ML20205C970
| ML20205C970 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/08/1985 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20205C937 | List: |
| References | |
| AP-2.2, NUDOCS 8509230374 | |
| Download: ML20205C970 (60) | |
Text
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i NEW YORK POWER AUTHORITY James A. FitzPatrick Nuclear Power Plant a
-l ATTACHMENT NO. 3 TO J PN-8 5-66 s
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Procedure for Emergency Operating l Procedures - Revision No. 5 Dated February 6, 1985 ,
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. 23 NOf YORK POWER AUTHORITY I JAKS A. FITZPATRICK NUCLEAR POWER PLANT A(Mil 5TRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 4
- REVIEWED BY: Plant Operations Review Committee I Meeting No. 85- 010 Date 02/06/85 APPROVED BY: (/ / h Date 2 /7/V ,
l Resident Manager APPROVED BY: d Date 2//// >-
Quality Assurance Superintendent i
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I Pace No. 1 2 3 4 5 6 7 8 9 10 11 12 13 14 ,
Rev. No. 5 2 4 4 5 4 4 5 4 4 4 4 4 4 Page No. 15 16 17 18 19 20 21 22 23 24 25 26 27 28 ,
Rev. No. 4 4 5 4 4 4 5 4 4 5 4 5 5 5 Page No. 29 30 31 32 33 34 35 36 37 38 39 40 41 42 Rev. No. 5 4 4 4 2 2 4 4 4 4' 5 4 4 4 l
- Page No. 43 44 45 46 47 48 49 50 51 52 53 54 55 56 Rev. No. 4 4 2 5 ' ' k' 2 2 2 2 2 2 2 2 2 r Page No. 57 58 59 Rev. No. 2 2 2 i i i
l Rev. No. 5 Date nnnn/es Page 1 of 59 r,-,-- -, . - ,w.,,,mn,.n. wnn--,--- .ys ,~,---n-,, - . , r.-,, ,,-r, ---.. ~ ,-n-- -- --- - -- e.-.---r-,--n--,.n -- -,,--,-----..-r,,,,r----,
NEW YORK POWER AUTHORITY .
. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 3 2.0 APPLICA8ILITY 3
3.0 REFERENCES
3 4.0 DEFINITIONS 3 i
5.0 RESPONSIBILITIES 3 6.0 SPECIAL INSTRUCTION / REQUIREMENTS 4 i
7.0- PROCEDURE 4 i 8.0 FICURES 7 9.0 EXHIBITS 8 ,._
)
, 10.0 APPENDIXES 8 l
APPEN0!X A FITZPATRICK WRITERS CUIDE FOR EMERGENCY OPERATING PROCEDURES TABLE OF CONTENTS 9 APPENDIX B E0P VERIFICATION CHECKLIST ADMINISTRATIVE REVIEW SECTION 34 l APPENDIX C ECP/EPG VERIFICATION CHECKLIST TECHNICAL REVIEW SECTION 40 APPENDIX 0 EDP VALIDATION CHECKLIST 43 Rev. No. 2 Date 05/11/83 Page 2 of 59
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- NEW YORK POWER AUTHORITY
. JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 l
1.0 PURPOSE
, The purpose of this procedure is to describe the method of preparing and <
maintaining Emergency Operating Procedures (EOPs).
2.0 APPLICABILITY
This procedure applies to Emergency Operating Procedures which prescribe
- ope stor actions for emergency response.
3.0 REFERENCES
1
. 3.1 Regulatory Guide 1.33, Quality Assurance Program Requirements 3.2 NUREG 0899 - Guidelines for the Preparation of Emergency Operating i Procedures 3.3 BWR Owner's Group Emergency Procedure Guidelines NEDO 24934
- 3.4 ANSI N18.7 - 1972 - Administrative control for Nuclear Power Plants 4
j ' 3.5 INPO 82-017, Emergency Operating Procedure Writing Guideline 3.6 NUREG/CR-2005, Checklist for Evaluating Emergency Operating Procedures Used in Nuclear Power Plants. ,
3.7 AP-1.3, Control of Administrative Procedures.
i 4.0 DEFINITIONS:
l 4.1 Validation - en evaluation performed to determine that actions
- specified in a procedure can be performed by the operator.
1 4.2 Verification - en evaluation performed to assess the written correct-j ness and technical securacy. of a procedure.
4.3 Writers Guide - a document that provides instructions for writing i
E0Ps, emphasizing the use of human factors principles.
l l 4.4 Technical Guidelines - a document that identifies equipment or systems i to be operated, and provides a sense of instructions for responding to I plant emergencies and to conditions which could degrade into emergen-cies, j
i i 5.0 RESPONSIBILITIES:
l 5.1 The Operations Superintendent is responsible for the development and
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verification of plant specific technical guidelines for E0Ps. j Rev. No. 4 l Date 05/16/84 page 3 or $9 I
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E W YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2
- 5.2 The operations Superintendent is responsible for the development, i validation and verification of E0Ps.
5.3 The Plant Operation Review Committee reviews E0Ps in accordance with
', Administrative Procedure 1.4.
"$ .4 ihe Resident Manager approves EDPs in accordance with Administrative j Procedure 1.4.
^
6.0 SPECIAL INSTRUCTIONS / REQUIREMENTS:
l None 1
7.0 PROCEDURE
7.1 Technical Guideline Development Generic technical guidelines for Emergency Operating Pro-7.1.1 cedures have been developed by the BWR Owner's Group for General Electric boiling water reactors. These guidelines
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are generic to GE-BWR 1 through 6 designs in that they add- ,m j ress all major systems which may be used to respond to emer-gencies. FitzPatrick, as any other 8WR, does not have all J
of these systems. The guidelines are applied to this plant by deleting steps, systems, and equipment not applicable, ,
identifying and adding instructions for systems and equip-ment unique to FitzPatrick, or substituting statements that are equivalent. In the generic guidelines, brackets 1. j enclose plant specific setpoints, desicp limits, pump shut- \
off pressures, etc., and parentheses within the brackets l indicate the source of the bracketed variable. The generic guidelines contain, as an appendix, calculational procedures
- for deriving values of the more complex of the bracketed plant-specific verisbles.
7.1.2 The generic guidelines shall be developed and reviewe'd by the GE-BWR Owner's Group prior to use in the development of FitzPatt.ick Emergency Operating Procedures.
7.1.3 A plant specific technical guideline shall be prepared from the generic guidelines through the process of deletion and substitution of statements and the substitution of plant specific variables. The person preparing the technical guideline signs the cover sheet.
i 7.1.4 The plant specific technical guideline is then subjected to -
4 an independent review. Using Appendix C, E0P/EPG Verifica-tion Checklist, Technical Review Section, the reviewer performs a step by step check to assure the technical ac- h Rev. No. A Date 05/16/84 Page 4 of 59
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICX NUCLEAR POWER PLANT AD6edISTRATIVE PROCEDURES I l
TITLE: PROCEDURE.FOR DERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 g
curacy of the guideline. Discrepancies found during the review are documented in the final section of the checklist.
The checklist is returned to tne writer for resolution of problems. The resolution la also documented in the final
! section of the checklist. The reviewer signs the cover sheet of the technical guidelines.
! 7.1.5 The Operations Superintendent a oves the plant specific
' technical guidelines for use in writing the Emergency Opers-
~ ting Procedures.
7.1.6 Plant Speciric Technical guidelines shall be controlled i
under the Quality Assurance Program.
7.2 Emergency Operating Procedure Development The Emergency Operating Procedure writer translates the plant specific technical guidelines into a series at action steps. These steps accomplish the objectives of the technical guideline and are written in a form to optimize the operator's performance. The FitzPatrick l .
Writers Guide for Emergency Operating Procedures, Appendix A, is used
- p throughout this development process. This assures the procedural
- A s steps are presented in a clear, definitive manner that adheres to I human factors principles for written material presentation.
7.3 Emergency Operating Procedure Verification l
7.3.1 Verification is performed to evaluate the written correct-ness and technical accuracy of the E0Ps. Persons perform- '
ing the verification conduct a step by step review of the E0Ps using as guidelines, Appendix B, E0P Verification Checklist, Administrative Review Section, and Appendix C, E0P/EPG Verification Checklist, Technical Review Section.
This review determines how well the procedures follow the E0P Writers Guide and FitzPetrick Technical Guideline. Dis.
- crepancies found during the review are documented in the final section of sach checklist. These are returned to the E0P writer, for resolution. The resolution is documented in the final section of the checklist.
7.3.2 The person preparing the draft E0P prepares a Procedure I Initiation / Revision Request Form in accordance with Adminis-trative Procedure 1.4, Control of Plant Procedures. The person or persons performing the verification review should sign or be referenced in the procedure initiation review form in the " Reviewed By" section. The name should also be labeled " Verifier". ,
P Rev. No. 5 l Date 02/06/85 Page 5 of 59 .
