ML20207S019
| ML20207S019 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/12/1987 |
| From: | Leonard J LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20207S020 | List: |
| References | |
| PROC-870312, NUDOCS 8703180431 | |
| Download: ML20207S019 (51) | |
Text
{{#Wiki_filter:. f SHOREHAM NUCLEAR POWER STATION Procedures Generation Package s I. INTRODUCTION ~ The Shoreham Nuclear Power Station Procedures Generation Package (SNPS PGP) has been prepared in order to describe the process for upgrading the Emergency Operating Procedures (EOPs) at Shoreham. The SNPS PGP consists of the following sections: o Plant Specific Technical Guidelines e Writers Guide for E0Ps e E0P Verification & Validation Program o E0P Training Program Each section describes the approach which will be followed as part of the overall E0P Upgrade Plan required by Attachment 1 of the Shoreham Operating License. This PGP has been developed in accordance with NUKEG 0737, Supplement 1, Item 7.2b. 7 / a 8703180431 B70312 PDR ADOCK 05000322 P PDR
a e SHOREHAM YUCLEAR POWER STATION Procedures Generation Package II. PLANT SPECIFIC TECHNICAL GUIDELINES The Plant Specific Technical Guidelines (PSTGs) will be developed by converting the Boiling Water Reactor Owners Group Emergency Procedure Guidelins (BWROG EPG) into a Shoreham specific technical guideline. The latest version of the BWROG EPG is currently Revision 4, which will be the source document for PSTG development. If subsequent revisions are published by the BWROG at a later time, LILCO will evaluate the need to revise the PSTGs to the new document. The methodology employed in converting the EPG to a Shoreham PSTG is as follows: o Collect plant-specific source documents - Shoreham Technical Specifications - Shoreham Safety Analysis Report - As-built plant drawings - Approved LILCO Nuclear Engineering Department Calculations - Shoreham Operating Procedures - Other special studies deemed appropriate e Translate EPG steps to SNPS PSTG steps - Delete systems / components not applicable to SNPS - Add all plant specific parameters e Justify all differences - Include a short written justification for each deviation from the EPG _2-
s SHOREHAM NUCLEAR POWER STATION Procedures Generation Package e Include references from the source docu=ents - all plant specific parameters - All justification for deviations The format illustrated in Figure II-1 will be utilized for the PSTGs. The Guidelines will be maintained as a Quality Assurance document in accordance with Shoreham Station Procedure 21.009.01, " Preparation, Review, Approval and Control of Plant Specific Technical Guidelines". The Shoreham PSTGs will be converted into Emergency Operating Procedures in accordance with the E0P Writer's Guide. Figure II-2 represents a simplified flow diagram showing how the BWROG EPG will be converted into the Shoreham E0Ps. I i 1 _-
e s SHOREHAM NUCLEAR POWER STATION Procedures Generation Packaga SHOREHM NUCLEAR POWER STATION Plant Specific Technical Guidelines RPV Control Guideline EPC Stes: RC/P-4 Wen the shutdown cooling RPV preseure interlock clears, initiate shutdown cooling tusing only those RER pumps not required to maintain RPV water level above [10 in. (RPV water level shutdown cooling interlock)] by operation in the LPCI mode). It shutdown coo 31ng cannot be established and turther cooldown is required, continue to cool down using one or more of the systems used for depressurization. SNPS PSTC Stept RC/P-4 Wen the shutdown cooling RPV pressure interlock clears, initiate shutdown cooling using only those RHR pumps not required to maintain RPV vater level above 12.5 in. by operation in the LPCI mode. If shutdown cooling cannot be established and further cooldown is requir~ed, continue to cool down using one or more of the systems used for depressurization. Justification for Differences / References RPV water level shutdown cooling interlock - Tech Spec Table 3.3.2. RC-26 Figure II-1.
e SHOREHAM NUCLEAR POWER STATION Procedures Generation Package BWROG EPG (Rev. 4) .Shoreham Station m Procedure, SP 21.009.01 n ~r SNPS PSTGs Shoreham E0P
- WritersGuide V
Shoreham Emergency Operating Procedures (Draft) v E0P V & V Program Resolution Yes E0P Formulated Discrepancy and approved ? IAW V6V Program No o SNPS Procedure Review Cycle - IAW SP 12.006.01 Figure II-2 Simplified Flow Path - E0P Upgrade Process e SHOREHAM NUCLEAR POWER STATION Procedures Generation Package III. WRITER'S GUIDE FOR EOPs The SNPS E0P Writer's Guide provides instruction on writing EOPs using good writing principles. The Writer's Guide promotes consistency among all E0Ps independent of the number of E0P writers. Information on the following topics is included in the SNPS E0P Writer's Guide: e E0P Text Preparation - Format - Instruction Step Length and Content e Flowchart Preparation - Logic Symbols - Functional Flow and Branching - Step Construction e Mechanics of Style - Punctuation - Abbreviations and Acronyms The SNPS E0P Writer's Guide has been written using the INPO Document 82-017 Emergency Operating Procedures Writing Guideline as guidance, and is appended to this PGP as Appendix 1. o SHOREHAM NUCLEAR POWER STATION Procedures Generation Package IV. E0P VERIFICATION AND VALIDATION PROGRAM E0P Verification will evaluate the written correctness and technical accuracy of the SNPS E0Ps. The verification process will also ensure that the human factors aspects presented in the Writer's Guide have been correctly applied. The SNPS verification process will address the following specific objectives: e The E0Ps are technically correct, e The E0Ps are written correctly. e The language and level of information presented in the E0Ps is compatible with the minimum number, qualification, training and experience of the operating staff. e There is a correspondence between the control room / plant hardware and the E0P. e The E0Ps are usable. 8 SHOREHAM NUCI. EAR POWER STATION Procedures Generation Package The Verification plan is based on the guidance provided in NUREG 0899 and INPO 83-004, " Emergency Operating Procedure Verifica:; ion Guideline", and will utilize a combination of table top review and slow walk and talk-through of the procedures by independent reviewers and operatir g crews. The review will consist of the following reviews: o Comparison of E0Ps with the requirements of the PSTGs. e Comparison of the E0Ps with the requirements of the SNPS E0P Writer's Guide e Tabletop review of the E0Ps by SNPS Operations personnel to initially assess usability and compatibility e Comparison of control room Instrumentation and Controls (I&C) with the references to I&C made in the E0Ps The step-by-step comparison of the E0Ps with the requirements of the SNPS PSTGs will ensure the completeness and technical accuracy of the E0Ps. Comparison of the E0Ps with the Writer's Guide will ensure written correctness and the incorporation of human factors engineering principles. The tabletop review by Operations personnel will identify early any potential problems that control room crews might have in accepting and adapting to the upgraded E0Ps. The control room walkthrough of the E0Ps will check each reference to I6C in the E0Ps against the control room labels displayed on the equipment. Additionally, units of measurement used in the procedures will be checked to ensure that they are consistent with those displayed on instruments. The verification process will be documented via checklists, discrepancy forms and a completion record, which will provide traceable history of the Verification effort. -s-
