Text

Rev 1 to Emergency Operating Procedures Implementation Plan for Emergency Response Capability Project
	ML20135F316
Person / Time
Site:	Hatch
Issue date:	08/26/1985
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20135F307	List: ML20135F303; ML20135F316;
References
	PROC-850826, NUDOCS 8509170219
	Download: ML20135F316 (120)
	v • d • e

___.

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 1 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY REC'ONSE CAPABILITY PROJECT 1 HATCH NUCLEAR PLANT

EMERGENCY OPERATING PROCEDURES PROCEDURES GENERATION PACKAGE i

ATTACHMENTS: 1) PLANT-SPECIFIC WRITER'S GUIDE PRB iAc<ti30 No. 3 5 . t 7 0

- l Date 8 l27 l6E

- t Approved for transmittal to NRC:.

General Manager M Date 8509170219 850909" PDR ADOCK 05000*321 p PDR.

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HATCH NUCLEAR PLANT PAGE 2 OF 36 DOCUMENT TITLE: l

' EOP IMPLEMENTATION PLAN FOR- REVISION: j EMERGENCY RESPONSE CAPABILITY PROJECT' 1 f

TABLE OF CONTENTS SECTION PAG.E

1.0 INTRODUCTION

.,............................................... 3 2.0 DEFINITIONS...................'............................... 3 3.0 IMPLEMENTATION ELEMENTS...................................... 7 1 3.1 ORGANIZATION OF IMPLEMENTATION ELEMENTS..................... 7 3.2 CREW AND SHIFT POLICY CHARACTERISTICS...................... 8 3.3 PROCEDURES SYSTEM AND NETWORK............................. 10 1

3.4 TECHNICAL GUIDELINE USE................................... 12 3.5 WRITERS GUIDE FOR EOPs.................................... 13 I

3.6. EOP UERIFICATION.......................................... 14 3.7 EOP UALIDATION................ . . . . . . . . . . . . ............... 16 1

3.8 EOP TRAINING.............................................. 17 3.9 REVISION, REVIEW, AND-APPROVAL PROCESS.................... 28 -

3.10 EOP CONTROL.............................................. 28 3.11 SUPPORTING DOCUMENTATION CONTROL......................... 28 3.12 EXPERIENCE FEEDBACK......................................

29 3.13 UPDATING EOPs......g..................................... 29 3.14 AVAILABILITY AND ACCESSIBILITY OF EOP'S.................. 30

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HATCH NUCLEAR PLANT PAGE 3 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 1.0 Introduction This implementation plan describes the elements of the Hatch .

Nuclear Plant program for implementing the new symptom-based Emergency Operating Procedures, based upon the generic guidelines for Emergency Operating Procedu'res, and addresses the concerns identified in NUREG 0899 and Supplement 1 to NUREG 0737. These ,

elements were identified and evaluated by the Emergency Operating .

Procedures Implementation Assistance (EOPIA) Review Group in accordance with the Activity Network described in the EOPIA Program Description (INPO 82-013). The elements presented are not to be construed as an exhaustive list.and are' considered to be generic to most plants and organizations. The elements have been reviewed by Georgia Power and are presented herein specifically for Hatch Nuclear Plant Units 1 and 2.

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This plan also acts as the cover document for the Hatch Procedures Generation Package required by NUREG 0899, section 7.0. A .

description of the Validation, Verification, and Operator Training Programs are contained herein, while the Plant Specific Technical Guidelines and Writer's Guide are attached as separate documents.

2.0 Definitions 2.1 Activity Network The system by which products resulting from the EOPIA Review Group are' developed and re0iewed by the representatives of the nuclear industry.

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-GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 4 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY. RESPONSE CAPABILITY PROJECT 1 2.2 Emergency Operating Procedures (EOPs)

Plant procedures directing operator actions necessary to mitigate the consequences of transients and accidents that cause plant

- parameters to exceed reactor protection system setpoints, engineered safety feature set' points, or other appropriate technical

_. limits. As implemented at Hatch, EOP's will be post-scram procedures, and will be supplemented by Abnormal Operating .

Procedures for pre-scram emergency conditions.

I 2.3 EOPIA Review Group j Representatives from the four owners group subcommittees chartered with the development of Emergency Procedure' Guidelines (EPGs), as well as representatives from NSSS vendors, and INPO. See the EOPIA Program (INPO 82-013) for further information.

2.4 Safety function A safety function is a function specifically required to keep the- -

plant in a safe condition so that public health and safety will not

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be endangered. .

2.5 Event-Oriented EOPs Event-oriented EOPs require that the operator diagnose the specific event causing the transient or accident in order to mitigate the

, consequences of that transient or accident.

2.6 Symptom-Oriented EOPs Symptom-oriented:EOPs provide the operator guidance on how to verify the adequacy of critical safety functions ~and how to restore ~

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and maintain these function $ when they are degraded.

Symptom' oriented emergency operating procedures are written in a way that the operator need not diagnose an event, such as a LOCA, to maintain a plant in a safe condition.

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-HATCH NUCLEAR PLANT PAGE 5 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 9 1

2.7 Writer's Guide F

The writer's guide provides detailed instructions on how to .

prepare text and visual aids for Emergency Operating Procedures so that they will be complete, accurate, convenient, and

-readable to control room per'sonnel. Its recommendations address all aspects'of writing these procedures from a human factors standpoint.

2.8 Technical Guidelines _

Technical guidelines are documents that identify the equipment or systems to be operated and. list the steps necessary to ,

mitigate the consequences of transients and accidents and restore safety functions. Technical gui,delines represent the translation of engineering data derived from. transient and accident analyses into information presentep in such a way.that it can be used to write EOPs. There are,two types of technical -

guidelines, as defined below.

2.9 Generic Technical Guidelines Generic technical guidelines are guidelines prepared for a group ofplantswithasimihardesign. '

' s 2.10 Plant-Specific Technica'l ', a Guidelines (PSTG)

Prepared fror. 'the Generic Guidelines but reflecting Hatch Nuclear Plar.t Units I and 2 plant ~ specific data, limits, operations and systems.

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ys EMERGENCY RESPONSE CAPABILITIES O 2.11 HNP Hatch Nuclear Plant O '

2.12 Verification

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. The process / procedure used to verify that:

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? - The EOPs are technically correct and accurately reflect the o technical guidelines

- The EOPs are written correctly and accurately reflect the writer's guide requirements

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- The controls and instrumentation called out in the EOPs actually exist and verbatim nomenclature,has been used This process'will be performed prior to implementation.

2.13 Validation The process / procedure used to dctormine that:

1 - The EOPs are usable in that they can be understood and followed without confusion, delays, errors, etc.

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- The operations c.alled out in the EOPs can be performed

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j - The language and level of information presented in the EOPs is compatible with the. minimum number, qualification, training, and experience of ihe operating staff

- There is a high level of assurance that the procedures will provide the operator the guidance he needs to mitigate the effects of transients and accidents This process will be performed in parallel with operator

, training and during EOP development.

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PAGE 7 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1

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3.0 Implementation Elements 3.1 Organization of Implementation Elements

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HNP IMPLEMENTATION *

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TECHNICAL WRITER'S GUIDELINE GUIDE V _ . _

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VERIFICATION

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IMPLEMENT EOPs AND OTHER PROCEDURE CHANGES ,

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-HATCH NUCLEAR PLANT PAGE 8 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 L

i 3.2 Crew and Shift Policy Characteristics l Tpe scope and structure of the EOPs must be, compatible with ,the

, crew and shift staffing levels, the crew and shift composition, ,

and the control room layout.

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1 3.2.1 control Room Staffing and' Division of Responsibilities The division of responsibility and leadership among the ,

contro1 room personnel, differing staff capabilities between r

shifts, and the turnover in control room shift crews, make ,

t,he goals of this section difficult to achieve. However, l - - -

the following guidelines are important to the efficient and I

accurate development and execution of EOPs, and have been.

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i .i 3.2.2 Division of Responsibility During an emergency, it is vital that the actions of the J

control room staff be carried out efficiently and ~

- - - - - - accurately. This will be determined in part by the quality of the EOPs and the training of the operators. However, for ,

i j the benefit of good procedures and training to be realized,

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~'it is important th,at control room personnel operate as a

s l team with pre-established leadership roles and divisions of ;

responsibility.The division of responsibilities amongst the 1

control room shift operators (On Shift Operations Supervisor, Shift Supervisor, and Reactor Operators) are

dilencated in the following Administrative Control

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Procedures and will be' emphasized and followed during i

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GEORGIA POWLR COMPANY HATCH NUCLEAR PLANT PAGE 9 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 i

, operator training of the EOP's:

Administrative - 10AC-MGR-001-OS .

10AC-MGR-006-OS 10AC-OPS-003-OS 3.2.3 Staffing of the Control R'oom The number and qualifications of personnel available in t_he ,

control room will determine the number of sequential actions, j concurr,ent actions and other responsibilities that can be carried out, and the efficiency with which they can be carried out. The following goals have been considered in i writing the EOPs.

j - Minimizing physical conflicts between personnel (carrying out actions at the same locations at the same timo, or crossing paths) t Avoiding unintentional duplication of tasks by control room ~

personnel

- Ensuring that the control room supervisor is able to keep up with staff actions and plant status 3.2.4 Consistency Between Staffing and Procedures The EOPs have been structured so that the number of people

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required to carry out sequential actions, concurrent actions, I and other responsibilitics, does not exceed the minimum shift staffing required by the Technical Specifications.

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GEORGZA POWER COMPANY HATCH NUCLEAR PLANT PAGE 10 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY P.ROJECT ,

1 1 3.3 Procedures System and Network EOPs are but one of many types of procedures within the plant

. procedures system. Their relationship to other plant procedures is the procedure network (shown pictorially below).

This network has been consido' red during EOP development to ensure continuity of the EOPs and other plant procedures. , ,

J 3.3.1 General Procedure Interaction -

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 11 OF 34 DOCUMENT TITLE: EOP IMPLEMENIATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 _ _ _

3.3.2 EOP Entry Conditions and Interrelationship of EOP Flow Charts and End Path Manuals.

REACTOR FAILURE -

LOSS OF ABNORMAL TRANSIENTS OF UITAL VITAL POWER HIGH EQUIPMENT SOURCE RADIATIOb ,

LOSS OF EXCESSIVE COOLANT RADIOACTIVE RELEASE

AUTOMATIC LOSS OF OR MALFUNCTION CONTAINMENT REQUIRED OF REACTIVITY INTEGRITY , MANUAL CONTROL SYSTEM SCRAM I f IMMEDIATE ACTION FLOW CHARTS

- SHORT TIME RESPONSE .

if END PATH MANUALS

- LONG TIME - .

REGPONSE

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HATCH NUCLEAR PLANT. PAGE 12 0F 36 l DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1

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i 3.3.3 Existing Event Procedures and EOP Support Procedures l

A review of existing HNP procedures series 1000, 1100-1700 ,

1900 and 2000 will be made with the following objectives:

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-- = Identification and development' of plant procedure--- - - -

revisions essential to ' support implementation of the EOPs 1

Ic'entification and review of plant procedures reference,d .

.by the-EOPs-that must be changed prior to EOP_.._ _ _a . i

_ . _ _ _ _ . . implementation .

Identification and reclassification of existing procedures l

within the procedure system network 3.4 Technical Guideline Use. -

- To effectively use the information provided'by technical guidelines, the methodology used to convert this material into EOPs must be adequately detailed in describing how the technical guidelines will be used.

Plant Hatch will use the two types of technical guidelines (generic and. plant-specific) as follows:

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~ GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 13 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.4.1 Generic Technical Guidelines Technical guidelines prepared by a group of plants or by owners groups for plants with a similar design. Theso guidelines, validated and supported by extensive engineering analysis, will be the doc'ument from which the plant-specific technical guidelines are derived. The Georgia Power QA _

Program will be utilized to verify that the plant-specific -

technical guidelines are true to the generic technical guidelines.

3.4.2 Plant-Specific Technical Guidelines (PSTG)

Technical guidelines will be prepared for Plant Hatch from the generic technical guidelines formulated by the BWR Ouners Emergency Procedure Subgroup. These generic guidelines (Revision 3) have been reviewed and approved by the NRC in SER dated November 23, 1983. The Plant-Specific Technical Guideline will be used to develop the EOPs and other support procedures. This process will be verified and l l

validated per section 3.6 and 3.7. !

3.5 Writer's Guide for EOPs This document is part of the Procedures Generation Package, prepared in accordance wit'h the guidance provided by INPO and NUREG 0899, and will be controlled as a Hatch procedure 30AC-OPS-OO4-0.

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 14 OF 36 {

DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.6 EOP Verification j EOP Verification will consist of ensuring that the EOP's are .

technically correct (accurately reflecting the plant-specific l technical guidelines), that they are written correctly (accurately

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reflecting the plant-specific writer's guide requirements), and that controls and instrumentation called out in the EOP's act,ually exist and verbatim nomenclature, in accordance with the EOP Writers -

Guidej has been used. EOP verification will be performed prior to ,

j the start of operator training, and will be performed in accordance 1

with supplement 1 of NUREG 0737 (and NUREG 0899 and INPO guidelines l

for EOP verification as they apply). This process will identify j any deviation from the PSTG, and describe any analysis performed to determine the safety significance of the deviation, and provide a l

technical justification to the plant specific approach, as

! required. Note that the generic EPG's identify all available BWR' i

equipment, regardless of plant model. The EPG instructions specify 4

that for any equipment so identified, but not existing in the plant '

of interest, the reference to it should simply be deleted, for example, EPG step RC/L-2 requires the operator to restore and maintain Reactor Water level with one or more of the following systems: condensate / food, CRD, RCIC, HPCI, HPCS, LPCS, and LPCI.

, Plant Hatch does not have a HPCS, and deleting it from the PSTG in accordance with EPG instruction on page I-2 (Rev. 3) does not alter

'the safety significance of the step, and no~ additional plant unique

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anal'ysis is necessary.