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NEW YORK POWER AUTHORITY , l JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES 1 TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 7.4 Emergency Operating Procedure Validation Validation is performed to evaluate the usability and operational correctness of E0Ps. The validation process consists of the following elements:
7.4.1 Selection of transients to be used in the validation pro-cess.
'7.4.1.1 The Operations Superintendent or designated alter-nate determines the scenarios that will best eval-uste the effectiveness of the draft E0Ps. This determination is generally made considering the relative probability of occurrence and industry experience. Examples of possible scenarios in-clude SBA, SBA with HPCI failure, DBA LOCA, etc.
l 7.4.2 Determination of the method of validation:
7.4.2.1 Validation may be performed using control room walk-through, " table-top", or simulator envirome nts. In general a combination of the three '
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methods provides the broadest evaluation of a %-
draft E0Ps acceptability. The control room walk-through allows evaluation of operator performance
) in the setting that the procedures must be capable of being performed. The availability of indica-tion, work space design, and the placement of controls are easily evaluated relative to the operator actions specified in the E0P. The walk-through method, however, is contrived and provides little time-dependent information concerning the response of the plant to operator action. The simulator provides insight into this interaction of the plant and the operators to the extent that computer modeling is able to simulate actual reactor performance. ,
"'The " table-top" validation method allows personnel to explain and/or discuss E0P decision and action steps in response to a proposed scenario or as a part of an actual industry operating experience review. This method is also limited as far as time-dependent responses re concerned, but still provides a forum for procedure evaluation when access to the control room is restricted.
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Rev. No. 4 Date 05/16/84 Page 6 of 59
. EW YORK POE R AUTHORITY i JAES A. FITZPATRICK MJCLEAR POWER PLANT ADW4ISTRATIVE PROCEDURES t
, TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 l ..
, 7.4.3 Performance of the validation 7.4.3.1 Walk-throu @s usually are cor. ducted in advance of simulator sessions to polish the procedure. They are conducted with a team of individuals consis-ting of an observer and one or more operators.
j The observer describes plant conditions and their changes as the operator (s) take action to stab-ilize the transient described in the scenario. As
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the operator (s) describe their actions the ob-l server using Appendix D, E0P Validation Checklist, ,
evaluates the E0Ps usefulness and operational l I correctness.
7.4.3.2 Simulator sessions are conducted using a normal i
crew of operators plus one or more observers.
j Ageln the observer sets up plant conditions con-sistent with the prescribed scenarios and evalua-i i tes the E0P as the operators use it to stabilize
! and mitigste the transient. Appendix D, E0P ,
i Validation Checklist is used to guide and document the evaluation.
i C 7.4.3.3 " Table-top" validation sessions are conducted
! using a normal crew of operators plus one or more observers. Staff licenses or plant engineers may -
t j take part to ensure a thorough assessment is per-
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formed. The evaluation takes place at a location j external to the plant and control room (e.g.
l Training Facility). As before, the observer (s) l presents a scenario or an incident similar to one experienced in the industry. The assembled crew utilizes the E0Ps to stabilize and mitigate the l
- transient. Appendix D, E0P Validation Checklist is used to guide and document the evaluation.
f 7.4.4 Resolution of Comments
! 7.4.4.1 '~ Comments made during the validation process are to be addressed. The resolution is documented in the E0P Validation Checklist.
t i 7.5 PORC Review and Approval !
j When discrepancies discovered during the verification and validation '
! process are resolved, the desft E0P is reviewed by PORC and approved
! in accordance with Administrative Procedure 1.4, Control of Plant j Procedures.
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{ Rev. No. 4 i l l Date 05/16/84 Page 7 of 59 i
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NEW YORK POWER AUTHORITY -
I JAE S A. FITZPATRICK NUCt. EAR POWER PLANT ADMNISTRATIVE PROCEDURES l
TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 1 7.6 Periodic Review and Procedure Revision 7.6.1 Siennial review of the Emergency Operating Procedure is required by Administrative Procedure 1.4, Control of Plant Procedures.
7.6.2 Revisions to the FitzPatrick Technical Guide or Emergency Operating Procedure having technical substance, should be made with the steps of this procedure, as applicable in
- addition to the requirements of AP-1.4. Revisions involving i
the correction of typographical errors or similar minor deficiencies .are made in accordance with the requirements of Administrative Procedure 1.4, Control of Plant Procedures.
8.0 FIGURES
None i
9.0 EXHIBITS
1 None e I m j 10.0 APPENDIXES:
10.1 Appendix A, FitzPatrick Writers Guide for Emergency Operating Pro-cedures.
10.2 Appendix 8, E0P Verification Checklist, Administrative Review Section.
10.3 Appendix C, E0P/EPG Verification Checklist, Technien1 Review Section.
10.4 Appendix 0, E0P Validation Checklist.
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I J Rev. No. 5 l
Date 02/06/85 Page 8 of $9 !
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT 4 ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A TO AP 2.2 FITZPATRICX WRITERS GUIDE FOR EMERGENCY OPERATING PROCEDURES TABLE OF CONTENTS SECTION PAGE 1 INTRODUCTION .................................... 12 1.1 PURPOSE .................................... 12 1.2 SCOPE ...................................... 12 2 E0P DESIGNATION AND NUMBERING ................... 12 2.1 COVER SMEET ................................ 12 2.2 PROCEDURE DESIGNATION AND NUMBERING ........ 12 FIGU RE 1 - COVER SHEET . . . . . . . . . . . . . . . . . . . . . 13
( 2.3 REVISION NUMBERING AND DESIGNATION ......... 14 2.4 P AGE IDEN TIF IC AT I ON AND NUMB ER ING . . . . . . . . . . 14 ,
FIGURE 2 - PAGE FORMAT ..................... 15 1 3 FORMAT .......................................... 16 3.1 PAGE F09 MAT ................................ 16 3.2 PROCEDURE ORGANIZATION ..................... 16 3.3 SECTION NUMBERING .......................... 16 l 3.4 INSTRUCTION STEP NUMBERING ................. 16 i ~
j 4 WRITING INSTRUCTIONAL STEPS ..................... 17 4.1 INSTRUCTION STEP LENGTH AND CONTENT ........ 17 4.2 USE OF LOGIC TERMS ......................... 18 4.3 USE OF CAUTIONARY INFORMATION ANO NOTES .... 19 I
l Rev. No. 4 Date 05/16/84 Page 9 of 59
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADiedISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A i
SECTION PAGE 4.4 CALCULATIONS ............................... 20 4.5 USE OF UNDERLINING ......................... 20
- 4.6 REFERENCING AND BRANCHING TO OTHER PROCEDURES i 'OR STEPS ................................... 20 4.7 COMPONENT IDENTIFICATION ................... 20 4.8 LEVEL OF DETAIL ............................ 21 4.9 PRINTED OPERATOR AIDS ...................... 22 4.9.1 UN I T S OF ME ASU R E . . . . . . . . . . . . . . . . . 22 4.9.2 TITL ES AND HE ADINGS . . . . . . . . . . . . . . 22 4.9.3 FIGURE, TABLE AND ATTACHMENT NUMBERING ........................ 22
)
5 MECHANICS OF STYLE .............................. 23 .
5.1 S P EL L I NG . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 5.2 HYPHENATION ................................ 23 5.3 PUNCTUATION ................................ 23 5.3.1 BRACKETS ......................... 24 5.3.2 COLON ............................ 24 5.3.3 COMMA ............................ 24
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5.3.4 P ARENTHESES . . . . . . . . . . . . . . . . . . . . . . 24 5.3.5 PERIDO ........................... 25 4 5.4 V OC A8 UL AR Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 I TABLE 1 - ACTION VERBS .................... 26-27 5.5 NUMERICAL VALUES ........................... 27 l
Rev. No. 4 I
Date 05/I6/84 Page 10 of 59 l
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADWIISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A ...
SECTION PAGE 5.6 AB8REVIATIONS, LETTER SYP90LS, AND ACRONYMNS 28 6
TYPING FORMAT ................................... 28 6.1 _ GENERAL TYPING INSTRUCTIONS .................. 28 6.2 PAGE ARRANGEMENT .......'...................... 28 6.3 HEADING AND TEXT ARRANGEMENT ................. 29 6.4 BREAKING OF WORDS ............................ 29 6.5 ROTATION OF PAGES ............................ 29 6.6 PRINTED OPERATOR AIDS ........................ 29 l 6.7 CAUTIONS AND NOTES ........................... 31
( 6.8 USE OF FOLDOUT PAGES ......................... 31 6.9 USE OF OVERSI ZED P AGES . . . . . . . . . . . . . . . . . . . . . . . 32 6.10 USE OF REDU CED P AGES . . . . . . . . . . . . . . . . . . . . . . . . . 32 7 R EP RODU CT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 i
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Rev. No. 4 Date 05/16/84 Page 11 of 59
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER, PLANT ADMNISTRATIVE PROCEDURES ,
TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A 1 INTRODUCTION 1.1 PURPOSE The purpose of this document is to provide administrative guidance on the preparation of E0Ps.
1.2 SCOPE This writers guide applies to the writing of Emergency Operating Pro-cedures (EOP's).
2 E0P DESIGNATION AND NUMBERING E0Ps are procedures that govern the plant operation during emergency con-ditions or conditions which could degrade into emergencies. They specify operator actions to be taken to return the plant to a stable condition.
Each Emergency Operating Procedure shall be uniquely identified. This -s identification permits easy administration of the process of procedure . )
preparation, review, revision, distribution, and operator use.
2.1 COVER SHEET Every E0P shall have a cover sheet (see Figure 1). The primary pur-poses of this cover sheet are (1) to identify the procedure and (2) to identify the authorized revision. To identify the procedure, a descriptive title is to be used that also designates the scope.
2.2 PROCEDURE DESIGNATION AND NUMBERING The Emergency Operating Procedure designator shall be F-EOP. A sequential number will follow the procedure designator and will consist of two digits EXAMPLE F-EOP-05 . ..
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l l Sequence Number l
l Procedure Designator i
I Rev. No. 4 Date 05/16/84 Page 12 of 59
NEW YORK POWER AUTHORITY 3AMES A. FITZPATRICX NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A _
l FIGURE 1 - COVER SHEET .
