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Category:ARCHIVE RECORDS
MONTHYEARML20116A0341996-07-17017 July 1996 Rev 0 to Temp Vs Distance Profile for 10 RHR Line Containing Stagnant Water ML20058Q4061993-08-30030 August 1993 Package Consisting of Employee Concerns Programs ML20128G9491993-01-22022 January 1993 Calculation of Weights Due to Fire Protection Matl ML20128G9551992-12-29029 December 1992 Design Validation of Conduits W/Thermolag ML20128G9861992-10-0202 October 1992 Ampacity of Power Cable Wrapped W/330-660 Installed as Free Air Drop ML20105A7981992-08-14014 August 1992 Rev 0 to Calculation of Thermal Response for Sprinkler & Raceway Supports ML20101G0471992-06-17017 June 1992 Rev 3 to Calculation 2-FP-0085 Raceway & Firezone R Cable Supports Analysis ML20115B6851992-03-0202 March 1992 Rev 0 to 2-NP-GENX-544, Reconciliation of Local Stress Evaluation Using ME215 Analysis ML20104B4001992-02-13013 February 1992 Rev 1 to Calculation RXE-TA-CP1/0-027, Undervoltage/ Underfrequency Reactor Trip Setpoints ML20127H2091991-11-12012 November 1991 Calculation 2-NP-GENX-551, Evaluation of NUREG-0797 Suppl 1A (Sser 14) App a Sections 12.1 & 12.2 ML20082U5851991-05-0808 May 1991 Liner Attachment Welds Serviceability ML20055E2881990-03-12012 March 1990 Package Consisting of Event Notification Worksheet Re 900312 Inadvertent Safety Injection from Single Train.No Equipment Malfunction/Failure Noted ML20072A8471990-01-23023 January 1990 Rev 2 to Calculation 071, Review Statement for Safety Related Calculations ML20042D3711989-09-28028 September 1989 Audit Rept ATP-89-146S, Scaling Calculations, on 890821-0928 ML20247G4111989-03-31031 March 1989 Transit Time Flow Meter Calculations ML20151T3841988-08-0101 August 1988 Protocol Between OSP & NRR for Technical Review of Comanche Peak Fsar ML20151K5841988-04-18018 April 1988 Page from Draft Rept on Plant Safeteam Activity & Ofc of Investigations Review IR 05000445/19820141988-03-11011 March 1988 Draft of Insp Rept 50-445/82-14 Originally Withheld from FOIA-84-210 Response & Typing Cover Sheets or Transmittal Pages of Documents Withheld from FOIA-86-181 Response ML20148F8201988-01-21021 January 1988 Rev 0 to Investigation of SIF for Weld Shrinkage ML20148F8631988-01-21021 January 1988 Rev 1 to Parallel Snubbers ML20148F2151987-11-19019 November 1987 Rev 0 to Potential Binding of Lugs in Axial Supports ML20237K9771987-08-19019 August 1987 Press Release 87-115 Informing of NRC Release of Documents Re Investigation of NRC Actions Involving Plant Under Const. Portions of Documents Deleted for Personal Privacy Reasons or Prospective Personnel Matters ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20148F2521987-05-22022 May 1987 Rev 0 to Evaluation of Fluid Transient Cutoff Forces & Development of Screening Criteria for Piping Sys ML20237K0381987-05-14014 May 1987 Record of 870514 Telcon W/S&W & Util Re Insp Requirements for Pipe Supports (Ref Item 4,SWEC NA-1140 Rept) ML20237K0201987-05-13013 May 1987 Record of 870513 Telcon W/S&W & Util Re Insp Requirements for Pipe Supports for Plant.S&W Does Not Consider Insp of Designs to Be Warranted ML20236M4011987-04-17017 April 1987 Package Consisting of 870417 Request for Premium Cost Mail Svc & Unsigned & Undated Ltr to Util Forwarding Draft Insp Repts 50-445/87-02 & 50-446/87-02 & Notice of Deviation ML20128G9681987-02-24024 February 1987 Cable Ampacity Derating Factors for Conduits Boxed in W/ Thermolag (TSI Product) ML20236L9091987-02-19019 February 1987 Rev 1 to CT-1-137-701-S25R, Pipe Support Calculation ML20236N4981987-02-0202 February 1987 Package Consisting of Comanche Peak Steam Electric Station Design Change Authorizations & Evaluation Summaries ML20207D7231986-12-23023 December 1986 Pipe Support Calculation:General Calculation for Richmond Insert/Tube Steel Connections Design Mods ML20207D7481986-12-23023 December 1986 Generic Calculation:Evaluation of Npsi Rear Brackets, Dimension for Design Calculation IA-86-386, Package Consisting of Potential Violations Not Included in Proposed Enforcement Package & Violations of Little Safety Significance Not Included in Proposed Enforcement Package1986-12-16016 December 1986 Package Consisting of