Similar Documents at Cook |
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999
Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases
ML17335A5611999-10-11011 October 1999
Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal
ML17335A5431999-10-0101 October 1999
Proposed Tech Specs Re Containment Recirculation Sump Water Inventory
ML17326A1591999-09-23023 September 1999
Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project
ML17326A1461999-09-17017 September 1999
Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality
ML17326A1181999-09-10010 September 1999
Proposed Tech Specs Pages,Revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling
ML17326A0941999-08-17017 August 1999
Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section
ML17326A1471999-05-28028 May 1999
Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2.
ML17325B6061999-05-21021 May 1999
Proposed Tech Specs Revising Limitations on Positive Reactivity Additions
ML17325B5891999-05-0707 May 1999
Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B5901999-05-0707 May 1999
Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
ML17325B5551999-04-19019 April 1999
Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs
ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A3581998-12-0303 December 1998
Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A3681998-12-0303 December 1998
Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys
ML17335A3651998-12-0303 December 1998
Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors
ML17335A3621998-12-0303 December 1998
Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17335A2781998-10-0808 October 1998
Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2691998-10-0808 October 1998
Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5
ML17335A2651998-10-0808 October 1998
Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp.
ML17335A2341998-09-14014 September 1998
Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
1999-09-23
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17325B5901999-05-0707 May 1999
Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
ML17325B5891999-05-0707 May 1999
Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4701996-02-0808 February 1996
In-Service Pump Test Plan, Units 1 & 2
ML17334B5661995-11-30030 November 1995
Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class,1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 1, Final Plan
ML17334B5671995-11-30030 November 1995
Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class 1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 2, Final Plan
ML17332A2521994-08-0303 August 1994
Rev 3 to Plant Manager Procedure (PMP) 12 PMP 3150 PCP.100, Radwaste Pcp.
ML17332A2491994-08-0303 August 1994
Rev 7 to Plant Manager Procedure (PMP) 12 PMP 6010 OSD.001, Odcm.
ML20063K0631994-02-11011 February 1994
Change Sheet 1 to Rev 5 to Plant Manager Procedure (PMP) 12 PMP 6010 RPP.304, Use of HEPA Vacuum Cleaners. W/ Updated Index,Page 14
ML17331B0441993-11-0909 November 1993
Rev 15 to Emergency Response Manual. W/931109 Ltr
ML17334B4851993-08-0909 August 1993
Rev 14 to Emergency Response Manual. W/930809 Ltr
ML17334B4821993-04-0202 April 1993
Rev 3 of Pump Inservice Test Program.
ML17329A5431992-06-11011 June 1992
Change Sheet 7 to Rev 6 to Procedure PMP 2080 EPP.107, Notification of Plant Personnel.
ML20077S7281991-03-14014 March 1991
Rev 3 to PMP 6010.OSD.001, Odcm
ML17325B3791990-03-0101 March 1990
Change Sheet 1 to Rev 3 to Procedure PMP 2080 EPP.106, Initial Offsite Notification.
ML17334B3551990-02-0505 February 1990
Rev 2 to DC Cook Nuclear Plant Units 1 & 2 Inservice Testing Pump Program.
ML17334B3561990-02-0505 February 1990
Rev 3 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML17334B3571990-02-0505 February 1990
Rev 3 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program.
ML20246M2191989-03-21021 March 1989
Procedure MS-3.2.1.9-1B, Maint & Surveillance Ite Medium Voltage Switchgear Equipment
ML17325B0511988-12-0909 December 1988
Interim Acceptance Criteria for Safety-Related Piping Sys.
ML17334B1491987-10-0505 October 1987
Rev 2 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program.
ML17334B1501987-10-0505 October 1987
Rev 2 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML20212A3191986-10-0202 October 1986
Rev 1 to Procedure 12 PMP 4021 TRP.001, Reactor Trip Review
ML17324A9301986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.001, Maint Procedure for Repowering RHR Pump.
ML17324A9321986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.003, Maint Procedure for Repowering Pressurizer Backup Heaters.
ML17324A9331986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.005, Maint Procedure for Repowering Containment Valves.
ML17324A9341986-05-29029 May 1986
Rev 0 to Procedure 1 Thp 6030 IMP.304, Pressurizer PORV Cable Repair.