. i NEW YORK POWER AUTHORITY JANES A. FITZPATRICK NUCLEAR POWER PLANT ENERGENCY OPERATING PROCEDURE TITLES RPV FLOODING NO. F-CDP 7 REVIEWED BY: Plant Operations Review Committee Nesting No. 84. Date / /84
.; APPROVED SY: Date Uperettone superantencent APPROVED BY: Date j Westcent Manager l
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l Pece No. 1 2 3 4 5 6 7 8 9 10 11 Rev. No. 0 0 0 0 0 'O O O O O O Page No. 12 13 14 15 16 17 18 19 20 21 22 Rev. No. 0 0 0 0 0 0 0 0 0 0 0 Pese No. 23 24 25 26 27 28 29 30 31 32 33 Rev. No. 0 0 0 0 0 0 0 0 0 0 0 Rev. No. 0 l Date Page 1 or 33 Rev. No. 4 Date 05/16/84 Page 13 of 59
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O NEW YORK POWER AUTHORITY ,
JAMES A. FITZPATRICK NUCLEAR POWER PLANT '
ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 l 1
APPENDIX A 2.3 REVISION MJ2ERING AND DESIGNATION One or more digits following the abbreviation "Rev. No." will be used to designate the revision level of the Emergency Operating Procedure.
EXAMPLE Rev. No.1~ -- - - - - - ----- -- -
I lI l .I Revision Level l
l Abbreviation To identify a revision to the test of an E0P, a change bar located in the right margin alongside the text change will be used. The revision number and date will appear on the lower left hand corner of each page.
2.4 PAGE IDENTIFICATION AND NUMERING
. Each page of the procedure will be identified by (1) the procedure title designator and number, (2) the revision number (including date), -~
t and (3) the page number specified as "Page of "
. This x_)
information will be formatted as shown on Figure 2.
Rev. No. 4 Date 05/16/84 Page 14 of 59
NOf YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR ENERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 i
APPENDIX A _ . _ _ . _ . .
FIGURE 2 - PAGE FORMAT I
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EMERGENCT OPERATING PROCEDURE TITLEt RPV FLOODING NO. F-EOP-7 A. ENTRY This procedure le entered whenever specified in the follow-ing procedurer
- Injection Not Required)"
- 8. OPERATOR ACTIONS
- 1. o IF ..... 7 or more SRV's are open, THEN .... continue in thle procedure et Step 4 (Pege 9).
o IF ...... less then 7 SRV's are open, THEN .... continue in thle procedure et Step 2
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(Pege 5).
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l Rev. No. 0 i Date p.g. 3 or 33 Rev. No. A Date 05/16/84 Page 15 of 59
NEW YDRK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A 3 PROCEDURE FORMAT The E0Ps shall be formatted in accordance with the conventions outlined below.
3.1 PROCEDURE ORGANIZATION Each' EDP shall contain the following sections:
A. ENTRY CONDITIONS B. OPERATOR ACTIONS The ENTRY CONDITIONS section of an E0P shall contain a statement of the conditions requiring entry into that procedure.
Example:
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1 A. ENTRY CONDITIONS I I I l Entry into this procedure is required whenever any of thel I following conditions occur: 1 I I l Parameter Condition l I I l 1. RPV water level -----------> below 177 in.- l 1 1 I 2. RPV p r essure --------------> above 1045 psig l I I I 3. LEtc.] l l l The OPERATOR ACTIONS section of an E0P shall contain the sequential steps of the proce. dure. Short, concise instructions giving appro-priate directions to the user shall be provided. Any required verif-ication of automatic plant response shall be included as an instruc-tional step. A mandatory step sequence shall be assumed unless other-wise stated.
Section titles shall be typed in upper-case letters and underlined.
Alphabetic designations "A" and "B" shall be used to designate section headings as indicated above.
Rev. No. 4
. .w Date 05/16/84 Page 16 of 59
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A 3.2 INSTRUCTIONAL STEP FORMAT Instructional steps shall be complete sentences presented in a single :
column format. The use of footnotes shall be minimized. l Both sides of the pages shall be used and numbered. Entry conditions and instructional steps shall be located on the right hand pages.
Override statements and figures shall be located on the left hand pages. (Refer to Section 3.4 below for a discussion of override statements.)
3.3 STEP NUMBERING
> Instructional steps shall be numbered as follows (see example in Figure 3 page 20):
- 3. 3 .1. Steps shall be designated by sequential Arabic numerals.
3.3.2. Substeps shall be designated by sequential decimal numbers (3.1, 3.2, 3.3, etc. ). If further subdivision is necessary,
(' single digit numbers or " bullets" shall be used. In general, numbers shall be used for action statements, bullets for conditional statements.
Example 1 (subdivision of an action statement):
I I l 4.3 WHEN . . . . boron injection has been initiated, 1 I I I THEN ...1. Confirm automatic isolation of or l l l manually isolate RWCU. I L i I j 2. Continue to inject boron into the RPV l l until 640 pounds of baron have been l.
I injected. I I I l
Rev. No. 5 Date 02/06/85 Page 17 of 59 l *
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 l
APPENDIX A Example 2 (subdivision of a conditional statement):
I I l 3.9 Start pumps in alternate injection subsystems which are I I lined up for injection into the RPV. 1 I I I _o IF . . . . . RPV pressure is increasing, 1 I I l THEN . . . . EMERGENCY RPV DEPRESSURIZATION IS l l REQUIRED. I I I I I I o WHEN . . . . RPV water level drops to 0.0 in., I I I I THEN . . . . continue in this procedure at Step 3.111 1 1 I I 3.3.3. Lists appearing as part of an instructional step shall have y
entries designated as follows: ~
- a. Lists of systems or components shall be itemized with bullets.
Example:
1 I l 5.2 Commence and slowly increase injection into the RPV with l l the following systems: I I I I o Condensate booster pumps I I i l o Condensate pumps l I I l o CR0 1 I ... I I I
- b. Lists of conditions or step numbers shall be itemized with lower-case letters.
h Rev. No. 4 Date 05/16/84 Page 18 of 59
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NEW YORK POWER AUTHORITY 3AMES A. FITZPATRICK NUCLEAR' POWER PLANT -
ADWIISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A __,_.
Example 1 (list of conditions):
I I l 2. IF . . . any one or more of the following conditions l l occur: 1 I i l a. Off-site whole body dose rate is projected l I to exceed 1 Rem OR l l l l b. Off-site child thyroid dose is projected l I to exceed 5 Rem OR I I I I c. Site boundary whole body dose rate I 1 I approaches or exceeds 50 mR/hr for 1/2 hourl i I
'l I s . Example 2 (list of step numbers):
1 I ,
Execute the following steps concurrently:
l 2. I I I l a. Step 3 . . . . RPV water level control l '
I I I b. Step 4 . . . . RPV pressure control l l I l c. Step 5 . . . . reactor power control l i I I I 3.3.4. Bullets and letter designators shall be indented two spaces to the right of the left margin of the main text of the associated step (see examples above).
l l
Rev. No. 4 l
i .
l Date 05/16/84 p g. 19 of 59
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NEM YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES ,
TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A Figure 3 - Instructional Steps Numbering Format I I l A. ENTRY CONDITIONS l 1 I l [ Text of Entry Conditionsj l 1 I I I I B. OPERATOR ACTIONS l l l l 1. (Text of stepj l i I l 2. [ Text of stepj l I I l ,
2.1 LText of substepj i l I
, 1 2.2 LText of substepj i l I i
I
- 1. (Text of substepj l i
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l 2. [ Text of substepj l l l l 2.3 LText of substepj l I I j l o (Itemj l I I I o LItem] I I I l o (Itemj i 1 I i l 3. LEtc.] l I I l [
l I i I ... I I I I I I I I I i
i Rev. No. 4 Dete 05/16/84 Page 20 of 59 1 *
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NEW YORK POER AUTHORITY JAE S A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PRGCEDURES TITLE: PROCEDURE FOR EMERGENCY CPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 l
3.4 OVERRIDE STATEMENTS Conditional statements applicable to a series of steps or actions are herein designated " override" statements. (e.g., "While executing Steps 8.2 and 8.3, if RPY water level can be determined, then continue
~
in this procedure at Step 9.") The following conventions shall apply to the use of overrides in the E0Ps (refer to the illustration in Figure 4):
3.4.1. Override statements shall be boxed and placed on the left hand pages, even with the first steps to which they apply.
3.4.2. Override statements shall be repeated on subsequent left
- hand pages if the steps to which they apply continue on following pages. This may be omitted in special circum-I stances if all the following are met: (1) An override is applicable throucfiout a procedure (2) the omission would greatly improve clarity on the override pages and (3) a vertical line shall be made as discussed in paragraph 3.4.6 to graphically show the presence of an override.
Arrows pointing to the left shall be placed immediately to l
p 3.4.3.
( the left of the step numbers of steps having associated override statements.
3.4.4 The top of the box where an override statement first appears l
shall be a double line ending with an arrow aligned with the l
arrow adjacent to the nunter of the step to which it applies. The text of the override statement, the double line forming the top of the box, and the arrow adjacent to the associated step number shall be printed in boldface type.
On subsequent pages, the text and the arrows shall be in regular type and the top of the box shall be a single line, also in regular type.
