Rev 2 to Emergency Plan Implementing Procedure FNP-0-AP-74, Emergency Response Procedures Verification| ML20213H101 |
| Person / Time |
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| Site: |
Farley  |
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| Issue date: |
05/12/1987 |
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| From: |
ALABAMA POWER CO. |
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| To: |
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| Shared Package |
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| ML20213H063 |
List: |
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| References |
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| FNP--AP-74, FNP-0-AP-74, NUDOCS 8705190137 |
| Download: ML20213H101 (7) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B1791999-10-0404 October 1999
Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions
ML20209B8161999-06-30030 June 1999
Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS
ML20196J8731999-06-30030 June 1999
Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation
ML20207D6421999-05-31031 May 1999
Proposed Conversion to ITSs for Chapter 3.3
ML20206H0001999-04-30030 April 1999
Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS
ML20206F4421999-04-30030 April 1999
Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8
ML20206B4721999-04-21021 April 1999
Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F
L-99-170, Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with1999-04-20020 April 1999
Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with
ML20205S9641999-04-20020 April 1999
Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with
ML20205G8571999-04-0202 April 1999
Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90
ML20205A2401999-03-19019 March 1999
Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation
ML20205A3101999-02-28028 February 1999
Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program
ML20207C2451999-02-22022 February 1999
Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details
ML20203A7711999-02-0303 February 1999
Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4
ML20205T0011998-12-23023 December 1998
Rev 17 to FNP-0-M-011, Odcm
ML20205T0081998-12-23023 December 1998
Rev 18 to FNP-0-M-011, Odcm
ML20196B6241998-11-20020 November 1998
Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0
ML20155J4561998-11-0606 November 1998
Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement
ML20154K2521998-10-12012 October 1998
Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety
ML20151V6991998-09-11011 September 1998
Snoc Jm Farley Nuclear Plant Startup Test Rept Unit 2 Cycle 13. with
ML20237D4111998-08-20020 August 1998
Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations
ML20217N4801998-05-0101 May 1998
Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs
ML20205S9971998-04-19019 April 1998
Rev 16 to FNP-0-M-011, Odcm
ML20217Q7261998-03-20020 March 1998
Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a
ML20202G1311998-02-12012 February 1998
Proposed Tech Specs Re Pressure Temp Limits Rept
ML20202F1121998-02-12012 February 1998
Revised Proposed Changes to TS Page 6-19a for Power Uprate
ML20198H3661998-01-0707 January 1998
Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied
ML20198E6621997-12-31031 December 1997
Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value
ML20198E3141997-12-30030 December 1997
Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances
ML20197B6691997-12-18018 December 1997
Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept
ML20212B1791997-10-31031 October 1997
1 SG ARC Analyses in Support of Full Cycle Operation
ML20211P5861997-10-16016 October 1997
Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F
