ML19350A671
| ML19350A671 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/10/1981 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| IEB-80-06, IEB-80-6, NUDOCS 8103160630 | |
| Download: ML19350A671 (3) | |
Text
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['O Common'iee!th Edison n ) One First Nationa Pt:za, Chicago. Illinois C'
Address RJpl; to: Post Ofhce Box 767 Chicago, Illirois 60690 March 10, 1981 s C.' } !$
o; Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
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Subject:
Zion Station Units 1 anri 2
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11 Supplemental Information
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y[g NRC Docket Nos. 50-295/304 p
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'Y' Reference (a):
June 10, 1980 letter from D.
L.
to J. G. Keppler.
Dear Mr. Denton:
This is to provide additional information regarding Zion's engineered safety feature reset controls.
The information contained in Attachment A was discusstrd with the NRC staff by telephone on March 3, 1981.
One (1) original End thirty-nine (39) copies of this letter are provided for your use.
Please address further questions to this office.
Very truly yours,
~?;}2, f W "'-
T. R.
Tramm Nuclear Licensing Administrator Pressurized Water Reactors Attachment
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cc:
Zion Resident Office Doug Hackett, EG&G i
.810816 041A 1255B: Q
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Attachment A Additional Information Regarding Zion's Engineered Safety Feature Reset Controls Question a.
In performing the required drawing review, were all systems serving safety-related functions considered?
List any safety-related systems that were not reviewed and provide a schedule for completion of your review.
Response a.
Yes, all systems were reviewed.
Question b.
Clarify why you have listed valves OA0V-SWOO20 (Unit
- 1) and OA0V-SWOO21 (Unit 2) in the category of "the following equipment will reset to the preactuateo position upon ESF reset" if they remain in their emergency mode as you stated in your response.
Response b.
0A0V-SW20 and 0A0V-SW21 will normally remain open un a reset of Safety Injection because the RHR pumps will be operating and their controls will keep the valves ~
open.
When the pumps are stopped, and service water is not needed, the valves will close.
Question c.
Provide a clarification and description of the proposed and/or implemented modification to valve OFCV-SW54.
Response c.
OFCV-SW54 will now stay closed.
The modification consists of a reset button which has to be pushed to pick up a relay that opens the valve.
This can only be done after Safety Injection has been reset.
Question d.
Provide a description of the modification (s) necessary to prevent the containment fan cooler dampers from changing from their emergency position upon reset of CVI.
Clarify and describe why you are not modifying
-this equipment so that it will remain in its emergency mode upon reset of the ESF actuation signal.
Response d.
The containment fan cooler dampers are not be'ing modified.
These dampers will stay in the actuated position on a reset of Safety Injection.
For these dampers to go'to the normal position, safety injection i
(
4 and containment ventilation isolation must be reset with the control switch left in the normal position.
The control switch would be placed in the accident l
position by the operator shortly after the safety injection.
Note:
All modifications involving NRC Bulletin 80-06 have been completed.
The testing on both units is done with all equipment staying in the actuated position as expected.
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