Letter Sequence Other |
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Results
Other: ML19262D021, ML19290E289, ML19296D679, ML19309A491, ML19323E338, ML19339C940, ML19343A810, ML19343A812, ML20009C533, ML20023C118, ML20028B195, ML20028E870, ML20038B523, ML20040B418, ML20040B423, ML20062A475, ML20204G206, ML20263D240, ML20263D295, ML20263D298, ML20263D301, ML20263D420, ML20263D425, ML20263D429, ML20263D430, ML20263D432, ML20263D440, ML20263D449, ML20263D456, ML20263D459, ML20263D463, ML20263D483, ML20263D494, ML20263D879, ML20263D883, ML20263D885, ML20263D888, ML20263D892, ML20263D894, ML20263D898, ML20263D901, ML20263D905, ML20263D908, ML20263D911, ML20263D913, ML20263D916, ML20263D918, ML20263D921, ML20263D924, ML20263D927... further results
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MONTHYEARML20263J0711972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly D (48 of 50), as-built Project stage: Other ML20263J0781972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly C Project stage: Other ML20263J0731972-07-10010 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly a, as-built Project stage: Other ML20263J0751972-07-18018 July 1972 Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly B (46 of 50), as-built Project stage: Other ML20263J0831979-06-0606 June 1979 Piping & Instrument Diagram HP & Auxiliary Turbines System. Sheet 1 of 3.Revision Date Illegible Project stage: Other ML19208D6001979-09-20020 September 1979 Summary of 790830 Meeting W/Utils in Bethesda,Md Re Preliminary Results of Auxiliary Feedwater Sys Reliability Study Project stage: Meeting ML19250A8351979-10-18018 October 1979 Responds to Requiring Util Commitment to Action Re NUREG-0578, TMI-2 Lessons Learned Task Force Status Rept. Forwards Implementation Plan Project stage: Request ML19210D9031979-11-19019 November 1979 Responds to NRC 791030 Request for Review of Util 791018 Response to NUREG-0578 Re Auxiliary Feedwater Sys.Sys Satisfies NRC short-term Position.Backup Capabilities Ensure That Water Reaches once-through Steam Generator Project stage: Request ML16138A4231979-12-17017 December 1979 Notification of 791220 Meeting W/B&W & B&W Licensees in Bethesda,Md to Discuss Control Rod Guide Tube Wear Project stage: Request ML19290E2891980-02-19019 February 1980 Forwards Auxiliary Sys Branch Position Re Auxiliary Feedwater Sys & Request for Adddl Info as Part of Followup to B&W 1979 Plant Shutdown Orders Project stage: Other ML19305A9911980-02-23023 February 1980 Summary of 800212 & 791129 Meetings W/Licensee in Bethesda, MD Re long-term Upgrading Requirements for Site Auxiliary Feedwater Sys Project stage: Meeting ML16245A4951980-02-24024 February 1980 Summary of 791108 Meeting W/B&W Owners Group in Bethesda,Md Re Responses to IE Bulletin 79-05C Project stage: Meeting ML19296D6791980-02-26026 February 1980 Forwards Comments & Requirements for Continued Facility Auxiliary Feedwater Sys Upgrade.Commitment to Provide Requested Info &/Or Design Mods Must Be within 15 Days Project stage: Other ML19309A4911980-03-18018 March 1980 Responds to NRC Re Requirements for Continued Upgrade of Auxiliary Feedwater Sys.Util Will Update Auxiliary Feedwater Reliability Study & Will Submit New Tech Specs by 800501 Project stage: Other ML19262D0211980-04-14014 April 1980 Withdraws 800308 Commitment Concerning Part B,Item 9 of NRC Re Proposed Mod of Auxiliary Feedwater Sys Operating Procedure A.51.Approval Would Imply Plant Could Be Safely Shutdown W/O Offsite Power or Diesel Generators Project stage: Other ML20263J0951980-04-21021 April 1980 Plant Areas Conduit Arrangement Plan at Turbine Deck. Sheet 2 of 2 Project stage: Other ML20263J0911980-04-21021 April 1980 Turbine Building Arfa II Conduit & Tray Arrangement Plan at Ground & Mezzanine Floor. Sheet 2 of 2 Project stage: Other ML20263J0991980-04-21021 April 1980 Turbine Building Area Conduit & Tray Arrangement Plan at Mezzanine Floor. Sheet 2 of 2 Project stage: Other ML20263J1011980-04-21021 April 1980 Turbine Building Area Conduit & Tray Arrangement Plan at Ground Floor. Sheet 1 of 1 Project stage: Other ML20263J1041980-04-21021 April 1980 Auxiliary Building Area - B Class II Conduits & Class I & II Tray Arrangement - Plan at Turbine Deck. Sheet 1 of 1 Project stage: Other ML20263J0631980-04-25025 April 1980 885-NI/RPS - Schematic Turbine Trip Subassembly C Project stage: Other ML19323E3381980-05-14014 May 1980 Forwards Addl Info Re Auxiliary Feedwater Sys Per 800226 Request Project stage: Other ML19343A8121980-07-24024 July 1980 Auxiliary Feedwater