ML20211Q911

Rev 1 to Grand Gulf Nuclear Station-Unit 1 Emergency Procedures Upgrade Program Procedures Generation Package

ML20211Q911
Person / Time
Site:	Grand Gulf
Issue date:	07/31/1986
From:	MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20211Q889	List: AECM-86-0208, Forwards Addl Info Re Emergency Containment Venting in Response to Item 1.1 of 860527 Request.Encl Rev 1 to ...Emergency Procedures Upgrade Program Procedures Generation Package Addresses Remaining Request ML20211Q911
References
PROC-860731, NUDOCS 8607280050
Download: ML20211Q911 (338)

Text

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GRAND GULF NUCLEAR STATION-UNIT 1 EMERGENCY PROCEDURES UPGRADE PROGRAM PROCEDURES GENERATION PACKAGE l

l Prepared for l -

U.S. Nuclear Regulatory Commission July 1986 l

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MISSISSIPPI POWER & LIGHT COMPANY i

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y GRAND GULF NUCLEAR STATION - UNIT 1 EMER2NCY PROCEDURES UPGRADE PROGRAM PROCEDURES GENERATION PACKAGE Prepared for:

U.S. NUCLEAR REGULATORY COMMISSION July 198f MISSISSIPPI POWER & LIGHT COMPANY

Mississippi Power & Light Company List of Revised Pages The following is a list of Revi.ed pages as requested by the NRC in their request for additional information letter dated May 27, 1986. The revised pages are also indicated by " Revised July 1986" in the lower right hand corner of each page.

Table of Contents i, ii, iii P_aje Page 3-4 4-9 3-5 4-10 3-8 4-13 3-9 4-20 3-10 4B-1 3-11 4F-1 3-12 5-2 3-13 3-14 3-15 3-16 3-17 3-18 3-19 3-20 3-21 3-22 3-23 3-24 3-25 3-26 J16 MISC 86071401 - 1

MISSISSIPPI POWER & LIGHT COMPANY TABLE OF CONTENTS Page

1. I NT RODU CT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1 Purpose.................................................. 1-1 1.2 Scope.................................................... 1-1 1.3 Organization............................................. 1-1 1.4 Acronyms................................................. "l-1 1.5 Re f er e n ce s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2

2. PSTG PREPARATION GUIDE......................................... 2-1 ,

2.1 Introduction............................................. 2-1 .

2.2 Methodology.............................................. 2-1 2.2.1 Mechanics of Conversion..... .................... 2-1 2.2.2 Documentation Requirements....................... 2-1 l 2.2.3 Reference Material............................... 2-1 2.2.4 Qualification Requirements....................... 2-2 2.3 Appendices............................................... 2-3 2.3.1 Appendix 2A - EPG to PSTG Conversion Documentation................................. 2A-1 2.3.2 Appendix 2B - Documentation List................ 2B-1 2.3.3 Appendix 2C - Sample Calculation Sheet.......... 2C-1

3. EP WRITER'S GUIDE.............................................. 3-1 3.1 Introduction............................................. 3-1 3.1.1 Purpose.......................................... 3-1 3.1.2 Relationship of EPs to Other Plant Procedures.... 3-1 j

3.1.3 How to Use This Guide............................ 3-1 3.2 EP Designation System.................................... 3-1 3.2.1 Numbering Scheme................................. 3-1 3.2.2 Title............................................ 3-3 3.2.3 Revision Numbering Scheme........................ 3-3 3.3 EP Structure............................................. 3-3 3.4 Flowchar t Prepar ation Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . 3-3 3.4.1 Identification and Numbering. . . . . . . . . . . . . . . . . . . . . 3-3 3.4.2 Review and Approva1.............................. 3-4 3.4.3 Logic Symbols.................................... 3-4 3.4.4 Entry Conditions................................. 3-6 3.4.5 Action and verification Steps.................... 3-6 3.4.6 Retainment Steps................................. 3-6 3.4.7 Decision Steps................................... 3-7 3.4.8 Concurrent Steps................................. .

3-7 3.4.9 Entr y and Exit Points . . . . . . . ~. . . . . . . . . . . . . . . . . . . . . 3-8 3.4.10 Cautions and Notes........"....................... 3-8 3.4.11 Functional Flow and Branching . . . . . . . . . . . . . . . . . . . 3-10 3.4.12 S te p N umb e r ing S cheme . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -10 3.4.13 Placekeeping Aid................................ 3-10 3.4.14 Readability Guidelines.......................... 3-10 3.4.15 Printed Operator Aids.............,.............. 3-11 i

Revised July 1986 j

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TABLE OF CONTENTS (Continued)

Page 3.5 Step Construction....................................... 3-12 3.5.1 Level of Detail................................. 3-12 3.5.2 Step Sequencing................................. 3-12 3.5.3 Step Length and content......................... 3-13 3.5.4 Types o f S teps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -14 3.5.5 Logic Terms..................................... 3-15 3.5.6 Cond i tiona l S tatements . . . . . . . . . . . . . . . . . . . . . . . . . . 3-16 3.5.7 Referencing and Branching....................... 3-18 -

3.5.8 Safety Parameter Display System References...... 3-19 l 3.5.9 Component Identification. . . . . . . . . . . . . . . . . . . . . . . . 3-19 3.5.10 Word Choice..................................... 3-19 3.5.11 Methods of Emphasis............................. 3-20 j 3.C Mechanics of Style...................................... 3-20 3.6.1 Spelling........................................ 3-20 3.6.2 Abbreviations and Acronyms...................... 3-20 3.6.3 H yph e n a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -21 3.6.4 Punctuation..................................... 3-22 3.6.5 Acceptance Criter ia and Calculations. . . . . . . . . . . . 3-23 3.6.6 Num e r i ca l va lue s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -2 3 3.7 EP Revisions and Updates................................ 3-24 3.7.1 Review Requirements............................. 3-24 3.7.2 Revi s i on P ro ce s s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2 4 1

3.8 Personnel Utilization to Accomplish EPs. . . . . . . . . . . . . . . . . 3-24 l 3.8.1 Personnel Responsibilities . . . . . . . . . . . . . . . . . . . . . . 3-24 3.8.2 Training........................................ 3-24 3.9 Use of Procedures to Combat Emergencies................. 3-25 3.9.1 Use of EPs...................................... 3-25 3.9.2 Use EPPs........................................ 3-25 3.9.3 Use of SOIs , IOTs , and ONEPs . . . . . . . . . . . . . . . . . . . . 3-2 5 3.10 Guidelines on Equipment Use during Emergencies.......... 3-25 3.10.1 Emergency Use of Equipment...................... 3-25 3.10.2 Documentation................................... 3-25 3.10.3 Return to Service............................... 3-26 4 3.11 Appendices.............................................. 3-26 3.11.1 Appendix 3A - Planning Guidance for the i

P r o ce d u r e Wr i t e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 A-1 3.11.2 Appendix 3B - List of GGNS-1 Emergency P r o ce d u r e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 B -1 3.11.3 Appendix 3C - Sample Format. . . . . . . . . . . . . . . . . . . . . 3C-1 I

3.11.4 Appendix 3D - Action Verbs ,..................... 3D-1 3.11.5 Appe nd ix 3 E - Vo ca bu la r y . . . 5. . . . . . . . . . . . . . . . . . . . . 3E-1 3.11.6 Appendix 3F - Abbreviations and Acronyms........ 3F-1 11 3

Revised July 1986 i

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TABLE OF CONTENTS (Continued)

Pace

4. VERIFICATION AND VALIDATION PLAN............................... 4-1 4.1 Introduction............................................. 4-1 4.2 PSTG and EP Verification................................. 4-2 4.2.1 Verification Preparation Phase................... 4-4 4.2.2 PSTG Verification Assessment Phase............... 4-4 4.2.3 EP Verification Assessment Phase................. 4-4 4.2.4 Verification Resolution Phase.................... 4-5 4.2.5 Verification Documentation Phase................. 4-6 4.3 EP Validation............................................ 4-6 .

i 4.3.1 Validation Preparation Phase..................... 4-6 4.3.2 Validation Assessment Phase..................... 4-15 4.3.3 Validation Resolution Phase..................... 4-18 4.3.4 Validation Documentation Phase.................. 4-20 4.4 Appendices.............................................. 4-20 4.4.1 Appendix 4A - EP Evaluation Checklist........... 4A-1 4.4.2 Appendix 4B - PSTG Discrepancy Sheet. . . . . . . . . . . . . 4B-1 4.4.3 Appendix 4C - EP Discrepancy Sheet.............. 4C-1 .

4.4.4 Appendix 4D - EP Verification Completion Record. 4D-1 I

4.4.5 Appendix 4E - Task Analysis Worksheet........... 4E-1 4.4.6 Appendix 4F - Sample Simulator Scenario. . . . . . . . . 4F-1

4.4.7 Appendix 4G - Sample List of Expected Operator Actions.............................. 4G-1

5. EP TRAINING PROGRAM DESCRIPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1 Introduction............................................. 5-1 5.2 Training Program Development............................. 5-1 5.3 Training Program Objectives.............................. 5-1 5.4 Training Methods......................................... 5-2 5.4.1 Classroom Instruction............................ 5-2 5.4.2 Simulator Exercises.............................. 5-2 5.4.3 Control Room Walk-Throughs....................... 5-2 5.5 Requalification Training................................. 5-2 5.6 Training on Revisions.................................... 5-3 5.7 Operator Feedback........................................ 5-3 i

Revised July 1986 l

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1. INTRODUCTION 1

1.1 Purpose This Procedures Generation Package (PGP) describes the process by which Mississippi Power & Light Company (MP&L) will develop, implement, and maintain the Emergency Procedures (EPs) for Grand Gulf Nuclear Station -

Unit 1 (GGNS-1).

1.2 Scope This document was developed in response to NUREG-0737 Supplement 1, Item 7.2b, and deals only with those procedures to be used by operations personnel to mitigate the consequences of transients and accidents.

1.3 Organization The remaining sections of this document are:

o PSTG Preparation Guide e EP Writer's Guide (Revision 1)

e Verification and Validation Plan e EP Training Program Description Each section describes the approach taken for a significant part of the overall EP Upgrade Program for GGNS-1.

1.4 Acronyms The following acronyms are used in this PGP:

BWR -

Boiling Water Reactor BWROG -

BWR Owners Group CF -

Control Function CR -

Control Room DCRDR -

Detailed Control Room Design Review EP -

Emergency Procedure o

EPGs -

Emergency Procedure Guidelines FSAR -

Final Safety Analysis Report GGNS-1 -

Grand Gulf Nuclear Station - Unit 1 I&C -

Instrumentation and Controls MP&L -

Mississippi Power & Light Company NRC -

U.S. Nuclear Regulatory Commission PGP -

Procedures Generation Package 1-1

MISSISSIPPI POWER & LIGHT COMPANY PSTGs -

Plant Specific Technical Guidelines SPDS -

Safety Parameter Display System SRO -

Senior Reactor Qperator TAW -

Task Analysis Worksheet TMI -

Three Mile Island

• V&V -

Verification and Validation 1.5 References 1.5.1 ' Boiling Water Reactor Owners Group - Emergency Procedure Guideline, Revision 3."

1.5.2 INPO 82-017, " Emergency Operating Procedures Writing ,

Guidelines."

1.5.3 INPO 83-004, " Emergency Operating Procedures Verification Guidelines."

1.5.4 INPO 83-006, " Emergency Operating ProceduAes Validation Guidelines."

1.5.5 NUREG-0737, " Clarification of TMI Action Plan Requirements."

1.5.6 NUREG-0737 Supplement 1, " Requirements for Emergency Response Capability."

1.5.7 NUREG-0899, " Guidelines for the Preparation of Emergency Operating Procedures."

1 5.8 NUREG/CR-2005, " Checklist for Evaluating . Emergency Operating Procedures Used in Nuclear Power Plants."

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2. PSTG PREPARATION GUIDE 2.1 Introduction This guide provides the administrative and technical requirements for the preparation of the Plant Specific Technical Guidelines (PSTG) to be used in developing the GGNS-1 Emergency Procedures. These guidelines identify the equipment or systems to be operated, and list the steps necessary to mitigate the consequences of transients and accidents.

They will be based on the Boiling water Reactor Owners Group (BWROG)

Emergency Procedure Guidelines (EPG), Revision 3. These generic guidelines have been validated by the BWROG and approved by the U.S.

Nuclear Regulatory Commission (NRC) (Letter LS05-83-11-045).

2.2 Methodology 2.2.1 Mechanics of Conversion

a. Each step of the BWROG EPG will be assessed to verify applicability to GGNS-1. Revision 3 of the EPG will be used as the primary source document; however, all current and pertinent information supplied by the BWROG will be reviewed for this assessment.

b. Where applicability is verified, the generic EPG will be converted to a plant specific guideline. This will require the inclusion of GGNS-1 specific information and the

'i deletion of nonapplicable information.

c. For all deviations from Revision 3 of the generic EPG that are not readily apparent, written calculations and/or decision processes will be documented.

d. Documentation of the conversion process will be performed as described in Section 2.2.2.

I 2.2.2 Documentation Requirements As each step of the BWROG EPG is converted to a QGNS-1 PSTG step, the documentation requirements will be satisfied by completing a copy of Appendix 2A, using the guidance listed below.

a. Column 1, "BWR Owners Group - Emergency Procedure Guideline," will contain a duplication of each of the EPG Revision 3 steps. This information will be used as the basis for the creation of the PSTG step.

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b. Column 2, "GGNS - Plant Specific Technical Guideline," will contain a guideline step that incorporates the intent of the corresponding generic step and includes GGNS-1 plant specific information, values, and limits. Column 2 will also be used to incorporate additional plant specific information not required by the generic EPG. These items may include Technical Specification requirements, licensing commitments, or operational techniques.

c. Column 3, " Deviation / Justification," will be used to document and explain all deviations between Column 1 and Column 2, and provide explanations for additional PSTG steps. For each plant specific value given in Column 2, Column 3 will list, as a minimum, the reference from which the value was obtained (i.e., FSAR tables, EPG Appendix C' calculation, Technical Specification, etc.), including ,

title, revision number, and location. ,

2.2.3 Reference Material

a. The basic plant specific technical information to be re-viewed for the production of the PSTGs will be the material i gathered as part of the GGNS-1 Detailed Control Room Design Review (DCRDR), and as documented in Appendix 2B.

b. In addition to this information, EPG Appendices A and B will be used to clarify the intent of the EPG. EPG Appendix C provides the plant specific calculations and curves necessary to convert the EPGs to plant specific guidelines.

c. Should additional plant specific calculations be required to support the PSTGs, they will be performed by personnel using the Calculation Sheet shown as Appendix 2C (or similar). Independent verification of all calculations will be in accordance with the Verification and Validation Plan.

d. The PSJG writing team will ensure that GGNS-1 licensing a commitments are incorporated into the PSTGs.

2.2.4 Qualification Requirements j a. Those personnel selected for the conversion of the EPGs to

the PSTGs will have, as a minimum, the following experience levels e Currently hold a Senior Reactor Operator (SRO)

Certification on a Boiling Water Reactor 2-2 1

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i MISSISSIPPI POWER & LIGHT COMPANY e Demonstrated previous experience in symptom-based EP development o 3,Have at least 0 years of nuclear experience

b. As proof of meeting the above requirements, resumes of personnel actually performing this activity will be included as part of the PSTG documentation package.

2.3 Appendices 2.3.1 Appendix 2A - EPG to PSM Conversion Documentation 2 3.2 Appendix 2B - Documentation List 2.3.3 Appendix 2C - Sample Calculation Sheet j

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l MISSISSIPPI POWER & LIGHT COMPANY APPENDIX 2B - DOCUMENTATION LIST DOCUMENT IDENTIFICATION DESCRIPTION MPL-120-03 System Lesson Plan (SLP) LPRMs C51-3 MPL-120-04 SLP IRMs C51-2 MPL-120-05 SLP Fuel Pool Cooling & Cleanup Sys G41/G46 i

MPL-120-06 SLP RWCU System G33/C36 MPL-120-07 SLP Liquid Radweste System G17 MPL-120-08 SLP Recirculation B33-1 MPL-120-09 SLP Vessel Instrumentation B21 MPL-120-10 SLP Auxiliary Steam System ~

MPL-120-11 SLP Condensate System N19 MPL-120-12 SLP Rod Control & Information Sys (RCIS) File C11-2 MPL-120-13 SLP Control Rod Drive Mechanism C11-1B MPL-120-14 SLP CRD Hydraulic System C11-1A MPL-120-15 SLP Heater Vents & Drains N23 MPL-120-16 SLP Feedwater System N21 MPL-120-17 SLP Main Turbine N30 MPL-120-18 SLP Circulating Water System N71 MPL-120-19 SLP Chlorination System N72 MPL-120-20 SLP CRWST P11 MPL-120-21 SLP Makeup Water System P21 MPL-120-22 SLP Standby Service Water System P41 MPL-120-23 SLP Low Pressure Core Spray E21 MPL-120-24 SLP Area Radiation Monitoring System D21 MPL-120-25 SLP Process Radiation Monitoring System D17 MPL-120-26 SLP Reactor Protection System C71 MPL-120-27 SLP MSIV E FWLC System E32/E38 MPL-120-28 SLP RCIC System E51 MPL-120-29 SLP Combustible Gas Control System E61 MPL-120-30 SLP Refuel & Vessel Service F11/F17 MPL-120-31 SLP Division III (HPCS) Diesel Generator P81 MPL-120-32 SLP RHR System E12 MPL-120-33 SLP Service Air System MPL-120-34 SLP Instrument Air System P53 MPL-120-35 SLP Fire Protection System i 2B-1

MISSISSIPPI POWER & LIGHT COMPANY DOCUMENT IDENTIFICATION DESCRIPTION HPL-120-36 SLP Plant Chilled Water P71 MPL-120-37 SLP Condenser Air Removal N62 MPL-120-38 SLP Hydrogen & Carbon Dioxide Bulk Storage System MPL-120-39 SLP Radwaste Building Ventilation V41

, MPL-120-40 SLP Turbine Building Ventilation U41 MPL-120-41 SLP Standby Gas Treatment T48 MPL-120-42 SLP ESF Electrical Distribution R21 MPL-120-43 SLP Recirculation Flow Control System B33-2 MPL-120-44 SLP Standby Diesel Generators P75 ,

MPL-120-45 SLP Component Cooling Water P42 MPL-120-46 SLP Turbine Building Cooling Water P43 MPL-120-47 SLP Plant Service Water / Radial Well Sys P44/P47 MPL-120-48 SLP Floor and Equipment Drains System P45 MPL-120-49 SLP HPCS E22-1 MPL-120-50 SLP Automatic Depressurization System E-22-2 MPL-120-51 SLP Nuclear Boiler & Vessel Internals B13/21 MPL-120-52 SLP Drywell Cooling System M51 MPL-120-53 SLP Containment Systems M41-1 MPL-120-54 SLP Containment Cooling System M41 MPL-120-55 SLP Nuclear Fuel MPL-120-56 SLP EHC Logic N32-2 MPL-120-57 SLP Turbine Auxiliaries N30/31-2 MPL-120-58 SLP Condensate & Suppression Pool Cleanup Sys N22/P60 MPL-120-59 SLP Radwaste Building Ventilation V41 MPL-120-60 SLP Generator N41/N51 MPL-120-61 SLP Extraction Steam N36 MPL-120-62 SLP Lube Oil Conditioning & Storage N34 MPL-120-63 SLP Seal Steam System N33 MPL-120-64 SLP EHC Control Oil System N32-1 MPL-120-65 SLP Source Range Monitors C51-1 MPL-120-66 SLP APRM C51 MPL-120-67 SLP Transversing Incore Probe System C51 MPL-120-68 SLP Standby Liquid Control System C41 MPL-120-69 SLP Feedwater Control System C34 2B-2

i MISSISSIPPI POWER & LIGHT COMPANY DOCUMENT IDENTIFICATION DESCRIPTION MPL-120-70 SLP Offgas System N64/65 MPL-120-71 SLP Supression Pool Makeup E-30 MPL-120-72 SLP Leak Detection System E-31 MPL-120-74 MP&L Plant Operations Manual Vol. 5 Section 2 MPL-120-75 MP&L Drawing J-0400 (Panel Location)

MPL-120-70 MP&L Technical Specifications MPL-120-77 MP&L DCRDR Program Plan GP-R-212123 MPL-120-79 MP&L Drawings, J-A0460A, J-A0460B, J-A0460C, J-A0460D, J-A0460E, J-A1470N, J-A1470U, J-B1470X ,

MPL-120-81 MP&L BWR Emergency Procedure Guidelines, Appendix C, Calculated Procedures MPL-120-82 MP&L Author's Guide. Plant Operations Manual, Vol. 1, Section 2 MPL-120-83 Grand Gulf FSAR Chapter 15, Accident Analysis MPL-120-86 MP&L Instrument Index MPL-120-87 Grand Gulf Preliminary Design Assessment Report MPL-120-88 Graphic Display Development Program MPL-120-90 MP&L Plant Procedures (EPs)

MPL-120-98 Letter from General Electric. BWR Emergency Procedure Guidelines (DRAFT)

MPL-120-99 Letter from General Electric. Distribution of Appendix B, Rev. 3A to the Emergency Procedure Guidelines.

