Letter Sequence Other |
|---|
|
Results
Other: ML19309B030, ML19350E212, ML19350E221, ML20004C255, ML20004D474, ML20010E323, ML20028B195, ML20031F293, ML20031F301, ML20032C816, ML20041C051, ML20195G282, ML20244B556
|
MONTHYEARML20263J0781972-07-10010 July 1972
Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly C
Project stage: Other
ML20263J0711972-07-10010 July 1972
Schematic Diagram:Bistable Trip String,Module Interlock, Test Trip Subassembly D (48 of 50), as-built
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
ML19309B0301978-01-20020 January 1978
Forwards Completed NRC 771228 Questionnaire Re Standby Diesel Generators & Addl Info About Util Insp Procedures. Sp 206.03B, Diesel Generator B Synchronization Surveillance Test, Encl
Project stage: Other
ML20244B5561978-01-31031 January 1978
Forwards Questionnaire Completed by Tv Greene Re Diesel Generator Per NRC
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
ML20263J1011980-04-21021 April 1980
Turbine Building Area Conduit & Tray Arrangement Plan at Ground Floor. Sheet 1 of 1
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
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
ML20263J0561980-09-10010 September 1980
885-NI/RPS - Schematic Turbine Trip Sub Assembly
Project stage: Other
ML20263J0591980-09-10010 September 1980
885-NI/RPS - Schematic Turbine Trip Subassembly C
Project stage: Other
ML20263J0661980-09-10010 September 1980
885-NI/RPS - Schematic Turbine Trip Subassembly B
Project stage: Other
ML20263J0621980-09-10010 September 1980
885-NI/RPS - Schematic Turbine Trip Subassembly E
Project stage: Other
ML20263J0681980-09-10010 September 1980
885-NI/RPS - Schematic Main Feed Water Pump Trip Subassembly a
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
ML20263J1211981-02-20020 February 1981
Trip Logic
Project stage: Other
ML20263J1291981-02-20020 February 1981
EFIC Logic 5 Initiate Logic
Project stage: Other
ML20263J1141981-02-20020 February 1981
EFIC Logic 2 Steam Generator B Level Input
Project stage: Other
ML20263J1101981-02-20020 February 1981
EFIC Logic 1 Steam Generator a Level Input
Project stage: Other
ML20263J1421981-02-20020 February 1981
EFIC Symbology
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
ML20263J1261981-02-20020 February 1981
EFIC Logic 12 Steam Generator Control
Project stage: Other
ML20263J1321981-02-20020 February 1981
EFIC Trip Test Philosophy
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
ML20004C2551981-05-22022 May 1981
Requests Extension Until 810617 to Ensure Thorough Assessment of Existing/Planned Emergency Procedures for Blackouts & Training Per NRC 810225 Request
Project stage: Other
ML20004D4741981-06-0101 June 1981
Comments on NRC 810225 Request Re Licensee Review of Station Blackout Events.Total Loss of Ac Power Was Not Considered as Dba.Specific Procedures & Operator Training in Prescribed Course of Action Are Not Necessary
Project stage: Other
ML20004D1471981-06-0202 June 1981
Memo to Operating Reactor & Licensing Project Managers Re NRC Review of Emergency Procedures & Training for Station Blackout.Licensee 90-day Responses to Generic Ltr 81-04 Should Be Provided
Project stage: Approval
ML19350E2121981-06-15015 June 1981
Forwards Station Blackout Rept, in Response to 810225 Generic Ltr 81-04 Re Emergency Procedures & Training for Station Blackout Events.Extension of Implementation Schedule Per NUREG-0737 Emergency Procedures Requested
Project stage: Other
ML19350E2211981-06-17017 June 1981
Station Blackout Rept
Project stage: Other
1980-04-14
[Table View] |
Commits to Review of Current Training Program to Determine Requirements for Addl Matl Re Emergency Procedures & Training for Station Blackout Events| ML20028B195 |
| Person / Time |
|---|
| Site: |
Rancho Seco |
|---|
| Issue date: |
11/24/1982 |
|---|
| From: |
Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT |
|---|
| To: |
Stolz J
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| REF-GTECI-A-44, REF-GTECI-EL, TASK-2.E.1.1, TASK-A-44, TASK-OR, TASK-TM GL-81-04, GL-81-4, TAC-43938, TAC-44673, TAC-48907, NUDOCS 8211300158 |
| Download: ML20028B195 (2) |
|
Text
-
$SMUD
~~~' SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento, Califomia 95813; (916) 452-3211 November 24, 1982 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION JOHN F STOLZ CHIEF OPERATING REACTORS BRANCH 4 U S NUCLEAR REGULATORY COMMISSION WASHINGTON O C 20555 DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT NO 1 EMERGENCY PROCEDURES AND TRAINING FOR STATION BLACK 0UT EVENTS In our June 1,1901 letter, we responded to your February 25, 1981 Generic letter 81-04 regarding the need for emergency procedures and training for station blackout events. Our position was that a specific procedure to handle the hypothetical case of loss of all offsite and onsite AC was unnecessary and undesirable. We further stated that we felt the District training in the areas of emergency systems, power distribution systems and heat removal by natural circulation using the steamdriven auxiliary feedwater pump was adequate to allow our operators to determine a proper course of action. Consequently, the District pro-posed to take no additional action relative to the issue.
Recently, Tom Cogburn of the District Licensing staff was contacted by your Mr. Sydney Miner regarding resolution of this issue. Mr. Miner explained that a commitment to prepare a written procedure was unnecessary; that a comitment to conduct operator training in the use of existing pro-cedures and tying these together to cover operator response to the loss of all AC scenario would be adequate to resolve the issue. The District is willing to commit to perform the necessary training to cover the loss of all AC event. We feel that much or all of the necessary material is presently covered in our operator training program. The District commits to review our current training program to determine additional material is needed and to add training material where needed. Our approach will be kOIS 8211300138 821124 PDR ADOCK 05000312 F
PDR AN ELECTRIC SYSTEM SERVING MORE IHAN 600,000 IN THE HEART OF cal!FORNiA
Director of Nuclear. Reactor Regulation Attention John F Stolz Chief November 24, 1982 to cover the training for this event from a symptom oriented perspective to insure that our operators can recognize the appropriate symptoms (e.g. loss of RC flow, no HPI, no pressurizer heaters, no condenser. vacuum, etc.) and j
understand the necessary actions and procedures to safely respond.
[ 'f~
b3A ohn J. Mattimoe General Manager ww
-J-k e
a4*
i e--r
-,w9'-no--w--<
..n.--
--.eww ww,---,-,.
w a y,. p
-.,,m w~,,-r---
--w.
e-wn--
, - ~ - - -
v-w
.- -~ <
-