ML20212A403
| ML20212A403 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/19/1987 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 5211-87-2025, NUDOCS 8703030343 | |
| Download: ML20212A403 (2) | |
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GPU Nuclear Corporation
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NggIgf Post Office Box 480
- y Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number
1 February 19, 1987 5211-87-2025 Dr. Thomas E. Murley Region I, Regional Administrator U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Remote Shutdown Integrated Test As documented in NRC Inspection Report 86-14, GPUN plans to perform an integrated test of the remote shutdown system prior to criticality for Cycle 6 operation. This letter is to inform you of the objective of the test and provide a description of the test.
The objective of the test will be to demonstrate the ability of Operations personnel to transfer plant cooldown control from the Control Room to the Remote Shutdown Panel and maintain stable hot shutdown conditions at approximately 532*F.
RCS temperature will then be reduced approximately 30*F and maintained for 30 minutes using remote shutdown system controls.
Prior to the performance of the integrated test, the following tests will have been performed:
remote shutdown comnunication system test o-diesel generator functional test from the 4160V ES switchgear lE tu o og adequacy of emergency lighting to conduct remote shutdown activities So individual control circuit tests for conponents n:c Eo The integrated test procedure will be based on the TMI-l Emergency Procedure om<
1202-37 "Cooldown from Outside the Control Room." It will be assumed that oL there is not a loss of offsite power since operation of the diesel will have so been demonstrated earlier.
It will also be assuned that there will be no loss l ma.a-of vital buses. Demonstration of de-energizing and re-energizing buses could potentially damage operating plant equipment.
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation reoi i
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5211-87-2025 February 19, 1987 Plant conditions for the test will be hot shutdown conditions with RCS temperature at approximately 532*F and all 4 reactor coolant pumps running.
The test will be performed by an operating crew of five with a standby operating crew remaining in the Control Room. The test will begin by simulating the nanual actions to be taken prior to leaving the Control Room as specified in the emergency procedure. Operators will simulate tripping the Reactor, the Turbine and the Main Feedwater punps. The steam-driven EFW pump and two motor-driven EFW pumps will then actually be started from the Control Room. The assunption is being made for the test that the circuitry for the 3 EFW pumps was not damaged by fire and therefore the pumps would have started when the Main Feedwater pumps tripped.
One Main Feedwater Pung, which will be running due to the plant condition, will remain running on rectre and the feedwater control valves will be closed. Manual control will be maintained in the control room as a contingency measure. Makeup Pump B will be running and remain running throughout the test.
Isolation transfer switches on the Remote Shutdown Transfer Panels for the affected components will be placed in the emergency position. However, during the test, only the components necessary to complete the evolutions will be used. Components not directly affected by the cooldown, such as certain intermediate cooling pumps and valves, nakeup valves and reactor coolant system valves, will not be used unless it is absolutely necessary due to potential damage to plant equipment.
Once cooldown control has been transferred to the remote shutdown station, the hot shutdown condition and RCS temperature of approximately 532*F will be maintained for 30 minutes primarily using the atmospheric dump valves and emergency feedwater control valves.
RCS tenperature will then be reduced
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approximately 30*F and maintained for 30 minutes using the atmospheric dump valves and emergency feedwater control valves.
Support components will be used as needed during the ~ test.
Upon completion of the test, control will be transferred back to the Control Room.
The test procedure and results will be available for your review at the site.
I Sincerely,
[
. D.
u ill Vice President & Director, TMI-l HDH/SM0/spb i
cc:
J. Thoma F. Young 0779A k
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