Rev 1 to Emergency Plan Implementing Procedure FNP-0-AP-74, Emergency Response Procedures VerificationML20213H072 |
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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 8705190129 |
Download: ML20213H072 (12) |
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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
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FNP-0-AP-74 '
ATTACHMENT 2 EMERGENCY RESPONSE PROCEDURES VERIFICATION 1 INTRODUCTION
~
1.1 PURPOSE The purpose of this attachment is to establish the administrative process used in the verification of the emergency response procedures (ERP's). This process governs the evaluation performed to confirm the written correctness of the procedures by addressing the following objectives:
ERP's are technically correct, i.e. they accurately _ reflect plant specific guidelines and other ERP source documents.
ERP's are written correctly, i.e. they accurately reflect the Writers Guide.
The language and level of information' presented in the ERP's are compatible with the qualifications, training and experience of the operating _ staff.
1.2 APPLICABILITY This procedure applies to ERP implementation and revisions for Unit I and Unit 2 of the Farley Nuclear Plant.
- t. AsiERENCES 2.1 Emergency Operating Procedures Verification Guideline INPO 83-004-2.2 Farley Nuclear Plant Emergency Response Procedure Writers Guide. FNP-0-AP-74 3 DEFINITIONS Emergency Response Procedures (ERP's) - Plant procedures directing operator actions necessary to mitigate the consequences of transients and accidents that cause plant parameters to exceed reactor protection system setpoints, engineered safety features setpoints, or other appropriate technical limits.
Emergency Response Guidelines (ERG's) - Guidelines that provide sound 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.
8705190129 870512 Page 1 of 3 Gen. Rev. 1 PDR ADOCK 05000348 F PDR -
FNP-0-AP-74 Attachment 2 ERP Verification - The evaluation performed to confirm the written correctness of the ERP's and to ensure that the generic and/or plant-specific technical aspects have been properly incorporated.
ERP Written Correctness - Proper incorporation of information from the writers guide for ERP's and other appropriate administrative policies into the ERP's.
Symptoms - Displayed plant characteristics that directly or indirectly indicate plant status.
4 RESPONSIBILITIES 0
4.1 Operations Superintendent The Operations Superintendent shall have overall responsibility b and approval authority for ERP verification. #
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 verification process.
4.3 Additional Personnel As deemed necessary by the Operations Superintendent, additional assistance to ensure technical accuracy and written correctness of the ERP's will be provided by the Technical Superintendent, Training Director and Nuclear Engineering Technical Support d"; , r r~=" r .
5 ERP VERIFICATION PROCESS The process of ERP verification consists of four phases: preparation, verification, resolution, and documentation.
5.1 Preparation Phase The preparation phase consists of the following activities:
Designate persoanel to conduct the verification Obtain and review the ERP source documents 5.1.1 Designate Personnel The Emergency Response Procedure Coordinator, under the direction of the Operations Superintendent, shall appoint the necessary personnel as evaluators to conduct the verification. Personnel should be appointed based on operating experience and understanding of plant hardware, the ERG's and the writers guide.
Page 2 of 3 Gen. Rev. 1
FNP-0-AP-74 Attachment 2 5.1.2 ERP Source Docum, ente Evaluators shall determine and list the ERP source documents on Figure 1 of the ERP Verification Forms.
These documents shall be obtained, verified to be current and complete and shall be reviewed _by the personnel conducting the verification.
5.2 Verification Phase In the verification phase the evaluator shall:
Complete the ERP verification cover page Figure 1.
Make a general review of the ERP using the procedure-specific portion of the evaluation criteria (Table 1) and source documents.
Make a step-by-step review of the ERP using the step-caution-note-specific portion of the evaluation criteria (Table 1) and source documents.
For all discrepancies identified, complete the discrepancy information on the Discrepancy Sheet (Figure 2) and if possible, provide a proposed resolution. Additional discrepancy sheets shall be utilized as required.
