ML20211F430
| ML20211F430 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/25/1997 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 97-532, GL-92-01, GL-92-1, NUDOCS 9710010074 | |
| Download: ML20211F430 (4) | |
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Ricuuoso, WGINI A 2M61 September 25, 1997 U.S. Nuclear Regulatory Commission Serial No.97-532 Attention: Document Control Desk NL&OS/ETS: R0 Washington, DC. 20555 Docket Nos.
50-338/339 License Nos. NPF-4/7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION CONCERNING REACTOR VESSEL INTEGRITY DATA in an August 9,1996 letter, the NRC documented acceptance of the Virginia Electric and Power Company response to Genede Letter 92-01, Revision 1, Supplement 1 for North Anna Power Station Units 1 and 2 (TAC Nos. M92702 and M92703). The NRC letter recognized that there were owners group efforts underway to establish a comprehensive reactor vessel integrity database, and that these activities were expected to be completed by the summer of 1997. Therefore, the NRC staff requested that Virginia Electric and Power Company provide the results of the ongoing owners group activities which pertain to North Anna Units 1 and 2. The attachment to this letter provides the requested information.
Should you have any questions or require additional information, please contact us.
James P. O'Hanlon Senior Vice President - Nuclear Attachment Commitment made in this letiar:
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U. S. Nuclear Regulatory Commission
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Region ll Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station llllllllllll{'l[lllllll 9710010074 970925 PDR ADOCK 05000338 P
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i Attachment j
Generic Letter (GL) 92-01 Ravision 1, Supplement 1 Reactor Vessel Structural integrity Assessment of Reactor Vessel Integrity Data -
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from North Anna Units 1 and 2 Sister Plants i
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4 AL 92-01 Revision 1. Supplement 1. " Reactor Vessel Structural Intearity" Assessment of Reactor Vessel Intearity Data from North Anna Units 1 and 2 Sister Plantt PURPOSE in an August 9,1996 letter, NRC staff requested that Virginia Electric and Power Company provide the results of ongoing owners group activities to develop a comprehensive reactor vessel integrity database, and to evaluate the results of these activities as they pertain to North Anna Units 1 and 2. NRC staff expected these activities to be completed by the summer of 1997. A comprehensive reactor vessel integrity database has not yet been established and issued by the owners groups. However, Virginia Electric and Power Company (Virginia Power) has investigated the existing databases, and has consulted with vendor and utility points of contact, to determine if any new data has been generated which has bearing on the analysos which demonstrate the integrity of the North Anna Units 1 and 2 reactor vessels. The results of this investigation are summarized below.
EVALUATION The Sequoyah Units 1 and 2 reactor vessel beltlines include materials wnich are also present in the North Anna Unit i reactor vessel beltline. Specifically, the Sequoyah Unit 1 circumferential weld and the North Anna Unit 1 Weld 05 A (Nozzle Belt to Intermediate Shell Circumferential Weld; OD 94%) were both fabricated with weld wire heat number 25295. Further, the Sequoyah Unit 2 circumferential weld, the North Anna Unit 1 Weld 05B (Nozzle Belt to Intermediate Shell Circumferential Weld; ID 6%), and the North Anna Unit 2 Weld 05A (Nozzle Belt to Intermediate Shell Circumferential Weld; OD 94%) were-fabricated with weld wire heat number 4278.
This information can be verified by-exam; nation of the NRC Reactor Vessel Integrity Database (RVID) Version 1.0. Virginia Power has determined that no additional surveillance capsules containing weld specimens fabricated from weld wire heat numbers 25295 and 4278, beyond those already considered in our response to GL 92-01 Revision 1 Supplement 1, have been tested.
The North Anna plant-specific reactor vessel materials surveillance programs include surveillance specimens fabricated from weld wire heat numbers 25531 (Unit 1) and 716126 (Unit 2). These materials are also included in the North Anna Units 1 and 2 reactor vessel beltlines. Since the preparation of the response to GL 92-01 Revision 1 Supplement 1, no additional North Anna plant-specific surveillance capsules have been analyzed. Therefore, Virginia Power has no additional surveillance data (e.g., chemical composition or 30 ft-Ib transition temperature shift data) to report for North Anna Units 1 and 2.
If an owners group activity or a plant specific surveillance program generates information which has bearing on the analyses which demonstrate the integrity of the North Anna Units 1 and 2 reactor vessels, Virginia Power will consider this information when updating our plant-specific reactor vessel integrity analyses.
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I C NCL0SION Virginia Power has investigated recent industry surveillance capsule activities, and has determined that no additional surveillance data applicable to North Anna Units 1 and 2 has been generated since our response to GL 92-01 Revision 1 Supplement 1 was issued. Therefore, there is no need to update the analyses which demonstrate compliance with regulations goveming reactor vessel integrity at this time.
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