ML080740029
| ML080740029 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 03/20/2008 |
| From: | Siva Lingam NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Lingam, Siva NRR/DORL 415-1564 | |
| References | |
| TAC MD7535 | |
| Download: ML080740029 (6) | |
Text
March 20, 2008 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNIT NO. 2, REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE REVISION OF TECHNICAL SPECIFICATION 4.4, PERTAINING TO THE CONTAINMENT LEAKAGE RATE TESTING PROGRAM (TAC NO. MD7535)
Dear Mr. Christian:
By letter dated December 17, 2007, Virginia Electric and Power Company (the licensee) proposed technical specification changes to permit a one-time 5-year exception to the 10-year frequency of the performance based leakage rate testing program for Type A tests, as required by Regulatory Guide 1.163 for Surry Power Station, Unit No. 2. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has determined that additional information is required to complete its evaluation.
The NRC staffs RAI is enclosed. The licensee is required to provide a response to the RAI within 30 days.
Sincerely,
/RA/
Siva P. Lingam, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-281
Enclosure:
RAI cc w/encl: See next page
- transmitted by memo dated OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/DSS/EMCB/BC NRR/LPL2-1/BC NAME SLingam MO=Brien KManoly MWong DATE 3/13/08 3/19/08 3/11/08*
3/20/08
Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION OF TECHNICAL SPECIFICATION PERTAINING TO THE CONTAINMENT LEAKAGE RATE TESTING PROGRAM SURRY POWER STATION, UNIT NO. 2 DOCKET NO. 50-281 By application dated December 17, 2007 (Agencywide Documents Access and Management System Accession Number ML073511682), Virginia Electric and Power Company (the licensee) proposed a license amendment to change Surry Power Station, Unit No. 2 (Surry 2) Technical Specifications (TSs). The proposed change would permit a one-time 5-year exception to the 10-year frequency of the performance based leakage rate testing program for Type A tests, as required by Regulatory Guide (RG) 1.163.
To complete our review of the proposed TS changes, the Nuclear Regulatory Commission (NRC) staff requests the licensees response to the following:
- 1. Please provide a summary list of those containment penetrations (including their test schedule intervals) that have not demonstrated acceptable performance history in accordance with the primary containment leakage rate program.
- 2. Please provide a summary table for Type B and Type C tests (including the interval schedule dates) that are planned to be performed prior to and during the requested 5-year extension period of the integrated leak rate test (ILRT) interval.
- 3. Regulatory Position C.3 of RG 1.163 recommends that visual examinations should be conducted prior to initiating a Type A test, and during two other refueling outages before the next Type A test based on a 10-year ILRT interval. Please describe, with a schedule, how you would supplement this 10-year interval-based visual inspections requirement for the requested 15-year ILRT interval.
- 4. Please provide information relative to the findings (if any) and actions taken where existence of or potential for degraded conditions in inaccessible areas of the containment structure and metallic liner were evaluated based on conditions found in accessible areas as required by Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(b)(2)(viii)(E) and 10 CFR 50.55a(b)(2)(ix)(A).
- 5. In Section 4.6 of Attachment 1 to the licensees letter dated December 17, 2007, it is stated that no augmented Category E-C examinations are planned for the second 10-year interval IWE examinations. Please provide a summary of areas that were identified for augmented examination in the first 10-year interval IWE. Considering the proposed TS change per the licensees letter dated December 17, 2007, to allow a 5-year extension of Type A test interval, please provide specific information to justify discontinuing the augmented examination of suspect area(s) during the second 10-year IWE interval.
- 6. Please provide a summary of any degradation identified during past inspections of the containment moisture barrier (e.g., between liner and concrete floor). If any, please describe the condition, corrective actions, and additional monitoring program.
- 7. Relative to the results of the last three Type A tests included in Section 4.2 of Attachment 1 to the licensees letter dated December 17, 2007, there is a significant reduction in measured as-found leakage from 0.414 La (May 1991) to 0.05 La (October 2000). Please provide further information relative to this reduction. Also, provide the actual as-left leakage results for the last three Type A tests, the Type B and Type C test results and their comparison with the allowable leakage rate specified in the plant TSs.
- 8. If bellows are used on penetrations through containment pressure-retaining boundaries at Surry 2, please provide information on their location, inspection, testing and operating experience with regard to detection of leakage through the penetration bellows.
- 9. Please provide an overview of the containment liner coating inspection program at Surry 2 including inspection intervals, findings and corrective actions identified during recent inspections.
- 10. In Section 4.6 of Attachment 1 to the licensees letter dated December 17, 2007, the following is stated:
The second ten-year interval IWE program for Surry meets the requirements of the 2001 Edition through the 2003 Addenda of [American Society of Mechanical Engineers] ASME Section XI. Categories E-D and E-G are no longer part of the Code. The relief requests above are not needed for the second ten-year interval since examination of seals and gaskets and bolt torque or tension tests are no longer addressed by ASME Section XI. As such, the extension request will no longer impact the ASME Section XI program upon second interval start for each unit. Given the short time period remaining in the first ten-year IWE lSI interval for Surry Unit 2, and the Type B and C tests performed during the first ten-year IWE lSI interval, the Appendix J, Type A extension is seen as having a negligible impact.
Please provide clarification for the following:
- a. The licensees letter dated December 17, 2007 is for Surry 2. It is not clear to the NRC staff why both units are being discussed in the above paragraph.
- b. Please discuss the examination method(s) in Surry 2 to ensure leak-tight integrity of penetrations with seals and gaskets, and bolted connections.
- c. Please clarify the last sentence of the subject paragraph (Given the short time period remaining ).
Surry Power Station, Unit 2 cc:
Mr. David A. Christian President and Chief Nuclear Officer Virginia Electrical and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
Building 475, 5th Floor Rope Ferry Road Waterford, Connecticut 06385 Mr. Donald E. Jernigan Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711