Complete.the verification completion sheet of the ERP Verification Forms (Figure 3) and forward the verification package with the cover and discrepancy sheets to the Emergency Response Proceda es. c r-dinatot 5.3 Resolution Phase In the resolution phase, the Emergency Response Procedures Coordinator shall:
Review the evaluator's comments and coordinate resolution of any conflicts between the writer's and evaluator's comments.
Coordinate documentation of final discrepancy dispositions (Figure 4).
Update applicable source documents and procedures with approved solutions. ,
Upon completion of the verification of each procedure, forward the completed package to the Operations Superin-tendent for review and validation determination.
5.4 Documentation Phase l The documentation developed throughout the process will be maintained in accordance with FNP-0-AP-4. 1 Page 3 of 3 !
Gen. Rev. 1
)
FNP-0-AP-74 Attachment 2 FIGURE 1 ERP VERIFICATION Page of ERP TITLE:
ERP NUMBER: REVISION:
ERP SOURCE DOCUMENTS REQUIRED:
1.
2.
3.
4.
5.
. 6.
7.
EVALUATOR (S):
Gen. Rev. 1
FNP-0-AP-74 Attachment 2 FIGURE 2 ERP VERIFICATION ERP REV DISCREPANCY SHEET Page of_
STEP, CAUTION, NOTE-SPECIFIC VERIFICATION STEP NO.
CAUTION OR NOTE DISCREPANCY BASIS PROPOSED RESOLUTION m, .
-e. * .-. . - = ma _.a_. ,m Gen. Rev. I
FNP-0-AP-74 Attachment.2 FIGURE 3 ERP VERIFICATION ERP REV VERIFICATION COMPLETION Page of Verification Completion Date:
Performed by:
All actions required by the verification have been completed and approved.
Date:
Gen. Rev. 1 l
E'NP-0-AP-74 Attachment 2 FIGURE 4 DISCREPANCY DISPOSITION STEP / NOTE /CAUTI0h NUMBER DISCREPANCY:
DISPOSITION:
__o-Gen. Rev. I
, - . . . . - - . . . . . . - . . . _ . _ . . . . . _ . _ _ . . . - . . _ . - .,.._.._...a- _.
FNP-0-AP-74 Attachment.2 TABLE 1 EVALUATION CRITERIA CHECKLIST Writers Guide Section Area Reference
- I. . PROCEDURE-GENERAL
- A. Written Correctness
- 1. Legibility
- a. Are the printed borders visible 5.8.3 on all procedure pages?
- b. Are the text, tables, graphs, 5.5 l figures, and charts legible to the evaluator?
- 2. ERP Format Consistency
- a. Do the following sections exist in 4.1 l
! each ERP:
i_ 1. TITLE
- 2. PURPOSE
.3 . 5YMPTOMS i 4. OPERATOR ACTIONS
- b. Is the operator actions section 4.1.3 I presented in a dual-column format?
- c. Is the page layout consistent with 5.8 l the sample page format?
1
- 3. Identification Information
- a. Is the procedure title descriptive 4.1 l of the purpose of the procedure?
- b. Does the Title Page correctly 3.1 l provide the following:
(1) procedure title (2) procedure number (3) unit number (4) revision number s
i
! Page 1 of 5 Rev. 2 4
-,.m.. - --,,,__,..,..~.,--._..-...~.-_m,...r_-,-..m_, - . . - . ~ . . - . , _ _ _ . ...~-.~.m ..,_.m. , - --m,.-..._- ...m.. - _ _ . -
FNP-0-AP-74 Attachment 2 TABLE 1
- c. Does each page correctly provide 3.4 the following:
(1) procedure designator (2) revision number (3) Page number / number of pages
- d. Does the procedure have all its pages in the correct order?
II. STEP, CAUTION, NOTE-SPECIFIC A. Written Correctness
- 1. Information Presentation
- a. Are instruction steps numbered 4.1.4 l correctly?
- b. Are operator-optional sequence 4.1 5 steps identified?
l
- c. Are instruction steps constructed to comply with the following:
(1) Steps deal with only one idea. 5.1.2 (2) Sentences are short and simple. 5.1.1 (3) Opa star actinns era =rac3 fi- 5.1.1 cally =L. Leu.
(4) Objects of operator actions 5.2.3 are specifically stated.