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 15 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 Additionally, during the development of the E0P's using the EPC's, plant specific information will be inserted between guideline stops to enablo the oper31or to perform the stops properly. For example, to feed the Reactor vessel with the condensate / food system folloJing a scram from high power, the startup level control value noods to be put into service to , ,

ensure that, should an SRV stick open and reactor pressuro fall below the shutoff head of the condensate booster pumps, the vessel and steam lines will not be floodod, proventing thermal shock to the vessel and damage due to water hammer. Thorofore, the stops necessary to put the startup level control valvo in service to meet RC/L-2 will be inserted into the Emergency Operating Proceduros with stop RC/L-2. Since those typos of additions do not change the sequence of steps or the intent of the generic EPG's as reflected in the PSTG, additional analysis or technical justification need not be provided. The actual verification process will be performed by Plant Hatch Shift Technical Advisors, and will be fully documented by writing a Plant Review Board-approved proceduro and executing the proceduro. :

It should be noted that EOP verification is a two '

I phase process. Phase I to be conducted prior to operator training and Phase II to be conducted after validation and oporator comments obtained during training have boon incorporated in the E0P's The E0P's will'then go to the Plant Review Board for approval (o implemont in thd control room.

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'T GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 16 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

i EMERGENCY RESPONSE CAPABILITY PROJECT 1 Administrative Control Proceduro 30AC-OPS-OO7-OS contains instructions and a check list to identify, by the Manager Of .

rOperations, what sections of the EOP Verification Procedure 30AC-OPS-006-OS need to be performed for all future revisions of the EOP's.This will also supp' ort efforts at implementation of i

_ future NRC-approved revisions to the EPG and subsequent , ,.

i re-verification of subsequent EOP revisions, i i -

Since verification will be completed prior to initial EOP f implementation at Plant Hatch, any discrepancies found during verification will also be completely resolved prior to approval

i and implementation of Rev 0 of the EOP's. " Note that verification j is a two-phase process. Phase 1 is performed prior to start of i

operator training and covers tho entire set of EOP's. Phase 2 is the verification of individual revisions entered during training i

resulting from the validation program. I Since EOP Verification as described herein addresses NUREG 0899, l Section 3.3.5.1,' items a, b, and d, the methods used to perform '

verification are control room walk-throughs and desk top reviews.

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control Procedure 30AC-OPS-006-OS j -

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addresses the specifics of the verification process inclusive of !

! identification and resolution of discropancies. All verification I 1 !

t steps and discrepa'ncy resolution will'be reviewed by the Plant

Review Board (Safoty Review) and approved by the plant Conoral

'Managor. *

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 17 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPADILITY PROJECT 1 3.7 EOP Validation E0P Ualidation will consist of ensuring that the language and level of information presentation in the EOPs are compatible with the qualifications, training and experience of the operating staff,and that there is a hig'h lovel of assurance that tho l

procedures will work, i.e., the procedures guide the operator in mitigating transients and accidents. E0P Validation will be performed in parallel with operator training, and will be performed in accordance with supplomont 1 of NUREG 0737 (and NUREG 0899 and INPO guidelinos for E0P validation as they apply).

An estimated 20 man-wooks will be spent in 'he t Hatch plant-specific simulator, with participation by EOP development team ongincors and toch writors, training department instructors, Hatch Senior Reactor Operators (Shift Supervisors), STA's, and reactor operators developing and validating the E0P's'(utilizing single failure, sequential and simultaneous multiple-event sennarios extensively) before operator training begins. 'Tho same types of singic failures and sequential and simultaneous multiple failures will -

be util,i od during operator training. This work will be fully documented including a list of scenarios run and significant results. During operator training.(approximately 1 year period), many additional man-wooks will be spent in the simulator with ovaluation of oporator responso and oporator Teodback included in the validation. ~ ' '

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GEORGIA PCWER COMPANY HATCH NUCLEAR PLANT PAGE 18 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION: "

EMERGENCY RESPONSE CAPA8ILITY PROJECT 1

EOP Validation will be performed in conjunction with the DCRDR program, reference letter Oct. 23, 1984, NED-84-556 Gucwa to i

Director of Nuclear Reactor Regulation. The following have boon i

extracted from the DCRDR Program to further illustrate the validation program. .

i "Section 2.2 Structure of the Review Team. The review team will 1

i have a coro group of specialists in the fields of human factors '

i engineering, plant operations (e.g., licensed operators), and instrumentation and controls. This core group may be supplemented i

1 by personnel from other disciplines such as nuclear, mechanical, .

electrical, and civil engineering if required. Review team

! selection will result in a team with collective experience in the ,

i I following areas:

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- Human factors Engineer !

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j - Reactor Operations .

i - Instrumentation and Controls d e.

i - Enginooring Disciplinos as required '

- Computer Operations j - Project Managomont .

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- Nuclear Licensing'

] - Safety Paramotor Display System (SPDS) 1

- Emergency Operating Procedures (EOPs) ' ' '

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1 i GEORGIA POWER COMPANY i HATCH NUCLEAR PLANT PAGE 19 OF 36

! DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION: l EMERGENCY RESPONSE CAPABILITY PROJECT 1 l 1

"Section 2.4.2 Emergency Operating Proceduros (EOPs) Upgrado '

! Program Integration. The Verification and Validation (VaV) phases 1

l of the DCRDR address some of the same concerns which must be

! addressed in the EOP upgrado V&U process described in NUREG-0899. ;

! Specifically, item 3.3.5.1d of 'NUREG-0899 states "that there is a j correspondence between the procedures and the control room / plant , ,

i i hardware," and it is noted in NUREG-0899 that this item can only be l adequately addressee? using control room / plant walkthroughs.

l Thorofore, the Verification and Validation phases of the DCRDR will I

be done in conjunction with the V&V for the EOP upgrade effort.

Oporator training on now EOPS is scheduled to' start in early 1985.

l The EOP training program will include extensive classroom and simulator components. Simulator exorcisos developed in support of i EOP training will be reviewed for their potential uso in

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supplomonting DCRDR and EOP validation efforts. Those operating

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scenarios that satisfy the objectives of the DCRDR and EOP 4

} validation program will be observed, videotaped and evaluated.

j It should also be noted.that the upgraded Hatch EOPs have been ,

integrated with the SPDS by uso of task footnotes that alert tho l i operator to the related SPDS display." -

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 20 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROTECT 1 "Section 4.3.2.2 Define Representive Scenarios. The BWR Owners Group Emergency Procedure Guidelines and the list of Hatch safety-related systems will be used to define a set of scenarios which adequately sample various emergency conditions and the plant systems and system functions us'ed in those conditions. The related Hatch plant-specific EOP pathway will be identified as well in this step.

In addition, a brief narrative description of each scenario will be prepared that establishes the symptoms and limits of the events to be analyzed. It will include:

- initial plant conditions

- sequence initiator symptoms

- progression of action d

- final plant conditions

- major systems involved" .

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 21 OF 36 _-

DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 Actual plant walk-throughs will be conducted on a case basis to ensure that the simulator represents the plant correctly and that in-plant name plates are used for proper nomenclature of equipment. Extensive table-top reviews will be performed during development, especially utilizing the STA/ reactor operator member of the development team, and a record of problems and resolution will be kept. Additionally, initial operator training will be in-classroom table-top use of the EOP's, and operator feedback will be recorded. Note that simulator scenarios will be chosen randomly until all possible paths down the EOP Flow Charts are followed, thus ensuring complete coverage.

Documentation will include records of operator comments, changes made as a result, exam results, simulator records, and operator simulator performance records, Since EOP Ualidation satisfies the requirements, as defined for ^

Plant Hatch, of NUREG 0899, Section 3.3.5.1, c,e, and f, Desk-top reviews, Control room walk-throughs, and simulator exercises on the Plant Hatch Unit 2 plant specific simulator will be used during EOP Va,11dation.

3.8 EOP Training The following elements will be included in the-EOP Training Program: '

- Type of operator training (initial, refresher)

- Nothod of operator training (simulator, self-study, classroom) '

l - Operator knowledge and s'R111' level requirements

- Procedure limitations requiring operator decision-making r .o,.: ha%. ~ x , . . , ,, ;s ;,;Q' ,.5., , . -..

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 22 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1

- Training material needed

- Method for operator feedback into the training program and EOP

. development

- Consideration of the effect on current plant operation while training operators on EOPs 'not yet in place at the plant 3.8.1 Course Description -

l 3.8.1.1 Course

Title:

Initial Training Course for Symptomatic .

l Emergency Operating Procedures at Hatch Nuclear Plant.

3.8.1.2

Description:

An introduction to the new concept of -

Symptomatic Emergency Operating Procedures which are to

~

l replace the current Emergency Operating Procedures.

During this course, the background for the'new type l

+

procedures will be discussed including the events that led -

i up to the changes and why it was necessary to make these changes.

The course will be conducted in the classroom and at the i

simulator.

t Since there is only one EOP for each unit for emergency operation within the control room all operators will exercise it during training. The Plant Hatch simulator is a duplicate of the Unit 2 control room so the EOP for Unit 2 will be used during the simulator exercises. The EOP e ()$[hl6 48 4k3 &$4 % M + " # 'N e 8 #

GEORGIA POWER COMPANY HATCH NUC'_ EAR PLANT PAGE 23 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT O I

for Unit 1 is identical except for valves and valve numbers and will be table top reviewed in the classroom

. along with the Unit 2 EOP. Thus all EOP's will be exercised by each operator during the simulator i

exercises.

It is important that the operators receive training on a, ,

wide variety of scenarios, including multiple simultaneous and sequential failures. Simulator ,

exercises were selected to meet the following objectives:

] a. Control manipulations required by the Harold Denton letter, dated March 28. 1980.

b. Exercise all portions of the flowcharts.

c. Exercise all procedures in the End Path Manual that the simulator is capable of simulating.

d. Exercise flowchart branching; i.e., path-to-path -

arrow changes, key parameter changes, path-specific parameter changes.

The scenarios used for training are the source for the ones used for, validation. -

For'any changes made to the EOP's as a result of the EOP Verification or EOP Validation programs, operator retraining needs will be determined by the Plant Hatch Training Department Manager and will be included, as I

appropriate to the type and magnitude of the change, in i

the operator quartchly licences requalification training programs.

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PAGE 24 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.8.1.3 Duration: Approximately 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months 3.8.1.4 Objectives: upon satisfactory completion of this course, the participant will be able to:

- Explain the background that led up to the development of the new procedur'es and why the change was made from

" Event Based" Procedures to " Symptom Based" Procedures. _

- Demonstrate an acceptable level of skill in the use of the new procedures during simulated emergency ,

conditions.

- Understand basis for and be able to use the various

^

new graphs and limits in the new EOPs.

3.8.1.5 Prerequisites: Should have Reactor Operator (RO) level of knowledge of GE-BWR plant operation for Module 1.

Modules must be taken in order given here, since each module assumes the information of previous modules.

3.8.1.6 Participant Eligibility: This course is appropriate for licensed Reactor Operators (RO), Senior Reactor Operators (SRO), individuals who are in training for an operator's ligense and other plant personnel who are familiar with plant operation and frequently monitor or review operational events. -

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 25 SF 36 I

DOCUMENT TITLE: EOP-IMPLEMENTATION PLAN FOR REVISION:

j- EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.E.1.7 Materials Required:

q

. Instructional Handout for this Course ,

Chalkboard t -

Overhead Projector

- Current HNP Procedu'res-New Symptomatic Emergency Operating Procedures ,

j Including Flowcharts and End Path Manuals Generic Emergency Procedure Guidelines j -

HNP Specific Technical Guidelines All changed HNP Procedures Appendices to Emergency Procedure' Guidelines that i

j contain bases.

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! HATCH NUCLEAR PLANT PAGE 26 0F 36 DOCUMENT-TITLE-: EOP IMPLEMENTATION PLAN FOR REVISION: s EMERGENCY ESPONSE CAPAHILITY PROJECT 1 3.8.2 Modulo 1 i i .

BACKGROUND i ANS STANDARDS FOR EMERGENCY PROCEDURES ANS 3.2 THREE MILE ISLAND ACCIDENT -

NRC CUIDANCE FOLLOWING THE TMI ACCIDENT ESSEX CORPORATIONS REVIEW OF TMI BWR (GE) OWNERS' GROUP ;

t-

- STUDY QUIZ , l

. i i

TIME ,

i t

MODULE - 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months -

I

. STUDY - I hour QUIZ - 1/2 hou'r .

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 27 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REUISION:

EMERGENCY RESPONSE CAPAllILITY PROJECT 1 3,8.3 Module 2

, EXISTING EVENT ORIENTED PROCEDURES REVIEW INSTRUCTIONS CURRENTLY USED BY OPERATIONS PERSONNEL PHILOSOPHY OF EMERGENCY INSTRUCTIONS - WHAT ACTUALLY

' CONSTITUTES AN EMERGENCY SYMPTOM ORIENTED UERSUS EVENT ORIENTED EMERGENCY INSTRUCTIONS USE OF CURRENT EMERGENCY INSTRUCTION IN.THE EVENT OF MULTIPLE FAILURES DISADUANTAGES OF CURRENT EMERGENCY INSTRUCTIONS

SUMMARY

STUDY

. QUIZ -

TIME ,

MODULE w 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ' STUDY - . I hour

. QUIZ -

1/2. hour

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l GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 28 OF 36 i DOCUMENT TITLE: ~

EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1

{

i 3.8.4 Modulo 3 +

i I j * ,

1 , BWR (GE) OWNERS' i GROUP GUIDELINES AND 'I r ..

l HNP SPECIFIC GUIDELINE

- i i

}

t .

INTRODUCTION TO GUIDELINES

- HNP SPECIFIC GUIDELINE '

! - HNP SPECIFIC GUIDELINE APPENDIX ,

OPERATOR CAUTIONS

j .

i -

REACTOR PRESSURE VESSEL CONTROL GUIDELINES i l' s i -

PRIMARY CONTAINMENT CONTROL CUIDELINES ,

]

j -

SECONDARY CONTAINMENT CONTROL GUIDELINES l RADIOACTIVITY RELEASE CONTROL GUIDELINE i.

CONTINGENCIES P i

SUMMARY

t i t r 4 - STUDY <

1 -

QUIZ i 4

i TIME ,

i d

, MODULE -

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months

I i

! STUDY -

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months t QUIZ - 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

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HATCH NUCLEAR PLANT PAGE 29 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.8.5 Module 4 BASES FOR EOP

! GUIDELINES, CURVES, LIMITS i

. . _ _ _ _8ASI_S FOR_ GENE.RAL.. CAUTIONS._ _,,_., _,,.

