ML19259D699
| ML19259D699 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 10/12/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-6577, NUDOCS 7910260263 | |
| Download: ML19259D699 (2) | |
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e-g DAIRYLAND POWER COOPERATIVE Sa Grone, QVhconda S4601 October 12, 1979 In reply, please refer to LAC-6577
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DOCKET NO. 50-409 Mr. James G. Keppler Regional Director U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 IE BULLETIN NO. 79 SEISMIC ANALYSES FOR AS-BUILT SAFETY RELATED PIPING S*ZSTEMS
Reference:
(1)
NRC Letter, Keppler to Linder, dated July 2, 1979; Revision 1 dated July 18, 1979; with Supplement 1 dated August 15, 1979 and Supplement 2 dated September 7,'1979.
(2)
DPC Letter, LAC-6492, Linder to Keppler, dated September 5, 1979.
(3)
DPC Letter, LAC-6543, Linder to Keppler, dated October 4, 1979.
Dear Mr. Keppler:
The La Crosse Boiling Water Reactor has just completed an unscheduled cold shutdown which allowed us to complete the actions required in Reference 1.
In response to Item 3 of the subject bulletin, the following informa-tion is presented:
..... inspect all other normally accessible safety-related systems....."
All normally accessible piping had been inspected and reported in Reference 3.
..... inspect...all normally inaccessible safety-related systems."
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. OcTl'81978 7910260 E rI
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Mr. James G. Keppler LAC-6577 Regional Director October 12, 1979 All piping 2 inches and greater in diameter of safety related systems in normally inaccessible systems has been inspected in response to Reference 1, except a portion of piping in two normally inaccessible areas.
The results of the inspection have been compared to the as-built drawings and no discrepancies nor deviations from the',
as-built drawings exist.
The piping in the two normally inaccessible areas that was not in-spected during this unscheduled outage is steam piping in the upper part of the reactor vessel cavity, and alternate core spray piping in the reactor vessel head cavity.
The steam piping has been in-spected during the course of the ISI program and no deviations from as-built drawings exist.
The alternate core spray piping has been examined twice under the ISI program and no deviations from as-built drawings exist for this piping either.
The inspected areas were the same as those stated in Reference 3.
All of the above information will be utilized in the seismic analysis input information in accordance with the commitment in Reference 2.
This completes our actions with regard to the subject bulletin as there are no non-conformances to be identified under Item 4.
If there are any questions regarding this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL: HAT:af cc:
Director, Office of Inspection and Enforcement Office of Nuclear Reactor Regulation Washington, D. C.
20555 Director, Division of Operating Reactors Office of Naclear Reactor Regulation Washington, D. C.
20555
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