ML20062E978

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Forwards Addl Info on Rev 1 to TS Change Request 181 Re ATWS Steam Flow & Suppression Pool Temp.Number of Safety Valves to Be Removed from Svc Revised from Eight to Seven.Info Re ATWS Steam Flow & Suppression Pool Temp Also Provided
ML20062E978
Person / Time
Site: Oyster Creek
Issue date: 11/16/1990
From: Laggart M
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C320-90-237, NUDOCS 9011270002
Download: ML20062E978 (13)


Text

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GPU Nuclear Corporation Nuclear

en:r 88 Forked River, New Jersey 087310388 j

609 971 4000 Writer's Direct Dial Nurnber; 1

November 16, 1990 C320-90-237 U. S. Nuclear Regulatory Commission Att Document Control Desk Washington, DC 20555 Gentlemen l

l Subject Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-219 License No. DPR-16 Technical Specification Change Request No. 181 (Rev. 1)

Reference:

GPUN Letter 4/30/90 At the request of the NRC Staff, the referenced letter of April 30, 1990 provided. supplemental information to delineate the plant response for eight L. safety valves. Based on subsequent conversations with Staff personnel, the number of safety valves to be removed from service has.been revised from eight to-seven. 'Two graphs have been revised to reflect this (graphs 3 and 4).

The remaining graphs-(1, 2, 5,

6,.7, and 8) do not impact the determination of the number-of-safety valves required.

~The staff also requested information concerning ATWS steam flow, and suppression pool temperature (16 vs. 8 safety valves). These are also attached (curves 9.and 10).

These curves were developed utilizing RETRAN licensing model plus a suppression pool heatup model.

In addition, the assumption was made that all safety valves discharge directly into the suppression pool rather

than the drywell. The heatup is calculated as a pure energy and mass deposition into the tort s, with instant perfect mixing.

This is the most conservative approach and results in suppression pool temperature reaching 110*F'(EOP action point of boron injection).at.almost identical times, utilizing either 16 or 8 safety valves. The change from 8 to 9 remaining safety valves would result in even less time difference.

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9011270002 901116,

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PDR ADOCK 050002iY

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GPU Nuclear Corporaticn is a subsidiary of General Pubhc Utsties Corporation

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,TSCR 181 (REV. 1)

'REF: GPUN LETTER 4/30/90 l

PAGE 2 i

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'If there are any questions or comments on this matter, please do not hesitate j

to contact me at (201) 316-7968.

i Sincerely, M. W. Laggart Corporate Nuclear Licensing Manager MWL/BMP/ pip j

Attachment l

cci Administrator

'f Regiot U. S. Hualear Regulatory Commission 475 Allendaic Road King of Prussia,;PA 19406 1

NRC Resident Inspector oyster Creek Nuclear Generating Station j

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Project Manager U. S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, DC 20555 i

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Attcchment LIST OF ENCLOSURES FIGURE NO.

1 Safety Valve Flow-Main Steam Isolation Valve Closure-No Scram (ATWS), Cycle 12, 16 Safety Valves 2

Heat Flux, Power, Core Flow-Main Steam Isolation Valve Closure-No Scram (ATWS), 16 Safety Valves 3

Normalized Power, MSIV Closure with Scram, cycle 12, 9 Safety Valves, No Recirculation Pump Trip 4

Reactor Vessel Lower Plenum Pressure Rise-MSIV Closure with Scram, Cycle 12, 9 Safety Valves, No Recirculation Pump Trip 5

Normalized Turbine Flow-MSIV Closure with Scram, Cycle 12, 8 Safety Valves, Recirculation Pump Trip t

6 Safety Valve Flow-MSIV Closure with Scram, Cycle 12, 8 Safety Valves, Recirculation Pump Trip 7

Reactor Vessel Lower Plenum Pressure Rise, MSIV Closure, ATWS, 8 Safety Valves, 5 Electromatic Relief Valves, Recirculation Pump Trip-8 Normalized Power, MSIV Closure, ATWS, 8 Safety Valves, 5 Electromatic Relief Valves, Recirculation Pump Trip 9

EMRV,and Safety Valve Steam Flow, ATWS (16 vs. 8 Safety Valves) 10 Suppression Pool Temperature, ATWS (16 vs. 8 Safety Valves)

BP C320237

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