Power Plant Shut equipment and Down by a Seismic Event," into the North outage schedules)

Anna licensing basis.

Dominion will perform a comparison of the 7

10/31/11 calculated load from the August 23, 2011 (Serial No. 11-566E) earthquake and the existing leak-before-break (LBB) analysis and submit the results.

Serial No. 11-520C Docket Nos. 50-338/339/72-16/72-56 Page 2 of 2 Item Dominion Letter Commitment Scheduled No.

Date/Serial No.

Completion Date Dominion will implement a design change to replace the existing seismic equipment and Main Control Room indication with upgraded and enhanced seismic monitoring instrumentation equipment, 8

10/31/11 including the installation of permanent, seismically December 31, 2012 (Serial No. 11-520B) qualified backup power to a new Seismic Monitoring Panel and a backup battery power supply. The project will also install seismic recording instrumentation at the station Independent Spent Fuel Storage Installation (ISFSI) pad.

Dominion will perform a re-evaluation of the plant 10/31/11 equipment identified in the IPEEE review with March 31, 2013 (Serial No. 11-520B)

HCLPF capacity <0.3g, which will include an assessment of potential improvements.

Dominion will develop a plan with the NSSS vendor 10 10/31/11 consisting of additional evaluations or inspections, February 29, 2012 (Serial No. 11-520B) as warranted, to assure long term reliability of the reactor internals.