ML18031A265

Interim Deficiency Rept Re Pipe Support Design Drawings, Released for Fabrication & Installation,Which Lacked Revised Piping Sys Stress Values Developed Subsequent to Initial Stress Calculations.Final Rept to Be Submitted by 800301

ML18031A265
Person / Time
Site:	Susquehanna
Issue date:	09/05/1979
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
PLA-391, NUDOCS 7909170188
Download: ML18031A265 (4)

Text

REGULATO Y

INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:7909170188 DOC ~ DATE! 79/09/05-NOTARIZED!

NO DOCKET FACILiS ~

usquehanna Steam Electric Stationr Unit 1~ Pennsylva 05000387 50<<388 S squehanna Ste~m Electr ic Stationr Unit 2i Pennsylva 05000388 AU

~NAM AUTHOR AI FILIATION CUR ISsN ~ siI ~

Pennsylvania Power 8 Light Co, RECIP ~ NAME RECIPIENT AFF ILIATIOIV GR IKRiB,H ~

Region 1 g Phi

'I adel phiai Office of the Director ID CODE/NAME LTT 15 BC LmR ~

1 21 AO 4~g 1

PM ~/8/Eg 20 LA z> ufg WH 1

ACTION!

SUBJECT:

Interim deficiency r ept re pipe. support design drawings released for fabrication 8 installation which lacked revised piping sys stress values developed subsequent to initial stress calculations,Final rept to be submitted by 800301s DISTRIBUTION CODE:

BOISS COPIES RECEIVEDilTR C ENCl +

SIZEi TITLKi Construction Deficiency Report (10CFR50

~ 55E)

NOTES:r<~>

~ ~ y~ a=as

.=.CC~ ~~~m..r.e ~y ~".~~P.~e>W<

REC IP IENT COP IKS REC IP IEiVT COPIES ID CODE/NAME I.TTR EN L

R ENCL" INTE'RNAL! 0

~II I8E 08 MPA 10 QAB 12 JORDANiK/IK 16 AD 'FOR ENGR 17 AD REAC SFTY 23 OELD D IRKCTOR DSE ILC SYS BR MECH ENG BR STRUCT ENG BR

,EXTERNAL! 03 LPDR 24 ACRS 1

2 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

16 1

02 NRC PDR 07 EDO 8

STAFF 09 DKPY DIR DVM 11 STANDRDS DEV 13F IKLD COOR/ IE 17 AD PLANT SYS 22 DIR DPM AD/S ITK TECH GEOSCIENCES BH MATL EiVG BR S

HANAUKR 04 NSIC 1

1 1

1 1

1 1

1 1

1 1

TOTAL NUMBER OF COP IKS RKQUIRKO! LTTR 46 ENCL

ppal.

TWO NORTH NINTH STREET.

ALLENTOWN, PA.

18'101 PHONE: (215) 821-5151 NORMAN W. CURTIS Vice President.Engineenng IL Constructrcn 821-5381 September 5, 1979 Mr. Boyce-H. Grier Director, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 SUSQUEllANNA STEAM ELECTRIC STATION INTERIM REPORT OF A DEFICIENCY ZN PIPE SUPPORT DESIGN DRAWINGS RELEASED FOR FABRICATION AND INSTALLATION ERs 100450/100508 FILE 840-4 PLA-391

Dear Mr. Gr'ier:

'This serves to confirm information provided to R. Gall'o, NRC, Reactor Inspector by A. R. Sabol,

PPSL, on August 2,'1979 regarding the subject deficiency which is deemed reportable under 10 CFR 50.55(e).

The deficiency involves discrepancies between the Bechtel Plant Design Group's finalized stress analyses calculations'nd the loads which wer'e used in the design of pipe support detail drawings which weie fabricated and.released for installation during the construction of the plant.

The released pipe support detail drawings did not have factored into them revised piping-systeIIL stress values which had been developed, subsequent to the initial piping system stress calculations.

h All of the safety implications are not known at this timey however, our best estimate is that there will be approximately 1000 pipe supports which may require design changes.

Had the deficiencies gone undetected, it is. anticipated that some supports could have been overstressed beyond allowable design limits by an order of 100 percent or greater.

The condition was first detected by Bechtel engineering personnel during preparations for piping systems stress walkdowns in the first quarter of 1979.

At that timer a review performed on the basis of a random sample indicated that the problem was not generic or widespread.

The problem appeared to have been confined to calculations which had been performed prior to mid-1976 and subse-,

quently revised.

>'~, o PENNS'YLYANIA POWER 8

LIGHT COMPANYf90

Mr. Boyce H. Grier September 5, 1979 Subsequently, in preparation for turnover of the feedwater system to startup, a relatively large number of pipe support details,.approximately 40 out of 276, which were found to be discrepant.

Therefore, in order to facilitate as orderly and complete as possible turnover of systems for startup, a

thorough verification program has been instituted.

The verification program, which instituted following discovery of the. condition, will cover all force,

'oment calculations and their related pipe support details.

On, July 25, 1979, Bechtel QA identified the condition in its MCAR-1-36 requesting that Bechtel engineering evaluate the condition for reportability.

Based upon Bechtel engineering's conclusion that the condition is reportable, a final report to MCAR-1-36 will be submitted to PPaL by December 28, 1979.

Following, PPGL will submit its final report of said deficiency to the

~

Commission by March 1, 1980.

Very truly yours, N. W. Curtis Vice President-Engineering 6 Construction ARS:mcb.

cc:. Mr. Robert M. Gallo U. S. Nuclear Regulatory Commission

~ P. 0 Box 52 Shickshinny, Pennsylvania 18655 Mr. Victor Stello (15)

Director&ffice of Inspection I Enforcement U. S. Nuclear Regulatory Commission-Washington, D.C.

20555 Mr. G., McDonald Office of Management Information a Program Control U. S. Nuclear Regulatory Commission Washington, D.C.

20555

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