HOW GENERAL CAUTIONS ARE USED i -

1 BASIS FOR SPECIFIC CAUTIONS j

l -

HOW SPECIFIC CAUTIONS ARE USED

{ -

BASIS FOR GUIDELINE STEPS j -

' BASIS FOR ALL CURVES AND LIMITS ;

]

- HOW TO READ, INTERPRET AND USE 1

SUMMARY

j - STUDY 1

I -

QUIZ f I i

~

TIME

[ MODULE' - 24 hou.rs '

STUDY -

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months '

. QUIZ - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months J

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HATCH NUCLEAR PLANT PAGE 30 0F 36 I DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION: ;

EMERGENCY RESPONSE CAPABILITY PROJECT 1 k

t 3.8.6 Module 5 -

j .

APPROACH TO BWR OWNERS' GROUP GUIDELINES AND NEW EOPs

.i

?

a FLOWCHARTS J

l END PATH PROCEDURES SYSTEM RECOVERY CONTINGENCIES l CONTAINMENT CONTROL GUIDE ANTICIPATED TRANSIENT WITHOUT SCRAM - AThS 1

HOW EXISTING PROCEDURES ARE TO,BE MODIFIED !

SUMMARY

STUDY QUIZ l

1 ,

[

]

TIME ,

1

. MODULE -

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months i

STUDY -

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months i

QUIZ -

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ..

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 31 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.8.7 Modulo 6 b

USE OF NEW EMERGENCY PROCEDURES

- SYMBOLS USED ON FLOWCHARTS i .

GENE.RA.LDES_CAIPTION OF THE FIVE FLCWCHARTS . PATHS

- TECHNIQUES FOR CHART AND END PATH PROCEDURE USE

- SINGLE FAILURE EVENT - CHART AND END PATH EXERCISE

- MULTIPLE FAILURE EVENT - CHART AND END PATH EXERCISE ,

- ADVANTAGES OF NEW PROCEDUNES

SUMMARY

- STUDY '

- QUIZ

? - . .

l TIME 1

l . MODULE -

- 24 hours j STUDY -

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

, QUIZ ,

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s .

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT .. PAGE 32 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.8.8 Module 7 l

l i

o SIMULATOR TRAINING USING NEW SYMPTOMATIC

_ , _ _ _ _ EMERGENCY PROCEDURES

.. a*

- ENTRY CONDITION - REACTOR SCRAM

~~

SYMPTOMS

- IMMEDIATE ACTIONS END PATH MANUALS ,

PATH CHANGES FLOWCHART EXERCISES

- SINGLE EVENT

- MULTIPLE EVENTS (sequential and simultaneous) l ~

CONTINGENCIES l SIMULATOR EVALUATION OF EACH TRAINEE i

l l

TIME MODULE - 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months .

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 33 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.8.9 Module 8 COURSE REVIEW

SUMMARY

OF MODIFIED PROCEDURES ,

- . SUMMA 8Y_OE_.E10W CHARTS _ _ _ . . . - _ _ _ _ -1

SUMMARY

OF END PATH MANUALS

- RESPONSE TO QUESTIONS / COMMENTS FROM ATTENDEES THROUGHOUT COURSE

SUMMARY

OF CURVES / LIMITS

- STUDY

- FINAL EXAM l TIME

-- . . - - MODULE -

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months STUDY -

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months FINAL EXAM- 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months s- '

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PAGE 34 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REUISION:

EMERGENCY RESPONSE-CAPABILITY PROJECT 1 m 3.9 Revision. Review and Approval Process Revision, review and approval of the EOPs and new support procedures will be in accordance with the existing Plant Hatch procedure " Preparation and Control of Procedures"

_.G O A C- MG R-00 3 - _O S ).._ _ . __,' ._ ,_

3.10 EOP Control E0Ps will be controlled within the existing plant document control system and in accordance with the Hatch procedure

" Preparation and Control of Procedures" (10AC-MGR-003-OS) and

" Emergency Operating Procedures Program (Writer's Guide)"

(30AC-OPS-004-OS).

3.11 Supporting Documentation Control The process used to develop the Plant Specific Technical Guidelines will be documented in sufficient detail to show the flow of information f. rom its analytical base to its use in the development of technical guidelines, thereby providing a complete documentation package. The development process

~

includes documentation of the assumptions, references to the

, results of the analy, sis, and a description of the actual process us'ed to gene ate the technical guidelines. This information, to be incorporated into an-appendix to the HNP Specific Technical Guidel'ine, will become, along with the guidelines themselves (Generic and Plant Specific), controlled documents subject to the existing plant procedures for control of those types of documents.

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GEORGIA POWER COMPAMY HATCH NUCLEAR PLANT PAGE 3G OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 3.12 Experience Feedback To ensure that the EOPs are maintained in a manner that is _

responsive to operating experience, the existing HNP procedures will be used to incorporate applicable recommendations derived from review of operating experien'ces and operator comments. Procedure change recommendations may be provided by plant operators, NSSS vendors, owners groups, other utility groups, industry groups, .

utilities and the NRC. Plant Hatch assesses these recommendations and makes appropriate changes in accordance with administrative procedures for control of changes to procedures (see section 3.9).

In addition, feedback from operator training and from plant audits will be considered as potential Input for procedure modifications.

3.12.1 On-Going Evaluation The EOP's will be subject to the normal periodic review of all Hatch procedures in accordance with 10AC-MGR-OO3-OS. ~

3.13 Updating EOP's When changes occur in the plant design, Technical Specifications, Technical Guidelines, Writer's Guide, other plant procedures or :

~

control room that wil.1 affect the EOPs, the EOPs will be revised on l a timely b' asis to reflect these changes, in accordance with Hatch procedure " Emergency Operating Procedure" Revision Requirements (30AC-OPS-OO7-OS). In addition, when operating and training ,

experience, simulator exercises, control room walk-thrcughs, or i other information indicate that incorrect ~or incomplete information exists in the EOPs, the EdPs shoul'd be revised on a timely basis.

These changes should be reviewed to ensure consistency with the Technical Guidelines and the Writer's Guide. Operators have been encouraged to suggest improvements to EOPs.

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_ HATCH NUCLEAR PLANT PAGE 36 OF 36 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR- REVISION:

EMERGENCY RESPONSE CAPABILITY PROJECT 1 1

1 j 3.14 Availability and Accessibility of EOP's, The EOP's, Flow Charts and End Path Manuals for each unit will be a

1 stored by the control (unit) operator's desk. The End Path Manuals 1

will be stored on shc19es under the process computer typewriters '

immediately to the left of t'he control operator's desk and the flow 7 charts in a rack installed on the curved divider immediately behind ,.

the control operator's desk. The End Path Manual will be laid out j on the control operator's desk when in use. Th'us the EOP's are immediately available and accessible for response to a potential or emergency condition requiring their use. These locations to be verified during Control Room. Design Review(DCRDR) or if human factors dictate alternate locations may be selected.

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f f HATCH NUCLEAR PLANT PAGE 1 OF 84 l DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

4 ! PROCEDURES PROGRAM (WRITER'S GUIDE) 1

/"' X SAFETY RELATED APPROVED DATE l NON-SAFETY RELATED EFFECTIVE DATE:

EXPIRATION DATE N/A

'l IREV. I I APPROVED I I APPROVED l I INO. I DESCRIPTION I DEPT. MGR. I DATE I GEN. MGR. I DATE I 1 I l I I l i I I I '

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i GEORGIA POWER COMPANY f HATCH NUCLEAR PLANT PAGE 2 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 4

TABLE OF CONTENTS SECTION . ,

PAGE 1.0 OBJECTIVE .......................................................-,5 1 . l ..S C O P E ... _ ..... . . . . . ... . . . . . . ... . . . '. ..... . . ... . ... . . . . . ... . . . ... . . . . . . . 5 l.2.RELAT.IQMSHIP._OF_EOPs TO OTHER PLANT PROCEDURES ....... .......6.

1.3. WHAT.CONST.ITUTES AN EOP..... ................................. 6 1.4 THE INTRODUCTION TO THE FLOW CHARTS PROCEDURE

. _ _ .._.(COVER PROCEDURE)...................................... 7 1.5 THE FLOW CHARTS............................................. 7 1.6 THE END PATH MANUALS........................................ 8 2.0 APPLICABILITY................................................. 8

3.0 REFERENCES

.................................................... 8 -

3..l'_ DEVELOPMENTAL REFERENCES.................................... 8

_3._2_. IMPLEMENTING REFERENCES..................................... 9

j. 4.0. RESPONSIBILITIES.............................................. 9

~

5.0 REOUIREMENTS................................................. 10 5.1 PERSONNEL REQUIREMENTS..................................... 10 5.2 MATERIAL AND EQUIPMENT..................................... 10 t

5.3 SPECIAL REQUIREMENTS.......'................................ 10 j MGR-0001. Rev.1 i

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 3 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 4

4 TABLE OF CONTENTS SECTION PAGE 6.0 PRECAUTIONS / LIMITATIONS...................................... 11 6.1 PRECAUTIONS................................................ 11 .

6.2 LIMITATIONS................................................ 11 7.0 PREREOUISITES................................................ 11 8.0 PROCEDURE.................................................... 11 8.1 ORGANIZATION OF AN EOP..................................... 11 8.2 ORGANIZATION OF FLOW CHARTS................................ 15 8.3 END PATH MANUAL PROCEDURE PREPARATION...................... 25 l

8.4 USE OF EOPS................................................ 54 8.5 USE OF OPERATOR AIDS....................................... 54 -

8.6 EXCEPTIONS................................................. 55

) 9.0 PSTG DISPOSITION IN EOP'S .

9.1_ INTRODUCTION................................................

9.2 RC/L - REACTOR VESSEL , LEVEL CONTROL.........................

9.3 RC/P - REACi'OR VESSEL PRESSURE CONTROL......................

9.4 RC/Q - REACTOR VESSEL POWER CONTROL.........................

9.5 CONTAIUMENT CONTROL........'.................................

9.6 RADIOACTIVITY RELEASE CONTROL...............................

9.7 CONTINGENCIES...............................................

MGR-0001, Rev.1

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 4 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 TABLE OF CONTENTS .

., ATTACHMENTS .

PAGE 1 RELATIONSHIP OF EOPS TO OTHER PLANT PROCEDURES...... 56 2 ENTRY CONDITIONS AND INTERRELATIONSHIP OF EOP FLOW CHARTS AND END PATH MANUALS................ 57 3 TITLE PAGE FORMAT FOR EOP'S......................... 50 4 DESIGNATION AND NUMBERING OF FLOW CHARTS............ 60 5 FLOW CHART LOGIC SYMBOLS............................ 61 6 EXAMPLE DECISION TREE UTILIZING STANDARD LOGIC SYMBOLS.............................. 64 -

7 SAMPLE ACTION VERB LIST............................. 65 MGR-0001, Rev.1

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 5 OF 84 )

DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 1.0 OBJECTIVE .

This Procedure outlines the content and format necessary to implement the requirements set forth in NUREG 0899, Guidelines for the Preparation of Emergency Operating Procedures, and result in stand-alone, user-oriented procedures. The purpose of this Procedure is to provide administrative and technical guidance on

- r the preparation of Emergency Operating Procedures, and to serve as a Writer's Guide.

1.1 SCOPE By broad definition, Emergency Operating Procedures (EOPs) are those procedures that direct actions necessary to mitigate the i consequences of transients and accidents that have caused plant parameters to exceed reactor protection system set points, engineered safety feature set points, or other established i limits. As specifically applied to Plant Hatch procedures, - ~

Abnormal Operating Procedures contain pre-scram actions and Emergency Operating Procedures contain post-scram actions. This Procedure pertains only to the Emergency Operating Procedures, with Abnormal Operatin,g Procedures covered by 10AC-MGR-003-OS, Prepa Ttion'and Control of Procedures.

The emergency operating procedures will, by incorporati g the BWR owners Group emergency procedure guidelines, specifically the !

PSTG for Plant Hatch, address and incor'porate appropriate operator

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 6 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

i PROCEDURES PROGRAM (WRITER'S GUIDE) 1 action for events as delineated in ANSI 18.7 Section 5.3.9.2, and in Section 8.2.1.2 of this document. The Abnormal Operating

! , Procedures.or the Site Emergency Plan will contain operator l actions for events such as natural disasters, civil

,. disturbances, and fires. .However, and where appropriate for these kinds of events, post scram operator actions will also be integrated into the EOPs.

, 1.2 RELATIONSHIP OF EOPS TO OTHER PLANT PROCEDURES The information contained in the EOPs should be compatible widh the information contained in other plant procedures that support

~

l the EOPs. Format for EOPs differs slightly from the format j

j specified for other procedures as. outlined in 10AC-MGR-003-OS.

The format of the EOPs, with Flow Charts for symptoms and j j immediate operator actions, and End Path Manuals for subsequent f operator actions, makes the EOPs uniquely identifiable. -

4 . .

i Attachment 1 and Attachment 2 depict the overall relation: hip of

~

the EOPs to other plant procedures. However, all instances are ,

. not covered by the attachments since the intent is to show that procedural flow is aceo~mplished throughout the procedure ,

i . ~ 's structure to ensure safety function knowledge and ultimately plant safety and recovery.

1.3 WHAT CONSTITUTES AN EOP l 1.3.1 An EOP shall consist of a cover procedure, five j symptom-oriented procedures which are to'be in Flow' Chart '

t I format, and End Path Manuals which are to be in the written i

i or prose format. -

1 A

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PAGE 7 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION: !

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ,

i 1.4 THE INTRODUCTION TO FLOW CHARTS PROCEDURE (COVER PROCEDURE)

The cover procedure provides the operator with the general cautions 4

4

.aome specific cautions and other information printed on the side of "

l 2

the Flow Charts. The cover procedure will contain the objective and l 3

entry conditions for.the Flow' Charts. The cover procedure's procedure section will contain an introduction to the Flow Chart

. \

{. i 1

2 methodology, an explanation of' Flow Chart ties to the End Path 1~

4 Manual, and an'overall method to use the Flow Charts with the End _

Path Manual. Additionally, the cover procedure contains a list of ;

i i

current revision numbers of all sections of the EOP. I

! 1.5 THE FLOW CHARTS I

The Flow Charts provide the operator with a systematic and explicit "

t means for determining the safety status of the plant for emergency 4

situations triggered by any automatic or required manual scram l

i regardless of the combination of initiating events. The Flow Charts J .

contain the immediate operator actions to effectively bound ;

multiple-event sequences and bring the plant to a known stable j .

state. Restoration of reactor and containment parameters and systems t

~

f recovery can be accomp1ished via the End Path Manuals. The.End Path

+.

