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 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 ML20135E8721985-09-0909 September 1985 Safety Evaluation Supporting Amend 74 to License DPR-54 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20149D6311988-01-0404 January 1988 Forwards Engineering Summary Repts for 16 Tdi Phase I Diesel Generator Components,Containing Detailed Info on Design Review/Quality Revalidation Program.Vibration Problems W/Turbocharger Support Bracket Resolved Project stage: Other ML20149F0031988-02-0101 February 1988 Informs of Intent to Submit Formal Rept Re Vibration Surveillance Program for Tdi Diesel Generators.Actions to Be Taken in Future to Monitor Diesels for Vibration Listed Project stage: Other ML20196E6971988-02-0505 February 1988 Rev 3 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20149L2391988-02-0909 February 1988 Forwards Amend 94 to License DPR-54 & Safety Evaluation. Amend Changes Tech Specs to Reflect Addition of Two Diesel Generators & Associated Mods to Facility Emergency Electrical Distribution Sys Project stage: Approval ML20196E6771988-02-22022 February 1988 Forwards Rev 3 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75, Presenting Clarification for Actual Configuration at Facility Project stage: Other 1987-11-09
[Table View] |
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~~ ' SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 15830, Sacramento CA 95852-1830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA l
- October 26,-1987 DTS87-092 U.' S. Nuclear Regulatory Commission Attr.: Frank J. Miraglia, Jr.
Associate Director for Projects Philips Bldg.
7920 Norfolk Avenue Bethesda, MD 20014 DOCKET'50-312 RANCHO SECO NUCLEAR GENERATING STATION.
LICENSE NO. DPR-54 EMERGENCY DIESEL GENERATOR ADDITIONAL INFORMATION
Dear Mr. Miraglia:
Subsequent to the District's October 8,1987 letter, the staff requested further. clarification and information with respect to their Emergency Diesel Generator review. The attached questions and answers provide this information.
Please contact me if you have any questions. Members of your staff with questions requiring additional information or clarification may contact John Atwell at extension 4917.
Sincerely, Bob G. Croley Director, Technical Services Attachment cc:
G. Kalman, NRC, Bethesda A. D'Angelo, NRC, Rancho Seco
(/
l 8710300069 871026
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h DR ADOCK 05000312 i
PDR l
l' RANCHO SECO NUCLEAR GENERATING STATION El 1444o Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935
i l:
j ATTACHMENT l
QUESTIONS / RESPONSES i
QUESTION #1:
Could failure of non-safety instrument (air) tubing cause a loss of all system compressed air?
q
RESPONSE
As currently designed, failure of the non-safety instrument
~
air' tubing will eventually cause loss of all system compressed air within a period of 3 or more days. The loss of air from the receiver tank is restricted by a throttled needle valve.
The District is pursuing several options to assure an adequate i
supply of compressed air. As stated in the District's October 8,1987 (response #5) the air receivers are currently being tested and upon completion, the.results of the test and design changes will be provided to the NRC.
QUESTION #2:
Have the auxiliary skid mounted piping and components which have been designed to ANSI B31.1 been pressure tested per ASME Section III, Class 3.
RESPONSE
Hydrostatic-testing of auxiliary skid mounted piping and components was performed by the vendor to ANSI B31.1 requirements.
QUESTION #3:
What is the status of the turbocharger permanent fix?
(i.e.,
Installed, tested, approved by TDI/0wners Group)
RESPONSE
The' turbocharger vibration problem has not yet been resolved nor have all supports been installed or tested.
However, the modification will be performed prior to restart. After restart the TDI vendor and owners group will be asked to review the modifications and provide their concurrence.
It should be noted that some members of the owners group are actively participating in designing the Rancho Seco modi fications.
QUESTION #4:
How does the communication system in the NSEB compare to that found in the Diesel Building.
RESPONSE
The communications in the NSEB is similar to that in the EDG Building.
Both buildings have equal types of communication devices such as telephones public address speakers and sound-powered phones.
Certain tiB rooms that contain equipment requiring periodic maintenance or operation actions are provided with at least two of the communication devices.
In the event of failure of these communication devices, UHF radio communications are available to plant personnel as backup.
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-. QUESTION. #5i,
Lighting PostLSeismic: Event:
J
~
Battery l lighting seismically' qualified? ~
i AC' Lighting'available post seismic?-
e
'or.,is-other means to be; provide'd?'-
~
-RESPONSE:
The! battery powered lighting has been seismically supported' though'the fixtures have no seismic documentation. With-
. respect.to ~the AC lighting.no battery backup. exists and the -
~ lighting.is not seismically installed.
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