ML17059C056
| ML17059C056 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/29/1998 |
| From: | Hood D NRC (Affiliation Not Assigned) |
| To: | Mueller J NIAGARA MOHAWK POWER CORP. |
| References | |
| GL-92-01, GL-92-1, TAC-MA1200, NUDOCS 9806040013 | |
| Download: ML17059C056 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 May 29, 1998 Mr. John H. Mueller Chief Nuclear Officer Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Operations Building, Second Floor P.O. Box 63 Lycoming, NY 13093
SUBJECT:
REQUEST FOR ADDITIONALINFORMATION REGARDING REACTOR PRESSURE VESSEL STRUCTURAL INTEGRITY AT'INEMILEPOINT NUCLEAR STATION UNIT 1 (TAC NO. MA1200)
Dear Mr. Mueller:
In May 1995, the NRC issued Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp. 1), "Reactor Vessel Structural Integrity." This GL requested licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of those data on 1) their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federal Re ulations (10 CFR Part 50.60), 10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and 2) any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits.
After reviewing your response, the NRC issued a letter dated August 26, 1996, for Nine Mile Point Nuclear Station.
In this letter we acknowledged receipt of your response, noted that additional RPV information may become available as a result of Owners Group efforts and requested that you provide us with the results of the Owners Groups'rogra'ms relative to your plant. We further indicated that a plant specific TAC Number may be opened to review this material.
Following issuance of these letters, the BWR Vessel and Internals Project (BWRVIP) submitted the report "Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity Issues (BWRVIP-46)." This report included bounding assessments of new data from 1) the Combustion Engineering Owners Group's (GEOG) database released in July 1997 which contains all known data for CE fabricated welds in PWR and BWR vessels; 2) Framatome Technologies Incorporated's (FTI) analyses of Linde 80 welds which are documented in NRC Inspection Report 99901300/97-01 dated January 28, 1998; 3) FTI's analysis of electro-slag welds which was referenced in a submittal dated September 20, 1996, regarding Dresden and Quad Cities P-T limits; and 4) Chicago Bridge and Iron's quality assurance records.
New data for one vessel fabricated by Hitachi was also included in the BWRVIP report.
y The NRC staff requests that you re-evaluate the RPV weld chemistry values that you have previously submitted as part of your licensing basis in light of the information presented in the GEOG, FTI and BWRVIP reports.
The NRC staff expects that you willassess this new information to determine whether any values of RPV weld chemistry need to be revised for our plant.
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J. H. Mueller In order that we may maintain our existing schedule for completing review of responses to items 2, 3 and 4 of the GL, the NRC staff requests that you respond to the enclosed request for additional information within 90 days of receipt of this letter. Ifa request does not apply to your situation, please indicate this in your response along with your technical basis and, per GL 92-01, Rev. 1, Supp. 1, certify that previously submitted evaluations remain valid.
The NRC staff willuse your response to update the Reactor Vessel Integrity Database.
- Also, the NRC staff acknowledges your letter dated May 28, 1998, stating that an application for license amendment to update the P-T curves in the Unit 1 Technical Specifications willbe submitted by June 19, 1998.
Ifyou should have any questions regarding this request or are unable to meet the requested response schedule, please contact me by phone at (301) 415-3049 or by electronic mail at dsh@nrc.gov.
Sincerely, Darl S. Hood, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-220
Enclosure:
Request for Additional Information ccw/encl: See next page
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May 29, 1998 J. H. Mueller ln order that we may maintain our existing schedule for completing review of responses to items 2, 3 and 4 of the GL, the NRC staff requests that you respond to the enclosed request for additional information within 90 days of receipt of this letter. Ifa request does not apply to your situation, please indicate this in your response along with your technical basis and, per GL 92-01, Rev. 1, Supp. 1, certify that previously submitted evaluations remain valid.
The NRC staff willuse your response to update the Reactor Vessel integrity Database.
- Also, the NRC staff acknowledges your letter dated IVlay 28, 1998, stating that an application for license amendment to update the P-T curves in the Unit 1 Technical Specifications will be submitted by June 19, 1998.
Ifyou should have any questions regarding this request or are unable to meet the requested response schedule, please contact'me by phone at (301) 415-3049 or by electronic mail at dsh@nrc.gov.
Sincerely, Original Signed by:
Darl S. Hood, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
Request for Additional Information cc w/encl: See next page D
Docket File PUBLIC PDI-1 R/F BBoger JZwolinski SBajwa S Little DHood GVissing OGC ACRS LDoerflein, Rl ALee DOCUMENT NAME: G:>NMP1>NM1A1200.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE PM:PDI 1
NAME DNood/Icc DATE 05/
98 LA:PDI-1q SLitt 05/J. /98 D:PDI-1 SBa wa 05/ g 7 /98 Official Record Copy 05/
/98 05/
/98
May 29, 1998 J. H. Mueller In order that we may maintain our existing schedule for completing review of responses to items 2, 3 and 4 of the GL, the NRC staff requests that you respond to the enclosed request for additional information within 90 days of receipt of this letter. Ifa request does not apply to your situation, please indicate this in your response along with your technical basis and, per GL 92-01, Rev. 1, Supp. 1, certify that previously submitted evaluations remain valid.
