ML20072A785
| ML20072A785 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/26/1983 |
| From: | Farrar D COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20072A768 | List: |
| References | |
| 6589N, NUDOCS 8306100250 | |
| Download: ML20072A785 (3) | |
Text
'
' ['~h Commonwealth Edison l
) Ona First National Plaza. Chictgo, filinois g TT ' Address Reply to: Post Office Box 767 Chicago. Illinois 60690 May 26, 1983 Mr. James G. Keppler, Regional Administrator Directorate.of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
LaSalle County Station Units 1 and 2 Response to Inspection Report Nos.
50-373/83-11 and 50-374/83-06 NRC Docket Mcs. 50-373 and 50-374 Reference (a):
J. F. Streeter letter to Cordell Reed dated April 28, 1983.
Dear Mr. Keppler:
This letter is in response to the inspection conducted by Messrs. R. D. Lanksbury and S. G. DuPont on March 7 through April 8, 1983, of activities at LaSalle County Station.
Reference (a) indicated that certain activities appeared to be in noncompliance with NRC requirements.
The Commonwealth Edison Company response to the Notice of Violation is provided in the enclosure.
To the best of my knowledge and belief the statements contained herein and in the attachment are true and correct.
In some respects these statements are not based upon my personal knowledge but upon l
information furnished by other Commonwealth Edison employees.
Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
If you have any further questions on this matter, please direct them to this office.
l Very truly yours,
~:,
u D.
L.
Farrar Director of Nuclear Licensing CWS/lm Attachment cc:
NRC Resident Inspector - LSCS g[qy g gg 8306100250 830606 6589N PDR ADOCK 05000373 Q
PDR L
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ATTACHMENT A Response-to Inspection Report Nos. 50-373/83-11 and-50-374/83-06 Item of Noncompliance
'10 CFR'50, Appendix B, Criterion V, states, in part,sthat " Activities affecting quality shall be prescribed by instructions, prccedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."
Contrary to the above requirements, the reactor protection system preoperational test procedure (PT-RP-201) was not appropriate to the circumstances in that:
(a)
The procedure did not provide adequate instructions to determine the end of cycle-recirculation pump trip system response time for the turbine' control valves.
(b)
'The station procedure referenced in the test procedure to. verify the trip setpoint of the valve position scram switches incorpo' rated the required trip setpoint incorrectly and nonconservatively.
Response
Corrective-Action Taken and Results Achieved An Action Item Record (AIR 01-83-178), has been initiated to ensure that the applicable station procedures are corrected prior to the performance of the affected portions of preoperational test PT-RP-201.
l-Corrective Action Taken to Avoid Further Noncompliance i
l This noncompliance has been discussed with all System Test Engineers, and.with other individuals in the review and approval r
chain for test procedures.
All Test Engineers have been reinformed l
of their responsibility for the technical adequacy of station proce-dures used during preoperational tests.
A review is accomplished at least twice:
once during test procedure preparation, and again just prior to use.
Apart from this station review, Project Engineering l
has recently completed a review of all station procedures utilized to obtain preoperational test data.
l l
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. J Date of Full Compliance Full compliance will-be achieved when preoperational test procedure PT-RP-201 is revised.
.This will be accomplished after the relevant station procedures are revised.
PT-RP-201 and the relevant station procedures will be revised prior to Unit 2 fuel load.
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s 6589N I
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