ML17331A464

Discusses Depth of Water Coverage Over Irradiated Fuel During Mode 6 Operation.Based on Wording of ,Util Does Not Meet Condition of at Least 23 Ft of Water.Revisions to Tech Specs 3.4.9.10 Will Be Formally Submitted

ML17331A464
Person / Time
Site:	Cook
Issue date:	09/26/1980
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8010020497
Download: ML17331A464 (5)

Text

e..~W REGULA ORY INFORMATION DISTR I BUT IOIR SYSTE. I (R IDS)

I ACCESSION NBR: 8010020497

',"-.DOC ~ DATE: 80/09/26 NOTARIZED:

NO FACI Donald C.

Cook Nuclear Power P

1 ant R Unit 1E Indiana 8

0-316 onald C.

Cook Nuclear Power Planti Unit 2r Indiana 8

AUTHOR AFFILIATION UNTERER.ST Indiana 8 'Iichigan Electric Co.

EC IP. NATE RECIPIKNT AFFILIATION DENTorIRH ~ R.

Office of Nuclear Reactor Regulationi Director DOCKET rr 05000315 05000316

SUBJECT:

Discusses deoth of water coverage over irradiated fuel during Mode 6 operation.Based on wording of 800815 ltrrutil does not meet condition of at 1'east 23 ft of water. Revisions to Tech Soec 3.4.9.10 will be formally submitted, OISTRISL'TIOM COOE:

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INDIANA L MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 AEP:NRC:0463 September 26, 1980 Donald C.

Cook Nuclear Plant Unit Nos.

1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 Depth of Water Coverage Over Irradiated Fuel During Mode 6'perations Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Denton:

By letter dated August 15, 1980, all Westinghouse Pressurized Water Reactor Licensees were-notified by your office that Westinghouse Standard Technical Specifications and Bases had been modified to require at least 23 feet of water over the top of the reactor pressure vessel flange during movement of fuel assemblies or control rods.

Licensees were requested to advise what measures, if any, were required to meet this modified requirement and to provide assurance that exposure of fuel assem-blies and control rods cannot occur during transfer while the plant is in Mode 6.

Please be advised that Units No.

1 and 2 of the Donald C.

Cook Nuclear Plant are in compliance with the above requirements during the performance of actual refueling operations;

however, based on the precise wording of your letter, we do not meet the condition of "at least 23 feet of water" while performing the initial unlatching of control rods, nor when performing the final latching, which is followed by a drag test on reassembled control rods.

For reasons of operating efficiency and enhanced personnel

safety, the unlatching and latching steps are carried out from a platform whose elevation only allows approximately 16 feet of water cover over the reactor pr essure vessel flange; the initial filling and the final draining of the refueling pit are interrupted for these operations.

The control rod drag test involves some movement (up to about 36 inches) of the control rods; a smaller movement occurs in connection with latching and unlatching.

During unlatching, latching and drag testing, which amount to a total time of approxiIIIately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, there is still a minimum of 23 feet of,water over the fuel.

no/

5

,ji 80 X 0 080 gq7

It should be noted that during these operations, the upper in-ternals are in place and that,"transfer" of fuel assemblies or control rods does not occur.

Therefore we meet'he intent of your letter "to prevent inadvertent exposure of a fuel assembly during transfer."

For completeness we will formally submit Technical Specification

• revisions to 3.4.9.10 commensurate with our operating practice in the near future.

Very truly yours, cc:

attached R.

S.

Hunter Vice President

CC'. Charnoff R.

C. Callen D. V. Shaller Bridgman John E. Dolan R.

W. Jurgensen NRC Region III Resident Inspector at Cook Plant Bridgman

I I

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