ML17324A9351986-05-29029 May 1986
Rev 0 to Procedure 1 Thp 6030 IMP.305, App R Post-Fire Repowering of In-Containment Valves.
ML17334A9711986-05-22022 May 1986
Rev 0 to Procedure 12-OHP 4023.100.001, Unit 1 Emergency Remote Shutdown.
ML20213F6011986-05-15015 May 1986
Rev 1 to Procedure PMP 6010.OSD.001, Offsite Dose Calculation Manual
ML17324A9001986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part Iv,Training for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML17324A8991986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part Ii,Writers Guide for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML17324A8971986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part I,Specific Technical Guidelines for Donald C Cook Nuclear Plant.
ML18005A0161986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part III, Verification/Validation for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML20195C5361986-03-15015 March 1986
Public Version of Emergency Response Manual for DC Cook Nuclear Plant
ML20141D7121986-02-28028 February 1986
Rev 0 to Master Insp Plan
ML20137J6061985-12-17017 December 1985
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 2 to Erp 2.07, Outside Agency Liaison, Rev 1 to Erp 2.08, Initial Assessment Group Runner & Rev 2 to Erp 5.01.W/860117 Release Memo
ML17334A9441985-11-0505 November 1985
Change Sheet 1 of Rev 9 to Spec DCCFP101QCN, Matl & Application Spec - Initial & Repair Installations, Revising App D Silicon Foam Scope of Work to Identify New Fire Barriers & for Cross Referencing Fire Zones
ML17334A9191985-10-15015 October 1985
Implementation Plan of Reg Guide 1.97,Rev 3 for Donald C Cook Nuclear Plant Units 1 & 2, Status Rept
1999-05-07
[Table view] |
Text
ATTACHMENT TO AEP:NRC:0773'ROCEDURES GENERATION PACKAGE PART IV TRAINING FOR DONALD C. COOK NUCLEAR PLANT EMERGENCY OPERATING PROCEDURES REVISION 1 MAY 1, 1986 86052'10275 S60516 PDR P
ADOCK
',050003i5 PDR
Q l J V
PART IV OPERATOR TRAINING 1.0 Program Summary.
The EOP Training Program at D. C. Cook includes over 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> of classroom lectures on the background, organization, and use of EOPs. In addition, simulator training is provi'ded to ensure operators are capable of implementing the upgraded EOPs under actual emergency conditions. To account for differences between the simulator and D. C. Cook, operators are required to perform individual control room walkthroughs of selected EOPs.
Acceptable trainee performance is verified through written examinations and simulator evaluations.
Continuing training on the EOPs will be implemented as part of the Operator Requalification Program. The RO and SRO Programs will be modified to include both classroom and simulator training on these procedures.
2.0 Classroom Training.
2.1 Phase I.
Operators will attend 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of classroom lectures introducing them to the Upgraded Emergency Operating Procedures. Lesson plans for this training will be developed using the Westinghouse Owners Group Emergency Response Guidelines and the initial draft of the DCC EOPs.
The training will focus on:
A. tushy these procedures were developed.
B. The types and uses of the procedures.
o Emergency Operating Procedures.
o Emergency Contingency Actions.
o ~
Functional Restoration Procedures.
o Critical Safety Function Status Trees.
C. EOP entry level conditions and procedural transition points.
D. Bases of procedural steps and setpoint development background.
Page 1 of 5 Rev. 1
2.2 Phase II.
A more detailed series of classroom lectures (approxi-mately 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />) shall be provided following completion of Phase I.
The objectives for Phase II of the classroom training will focus on:
A. Procedure immediate actions.
B. Major actions and evolutions contained within the procedure.
C. Procedure transitions.
D. Bases for major evolutions and procedural steps.
E. Entry level conditions for specific procedures.
F. Critical Safety Function red path transitions.
2.3 Evaluation.
Periodic written examinations will be administered to each licensed operator. These examinations shall be based entirely on the learning objectives presented during the classroom lectures.
An overall score of 80% or greater shall be the minimum acceptable for passing. When examination performance falls below the acceptable standard, the trainee shall be assigned remedial training and shall be re-examined on identified weak areas. A written or oral re-examination shall then be administered to verify acceptable trainee performance.
