ML20235Z238

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Responds to Re Violations Noted in Insp Rept 50-293/87-15.Ltr Provided No Addl Info That Would Justify Withdrawing Notice of Violation a Re Linear Indication in Weld That Exceeded Code Acceptable Length
ML20235Z238
Person / Time
Site: Pilgrim
Issue date: 07/21/1987
From: Johnston W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Bird R
BOSTON EDISON CO.
References
NUDOCS 8707270234
Download: ML20235Z238 (2)


See also: IR 05000293/1987015

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JUL P 11987

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' Docket No.

50-293

- Boston Edison Company M/C Nuclear

ATTN: Ralph G. Bird

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Senior Vice President - Nuclear

800 Boylston Street

Boston, Massachusetts 02199

Gentlemen:

1

Subject:

Inspection No. 50-293-87-15

Thb ?etter is in respoiise to your June 10, 1987 letter regarding our

tran wittal of Inspection Report 50-293/87-15. Our transmittal was dated

May b 1937 and. contained two Notices of Violation related to your Inservice

Inspection (ISI) activities.

We have reviewed the information you have provided and our response is ai,

follows:

Notice of Violation A was issued after NRC inspectors identified a linear

indication in a weld that exceeded the code acceptable length. This finding

represents a failure to satisfy ASME Code requirements as required by

10 CFR 50.55a(g). Your June 10, 1987 letter provided no additional informa-

tion that would justify withdrawing the subject Notice of Violation.

With regard to Notice of Violation B, our Inspection Report (IR 50-293/87-15)

acknowledged that all contractor personnel performing. level II visual'inspec-

tion activities during refueling outage No. 7 satisfied the ANSI 45.2.6

requirement of a minimum of four years of actual visual inspection experience.

The breakdown occurred in the ISI contractor procedure No. QC-7, Rev. 3 which

required on.ly fcur months of total experience. Had any of the subject person-

nel not satisfied the ANSI requirement a higher severity level violation could

have resulted. The fact that this deviation in the contractor's procedure

was identified at another site and that the contractor was taking action to

correct the procedure does not relieve Boston Edison of the responsibility for

implementing appropriate measures to ensure that contractor activities are

completed in accordance with NRC requirements and license commitments.

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 program.

8707270234 870721

PDR

ADOCK 05000293

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PDR

OFFICIAL RECORD COPY

RL PILGRIM 87-15 - 0001.0.0

07/21/87

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Boston Edison Company M/C Nuclear

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Your cooperation with us is appreciated.

Sincerely,

Or;ginal Signed By 3

William V. Johnston, Acting Director

Division of Reactor Safety

cc:

K. P. Roberts, Station Manager

Paul Levy, Chairman, Department of Public Utilities

Chairman, Board of Selectmen

Plymouth Civil Defense Director

J. D. Keyes

The Honorable E. J. Markey

Senator Edward P. Kirby

The Honorable Peter V. Forman

Sharon Pollard, Secretary of Energy Resources

Rachel Shimshak, MASSPIRG

Public Document Rnom (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector

Commor, wealth of Massachusetts (2)

bec:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o encl)

Section Chief, DRP

W. Raymond, SRI, Vermont Yankee

T. Shediosky, SRI, Millstone 1&2

.

H. Eichenholz, SRI, Yankee

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R. Wessman, PM, NRR

PA0 (2) SALP Reports Only

Robert J. Bores, DRSS

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M. Gay

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07/2) /87

0FFICIAL RECORD COPY

RL PILGRIM 87-15 - 0001.1.0

07/16/87

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80STONEDISON

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Executive Othces

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800 Boylstor' street

Boston. Massachusetts 02199

' Ralph G. Bird

Senior Vice President - Nuclear

June

10, 1987

BECo Ltr. #87-101

Document Control Desk

U.S. Nuclear Regulatory Commission

Washington, D.C. 20555

Docket No. 50-293

License No. DPR-35

Subject: NRC Inspection Report 50-293/87-15

Reference:

Boston Edison Company Letter Number 87-94

Dear Sir:

Attached is Boston Edison Company's response to the Notice of Violation

contained in the subject inspection report.

On June 2, 1987 members of Boston Edison Company management held a telephone

conversation with members of NRC Region I involved with the subject

inspection. Additional information not available at the time of the

inspection was discussed.

