ML17059C218
| ML17059C218 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/24/1998 |
| From: | Hood D NRC (Affiliation Not Assigned) |
| To: | Mueller J NIAGARA MOHAWK POWER CORP. |
| References | |
| TAC-MA1945, NUDOCS 9808310001 | |
| Download: ML17059C218 (12) | |
Text
-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 August 24, 1998-
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONALINFORMATION REGARDING INCREASED SPENT FUEL POOL STORAGE CAPACITY AT NINE MILE POINT NUCLEAR STATION, UNIT 1 (TAC NO. MA1945)
Dear Mr. Mueller:
By letter dated May 15, 1998, you submitted an application for license amendment to change Technical Specification 5.5, "Storage of Unirradiated and Spent Fuel." The changes would reflect proposed modifications to increase the storage capacity of the spent fuel pool at Nine Mile Point Nuclear Station, Unit 1. The NRC staff is reviewing this application and finds that additional information, identified in the enclosure, is needed.
The requests in the enclosure supplement our requests by letter dated August 11, 1998.
Your response to the enclosure is requested within 45 days of receipt of this letter. 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:
Docket No. 50-220 Darl S. Hood, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Supplemental Request for Additional Information cc w/encl: See next page DISTRIBUTION:
Docket Filel PUBLIC PDI-1 R/F JZwolinski (A)
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Mr. John H. Mueller Chief Nuclear Officer Niagara Moha'wk Power Corporation Nine Mile Point Nuclear Station Operations Building, Second Floor P.O. Box 63 Lycoming, NY 13093 August 24, 1998
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONALINFORMATION REGARDING INCREASED SPENT FUEL POOL STORAGE CAPACITY AT NINE MILE POINT NUCLEAR STATION, UNIT 1 (TAC NO. MA1945)
Dear Mr. Mueller:
By letter dated May 15, 1998, you submitted an application for license amendment to change Technical Specification 5.5, "Storage of Unirradiated and Spent Fuel." The changes would reflect proposed modifications to increase the storage capacity of the spent fuel pool at Nine Mite Point Nuclear Station, Unit 1. The NRC staff is reviewing this application and finds that additional information, identified in the enclosure, is needed.
The requests in the enclosure supplement our requests by letter dated August 11, 1998.
Your response to the enclosure is requested within 45 days of receipt of this letter.
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:
Supplemental Request for Additional Information ccw/encl: See next page DISTRIBUTION:
Docket File PUBLIC P,DI-1 R/F JZwolinski (A)
SBajwa SLittle DHood LKopp OGC ACRS LDoerfleln, Rl KParczewski YKim CHinson DShum DOCUMENT NAME: G:>NMP1>NM1A1945.RA2 To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N"= No co OFFICE PH:PDI-1 E
LA:PDI 1
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 August 24, 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:
SUPPLEMENTAL REQUEST FOR ADDITIONALINFORMATION REGARDING INCREASED SPENT FUEL POOL STORAGE CAPACITY AT NINE MILEPOINT NUCLEAR STATION, UNIT NO. 1 (TAC NO. MA1945)
Dear Mr. Mueller:
By letter dated May 15, 1998, you submitted an application for license amendment to change Technical Specification 5.5, "Storage of Unirradiated and Spent Fuel." The changes would reflect proposed modifications to increase the storage capacity of the spent fuel pool at Nine Mile Point Nuclear Station, Unit No. 1; The NRC staff is reviewing this application and finds that additional information, identified in the enclosure, is needed.
The requests in the enclosure supplement our requests by letter dated August 11, 1998.
Your response to the enclosure is requested within'45 days of receipt of this letter. Ifyou should have any questions regarding this request or are unable to meet the requested response schedule, please contact me by phone on (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 No. 50-220
Enclosure:
Supplemental Request forAdditional Information cc w/encl: See next page
i
~ t John H. Mueller Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No. 1 CC:
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
SUPPLEMENTAL REQUEST FOR ADDITIONALINFORMATION REGARDING SPENT FUEL POOL MODIFICATIONS NIAGARAMOHAWKPOWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT NO. 1 DOCKET NO. 50-220 In addition to the information requested by the NRC staff by letter dated August 11, 1998, provide the following additional information regarding the application for license amendment by letter dated May 15, 1998:
III.
PLANT SYSTEMS
.7.
On page X-30 of the Updated Safety Analysis Report (UFSAR) for Nine Mile Point Nuclear Station Unit 1 (NMP1), Niagara Mohawk Power Corporation (NMPC) stated that it "committed to the Nuclear Regulatoiy Commission (NRC), in Technical Specification Amendment 54, that refueling and core offload operations would not begin until it was determined that spent fuel pool [SFP] cooling systems were operable, to ensure that the 125
'F pool temperature would not be exceeded."
In the May 15, 1998 submittal, 140'F is used as the SFP temperature limit in the thermal-hydraulic analyses.
Thus, it appears that the SFP temperature limit is being raised from 125 F to 140 F. Ifthis is correct, please provide detailed evaluation of the effects of this elevated SFP temperature limit on the design and operation of the SFP cooling systems.
This should include the affect upon operator reaction time before pool boiling would occur in the event of a loss of all mechanical cooling systems.
8.
In the thermal-hydraulic analysis (Section 5.0 of Attachments C and F of your submittal) for the unplanned (abnormal) full-core offload scenario, HOLTEC, International assumed, in part, that 36 days after 148 spent fuel assemblies (SFAs) from the previous planned refueling were discharged to the SFP, a full core was transferred to the pool, beginning no sooner than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after reactor shutdown.
Table 5.5-1 of the SFP Re-racking Licensing Report indicates that after each planned refueling, 200 SFAs would be left in the pool.
Therefore, it appears that the thermal-hydraulic analysis for the unplanned full-core offload scenario should be revised using 200 SFAs as the previously discharged SFAs.
Ifthis is correct, provide the revised results (i.e., decay heat load, SFP peak temperature, etc.).
If this is not correct, explain why you consider the use of 148 SFAs to be acceptable for the unplanned full-core offload scenario.
9.
As indicated in the SFP Re-racking Licensing Report, the heat removal capability of the SFP cooling system heat exchangers is a function of the temperature of the reactor building closed loop cooling (RBCLC) water system.
To maintain the SFP water below the temperature limitof 140 'F, the reactor shutdown time required before any SFAs are discharged to the SFP varies with RBCLC water temperature.
Specifically, the following Enclosure
Q f
~
I ~ reactor shutdown times required before discharging SFAs to prevent the SFP from exceeding the 140'F temperature limitduring a planned full-core oNoad (normal refueling) operation have been established with RBCLC water at four temperatures:
RBCLC Water em crau SFAs In Reactor Decay 40 60 80 95 72 116 405 916 Provide the following information:
- a. Has single active failure of the SFP cooling system been considered in establishing the above constraints'
- b. HOLTEC, International recommends that the above constraints to fuel discharge operations be Incorporated into appropriate plant procedures.
What is NMPC's position regarding the establishment of procedures for these fuel discharge constraints'
- c. What is NMPC's position and reasoning as to whether these restrictions should be included in the NMP1 TS'?
10.
Discuss the procedures to be utilized by NMPC staff to monitor and control SFP water temperature and decay heat load so that these parameters willremain within the design basis limiting values for planned or unplanned full core offload events.
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