ML20238C757

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|{{#if:ML20238C757|Download: [[URL::http://pbadupws.nrc.gov/docs/{{#sub:ML20238C757%7C0%7C6}}/ML20238C757.pdf%7CML20238C757]]|[[URL::http://pbadupws.nrc.gov/docs/{{#sub:%7C0%7C6}}/.pdf%7C]]}} }} See also: see also::IR 05000344/1987013

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l September 4, 1987 o% ***.*/ j Docket No. 50-344 '- { I Mr. David W. Cockfield 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 , 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 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 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 G PDR -__--_-

,- _ _- . . . . -Portland General Electric Company -2- 1 l 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, . - 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 i 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 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 . m

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September 4, 1987 . 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 PD35 Resding i 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

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. . , ! . . l . Portland General Electric Company i { v- APPENDIX A I 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 resistance temperature detectors (RTDs) did not demonstrate that the plant , 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 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) i 1 _ . _ . _ _ _ _ _ . _ _ . _ _ }}