ML20214U880
| ML20214U880 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/02/1986 |
| From: | Wilson R GENERAL PUBLIC UTILITIES CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM 5000-86-1093, NUDOCS 8612090433 | |
| Download: ML20214U880 (2) | |
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GPU Nuclear Corporation NUDIM7 100 Interpace Parkway Parsirpany, New Jersey 07054-1149 (201)263-6500 TELEX 136-482 es nect Dial Nden December 2, 1986 5000-86-1093 Mr. John A. Zwolinski, Director BWR Licensing Directorate #1 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Zwolinski:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 NUREG 0737 Item II.E.4.2(7)
Containment Isolation Dependability
Reference:
Letter from J. N. Donohew, Jr. to P. B.
Fiedler dated August 4,1986 and Enclosures We have reviewed both the generic NRC staff safety evaluation, " Evaluation of the Radiological Consecuences for Accidental Releases Through BWR 2-inch Vent and Purge Lines" and the Boiling Water Reactor Owners' Group (BWROG) evaluation of the subject NUREG 0737 item. We have confirmed that both evaluations, which conclude that BWR purge and vent lines of 2 inches in diameter or less need not be provided with a containment high radiation isolation signal, are applicable to the Oyster Creek Nuclear Generating Station, as discussed below.
Utilizing the BWROG evaluation method and additional conservatisms adopted by the NRC staff evaluation, dose rates were calculated using plant specific values together with generic parameter values. The dose rates were shown to be several orders of magnitude less than the acceptance criteria of 10% of 10CFR100 limits assuming both 2 inch vent lines are open.
0617090433 861202 PDR ADOCK 05000219 P
PDR AA GPU Nuclear Corporation is a subs @ary of General Pubhc Utihties Corporahon j
a - ;f 1 As regards the 30 minute operator response time, we have concluded that the appropriate indication to initiate closure verification of the 2 inch containment vent and purge line valves is the control room alarm which annunciates on containment high radiation. The alarm annunciates at a radiation level which is approximately 30% of the level associated with a source term in containment that would result in offsite dose rates at the l
10% of 10CFR100 limits from the large containment vent and purge lines.
l The alarm setpoint, therefore, provides acceptable conservatism. The applicable alarm response procedure will be revised prior to restart from the current Cycle llR outage to require the operators to verify closure of the small containment vent and purge valves. The valve controls and their status indication are in the control room, and this action can be conpleted within 30 minutes. Operator training on this procedure will be conducted during cyclic training.
If you should have any questions concerning the above information, please contact Mr. M. W. Laggart at (201) 263-6205.
yt ly yours, Y.
W R. F. Wil on Vice President Technical Functions RFW/pa(1518 )
9 cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA.
19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N.J.
08731 Mr. Jack N. Donohew, Jr.
U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Phillips Building, Mail Stop 314 Bethesda, Maryland 20014
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