a SHOREHAM NUCLEAR POWER STATION Procedures Generation Package The SNPS E0P Validation Program will determine whether the actions specified in the E0Ps can be performed by trained operators to manage emergency conditions successfully. The validation process will evaluate the E0Ps against the following objectives: o The E0Ps are usable: 1.e., they can be understood and followed without confusion, delays and errors. e The presentation of language and level of information in the E0P is compatible with the minimum number, qualifications, training and experience of the operating staff. e That there is a high level of assurance that the procedures will work: 1.e., the procedures guide the operator in mitigating transients and accidents. l The SNPS validation process is modeled after INPO 83-006, " Emergency Operating Procedures Validation Guidelines". It includes the four phases of preparation, assessment, resolution, and documentation. The preparation phase will focus on the development of lists of expected operator actions and performance evaluation l guidelines for the scenarios to be used in exercising the E0Ps. During the assessment phase, the scenarios will be run on the SNPS simulator in real time j and as a slow paced walk and talk through. The control room operating crew will
s SHOREHAM NUCLEAR POWER STATION Procedures Generation Package use the E0Ps to restore the plant to a safe condition. Based on a debriefing of the operators and an analysis of videotapes of the simulator runs, any procedure-related errors will be identified'. The E0P discrepancies causing any ~ errors will be listed, and resolutions will be developed during the resolution phase. Documentation produced during the process will be collected and organized during the documentation phase to provide a traceable history of the validation effort. s SHOREHAM NUCLEAR POWER STATION Procedures Generation Package V&V Process Components NUREG-0899 V&V Objectives Verification Validation a. Technically correct e Comparison of PSTG and E0Ps (TT) b. Written _ correctly e Comparison of E0P Writer's Guide (TT) e Evaluation Criteria Checklist (TT) c. Compatible with e Review by operating e Evaluation during minimum number, shift complement slow-paced walk-qualification, train-in conjunction with throughs and "real-ing and experience tabletop review time" scenario of operating staff for objective "d" exercises (WT & SIM) (TT) d. Usable e Review by operating e Evaluation during shift complement to slow-paced walk-evaluate readability, throughs and "real-completeness, accuracy, time" scenario and convenience (TT) exercises (WT & SIM) e. Correspondence exists e Comparison of con-between procedures trol room instru-and control room / mentation and plant hardware controls (I&C) and E0P references to I&C (WT) f. Guide operators in e Evalur.tien of mitigating transients "real-time" scenario and accidents exercises (SIM) V&V Methods: TT - Table top - Individual or group evaluation WT - Walk-through - Step-by-step enactment of scenario operator actions without carrying out actual control functions SIM - Simulator - Control functions performed by operators in simulator Figure IV-1 Correlation between V&V Objectives and Process s SHOREHAM NUCLEAR POWER STATION Procedures Generation Package V. EOP TRAINING PROGRAM A formal E0P training program will be developed to support implementation of the upgraded E0Ps. The E0P writer will interface with the Office of Training to ensure a supportive program. This description outlines the approach to be used to train licensed Shoreham operators on the upgraded E0Ps and to ensure the operators are informed and knowledgeable of any future changes to the E0Ps. Training Program Goals The initial, overall training goals for the E0P training program are as follows: e to enable the operators to understand the structure of the E0Ps including the flowcharted version of the E0Ps e to enable the operators to understand the technical bases of the E0Ps e to enable the operators to have a working knowledge of the technical content of the E0Ps e to enable the operators to use the E0Ps under operational conditions Training program objectives to support these goals will be developed for each lesson plan. t s SHOREHAM NUCLEAR POWER STATION Procedures Generation Package Initial Training on Upgraded E0Ps The E0P training program will be established to instruct operators in the upgraded E0Ps. It will consist of classroom instruction, simulator control room walk-throughs, and real time simulator exercises as follows: o Classroom instruction sessions will be conducted. Included in the information to be presented during this section will be: - the logic behind the development of E0Ps - the process used to develop the E0Ps - the E0Ps themselves, including supporting technical and human-factors information e Simulator control room walk-throughs will be conducted. During this method of training, the team approach to using E0Ps will be stressed. This walk-through training will also concentrate on information flow and interactions of the operators in the control room, e Training on the EOPs will be conducted for all licensed operators using scenarios run on the Shoreham control room simulator. Training will be conducted with all operators performing their normal control room functions. Additf oral training will be conducted whereby the members of a crew alternate responsibilities. This additional training is important to promote understanding of the other operators' responsibilities in the overall conduct of the actions leading to enhanced communications within the control room.
s s SHOREHAM NUCLEAR POWER STATION l l l Procedures Generation Package 1 I Refresher Training All licensed operators will conduct control room walk-throughs and real time simulator exercises using the E0Ps during refresher training. The walk-throughs ~ will be conducted on the Shoreham simulator. Training on EOPs will be conducted in such a manner that each crew conducts the walk-throughs with each operator simulating the actions that he normally would be responsible for during an emergency incident. Licensed operators not assigned to a shift will participate in the walk-throughs as part of a control room crew. The plant training and operations staffs will participate in the development and execution of refresher training. The training staff is responsible for developing the scenarios, observing and evaluating the walk-throughs, and critiquing the results. Any additional training needs will be determined from the performance of the operators. The simulator exercises will be varied sufficiently to ensure the operators do not develop a set pattern of responses to incidents but are able to respond to the symptoms as they develop. Training on Revisions Training on minor procedure revisions will be conducted through a program of required readings (self-taught), preshift briefings, or lectures in the requalification program. Training on major revisions will be conducted by the use of classroom instruction and walk-throughs in the control room or on the Shoreham simulator. j 1
s SHOREHAM NUCLEAR POWER STATION Procedures Generation Package Inputs Into Training Program Changes Changes to supporting training material will be factored into updated lesson plans and student handouts. Operator feedback resulting from E0P verification, E0P validation, and training critique forms will be used to keep the training program and E0Ps current and relevant. l APPI21 DIX 1 SHORE!!AM NUCLEAR PCIfER STATION EMERGENCY OPERATING PROCEDURES WRITER'S GUIDE l t I i
s SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE TABLE OF CONTENTS
- 2. age 1.0 EMERGENCY OPERATING PROCEDURES WRITER'S GUIDE............................
