ML17059A457
| ML17059A457 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/16/1994 |
| From: | Brinkman D Office of Nuclear Reactor Regulation |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| References | |
| GL-94-03, GL-94-3, TAC-M90102, NUDOCS 9409210140 | |
| Download: ML17059A457 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 16, 1994 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63'ycoming,New York. 13093
SUBJECT:
RE(VEST FOR ADDITIONAL INFORMATION (RAI) REGARDING RESPONSE TO GENERIC LETTER (GL) 94-03 (TAC NO. H90102)
Dear Hr. Sylvia:
By letter dated August 23, 1994, Niagara Mohawk Power Corporation (NMPC) responded to GL 94-03, "Integranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors," for Nine Mile Point Nuclear Station, Unit No. 1.
The NRC staff has begun its review of NMPC's response.
- However, we have determined that additional information, as identified in the enclosure, is required to complete our review of the NMPC response.
NHPC is requested to respond to this RAI by September 26, 1994, in order for us to complete our review in a timely manner.
If you have any questions regarding this RAI, please contact me at 301-504-1409.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, Docket No. 50-220
Enclosure:
Request for Additional Information Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor.
Regulation 9409210140 940916 PDR ADOCK 05000220i P
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Cj(i B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Hile Point Nuclear Station Unit No.
1 CC:
Hark J. Wetterhahn, Esquire Winston 8 Strawn 1400 L Street, NW Washington, DC 20005-3502 Supervisor Town of Scriba Route 8, Box 382
- Oswego, NY 13126 Hr. Louis F. Storz Vice President Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093 Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 126
- Lycoming, NY 13093 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, NY 13202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Hs.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, NY 12223 Hr. Richard B. Abbott Unit 1 Plant Manager Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093 Hr. David K. Greene Manager Licensing Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway
'ew
- 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 Hr. Hartin J. HcCormick, Jr.
Vice President Nuclear Safety Assessment and Support Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093
RE VEST FOR DDI IONAL INFORMATIO EGARDING ESPONSE 0
G 94-03 NIAGARA MOHAW POWE CORPORATION NINE MILE POINT NUCLEAR STATION UNIT NO.
1 DOCKET NO. 50-220 Generic Letter 94-03 required that a plant-specific assessment of the shroud response to the structural loadings resulting from design basis events assuming a postulated 360'hrough-wall crack be performed.
The NRC staff has reviewed the licensee's-submittal and has determined that the licensee has not met the requirements of the generic letter.
Therefore, the following additional information is required.
1.
Specifically, the licensee used Oyster Creek's RELAP 5 model to assess the consequence of a main steamline break (HSLB).
The licensee did not specify why Oyster Creek's model was used and not a plant-specific model.
The staff did not agree with Oyster Creek's conclusion that 0.025 inches provided sufficient margin of safety to consider the postulated HSLB with a 360'hrough-wall crack as not significant.
Niagara Mohawk Power Corporation (NHPC) should perform a plant-specific consequence assessment to ensure that the top guide will not clear the top of the active fuel during an HSLB.
2.
Th'e licensee did not perform a plant-specific assessment of any structural loadings due to a seismic event, a seismic event plus a recirculation line break (RLB), and a seismic event plus an HSLB.
NHPC should perform a
consequence assessment of seismic events stated above to ensure core spray operability and control rod insertion assuming a 360'hrough-wall crack.
3.
Furthermore, the licensee did not assess a postulated 360'hrough-wall crack at the H8 weld during an RLB at Nine Mile Point Nuclear Station Unit No.
1 (NMP-1).
The licensee did not believe that this was a credible failure.
The licensee stated that cracking in H8 would have to be about 90 percent through-wall for 360'n order for. H8 to fail during an RLB.
The staff questions why continued operation of NHP-1 is justified if a 360'rack that is 90 percent or greater through-wall is present at the HB weld.
The licensee did not evaluate the acoustic and blowdown loads associated with the RLB.
NMPC should justify continued operation assuming a 360'hrough-wall crack at the H8 weld.
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September 16, 1994 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation Nine Nile Point Nuclear Station P.O.
Box 63
- Lycoming, New York 13093
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING RESPONSE TO GENERIC LETTER (GL) 94-03 (TAC NO. H90102)
Dear Hr. Sylvia:
By letter dated August 23,: 1994, Niagara Mohawk Power Corporation (NHPC) responded to.GL 94-03, "Integranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors,"
for'Nine Mile Point Nuclear Station, Unit No. l.
The NRC staff has begun its review of NHPC's response.
- However, we have determined that additional information, as identified in the enclosure, is required to complete our review of the NHPC response;,
NHPC is requested to respond to this RAI by September 26, 1994, in'order for us to complete our review in a timely manner.
If you have any questions regarding'his RAI, please contact me at 301-504-1409.
This requirement affects one respondent and, therefore, is not subject to Office of Management-and Budget review under P.L.96-511.
Sincerely, Docket No. 50-220
Enclosure:
Request for Additional Information Distribution:
Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II
'Office of Nuclear Reactor Regulation Docket File.-
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