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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test 1999-06-16
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20127N2711992-11-24024 November 1992 Rev 4 to Pilgrim Nuclear Power Station Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20128M7701992-03-31031 March 1992 Amend 92-01 to Second Ten Year ISI Program ML20094P5411992-03-19019 March 1992 Rev 23 to Procedure 5.4.6, Primary Containment Venting & Purging Under Emergency Conditions, Revising Coversheet & Attachment 1,Sheet 3 of 5,page 8 of 20 ML20058E5281990-10-25025 October 1990 Rev 1 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20005F0791989-12-13013 December 1989 Rev 0 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program. ML20247N3611989-07-31031 July 1989 Rev 2 to Dcrdr Program Plan ML20245D6551989-04-21021 April 1989 Power Ascension Program Resumption Plan ML20235R3441988-12-28028 December 1988 Rev 26 to, Pilgrim Nuclear Power Station Secondary Containment Leak Rate Test ML20235R4671988-12-22022 December 1988 Rev 25 to, Pilgrim Nuclear Power Station Secondary Containment Leak Rate Test ML20155C0141988-09-28028 September 1988 Rev 3 to Appendices to Restart Plan ML20155F9041988-09-0707 September 1988 Rev 3 to Pilgrim Nuclear Power Station Plant-Specific Technical Guidelines for Emergency Operating Procedures ML20153H6481988-08-31031 August 1988 Ascension Program ML20235R3801988-08-0909 August 1988 Special Post-Startup Training Program to Satisfy Requirements of NUREG-1021,Section ES-109,Parts B.2.e & B.2.f for Reactor Operator Licensed Personnel & Parts D.2.e & D.2.f for Senior Reactor .. ML20150C0271988-05-26026 May 1988 Rev 2 to Vol 2 to Apps to Restart Plan ML20151F9481988-04-0606 April 1988 Rev 2 to Emergency Operating Procedure 1.3.4-13, Emergency Operating Procedures Verification Program ML20151C8111988-04-0606 April 1988 Rev 3 to Emergency Operating Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures ML20151F9681988-04-0606 April 1988 Rev 2 to Emergency Operating Procedure 1.2.4-14, Emergency Operating Procedure Validation Program ML20151C8151988-03-28028 March 1988 Emergency Operating Procedures Training Program Summary Description ML20153B1061988-03-14014 March 1988 Rev 1B to Inservice Testing Program for Pumps & Valves, Pilgrim Nuclear Power Station ML20236T2171987-11-20020 November 1987 Rev 3 to Pilgrim Nuclear Power Station Plant-Specific Technical Guidelines for Emergency Operating Procedures ML20236T2241987-11-20020 November 1987 Rev 3 to Apps to Pilgrim Nuclear Power Plant-Specific Technical Guidelines ML20236T2361987-11-20020 November 1987 Collection of Plant Operating Procedures Utilized to Develop,Process & Issue Plant-Specific Emergency Operating Procedures ML20236N7751987-11-12012 November 1987 Rev 1 to Procedure 3.M.1-1, Preventive Maint ML20236F0201987-10-26026 October 1987 Rev 1 to Vol 2 of Pilgrim Nuclear Power Station Apps to Restart Plan ML20155F9171987-10-16016 October 1987 Rev 1 to Procedure 1.3.4-13, Emergency Operating Procedure Verification Program ML20155F9111987-10-15015 October 1987 Rev 2 to Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures ML20235X2461987-10-15015 October 1987 Power Ascension Program ML20195H6341987-09-22022 September 1987 Rev 23 to Procedure 8.7.3, Secondary Containment Leak Rate Test ML20238E8311987-09-0101 September 1987 Revised Nuclear Operations Dept Procedures,Including Rev 5 to Procedure 5.7.4.1.1, Post-Accident Sampling Sys,Small Vol Liquid Sample from Jet Pump Flow Sensing Line & Rev 6 to Procedure 5.7.4.1.2, ...Undiluted Liquid Sample.. ML20236G4071987-07-30030 July 1987 Vol 1 to Pilgrim Nuclear Power Station Restart Plan. Rev 0 to Vol 2,appendices,encl ML20236F9531987-07-28028 July 1987 Matl Condition Improvement Action Plan ML20155F9201987-07-10010 July 1987 Rev 0 to Procedure 1.3.4-14, Emergency Operating Procedure Validation Program ML20204F7431986-06-16016 June 1986 Rev 1 to Temporary Procedure Tp 86-85, RHR Intersys Leakage Assessment & Controlled Leakoff ML20204F7301986-06-10010 June 1986 Rev 11 to Procedure 2.3.2.1, Panel Procedures Panel 903 Left ML20204F7481986-06-10010 June 1986 Rev 0 to Temporary Procedure Tp 86-84, RHR Discharge Piping Venting Procedure ML20137M4811985-08-21021 August 1985 Rev 1 to Procedure 5.7.5, Estimating Core Damage ML20138R4501985-07-19019 July 1985 Rev 0 to Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures ML20128N9341985-03-0606 March 1985 Rev 0 to Procedure 5.7.5, Estimating Core Damage ML20101S7121984-12-13013 December 1984 Rev 11 to Procedure 2.1.12, Daily Diesel Generator Surveillance ML20101S7201984-12-12012 December 1984 Rev 15 to Procedure 8.9.1, Manually Start & Load Each Diesel Generator Once Per Month 1999-03-23
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PILGRIM NUCLEAR POWER STATION EMERGENCY OPERATING PROCEDURES (EOPs)
TRAINING PROGRAM
SUMMARY
DESCRIPTION 4
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Chief Operating Engineer I
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23900/2 EHERGENCY OPERATING PROCEDURES (EOP) - TRAINING PROGRAM General The E0P Training Program has been developed with the guidance of existing regulations and guidelines. Among the major guidelines considered include NUREG-0899, Guidelines for the Preparation of Emergency Operating Procedures; INPO 85-002, the Accreditation of Training in the Nuclear Power .
