IR 05000344/1986017

Insp Rept 50-344/86-17 on 860505-09.No Noncompliance or Deviations Noted.Major Areas Inspected:Onsite Review Committee,Qa Test & Measurement Equipment Program & Surveillance Program

ML20211A855
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/19/1986
From:	Jim Melfi, Mendonca M, Pereira D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20210V319	List: IR 05000344/1986017 ML20210V316
References
50-344-86-17, NUDOCS 8606110386
Download: ML20211A855 (6)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION V

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. Report No.' 50-344/86-17 Docket No. 50-344 License No. NPF-1 Licensee: Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Name: Trojan Nuclear Plant'

Inspection at: Rainier, Oregon Inspection Con cted: My -9, 1986 Inspectors: #f(thf 8 6 [b D. B. Pereira, Reactor Inspector Date Signed

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n YWe 4d Melfi, Reacto M nspector 6f//~

D5te Signed Approved By:

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" ##r " MO M. M.' Mendonca, Reactor Project Section 1 Date Signed Summary:

Inspection During the Period of May 5-9, 1986 (Report No. 50-344/86-17)

Areas Inspected: Routine, unannounced inspection of the Onsite Review Committee, Quality Assurance (QA) Test and Measurement Equipment Program, and the Surveillance Program by two NRC inspectors. The inspection modules followed were: Onsite Review Committee (40700), QA Test and Measurement Equipment Program (35750), and Surveillance Program (61700).

, ResuQs: No items of noncompliance or deviations were identified.

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8606110386 860520 PDR ADOCK 05000344 G PDR

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. 1 DETAILS

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1. . Persons Contacted J*W. S. Orser, General Manager

• C. A. Olmstead, Manager, Quality Assurance Department

• J. D. Reid, Manager, Plant Services

• D. W. Swan, Supervisor, Maintenance  ?-

• M. R. Snook, Specialist, Quality Assurance Department

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A. Puzy, Office Supervisor

• S. ' Bauer, Engineer, Nuclear Safety and Regulation Department .

R.~Reinart, Supervisor, Instrumentation and Control .

• D. Keuter, Manager, Technical Services

• S. Richards, Senior Resident Inspector, U. S. Nuclear Regulatory Commission

• Denotes attendance at exit interview conducted at Trojan Nuclear Plant'

on May 9, 198 . Onsite Review Committee This inspection performed a functional review of the-Onsite Review -

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Committee, normally called at Trojan the Plant Review Board (PRB). The inspector reviewed the PRB's composition, duties, and responsibilities as '

delineatedLin the Technical-Specifications (TS) Section 6.5.1. The inspector verified that the composition, duties, and responsibilities were as specified. The inspector examined the PRB to determine if they fulfilled their function in the following areast Review and. analysis of reportable events. requiring submission of a Licensed Event Report (LER). Investigation of violations of the TS and corrective action Review of current plant operations to detect potential nuclear safety hazard Review of proposals which could affect nuclear safety such as . plant '

tests or experiments, plant procedures, plans, programs, or changes thereto, and modifications to systems or equipmen t The inspector reviewed 13 PRB meeting minutes to determine whether the '

, PRB fulfilled their function. The examined PRB meeting minutes indicated that the PRB fulfilled-the function and that they performed the r,equired nuclear safety reviews for event reports, current plant operations, and -

plant proposal ,

l The inspector attended a PRB meeting on May 7,1986, at 1:00 p.m. During

! this meeting, the PRB members discussed current problems with the' steam

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generator snubbers, and their failure to operate properly and the

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resultant potential' effects on reactor coolant hot legs. ~ The inspector asked the PRB members to explain the plant's program for independent

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verification of tagouts and valve lineups. The PRB chairman indicated that an administrative order will be issued to perform independent verifications of tagouts and valve lineup to assure acceptable system configuration control in this are The licensee's PRB appeared to have acceptably administered its function in reviewing event reports, investigating violations of the TS, reviewing plant operation, and plant proposals. The licensee's PRB activities appeared to be conducted in accordance with the Technical Specifications, licensee-commitments, and regulatory requirement No violations or deviations were identified in this are . Quality Assurance Test and Measurement Equipment Program The inspector examined the licensee's subject program and its conformance with regulatory requirements,~ commitments, and industry standards. The inspection included a= verification that administrative controls for test and measurement equipment calibration / adjustment frequency have been established. Maintenance Procedure MP-2-2, " Portable Measuring and Test Equipment",. dated January 24, 1986, Revision 5, provides a procedure to ensure control and calibration of portable measuring and test equipment.