Sys for Smud Project stage: Other ML20263J1081980-08-10010 August 1980 Cm&D Equipment OTSG Level Sensing Project stage: Other ML20263J0861980-08-20020 August 1980 Figure 3.1-1 Auxiliary Feedwater System P&Jid Project stage: Other ML20263J0801980-09-0808 September 1980 Piping & Instrument Diagram HP & Auxiliary Turbines System. Revision Illegible Project stage: Other ML20263J0681980-09-10010 September 1980 885-NI/RPS - Schematic Main Feed Water Pump Trip Subassembly a Project stage: Other ML20263J0661980-09-10010 September 1980 885-NI/RPS - Schematic Turbine Trip Subassembly B Project stage: Other ML20263J0591980-09-10010 September 1980 885-NI/RPS - Schematic Turbine Trip Subassembly C Project stage: Other ML20263J0561980-09-10010 September 1980 885-NI/RPS - Schematic Turbine Trip Sub Assembly Project stage: Other ML20263J0621980-09-10010 September 1980 885-NI/RPS - Schematic Turbine Trip Subassembly E Project stage: Other ML19343A8101980-11-17017 November 1980 Forwards B&W Upgraded Design, Auxiliary Feedwater Sys for Smud. Requests NRC Approval Prior to Design Freeze & Preparation of Equipment Purchase Specs on 801205.Oversize Drawings Available in Central Files Project stage: Other ML19339C9401981-01-22022 January 1981 Advises That Util 801117 Preliminary Auxiliary Feedwater Sys Upgrade Design Is Acceptable.Licensee Must Provide Schedules for Design Submittals,Tech Specs & Final Implementation Project stage: Other ML20263J1181981-02-20020 February 1981 EFIC Logic 3 Steam Generator Pressure Project stage: Other ML20263J1241981-02-20020 February 1981 EFIC Logic 6 Vector Logic Project stage: Other ML20263J1291981-02-20020 February 1981 EFIC Logic 5 Initiate Logic Project stage: Other ML20263J1211981-02-20020 February 1981 Trip Logic Project stage: Other ML20263J1321981-02-20020 February 1981 EFIC Trip Test Philosophy Project stage: Other ML20263J1261981-02-20020 February 1981 EFIC Logic 12 Steam Generator Control Project stage: Other ML20263J1421981-02-20020 February 1981 EFIC Symbology Project stage: Other ML20263J1101981-02-20020 February 1981 EFIC Logic 1 Steam Generator a Level Input Project stage: Other ML20263J1141981-02-20020 February 1981 EFIC Logic 2 Steam Generator B Level Input Project stage: Other ML20040B4231981-04-30030 April 1981 Auxiliary Feedwater Sys Upgrade Reliability Analysis for Rancho Seco Nuclear Generating Station Unit 1 Project stage: Other ML20009C5331981-07-17017 July 1981 Repeats & Notarizes Util 810713 Response to NRC 810210 Generic Ltr 81-14 Re Seismic Qualification of Auxiliary Feedwater Sys Project stage: Other ML20263J1531981-09-0808 September 1981 One Line Diagram 4160 Volt System. Sheet 6.No Revision Date Project stage: Other ML20263J0881981-09-0808 September 1981 Anticipatory Reactor Trip System Instrument Installation. Sheet 1 of 2 Project stage: Other ML20263J1481981-09-0808 September 1981 One Line Diagram 4160 Volt System. Sheet 7.No Revision Date Project stage: Other ML20038B5231981-11-30030 November 1981 Forwards Auxiliary Feedwater Sys Flow Evaluation Verifying That Existing Flow Capacity Is Adequate to Meet Sys Requirements Per ALAB-655 & NRC .Abnormal Transient Operator Guidelines Will Be Submitted by 820701 Project stage: Other ML20040B4181982-01-18018 January 1982 Forwards Auxiliary Feedwater Sys Upgrade Reliability Analysis for Rancho Seco Nuclear Generating Station Unit 1. Rept Provides Info Requested in NUREG-0737 Item II.E.1.1 Project stage: Other ML20028E8791982-07-0606 July 1982 Responds to 820507 Request for Addl Info Re Seismic Qualifications of Auxiliary Feedwater Sys.Seismic Qualifications Described for Items Questioned Project stage: Request 1980-04-21
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UNITED STATES S j 3 eq [,j NUCLEAR REGULATORY COMMISSION
- .\\".
E WASHINGTON. D. C. 20555 o,,. ] i
%, N /
February 26, 1980
- ..o Docket No.: 50-312 Mr. J. J. Mattimoe Assistant General Manager and Chief Engineer Sacramento Municipal Utility District 6201 S Street P. O. Box 15330 Sacramento, California 95813
Dear Mr. Mattimoe:
SUBJECT:
NRC REQUIREMENTS FOR THE CONTINUED UPGRADE OF THE RANCHO SECO AUXILIARY FEEDWATER (AFW) SYSTEll We have completed our review of your letter dated December 17, 1979, in which you forwarded the final auxiliary feedwater reliability analysis for Rancho Seco (Attachment 1) and addressed your proposed actions on the items considered outstanding with respect to the Rancho Seco AFW system (Attachment 2). Enclosure (1) to this letter provides the results of our review of Attachments 1 and 2 to your letter.