Manuals. ent'ered from the Flow Charts, provide the guidance to complete the safe recovery of the plant and provide conditions from ,

i a

which repairs and return to power operation can be accomplished, l Regardless of the event-specific initiating sequences, the ;

' symptom-based flow'c' harts have built into them numerous " verification i

of action" steps to assist the operator in diagnosis of the

initiating events.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 1.6 THE END PAT!! MANUALS The End Path Manuals are entered from the Flow Charts when the pperator has completed a particular path on the Flow Chart he is utilizing. Each Flow Chart will indicate which End Path Manual and

, contained procedure are to be' entered. The End Path procedures are made up of information derived from the previous' event specific procedures (e.g., HNP 1900 Series), contingency action, emergency Procedure guidelines, system recovery. procedures, primary and secondary containment control procedures, reactivity control

guidelines, Reactor Pressure Vessel (RPV) control guidelines, and radioactivity release control guidelines.

2.0 APPLICABILITY This Procedure (Writer's Guide) applies to the writing of all Plant Hatch Emergency Operating Procedures, consisting of Flow Charts and End Path Manuals. -

3.0 REFERENCES

3.1 DEVELOPMENTAL REFERENCES 3.1.1 10CFR50 Appendix B, Criterion V, Instructions, Procedures and Drawings

3.1.2 10CFR50734, Contents of Applications: Technical Information 3.1.3 ANSI-N18.7-1976, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants MGR-0001, Rev.1

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 i

3.1.4 Regulatory Guide 1.33, Revision 2, Appendix A, Quality Assurance Program Requirements (Operation) 3.2 . IMPLEMENTING REFERENCES 3.2.1 INPO 82-017 Emergency Operating Procedures Writing

< Guideline, July 1982 I 3.2.2 BWR Emergency Procedure Guidelines, BWRl-6, Revision 3 l December 8, 1982 3.2.3 NRC Safety Evaluation Report dated November 23, 1983.

3.2.4 NUREG-0899. August 1982, Guidelines for the Preparation of Emergency Operating Procedures 3.2.5 lOAC-MGR-003-OS, Preparation and Control of Procedures i 4.0 RESPONSIBILITIES 4.1 Manager of Operations 4.1.1 Has primary responsibility for procedures generated as EOP's.

4.1.2 Ensure proper use of " Preparation and Control of Procedures" -

(10AC-MGR-003-OS) for review and approval *of EOP's.

4.1.3 Ensure proper use of " Emergency Operating Procedure Revision Requirements "(30AC-OPS-007-OS), including checklist as 1 .

appropriate. ,

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PAGE 10 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 5.0 REOUIREMENTS 5.1 PERSONNEL REQUIREMENTS

. Personnel developing or performing reviews of the EOP's shall be knowledgeable in the disciplines and bases of the Emergency Procedure Guidelines (EPG's).' Because of the vast areas of information and expertise involved, writing a successful EOP is a team effort. The team should include, but not be limited to, people who are skilled in the areas of technical writing, power plant operations, operator training, engineering design and human factors.

5.2 MATERIAL AND EQUIPMENT

_N/A - Not applicable to this procedure.

5.3 SPFCIAL REQUIREMENTS 5.3.1 Generic BWR Emergency Procedure Guidelines I The background information shall consist of appendices to ~~

the Generic BWR Emergency Procedure Guidelines and shall be documented both as a learning tool and as an aid for verification of actions / analyses performed to achieve the level of accuracy in the technical guidelines.

5.3.2 Plant Specific Tec nical Guidelines 5.3.2.1 The plant specific technical guidelines will be s

identical to the generic emergency procedure guidelines except that Hatch Plant specific data will be used in the various limits, tables, and graphs: references to systems not found at Plant Hatch will be deleted.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 5.3.2.2 The generic and plant specific guidelines are oriented 4 so that emergency operating procedures written from them

. can be used by an operator to mitigate the consequences of an emergency without first having to diagnose the event or event combindtion causing the emergency. The generic and plant specific guidelines are based upon the requirements of NUREG b737, Clarification of TMI Action Plan Requirements, and will be the latest revision approved by the NRC.

6.0 PRECAUTIONS / LIMITATIONS 6.1 PRECAUTIONS i N/A - Not applicable to this procedure.

6.2 LIMITATIONS N/A - Not applicable to this procedure.

7.0 PREREOUISITES -

I' N/A - Not applicable to this procedure.

l 8.0 PROCEDURE i 8.1 ORGANIZATION OF AN EOP 8.1.1 The EOPs will be o,r'ganized in the following general sections:

TitlePage()

ObjectiveofEOP()

EntryCondition()

ProcedureBody()

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8.1.2 The three parts of the EOP will contain the sections from the list above as follows:

EOP PART SECTIONS CONTAINED Cover Procedure h hh hh Flow Charts End Path Manual Procedures hhhh

As modified for Flow Chart methodology and implementation 8.1.3 Title Page The title page of an EOP will be identical to that shown in Attachment 3 of this Writer's Guide. -

8.1.4 Objective of an EOP

, The objective of an EOP (which is the purpose.of the EPG) will be a precise and simply stated paragraph of what the EOP is to accomplis'h.

~

8.1.5 Entry Conditions The single entry condition for all Flow Charts shall be "Any Scram".

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.1.6 Procedure Body 8.1.6.1 The Cover procedure is intended to introduce the flow

. chart methodology and cautions. It also explains for general. interest _the ties _between.the Cover procedure,

, <- Flow Charts, and End Path Manuals. The Cover procedure is included as a reference and repository document for general information desirable for the operator to have access to (e.g. General Cautions). The Cover procedure is.not required to.be used.or entered before the operator can react to the emergency nor is he taught to j do so. All the operator need do upon receipt of any i

l automatic or required manual scram, as he is taught to do, is to take any flow chart and proceed to follow its instructions. .Should the plant be at steady state power level and should the operator review the EOP, the Cover procedure is conveniently placed to refresh his memory on general information. The Cover procedure is also useful in training as a big picture view of the EOP.

~

8.1.6.2 The Flow Chart,s body shall contain opera' tor immediate actions which will include but not be limited to verification and check statements to ensure that the indicated' automatic system action is accomplished, assurance that the reactor is in a safe shut down 1

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DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) I condition, notification of the emergency to plant personnel, determination that the reactor coolant

, system boundary is intact, confirmation of availability of adequate power sources, and

., confirmation that containment and exhautt systems are operating properly.

The flow charts, as a minimum will contain the following sections of the PSTG:

RPV Control _

RC/L - To start of cooldown RC/P - To start of cooldown RC/Q - All PCC (Primary Containment Control)

Drywell cooling Drywell Venting Suppression Pool cooling Contingencies _

C1 - Level restoration - All C2 - Em'ergency Depressurization - All as it applies to RPV Flooding l

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DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 C3 - Steam Cooling - All C4 - Core Cooling Without Level Restoration - All C6 - RPV Flooding.- All C7 - Level / Power Control - All 8.1.6.3 The End Path Manual shall contain End Path Procedures which have subsequent action steps that the operator takes to return the plant to a normal steady-state condition or to provide for a safe extended shutdown

! ~

period. The subsequent operator actions follow completion of the Immediate Operator Actions and are wholly contained in the End Path Manual. As a minimum, the End Path Manual in its various sections will contain all of the sections of the EPG, specifically for Revision 3, dated Dec. 8, 1982, and from which the PSTG has been developed, as follows: ~ ~

RPV Control RC/L - All RC/P - All RC/Q u

,Subseq'ent actions to refill SLC tank.etc.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 i

PCC (Primary Containment Control)

All -

. SCC (Secondary Containment Control)

All -

RR (RADIOACTIVITY RELEASE CONTROL)

Site Emergency Plan Procedures w'ill also contain entry conditions.

, Contineencies All Additionally, the End Path Manual will contain the following:

8.1.6.3.1 Cover Procedure The cover procedure will be placed at the front of the End Path Manual, for convenience to the operator.

8.1.6.3.2 Contingencies ~'

This section of the End Path Manual shall contain the contingency actions of the BWR Emergency Procedure Guidelines, and other actions as determined,necess'ary.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.1.6.3.3 System Recovery _ Procedures This section of the End Path Manual shall contain the procedural guidance to recover selected systems that were lost either during the initiating event sequence or as a result of'the initiating event sequence.

8.1.6.3.4 Containment Control Procedures This section of the End Path Manual shall contain the bulk of the BWR Emergency Procedure Guidelines dealing with primary and secondary containment control.

8.1.6.3.5 Reactivity Control Procedures This section of the End Path Manual shall contain reactivity control guidance of the BWR Emergency Procedure Guidelines.

8.1.6.3.6 Sequencing Sequencing of the above sections is as required by the PSTG. This required PSTG sequencing is to be contained within the guidance of the End Path Procedure specified in 8.1.6.3.

8.1.6.3.7 Section Access Each section of the End Path Manual will be tab divided. The Cover page of each section will have on it the' number and name of each tab's contents and locator lines will be used to aid the operator's access to the individual tabs.

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and Secondary Containment Control will be visible on a card easily visible to the operator at all times while using the End Path Manual, e.g..on the inside binder spines.

8.2 ORGANIZATION OF FLOW CHARTS The Flow Charts shall consist of 5 symptom-oriented decision tree action paths. The Cover Procedure shall contain the objective and introduction to the Flow Charts and shall describe how these instructions are to be used by the plant operators to handle emergency or potential emergency situations. . .

8.2.1 Designation and Numbering 8.2.1.1 The Flow Charts are the procedures that govern the plant operation during emergency conditions and specify immediate operator actions to be taken to bound the problem and to return the plant to a stable condition. -

Each Flow Chart shall be uniquely identified (see

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i Attachment 4). . This identification (acting as the title

, page) permits easy administration of the process of

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procedure revi,sion, distribution, and operator use.

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HATCH NUCLEAR PLANT PAGE 19 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.2.1.2 The various Paths will have some overlapping information on j them as required to ensure each can stand alone, but they can be generally described as follows:

Path 1 - Malfunction of reactivity control system Path 2 - Reactor trans'ients or failure of vital equipment from low reactor power (mode switch in Startup/ Standby)

Path 3- - Reactor transients or f ailure of vital equipment from high reactor power (mode switch in Run)

Path 4 - High steam line radiation, loss of vital power, failure of vital equipment, or loss of coolant

, (under degraded conditions)

Path 5 - High radiation, loss of coolant, and control of primary containment integrity (under degraded conditions)

The Flow Charts shall not have identifying titles. The L

philosophy is for the operator to immediately enter any ;

Flow Chart when the entry condition occurs. Once the operator enters s the Flow Chart, it will lead to the proper f procedural steps.

8.2.2 Revision and Authorization Each Flow Chart shall include the current revision number and authorizing signatures. This information shall be located at the upper right of each Flow Chart (see Attachment 4).

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, HATCH NUCLEAR PLANT PAGE 20 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

, PROCEDURES PROGRAM (WRITER'S GUIDE) 1 i i-

8.2.3 Identification for Flow Charts '

There shall be site identification and unit identification for ,

. the Flow Charts as shown on Attachment 4. The identification !

block shall be printed black-on-white for Unit 1 and i

white-on-black for Unit 2'to allow easy identification.

~

l i !

8.2.4 Page Identification !

! There shall be no page identification on the Flow Charts.' The !

j I l Flow Charts will be identified by Path (i.e. Path 1, Path 2,

! etc.). (See subsection 8.2.1.)

I L i 8.2.5 Format i j The Flow Charts shall utilize logic symbols as specified on 1 i

] Attachment 5. These symbols shall be arranged in a decision i - -

r tree type Flow Chart that provides the operator with guidance ;

i i

intended to bound the problem and get the plant into a safe E

{ condition quickly, systematically and consiste'ntly (see -

Attachment 6). Information in all the logic symbols shall be l

i of typewriter quality and be in all CAPITAL letters so that '

1 readability is maintained on the reduced size charts. -

~ i

! 8.2.6 Decision Symbol ' -

i i

{ 8.2.6.1 This symbo1*shall contain a question which the operator is to answer YES or NO. ,

The question shall pertain to a plant

~

parameter,' setpoint, switch position, or system condition.

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PROCEDURES PROGRAM (WRITER'S GUIDE) I l

8.2.6.2 If the particular step is designated as a " key" parameter, (See Attachment 5) it shall' have an action symbol super-imposed over the standard decision symbol and the decision symbol shall be in bold lines. This identifies steps which require the operator'to return to the top of the chart and a

restart in the event this " key" parameter changes state after having been passed. A normal decision block chang-ing state after having been passed only requires the oper-ator return to that one decision block and continue.

l 8.2.6.3 In order to indicate to the operator which path he should take in the event he does not know the answer to a given decision box, a small black triangle shall be placed in the corner of the symbol in the direction of the desired Path. Examples are shown on page 3 of Attachment 5.

These special operator aids are placed only in those decisions where a possibility exists'of not knowing the answer. EXAMPLES: In the question "IS CONTROL ROOM EVACUATION REQUIRED?", the small triangle is not required. In,the question "HAS DRYWELL PRESSURE BEEN ABOVE 1.8 PSIG SINCE SCRAM?", the small triangle would go in the "YES" corner, indicating the conservative path.

8.2.7 Action Step Symbol (Sequence Sensitive)

This symbol shall contain a specific action or command which the operator performs, and must be performed in the sequence indicated.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.2.8 Action Step Symbol (Sequence Insensitive)

This symbol shall contain a specific action or command which the operator performs, and may be performed at the operator's option prior to reaching the step on the Flow Chart, (See Attachment 5).

These steps may be performed in parallel (concurrently) uith other steps as operators are available. Concurrent actions are to be specified in the body of the step in the End Path Manual.

8.2.9 Information and Scram Entry Symbol This symbol shall contain information which may be useful to assist the operator in diagnosing plant conditions. The symbol is also used to provide operator cautions. The most significant use of this symbol is as the ANY SCRAM entry symbol for any of the flow charts (see Attachment 5).

8.2.10 Additional Information Page 2 of Attachment 5 shows how reference is made to available displays on the SPDS system, fire actions, cautions, note, and other miscellaneous information.

8.2.11 Arrow Symbols There shall be two, basic types of arrow symbols used on the Flcw

. ~.

Charts (see Attachment 5). The path-to-path arrows guide the ,

operator from one Flow Chart to another or to another location on the same chart'. The path-to-end-path arrows shall guide the operator from the Flow Chart Immediate Action Steps to End Path Procedures. Attachment 6 shows how the path-to-path arrows are MGR-0001, Rev 1

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 individually modified to key the operator to a specific corresponding arrow on the new path, and how the grid locations are noted (see subsection 8.2.18).

