ML20207L141
| ML20207L141 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/07/1988 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20207L145 | List: |
| References | |
| NUDOCS 8810170208 | |
| Download: ML20207L141 (2) | |
See also: IR 05000254/1988021
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OCT 7
1988
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Docket No. 50-254
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Docket No. 50-265
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EA 88-240
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Commonwealth Edison Company
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ATTN: Mr. Cordell Reed
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denior Vin President
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Post Office Box 767
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Chicago, IL 60690
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Gentlemen:
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This refers to the special safety inspection conducted by Messrs. J. Holmes,
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R. Hodor, and K. Sullivan, of this office during the period of February 22-26,
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June 27-28 and September 1, 1988, of activities at Quad Cities Nuclear Power
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Station, Units 1 and 2, authorized by NRC Operating Licenses No. DPR-29 and
No OPR-30, and to the discussion of our findings with Mr. N. Kalivianakis
at the conclusion of the inspirettor..
This inspection was conducted to assess
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compliance with 10 CFR 50, Appendix R, and to review implementation of certain
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Fire Protection Program requirennts.
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The enclosed copy of our inspe.: tion report identifies areas examined during
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the inspection. Within these areas, the inspection consisted of a selective
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examination of procedures and representative records, observations, and
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interviews with personnel.
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During this inspection, certain of your activities appeared to be in violation
of NRC requirements,
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We are releasing this report at this time for your information.
Following an
Enforcement Confe ence, you will be notified by separate correspondence of our
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decision regarding enforcement actions based on the findings of this inspection.
No written response is required for the apparent violation until you are
notified of the proposed enforcem6nt actions.
We are concerned with what appears to be a lack of adequate Safe Shutdown
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Procedures as required by Appendix R.
We request that you address at the
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upcoming Enforcement Conference the actions that would have been required
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to be taken in the event of a disabling fire in fire areas 11.1.1.B. 8.2.6.C
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and 8.2.7.C prior to the February NRC inspection.
In fire areas S.2.6.c and
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8.2.7.c you should also consider a disabling fire that would cause a spurious
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closure of the RCIC Inboard Steam Supply Isolation Valve concurrent with a loss
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of Switchgear 18 due to high impedance faults.
You should in,.lude in your
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discussion the length of time to complete all manuc1 operations.
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8810170208 081007
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Connonwealth Edison Company
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OCT 7
19B8
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
this letter and the enclosure will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
(;,'.;!::Al. SICMED D( llVBERT J. f.UJ.ER
Hubert J. Miller, Director
Division of Reactor Safety
Enclosure:
Inspection Reports
No. 50-254/88021 DRS ;
No. 50-265/88021 DRS
cc w/enclorure:
H. Bliss,ib clear
Licensing Manager
R. L. Bax, Plant Manager
DCD/DCD (R!DS)
Licensing Fee Management Branch
Resident Inspector, R!l!
Richard Hubbard
J. W. McCaffrey, Chief, Public
utilities Division
A. Datta, RES
C. McCracken, NRR
A. Krasopoulos, RI
G. Wiseran, RI!
A. Singh, RIV
C. Ramsey, RV
R. Hodor, DNL
K. Sullivan, BNL
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