ML042470354
| ML042470354 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/03/2004 |
| From: | Stephen Monarque NRC/NRR/DLPM/LPD2 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Monarque S, NRR/DLPM, 415-1544 | |
| References | |
| BL-04-001 | |
| Download: ML042470354 (5) | |
Text
September 3, 2004 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING NRC BULLETIN 2004-01, INSPECTION OF ALLOY 82/182/600 MATERIALS USED IN THE FABRICATION OF PRESSURIZER PENETRATIONS AND STEAM SPACE PIPING CONNECTIONS AT PRESSURIZED-WATER REACTORS
Dear Mr. Christian:
The NRC staff has reviewed your submittal dated July 27, 2004, which provided the 60-day response to NRC Bulletin 2004-01 for North Anna Power Station, Units 1 and 2. Your response to the enclosed request for additional information (RAI) is required in order for the NRC staff to complete its review.
Our questions are provided in the Enclosure. The NRC staff requests a response to the RAI within 30 days of the date of this letter.
Sincerely,
/RA/
Stephen R. Monarque, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosure:
As stated
September 3, 2004 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING NRC BULLETIN 2004-01, INSPECTION OF ALLOY 82/182/600 MATERIALS USED IN THE FABRICATION OF PRESSURIZER PENETRATIONS AND STEAM SPACE PIPING CONNECTIONS AT PRESSURIZED-WATER REACTORS
Dear Mr. Christian:
The NRC staff has reviewed your submittal dated July 27, 2004, which provided the 60-day response to NRC Bulletin 2004-01 for North Anna Power Station, Units 1 and 2. Your response to the enclosed request for additional information (RAI) is required in order for the NRC staff to complete its review.
Our questions are provided in the Enclosure. The NRC staff requests a response to the RAI within 30 days of the date of this letter.
Sincerely,
/RA/
Stephen R. Monarque, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosure:
As stated Distribution:
ACRS KLandis DLPM DPR PUBLIC SMonarque TColburn SCoffin PDII-1 Rdg.
EDunnington (paper copy)
EHackett EAndruszkiewicz MMitchell Adams Accession Number: ML042470354 NRR-088 OFFICE PDII-1/PM PDII-2/LA EMCB/SC PDII-1/SC NAME SMonarque EDunnington SCoffin MJRoss-Lee DATE 09/02/2004 09/03/2004 09/02/2004 09/03/2004 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION NRC BULLETIN 2004-01, "INSPECTION OF ALLOY 82/182/600 MATERIALS USED IN THE FABRICATION OF PRESSURIZER PENETRATIONS AND STEAM SPACE PIPING CONNECTIONS AT PRESSURIZED-WATER REACTORS NORTH ANNA POWER STATION, UNITS 1 AND 2 VIRGINIA ELECTRIC & POWER COMPANY By letter dated July 27, 2004, Virginia Electric & Power Company provided the 60-day response to NRC Bulletin 2004-01 for the North Anna Power Station, Units 1 and 2.
The NRC staff has completed its preliminary review of your response and has determined it needs the following additional information to complete our review:
Your response to NRC Bulletin 2004-01 Question (1)(c) did not clearly communicate your intentions with respect to ensuring that an appropriate dialogue would be established with the NRC staff in the event that circumferential primary water stress corrosion cracking (PWSCC) is identified at any locations covered under the scope of NRC Bulletin 2004-01. The NRC staff addressed this issue, in part, on page 5 of NRC Bulletin 2004-01 stating,... the NRC staff believes that the topic of NDE
[nondestructive examination] scope expansion should be discussed with the NRC staff if circumferential PWSCC is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of this bulletin to ensure that the licensee has performed an adequate extent-of-condition evaluation.
Because of the potential plant-specific and generic significance of circumferential PWSCC at locations covered under the scope of NRC Bulletin 2004-01, it is the NRC staffs position that cognizant members of the Office of Nuclear Reactor Regulations Materials and Chemical Engineering Branch should be promptly made aware of any emerging issue regarding this degradation phenomena at your facility. This is important not only for the reason cited in the passage above from NRC Bulletin 2004-01, but also so that the NRC staff can evaluate any such information and fulfill its obligation to inform other U.S. nuclear power plant licensees of new operational experience that may be relevant to the continued safe operation of their facilities.
It is the NRC staffs expectation that if you obtain inspection results in the future that indicate that circumferential PWSCC may be occurring at any location covered under the scope of NRC Bulletin 2004-01, you should request a teleconference call or meeting with the NRC staff. This would provide you with the opportunity to incorporate any insights from the aforementioned teleconference call or meeting into your plans for evaluating the extent of the condition at your facility prior to the end of the outage during which the degradation was discovered.
In order to document your intent to follow the guidance provided above, please provide a supplement to your NRC Bulletin 2004-01 item (1)(c) response that states:
If circumferential cracking is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of this bulletin, [we] will develop plans to perform an adequate extent-of-condition evaluation and [we] will discuss those plans with cognizant NRC technical staff prior to restarting the affected unit.
North Anna Power Station, Units 1 & 2 cc:
Mr. C. Lee Lintecum County Administrator Louisa County Post Office Box 160 Louisa, Virginia 23093 Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dominion Resources Services, Inc.
Building 475, 5 th floor Rt. 156, Rope Ferry Road Waterford, Connecticut 06385 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U. S. Nuclear Regulatory Commission 1024 Haley Drive Mineral, Virginia 23117 Mr. Jack M. Davis Site Vice President North Anna Power Station Post Office Box 402 Mineral, Virginia 23117-0402 Mr. Richard H. Blount, II Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218 Mr. William R. Matthews Vice President-Nuclear Operations Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, Virginia 23060-6711