ML17059A803
| ML17059A803 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/05/1995 |
| From: | Edison G Office of Nuclear Reactor Regulation |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| References | |
| TAC-M91221, NUDOCS 9505090258 | |
| Download: ML17059A803 (8) | |
Text
Hay 5, 1995 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093 Distribution:
Docket File 7
PUBLIC PD I-l Rdg.
SVarga JZwolinski RFrahm ACRS (4)
LMarsh CCowgill, RI SLittle GEdison OGC
SUBJECT:
NINE MILE POINT NUCLEAR STATION UNIT NO.
1 REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M91221)
Dear Mr. Sylvia:
The purpose of this letter is to request additional information related to your license amendment proposal regarding instrument calibration frequency and fuel cladding integrity limits.
In a letter dated December 23,
- 1994, you submitted a request to amend the technical specifications for fuel cladding integrity limits and for certain instrumentation.
In order to complete our review, we require additional information (enclosure).
This requirement affects 9 or fewer respondents and, therefore, is not subject to the Office of Management and Budget Review under P.L.96-511.
II I
Please provide your response by May 31,
- 1995, so that we can continue our review consistent with your schedular needs.
The enclosure and schedule were discussed with D. Baker of your staff on April 28, 1995.
Sincerely, Docket No. 50-220
Enclosure:
Request For Additional Information Original signed by:
Gordon E." Edison,,Senior Project Manager Project Directorate I-l Division of Reactor Projects -'/II Office,of'Nuclear Reactor Regulation cc w/encl:
See next page DOCUMENT NAME:
G: iNMPIiNM191221. RAI To receive e copy of this document, indicate in the box:
C't ~
opy without enclosures "E" ~ Copy with enclosures "N" ~ No copy DATE 05/ it /95 05/
/95 OFFICE LA:PDI-1 E'M:PDI-1 NAME SLittle GEdison:smm D: PDI-1 LMarsh 08~5 9505090258
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 Hay 4, 1995
'r.
B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093
SUBJECT:
NINE HILE POINT NUCLEAR STATION UNIT NO.
1 - REQUEST FOR ADDITIONAL INFORHATION (TAC NO. H91221)
Dear Hr. Sylvia:
The purpose of this letter is to request additional information related to your license amendment proposal regarding instrument calibration frequency and fuel cladding integrity limits.
In a letter dated December 23, 1994, you submitted a request to amend the technical specifications for fuel cladding integrity limits and for certain instrumentation.
In order to complete our review, we require additional information (enclosure).
This requirement affects 9 or fewer respondents and, therefore, is not subject to the Office of Management and Budget Review under P.L.96-511.
Please provide your response by Hay 31,
- 1995, so that we can continue our review consistent with your schedular needs.
The enclosure and schedule were discussed with D. Baker of your staff on April 28, 1995.
Sincerely, Docket No. 50-220
Enclosure:
Request For Additional Information cc w/encl:
See next page Gordon E. Edison, Senior Project Hanager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
e c'
B. Ralph Sylvia Niagara Mohawk Power Corporation 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, NY 13126 Mr. 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 Ms.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, NY 12223 Nine Mile,Point Nuclear Station Unit No.
1 Mr. Richard B. Abbott Unit 1 Plant Manager Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093 Mr. 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 New York, NY 10271 Hr. 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.
McCormick, Jr.
Vice President Nuclear Safety Assessment and Support Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, NY 13093
t J
FOR ADD IO FO PO NT UC R STA 0
NI N
Please provide assurance that the limiting neutron flux transients remain limiting with the new setpoints and with subsequent
- reloads, or that a new limiting transient will be identified for establishing operating limits.
Provide assurance that the limiting Hinimum Critical Power Ratio (HCPR) transient is identified with each reload and has not changed with this new setpoint change.
Please discuss your analysis of the limiting Anticipated Operational Occurrences (AOOs) assuming a single failure, i.e. the direct position
If the Safety Limit HCPR (SLHCPR) is exceeded assume the fuel rods that are predicted to be in boiling transition are failed and show that the consequences are still an acceptable small fraction of 10 CFR Part 100.
See pages
- 15. 1. 1-354 and 15.2.1-4 of the Standard Review Plan (SRP) for guidance.
The discussion of the Control Rod Withdrawal Error (CRWE) needs clarification.
The discussion of the CRWE discusses mitigation with the APRH flow-biased rod block system and states this parameter setpoint is increased by 8X.
The GE discussion states that the parameter setpoint is increased by 2X.
Please clarify this possible inconsistency.
The submittal also states, that no credit is assumed for the function of this system in the analysis.
How is this transient mitigated7 What fuel design limits were evaluated when analyzing this event?
See pages 15.4.1-354 and 15.4.2-384 of the SRP for guidance.
Please provide assurance that the Inadvertent Startup of a Cold Loop will not become a limiting HCPR event and that all fuel design limit acceptance criteria will not be violated.
Please provide assur ance that the fuel design limits for the low power transients are always bounded by the reload-specific limiting HCPR full power transients for the changes requested in this license amendment.
Encl osure
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