MPL-120-100 MP&L Drawings MPL-120-103 NPE Technical Specification / Standard MP&L ES-01 MPL-120-104 Drawing Reference MPL-120-105 MP&L FSAR Section 3 MPL-120-107 US NRC Standard Review Plan MPL-120-110 MP&L BWROG-8452 Draft MPL-120-111 MP&L DCRDR Program Plan MPL-120-131 MP&L Project Plan DCRDR (GP-R-212133) i 2B-3

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APPENDIX 2C - SAMPLE CALCULATION SHEET CALCULATION SHEET Project Calculation No.

Title Calculated By Date Page of Checked By Date Reviewed By Date j

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3. EP WRITER'S GUIDE 3.1 Introduction 3.1.1 Purpose This document establishes format and content standards for (GGNS-1) Emergency Procedures and gives guidance to the EP writer for the creation and revision of all EPs. The standards established in this document reflect all EP flowchart revisions through January 31, 1986.

3.1.2 Relationship of EPs to Other Plant Procedures EPs are but one of many types of procedures within the plant procedure system. The relationship of EPs to other procedures is shown in Figure 3-1. To ensure compatibility of the EPs with other plant procedures, all EP-referenced procedures will be verified: (1) to exist and (2) to contain instructions I addressing the EP-required evolution.

3.1.3 How to Use This Guide This guide was prepared to give the EP writer complete guidance in preparing GGNS-1 EPs. The following process is recommended:

a. Review Appendix 3A, which contains references and other information that will help plan the procedure (s) .

b. Then review Sections 3.2 and 3.3, which give an overview of the EP system and the structure of the individual EPs.

c. Then use Sections 3.4, 3.5, and 3.6 and the remaining

[ appendices to draft the procedure (s) . These sections deal

( with general flowchart guidelines, then action step

. construction, then specific points of style.

Sections 3.7 through 3.10 contain information on when and how EPs are revised, and how they are used in an actual emergency.

3.2 EP Designation System 3.2.1 Numbering Scheme Each EP has a unique number. The following scheme is used for all GGNS-1 Operations Procedures Procedure Sequential Volume (l) Unit (2) Section(3) Type (4) No.(5)

XX -

X - X -

XX - XXX 3-1

MICSISSIPPI PONEk & LIGHT COMPANY ADMINISTRATIVE PROC 301,101 EPP ONEP xs

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ARI Legend ARI Alarm Response Instructions EP Emergency Procedures EPP Emergency Plan Procedures ONEP Off-Normal Event Procedures S01,10I System Operating Instructions, Integrated Operating Instructions Figure 3-1. Relationship of EPs to Other Procedures 3-2

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.f KEY (1) Operations Manual volume Number (2) Generating Unit 1, 2, or S (shared)

(3) Section Number,within the Operations Manual Volume. Nhen there is only one section in a volume, this number may be deleted.

(4) Procedure Types e.g., EP (5) Sequential Number: The sequential numbering scheme begins with 1 and can go to 999.

Appendix 3B is a list of GGNS-1 EPs with their assigned numbers.

3.2.2 Title ,

The EP titles are to be brief, yet descriptive. The flowchart format of the EPs enforces brevity. Two principles are to be used in titling EPs:

a. The title is to be 10 words or less.

, b. Important words are to be at or near the beginning of the title.

3.2.3 Revision Numbering Scheme Revisions of EPs are numbered sequentially with arabic numerals with the revision date shown on each procedere. (See Section 3.4.1 for an example.)

3.3 EP Structure The structure of the procedure consists of the flowchart. Appendix 3C contains a sample of the flowchart format. The flowcharts contains

a. Entry conditions

b. Action steps (to bring the plant to a stable condition, or to branch to another procedure that will do so)

, c. Exit criteria Section 3.4 below contains detailed guidelines on flowchart development.

3.4 Flowchart Preparation Guidelines 3.4.1 Identification and Numbering A title block in the lower right corner of each flowchart will contain the EP number, title, revision number, revision date, page number, an3 plant name. See Figure 3-2.

3-3 I

MISSISSIPPI POWER & LIGHT COMPANY PROCEDURE NO.

PROCEDURE TITLE GRAND GULF NUCLEAR STATION REVO REV DATE XX/YY/ZZ Figure 3-2. Sample Flowchart Title Block 3.4.2 Review and Approval A review and approval block appears on each flowchart in a location that does not interfere with the function or use of the flowchart. This block contains blanks to write in the type of validation conducted and the date it was performed. It also provides approval signature and date blanks for the preparer; Nuclear Plant Quality Assurance Superintendent; Technical Reviewer; Operations Superintendent; Chemistry / Radiological Superintendent; and Manager, Grand Gulf Nuclear Station. See Figure 3-3.

Active TCNs: Tech Reviewer: Date:

Preparer: Date: OPS Sup: Date:

Type of Validation: Date: CHEM / RAD Sup: Date:

Nuc Plant QA Sup: Date: Manager GGNS: Date:

Figure 3-3. Sample Flowchart Review and Approval Block 3.4.3 Logic Symbols ..

Figure 3-4 contains the standard flowchart symbols used in EPs.

3-4 Revised July 1986

MISSISSIPPI POWER fi LIGHT COMPANY ENTRY CONDITION i ( Contains the condition requiring entry into and execution of this procedure.

ACTION STEP Contains the procedural actions. Also defines contingency action steps (IF...TH EN).

RETAINMENT STEP Contains information or contingency action conditions the operator must remember while performing the steps that follow.

DECISION STEP -

Contains a question to which the answer determines the next step.

I EXECUTE CONCURRENTLY E P-5

} Requires the operator to enter the designated procedure and perform the stated actions while continuing in the existing N/ flow path.

ENTRY ARROW E F-5

\ Designates the entry point for this procedure when directed by

1. the procedure step in the arrow.

EXIT ARROW Requires the operator to leave the flow path at that point.

E P-5

} If required,it contains the procedure number and/or step D-Y that must then be entered.

I OPERATOR CAUTION OR NOTE 8 ACTION Indicates that a specific caution or note is applicable to the step. The number in the symbol corresponds I to a statement at the bottom of the procedure.

CAUTION NOTE SAFETY PARAMETER DISPLAY SYSTEM (SPDS) 3 Indicates that the SPDS would be applicable to the step.

The number in the symbol corresponds to the page(s)" on the SPDS.

EPP EMERGENCY PLAN PROCEDURE Requires the operator to enter the designated emergency plan procedure and perform the stated actions while continuing in the existing flow path.

Figure 3-4. Flowchart Symbols.

3-5 Revised July 1986

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MISSISSIPPI POWER & LIGHT COMPANY 3.4.4 Entry Conditions The entry conditions or symptoms are generally brief noun phrases that initiate the EP actions. The entry conditions are located at the top of each flowchart within entry condition symbols. The positioning of the symbols indicates to the operator whether any one of the conditions is necessary before operator actions commence. See Figure 3-5.

' (CONDITION ) (CONDITION ) (CONDITION)

I I ACTION Figure 3-5. Any One Condition Initiates Action 3.4.5 Action and Verification Steps In the flowcharts, action steps and verification steps are not differentiated in that both are shown as actions in an action step symbol. See Figure 3-6.

I I RESET . . . VERIFY , . .

I I Figure 3-6. Identical Symbols Used for Action and Verification 3.4.6 Retainment Steps A retainment step gives operatora information or contingency action conditions that they must remember while executing the steps that follow. See Figure 3-7.

IF WHILE EXECUTING THC FOLLOWING STEPS:

THE SCRAM CAN BE RESET, THEN RESET THE SCRAM AND RETURN TO STEP AA/B-CC Figure 3-7. Sample Retainment Step 3-6

MISSISSIPPI POWER & LIGHT COMPANY l

3.4.7 Decision Steps All decision steps require a choice between only two opposite possibilities, for example, yes/no or high/ low. These steps are phrased as questions, but are not followed by question marks.

See Figure 3-8.

RESET THE SCR AM ACTION INSTRUCTION LEADING TO DECISION O YES 4 THE SCRAM BE RESET p DECISION Figure 3-8. Sample Decision Step 3.4.8 Concurrent Steps A concurrent step symbol is used when an operator is to enter another procedure while at the same time continuing in the current flow path. The symbol contains the number of the additional procedure. See Figure 3-9.

I ACTION I

EP 5

)

ACTION I

Figure 3-9. Sample Concurrent Step 3-7

MISSISSIPPI POWER & LIGHT COMPANY 3.4.9 Entry and Exit Points An entry arrow symbol is used to show where a procedure is entered from another procedure. The symbol contains the procedure number that was exited, and is located to the lef t of the entry point. The step number is placed below the entry arrow symbol. See Figure 3-10.

EP-4 XX-Y

) ACTION Figure 3-10. Entry Arrow Symbol -

k An exit arrow symbol requires the operator to leave the flow path at that point. The symbol contains the number of the procedure that must be entered. The step number is placed below the symbol. An exit arrow is located below and to the right of the step exited. See Figure 3-11.

ACTION I EP-4

)

XX-Y Figure 3-11. Exit Arrow Symbol 3.4.10 Cautions and Notes Cautions and notes give additional information to the operator. They are never used to convey a required action step. But they may be used to express conditional actions,

a. Definitions i

1) CAUTION: A caution is a means of attracting attention to essential or critical information in a procedure.

This information addresses conditions, practices, or procedures that must be observed to avoid personnel injury, loss of life, a long-term health hazard, or equipment damage.

2) Note: A note gives the' operator information to clarify the instruction. It never deals with personnel or equipment hazards.

l 3-8 Revised July 1986 l

MISSISSIPPI POWER & LIGIT COMPA!E C

b. Format A specific caution applicable to a step is indicated by a double-line hexagon above the step. When more than one caution applies to a step, place the hexagons in series on the flow path above the step. A brief description of the caution (in parentheses) appears to the right of the hexagon. See Figure 3-12.

(DESCRIPTION)

CAUTION IF CONTINUOUS LPCI 1g (DO NOT 8

• OPERATION IS REOUIRED (DESCRIPTION)

DIVERT LPCI)

O18 TO ENSURE ADEQUATE CORE COOLING. DO NOT DIVERT RHR PUMPS FROM LPCt MODE- (This

"* INITIATE SUPP ACTION

$e b ttom oe POOL COOUNG procedure.)

i I Figure 3-12. Placement of Caution Symbols A note is indicated by a circle within the step. For multiple note statements, place the corresponding note numbers (separated by commas) within the step. See Figure 3-13.

I NOTE CONTINUE INJECTING WATER NTO THE RPV UNTIL:

RPV WATER LEVEL

. TEMP NEAR THE COLD

@ INSTRUMENTATION REFERENCE LEGS MAY REFERENCE LEG IS REQUIRE FILLING TO BELOW 212'F ENSURE ACCURATE  !

ano LEVELINDICATION (This statement would appear at . RPV WATER LEVEL the bottom of the INSTRUMENTATION IS ON 6,7 procedure ) AVAILABLE I I l

1 Figure 3-13. Placement of N$te Symbols

! Caution and note statements are listed separately at the bottom of the flowchart (similar to a footnote on a text page) with the corresponding symbol and number to the left of each statement.

3-9 Revised July 1986 i

I

^

MISSISSIPPI POWER & LIGHT COMPANY 3.4.11 Functional Flow and Branching

a. Sufficient spacing will be allowed between paths so that the operator does not inadvertently enter an adjacent path,

b. Arrowheads will be used on connecting lines to clarify the.

direction of the path. Arrowheads will enter flowchart symbols from the top, not from the side.

3.4.12 Step Numbering Scheme

a. Multiple-Branch EPs Multiple-branch EPs use an AA/B-C format, where:

AA = the procedure designator B = the branch of the procedure C = the sequential step number For example, Reactor Control, Level Branch, Step 3 would be numbered RC/L-3.

b. Single-Branch EPs Single-branch EPs use an AA-B format, where:

AA = the procedure designator

, B = the sequential step number For example, Level Restoration, Step 5 vould be numbered LR-5.

3.4.13 Placekeeping Aid

A _J is placed next to each step as a placekeeping aid to the operator.

3.4.14 Readability Guidelines The following apply: ,

a. The flowchart typeface will be a sans-seraph style, in full capitals, at least 10 points in size.

l b. The spacing between letters and between words will be distinct so that the flowcharts can be easily read in emergency lighting. s l

c. All EP lettering will be black type on white background for the highest possible contrast.

3-10 Revised July 1986 l

.- _ _ _ _ _ _ . . _ _- _ _ , ~ _ . _ _ _ . _ , , _ _ . - _ _ _ . . , _ _ _ . . _ . _ _ . _ . _ _ _ _ . . _ . _ , _ - . _ . . . _ _ -

l MISSISSIPPI POWER & LIGHT COMPANY l

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1

d. Copies of flowcharts will be of high quality, i.e., without fuzzy type.

1

e. The flowcharts will have a ncnglare surface.

f. The flowcharts will be no larger than 36" x 60" and no '

smaller than 8-1/2" x 11".

g.

Two sets of flowcharted EPs will be maintained in the control room. One set will be 36" x 60" laminated on hard cardboard backing to be used by the Shift Suprvisor who is in charge of the plant at all times per GGNS-1 Procedure 01-S-06-2, " Conduct of Operations." The other set will be 8-1/2" x 11" size for easy portability in the event that l the Shift Supervisor wants mobility in the control room. '

The flowcharted EPs will be stored in a pouch on the side of the Shift Supervisor's desk and will be maintained by the Shift Supervisor. Operating crew responsibilities are defined in GGNS-1 Procedure 01-S-06-2, " Conduct of Operations." Teamwork will be stressed in training on EP use held before procedure implementation.

3.4.15 Printed Operator Aids Figures (such as graphs and charts) and tables may be used to I aid the operator in performing the action steps. For example, a table of values could be used so that a calculation is avoided,

a. Labeling Scheme

1) Graphs and tables will be titled.

2) Graphs and tables will be numbered in the XX-Y-Z format, where:

e XX is the branch of the flowchart that the graph or table applies to.

e Y is the parameter of concern in the flowchart branch.

e Z is a sequential number of grephs or tables used in that branch.

For example, Drywell Pressure Control Curve No. 2 would be numbered Curve DW-P-2.

3) The numbers and titles of graphs or tables will be placed above each graph / table.

1

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Revised July 1986

MISSISSIPPI POWER & LIGHT COMPANY 4

4) Graphs and tables will be referred to by number within the action step.

b. Placement A graph or table is located on the flowchart near the first step that refers to it. Dashed lines link the graph or table and the applicable step.

c. Quality Operator aids will be self-explanatory and legible under the expected conditions of use. Specifically,

1) The typeface will be a sans-seraph style, in full

• capitals, at least 5 points in size.

2) The aid will be a high-quality reproduction (or reduction), i.e., not a blurry photocopy.

d. Consistency The terms used in the aid (i.e., equipmen. designations, parameter units, etc.) will match those r. sed in the procedure steps and in the control room itself. Units of measure and numerical values will be coasistent with GGNS-1 Technical Specifications and with actual control room indicators.

3.5 Step construction 3.5.1 Level of Detail The detail required in the flowcharts is that required by the least trained operator expected to use the procedure, specifically a newly trained and licensed operator working under emergency (stressful) conditions. The flowchart format leaves little room for supporting instruction or information, and operators are trained on the procedures, so a cluttered flowchart will only hinder efficient performance.

3.5.2 Step Sequencing Steps will be listed in the required sequence. The operator assumes the sequence is mandatory unless the procedure specifically states otherwise...

Other considerations in sequencing action steps are:

a. Structure the control room action steps to ensure that minimum control room staff can perform the actions.

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MISSISSIPPI POWER & LIGHT COMPANY i

b. Sequence the steps to minimize physical conflicts among operators,

c. Sequence the steps to avoid unintentional duplication of steps by different operators.