1-1 1.1 Introduction........................................................ 1-1 1.1.1 Purpose...............................................'..... 1-1 1.1.2 How to Use This Guide..................................... 1-1 1.2 E0P. Designation System............................................... 1-1 .1.2.1 Numbering Scheme........................................... 1-1 1.2.2 Tit1e..................................................... 1-1 1.2.3 Revision Numbering Scheme................................. 1-1 1.3 E0P Structure....................................................... 1-2 1.4 Flowchart Preparation Guidelines.................................... 1-2 1.4.1 Identification and Numbering.............................. 1-2 1.4.2 Review and Approval....................................... 1-2 1.4.3 Lo g i c S ymb o l s............................................. 1-3 1.4.4 Entry Conditions........................................... 1-3 1.4.5 Action and Verification Steps............................. 1-3
- 1. 4. 6.
Retainment Steps........................................... 1-3 1.4.7 Decision Steps............................................ 1-5 1.4.8 Concurrent Steps.......................................... 1-5 1.4.9 Entry and Exit Points...................................... 1-5 1.4.10 Cau t ion s and }J a t e s........................................ 1-6 1.4.11 Functional Flow and Branching............................. 1-7 1.4.12-Step Numbering Scheme..................................... 1-7 1.4.13 Text Procedure Step Numbering Scheme....................... 1-7 1.4.14 Placekeeping Aid.......................................... 1-7 1.4.15 Readability Guidelines.................................... 1-7 1.4.16 Printed Operator Aids..................................... 1-8 1.5 Step Construction.................................................... 1-9 1.5.1 L eve l o f De t ai1........................................... 1-9 1.5.2 Step Sequencing............................................ 1-9 1.5.3 . Step Length and Content.................................... 1-10 1.5.4 Types of Steps............................................. 1-11 1.5.5 Logic Terms................................................ 1-12 1.5.6 Conditional Statements..................................... 1-13 1.5.7 Referencing and Branching................................. 1-15 1.5.8 Safety Parameter Display System References................. 1-16 1.5.9 Component Identification.................................. 1-16 1.5.10 Word Choice................................................ 1-16 1.5.11 Methods of Emphasis........................................ 1-17 1.6 Mechanics of Sty1e................................................... 1-17 1.6.1 Spelling.................................................. 1-17 1.6.2 Abbreviations and Acronyms................................ 1-17 1.6.3 Hyphenation................................................ 1-18 1.6.4 Punc t u a t ion............................................... 1 - 18 1.6.5 Acceptance Criteria and Calculations....................... 1-20 1.6.6 Numerical Values........................................... 1-20 i
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE TABLE OF CONTENTS (continued) ?.*L' 1.7 Text Preparation Guidelines......................................... 1-21 1.7.1 Procedure Organization.................................... 1-21 1.7.2 Section Numbering......................................... 1-21 1.7.3 Instruction Step Length and Content........................ 1-21 1.7.4 Use of Logic Terms......................................... 1-23 1.7.5 Cautions and Notes........................................ 1-23 1.7.6 Calculations............................................... 1-25 1.7.7 Figure, Table and Appendix Designation.................... 1-25 1.8 E0P Revisions and Updates........................................... 1-25 1.8.1 Review Requirements........................................ 1-25 1.8.2 Revision Process........................................... 1-26 APPENDIX A PLANNING GUIDANCE FOR THE PROCEDURE WRITER APPENDIX B SAMPLE DUAL-COLUMN FORMAT PROCEDURE l i l 11
t a ,o e SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.0 EMERGENCY OPERATING PROCEDURES WRITER'S GUIDE 1.1 Introduction 1.1.1 Purpose This document establishes format and content standards for the Shoreham Nuclear Power Station (SNPS) Emergency Operating Procedures (EOPs) and gives guidance to the E0P writer for the creation and revision of all E0Ps. 1.1.2 How to Use This Guide This guide was prepared to give the E0P writer guidance in preparing SNPS E0P's. The following process is recommended: a. Review Appendix A, which contains references and other information that will help plan the procedure (s). b. Then review Sections 1.2 and 1.3, which give an overview of the E0P system and the structure of the individual E0Ps. c. Then use Sections 1.4, 1.5, and 1.6 and the remaining appendices to draft the procedure (s). These sections deal with general guidelines, then action step construction, then specific points of style. 1.2 E0P Designation System 1.2.1 Numbering Scheme The numbering scheme for all SNPS Station Procedures is delineated in SP 12.001.01, "Index and Organization of Station Operations Manual." 1.2.2 Title The E0P titles are to be brief, yet descriptive. The flowchart format of the E0Ps enforces brevity. Two principles are to be used in titling E0Ps: a. The title should be 10 words or less. l b. Important words should be at or near the beginning of the title. 1.2.3 Revision Numbering Scheme Revisions of E0Ps are numbered sequentially in accordance with SP + 12.006.01, " Station Procedures - Preparation, Review, Approval, Change Review and Cancellation." l-1 1
e O e SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.3 E0P Structure The E0Ps consist of flowcharts and text. The flowcharts contain: a. Entry conditions b. Actions steps (to bring the plant to a stable condition, or to branch to another procedure that will do so) c. Exit criteria a 1.4 Flowchart Preparation Guidelines 1.4.1 Identification and Numbering A title block in the lower right corner of each flowchart will contain the E0P number, title, revision number, revision date, page number, and plant name. See Figure 1-1. PROCEDURE NO. PROCEDURE TITLE SHOREHAM NUCLEAR POWER STATION + REV 0 REV DATE XX/YY/ZZ Figure 1-1. Sample Flowchart Title Block 1.4.2 Review and Approval SNPS E0P Flowcharts shall be included as appendices to the written E0Ps. The Review and approval cycle for the written procedures shall be in accordance with SP 12.006.01, " Station Procedures - Preparation, Review, Approval, Change Review and Cancellation". Full-size E0P Flowcharts, derived from the appendices of the written procedures, shall include a signature block as shown in l Figure 1-2. DRAWN BY: DATE: REVIEWED BY: DATE: APPROVED BY: DATE: l i 1-2
