ML19338E170

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Forwards Relevant Portions of IE Insp Repts 50-322/78-01, 50-322/78-17 & 50-322/79-12,in Response to
ML19338E170
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 09/23/1980
From: Bordenick B
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Hubbard R, Latham S
MHB TECHNICAL ASSOCIATES, TWOMEY, LATHAM & SHEA
References
NUDOCS 8009250003
Download: ML19338E170 (5)


See also: IR 05000322/1978001

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D. C. 20555

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September 23, 1980

Mr. Richard B. Hubbard

MHB Technical Associates

1723 Hamilton Avenue

Suite K

San Jose, California 95125

Stephen B. Latham, Esq.

Twomey, Latham & Schmitt

Attorneys at Law

P.O. Box 398

33 West Second Street

Riverhead, New York 11901

In the Matter of

Long Island Lighting Company

(Shoreham Nuclear Power Station, Unit 1)

Docket Nc,. 50-322

Gentlemen:

By letter dated July 31, 1980, addressed to Jerry Wilson, Mr. Hubbard asked

to be provided "with copies of all documents, and associated examples of QA

program breakdowns accumulated by the NRC Staff relevant to Shoreham that

fom the basis of the NRC concern expressed in IE Information Notice 80-26."

I am advised that two inspection reports apparently meet the specifications

of your above-quoted request.

These are identified below.

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1.

Courter & Co. QA Program Deficiencies. This was identified during

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Inspection 78-01 (1/10-13/78), shortly after Courter was given

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responsibility for welding QA/QC and prior to perfomance of any welding

under the Courter QA/QC progran.

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2.

Nuclear Energy Services (NES) Insp. Procedure 80A0467. This was identified

during Inspection 78-01 (1/10-13/78).

It was reviewed during Insp. 78-17,

(11/1-2/78) and was closed during Insp. 79-12 (8/13-16/79).

Copies of the relevant portions of the cbove-noted inspection reports are

enclosed.

If you need any further infomation, let me know.

Sincerely,

A

Bernard M. Bordenick

Counsel for NRC Staff

Enclosures

As Stated

cc:

See Page Two

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8009250@

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cc w/encls:

Elizabeth S. Bowers , Esq.

Dr. Oscar H. Paris

Mr. Frederick J. Shon

Edward M. Barrett, Esq.

Edward J. Walsh, Esq.

Ralph Shapiro, tsq.

Howard L. Blau, Esq.

W. Taylor Reveley III, Esq.

Jeffrey Cohen, Esq.

Irving Like, Esq.

Joel Blau, Esq.

Mr. J. P. Novarro

Energy Research Group, Inc.

Hon. Peter Cohalan

David H. Gilmartin, Esq.

Atomic Safety and Licensing Board Panel

Atomic Safety and Licensing Appeal Board

Docketing and Service Section

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Courter'a Company. procedures do not assure that weld filler

metal'will be rebated in accordance with

equirements of

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specification SH-258B after exposure to ambient environment

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for per,iods longer than those specified in specification SH-

1-258B.

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censee advised the inspector by telep

on January 18, !

1978, that EEDCR-F-llll3-W has been issued to provide additional'

guidance to C/C and other contractors relative to specification

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SH-1-238B weld electrode handling.

The E&DCR requires use of

portable, o,vens for certain electrodes, and prohibits return of

electrodes to the portable oven, once withdrawn by the welder

in the field (32_2/7_[-Ol-04).C

Courter & Company weld procedure WPS-NW-100 does not address

cooling rate restrictions for post-weld heat treatments as

defined in ASME Section III Paragraph NE-4623.5.

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The licensee stated that PWHT has not yet been performed under

this proced!. ire and the procedure will be corrected prior to

use, in that a separate PWHT has already been issued for

co=ent (322/78-01-05).

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Courter & Company QC inspection procedures (QAP-10-1 thru

QAP-10-3) do not contain acceptance criteria for assuring that

piping minimum wall dimensions have not been encroached upon

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during blending of weld contours with base metal.

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The licensee stated.that this matter will be returned to S&W

for review (322/78-01-07).r

L tc6HSEs Acrova ou Peevices lasrEcrica nowit* 4 ' (inse, 7E-c4

(Closed) Unresolved Item (322/78-01-04): J

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Weld filler metal re-

baking.

The inspector examined EADCR-F-llll3-W and Courter and

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Company memorandum #78-56.

These establish controls to assure that

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icw-hydrogen electrode will not be exposed.to ambient environment

for periods exceeding specifications.

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(Closed) UnresolveTItem (322/78-01-05):' Cooling" rate restrictions

for Courter post weld heat treatment.

The inspector examined a

new Appendix D to Courter weld procedure WPS-NW-100, which describes

">st-weld-heat-treatment.

This includes cooling rate restrictions

consistant with the applicable ASME Code Section III.

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. (Closed) Unresolved Item (332/78-01-07): Courter and Company QC

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Inspection procedure. criteria for evaluation of pipe base metal

grinding. .The inspector examined Courter & Company procedure QAP-

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.10.7, which assigns responsibilities, duties, acceptance criteria,

definitions, and corrective action evaluation /dispostion mechanics

~ for grinding marks or other surface irregularities observed on

. piping.

This procedure appropriately considers possible encroachment

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on minimum pipe wall thickness.

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. This. item is' resolved.

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Inservice Inspection Procedures

The inspector reviewed procedures for work activities relative to

preservice examinations.