F (M&TE) at specific periods to maintain accuracy within prescribed limit Table 1 of MP-2-2 provided an' equipment' inventory list which identified the following: All' test and measurement equipment for safety-related structures, systems, or. component The calibration / functional check interval for each piece of equipmen The serial number and Trojan number for each piece of equipmen The inspector verified that formal requirements existed for marking the latest inspection / calibration'date on each piece of equipmen Procedure MP-2-2, Paragraph 6.4.8, " Calibration Stickers and Tags",

requires calibration stickers be placed on equipment calibrated by the Trojan I&C calibration laboratory. This label denotes that the instrument was fully and completely calibrated and met the approved specifications. The calibration sticker indicates date calibrated, date calibration due, and initial of person performing calibratio The inspector verified that a system has been provided to assure that each piece of equipment is to be calibrated and adjusted on or before the date required. Accordingly, Procedure MP-2-2, Paragraph 6.4.6,

" Calibration Schedule and Interval", required that the Instrument and Control (I&C) Department maintain a schedule for the M&TE covering both calibrations and functional check In general, M&TE is on a periodic calibration schedule, which is scheduled monthly by use of a computer syste The inspector verified that a written requirement, Procedure MP-2-2 prohibited the use of test and measuring equipment which has not been

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c calibrated'within the prescribed frequency. The procedure also described

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controls to prevent inadvertent use of such equipment. Procedure MP-2-2, Paragraph 2, " Responsibility", provided that users of M&TE ensure that a piece of M&TE is not used after its calibration due date and ensure that any malfunctions or suspected malfunctions are reported to the I&C test equipment technician promptly so that the equipment can be removed from service and repaired. The procedure MP-2-2 also describes that it is each supervisor's responsibility to ensure that each M&TE is made available for calibration prior to its due date. These controls ensure that M&TE is calibrated prior to use or put the equipment into the calibration program if out of calibratio The inspector verified that out-of-calibration controls were established which require when a piece of equipment is found 'to be out-of-calibration, the acceptability of items previously tested or measured will be evaluated and documente In addition, an evaluation of the cause of out-of-calibration will be performed. Procedure MP-2-2, Paragraph 6.4.9.8, " Test Equipment Out-of-Calibration Investigation",

described that an investigation shall be performed whenever M&TE is found: to exceed required calibration tolerance; or to have been subjected to possible damage; or to be non-functional. This action could be the result of an offsite calibration, onsite calibration, or other event. All equipment tested or calibrated using that M&TE since the last valid calibration shall be identifie The validity of these calibrations and tests should be determined, and if necessary, the tests and calit rations should be repeated using calibrated equipmen This procedure conducts an investigation or evaluation of the cause of out-of-calibratio The'inspec. tor verified that a formal system has been established to assure tha: new M&TE will be added to the inventory list and calibrated prior to bring placed in servic Procedure MP-2-2, Paragraph 6-1,

"Procuremes t and Acceptance of M&TE", describes the procurement process of M&TE as initiated by the plant supervisor for new purchases and replacement. purchases of worn nut or missing M&T The inspec:or performed a review of Trojan Nuclear Plant's measurement standards calibration data as maintained by the I&C Department. The eleven measurement standards reviewed were satisfactory in that the M&TE was mainta ined, calibrated, and issued in accordance with MP-2- No violations or deviations were identifie . Surveillance Procedures and Records This inspection was to determine whether the surveillance of safety-related systems and components was being conducted in accordance with approved procedures as required by the Technical Specifications (TS), In Service Inspection (ISI) and In Service Testing (IST) programs, and NRR approved fire protection / prevention program.

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The inspectors verified that Technical Specification surveillance tests on safety-related systems are written and approved in the following areas: Reactivity Control and Power Distribution, Reactor Coolant System, Emergency Core Cooling System, Instrumentation, Containment Systems, Plant and Electrical Power Systems, Fire Protection / Prevention-Systems, and IST progra In each area, at least three surveillance test procedures were examined to assure that prerequisites and preparations were specified, acceptance criteria for test specified, and return to normal instructions to ensure systems or components are restored to operatio In the Periodic Operating Tests (POTS), prerequisites, preparations, and equipment used in the tests are not explicitly written as they are detailed in the Periodic Instrument and Control tests. Engineering judgment is relied upon for the preparations and equipment used. In addition, some of the prerequisites are implied in the initial condition For the completed tests that were examined, the following attributes were verified: Tests were in conformance with TS, ISI program, and procedural requirements, Completed tests were reviewed as required by facility administrative requirement Tests were performed within the time frequencies specified by the TS.

l Corrective action was taken for any item failing acceptance

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criteria.

! Tests were performed by qualified individual The inspectors noted during their examination of Periodic Instrument and Control Test (PICT)-11-3, Rev. 8, dated October 2, 1984, entitled

" Nuclear Instrumentation, Source Range", records that the prescribed test, interval stated " weekly during power operation" and that no weekly data was observed. Examination of the Technical Specifications revealed no weekly test interval, requirement during power operation since source i range channels are normally deenergized. Upon questioning the licensee, j it was discovered that Rev. 6 and Rev. 7 had the phrase "if desired" inserted at the end of the test interval but that Rev. 8 had incorrectly L dropped the phrase "if desired" out of the procedure. The licensee initiated a change request to reinsert the phrase.

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l The licensee's Surveillance Procedures and Records appear to be conducted

! in accordance with approved procedures as required by the Technical Specifications, inservice inspection and inservice testing programs, and NRR approved fire protection / prevention progra No violation or deviations were identified in this area.

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5. -Exit Interview

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, The inspectors met with the licensee representatives denoted in paragraph

,, 1 on May 9, 1986, and sunenarized the scope and findings of the inspection activitie i.

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