IR 05000344/1986039

Insp Rept 50-344/86-39 on 861020-24.No Violations or Deviations Noted.Major Areas Inspected:Mod Program,Ie Bulletins,Generic Ltr Followup & Cold Weather Preparations

ML20213H029
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	11/04/1986
From:	Mendonca M, Pereira D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20213H021	List: IR 05000344/1986039 ML20213H019
References
50-344-86-39, IEB-79-24, IEB-86-002, IEB-86-2, NUDOCS 8611190036
Download: ML20213H029 (4)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report N /86-39 Docket N License N NPF-1 License: Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Name: Trojan Nuclear Plant Inspection at: Rainier, Oregon Inspection Conducted: 'Deto r 20 4, 1986 Inspector: #d 62/// // Y [d D. B. Pereira, Reactor Inspector Date Signed Approved By: % \ D" " /V/PG M. M. Mendonca, Reactor Project Section 1 Date Signed Summary:

Inspection During the Period of October 20-24, 1986 (Report No. 50-344/86-39)

Areas Inspected: Routine, unannounced inspection of the Facility Modification Program, IE Bulletin, Generic Letter followup, and cold weither preparation The inspection modules followed were: 71714, 92703, 30703, and 37701.

l Results: No violations or deviations were identified.

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I B611190036 861104 PDR ADOCK 05000344 G PDR

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DETAILS Persons Contacted

• S. Orser, General Manager

• R. P. Schmitt, Manager, Operations and Maintenance J. D. Reid, Manager, Plant Services D. W. Swan, Supervisor, Maintenance D. L. Bennett, Supervisor, Control and Electrical R. Reinart, Supervisor, Instrumentation and Control

• G. C. Kellund, Resident Inspector, U. S. Nuclear Regulatory Commission H. Moomey, Senior Resident Inspector, Oregon Department of Energy A. S. Cohlmeyer, Engineering Supervisor

• Denotes attendance at exit interview conducted at Trojan Nuclear Plant on October 24, 1986. Facility Modifications The facility modification program was reviewed for conformance with Technical Specifications, regulatory requirements, requirements in the facility license, 10 CFR, and applicable codes and standards to which the facility was built. Facility modifications were examined to ensure that applicable industry codes and standards were used. The applicable regulatory guides and the licensee's QA program were ~ reviewed by the inspector to ensure compliance for the modification The inspector reviewed the following plant facility modifications: Plant Design Change (PDC)84-008 - Provided verification of fuse type and size, and replacement of improper fuses where require PDC 84-021 - Provided individual circuit blown fuse indication for freeze protection systems for the main steam pressure transmitters, auxiliary feedwater flow indication, and reactor vessel level indicating system pressure transmitter located in the Main Steam Support Structur PDC 83-054 - Provided environmentally qualified disconnects on solenoid valves for the containment hydrogen analysis system sampling valves and reactor vessel head vent valve PDC 83-053 - Modified the start circuitry on the emergency diesel generator to block any high crank case pressure signal immediately on receipt of an AUTO START signa PDC 83-043 - Reinstalled the pressurizer level transmitter upper sensing lines, formerly unreliable due to improper installation of the reference leg condensing pot PDC 83-004 - Provided for train separation for wide-range pressure transmitters PT-403 and PT-405, and associated input ^

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2 PDC.82-063 - Provided the necessary design change'to ensure the condition'of the trip and throttle valve, MO-3071,'on the turbine-driven auxiliary feedwater pump is alarmed if abnorma PDC 85-013 - Installed a splash guard plate between the emergency, diesel generator engine crank case pressure detector and the engine housing per the manufacturer's recommendation; PDC 81-075 - Revises the smoke detec' tor system in. containment and in the Electrical Penetration Area.< Lic'nse.e Change Amendment-must ' be

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received before Containment Detdctors U18A, B and U19 may be

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disconnected from KZIU6- ~

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The inspector verified that the above facility modifications were installed.in accordance with the approved design by examinin installation records and inspection records of-the' licensee's QA progra The inspector examined the revised procedures to ensure they were completed and approved in accordance with Technical Specification (TS),

requirements. The. inspector examined the modifications completed test documentation'to ensure that the licensee conducted a review an3 evaluation of test results, that the test results were within established acceptance criteria, and test deviations'w'ere resolved-and retesting

, accomplished as necessary. Finally, the inspector verified that the as-built drawings were revised to reflect the modificatio No violations or deviations were identified in this are . Cold Weather Preparations This inspection is to determine whether the licensee has maintained an

, effective implementation program of protective measures for extreme cold

weather. IE Bulletin, 79-24, dated September 27, 1979, requested licensees to review their plants to determine that adequate protective measures have been taken to assure that safety-related process, instrument, and sampling lines do not freeze during extremely cold weather. The. inspector conducted a walk-down of the main steam support structure and the refueling water storage tank. In the main steam

, support structure, the main steam line.and flow instrumentation have heat tracing circuits and are energized. The inspector noticed that in FACADE

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I Freeze Protection Circuit Breaker Box that circuit breaker #17 was tripped. The inspector notified the control room operators who sent an operator to reshut-breaker #17. The inspector examined that the main l steam and flow instrument lines were insulated where necessary and that heaters were installed in the spaces needing heat.

! The inspector examined the refueling water storage tank level ( instrumentation and verified that they were heat traced and energize The licensee was also conducting a cold weather preparation walkdown ;

during the week of this inspection. The licensee's examination appeared to be. thorough and extensiv No violations or deviations were identified in this are a

. .o (Follow-up Item IE Bulletin 86-02 Closed) Static "0" Ring Differential Pressure Switches IE Bulletin 86-02 was issued on July 18,.1986, and requested pressurized water reactor (PWR) licensees to determine whether or not they have Series 102 or 103 differential pressure switches supplied by SOR, Incorporated (formerly Static "0" Ring Pressure Switch Company).

The licensee's letter of July 28, 1986, provided a complete response to the IE Bulletin 86-02 in that SOR Model 102 or 103 differential pressure switches are not installed, or planned to be installed in safety-related or important-to-safety equipmen IE Bulletin 86-02 is considered close . Exit Interview The inspector met with the licensee representatives denoted in paragraph 1 on October 24, 1986, and summarized the scope and findings of the inspection activitie E s

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