ML20211J1501997-09-30030 September 1997
Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept
ML20217C0341997-09-25025 September 1997
Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage
ML20211A6891997-09-17017 September 1997
Proposed Tech Specs Re Primary Coolant Specific Activity
ML20216D0031997-09-0303 September 1997
Proposed Tech Specs Re Moveable Incore Detector Sys
ML20149K1001997-07-23023 July 1997
Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits
ML20148Q1041997-06-30030 June 1997
Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec
ML20148R7521997-06-30030 June 1997
Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis
ML20148K7501997-06-13013 June 1997
Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement)
ML20140A3931997-05-28028 May 1997
Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis
ML20148F2381997-05-27027 May 1997
Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends
ML20148E5921997-05-27027 May 1997
Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves
ML20138B9251997-04-23023 April 1997
Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing
ML20198T4921997-03-31031 March 1997
Small Bobbin Probe (0.640) Qualification Test Rept
ML20137H6091997-03-25025 March 1997
Proposed Tech Specs Re Primary Coolant Specific Activity
ML20136F8231997-03-0707 March 1997
Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements
ML20135C4941997-02-24024 February 1997
Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend
ML20135C6731997-02-24024 February 1997
Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems
ML20135C8641997-02-14014 February 1997
Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power
1999-06-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205T0011998-12-23023 December 1998
Rev 17 to FNP-0-M-011, Odcm
ML20205T0081998-12-23023 December 1998
Rev 18 to FNP-0-M-011, Odcm
ML20205S9971998-04-19019 April 1998
Rev 16 to FNP-0-M-011, Odcm
ML20138A3661996-04-25025 April 1996
Rev 15 to Procedure FNP-O-M-011, Offsite Dose Calculation Manual
ML20071P9561994-06-15015 June 1994
Rev 1 to FNP-0-ETP-4338, Svc Water Storage Pond Sounding Survey
ML20071Q2831994-03-0808 March 1994
Rev 1 to FNP-0-ETP-4381, Svc Water Storage Pond Piezometer Well Readings
ML20071Q3151994-03-0808 March 1994
Rev 1 to FNP-0-ETP-4389, Svc Water Storage Pond Dam Biennial Insp
ML20063H7681994-01-0101 January 1994
Rev 13 to Odcm
ML20071Q3551993-10-18018 October 1993
Rev 7 to FNP-0-ARP-8, Svc Water Structure
ML20071Q3661993-07-13013 July 1993
Rev 26 to FNP-1-ARP-1.1, Main Control Board Annunciator Panel a
ML20071Q3751993-06-24024 June 1993
Rev 8 to FNP-0-AOP-31.0, Loss of Svc Water Pond
ML20071Q3341993-01-29029 January 1993
Rev 0 to FNP-0-ETP-1035, Svc Water Dam & Structure Monthly Insp
ML20071Q4031993-01-0606 January 1993
Rev 8 to FNP-0-STP-125, Svc Water Bond Seepage Test
ML20126A1941992-12-0808 December 1992
Rev 2 to FNP-0-M-011, Odcm
ML20071Q3051992-05-12012 May 1992
Rev 0 to FNP-0-ETP-4384, Svc Water Pond Deformation Monument Readings
ML20071Q3871991-03-28028 March 1991
Rev 4 to FNP-0-STP-611.1, Spillway Channel & Structure Verification
ML20071Q3601991-03-28028 March 1991
Rev 4 to FNP-0-STP-611.0, Spillway Channel Insp
ML20059D8331990-08-30030 August 1990
Rev 76 to EPIP FNP-0-EIP-008
ML20059J1841990-08-24024 August 1990
Rev 10 to ODCM
ML20058P6261990-08-15015 August 1990
Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Classs 1,2 & 3 Components
ML20058Q1541990-08-15015 August 1990
Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components
ML20248H8811989-10-0404 October 1989
Rev 3 to FNP-1-M-042 Re Second 10-yr Interval Inservice Testing Program for ASME Code Class 1,2 & 3 Pumps & Valves
ML19325C6751989-09-25025 September 1989
Rev 8 to FNP-0-M-011, Odcm.
