IR 05000423/1985022

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-423/85-22

ML20138G272
Person / Time
Site:	Millstone
Issue date:	10/18/1985
From:	Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Opeka J NORTHEAST NUCLEAR ENERGY CO.
References
NUDOCS 8510250443
Download: ML20138G272 (2)

Text

. o OCT 1 0 IS35 Docket No. 50-423 License No. CPPR-113 Northeast Nuclear Energy Company ATTN: Mr. J. F. Opeka Senior Vice President - Nuclear Engineering and Operations Group P. O. Box 270 Partford, Connecticut 06101 Gentlemen:

Subject: Inspection No. 50-423/85-22 This refers to your letter dated September 12, 1985, in response to our letter dated August 13, 198 Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed progra Your cooperation with us is appreciate

Sincerely, c6 .Ath ts

[ Ste/ t D. Ebneter, Director oy Division of Reactor Safety cc:

. V. Papadopoli, Construction Quality Assurance Supervisor

. E. R. Foster, Director of Generation Construction

, E. J. Mroczka, Vice President, Nuclear Operations

. D. O. Nordquist, Manager of Quality Assurance

. R. T. Laudenat, Manager, Generation Facilities Licensing W. D. Romberg, Station Superintendent Public Document Room (POR)

Local Public Document Room (LPOR)

Nuclear Safety Information Center (NSIC)

NRC Senior Resident Inspector

. State of Connecticut h0yj f G

OFFICIAL RECORD COPY RL MILL 3 85-22 - 0001. /09/85 50$

__ - _____ _ __- ___ ________________- __ __- ___- ___ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

'

,

l l Northeast Utilities 2 i

'

bec:

, Region I Docket Room (with concurrences)

Management Assistant, DRMA

. DRP Section Chief

, G. Walton, SRI, BV-2

.T. Shedlosky, SRI, Millstone 1&2

, B. Doolittle, LPM, NRR l

y

!

l l

l

{

'

,

(

l RI:0RS \ RI:0RS RI:0RS

Kerch/djh G V Wiggins Durr 10/p/85 10/N85

10/7/85 0FFICIAL RECORD COPY RL MILL 3 85-22 - 0001. /09/85 l

l

,

..,

O Generst Offices * Selden Street. Berkn. Connecticut

[.oi L < T ; CC'C',*0,;g;;

.

H'ARTFORD. CONNECTICUT 061410270 t2m ses5000 September 12,1985 Docket No. 50-423

, _Bil707 M.. Steward D. Ebneter, Director Duision of Reactor Safety U.S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406 i

References: (1)

5. D. Ebneter to 3. F. Opeka, IE Inspection Report No. 50-423/85-22, dated August 13,198 (2) 3. F. Opeka to T. E. Murley, F0690A, dated June 28,198 Dect Mr. Ebneter:

Millstone Nuc! car Power Station, Unit No. 3 IE Inspection Rep $rt No. 50-423/85-22 As a 14,1985, June result of an inspection conducted by your office from20, May1985 through

/

violations were identified and transmitted to us in Reference (1).at Mi VIOLATION IGCTRSO, Appendix B Criterion IX requires nondestructive examination to be controlled and accomplished in accordance with applicable codes, sta.3dards, specifications, criteria and other special requirement Site fabrication and engineering procedures 2280.000-968 and 2280.000-149 and radiographic procedures QAD-9.41ML, Revision A, change 1 and RT-405, Code, Revision 1971 11, invoke Section III of the ASME Boller and Pressure Vessel edition with addenda through

'

1973, for the neceptan7e/ rejection criteria associated with Class 2 component Article ND/NC 5320 of Section ill of the Code requires that welds with indications of zones of incomplete fusion or with elongated indications greater than 1/4 inch for material thicknesses up to 3/4 inch be rejected and Article NB5310 provides the disposition for welds so rejecte Contrary to the above, an NRC review of site radiographs disclosed that field weld RSS-9-FW2 in an ASME Class 2 pipe contained a zone of

) , incomplete fusion which was not previously identified and dispositioned by

.

'

LL.l l ~

,'

6 \

, . .

-2-site personnel and that ASME Class 2 shop weld RSS-7-3-4-2-SWB contained an elongated indication exceeding Code acceptable limits which had not been identified and dispositioned by the vendo This is a Severity LevelIV Violation. (Supplement II)

Response Extent of Condition Raolographic film and weld quality problems had previously been identified by NNECO with the subject vendor, TUBECO. A potential significant deficiency in accordance with 10CFR50.55(e) has been submitted and the magnitude of the nonconforming conditions have been identified in a recent update (Reference (2)).

Field weld radiographic film and associated documentation problems have been previously identified during the NRC Construction Appraisal Team Audit, NUSCO quality assurance audits and Stone & Webster Engineering quality assurance audits. A small percentage of the field weld radiographic film audited have had ASME Code rejectable indication Cause '

The cause of the violation is attributable to the TUBECO and Stone &

Webster Engineering Field Quality Control radiographic film int:.rpreters'

failure to follow procedures and properly interpret radio 9eaph film indication Corrective and Preventative Actions A series of preventative actions has been taken both prior to and after the NRC Inspection to address the subject violation. These conditions are summarized below:

o Nonconformance and Disposition Reports have been initiated to repair the subject weldments in accordance with ASME Code requirement o

' performe A 100% review of TUBECO ASME Code weld radiographic film was o

.

NUSCO Quality Ass'urance personnel have performed additional audits of radiographic fil o ,

Stone & Webster Engineering Quality Assurance personnel have performed additional audits of field weld radiographic fil ~

o All Stone & Webster Engineering Field Quality Control radiographic film interpreters have been reinstructed to evaluate and document any and all conditions noted on film, i

l

_

.

'

, VIOLATION 10CFR50, Appendix B Criterion V requires that activities affecting quality shall be accomplished using appropriate procedure Site Quality Assurance and Quality Control manual, ASME Section III Div.1 Section 9 Rev. L. (Fabrication and Installation Control)

paragraph 2.2.4A. requires that items fabricated by other than site organizations shall be identified on the controlled drawings by their unique identification number Contrary to the above, all items shown on control drawing 2179 C.I. MSS-32 Rev. 2, dated August 30, 1984, were not uniquely identified in that the procedure depicted two shop welds on a pipe spool which were identified as TUBECO welds SWIC and SWID when, in fact, these welds had been removed and replaced by Southwest Fabrication shop welds SW-2 and SW- This is a Severity Level V Violation. (Supplement II)

Response Extent of Condition The condition identified is isolated to pipe spools that were originally fabricated by TUBECO and subsequently modified by Southwest Fabricating and Welding Compan A total of five weldments were identified which isometric drawings. required revision on Stone &' Webster Engineering

_Cause Several pipe spools originally fabricated by TUBECO were subsequently modified by Southwest Fabricating and Welding Company. Southwest

- Fabricating and Welding Company weld identification numbers were not identified on the appropriate isometric drawings. The problem had been identified previously, but appropriate corrective drawing change notices were not initiated. Revisions to drawings were planned to be made during final documentation revie Corrective Actions Drawing revision notices have been initiated to implement appropriate drawing changes. The condition noted was isolated to three pipe spool ,

.

@

e e

. . . . *

-4-We consider this to be our final report closing out both violations. We trust that the above information satisfactorily responds to your concern Very truly yours, NORTHEAST NUCLEAR ENERGY COMP'. ,

.

3. FSOpeka '

Senior Vice President o a W By: W. F. Fee

Executive Vice President i

.

L

.

!

,

a

,