3.4.5. The text of the override statement shall specify the exact steps to which it applies.
3.4.6. An arros e'xtending down from the left side of the box containing an override statement shall be used to graph-ically identify the steps to which the statement is applicable. The arrow shall extend from the top of the box to a point even with the last line of the last step to which the statement applies. The end point shall be marked with a horizontal double line.
Rev. No. 5 Date 02/06/85 Page 21 of 59
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A FIGURE 4 - FORMAT OF OVERRIDE STATEMENTS
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Rev. No. A
! Dete 05/16/84 Page 22 of 59
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICX NUCLEAR POWER PLANT ADtNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A 3.5 CAUTIONS AND NOTES 3.5.1 Each caution applicable to the E0Ps shall be identified with a number and succint title, descriptive of the caution content. The full texts of all E0P cautions shall be separately listed in F-EOP-1, "EOP Cautions".
" ~ ~ ~ ~ ~~ ~
~ With'in an E0'P", the number andlitle of cautions applicable
- - to a particular step shall be typed in upper-case letters in ~
a box to the right of th&t step.
Examp'les I
l 2.4 IF ...... suppression pcol l CAUTION #8 l l l 1 085ERVE I l l temperature cannot l NPSH LIMITS 1 1 I I I I
' I be maintained below I CAUTION #13 l l
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l l RAFID 1 l s.
l the Heat Capacity i MAY BE REQD 1 1 1 I I I l Temperature Limit, I CAUTION #14 l l l l CHECK l l I THEN .... maintain RPV pressure l HOTOR ORIVENI l l l PUMPS AVAIL l l l l below the Limit. l l l 1
1 3.5.2 Notes, where appropriate, shall be typed in italics, between the margins of the associated step. The word " NOTE" shall be typed in upper-case letters centered over the text of the note.
Example:
I I I NOTE I I I l Defeating RSCS interlocks may be required to l l accomplish the following step \
I I i
Rev. No. 4 59 Date 05/16/84 Page 23 of
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EW YORK POWER AUTHORITY JAMES A. FITZPATRICK WCLEAR POWER PLANT
, ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPEWIX A 4 WRITING INSTRUCTIONAL STEPS 4.1 INSTRUCTICN STEP LENGTH AND CONTENT Instruction steps should be concise and precise. Conciseness denotes brevity; preciseness means exactly defined. Thus, instructions should be short .and exact. This is easily stated, but not so easily achieved. General rules to be used in meeting these objectives are as follows:
- Instruction steps should deal with only one idea.
- Short, simple sentences should be used in preference to long, compound, or complex sentences.
- Complex evolutions should be prescribed in a series of steps, with each step made as simple as practicable.
- Objects of operator actions should be specifically stated. This includes identification of exactly what is to be done and to ]
what.
For instructional steps that involve an action verb relating to
- three or more objects, the objects will be listed.
Limits should be expressed quantitatively whenever possible (refer to subsection 5.5).
Instruction content should be written to communicate to the user.
- Expected results of routine tasks need not be stated.
- When acticns are required based upon receipt of an annunciated alarm, list the setpoint of the alarm for ease of verification.
When requiring reset or restoration of an alarm or trip, list the expected results immediately following the reset or restoration if it would be beneficial to the operator.
When considered beneficial to the user for proper understanding i and performance, describe the system response time associated j with performance of the instruction. '
h Rev. No. 5 Date 02/06/85 Page 24 of 59 _
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A .._ ._
- When system response dictates a time frame within which the instruction must be accomplished, prescribe auch a time frame.
If possible, however, avoid using time to initiate operator
- actions. Operator actions should be related to plant parameters.
- When anticipated system response may adversely affect instrument indications, describe the conditions that will likely introduce instrument error and means of determining instrument error has occurred by using a NOTE.
- When additional confirmation of system response is considered necessary, prescribe the backup readings to be made.
4.2 USE OF LOGIC TERMS j The logic terms AND, OR, NOT, IF, IF NOT, WHEN, and THEN are often necessary to describe precisely a set of conditions or sequence of actions. When logic statements are used, logic terms will be high-lighted so that all the conditions are clear to the operator. Emphasis
- h. .
will be achieved by using capitalization. All letters of the logic terms will be capitalized. The following is an example of the proper construction of these logic statements:
l t
l l
\
Rev. No. 4 Date 05/16/84 Page 25 of 59
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- l NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EHERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPOOIX A Example I i l 5 Monitor and control suppression pool water level (Cont'd)l 1 I I 5.3 (Continued) l I I I 2. BEFORE ....... primary containment water level l I reached 104 ft., l l I l BUT ONLY IF... adequr.te core cooling is assured,l I I l THEN ......... terminate injection into the RPV i i from sources external to the l l primary containment I l l EXCEPT .. do not terminata l l injection into the RPV l 1 from SLC OR CRD. l f i . I l 3. WHEN ........ primary containment water level I
l
]-
j l reached 104 ft., I I I l THEN ........ irrespective of whether adequate l I core cooling is assured, termin- I l ate injection into the RPV from 'l I sources external to the primary l l containment. l I I l 2. IF . . . any one or more of the following conditions l l occur 1 1 I l a. Off-site whole body dose rate is projected I l to exceed 1 Rem OR I I I l b. Off-site child thyroid dose is projected I ;
I . to exceed 5 Rem OR l l I I c. Site boundary whole body dose rate l l approaches or exceeds 50 mR/hr for 1/2 hourl i I The use of AND and OR within the same action will be avoided. When Am and OR are used together, the logic can be very ambiguous.
h Rev. No. 5 Date 02/06/85 Page 26 of 59 ___
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EW YORK POER AUTHORITY 3AES A. FITZPATRICK NUCLEAR POWER PLANT
. ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 i
j APPEM)IX A __
- Use other logic terms as follows
~
I
- When attention should be call'ed to combinations of conditions, the word APC will be placed between or at the end of the description of each condition. The word AND will not be used to 4 join more than three conditions. If four or more conditions need to be joined, a list format will be used.
1 l
- The word OR will be used when calling attention to alternative l combinations of conditions. The use of the word OR will almost
! always be in the inclusive sense. To specify the exclusive "0R,"
the following may be used: "either A OR B but not both." ,
- When actions steps are contingent upon certain conditions or i combinations of conditions, the step will begin with the words IF or WHEN followed by a description of the condition or conditions (the antecedent), a comma, the word THEN, followed by the action i to be taken (the consequent). WHEN is used for an expected con-
! dition. IF is used for an unexpected by possible condition.
- Use of IF NOT should be limited to those cases in which the operator must respond to the second of two possible conditions.
l IF should be used to specify the first condition.
1 i - THEN will not be used at the end of an action step to instruct the operator to perform the next stop because it runs actions together.
- EXCEPT will be used following an action step to describe a con-dition when the action should not be performed and what alter-native action is necessary.
- BEFORE will be used to indicate that en action should be performed prior to reaching a specified parameter.
- UNTIL will be used to indicate the point at which a specified action should be stopped.
- BUT ONLY IF, or BUT ONLY WHEN will be used to place an additional limitation on when an action will be performed.
4.3 CAUTI(NS APO NOTES Cautions shall be used to identify a potential hazard to personnel or equipment. Notes shall be used to provide supplementary information related to a particular step. Refer to Section 3.5 for correct format.
l
! Rev. No. 5 Date 02/06/85 Page 27 of 59
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__ , . . _ . . e, NEW YORK POWER AUTHORITY JAES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A Use of both cautions and notes should be minimized. Neither should l contain instructional steps. i 4.4 CALCULATIONS Mathematical calculations should be avoided in E0Ps. If a value has to be determined in order to perform a procedural step, a chart or graph should be used whenever possible.
4.5 USE OF Uf0ERLINING Underlining will not be used for emphasis.
4.6 REFERENCING AW BRANCHING TO OTHER PROCEDURES OR STEPS When a requirement for Emergency RPV Depressurization, Steam Cooling, RPY Flooding, Alternate Shutdown Cooling, or Baron Injection is established within a procedure, the statement shall be typed in upper-case letters.
Example n]
'~
l o IF ......... suppression pool temperature I i' i I I and RPV pressure cannot be re- l 1 l l stored and maintained below the l I I I Heat Capacity Temperature Limit, 1 I I l THEN ....... EMERGENCY RPV DEPRESSURIZAIION I I I l IS REQUIRED. l 1 1 4.7 COMPONENT IDENTIFICATION With respect to identification of components, the following rules are to be followed:
- Equipment, controls and displays will be identified in operator language (common usage) terms. These terms may not always match engraved names on panel but will be complete.
- When the engraved names and numbers on alarm windows are spec-ifically the item of concern in the procedure, the engraving I should be quoted verbatim and emphasized by using all capitals.
Rev. No. 5 Date 02/06/85 Page 28 of 59 l,
EW YORK POER AUTHORITY JAE S A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES 1
TITLE: PROCEDURE FOR EMERGENCY OPERATDC PROCEDURES" PROCEDURE NO. AP 2.2 APPEl@IX A
- If the component is seldom used or it is felt that the component would be difficult to find, location information should be given :
in parsntheses following the identification.
l 4.8 CAPITALIZATION FOR EMPHASIS Capitalization will be used as emphasis in the following instances
- caution statements
- logic terms
- procedure titles
- title names and labels on the actual table or figure
- abbreviations for systems and components
- contingency statements (e.g. RPV FLOODING IS REQUIRED, or EMER-( -
CENCY DEPRESSURIZATION IS REQUIRED).
terms describing switch or control positions (e.g., " place the control switch for each SRV in the CLOSE position").
l 4.9 LEVEL OF DETAIL I
- Too much detail in E0Ps should be avoided in the interest of being
- able to effectively execute the instructions in a timely manner. The level of detail required is the detail that a newly trained licensed
- operator would desire during an emergency condition.
l To assist in determining the level of E0P detail, the following general rules apply:
> - For control circuitry that executes an entire function upon actuation of.the control switch, the action verb appropriate to l the component suffices without further amplification of how to l
manipulate the control device; for example, " Shut Feed Pump A
- Discharge Valve (34-M3V-100A)." Recommended actions verbs are as l follows
- a. For power-driven rotating equipment, use " start", "stop".