ML20244B4531989-04-0303 April 1989
Rev 7 to FNP-0-M-011, Odcm
ML20247C7721989-03-24024 March 1989
Rev 0 to FNP-2-M-068-1, Updated Inservice Insp Program for ASME Code Class 1,2 & 3 Components
ML20151U2981988-05-31031 May 1988
Suppl 1 to EQDP-ESE-68B, ATWS Mitigating Sys Actuation Circuitry in Amco Cabinet & Wall Mounted Hoffman Relay Enclosure
ML20151Y7341988-04-30030 April 1988
Westinghouse MT-SME-186, Background & Technical Basis for Handbook on Flaw Evaluation for Jm Farley Nuclear Plant, Units 1 & 2 Reactor Vessel Beltline & Nozzle to Shell Welds
ML20151R3301988-04-14014 April 1988
Rev 5 to General Ofc Emergency Implementing Procedure GOP-EIP-116, Emergency Operations Facility Shift Turnover
ML20151S0141988-04-12012 April 1988
Rev 4 to Offsite Dose Calculation Manual
ML20236T2641987-11-23023 November 1987
Draft Rev 0 to FNP-1-M-043, Second 10-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components
ML20150C2271987-09-18018 September 1987
Rev 4 to FNP-0-M-011, Offsite Dose Calculation Manual
ML20150C2201987-08-0505 August 1987
Rev 3 to FNP-0-M-011, Offsite Dose Calculation Manual
ML20214P4381987-05-27027 May 1987
Rev 0 to FNP-1-M-042, Second 10-Yr Pump & Valve Inservice Testing Program
ML20213H0721987-05-12012 May 1987
Rev 1 to Emergency Plan Implementing Procedure FNP-0-AP-74, Emergency Response Procedures Verification
ML20213H1011987-05-12012 May 1987
Rev 2 to Emergency Plan Implementing Procedure FNP-0-AP-74, Emergency Response Procedures Verification
ML20213A1771986-12-31031 December 1986
Rev 1 to Incident Investigation Manual
ML20214K4911986-07-11011 July 1986
Rev 2 to Offsite Dose Calculation Manual
ML20154C8681986-02-21021 February 1986
Revised Emergency Plan Implementing Procedures,Including Rev 40 to FNP-0-EIP-8, Emergency Communications & Rev 13 to FNP-0-EIP-26, Offsite Notification
ML20133H1181985-10-11011 October 1985
Attachment to Procedure FNP-85-1072 Re on-call Schedules Concerning Both Plant & Nuclear Generation Personnel. Schedules Effective 851001
ML20132E9211985-07-23023 July 1985
Corrected Rev 15 to Emergency Plan Implementing Procedure FNP-0-EIP-4, Chemistry & Environ & Health Physics Support to Emergency Plan
ML20133G9431985-05-21021 May 1985
Rev 1 to FNP-0-M-011, Offsite Dose Calculation Manual
ML20100H4071985-02-26026 February 1985
Public Version of Revised Attachments a & B to Procedure FNP-0-EIP-8 Re on-call Schedule for Plant Personnel for 1985 & on-call Schedule for Nuclear Generation Personnel for First Quarter 1985
ML20101L5421984-12-27027 December 1984
Rev 5 to General Ofc Emergency Implementing Procedure GO-EIP-131, Emergency Operations Ctr - Flintridge Emergency Equipment & Supplies
ML20101L5121984-12-27027 December 1984
Rev 9 to General Ofc Emergency Implementing Procedure GO-EIP-111, Corporate Activation & Notification Procedures
ML20101E6061984-12-14014 December 1984
Rev 1 to Emergency Implementing Procedure FNP-0-EIP-30, Post-Accident Core Damage Assessment
ML20198D3081984-09-24024 September 1984
Rev 3 to STD-P-05-003, Process Control Program for In-Container Solidification of 4 to 20 Weight Percent Boric Acid
ML20095D4101984-08-17017 August 1984
Revised Emergency Plan Implementing Procedures,Including GO-EIP-101 Re Corporate Emergency organization,GO-EIP-135 Re Emergency Plan Review & Rev & GO-EIP-120 Re Ref Guidance for Recovery Manager
ML20198D3171984-08-0606 August 1984
Rev 5 to STD-P-05-004, Progress Control Program for In-Container Solidification of Bead Resin
ML20093G4051984-07-17017 July 1984
Public Version of Rev 5 to Emergency Plan Implementing Procedure GO-EIP-111, Corporate Activation & Notification Procedures. W/Jm Felton 840717 Release Memo
ML20093G3561984-07-17017 July 1984
Public Version of Rev 29A to Emergency Plan Implementing Procedure FNP-0-EIP-8, Notification Roster
1998-04-19
[Table view] |
Text
.