8.7.12 Connecting Lines .

There shall be two basic line widths used to guide the operator through the Flow Chart. The operator should follow these lines always entering the symbols at the top and exiting the symbols at the side or bottom.

The wide line represents the expected plant response for each Flow Chart for normal plant recovery. All lines are equally important. They represent possible response of the plant for many situaticas on each Flow Chart. No lines shall cross or intersect on the Flow Charts, except where two or more enter the came symbol.

8.2.13 Entry Condition - -

The entry condition for each Flow Chart is identical (see Attachment 6) and is identified in the cover procedure. The entry condition shall be "Any Scram", and is contained in an information symboi. (See Attachment 5) 8.2.14 Flow C' hart Initial Format jEach Flow Chart shall have an identical initial series of symbols as shown on Attachment 6. The placement of YES/NO and type of connecting line will vary according to individual path

~

r equ i r emen't s . This initial'sek'uence establishes priority of actions and guides the operator to the appropriate Flow Chart.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 Plow Charts for Shutdown Outside the Control Room may have additional actions between the ones shown on Attachment 6,due to the special nature of those procedures.

8.2.15 Automatic Actions -

Important safety systems automatic initiation verifications shall be included in the Flow Charts. The following statement enclosed within an action symbol is an example of operator verification of automatic actions: " Verify Auto or .

Manually Start UpCI".

8.2.16 Immediate Operator Actions -

The steps on the Flow Charts are the Immediate Operator Action Steps. These operator actions are taken to stop further degradation of existing conditions and to mitigate their consequences or to bound the problem. The immediate operator actions are visible at all times to the operator:

therefore, there is no need for the operater to memorize these actions.

8.2.17 Operator Cautions Operator caution,s may be included on the Flow Charts where

_ s appropriate. The caution will precede the procedural step to which it applies, and shall be highlighted as shown in Attachment 5. Cautions of a more general or frequently used nature may appear in boxes down the right side of the flow charts as shown in Attachment 4, and referenced in the flowcharts as specifi'e'd in Attachment 5, page 2 of 3.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.2.18 Grid System Each Flow Chart shall have a series of letters along the ,

sides and arabic numerals along the top and bottom to act as a grid locator system (see Attachment 6). The resulting intersecting a'reas (B1 for example) should be arranged to encompass approximately 3 to 5 Flow Chart symbols. The grid system is used for path-to-path arrows and to allow operators to indicate to other personnel where they currently are in the chart. EXAMPLE: to allow the managers in the Technical Support Center to follow progress on the Flow Charts.

8.2.19 Preparing and Mounting Flow Cnarts The Flow Charts will require off-site assistance to prepare since they are extensively color-coded and computer-generated. The completed charts shall be reduced to approximately 20" x 35" (or as small as deemed practical and readable) and mounted on lightweight boards such as styrofoam. Each board will then be laminated with

~

a thin, transparent pla'stic material.( Each Flow Chart board may be framed with lightweight aluminum'for additional strength. The Control Room Flow Charts shall have at least a one half inch blank border on all sides to '

increase readability.

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!f. < DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1

.8.2.20 Reproduction of Flow Charts For training or other administrative purposes, the flow charts may be reproduced on a standard blueprint copier.

The copies of the flow charts used in the control room and simulators must'be original, color-coded, laminated charts as delineated in subsection 8.2.19.

8.2.21 Revisions to Flow Charts q, The revision process for the Flow Charts requires the same.

administrative controls as all other procedures, in accordance with 10AC-MGR-003-OS. In addition, special requirements for control of revisions to the Emergency Operating Procedures are contained in 30AC-OPS-007-OS, Emergency Operating Procedures Revision Requirements.

Also contained therein is a checklist to track progress of the revision process. ~

, The current revision of each Flow Chart'shall be maintained in accordance with Hatch procedures for control of procedures.

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GEORGIA POWER COMPANY' MATCH' NUCLEAR PLANT PAGE 27 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING . REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.2.22 Color Coding On any given Path 1 through 5, yellow indicates the expected, though unverified response path, and is used exclusively for the mainpath down the chart. Green is.a deviation, but is otherwise normal. . Orange is also a deviation; however, a degraded plant response may be involved. Red is a deviation with definite degradation of plant equipment. The color of a logic symbol indicates the degradation associated with that specific sequence of actions. Connecting lines should be the same color as the logic symbol from which they originate, except for lines coming out of decision symbols, where the color of the line in'dicates the implied level of degradation

, associated with the answer to.the question asked in the decision symbol.

8.2.23 Equipment Nomenclature * ~~~

8.2.23.1 Nomenclature used shall assist personnel in quick location or identification of equipment, controls, and 3

displays. Use a consistent system of identification.

~

which corresponds closely to component identification

. po'sted on eq ipment and control panels. Location information will also be included as follows:

For shutdown outside'the control room, location information will be provided for every valve, switch, pump,' panel, etc.

For shutdown'inside the control room, location information will be provided for those components not normally used by the operator.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.2.23.2 A common sense approach to equipment nomenclature must be taken. In cases where the full, exact data taken ,

from actual nameplates is considered confusing or otherwise inadequate, the exact nameplate data should not be used, instead operator accepted common usage terms will be included. This is a very important decision to be made and all good human factors engineering judgment shall be used. Ultimately, the procedure validation program will demonstrate the adequacy of names used.

8.2.23.3 If nameplate data and commonly used name are used together in a step, the nameplate data shall be placed in parentheses after the commonly used name.

EXAMPLE: ARE PLANT SERVICE WATER TURBINE BUILDING (PSW T/B ISOL) VALVES 2P41-F316 A, B, C, D CLOSED? ~

8.3 END PATH MANUAL AND COVER PROCEDURE PREPARATION 8.3.1 Purpose This section gives guidance on how to write and assemble the subsequent actions End Path Manual" f or the symptom-based flow-cnart oriented EOP's.

8.3.2 Procedure Identification Proper identification of procedures is necessary to avoid errors in selection and implementation. Complete identification of a procedure includes its title, number, facility (i.e., HNP),' revision and type.

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DOCUMENT TITLE: EMERGENCY OPERATING REVISION: J l PROCEDURES PROGRAM (WRITER'S GUIDE) 1 i~

l , 8.3.2.1 Procedure Title Each procedure will be given a title which accurately .

reflects its' intended purpose. Within this constraint, procedure titles shall be kept as short and concise as s I j - - possible..

8.3.2.2 Procedure Designation i The eleven significant character alphanumeric designator for the Emergency Operating Procedures shall be~in j accordance with 10AC-MGR-003-0.

8.3.2.3 Procedure Numbers ,

1 8.3.2.3.1 Each procedure will be assigned a unique and .l i

permanent number within'its associated Path and

1 i

Section of the End Path Manual. Whenever a

procedure is deleted, the associated procedure I number will not normally be reassigned for the ,

ensuing 2-year period. If reassignment is made within this. period, consideration should be given to

user retraining to avoid confusion or-error.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.2.3.2 Procedure numbering shall be controlled as follows:

. Sections 2.20-2.29 - End Path Manual Procedures from Flow Charts . Path 2, 20-29 Sections 3.30-3.39 - End Path Manual Procedures from Flow Charts - Path 3, 30-39 Sections 4.40-4.49 - ' End Path Manual Procedures from '

Flow Charts - Path 4, 40-49 Sections 5.50-5.59 - End Path Manual Procedures from Flow Charts . Path 5, 50-59 l NOTE l l l l "X" in Section Number indicates the End Path Manual number l l (i.e. which Flow Chart was exited). l

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S e c t i o n s X . 0 ,0 - X . 0 9 - - Cover Procedures

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 31 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 4

8.3.3 Page Identification Beginning with the Title Page, the top of each page of each ~

procedure will bear the procedure designation, current revision number and page number as an aid to validation by the-user. Each procedure'shall begin with a new page. .

2 The title page format will be as shown in Attachment 3.

8.3.3.1 Revision Number The revision number shall be a one or two digit number indicating the current approved revision.

8.3.4 Page Numbering Each page of each procedure shall be numbered sequentially beginning with'the Title Page. If pages are added to a procedure, complete renumbering of all pages shall be Performed.

j The page number shall appear in the following format:

PAGE OF i

Likewise, when pages are deleted by revision, the procedure i

l .

pages shall be renumbered.

8.3.5 Identification of Revised Material 2

Revised' material shall be identified with a vertical line in the right-hand margin opposite the revised text. Vertical lines from any previous revision shall be deleted.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.6 General Writing Techniques The following section provides a set of standards which sha.11 be considered in the preparation and review of all EOPs. In .

considering these guidelines, writers shall keep in mind that some are more important than others for different sections of procedures. The writer shall always consider the conditions l under which the procedure will be implemented, the time available .

for its implementation, and the possible consequences,of errors _

in implementation.

8.3.6.1 Multiple-Unit Procedures Procedures which contain multiple sets of equipment identifications for use with more than one unit are more difficult to read and comprehend than procedures dedicated to a single unit. Therefore, a unique set of procedures for each unit shall be developed. To ease identification, color coding may be used wherever appropriate.

8.3.6.2 Page Format A single column format shall be used. The general appearance of procedural pages c'ontributes significantly to comprehension and the elimination of confusion and error.

Information on pages shall be displayed with minimum clutter, sufficient' spacing between lines, and adequate margins for reproduction and binding. Binding shall not obscure information. The remaining sections of this procedure give !

further guidance.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.6.3 Step Numbering, Indenting, and Checkoffs Instructional steps must be readily identifiable by the_

user. Step numbering, indenting, and checkoffs are used to assist procedure users in keeping track of step sequence and subordination. The following guidelines apply:

Only Arabic numerals shall be used in step numbering.

The same step numbering and indenting scheme will be applied consistently to all procedures.

The acceptable numbering scheme is as follows with the optional checkoff spaces shown:

1.0 1.1 1.1.1 1.1.1.1 1.1.1.1.1 Numbering and indenting beyond the section of the example above shall not be used. If necessary, procedures.should;be reorganized to produce an acceptable number of subsections. Subsection numbers should be indented two spaces from the preceding section or subsection number margin.

Checkoff spaces shall be placed as shown for all steps requiring an operator action, and may be used elsewhere if it'will enhance the operator's ability to keep track of his place in the procedure.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.6.4 Step Sequencing Instructional steps in the End Path Manual procedures .

will be presented in the sequence most appropriate for the situation. Instructional steps which can be

,' 'performedconcurrent1hshallbesomarked.,Whenthe sequence of actions is critical, the phrase "in the order given" or similar phrase may be used in the step introducing the actions, if so desired.

8.3.6.5 Caution Statements l NOTE 'l l 1 l Cautions on the flow charts are specified in l l subsection 8.2.17. l l 1 8.3.6.5.1 Cautionary information can be considered in two _

fundamental categories, those that apply to the entire procedure and those that apply to r portion

or a specific step of the procedure. Those that apply to the entire procedure, so-called " General

-Cautions",**will be contained in the cover procedure. Those that apply to a portion of a procedure are placed immediately before the procedural steps to which they apply.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1

, 8.3.6.5.2 Cautions shall extend across the entire page and i shall be highlighted as shown in the Example ,,

CAUTION. This placement of cautions helps ensure that the procedure user observes the caution before performing the step. A caution cannot be used instead of an instructional step. It should be used to denote a potential hazard to equipment or personnel associated with or consequent to the subsequent instructional step. The caution shall be capitalized with the word CAUTION underlined.

Caution statements shall be written so that they can be read completely without interruption by page turning.

EXAMPLE:

CAUTION CAUTIONS SIIALL BE TYPED IN ALL CAPITAL LETTERS ONLY 4

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.6.6 Notes A note provides descriptive or explanatory information intended to aid personnel in performing an instructional

' step. Notes shall not contain action steps. Notes shall be as close to the applicable instruction as possible, and shall be approximately aligned with the text of the -

appilcable instruction step as shown in the Example. The word NOTE shall be capitalized and underlined, and shall be highlighted as shown in the Example.

EXAMPLE:

I I l NOTE l l

l Notes shall be typed in structured sentences.

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l PROCEDURES PROGRAM (WRITER'S GUIDE) 1 i

I 8.3.6.7 Calculations ,

Mathematical calculations should be avoided in EOPs. If h

.- a value has to be determined in order to perform a l procedural step, a chart or graph should be used

, 'whenever possible. When calculations are required, they' shall be as simple as possible, and space shall be provided for the calculations.

8.3.6.8 Referencing and Branching _

\ l j 8.3.6.8.1 Referencing implies that an additional procedure or i

! additional steps will be used as a supplement to the i

procedure presently being used. Referencing other steps within the procedure being used, either future steps or completed steps, should be minimized. When only a few steps are involved in the referencing, i

the steps should be stated in the procedure wherever they are needed.

l 8.3.6.8.2 To minimize potential operator confusion, branching will be used when the operator is to leave one Procedure or step'and use another procedure or

. s step. .Use explicit language, such as "go to".

Therefore, the operator will know to leave the presen't stop and not return until directed. Use quotation marks to emphasize the title of the referenced or branched procedure; examples: Go to E-1, " Loss of R'eactor Coolant". Go to Step 20.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.6.9 Style of Expression Style of expression refers to the way in which _

instruction steps are written. Steps will be written in a style that presents information in a simple, familiar

.' and clear manner. The following guidance shall be followed:

8.3.6.9.1 Use words that are common in ordinary conversation.

8.3.6.9.2 Use terms personnel are trained to use and which are standard in the industry.

8.3.6.9.3 Use action verbs that describe exactly what the user is to do. Ensure that these verbs are understood

.l and used consistently throughout procedures.

! Samplos of action verbs are given in Attachment 7.

8.3.6.9.4 When there are more than two objects of an action 1

verb, list them below the instruction step rather

, than in the step.

4 EXAMPLE: USE OBJECTS OF VERBS AS FOLLOWS 3.2.9 open the following valves:

2.B21-F016 l

2B21-F019 1

2B21-F038 j EXAMPLE: DO NOT USE

! 3.2.9 open valves 2B21-F016, 2B21-F019 and 2D21-F038 l

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 s

Objects of verbs and their usage as in this example ,

should not be confused with combination of ..

r conditions (8.3.7.4.4) where acceptable usage is as follows: .

