ML20024B657
| ML20024B657 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/01/1983 |
| From: | Broehl D PORTLAND GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM TAC-44482, NUDOCS 8307110143 | |
| Download: ML20024B657 (3) | |
Text
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Donald J. Br W Assistant Vee President July 1, 1983 Trojan Nuclear Plant a
Docket 50-344 License NPF-1 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclet.r Regulatory Commission Washington DC 20555
Dear Sir:
TROJAN NUCLEAR PLANT NUREG-0737 Item II.B.3 (Post-Accident Samplina System) eac letter of June 28, 1983 r quested an extension of the date for which we had comunittsd to have this system fully operational. There were some tests that could not be accomplished until the Trojan Nuclear Picat was returned to power operation and an adequate inventory of radionuclides had accumulated in the Reactor Coolant System. However, the checkout of the system has now identified several other items which we feel should be clarified with you at the present time. For that reason, we have provided the attached list of items that affect the system end which we are in the process of resolving.
Except as noted on the attachment, the system has undergone a checkout of all aspects that can be accomplished for the present Plant status and has been found to be acceptable for these Plant conditions. Final preoperational testing and correction of problems that are discovered during power testing will be corrected as discovered. If you have questions regarding the status of the Post-Accident Sampling System, please do not hesitate to contact me.
Sincerely, Attachment c:
Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. John B. Martin Regional Administrator Nuclear Regulatory Cosuaission Region V 8307110143 830701 I[
-PDR ADOCK 05000344 p
PDR 121 SW Salmon Street. Portand. Oregon 97204
s-4 Trojan Nuclear Plant Robert A. Clark l
Docket 50-344 July 1,1983 -
License NPF-1 Page 1 of 2 TROJAN NUCLEAR PLANT Post-Accident Sampling System (PASS)
Items Identified Durinz Functional Testing Requirint' Resolution
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1.
The Liquid Sampling System radiation detectors have not been calibrated due to a shipping problem with General Atomics (GA) calibrator. These problems were caused by the GA calibrator being stranded at the Los Angeles airport.
Continued shipment of the calibrator to PGE was expedited. It is expected that the calibration will be completed by July 8, 1983.
'2.
The reacte counting equipment (ND-6 gmama analyzer) has not been cali-beated, due to a nonfunctioning amplifier. The vendor service represen-tative is working on the-problem now and estimates it will be two weeks
.for repair.
i 3.
A' particulate filter has been installed upstream of the silver zeolite iodine cartridge to prevent short-lived particulates from contaminating the silver zeolite. No provisions have been provided for analyzing the particulate filter.
4'
-Modifications to the inlet portion of the gas chromatograph to accommo-date the remote syringe handling tool still must be completed. This installation and checkout will.be complete by July 8, 1983.
- 5..Since sampling and analysis will be performed onsite, no provisions are provided for offsite transport of samples and their subsequent analysis.
6.
Two flow elements (FE5624 and FE5650) did,not. pass.the calibration tests. Nuclear Projects Engineering and the Trojan Plant Staff are work-ing on resolving the calibration problems. Also, the flow switch for FE5624 has malfunctioned and must be replaced.
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7.
Additional testing is required to confirm consistent sample analysis results with the Reactor Coolant Sampling System. Procedure changes should correct this problem. Further functional testing will confirm the results.
8.
The present provisions for temporary lighting in the hot lab, fume hood, and the reactor coolant liquid PASS control panel area are considered
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marginal. PGE will evaluate and provide improved lighting to those areas.
9.
There'are presently no provisions for additional Scott Air Pack air 4
bottles at Elevation 93 ft near the Containment-atmosphere panel. PGE will obtain additional air bottles for this use.
a 1
s Trojan Nuclear Plant Robert A. Clark Docket 50-344 July 1, 1983 License NPF-1 Page 2 of 2 10.
Additional training is required to improve overall PASS coordination and integration of-procedures and personnel to meet the 3-hour sampling time requirement following a decision.to take a sample. This training will be
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completed upon completion of the functional test at power.
11.
The CCW System operating procedure is being required to specifically identify steps necessary to valve in the nonsafety-related portion of the CCW System to supply cooling water to PASS following a safety injection signal. The revisions will be completed by July 8, 1983, 12.
The second transport shield cask for the undiluted RCS sample is now being fabricated and will be available by Plant startup. This cask is not necessary to meet the 3-hour time requirement for the diluted ECS sample.
13.
The RCS PASS panel operating procedures are being refined and improved.
Recent changes to the procedures will be incorporated into panel overlay cards that can be used by the chemistry technicians for taking RCS sem-ples. These programmed cards sequence the procedural steps to prevent mistakes and improve time required for sampling. We expect to have these cards in place upon completion of the functional testing at power.
14.
Minor miscellaneous items to the control panels, such as control valve lights and mimic graphic displays, need to be upgraded to reflect system modes during testing.
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l DJB/JWL/GAZ/4sf 6216G.683 l
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