FNP-0-AP-74 ATTACHMENT 3 EMERGENCY RESPONSE PROCEDURES VALIDATION 1.0 Introduction 1.1 Purpose The purpose of this attachment is to guide the administrative process used in the validation of the Emergency Response Procedures (ERPs).
1.2 Applicability This procedure applies to ERP validation before and after initial implementation for Unit 1 and Unit 2 of the Farley Nuclear Plant.
2.0 References 2.1 Emergency Operating Procedures Validation Guideline INPO 83-006.
2.2 Farley Nuclear Plant Emergency Response Procedures Writers Guide, FNP-0-AP-74, Attachment 1.
. 3.0 Definitions Emergency Response Procedures (ERP's) - Plant procedures directing operator actions necess--v *e citicata the ;scrquences of transients and accidents that cause ptauc parameters to exceed reactor protection system setpoints, engineered safety features setpoints, or other appropriate technical limits.
Emergency Response Guidelines (ERG's) - Guidelines that provide round technical bases for the development of ERP's.
ERP Source Documents - Fundamental documents or records upon which ERP's are based.
ERP Technical Accuracy - Proper incorporation of generic and/or' plant-specific technical information from ERP source documents and plant hardware into the ERP's.
ERP Validation - The evaluation performed to determine that the actions specified in the ERP can be followed by trained operators to' manage the emergency conditions in the plant.
Scenario - A structural plan of parameter and plant symptom changes that provide operating cues for the conduct of assessment.
K oj4g Page 1 of 4 Gen. R m 2 PDR
FNP-0-AP-74 4.0 Responsibilities 4.1 Operations Superintendent The Operations Superintendent shall have overall responsibility for ERP validation.
4.2 Emergency Response Procedures Coordinator The Operations Superintendent shall designate an Emergency Response Procedures Coordinator who shall be responsible for coordination of the ERP validation process.
5.0 ERP Validation Process The process of ERP validation consists of three phases: ,
preparation, assessment and resolution.
5.1 Preparation The preparation phase consists of the following activities.
1
- Scenario preparation 5.1.1 Scenario selection
~
A set of scenarios to be used for validation shall be approved.by the Operations Superintendent. The scenarios selected shall be sufficient to provide reasonable assurance that operators s __ _. ..
emergency conditions using the ERP's and that ERP's are operationally correct. It is not intended or desireable that scenarios be selected to individually perform each procedure. Instead scenarios which integrate the performance and interaction of the ERP's as a whole should be utilized. As a minimum sufficient scenarios shall be selected to demonstrate satisfactory operator response and control over the following emergency conditions.
' Reactor Trip
' Loss of Coolant Accident
' Major Steam Break
, ' Loss of Offsite Power 4
'A severe (red path) challenge to any critical safety function.
Page 2 of 4 Gen. Rev. 2
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FNP-0-AP-74 5.1.2 Scenario preparation For each scenario a scenario cover page shall be prepared (Figure 1). The cover page shall include the general scenario description, expected ERP's to be used, the initial plant conditions and the desig-nated evaluator. Following the cover page the 3
expected sequence portion of the scenario evaluation form will be completed (Figure 2) using as many sheets as necessary. The expected sequence shall specify the procedure and step number sequentially listed in the assumed order of performance for the associated
, scenario. The expected sequence will include cautions and note performance and 'shall detail expected transfers between procedures. For scenarios in which more than one sequence of performance is possible, an expected sequence shall be prepared for each alternative sequence.
During the scenario assessment phase the evaluator shall then utilize the associated sequence chosen.
5.2 The assessment phase consists of the following activities.
' Crew Briefing
- Scenario Performance and Evaluation
- Crew Debriefing 5.2.1 Crew Briefing
. The d. cd r, -? " slu tor shall brief the operating crew on the validation process and how the assessment
' will be conducted. During crew briefings general familiarization with the Emergency Response Procedures and presentation of initial plant conditions shall be conducted. Discussion of the specific scenario to be utilized however should be avoided to preclude "preprograming" the operator response .
