ML20038B008
| ML20038B008 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/13/1981 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| REF-SSINS-6820 1-223, IEB-79-02, IEB-79-14, IEB-79-2, NUDOCS 8111240592 | |
| Download: ML20038B008 (3) | |
Text
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s Docket No. 50-346 e
TOLEDO License No. NPF-3 keen EDISON Serial No. 1-223 Acano P CmusE vu p,-
November 13, 1981 Z3,
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United States Nuclear Regulatory Commission 3
Region III 9j NOV 2 31981*,
799 Roosevelt Road u s Glen Ellyn, Illinois 60137
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Dear Mr. Keppler:
4 V,i This letter is to provide a current status and to outline future activity in the areas of piping supports and anchor modifications resulting from IE Bulletins 79-02 and 79-14 at the Davis-Besse Nuclear Power Station Unit No. 1.
Currently, all piping supports at the facility meet or exceed the criteria for interim system operability as defined by Supplement 1 of Revision 1 to IE Bulletin 79-02.
The completion date previnusly identified for the support modifications outside of containment was December 31, 1981. The construction activity has been, and continues to be, adversely affected by labor productivity problems. These problems were not anticipated in the development of the construction schedule.
A large increase of construction manpower would be required to achieve completion of the work in December. This buildup of manpower would detract from the other plant modification work and refueling outage activities.
The manpower expansion would also be undesirable from a security and safety aspect.
Toledo Edison has reviewed the situation and is taking step.c to improve productivity while allocating resources so as not to adversely impact other important plant. modifications.
Our review has resulted in an alternate approach to complete the IE Bulletin 79-02 and 79-14 modification work.
The revised approach includes:
1.
Continuation of the Bulletin 79-02/79-14 associated modifications outside the containment vessel. Work during this continuation will generally be directed toward gf/
completion of safety systems and important operrting systems 3
first.
This prioritization is further described below.
I I THE TOLEDO EDISON CL,MPANY ED! SON PLAZA 300 MADISCN AVENUE TOLEDO. CH:0 43652 8111240592 811113 PDR ADOCK 05000346 NOV 18 1981 g
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Serial No. 1-223 November 13, 1981 2.
The activity outside containment vessel will be redirected during the 1982 refueling outage to assure completion of all support modifications inside the containment vessel during the outage.
3.
After the 1982 refueling outage the remaining support modifications will be completed under the general system-
. group prioritization until all have been completed. We now expect to complete the work by the end of'1982.
4.
Quarterly, status reports will be provided to advise you of the progress.
To prioritize for the completion of this effort, the remaining modifications have been grouped by their importance in accident mitigation and plant operations. Table 1 identifies, by system, three levels of importance, Groups I, II and III. Group I is considered the most important.
In addition, other factors relating to constructability, task complexitity and operational restraints have been compiled. The greatest priority will be given to the support modifications of system importance (Group I). However, this will not be the sole criteria. The factors of constructability, complexitity and operational restraints must be considered. This could identify alternate sequences for particular supports to maintain overall program-efficiency.
Selection of each successive support modification will be made by the Nuclear Construction Superintendent. He will be responsible to take into account plant operational conditions, system grcup priorities and other work force interference.
A current status of remaining modifications by system is provided in Table 1.
As stated this status will be updated regularly to identify progress. We will be glad to discuss any aspect of our program with you.
Very truly yours, e
j RPC:TJM: lab cc: DB-1 NRC Retident Inspector Docket No. 50-346 License No. NPF-3 Serial No. 1-223 November 13, 1981 TABLE 1: STATUS AND PRIORITIZATION FOR SUPPORT MODIFICATIONS OUTSIDE THE CONTAINMENT VESSEL (As of October 25, 1981)
Modifications Remaining Group I - Highest Priority Emergency Core Cooling 20 Auxiliary Feedwater 8
Service Water 20 Diesel Generator Exhaust 3
Component Cooling Water 21 Hydrogen Dilution 0
Group II Fire Protection 3
Spent Fuel Cooling 4
Main Feedwater 6
Group III Demineralized Water 2
Auxiliary Steam 2
Makeup and Purification 1
Reactor Coolant Drains 1
Auxiliary Building Drains 27 Circulating Water 1
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