Based upon information discussed in this

conversation, and presented in the attachment to tnis letter, we request'that-

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Notice of Violation *A*be" withdrawn:

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Notice of Violation B identifies a deficiency in our method of reviewing ISI

contractor qualifications in that a potential for error was present. Although

we agree that our written procedures did not provide adequate evidence of

control over the review and selection of contractor ISI personnel, it should

be noted that our practices have not resulted in the use of insufficiently

qualified personnel.

Please do not hesitate to contact me directly if you have any questions.

R . G'.

r$

EH/la

Attachment

cc: Regional Administrator, Region I

Director Office of Inspection

U.S. Nuclear Regulatory Commission

and Enforcement

631 Park Avenue

U.S. Nuclear Regulatory Commission

King of Prussia, PA 19406

Hashington, D.C. 20555

Senior Resident Inspector

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Attachment

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Boston Edison Company

Docket No. 50-293

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Pilgrim Nuclear Power Station

License No. DPR-35

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Notice of Violation A

10CFR50.55a (g) requires that ASME Code Class 1, 2, and 3 components meet the

inservice inspection requirements set forth in the applicable edition of

Section XI of the ASME Code. The 4 Pi l g ri m ' Magnet i c" Pa rt i c l e < Exami nati on .

Pr.ocedu,re;50.2.0,Jevision 2.t. implements-the ASMEcCode ~Section'XI" inservice'

inspection.arequirementssincluding,the, requirements,that" surface-indications w

not exceedethe< allowable, size. limit,as-specifiedtin Table IWB<3514-2'of e

m

Section+XI. war-

Contrary to the above, on March 10, 1987 weld DB23-2-1C was found to have a

surface linear indication (3/4" in length) that exceeded the limits specified

within the site magnetic particle procedure and AMSE Code Section XI, Table

IWB 3514.2.

This indication had not been identified or dispositioned during a

previous magnetic examination performed by the licensee.

Response

Investigation of Violation

Boston Edison has reviewed the chronology of activities associated with

the inspection of weld D8-23-2-1C.

This review determined that our

initial magnetic particle examination of October 18, 1986 was performed in

accordance with all applicable code requirements.

Further review of the

facts associated with the NRC inspection of the weld on March 10, 1987

revealed that the surface condition of the weld had been altered between

our examination and the NRC's by further surface preparation for

ultrasonic testing.

It is hypothesized that this additional surface

preparation produced the surface indication identified by the NRC.

Based

upon the intervening activity, i.e. the further surf ace preparation, it

appears that the NRC's March 10, 1987 examination was not conducted on a

weld under the Game conditions as the original magnetic particle exam and

thus was not an accurate test case to determine the adequacy of our

surface examination program. Based upon the forgoing, there appears to

have been no violation.

The chronology of events is presented below.

Weld DB-23-2-1C was scheduled for both magnetic particle and ultrasonic

examination during this refueling outage. To prepare the weld surface for

examination the protective paint coating was removed from the pipe by

means of a mechanical buffer. The original preparation removed paint two

inches on each side of the weld which was adequate for magnetic particle

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examination.

The magnetic particle examination (yoke method) was

performed on October 18, 1986 and found acceptable.

In order to conduct the ultrasonic examination, an additional two inches

of pipe surface required paint removal to allow for an adequate scan

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surface.

It should be noted that after the completion of this additional

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surface preparation no additional magnetic particle examination was

conducted.

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On March 10, 1987, the NRC examined the weld and found a surface

indication that exceeded the specified limits.

Following NRC

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identification of the indication, BECo reinspected 08-23-2-1C on March 10,

1987 and_ initiated Nonconformance Report (NCR)87-099 to document the

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linear indication.

On May 21, 1987 the_nonconformance report 87-099 was dispositioned to

require an ultrasonic thickness measurement. ~ The wall thickness was

determined to be 1.0134".

The indication was then removed by mechanical

process. . Once the indication was visually removed a magnetic particle

examination was performed and found acceptable.

A second. ultrasonic thickness measurement was' performed to determine the

new wall thickness which is 0.992".

Therefore, 0.042" of material was

removed to obtain an acceptable magnetic particle examination.

Corrective Steps Taken

The Operational Quality Control Group (00C) reviewed documentation for all

welds performed during the current outage to identify any similar

problems. 00C identified three other welds that had additional surface

preparation after the magnetic particle exam was completed. These welds

were reinspected on March 12, 1987 with no unacceptable indications

identified.