5.2.2 Scenario Performance and Evaluation Each scenario shall be run on the plant simulator.
During the scenario performance the designated evaluator shall complete the evaluation portion of the scenario evaluation form. Each step, Note and Caution shall be evaluated in the categories of operational correctness, useability / understand 4bility, and plant response.
Additional guidance in assessing these categories is contained on the scenario evaluation form. If any additional actions not contained in the procedures are necessary the evaluator shall indicate this at j the appropriate location on the scenario evaluation fo rm .
i Page 3 of 4 Gen. Rev. 2 4
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FNP-0-AP-74 During performance of the simulator run, interaction between the operating crew and the evaluator should be minimized. It is permissible for the evaluator to resolve any obvious clerical errors or to provide information relating to parameters not observable from within the. control room. Any corrections required will be noted on the scenario evaluation form. If an alternative sequence other than one of the expected sequences is selected by the operating
- crew it is permissible for the evaluator to redirect the scenario to one of the expected paths. In such circumstances however the initial selection by the operating crew shall be documented on the scenario evaluation form for subsequent review during the resolution phase.
5.2.3 Crew Debriefing 8
Immediately following completion of the simulator run a crew debriefing shall be conducted. The designated evaluator shall request any procedure problems noted by the operating personnel. Problems mentioned shall be documented in the comments section of the scenario evaluation form adjacent to the associated steps. Upon completion of comments by the operating crew, the evaluator may solicit comments regarding potential problems he identified during the simulator run. All valid discrepancies shall also be included on the scenario evaluation form.
1, ' ad an The designated evaluator will review all comments and discrepancies. All valid discrepancies shall be recorded on a discrepancy resolution form (Figure 3) along with a proposed resolution. All discrepancy resolution sheets along with the scenario cover page and scenario evaluation forms shall be forwarded to the Emergency Response Procedure Coordinator.
The Emergency Response Procedures Coordinator shall coordinate the selection of final resolution for all discrepancies and 4
the preparation of any procedure revisions required.
Upon completion of all scenarios the scenario packages shall be forwarded along with the updated Emergency Response -
Procedures to the Operations Superintendent for final review and approval.
i r
t i Page 4 of 4 Gen. Rev. 2
2 FNP-0-AP Attachment 3 FIGURE 1 ERP VALIDATION Page of
, (cover page) s .ERP TITLE:
ERP NUMBER: REVISION:
DATE:
SCENARIO DESCRIPTION:
1
)
1 i'
I J
1 4
i j
j . . .
i t
t ,
i 1
INITIAL PLANT CONDITIONS:
i' s
4 l
I EVALUATOR (S)
, t 4
i ,
Approved
,t i
i N
i
- Gen. Rev. 2 i
1
. , - = . - - _ . _ . . . - - . , _ . - - - - - _ _- . _ , . . - - _ - . -
FNP-0-AP-74 Attachment 3 FIGURE 2 SCENARIO EVALUATION FORM Step Evaluation No Expected Step -Step - Plant Additional S:quence Operationally Useable / Response Actions Comments ERP/ Step correct Understandable as expected Required Y N Y N Y N Y N l
I i l l
l Operational Correctness: 1) Performed in expected sequence.
- 2) Performed in manner consistent with step presentation Usable / Understandable 1) Sufficient detail
- 2) Adequate feedback available
- 3) Compatible with plant layout, hardware and shift components
- 4) Figures, Tables, Notes and Cautions understandable Plant Response as 1) Sufficient contingencies to address plant systems expected 2) Plant response consistent with step intent
- 3) Plant response consistent with expected procedures branches
) additional actions 1) No missing information required to manage emergency cequired Gen. Rev. 2
FNP-0-AP-74 Attachment- 3 FIGURE 3 DISCREPANCY DISPOSITION STEP / NOTE / CAUTION NUMBER DISCREPANCY:
DISPOSITION: .
Gen. Rev. 2