ML20081C790
| ML20081C790 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/29/1984 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| NJK-84-79, NUDOCS 8403150019 | |
| Download: ML20081C790 (3) | |
Text
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Commonwealth Edison Q ') 22710 206 Av:nus North C
Outd Citi2s Nucl2ar Powsr Station Cordova, Illinois 61242 Telephone 309/654-2241 l
F NJK-84-79 March 8, 1984 Mr. Edson G. Case, Deputy Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Case:
Enclosed please find a listing of those changes, tests, and experi-ments completed during the month of February 1984, for Quad-Cities Station Units 1 and 2, DPR-29 and DPR-30. A summary of the safety evaluation is being reported in compliance with 10 CFR'50.59.
Thirty-nine copies are provided for your use.
Very truly yours, C0;Df0NWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION l/
N. J. Kalivianakis Station Superintendent bb Enclosure cc:
B. Rybak I[
'Il 8403150019 840229 PDR ADOCK 05000254 R
PDR.
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Safety Evaluation On-Site Review 84-10 Summary Block Wall #63 was repaired in accordance with M-4-2-84-4 which followed Bechtel's Specification for masonry walls.
The wall was initially poured on February 8,1984.
Some miner repairs were perforned on February 13, 1984.
The grout batch which was used on February 13 will not be compression tested until February 20.
The unit is due to startup on February 16, 1984. This safety related wall is adjacent to the M0 2-1201-5 valve and Penetration X-14.
Conclusion i
Based on the attached safety evaluation, plant safety is not
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jeopardized nor does an unreviewed safety question exist in regards to putting Unit Two in operation prior to the grout test sample results.
1)
The probability of an occurrence or the consequences of an accident or mal function of equipment important to safety as previously evaluated in the FSAR is not increased.
The wall has been inspected and found to be acceptable.
No flaws or discrepancies have been identified which could cause the structure to fall.
Installation was performed I AW Peterson Contractor's approved procedure per Bechtel's Speci fication 13524-088-CP(ll)Q.
All the grout used was from the same tot Number, and the first batch has been successfully tested. The second batch of grout has been partially tested and found acceptable.
- 2) The possibility for an accident er malfunction of a different type than any previously evaluated in the FSAR is not created.
This wall (#63) is adjacent to valve M0 2-1201-5, Line 2-1202-6",
and Penetration X-14.
The likelihood of a seismic event is highly re mo te. The fact that the test results are not completed does not indicate the wall will not perform as designed.
Should the 6 inch line or valve become damaged, the inboard Reactor Water Cleanup System isolation valve will provide the necessary isolation function.
Therefore, Reactor safety is unaf fected. The Containment 'enet rat ion is not likely to be affected by the failure of this wall, due to the fact it is embedded in concrete and a wipe restraint is in place which acts as a shield.
Containnent integrity remains unaf fected.
- 3) The margin of safety, as defined in the basis for any Technical Specification is not reduced.
The Reactor Water Cleanup -5 valve will perform as designed.
Containment integrity will remain intact.
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