ML19247B282
| ML19247B282 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/20/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| NUDOCS 7908080299 | |
| Download: ML19247B282 (4) | |
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NUCLEAR REGULATORY COMMISSION
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' JULY 2 0 1979 Dockat No. 50-409
.dr. Frank Linder General Manager Lair" land Power Cooperative 2ui$ East Avenue South La Crosse, Wisconsin 54601
Dear Mr. Linder:
RE: LA CROSSE We are reviewing your submittals dated April 27, May 2, May 23, and May 29, 1979, in response to IE Bulletin 79-08. We have determined that the additional informat:on requested in the enclosure is necessary in order to conplete our safety evaluation.
We request that responses to the items in the enclosure be forwarded co this office within two weeks of your receipt of the enclosure, which was previously transmitted to you by telecopy. Please contact William F. Kane at (301) 492-7745 if you require additional discussions or clarification regarding the information requested.
i ncerely, T
Dennis Zienann, C ief Operating Reactors Branch 42 Division of Opera' 'ng Reactors
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page r.
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Mr. Frank Linder CC Fritz Schubert, Esquire Staff Attorney Dairyland Power Cooperative 2615 East Avenue South La Crosie, Wisconsin 54601
- 0. S. H!istand, Jr., Esquire Morgan, Lewis & Bockius 1800 M itreet, N. W.
Washing ;on, D. C.
20036 Mr. R. Z. Shimshak La Crosse Boiling Water Reactor Dairyland Power Cooperative P. O. Box 135 Genoa, Wisconsin 54632 Coulee Region Energy Coalition ATTN: George R. Nygaard P. O. Box 1583 La Crosse, Wisconsin 54601 La Crosse Public Library 800 Main Street La Crosse, Wisconsin 54601 h il F'
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Enclosure LACROSSE REQUESTS FOR ADDITIONAL INFORMATION IEB 79-08 Item No. 2 1.
Verify that initiation of containment isolction of the following lires or systems (reported in your response to Item 7) occurs simultaneous with or prior to all initiations of safety injection:
. Retention Tank Pump Discharge Line
. Decay Heat Blowdown Lines Main Steam System
. Reactor Building Ventilation System Provide justification for not isolating these lines or prepare and implement the necessary changes to isolate these lines as required by the Bulletin.
2.
Prepare and implement all necessary procedural and design changes required to conform to Item No. 2 of IEB 79-08 and provide the schedule for completion of these actions.
Item No. 4 1.
Clarify your response to indicate whether operators have been instructed to utilize other available information to initiate safety systems. Pro-vide your schedule for completion of this action.
Iten No. 5 1.
Your response to item Sa and 5b does not address training instructions Amena your response to address this matter.
2.
Your response to item Sa is incomplete.
Your review of operating procedures and training instructions should assc a that operators are directed not to override automatic actions of engineered safety features
.... (e.g., vessel integrity). Amend your response to -lari fy this point.
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. 3.
It is not clear from your response whether your review of operating procedures and training instructions with respect to the actions directed by item 5b included additional information and instructions to operators to not rely upon vessel level indication alone for manual actions but to also examine other plant parameter indications in evaluat-ing plant conditions. Amend your responsa to clarify this point.
4.
Provide a schedule for any actions on item 5 that have not yet been compl eted.
Item No. 6 1.
Your response did not clearly indicate that all accessible safety-related valves had been inspected to verify proper position.
Nor was a schedule for performing the positica verification for all safety-related valves provided.
Please supplement your response to provide this information.
Item No. 7 1.
Discuss how assurance is achieved for oreventing inadvertent transfer of radioactive gases and liquids on resetting of engineered safety features.
2.
Provide your schedule for completion of the study regarding the basis upon which continued operability of the features designed to prevent inadvertent transfer of radioactive liquids and gases from primary containment.
Item No. E 1.
We understand from your response that operability tests are performed on redundant saiety related systems prior to removal of any safety related system from service.
Since you may be relying on prior operability verification within the current technical specification surveillance interval, operability should be further verified by at least a visual check of the system status to the extent practicable, prior to removing the redundant equipment from service.
Please supplement your response to provide a commitment what you will revise your maintenance and test procedures to adopt this position.
2.
It is not clear from your response that all involved reactor operational personnel in the oncoming shift are explicitly notified about the status of systems removed from or returned to service.
Please indicate hoa thic information is transferred at shift turnover.
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