3.5.3 Step Length and Content Instruction steps will be short and simple sentences dealing with only one idea. The following specific guidelines apply:

a. Limit the number of action verbs per step to one, unless the actions are closely related, in which case up to three action verbs are acceptable. Appendix 3D defines some of the action verbs commonly used in EPs. *

b. Describe complex evolutions in a series of steps,

c. Do not state the person performing the action; that is, do not begin a step with "The operator shall . . ."

d. Do not use imprecise adverbs (for example, frequently or slowly),

e. Avoid double negatives

f. When an action has three or more objects, list them vertically using bullets. For example:

CLOSE OR VERIFY CLOSED:

i e RPV HEAD VENTS B21-F001 AND B21-F002 e MSIVs

e MAIN STEAM LINE DRAINS e RCIC STEAM ISOLATION VALVES

g. When actions are required based on receipt of an annunciated alarm, state the alarm and its setpoint.

h. If required for proper understanding, describe the system response time associated with step performance.

i. When system response dictates a time frame within which the instruction must be accomplished, state the time frame.

However, avoid using time to initiate operator actions because operator actions should be related to plant parameters. .

j. When anticipated system responses may adversely affect instrument indications, describe in a CAUTION: (1) the conditions that will very likely introduce instrument error and (2) a means of determining whether instrument error has occurred.

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MISSISSIPPI POWER & LIGHT COMPANY

k. When additional confirmation of system response is necessary, state the backup readings to be made.

3.5.4 Types of Steps Guidance for different types of actions follows,

a. Simple Action Step Begin this type of step with the action verb:

CLOSE . ..

OPEN . ..

POSITION . ..

b. Verification Step Begin with an action verb that clearly indicates that verification is to be performed:

VERIFY . . .

As stated in the guidelines above, list three or more items to be verified vertically.

c. Continuous Step Indicate clearly that a.n action is to be performed continuously:

CONTINUE TO SCAN...

MAINTAIN CONTINUOUSLY. . .

d. Recurrent Step Indicate clearly (1) when or how of ten the step is to be performed and (2) under what conditions the step should no longer be carried out. Remind the operator at a later point in the flow path to keep performing the step.

An example of a recurrent step is:

CHECK TANK LEVEL EVERY 30 MIN

e. Alternative Step State specifically that thE prescribed step may be performed in alternative ways (if any) by using the logic word OR.

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MISSISSIPPI POWER & LIGHT COMPANY

f. Concurrent Steps Indicate clearly whether any steps need to be performed concurrently (i.e., operating within different parts or sections of a single procedure or the use of more than one procedure at the same time) with other steps by using such words as " simultaneously," "at the same time," or

" concurrently."

e If the actions are closely related, join the actions with "and" within the same step. However, "and" does not in itself imply simultaneous performance, so the need for simultaneous action still needs to be stated.

e If the actions are not closely related enough to be -

included in the came step, or if there are more than three closely related actions, list the steps with a lead-in instruction indicating the need for simultaneity, such as " perform the following actions concurrently."

The number of concurrent steps should not be beyond the capability of the control room staff to perform them.

3.5.5 Logic Terms The following guidelines apply to the use of logic terms.

Logic terms will be underlined for emphasis.

a. AND/OR Avoid the use of AND and OR within the same action. When AND and OR are used together, the logic can be very ambiguous. For example, the following instruction could be interpreted in more than one sense:

E CONDITION 1 AND CONDITION 2 O_RRCONDITION 3 OCCURS, THEN GO TO STEP 3.

b. AND When attentien should be called to combinations of conditions or closely related actions, use the word AND between the actions or conditions. Do not use the word AND to join more than three actions or conditions. If four or more actions or conditions,,need to be joined, use a list format. .

STOP THE PUMP AND PLACE IT IN STANDBY 3-15 Revised July 1986

MISSISSIPPI POWER & LIGHT COMPANY

c. OR Use the word OR when calling attention to alternative combinations of actions or conditions.

d. IF or W EN . . .THEN When action steps are contingent on certain conditions or combinations, begin the step with IF or WEN followed by a description of the condition (s), a comma, and the word THEN followed by the action to be taken. WHEN is used for an expected condition. IF is used to determine the specific course of action based on plant conditions,

e. IF WHILE...THEN This combination of logic terms is used in retainment steps, where operators must remember information about a condition that may occur while they are performing subsequent steps. Begin the step with IF WHILE followed by a description of the condition or conditions, a comma, and the word THEN followed by the action to be taken. See Figure 3-7 for an example.

f. IF NCTP Use IF NOT only where the operator must respond to the second of two possible conditions. IF should be used for the first condition. For example:

E PRESSURE IS INCREASING, THEN STOP THE INJECTION PUMP IF NOT, THEN START AN ADDITIONAL INJECTION PUMP.

Examples of conditional statements tosing logic words are given in Section 3.5.6 below.

3.5.6 Conditional Statements Conditional action steps must be constructed simply and clearly because of the often complex logic and ideas therein. The following rules apply:

a. The IF or WHEN clause precedes the action:

IF SUPP POOL TEMP REAblES 1100 F, THEN SCRAM THE REACTOR WHEN RPV PRESSURE DECREASES TO 800 PSIG, THEN OPEN ALL ADS VALVES AND GO TO EP-ll 3-16 Revised July 1986

MISSISSIPPI POWER & LIGHT COMPANY

b. Where three or more conditions exist, a listing approach is preferable:

E WRILE EXECUTING THE FOLLOWING STEPS:

e REACTOR POWER IS ABOVE 4% OR UNKNOWN

, AND e RPV WATER LEVEL IS ABOVE -166IN AND e SUPP POOL TEMP IS ABOVE 1100 F AND e EITHER AN SRV IS OPEN OR OPENS g DRYWELL PRESSURE IS AEOVE 1.23 PSIG, THEN RETURN TO STEP LP-9 -

c. Where only one of two conditions produces an action, use the following approach:

E BORON INJECTION IS REQUIRED O_R R BORON INJECTION HAS BEEN INITIATED, THEN TERMINATE AND PREVENT INJECTION FROM ALL SYSTEMS EXCEPT BORON INJECTION AND CRD If there were three or more conditions in the above example, a listing approach would be preferable, with each condition linked by OR (underlined and centered between the conditions).

d. When an action step has specific conditions relating to sequence and plant parameters, use the following approach:

BEFORE CONTAINMENT TEMP REACHES 1850F AND

! IF CONTAINMENT PRESSURE IS BELOW CURVE

~

CN-T-1, THEN INITIATE CDNTAINMENP SPRAY Conditional statements are treated in further detail in NUREG-0899, " Guidelines for the Preparation of Emergency Operating Procedures," Appendix B, and in INPO 82-017,

" Emergency Operating Procedures Writing Guidelines,"

Section 2.3.18.

e. Spacing above and below centered logic words (i.e. , AND, OR) in conditional statemen.ts should be consistent throughout the flowchart. The spaces between bulleted items (single or double space) should also be consistent.

3-17 Revised July 1986

MISSISSIPPI POWER & LIGHT COMPANY 3.5.7 Referencing and Branching

a. Definitions The term " referencing" in connection with another procedure implies that the referenced procedure will be used as a supplement to the initial procedure. Referencing can also occur within a procedure, either forward or backward.

The term " branching" means that operators exit the initial procedure and enter a new procedure, so that at any given time they are working with only one procedure.

b. Guidelines ,

Excessive referencing to other procedures or forward / backward within a procedure causes operator errors. The following guidelines apply:

1) If the length or complexity of the flowchart will not be substantially increased, repeat the needed information rather than referencing.

2) Reference complete procedures or sections of procedures if possible. Requiring an operator to use another procedure for just a few steps is to be avoided. .

3) Be sure to clearly direct operators back to where they left off.

4) Include references to GGNS-1 Emergency Plan Procedures (EPPs) as appropriate on the flowchart.

c. Format

1) When referencing another step, flow path, or procedure to be used as a supplement, use words such as " REFER

( TO" or ". . . USING PROCEDURE E-5." For example:

l t

E SUPP POOL WATER LEVEL INCREASES TO X PT, THEN RESTORE LEVEL WITH NORMAL SUPP POOL DRAIN USING PROCEDURE 04-1-01-P-ll-2.

A procedure may also be referenced using the concurrent step symbol, described earlier in Section 3.4.7.

3-18 Revised July 1986

MISSISSIPPI POWER & LIGHT QMPANY i

2) When branching to another procedure or flow path, use words such as "GO TO" or " EXIT / ENTER," and the entry and exit symbols described earlier in Section 3.4.8.

For example:

IF RCIC IS NOT READY FOR OPERATION AND RPV PRESSURE IS INCREASING, THEN GO TO EP-12 3.5.8 Safety Parameter Display System References i

An ellipse will be placed on the flowchart at appropriate points to indicate that pertinent information is available on the Safety Parameter Display System (SPDS). Within the ellipse, place the appropriate SPDS "page" number. Use a hyphen instead of listing consecutive page numbers in a series. For example, 2-7.

3.5.9 Component Identification Equipment, controls, and displays should be identified in operator language (common usage) terms without the location, with the following exceptions:

a. When the engraved names and numbers on legend plates and alarm windows are specifically the item of concern in the procedure, the engraving should be quoted verbatim.

b. If the component is seldom used or difficult to locate, location information such as the panel number should be given.

3.5.10 Word Choice The flowchart format requires brevity, so words must be selected carefully. The following guidelines apply- '

i

a. Use simple, short, familiar words commcnly understood by )

the trained operator.

{

b. Use concrete, specific words.

c. Use specific action verbs such as those listed in Appendix 3D. For control circuitry that executes an entire function upon actuation of the control switch, use the action verb without further instructions on how to manipulate the control devLce. Recommended action verbs are:

e For power-driven rotating equipment: START, STOP e For valves: OPEN, CLOSE, THROTTLE OPEN, THROTTLE CLOSED, THROTTLE 3-19 Revised July 1986

MISSISSIPPI POWER & LIGHT COMPANY l

e For power distribution breakers: SYNCHRONIZE, CLOSE, TRIP For multiposition control switches that have more than one position for a similar function, placement to the desired position should be specified.

d. Use Appendix 3E for recommended spellings and words to avoid.

e. Use Appendix 3F for acceptable abbreviations and acronyms.

f. Define any key words that may be understood in more than 4

one sense.

3.5.11 Methods of Emphasis The following methods are to be used:

a. Logic terms: underlining ( F, WHEN, THEN, AND, OR_, NOT)

b. Other types of information: underlining when appropriate for special emphasis.

3.6 Mechanics of Style 3.6.1 Spelling Use spelling consistent with a current dictionary. When a choice of spellings is offered, use the first listed.

Several industry-specific terms have varying spellings, such as "startup" versus " start-up." Common usage at GGNS-1 is the guidance here, and Appendix 3E lists these terms.

3.6.2 Abbreviations and Acronyms The use of abbreviations and acronyms depends heavily on user familiarity; that is, their meaning must be unquestionably clear to an expected procedure user. On the other hand, they are needed to save space in the flowchart format, and it is virtually impossible to spell them out at their first mention, 1 which is normally done in single- or double-column format procedures. Therefore, the following guidelines apply:

a. Spell out all words in procedure titles.

b. Use abbreviations and acronyms that the operator learns in the course of training.

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MISSISSIPPI POWER & LIGHT COMPANY

c. Ensure that abbreviations and acronyms are consistent with labels in the control room.

d. Use abbreviations for units of measure FT, not PEET; PSI, not POUNDS PER SQUARE INCH.

e. Be consistent in using abbreviations and acronyms; always spell them the same way.

f. To make an abbreviation plural, add a lowercase a: SJAEs, not SJAE'S. Reserve the apostrophe for showing possessive.

Appendix 3F contains abbreviations and acronyms used in GGNS-1 -

EPs.

• 3.6.3 Hyphenation Hyphenating (dividing) a word at the end of a text line should be avoided in the flowcharts. If hyphenation is difficult to avoid because of space, words must be divided as shown in a current dictionary, and at least three letters must be carried down to the next line.

Hyphens are used to link elements of a compound word (called a unit-modifier), such as "nine-digit number" and "long-term control." Hyphens are also used in the following circumstances:

e In compounds with "self": self-explanatory e When the last letter of the first word or prefix is the same vowel as the first letter of the second word: re-energize o When misleading or awkward consonants would result by joining the words: non-nuclear e To avoid listing consecutive numbers in a series when space is limited.

Hyphens are not used with the following prefixes unless confusion results from closing up the word.

e pre e micro e post e mini ...

e re e multi 6 e sub o non i e super

-21 Revised July 1986

MISSISSIPPI POWER & LIGHT COMPANY 3.6.4 Punctuation

a. Colon Use a colon to indicate that a list of items will follow.

b. Comma The following rules apply:

1) Use a comma between the "if" or "when" clause and the action clause of a conditional ~ statement.

2) Use a comma for numerical values of five digits or .

more, e.g., 100,000, 50,000, 2000. -

3) Use a comma to set off an introductory phrase or word.

4) Use a comma before the conjunction connecting the last item in a series of three or more:

AVOID RPV HIGH NATER LEVEL TRIP ON RFPTs, RCIC, AND HPCS INJECTION VALVE (E22-F004)

Note that within the flowcharts a series of three or more items is listed vertically, so commas are not used.

c. Parentheses Parentheses are used to give additional, defining information:

RHR (STEAM CONDENSING MODE)

d. Period i

A period is used to end a complete statement, although it is generally not used within the flowchart symbols. A period is omitted when:

1) Listing items vertically. For examples e RCIC e HPCS ..,

e LPCS .

e LPCI l

1 l

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MISSISSIPPI POWER & LIGRT COMPANY

2) Spelling an acronym HPCS, not H.P.C.S.

3) Abbreviating units of measure: FT, LB, PSI. However, IN. is used to avoid confusion with the word IN.

e. Question Mark Question marks are not used within the decision step symbol on flowcharts.

3.6.5 Acceptance Criteria and Calculations The following rules apply:

a. Be as specific as possible when stating qualitative '

acceptance criteria. Avoid using vague words like

" satisfactory" or " normal."

b. Express quantitative acceptance criteria and tolerances in ranges so that the operator does not need to mentally add or subtract.

c. Use tables of values or graphs in the procedure to avoid operator calculation.

d. If calculation cannot be avoided, simplify the calculation, provide the formula, and provide space for calculating. For example:

RECORD FEED PUMP SUCTION PRESSURE: P= PSIG RECORD FEED PUMP SUCTION TEMP: O T= F LOOK UP VAPOR PRESSURE AT T: VP = PSIG NPSH = 2.3 (P: ) - (VP: ) = FT OF HEAD 3.6.6 Numerical Values The following rules apply:

a. Always use arabic numerals.

b. For brevity in the flowchart format, use the numeral instead of the word: 3, not three.

c. For numbers less than one"," sprecede the decimal point by a zero; for example: 0.1.

d. Ensure that the number of significant digits is equal to l the number of significant digits available from the

! display (and required by the nece,ssary reading precision l of the operator).

l

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MISSISSIPPI POWER & LIGHT COMPANY

e. Specify engineering units for numerical values of process variables, and ensure that they are consistent with the units predominantly displayed to the operator.

3.7 EP Revisions and Updates 3.7.1 Review Requirements EPs may be reviewed as a result of:

a. Revision of the BWROG Emergency Procedure Guidelines

b. Revision of other procedures referenced in the EPs

c. Revision of the FSAR -

d. Revision of Technical Specifications

e. Feedback received from Verification and Validation (V&V) activities

f. NRC correspondence received that changes the scope' of the EPs

g. Operating experience 3.7.2 Revision Process If it is determined that a revision is necessary, the revision will be prepared in accordance with this writer's guide. If the revision is significant, a special training session may be required. (Minor revisions are covered in routine requalification training.)

3.8 Personnel Utilization to Accomplish EPs 3.C.1 Personnel Responsibilities Specific personnel (i.e., Shift Supervisor, Shift Superintendent, etc.) will have defined responsibilities when the EPs are in use. These responsibilities will be developed by the GGNS-1 Operations Department and modified as necessary after the V&V activities.

3.8.2 Training l

Personnel responsibilities during EP use will be addressed during initial and requalification training for all GGNS-1 licensed operators. Additional training experience will be gained during the annual Emergency Preparedness exercises.

3-24 Revised July 1986

MISSISSIPPI POWER & LIGHT COMPAhT l I

i 3.9 Use of Procedures to Combat Emergencies 3.9.1 Use of EPs The EPs provide guidance to mitigate the consequences of transients and accidents. These procedures are organized for entry based on specific plant symptoms.

3.9.2 Use of EPPs The EPPs direct the operations required if other site personnel or outside agencies need to be involved. These procedures are normally executed concurrently with the EPs where required.

3.9.3 Use of SoIs, IOIs and ONEPs

• System Operating Instructions, Integrated Operating Instructions, and Off-Normal Event Procedures may be used to:

a. Perform specific, complex evolutions that are too detailed to be included in an EP.

b. Maintain the plant in a stable shutdown state after the EP (s) has been exited.

3.10 Guidelines on Equipment Use during Emergencies 3.10.1 Emergency Use of Equipment SOIs and IOIs provide for plant operation or shutdown using equipment within design limits. However, it may be necessary during emergencies to use equipment in a manner beyond its design limit. Guidance will be provided where practicable to

ensure successful temporary operation, although a shortened service life may result.

I 3.10.2 Documentation If any equipment is operated beyond its design specification, the following should be noted in the control room log:

o Component affected e Parameter exceeded or value operated at e Length of time operated above design limits 3-25 Revised July 1986

MISSISSIPPI POWER & LIGIT COMPANY l

3.10.3 Return to Service Equipment operated above design limits during EP use should not be used for " normal" operations until evaluated by the technical staff.

3.11 Appendices 3.11.1 Appendix 3A - Planning Guidance for the Procedure Writer 3.11.2 Appendix 3B - List of GGNS-1 Emergency Procedures 3.11.3 Appendix 3C - Sample Format 3.11.4 Appendix 3D - Action Verbs 3.11.5 Appendix 3E - Vocabulary 3.11.6 Appendix 3F - Abbreviations and Acronyms s

3-26 Revised July 1986

[ MISSISSIPPI POWER & LIGHT COMPANY f

APPENDIX 3A - PLANNING GUIDANCE FOR THE PROCEDURE WRITER Before starting a first draft of any document, a writer should research the topic, analyze the audience, and either outline or diagram the major points to be covered to establish organization and sequence. This appendix contains guidance in these areas that is specific to the GGNS-1 EP writer.

3A.1 Gather Technical References The first step in procedure development is research into the technical documents to which the procedure must adhere. These documents include:

a. PSTGs: The EPs are to be written based on these guidelines.

b. BWROG EPGs: Although the EPs are directly derived from the PSTGs, it may be necessary to verify technical information by referring .

to the generic EPGs.

c. Technical Specifications: All acceptance criteria must conform to the GGNS-1 Technical Specifications.

d. FSAR: This report will be needed to verify plant commitments.

