ML20042C070
| ML20042C070 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/26/1982 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.4.2, TASK-2.F.1, TASK-TM GL-81-29, GL-82-05, GL-82-5, P-82092, NUDOCS 8203300138 | |
| Download: ML20042C070 (3) | |
Text
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public Servlee Company cf Odarado V8 '
16305 WCR 19 1/2, Platteville, Colorado S0651
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March 26, 1982 g
L Fort St. Vrain MAR 2 91982*
Unit #1 yM P-82092
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.s Mr. Darrell G. Eisenhut, Director N '*
Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
Fort St. Vrain Unit No. 1 Post TMI Requirements
REFERENCE:
Dear Mr. Eisenhut:
In accordance with the above referenced letter, pleae
-ind attached our response to those items that are applicable to Fo-St. Vrain.
Very truly yours, h W n%nl Don W. Warembourg Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station DW/skd Attachment cc:
Bob Clark G. Kuzmyc:
John Collins (Region IV)
Oh t
i 8203300138 820326 PDR ADOCK 05000267 6I (
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., Attachment 1 NUREG 0737 Items Requiring Licensee Response P-82092 Item 1.A.3.1 Simulator Exams As you are aware, Fort St. Vrain is in a very unique position concerning simulator examinations in that we have no site specific simulator and we have no generic simulator that we can utilize.
We originally appealed to the Commission in December, 1980 (see P-80443) for relief from simulator training and in a letter form Dr. Hendrie dated April 2, 1981 we were advised to wait until proposed rule changes to 10CFR55 were issued.
Subsequently, we received NRC Generic Letter 81-29 requesting simulator examination schedules, and in our response (see P-81209) we informed the NRC Division of Human Factor Safety of our position.
In response to our letter, P-81209, we received a request for additional information from the Division of Human Factors Safety in a letter, dated October 7, 1981.
On December 3,
1981, we met on site with our NRC Project Management, ORNL, and the Emergency Preparedness Group wherein the subject of simulator examinations was discussed.
As l
recorded in NRC's letter of December 23, 1981 under Item 1.A.3.1 further action was outlined to resolve this issue.
Subsequent to this meeting, PSC has been investigating various alternatives to a full scope site specific simulator.
Our investigation and our immediate plans are set forth in our letter P-82067 dated March 12, 1982.
As indicated in this letter, we are not in a position, at this time, to provide you with a firm program or firm schedule.
, Item II.B.2 Plant Shielding Item II.B.3 Post Accident Sampling We believe we are in compliance with these items.
As recorded in NRC's December 23, 1981 letter, ORNL has been charged with a review of source term calculations.
As indicated in ORNL's report dated March 16, 1982, ORNL has requested additional information from the NRC.
Pending ORNL's review we cannot offer any further specific information.
Item II.B.4 Training for Mitigating Core Damage Although we are reviewing and developing some additional items involving management decisions, we believe we are in full compliance.
NRC's December 23, 1981 letter is not very specific in this area, but we are not aware of any further action requirements.
Item II.E.1.2 Aux Feedwater As indicated in NRC's letter of December 23, 1981 this item is not applicable to Fort St. Vrain.
Item II.E.4.2 Containment Isolation As indicated in NRC's letter of December 23, 1981, PSC is in compliance.
Item II.F.1 Accident Monitoring This item is still under review by ORNL. We believe we are in compliance.
See comment under II.B.2 above.
Items II.K.2.10, II.K.3.15, II.K.3.19, II.K.3.22, II.K.3.24, and II.K.3.27 are not applicable to Fort St. Vrain.
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