I
- b. For valves, use "open", " shut", " throttle", "open",
" throttle shut", " throttle".
Rev. No. 5 Date 02/06/85 Page 29 -of 59
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, W POWER AUTHORITY
, , , 4 TRICK NUCLEAR POWER PLANT
.' TRATIVE PROCEDURES
- TIRE: OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPEPOIX -
- ribution breakers, use " synchronize", "close",
so with a positional placement that establishes s condition, the verb " Place" should be used, raved name of the desired position. Positional ically associated with establishing readiness ions and are typically named AUTO or NORMAL; e the Gland Seal Vacuum Pump Control Switch in i for observing for abnormal results need not be procedural steps. For example, observation of erratic flow, or discharge pressure need not be s that start pumps.
4 .11 esented using tables and figures, these aids 'j ry, legible, and readable under the expected v within the reading precision of the operator.
sure ,
isure on figures, tables, and attachments should
- numerical values that represent observed, data, or calculated results. A virgule (slant i be used instead of "per"; examples: ft/sec, e units should match the units on the instru-f Pigures and Tables
'igures and tables are placed at the end of the Miniature figures are placed in the OPERATOR
- ion of the procedure preferably on the left side of the page next to the action step to which
. If ,because of the number of override state-a is not available, it is placed below the action
, e right side of the page. Miniature figures need r once on a page if referenced in more than one ver, they should appear on each page that they are l
1 Rev. No.
Date Page 30 of 59
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l NOf YORK POWER AUTHORITY JAES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES f TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A .
4.10.3 References to Figures and Tables Action steps which refer to a figure or table should do so by stating the title, figure nu 2 er of the full size figure and the page that the full size figure appears.(e.g., ...
cannot be maintained below the Heat Capacity Temperature
. Limit, Figure F-EOP-3.1 (Page 15)). There are no references to miniature figures.
4.10.4 Figure and Table Numbering Sequential numbering as shown below will be used:
Table F-EOP-4.3 Figure F-EOP-3.1 1I ll Sequential Number i
l E0P Number 4.10.5 General Rules for Figures and Tables
- Page identification will be consistent with the sec-tions 2.2 through 2.4.
l
- For full size figures, figure number and title are placed inside the figure field in an area where data is not plotted.
l
- For miniature figures, no nunber applies. Figure title should be placed in the field if it can be fitted with-out interference with data presentation.
l
( - "Do not operate" areas of figures will be shaded by hatching.
l
- The figure field must not violate specified page mar-gins.
- The figure field should be of sufficient size to offer good readability.
i l
- The essential message should be clear; simple presen-tations are preferred.
- for full size figures, grid lines of graphs should be at least 1/8-inch spart; numbered grid lines should be bolder than unnumbered grid lines.
Rev. No. 4 l Date 05/16/84 Page 31 of 59 _
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADHNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR* EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A
- for miniature figures, no grid lines should appear.
Axis divisions should be ,> 3/8-inch.
- The items within the figure should be oriented nat-urally insofar as possible. For example, height on a graph should be along the vertical axis.
In general, items within the figure should be labeled.
Labels should be printed, using all capitals, with letters and numbers at least 1/8-inch high.
- All lines in figures should be reproducible.
Tables should be typed using the following rules.
- Type style and size should be the same as that for the rest of the procedure.
The table number and title should be located above the table field and three lines spaces below preceding )
text.
- A heading should be entered for each column and cen-tered within the column; column headings should be
^
capitalized.
- Horizontal lines should be placed above and below the column headings; vertical lines, while desirable, are not necessary or required.
5 MECHANICS OF STYLE 5.1 SPELLING Spelling should be consistent with modern usage. When a choice of spelling is offered by a dictionary, the first spelling should be used.
5.2 HYPHENATION Hyphens are used between elements of a compound word when usage calls for it. The following rules should be followed for hyphenations, i
l l R ev . No. 4 1
Date 05/16/84 Page 32 of 59
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. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A
- When doubt exists, the compound word should be restructured to avoid hyphenation.
- Hyphens should be used in the following circumstances
- a. in compound numbers from twenty-one to ninety-nine;
' Example : one hundred thirty-four
- b. in fractions; i
Example: one-half, two-thirds
- c. in compounds with "self";
Examples self-contained, self-lubricated
- d. when the last letter of the first word is the same vowel as
(' the first letter of the second word--as an alternative, two words may be used; Example: fire-escape or fire escape
- e. when misleading of ewkward consonants would result by joining the words; Examples bell-like ,
l f. to avoid confusion with another word; I
Examples: re-cover to prevent confusion with recover, pre-position to avoid confusion with preposition
- g. when a letter is linked with a noun;
! Examples 4 X-ray, 0-ring, U-Bolt, I-beam
- h. to separate chemical elements and their atomic weight; l Exaspies: Uranium-235, U-235 l
Rev. No. 2 Date 05/11/83 Page 33 isf 59 t
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A 5.3 PUNCTUATION Punctuation should be used only as necessary to aid reading and pre-vent misunderstanding. Word order should be selected to require a minimum of punctuation. When extensive punctuation is necessary for clarity, the sentence should be rewritten and possibly made into several sentences. Punctuation should be in accordance with the following rules.
5.3.1 Brackets Do not use brackets.
5.3.2 Colon Use a colon to indicate that a list of items is to follow, for example: Restore cooling flow as follows:
5.3.3 Comma n)
(
Use of many commas is a sign that the instruction is too complex and needs to be rewritten. Therefore, evaluate the number of commas to ensure the instruction is not too complex.
Use a conaa after conditional phrases for clarity and esse of reading. (e.g.,: WHEN level decreases to 60 inches, THEN st art pump . . . . )
i 5.3.4 Parentheses Parentheses shall be used to indicate alternative items in a procedure, instruction, or equipment numbers. They shall also be used to denote location (e.g. verify relay SA-K23A i
(panel 09-5) has energized).
5.3.5 Period
- Use a period at the end of complete sentences and for indicating the decimal place in numbers.
5.4 VOCABULARY
( Words used in procedures should convey precise understanding to the trained person. The following rules apply:
Rev. No. 2 Date 05/11/83 Page 34 of 59
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- l NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A ,
- Use siaple words. Some words are usually short words of few syllables. Simple words are generally common words.
- Use cosmon usage if it makes the procedure easier to understand.
- Use words that are concrete rather than vague, specific rather than general, familiar rather than formal, precise rather than blanket.
- Define key words that may be understood in more than one sense.
- Verbs with specific meanings should be used. Examples are listed i in Table 1.
l
- Equipment status should be denoted as follows:
- a. Operable / operability -- These words mean that a system, subsystem, train, component, or device is believed to be capable of performing its specified function (s) in the intended manner. Implicit in this definition is the assump-f-
tion that necessary attendant instrumentation, controls, normal and emergency electrical power seurces, cooling or seal water, lubrication or other auxiliary equipment req-uired for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing related support function (s).
i l
- b. Operating - This word means that a system, subsystem, train, component, or device is in operation and is per-t forming its specified function (s), and that other conditions i do not prevent it froer maintaining that service.
i c. Available -- This word means that a system, subsystem, train, component, or device is believed to be operable and can be used as desired; however, it need not be operating.
~ '
i Tk8LE1-ACTIONVERBS
- VERS APPLICATION ALLOW To permit a stated condition to be achieved prior to pro-coeding, for example, " Allow discharge pressure to stabilize".
CHECK To perform a comparison with a procedural requirements,
" Check if LPCI can be terminated".
Rev. No. 4 Date 05/16/84 Page 35 of 59 I .
.- - . _ _ . _ _ _ , , , _ . . _ . , , - _ _ . _ _ - , . _ . , , . , _ . , , _ . , , - _ _ _ _ . - - _ _ , . . - _ , _ _ _ , - . .,. ,--__...,_ _, m , ,.-..._,,_,,,_4 _, ,
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE TOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A CLOSE To change the physical position of a mechanical device so that it prevents physical access or flow or permits passage of electrical current, for example, "Close breaker 10012".
~
COMPLETE To accomplish specified procedural requirements, for example, " complete valve checkoff list 'A'", " COMPLETE data report QA-1", " complete steps 7 through 9 of Section III".
CONFIRM To remove any doubt of an expected condition by observa-tion.
DECREASE Do not use because of oral connunication problems. Use
" lower" instead.
ESTABLISH To make arrangements for a stated condition, for example, "Eatablish communication with control room".
INCREASE Do not use because of oral communication problems. Use -x
" raise" instead. )
INITIATE To begin to perform those actions that result in a change in mode of operation, for example, " Initiate drywell spray".
INSPECT To measure, observe, or evaluate a feature or characteristic for comparison with specified limits; method of inspection should be included, for example, " visually inspect for leaks".
MAINTAIN To keep a parameter or plant condition in an existing state or range.
OPEN To change the physical position of a mechanical device so that it permits physical access or flow of a fluid, or prevents the passage of electrical current, for example, "Open valve 10-M3V-17A".