3A.2 Gather Supporting References and Guidelines 3A.2.1 Writing Guidelines Additional references on writing and style are needed to write the procedure. The following are recommended:

a. A current dictionary: A dictionary is needed to determine spelling and hyphenation of words.

b. McGraw-Hill Dictionary of Scientific and Technical Terms, 1984 ed.: This dictionary may be used to determine the spelling and abbreviations of terms too technical to be included in a nontechnical dictionary.

c. Words into Type, 3rd ed., Prentice-Hall, 1974: This book.

may be used to clarify principles of grammar, usage, and style.

d. NUREG-0899, " Guidelines for the Preparation of Emergency Operating Procedures," August 1982: This NUREG contains the human f actors principles upon which this writer's guide is based, and may be helpful to clarify or amplify this guide.

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} MISSISSIPPI POWER & LIGHT COMPANY 1

I e. INPO 82-017, " Emergency Operating Procedures Writing Guidelines," July 1982: Many of the principles outlined in this INPO document are restated in this writer's guide. The original INPO document may be needed for further guidance on a specific point.

3A.2.2 MP&L Procedures

a. Administrative Procedure 01-S-02-3, Rev. 13, " Author's Guide, Safety Related," September 4, 1984.

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b. Operations Section Procedure 02-S-01-1, Rev. 10,

" Author's Guide for Operations Section Instructions, Safety Related," June 29, 1984.

s 3A.3 Analyze the User i

Research into the expected procedure user is needed to ensure a workable procedure. Most questions on style and content can be answered by first asking "Who is the user?"

Factors to be considered in user analysis include:

( a. Level of training and education

1) What is the level of the least trained?

2) What is the level of the most trained?

3) Is there a wide range of operators with different levels of '

training?

b. Years of experience: The same questions apply.

c. Expected environment

1) What are the physical conditions, such as lighting, control room layout, and number of operators in the control room?

2) What is the expected stress level? How will it affect the operator's ability to read, comprehend, and efficiently

, execute the procedures?

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d. Past problems with procedures

1) What kind of procedural deficiencies have led to user dif ficulties at GGNS-17

2) What problems have other plants had and how did they resolve th em?

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MISSISSIPPI POWER & LIGHT COMPANY 3A.4 Outline the Major Points Outlining or charting out the procedure's major paths or steps helps the writer examine the logic and organization early. In the outline, flow diagram, or event tree, show the following:

a. Sequence, including concurrent flow paths

b. Decision points

c. Any third party verification, approval, or notification points

d. Interfaces with other EPs

e. Interfaces with other plant procedures, such as EPPs The outline or chart can then be filled out into a procedure draft. ,

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e MISSISSIPPI POWER & LIGIT CX)MPANY APPENDIX 3B - LIST OF GGNS-1 EMERGENCY PROCEDURES Nureber Title 05-S-01-EP-1 Scram i

05-S-01-EP-2 Reactor Pressure Vessel (RPV) Control 05-S-01-EP-3 Containment Control 05-S-01-EP-4 Secondary Containment Control

} 05-S-01-EP-5 Padioactivity Release 05-S-01-EP-ll RPV Level Restoration 05-S-01-EP-12 Emergency RPV Depressurization 05-S-01-EP-13 RPV Flooding 05-S-01-EP-14 Reactor Level / Power Control 3B-1 f- _

I MISSISSIPPI POWER & LIGHT COMPANY APPENDIX 3C - SAMPLE FORMAT 3C.1 Margins The flowcharts will have at'least a 1" margin on all four sides. The title block in the lower right corner will be at least 1" from the j right and bottom edges of the chart. l 3C.2 Page Layouts Figure 3C-1 contains a sample flowchart segment that illustrates flowchart format.

3C-1

l MISSISSIPPI POWER & LIGHT COMPANY iI it RESTORE AND MAINTAIN APV LEVEL ._

BETWEEN +11.4 IN. AND +53 5 IM.

LLP-34

<r

-IFRPV LEVEL CANNOT BE RESTORED TO BETWEEN +11.4 IN. AND +53 5 IN.

THEN MAINTAIN RPV LEVEL A80VE TAF b LP-35 8

CAN g RPV LEVEL YE5 .

BE MAINTAINED A80VE

'^'

L LP-35

{ o EMERGENCY DEPRES5URIZATION RPV CONTROLK EP.12 EP-2 /

ED-1 RC/P-10

[

lLP-25) .

E P-14 LEVEL / POWER CONTROL ,

GRAND GULF NUCLEAR STATION Rev 0 "!?i1/31/86 o

Figure 3C-1. Flowchart Segment 3C-2

i MISSISSIPPI POWER & LIGHT COMPANY APPENDIX 3D - ACTION VERBS The following are some of the action verbs commonly used in the EPs.

Allow - To permit a stated condition to be achieved before proceeding, for example, " allow pressure to stabilize."

Check - To perform a physical action that determines the state of a variable or status of equipment without directing a change in status, for example, " check suppression pool level."

Close - To change the physical position of a mechanical device so that it prevents physical access of flow or permits passage of electric current, for example, "close valve."

Complete - To accomplish specific procedural requirements, for example,

" complete valve checkoff list."

Establish - To make arrangements for a stated condition, for example,

" establish communication with control room."

l Inspect - To measure, observe, or evaluate a feature or characteristic for comparison with specified limits; method of inspection should be included, for example, " visually inspect for leaks."

qpen - To change the physical position of a mechanical device, such as a valve or door, to an unobstructed position that permits access of flow, for example, "open valve."

Record - To document a specified condition or characteristic, for example,

" record pressure."

Set - To physically adjust to a specified value an adjustable feature, for example, " set diesel speed to . . ."

Start - To originate motion of an electric or mechanical device directly or by remote control, for example, " start charging pumps."

Stop - To terminate operation, for example, "stop charging pumps."

Throttle - To operate a valve in an intermediate position to obtain a certain flow rate, for example, " throttle valve to . . ."

Trip - To activate a semiautomatic feature, for example, " trip breaker."

Vent - To permit a gas or liquid confined under pressure to escape at a vent, for example, " vent pump."

Verify - To observe an expected condition or characteristic, for example,

" verify discharge pressure is stable."

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. . _ . _ _ _ . _ . - - , . . . ~ ~ _ , _ _ _ _ - . _ - . -

i MISSISSIPPI POWER & LIGHT COMPANY APPENDIX 3E - VOCABULARY 3E.1 Use of Shall, Will, Should, May, and Must The following definitions apply when these words are used in EPs:

shall/will -

A requirement established by a specific regulation or regulatory requirement.

l should -

A recommendation but not an enforceable regulatory requirement. Management expects each employee i using plant directives to carry out any "should" statement unless circumstances prevent or necessitate deviation. In those unusual .

! occurrences where deviation is necessary, the employee must justify the exception to the responsible Manager.

may -

An option, neither a recommendation nor a requirement.

must -

A requirement that is established by MP&L management. "Must" may also be used to meet i

regulatory intent.

3E.2 Recommended Spellings bleed line (two words) blowdown (noun or adj.): " blowdown mode" bus (singular), busses (plural) cool down (verb) cooldown (noun or adj.): " plant cooldown" de-energize (use the hyphen) drywell (one word) feed line (two words) feed pump (two words) feedwater (one word) flow path (two words) igniter line up (verb): "Line up the feed line."

lineup (noun): " Verify valve lineups."

letdown (noun): " Return letdown to normal."

makeup (noun or adj.): " makeup water" motor driven (no hyphen) motor operated (no hyphen) offsite (one word) onsite (one word) re-energizo (use the hyphen) reestablish 3E-1

MISSISSIPPI POWER & LIGHT COMPANY setpoint (one word) shut down (verb): " Shut down reactor."

shutdown (noun): " Verify reactor shutdown."

stand by (verb): "to stand by" standby (noun or adj.): "On standby," standby pumps start up (verb): " Start up water treatment" startup (noun): " plant startup" steam line (two words) subcooling (one word) 3E.3 Words to Avoid frequently - Imprecise. ,

normal - Do not use as the sole acceptance criterion; too vague.

satisfactory - Do not use as the sole acceptance criterion; too vague, shut, as in " shut the valve" - Use "close."

slowly - Imprecise.

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MISSISSIPPI POWER & LIGHT COMPANY APPENDIX 3F - ABBREVIATIONS AND ACRONYMS ADS automatic depressurization system APRM average power range monitor ARI Alarm Response Instruction ATHS anticipated transient without scram

CTNT/DRWL containment /drywell CRD control rod drive CST condensate storage tank DIFF differential ECCS emergency core cooling system EP Emergency Procedure ,

EPP Emergency Plan Procedure FSAR Final Safety Analysis Report HCU hydraulic control unit HPCS high pressure core spray HVAC heating, ventilating, and air conditioning IC isolation condenser IOI Integrated Operating Instruction IRM intermediate range monitor LOO limiting condition for operation LOCA loss of coolant accident LER Licensee Event Report LFMG low frequency motor generator LPCI low pressure coolant injection LPCS low pressure core spray MAX maximum MCC motor control center l MG motor generator 3

MIN minimum '

MR millirem MSIV main steam isolation valve MSL main steam line l

NDTT nil-ductility transition temperature NPSH net positive suction head

. ONEP Off-Normal Event Procedure

PCT peak cladding temperature

PRESS pressure PSID pounds per square inch differential PSIG pounds per square inch gage PSRC Plant Safety Review Committee QA Quality Assurance l

3F-1 4

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l MIS 3ISSIPPI POWER & LIGRT COMPANY RAD radiation RCIC reactor oore isolation cooling RECIRC recirculating RFPT reactor feed pump turbine RER residual heat removal RPM revolutions per minute RPS reactor protection system RPV reactor pressure vessel RSCS rod sequence control system RWCU reactor water cleanup SBGT standby gas treatment SDV scram discharge volume

• SJAE steam jet air ejector SLC standby liquid control SOI System Operating Instruction SORV stuck open relief valve SP Surveillance Procedure SPDS Safety Parameter Display System SPMS suppression pool makeup system SRM source range monitor SRV safety relief valve SUr? suppression TEMP temperature TAF top of the active fuel TCN Temporary Change Notice TE temperature element i

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I MISSISSIPPI POWER & LIGHT COMPANY

4. VERIFICATION AND VALIDATION PLAN 4.1 Introduction As part of the EP Upgrade Program for GGNS-1, the new procedures will undergo verification and validation (V&V) after they are written. This section presents MP&L's plan for conducting the EP V&V process.

The plan is based primarily on the guidance provided in four industry documents: (1) NUREG-0737, Supplement 1, " Requirements for Emergency Response Capability," (2) NUREG-0899, " Guidelines for the Preparation of Emergency Operating Procedures," (3) INPO 83-004, " Emergency Operating Procedures Verification Guidelines," and (4) INPO 83-006, "Beergency Operating Procedures Validation Guidelines." In particular, the overall EP V&V effort for GGNS-1 will address the following six objectives (from ,

Section 3. 3. 5.1 of NUREG-0899):

a. That EPs are technically correct; i.e., they accurately reflect the PSTGs.

b. That EPs are written correctly; i.e., they accurately reflect the GGNS-1 EP Writer's Guide.

c. That the language and level of information presentation in the EPs are compatible with the minimum number, qualification, training, and experience of the operating staff.

d. That EPs are usable; i.e., they can be understood and followed without confusion, delays, and errors.

e. That there is a correspondence between the procedures and the control room / plant hardware; i.e., control / equipment indications that are referenced are available inside and outside of the control I room, use the same designation, use the same units of measurement, l and operate as specified in the procedures.

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f. That there is a high level of assurance that the procedures will work; 1.e., the procedures guide the operator in mitigating transients and accidents.

The Institute of Nuclear Power Operations (INPO) defines EP verification as an evaluation performed to confirm the written correctness of the EPs and to ensure that the generic and plant specific technical aspects have been properly incorporated. In following this definition, EP verifi-I cation for GGNS-1 will address aspects of the first five objectives stated above. This evaluation will encompass all the actions necessary to ensure that a correct translation of all source documents into the EPs has occurred. The evaluation will also ensure that an auditable trail of documentation shows step by step how the BWROG EPGs are converted into the GGNS-1 EPs. This will require that the GGNS-1 PSTGs j (developed before drafting the EPs) be evaluated for written correctness and technical accuracy as well.

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-I MISSISSIPPI POWER & LIGHT COMPANY INPO defines EP validation as an evaluation to determine that the actions specified in the EP can be followed by trained operators to manage the emergency conditions in the plant. NUREG-0899 objectives "c," "d," and "f" above will be addressed by a method that is fully auditable.

Figure 4-1 correlates each of the six NUREG-0899 objectives with specific portions of the GGNS-1 VEV process. As shown in the figure, EP verification will evaluate objectives "a," "b," and "e" fully, and objectives "c" and "d" partially. EP validation will complete the evaluation of "c" and "d" and will also fully evaluate objective "f."

As noted at the bottom of Figure 4-1, three primary VGV methods to be used by GGNS-1 are tabletop discussions, walk-throughs, and simula-tion. In the tabletop method, personnel will explain and discuss procedure steps in response to a proposed scenario. In the walk-through .

method, control room operators will conduct a step-by-step enactment of a proposed scenario for validation team observers without carrying out the actual control functions. In the simulator method, control room operators responding to a simulated scenario will perform actual control functions on the GGNS-1 simulator for evaluation by validation team obse rvers .

4.2 PSTG and EP Verification The focus of the verification process will be to evaluate the written correctness and technical accuracy of the GGNS-1 PSTGs and EPs. Static aspects of the PSTGs and EPs such as plant specific valve numbers, setpoints, footnotes, and format will be confirmed to be in accordance with the BWROG EPGs, the GGNS-1 PSTG Preparation Guide, and the GGNS-1 EP Writer's Guide. Supporting procedures that are referenced or utilized will be documented to exist and evaluated to ensure that the intended functions referenced by an EP can be accomplished. In addition, the EPs will be partially evaluated for usability and compati-bility with the minimum number, qualifications, training, and experience of the GGNS-1 operating staff. Finally, the existence of adequate documentation for the PSTG and EP verification will be confirmed.

The verification process described in this section is modeled after INPO 83-004, " Emergency 0perating Procedures Verification Guidelines," and includes four phases: preparation, assessment, resolution, and documen-tation. Each of these phases is described separately below. The preparation phase will be conducted prior to verifying the PSTGs, and will apply to both PSTG and EP verification. The assessment, resolu-tion, and documentation phases will be performed for each of the PSTG and the EP verification efforts.

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NUREG-0899 V&V Process Components V&V Objectives Verification Validation

a. Technically correct e Comparison of PSTG and EPs (TT) i

b. Written correctly e Comparison of EP Writer's Guide (TT) e Evaluation Criteria Checklist (TT)

c. Compatible with e Review by operating e Evaluation during minimum number, shift complement slow-paced walk-qualification, train- in conjunction with throughs and "real-ing and experience tabletop review time" scenario of operating staff for objective "d" exercises (WT &

(TT) SIM)

d. Usable e Review by operating e Evaluation during shift complement to slow-paced walk-evaluate readability, throughs and "real-completeness, accuracy, time" scenario and convenience (TT) exercises (WT & SIM)

e. Correspondence exists e Comparison of con-l between procedures trol room instru-and control room / mentation and plant hardware controls (I&C) and EP references to IEC (WT)

f. Guide operators in e Evaluation of mitigating transients real-time" scenario and accidents exercises (SIM)

V&V Methods:

TT - Tabletop -

Individual or group evaluation WT - Walk-Through -

Step-by-step enactment of scenario operator actions without carrying out actual control functions SIM - Simulator -

Control functions performed by operators in simulator I

i Figure 4-1. Correlation between V&V Objectives and Process l

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MISSISSIPPI POWER & LIGHT COMPANY 4.2.1 Verification Preparation Phase The first step in the preparation phase will be to designate personnel, including a human factors engineer, as an Independent Review Team. These evaluators will be persons other than those who write the PSTGs and/or EPs. Also, selected GGNS-1 operations personnel will review the procedures and provide input from their operating experience and philosophy.

After the Independent Review Team has been designated, applicable source documents for conducting the verification will be identified and obtained. The principal source documents for the verification will be the BWROG EPGs, the PSTG Preparation Guide, and a GGNS-1 specific EP Evaluation Checklist. This checklist (Appendix 4A) has been developed from the guidance presented in three documents: (1) NUREG/CR-2005, " Checklist for

• Evaluating Emergency Operating Procedures Used in Nuclear Power Plants," (2) INPO 83-004, " Emergency Operating Procedures Verification Guidelines," and (3) the GGNS-1 EP Writer's Guide. Finally, PSTG and EP discrepancy sheets and EP verification completion records (as shown in Appendices 4B, 4C, and 4D) will be prepared to provide adequate documentation of the verification.

4.2.2 PSTG Verification Assessment Phase During the assessment phase, the PSTGs will be reviewed by the Independent Review Team. A step-by-step comparison of the PSTGs with the BWROG EPGs and the PSTG Preparation Guide will ensure proper incorporation of generic and/or plant specific technical information into the PSTGs. In addition, the Independent Review

, Team will verify that the documentation required to support the PSTGs (including calculations, tables, and figures) is complete.

The discrepancy sheet shown as Appendix 4B will be used to document the results of all these verification reviews and to record any discrepancies noted. This form provides not only for documenting each discrepancy but also for documenting the resolution of each discrepancy.

4.2.3 EP Verification Assessment Phase During the EP assessment phase, the EPs will be reviewed by the Independent Review Team and by GGNS-1 operations personnel.

They will be compared to the appropriate source documents assembled during the preparation phase. In particular, the following comparisons and reviews will be conducted:

o Comparison of the EPs with the requirements of the GGNS-1 PSTGs 4-4 l

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.i e comparison of the EPs with the GGNS-1 EP Writer's Guide i e Review of the EPs using the EP Evaluation Checklist e Tabletop review of the EPs by GGNS-1 operations personnel to initially assess usability and compatibility l e Comparison of control room IEC with the references to IEC made in the EPs The step-by-step comparison of the EPs with the requirements of the GGNS-1 PSTGs will ensure the completeness and technical accuracy of the EPs. Comparison of the EPs with the Writer's Guide will ensure written correctness and the incorporation of human factors engineering principles. The EP Evaluation Checklist will act as a further tool for confirming written ,

! correctness. The tabletop review by operations personnel, l though subjective in nature, will identify early any potential

! problems that control room crews might have in accepting and adapting to the upgraded EPs. The control room walk-through of the EPs will check each reference to IEC in the EPs against the control room labels displayed on the equipment. Additionally, units of measurement used in the procedures will be checked to ensure that they are consistent with those displayed on instruments.

