ML20004B910
| ML20004B910 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 05/27/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 81-35, GL-81-04, GL-81-4, NUDOCS 8106010294 | |
| Download: ML20004B910 (2) | |
Text
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SNUPPS Sb 2 b 1bS1 Standardized Nuclear Unit Power Plant System M,* f 5 Choke Cherry Road Nicholas A. Petrick Exocutive Director Rockvdie, Meryland 2005o g
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(sou ses.aoio May 27, 1981 SLi'4RC 81-35 FILE: 0278 SUBJ: Emergency Procedures and Training for Station Blackout Events
!!r. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. iluclear Regulatory Commission Washington, O. C.
20555 Occket rios. : STd 50-482, STN 50-483, STil 50-486
References:
1.
ilRC Generic Letter 81-04, February 25, 1981, Same subject 2.
Westinghouse Owners Group Letter 0G-56, April 9,1981, Same subject Jear Mr. Denton:
Reference 1 requested an assessment of procedures and training programs relative to station blackout events.
This letter requested evaluations in seven specific areas as well as a definition of training programs for the loss of all AC power event.
The Sr4UPPS Utilities are participants in the Westinghouse Owners Group which is developing generic guidelines for the loss of all AC Power event.
Reference 2 reported the activities of this group and stated that the generic guidelines would be submitted to the :lRC by September 1,1981.
tmergency operating procedures for the Si1UPPS plants are still under devel-opment and review. Completion of the procedures will support the plant schedules. Guidelines developed by the Westinghouse Owners Group for items a, o, e and g of Reference 1 will be considered in the procedure develop-ment. Procedures for the SNUPPS plants will also include consideration of restoring offsite power as requested in items c and d of Reference 1.
The SituPPS FSAR Section 9.5.3 describes emergency lighting (item f of Reference 1).
tach SNUPPS site includes a simulator which will have the capability of simulating tne loss of all AC power and demonstrating the removal of cecay neat by natural circulation and the steam-driven auxiliary feedwater pump.
Operator requalification programs and simulator exercises are still under cevelopment. However, tne above evolution will be included in these programs.
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8 Page Two The plans outlined above show that the recommendations of Reference I will be met by the SNUPPS plants prior to fuel load at Callaway Unit I and Wolf Creek.
Very, truly yours, b
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Nicholas A. Petrick RLS/srz l
cc:
J. K. Bryan UE G. L. Koester KGE
- 0. T. McPnee KCPL W. A. Hansen NRC/ Cal T. E. Vandel NRC/WC
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