IR 05000344/1982017
| ML20054L595 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/14/1982 |
| From: | Johnson P, Zwetzig G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20054L593 | List: |
| References | |
| 50-344-82-17, NUDOCS 8207080278 | |
| Download: ML20054L595 (3) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No. 5,0-344/82-17 Docket ilo. 50-344 License flo. NPF-1 Safeguards Grouo Licensee:
Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Name: Trojan Inspection at:
Rainier, Oregon Inspection conducted: May 25-28, 1982
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Inspector:
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Date Signed P.H.Jyhnson,ReactorInspector L
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Approved by:
_. Zs iig,QCh\\jef, Reactor Protects (/
Date ' Signed i
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G. Section 1, Reactor Operations Project Branch Summary:
Inspection on May 25-28, 1982 (Report No. 50-344/82-17)
Areas Inspected:
Routine, una,4nounced inspection of requalification training and design changes and modifications. The inspection involved 23 inspector-hours onsite by one NRC inspector.
Resul ts: No noncompliance items or deviations were identified.
l 0207080278 820615 PDR ADOCK 05000344 G
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DETAILS
1.
Persons Contacted
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- R. P. Barkhurst, Manager, Operations and Maintenance
- A. S. Cohlmeyer, Engineering Supervisor
- P. Morton, Quality Assurance Supervisor
- C. A. Olmstead, Manager, Technical Services
- J. D. Reid, Manager, Plant Services
- R. P. Schmitt, Prosnective Manager, Technical' Services
- M. R. Snook, Senior Quality Assurance / Quality Control Inspector
- R. E. Susse, Training Supervisor
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l The inspector also interviewed other licensee emnloyees during the course of the inspection. These ircluded nuclear plant engineers, shift supervisors, licensed operators, and training assistants.
- Present at exit interview.
2.
Design, Design Changes, and Modifications Selected design changes were examined for proper review and approval, a
adherence to established procedures, evaluation of test results, and updating of appropriate procedures.
Each Request for Design Change (RDC)
had been developed into one or more Detailed Construction Packages (DCPs).
Design changes selected for examination were as follows:
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RDC 76-520, Waste Gas Compressor Modification RDC 77-056, New Safety Injection Reset Switches
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RDC 79-092, Containment Pressure Indicators / Recorder
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RDC 79-105, Containment Post-Accident Sampling System (inspection of this RDC not completed)
This insoection activity will be comoleted during a future inspection.
No noncompliance items or deviations were identified.
3.
Recualification Training i
The licensed coerator requalification training program was inspected
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against the requirements of 10 CFR 50.54.1-1 and 10 CFR 55, Appendix A.
The licensee's program was defined in Training Procedure TP-2-2, Revision 8, which was submitted to the Onerator Licensing Branch for review in July 1980. This inspection of reaualification training included discussions with training personnel, one shift supervisor, and two licensed operators, and examination of the following documents:
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Requalificationtrainingscheduleandattendancerecords,l
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1982 cycle.
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Selected lesson plans.
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1982 examinations and results.*
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Documentation of additional training required for one reactor operator.
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Simulator training and reactivity manipulation records.*
Annual performance evaluations.*
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Oral examination records.*
The training supervisor stated that a major rewrite of lesson plans was being conducted by two consulting firms, and was expected to be ccmpleted later in 1982. No training lectures were given during the period of the inspectio.., so none were observed by the inspector.
No noncompliance items or deviations were identified.
4.
Exit Interview The inspector (and Senior Resident Inspector) net with licensee representatives (denoted in paragraph 1) at the conclusion of the
inspection. The inspection findings of paragraphs 2 and 3 were discussed.
- For selected individuals.
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