Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
Results
Other: A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station, ML19317G911, ML20086J905, ML20126J866, ML20126J973, ML20135E867, ML20149D631, ML20149F003, ML20196E677, ML20196E697, ML20206H162, ML20212B420, ML20215G661, ML20234C529, ML20234C558, ML20234D524, ML20234D615, ML20234D649, ML20235M565, ML20235Q511, ML20236L543, ML20236N639, ML20236S088, ML20237B265, ML20237B279
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MONTHYEARML19317G9111977-06-0303 June 1977 Model Tech Spec Tables 3.3,3.3-4 & 4.3-2 Re Engineered Safety Feature Actuation Sys Instrumentation & Section 4.8.1 Concerning Surveillance Requirements of Electrical Power Sys Project stage: Other ML19317G9021977-06-0303 June 1977 Safety Evaluation & Statement of NRC Positions Re Emergency Power Sys for Operating Reactors Project stage: Approval ML19317G8981977-06-0303 June 1977 Forwards NRC Safety Evaluation & Model Tech Specs Re Emergency Power Sys.Util Requested to Submit OL Amend Application Incorporating Tech Specs Comparable to Model Tech Specs Project stage: Approval ML20086J9051984-01-0404 January 1984 Temporary Loss of All Ac Power Due to Relay Failures in Diesel Generator Load Shedding Circuitry (LER 83-18) Project stage: Other NRC Generic Letter 1985-061985-04-16016 April 1985 NRC Generic Letter 1985-006: Quality Assurance Guidance for ATWS Equipment That Is Not Safety-Related Project stage: Request ML20126J8661985-06-0404 June 1985 Amend 68 to License DPR-54,defining Operability & Surveillance Requirements for Plant Essential Electrical Sys & Operability Requirements for Components of Fire Protection Sys Project stage: Other ML20126J8901985-06-0404 June 1985 Safety Evaluation Supporting Amend 68 to License DPR-54 Project stage: Approval ML20126J9731985-06-0404 June 1985 Notice of Denial of Amend to License DPR-54 & Opportunity for Hearing Re Proposed Tech Spec Establishing Operability Requirements for Essential HVAC Sys Project stage: Other ML20135E8671985-09-0909 September 1985 Amend 74 to License DPR-54,revising Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources Project stage: Other ML20135E8721985-09-0909 September 1985 Safety Evaluation Supporting Amend 74 to License DPR-54 Project stage: Approval ML20135E8571985-09-0909 September 1985 Forwards Amend 74 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources Project stage: Approval ML20215C9951986-10-0202 October 1986 Forwards Replacement Pages Inadvertently Omitted from 860723 Amend 4 to Updated FSAR Re Reactor Vessel & Steam Generator Design Data Project stage: Request ML20212B3781986-12-19019 December 1986 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 147,changing Electrical Distribution Sys. Design Basis Repts,Response to NRC Question from 861125 Telcon & Summary of Changes Encl Project stage: Request ML20212B4201986-12-19019 December 1986 Proposed Tech Specs Reflecting Changes to Electrical Distribution Sys & Mods to Inverter Power Supply Sys & Undervoltage/Overvoltage Protection Sys.W/Five Oversize Diagrams Project stage: Other ML20234D5241986-12-31031 December 1986 Baseline Vibration Survey Emergency Diesel Generator a Rancho Seco Nuclear Power Plant Project stage: Other ML20234D6151986-12-31031 December 1986 Pipe Vibration Survey Emergency Diesel Generator a Rancho Seco Nuclear Power Plant Project stage: Other ML20234D6491987-01-31031 January 1987 Crankshaft Torsional Vibration Measurements Emergency Diesel Generator a Rancho Seco Nuclear Power Plant Project stage: Other A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station1987-02-28028 February 1987 Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station Project stage: Other IR 05000312/19870081987-04-0101 April 1987 Insp Rept 50-312/87-08 on 870209-0306.No Violations Noted. Major Areas Inspected:Licensee Program for Environ Qualified Electrical splices,follow-up of Insp Open Items,Ie Bulletins & Info Notices,Unresolved Items & LERs Project stage: Request ML20206H1281987-04-0101 April 1987 Application for Amend to License DPR-54,revising &/Or Adding Addl Sections to Tech Specs & Addressing Safety Impact of Bringing Tdi Diesel Generators Into Svc. Description of Proposed Changes Encl Project stage: Request ML20206H1621987-04-0101 April 1987 Proposed Tech Specs Re Safety Impact of Bringing Tdi Diesel Generators on Line Project stage: Other ML20215G6611987-04-13013 April 1987 Informs That Seismic Qualification of Either of Listed Options Re Resolution of Issue of Class 1 Indication of Tdi Diesel Generator Status in Control Room Will Be Based on Generic Ltr 87-02,per 870401 Commitment Project stage: Other ML20210B4921987-04-30030 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 ML20234C5581987-06-10010 June 1987 Rev 0 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other 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 ML20234C5291987-06-26026 June 1987 Forwards Rev 0 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75, Per Discussions on 870602 & 03 Re Rev 2 to Proposed Amend 147 to License Project stage: Other ML20235M5651987-07-0808 July 1987 Forwards Design Review/Quality Revalidation (Dr/Qr) Program for Rancho Seco Tdi Diesel Generators, Final Engineering Summary Rept.Preliminary Turbocharger Final Rept Will Be Submitted by 871001 Project stage: Other 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 ML20235F5251987-09-22022 September 1987 Forwards Supplemental Info Re Previous Submittal of Proposed Amend 147,Rev 2 Re Electrical Sys Tech Specs.Info Reflects More Restrictive Limiting Condition of Operation for Diesel Generators to Be out-of-svc Project stage: Supplement ML20235F5301987-09-22022 September 1987 Proposed Tech Specs