The discrepancy sheet shown as Appendix 4C will be used to document the results of all EP verification reviews. The sheets will also document the resolution of each discrepancy. The l checklist item number for each deviation from the EP Evaluation Checklist will be noted on the corresponding discrepancy sheet.

All discrepancy sheets will be routed back to the Independent Review Team leader. He will present all sheets to the EP l

Upgrade Program project manager for designation of corrective I action to be taken.

l A key element of the assessment phase will be to ensure an auditable documentation trail showing the step-by-step conversion of the BWROG EPGs to the OGNS-1 EPs. This requirement will be met through the review of all PSTG/EP documentation used during procedure development.

4.2.4 Verification Resolution Phase During the resolution phase, the GGNS-1 EP Mpgrade Program project manager will distribute the discrepancy sheets to appropriate GGNS-1 personnel for the determination of corrective action to be taken on the PSTGs or EPs. The project manager will ensure that an adequate resolution is provided for each discrepancy, and will approve the resolutions by signing each discrepancy sheet. Resolutions will be incorporated by the 4-5

MISSISSIPPI POWER & LIGHT COMPANY personnel who prepared the PSTGs or EPs, and each discrepancy )

sheet will be signed off by the writer incorporating the l resolution. The discrepancy sheets will then be forwarded to the project manager for a review of the resolutions.

l 4.2.5 Verification Documentation Phase '

Following review of the EPs and acceptance of all resolutions, an EP verification completion record (Appendix 4D) will be completed for each EP. This record (along with accompanying verification worksheets and discrepancy sheets) will provide the verification documentation package for each EP.

43 EP Validation The EP validation, which is to be performed concurrently with the ,

Detailed Control Reom Design Review (DCRDR) Validation, will determine whether the actions specified in the EPs can be performed by trained operators to manage emergency conditions successfully. As shown in Figure 4-1, the validation process will evaluate the ability of the EPs to effectively guide operators in mitigating transients and accidents.

In addition, validation will complete the evaluations of EP usability and compatibility initiated during the EP verification.

The GGNS-1 validation process is presented in Figure 4-2 and is modeled after INPO 83-006, " Emergency Operating Procedores Validation Guidelines." It includes the four phases of preparation, assessment, resolution, and documentation. The preparation phase will focus on the development of lists of expected operator actions and performance evaluation guidelines for the scenarios to be used in exercising the EPs. During the assessment phase, the scenarios will either be run on the GGNS-1 simulator or be walked through in the control room. The control room operating crew will use the EPs to restore the plant to a safe condition. Based on a debriefing of the operators and an analysis of videotapes of the simulator runs, procedure-related errors will be identified (equipment and man / machine interface concerns will also be identified for resolution as a part of the DCRDR program). The EP discrepancies causing these errors will be listed, and resolutions will be developed during the resolution phase. Documentation produced during the validation will be collected and organized during the documentation phase to provide a traceable history of the initial validation effort.

This documentation will also lay the groundwork for instituting an ongoing EP validation program coupled with the training program. The ongoing validation program will provide a means of continuously evaluating the EPs.

4.3.1 Validation Preparation Phase As shown in Figure 4-2, the key steps involved in preparing for EP validation will be as follows:

a. Designate Validation Team personnel.

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MISSISSIPPI POWER & LIGHT COMPANY

b. Define and develop representative scenarios for both the simulator and walk-through methods of validation.

c. Conduct walk-throughs to refine the scenario descriptions,

d. Evaluate differences between the simulator and the control room that may affect how the simulator scenarios are written.

e. Prepare necessary observer forms and checklists prior to the exercises.

f. Familiarize operating crews being used for the validation with the new EPs.

Each of these steps is discussed below:

a. Designate Validation Team Personnel A team of qualified personnel will be appointed to prepare and conduct'the validation effort. The team will include training / operations personnel, a human factors engineer, simulator instructors, operating crews, and videotape camera operators. Figure 4-3 outlines the responsibilities of these members of the team.

The subject matter experts from training and operations will be familiar with the new procedures and with the design and operation of the simulator and control room.

The simulator instructor will understand the hardware design, sof tware programming capabilities, and operation of the simulator. Operations personnel will respond to simulated transients and accidents, or walk through scenarios in the control room. To the extent possible, the control room staffing during simulator runs will resemble

! the staffing under normal plant operating conditions.

Validation Team personnel will run videotape cameras during simulator runs and walk-throughs.

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MISSISSIPPI POWER & LIGHT COMPANY t

PREPARATION DESIGNATE VALIDATION TEAM PERSONNEL DEFINE REPRESENTATIVE SCENARIOS I

DEVELOP SCENARIO TASK ANALYSIS WORKSHEETS CONDUCT WALK THROUGHS EVALUATE DIFFERENCES TO REFINE SCENARIO BETWEEN SIMULATOR DESCRIPTIONS AND CONTROL ROOM i

PREPARE SIMULATOR EXERCISE FORMS AND LISTS OF EXPECTED OPERATOR ACTIONS FAMILIARIZE OPERATING CREWS WITH NEW EPs CONDUCT CONTROL ROOM WALK THROUGHS AND SIMULATOR VALIDATION RUNS DEBRIEF OPER ATORS AN ALYZE VIDEOTAPES IDENTIFY DISCREPANCIES i

) CLASSIFY DISCREPANCIES RESOLUTION IDENTIFY AND INCORPORATE RESOLUTIONS DOCUM ENTATION

Fiaure 4-2. EP Validation Process 4-8

...a

MISSISSIPPI POWER & LIGHT COMPANY TRAINING HUMAN OPERATIONS FACTORS SIMULATOR OPERATING CAMERA PERSONNEL $PECIALIST INSTRUCTOR CREW OPERATORS PREPARE FoR ON. SITE DATA COLLECTION X X

)

PERFORM S!MULATOR

• RUNS ~X X X ,

X X

]

DEBRIEF OPER ATORS X X X X DETERMINE DISCREPANCIES X X X FILL OUT DISCREPANCY SHEETS X X Figure 4-3. Validation Team Members and Their Responsibilities

b. Define and Develop Representative Scenarios The initial basis for EP validation will be the DCRDR validation scenarios. Additional scenarios to fully exercise the EPs will be developed for EP validation. To the extent possible, each scenario will be planned to include multiple failures (simulataneous and sequential) that use a unique set of paths through the EPs so that the entire collection of scenarios will exercise as much of the procedure network as possible. Each scenario will include the initial plant conditions, action sequences, and expected outcome for a hypothetical plant emergency.

A systematic process will be used to choose transient and accident events for constructing scenarios. This will provide a representative sampling of events to ensure that the EPs will be exercised sufficiently. First, scenarios designed for use in the DCRDR Verification and Validation will be examined to see how much of the EP network is exer-cised. A matrix (see Figure 4-4) of emergency procedures (control functions) versus NRC identified critical safety functions (CSFs) will be used to identify which control functions and CSFs are challenged by the DCRDR scenarios.

Training and operations personnel on the Validation Team will then develop additional scenarios to ensure that all emergency procedure control- functions are challenged.

I 4-9 -

Revised July 1986

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- f es.. treswetee, es Re Core .e, NrA N/A O

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8 Figure 4-4e g

Sample BWR Matrix of EPs versus CFs and Corresponding Events

MISSISSIPPI POWER & LIGHT COMPANY f

A brief narrative description of each scenario will be prepared and will include t

e Initial plant conditions e Sequence initiator e Progression of actions e final plant conditions e Major systems exercised Task Analysis Worksheets (as shown in Appendix 4E) will also be completed for each scenario. This will indicate the anticipated operational steps required in each scenario, as well as the appropriate information and

} control requirements, means of operation, and IEC present on the control boards. Completed Task Analysis Worksheets will serve as templates for conducting the scenario run-throughs during the assessment phase. The worksheet will be completed in the following manner:

1) The discrete steps in the GGNS-1 EPs will be recorded in order of performance in the " Procedure Step Number" column of the Task Analysis Worksheet. Branching points, if any, will be recorded in the " Scenario Response" column.

2) A brief description of operator tasks (in order of procedural steps) will be recorded in the

" Task / Subtask" column of the Task Analysis Worksheet.

More tasks may be described than are explicitly called out in the procedural steps. In this case, a dash will be entered in the " Procedure Step No." and " Scenario Response" columns when no explicit procedural step is present in the EPs. All tasks, both explicit and

, implicit, will be documented by using operations, i engineering, and human factors personnel.

3) The operator decision and/or actions linked to task

( performance will be recorded in the " Decision and/or l Contingent Action Requirements" column. System functional response will be described when appropriate in this column. This set of data will include branching points in the EPs that determine the outcome of the scenario.

4) Requirements for successful task performance will be recorded in the "Information and Control Requirements" column. These requirements typically will be parameters, components, or procedural information necessary for operators to assess plant conditions or system status adequately.

4-11

. .- _- ~ .

I MISSISSIPPI POWER & LIGHT COMPANY 3

Steps 1 through 4 above will be completed prior to exercising the scenarios, using independent sources of data other than the actual IEC present in the control room. The remaining columns of the Task Analysis Worksheet will be completed from data obtained during the EP and DCRDR validation.

5) After the tasks, decision requirements, and information and control requirements have been specified, the specific IGC that the operator actually uses for each procedural step will be documented. All IEC will be listed that is needed to: (1) initiate, maintain, or remove a system from service, (2) confirm that an appropriate system response has or has not occurred, (3) make a decision regarding plant or system status.

The "Means" column on the Task Analysis Worksheet ,

refers to how the information and control requirements are presented on the control boards (e.g., switch or meter). The "IEC Identification" column will provide

!' the specific panel number and identification number of the control or instrument.

c. Conduct Walk-Throughs to Refine Scenarios Using the scenario descriptions and Task Analysis Worksheets, preliminary walk-throughs of the scenarios will be conducted in the GGNS-1 simulator to ensure that the scenarios are consistent with the simulator capabilities.

i The scenario descriptions and task analysis information will be modified as necessary. These walk-throughs will also provide the necessary information for preparing the lists of expected operator actions and performance evaluation criteria for the simulator validation runs.

d. Evaluate Differences between Simulator and Control Room Prior to conducting simulator scenario runs, an assessment

! will be made of the differences between the simulator and i

the control room. This evaluation will determine any significant differences that will affect the scenarios.

Differences in control room design will be noted when lists l of expected operator actions are prepared so that attention l can be given to the differences during the simulator runs

and subsequent analysis. If necessary, the portion of the scenario that requires use of a panel not in the simulator will be walked through in the control room.

4-12

MISSISSIPPI POWER & LIGHT COMPANY

e. Prepare Revised Validation Scenarios and Checklists Using the Task Analysis Worksheets, the validation Team will revise the Simulator Validation Scenarios (Appendix 4F) . The Simulator validation Scenarios will present a synopsis of the transient to be used for the simulator runs

and will identify the plant conditions that need to be simulated. Scenarios that cannot be simulated will be readily identified, and will be performed by the walk-through method. For maximum efficiency, personnel familiar with simulator operations will be involved with this stage of the preparation.

After defining the scenario and the procedure steps that the operators could follow in responding to the emergency,'

the Validation Team will prepare a List of Expected Operator Actions (Appendix 4G) for use in evaluating the scenario run-throughs. The list will identify:

o A procedure set for the scenario and specific steps from each procedure e Operator actions that follow an expected path through the scenario e A description of specific points at which differences between the control room and simulator may affect operator performance i

e Discrepancies between actual performance and expected performance e Categorization of discrepancies The expected operator actions will be taken directly from the procedures and the Task Analysis Worksheets. Addition-al actions will be specified for any case in which the procedures or Task Analysis Worksheets do not actually delineate actions explicitly. The actions will not need to be copied in detail from the Task Analysis Worksheets:

however, a level of detail sufficient for observers to follow the action will be needed. The form will provide a concise description of expected actions in one place,

rather than requiring observers to flip through worksheets grouped by scenarios. The forms will also provide space for additional data such as, simulator / control room differences and notation of. potential procedure-i i

4-13

Revised July 1986

s t

MISSISSIPPI POWER & LIGHT COMPANY related errors. A trial simulator run may be conducted by the validation Team to ensure that the simulator script is consistent with the delineation of operator actions and simulator modeling.

It is recognized that several operator options may exist in the procedures and.that the operators' actual path through the procedure set may differ from the path defined by the Validation Team. The procedure for dealing with deviations from expected operator action is described in Section 4.3.2.

Finally, the Validation Team will prepare a checklist of exercise evaluation criteria to be used during the assessment phase, as well as a debriefing checklist to be used af ter each scenario is run on the simulator. The .

checklist and debriefing form will be developed from the guidance provided in INPO 83-006, " Emergency Operating Procedures Validation Guideline."

f. Documentation The necessary documentation for the assessment phase will include the following:

o Copies of the appropriate EPs from which the scenarios were derived e Description of differences noted between the simulator and the control room o Task Analysis Worksheets e Simulator Exercise Forms e Lists of Expected Operator Actions e Exercise Evaluation Criteria Checklist e Operator Debriefing Checklist

g. Conduct Crew Familiarization Before their arrival at the simulator, the operating crew (s) to be used for the assessment phase will be familiarized with the new procedures during classroom and simulator training sessions. In addition, control room /

simulator differences, such as human factors design, operation design, and workspace design, that may affect the run-throughs will be discussed.

4-14

l MISSISSIPPI POWER E LICHT COMPANY Before starting the assessment, operators taking part will be briefed concerning:

e validation objectives e Validation methodology e operator responsibilities during validation After all personnel have been briefed and are in place at the simulator or control room, the assessment phase will begin.

4.3.2 Validation Assessment Phase The assessment phase will focus on collecting information during j the simulator runs and control room walk-throughs, and on ,

analyzing the results of these exercises to identify differences in actual versus expected operator actions. Operator performance deviations will then be used to identify potential discrepancies in the EPs.

Certain general actions will be applicable to the assessment phase regardless of the method used. The Validation Team leader will review the responsibilities of each team member. Some individuals will be observers and data recorders, while others will be support equipment operators. All Validation Team per-sonnel will be familiarized with the overall format and sequence for conducting the assessment. If feasible, they will perform a

" dry run" of the assessment using an abbreviated form of the scenario (s). If the team has questions concerning use of either the observation or debriefing forms, the questions will be clarified. Coordination with the video crew will be finalized ,

at this time.

a. Conduct Simulator Validation Runs simulator runs will provide an objective context within which to evaluate the usability, compatibility, and effectiveness of the procedures (refer to Figure 4-1). In I contrast to walking through the procedures in a static environment in which oversights may occur, the simulation i environment will mimic the operating conditions for a more realistic challenge to the procedures, requiring the operators to diagnose the observed symptoms and use the EPs to implement corrective actions.

Each scenario will be simulated separately with a debriefing session after the run. During the run, validation Team members will be observerst at a minimum, two training / operations personnel and one human f actors i

4-15

4 MISSISSIPPI POWER & LIGHT COMPANY  !

i specialist will participate. As necessary, notes will be made to document potential deviations from the expected operator actions and/or deviations from expected simulator performance. The videotape recording of the scenario will permit the observers to analyze the run in greater detail.

During the simulator runs, if the operating crew takes an acceptable alternate path, they will be allowed to continue. If the crew takes an incorrect path but returns to the correct path within a reasonable amount of time, the simulation will continue. However, if the crew takes an incorrect path and shows no sign of recovering, the simulation will be stoppeds if an obvious, remediable error is involved (e.g., a page of the procedure is missing), the problem will be corrected and the run resumed. If, the problem is not obvious or readily correctible, the simulator run will be postponed until the problem is diagnosed or corrected.

b. Conduct Control Room Walk-Throughs For the walk-through method of validation, the following steps will be carried out by the operators:

e Walk or talk through the actions they would take during the specific situations covered by the scenario (s) e Describe actions they are taking e Identify information sources used to take actions e Identify controls used for carrying out actions, expected system responses, how these responses are verified, and the actions to be taken if the responses do not occur validation Team personnel will:

1 e Direct the walk-through i e Coordinate the efforts of operators, observer /

reviewers, and video crew e Review scenarios e Ask appropriate "what if" questions e Note problems and discrepancies encountered by operators l

l e Record operator comments 4-16 l

MISSISSIPPI POWER & LIGHT COMPANY

c. Debrief Operators after Simulator Runs The operator debriefing session will be conducted immediately after each scenario run on the simulator. The comments of the operators who have participated in the exercise will provide one of the most important sources of information for evaluating the procedure set. Operator actions that do not lend themselves to direct observation, such as symptom diagnosis or conversion of displayed values, will be described by the operators during the debriefing. The operators' comments will also contribute greatly to analyzing the deviations from the expected operator actions. All discrepancies, possible causes, and potential solutions identified during the debriefing will be documented.

A Validation Team member will explain the debriefing process to the operators and elicit thier general comments on the procedures. This may be augmented by a videotape display of the specific action or set of actions in question. The operators will be asked to identify possible reasons for any procedure-related problems they encoun-tered. Questions from the operator debriefing checklist will be asked to prompt the operators. The operators will also be asked to present potential solutions to any procedure-related problems.

The Validation Team members will then present problems and discrepancies they identified during the scenario. If the operators deviated from the EPs, regardless of the path they took through the scenario, this will be discussed.

This discussion may also be augmented by a videotape display of the specific action or set of actions in question. The operators will be asked to identify possible reasons for procedure-related problems. Again, the questions in the operator debriefing checklist will be used to determine whether the procedure caused the discre-pancy. The operators will be asked to present potential j

solutions to these problems.

d. Analyze Videotapes of Simulator Runs The form shown as Appendix 4G will be used during the analysis of the simulator runs. By comparing the expected operator actions with the actions performed during the scenario, the Independent Review Team will be able to note any discrepancies.

The observers will have made notes on the forms during the scenario runs. However, it will not be possible to record l

4-17 I

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MISSISSIPPI POWER & LIGHT COMPANY all operator actions during the run. A review of the videotapes will be necessary to record all actions and to identify all discrepancies. Comments elicited from the operators during the debriefing will be helpful in the analysis of the videotapes.

433 Validation Resolution P'ase h The discrepancies identified during assessment will be evaluated in the resolution phase of validation. For some discrepancies, no resolution will be required. Discrepancies that require resolution vill be evaluated for the specific type of error involved, and for recommended resolutions.

a. Classify Discrepancies The purpose of analyzing the discrepancies between expected and actual operator actions will be to identify potential deficiencies in the procedures. Each discrepancy identified during the debriefing and videotape review will be analyzed case by case to determine whether it is a procedural error or an acceptable discrepancy. Figure 4-5 outlines the steps involved in analyzing the discrep-ancies. A discrepancy that adversely affects operator performance or plant conditions will be considered an error.

