ML19291B943
| ML19291B943 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/11/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| LAC-6688, NUDOCS 7912140416 | |
| Download: ML19291B943 (3) | |
Text
..
f IRAIItYLANib I*0 Welt C00f*EIRATIVE Ba Crone, 0)'scondu i
04601 December 11, 1979 In reply, please re fe r to LAC-6 6 88 DOCKET NO. 50-409 U.
S.
Nuclear Regulatory Commission ATTN:
Mr. Dennis L.
Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors Washington, D.
C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING HATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 RESPONSE TO MICHELSON'S CONCERNS
REFERENCES:
(1)
NRC Letter, Ziemann to Linder, Dated October 18, 1979.
(2)
"La Crosse Boiling Water Reactor Safeguards Report," ACNP 65544, August 1967.
(3)
" Description of Post-Accident Safeguards Prov13 ions for the LACBWR, " ACNP-66564, Amendment No. 29 to CAPR-5, September 1966.
(4)
" Additional Information on the La Crosse Boiling Water Reactor," ACNP-66572, Amendment No. 30 to CAPR-5, October 1966.
(5)
" Technical Evaluation, Adequacy of La Crosse Boiling Water Reactor Emergency Core Cooling System," Report SS-942, Gulf United Nuclear Corporation, May 31, 1972.
(6)
" Response to Questions by AEC/DL With Regard to Gulf United Report SS-942, Technical Evaluation, Adequacy of La Crosse Boiling Water Reactor Emergency Core Cooling System,"
Report SS-1075, Gulf United Nuclear Corporation, April 30, 1973.
1580 179 1-7910] 4 o qL/g
Mr. Dennis L.
Ziemann, Chief LA7-6688 Operating Reactors Branch #2 December 11, 1979 Gentlemen:
Your request for a review of the concerns expressed by C.
Michelson, ACRS consultant (Reference 1) has been reviewed and our status as regards each enclosure is as follows:
Enclosure A The concern is not applicable as it addressed Combustion Engineering System 80 Pressurized Water Reactor designs.
LACBWR is a boiling water reactor and the concerns addressed do not apply to this design.
Enclosure B The concern is not applicable as it addressed Babcox & Wilcox 205 FA Pressurized Water Reactor.
LACBWR is a boiling water reactor and the concerns addressed do not apply to this design.
Enclosure C The concern addressed the isolation of Boiling Water Reactor forced circulation loop pipe breaks following partial blowdown.
The LACBWR plant high pressure ECCS (High Pressure Core Spray System) includes an individual spray line for each fuel assembly.
Analyses reported by References (2) thru (6) show that high pressure core spray is capable of cooling the core without assistance from the low pressure core cooling system ( Alte rn ate Core Spray System) regardless of reactor water level.
In the event that water level cannot be maintained above the core, LACBWR Technical Specifications and LACBWR Operating Procedures require that the plant be depressurized using the single-failure proof Shutdown Condenser System and Manual Depressurization System to allow operation of the Alternate Core Spray System.
Therefore, any action to require operators not to isolcte a pipe break causing a LOCA is not appropriate at this facility.
Enclosure D This concern is a compilation of Enclosure A and Enclosure B and does not apply to LACBWR for the reasons previously stated.
No action is required at LACBWR to addresa the concerns of the request.
If there are any questions on this response, please contact us.
"8
'8 P00R DL9K 2-
r Mr. Dennis L.
Ziemann, Chief LAC-6688 Cperating Reactors Branch #2 December 11, 1979 Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL:FD: abs CC:
J.
Keppler, Reg. Dir., NRC-DRO III j
i 1580 181 3-