EXAMPLE: USE COMBINATION OF CONDIT[ONS AS FOLLOWS: l

-3.2.15 IE all rods not inserted past position 02 ;

l AND reactor power is above 3% AND suppression pool temperature is above 110 F, THEN......... ,

1 1

1 i

1 8.3.6.9.5 Use short, direct sentences. Establish a style of 1 1

sentence construction suitable for the procedure ^

i i

i type and use it consistently. '

l 8.3.6.9.6 Number of actions per step shall be minimized, and

( .

j limited to one action where possible. Where two actions are inclu'ded in one step, use the connective AND rather than two sentences.

8.3.6.9.7 Avoid adverbs that have imprecise meanings,such as '

frequently, quickly, slowly, rapidly, words that t

connotate a time interval, rather use words as in tho following example.

EXAMPLE: Une "'every 5 minutes until...."

4 I

rather than " frequently until.."

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l PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.6.10 Instrumentation Values When specifying instrumentation values, an appropriate range, tolerance or limit will be used rather than a single point value. Avoid the use of mathematical 9

symbols in specifying these ranges. Instead, use Phrases such as " greater than", "above", "below",

"between", " greater than or equal to", etc., that are as familiar as possible to the operator.

8.3.6.11 Equipment. Controls, and Display 8.3.6.11.1 Nomenclature used shall assist personnel in quick location or identification of equipment, controls, and displays. Use a consistent system of identification which corresponds precisely with component identifications posted on equipment and control panels. Location information will also be included as follows: '

For shutdown outside the control room, location information will be provided for every valve, switch, pump, p'anel, etc. For shutdown inside the control room, location information will be Provided for tho,se components not normally used by the ' operator.

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PROCEDURES PROGRAM (WRITER'S CUIDE) 1 8.3.6.11.2 A common sense approach to equipment nomenclature must be taken. In cases where the full, exact data taken from actual nameplates is considered confusing or otherwise inadequate, the exact nameplate data s'hould not be used, instead operator accepted common usage terms will be included. This is a very important decision to be made and all good human factors engineering judgment sha11 be ,

used. Ultimately, the procedure validation program will demonstrate the adequacy of names used. .

8.3.6.11.3 If nameplate data and commonly used name are used together in a step, the nameplate data shall be placed in parentheses after the commonly used name.

EXAMPLE: ARE PLANT SERVICE WATER TURBINE BUILDING (PSW T/B ISOL) VALVES 2P41-F316 A B, C, D CLOSED 7 -

8.3.6.12 Abbreviations. Letter Symbols, and Acronyms 8.3.6.12.1 Abbreviations may be used where necessary to save time and space, and when their meaning is unquesti nably' clear to the intended reader. Write in the full meaning of the abbreviation before the first use of the abbreviation and whenever in doubt. Maintain consistency throughout the procedure, including use of capitalization in the abbreviations. If the abbreviation is comprised of lower caso letters, it should appear in lower caso MGR-0001, Rev.1 GilllNi $rYk 0'E . - o, n bl.5E ll1%Ygl& 5.,s. .:nt v.M.* -

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 in a title or heading. Omit the period in abbreviations except in cases where the omission would

. result in confusion. Where an abbreviation is not

, currently used in plant procedures, the abbreviation will be discussed in the training program. A listing of acceptable Abbreviations Acronyms, Letter symbols, etc. is contained in the PSTG, Table 1.

8.3.6.12.2 Letter symbols may be used to represent operations, quantities, elements, relations, and qualities.

8.3.6.12.3 An acronym is a type of symbol formed by the initial i

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 commonly used, and they need not be written out in full. EXAMPLES: HPCI, RCIC, ECCS.

8.3.6.12.4 Abbreviations, symbols, and acronyms should not be -

! overused. Their use should be for the benefit of the l reader. They can be beneficial by.saving reading time, j .

i ensuring clarity when space is limited, and

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communic,ating mathematical ideas.

8.3.6.13 Le' vel of Detail Too much detail in EOPs should be avoided in the 8.3.6.13.1

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interest of 'being able to effectively execute the i instructions in a timely manner. The level of detail required is the detail that a newly trained and licensed opet'ator would desire during an emergency condition.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.6.13.2 Recommended action verbs are as follows:

For power-driven rotating equipment, use Start, Stop.

For valves, use Open, Close, Throttle Open, Throttl'e Close. Throttle. -

For power distribution breakers, use Synchronize and Close, Close, and Trip.

For control switches with a positional placement that establishes a standby readiness condition, the verb

" Set" should be used, along with the engraved name of the desired position. Positional placements are typically associated with establishing readiness of automatic functions and are typically named AUTO or NORMAL: for example, " Set the GLAND SEAL AIR COMPRESSOR Control Switch (S15) in AUTO".

For multiposition control switches that have more than one position for a similar' function, placement to the desired position should be specified: for example, " Place DIESEL FIRE pump selector switch to TEST No.,2".

8.3.6.13.3 Standard practices for observing abnormal results need not be prescribed within procedural steps. For example, observation of noise, vibration, erratic flow, or discharge pressure need not be specified by steps that start pumps.

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DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ,

, , 8.3.6.14 Equipment Status Equipment status should be denoted as follows: ,,

j 8.3.6.14.1 Operable / operability - See definition contained in Unit 2 Technical Specifications, section 1.0, Amendment 14.

I 8.3.6.14.2 Operating - This word means that a system. . ,

j subsystem, train. component, or device is in .

operation and is performing its specified , ,

l function (s), and that "Out of Service Cards" or i

j other conditions do not prevent it from maintaining that service.

j 8.3.6.14.3 Available - This word means that a system, j subsystem, train component, or device is capable of

performing its specified function (s) in the '

intended manner, but does NOT necessarily imply i j

that all redundant support systems are in service. i

{ EXAMPLE: If RFPT A DC oil pumps are out of service t

but the RFPT is otherwise normal, RFPT A would not be considered operable, but would be considered available.

! 8.3.7 Instructional Steps -

1 l

8.3.7.1 Instruction Step Le'ngth and Content I

j 8.3.7.1.1 Instruction steps shall be concise and precise.

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j Conciseness denotes brevity; preciseness means exactly defined'. Thus, instructions shall be short 1

i and exact and conform to American Standard usage 1

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PROCEDURES PROGRAM (WRITER'S GUIDE) I except where preciseness dictates otherwise.

8.3.7.1.2 Instruction steps shall deal with only one idea. Short,

. simple. sentonces shall be used in preference to long, compound, or complex sentences. . Complex evolutions shall be prescribed in a series of steps, with each step made as simple as practicable.

8.3.7.1.3 Objects of operator actions shall be specifically ,

stated. This includes identification of exactly what is to be done and to what and should be in the imperative form.

8.3.7.1.4 Each action step shall be wholly contained on a single page.

8.3.7.1.5 For instructional steps that involve an action verb, relating to three or more objects, the objects shall be listed with space provided for operator checkoff.

8.3.7.1.6 Limits shall be expressed quantitatively whenever possible (see Subsection 8.3.6.10). .

8.3.7.1.7 Identification of components and parts shall be complete. ,(See subsection 8.3.6.11.)

. *s 8.3.7.1.8 When system responso dictates a time frame within which the instruction must be accomplished, prescribe such time frame. If possible, however, avoid using time to initiate operator actions; operator actions shall be,

~~

' where possib'10, related to plant parameters.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ,

8.3.7.1.9 When actions are required based upon receipt of an annunciated alarm, list the setpoint of the alarm for case of verification. When requiring resetting or restoration of an alarm or trip.. list the expected results immediately following the resetting or restoration if it would be beneficial to the operator.

8.3.7.1.10 Expected results of routine tasks nood not be .

stated. When considered beneficial to the user for proper understanding and performance, describe the system response time associated with performance of the instrucLion. When anticipated system response may adversely affect instrument indications.

describe the conditions that will likely introduce instrument error and means of determining if instrument error has occurred by using a NOTE.

8.3.7.1.11 When additional confirmation of system response is considered necessary, prescribe the backup readings to be made.

8.3.7.2 Instruction Co,lumns Only single-column format shall be used in the EOP's.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.7.3 Contingency Actions

. 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 results. The need for contingency action occurs in conjunction with tasks involving verification, observation, confirmation, and monitoring. Contingency actions will be specified i

for each circumstance in which the expoeted results or actions might not be achieved. The contingoney actions shall identify, as appropriato, directions to overtido automatic controls and to initiate manually what is normally automatically initiated.

8.3.7.3.1 Alternative Actions l Where steps for a number of alternativo actions are equally acceptable, those stops should be provided.

8.3.7.4 Use of Logic Terms ,

8.3.7.4.1 The logic terms AND, OR, NOT, IF, IF NOT, WHEN, and THEN are of' ten nocoscary to describe procisely a set

'of conditions or sequence of actions. When logic

~

statements are used in the End Path Manual text, logic terms will be highlighted by capitalization and underlining so that all the conditions are clear to the operator. N6 such underlining of' logi'c terms is to be dono on the Flow Charts.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.7.4.2 The use of AND and OR within the same action shall be avoided. When AND and OR are used together, the logic can be very ambiguous.

8.3.7.4.3 When attention should 'so called to combinations of conditions. the word AND shall be placed betwoon the description of each condition. The word AND shall not be used to join more than throo conditions. If four or more conditions nood to be joined. a list format shall be used.

8.3.7.4.4 The word On shall be used when calling attention to alternativo combinations of conditions. The use of the word OR shall always be in the inclusive senso.

To specify the exclusivo "OR", the following may be used: "oither A OR D but NOT both." When action stops are contingent upon cortain conditions or combinations of conditions, the stop shall begin with the words IF or WHEN followed by a description of the condition or conditions, a comma, the word THEN, followed by"the action to be taken. WHEN is usod for '

an expected condition. IF is used for an unexpected but possible condition. Uso of IF NOT shouId bo limited to those casos in which the operator must respond to the second of two possibio conditions. IF should be used to specify the first condition. THEN shall not bo usbd at the end of an action stop to MGR-0001, Rev.1

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l LEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 49 OP 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 instruct the operator to perform the next step because it runs actions together.

.4.3.7.5 Use of Underlining ,

, Underlining will be used for emphasis of logic terms and CAUTION and NOTE.

8.3.7.6 Use of Capitalization 8.3.7.6.1 American Standard usage will prevail except where emphasis for clarity dictates otherwise. The names of plant system titles shall be emphasized by capitalization, with the word " system" deleted or.not doloted at writer's discretion.'

8.3.7.6.2 Capitalization may be used wherever else in the writer's opinion it will enhance usability or emphasis of the proceduto steps.

8.3.8 Printed Operator Aids When information is presented using graphs, charts, tables, and figures, these aids must be self-explanatory, legible, and readable under the expected conditions of use and within the reading precision ot the operator. -

8.3.8.1 Units of Measure Units of measure on figures, tables, and attachmonto shall be given for numerica'l values that represent observed data or calculated results. A virgule (slant line) should be used -

instead of "por". Units of' measure and numerical values will l be used that are an' familiar as possible to the operator.

EXAMPLES: ft/sec, 1bs/hr.

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LEORGIA POWER COMPANY l' HATCH NUCLEAR PLANT PAGE 50 OF 84 l DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

l PROCEDURES PROGRAM (WRITER'S GUIDE) I f ,

8.3.8.2 Figure Table, and Attachment Numbering 8.3.8.2.1 Sequential arabic numerals shall be assigned to ,,

. figures, tables, and attachments in separate series. The sequence shall correspond with the order.of their reference in the text. The symbol

"#" and abbreviation "No." are unnecessary and shall not be used. .

8.3.8.2.2 Page identification for attachments shall consist of a block of information that identifies (1) procedure number, (2) attachment number, (3) page number, and (4) revision number. Page numbering of attachments shall meet the requirements of Subsection 8.3.4.

8.3.8.2.3 Where standard forms are used from other procedures, they should be referenced and used in preference to complete duplication, where possible. -

8.3.9 Mechanics of Style 8.3.9.1 Spelling .

Spelling should be consistent with modern usage.

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LEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 51 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.9.2 Hyphenation Hyphens are used between elements of a compound word ,,

when usage calls for it. ,The following rules shall be followed for hyphenation. When doubt exists, the compound word shall be restructured to avoid hyphenation.

Hyphens shall be used in the following circumstances:

In fractions, examples: one-half, two-thirds; ,

In compound numerals from twenty-one to ninety-nine, i

example: one hundred thirty-four:

To separate chemical elements and their atomic weight, examples: Uranium-235, U-235; When a letter is linked with a noun, examples: x-ray, 0-ring, U-bolt, I-beam; In compounds with "self", examples: self-contained, self-lubricated; When misleading or awkward consonants would result by joining the words, example: bell-like:

~

To avoid confusion with another word, examples: re-cover

, s to prevent confusion with recover, pre-position to avoid confusion with preposition.

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 52 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.9.3 Punctuation Punctuation should be used only as necessary to aid reading and prevent misunderstanding. Word order shall 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 shall be in accordance with American Standard usage and in accordance with the following rules:

Brackets - do not use brackets, i

Colon - use a colon to indicate that a list of items is to follow.

Comma - use of many commas is a sign 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 comma after conditional phrases for clarity and ease of reading. EXAMPLE: WHEN level decreases to 60 inches, THEN start pump.... .

Parentheses - parentheses shall be used to indicate

~

alternative items in a procedure, instruction, or equipment s

numb'er, and to mark when verbatim equipment nomenclature is being used. (See subsection 8.3.6.11.3.).

Period - use a period at the end of complete sentences and for indicating the decimal place in numbers.

Dash-maNbeusedtoset off items in a list.

MGR-0001, Rev.1 l

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 53 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.9.4 Vocabulary Use simple words. Simple words are usually short words of

. few syllables. Simple words are generally common words.

Words used in procedures shall be selected to convey

, - precise understanding to the trained person.

8.3.9.5 Numerical Values The use of numerical values should be consistent with the following rules:

Arabic numerals shall be used.

For numbers less than one, the decimal point shall be preceded by a zero. EXAMPLE: 0.1.

The number of significant digits should be equal to the number of significant digits available from the display and the reading precision of the operator.

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. EXAMPLE: psig instead of psi.

Acceptance val'ues should be specified in such a way that

.,,e' addition and subtractidn by the user are avoided if possible. This can generally be done by stating acceptance values as limits. EXAMPLES: slo *F maximum, 300 psig minimum. 580* to 600*F. 'For calibration points, statementofthemidpointanditslowerandupper'limkts'

' ' ~

for each dat'a cell' would accomplish the same purpose; for

' example, 10 milliamperes (9.5 to 10.5). Avoid using 1

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 54 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 i

8.3.10 Typing Format 8.3.10.1 Page Arrangement

. Page margins shall be such as to facilitate readability, approximately one-half to one inch in width on all

, sides.

