ML20212Q432

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Discusses NRC & Safety Evaluation Re Compliance W/Reg Guide 1.97.Mod of Quench Tank Temp Instrumentation Will Be Completed by End of 1988 Refueling Outage
ML20212Q432
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 01/26/1987
From: Lindblad W
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-51362, NUDOCS 8702020256
Download: ML20212Q432 (2)


Text

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a PORTLAND GENEHAL ELEcTurc COMPANY 123 S W. S ALM O N STREET WILLIAM J. LIN D B LAD PO RTLAN o. O R EGO N 972C4 1503)226-8875 January 26, 1987 Trojan Nuclear Plant Docket 50-34A License NPF-1 U.S. Nuclear Regulatory Commission ATTN: -Document Control Desk Washington DC 20555

Dear Sir:

Regulatory Guide 1.97 Review By letter dated September 29, 1986, your staff transmitted its safety evaluation (SE) of PGE's Regulatory Culde (RG) 1.97 submittal and subse-quent transmittal of additional information requested by the EC&G Idaho, Inc. review of the submittal. The SE concluded that ". . .the instrumenta-tion which PGE provided for meeting the recommendations of RG 1.97 is acceptable, except for the variables quench tank temperatures and neutron flux". These instruments were requested to be upgraded in accordance with RG 1.97 Revision 2, and be operational no later than s'c artup following the second refueling outage after receipt of your letter. An additional request was made to inform your office, in writing, of any significant changes in the aforementioned schedule.

With respect to compliance with RG 1.97, PGE has committed to Revision 3 not Revision 2. This does not affect the instruments to be upgraded; however, we wish to remain consistent with our previous commitment to Revision 3 in our original submittal dated December 28, 1984.

The quench tank temperature instrumentation will be modified to meet the extended range of at least 50*F to 338'F as requested. This modification will be completed by the end of the 1988 refueling outage.

Our estimated completion schedule for adding the required second channel of Category 1 neutron flux instrumentation is by the end of the 1990 refueling outage based on the following considerations:

a. The first channel was the easiest to install. Its design took advanterge of the most accessible train in terms of cable routing, power supply, rack location, and instrument well. The second channel will be harder to design and install.

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4 PORTLAND GENERAL ELECTRIC COMPANY Document Control Desk January 26, 1987 Page 2

b. One fully qualified channel of neutron monitoring has been installed and will be operational by the end of the 1987 refueling outage. This fully qualified neutron monitoring channel, coupled with the existing control rod position indication and RCS soluble boron concentration monitoring, provides sufficiently diverse means to monitor neutron flux for all types of accidents, pending installation of a second fully qualified channel.

With a commitment to a second channel, we intend to make all connections to the TSC computer and EOF at that titte. Recording of neutron flux indication will also be provided as part of the installation of the second channel.

Sincerely.

c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Cormnission Mr. Gary Kellund Resident Inspector Trojan Nuclear Plant Mr. David Kish, Acting Director State of Oregon Department of Energy l

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