ML20069M417
| ML20069M417 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/10/1994 |
| From: | Tremblay L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-94-62, GL-92-01, GL-92-1, NUDOCS 9406210354 | |
| Download: ML20069M417 (35) | |
Text
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I VERMONT YANKEE 1 NUCLEAR POWER CORPORATION
. ,- Ferry Road, Brattleboro, VT 05301-7002 ENGINE RIN OFFICE ;
580 MAIN STREET l BOLTON. MA 01740 l
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(508) 779-6711 l June 10,1994 BVY 94 - 62 United States Nuclear Regulatory Commission ATrN: Document Contml Desk i Washington, DC 20555 i
References:
- a. License No. DPR-28 (Docket No. 50-271) l
- b. Letter, USNRC to [All Licensees], NVY 92-041, dated 3/6S2
- d. Letter, USNRC to VYNPC, NVY 93-107, dated 7/21B3
- e. Letter, VYNPC to USNRC, BVY 93-107, dated 9/24S3
- f. Telecon, USNRC to VYNPC, dated 11/5S3
- g. Letter, VYNPC to USNRC, BVY 93-146, dated 12/21S3 1
- h. Letter, USNRC to VYNPC, NVY 94-47, dated 4/18S4
Subject:
Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity" The purpose of this letter is to provide supplemental information with regard to the subject issue,in accordance with our previous correspondence [ Reference (i)].
Reference (b), USNRC Generic Letter 92-01, was sent to all operating reactors requesting information pertaining to the structural integrity of the reactor pressure vessel, specifically its capability of withstanding neutron embrittlement without violating the regulatory requirements of 10CFR50 Appendices G and H.
Vermont Yankee responded to Reference (b) with Reference (c). In Reference (d) NRC requested that Vermont Yankee detail how we complied with the necessary criteria, as well as requesting that materials data be provided. Reference (e) provided the requested information.
In Reference (f) NRC indicated that additional information was required for the Staff to complete their review of the Vermont Yankee submittal. These items are discussed below:
- 1. Submit upper shelf energy values for beltline plates 1-15,1-16 and 1-17. If actual plate data do not exist submit test data from a sample of plates, using the mean minus two standard deviations value as a generic value for Vermont Yankee. In lieu of that submit an Equivalent Margins Analysis in accordance with ASME Code Case N-512. ,
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- 2. Submit upper shelf energy values for all weld wire used in the core beltline region. If actual l weld data do not exist submit test data from a sample of welds, using the mean minus two standard deviations value as a generic value for Vermont Yankee. In lieu of that submit an Equivalent Margin Analysis in accordance with ASME Code Case N-512.
Reference (g) transmitted the equivalent margin analysis for the Vermont Yankee reactor pressure vessel; it was applicable to Plates 1-14,1-15 and 1-16 and all welds.
9406210354 940610 PDR ADOCK 05000271 h I P PDR
Vt RMovr YAmt NUCLEAR POWER CORPOR ATION United States Nuclear Regulatory Commission June 10,1994 Page 2 Reference (h) provided two tables reporting the data for the Vermont Yankee reactor vessel that the NRC intended to enter into its database. NRC requested that Vermont Yankee verify the data and notify NRC of any inconsistencies within 30 days. Reference (i) notified NRC that some inconsistencies were identified, and that furtherinformation would be provided upon completion of our evaluation effort. This letter reports the inconsistencies we observed. For convenience we have also provided a marked-up set of tables in NRC format.
Following are the inconsistencies we observed:
- 1. In the " Summary Table for Pressure-Temperature Limits" the method of determining IRTNIrr for Plates 1-15,1-16 and 1-17 should be MTEB 5-2, as reported in Reference (e).
- 2. In the " Summary Table for Pressme-Temperature Limits" the chemistry factors should be whole numbers since that is how they are presented in USNRC Regulatory Guide 1.99.
- 3. In the " Summary File for Upper Shelf Energy" the 1/4T USE at EOIJEFPY for Plate 1-14 should be 77 ft-lbf using the adjusted USE drop documented in Reference (g).
- 4. In the " Summary File for Upper Shelf Energy" the 1/4T USE at EOl/EFPY for Plates 1-15,1-16 and 1-17 and Welds should by the Equivalent Margin Analysis (EMA) as requested by the USNRC in Reference (f) and as submitted by VYNPC in Reference (g).
- 5. In the " Summary File for Upper Shelf Energy" the " Method of Detennin. Unirrad. USE" for Plates 1-15,1-16 and 1-17 and Welds should be blank.
- 6. In the " Summary File for Upper Shelf Energy" the "Unirrad. USE" for Plates 1-15,1-16 and 1-17 and Welds should be EMA.
In the course of discussing these observed discrepancies with NRC staff we were requested to document the basis for the copper content used for the weld material. We stated that the upper bound assumption of 0.10 w/o copper was based on a previous USNRC accepted value for a similar reactor vessel fabricated by the same vendor at the same time frame; most of the weld wire heats were the same for both vessels. The NRC stated that they were rescinding that approval and ,
requested that we obtain generic data to support our assumption, using the mean plus one standard i deviation value from the generic data. l 1
We obtained twenty-two (22) material certifications from the same vendor who produced the l welding electrodes used to fabricate the Vermont Yankee reactor pressure vessel. These electrodes l were produced contemporaneously with the Vermont Yankee electrodes, but they had copper i content data. There are 22 data points with a mean value of 0.03 w/o copper and a standard i deviation of 0.01 w/o, with a maximum value of 0.04 w/o copper. Since the 8018 weld electrode has no added copper, this sample is considered representative of generic 8018 material. Tims, the originally stated upper bound of 0.10 w/o copper is shown to be conservative. Using a generic value of 0.04 w/o copper, based on NRC requirements, with an upper bound of 1.00 w/o nickel for the welds requires the Chemistry Factor to be 54 in the " Summary File for Pressure-Temperature Limits".
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VERMONT YANKEE NUCLEAR POWER CORI' ORATION United States Nuclear Regulatory Commission June 10,1994 Page 3 We trust that the information provided herein satisfactorily responds to your request and serves to close this issue as it pertains to Vermont Yankee. However, should additional information be required, please contact this office.
Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION cota , e '
t .
Leonard A. Tremblay, Jr., P.E.
Senior Licensing Engineer Enclosed: Attachments 1 and 2 cc: USNRC Region I Administrator USNRC Resident Inspector- VYNPS USNRC Project Manager- VYNPS l
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1 9 SuCrnary file for Pressure-Temperature Limits Plant Beltline Heat No. 10 hevt. I R T. 4thod of Ch eml e t ry Ident. Nthod of ICu home Ident. Fluence et Determin. Factor Deterutn.
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