ML17275B034

Final Deficiency Rept Re Containment Mod QA Program Breakdown,Initially Reported on 801215.Evaluation Concludes That Contract 213A QA Program Breakdown Is Not Reportable Condition

ML17275B034
Person / Time
Site:	Columbia
Issue date:	05/15/1981
From:	Matlock R WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, G2-81-98, GO2-81-98, NUDOCS 8105260389
Download: ML17275B034 (6)

Text

REGULATO i

INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:8105260389 DOC ~ DATE: 81/05/15 NOTARIZED:

NO DOCKET FACIL':50"397 NPPSS Nuclear Projects Unit 2i l'washington Public Powe 05000397 AUTH~ NAME AUTHOR AFFILIATION MATLOCKg R G'<as hi ng ton Pub 1 i c Power. Supp 1 y System RECIP ~ NAMEl RECIPIENT AFFILIATION, ENGELKENiR+H, Region 5i San Francisco'ffice of the Director

SUBJECT:

Final deficiency rept re containment mod QA program breakdowniinitially reported on 801215 'valuation concludes" that Contract 213A QA program breakdown is not reportable condition.

DISTRIBUTION CODE:

8019S COPIES RECEIVED:LTR ENCL ~

SIZE:

TITLE'. Construction Deficiency Repor t

( 10CFR50

~ 55E)

NOTES:PR,:

2 copies of all material F 1 cy'.BNR<<LRG PM(L-,RIB) 05000397 RECIPIENT I D C 0 DE/N At 1 E'-

ACTION:

A/D LICENSNG 04 RUSHBROOKgM ~

06 INTERNAL: ASLBP/JHARD EDO L STAFF 19 HYD/GEO BR 22 IE/EES MPA 20 OELD 21 QA BR 14 STANDRDS DEV 21 COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

RECIPIENT ID CODE/NAME L'IC BR 42 BC 05 AULUCKgR~

07 D/DIR HUM FAC 15 EQUIP QUAL BR11 I8E 09 LIC QUAL BR 12 NRC PDR 02 PROC/TST REV 13 G FIL 01

.COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 EXTERNAL; ACRS NSIC 16 16 16 08 1

1 LPDR 03 ggy 28 >981 TOTAL NUMBER OF COPIES REQUIRED:

LTTR ~

ENCL

ll I"

9

~

W

Washington Public P er Supply System P.O. Box 968 3000 George Washington Way ichland, Washington 99352 (509) 372-5000 Docket No. 50-39 Mr. R.

H. Engelken, Di c

May 15, 1981 Office of Inspection a d'nf rce ent G02-81-98 Nuclear Regulatory Co issio Region V

Suite 202, Walnut Creek Pl a

1990 North California Blvd.

Walnut Creek, California 9459

Subject:

WPPSS NUCLEA PROJECT NO.

2 g

POTENTIALLY EPORTABLE DEFICIENCY - 10CFR50.55(e)

CONTAINM MODIFICATION QA PROGRAM BREAKDOWN

Reference:

Letter G02-80-299 dated December 15, 1980 RG Matlock to RH Engelken (2)

Letter G02-81-53, dated March 10,

1981, RG Matlock to RH Engelken Reference (1) provided notification and a preliminary report regarding the Contract 213A (primary containment modification)

QA Program breakdown, which was being evaluated as a potentially reportable deficiency in accordance with 10CFR50.55(e).

Reference (2) provided a status report on the results of the evaluation, and reported that no significant design or construction deficiencies which could have adversely affected the safety of operation of the plant had yet been identified.

The preliminary report transmitted by Reference (1) described the documentation review and resolution process involving the Contractor and Architect-Engineer.

Although this evaluation effort is not completed, it has progressed to the point where final conclusions can be drawn regarding the reportability of this item as a 10CFR50.55(e) condition.

The Supply System evaluation has concluded that the Contract 213A QA Program breakdown, as described in References (1) and (2), is not a reportable condition, and this letter constitutes our final re-port on this matter.

The basis for this conclusion is as follows:

In general, the Contract 213A.QA Program breakdown involves documen-tation deficiencies rather than physical deficiencies.

The effect of these deficiencies is an initial lack of.verification that materials and welding are acceptable.

Through additional research of available documentation, resort to alternative means of verifying adequacy, and reinspection, much of the work for which these documentation deficien-cies existed has been judged acceptable.

While some minor physical deficiencies have been identified, there is no evidence that materials or welding are incapable of meeting their design function or complying with plant safety requirements.

8105 86038 g

I r

S

RH Engelken Page 2

b.

C.

The apparent gA Program breakdown identi ied in Reference (1) can better be characterized as a failure to perform quality verifi-cation in a timely manner.

The Con ractor's OA Program was suc-cessful in ultimately identifyino the deficiencies, but a more timely quality verification program would have reduced the scope

- of the problem.

In some cases, ASHE Cole material traceability, welder identifi-

cation, and documentation reouirements for containment pressure boundary items had been unnecessarily applied to non-ASHE struc-tures (downcomer bracing system) and to attachments to contain-ment pressure boundary materials.

Consequently, many of the ap-parent documentation deficiencies initially identified have been determined to be acceptable.

Although the consequences of the Contract 213A gA program breakdown have been determined to be not reportable under the terms of 10CFR50.55(e),

cor-rective action has been taken by the Contractor and the Supply System.

The Contractor's guality Assurance and guality Control programs have been up-

graded, and condi.ions which led to the loss o

process control identified i n Reference (1) have been eliminated.

In addition, the Supply System has installed an Architect-Engineer Task Force made up of engineering and quality assurance personnel, working directly with the contractor

.o participate in the identification and resolution of engine ring and ouality-related problems.

With these steps, we consider the condi-'ions which led to the loss of process control identi ied in Peference (1) to have been corrected.

Very fluly yours, R.

G. Hatlock Program Director

'lJNP-2 EAF:taj CC:

V. -Stello -

NRC AD Toth -

NRC Resident Inspector RC Root -

BSR Site TA Hangelsdorf - Bechtel Site RE Snaith - BSR NY H. Izaak - h'PPSS',

NY l!S Chin - BPA HNP-2 Files

c

~

~

t

~

~@7