In addition, Enclosure (2) sets an implementation schedule for completing all necessary actions with respect to the continued upgrade of the timeliness and reliability of the Rancho Seco AFW system.
Enclosure (1) to this letter is divided into four parts: Part A provides staff comments on the Rancho Seco AFW system reliability analysis and identi-fies areas of the report which need to be revised; Part B identifies staff positions and requests for additional information on the AFW system outstand-ing items; Part C identifies concerns regarding the Rancho Seco AFW system related to Section 10.4.9 of the Standard Review Plan and requests certain additional information; and Part 0 identifies our generic concerns regarding the design basis for pressurized water reactor AFW system flow requirements.
The staff positions in Part 8 are derived from four principal sources:
(1)
IE Bulletin 79-05A; (2) staff review of the Rancho Seco AFW reliability analy-sis (submitted in support of compliance with the long-term portion of the Commission Order of May 7,1979); (3) items 2.1.7.a and 2.1.7.b of NUREG-057S; and (4) other generic requirements for AFW systems applicable to most pressur-ized water reactors.
Part C and Part D were included in our review of the Rancho Seco AFW system to provide consistency with the Westinghouse and Combustion Engineering operating plant AFW system reviews accomplished previously by the staff's Bulletins and Orders Task Force.
8003120 M[
Mr. J. J. Mattimoe Please review the information requested and the schedule for required actions set forth in Enclosures (1) and (2), respectively. Within 15 days of receipt of this letter you should confirm in writing that you will pro-vide the requested information and/or design modifications in accordance with the schedule provided.
If, for any reason, you cannot comply with the schedule or if you object to any of the staff positions, you should provide a complete explanation and justification, as well as your proposed alternative.
Sincerely, r
Rii{bertW.Reid, Chief a
i++
y Operating Reactors Branch #4 Division of Operating Reactors
Enclosures:
1.
NRC Staff Comments on AFW Reliability Analysis 2.
Summary of Required Actions cc w/ enclosures:
See next 2 pages
Sacramento Municipal Utility District cc w/ enclosure (s):
Christopher Ellison, Esq.
David S. Kaplan, Secretary and Dian Grueufch, Eso.
General Counsel Cali fornia Energy ' Commission 6201 S Street 1111 Howe Avenue P. O. Box 15830 Sacramento, California 95825 Sacramento, California 95813 Ms. Eleanor Schwartz Sacramento County California State Office 600 Pennsylvania Avenue, S.E., Rm. 201 Board of Supervisors 827 7th Street, Room 424 Washington, D.C.
20003 Sacramento, California 95814 Docketing and Service Section Office of the Secretary ausiness and Municipal Department U. S. Nuclear Regula ory Commission Sacramento City-County Library Washington, D.C.
20555 828 I Street Sacramento, California 95814 Resident Insnector P. 0. Box 48 Director, Technical Assessment Fair Oaks, California 95628 Divisicn Office of Radiation Programs Dr. Richard F. Co-le U.
nvironnental Protection Agency 1
Crys 21 Mall #2 U. S. fluclear Regulatory Commission Arlington, Virginia 20460 Washington, D.C.
20555 U. S. Environment-1 Protection Agercy Mr. Frederick J. Shon Regior. IX Office Atomic Safety and Licensing Board ATTN:
EIS COORDINATOR Panel 215 Fremont Street U. S. Nuclear Regulatory Commission San Francisco, California 94111 Washington, D.C.
20555 Mr. Robert B. Borsum Elizabeth S. Bowers, Esq.
Babcock & Wilcox Chairman, Atomic Safety and
- !uclear Power Generation Division Licensing Board Panel suite 420, 7735 Old Georgetown Road U. S. Nuclear Regulatory Commission I.othesda, Maryland 20014 Washington, DC 20555 James S. Reed, Esq.
Thomas Caxter, Esq.
Michael H. Remy, Esq.
Shaw, Pittmn, Potts e Troweridge Reed, Samuel & Remy 1800 M Street,i!M 717 K Street, Suite 405 3ashington, D. C.
2003G Sacramento, California 95814 Herbert H. Brown, Esq.
Mr. Michael R. Eaton Lawrence Coe Lanpher, Esq.
Energy Issues Coordinator Hill, Christopher and Phillips, P. C.
Sierra Club Legislative Office 1900 M St., NW 1107 9th St., Room 1020 Washington, D. C.
20036 Sacramento, CA 95814 Helen Hubbard P. O. Box 63 Sunol, California 94586
Sacramento Municipal Utility District cc w/ enclosure (s):
Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Atomic Safety and Licensing Appeal Board Pa'nel U. S. Nuclear Regulatory Commission Washington, D.C.
20555 California Department of Health ATTN:
Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814
.