The Validation Team will use the exercise evaluation criteria developed from INPO 83-006 to assist them in determining whether an error was or was not procedure related. Errors identified as procedural deficiencies will be documented on EP Discrepancy Sheets (Appendix 4C). When the procedure-related errors have been identified, they will be categorized as follows:

1) Error of omission e omits an entire task e omits a step in a task

2) Error of commission e Selects wrong control e Mispositions control

3) Error of sequence

4) Timing error e Too early e Too late 4-18

. _ _ -. - - - . . . - . .-_ ~- - . . . _ . .

. . ~

I MISSISSIPPI POWER & LIGHT COMPANY IDENTIFY j DISCREPANCIES BETWEEN SIMULATOR RUN AND EXPECTED OPERATOR ACTIONS U

WOULD DISCREPANCY HAVE AN ADVERSE NO CATEGORIZE AS EFFECT ON SAFE OR 5 ACCEPTABLE EFFICIENT PLANT DISCREPANCY OPERATION?

YES If NO E AS WAS THE ERROR PR OC EDUTIE- "

h0R ATTRIBUTED TO RELATED7 PROCEDURES YES 1f CATEGORIZE TYPE OFERROR Fleure 4-5. Flowchart for Discrepancy Analysis 4-19

-w--ww-- ,-, - - . - ~ ,....,,-y , - - , - - ,,--y. . . - , . . . . , _ . - , - . . _, , , _ _ _ _ . , _ . _ , , _ _ _ _ , _ _ _ , , _ - . , . _ , , . _ _ , , , , , , . , _ . . , , , , _ _ _ , ,

MISSISSIPPI POWER & LIGHT CDMPANY

5) Qualitative error e Too little e Too much

b. Identify and Incorporate Resolutions Recommendations for discrepancy resolutions will be noted on the EP Discrepancy Sheets by the Independent Review Team and approved by the project manager. Resolutions will be incorporated into the deficient EPs, and these revised EPs reverified prior to final review and approval.

The GGNS-1 simulator training program will provide periodic feedback on the EPs in an informal manner that effectively.

uses GGNS-1 material and personnel resources. Regular classroom or simulator instructors will identify any discrepancies or problems with the EPs found during operator training.

4.3.4 Validation Documentation Phase To provide an auditable history of the initial validation of the EPs, all documentation generated during the validation process will be organized for retention. As a minimum, this documen-tation will include:

e List of Independent Review Team members e Evaluation guidelines e Discrepancy Sheets e Simulator Exercise Forms e Lists of Expected Operator Actions 4.4 Appendices -

4.4.1 Appendix 4A - EP Evaluation Checklist 4.4.2 Appendix 43 - PSTG Discrepancy Sheet 4.4.3 Appendix 40 - EP Discrepancy Sheet 4.4.4 Appendix 4D - EP Verification Completion Record 4.4.5 Appendix 4E - Task Analysis Worksheet 4.4.6 Appendix 4F - Sample Simulator Scenario 4.4.7 Appendix 4G - Sample List of Expected Operator Actions 5

4-20 Revised July 1986

MISSISSIPPI POWER & LIGHT COMPANY APPENDIX 4A - EP EVALUATION CHECKLIST Area Yes N/A

}ict I. OVERALL PROCEDURE: WRIFTEN CORRECTNESS A. Legibility

1. Are the borders adequate on all procedure pages?

2. Are the text, tables, graphs, figures, and charts legible to evaluator?

B. Format Consistency .

Does the procedure contain all sections required by policy?

i C. Identification Inforwation

1. Does the precedure title describe the purpose of the procedure?

2. Does the cover sheet correctly provide the followings

a. Procedure title , _ _ _

b. Procedure number

c. Revision number

d. Number of pages

3. Does each page correctly provide the following:

a. Procedure number

b. Revision number --

c. Page of

4. Does the procedure have all its pages in the correct order?

4A-1

MISSISSIPPI POWER & LIGHT COMPANY I

Area Yes }kt N/A II. SPECIFIC STEPS, CAUTIONS, AND NOTES A. Written Correctness

1. Information Presentation

a. Are instruction steps numbered correctly?

b. Are user-optional esquence steps

, identified?

c. Are instruction steps constructed to

} comply with the following:

(1) Steps deal with only one idea.

j (2) Sentences are short and simple.

(3) User actions are specifically stated.

(4) Objects of user actions are specifically required.

(5) Objects of user actions are adequately stated.

(6) If there are three or more objects, they are in a list.

(7) Punctuation and capitalization are proper.

(8) Abbreviations are correct and understandable to the operator.

(9) Acronyms are defined the first time and used consistently.

d. Are instruction steps presented in the correct sequence?

e. When an action instruction is based on receipt of an annunciator alarm, is the setpoint of the alarm identified? _ , _ ,

f. Are cautions placed properly?

4A-2

MISSISSIPPI POWER & LIGHT COMPANY l

Area Yes No N/A

g. Are cautions constructed to comply with the following?

(1) They do not contain user actions.

(2) They do not use extensive punctuation for clarity.

(3) They make proper use of emphasis.

i. Are notes properly used? ,

j. Are notes properly placed?

k. Are notes worded so that they do not contain user actions?

1. Are numerical values properly written?

m. Are values specified in such a way that mathematical operations are not required of the user?

n. Is a chart or graph provided in the procedure for necessary user calcu-lations?

o. Are units of measurement in the procedure the same as those used on equipment?

2. Procedure Referencing and Branching

a. Do the referenced and branched procedures exist?

b. Is the use of referencing minimized?

c. Are referencing and branching instructions correctly worded?

(1) "Go to" (branching)

(2) " Refer to" (referencing)

d. Are the exit conditions compatible with the entry conditions of the referenced or branched procedure?

4A-3

MISSISSIPPI POWER & LIGHT COMPANY Area Yes }ict N/A B. Technical Accuracy

1. Entry Conditions or Symptoms Information

a. Are the entry conditions of the procedure listed correctly?

b. If additional entry conditions have been added, do they cceply with the following:

(1) Appropriate entry conditions for which the procedure should be used (2) Not excessive

2. Quantitative Information

a. Do the quantitative values comply with the applicable source document?

b. Are values used in procedure computed accurately?

c. When calculations are required, are equations presented with sufficient information for user to use?

3. Plant Hardware Information: Is the following plant hardware specified in the procedure available to the users

a. Equipment

b. Controls

c. Indicators

d. Instrumentation 4A-4

MISSISSIPPI POWER & LIGHT COMPANY APPENDIX 4B - PSTG DISCREPANCY SHEET PSTG DISCREPANCY SHEET EP

Title:

EP Number: PSTG Step Number:

Discrepancy:

Evaluation: Dates Resolution:

i Resolution Approved: YES NO (Circle One)

Approved by: Date:

Resolution Incorporated by: '

Date:

l 1

4B-1 Revised July 1986 l

f MISSISSIPPI PODER & LIGIT CDMPANY 3 APPENDIX 4C - EP DISCREPANCY SHEET EP DISCREPANCY SHEET EP

Title:

IP Nabe rt EP Step Number: ,

I Evaluation Criteria Checklist Item Number:

l Discrepancy:

Evaluation: Date:

Resolution:

Resolution Approved: YES NO (Circle One)

Approved by: Date:

Resolution Inco.porated by: Date:

4 C-1 ,

i MISSISSIPPI POWER & LIGIT (DMPANY APPENDIX 4D - W VERIFICATIGi (DWLETIGI RECDRD E VERIFIOLTIGi (DWLETIGi RECDRD EP

Title:

W Numbe r: Revision l

t

1. Resolution eff ected for all applicable Discrepancy Sheets i

2. Verification is complete I

l verification Engineer Date:

Approved by: Date:

i 1

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MISSISSIPPI POWER & LIGHT COMPANY APPENDIX 4F - SAMPLE SIMUIATOR SCENARIO C. Operating Sequence: Large Break Loss of Coolant Accident Initial Conditions: The plant is at 100% power in the middle of core life; it has been operated at full power for two weeks with a normal full power lineup.

Sequence Initiator: Complete sever of "B" main steamline.

NOTE: Simulator malfunction - complete sever of main steamline "B" between the flow element and the inboard MSIV.

Progression of Action: The crew acknowledges annunciators and attempts to verify the SCRAM, containment, and reactor isolation. The sudden reactor ,

vessel depressurization causes reactor vessel level to swell to reactor Level 8, tripping the reactor feed pumps, Reactor Core Isolation Cooling turbine and the High Pressuse Core Spray injection valve. The crew confirms initiation of available ECCS. The crew monitors containment and drywell parameters and takes action to maintain their integrity. Suppression pool cooling is placed in service.

The Shift Supervisor declares a site emergency and plant personnel are notified.

The operating crew returns the feedwater system to operation, restoring and maintaining reactor vessel level. The reactor vessel is depressurized through the main steamline break. Shutdown cooling is placed in operation as necessary.

Final Conditions: The reactor is shutdown, depressurized and being cooled by Shutdown Cooling Mode of RER.

Major Systems: Reactor Protection System, Emergency Core Cooling Systems, Containment and Reactor Vessel Isolation Control, Standby Gas Treatment, Combustible gas Control, Containment Cooling System, Residual Eeat Removal, Standby Service Water, Control Building Ventilation, Auxiliary Building Ventilation, Reactor Core Isolation Cooling, Neutron Monitoring System, Safety Relief Valves, Chilled Water System, Div III Diesel Generator, Nuclear Steam Supply Shutoff System, ESF Electrical Distribution System, Drywell Cooling System, Vessel Instrumentation, Condensate System, Condensate Refueling Water and Transfer Ssytem, Control Rod Drive Hydraulic System, Circulating Water System, Electrical Distribution Systems, Feedwater Systems, Containment Cooling System, Instrument Air System, Main Steam System, Rod Control and Information System, Reactor Recirculation Eystem, Component Cooling Water System, Plant Service Water System, Drywell and Containment Leak Detection System, Suppression Pool Makeup, Feedwater Control System, Generator System, Condensate and Suppression Pool Cleanup System, Service Air System, Area Radiation Monitoring.

4F-1 Revised July 1986

APPENDIX 4G - SAMPLE LIST OF EXPECTED OPERATOR ACTIONS Initial Conditions: 10% power, all stations in " Auto" Simulator /

Reference to Control Procedure Expected Operator Room Simulator Step Action Differences Discrepancy Category Exercise 1, .

2. - Recognize RCS pressure reduction as symptom of

' abnormal occurrence.

O Attempt to locate cause H and correct.

3. RP-X, Perform immediate actions - - -

for reactor trip (EP-X, 2 steps A-D; a

EP-Y, steps A-D). Go to EP-Y; perform steps A-D steps A-D. Continue attempts g m

to isolate cause.

9 4

- - - M

4. EP-Z, Perform verification of steps A-Z ESFAS Subsystem actuation.

Verify PORVs shut; if not, W shut block valves.

C ,

Initiate monitoring of Q H

CSFSTs. Branch to EP-XX.

n

MISSISSIPPI POWER & LIGHT COMPANY i

5. EP TRAINING PROGRAM DESCRIPTION 5.1 Introduction EP training will be a vital element in the overall operator training program at GGNS-1. A unified effort on the part of the training department and the EP writers will result in operators who are knowledgeable in both the intent and use of these procedures.

5.2 Training Program Development when developing training on EPs, the following major items will be considered:

e The type of operator training to be provi6ed (initial, refresher), -

k e The operator knowledge and skill level required to effectively use the EPs

}

I e The method of operator training to be used (classroom instruction, control room walk-throughs, and/or simulator exercises) o The training materials needed to support EP training requirements e The current operator licensing requirements and guidelines 5.3 Training Program Objectives The objectives of this training program are:

5.3.1 To enable the operators to understand the regulatory requirements for the EPs, by the review of t e NUREG-0737 " Clarification of TMI Action Plan Requirements" l

! e NUREG-0737 Supplement 1 " Requirements for Emergency Response Capability" l

e NUREG-0899 " Guidelines for the Preparation of Emergency Operating Procedurer" 5.3.2 To enable the operators to understand the philosophy behind the approach to the EPs including e The need for symptom-oriented procedures as opposed to event-oriented procedures e The content and use of each EP, including entry conditions and exit criteria (i.e., its structure and approach to 5-1

... .- - . _ _ . _ , . _ . ~ . . _ _ . . _ _ . .__ _ . . _ _ . _ _ _ _ . - - _ - _ _ . _ _ _ _ _ , _ . _ _ _ _ - - - _ . _ . . _ _ . _ _ _ _ _ _

MISSISSIPPI POWER & LIGHT COMPANY i

transient and accident mitigation, including the control of safety functions, accident evaluation and diagnosis, and the achievement of safe, stable, or shutdown conditions) e The use of flowcharts for operator actions 5.4 Training Methods As part of the overall training program, EP training will be included to establish an operating staff that is capable and competent to respond to any off-normal plant situation. This training will consist of classroom instruction, simulator exercises, and/or control room walkthroughs, as appropriate, conducted before procedure implementation.

5.4.1 Classroom Instruction The classroom instruction will give the operators an understanding of the:

e Structure of the EPS e Technical basis for procedure steps e Philosophy behind the procedures e Relationships among procedures e Use of flowcharts 5.4.2 Simulator Exercises Simulator exercises will provide practical experience in executing each procedure individually and multiple procedures concurrently. A variety of scenarios, including multiple, simultaneous, and sequential failures, will be used. These scenarios will stress knowledge of the procedure inter-j relationships, ability to locate and use instrumentation, and experience in using the procedures as a shift. This training will be conducted with all operators performing their normal control room functions as shown in Figure 5-1.

5.4.3 Control Room Walkthroughs For those EPs, or portions of EPs, not amenable to simulation, control room walkthroughs will be conducted. The areas to be emphasized during the walkthroughs are identical to those emphasized during the simulator exercises, but will be addressed in a static, rather than dynamic, environment.

l 5.5 Requalification Training Requalification training covering the E5s will be given annually. This training will use a teamwork approach in EP implementation. Operating crew responsibilities are defined in GGNS-1 Procedure 01-S-06-2,

" Conduct of Operations."

l 5-2 Revised July 1986

! MISSISSIPPI POWER E LIGHT COMPANY 4

5.6 Training on Revisions l Procedure revisions will be reviewed to determine whether retraining is i necessary. If necessary, training on minor revisions will be conducted through a progra= cf preshift briefings, lectures, or required t reading. Training on major revisions will be conducted by classroom I

instruction, control room walk-throughs, and/or the GGNS-1 simulator.

5.7 Operator Feedback Operator feedback concerning EP training will be considered in determining any additional training needs in this area.

i

}

4

?

5-3

POTG LutDE

' Rev. U APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 1 of_d5_

J BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGHS- PLANT SDECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION RPV CONTROL GUIDELINE RPV CONTROL CUIDELINE

a. 1.2 I psig and 1064.7 Entry Conditions Entry Conditions psig from Tech. Spec.

Table 2.2.1 1 The entry conditions for this guideline are any of tr.e The entry condition for this guideline are any of the following followings b. MS!V isolation deleted to allow o RPV water level below (el2 in. (10w level scram setpoint)) o RPV water level below -41.6 in. operation with the o RPV pressure above (1043 psig (high RPV pressure scram o RPV pressure above 1064.7 psig MSIVs closed with-se tpoin t)) o Drywell pressure above I.23 psig out requarang a o Drywell pressure above (2.0 psig (high drywell pressure o A condition which requires reactor scram, and scram scram seapoint)) power above 4% or cannot be determined o A condation which requires MSIV isolation c. 4% from Tech. Spec.

. o A condition which requires reactor scram, and reactor power Table 3.3.6-2 above (3% (APRM downscale)) or cannot be deiermined

d. -41.6 inches found in Tech. Spec. Table 3.3.2-2

p e. Entry condition on

.J H PV low levei es ch.inged to Level 2 from Level 3 since a Level 3 scram ss addressed in the scram procedure (EP.I) 1 f*

i J

PSTG GUIDE i Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _ _2 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/ JUSTIFICATION 1

OPER ATOR ACTIONS RC-1 If reactor scram has not been initiated, initiate RC-1 If reactor scram has not been initiated, reactor scram. Initiate reactor scram, i

4 1

1 l

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BWR OWNERS GRO'JP- EMERGENCY PROCEDURE GUIDELli4E GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE

_ DEVIATION /JUSTIFICATloN Inwrt SRM's and IRM's a. lYovides the ability to trend the decrease

, in reactor power that would be expected followind a scram.

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,e Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page -4 of 45

{ BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEvlATION/ JUSTIFICATION trrespective of the entry condition, execute (Steps RC/L, Irrespective of the entry conditions, execute RC/P, and RC/Q) concwrently.

Steps RC/L, RC/P and RC/Q concurrently.

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' e Rev. O APPENDtX A Res. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 5 of 45 -

BWR OWNERS GROUP- EMERGENCY PROCEDURE' GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION RC/L Monitor and control RPV water level RC/L Monitor and control RPV water level.

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, Rev. O APPENDIX A Rev. O j Mississippi Power & Light Company- Grand Gulf Nuclear Station Page__ 6 _ of _45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION RC/L-l Confirm init.ation of any of the following: RC/L-1 Initiate each of the following which should have initiated but did noti wording change for o isolation clarif scation.

o ECCS o isolation (o Emergency diesel generator) o ECC5 o Emergency diesel generator Imtiate any of these which should have initiated but did not.

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' PSTG GUIDE Rev. O APPENDIN A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page '7 _ of _45 F

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If while executing the following step: If while executine the following step:

EP.H is & kvel/

o Baron Injection is required, enter (procedure developed from o Ibron injection is required or boron has been CONTINGENCY #7), injected into the RPV, enter EP.14 aruf exit Gr i o RPV water level cannot be determined. RPY FLOODING 15 RFQUIRED; ~

enter (procedure developed from CONTINGENCY #6). o sur zat on is -

PPV water level cannot be determined. RPV formed in preparation FLOODING 15 RE01 fir"D enter EP-12 and cult for RPV Flooding o R PV Flooding is required, enter (procedure developed from RCll.

CONTINGENCY #6).

o RPV Flooding is require f, enter EP.12 and cult RPV Flooding will be performed (EP.I3) when RC/L the Emertency Depres-surization procedure (EP.12) as completed.

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PSTG GutDE e Rev. O APPE NDIN A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 8 of_45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUID LINE DEVIATION / JUSTIFICATION I

a. Levels +18.4 in and RC/L-2 Restore and maintain RPV water level between (+12 79 RC/L-2 Restore and maintain RPV water level #9 +53.5 in from Tech.

