ML19350B658
| ML19350B658 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/30/1981 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.1, TASK-TM IEB-79-01B, IEB-79-1B, NUDOCS 8103230204 | |
| Download: ML19350B658 (3) | |
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Ban D wmers Vce Prescent January 30, 1981 Trojan Nuclear Plant Docket 50-344 License NPF-1 g
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Mr. R. H. Engelken, Director N
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Dear Mr. Engelken:
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Supplement No. 3 to IE Bulletin 79-01B, dated October 24, 1980, clarified two issues raised by Supplement No. 2 regarding (1) the submittal of qualification information for equipment resulting from TMI Action Plan requirements and (2) the qualification of equipment which is required to achieve a cold-shutdown condition. Our response to these two items delineated in Supplement No. 3 is as follows:
1.
The minimum equipment needed to complete one method of achieving and maintaining a cold-shutdown condition is either already included in our previous submittals on IE Bulletin 79-01B or is located in a nonharsh environment.
This determination was based on an identification of the minimal essential equipment needed to achieve cold shutdown following an accident (LOCA or HELB) assuming no random single failures, loss of offsite power, or seismic event.
This, in our view, meets the intent of the " enveloping staff position" as explained in the NRC's information letter of January 19, 1981 (Generic Letter 81-05) from D. G. Eisenhut to licensees.
2.
The submittal status of qualification information for IMI Action Plan (NUREG-0737) equipment is as follows:
121 SW Satmon St'eet. Portand. Oregon 97204 810323 0 6ng 4
Portland General ElectricCompany Mr. R. II. Engelken January 30, 1981 Page two a.
Qualification information for installed NUREG-0737 equipment has already been included in our IE Bulletin 79-01B submittals of September 5, 1980 and January 13, 1981. Equipment in this category, which corresponds to Category (2)a in Supplement No. 3, includes:
II.D.3, Direct Indication of Relief and Safety Valve Position; and II.F.2, Primary Coolant Saturation Monitors.
b.
Qualification information for NUREG-0737 equipment not yet installed, which does not require preimple-mentation review for installation, will be submitted to the NRC for review by the installation date as follows:
II.B.1, Reactor Coolant System Vents (July 1, 1982);
II.B.3, Post-Accident Sampling Capability (January 1, 1982);
II.E.1.2 (Part 2), Auxiliary Feedwater System Flowrate Indication (July 1, 1981);
II.F.1.3, Containment High Range Radiatic' Monitors-(January 1, 1982);
II.F.1.4, Containment Pressure Monitors
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(January 1, 1982);
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II.F.1.5, Containment Water Level Moni-l tors (January 1, 1982); and II.F.2, Reactor Vessel Level Instrumenta-tion System (January 1,1982).
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Picase note that this category basically corresponds so Category (2)d in Supplement No. 3.
We could not identify i
I any future NURF'~0737 equipment in Categories (2)b or (2)c l
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a mmm Mr. R. H. Engelken January 30, 1981 Page three (in Supplement No. 3) which requires NRC preimplementation reivew prior to installation or which is currently under h3C preimplementation review.
Sincerely, filWa. m Bart D. Withers Vice President Nuclear c:
Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission I
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