ML20083D668
| ML20083D668 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/21/1983 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8312280191 | |
| Download: ML20083D668 (3) | |
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101 SHIELDS L. DALTROFF stsc'in'ic rnNS som December 21, 1983 Docket Nos. 50-277 50-278 Mr. Darrell G. Eisenhut, Director Division of Licensing Of fice of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Peach Bottom Atomic Power Station NUREG-0612 - Control of Heavy Loads
Dear Mr. Eisenhut:
The purpose of this letter is to update our progress on NUREG-0612, ' Control of Heavy Loads at Nuclear Power Plants'.
I In your letter of December 22, 1980, you requested in part that " modifications you find are.necessary will commence as soon as possible...... so that all such changes...... will be completed within two years of submittal of Section 2.4 (Sections 2.1 through 2.3 for BWRs).....".
In our report of December 22, 1981, and the subsequent submittals of May 20, 1982, October 25, 1982 and August 10, 1983 (which were, in f act, responses to the NRC's Draf t Technical Evaluation Report of April 5,1982), we identified certain handling equipment on the refueling floor which would require modification in order to meet NUREG-0612 requirements, specifically the following:
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Mr. Darrell G. Eisenhut Page 2 ITEM REFERENCE Reactor Pressure Vessel October 25, 1982 Head Strongback Dryer / Separator Sling October 25, 1982 Service Platform Lifting October 25, 1982 Rings Hydraulic Tensioner October 25, 1982 Lif ting Attachment As part of the NUREG-0612 work effort, our Nuclcar Steam System Supplier, General Electric Company, developed site specific sof tware programs to evaluate the design and consequences of load drops for each of the special lif ting devices, such as the Reactor Pressure Vessel Head Strongback, Dryer / Separator Sling, Service Platform Lif ting Rings, and Hydraulic Tensioner Lif ting Attachment.
The development of this site specific sof tware delayed the completion of the analysis, which Philadelphia Electric Company submitted to the NRC as Attachments 5 and 6 in our letter of October 25, 1982 (S. L.
Daltroff to J. F. Stolz).
Design modifications for this work were completed by August 1983.
In addition, the significant ef fort involved by Philadelphia Electric Company, in responding to IE Eulletin 83-02 for the examination and repair of IGSCC sensitive pipe welds between July 4 and November 30, 1983, for Unit 2, has had a significant impact on the resources available to plan and implement these modifications.
Therefore, we will be unable to complete these modifications prior to December 22, 1983.
It should be noted that, although the necessary modifications will not be completed prior to December 22, 1983, the time limit specified in your letter of December 22, 1980, Philadelphia Electric Company will complete these modifications prior to the next use of the equipment (the next refueling outage) for each unit.
As part of its NUREG-0612 commitment, Philadelphia Electric Company has modified the Circulating Water Pump Structure Crane to include crane travel limit switches (with key overrides) to prevent the movement of heavy loads over the safety-related equipment in the circulating water pump structure.
The Circulating Water Pump Structure Crane is presently undergoing pre-operational testing.
P I
l Mr. Darrell G. Eisenhut Page 3 If you have any further questions, please do not hesitate to contact us.
Very truly yours, y: _.
, u$lw '
DWB vdw cc:
A. R. Blough, Site Inspector
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