ML20011A424
| ML20011A424 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/05/1972 |
| From: | Madgett J DAIRYLAND POWER COOPERATIVE |
| To: | Bloch E US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20011A420 | List: |
| References | |
| LAC-1144, NUDOCS 8110130332 | |
| Download: ML20011A424 (3) | |
Text
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DMRYLitND POR'ER COOWNRitTIVE b Cwuz, (1konan
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54601 Juna 5, 1972 in reply, please ref er to LAC-I l44 Docket No. I15-5 Mr. Edward J. Bloch Acting Director Directorate of Licensing U. S. Atomic Energy Cerenission Washington, D. C. 20545 WRU:
Mr. Kenneth A. Duncer, Manager U. S. Atomic Energy Comission
SUBJECT:
PROVISIONAL OPERATING AUT IZATION NO. OPRA-6 LAC 8WR EMERC-fNCY CORE COOQg SYSTEM (ECCS)
Dear Mr. Bloch:
L l {
As requested (Ref.1), we have performed additional analyses to determine the effectiveness of the LAC 8W; ECCS and the results a m presented in the report designated SS-942 dated May 31, 1972, (sixty copies enclosed). The analyses substantiate that the installed ECCS is capable of providig adequate cooling for all postulated loss-of-coolant accident (LOCA) situations, as previously reported in 1966 by Allis-Chalmers (Puf. 6 and 7), and is in compliance with D e interim acceptance criteria for the performance of ECC systems as adopted by the AEC on June 19, l'71.
Ar a result of the failure mode and of fects analysis performed to the specifications of the single failure criterion as defined
' FEE Standard 279, it is concludec that there is a possibility that single failures of active components or circuit f aults could inhibit the function of the ECCS (See Section 8 of SS-942),
in ordor to eliminate this possibility we propose to make the following modifications:
l.
Install a redundant emergency diesel generator and associateo switchgaar.
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$!A AS8SA*oS$8h P
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Mr. Edward J. Bloch Page 2 Acting Director June 5, 1972
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j 2.
Modi.5y reactor water level safety channel No. I to eliminate the HPCS pump automatic trip function by a high water level signal.
3.
Provide separate powr,r supplies for each reactor water level sensing system.
4 Eliminate the single HPCS pump selector switch.
If these proposed modifications are generally acceptable to the AEC, details will be developed for submittal with the schedule for completion set at July 1,1974, or before.
It is our opinion that this letter and enclosed report in addition to previous submittals (Ref. 2 and 3) fulfills your request (Ref. 1).
If you do require additional infcrmation, let us know.
Very truly yours, DAIRYLAf;9 POWER COOPERATIVE J
P. Madgett
\\
cal Manager JPM:bms
Enclosure:
55-942 (6G) l n *
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REFERENCES
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l.
Letter P. A. Morris to J. P. Madgett, July 20, l'#71 (Request for re-evaluation of LACBWR ECCS, etc.)
2.
LAC-936, Letter J. P. Madgaf t to P. A. Morris, January 18, 1977 (Partial response to Refenance I above).
3.
UC-984, Letter J. P. Madgett to P. A. Morris, February 10, 1972 Wartial response to Reference I above).
4 Letter D.J. Skovholt to J. P. Madgett, February 29, 1972,
" Change No. 5, Provisional Operating Authorization No. OPRA-6" 5.
LAC-1014, Letter J. P. Madgett to P. A. Morris, March 6,1972 (Transmittal of " interim Report LACBWR Emergency Core Cooling System Evaluation", SS-920, February 25, 1972).
6.
ACNP-66564, Amendment No. 29 to CAPR-5, " Description of Post-Accident Safeguards Provisions for the LACBWR", September 1966.
7.
ACNP-66564.1, (Supplement to Ref. 6 above), October 1966.
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