8.3.10.2 Heading and Text Arrangement The expanded block style used herein is to be used.

8.3.10.3 Breaking of Words Breaking of words shall be avoided to facilitate operator reading.

8.3.10.4 Rotation of Pages Pages should not be rotated. Tables and figures should be readable with the page arranged vertically.

8.3.10.5 Printed Operator Aids (graphs, drawings, diagrams, tables and illustrations) 8.3.10.5.1 The figure field must not violate specified page margins. .The essential message shall be clear;

, simple presentations are preferred. The figure number and its title are placed below the figure

~

field (refer to Subsection 8.3.8).

8.3.10.5.2 The figure field shall be of sufficient size to offer good readability.

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PROCEDURE 3 PROGRAM (WRITER'S GUIDE) 1 8.3.10.5.3 In general, items within the figure shall be labeled. Typed labels shall be used, where

. possible. Handwritten labels shall be printed, using all capitals, with letters and numbers at least 1/8 inch high. Labeling of items within the-figure shall be accompanied by arrows pointing to the item.

8.3.10.5.4 Grid lines of graphs shall be at least 1/8 inch apart.

8.3.10.5.5 The items within the figure shall be oriented naturally insofar as possible. For example, height on a graph should be along the vertical axis.

8.3.10.5.6 Tables shall be typed using the following rules

Type style and size shall be the same as that for - '

the rest of the procedure. A heading shall be entered for each column and centered within the column. The table number and title shall be located a'bove the table field.

s 8.3.10.5.7 Tabular headings shall be aligned as follows:

Horizontally by related entries, vertically by decimal point for numerical entries, and vertically by first letter'for word entries.

However, run-over lines shall be indented.

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.10.5.8 There shall not be a vacant cell in the table. If no entry is necessary, "N.A." shall be entered to indicate not applicable.

8.3.10.5.9 Double spacing between horizontal entries suffices to segregate such entries, although horizontal lines may also be used if desired.

8.3.10.5.10 Do not clutter the field of the figure with extraneous and nonessential information. _

8.3.10.6 Cautions and Notes The applicable heading " NOTE" and " CAUTION" shall be capitalized and centered. The text of the note or caution shall be block format. All words in cautions shall be capitalized. Examples are presented in Subsections 8.3.6.5 and 8.3.6.6.

8.3.10.7 Use of Foldout Pages When used, a foldout page is treated as a single page.

It shall follow the same format as a standard page as described in this procedure except the width is different. ,The page shall be folded so that a small margin exists between the fold and the right-hand edge of standard pages, to reduce wear of the fold. Foldout pages shall not be used if the foldout section will cover any other procedures as placed in the End Path Manual.

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 57 OF 84 DCCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 8.3.10.8 Reverse Page Printing Reverse page printing may be beneficial in order to keep .

certain curves or limits associated with the procedural text. If this is the case, the curve or limit shall be printed on the reverse side of the previous page in the same orientation as the text page so that it is directly readable by the operator. No text will be placed on the .

reverse side of a figure so printed, except for standard page header information and the statement "[ figure name]

printed on reverse side - turn page".

All other curves, limits, tables, data packages, etc. not printed on reverse pages will be referenced in the text as Attachments and so included.

8.3.10.9 Reproduction All copies of the End Path Manual procedures shall be ~

clearly legible. When it is necessary to replace an entire procedure or make partial revisions as a result of wear, use, etc, the replacement copy shall be equal to

, thequalityof[the' original, contain as a minimum all the info'rmation of the original or have identified changes and care will be taken to insure all reverse page Printing is accomplished as correctly as in the original.

8.4 USE OF EOPs ,9 The EOPs are to be utilized as a set with the Flow Charts as the MGR-0001, Rev 0

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PROCEDURES PROGRAM (WRITER'S CUIDE) 1

" entering" media. If no automatic or manual scram signal is present, the operator will utilize his abnormal, annunciator, or normal operating procedures for guidance. If, at any time, the entry condition exists, the operator is directed to utilize the EOPs. -

8.5 USE OF OPERATOR AIDS Operator aids (such as Flow Charts and Checkoffs) will be used to assist the operator in returning the plant to a controlled condition.

8.5.1 Flow Charts Flow Charts will be used as a job performance aid for immediate operator actions in place of written procedures. They will be ,

plastic coated so that a grease pencil or marker can be used to track progress. Reduced, paper copies of Flow Charts can then be marked up to be included in a post scram report.

8.5.2 Check Offs The End Path Manuals will have places for operator initials to track position in the procedure, as specified in section 8.3.6.3. .

6.6 EXCEPTIONS This procedure, a Writer's Guide for the development of Emergency Operating Procedures, should be considered as a guide. All procedures or revisions of procedures written in accordance with this procedure must be individually reviewed and approved by the Plant Review Board. '

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1 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 59 OF 84 -

l DOCUMENT TITLE: ' EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S CUIDE) 1 9.0 PSTG Disposition in EOPs.

9.1 INTRODUCTION

The PSTG was used throughout the Plant Hatch EOPs. However, the guideline was used as a guide only, not a procedure.

The flowcharts have been designed to eliminate operator confusion associated with when to enter the EOP and exactly what actions should be taken during the initial few minutes following the onset of the potential emergency condition.When the flowchart steps are

, completed, the operator will be directed to one of the procedures in the End Path Manual.

The purpose of this section is to assist the procedure writer / reviewer in determining how to convert the PSTG into the EOP. It identifies where the PSTG appears in the EOP.

The entry condition to the Plant Hatch EOPs is any condition which requires or initiates a reactor scram. The operator then needs only to remember to pick up any one of the five flowcharts following a scram and act as indicated.

The steps from RC/L and RC/P are contained on Paths 1, 2, 3, 4, and

5. The key parameters,on each flowchart prioritize the order of

. ~s executidn of these sections. The steps from RC/Q are contained on Path 1.

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PAGE 60 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 9.2 RC/L - REACTOR VESSEL LEVEL CONTROL The flowcharts direct the operator to verify automatic actions as

required. The first action steps past the key parameters direct the operator to verify automatic start or to-manually start HPCI, RCIC, and SBGT. ..Three steps later the operator is directed to verify closure of Groups 1, 2, and 5 isolation valves. If auxiliary power is not available (on any flowchart), the operator is directed to verify on or to manually start the diesel generators. The operator is also directed to start the diesel generators, RHR, and core spray pumps if the RPV water level decreases to -116 inches. ,.

This guidance is shortly after the key parameter evaluation. Where '

the flowchart has identified a parameter that an automatic action is associated with, the flowchart will verify that automatic action has occurred or will require that appropriate manual action be taken. -

If the reactor does not scram (i.e., all control rods do not insert past position 02) or the power is above 31 following the initiation of a scram signal, the operator is directed to Path 1. If boron injection is then requ, ired while on Path 1, the operator is directed to execute the boron injection steps of Contingency #7 contained on Path 1.

If the RPV water level cannot be determined while on the flowchart, the operators are led through the required steps to line up all high pressure and low pressure ECCS prior to exiting t e flowchart.- The end path pfo'cedure provides the following type of

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 61 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 guidance for this type of situation: "UE while executing this Procedure, reactor vessel level CANNOT be determined OR reactor evessel flooding is required. THEN EXIT this End Path Procedure and ENTER the " Flooding Procedure" in the Contingency section of this End Path ~ Manual."-

RPV flooding is required for two severe containment problems; i.e.,

when the primary containment temperature increases to the RPV saturation point and when the primary containment pressure reaches the design pressure.

The Plant Hatch containment control procedures, primary containment temperature and primary containment pressure control. direct the operator to the flooding procedure for each problem and all steps are contained in the End Path Manual.

Rather than merely listing systems to maintain vessel level, the Plant Hatch flowcharts prioritize the use of sys'tems by defining plant conditions through fault tree logic; e.g., on Path 4.if the vessel level has decreased below the level which automatically closes or directs the operator to close the MSIVs, the procedure then directs the operator to use HPCI, RCIC, and CRD to maintain level since the Feedwater System in now unavailable.

If the operator is unable to maintain RPV level with high pressure systems, the react'r o is depressurized and low pressure systems are used to restore level.

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PAGE 62 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 On Paths 2 and 3, if the MSIVs are open or pressure is below 600 psig, the Condensate /Feedwater System is used to maintain RPV

level. If the operator is unable.to maintain level with Condensate /Feedwater, HPCI and/or RCIC are used. IF level still cannot be maintained, the operator will be directed to Path 4 in preparation for LPCI or Core Spray use.

Each flowchart directs operators to continue increasing injection flow to the reactor until level is either increasing, stable, or above the high level trip setpoint. Each end path procedure provides guidance to maintain level between +12 and +50 inches. If this level cannot be maintained, the alternate band (above -164 inches) is specified.

Paths 1 and 5 follow the same pattern; the most desirable system that is available is used to maintain level. Each flowchart specifies level to be maintained between +12 and +50 inches.

Instructions to restore and maintain level between +12 and +50 inches and a list of systems and pressure ranges are included as one of the first steps in each end path procedure.

Flowcharts 2, 3, and 4 do not inhibit the ADS timer.

s Flowcharts 1 and 5 contain this action since a high drywell pressure signal is required. ,

If level control problems are encountered while in the End Path Manuals, operators will be directed to the Level Restoration Contingency, which contains the guidance to prevent automatic MGR-0001, Rev.1 4 .u wtM41$.YA.L ".,a.m~ .. : aw.. U .. . .s <UC&G $ $ % & e.u,

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GEORGIA POWER COMPANY MATCH NUCLEAR PLANT PAGE 63 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 initiation of ADS if RPV level can be maintained above -164 inches.

If, while using the flowcharts, the RPV water level cannot be maintained in the normal range, the operator is directed to the level restoration actions (Contingency #1) found on Path 4 or Path

~

.' 5.

All end path procedures also direct the operators to Contingency #1 if level cannot be maintained above -164 inches.

End Path procedures direct operators to normal procedures _for the purpose of taking the reactor to cold shutdown. If normal shutdown cooling cannot be established, the Abnormal Operating Procedures ,

would be entered.

When the emergency conditions no longer exist (i.e., the RPV level, pressure, and power are under control (normal) and no containment problems exist), the operator exits the EOP and enters the Normal Operating Procedure to take the plant to the desired mode; e.'.,

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hot standby or cold shutdown as directed by Plant Management.

9.3 RC/P - REACTOR VESSEL PRESSURE CONTROL -

Emergency RPV depressurization is not expected to be required within the first few minutes'following

~.

a reactor scram; i.e.. while the operators are using the flowcharts. The only times the ,

operator is directed to rapidl,y depressurize the RPV on the flowcharts is in e'xtremely degraded, low water level situations; e.g., the water level is below the top of active fuel or the RPV pressure must be maintained below 350 psig to accommodate low pressure system injection a'nd for flooding on Path 1.

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GEORGIA POWER COMPAWY HATCH NUCLEAR PLANT PAGE 64 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 It is unlikely that the main condenser would be available in this case. If depressurization is required while in the end path Procedure, the operator is directed to first attempt to use the main turbine bypass valves and then the SRVss In both' flowcharts and end path procedures, if depressurization is required and cannot be accomplished with SRVs or to the main condenser, the operators are directed to the Contingency action of using Alternate Depressurization Systems. ,_

If flooding is required while in the end path manual, the operator will be directed to Contingency M6 (Flooding Procedure) from the end path procedure. The Depressurization Steps are contained in Contingency M6. This simplifies the procedure by not going from an end path procedure, to a depressurization procedure, and then to a flooding procedure.

~

The flowchart directs the operator to prevent SRV cycling; e.g.,

immediately following the key parameters, the'HPCI, RCIC, and SRVs are used to control RPV pressure below 927 psig if Lo,w Low set fails to function properly. This guidance is repeated several times throughout the flowchar't at the appropriate locations. The end path procedures also contain adequate RPV pressure control guidance. ,

The heat capacity ' temperature limit is included in the Plant Hatch Containment Control Procedure (Suppression Pool Temperature Control-SP/T) as follows: IF suppression pool temperature CANNOT be maintained below the hea't capacity temperature limit, REDUCE

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, PROCEDURES PROGRAM (WRITER'S GUIDE) I reactor pressure with the Bypass Valve Opening Jack or SRVs to maintain reactor pressure below the limit.

The suppression pool load limit guidance is included in the Suppression Pool Level Control - High Level (SP/L) Procedure in the End Path Manual as follows: F suppression pool water CANNOT be' maintained below the suppression pool load limit, REDUCE reactor Pressure with the Bypass Valve Opening Jack or SRVs to maintain reactor pressure below the limit. _

Other methods of pressure control are also provided should both of these fail.

If steam cooling is required, the operator is directed to leave the Level Restoration Procedure.

When entering the Plant Hatch EOPs, if an ATWS (reactivity control system failure) condition exists, the operator is quickly directed i

to Path 1 by the first (highest priority) key parameter. Path 1 - "~

directs the operator to reopen the MSIVs and to reestablish the main condenser as a heat sink if boron injection in rbquired. At i all locations in the EOPs, when this guidance is provided, the operator is directed to check'the availability of the condenser and to check for indications of fuel failure or steam line break.

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HATCH NUCLEAR PLANT PAGE 66 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 i

All flowcharts contain Pressure Control Steps following the key parameters. The instruction is to maintain pressure below 927 .psig

.. .wi th SRVs, if Low Low set does not auto actuate and it becomes necessary to manually control pressure. Following a scram, the main turbine bypass valves should automatically control reactor pressure if the MSIVs are open. If the bypass valves fail to control reactor pressure or the MSIVs close, it is appropriate to use SRVs to control pressure at this early point in a transient.

All flowcharts also contain instructions to use HPCI and RCI for pressure control if required. Flowchart 1 and 3 also attempt to l i

restore the main condenser as a heat sink if plant conditions allow.

The End Path Procedures prioritize the systems used for pressure i control. The first priority is the main condenser, followed by SRVs, HPCI, RCIC, steam condensing mode, MSL drains, and RWCU. The choice at this point is left to the dis'cretion of the operator. -

Shutdown cooling is established in End Path Manual. If normal shutdown cooling cannot be established, operators are directed to Abnormal Operating Procedures for Alternate Shutdown Cooling methods for the proper,quidan'ce to establish an alternate means of shutdown cooling.

