ML20125A605
| ML20125A605 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 03/13/1985 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| RTR-NUREG-0654, RTR-NUREG-654 LAC-10629, NUDOCS 8506110129 | |
| Download: ML20125A605 (4) | |
Text
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March 13, 1985 09A LLC
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oas at In reply, please Mt / mss CL refer to LAC-1067.9 6
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mE DOCKET h0, 50-409 Mr. James G. Keppler, Regional Administrator U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 EMERGENCY PLAN
Dear Mr. Keppler:
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In accordance with 10CFR50.54q, Dairyland Power Cooperative proposes the enclosed changes to the LACBWR Emergency Plan. The proposed changes affect Table E-1, which categorizes possible plant conditions into Emergency Action Levels.
Four conditions, which were categorized as unusual events, are being eliminated from the table. Thesa are:
(1) MSIV failure to close after steam pressure decreases to 900 psig, (2) unanticipated loss of Emergency Diesel Generator when required ta be operable, (3) unanticipated loss of Diesel l
Building DC power supply, and (4) unanticipated loss of ESWSS when required to be operable. The guidance provided in NUREG-0654, Revision 1, does not list any of these conditions, as example unusual events.
The LACBWR Emergency Plan does include as an unusual event: "other plaat conditions exist that require plant shutdown under Technical Spec'ifications.
Based on the inclusion of this criteria and that the four conditions are not listed in NUREG-0654, Revision 1, Dairyland Power Cooperative feels these conditions can be removed from the list of Emergency Action Levels without a significant degradation of the plan.
'Therefore, Dairyland Power Cooperative requests that the NRC approves the proposed changes. The proposed changes have been reviewed by the LACBWR Operations Review Committee and the Safety Review Committee. The proposed revised pages are attached to this letter.
Ib 8506110129 850313 PDR ADOCK 05000409
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Mr. James G. Keppler, Regional Administrator
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- U. S. Nuclear Regulatory _ Commission I
Directorate of Regulatory Operations March 13, 1985 Region III.
LAC-10629 If there are any questions, please contact us.
Sincerely yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL:LSG:aes Enclosures
-CC: Resident Inspector i
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_. WPl.6.7 - L
TABIE E-1 (Continued)
EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY System /
Emergency Core Spray Flow (Lo)
Unanticipated complete loss of I
Equipment Annunciator E14-1 ECCS during Operating Conditions Failure or Alternate Core Spray System Lo Flow 1-3.
Malfunction Annunciatcr E15-3 (Loss of Safety System)
Fire Header Water Pressure (Lo)
Loss of fire protection system X
Annunciator B8-4.
functions requiring shutdown by Technical Specifications.
7 8
System /
Airlocks fail Loss of containment integrity X
Equipment Surveillance Test during operation such that the Failure or Technical Specifications require Malfunction Reactor Shutdown.
(Loss of Contain-cant Integrity)
WP60
G a *L) s t
(THIS PAGE IS INTENTIONALLY LEFT BLANK.)
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