ML20064J333
| ML20064J333 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/23/1979 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-08-02, TASK-08-03.B, TASK-8-2, TASK-8-3.B, TASK-RR NUDOCS 7901300143 | |
| Download: ML20064J333 (4) | |
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Jersey Contral Power & Light Company
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Masson Aenue a* Pt.nch Scwl Acad m% w.rs Mcrnstown. New e sey 07960 (201)455-8200 January 23, 197.'
Mr. Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactcrs Nuclear Regulatory Commission Washingten, D. C.
20555
Dear Mr. 2iemann:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Request for Additional SEP Information The enclosed informatica is being forwarded to you in response to your letter dated October 26, 1978.
The information herein is as follows:
1.
schematic diagrams of load transfer switches IT-3, IT-4, LAB 2, VACP-1, and PS-1.
2.
Oyster Creek plant drawing index 3.
drawing number D-3033-1A showing the battery and charger alarms and indications.
4.
list of diesel generator loads supplied under emergency conditions.
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In addition to the above information you had requested the following:
1.
Topic VI-7.B ESF Switchover from Iniection to Recirculaticn Mode (Automatic ECCS Realignment).
Schematics for the automatic controllers used (if any) to perform the changeover.
This system is not ap'plicable to the Oyster Creek Nuclear Generating Station.
2.
Topic VII - 1. A Isolation of Reactor Protection System from Non-Safety Systems, Including Qualification of Isolation Devices Drawings and schematics which show:
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How the Reactor Protection System gets its g(
input signals.
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Jerrey Certrat Power & Lart Cctrcany.s 3 Mem::e* of Te Genera: Puthe UNtes 3. stem D*
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How the other system inputs are isolated from the Reactor Protection System inputs.
The schematics and drawings pertaining to this subject were enclosed in our June 26, 1978 submittal. The information is found on drawing number GE 237E566, " Reactor Protection System".
If there are any questions regarding any of the enclosed infor-mation please contact Jim Knubel, Supervisor, Nuclear Safety 5 Licensing (201/455-8753) or myself.
Very truly yours, r
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't Ivan R. Finfrock, Jr.
Vice President cp i
DIESEL GENERATOR LOADS SUPPLIED UNDER EMERGENCY CONDITIONS NORMAL OPERATION (BUS 1C and BUS ID AVAILABLE)
Nameplate Rating Rated Condition Emergency Lighting (immediately) 70 70 Instruments, Controls, Misc. Small 250 250 Motors, and Systems Losses (immediately)
- Security System Loads (immediately)DG-1(DG-2) 88(76HP) 30 (76 HP)
Closed Cooling Water Pumps (after 200 176
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approximately 166 sec.)
Standby Gas Treatment (immediately) 70 70 Core Spray Pump (immediately 500 462 on Command)
Core Spray Booster (5 seconds 300 285 after CSP)
Control Rod Drive Feed Pumps 250 252 (After booster discharge pressure attained - after approximately 60 sec.)
Service Water (2 minutes delay) 250 252 Containment Spray (45 seconds delay) 300 237 Emergency Service Water Pump 400 405 (3 minutes after containment spray)
Normal Operation Total DG-1 (DG-2) 2678 HP (2666 HP) 2547 HP (2535 Category 1 load HP)
Equivalent kw DG-1 (DG-2) 1988 KW (1989 KW) 1900 KW (1891 KW)
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DIESEL GENERATCR LOADS SUPPLIED UNDER EMERGENCY CONDITIONS (CONT'D)
ADDITIONAL CSS LOADS (BUS IC or BUS 1D UNAVAILABLE)
Nameplate Rating Rated Condition Additional Core Spray Pump 500 162 (5 seconds after first booster)
Additional Booster Pump 300 289 (5 seconds after additional CSP)
Total Category 1 Load which must 3540 HP 3356 HP start automatically J.'
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Equivalent KW 2640 KW 2500 KW Assume 95% Efficiency for large 2760 KW 2616 KW Motors, Total Load
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