The inspector noted that the ultrasonic testing calibration technique

used for examining welds using procedure 80A0467, ray not accomplish

a full volumetric coverage of the weld as required by ASME Section

XI Table IS-261jtem 1.2 Category B.

WFrTre'reTce'dW6cedure states =,

that calib' ration ~from the reference holes is only necessary from

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EITibF'aTion holes at the 1/4T and 3/4T (T = thickness) location.

This calibration does not assure defect detectability at the r.aterial

surfaces.

This item remains unresolved p, ding further action by

the licensee and subsequent inspection by the inspector (322/1850liO9M

LicenseeActiononPreviousInspectionFindinosfiN.sP. 77-Oj'

(0 pen) Unresolved Item (322/78-01-09):

Nuclear Energy Services

Incorporated Procedure 80 A0 467 does not assure detection of flaws

at material surface upon which transducer is placed.

Procedure 80 A0 d67 provides for the ultrasonic examination for the

reactor pressure vessel head meridional, circumferential dome and

flange i. elds.

The calibration requirements of this procedure are

such that it does not provide for the detection of defects near the

ou' er surface of the welds and adjacent material.

This procedure

was used during the previous examination of the vessel head welds.

In view of the vessel head design, wherein the internal surface is

unclad, the inspector found that full vet-path calibration was

practical to permit examination of the full valume of material

surface in the area of interest.

On June 27, 1978, Mr. F. Gerecke of LILC0 telephoned Mr. R. C.

Haynes of the Region I office and informed him that the preservice

examination of the vessel head welds would be repeated as necessary -

to assure ultrasonic examination of the full volume of the material.

This item remains open pending review of the retesting results.

Licensee Action On Previous Inspection Findinas [/NSP. 76-/7f

(0 pen) Unresolved Item (322/78-01-09):

Nuclear Energy Services

ncorporated Procedure 80A0467 does not assure detection of flaws

at material surface upon which transducer is placed.

The licensee has informed Region I office that they intend to

retest the reactor pressure vessel head welds to asssure full

volumetric examination is achieved.

The licensee's contractor is

presently revising the procedure for this examination.

This item remains open pending review of the retesting results.

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ticenne Action on Previous fiRC Insouction Findinos"(/N.5F. 79'l2

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(Closed) Unresolved item (3?2/78-01-09):

Preservice inspection procedure

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ties-80A0467 provisions to assure detection of flaws at the material surface

upon which the transducer is placed.

The inspector examined Revision 4 of

procedure I;ES-80A0467, dated October 30, 1978.

The procedure has been

revised to include full-V calibration for testing for transducer-side

surfece-flaws.

The inspectors also intervicwed responsible personnel

regarding retesting of the RPV closure head welds, and examined I;uclear

Er.ergy Scrvices Inc. letter t;o. 5535-99 which comits to reperior.T.ence of

the RFV closure head ultrasonic e> air.inations.

The LILC0 OA Level 111

engir.cer hes included this item for follcaup in his open ite.: list.

The inspector had no further questions regarding this matter.

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UNITED STATES

551N5 No.-

6835

NUCLEAR REGULATORY COMMISSION

Accession No.:

OFFICE OF INSPECTION AND ENFORCEME_NT

8005053064

WASHINGTON, D.C.

20555

June 10, 198C

IE Information Notice No. 80-26

To All Part 50 Licensees

-> EVALUATION OF CONTRACTOR QA PROGRAM 5

Description of Circumstances:

Appendix B to 10 CFR 50 requires that each applicant and licensee establish

and execute a Quality Assurance Program, and that each licensee "shall require

contractors or subcontractors to provide a quality assurance program"

Further Appendix B requires each applicant and licensee to regularly review

the status and adequacy of subcontractor programs.

The NRC is becoming increasingly concerned by continuing evidence that many

holders of construction permits and operating licenses are not properly

implementing these facets of their quality assurance programs.

Examples of

this lack of effectiveness of contractor QA program implementation, and

inadequacy of licensee overview of contractor QA program implementation are

appearing in every facet of project activity.

Instances have been observed

where architect engineers have released documents for procurement with

inappropriate material specifications.

Nuclear steam system suppliers have

overlooked erroneous assumptions in analysis of instrument system response to

design basis transients.

Other cases have been observed where both AE's and

N555 have not followed through on commitments to review vendor detailed

designs.

Vendors' quality assurance programs have been found to contain

errors of both omission and commission.

A containment tendon installation contract was awarded to a specialty contractor.

During a licensee audit some three months after work started it appeared that a

contractor inspector was falsifying records by initialing inspection points not

actually observed.

A subsequent investigation by the licensee revealed that the

contractor had required that QC inspections be performed only on a random basis

even though all records had QC signatures.

The signatures could mean that the

activity was inspected or that record signoffs by others were reviewed; or that

the_ data were recorded by the QC' inspector.

It is apparent that the licensee

had not appropriately reviewed the contractor's inspection program prior to the

start of work.

In another instance, after completion and acceptance of a major structural

steel installation, the licensee fcund that significant rework would be

required to correct construction quality problems.

NRC inspection at the

contractors fabrication facility disclosed that in addition to work for that

licensee, the contractor had contracts for "high density" fuel storage racks

from_several operating licensees.

None of the NRC licensees had inspected

the contractor's shop or examined his quality assurance programs.

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Response to Information Notice.No. 80-26 is not required.

The NRC expects

appropriate action from all licensees and organizations engaged in nuclear

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activities and actions will be examined in the ongoing NRC inspection program.