l . o SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.4.3 Logic Symbols Figure 1-3 contains the standard flowchart symbols used in the E0Ps. 1.4.4 Entry Conditions The entry conditions or symptoms are generally brief noun phrases j that initiate the E0P actions. The entry conditions are located at 1 the top of each flowchart within entry condition symbols. The positioning of the symbols indicates to the operator whether any j one of the conditions is necessary before operator actions commence. See Figure 1-4. CONDITION CONDITION CONDITION t i ACTION Figure 1-4. Any one Condition Initiates Action 1.4.5 Action and Verification Steps In the flowcharts, action steps and verification steps are not differentiated in that both are shown as actions in an action step. symbol. See Figure 1-5. l l RESET... VERIFY... I I Figure 1-5. Identical Symbols Used for Action and Verification 1.4.6 Retainment (Override) Steps A retainment step gives operators information or contingency action conditions that they must remember while executing the steps that follow. See Figure 1-6. gr WHILt tufCUTINC THE FOLLeutwC titPS: IME SC#an CaN DE ptsti, SM S EP aa,3-CC Figure 1-6. Sample Retainment Step 1-3
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE ENTRY CONDITION (' } Contains the condition requiring entry into and ) execution of this procedure. ACTION STEP Contains the procedural actions. 'Also defines contingency action steps (IF...THEN). RETAINMENT STEP Contains information or contingency action conditions the operator must remember while performing the steps that follow. DECISION STEP Contains a question to which the answer determines the next step. EXECUTE CONCURRENTLY Requires the operator to enter the designated I se es. ora.e ;> procedure and perform the stated actions while continuing in the existing flow path. ENTRY ARROW Designates the entry point for this procedure SP 29. 923. 01 )>-- when directed by the procedure step in the XX-Y arrow. EXIT ARROW ---{ SP 29. 9 23. 81 )> Requires the operator to leave the flow path at that point. If required, it contains the XX-Y procedure number and/or step that must then be entered. OPERATOR CAUTION OR NOTE Indicates that a specific caution or note is 8 applicable to the step. The number in the symbol corresponds to a statement at the bottom of the procedure. SAFETY PARAMETER DISPLAY SYSTEM (SPDS) Indicates that the SPDS would be applicable to 3 the step. The number in the symbol corresponds to the "page(s)" on the SPDS. EMERGENCY PLAN PROCEDURE EPP Requires the operator to enter the designated I emergency plan procedure and perform the stated actions while continuing in the existing flow path. Figure 1-3. Flowchart Symbols 1-4
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.4.7 Decision Steps All decision steps require a choice between only two opposite possibilities, for example, yes/no or high/ low. These steps are phrased as questions, but are not followed by question marks. See Figure 1-7. h u,.. Quin'!!"=ci.i u.., N nu. Figure 1-7. Sample Decision Step 1.4.8 Concurrent Steps A concurrent step symbol is used when an operator is to enter another procedure while at the same time continuing in the current flow path. The symbol contains the number of the additional procedure. See Figure 1-8. l ACTION I l w r,..za..i ) I atflon ACTION Figure 1-8. Sample Concurrent Step 1.4.9 Entry and Exist Points An entry arrow symbol is used to show where a procedure is entered from another procedure. The symbol contains the procedure number l that was exited, and is located to the left of the entry point. The step number is placed below the entry arrow symbol. See l Figure 9. l l ::,' Pv. era.es M Acn0N xx-y Figure 1-9. Entry Arrow Symbol 1-5
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE An exit arrow symbol requires the operator to leave the flow path at that point. The symbol contains the number of the procedure that must be entered. The step number is placed below the symbol. An exit arrow is located below and to the right of the, step ~ exited. See Figure 1-10. ACTION SPE9.023.01)> XX-Y Figure 1-10. Exit Arrow Symbol 1.4.10 Cautions and Notes Cautions and notes give additional information to the operator. They are never used to convey a required action step. But they may be used to express conditional actions. a. Definitions 1) CAUTION: A caution is a means of attracting attention to ' essential or critical information in a procedure. This information addresses conditions, practices, or procedures that must - be observed to avoid personnel injury, loss of life, a long-term health hazard, or equipment damage. 2) NOTE: A note gives the operator information to clarify the instruction. It never deals with personnel or equipment hazards, l b. Format A specific caution applicable to a step is indicated by a double-line hexagon above the step. When more than one caution applies to a step, place the hcxagons in series on the flow path above the stop. A brief description of the caution (in parentheses) appears to the right of the hexagon. See Figure 1-11. toceCnIPrION (DESCRIPfl0N) 400 NOT e OlVERT LPCI) INITIATE SUPP ACTION PSOL COOLING Figure l'-11. Placement of Caution Symbols 1-6
SHORERAM NUCLEAR POWER STATION WRITER'S GUIDE 1.4.11 Functional Flow and Branching Sufficient spacing will be allowed between paths so that the a. operator does not inadvertently enter an adjacent path, b. Arrowheads will be used on connecting lines to clarify the direction of the path. Arrowheads will enter fl6wchart symbols from the top, not from the side. 1.4.12 Flowchart Step Numbering Scheme a. Multiple-Branch E0Ps Multiple-branch E0Ps use an AA/B-C format, where: AA = the procedure designator B = the branch of the procedure C = the sequential step number For example, Reactor Control, Level Branch, Step 3 would be numbered RC/L-3. b. Single-Branch E0Ps Single-branch EOPs use an AA-B format, where: AA = the procedure designator B = the sequential step number For example, Level Restoration, Step 5 would be t. -hered LR-5. 1.4.13 Text Procedure Step Numbering Scheme Text procedure steps shall be numbered in accordance with SP 12.006.01, " Station Procedures - Preparation, Review, Approval, Change Review and Cancellation." 1.4.14 Placekeeping Aid A L. is placed next to each step as a placekeeping aid to the operator. 1.4.15 Readability Guidelines The following apply: a. The flowchart typeface should be a simple style, in full capitals, at least 1/8 inch in height. 1-7
a SHOREHAM NUCLEAR POWER STATICN, WRITER'S GUIDE e b. The spacing between letters and between words should be distinct so that the flowcharts can'he easily read ia emergency lighting. All E0P lettering should be black type on white b,ackground for c. the highest possible contrast. d. Copies of flowcharts should be of high quality, i.e., without fuzzy type. The flowcharts should have a nonglare surface. e. 4 f. The flowc:' arts should.be no larger than 36" x 60" an'd no -.. s smaller than 8-1/2" x111". 1.4.16 Printed Figures Within E0P Flowcharts Figures (such as graphs and charts) and tables mdy be used to aid the operator in performing the action steps. For exa'mple, a table of values could be used so that a calculation is avoided. Labe' ling Scheme / a. 1) Graphs and tt.bles will be titled. 2) Graphs and tables will be numbered in tha XX-Y-Z format, where:- XX is the branch of the flowchart that the graph or e table applies tv. e Y is the parameter of concern in the flowchart branch. Z is a sequential number of graphs or tables used in e that branch. For example, Drywell Pressure Control curve No. 2 would be numbered Curve DW-P-2. i 3) The numbers and titles of graphs or tables will be placed above each graph / tables. 4) Graphsandtableswillbereferredtobyhemberwithin the action step. b. Placement A graph or table is located on the flowchart near the first step that refers to it. ' Dashed lines link the graph or table and the applicable step. a, 1-8