RECORD To documen't specified condition or characteristic, for example, " Record discharge pressure".
SHUT To change the physical position of a mechanical device in order to prevent physical access or flow.
START To originate motion of an electric or mechanical device directly or by remote control, for example, " Start ....
pump" .
STOP To cease operation, for examole, "Stop .... pump".
Rev. No. 4 Date 05/16/84 Page 36 of 59
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b NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADDWISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A SYNCHRONIZE To closely match frequencies and phase angle between two electrical generating units prior to closing a circuit l
breaker, resulting in parallel generator operation.
TERMINATE To ease operation, for example, " Terminate all injection THROTTLE To operate a valve in an intermediate position to obtain a cor in flow rate, for example, " Throttle valve CRD-110 to TRIP To manually activate a semi-automatic feature, for example,
" Trip breaker ....."
VENT To permit a gas or liquid confined under pressure to escape at a vent, for example, " Vent .... pump".
VERIFY To remove any doubt of an expected condition by observa-tion. i C_ .
, 5.5 NUMERICAL VALUES The use of numerical values should be consistent with the following rules:
- Arabic numerals should be used.
- For numbers less than unity, the decimal point should be preceded by a zero; for example: 0.1.
l
- The nunter of significant digits should be equal to the nunt)er of significant digits available from the display and reading pre-cision of the operator.
I - Acceptance values should be specified in such a way that addition and subtraction.by the user is avoided if possible. This can generally be done by stating acceptance values as limits.
Examples: 510*F maximum, 300 psig minimum, 580* to 600*F. For calibration points, statement of the midpoint and its lower and
' upper limits would accomplish the same purpose; for example,10 mil 11 amperes (9.5 to 10,5). Avoid using 3
- Engineering units should always be specified for numerical values of process variables. They should be the same as those used on the control room displays, for examples psig instead of psi.
Rev. No. 4 l
Dete 05/16/84 Page 37 of 59
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NEW YORK POWER AUTHORITY JAMES A'. FITZPATRICK PAJCLEAR POWER PLANT ADMISTRATIVE PROCEDURES 1
TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 l l
l APPENDIX A 5.6 ABBREVIATIONS, LETTERS SY>e0LS, AND ACRONY M S The use of abbreviations should be minimized because they may be con-fusing to those who are not thoroughly familiar with them. Abbrevia- ;
tions may be used where necessary to save time and space, and when ,
their meaning is unquestionably clear to the intended reader. The l complete noun name should be written before the first use of an l abbreviation, whenever doubt exists regarding meaning. Consistency '
should be maintained throughout the procedure.
Capitalization of abbreviations should be uniform. If the abbrevia-tion is comprised of lower case letters, it should appear in lower case in a title or heading. The period should be omitted in abbrev-istions except in cases where the omission would result in confusion.
Letter synbols may be used to represent operations, quantities, ele-ments, relations, and qualities.
An acronym is a type of symbol formed by the initial letter or -
letters of each of the successive parts or major parts of a compound -
term. Acronyms may be used if they are defined or coemnonly used.
Table 2 lists commonly recognized acronyms.
Abbreviations, symbols, and acronyms should not be over used. Their use should be for the benefit of the reader. They can be beneficial i by saving reading time, ensure clarity when space is limited, and com- j municating mathematic ideas.
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Rev. No. 4
- Date 05/16/84 Page 38 of 59
_ _. ._. ~~._. . . . .
~ ~ ~ '
, . L .- . . . . . . . . . . . _ _ . . . . . .. - . _ . . . - . . - ,
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPOOIX A _
TABLE 2 N
i ADS - Automatic Depressurization System APRM - Average Power Range Monitor CRD - Control Rod Drive CS - Core Spray ECCS - Emergency Core Cooling System GEMAC - General Electric Measurement and Control HCU - Hydraulic Control Unit
- ifCI - High Pressure Coolant Injection HVAC - Heating, Ventilating and Air Conditioning il LCO - Limiting Condition for Operation LOCA - Loss Of Coolant Accident LPCI - Low Pressure Coolant Injection MSIV - Main Steam Isolation Valve i NOTT - Nil-Ductility Transition Temperature l NPSH - Net Positive Suction Head
(
~
RHR - Residual Heat Removal RPS - Reactor Protection System i RPV -
! RSCS - Rod Sequence Control System RWCU - Reactor Water Cleanup
! SBGT - Standby Gas Treatment SLC - Standby Liquid Control SORY - Stuck Open Relief Valve SRV - Safety Relief Valve 6 TYPING FORMAT 6.1 GENERAL TYPING INSTRUCTIONS .
For Emergency Operating Procedures, the following general requirements are to be followed:
- Paper size should be 8-1/2 x 11 inches.
- Procedures are to be typed on an electric typewriter, word pro-cessor or equivalent.
- Courier, 10 pitch element is to be used.
l Rev. No. 5 Date 02/06/85 Page 39 of 59 _
=-- -.
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 i
APPENDIX A 6.2 PAGE ARRANGEE NT
- Page arrangement will' be as illustrated on Figure 2. The outside i
margin is 3/4 inch in width, the bound margin, one inch.
- Tables and figures should be readable with the page so arranged.
Rotation of printed matter should be avoided for Emergency Operating Procedures. Refer to Subsection 6.5 if rotation is absolutely necessary.
6.3 HEADING AND TEXT ARRANGEMENT Block style is to be used. First-level section headings should be in full capitals, with an underscore; second-level section headings shall be in full capitals without an underscore; and third-level section headings shall be in initial capital capitals without an underscore (refer to Subsection 3.3 for its numbering).
- Section numbers should begin at the left-hand margin.
' - Three line spaces should be allowed between headings and respec- ,-).
s_
tive text.
- Three line spaces should be allowed between paragraphs.
l 4
- Text will be typed using double line spacing. Override statements may be single spaced text with double spaced headings.
Identification of cautions is also single spaced.
6.4 BREAKING OF WORDS l Breaking of words should be avoided to facilitate operator reading.
l 6.5 ROTATION OF PAGES
- If pages need to be rotated, these rules should be followed:
i 1
! - The top of the page with rotated print is the r.ormal left-hand page.
- The page margins rotate.
- Page identification and numbering rotates.
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Rev. No. 4 Date 05/16/84 Page 40 of 59
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e .-
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NEW YORK POWER AUTHORITY i JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADWil5TRATIVE PROCEDURES TITLE: PROCEDURE FOR EE RGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX A 6.6 CAUTIONS AFO NOTES Cautions and notes shall be distinguished from other text through use of the. following format:
- Caution titles shall be typed in upper-case letters and boxed at the right of the steps to which they are applicable as specified in Section 3.5. The right side of the box shall be even with the right margin.
- Notes shall be typed in italics, centered between the margins of the l
associated step as specified in Section 3.5. The heading " NOTE" shall be typed in upper-case italics centered over the text of the note. .
l 6.7 USE OF FOLDOUT PAGES When used, a foldout page is treated as a single page. It should follow the same format as a standard page except the width is (2-
-- di f ferent. The page should be folded so that a small margin exists between the fold and the right-hand edge of standard pages. This will reduce wear of the fold..
6.8 USE OF OVERSIZED PAGES Oversize pages should not be used. They should be re-organized or i
reduced to a standard page. If this cannot be done, a foldout page
( should be used.
! 6.9 USE OF REDUCED PAGES I
l . Reduced pages should be avoided whenever possible. Final size of l reduced pages should be standard page size. Reduced pages should be readable.
l 7 REPRODUCTION Reproduction will be done on a standard copier.
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05/16/84 Page 41 of 59 Date
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s NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX B, E0P VERIFICATION CHECKLIST ADMINISTRATIVE REVIEW SECTION PROCEDURE TITLE /NO.
REVISION REVIEWED BY - DATE The checklist presented in this appendix can be thought of as a screening device to aid reviewers in identifying the procedural deficiencies that are most important in terms of their impact on a quality of operator performance. The most important procedural deficiencies re those that have contributed to operator performance deviations. To identify these performance deviations, an analysis of 890 License Event Reports (LERs) by the RNC dealing with operator errors during the four-year period from 1975 to 1978 was performed. The specific kinds of errors that are amenable -to procedures solutions were determined. Each of the procedures evaluation criteria comprising the checklist items is aimed at correcting one or more kinds of operator performance deviations. ~.
)
Review the procedure for each of the following characteristics. If it possesses the characteristics, check YES; if it lacks the characteristic, check NO. -
Check N/A (Note Applicable) If the characteristic does not apply to the procedure. Note discrepancies at the end of the checklist.
i ITEM YES NO N/A
- 1. Does the title describe the emergency for which the procedure is provided?
- 2. Does each page provide the following identification information? See writers guide Section 2.4
- a. Procedure number and title
- b. Date of revision . .
- c. Revision number
- d. Page number
- 3. Is the last page of the procedure clearly identified J by marking, e.g., Page 46 of 46 ? -
- 4. Are the operator actions referencing operators to other procedures for instructions necessary? Are all infrequently performed or unusual evolutions adequately referenced? '
Rev. No. 4 Date os/1A/na Page 42 of 59
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i NEW YDRM POWER AUTHORITY 3AMES A. FITZPATRICK NUCLEAR POWER PLANT ADtWISTRATIVE PROCEDURES ,
1 TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 YES NO N/A
_ _ , , _ APPENDIX B _
- 5. Are the titles and numbers of all references i documents identified correctly?