Industry; and INPO 86-026 Guidelines for Simulator Training. The program has also benefited immensely from the BHROG - EPG development program and its seminars and training sessions. .
The goals of the E0P Training Program are to enable the operator to:
- Understand the structure and technical bases of the E0P.
- Develop a working knowledge of the E0Ps.
- Use the E0Pb under adverse operating conditions. ,
The following description outlines the approach Boston Edison uses to
- train current and new licensed operators and STAS on E0Ps, and to ensure that they are kept proficient and knowledgeable about future revisions to E0Ps.
PROGRAM DESCRIPTION Particioation 1
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All current operators, and Shift Technical Advisors (STAS) receive E0P training prior to E0P implementation. Current operators and STAS receive E0P training as a component of required Requalification Training. New operators and new STAS are to receive this training during licensing or STA qualification training. I Replacement operators - who hold inactive licenses, also maintain their ,
qualification by successfully participating in Requalification Training.
They receive the same E0P training as operators with active licenses. !
No replacement operator is allowed to perform licensed duties until he/she meets all the requirements for an active license and completes E0P training.
Proaram Content E0P training for current, new and replacement operators and STAS consists
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of two weeks (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) of combined classroom, simulator and walk-through training.
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23900/3 In the classroom, lectures are supplemented with questions and answers and table-top exercises. The content is based on both Appendix B to the BWROG Emergency Procedure Guidelines (Rev. #4), "Detailed Discussion of Cautions and Operator Actions" and on human factors considerations used in the formatting of the E0Ps as presented in the Pilgrim Nuclear Power Station (PNPS) Writer's Guide.
The training approach and content have been specifically tailored to PNPS and includes the following:
- The bases for all cautions.
Additionally, the classroom trains on roles and responsibilities and communication skills. The table-top exercises allow crews to work-through each E0P step and resolve misinterpretations under controlled-stress condi-tions. Regularly scheduled homework assignments are provided to supplement the classroom presentations. Written and oral quizzes are utilized to test retention of this material.
The simulator segment of this training comprises approximately 501,of the training time. On Boston Edison's PNPS-Specific Simulator, crews exercise the E0Ps under operating conditions. Each scenario develops technical skills, E0P management techniques, crew management, team and communication skills. Because of the importance of communication and teamwork, these receive as much emphasis as technical competence in each scenario.
The simulator scenarios are designed to be as realistic as possible. The scenarios build expertise by starting with simple, singular failures and building to multiple simultaneous and sequential failures.
Appropriate repetition of E0Ps is provided to increase retention and avoid negative transfer. Retention is improved through coaching, feedback and critiques of performance conducted by both instructors and crews. Video taping of crews may be used in critiquing performance to enhance analysis of events and actions.
Walk-throughs are used in situations where steps have been sufficiently exercised, or when constrained by simulator or plant controls. Halk-throughs and simulation training focus on improving operator ability to use E0Ps, operator responsibility, information flow and interaction between operators in the control room.
Simulations and walk-throughs are conducted with operators performing as crews in their normal control room positions, to the maximum extent possible. To ensure the Hatch Engineer's ability in using E0Ps, he/she alternates as the Nuclear Operating Supervisor (NOS) in implementing E0Ps during training. This role alternation allows both the NOS and Hatch Engineer to become proficient in using E0Ps. As time allows, Reactor Operators are given an opportunity to rotate into or assist the N05.
23900/4 Evaluation i
Throughout the course, crew progress toward reaching established per-formance standards are continually monitored. The results are used to diagnose the strengths and weaknesses of crews and individuals. As needed, training is adjusted to meet the needs ',1entified. Monitoring includes daily written quizzes and continual obsirvations of exercise performance, including a numerical tracking of , ammunication errors during scenarios. Operator performance during each s'aulator exercise is docu-mented via scenario evaluation forms. Both 'adividual and team performance are measured and evaluated against the esb' ahed performance standards.
At the completion of training, all trai e active personnel undergo e E0P certification process. Using the perfo mance standards, team and indi-vidual performance are observed and me sured. To attain certification, crews must prove technical competence and meet communication skills criteria. Prior to performing licens !d duties, all inactive personnel are likewise certified. .
REOUALIFICATION Maintaining Proficiency Proficiency in E0Ps is maintained thrc. gh required Requalification Training and by periodic in-plant observations 'nd critiques of communication skills as well as case studies or questions r lated to E0P use. At a minimum, four hours of each Requalification Tri,ning week are devoted to E0P review. This review consists of bott classroom and simulator components.
In this manner, all E0Ps and any re ,sions to the E0Ps are reviewed during the course of a retraining cycle.
Revision E0Ps are controlled procedv es. Revision to them is evaluated by the NUORG Procedure Review process. the Training Department participates in this review and selects appror iate training, as necessary. Requalification Training is used to train on major revisions and crews receive training on minor revisions through on-watch staf fing led by the Hatch Engineer or designee. Should major revisions be required, crews receive this training prior to implementation of the E0P.
Changes made for Requalification Training are incorporated in initial license or qualification training through the regular curricular control path used by training. Only controlled procedures are used in training.