-e m SHOREHAM NUCLEAR POWER STATION ~ (: ~ WRITER'S GUIDE /. 1 c. Quality Figures vill be self-explanatory and legible under the eypectedconditionsofuse. Specifically,
- 1) ' The typeface will be a simple style, in full capitals, at i(
least 1/8 inch in height. b *$ l 2) The figure will be a high-quality reproduction (or reduction), i.e., not a blurry photocopy. ~ d. Consistency (~ The terms used in the figure (i.e., equipment designations, parameter units, etc.) will match those used in the procedure steps and in the control room itself. Units of measure and numerical values will be consistent with SNPS Technical J' Specifications and with actual control room indicators. i 1.5 Step Construction .I.5.1 . Level of Decail j The detail required in the flowcharts is that required by the least trained operator expected to use the procedure, specifical3y a newly trained and licensed operator working under emergency (stressful) conditions. Although abbreviated, the procedural instruction in the flowchart shall reflect the exact intent of the E0P. The flowchart format leaves little room for supporting instruction or information, and operators are trained on the procedures, so a cluttered flowchart will only hinder efficient . ~ f performance, li = 1.5.2 Step Sequer.cing Steps will be listed in the required sequence. The operator assumes the sequence is mandatory unless the procedure specifically states otherwise. Other considerations in sequencing action steps are: l a. ~ Structure the control room action steps to ensure that minimum control room staff can perform the actions. b. Sequence the steps to minimize physical conflicts among i operators. c. Sequence the stops to avoid unintentional duplication of steps y by different operators. 1-9
c SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.5.3 Step Length and Content Instructions steps will be short and simple sentences dealing with, only one 1, dea. The following specific guidelines apply: Limit the number of action verbs per step to one unless the a. actions are closaly related, in which case up to three action verbs are acceptable. b. Describe complex evolutions in a series of steps. t Det not state the person performing the action; that is, do not c. i begin a step with "The operator shall... " d. Do not use imprecise adverbs (for example 3 frequently or slowly). i e. Avoid double negatives f. When an action has three or more objects, list them vertically using bullets. For example: CLOSE OR VERIFY CLOSED: RPV HEAD VENTS IB21)MOV083 AND 1B21sMOV084 e ,a e MSIVs e MAIN STEAM LINE DRAINS e RCIC STEAM ISOLATION VALVES When actions are requiYed based. on receipt of an annunciated g. alarm, state the alarm, the Alarm Response Procedure number and its setpcint. h. If required for proper understanding, describe the system response time associated with step performance, i. When system response' dictates a time frame within which the instruction must be accomplished, state the time frame. However, avoid using time to initiate operator actions because operator actions should be related to plant parameters. J. When anticipated system responses may adversely affect instrument indications, describe in a CAUTION: (1) the conditions that will very likely introduce instrument error .and (2) a means of determining whether instrument error has occurred. k. Waen additional confirmation of system response is necessary, state the backup readings to be made. 1-10 - ~
SHOREHAM NUCLEAR POWER STATION r WRITER'S GUIDE 1.5.4 Types of Steps Guidance for different types of actions follows, a. Simple Action Step Begin this type of step with the action verb: CLOSE.. OPEN. POSITION. b. Verification Step Begin with an action verb that clearly indicates that verification is to be performed: VERIFY, As stated in the guidelines above, list three or more items to be verified vertically. c. Continuous Step Indicate clearly that an action is to be performed continuously: CONTINUE TO SCAN... MAINTAIN CONTINUOUSLY... d. Recurrent Step Indicate clearly (1) when or how often the step is to be performed and (2) under what conditions the step should no longer be carried out. Remind the operator at a later point in the flow path to keep performing the step. An example of a recurrent step is: CHECK TANK LEVEL EVERY 30 MIN l e. Alternative Step State specifically that the prescribed step may be performed in alternative ways (if any) by using the logic word OR. 1-11
SHOREHAM NUCLEAR POWER STATION WRITER'S CUIDE f. Concurrent Steps Indicate clearly whether any steps need to be performed concurrently (i.e., operating within different parts or sections of a single procedure or.the use of more than one procedure at the same time) with other steps by u, sing such words as " simultaneously," "at the same time " or " concurrently." If the actions are closely related, join the actions with e "and" within the same step. However, "and" does not in itself imply simultaneous performance, so the need for simultaneous action still needs to be stated. If the actions are not closely related enough to be e included in the same step, or if there are more than three closely related actions, list the steps with a lead-in instruction indicating the need for simultaneity, such as " perform the following actions concurrently." The number of concurrent steps should not be beyond the capability of the control room staff to perform them. 1.5.5 Logic Terms The following guidelines apply to the use of logic terms. Logic terms will be underlined for emphasis, a. AND/OR Avoid the use of AND and OR within the same action. When AND and OR are used together, the logic can be very ambigueus. For example, the following instruction could be interpreted in more than one sense: IF CONDITION 1 AND CONDITION 2 OR CONDITION 3 OCCURS, THEN GO TO STEP 1. b. AND When attention should be called to combinations of conditions or closely related actions, use the word AND between the actions or conditions. Do not use the word AND to join more than three actions or conditions. If four or more actions or conditions need to be joined, use a list format. STOP THE PUMP AND PLACE IT IN STANDBY c. jy! Use the word OR when calling attention to alternative combinations of actions or conditions. 1-12
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE d. IF or WHEN. . THEN When action steps are contingent on certain conditions or combination, begin the step with IF or WHEN followed by a description of the condition (s), a comma, and the word THEN followed by the action to be taken. WHEN is used for an expected condition. IF is used to determine the specific course of action based on plant conditions. e. IF WHILE...THEN This combination of logic terms is used in retainment steps, where operators must remember information about a condition that may occur while they are performing subsequent steps. Begin the step with IF WHILE followed by a description of the condition or conditions, a comma, and the word THEN followed by the action to be taken, f. IF NOT Use IF NOT only where the ' operator must respond to the second of two possible conditions. IF should be used for the first condition. For example: ))[ PRESSURE IS INCREASING, THEN STOP THE INJECTION PUMP IF NOT,
- THEN, START AN ADDITIONAL INJECTION PUMP.
