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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A8301997-03-31031 March 1997 Wppss WNP-2 RPV Surveillance Matls Testing & Analysis. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B1751995-12-31031 December 1995 Reactor Power Uprate Startup Test Rept, for WNP-2. W/951215 Ltr ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. 1999-08-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291B1621995-03-0606 March 1995 Rev 9 to Procedure Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii. ML17291A1341994-06-16016 June 1994 Pages 9 & 10 to Rev 11 to PPM 13.12.15,inadvertently Omitted from Original Submittal ML17291A6661994-04-30030 April 1994 WNP-2 Odcm. ML17290A9951993-12-31031 December 1993 Amend 16 to Odcm. ML17290A3771993-05-27027 May 1993 Amend 1 to Inservice Insp Program Plan,First Insp Interval. New Relief Request Will Be Submitted to Define Areas of Limited Exam of RPV nozzle-to-shell Welds ML17272B0141993-04-28028 April 1993 Amend 1 to Vols 1-3 of ISI Program Plan. ML17289B2621993-02-22022 February 1993 Rev 1 to LTI7.4, Operations Liaison Responsibilities. ML17289B1931993-01-31031 January 1993 Offsite Dose Calculation Manual. ML17289A7811992-07-31031 July 1992 Revised Plant Procedures Manual Including Rev 10 to 13.8.2, Backup Emergency Dose Projection Sys Operations & Rev 7 to 13.11.1, Recovery Manager Duties. ML20097H7511992-04-23023 April 1992 Plant Procedure 10.25.89, One Hour - Three Hour Fire Barrier Installation ML17289A5031992-04-0101 April 1992 Washington Nuclear Plant - 2 Licensed Operator Requalification Program Corrective Action Plan Resolution Documentation. ML17286B1791991-11-21021 November 1991 Rev 4 to Pump & Valve Inservice Test Program Plan,WPPSS-2. ML17286A9051991-06-28028 June 1991 Odcm. ML17286A7381991-04-30030 April 1991 Revised Plant Procedures Manual Including,Procedures 13.7.7, 12.7.8,13.8.1 & 13.11.15 ML17286A4971990-12-0505 December 1990 Revised Epips,Including Rev 8 to 13.8.2,Rev 10 to 13.10.9, Rev 8 to 13.11.13,Rev 8 to 13.14.1,Rev 6 to 13.14.3,Rev 10 to 13.14.4 & Rev 7 to 13.14.9 ML17285B0621990-02-26026 February 1990 Amend 7 to Odcm. ML17285B0501990-02-22022 February 1990 Rev 6 to Plant Procedures Manual 13.8.2, Manual Offsite Dose Calculations. W/900222 Ltr ML20066K0451989-03-28028 March 1989 Rev 5 to Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii ML17285A2621988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML17285A2511988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML20090M2951987-11-17017 November 1987 Rev 4 to FATE-84-100, Vipre Code Maint Procedures Manual ML20236N3071987-11-0606 November 1987 Corrected Page 16 of Rev 7 to Procedure 13.14.2, Process for Determining Protective Action Recommendations & Protective Action Decisions ML17279A5931987-10-0808 October 1987 Rev 3b to Pump & Valve Inservice Test Program Plan. ML17284A3901987-06-30030 June 1987 Draft A-3453-87-6, Washington Nuclear Plant 2 Generic PRA- Based Insp Plan. ML17278B1221986-11-17017 November 1986 Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency). ML20215B7551986-07-24024 July 1986 Rev 3 to NDE & I Instruction Qci 6-4, Ultrasonic Exam BWR Nozzle Inner Radius ML20215B7631986-03-20020 March 1986 Rev 3 to NDE & I Instruction Qci 6-13, Ultrasonic Exam of Piping Welds (Manual) ML17278A5681986-01-0606 January 1986 Rev 5 to Emergency Plan Implementing Procedure 13.14.7, Emergency Training. ML17278A5341985-12-20020 December 1985 Rev 3a to Pump & Valve Inservice Test Program Plan. ML17278A4731985-11-0101 November 1985 Revised Emergency Procedures,Including Rev 1 to Procedure 5.0.0, Emergency Procedure General Precautions, Rev 0 to Procedure 5.0.1, Emergency Operating Procedure Flow Chart & Rev 1 to Procedure 5.1.3, Reactor Power Control. ML17278A5491985-09-24024 September 1985 Rev 0 to Procedure Tp 8.6.6, Special Test Procedure for Tdas Class 1E Isolators. ML20133N3611985-09-0909 September 1985 WPPSS-2 Emergency Preparedness Exercise Manual for 850909-13 ML20129B5491985-05-0606 May 1985 Vol 1 of Rev 0 to Inservice Insp Program Plan ML17278A4291985-03-20020 March 1985 Rev 1 to Operating & Engineering