ML20238C757

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Forwards Equipment Qualification Insp Rept 50-344/87-13 on 870518-22.Encl App a Identifies Three Deficiencies Classified as Potential Enforcement/Unresolved Items.Items Being Referred to Region V for Further Action
ML20238C757
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 09/04/1987
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
Shared Package
ML20238C759 List:
References
TAC-42502, NUDOCS 8709100356
Download: ML20238C757 (4)
v • d • e


See also: IR 05000344/1987013

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g UNITED STATES

8 o NUCLE.AR REGULATORY COMMISSION '

  • WASMNGTON, D. C. 20555

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September 4, 1987

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Docket No. 50-344

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Mr. David W. Cockfield I

Vice President, Nuclear

Portland General Electric Company >

121 S.W. Salmon Street j

Portland, Oregon 97204 j

Dear Mr. Cockfield:

SUBJECT: EQUIPMENT QUALIFICATION INSPECTION OF TROJAN NUCLEAR PLANT

INSPECTION REPORT NO. 50-344/87-13

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Enclosed is the report of the team insaection conducted by Mr. S. D. Alexander  !

and other NRC representatives during t1e period of May 18 through 22, 1987 at

your engineering offices in Portland, Oregon and at the Trojan Nuclear Plant of l

activities authorized by NRC License No. NPF-1. The team's findings were 1

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 qualification

(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 plunt equipment, interviews with personnel, and other

observations by the inspectors. i

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

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

enclosed inspection report. Three of these deficiencies, summarized in

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

be referred to the NRC Region V office for further action. They included )

failure of EQ documentation to establish that required accuracies were demon-

strated during design basis accident conditions for Minco S8809 resistance  ;

temperature detectors (RTDs) used for density compensation in the reactor ,

vessel level indication system (RVLIS), and for Rosemount 176KF RTDs, which '

provide signals to the subcooling margin monitoring (SMM) system. The third 1

Potential Enforcement / Unresolved Item related to the failure to maintain  !

Limitorque motor-operated valve actuators in containment in a qualified config- i

uration in that gear case grease relief dust / shipping caps had not been removed. i

8709100356 870904

PDR ADOCK 05000344

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-Portland General Electric Company -2-

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Seven 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. ,

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 Y Offico.

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

inspection. j

Silcerely,

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Dn. II Crutchf e . Dir tor

Division of Reacter Proje s III,  !

IV, Y and Special Projects

Office of Nuclear Re6ctor Regulation

Enclosures: '

1. Appendix A - Potential Enforcement / Unresolved Items

2. Inspection Report No. 50-344/87-13 j

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cc w/ enc 1:

E. L. Davis, Chief Electrical Engineer H. F. Moomey, Trojan Resident

Nuclear Plant Engineering Department Gregon Department of Energy

Portland General Electric Company Trojan Nuclear Plant

121 S.W. Salmon Street Post Office Box 439

Portland, Oregon 97204 Rainier, Oregon 97048

D. Swanson, Manager C. A. O bstead, Plant lianager

Nuclear Safety Branch Trojan Nuclear Plant

Portland General Electric Company Post Office Box 439  !

121 S.W. Salmon Street Rainier, Oregon 97048 1

Portland, Oregon 97204

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A. R. Ankrum Michael J. Sykes, Chairman l

Licensing and Regulatory Compliance Board of County Commissioners l

Portland General Electric Company Columbia County )

121 S.W. Salmon Street 'St. Helens, Oregon 97501

Portland, Oregon 97204

Mr. David Kish

Oregon Depcrtment of Energy

Labor and Industries building )

Room 111

Salem, Oregon 97310

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September 4, 1987

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Portland General Electric Company -3-

DISTRIBUTION:

PDk

LPDR

OGC-Bethesda (11NBB-904)

ACRS(10) (1016-H)

VJB Docket Files (50-344)

d ocket Files (50-344) ,__

DRIS Reading

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PD35 Resding

l VIB Reading

JPartlow f

BGrimes

Eherschoff

UPotapovs

SAlexander

RWilson

TChan, PDS (P-302)

GKnighton, PD5

GHolahan

DCrutchfield.

HWalker, 1

EJordan

MYost, INEL

JStoffel, INEL

HStromberg, INEL

DBeahm. INEL

MJacobus, SNL  ;

VNicolette, SNL

REGION V DISTRIBUTION:

JMartin, ADN, RV(LTR ONLY)

DKirsch,(A)D:DRS&P

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

1

SRichards, C:ES, RSB

Achaffee, C:RPB, tr W e4ptedtp

MMendonca, C:RPSI, RPB esamis 5. ersaewteta ,

'

JBurdoin, RPS1, RSB

Robert C Barr, SRI

Trojan Nuclear Plant

Post Office Box 0

Rainier, Oregon 97048

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NAME :SAlexandeA :UPot s :Elle f 'me :JPar og [3 :  :

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DATE :8/th/67 :8/31/87 :8 87 :9/4/87 :9/3 /87  :  :

OFC :D: ,4,5&5P :  :  :  :  :  :

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DM afield :  :  :  :  :  : i

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Portland General Electric Company

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APPENDIX A

Potential Enforcement / Unresolved Items

As a result of the equipment qualification inspection conducted Ray 18 through

22, 1987 at the Portland General Electric Company's (PGE's) engineering offices

and the Trojan Nuclear Plant (TNP), the following items have been referred to

the NRC Region V office as Potential Enforcement / Unresolved Items. (References t

in parentheses at the end of each item cite the pertinent paragraphs in the

inspection report):

1. Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Sections 5.2.5 dnd

8.0 of Enclosure 4 to IE Bulletin 79-01B, the Division of Operating Reactors

(DOR) Guidelines, Qualification file No. 54 for tiinco Type S8809

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resistance temperature detectors (RTDs) did not demonstrate that the plant

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functional performance requirements for their application were met under

postula,ted accident conditions. (Item 50-344/87-13-01, paragraph 4.4.1)

2. Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Sections 5.2.5 and

8.0 of the D0R Guidelines, Qualification file No. 15 for Rosemount Type

17CKF and 176KS RTDs did not demonstrate that the plant functional perfor-

nance requirements for their application were met under the postulated

accident conditions. (Item 50-344/87-13-02, paragraph 4.4.2)

3. Contrary to paragraphs (f) and (k) of 10 CFR 50.49 and Sections 5.2.2 and

8.0 of the DOR Guidelines, Limitorque valve actuators in containment were

not maintained in a condition similar to that in which they were tested, in

that many of their gear case grease relief valves had dust caps installed

and qualification

contain files covering

any justification these

for the Limitorq(ue

deviation. Itemvalve actuators did

50-344/87-13-03, not

paragraph 4.5.2)

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