ML20204E233

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Forwards Insp Repts 50-275/86-33 & 50-323/86-31 on 861215-19 & Potential Enforcement/Unresolved Items.Four Deficiencies Will Be Referred to Region V for Further Action.Corrective Actions Should Be Not Be Delayed
ML20204E233
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 03/20/1987
From: Merschoff E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Shiffer J
PACIFIC GAS & ELECTRIC CO.
Shared Package
ML20204E236 List:
References
NUDOCS 8703250654
Download: ML20204E233 (5)


See also: IR 05000275/1986033

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o UNITED STATES

!' n NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20666

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\...../ March 20, 1987

Docket Nos. 50-275 and 50-323

Pacific Gas and Electric Company

ATTN: Mr. James D. Shiffer, Vice President

Nuclear Generation Department

77 Reale Street, Room 1435

San Francisco, California 94106

Dear Mr. Shif#er:

SUBJECT: INSPECTION PEPORT N05. 50-275/86-33, 50-323/86-31

Enclosed is the report of the team inspection cenducted by Mr. S. D. Alexander

and other NRC representatives during the period of December 15 through 19, 1936

at the Diablo Canyon Power Plant, of activities authorized by hRC License Nos.

DPR-80 and DPR-81. The team's findings were discussed with you and members of

your staff at the conclusion of the inspection. The inspectors reviewed your

implementation of a program as required by 10 CFR 50.49 for establishing and

maintaining the environmental cualification (EQ) of electrical equipment within

the scope of 10 CFR 50.49. Within these areas, the inspection consisted of

examination of selected procedures and records, inspection of selected plant

equipment, interviews with personnel, and other observations by the inspectors.

The inspectors determined that you have implemented a proaram to meet the

requirements of 10 CFR 50.49 except for certain deficiencies identified in the

enclosed inspection report. Four of these deficiencies, summarized in

Appendix A, are classified as Potential Enforcement / Unresolved Items and will

he referred to the NRC Rec 2 ion V office for further action. These defiriencies

related to incomplete spebification of functional performance requirements #or

Conax containment sump temperature sensors and reactor coolant loop subcooling

margin temperature sensors, failure to upgrade (or .iuttify not opgredirg) to

10 CFR 50.49 requirements the level of qualification of a tape and putty solice

insulation system used on equipment qualified to 10 CFR 50.49, lack of submer-

ger.ce type test on Minco temperature sensors subject to submergence used fnr

reactor vessel level indication system density compensation and leck of gear

case ' grease relief valves on certain in-containment Limitorque motorized valve

actuators. ,

B703250654 870320

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-2- March 20, 1987

Pacific Gas and Electric Company

Four additional concerns were classified as Open Items, and a future NRC

inspection will review your actions concerning them. Details of all the

deficiencies and concerns are discussed in the enclosed inspection report.

Corpletion of your corrective actions regarding the identified deficiencies

and concerns should not be delayed pending either a future NRC inspection or

further action by the NRC Region V Office.

We are available to discuss any questions you may have concerning this

inspection.

Sincerely,

. /

E lis W. M'erschoff, ting Chief

Vendor Program Bra

Division of Quality Assurance, Vendor

and Technical Training Center Programs

Office of Inspection and Enforcement

Enclosures:

1. Appendix A - Potential Enforcement / Unresolved Items

2. Appendix B-Inspection Peport Nos. 50-275/86-33 and 50-323/86-31

cc w/ enclosures

Pacific Gas & Electric

ATTN: C. Coffer, Supervisor

Nuclear Regulatory Affairs

77 Beale Street

San Francisco, California 94106

Pacific Gas & Electric

ATTN: R. Oman, EQ Task Force Coordinator

77 Beale Street

San Francisco, California 94106

Pacific Gas & ETectric

ATTN: J. Blakely, Special Projects

Nuclear Regulatory Affairs

77 Beale Street

San Francisco, California 94106

Diablo Canyon Power Plant

ATTN: R. Thornberry

Plant Manager

P. O. Box 56

Avila Beach, CA 93424

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March 20, 1987

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AChaffee, C:RPB,

MMendonca, C:RPS1, RPB

JBurdoin, RPS1, RSB

Diablo Canyon Power Plant

ATTN: P. Narbut, USNRC Senior Resident Inspector,

Post Office Box 396,

Avila Beach, CA 93424

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Distribution:

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IE Docket Files (50-275/323)

DQAVT Reading

VPB Reading

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BGrimes

HMiller

UPotapovs

SAlexander

GHubbard

RWilson

RLasky

HWalker, PAEI/NRR

HSchierling, PAD 3/NRR

MYost, INEL

RCarpenter, INEL

RVanderbeek, INEL

DBeabm, INEL

MJacobus, SNL

REGION V DISTRIBUTION:

JMartin, ADM, RV

DKirsch,(A)D:DRS&P

RPate,(A)C:RSB,DRS&P

SRichards, C:ES, RSB

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DWillett, ES,RSB

AChaffee, C:RPB,

MPendonca, C:RPS1, RPB

JBurdoin, RPS1, RSB

Diablo Canyon Power Plant

ATTN: P. Narbut, USNRC Senior Resident Inspector.

Post Office Box 396,

Avila Beach, CA 93424

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APPENDIX A

Potential Enforcement / Unresolved Items

As a result of the equipment qualification inspection during the period of

December 15 through 19, 1986 at the Pacific Gas and Electric Company's (PGAE)

Diablo Canyon Power Plant (DCPP), the following items have been referred to the

NRC Region V office as Potential Enforcement / Unresolved Items. (Paragraph

references in parentheses are to detailed portions of the inspection report.)

1. Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and sections 2.2 and

5(1) of NUREG 0588, Category II, PG&E did not establish complete

functional performance requirements for safety-related Conax RTDs in that

the required accuracy for the RTDs was specified in the file as " 1.75 F",

but there were no criteria or standard values established with which to

evalute the data against this specification. Examination of the raw data

showed that several of the semples during the design basis event simula-

tion deviated from the others by nore than 1.75 F. (Paragraph 4.0(1),

Items 50-275/86-33-01 and 50-323/86-31-01)

2. Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Sections 2.2, 2.4

and 5(1) of NUREG-0588, Category II, PG8E had not established cualifica-

tion for safety-related Minco resistarce temperature detectors (RTD)

subject to submergence in that documentetion of a submeroence type test

was not provided. (Paragraph 4.0(2), Items 50-275/86-33,50-323/86-31-02)

3. Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and section 5(1) of

NUREG 0588, Category II, the qualification documentation for Limitorque

motorized valve actuators (ID No.: 8703) did not establish sirilarity

between the installed actuator and that tested in that, unlike that tested,

there was no gear case grease relief on the installed actuator. The files

contained no analyses to demonstrate that grease reliefs were not required

for the DCPP applications. (Paragraphs 4.D(6) and 4.E(4), Items 50-275/

86-33-03 and 50-323/86-31-03)

4. Contrary to paragraph (1) of 10 CFR 50.49, PG&E had not upgraded to

10CFR 50.49 requirements the level of cualification of their Scotch 33*/

Scotchco putty cable splice insulation system used on qualified equipment

purchased after the effective date of 10 CFR 50.49 (February 22,1983)

and the file contained no sound reasons to the contrary. (Paragraphs

4.E(6), Items 50-275/86-33-04 and 50-323/86-31-04)

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