ML20210T274

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Forwards Insp Repts 50-361/97-15 & 50-362/97-15 on 970630-0902 & Nov.Presentations Made by Staff During Meeting in Region 4 Ofc on 970821 Have Been Included as Attachments 3 & 4 to Insp Rept
ML20210T274
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 09/10/1997
From: Howell A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Ray H
SOUTHERN CALIFORNIA EDISON CO.
Shared Package
ML20210T281 List:
References
50-361-97-15, 50-362-97-15, EA-97-414, NUDOCS 9709150036
Download: ML20210T274 (6)


See also: IR 05000361/1997015

Text

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ARLINGTON, TE XAS 760118064 -

September 10,1997

EA 414

Harold B. Ray, Executive Vice President

Southern Californie Edison Co.

San Onofre Nuclear Generating Station

P.O. Box 128

San Clemente, California 92674 0128

kJBJECT: NPC INSPECTION "3

ST 50-361/9715; 50 362/9715 AND NOTICE OF

VIOLATION

Dear Mr. Ray:

l

An NRC inspection was conducted onsite June 30 through July 3,1997, at your San

Onofre Nuclear Generating Station, Units 2 and 3, reactor facilities, as a result of the

identification during the Units 2 and 3 Cycle 9 refueling outages of recurring through wall _

cracking in inconel 600 reactor coolant system nozzle penetrations. Additional in-office

and onsite inspection was performed during July 25 through September 2,1997. The

,

additional inspection included review of a July 22,1997, letter from your staff pertaining

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to compliance with Criterion XVI of Appendix B to 10 CFR Part 50. The July 22,997,

letter has been included as Attachment 2 to the inspection report. Presentations made by

your t.taff during a meeting in the Region IV office on August 21,1997, have been-

included as Attachments 3 and 4__to the inspection report._ The enclosed report pr9sents -

the scope and results of this inspection.

The inspection identified one violation pertaining to the placing of the Unit 3 reactor

coolant system in a 10_ CFR 50.65(a)(2) category as of July 10,1996, despite the

identification in 1995 of through wall cracking in four reactor coolant system norrie

pene: rations.

The volation is cited I, die enclosed Notice of Violation (Notice) and the circumstances

surrounding the violat;on are described in detailin the enclosed report. Please note that

you are required to respond to this letter and should follow the instructions specified in the

enclosed Notice when preparing your response. The NRC will use your response, in part,

_

to determine whether further enforcement action is necessary to ensure compliance with _

regulatory requirements,

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9709150036 970910

-PDR - ADOCK 05000361

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Southern California Edison Co.

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The results of the inspection indicate that refueling outage inspections have identified

recurring through wall cracking in inconel 600 reactor coolant system nozzle penetrations,

with the predominant degradation mechanism determined to be primary water stress

corrosion cracking. While you have conducted repairs upon identification of cracking in

individual nozzle penetrations, we consider your overall response to be of concern.

Specifically, your current approach to this degradation issue allows the potential for reactor

- coolant system pressure boundary leakage to occur during Mode 1 power operations, a

condition not permitted by sour Technical Specifications. We further note that repetitive

,

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f ailures have occurred in individua! heats of Inconel 600 alloy nozzle penetrations,

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indicating certain heats of material are particularly susceptible to primary water stress

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corrosion cracking.

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Based on the resulta of this inspection, one apparent violation was also identified and is

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being considered for escalated enforcement action in accordance with the " General

Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy),

NUREG 1600. Accordingly, no Notice of Violation is presently being issued for this

inspection finding. The apparent violation involved the failure to implement actions to

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preclude recurrence of Heat NX7630 nozzle penetration cracking in accordance with the

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requirements of Criterion XVI of Appendix B to 10 CFR Part 50. In addition, please be

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advised that the number and characterization of the apparent violation described in the

enclosed inspection report may change es a result of further NRC review,

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A predecisional enforcement conference to discuss this apparent violation has been

scheduled for September 24,1997, at 1 p.m. CDT. The decision to hold a predecisional

enforcement conference does not mean that the NRC has made a final determination that a

violation has occurred or that enforcement action will be taken. This conference is being

held to ubtain information to enable the NRC to make an enforcement decision, such as a

common understanding of the facts, root causes, missed opportunities to identify the

apparent violation sooner, corrective actions, significance of the issues and the need for

lasting and effective corrective action, in addition, this is an opportunity for you to point

out any errors in our inspection report and for you to provide any information concerning

your perspectives on 1) the severity of the apoarent violation, 2) the application of the

factors that the NRC considers when it determines the amount of a civil penalty that may

be assessed in accordance with Section VI.B.2 of the Enforcement Policy, and 3) any other

application of the Enforemnent Policy to this case, including the exercise of discretion in

accordance with Section Vll. This conference will be open to public observation in

accordance with the Enforcement Policy.

You will be advised by separate correspondence of the results of our deliberations on this

matter No response regarding the apparent violation is required at this time,

in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter

and its enclosure will be placed in the NRC Public Document Room (PDR).

.

.

'

Southern California Edison Co.

3

Should you have any questions concerning this inspection, we will be pleased to discuss

them with you.

Sincerely,

1

[1

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h Art ur T. HowellIll, Director

Division of Reactor Safety

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Docket Nos.: - 50 361; 50 362

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License Nos.: NPF 10; NPF 15

Enclosure:

NRC Inspection Report

-50 361/97 15;50 362/97 15

4

cc w/ enclosures:

Chaltman, Board of Supervisors

County of San Diego

1600 Pacific Highway, Room 335

San Diego, California 92101

Alan 'c . Watts, Esq.

Woodruff, Spradlin & Smart

701 S. Parker St. Suite 7000--

Orange, California 92868-4720

Sherwia Harris, Resource Project Manager

Public Utilities Department

City of Riverside

3900 Main Street -

Riverside, California 92522

R. W. Krieger, Vice President

- Southern Californla Edison Company

- San Onofre Nuclear Generating Station

- P.O. Box 128

San Clemente, California 92674 0128

.

.

Southern California Edison Co.

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Dr. Harvey Collins, Chief

Division of Drinking Water and

Environmental Management

California Department of Health Services

P.O. Box 942732

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Sacramento, California 94234 7320

Terry Winter, Manager

Power Operations

San Diego Gas & Electric Company

P.O. Box 1831

San Diego, California 92112

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Mr. Steve Hsu

Radiological Health Branch

State Department of Health Services

P.O. Box 942732

Sacramento, California 94234

Mayor

City of San Clemente

100 Aven:da Presidio

San Clemente, California 92672

Mr. Truman Burns \\Mr. Robert Kinosian

California Public Utilities Commission

505 Van Ness, Rm 4102

San Francisco, California 94102

.

.

Southern California Edison Co.

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