End Paths 2, 3, 4, and 5 direct the operator to proceed to cold shutdown as directed by plant management. If boron has been injected, operators will be provided the necessary guidance to prevent inadvertent criticality and limit the spread of boron to other plant systems. ,

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PROCEDURES PROGRAM (WRITER'S GUIDE) 1 9.4 RC/O - REACTOR VESSEL POWER CONTROL The Operators are trained to monitor reactor power. This key

parameter on the Plant Hatch flowchart directs the operator to determine whether or not the control rods are inserted past position 02 and that reactor power is less.than 31.

If the reactor fails to shut down upon the initiation of a scram signal, the operator is directed, by the key parameter, to go to Path 1. If boron is not injected and if the control rods can be fully inserted, the operator will be directed to return to one of I

the other flowcharts: 1.e., Path 2, 3, 4, or 5. However , if boron injection is initiated, the operator remains on Flow Chart 1 and when boron injection is complete, will be directed to the Reactor Power Control section of the End Path Manual appropriate for the then existing plant conditions.

All flowcharts require placing the mode switch to shutdown. '

On Path 1, the reactor recirculation pumps are placed at minimum speed as one of the initial actions. _

On Path 1, the reactor recirculation pumps are tripped following runback to minimum spe,ed if power is above 3% or can not be

~

determined.

The Path 1 flowchart contains the necessary guidance.for boron injection and also' requires the execution of alternate control rod insertion concurrently with the boron injection.

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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 60 OP 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 If neither SLC pump will operate, the Path 1 flowchart directs the operator to Alternate Boron Injection procedures which contains the steps necessary to inject boron from systems other than SLC.

If boron injection is required and an SLC pump is successfully started,' RWCU will be' isolated. If an SLC pump cannot be started.

RWCU will be isolated if it is not being used to inject boron.

If boron injection is required while in the End Path Manual, operators will be directed to return to Flow Chart 1. .

9.5 CONTAINMENT CONTROL (PRIMARY AND SECONDARY)

The Plant Hatch containment control procedures are located in the Containment Control section of each End Path Manual. These procedures are not expected to be needed immediately following the i onset of a potential emergency condition. However, for those conditions requiring entry into the containment control procedures

. Prior to the time the reactor is scrammed, the initial EOP guidance ~~

has been included in other procedures. For example, should the suppression pool temperature exceed 95 F during normal operation,

, an abnormal operating procedure provides guidance for the operator to initiate suppression ~.pool ' cooling and to scram the reactor prior to the pool temperature reaching 110 F.

Upon manual scram, the EOP would be entered, Immediate Action (flowchart) Steps ' executed, and the end path procedure entered, at which time the operator is directed to enter the containment control procedures (if an entry condition exists) and to execute the containment control pro'cedure concurrently with the end path procedure.

MGR-0001, Rev.1 l

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GEORGIA POWER COMPANY

-HATCH NUCLEAR PLANT PAGE 69 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 The entry conditions and operator actions for the containment control procedures for the Plant Hatch EOP are identical to the

.P STG . Plant-specific information is added as required.

9.6 RADIOACTIVITY RELEASE CONTROL -

The Plant Hatch Radioactivity' Release Control guideline entry conditions are referenced in the Site Emergency Plan and actions have been incorporated in Flow Chart Path 5 End Path Manual sections. As with Containment Control these procedures a,re not needed immediately, _hence are not contained in the flow charts.

9.7 CONTINGENCIES 9.7.1 LEVEL RESTORATION (CONTINGENCY #1)

Contingency 1 is contained in the Level Restoration procedure in the Contingency section of each End Path Manual. The entry conditions and operator actions are identical to the PSTG with plant-specific information added as required. This procedure is also written into Flow Charts 4 and 5.

9.7.2 EMERGENCY DEPRESSURIZATION (CONTINGENCY #2) .

Contingency 2 is contained in the Emergency Depressurization procedureinthe{ntingencysectionofeachEndPathManual.

The entry conditions and operator actions are identical to then PSTG with plant-specific information added as required.

9.7.3 STEAM COOLING'(CONTINGENCY #3)

Contingency 3 is contained within the procedure in each End Path Manual when it is required. This procedure has also been written into Flow Chart' 1 if no AC power is available.

MGR-0001, Rev.1

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L GEORGIA POWER COMPANY HATCH NUCLEAR PLANT -- -

PAGE 70 OF 84 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 9.7.4 SPRAY COOLING (CONTINGENCY #4)

Contingency 4 is contained within the procedures in each End Path Manual where it is required..

9.7.5 ALTERNATE SHUTDOWN COOLING (CONTINGENCY # 5)

Contingency 5 is' contained in Abnormal Operating Procedures 'and in the contingency section of each End Path Manual.

9.7.6 FLOODING PROCEDURE (CONTINGENCY #6)

Contingency 6 is contained in the Flooding Procedure.in the Contingency section of each End Path Manual with plant-specific information added as required. This procedure is also written into Flow Chart 1.

9.7.7 LEVEL / POWER CONTROL (CONTINGENCY #7)

Contingency 7 is contained in Flow Chart 1. The Reactivity Control section of each End Path Manual also contain some of this guidance plus long term guidance of boron diluti,on control.

~,

1 I

MGR-0001, Rev.1

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' ATTACHMENT 1 PAGE 71 OF 84

' GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE1 OF 1

' DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

TITLE PAGE' FORMAT FOR EOP'S

'SO L

t -

GM/Sy A3

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SYSfEM OPERATING PROCEDURES -

AB -

ABNORMAL OPERATING PROCEDURES EM -

EMERGENC.Y OPERA' TING PROCEDURES

_ s AR -

ANNUNCIATOR RESPONSE PROCEDURES .

. GM/SU- GENERAL MAINTENANCE OR SURVEILLANCE PROCEDURES MGR-0009, Rev.1

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ATTACHMENT 2 PAGE 72 0F 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE1 OF 1 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PRCGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

TITLE PAGE FORMAT FOR EOP'S REACTOR FAILURE LOSS OF ASNORMALLY

~

TRANSIENTS OF UITAL , VITAL POWER HIGH EQUIPMENT SOURCE RADIATION LOSS OF EXCESSIVE COOLANT RADIOACTIVE

. . %N I, AUTOMATIC LOSS OF OR MALFUNCTION CONTAINMENT REQUIRED OF REACTIVITY INTEGRITY MANUAL / CCNTROL SYSTEM

! SCRAM .

4 I . '

Y .

IMMEDIATE ACTION ,

FLON bHARTS

.- SHO3T" TIME

. RESFONSE I

Y -

. END PATH MANUALS

. . . . . . . .- . "#* ' ' ' -~ ' " - ~

._.LONG' TIME -

RESPONSE ,

1 MGR-0009, Rev.1

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ATTACHMENT 3 PAGE 7 3 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 2 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

TITLE PAGE FORMAT.FOR EOP'S N

INSTRUCTIONS

~ Block 1 - Procedure page identifie'r: Page (what) of (how many) .

Block 2 - Type of procedure ,

Block 3 - Complete procedure title Block 4 - Procedure number Block 5 - Revision Number (0 for original; 1,2,3, etc. for revisions)

'( 2 locations)

Block 6 - Safety related classification Block 7 - Approved date Block 8 - Effective date Block 9 - Expiration date. If not applicable, enter N/A Block 10 - General description of the revision Block 11 - Responsible department manager's signature Block 12 - Date approved by department manager Block 13 - General Manager's signature, indicating approval. If not applicable, enter N/A Block 14 - Date approved. If not applicable ' enter N/A Block 15 - Path number and section number MGR-0009 Rev.1

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ATTACHMENT 3 PAGE 74 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 2 OF 2 DOCUMENT TITLE: EMERGENCY OPERATING REVISION: -

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

TITLE PAGE FORMAT FOR EOP'S cI?sG;. ic.sa c;.ed..w r r,3 parew nuettes etswr

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GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

DESIGNATION - AND NUM' BERING OF FI'OW CHARTS

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ATTACHMENT 5 PAGE 76 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 3 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

FT.OW CHART LOGIC SYhBOLS

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ATTACHMENT 5 PAGE 77 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 2 OF 3 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

FLOW CHART LOGIC SYMBOLS

~ ~

1. For the upper right corn,or,

' - the letters "SPDS" are r FIRE 4 N ~SPOP replaced with one of the following four choices:

"EMER": Info available on an SPDS emergency a" . .

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display W ~- - -

" DIAG": Info available on an SPDS diagnostic display "PRI" : Info available on

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the reference is to the

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--- 4 O i 3. for the Icwer right corner, ~

the reference is to the E4 % numbered " cautions" on the

~

right-most column of the

^ 4 chart.

e I FIRE 3 SPOS 64 4. The lower left corner is used for miscellaneous g

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i, ,information such as ,, , , ,,

+ 1, procedure numbers, note n

t NOTE 1 +3 1 references, etc.

5. The location of those extra information notes may not f(

l 3-vary...for example ,SPDS notes are always in t'h'e to,p,

- - - right. ,

6. 'Except for key parameter symbols, only those

" corners" needed to contain information need be printed on the chart.

Note - Minimum sizes for 33x50 inch drawing shown.

MCR-0009, Rev.1 gr It e / f .$, , , "j g g y 4

ATTACHMENT 5 PAGE 78 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 3 OF 3 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

FLOW CHART LOGIC SYMBOLS -

..EflTER r

JQ ^

~ .

. Small black triangles shown indicate the direction which should be taken in the event the answer to the question is

. E.'tTER unknown. The triangle indicates the intended conservative path and as shown -

is only in example location.

The location may be either side or bottom and depends upon the actual exits on the flow chart.

/ .

'LINE SIZES

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ATTACHMENT 6 PAGE 79 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE: EXAMPLE DECISION TREE UTILIZING STANDARD f.OGIC SYMBOLS

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ATTACHMENT 7 PAGE 80 OF 84

-GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 5 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT-TITLE:

SAMPLE ACTION VERB I,IST Since.this is intended to be a sample list of verbs, standard English usage will apply to verbs necessary to be used in the EOP's but not contained herein.

VERB MEANING / APPLICATION Adjust To regulate or bring to a more satisfactory state. EXAMPLE: " Adjust Reactor Water Level setpoint to +36 inches".

Align To place a system in proper or desired configuration for an intended purpose.

EXAMPLE: " Align CAD vaporized to Reactor - ~

Building" Allow To permit a stated condition to be achieved prior,to proceeding. EXAMPLE: " allow discharge

~

pressure to stabilize" Check To perform a physical action which determines the state of a variable or status of equipment without directing a change in status. EXAMPLE:

" check for' satisfactory lube oil level" MGR-0009, Rev.1

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ATTACHMENT 7 PAGE 81 OF 84 GEORGIA POWER COMPANY ~ ATTACHMENT HATCH NUCLEAR PLANT PAGE 2 OF S DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

SAMPLE ACTION VERB LIST ~

VERB MEANING / APPLICATION

,. Close . To change the physical position of a mechanical-device to the closed position so that it prevents fluid flow or permits passage of electric current. .

EXAMPLE: "close valve 2B21-F019" Complete To accomplish specific procedural requirements.

d EXAMPLE: " complete valve check-off list 3.7.1",

" complete data report QA-1", " complete steps 7 through 9 of Section III" Establish To make arrangements for a stated condition. - --

EXAMPLE: " establish communication with control room"

. Iso, late To close one or more valves in a system for the purpose of separating or setting apart a complete

~

system or a portion of the system from the rest of the system or plant. EXAMPLE: " isolate interruptible instrumenE air M eitdct by shutting valve 2P51-F011" s

MGR-0009, Rev.1 m... . ,NtGl%%.5%$kW. ~ a c. . : na. d @:htgi & raau~,..n...i;Gu,,

ATTACHMEE4T 7 PAGE 82 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 3 OF 5 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT T1.LE:

SAMPLE ACTION VERB LIST -

VERB MEANING / APPLICATION 4 Inspect -

1N) measure, observe, or evaluate a feature or characteristic for comparison with specified limits; method of inspection should be included. EXAMPLE:

" visually inspect for leaks"

-Maintain To keep in an existing state. EXAMPLE: " maintain the reactor vessel water level between +15 and +55 inches, with one or more of the following systems...."

Open To change the physical position of a mechanical - -

device to the open position so that it allows fluid flow or prevents passage of electrical current, EXAMPLE: "open valve 2B21-F016". Unless specifically directed otherwise, open means fully

~

open.

Place To put in a particular position. EXAMPLE: " place mode switch to Shutdown" 1

' ; MGR-0009, Rev.1 2 [J,kNA3),%ief8#A .' , . - ~ ,, . -

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ATTACHMENT 7 PAGE B3 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 4 OF 5 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

SAMPLE ACTION VERB LIST VERB MEANING / APPLICATION

, Record . 1N) document specified condition or characteristic.

EXAMPLE: " record discharge pressure" Reduce To cause a parameter to decrease in value. EXAMPLE:

" reduce reactor pressure with bypass valve manual jack" Set To physically adjust to a specified value on adjustable feature. EXAMPLE: " set diesel speed to

.... rpm" Start ,

To energize an electro-mechanical device by manipulation of a start switch or button. EXAMPLE:

" start a second CRD pump"

~

Stop Opposite of start. EXAMPLE: "stop admitting steam by shutting valve 2B21-F044" Synchronize To make synchronous in operation. EXAMPLE:

" Synchronize the Diesel Generator to 4160V Bus 2E" MGR-0009, Rev.1

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ATTACHMENT 7 PAGE 84 OF 84 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 5 OF 5 DOCUMENT-TITLE: EMERGENCY OPERATING REVISION:

PROCEDURES PROGRAM (WRITER'S GUIDE) 1 ATTACHMENT TITLE:

SAMPLE ACTION VERB LIST VERB MEANING / APPLICATION

, Throttle . To operate a' valve in an intermediate position to obtain a certain flow rate. EXAMPLE: " throttle valve 2B21-F077 to obtain 2000 lb/hr flow" ,

Trip To manually activate a semi-automatic feature.

EXAMPLE: " trip breaker..."

Vent To permit a gas or liquid confined under pressure to escape at a vent. EXAMPLE: " vent the heat exchanger before placing it in service" Verify To prove to be true, exact, or accurate by observation of a condition or characteristic for comparison with an original or procedural requirement.- Example: " verify discharge pressure" MGR-0009, Rev.1

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Text

1.0 INTRODUCTION

Title:

Description:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

3.0 REFERENCES

3.0 REFERENCES

9.1 INTRODUCTION

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