6n. How level scram setpoint)) and (+33 in. thigh #10 between +11.4 inches and +33.5 inches Spec. Table 2.2.5-1 level trip setpoint)) with one or more of the #10

1. 18 with one or more of the following All followin6 systems: systems b. HPCI is not ins talled at Grand Gulf o Condensate /feedwater system (!!!0 - O psig (RPV o Condensate /feedwater system pressure range for system operation))

o CRD system o CRD system (1110 - O psig (RPV pressure range fer system operation)) o RCIC System #12 o RCIC system (1810 - 30 psig (RPV pressure #12 o HPC5 System range for system operation)) ,

o LPCS System o HPCI system (1810 - 100 psig (RPV pressure range for system operation)) i o LPCI System o HPC5 system (1810 - O psig (RPV possure range for f system operation))

o LPCS system (425 - O psig (RPV presare range for system opera tion))

o LPCI (250 - O psig (RPY pressure range for system opera tson))

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.crtNOlx A Rev. 1 Mississippi Pow::r & Light C:mpany- Crrnd Gulf Nucirar Str. tion Page 9 of 45 '

BWR OWNERS GROUP- EMERGENCY PROCEDURE CUfDELINE ,

GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEylATION/ JUSTIFICATION '

31 Hl'v mater > vel cannot be restored and maintain-d above f.12 m. (in level scram s-tpoint)). mamtain RPV water level Il RPV water level cannot he restored and above (-164 an. (top of active fuel)). mantained above +ll.a nches, a maintain RPV water level above -167 enches. a. Level ell.4 from Tech. Spec. Table 2.2.1 -1 I

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Res. 1 Mississippi Pow:r & Light Ccmpany- Grand Gulf Nuclear Ststion Page _10 of _iS_ j BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE ff HPV water level can he maintained above (-864 en.(top of DEVIATION / JUSTIFICATION active fisel)) and the AD% temer has inituted, prevent auto- If RPV water level can he maintained above matre RPV depressoraration by resertsng the ADS timer. -167 inches and the A95 timer has initiated, prevent automatic RPV denress erization by rewsting the ADS timer.

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.<w. 1 Misrissippi Powar & Light C:mpany- Grand Gulf Nucl~ar Stati:n Page 11 of _4 5_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDE'lNE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If fil'V mater level carwet he enamtamed above ( l(4 in.(top cl acteve f..< th, cr.tcr (nr wces.ere riavekww-rf from CONilNGENCY P fl. If I?i'V main 1. v l c.unwst he enant.sened above

.l67 inches, enter EP.ll.

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< PSTG GUIDE e Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 12 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION

!! Alternate Shutdown Cooling is s equired, enter (procedure developed from CONTINGENCY #3). a. Alternate shutdown cooling will be adtfressed in ONEP 05-1-02-311-1 (inade.

quate decay heat re-moval) and entered from 101-4 Plant itestoration l'ro-cedure.

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. PSTG GUIDE

+ Rev. O APPEND 8x A Rev. O

! Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 14 of _4_5_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/JUSTIFICf. TION i

RC/P Monitor and control RPV pressure. RC/P Monitor and control RPV pressure.

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, R ev. O APPENDIX A Rev. O

, Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 15 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION It while executing the following steps: If while executing the following steps: a. Use of bypass valves o Emergency RPV Depressurization is anticipated, rapidly #13 for depressurization depressurize the RPV with the main turbine bypass valves. o where boron injection Emergency RPV Depressurization is anticipated is required is un-and Boron Injection is not required. #13 o Emergency RPV Depressurization or RPV Flooding is required and rapidly depressurize the RPV with the main acceptable since the less than (1 (number of SRVs dedicated to ADS)) 5RVs are open, twbane bypass valveh use of minunum . niter-enter (procedure developed from CONTINGENCY #2). nate floodmg pressures

' o may be required. Timse o RPV Floodsng is required and at least (7 (number of SRVs Emergency RPV Depressurization is required pressures are based enter EP-t 2.

dedicated to ADS)) 5RVs are open, enter (procedure developed on SRV flow and are from CONTINGENCY #O. o RPV Flooding is required enter EP-12 in therefore invahd preparation for RPV Floo.fing. with any tiow through the bypass valves.

, b. At Grand Gulf the 1 Emergency Depressuri.

zation Procedure is perlormed prior to

p entry into the RPV Flouchna; Prucedure.

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P5TG GulLE Rev. O APPENOtX A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 16 of 45 I BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNt::AL GUIDELINE DEVIATION / JUSTIFICATION RC/P-1 11 any SRV is cycling, initiate IC and manually open SRVE R C/P.! If any SRV is cycling, verify operation of SRV until RPV pressure drops to (931 psig (RPV pressure at a. IC is not applacable j which all turbine bypass valves are fully open)). Lo-Lo set and manually lower RPV pressure to to Grand Gulf.

900 psig w

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+ APPDeDIN A Rev. O Alcciccippi Power & Light Company- Grand Gulf Nuclear Station Page 17 of 45 JR CWNERS GROUP - EMERGENCY PROCEDURE GUIDELINE GGNS - PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 11 while executmg the following steps It while executing the following steps

1. 8 o suppression pool temperature cannot be #3 o Suppression pool temperat se cannot be maintained below maintained below the Heat Capacity #13 the Heat Capacity Temperature Limit, maintain RPY #13

1. 14 Temperature Limit, maintain RPV pressure #14 pressure below the Limit.

below the Limit.

o Suppression pool water level cannot be maintained #11

1. 16 o suppression pool water level cannot be f13 below the Suppression Pool Load Limit, maintain RPV #I4 maintained below iSe Suppression Pool pressure below the Limit. Load Limit, maintain RPV pressure below o Steam Cooling is required, enter @ocedwe developed from the Limit.

CONTINGENCY #3). 5 team Cooling is required, enter EP.II.

o At 5tep LR-31

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PSTG GUIDE

, R ev. O

< APPErdDix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page .18 of _45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/ JUSTIFICATION The main condenser vacuum is maintained to allow the condenser to be utilized as a heat sink, l

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, Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 19_~of _45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If while executing the following steps: It while executing the following steps o Baron injection is required, and o Boron injectioa is required, and o The main condenser is avaltable, and o The main condenser is available, and o There has been no indication of gross fuel f ailure or steam line o There has been no indication of gross fuel failure break, or steam line break, open M51Vs to re-establish the main condenser as a heat #16 open M51Vs to re-establish the main condenser sank. #16 as a heat sink 1

Il PSTG GulDE

. Rev. O APPENO4M A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_20._of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION RC/P.2 Control RPV pressure below (It,M psig (lowest SRV fit **

lifting pressure)) with the main t..ine bypass valves. R C/P.2 Control ftPV pressure below 1013 psig *P*y*f*f*y'*

with the main turbine bypass valves. fit 4

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new. o APPENDtX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 21 of 45 '

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION RPV pressure control may be augmented by one or more of the following systems: RPV pressure control may be aurmented by one or more of the **

following systems: i[" talled o IC o SRVs only when suppression pool water level is above 6.5 ft. b.

o SRVs only when suppression pool water level is above If the continuous SRV pneJmatic supply is #15 at a .

1. 15 (4 ft.9 in.(elevation of top of SRV discharge devre)). If or becomes unavailable, place the control switch for each $RY in CLO5F position. c. Loss of the continuous the continuous SRV pneumatic supply is or becomes unavailable.

depressurize with sustained SRV opening. #12 SRV mmatic wpply o DCIC limits the nunber of

.o HPCI times the SRV can be I!? o RWCU (recirculation modt) if no boron has been injected into I

, p D'

• feas t 51 Y s closed to conserve o (Other steam driven equipment) o Main steam line drains N ** F"

o o * ###.'E'"Y RWCU (recirculation mode)If no boron has been Injected RWCU (blow <fown mode) If no boron has been in}ceted into the I' into the RPV. P PV. Refer to sampling procedures prior to initiating blowdown. g((,,'

'y*,

O Main steam line drains o FFPT4 d. RHR steam condensing o mode is not currently RWCU (blowdown mode) If no boron has been iniected into the o 53Ars p RPV. Refer to (sampling procedures) prior to initiating I " " '

r blowdown. nd (iu I

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PSTG GUIDE Rev. O APPENDIM A Rev. O

.i Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _22 of_d5_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If while executing the following steps the reactor is not shutdown.

return to (Step PC/P-2) This step is addressed in 101-4 Plant Restoration Procedure.

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EV'F OV*l1ERI GR3J~ - EVERGENCY ?930EOURE GUIDE !NE l GGNe o_Ak EDE:::'t; TE;MNi r., gut 3E;tyg t 57 r;, /e . tv  ; m.: l ggg ;g-.3 *gt.e ;t i- ;)g

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, . ,73 3 (7t*, nounds ("ot: 5 rst3ou n Soron R esent)1 of bo on have hace pir- tad snto tne RPV. or s

o teor. Pro:coart.

7"2.496 lbs. o' horor, have baer. mk:tec' into tn- RPY, o-e o TneRV, reacto as snu:down and no boron has been inrartee rite The reactor to- into the RPV, is shierdown eid no bo on has been inn :ted denressurae the RV and maintain cooldown rate exit EP-2 and enter IO!-4  ?

beine (100*r/hr (RPV conidown rate LCO)).

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PST; GUIDE

, Rev. O APPEt4 Dix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 24 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION RC/P4 When the RHR shutdown cooling interlocks clear. 818 initiate tie shutdown Cooling mode of RHR. This step is addressed In 1014 Plant Restore-i tion Procedure.

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, Res. O APPEN0lx A Res. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page__25_ of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE

! DEVI ATION/ JUSTIFICATION If the RHR shutdown cooling mode cannot be established and further cooldown is required, continue to cool down using one This step is addressed or more of the systems used for depressurization. in 1014 Plant Restora-tion Procedure.

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PSTG GUIDE a , Rev. O APPENotX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 26_ of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If RPV cooldown is required but cannot be accomptlAed and a!! This step is addressed control rods are inserted beyond position (06 (maximum suberitical is 1014 Plant Restora-J banked withdrawal position)) ALTERNATE $HUTDOWN COOLING 15 REQUIRED: tion Procedure.

enter (procedure developed from CONTINCENCY #3).

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i PSTG GulDE Rev. O APPENDIX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 27 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION i

1 This step is addreswd j in 1014 Plant Restora-j RC/P-3 Proceed to cold shutdown in accordance with (procedure for * *

cooldown conditions).

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OC/Q Monitor and control reactor power. RC/Q Monitor and control reactor power, 1

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PSTG GUIDE Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 29_ of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEvlATION/ JUSTIFICATION It while cuecutmg the folkmmg steps If while executing the following steps:

o

4. All actions that A!! control rods are inserted beyond position (06 (maximum sub. o normally would be critical banked withdrawal position)), terminate boron injection All control rods are inserted to or beyond position 02 performed M the and enter (scram procedure). terminate boron injectinn and crit RC/O.

Scram Procedure o are performed in The reactor is shutdown and no boron has been injected into the o RC/L and RC/P once RPV, enter (scram procedurel The reactor is shutdown ind no boron has been injected into the RPY, exit RC/O- this procedure is entered.

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PSTG GutDE Rew. O APPENDIX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 30 of _45_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE a

DEVI ATION/ JUSTIFICATION I

, RC/Q-4 (Confirm or place the reactor mode switch in SHUTDOWN.) RC/Q-1 Confirm or place the reactor mode switch Iri 5HUTDOWN.

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. APPENDem A Res. O Ml2:Issippi Power & Light Company- Grand Gulf NuclearStation Page 31 of 45 SWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION j RC/Q-2 If the main turbane-generator is on-Isne (and the MSIVs are RC/Q-2 If the main turbine-generator is on-line, confirm l open), contarm or inatiate recirculatson flow runback to or initiate recirculation pumps shif t to the LFMG.

The term "on-line" l

at Grand Gulf implies I

that the M51V's are j open and the main

> turbine gererrator is capable of con.

tinuing operation.

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, R ev. O APPENDIX A Rev. O l Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_32_ of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 4

RC/Q-3 ff reactor power is above (3% (APRM downscale tripl) or RC/Q-3 11 reactor power is above 4% or cannot be a. 4% from Tech. Spec.

cannot be determaned, trip the recirculation pumps. determined, trip the recirculation pumps. Table 3.3.6-2 1

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• Rev. O APPENDtx A Rev. O

! Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 33_ of 45_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION trecute (Steps RC/Q-4 and RC/Q-5) concwrently. Execute steps RC/Q-4 and RC/Q-5 concwrently, i

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l

) RC/Q-4 !! the reactor cannot be shutdown before suppression #19 RC/Q-4 If the reactor cannot be shutdown before suppression a. Il0*F from Tech. Spec.

j pool temperatwe reaches (I10*F (Boron injecten Initiation pool temperature reaches I10*F #19 3.6.3. 8

) Temperature 4 BORON INJECTION IS REQUIRED; insect boron BORON INJECTION IS IIEQUIRED inject boro.i into

into the RPV with $LC and prevent automatic initiation of the RPV with SLC and prevent automatic snitiation AD5 of ADS.

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BWR OWNERS GROUP- EhlERGENCY PROCEDURE GUIDELINE t GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE It hewne. carwet he arue-ted = sth 5LC. mp et twee. ente, the If borewi r cnnt he enFrted wit's SLC,ineret DEvit. TION [ JUSTIFICATIO -

Rl'Y hy swer or enort- of the lotinwmc alterrute rosathcarts:

lHwcru ento the RPY tw sme or m3re of the following CRD a wt 4:4 Ctl are alw systems chosen at Oranaf e CRD afternate mettuwtst e Hf'C5 Cull to be utilared for e RECU o CRD alternate boron injec tion.

e Teed ater o R F Ctt e HPCI o 0414I.Pil.1 fSection 6.1) Condensate Refueling and Transfer

• o RCIC System e Hydro rump t

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, , Rev. O APPENDtX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 36 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVlATION/ JUSTIFICATION l

l RC/Q-4.1 It boren is not beang bjected into the RPV by RWCU, RC/Q-4.3 If baron is not being injected into the

] cantarm utomatac isolation of or manually isolate R WCU. RPV by R WCU, confirm automatic isolation of or a

manually isolate R'WCU.

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, , n ew. o APPEND 0M A Rev. O j Mississippi Power & Light Company- Grand Gulf Nuclear Station Page__37 of 45 j O BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE

, GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION

! R C/Q-4.2 Continue to inWt boron until(250 pounds (Coki Shutdown 1 R C/O-4.2 Continue to inject horon until 782.496 pounds of Baron Height)) of baron have been inrected into the RPV.

t boron have been iniacted into the PPV.

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, How 0 APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 38 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION RC/Q-4.3 Enter (scraan procedure).

R C/Q-4.3 Enit RC/Q a. The operator will remmitt in thas procedure (sections RC/L, RC/P) to periorer. the snene actions that would be rcegesercel its tln* .e F.sm Pt N53*8 '-

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P3TG GutDE P'E NDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_39 of 45 BWR OWNERS GROUP- EMERGENCY PPOCEDURE GUIDELINE GGNS- PLANT SOECIFIC TECHNICAL GUIDELINE DEVIATION [JUSTlFICATION RC/Q-3 inwrt control rods as follows: RC/Q-5 inwrt control rods as follown I

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• L o*E NDt1 6 Ae>. 1 Missitsippi Power & Light Company- Grand Gulf Nuclerr Station .

Page_40 of 45 BWR OWNERS GROUP - EMERGEN0Y PROCEDURE GUIDELINE GGNS ptANT SPECIFIC TECHNICAL GUIDELINE R CAL 5.8 ft am s ram salve es not opem DEVIATIONj' JUSTIFICATION l DC/O-5.1 61 a*w s ram valve is not open:

o Remove: a. A step bv step pro-o T b enare: 7e the scram solenoids 03-1-EP-10 (Reactivity cedure will be pro-Controll veded in accomplish Hii-P609 C 71 -F l 8 A.E.C.C these tasks.

Hil-P611 C71-F18M,F D.H o

Isolate and vent the scram air header 05-1-EP-10 (Reactivity Controp b. A step by step (fuses which de+nergue RPS scram solenoids)).

restoration pro.

o Clow(Cll-F093 (scram air header sunoly valvell and Then control rods are not movin; inward; restore systems to cedure will be pro-nor mal, vided, open (ClI-F003 (scram air header vent valvell.

W hen controt rods are not moving; inward:

o (Replace:

Hil-PO9 C71-F18 A.E.C.C Hil-P6Il C71-Fl8B.F,D,H (fases which de+nergire RPS scram solenoids)).

o Close (Cil-F009 (scram air header vent valve)) and open (CII-F093 (scram air header supoly valvell.

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, Res . O APPEN0tX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 40 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION RC/Q-3.1 If any scram valve is not open:

R C/Q-3.1 if any scram valve is not opens a. A t y st o Removes o De-energize the scram solenoids (plant specific vided to accoenplish procedure) these tasks.

Hil-P609 C7 8-Fl8A.E.C.C Hil-P6tl C78-F l 88,F,D,H o Isola nd went the scram air header (plant specific b. A step tep (fuses which de-energize RP5 scram solenoids)).

cedise will be pro-o Close (Cil-F093 (scram air header supply valve)) and When control rods are not moving inward; restore systems to vided.

normal.

open (CII-F003 (scram air header vent valve)).

When control rods are not moving inwards o (Replaces '

H!l-P609 C78-F18A,E.C.C Hll-P611 C71-F188,F,D,H p (fuses which de-energize RPS seram solenoids)).

o Close (Cil-F008 (scram air header vent valve)) and open (Cl1-F093 (scram an header supply valvell, U

PSTG GUIDE

, R ev . O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 41 of _45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDEL.INE DEVIATION / JUSTIFICATION R C/Q-5.2 Reset the reactor scram. RC/Q-3.2 Rewt the reactor scram,

a. ICal-F034 found on if the reactor scrarte cannot be rewet P & ID M-10810, if the reactor scram cannot be reset: Rev.I4

1. Start all CRD pumps. I. Start all CR D pumps if no CRD pump can be started, continue in this if no CRD pump can be started, continue procedure at (Step RC/Q-3.6.tk in th.s procedure at Step RC/Q.5,6.1.

2. Close (Cil-F034 (HCU accumulator charging water 2. Close ICI1.F034 header valve)k

3. Rapidly insert control rods manually until

3. Rapidly insert control rods manually until the #2C the reactor scram can be reset. # 20 reactor scram can be reset.

4. Reset the reacter scram.

4. Reset the reactor scram.

3. Open ICll-F034.

5. Open (Clif034 (HCU accumulator charging mater header valve)L f

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R ev. O APPENDlX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 42 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE ~ GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION ~/ JUSTIFICATION RC/Q-5.3 If the scram dascharge volume vent and drain valves are RC/Q-5.3 Drain the scram disch rge volume and a. Wording change for open, instaate a manual reactor scram. initsate a manual reactor scram, clarification

t.  !! control rods moved inward, return to Otep RC/Q-3.2L f. It control rods moved inward, return to Step RC/Q-5.2

2. Reset the reactor scram.

2. Reset the re. actor scram.

If the reactor scram cannot be reset, continue in this procedure at Step RC/Q-3.3.tk if the reactor scram cannot be reset, continue in this procedure at Step RC/Q-3.5.1.