Potential Violations Not Included in Proposed Enforcement Package & Violations of Little Safety Significance Not Included in Proposed Enforcement Package ML20211P4701986-12-16016 December 1986 Package Consisting of Potential Violations Not Included in Proposed Enforcement Package & Violations of Little Safety Significance Not Included in Proposed Enforcement Package IA-85-799, Partially Withheld Package of Info Re Plant Investigation, Including Draft NRC Ltr to Aslb,Partial Transcript & Handwritten Notes1986-12-0101 December 1986 Partially Withheld Package of Info Re Plant Investigation, Including Draft NRC Ltr to Aslb,Partial Transcript & Handwritten Notes ML20214R3351986-12-0101 December 1986 Partially Withheld Package of Info Re Plant Investigation, Including Draft NRC Ltr to Aslb,Partial Transcript & Handwritten Notes ML20235S1101986-11-15015 November 1986 Package of Documents Re Nomination & Authorization for Cash Awards to NRC Personnel Involved W/Insp Efforts Re Implementation of Util Comanche Peak Response Team Program IA-87-528, Package of Documents Re Nomination & Authorization for Cash Awards to NRC Personnel Involved W/Insp Efforts Re Implementation of Util Comanche Peak Response Team Program1986-11-15015 November 1986 Package of Documents Re Nomination & Authorization for Cash Awards to NRC Personnel Involved W/Insp Efforts Re Implementation of Util Comanche Peak Response Team Program ML20210E5991986-11-0707 November 1986 Rev 2 to Calculation 020-040-M19, Clip Stiffness Production Value ML20210E6811986-10-31031 October 1986 Rev 4 to Calculation M-03, Cable Tray Properties ML20236L8891986-10-31031 October 1986 Rev 1 to CT-1-137-702-S25R, Pipe Support Calculation. Supporting Documentation Encl ML20210E5221986-10-15015 October 1986 Rev 2 to Calculation M-10, Cable Tray - Clip Angle Stiffness ML20210E5751986-10-10010 October 1986 Rev 2 to Calculation M-12, Qualification Procedures for Cable Tray Support Evaluation ML20148F4591986-09-16016 September 1986 Rev 0 to Fatigue Cycle Determination for Pipe Supports ML20148F4921986-09-10010 September 1986 Rev 2 to Documentation of Use of Low Strength A563 Grade a Double Nuts on High Strength SA 193 Grade B-7th D Rod for Richmond Insert Bolt Connection ML20210E6261986-08-31031 August 1986 Rev 0 to Calculation M-28, Justification of Clip Modeling Procedure ML20148F3351986-08-28028 August 1986 Rev 2 to Development of Method for Evaluating Local Stress in Pipe Support Members ML20210E4611986-08-25025 August 1986 Rev 3 to Calculation M-25, Base Plate Prying Action Factors ML20236L9371986-07-31031 July 1986 Rev 1 to Calculation CT-1-032, Texas Util Generating Co Comanche Peak Steam Electric Station Containment Spray Sys 15454-NP(H) ML20211K2971986-06-11011 June 1986 Partially Withheld Package of 850711 & 860611 Lists of Allegations on Comanche Peak 1996-07-17
[Table view] Category:PHOTOGRAPHS & SLIDES
MONTHYEARML20137A7031984-05-0707 May 1984 Slide Presentation from 840507 Meeting in Bethesda,Md to Discuss Facility.Ten Oversize Pages of bar-chart Plot Based on Schedule Dates Encl IA-85-547, Slide Presentation from 840507 Meeting in Bethesda,Md to Discuss Facility.Ten Oversize Pages of bar-chart Plot Based on Schedule Dates Encl1984-05-0707 May 1984 Slide Presentation from 840507 Meeting in Bethesda,Md to Discuss Facility.Ten Oversize Pages of bar-chart Plot Based on Schedule Dates Encl ML20091K2901984-02-24024 February 1984 Slide Presentation Entitled, Industry Evaluation of Operating Shift Experience Requirements, Presented at 840224 Meeting Before Commissioners in Washington,Dc ML20054E7861982-05-27027 May 1982 Slide Presentation Entitled, Control Room Design Review at Comanche Peak Steam Electric Station ML19340C4171980-11-0707 November 1980 Nonproprietary Version of Slides Used in Westinghouse Proposal for Addressing Inadvertent Boron Dilution Event at Facility ML20003A0831980-10-15015 October 1980 Slide Presentation Entitled, Inadvertent Boron Dilution. ML19323H1161980-03-25025 March 1980 Slide Presentation Used During 800325 Meeting 1984-05-07
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l INDCSTRY EVALGLTICN OF OPEPATING SHIFT EXPERIENCE Mwuu24ENTS crr.mm i
BY: J. H. Miller, Jr.