Test Procedure 8.2.92, UHS Performance. ML17277B6461985-03-0505 March 1985 Amend 4 to 85-01, Preservice Insp Program Plan, Vols 1-4 ML17277B3101984-02-29029 February 1984 Control Room Design Review Program Plan. ML17277B3091984-02-17017 February 1984 Function & Task Analysis of Emergency Operating Procedures. ML17277B7331983-12-28028 December 1983 Rev 2 to 23A1900AA, RHR Sys. ML17277B0401983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.3.8, Equipment Clearance & Tagging. ML17277B0421983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.5.1, Tech Spec Surveillance Testing Program. ML17277B0361983-11-0707 November 1983 Rev 5 to Administrative Procedure 1.3.1, Standing Orders/ Night Orders. 1999-08-27
[Table view] |
Text
FUNCTION, AND TASK ANALYSIS CF THE WNP-2 EMERGENCY OPERATING PROCEDURES
" WASHINGTON PUBLIC POWER SUFPLY SYSTEM 8402280229 840217 PDR ADDCK 05000397,, F,'PDR Ij TABLE OF CONTENTS
1.0 INTRODUCTION
.~l~~~~~~~~~1~~~~~t~~~~1 2.0 DEFINITIONS.
~~~~~~~1 3.0 METHODOLOGY.
~~~~~~~3 3.1 General......
~~~~~~~3 3.2 Identification of Princial Control Functions.........
4 3.3 Identification of Decision and Action Functions.......
5 3.4 Decision Analysis.3.5 Action Analysis.~~~~~6~~~7 3.6 Classification of Information................
8 4.0 AFPLICATION.
9 5.0 SLWARY.~~~~~~~~~~~~10 l.0 INTRODUCTION This docuoant describes a methodology f'r function and task analysis of WP-2 EOPs.Applications for the results of the analysis are also dis-cussed.2.0 DEFINITIONS Action Function: An operator function involving a con-scious movement, operation of con-trois, or execution of a series of procedural steps.Example: "Inject boron into the RPV with SLC." Control Requirement:
The specific controls required to en-able the operator to accomplish an action.Examples: Pump breaker con-trol switch, valve control switch, selector switch.Decision Analysis: A form of task analysis in which ope-rator decisions are identified and systematically examined to identify information requirements.
Page 1 of 11 Decision Function: An operator function involving a determination, evaluation, or judge-ment through which a procedural branch path is selected.Example: " f sup-pression pool temperature cannot be maintained below the Heat Capacity Temperature Limit..." Function: A higher order activity by which the plant operating crew meets the objec-tives of the operating procedures.
Within the context of this document, functions include decisions and actions.Information Requirement:
Knowledge of system or plant status required as an input to a decision.Examples: Pump status, breaker stat-us, valve lineup status, RPV water level status.Page 2 of 11 Instrum ntation Requirement:
Specific parameters, displays, and design characteristics required to fulfill an information requirement.
Example: Pressure indicator with a range of 0-150 psig.Task: A well defined subdivision of a func-tion;a specific activity contributing toward the accomplishment of a func-tion.Examples: Closing a valve, tripping a breaker.Task Analysis: A systematic process by which operator tasks are identified and examined in terms of the conditions, control, in-'trumentation, skills, etc.associated with the task.3.0 METHODOLOGY 3.1 General The EOPs specify the emergency functions of the plant-operating crew.Through analysis of these functions and their constituent tasks, control and information requirements necessary to support the performance of the EOPs will be determined.
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The function and task analysis of the,EOPs will be conducted in the following steps: (1)Principal control functions will be ide<<tified.
(2)Decision and action functions will be identified for each prin-cipal control function.(3)Control and information requirements will be identified for each decision and action function.The result of the function and task analysis will be identification and application of action and decision functions and the control and information requirements necessary to performing the procedures.
3.2 Identification of Princi al Control Functions The new, symptomatic BWR EOPs typically define principal control functions.
