ML20238C757
| 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) | |
See also: IR 05000344/1987013
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UNITED STATES
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NUCLE.AR REGULATORY COMMISSION
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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
Vice President, Nuclear
Portland General Electric Company
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121 S.W. Salmon Street
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Portland, Oregon 97204
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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
activities authorized by NRC License No. NPF-1. The team's findings were
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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.
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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
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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
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provide signals to the subcooling margin monitoring (SMM) system. The third
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Potential Enforcement / Unresolved Item related to the failure to maintain
Limitorque motor-operated valve actuators in containment in a qualified config-
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uration in that gear case grease relief dust / shipping caps had not been removed.
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8709100356 870904
ADOCK 05000344
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-Portland General Electric Company
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Seven additional concerns were classified as Open Items, and a future NRC
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inspection will review your actions concerning them. Details of.all the
deficiencies and concerns are discussed in the enclosed inspection report.
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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
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inspection.
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Silcerely,
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II Crutchf e . Dir tor
Division of Reacter Proje s III,
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IV, Y and Special Projects
Office of Nuclear Re6ctor Regulation
Enclosures: '
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Appendix A - Potential Enforcement / Unresolved Items
2.
Inspection Report No. 50-344/87-13
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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
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121 S.W. Salmon Street
Rainier, Oregon 97048
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Portland, Oregon 97204
A. R. Ankrum
Michael J. Sykes, Chairman
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Licensing and Regulatory Compliance
Board of County Commissioners
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Portland General Electric Company
Columbia County
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121 S.W. Salmon Street
'St. Helens, Oregon 97501
Portland, Oregon 97204
Mr. David Kish
Oregon Depcrtment of Energy
Labor and Industries building
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Room 111
Salem, Oregon 97310
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September 4,
1987
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Portland General Electric Company
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DISTRIBUTION:
PDk
LPDR
OGC-Bethesda (11NBB-904)
ACRS(10) (1016-H)
VJB Docket Files (50-344)
d ocket Files (50-344)
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DRIS Reading
PD35 Resding
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VIB Reading
JPartlow
f
BGrimes
Eherschoff
UPotapovs
SAlexander
RWilson
TChan, PDS (P-302)
GKnighton, PD5
GHolahan
DCrutchfield.
HWalker,
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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
SRichards, C:ES, RSB
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Achaffee, C:RPB,
tr W e4ptedtp
MMendonca, C:RPSI, RPB
esamis 5. ersaewteta
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JBurdoin, RPS1, RSB
Robert C Barr, SRI
Trojan Nuclear Plant
Post Office Box 0
Rainier, Oregon 97048
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- 8/31/87
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Portland General Electric Company
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APPENDIX A
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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
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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
resistance temperature detectors (RTDs) did not demonstrate that the plant
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functional performance requirements for their application were met under
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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 files covering these Limitorq(ue valve actuators did not
contain any justification for the deviation.
Item 50-344/87-13-03,
paragraph 4.5.2)
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