IR 05000344/1998201

Insp Rept 50-344/98-201 on 980223-26.No Violations Noted. Major Areas Inspected:Safety Review Program & Insp follow- Up

ML20217L065
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/29/1998
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217L062	List: IR 05000344/1998201 ML20217L057
References
50-344-98-201, NUDOCS 9805040284
Download: ML20217L065 (6)

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U. S. NUCLEAR REGULATORY COMMISSION

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OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-344 l

License No: NPF-1 i

Report No: 50-344/98-201 Licensee: Portland General Electric Company Facility: Trojan Nuclear Plant .

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Location: 121 S.W. Sa! mon Street, TB-17 Portland, Oregon Dates: February 23-26, 1998 Inspectors: Lee H. Thonus, Project Manager John Minns, Project Manager Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation

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t 9805040284 980429 PDR ADOCK 05000344 0 PDR

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EXECUTIVE SUMMARY This routine, announced inspection consisted of evaluation of the licensee's safety review program and review of corrective actions previously committed to by the licensee, and related discussions with licensee personnel. The inspection was conducted following the l guidance of the NRC Inspection Manua *

The licensee's safety review, design change, and modification programs; including training, procedural controls, and safety reviews were found to be acceptabl .

The licensee had satisfactorily implemented corrective actions related to a previously identified violation in the area of safety review; this item is closed (344/96003-01).

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Report Details Summary of Plant Status Decontamination and dismantlement of the facility continued. The licensee had completed construction of the Independent Spent Fuel Storage Installation (ISFSI) with the exception of the cask transfer statio Safety Review Program (37801)

01.1 Administrative Controls a. Insoection Scone

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The inspector reviewed the licensee's administrative control procedures for training and certification of reviewers, control of plant work activities and plant modifications, and implementation and control of the safety review process,

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b. Observations and Findinas PGE procedures TPP 14-4 " Decommissioning Work Control Process," Revision 0, dated September 23,1996, and TPP 14-3 " Work Control Process", Revision 11, dated May 1,1995, are used to initiate work activities and decommissioning work activities in the plant. The inspector found that these procedures contained sufficient guidance to cause an individual to initiate implementation of TPP 1 i

"10 CFR 50.59 and Other Regulatory Evaluations"in those cases where it was warranted. The inspector also found that TPP 30-5 "Defueled Plant Modification implementation," Revision 5, dated May 5,1997, contained sufficient guidance to initiate implementation of TPP 18.1, for plant modification activities if warrante TPP 18-1'"10 CFR 50.59 and Other Regulatory Evaluations," Revision 7, dated

! April 16,1997, contained PGE guidance and requirements for initial screening of proposed activities to determine if a more detailed review was required. TPP 18-1 also contained PGE guidance and requirements for performing r(views in support of:

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1) Changes, tests, and experiments authorized by 10 CFR 50.59 and/or 10 CFR 72.48 2) Changes, tests and experiments authorized by license NPF-1, Appendix B, Section ) Changes to the Emergency Plan l

4) Changes to the Security Plan j 5) Changes to the Decommissioning Plan t

6) _ Changes which affect the Fire Protection Plan

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7) Changes which affect the Radiological Environmental and Effluent Monitoring Plan 8) Changes which affect the Environmental Report l l