Examples of conditional statements using logic words are given in Section 1.5.6 below. 1.5.6 Conditional Statements Conditional action steps must be constructed simply and clearly because of the often complex logic.and ideas tharein. The following rules apply: a. The IF or WHEN clause precedes the action: IF SUPP POOL TEMP REACHES 110*F, THEN SCRAM THE REACTOR WHEN RPV PRESSURE DECREASES TO 800 PSIC, THEN OPEN ALL ADS VALVES AND C0 TO SP 29.023.01 1-13
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE b. Where three or more conditions exist, a listing approach is preferable: I_F,WHILE EXECUTING THE FOLLOWING STEPS: F e REACTOR POWER IS ABOVE 5% OR UNKNOWN AND e RPV WATER LEVEL IS ABOVE -158IN AND e SUPP POOL TEMP IS ABOVE 110*F AND e EITHER AN SRV IS OPEN OR OPENS OR DRYWELL PRESSURE IS ABOVE 1.69 PSIG, THEN RETURN TO STEP LP-9 Where only one of two cenditions produces an action, use the c. following approach: E BORON INJECTION IS REQUIRED $ BORON INJECTION HAS BEEN INITIATED, THEN TERMINATE AND PREVENT INJECTION FROM ALL SYSTEMS EXCEPT BORON INJECTION AND CRD If there were three or more conditions in the above example, a listing approach would be preferable, with each condition linked by OR (underlined and centered between the conditions). d. When an action step has specific conditions relating to sequence and plant parameters, use the following approach: BEFORE DRYWELL TEMP REACHES 340*F AND Ij[ DRYWELL PRESSURE IS BELOW CURVE DW-T-1, THEN INITIATE DRYWELL SPRAY Conditional statements are treated in further detail in NUREG-0899, " Guidelines for the Preparation of Emergency Operating Procedures," Appendix B, and in INP0 82-017, " Emergency Operating Procedures Writing Guidelines," Section 2.1.18. Spacing above and below centered logic words (i.e., AND, OR) e. in conditional statements should be consistent throughout the flowchart. The spaces between bulleted items (single or double space) should also be consistent. 1-14
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.5.7 Referencing and Branching a. Definitions The term " referencing" in connection with another procedure implies that the referenced procedure will be use.d as a supplement to the initial procedure. Referencing can also occur within a procedure, either forward or backward. b. Guidelines Excessive referencing to other procedures or forward / backward within a procedure causes operator errors. The following guidelines apply: 1) If the length or complexity of the flowchart will not be substantially increased, repeat the needed information rather than referencing. 2) Reference complete procedures or sections of procedures if possible. Requiring an operator to use another procedure for just a few steps is to be avoided. 3) Be sure to clearly direct operators back to where they left off. 4) Include references to SNPS Emergency Plan Implementing Procedures (EPIP) as appropriate on the flowchart. c. Format 1) When referencing another step, flow path, or procedure to be used as a supplement, use words such as " REFER T0" or "... USING PROCEDURE SP 23.708.01." For example: E SUPP POOL WATER LEVEL INCREASES TO X FT, THEN RESTORE LEVEL WITH NORMAL SUPP POOL DRAIN USING PROCEDURE SP 23.708.01. A procedure may also be referenced using the concurrent step symbol, described earlier in Section 1.4.7. 2) When branching to another procedure or flow path, use words such as "GO T0" or " EXIT. ENTER." and the entry and exit symbole described earlier in Section 1.4.8. For example: E RCIC IS NOT READY FOR OPERATION AND RPV PRESSURE IS INCREASING, THEN GO TO SP 29.023.05 1-15
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.5.8 Safety Parameter Display System References An ellipse will be placed on the flowchart at appropriate points to indicate that pertinent information is available on the Safety Parameter Display System (SPDS). Within the ellipse, place the appropriate SPDS "page" number. Use a hyphen instead.of listing consecutive page numbers in a series (see Figure 1-4). 1.5.9 Component Identification Equipment, controls, and displays should be identified in operator language (common usage) terms without the location, with the following exceptions: When the engraved names and numbers on legend plates and alarm a. windows are specifically the item of concern in the procedure, the engraving should be quoted verbatim. b. If the component is seldom used or difficult to locate, location information such as the panel number should be given. 1.5.10 Word Choice The flowchart format requires brevity, so words must be selected carefully. The following guidelines apply: a. Use simple, short, familiar words commonly understood by the trained operator. b. Use concrete, specific words. c. Use specific action verbs. For control circuitry that executes an entire function upon actuation of the control switch, use the action verb without further inscructions on how to manipulate the control device. Recommended action verbs on: For power-driven rotating equipment: START, STOP e e For valves: OPEN, CLOSE, THROTTLE OPEN, THROTTLE CLOSED, THROTTLE o For power distribution breakers: SYNCHRONIZE, CLOSE, TRIP e For multiposition control switches that have more than one position for a similar function, placement to the desired position should be specified. 1-16
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE d. Define any key words that may be understood in more than one
- sense, The same words should be used consistently.