- 6. Are the capitalization and typing formats utilized ,
in accordance with writers guide Sections 4.8 and 6.1, respectively? , , . .
- 7. Are instructions written in short, concise ;
e identifiable steps as opposed to multi-step paragraphs?
, 8. Are steps that may be performed concurrently j clearly identified to the user? ;
l 9. If a step contains more than two objectives of action, are they listed rather than imbedded in the sentence?
l For example, if an operator is directed to close three j
or more valves, are they listed rather than strung out i in a sentence.
l 10. If cautions are applicable to the performance of
{'- specific steps or series of steps, are they utilized with a format and construction in accordance with the
- writers guide Sections 3.5 and 6.6 respectively?
) 11. Are cautions separate and easily discriminable ,
l in appearance from instructional steps? Are they enclosed in boxes, headed with the word l CAUTION?
i
. 12. Do cautions avoid the use of action statements?
i (Statements directing personnel to perform actions must not be imbedded in cautions. Cautions should be expressed in the passive voice.)
- 13. Are acceptance criteria and limits expressed in ;
quantitative terms when possible?
- 14. Are quantitative acceptance criteria and limits
! expressed as ranges as opposed to point values or point values with f, tolerance?
! 15. Does the procedure provide instructions for j reasonable contingencies? For example, if i equipment is operating outside the range specified by the procedure, is the operator instructed what actions to take?
Rev. No. 4 Date 05/16/84 Page 43 of 59 i
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NEW YORK POWER AUTHORITY JAES A. FITZPATRICX NUCLEAR POWER PLANT .
ADM(ISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2
- APPEM)IX B YES NO N/A
- 16. When a set of conditions or sequence of actions are prescribed by the E0Ps, are they accompanied by the correct use of logic statements? See -
4 Section 4.2 of the writers guide.
- 17. Are logic statements unenbiguous? For example, if three or more conditions must be met before action -
is directed, sre the conditions listed separately and ahead of the action statement? See Section 4.2 of the writers guide.
- 18. If calculations are required, is space provided in the procedure to perform the computations and to record the results?
- 19. Do graphs, charts, and tables conform to the require-ments of Section 4.10 of the writers guide?
- 20. Complexity Index (CI): Evaluate the complexity t
of the instructions by determining the average '~ ~)
number of actions per step that the user is directed to perform. Use all steps to calculate the average. Is the average nunter of actions per j step 1.5 or less?
I'
- 21. Specificity Index (SI): Evaluate the level of specificity of the instructions by determining the percent of steps in the procedure that meet all of the following criteria. Use all steps in calculating the percent.
i s. The action to be taken is specifically identified (open, close, rotate, etc.).
- b. Limits are expressed quantitatively, e.g.,
2 turns, 80 (75-85.) in Ibs.
- c. Equipment and parts are identified completely with either mark nunbers or written name or both. 10-MOV-27A) etc.
Do 90*. of the steps meet the above criteria?
i Rev. No. 4 Date 05/16/84 Page 44 of 59
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- ,,-,_.,-,.,-.,--n,-- -
---,-----.-r~..--y
a NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2
! YES NO N/A
_ APPENDIX B
- 22. Do the alignment instructions in the procedure meet all of the following criteria?
- s. Each item requiring alignment is individually specified. (It is not aceptable to refer personnel to previous steps.) .
- b. Each item is identified with a unique number or nomenclature.
- c. the position in which the item is to be placed is specified.
- 23. If the procedure specifies an action that must .
be performed at a later time or repeated at periodic intervals, does it contain provisions for flagging the operator to perform the action? For example, if an action must be repeated every 15 minutes, are there spaces to record the times at which the
, action must be performed?
- 24. OTHER COMENTS:
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Rev. No. 2 Date 05/11/84 Page 45 of 59
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NDI YORK POWER AUTHORITY JAES A. FITZPATRICK NUCLEAR POWER PLANT
)
< ADtmISTRATIVE PROCEDURES 1 r
4 TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX B
- 25. Discrepancies Resolutiona l t
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! Rev. No. 5 Date 02/06/85 P 46 of 59
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s NEW YORK POWER AUTHORITY 3AMES A. FITZFATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 1
APPENDIX C, E0P/EPG VERIFICATION CHECKLIST TECHNICAL REVIEW SECTION
- PROCEDURE TITLE /NO. '
REVIEWED BY DATE REVISION OBSERVER Review the procedure for each of the following characteristics. If it possesses the characteristic, check YES; if it lacks the characteristic, check NO check N/A (Not Applicable)7 the characteristic does not apply to th7 a procedure.
ITEM YES NO N/A J
- 1. Are the entry conditions of the technical guide-line (EOP) listed correctly?
( - 2. If additional entry conditions are added, do they comply with the following
! s. Are they appropriate for the E0P/EPG7
- b. Do they constitute a minimum, but complete list of additional conditions?
l 3. Are differences between the generic technical i guideline and the plant specific guideline (or
- plant specific guideline and E0P)
l l a. Documented?
I b. Explained?
! 4. Is the generic (Plant specific) technical guide-l line strategy modified by one or more of the
)
following changes in the plant specific technical -
j guide (EOP) steps, cautions, or notes:
- a. Elimination?
- b. Addition?
! c. Sequence?
- d. Alteration? ;
Rev. No. 2 Date 05/11/84 Page 47 of 59 r
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---.--,-v- , . - - , . . . , - - , _ - . . . --y.,._m.---, -,.. ,_,m, - - . - -,.,,,.-m_.-,w-.
- . ~ ~ ~ . . . .
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPDOIX C YES NO N/A
- 5. Are plant specific adspations incorporated?
i s. Systema?
" ' ~ ~
- b. Instruments? "
- c. Limita?
4
) d. Controla?
- e. Indications?
- f. Setpoints?
- 6. Do quantitstive values in the E0Ps agree with the i plant specific technical guideline?
}.
l ?. Are calculated values in the plant specific
- technical guideline checked by an 13 dependent ]
individual? ,_,
.r
- 8. If calculations are required in the E0P are j equations given?
- 9. OTHER OBSERVATIONS:
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Rev. No. 2 Date 05/11/84 Page 48 of 59 l
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NEW YORK POWER AUTHORITY 1
JAMES A. FITZPATRICX NUCLEAR POWER PLANT ADieilSTRATIVE PROCEDURES i TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX C .--
- 10. Discrepancies Resolutions i
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Rev. No. 2 49 of 59 Date 05/11/04 Page
. - - - , - , - - ,wn-- ,-..-,w,- ,-m.,-w,, ,-,- m._ ------,----,,---,-....-.,--,-c- - - . , - - - - - - , - - - - . . - - - , - n.- ,rv----.-..-,,n .,.--e- .,nn. ,e,,-
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT I ADMNISTRATIVE PROCEDURES l TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES * 'ROCEDURE P NO. AP 2.2 1 APPENDIX 0, E0P VALIDATION CHECKLIST Procedure No. Title , _
~ '~
Date Observer 3 .. . . .
Purpose Scenario I. USABILITY
~
^
A. LEVEL OF DETAIL
)
l ITEM YES NO N/A l
- 1. Did the operator appear to have sufficient information to perform the specified actions at each step?
Comments 1
1
! Resolution
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- 2. O'Idtheoperatorseemuncertainatanydecision point?
Comments i
Rev. No. 2 Date 05/11/84 Page 50 of 59 J
j . _ - .
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT I
ADMNISTRATIVE PROCEDURES l
. TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX D YES NO N/A j Resolution _.
- 3. Was the operator 'able to find needed equipment with the labels, abbreviations, symbols and location information provided him in the E0Ps? ;
Comments l
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- 4. Was the operator able to manage the emergency condition with the information provided him?
I Comments f
Resolution l
- 5. Were the operator's contingency actions sufficient to address the symptoms?
Comments t
i Rev. No. 2 i
- Date 05/11/84 Page 5, of 59
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX D YES NO N/A Resolution
]
- 6. Was the operator able to find referenced and branched procedures?
Comments Resolution l
}
B. UNDERSTANDABILITY i
- 1. Did the operator appear to have problems with any j of the following?
(a) reading the E0P j (b) reading figures and tables (c) determining values on figures and charts (d) complying with E0P step (d) complying with caution and note statements (f) understanding the organization of the E0Ps Comments 1 i i
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- Resolution i i I
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Rev. No. 2 Date 05/11/84 Page 5'2 of 59 i
4
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e .
i NEW YORK POWER AUTHORITY JAMES A. TITZPATRICX NUCLEAR POWER PLANT
- ADDWISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2
,.APPDOIX D __
YES NO N/A II. OPERATIONAL CORRECTNESS
. . A. . PLANT COMPATIBILITY . . ..
. _1. Were the actions specified in the E0Ps able to be performed in the designated sequence?
- Comments Resolution
(
} 2. Were alternate success paths found which were not included in the E0Ps?
Comments E
l Resolution
- l 3
- 3. Was the opera. tor able to obtain the necessary information from plant instru-j mentation as specified in the procedure?
! Comments i
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t Rev. No. 2 j Date 05/11/84 Page 53 of 59
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JAMES A. FITZPATRICX NUCLEAR POWER PLANT i ADemISTRATIVE PROCEDURES l
I TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX D YES NO N/A i
1 Resolution ._ ., __ _
I i
s 4. Did the plant symptoms provide adequate information for the operator to select the applicable EGP?
Comments ;
Resolution i
- 5. Were the ECP entry conditions appropriate
, for the plant symptoms seen by the .
operator?
j ,
l Comments .