The NRC staff will use your response to update the Reactor Vessel Integrity Database.
- Also, the NRC staff acknowledges your letter dated May 28, 1998, stating that an application for license amendment to update the P-T curves in the Unit 1 Technical Specifications will be submitted by June 19, 1998.
Ifyou should have any questions regarding this request or are unable to meet the requested response schedule, please contact me by phone at (301) 415-3049 or by electronic mail at dsh@nrc.gov.
Sincerely, Original Signed by:
Darl S. Hood, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
Request for Additional Information ccw/encl: See next page DISTRIBUTION:
~Do'cket'Filets SBajwa PUBLIC SLittle PDI-1 R/F DHood BBoger GVissing JZwolinski OGC ACRS LDoerflein, RI ALee DOCUMENT NAME: G:)NMP1>NM1A1200.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE PH:PDI-1 E
LA:PDI-1 D:PDI-1 HAHE DHood/icc SLitt 05/
/98 DATE 05/
98 SBaiwo 05/ g 7 /98 Official Record Copy 05/
/98 05/
/98
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John H. Mueller Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No. 1 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 126 Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Paul D. Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza Albany, NY 12223 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mark J. Wetterhahn, Esquire Winston 8 Strawn 1400 L Street, NW Washington, DC 20005-3502 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, NY 13202 Supervisor
.Town of Scriba Route 8, Box 382 Oswego, NY 13126
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REQUEST FOR ADDITIONALINFORMATION REGARDING REACTOR PRESSURE VESSEL STRUCTURAL INTEGRITY NIAGARAMOHAWKPOWER CORPORATION NINE MILEPOINT NUCLEAR STATION UNIT NO. 1 OPERATING LICENSE NUMBER DPR-63 DOCKET NOS. 50-220 The NRC staff recently received the Boiling Water Reactors Vessel and Internals Project (BWRVIP) report "Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity Issues (BWRVIP-46)." In accordance with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests an evaluation of the bounding assessment in BWRVIP-46 and its applicability to the determination ofthe best-estimate cliemistry for all of your Unit 1 RPV beltline welds.
Based upon this reevaluation, supply the information necessary to completely fillout the data requested in Table 1 for each Unit 1 RPV beltline weld material. Ifthe limiting material for the Unit 1 vessel's P-T limits evaluation is not a weld, include the information requested in Table 1 for the limiting material also.
During a public meeting on November 12, 1997, between the NRC staff, Nuclear Energy Institute (NEI), and industry representatives, the NRC staff discussed some of the issues regarding the evaluation of the data. The summary of this meeting (see memorandum dated November 19, 1997, from Keith R. Wichman to Edmund J. Sullivan, "Meeting Summary for November 12, 1997 Meeting with Owners Group Representatives and NEI Regarding Review of'Responses to Generic Letter 92-01, Revision 1, Supplement 1") should be considered in your response.
In addition to the issues discussed in the public meeting, you should also consider the method used to group sets of chemistry data (in particular, those from weld qualification tests) as being from "one weld" or from multiple welds. This is an important consideration when a mean-of-the-means or coil-weighted average approach is determined to be the appropriate method for determining the best-estimate chemistry.
If a weld (or welds) were fabricated as weld qualification specimens by the same manufacturer, within a short time span, using similar welding input parameters, and using the same coil (or coils in the case oftandem arc welds) ofweld consumables, then it may be appropriate to consider all chemistry samples from that weld (or welds) as samples from "one weld" for the purposes of best-estimate chemistry determination.
Ifinformation is not available to confirm these details, but sufficient evidence exists to reasonably assume the details are the same, then tPe best-estimate chemistry should be evaluated both by assuming the data came from "one weld" and by assuming that the data came from an appropriate number of "multiple welds." A justification should then be provided as to which assumption was chosen when the best-estimate chemistry was determined.
Attachment:
Table 1
Enclosure
TABLE 1 Facility:
Vessel Manufacturer:
Information requested on RPV Weld and/or Limiting Materials RPV Weld Wire Heat ">
Best-Best-Estimate Estimate Copper Nickel EOL ID Fluence (x 10' Assigned Material Chemistry Factor (CF)
Method of Determining CFi'>
Initial RTiio, (RTiio~iiii)
Margin ART or RTndt at EOL (1) or the material identification of the limiting material as requested in the first paragraph of the RAI (2) determined from tables or from surveillance data Discussion of the Anal sis Method and Data Used for Each Weld Wire Heat Weld Wire Heat
. Discussion
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