TPP 18-1 provided adequate and appropriate guidance on unreviewed safety question determinations and on activities which would require NRC review prior to implementation. TPP 18-1 additionally provided licensee requirements for those activities requiring review and approval by the Oregon Office of Energy and the Oregon Energy Facility Siting Council. TPP 18-1 promulgates the training and certification requirements for qualified evaluators, independent reviewers, and independent safety reviewers and delineates which review activities each can perform. TPP 18-1 references TPP 10-9 " Trojan Nuclear Plant and Trojan ISFSI Independent Safety Reviewer Charter"(currently revision 6, dated April 24, 1997). l TPP 10-9 contains PGE's qualification process for independent safety reviewers and the requirements and guidelines for the independent safety review and approval proces c. Conclusions PGE's work control process contained sufficient guidance to initiate the safety review process when appropriate. PGE's safety review system and processes provided an adequate framework for personrel to properly complete safety review .2 Safety Review Trainina a. Insoection Scone The inspector reviewed the lesson plans, training materials, and training records, for training and retraining of evaluators, independent reviewers and independent safety reviewers. The inspector also reviewed the certification /recertification program for independent safety reviewer b. Observations and Findinos Training requirements for evaluators, independent reviewers, and independent safety reviewers were specified in TPP 18-1 and TPP 10-9. The PGE training department's lesson plans for safety review training were thorough and well organized. The training department had updated the training materials to replace NSAC (Nuclear Safety Analysis Center) 125 " Guidelines for 10 CFR 50.59 Safety Evaluations" with l NEl (Nuclear Energy Institute) 96 07 [ Revision 01 " Guidelines for 10 CFR 50.59 Safety Evaluations" since the previous NRC inspection in this area. PGE also uses j 10 CFR 50,10 CFR 72, and plant procedures as training materials. The inspector found that the training materials were appropriate and up to date. The safety review training included a written examination.

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c. Conclusions The licensee's safety review training program was thorough, appropriate, well-thought and effectiv .3 Screeninos and Safetv Evaluations a. Insoection Scone The inspector selected for evaluation 12 work activities for which the licensee's screening process had indicated that safety reviews were not required. Additionally, 14 licensee safety evaluations were selected for revie b. Observations and Findinas The screening level safety review of the 12 work activities had been appropriate, and ,

correctly indicated that these activities had not required an additional full scope l safety review. The inspector also reviewed 14 safety reviews that had been I performed in accordance with the licensee's procedures and found that the reviewers had reached appropriate conclusions. The inspector observed that the evaluators, independent reviewers, and independent safety reviewers who had participated in the evaluation and review process were all qualified and their training was curren i The content of the evaluations included appropriate analysis and justification for the conclusions reached. The documentation had been properly completed in each cas c. Conclusions PGE's safety review program had been properly implemented and the safety reviews had been properly performed and documented by qualified individual l

2 Inspection Follow-up (92702)

(Closed) Violation 50-344/96003-01: Expired safety reviewer qualifications. The licensee modified the database system which tracks safety reviewers to provide a warning prior to expiration of an individual's qualifications, to provide a double check of the qualification list, and to provide written notification to reviewers and their supervisors of qualification expiration dates. The licensee also modified TPP 18-1 to include a line where the reviewer must indicate their qualification expiration date just below space for the date that the evaluation is performed. The inspector examined 14 safety reviews in conjunction with the current list of qualified reviewers and verified that the evaluations, independent reviews and independent safety reviews had been performed by individuals with current qualification Exit Meeting The inspector presented the inspection results to members of licensee management at j the conclusion of the inspection on February 26,1998. The licensee acknowledged the j findings presented. No material examined during the inspection was identified as

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PARTIAL LIST OF PERSONS CONTACTED Licensee C. Brown, Training

, M. Gatlin, Nucleer Security l D. Gildow, Engineering M. Lackey, Engineering / Decommissioning T. . Meek, Radiation Protection J. Mihalich, Engineering l- D. Nordstrom, Nuclear Oversight

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R. Pate, Ucensing J. Reid, Quality Assurance

S. Schneider, Operations

! J. Vingerud, Maintenance

P. Yundt, Plant Support NRC J. Minns, Project Manger L. Thonus, Project Manager Oreann Office of Enerav A. Bless, Resident inspector INSPECTION PROCEDURES USED IP 37801 Safety Reviews, Design Changes, and Modifications at Permanently Defueled Reactors IP 92702 Follow-up On Corrective Actions For Violations ano leviations ITEMS OPENED, CLOSED, AND DISCUSSED Opened None

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Closed 50-344/96003-01 VIO expired qualification of safety reviewer Discussed None

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