1 i
h Resolution
- 6. Did the operator have to use information .
or equipment not specified in the E0Ps j
- to accomplish his task?
4 Comments l
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Rev. No. 2 !
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- - - -_ . _ _ . . . .. . ... . r
- s. .
i NEW YORK POWER AUTHORITY f ,i 3AMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES ,
TITLE: gE FOR EE RGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 i
- i. .
I YES NO N/A T APPOCIX D Resolution t
I 1 the plant responses agree with the
' basis?
Comments _
4
. . . . , _ . . ...e . .s -,
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Resolution l
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- o the instrument readings and toler-i :es consistent with the instrument ,
i lues stated in tr.e E0P7 Coments i in
\ -
i I liesolution 1
re the E0Ps physically compatible with a work situation (too bulky to hold,
! nding wouldn't allow them to lay flat the work space, no place to lay the l Ps down to use)?
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Date '84 Page 55 or 59 ,
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICX NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES 4
TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 i'
APPENDIX D YES NO N/A 1
Comments ,,
Resolution i
B. OPERATOR COMPATIBILITY I 1. If time intervals were specified, were j the procedure action steps able to be performed on the plant within or at the designated time intervals?
j Comments -
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- 2. Could the procedure action steps be performed by the operating shift?
Comments i
Resolution 1
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i, Rev. No. 2 Date 05/11/84 Page 56 of 59 i
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--. .. .1 __. ,
e ' ._
e NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ADHNISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EMERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2
_ APPENDIX D YES NO N/A
- 3. If specific actions were assigned to individual shift personnel, did the ECPs appear to help coordinate the actions
"~ ~ 'where neces,sary?
~
Coments l
Resolution i
- 4. Was the operating shift able to follow ,
the designated action step sequences?
(' '
i Comments Resolution l
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- 5. Was the operator able to do the following?
(a) find the particular step or set of
- steps when required (b) return t"'o 'the procedure exit point l without omitting steps when required (c) enter the branched procedure at the l
correct point (d) exit from the given E0P at the correct branch Rev. No. 2 Date 05/11/84 Page 57 ' of 59
. - - - . - . . - . . -- . . _ _ . . . . _ , _ . . . _ g NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ,
ADtWISTRATIVE PROCEDURES TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 4
N/A APPEM)IX D YES NO 9
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- 6. Was the operator able to locate the specified instruments and controls without delay?
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- 7. Are equipment numbers and nomenclature used in the procedures similar enough to those displayed on the panel so as not to cause confusion?
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Rev. No. 2 Date 05/11/84 Page 58 of 59 f .
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- NEW YORK POWER AUTHORITY
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3AMES A. FITZPATRICK NUCLEAR POWER PLANT ADMNISTRATIVE PROCEDURES l
TITLE: PROCEDURE FOR EERGENCY OPERATING PROCEDURES
- PROCEDURE NO. AP 2.2 APPENDIX D
- 8. OTHER OBSERVATIONS:
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'O e-NEW YORK POWER AUTHORITY James A. FitzPatrick Nuclear Power Plant 1
l ATTACHMENT NO. 4 TO JPN-8 5-66 comparison of Significant Differences Between FitzPatrick's EPG Rev. 3 and Generic BWR Owners Group EPG Rev. 3 l (NRC SER)
- 1. The FitzPatrick Emergency Procedure Guidelines (EPGs) have eliminated generic statements and system applicability and have inserted plant specific statements and systems (Ex: FitzPatrick i EPGs do not address " containment" parameters but refer to "drywell" and " suppression pool" or " torus" parameters).
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- 2. ' Caution 48 (NPSH for pump taking suction from suppression pool) of generic EPG has been expanded to include NPSH curves for
- different water levels as well as different temperatures. This provides more information to the operators.
I 3. In Step RC/P-1, the pressure selected is a little lower than j what the generic EPG specifies (i.e., RPV pressure at which all i
turbine bypass valves are fully open) in order to provide a better balance between pressure control when an SRV has
, erroneously lifted (more probable) and when an SRV has lifted during an ATWS event (less probable).
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- 4. RC/P Section - The initial override statement first bullet paragraph has had the following words added "and Boron Injection is not required". Revision 3 of the generic EPGs would have one rapidly depressurizing the RPV with the main turbine bypass valves even if boron injection was in progress.
This oversite was corrected in later revisions of the generic owner's group EPGs.
! control; "if the continuous SRV pneumatic supply is or becomes
- unavailable, depressurize with sustained SRV opening."
The FitzPatrick EPG states "If the continuous SRV pneumatic j supply is or becomes unavailable, close each SRV." This j statement'is consistent with Revision 3A of the generic owner's j' group EPG in which the paragraph was changed since it was inappropriate to "depressurize" with SRVs when Step RV/P-2 j concerns itself with " control" of pressure. The intent is the same, to not use up the pneumatic supply which enables operation of the SRVs. Therefore, by closing the SRVs, the i
accumulator supply in conserved for future use while pressure control is maintained by other systems, i
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- 6. Step RC/P Added the paragraph "If one or more SRVs are being used to depressurize the RPV and the continuous SRV pneumatic supply is or becomes unavailable, depressurize with sustained SRV opening" which is consistent with Revision 3A of the generic owner's group EPG.
This paragraph was added to provide the guidance which was changed in the previous paragraph (RC/P-2). i
- 7. Step SP/T Moved sentence: " Enter RPV control guideline at Step RC-1 and execute it concurrently with this procedure" from first paragraph to last. This is consistent with Rev. 3A of generic owner's group EPG which relocated the Step RC-1 entry to accommodate failure to scram events. This ensures conditions for boron injection, if required, are in effect prior to emergency depressurization, if required.
- 8. Step PC/P FitzPatrick EPG has deleted first paragraph to ,
operate containment pressure control systems.
These systems would be the drywell cooling systems which are required to be operated by Step DW/T-1. To prevent redundancy and possible confusion, the requirement was deleted from Step PC/P-1.
- 9. Step SP/L The FitzPatrick EPG in the first paragraph does not refetence a sampling procedure prior to discharging water from the euppression pool since all water is processed via the plant's RaC Waste System and its applicable procedures.
- 10. Secondary Coi.tainment control Guideline - The FitzPatrick EPG entry condition considering HVAC cooler specifies a maximum inlet temperature rather than the differential temperature specified in the generic EPG due to lack of instrumentation,
- 11. Step SC/L-2 and L the FitzPatrick EPG does not include reference to the. floor drain sumps exceeding their maximum safe operating value since no value is applicable.
- 12. Step RR FitzPatrick EPG also includes site area emergency requirements as a reason for emergency depressurization.
- 13. Step C2 FitzPatrick EPG refers back to Step RC/P-3; where
. as, the generic Rev. 3 refers back to Step RC/P-4. The change was introduced by Rev. 3A of the generic owner's group EPGs to ensure that all the required boron (via SLC) or all control rods were inserted or the reactor was definitely shutdown prior to entering shutdown cooling.
1 14. Step C6-2.1 - The minimum number of open SRVs is one (1) rather than the two (2) specified in Revision 3 of the generic EPG. A
- later revision (3I) of the owner's group generic EPG reduced the open SRVs to 1, which is still based on calculations which ensure adequate core cooling if the RPV pressure is greater than the minimum alternate flooding pressure.
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- 15. Step C6-5.1 - The Revision 3 step referring to filling the instrumentation water columns was deleted in FitzPatrick's EPG. This step was deleted in Revision 3A of the generic owner's group EPG for the following reasons: a) Due to previous steps, if all rods were not inserted or the reactor was not shutdown, an operator would not get to this step for some time, therefore as a minimum, the step must come earlier in the contingency, b) The operator should be trying to restore PRV water level instrumentation whenever he gets the problem whether electrical, columns flashing, etc. The owner's group concluded that this level of detail was not consistent with the rest of the EPG s therefore, it was removed and included in the Appendix B discussion.
- 16. Step Contingency 67 initial override - FitzPatrick's EPG has deleted reference to reactor flow stagnation power which is consistent with later revisions of the generic owner's group EPG. The later revisions are only concerned on whether RPV flooding is required or not since if the stagnation power was unknown or couldn't be maintained then flooding was required anyway.
- 17. Step C7-2.1 - See answer to Item 14.
- 18. Step RC/P-2, The seventh bullet paragraph has been changed to reflect sampling only if the core has been uncovered. The generic EPG states " refer to (sampling procedure) prior to initiating blowdown." The concern as discussed, in Appendix B of the generic EPG, is to preclude the possibility of discharging highly radioactive water to the environment. At FitzPatrick, any blowdown of RWCU would go either to the condenser or to the Rad Waste facility. Specific procedures govern the discharge of liquids from Rad Waste. Therefore, the wording in the generic EPG is not applicable. However, prior to discharging water to the Rad Waste, which could be highly contaminated, (i.e., resulting from core uncovery), a sample should be taken for information and caution.
- 19. Step PC/P A note was added which provides guidance on when to secure suppression pool sprays, if initiated. This was added in Revision 3G of the generic EPG to provide this guidance.
- 20. Step SC/R Added " reactor building ventilation exhaust" to
" area radiation level" for clarity and to minimize release of radioactivity to outside the secondary containment.
- 21. Step SP/T The FitzPatrick EPG has deleted the step for requiring a scram if a SORV can not be closed. That is, FitzPatrick has opted for the optional time frame of infinity.
It was decided that the 110 degrees Farenheit limit in Step SP/T-3 should be the governing parameter for the scram since torus temperature could be under control with various steps being taken to get the valve shut.