JPN-91-027, Forwards Response to NRC Request for Addl Info Re 900531 Application for Amend to License DPR-59,changing Tech Specs Covering Spent Fuel Storage Capacity
| ML20077G888 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/26/1991 |
| From: | Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JPN-91-027, JPN-91-27, NUDOCS 9107030006 | |
| Download: ML20077G888 (7) | |
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llmMr2..r' Jurm 26, 1991 JIN-91-027 U.S. Nuclear Rogulatory Commlssion ATTN: Cocument Control Desk Mall Station P1 137 Washington, D.C. 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50 333 Request No. 3 for Additional Information -
Proposed Changes to the Technical Specifications Spent Fuel Pool Storage Capacity (JPTS 90-035)
Reference:
NYPA lotter, J.C. Brons to NRC, dated May 31,1990 (JPN40-042), ' Proposed Changes to the Technical Spocifications Regarding Spont Fuel Pool Storage Capacity."
tear Sir:
The NRC Informally requested additior,N hformation concoming the Authority's proposed changes to the FitzPatrick Technic 5 Specifications for increased spent fuel storage cepacity. The proposed changes were submitted with the reference lotter.
Attachment I provides the Authority's response, li you have any further quest'ons, please contact Mr. J. A. Gray, Jr.
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Ralph E.*Boedle Exocutive Vice President Nuclear Gonoration l
STATE OF NEW YORK COUNT ( OF WESTCHESTER Subscribed and swpm to before me thisA(, d.r.iay of M 1991.
l Notary Public not E D [.l.D3 N,, m cc: see next page
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Roglonal Administrator U.S. Nuclear Rogutatory Commissico 475 Allondale Road King of Prussia, PA 19406 i
Office of the Resident inspector U.S. Nuclear Rogulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Brian C. McCabo Project Directorato 11 Division of Roactor Projects.1/11 U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, D.C. 20555 r-m
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Attachment I to JPN 91027 f
RESPONSE TO NRC REQUEST No. 3 FOR ADDITIONAL INFORMATION SPENT FUEL POOL STORAGE CAPACITY INCREASE i
NRC Ovostion 1.
In your submittal dated May 31,1990, you indicated that the spont fuoi pool cooling system consists of two 100 porcont capacity cooling pumps and two 50 percent capacity heat exchangers. You have also indicated that the maximum normal heat load will be 13.10 X 10e BTU /Hr and that the maximum pool temperature will be 145.84* F with both cooling pumps oporating. What will be the maximum normal fuol pool temporaturo assuming a single active failure in the cooling systom? Is the heat exchanger rated for both pumps operating?
NYPA Rosponso:
The spent fuel pool cooling (SFPC) system can be cuppbmonted by tho use of the Residual Heat Removal (RHR) system in the spent fuol coolhg assist mode. The RHR assist mode is only availabio during plant sN'..iowns. After the reactor has been shutdown for 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and tho fuel has been moved to the spent fuel pool (SFP), the total docay hoat load at 0
the maximum pool temperature in the SFP will be 13.10 X 10 BTU /hr.
The following subsections discuss the changes in spent fuol pool temperature whon a single active failuro in SFPC system occurs during plant shutdowns and plant operations.
PLANT SHUTDOWN The maximum fuol pool temperature, assuming a single activo f ailuro in the SFPC system during a plant shutdown, is less than 150* F.
In the event of a failure in the SFPC system, the RHR assist modo can Supploment the cooling capacity during plant shutdowns. Any one of tho four RHR pumps can be used with one of the two RHR heat exchangers i
to supplement the SFPC capacity. When the plant is shutdown, one RHR pump and one RHR heat exchanger are already in service or linod up in the shutdown cooling mode to remove decay heat from the coro. The remaining RHR host exchanger and one of it's two associated RHR pumps are availab!e for RHR SFPC assist modo. If one SFPC pump fails at any timo during a refueling outage, the RHR assist modo can maintain the bulk temperature at less than 150* F. The RHR assist mode may be used for SFPC only when the reactor coolant temperatmm below 212* F.
Pl. ANT OPERATION The maximum fuol pool temperatur0, assuming a single active falluto in the SFPC system during plant operation, would be loss than 150* F.
A 45 day refueling outage was selected for this analysis becauso it is conservative with respect to the decay heat load. The shorter the outogo, the highor the heat load. Forty five days is the shortest realistic timo nooded to complete refueling and mhor tasks prior to plant restart.
1
Attachment I to JPN.91027 Attor a 45 day refueling outago, the spent fuel pool water temperaturo will drop below 130' F. When the plant restarts, the RHR assist modo is unavailable if one SFPC pump becomes disabled at this time, the total 8
decay heat load would be 7.724 X 10 BTU /hr at the maximum bulk temperature of 147' F (see case 1 on Table 1). If ono SFPC pump falls while one SFPC heat exchanger is out of service, the total heat docay 8
load would be 7.705 X 10 BTU /hr at the maximum bulk temporaturo of 153.91* F (see case 2 on Table 1).
Table 1 shows the madmum bulk pool temperature assuming differont combinations of SFPC equipment in oporation. Figuros 1 and 2 provido the pool bulk temperaturo versus timo for two diiforent SFPC falture scenarios. Figure 1 providos the bulk temperature whon ono SFPC pump falls 45 days ofter reactor shutdown (caso 1 on Table 1). Figuro 2 providos bulk temperature when ono SFPC heat exchangor is out of service and one SFPC pump falls 45 days after reactor shutdown (case 2 on Table 1).
In responso to the second part of the question, the output of each SFPC pump is 350 gpm and each SFPC heat exchangor is rated for 700 gpm (soo case 3 on Table 1). Each SFPC heat exchanger is designed to support simultaneous operation of both pumps.
NRC Ouestion 2.
In Table 5.3.1 of your submittal, you have assumed 3344 fuel assemblics stored in the spent fuel pool for heat load calculations. Why have you used the number 3344 while the total storago copacity of the spent fuel pool with the proposed expansion will only be 27977 NYPA Responso:
The spent fuel pool (SFP) heat load calculations conservatively assumed the presence of 3344 fuel assemblics. Using 3344 fuel assemblics, the calculation demonstratos the SFP cooling systom's ability to adoquately cool the higher heat load associated with a pool filled with consolidated spent fuel. However, the Authority does not plan to consolidato FitzPatrick spent fuel at this time. In the ovent that consolidated fuel storage becomes necessary, the SFPC systom's ability to handle this heat load w31 have been demonstrated.
2-
Attachment I to JPN 91 XXX Tablo 1 Maxirnum Norrnal Dischar00 Pool Temperaturo Fuol Poc4 Water Fkm Max. Bulk Caso Component Rato Through Pool Tomp HAF*
THl."
N o.
In Operation Each Cooler F
hr.
Btu /hr 1
1P + 2HX"*
189 gpm 147.00 68 7.724EG 2
1P + 1HX 375 gpm 153.91 78 7.705EG 3
2P+ 1HX 700 gpm 141 G5 59 7.742EG Hours after oquipment failure Total docay heat load at the maximum bulk pool temperaturo P = pump; HX = Heat Exchangor 3-
Attachment I to JPN 91427 1
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