e. 1.5.11 Methods of Emphasis The following methods are to be used: a. Logic terms: Underlining (IF, WHEN, THEN, OR, NOT) b. Other types of information: underlining when appropriate for special emphasis. 1.6 Mechanics of Styie The following subsections provide guidance to the procedure writer in terms of style. All punctuation shall be in accordance with a Merriam-Webster dictionary. 1.6.1 Spelling Use spelling consistent with a current dictionary. When a choice of spellings is offered, use the first listed. 1.6.2 Abbreviations and Acronyms The use of abbreviations and acronyms depends heavily on user familiarity; that is, their meaning must be unquestionably clear to an expected procedure user. On the other hand, they are needed to save space in the flowchart format, and it is virtually impossible to spell them out at their first mention, which is normally done in single-or double-column format procedures. Therefore, the following guidelines apply: a. Spell out all words in procedure titles. b. Use abbreviations and acronyms that the operator learns in the course of training, and only those listed in SP 11.011.01, " Standard Abbreviations." c. Ensure that abbreviations and acronyms are consistent with labels in the control room, d. Use abbreviations for units of measure: FT, not FEET; PSI, not POUNDS PER SQUARE INCH. 1-17
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE Be consistent in using abbreviations and acronyms; always e. spell them the same way. f. To make an abbreviation plural, add a lowercase s: SJAEs, not SJAE's. Reserve the apostrophe for showing possessive. 1.6.3 Hyphenation Hyphenating (dividing) a word at the end of a text line should be avoided in the flowcharts. IF hyphenation is difficult to avoid because of space, words must be divided as shown in a current Merriam-Webster dictionary, and at least three letters must be carried down to the next line. Hyphens are used to link elements of a compound word (called a unit-modifier), such as "nine-digit number" and "long-term control." Hyphens are also used in the following circumstances: In compounds with "self": self-explanatory e When the last letter of the first word or prefix is the same e vowel as the first letter of the second word: re-energize When misleading or awkward consonants would result by joining e the words: non-nuclear To avoid listing consecutive numbers in a series when space is e limited. Hyphens are not used with the following prefixes unless confusion results from closing up the word. e pre e micro e post e mini e re e multi e sub o non e super 1.6.4 Punctuation a. Colon Use a colon to indicate that a list of items will follow. 1-18
~. SHOREHAM NUCLEAR POWER STATION WRITER'S CUIDE .b. Comma The following rules apply: 1) Use a comma between the "if" or "when" clause and the action clause of a conditional statement. 2) Use a comma for numerical values of five digits or more, e.g., 100,000, 50,000, 2000. 3) Use a comma to set off an introductory phrase or word. 4) Use a comma before the conjunction connecting the last item in a series of three or more: AVOID RPV HIGH WATER LEVEL TRIP ON RFPTs, RCIC, AND HPCI INJECTION VALVE (1E41*MOV035). Note that within the flowcharts a series of three or more items is listed vertically, so commas are not used. c. Parentheses Parentheses are used to give additional, defining information: RHR (STEAM CONDENSING MODE) d. Period A period is used to end a complete statement, although it is generally not used within the flowchart symbols. A period is omitted when: 1) Listing items vertically. For example: e RCIC e HPCI e CS e LPCI l 2) Spelling an acronym: HPCI, not H.P.C.I. 3) Abbreviating units of measure: FT, LB, PSI. However, IN. is used to avoid confusion with the word IN. e. Question Mark Question marks are not used within the decision step symbol on flowcharts. l l 1-19 I
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.6.5 Acceptance Criteria and Calculations The following rules apply: a. Be as specific as possible when stating qualitative acceptance criteria. Avoid using vague words like " satisfactory" or " normal". b. Express quantitative acceptance criteria and tolerances in ranges so that the operator does not need to mentally add or subtract. c. Use tables of values or graphs in the procedure to avoid i operator calculation. d. If calculation cannot be avoided, simplify the calculation, provide the formula, and provide space for calculating. for example: RECORD FEED PUMP SUCTION PRESSURE: P= PSIG RECORD FEED PUMP SUCTION TEMP: T=
- F LOOK UP VAPOR PRESSURE AT T:
VP= PSIG NPSH = 2.3 (P: ) - (VP: )= FT OF HEAD 1.6.6 Numerical Values i The following rules apply: a. Always use arabic numerals. b. For brevity in the flowchart format, use the numeral instead of the word: 3, not three. c. For numbers less than one, precede the decimal point by a zero; for example: 0.1. d. Ensure that the number of significant digits is equal to the number if significant digits available from the display (and required by the necessary reading precision of the operator). e. Specify engineering units for numerical values of process variables, and ensure that they are consistent with the units predominantly displayed to the operator. i 1-20
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.7 Text Preparation Guidelines A dual-column page format will be used in which the left-hand column is designated for operator actions and notes, and the right-hand column is designated for information and caution. 1.7.1 Procedure Organization The following section headings will be used for all EOPs. a. TITLE - The title will be stated with the ENTRY CONDITIONS for operator association, b. PURPOSE - A brief purpose for the E0P will be included. c. ENTRY CONDITIONS - The entry conditions will be those plant parameters which, when exceeded, require entry into and execution of the E0P. d. OPERATOR ACTIONS - The operator actions will be succinct, identifiable instructions that give appropriate directions to the user. See Appendix B for a dual-column format procedure sample. 1.7.2 Section Numbering Section numbering shall be in accordance with SP 12.006.01, " Station Procedures - Preparation, Review, Approval, Change Review and Cancellation." 1.7.3 Instruction Step Length and Content Instruction steps will be succinct and precise and will be located in the instructions column of the right hand page. General rules to be used in meeting these objectives are as follows: a. Instruction steps should deal with one idea only. b. Short, simple sentences should be used. c. Complex evolutions should be described in a series of steps, with each step made simple. d. Objects of operator actions should be specifically stated. l e. For instructional steps that involve an action verb relating to three or more objects, the objects will be listed with space provided for operator checkoff. 1-21
. o SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE f. Limits should be expressed quantitatively. g. identification of components and parts should be technically correct and complete. h. When actions are required based upon receipt of an annunciated alarm, the alarm set point should be listed. i. If required for proper understanding, describe the system response time associated with performance of the instruction. J. When system response dictates a time frame within which the instruction must be accomplished, denote the time frame. However, avoid using time to initiate operator actions, as operator actions should be related to plant parameters. k. When anticipated system response may adversely affect instrument indications, (1) describe the conditions that will likely introduce instrument error and, (2) describes a means of determining if instrument error has occurred by using a CAUTION. 1. When additional confirmation of system response is considered necessary, prescribe the backup readings to be made. 1.7.3.1 Instruction Column The left-hand column of the dual-column format contains the operator instructional steps. In addition to the rules above, general rules to be used in meeting these objectives are as follows: a. Expected indications (e.g., specific meter or display readings or general plant response) should be presented in this column. b. Operator actions in this column should be appropriate for the expected indications. 1.7.3.2 Contingency Actions Column Contingency actions are operator actions that should be taken in the event a stated condition, event, or task does not represent or achieve the expected result, and will be presented as additional steps in the instructional column. 1-22