Consisting of Supplemental Info to Proposed Amend 147,Rev 2 Re Diesel Generator Outages Project stage: Supplement 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 NL-87-1295, Forwards Supplemental Emergency Diesel Generator Info,Per NRC Request.W/One Oversize Drawing Change Notice1987-10-0808 October 1987 Forwards Supplemental Emergency Diesel Generator Info,Per NRC Request.W/One Oversize Drawing Change Notice Project stage: Supplement ML20236E9361987-10-26026 October 1987 Forwards Response to 871008 Request for Clarification & Info Re Emergency Diesel Generator Review Project stage: Request 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 ML20236L5431987-10-30030 October 1987 Forwards Requested Addl Info Re Proposed Amend 147 to License DPR-54 & Plant Electrical Distribution Sys.Single Failure at Switch 52-4B202 Has No Safety Impact Project stage: Other ML20236N6391987-11-0909 November 1987 Confirms That 15% Damping Value Used During Design of Cable Tray Supports in Tdi Diesel Generator Bldg,In Response to Request Project stage: Other ML20236N3211987-11-0909 November 1987 Forwards Three Pages Inadvertently Omitted from Util 871030 Response to NRC Request for Addl Info Re Proposed Amend 147 to License DPR-54 Project stage: Request ML20236Q2461987-11-10010 November 1987 Safety Evaluation Supporting Util & Related Submittals Re Design Mods to Emergency Electrical Distribution Sys (Ref Tdi Diesel Generators) Project stage: Approval ML20236Q2381987-11-10010 November 1987 Forwards Safety Evaluation Supporting Plant Electrical Distribution Sys Design (Ref Tdi Diesel Generators).Approval of Design Required Before Performance of Loss of Offsite Power Test Project stage: Approval ML20236S0821987-11-17017 November 1987 Supplemental Application for Amend to License DPR-54, Consisting of Suppl 2 to Rev 2 to Proposed Amend 147, Concerning Diesel Generators Project stage: Supplement ML20236S0881987-11-17017 November 1987 Proposed Tech Specs,Consisting of Suppl 2 to Rev 2 to Proposed Amend 147,concerning Diesel Generators 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 ML20236U0821987-11-25025 November 1987 Proposed Tech Specs,Consisting of Suppl 1 to Rev 0 to Proposed Amend 164 Project stage: Other ML20237B2791987-12-0101 December 1987 Rev 2 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 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 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 ML20237B2651987-12-0808 December 1987 Forwards Rev 2 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Electrical Installation to Reg Guide 1.75, Per Class 1 & 2 Cable Trays & Raceways Described in NUREG-1286,Section 4.7.3.2 a 1 & 2 Project stage: Other ML20234D5061987-12-29029 December 1987 Forwards Listed S&W & Failure Analysis Assoc Repts Re Vibration on Tdi Emergency Diesel Engines,In Response to M Hartzman 871215 Request for Addl Info Project stage: Request 1987-11-25
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+: 4 MSMUD SACRAMfNTO MUNlr.lPAL UTILITY DISTRICT O P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA AGM/NPP 87-265 OCT J 1 '.U U. S. Nuclear Regulatory Commission Attn:
Frank J. Miraglia, Jr.-
Associate Director for Projects Philips Building 7920 Norfolk Avenue Bethesda, MD 20014 DOCKET N0. 50-312 RANCHO SECO NUCLEAR GENERATING STATION LICENSE NO. DPR-54 PROPOSED AMENDMENT NO. 164
Dear Mr. Miraglia:
In accordance with 10 CFR 50.90, the Sacramento Municipal Utility District proposes to amend its Operating License, DPR-54, for the Rancho Seco Nuclear Generating Station.
Proposed Amendment No. 164 consists of enhancements to the Technical Specifications to resolve certain comments resulting from an NRC-Region V contracted comparison of the Rancho Seco Technical Specification (RSTS) to the Standard Technical Specifications (STS) performed in February and March,1987.
In a meeting between NRR and SMUD on June 11, 1987, seventeen of these comments were identified and mutually agreed upon as being sufficiently significant to require early resolution.
Five more issues were subsequently added, either through discussions with the NRC, or voluntarily by SMUD.
The resulting 22 items comprising this proposed amendment are discussed in detail in Attachment II to this letter. Attachments.I and III. consist of the revised pages of the Technical Specifications, and the No Significant Hazards Consideration, ) respectively.
The addition of Standard Technical Specification Sections 3.0 and 4.0 affects previously submitted Proposed Amendnients as described in Attachment IV.
Pursuant to 10 CFR 50.91(b)(1), the Radiological Health Branch of the California State Department of Health Services has been informed of this i
proposed amendment by mailed copy of this submittal
\\
l 8710070602 871001 PDR ADOCK 05000312 g p, s so *
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aom 1
RANCHO SECo NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935
(
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n--___---___.
bCT 01 yy AGM/NPP 87-265 F. J. Miraglia Enclosed is a check in the amount of $150.00 as required by 10 CFR 170.21,
" Schedule of Fees."
Should you require any further information with respect to this Proposed Amendment, please contact Mr. Jerry Delezenski at Rancho Seco Nuclear Generating Station, extension 3909.
Sincerely,
'{
ly oseph F. Firlit Assistant General Manager, Nuclear Power Production Sworn to and subscribed before me this
/or day of October,1987.
[bau) kr $by Notary Public U ANNE SHELBY l
Attachments NoTARYPUBUC CALFORNIA i
sAcmw.NTo COUNTY cc:
G. Kalman, NRC, Bethesda (w/atch)
N I !.'$'-
A. D'Angelo, NRC, Rancho Seco (
)
J.B. Martin, NRC, Region V
(
)
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