(5) Objects of operator actions 5.2.3 are adequately stated.
(6) If there are three or more 5.3.2 objects, they are listed (and space is provided for operator check-off).
(7) Punctuation and capitalization 5.3.6, 5.7.2 are proper.
(8) Abbreviations are correct and 5.3.7 understandable to the operator.
- d. Do instruction steps make proper 5.3.8 I use of logic structure?
, e. When an action instruction is based 5.4.4 l on receipt of an annunciator alarm, is the setpoint of the alarm identified?
Page 2 of 5 Rev. 2
FNP-0-AP-74 Attachment.2 TABLE 1
- f. Are cautions used appropriately? 4.1.6
- g. Are cautions placed properly?. 4.1.6 l
- h. Are cautions constructed to 4.1.6 l comply with the following:
(1) They do not contain operator 4.1.6 actions.
(2) They do not use extensive 4.1.6 punctuation for clarity.
(3) They make proper use of emphasis. 5.7
- i. Are notes properly used? 4.1.7 l
- j. Are notes properly placed? 4.1.7 l
- k. Are notes worded so that they do 4.1.7 l not contain operator actions?
- 1. Are numerical values properly 5.4.1 l written?
- m. Are values specified in such a way 5.4.5, 5.4.6 l that mathematical operations are not required of the user?
o Tc $ *able or graph provided in the procedure for necessary operator calculations?
- o. Are units of measurement in the ERP 5.4.2 l the same as those used on equip:nent?
- 2. Procedure Referencing and Branching
- a. Do the referenced and branched 5.6 {
procedures identified in the ERP's exist for operator use?
- b. Is the use of referencing minimized? 5.6.1 l
- c. Are referencing and branching 5.6 l instructions correctly worded?
(1) "go to" (branching)
(2) " refer to" (referencing)
- d. Do the instructions avoid routing 5.6 l users past important information such as cautions preceding steps?
Page 3 of 5 Rev. 2
FNP-0-AP-74 Attachment 2 TABLE 1
- e. Are the exit conditions compatible 5.6 with the entry conditions of the referenced or branched procedure?
B. Technical Accuracy
- 1. Entry conditions or Symptoms Information
- a. Are the entry conditions of the ERG l listed correctly?
- b. If additional entry conditions have been added, do they comply with the following:
(1) appropriate entry conditions for which the ERP should be used (2) not excessive
- 2. Instructional Step, Caution, and Note Information
- a. Are ERP/ ERG differences:
(1) documented .
- (2) explained
- b. Is the ERG technical foundation !
(strategy) cf.a a;."8 by the Td ?r O changes in ERP steps, cautions, or notes:
(1) elimination (2) addition (3) sequence (4) alteration
- c. Are correct plant-specific adaptations incorporated per ERG:
(1) systems (2) instrumentation (3) limits (4) control (5) indications
- d. Have licensing commitments applicable to ERPs been addressed?
j ___
- e. Are differences between the licensing commitments and the ERPs or ERGS documented?
Page 4 of 5 Rev. 2
- _ _ . _ _ . _ .. _ ...-__ _ ,___ _ _ _ . . . . _ . , _ , _ _ _ , _ _ , _ . _ _ . . _ _ . . _ _ _ . . _ . _ . _ . _ . ~ . . _ . _ _ .
FNP-0-AP-74 Attachment-2 J
TABLE 1
)
s 3; Quantitative Information
- a. Do the quantitative values, including tolerance bands, used in the ERP comply with applicable ERP source document?
- b. Where ERG values are not used in the ERP, are the ERP values computed accurately?
- c. When calculations are required by the I ERP, are equations presented with sufficient information for operator use?
- 4. Plant Hardware Information
- a. Is the plant hardware specified in the ERP available for operator use:
(1) equipment (2) controls ,
(3) indicators
~-
(4) instrumentation 9
4 j
'I i
i Page 5 of 5 Rev. 2 1
- . . . . - , -.--.._,.._.,.c.,. . _ - _ . - - - . - - . _ , , . , , _ . - _ - , . ..- . . - . - . - , _