President, Georgia Power Ccapany For: NRC Ccanissioners
.11th Floor Conference Rocu 4 1717.H. Street, Northwest Washington, D.C.
February'24, 1984 l l
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BACKGROUND DATE EVENT January 26
- NRC Staff Meeting with NTOLS to Present
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Objectives February 2-22
- Operating Shift Experience Meetings Held .
- Industry Working Group Formed
- Utility Management Accepted industry Working Group Findings February 24
- Presentation to NRC Commissioners
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__ _ . . . ,_ ,. ,.a_,s PURPOSE Present industry po'sition on the level and type of operating shift experience required for the safe startup and initial operation of a nuclear generating plant. -
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7 ELEMENTS OF PLANT EXPERIENCE -
- Power Plant Machinery and Controis
- Plant Specific Layout and Design Parameters
- Highly Disciplined, Tightly Controlled Environment
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TYPES OF NUCLEAR EXPERIENCE AND WEIGHTING FACTCRC FORMULA Nuclear Experience = (Type of Nuclear Experience) x (Weighting Factor)
TYPES OF NUCLEAR EXPERIENCE SROlRO Sr.me Type Plant SROlRO Commercial Plant Navy (Military) Plant Simulator Participation at Operating Nuclear Plant License Training Other Nuclear Experience Degree Experience on Own Plant 9
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St,IDE 5 l.
P, OPERATING SHIFT EXPERIENCE REQUlHEMENTS !
Hot Participation Experience .
Power Nuclear at Same Type Plant
- Plant Plant Startup Experience Experience and 6 Months Years Years License >20% Pwr Shutdown on Shift Position i 4 2 SRO 6 weeks X Either Shift Supy Sr Operator 3 2 SRO 6 weeks SRO Licensed Oper 3 1 .. -- RO Licensed Oper 3 1 RO Totals 13 6 i
- ll any of the Hot Participation Experience requirements are not satisfied by the SRO's, a qualified
- advisor is required.
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l NRC STAFF OBJECTIVES
- 1. At least one SRO on each operating shift should have a minimum of one year of. hot operating experience on a similar type commercial piant at the SRO level
- 2. Eliminate use of technical advisors for meeting minimum shift crew experience levels
- 3. All SROs should have substantial hot operating experience as ROs at facility on which licensed or similar facility i
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i EFFECTS OF NRC STAFF OBJECTIVES
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- Dilute Shift Experience for Operating Plants
- Result in Loss of Pre-Op Test Experience in Own Plant
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- Delay Startup of Some Plants ~
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SUMMARY
INDUSTRY POSITION'ON OPERATING SHIFT ~
EXPERIENCE REQUIREMENTS
- Follow Stated Experience Requirements for Operating Shift Personnel Shown on Slide 5 (Derived from ANS 3.1-1981)
- Use Weighting Factors in Assessing Experience
- Have at Least Ono SRO with Six Months " Hot" Participation at the Same Type Plant o'n Each Shift
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Provide a Qualified Advisor Until the Plant Staff Meets Stated Experience Requirements 1
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