ML18153A732
| ML18153A732 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 08/10/1995 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 95-270, GL-92-01, GL-92-1, NUDOCS 9508160162 | |
| Download: ML18153A732 (4) | |
Text
'
~- '
e e
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 10, 1995 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 Serial No.
NL&P/CGL Docket Nos.
License Nos.
90-DAY RESPONSE TO GENERIC LETTER 92-01, REV. 1, SUPP. 1 REACTOR VESSEL STRUCTURAL INTEGRITY 95-270 R1" 50-338 50-339 50-280 50-281 NPF-4 NPF-7 DPR-32 DPR-37 Generic Letter 92-01, Revision 1, Supplement 1, entitled "Reactor Vessel Structural Integrity," was issued on May 19, 1995. The NRC issued this supplement to require licensees to identify, collect, and report any new data pertinent to analysis of structural integrity of their reactor pressure vessels (RPVs). Licensees were also requested to assess the impact of pertinent data on their RPV integrity analyses relative to the requirements of 1 OCFR50.60 and 1 OCFR50.61, Appendices G and H to 1 OCFR50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (L TOP) limits or pressure-temperature (P-T) limits.
Specifically, Part (1) of the generic letter requires that the following information be provided:
"a description of those actions taken or planned to locate all data relevant to the determination of RPV integrity or an explanation of why the existing data base is considered complete as previously submitted" North Anna Units 1 and 2 Welds, Plates, and Forgings Surry Units 1 and 2 Rotterdam Welds The North Anna Units 1 and 2 reactor vessels, as well as portions of the Surry Units 1 and 2 reactor vessels, were fabricated by the Rotterdam Dockyard Company. To date, the following sources of information have been identified and utilized in the evaluation of the North Anna Units 1 and 2 reactor vessel beltline materials (welds, plates, and forgings) and the Surry Units 1 and 2 Rotterdam weld materials:
r------------ ---- --
9508160162 950810 ____ _
PDR ADDCK 05000280 p
PDR w,0 j
" Plant-specific reactor vessel materials surveillance reports and Virginia Power documentation of reactor vessel materials (e.g., vendor correspondence, reports, etc.).
Because several other U. S. nuclear reactor vessels were fabricated by the Rotterdam Dockyard Company, additional information on Rotterdam weld materials and weld material surrogates may exist for the weld wire heats used in the fabrication of the North Anna and Surry reactor vessels.
To ensure that relevant chemical and mechanical test data have been identified, confirmatory searches of known data sources for these reactor vessel beltline materials will be conducted.
Potential sources of additional data include:
Westinghouse Electric Company records, Rotterdam Dockyard Company fabrication records, Virginia Power internal documentation, and Industry data bases (e.g., RPVDATA, PREP3, PR-EDB, AVID, etc.).
Surry Units 1 and 2 Linde so Welds, Plates. and forgings The portions of the Surry Units 1 and 2 reactor vessels that were not fabricated by Rotterdam Dockyard Company were. fabricated by Babcock & Wilcox (B&W). The.
- response to Part (1) of Generic Letter 92-01, Revision 1, Supplement 1, for the B&W-fabricated portions of the Surry Units 1 and 2 reactor vessels (i.e., Linde 80 welds, plates, and forgings) is included in B&W Report BAW-2257, dated July 1995.
This report has been transmitted separately to the NRC by B&W Owners Group (B&WOG) letter OG-95-1527, dated August 1, 1995. As indicated in that report, the B&WOG Reactor Vessel Working Group (RVWG) believes that the available data, relevant to the assessment of its member plant vessels, have been appropriately considered in the submitted reactor vessel integrity evaluations.
- The six-month response to Parts (2), (3), and (4) of the generic letter for North Anna and Surry will be provided by November 20, 1995.
If you have questions regarding this response to Part (1) of Generic Letter 92-01, Revision 1, Supplement 1, please contact us.
Very truly yours,
~p~
James P. O'Hanlon Senior Vice President - Nuclear
cc:'. U. *s. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. R. D. Mcwhorter NRC Senior Resident Inspector North Anna Power Station Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station
e COMMONWEAL TH OF VIRGINIA )
)
COUNTY OF HENRICO
)
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. P. O'Hanlon, who is Senior Vice President -
Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this /(l 7J' day of hy,
19q__b.
My Commission Expires: ~
3/
, 19'3..£..
'(SEAL)