ML20005A484
| ML20005A484 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
| Issue date: | 06/22/1981 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8106300383 | |
| Download: ML20005A484 (1) | |
Text
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Commonwealth Edison i
~ One First National Plaza. Chic'go. Illinois j
AJdress Reply to: Post Office Box 767
.3 Chicago, lilinois 60690 j
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N June 22, 1981 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Dresden Station Units 1, 2 and 3 Quad Cities Station Units 1 and 2 Zion Station Units 1 and 2 LaSalle County Station Units 1 and 2 Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Emergency Procedures and Training for Station Blackout Events NRC Docket Nos. 50-10/237/249/254/
265/295/304/373/374/454/455/456/457 Reference (a):
February 25, 1981, letter from D. G.
Eisenhut to All Licensees and Applicants
Dear Mr. Denton:
This letter provides information requested in reference (a) regarding emergency procedures and training for station blackout events at all Commonwealth Edison nuclear power plants.
Attachment A to this letter provides an assessm',nt of the existing procedures and training programs.
Schedules for planned changes are supplied where necessay.
Please address further questions regarding this matter to this office.
Very truly yours, kt M
30M T. R. Tramm Nuclear Licensing Administrator J
!I 1m 2209N 81068003&3 I'
4 ATTACHMENT A Assessment of Procedures and Training for Station Blackout Events This assessment addresses the issues identified in reference (a) in the format of that letter.
Item a:
The actions necessary and equipment available to maintain the reactor coolant inventory and heat removal with only DC power available, including consideration of the unavailability of
-auxiliary systems such as ventilation and component cooling.
Assessment:
Procedures and training programs will be revised to more completely specify the required actions at each of our nuclear plants.
Th schedules for these changes vary between plants.
The Westinghouse Owner's Group is preparing emergency operating guidelines that will be the basis for revisions to procedures at Zion,. Byron and Braidwood.
As a result of Generic Letter 87-04, the schedule for sending these guidelines to NRC has been advanced to September 1, 1981.
Implementation of the guidelines in plant procedures and training programs will be consistent with our schedules for NUREG-0737, Item I.C.1 and is dependent upon timely NRC review of the guidelines.
At Dresden, Quad Cities and LaSalle County the necessary procedure changes and training will be complete by September 3, 1981.
Item b:
The estimated time available to restore AC power and its basis.
Assessment:
The time to restoration will vary according to the nature of the equipment outages.
Switching operations and restarting emergency diesels can be done in a few minutes.
Temporary reconstruction of the switchyard would take several days.
a n
s Item c:
.The actions for restoring offsite AC power in the event of a loss.of the grid.
-Assessment:
The present Commonwealth Edison transmission. system emergency plan provides adequate guidance for fastest system
-restoration in the event of a complete shutdown.
The plan is reviewed and revised annually.
It provides for independent restoration in each of our seven main geographic areas.
When the interties with neighboring utility systems are unavailable, restoration begins et the generating stations having " black start" capability.
Power is then restored to the other generating station switchyards.
Any nuclear station without emergency AC power would have first priority in such a restoration.
Item d:
The actions for restoring off-site AC power when its loss
,is due to postulated on-site equipment failures.
Assessment:
The transmission system emergency restoration plan described above encompasses events involving on-site equipment failure and is adequate from the standpoint of system restoration.
Special interconnections are available at each multiple unit generating station to enable quick restoration of off-site AC power if a plant transformer fails.
Plant procedures adequately address switching operations necessary to use these interconnections.
Where use of i nterconnections requires the involvement of maintenante personnel, the appropriate maintenance procedures will be revised or instituted by September 3, 1981, at the operating stations and prior
'to fuel loaa at the plants under construction.
Item e:
The actions necessary to restore emergency on-site AC power.
The actions required to restart diesel generators should include consideration of loading sequence and the unavailability of AC power.
Assessment:
Existing procedures are generally adequate in this regard.
Mino,* revisions will be complete by September 3, 1981, at the operating stations and prior to fuel load at the plants under construction.
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Item f:
Consideration of the availability of emergency lighting, and any actions required to provide such lighting, in equipment areas where operator or maintenance actions may be necessary.
Assessment:
The emergency lighting at operating stations is being upgraded to comply with Appendix R.
Changes will be complete by January-1, 1982.
At the plants under construction, emergency lighting will be available prior to fuel load.
Item 9:
Precautions to prevent equipment damage during the return to normal operating conditions following restoration of AC power.
For exampic, the limitations and operating sequence requirements which must be followed to restart the reactor coolant pumps folicwing an extended loss of seal injection water-should be considered in the recovery procedures.
Assessment:
Existing and planned procedures include precautions for equipment startup following outages of any type.
Additional guidelines will be incorporated as they become available from generic investigations such as those undertaken by Owner's Groups and equipment suppliers.
Additional Item:
The annual requalification training program should consider the emergency procedures and include simulator exercises involving the po3tulated loss of all AC power with decay heat removal being accomplished by natural circulation and the steam-driven RCIC and/or HPCI and the safety-relief valves in BWR plants.
Assessment:
The annual requalification training programs consider emergency procedures and will include simulator exercises for loss of all AC power.
2209N