3.0 Simulator Training.
3.1 Description.
Upon completion of Phase I classroom training, operators will begin using the upgraded EOPs during annual simulator training at the Westinghouse SNUPPS simulator in Zion, Illinois.
Page 2 of 5 Rev. 1
The simulator exercises shall be structured to introduce the operator to the upgraded EOPs and the mechanics of how they are used. WOG background documents will be made available during the sessions to clarify procedural steps. Initially, the scenarios will be kept relatively simple. Multiple failures will be avoided and casualties will be limited to the major plant failures of:
o Loss of primary coolant.
o Loss of secondary coolant.
o Steam generator tube rupture.
o Anticipated transient without reactor trip.
Near the end of the simulator training, scenarios will include multiple failures and casualties which require the use of as many EOPs, ESs, ECAs, and FRx are practical.
Typically, teams of three operators will attend the simulator, filling the Reactor Operator, Balance of Plant, and Control Room supervisor positions. The operators will periodically rotate to give each other the opportunity to direct and perform actions required by the procedures.
3.2 SNUPPS Simulator vs. Cook Control Room Differences.
Westinghouse and D. C. Cook have taken several .actions to limit the impact of control room differences on the simulator training process.
Differences between the simulator and the Cook Plant are identified and reviewed with the trainees at the beginning of each simulator training course. Addition-ally, simulator instructors provide guidance to the trainees when Plant/simulator differences might confuse or otherwise hinder the training process.
Magnetic labels are used to identify D. C. Cook specific valve numbers for SNUPPS-equivalent valves in the Chemical and Volume Control, Emergency Core Cooling, and Feedwater systems.
The simulator agreement contains a Westinghouse commitment to send instructors to the Cook Plant to maintain familiarity with the plant and enhance the knowledge level of the instructors. Westinghouse has also agreed to modify its simulator software as necessary to enhance the similarity to the Cook Plant.
Examples of software modifications which have been implemented include:
Page 3 of 5 Rev. 1
o Reactor Protection System setpoints.
o Normal operating parameters (e.g., Boron concentration in CVCS and ESF components).
o Steam generator shrink and swell modeling.
o Pressurizer PORV flow capacity.
o Spray line/surge line flow capacity.
o Control system circuitry modifications.
3.3 Evaluation.
The simulator instructor will verify the satisfactory completion of these exercises based upon proper student response to identify the problem, diagnose the situation and'ake the proper corrective action(s).
Response to oral questions regarding systems knowledge are part of this evaluation process.
Upon completion of each exercise, operational errors and weaknesses identified are reviewed with the students. Discussion is encouraged.
4.0 Control Room Walkthroughs.
4.1 Guided Walkthroughs.
In conjunction with the classroom training, each operator will be issued selected EOPs to walkthrough in the control room. The purpose of this individual walkthrough is threefold:
A. To provide additional familiarization of the procedures, B. To familiarize the student with the control board locations of indications and controls identified in the upgraded EOPs, and C. Provide feedback to the Training Department as to the adequacy of the training program.
4.2 Documented Procedure Review.
To supplement the procedure walkthrough, INFORMATION ONLY, draft copies of the EOPs will be made available to the operators on-shift.- Operators will be required to review these procedures on a periodic basis to ensure the level of training is maintained throughout the implementation process.
Page 4 of 5 Rev. 1
5.0 Continuing Training.
After implementation of upgraded EOPs, continuing training on these procedures will be rolled into the Operator Requalification Program. On an annu'al basis, operators will complete the following:
A. Individually, or in a group discussion, review all EOPs.
B. Attend a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> simulator retraining course which includes application of EOPs.
C. Participate in classroom training consisting of lectures on selected EOPs.
The EOP lecture series will be added to the Replacement Operator Program to ensure that license candidates preparing for the NRC Reactor exam will be qualified to use the EOPs.
This program also includes simulator training which will require license candidates to use the EOPs in response to casualty scenarios.
The RO and SRO Upgrade Program will also be modified to include additional EOP refresher lectures and simulator training using the upgraded EOPs.
Page 5 of 5 Rev. l
l P
/
I.
P 1
I 0
