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MONTHYEARML20210B4921987-04-30030 April 1987
Informs That Region V Will Provide Detailed Contractor Review of Facility Tech Specs for Errors,Omissions & Ambiguities,Per Discussion at 870428 Meeting.Recommends That Util Review Rept for Addl Changes to Tech Specs
Project stage: Meeting
ML20215L3041987-06-22022 June 1987
Summary of Meeting W/Util & NUS on 870611 in Bethesda,Md Re Adequacy of Tech Specs.List of Attendees,Viewgraphs & Candidate Tech Specs for Consideration During Finalization of Program Encl
Project stage: Meeting
ML20236C4011987-07-22022 July 1987
Discusses Schedule for License Changes,Based on NRC 870430 Tech Spec Evaluation Rept.Understands from 870611 Meeting That Items Not Yet Approved by NRC as License Amends Shall Be Procedurally Implemented Prior to Facility Startup
Project stage: Meeting
ML20234C6011987-09-0808 September 1987
Discusses Status of 870722 License Changes Based on NRC Tech Spec Evaluation Rept.Proposed Amend 164 Incorporates 19 Items Scheduled for Submittal by 870930.Remaining 33 Concerns Under Evaluation.Resolution Expected by 871029
Project stage: Other
ML20235Q4781987-10-0101 October 1987
Application for Proposed Amend 164 to License DPR-54, Consisting of Enhancements to Tech Specs to Resolve Certain Comments Resulting from NRC Region V Feb & Mar 1987 Contracted Comparison of Plant Tech Specs to Sts.Fee Paid
Project stage: Request
ML20235Q5111987-10-0101 October 1987
Proposed Tech Specs Re Comparison of Plant Tech Specs to STS
Project stage: Other
ML20236G6421987-10-28028 October 1987
Forwards Response to 34 NRC Concerns Identified in 870611 Meeting in Bethesda,Md Re Tech Spec Evaluation Rept Concerning Proposed Amend 164.Proposed Changes Will Be Procedurally Implemented Prior to Plant Restart
Project stage: Meeting
ML20236U0821987-11-25025 November 1987
Proposed Tech Specs,Consisting of Suppl 1 to Rev 0 to Proposed Amend 164
Project stage: Other
ML20236U0681987-11-25025 November 1987
Suppl 1 to Rev 0 to 871001 Application for Amend to License DPR-54,consisting of Proposed Amend 164.Attachment 1 Consists of Response to NRC Questions & Comments on Subj Proposed Amend & Util 871028 Responses to 34 Concerns
Project stage: Request
ML20236W8671987-12-0303 December 1987
Proposed Tech Spec,Combining Tech Specs 3.3.1.E & 3.3.1.F for Nuclear Svc Cooling & Raw Water
Project stage: Other
ML20236W8581987-12-0303 December 1987
Application for Amend to License DPR-54,consisting of Rev 0, Suppl 2 to Proposed Amend 164,combining Tech Specs 3.3.1.E & 3.3.1.F for Nuclear Svc Cooling & Raw Water.Revised Tech Spec Page 3-21 Encl
Project stage: Request
ML20149G1611988-02-0808 February 1988
Application for Amend to License DPR-54,consisting of Rev 0, Suppl 4 to Proposed Amend 164,adding Note to Tech Spec 3.3 to Eliminate Conflict W/Tech Spec 3.2.2.2
Project stage: Request
ML20196B8761988-02-0808 February 1988
Provides Commitment Not to Use Two Pump Option During Startup Through Power Operation.Commitment Will Be Implemented Administratively & Procedurally Prior to Startup from Current Outage
Project stage: Other
ML20149G1781988-02-0808 February 1988
Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys
Project stage: Other
ML20147F0431988-02-25025 February 1988
Forwards Suppl 5 to Rev 0 to Proposed Amend 164 to License DPR-54,revising Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2 to Require That Surveillances Be Performed Only When Gaseous Chlorine Onsite,Per NRC Request
Project stage: Other
ML20147F0771988-02-25025 February 1988
Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite
Project stage: Other
ML20153B2671988-03-15015 March 1988
Forwards Amend 97 to License DPR-54 & Safety Evaluation. Amend Modifies Various Sections of Tech Specs to More Closely Resemble B&W STS
Project stage: Approval
ML20151B3201988-03-30030 March 1988
Forwards Errata to Amends 97 & 98 to License DPR-54, Correcting Inadvertent Errors in Tech Specs
Project stage: Other
1987-06-22
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hSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 1583o, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA FEB 0 81988 GCA 88-073 U. S. Nuclear Regulatory Comission Attn: Frank J. Miraglia, Jr.
Associate Director for Projects Phillips Building 7920 Norfolk Avenue Bethesda, MD 20014 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 OPERATION AT POWER WITH TWO REACTOR COOLANT PUMPS
Dear Mr. Miraglia:
The Rancho Seco Technical Specifications presently allow power operation with one Reactor Coolant Pump operating in each Reactor Coolant Loop (2 pumps total).
Two pump operation is normally required during plant heatup-cooldown.
Based on discussions between District and NRC staffs, the District commits not to use this two pump option during Startup through Power Operation (keff >0.99).
This commitment will be implemented administrative 1y and procedurally prior to startup from the current outage. The District will provide additional justification for this option or submit proposed Technical Specification changes eliminating this option prior to the next refueling outage.
Please contact me if you have any questions.
Members of your staff with questions requiring additional information or clarification may contact Mr. Jerry Delezenski at (209) 333-2935, extension 4914 Sincerely, 8802120171 800200 ADOCK 050 2
wde hDR ua, G. Carl Andogn1ni Chief Executive Officer,
[ 00 I Nuclear 10 cc:
G. Kalman, NRC, Bethesda A. D'Angelo, NRC, Rancho seco J. B. Martin, NRC, Walnut Creek RANCHO SECO NdCLEAR GENERATING STATloN O 1444o Twin Cities Road, Herald, CA 95638 9799;(209) 333 2935
'