NUREG/CR-5729, Recommends That Util Perform elastic-plastic Fracture Mechanics Analysis Using Criteria in Latest Rev of App X to Section XI of ASME Code & Matl Properties from NUREG/CR-5729 & Submit Results within 60 Days of Ltr Receipt,For Review
| ML17056B944 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/12/1992 |
| From: | Brinkman D Office of Nuclear Reactor Regulation |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| References | |
| RTR-NUREG-CR-5729 GL-92-01, GL-92-1, TAC-M83486, NUDOCS 9208190095 | |
| Download: ML17056B944 (8) | |
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Docket No. 50-220 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 August 12, 1992 Hr.
B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Sylvia:
SUBJECT; NINE MILE POINT NUCLEAR STATION UNIT NO.
1
RESPONSE
TO GENERIC LETTER 92-01, REVISION 1, "REACTOR VESSEL STRUCTURAL INTEGRITY, 10 CFR 50.54(f),"
(TAC NO. H83486)
In order to demonstrate that plates with Charpy USE less than 50 ft lb have margins of safety against fracture equivalent to those required by Appendix G
of the ASME Code, the NRC staff recommends that NMPC perform an elastic-plastic fracture mechanics analysis using the criteria in the latest revision of Appendix X to Section XI of the ASHE Code and the material properties from NUREG/CR-5729, "Multivariable Modeling of Pressure Vessel and Piping J-R Data."
The NRC staff recommends that a lower 95 percent confidence value for Jd be used to represent conservative material properties for Levels A, B and C
Service Loadings and a mean value for Jd be used to represent the best estimate properties for Level D Service Loadings.
The service conditions
+o be evaluated are those in the NHP-1 design specificatio n.
However, if the l
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The NRC staff has performed a preliminary review of Niagara Mohawk Power Corporation's (NMPC) July 2,
- 1992, response to Generic Letter 92-01, Revision 1, "Reactor Vessel Structural Integrity, 10 CFR 50.54(f)," for Nine Mile Point Unit No.
1 (NMP-1).
Your response stated that the Charpy upper shelf energy (USE) of two beltline plates of the reactor vessel is predicted to be below the 50 ft lb screening criteria in Appendix G,
10 CFR Part 50, at the present time when the Charpy USE is calculated using the guidance of Branch Technical Position - HTEB 5-2, "Fracture Toughness Requirements,"
in Standard Review Plan 5.3.2 (65 percent correction factor for orientation) and Regulatory Guide (RG) 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials."
Your response also stated that an alternative calculation method was used to predict that both plates'harpy USE will not fall below 50 ft lb pr'ior to end of the NMP-1 operating license.
The alternative method used an 80 percent correction factor for orientation and a smaller amount of correction for irradiation than the amount recommended in RG 1.99, Revision 2.
The orientation correction factor is based on tests from one plate in the NHP-1 reactor vessel beltline and from material similar to those in the NHP-1 reactor vessel beltline.
The irradiation correction factor is based on irradiation data from a plate in the NMP-1 reactor vessel with less copper than the limiting NMP-1 plate and is only for one neutron fluence.
Since the correction factor is based on a very limited amount of data, the alternative calculational method is not fully acceptable.
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Hr. B. Ralph Sylvia August i2, i992 design specification does not include loadings for Level C or D Service Conditions, NHPC should evaluate these service conditions using Level C or D
Service Loadings from more recently licensed BWR plants.
As discussed in an August 6,
- 1992, telephone conference call with members of your staff (Hr. Nick Spagnoletti, et al.)
and members of the NRC staff and as further discussed in an August 10,
- 1992, meeting held with members of your staff in the NRC office in Rockville, Maryland, we request that NMPC submit the results of the requested supplemental analysis for our review within 60 days of receipt of this letter.
This requirement affects one respondent and, therefore, is not subject to the Office of Management and Budget review under P.L.96-511.
Sincerely, cc:
See next page Donald S.
Brinkman, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
'li r
Hr.
B. Ralph Sylvia August 12, 1992 design specification does not include loadings for Level C or 0 Service Conditions, NHPC should evaluate these service conditions using Level C or D
Service Loadings from more recently licensed BWR plants.
As discussed in an August 6,
- 1992, telephone conference call with members of your staff (Hr. Nick Spagnoletti, et al.)
and members of the NRC staff and as further discussed in an August 10,
- 1992, meeting held with members of your staff in the NRC office in Rockville, Maryland, we request that NHPC submit the results of the requested supplemental analysis for our review within 60 days of receipt of this letter.
This requirement affects one respondent and, therefore, is not subject to the Office of Management and Budget review under P.L.96-511.
Sincerely, Original Signed By:
Donald S.
Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:
See next page DISTRIBUTION:
(Docket File,'RC 8 Local PDRs PDI-1 Reading S.
Varga J.
Calvo R. A. Capra C.
Vogan D. Brinkman OGC B. Elliot 7-D-4 W. Russell 12-G-)8 K. Wichman, 7-D-4 J.
Richardson B.
D. Liaw D. HcDonald H. Hayfield A. Hiser J.
Tsao S.
Sheng W.
Bateman ACRS (10)
Plant File - Nine C. Cowgill, RI 7-0-26 7-0-26 NLS 217-C NLS 217-C 7-0-4 7-D-4 7-0-4 Mile 1
OFFICE
- See revious concurrence LA:PDI-1 PH'D I-1 EHCB D:PDI-1 IIAME CVo an od DBrinkman:ln
- WBateman RACa ra DATE F/I /92 f/I~ 92 08 11/92 OS Q,92 OFFICIAL RECORD COPY Document Name:
NMP183486. LTR
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B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No.
1 CC:
Mark J. Wetterhahn, Esquire Winston 5 Strawn 1400 L Street, NW Washington, DC 20005-3502 Supervisor Town of Scriba Route 8, Box 382
- Oswego, New York 13126 Hr. Neil S.
Cams Vice President - Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 126
- Lycoming, New York 13093 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ms.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Hr. Kim Dahlberg Unit 1 Station Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Hr. David K. Greene Manager Licensing Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Hr. Paul D.
Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza
- Albany, New York 12223
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