ML19275A234

Requests Amends to CPPR-99 & CPPR-100 to Revise Completion Dates to 810630 & 820331,respectively.Revised Dates Reflect Conservative Const Schedule Allowing Margin for Potential Future Delays

ML19275A234
Person / Time
Site:	LaSalle
Issue date:	09/24/1979
From:	Peoples D COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML19275A235	List: ML19275A234 ML19275A240
References
NUDOCS 7910030369
Download: ML19275A234 (4)

Text

Commonwealth Edison One First National Plaza. Chicago. Illmots .,

p Address Reply to: Post Omce Box 767 J f Chicago, Illinois 60690 . j

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September 24, 1979 Mr. H. !. Denton, Director k

Office of *:uclear Reactor Regulation U.S. Nuclear T,egulatory Commission 4antin7 ton, D.C. 20555

Subject:

LaSalle County Station Units 1 and 2 Construction Permit Extension Request NRC Docket Mos. 50-37 3 and 50-374

.e:erences (a) : V. A. Moore letter to B. Lee, Jr. dated September 10, 1973 tt ansmitting Construction Permit Nos. CPPR-91 and CPPR-100 (b): R. S. Boyd letter to B. Lee, Jr. dated May 31, 1978 transmitting extension to Construction Permit Nos. CPPR-99 and CPPR-100 (c) : C. Reed letter to O. D. Parr dated February 2, 1979 Dect :t . Denton:

"Connonwealth Edison Company requests an amendment to the LaSalle County Station Construction Permits CPPR-99 and CPPi-100, as issued by Reference (a) and amended by Reference (b).

This request is made pursuant to the provisions of 10 CPR 50.55 (b) .

For the reasons delineated below, we request that the " latest com-pletion dates" be revised to June 30, 1981 and March 31, 1932 for Units 1 and 2 respectively. This amendment does not, in the judgenent of the applicant, involve a significant hazard con-sideration. The revised completion dates reflect a conservative construction schedule allowing some margin for potential future delays, as well as for the installation of additional lateral reinforcing braces between downconers and additional piping supports in the suppression pool volume required by the Mark II containment studies.

1. The construction schedule has been adversely affected by a labor strike and work stoppage from September 5, 1978 to September 22, 1978 3rr? 284 (3 weeks) by the Boilermaker's Union and -

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jurisdictional work stoppages totaling 6 days since June 1, 1978. j k

)b gelooso ni.

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NRC Docket Nos. 50-373/374 f4r. H. R. Denton: -

2- September 24, 1979 y

Moreover, the above work stoppages have resulted in signific ant skilled manpower losses, primarily in the mechanical and electrical trades, for extended periods following the work stoppage. The consequences of work stoppages of this type, both f direct and indirect, were discussed in detail in Reference (c).

2. The physical installation of downcomer bracing and T-quencher devices in the suppression pool will have a material effect on the construction schedule. It is important te note that these modifications are being made to comply with the criteria defined by the NPC in NURE3-0407.

3. Accommodation of additional NRC criteria in the area of fire protection and containment isolation testing, as well as expanded preoperational testing, contribute both to the delay of previously defined dec1gn analysis and the extension of construction activities.

The attached bar graph schedule (Figure 1) indicates the interrelation of the various schedule f actors which have contributed to the schedule extension request for Unit 1. Efforts to minimize Unit 1 delays continue to resitlt in reallocation of Unit 2 manpower to Unit 1 work, thus significantly increasing the effect of manpower shortages on the Unit 2 schedule.

It has been stated in the body of this request, and should again be emphasized, that the design evaluation and modifications discussed do not involve a significant hazard consideration. There are no major unreviewed safety questions involved because those issues e.e being reviewed as a part of the LaSalle FSAR. With regard to the containment design evaluation, the LaSalle County design con-forms to the criteria defined in NUREG-0487 with minor exceptions that have been reviewed by the NRC Staff and for which a basis for resolution was presented by the NRC Staff to a meeting of the Advisory Committee on Reactor Safeguards (ACRS) held on September 13, 1979.

. Also attached is a proposed " Finding of No Significant

. Impact" (PONSI) prepared by Commonwealth Edison to address the

[negativeenvironmentalimpactofthisconstructionpermit extension

, request.

s lt;2 285

NRC Docket Nos. 50-373/374

r . H. .. Centons September 24, 1979 Moreover, the above work stoppages have resulted in significant skilled nanpower losses, primarily in the cochanical and electrical trades, for extended periods following the work stoppage. The consequences of work stoppages of this type, both direct and indirect, were discussed in detail in reference (c).

2. The physical installation of downcomer bracinq and T-quencher devices in the suppression pool will have a material effect on the construction schedule. It is important to note that these modifications are beinc nade to comply with the criteria defined by the Nrc in NCRES-0407.

3. Accommodation of additicLal NRC criteria in the area of fire protection and containment isolation testing, as well as expanded preoperational testing, contribute both to the delay of previously defined design analysis and the extension of construction activities.

The attached bar graph tchedule (Piqure 1) indicates the interrelation of the various schedule factors which have contributed to the schedule extension request for Unit 1. Efforts to minimize

, nit 1 delays contir.ue to result in reallocation of Unit 2 manpower to nnit 1 work, thus significantly increasing the effect of manpower shortages on the Unit 2 schedule.

It has been stated in the body of this request, and should age.in be emphasized, that the design evaluation and modifications ciccacce' do not involve a significant hazard consideration. There are no r.cjor unreviewed safety questions involved because these issues are being reviewed as a part of the LaSalle PSAR. With regard to the containment design evaluation, the LaSalle County design con-f or ar, to the criteria defined in NUREG-0487 with minor exceptions thct have been reviewed by the NRC Staff and for which a basis for resolution was presented by the NRC Staff to a necting of the Advisory Comnittee on Reactor Safeguards (ACRS) held on Septenber 13, 1979.

Also attached is a proposed " Finding of No Significant Impact" ( PGiSI) prepared by Commonwealth Edison to address the negative environmental impact of this construction permit extension request.

3, ^ .?. 286

Existing Permit Revised Permit -

Latest Completion Date Latest Completion Date March 31, 1979 June 30, 1980

1. Strikes - Sept., 1978 to Sept., 1979

2. Containment Modifica-tions & Design Analysis

3. NRC Criteria A

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N PJ C0 5 10 15 20

~a Unit #1 Schedule Delay (Months)

Figure 1