ML20117A277

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Advises That Mods in Response to Generic Ltr 84-23, Reactor Vessel Water Level Instrumentation in BWRs & NUREG-0737, Item II.F.2 Will Not Be Completed Until After First Refueling Outage Based on Reasons Listed
ML20117A277
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 05/03/1985
From: George Alexander
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 0070K, 70K, GL-84-23, NUDOCS 8505080167
Download: ML20117A277 (2)


Text

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J' / h Commonwealth Edison

,[ ) One First National Plaza. Chicago. liknois

\ ] Address Riply to: Post Office Box 767 (f Chicago lilinois 60690 -

2 May 3, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station Units 1 and 2 Generic Letter 84-23 and NUREG 0737 Item II.F.2 NRC Dockets 50-373/374 References (a): December 4, 1984 G. L. Alexander letter to H. R. Denton (b): March 26, 1985 A. Schwencer letter to D. L. Farrar

Dear Mr. Denton:

Reference (a) contained our initial response to Generic Letter 84-23 " Reactor Vessel Water Level Instrumentation in BWRs".

In that response we stated that we thought it might be possible to complete required modifications on both units by the end of their respective first refueling outage. During a March 1985 telephone

. conference between Dr. Bournia of the NRC and Jim Marshall of CECO, we were requested to firm up our commitments. At that time we commited to the following:

Unit 1 - Implement changes by the end of the second refueling Unit 2 - Implement changes by the end of the first refueling mbd

S '5 The Unit 1 completion date has slipped because:

1R 1) revision of our initial design from a guard pipe cooling UJ system to using existing penetrations has proven to be more rgg difficult than origially expected.

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2) satisfying the original General Electric Design Criteria has caused moving both the narrow range sensing lines an o the reference-legs.

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3) the existing penetrations are not ideally suited to camp y with separation criteria thus causing more design work.
4) a significant portion of the guard pipe design also p mains uncompleted.

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H. R. Denton May 3, 1985 ,

Basedaan the current status it is not possible to complete engineering designs, installation drawings, complete design reviews

-and purchase the necessary code materials by the September Unit 1 Refueling Outage.

Reference (b) included a review of our original-submittal which was docketed, but made no comment on the subsequent telephone conference.

The purpose of this letter is to officially docket the most-recent commitment and to request that the NRC amend its review letter to incorporate these dates.

Respectfully, Greg Mexan er Nuclear Licensing Administrator bs occ: A. Bournia - NRR Resident Inspector - LSCS 0070K f

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