These functions generally correspond to the grouping of procedural steps within the EOPs.Examples include RPY water level control, reactor power control, suppression pool level control, and primary containment pressure control.Page 4 of ll
'I~~
3.3 Identification of Decision and Action Functions-The EQPs specify performance of the principal control functions in 8 series of procedural steps containing decision and action func-tions.These decisions and action functions will be separately identified for analysis in terms of control and information require-ments.To facilitate subsequent analysis, the decision and action functions identified in the functional analysis will be classified as follows: Dl-Decisions which require comparison of a parameter to a pre-determined value or limit, such as"above" or"below".D2-Decisions related to system status, such as"open" or"initi-ated".03-Decis'ns based upon a procedural requirement, such as"If Boron Injection is required".
04-Decisions that are judgmental or which require an estimation of the future state of parameters or system status.Examples in-elude"If RPV water 1 vel cannot be maintained","If RCIC is available", and"If adequate core cooling can be assured".Page 5 of 11 Al-Actions that are not directly conditioned upon an explicit decision process, such as"Open the discharge valve" or"Monitor RPV water level".A2-Actions that are directly based on the less complex decision functions (type Dl and D2), such as"If pressure is below 10 ps'.g then shop the pump" A3-Actions that are directly based on the more complex decision functions (type DZ and D4), such as"If reactor power is above the AFRM downscale trip or cannot be determined, then trip the recirculation pumps".3.4 Decision Anal sis Before making a,decision, the operator oust gather and process a set of information.
This set includes both information explicitly identified in the step itself such as plant variables, system para-meters, and associated limits, and certain supplemental or implicit information.'mplicit information may be required to varying degrees, depending upon existing plant conditions, and on system or component availability at the time the decision must be made.'age 6 of ll
~~In the decision analysis process, each identified decision function will be examined in terms of the information, both explicit and implicit, the operator requires to effect an evaluation of plant a conditions and make"he decision.Explicit information needs may be obtained directly from the EOP step itself.Implicit information needs must be derived through analysis of the operator's expected response, system characteristics, and procedural requirements.
Actions specified in the EOPs generally require the performance of a particular act or the execution of a series of procedural steps.In the task analysis process, each identified action function will be examined in terms of its constituent tasks.Controls gequired for the performance of each task may then be identified using available technical reference material, operator input, and installed equip-ment.In addition to identifying control requirements, analysis of operat-or actions will also identify a set of implicit information require-ments.Once the action has been taken, the operator must obtain feedback information to verify that the action was performed pro-perly and that it resulted in the desired effect.This feedback Page 7 of 11 information may be the same set of information processed to make the decision leading to the action, an independent set, or more likely, ari intersecting set.It necessarily includes considerable informa-tion pertaining to system status, system availability, component operating status and system performance., All of this information falls into the category of implicit information.
3.6 Classification of Information To facilitate subsequent analysis, the information requirements identified through the analysis of operator decision and action functions wiH~be classified as follows: Il-Directly measurable plant.parameters, such as RPY water level, suppression pool temperature, or RCIC steam.line pressure.I I2-Parameters derived from one or more type Il parameters, such as RPV saturation temperature or the Meat Capacity Temperature Limit.I3-Type Il parameters as a function of time, such as RPV cooldown rate.I4-Parameters related to system status, such as valve position or breaker status.Page 8 of 11
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~~As previously discussed, the information may be explicit, implicit, or both, depending upon the decision or action function which requires it.4.0 APPLICATION A sample functional analysis is illustrated in Figure 1.The format and content shown is for illustrative purposes only and is not designed to be prescriptive.
The results of the function and task analysis will be used in the follow-ing applications: (a)Identifying operator information and instrumentation requirements for refining the Graphics Display System (SPDS).I (b)In conjunction with the DCRDR, identifying operator control, infor-mation and instrumentation requirements for emergency operating procedures.(c)Verifying provision of instrumentation under Regulatory Guide 1.97.(d)Refining plant-specific emergency operating procedures.
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~~~q (e)Identifying performance and knowledge requirements f'r development of operator training programs.5.0 RMMARY Through functional analysis of the WNP-2 emergency operating procedures,'principal control functions and specific emergency response action and decision functions will be identified.
The identified action and deci-sion functions will then be analyzed to detemine the information and con-trol requirements necessary to support the accomplishment of these func-tions.The information and control requirements thus determined are used to define or prioritize requirements for procedures, training, and con-trol room system improvements.
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~ele<<ye>>II preswro ate OOI<<0 Ol Nsno tl>>oryeet I spray lnl tl atl>>l pyeswpo llolt)e 12Figure X.Sarple Functiona1 Analysis Page H.ak 11