ML17059C076
| ML17059C076 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/04/1998 |
| From: | Hood D NRC (Affiliation Not Assigned) |
| To: | Mueller J NIAGARA MOHAWK POWER CORP. |
| References | |
| GL-97-04, GL-97-4, TAC-MA0014, TAC-MA14, NUDOCS 9806120004 | |
| Download: ML17059C076 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 June 4, 1998 Mr. John H. Mueller Chief Nuclear Officer Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Operations Building, Second Floor Lycoming, NY 13093
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 97-04, NINE MILE POINT NUCLEAR STATION, UNIT NO. 2 (TAC NO. MA0014)
Dear Mr. Mueller.
On October 7, 1997, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps," to all holders of operating licenses or construction permits.
The NRC issued GL 97-04 to confirm the adequacy of the net positive suction head (NPSH) available for emergency core cooling (including core spray and decay heat removal) and containment heat removal pumps under all design-basis accident scenarios.
In GL 97-04, the NRC staff specifically requested that licensees provide the following information for each of their nuclear power plants:
1.
Specify the general methodology used to calculate the head loss associated with the ECCS suction strainers.
2.
Identify the required NPSH and the available NPSH.
3.
Specify whether the current design-basis NPSH analysis differs from the most recent analysis reviewed and approved by the NRC for which a safety evaluation was issued.
4.
Specify whether containment overpressure (i.e., containment pressure above the vapor pressure of the sump or suppression pool fluid) was credited in the calculation of available NPSH. Specify the amount of overpressure needed and the minimum overpressure available.
5.
When containment overpressure is credited in the calculation of available NPSH, confirm that an appropriate containment pressure analysis was done to establish the minimum containment pressure.
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June 4, 1998 J. H. Mueller You responded to GL 97-04 by letter dated December 30, 1997, for Nine Mile Nuclear Station, Unit 2 (NMP2). Your response indicates, in part, that you do not take credit for containment overpressure in current NMP2 calculations of NPSH. The NRC staff acknowledges that you also provided NPSH analysis results for item 2 above considering the new Emergency Core Cooling System suction strainers that were installed during the current NMP2 refueling outage, RFO-6.
The NRC staff has reviewed your response and has concluded that all requested information has been provided. Therefore, we consider GL97-04 to be closed for NMP2. Thankyou foryour prompt and complete response.
Ifyou have any questions regarding this matter, please contact me by phone at (301) 415-3049 or by electronic mail at dshonrc.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. 50-410 cc: See next page Distribution:
ocket"~FileP~M PUBLIC PDI-1 Reading OGC ACRS L. Doerflein, RGN-I D. Hood S. Bajwa D. Skay, Lead PM K. Kavanagh S. Little J. Kudrick R. Caruso DOCUMENT NAME: G:>NMP2<NM2A0014.LTR
- See previous concurrence To receive a copy of this document, indicate in the box: "C" ~ Copy without enclosures "E" ~ Copy with enclosures "N" ~ No copy OffICE PH: PDI-1 LA:PDI-1 D:PDI-1 SXRB*
SCSB*
NAME DHood:lcc PD 0 SLittl SBajwa RCaruso JKudrick DATE 06/rt'/98 06/
/98 06/
/98 OFFICIAL RECORD COPY 06/02/98 06/04/98
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3une 4, 1998 J. H. Mueller You responded to GL 97-04 by letter dated December 30, 1997, for Nine Mile Nuclear Station, Unit 2 (NMP2). Your response indicates, in part, that you do.not take credit for containment overpressure in current NMP2 calculations of NPSH. The NRC staff acknowledges that you also provided NPSH analysis results for item 2 above considering the new Emergency Core Cooling System suction strainers that were installed during the current NMP2 refueling outage, RFO-6.
The NRC staff has reviewed your response and has concluded that all requested information has been provided. Therefore, we consider GL97-04 to be closed for NMP2. Thankyou foryour prompt and complete response.
Ifyou have any questions regarding this matter, please contact me by phone at (301) 415-3049 or by electronic mail at dshonrc.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. 50-410 cc: See next page Distribution:
Docket File PUBLIC PDI-1 Reading OGC ACRS L. Doerflein, RGN-I D. Hood S. Bajwa D. Skay, Lead PM K. Kavanagh S. Little J. Kudrick R. Caruso DOCUMENT NAME: G:)NMP2>NM2A0014.LTR
'See previous concurrence To receive e copy of this document. indicete in the box: "C" ~ Copy without enciosures "E" ~ Copy with enclosures "N" ~ No copy OFFICE PM: PDI-l LA:PDI -lr,':PDI-1 SXRB*
SCSB*
DATE 06/+/98 06/
/98 NAME DHood:lcc PD 8 SLittl SBajwa 06/
/98 OFFICIALRECORD COPY RCaruso 06/02/98 JKudrick 06/04/98
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J. H. Mueller You responded to GL 97-04 by letter dated December 30, 1997, for Nine Mile Nuclear Station, Unit 2 (NMP2). Your response indicates, in part, that you do not take credit for containment overpressure in current NMP2 calculations of NPSH. The NRC staff acknowledges that you also provided NPSH analysis results for item 2 above considering the new Emergency Core Cooling System suction strainers that were installed during the current NMP2 refueling outage, RFO-6.
/
The NRC staff has reviewed your response and has concluded that all requested information has been provided. Therefore, we consider GL 97-04 to be closed for NMP2. Thank you foryour prompt and complete response.
Ifyou have any questions regarding this matter, please contact me by phone at (301)'415-3049 or by electronic mail at dshnrc.gov.
Sincerely, O~st~
Darl S: Hood, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-410 cc: See next page
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John H. Mueller Niagara Mohawk Power Corporation CC:
Regional Administrator, Region I
U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector Nine Mile Point Nuclear Station P.O. Box 126 Lycoming, NY 13093
, Mr. Jim Rettberg NY State Electric 8 Gas Corporation Corporate Drive Kirkwood Industrial Park P.O. Box 5224 Binghamton, NY 13902-5224 Mr. John V. Vinquist, MATS Inc.
P.O. Box 63 Lycoming, NY 13093 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. Richard Goldsmith Syracuse University College of Law E.I. White Hall Campus
- Syracuse, NY 12223 Nine Mile Point Nuclear Station Unit No. 2 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Timothy S. Carey Chair and Executive Director State Consumer Protection Board 5 Empire State Plaza, Suite 2101 Albany, NY 12223 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 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399
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