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE The contingency actions should identify, as appropriate, directions to override automatic controls and to initiate manually what is normally automatically initiated. Contingency actions will be specified for each circumstance in which the expected r'esults or actions might not be achieved. 1.7.4 Use of Logic Terms When logic statements are used, logic terms will be highlighted so that all the conditions are clear to the operator. Highlighting will be achieved by using capitalization and spacing. Use logic termslas follows: a. Avoid the use of AND and OR within the same action. When AND and OR are used together, the logic can be very ambiguous, b. When attention should be called to combinations of conditions, the word AND shall be placed between the description of each condition.. The word AND shall not be used to join more than three conditions. If four or more conditions need to be joined, a list format shall be used. c. The word OR shall be used when calling attention to alternative combinations of conditions. The use of the word OR shall always be in the inclusive. sense. d. When action steps are contingent upon certain conditions or combinations of conditions, the step shall begin with the words Il[ or WHEN followed by a description of the condition or conditions, a comma, and the word THEN followed by the action to be taken. WHEN is used for an expected condition. IJ[ is used to determine the specific course of action based upon plant conditions. e. Use of IF NOT should be avoided. See Figure 1-13 for examples of good and bad logic statements. 1.7.5 Cautions and Notes Cautions shall be highlighted by the use of bold type. Cautions are proceeded by a number which corresponds to the cautions in the EPGs. Those cautions will be of an abbreviated nature and will be located in the right-hand column of the page immediately opposite the procedure step or steps to which they apply. 1-23
o. SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE BAD: If Condition A AND Condition B Olt Condition C occurs, go to Step 36. GOOD: If both of the following occur: e A e B or C e Go to Step 36 BAD: Insert sufficient control rods to bring the reactor suberitical if directed by the Shift Supervisor. GOOD: If directed by the Shift Supervisor, insert sufficient control rods to bring the reactor suberitical. BAD: Go to Step 30 when reactor pressure reaches 50 psig. GOOD: When reactor pressure reaches 50 psig, go to Step 30. Figure 1-13. Good and Bad Logic Statements 1-24
. a SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE A NOTE shall be used to define information which must be considered in conjunction with an action instruction. A NOTE should present information only, not instructions, and should be located in the left-hand column as close to the applicable instruction as possible. 1.7.6 Calculations Mathematical calculations should be avoided in E0Ps; a chart or graph should be used if a value has to be determined. These charts or graphs shall be located on the left-hand page across from the appropriate procedure step, if possible. 1.7.7 Figure, Table, and Appendix Designation Figures and tables will be specifically designated by an abbreviation of the procedure in which they reside and the sequential number of the table. For example, the third table in a Drywell Temperature (DW) procedure would be designated as: DW/T3 Page identification for appendices shall consist of a block of information that identifies (1) procedure number, (2) appendix letter, (3) page number, and (4) revision number. 1.8 E0P Revisions and Updates 1.8.1 Review Requirements E0Ps may be reviewed as a result of: l a. Revision of the BWROG Emergency Procedure Guidelines ( b. Revision of other procedures referenced in the E0Ps c. Revision of the SAR d. Revision of Technical Specifications e. Feedback received from Verification and Validation (V6V) activities f. NRC correspondence received that changes the scope of the l E0Ps g. Operating experience I i 1-25
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 1.8.2 Revision Process If it is determined that a revision is necessary, the revision will be prepared in accordance with SP 12.006.01, " Station Procedures - Preparation, Review, Approval, Change Review and Cancellation". If the revision is significant, a special training session may be required. (Minor revisions are covered in routine requalification training.) 1-26
.~. f SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE E 4 4 J j 1 J i s i APPENDIX A 1 PLANNING GUIDANCE FOR THE PROCEDURE WRITER I I i f i
A o-SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE PLANNING GUIDANCE FOR THE PROCEDURE WRITER Before starting a first draft of any document, a writer should research the topic, analyze the audience, and either outline or diagram the major points to be covered to be covered to establish organization and sequence. This .*Endix contains guidance in these areas that is specific to the SNPS E0P wrf er. 1.0 Cather Technical References The first step in procedure development is research into the technical documents to which the procedure must adhere. These documents include, but are not listed to: a. PSTGs: The E0Ps are to be written based on these guidelines. b. BWROG EPGs: Although the E0Ps are directly derived from the PSTGs, it I may be necessary to verify technical information by referring to the generic EPGs. c. Technical Specifications. d. SAR: Safety Analysis Report. 2.0 Gather Supporting References and Guidelines 2.1 Writing Guidelines Additional reference on writing and style are needed to write the procedure. The following are recommended: a. A current Merriam-Webster dictionary: A dictionary is needed to determine spelling and hyphenation of words. A-1
O e SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE b. NUREG-0899 " Guidelines for the Preparation of Emergency Operating Procedures," August 1982: This NUREG contains the human factors principles upon which this writer's, guide is based, and may be helpful to clarify or amplify this guide. c. INPO 82-017 " Emergency Operating Procedures Writing Guidelines," July 1982: Many of the principles outlined in this INPO document are restated in this writer's guids. The I original INP0 document may be needed for further guidance on a specific point. 4 b I l t 6 A-2
. o SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 3.0 Analyze the User Research into the expected procedure user is needed to ensure a workable procedure. Most questions on style and content can be answered by first asking "Who is the user?" Factors to be considered in user analysis include: a. Level of training and education 1) What is the level of the least, trained? 2) What is the level of the most trained? 3) Is there a wide range of operators with different levels of training? b. Yests of experience: The same questions apply. c. Expected environment 1) What are the physical conditions, such as lighting, control room layout, and number of operators in the control room? 2) What is the expected stress level? How will it affect the operator's ability to read, comprehend, and efficiently execute the procedures? d. Past problems with procedures 1) What kind of procedural deficiencies have led to user difficulties at SNPS? 2) What problems have other plants had and how did they resolve them? A-3
SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE 4.0 Outline the Major Points Outlining or charting out the procedure's major paths or steps helps the writer examine the logic and organization early. In the outlina, flow diagram, or event tree, show the following: a. Sequence, including concurrent flow paths b. Decision points Any third party verification, approval, or notification points c. d. Interfaces with other E0Ps e. Interfaces with other plant procedures, such as EPIPs The outline or chart can then be filled out into a procedure draft. l l A-4
e-e SHOREHAM NUCLEAR POWER STATION WRITER'S GUIDE O APPENDIX B SAMPLE DUAL-COLUMN FORMAT PROCEDURE
.se SHOREHAM NUCLEAR POWER STATION WRITER'S CUIDE 3.0 OPERATOR ACTIONS 3.1 IF a reactor scram has not been initiated, THEN initiate a reactor scram. 3.2 Irrespective of the entry conditions, execute the following sections concurrently: Section 3.3; Monitor and control reactor power Section 3.4; Monitor and control RPV water level Section 3.5; Monitor and control RPV pressure 3.3 MONITOR AND CONTROL REACTOR POWER 3.3.1 IF while executing Section 3.3 (A) All control rods are (A) Ref. to SP 29.010.01 inserted to or beyond Emergency Shutdown position 02, 2R It has been determined that the reactor will remain shutdown without
- boron, THEN terminate boron injection and enter SP 29.010.01, Emergency Shutdown (B)
The reactor is shutdown (B) Ref. to SP 29.010.01, and no boron has been Emergency Shutdown injected into the RPV, THEN enter SP 29.010.01, Emergency Shutdown 3.3.2 Confirm or place the reactor mode switch in SHUTDOWN B-1 .}}