ML17306A180

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Forwards Insp Repts 50-528/91-25,50-529/91-25 & 50-530/91-25 on 910708-12 & 22-26.Violation Noted.Findings Suggest Need for Addl Emphasis on Timely Assessment of Potential Generic & Programmatic Implications of MOV Problems
ML17306A180
Person / Time
Site: Palo Verde  
Issue date: 09/20/1991
From: Kirsch D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Conway W
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
Shared Package
ML17306A181 List:
References
GL-89-10, NUDOCS 9110070112
Download: ML17306A180 (3)


See also: IR 05000528/1991025

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION V

1460 MARIALANE. SUITE 210

WALNUTCREEK, CALIFORNIA94696-6368

SEP

Docket Nos. 50-528,

529,

and

530

Arizona Public Service

Company

P. 0.

Box 53999, Sta.

9012

Phoenix, Arizona

85072-3999

Attention:

Mr. M. F.

Conway

Executive Vice President,

Nuclear

SUBJECT:

NRC INSPECTION AT PALO VERDE NUCLEAR GENERATING STATION

This letter refers to the inspection

led by Mr. Dave Corporandy of this office

during the weeks of July 8 and July 22, 1991, of activities authorized

by NRC

License

Nos.

NPF-41,

NPF-51

and NPF-74,

and to the discussion

of our findings

held with members of your staff on July 26, 1991.

Additional in-office review

of licensee

provided documents

continued through August 13,

1991.

The

inspection evaluated

the adequacy of Palo Verde actions to assure

the

reliability of motor operated

valves

(MOVs).

Our inspectors

reviewed the

program that you have developed in response

to

NRC Generic Letter 89-10,

"Safety-Related

Notor Operated

Valve Testing

and Surveillance."

Generic Letter 89-10 provides

recommendations

for licensees

to develop

and implement

programs to ensure that

MOVs will operate properly under design basis

conditions.

Specific areas

examined during this inspection

are described in the enclosed

inspection report.

Mithin these

areas,

the inspection consisted of selective

examinations=of

procedures

and representative

records,

interviews with

personnel,

and observations

of ongoing maintenance

of MOVs.

Based

on the results of this inspection, it is clear that you are developing

an ambitious

program for your MOVs, with an

MOV group that appears

to be

staffed with knowledgeable

and dedicated

personnel.

However, the findings of

this inspection indicate the need for additional

emphasis

on more timely

assessment

of the potential generic

and programmatic implications of MOV

problems

being identified by your program activities.

In this regard,

the

inspectors identified two of your activities that appeared

to be in violation

of NRC requirements,

as

documented

in the attached

Notice of Violation

(Notice), and two other weaknesses

in your program:

a.

Potential

generic deficiencies

associated

with repeated

MOV torque switch

chattering

had not been properly evaluated

in accordance

with your

administrative

and technical

procedures.

(Violation A)

b.

Appropriate acceptance

criteria had not been established

for certain

NOV

tests to properly demonstrate

MOV capability to perform under design

basis conditions or properly validate your.MOV design methodology.

(Violation B)

9110070112

910920

PDR

ADDCK 05000528

8

PDR

-2-

c.

Valve factors

were revised for specific

MOVs which had failed design

basis tests without providing timely evaluation of generic applicability

to other

MOVs of similar design.

(Report Section 4.3)

d.

Stem friction coefficients

used in engineering calculations

assumed

stem

condi tion and 1ubri cant quali ties whi ch had not been appropri ately

incorporated into applicable preventive maintenance

procedure

verifications.

(Report Section 4.3)

These

and other inspection findings are discussed

in detail in the attached

inspection report.

In accordance

with 10 CFR 2.790(a),

a copy of this letter

will be placed in the

NRC Public Document

Room.

Should you have

any questions

concerning this inspection,

we will be pleased

to discuss

them with you.

You are required to respond to this letter and should follow the instructions

in the enclosed

Notice when preparing your response.

In your response,

you

should document the specific actions

taken

and any additional actions

you plan

to prevent recurrence.

After reviewing your

response

to the Notice, including

your proposed corrective actions

and the results of future inspections,

the

NRC will determine

whether further

NRC enforcement action is necessary

to

ensure

compliance with NRC regulatory requirements.

t

The responses

directed

by this letter

and the enclosed

Notices are not

subject to the clearance

procedures

of the Office of Management

and Budget

as

required

by the Paperwork

Reduction Act of 1980,

Pub.

L. No.96-511.

Sincerely,

D. F. Kirsch, Chief

Reactor Safety Branch

Enclosures:

l.

Appendix

A - Notice of Violation

2.

Inspection Report Nos. 50-528/91-25,

50-529/91-25,

50-530/91-25

cc:

Mr. W. Mark DeMichele,

APS

Mr. James

M. Levine,

APS

Mr. Jack

N. Bailey,

APS

Mr. E.

C. Simpson,

APS

Mr. Blaine E. Ballard,

APS

Mr. Thomas

R. Bradish,

APS

Mr. Robert

W. Page,

APS

Mr. Arthur C. Gehr, Esq., Snell

5 Wilmer

Mr. Al Gutterman,

Newman

5 Holtzinger P.C.

Mr. James

A. Boeletto, Esq., Assistant Counsel,

SCE Company

Mr. Charles

B. Brinkman, Combustion Engineering,

Inc.

Mr. Charles Tedford, Director, Arizona Radiation Regulatory Agency

Chairman,

Maricopa County Board of Supervisors

Mr. Steve

M. Olea, Chief Engineer, Aiizona Corporation

Commission

Ignacio R. Troncoso,

El Paso Electric Company

Roy P. Lessy, Jr., Esq., Akin, Gump, Strauss,

Hauer

and Feld

Bradley

W. Jones,

Esq., Akin, Gump, Strauss,

Hauer and Feld

cc w/enclosures:

Project Insepctor

Resident

Inspector

Docket File

P.

K.

Eapen

HRRlDET/EHER~

R. Jape,

RII

D. Danielson,

RII

T. Stetka,

RIV

G.

Cook

K. Perkins

R.

Zimmerman

B. Faulkenberry

J. Martin

bcc w/o enclosures:

M. Smith

J. Zollicoffer

J.

Bianchi

Region V/ann

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