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MONTHYEARML20024D0711983-07-28028 July 1983
Forwards Description of Proposed Equipment & Outline of Procedure to Be Followed to Meet App R Requirement Re Alternate Shutdown Capability,In Response to NRC 830110 Exemption Request Denial
Project stage: Other
ML20261C2971983-09-0707 September 1983
One Line Diagram:4160 Volt System. Sheet 2
Project stage: Other
ML20261C3011984-01-0707 January 1984
One Line Diagram:480 Volt System. Sheet 1
Project stage: Other
ML20261C3061984-01-24024 January 1984
One Line Diagram:480 Volt System. Sheet 8
Project stage: Other
ML20261C3191984-02-0505 February 1984
One Line Diagram:120 Volt AC System. Sheet 1
Project stage: Other
ML20261C3151985-04-0505 April 1985
One Line Diagram:125 Volt DC System
Project stage: Other
ML20261C3111985-04-0505 April 1985
One Line Diagram:480 Volt System. Sheet 8A.Rev Date Illegible
Project stage: Other
ML20128K7491985-07-12012 July 1985
Summary of Operating Reactor Events Meeting 85-11 on 850701. List of Attendees,Events Discussed,Significant Elements of Events & Assignment of Followup Review Responsibility Encl
Project stage: Request
ML20129C2481985-07-12012 July 1985
Forwards Revised Response to Generic Ltr 81-12 Re Alternative Shutdown Capability for Computer & Control Room, Per 850506,13 & 20 Telcons & 850618 Meeting
Project stage: Meeting
ML0311507181985-09-27027 September 1985
Withdrawn NRC Generic Letter 1985-018: Operator Licensing Examinations
Project stage: Request
ML20137W1741985-09-27027 September 1985
Forwards Addl Clarifying Info to 850712 Response to Generic Ltr 81-12 Re Alternative Shutdown Capability for Computer & Control Room
Project stage: Other
ML20138M9991985-10-30030 October 1985
Submits Addl Info Re Alternative Shutdown Capabililty for Computer & Control Room.Procedure C.13B to Change Pressurizer Level as Required by Analysis Will Be Revised by 860201
Project stage: Other
ML20198C2341985-11-0707 November 1985
Forwards Revised Requests for Exemptions from Requirements of 10CFR50,App R,Including Update of Previous Requests List of Required Mods & Respective Schedule for Installation & Addl Request Re Lack of Suppression in Control Room
Project stage: Other
ML20206F8651986-05-19019 May 1986
Forwards Exemption from Subsection Iii.L of 10CFR50,App R Re Capability to Achieve Cold Shutdown in 72 H & Safety Evaluation Supporting Util Request for Exemption from Subsection of 10CFR50,App R
Project stage: Approval
1985-10-30
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h asuun SACRAMENTO MUNICIPAL UTILITY DISTRICT 'J 6201 S Street P.0, Box 15830 Sacramento CA 958521830.(916) 452 3211 RJR 85-527 AN ELECTRIC SYSTEM SERVING THE HEART OF CAUFORNIA October 30, 1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION: HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING US NUCLEAR RFOULATORY COMMISSION WASHINGTCN DC 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 ADDITIONAL INFORMATION ON ALTERNATIVE SHUTDOWN CAPABILITY FOR COMPUTER AND CONTROL ROOM In a September 27, 1985 letter the District committed by November 1, 1985, to have a boric acid pump repair procedure in place or have an analysis that justifies the use of the present procedure without a boric acid pump repair procedure. The District's analysis shows that the required 1 percent delta k/k shutdown margfn can be maintained for Cycle 7 until the end of life by revising Procedure C.13B, "Cooldown from Hot Shutdown to Cold Shutdown with a Fire in the Contro Room" to require the pressurizer' level be increased to 225 inches when RCS temperature is below 4000F.
This analysis further shows that this change is not required until 310 effective full power days into Cycle 7 and that a boric acid pump repair procedure is not required. By February 1, 1986, the District will revise Procedure C.13B to change pressurizer level as required by the analysis.
If you have any questions concerning this submittal, please contact Larry Young at Rancho Seco.
TJ V A R. J.
ODRIGUE ASSISTANT GENE'P HANAGER, NUCLEAR r
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