We recognize that inconsistencies in repetitive magnetic particle

examinations may invite questions as to the adequacy of the previously

conducted examination. Therefore, to insure that subsequent periodic

examination of the surface can accurately be compared to the "as left"

condition of the surface, 00C prepared and issued Quality Control

Instruction (QCl) 20.41, " Surf ace Preparation Requirements of Weldments

that Require NDE".

This new QCl requires that all NDE surface preparation

of a weld be completed prior to that weld being released to inspection

personnel.

In addition, this QCI requires the examiner to document that

all surface preparation has been completed prior to the start of the

surface examinations.

If f urther surface preparation is required af ter

the surface examination has been conducted, a reinspection will be

performed to detect any changes in the surface conditions.

All 151 NDE personnel at PNPS have reviewed QCI 20.41 and have documented

their understanding of the contents.

The appropriate forms included in QCl 50.10 (Liquid Penetration

Examination) and 001 50.20 (Magnetic Particle Examination) have been

revised to include documentation of adequate surface preparation.

Date When Full Compliance Was Achieved

Boston Edison continues to be in compliance. Additional BECo activities

associated with this item have been completed. QCI 20.41 was issued on

March 26,1987. All 1S1' NDE personnel reviewed the procedure by April 15,

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1987.

On May 26, 1987 the indication reported on NCR 87-099 was removed

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by the grinding process; the area was reinspected by the magnetic particle

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process and found acceptable.

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Notice of Violation B

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10CRR50.5S(g) requires that ASME Code Class 1, 2, and 3 components meet

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the inservice inspection requireraents set forth in the applicable edition

of Section XI of the ASME Code and 10CFR Appendix B, Criterion IX requires

that personnel qualifications be in compliance with requirements of

applicable codes and standards. ASME Code Section XI, IWA 2300, 1980

Edition and Pilgrim implementing procedure 00-10.06, Revision 4, invoke

ANSI 45.2.6 requirements that a Level 11 visual examiner have four years

of experience in testing or inspection or both Of power plant, heavy

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industry or other similar f acility equipment.

Contrary to the above, on March 7,1987, NRC review of the ISI contractor

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procedure no. OC-7, Rev. 3 in use at the site, disclosed that the

procedure required only four months of total experience rather than the

/ "~ ANSI 45.2.6 requi' red four years.

Response

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Prior to the commencement of any nondestructive examination,

qualifications of contractor personnel are reviewed by Boston Edison's NDE

Level Ill certified inspector. All contractor personnel performing NDE

during RF0 #7 have a minimum of four years of actual NDE experience even

though ISI contractor procedure No. QC-7, Rev. 3 required four months of

total experience.

It should be noted that this deviation had been previously identified by

the NRC at another utility in November, 1986 and corrective action by the

151 contractor was already in progress prior to the commencement of the

NRC inspection at Pilgrim Station.

The contractor's procedure was revised

on November 26, 1986 to require a minimum of four years experience

however, it was not issued at PNPS until March 12, 1987.

Corrective Steps Taken and Results Achieved

To remove the potential for misapplication of BECo requirements for

qualification of NDE personnel, BECo Quality Control Instruction (OC1)

20.40 has been revised to require that all personnel performing

nondestructive examinations be certified in accordance with SNT-TC-1 A and

ANSI 45.2.6,1973/1978 as applicable to the type of inspection to be

performed.

The QC1 was further revised to state that prior to the

commencement of any nondestructive examination, the contractor NDE

certification procedures (such as 0C-7) and personnel certifications

receive a documented review by the Boston Edison Level III for

verification of consistency with BEco commitments to codes and standards.

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Date When Full Compliance Was Achieved

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Boston Edison's position is that there was a deficiency in our procedure

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which might have allowed the use of inspectors which were not fully

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qualified to the level required by the BECo Quality Assurance Manual.

However, there was.no degradation in the implementation of the

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requirements of ANSI 45.2.6 for Level II visual examiners as implied in

the Notice of Violation.

In order to correct the identified procedural deficiencies, QCI 20.40 was

revised to incorporate the review of contractor procedures and personnel

qualifications to the requirements of ANSI 45.2.6 1973/1978 as applicable

and ',ssued on March 20, 1987. The revised, ISI contractor procedure QC-7

was received on site on March 12, 1987.

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