3. Open the scram discharge volume vent and drain valves.

3. Open the scram discharge volume vent and drain valves.

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PS TG GO'OE Rew. O APPENDIN A Rew. O Mississippi Power & Light Company- Grand Gulf NuclearStation b Page 43 of 45 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION RC/Q-3.4 bdividually open the scram test switches for control R C/O-5.4 twisvidually open the scram test switches rods not inserted beyond position (06 (manimum sub-critical barked withdrawal position)). for control rods not inserted to or bevond position.

When a control rod is not moving inward, close its scram test switch. when a control rod is not moving inward, close Its scram test s nitch.

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PSTG GulDE e R ew. Q APPENOax A Res. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 44 of _4_5_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION RC/Q.3.3 Reset the reac. tor scram. RC/Q.3.3 Rewt the reactor scram, s. ICll-F034 found on P & ID M.108ID, Rev, Ie it the reactor scram cannot be resets  !! the reactor scram cannot be resets I. Start all CRD pumps. I. $rart all CR D pumps.

If no CRD pump can be started, continue in this if no CRD puenp can be started, continue in this procedure at (Step RC/Q-3.6.1). psacedure at Step RC/Q-5.6.I.

2. Close (CIll.F034 (HCU accumulator charging water 2. C ese Cil-F034.

header valve)).

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Page 45 of _45 -

BWR (7NNERS GROUP- EMERGENCY PROCEDURE GUIDE *.INE b ftC/O.' .6 ft.medh mwrt control rods nianialty until 11 GGNS - PLANT SPECIFIC TECHNICAL GulDEl.lNE DEVIATION /JUSTIFICATIDN 729 R C.IO-5.6 control rods are mer ted S-voruf riosetson (06 (mameism. sub- Ranediv enwr control rods manually until cratscal banked withdrasal positionll. all rentrol rods are inserted to or bevond a. ICII.FIO2 Foutui on rmuten 02 P A in W 8038ti, lies.It F20 If anv control rod cannot be inserted bevond riosatum (06 Imansmum subcratical banked withdrawalf *nsitinnth If any enntrot rod evmot be inserted to or beyond positmn 02

l. Individually drect the effksent from (Cil-Fl02 (CRD withdraw hne vent valve)) to a contamei radwaste l.

Individually direct the effluent from ICll.FIO2 drain and open (Cl1.Flo? (CRD withdraw imr vent valvel) to a contained radwaste drain and ooen for each controf rod not inserted beyond positson (% I Cll-F102 fv cach (manamum suheritical banked withdrawal positson)l. beyond position 02 conerof rod not inserted to or '

2, then a controf rod is not moving inward, close its 2.

(Cil-F102 (CRD withdraw Inne vent valve)). When a control rod is not rnoving inward, close Its Cll-FIO2.

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BWR OWNERS GROllP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION PRIM ARY CONTAINMENT CONTROL CUIDELINE

_ PRIM ARY CONTAINVENT MNTPOL CtilnFLINE a. 93'F from Tech. Spec.

Entry Condit g Entry conditlans 34.3.1

.l The entry conditions for this guideline are any of the following: b. 133'F from Tech. Spec.

The entry conditions for thle e11deline are any of 34.24 o the followines Suppressen pool te mperature above (95'F (most limiting suppressiisa pool te mperature LCO))

o Suppression pool temperat sre mbove 9FF

c. 900F from Tech. Spec.

34.1J o Drywell temperatse above (1330F (drywell temperature LCO or o Drywell temperature above 135'F manimum normal operating temperature, whichever is higher)) d. 1.23 from Tech. Spec.

Table 2.2.1 1 1 o Containrrent tentperature above (90*F(containment temperature LCO)) e. Suppression pool o Drywell pres sure above 1.23 psig levels from Tech.

o Drywellyessur e above (2.0 psig (high drywell pressure scram setpomen o Suppression pool water levtl above 18.81 ft.

o Suptwession poil water level above (12 f t. 6 in,(maximum o Suppression pool water levtl below 18.% ft.

suppression post water level LCO))

o Sup >ression poal water level below (12 f t. 2 in. (minimum p sup wession p.>ol water level LCO))

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PSTO GUIDE R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _ 2 of 48 i

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION OPER ATOR ACTIONS OPER ATOR ACTIONS Irrespective of the entry condition, execute (Steps SP/T, DW/T, CN/T, PC/P, and SP/O concurrently. irrespective of the entry condition, execute Steps SP/T, DW/T, CN/T, PC/P, arwt SP/L, concirrentiv.

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PSTG G JtLE Rev. O APPENWX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station of 48 r EWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE Page __ 3 GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SP/T Monitor and control suppression pool temperature. SP/T Monitor and control suppression pool temperature.

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• APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 4 of 48 r BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SP2CIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SP/T-1 Close all SORVs. SP/T-1 Close all 50RV5. a. 103*F limitation added If any 50RV cannot be c20 sed (within 2 m nutes (operational to conform to Tech.

plant-specils time interval)), scram the reactor.

if any SORY cannot be closed within 2 minutes or suppression Spec. 3A2.5 pool temperature is 103*F or greater, scram the reactor.

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• STG GUCE h ev. O ADPENDIK A Rev. O Mississippl Power & Light Company- Grand Gulf Nu:: lear Station Page 5 of _48__

[ BV/R OVINERS GROUP- EMERGIN0Y PROCEDURE GUIDELINE GGN5- PLANT 3DE0lFIO TE':HNIOAL GUIDELINE DEVIATION / JUSTIFICATION 3

Sp/T-2 When suppression pool temperatwe exceeds (93*F #18 (most limiting suppression pool temperature LCO)). SP/T.2 When suppression pool temperatwe exceeds #18 a. 93*F from TecA W operate available suppression pool cooling. 91'F, operate available suppression pool cooling. 3*'* 3* I l

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PSTG GutDE Rev. O APPEN0lx A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page .6_ of 48-F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 5P/T-3 Betore suppression pool temperature reaches (t10'F (Boron SP/T. Before suppresdon pool temperature reaches 110*F Insection instiation Temperature)), scram the reactor. a. Ilo*F frorn Tech. Spec. 3.6.3.1 scram the reactor.

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Page -7 _ of .48.

P BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Maintain suppression pool temperature below 120'F.

a. This step was added If suppression pool temperature can be maintained below 120'F.

to give the operator return suppression pool temperature to below 93*F some directen once the temperature rise If suppression pool temperature cannot be maintained below 120*F, is under control.

depressurize the reactor.

b. 120'F is fomd in Tech. Spec. 3.6.3.1.

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PSTG GUIDE

' Rev. O APPENOlx A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _-8 of 48 BWR OWNERS GROUI - EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SP/T-4 If suppression puoi temperatwe cannot be #8 SP/T.4 If suppression pool temperature cannot be #8 maintained below the Heat Capacity Temperature f13 Limst, maintaan RPV pressure below the Limit. maintained below the Heat Capacity #13

1. I4 Temperatwe Limit, maintain RPV pressure #14 below the Limit t

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• R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Sta'tlon Page 9 = of 48

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNI::AL GUIDELINE DEVIATION / JUSTIFICATION 11 suppression pool temperature and RPY pressure cannot be restored If suppression pool temperature and RPV pressure cannct be main

• and maintamed beisw the Heat capacity Temperature Limit, EMERGENCY tained below the Heat Capacity Temperature Limit EMFRGENCY a. "Res tored" is deleted R PV DLPRES$URIZATION 15 REQUIRED: enter (procedure developed from from this step because RPV DEPRE55URIZATION 15 REQUIRED

• its use implees that the RPV Control Guideline) at (Step RC-1) and execute it concur-rently math this procedwe. encerdang the HCTL is acceptable.

b. RPV Control Guide-lane is deleted be.

cause the operator is directed directly to the Emergency Depressuriza tion Procedure.

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' Rev. O APPENOlk A Rev. O

,O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 10 of 48 -

l BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION DW/T Monitor and control drywell temperature. Dw/T Monitor and control $rywell temperature b

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' R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 11 of A _8

'F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION I

DW/T.1 Dhen drywell temperature exceeds (133'F (drywell temp- DW/T-1 When drywell temperature exceeds 133*F a. 133*F from Tech.

erature LCO or manimum normal operating #6 5pec. 3.6.2.6.

temperature, whichever is fugher)), operate available operate available drywell cooling #6 drywell coohng, s

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE l DEVIATION / JUSTIFICATION Execute (Steps DW/T-2 and DW/T-3) concurrently. Execute Steps DW/T-2 and DW/T-3 concurrently.

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PSTG GUID E Rev. O APPENOtx A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page _13 _ of A8_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION Dw/T-2 11 drywell temperature (near the cold reference leg instru.

ment vertical runs) reaches the RPY Saturation Temperature, DW/T-2 If drywell temperature near the cold reference leg a. When conditions esist RPV FLOODING 15 REQUIRED; enter (procedure developed from Instrument vertical runs reaches the RPV Saturation that warrant RPV flood.

the RPV Control Guidelsne) at (5tep RC-1) and esecute it Temperature, RPV FLOODING IS REQUIREDs ing, the operator wall concurrently with this procedure. be directed to the Flooding Procedure from the Emergency Depres-surization Procedure.

Entry anto the RPV control 6uidelsne as therefore not necessary.

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l PSTG Gul0E 9 Rev. O APPENOtX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page -14 of 48

'F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE 1

DEVIATION / JUSTIFICATION DJ/T.) Before drywell temperature reaches (140*F (maulmum #II a. This step is deleted temperature at which ADS qualified or drywell design since drywell spray temperature, whichewer is lower)) but only if (suppression is not installed at chamber temperature and drywell pressure are below the Grand Gulf.

Drywell Spray Initiation Pressure Limit),(shut down recirculatoon pumps and drywell cooling fans and) initiate drywell sprays (restricting flow rate to less than 720 gpm (Maximum Drywell Spray Flow Rate Limit)).

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PSTG GUIDE Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 15 of AB_

r BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 11 drywell temperature cannot be maintained below (340'F (m.nimum teenperature at which AD5 qualified or drywell design temperature, if drywell temperature cannot be maintained below 3N'F, a. At Grand Gutt the whnhever is lower)), EMERGENCY RPV DEPRE55URIZATION 15 REQUIRED: EMERGENCY RPV DEPREMURIZATION IS REQUIRED: enter EP-12 Emergency Depres.

and execute it concurrently with this procedure, surizatioei Procedure enter (procedure developed from the RPV Control Guideline) at (Step RC-1) and execute it concwrently with this procedure. is entered directly when required without first performing tie RPV Control Prut edure.

b. 330'F is the Drywell Design Ternperature found in FSAR Table 6.2- 1.

POTG GulDE

! e hev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 16_ of .4_8__

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CN/T Monitor and control cositainment temperature. CN/T Monitor and control containtrent temperature.

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R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 17 of _18_

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 1

1 CN/T.! when containment temperature exceeds (90'F (contain- #6 CN/T-1 When containment temperature exceeds 90*F, operate a. 90'F from Tech. Spec, ment temperature LCO)), operate available containment available containment cooling. 3.6. 8.8.

cooling.

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APPENDtX A Rev. O l Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 18_ of 48_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE i

DEVIATION / JUSTIFICATION If while executing the followbg steps containment soray a. lhis step was added has been intilated, before containment pressure drops below O psig, terminate containment spray. to ensure tiut con-tainment spray was l termmated prior to exceeding the contain-rnent design negative pressure.

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POTG GulDE hev. O APPEraDtx A Rev. O Mississippi Power & Light Company- Grant: Gulf Nucisar Station Page 19 of _!8_.

I l awn owwzes snou=- mzasze::V ano:zounz sumzunz l sces- PLANT s=I:i=i: TI:Hisi:t.L suto:urs l ozviATiots/JucTi=i:niot: !

CN/T-2 Before containment temperature reaches (t 850F (con- #18 CN/T-2 14efore containment temperature reaches 1850F but only tamment design temperaturr)) but only if (suppression if containment pressure is above Containment #18

a. At Crand Culf contain.

chamber pressure a,s above ,l.7 psig (Mark Ill Containment Spray initiation Curve, initiate containment sprays. ment spray is utilised Spray Initiation Pressure Lamit), initiate suppression Instead of suppression PNI Sprays. pool spray whsch is not installed.

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b. 1850F from FSAR Table 6.2-1.

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' h ev. O APPENDIX A Rev O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _20 of 48 F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CN/T-3 11 containment temperature cannot be maintained below CN/T-3 If containment temperature cannot be maintained a. At Grand Gulf ee (183*F)(containment design temperature)), EMERGENCY below 183'F, EMERGENCY DEPRE55URIZATION 15 'nef8 N Y Pres-R PV DEPHE550RIZATION IS REQUIR ED: enter (procedure developed REQUIRED; enter EP-12 and execute it concurrently surization Procedure from the RPV Control Guidelme) at (Step RC-l) and execute with this procedure.

at concurrently with this procedure, '[" d ' C'ff,,

,, gg,

b. 183*F froen F5AR T able 6.2 1.

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Fier. O ADFIf;DtX .*.

Rev. O M! sissin?! Powe- E '_iph'. Com; any- Gran:'. GuK hiu::isa: Station Pags_21_ o.- 48 I . Dvtr; ors!rn: accu =- n::ac::::; or:a: cun curezurs:

l sse: ,_ c.

_ ar:7 suz:i=l: T :m:::e_ cur:: _ti!  : :.svit.Tsor:/au:; s=i:t.Ti: i-CN/T-4 If containment tempera.ure (near the cold reference leg instrument vertical runs) reaches the RPV Saturation This step is deleted due to Temperature. RPV FLOODING 15 REQUIRED. containment design tempera-

, ture being 1850F and is be-low the lowest point of con.

' 'cern (2120F) on the RPV

I saturation curve, therefore.

' the step is not reached as

! ,1850F is limiting.

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APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 22_ of 48-P BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELlhE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATs ON/ JUSTIFICATION PC/P Monitor and control primary containment pressure. PC/P Monitor and control primary containment pressure, e

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PSTG GUIDE Rn. O APPENDIM A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_22 of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JusTIF8 CATION PC/P-1 Operate (the following systems, as required:

o a) Grand Gulf is not Containment pressure control systems. Use containment equipped with con-

! Pressure control system operating procedure.) tainment pressure control systems.

(o) SBGT (and drywell purge), only when the temperature in

, the space being evacuated is below (212*F (Maximum b) 5GTS and drywell 1 Noncondensible Evacuation Temperature)). Use #2 purge cannot be used (SBGT and drywell purge operating procedures), at Grand Gulf to con.

i trol primary contain.

ment pressure, e

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PSTC GUIDE Rev. O APPENDIX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _24 of 48__

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION if while cuecuting the following steps containment 4 a. D.is step was added to spray has been initiated, before containment pressure drops i below 0 ps1.

R terminate contahment spray. ensure that containment spray was terminated prior to exceeding the contain.

ment design negative pressure.

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.a**EfvDit #1 nie. i Mississippi Power & Light Ccmpany- Grand Gulf Nucl:ar Station Page_25 of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE b P' /l'-2 t$alore wppressson ctumber preswre re.achas GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE f 5. (l5 PC/P-? DEVIATION / JUSTIFICATION l Ithe Preswre Suporession Pressure (I7J. puc (Suporesuon Itefore emtaennw nt preswre reaches Pressure 5uppression Chamber Spras initiation Pressure)). but rmk if (sun- l'ressure Curve but o nly il containment pressure is above presuon chamber pressure is above 1.7 psig Blark 111 Containment % pray Imtiation Curve emtiate containment Contaenment spray Initiation Pressure Limit))(suppres. spray

1. 8,#13,#21 soon pool mater level is t>alom 24 ft. f. an.(elevaterm of sierressian pool spray nozzles)), metiate suppression pool sprays.

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F BWR OWNERS GROUP- EMERGEt4CY PROCEDURE GUIDELINE GGNS- PLANT SotCIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION

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PC/P.3 If suppression chamber pressure exceeds (17.4 g33 psig (Suppression Chamber Spray Initiation Presswe)) but 4. This arep is deleted only it (suppression chamber temperature and drywell si.xe Grand Gullis pressure are below the Drywell Spray Initiation Pressure not equipped wi 5 Limit), (shut down recirculation pumps and drywell Drywell sprays, '

cooling f ans and) initiate drywell sprays (restricting flow rate to less than 720 gpm (Maximum Drywell Spray Flow Rate Limit)).

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' Rev. O APPENDtX A Ree. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_27 of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION PC/P4 !! suppression chamber pressure cannot be maintained below (the Pressure Suppression Pressure) EMERGENCY RPV PC/P4 ff containment pressure cannot be maintained below Pressure Suppression Tessure Curve, EMERGENCY RPV DEPRE55URIZATION 15 REQUIRED.

DEPRESSURIZATION t$ REOUIDEO.

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Rev. O t APPEN0tX A i Rev. O i Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _28_ of _4 I s l SWR OVINIF:3 GROUo- IMERGIFCY PRO IDURI GUIDILINI l GGNS- PLAlli SDI:l:lO TE Hill 0AL GUIDELINE I

l DIVIATIOt!/JUSTI:10ATION l

'C/P-1 If suppression chamber pressure cannot he maintained below  !

(the Primary Containment Desirn Pressure), RPV FLOOf) LNG PC/P-3 If containment press are cannot he maintained below t 5 psig. ,

15 RECtilRED. RPV FLOODING li '.COUIRED, l I

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUfDELINE DEVIATION /JUSTlFICATioN PC/P-6 If suppression chamber presmire cannot be maintained below PC/P-6 If containment pressurs cannot be maintained below 30 psig, the Primary Containment Pressure Limit, then irrespective of a) Suppression pool spray whether adequate core coolirt is assured: tlien irrespective of whether adequate core cooling is assurerf, and drywell spray are initiate containment spray. not installed at Grand o (If suppression pool water level is below 24 f t. 6 in. Gulf.

(elevation of suppression pool spray nozzles).) initiate suppression pool sprays. t o  !! (suppression chamber temperature and drywell pressure are ,

t below the Drywell Spray hitiation Pressure Limit),(shut down recirculation pumps and drywe!! cooling fans and) initiate drywell sprays (restricting flow rate to less than 720 gpm (Maximum Drywell 5 pray Flow Rate Limit)).

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE ,

L GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION [ JUSTIFICATION l'C/P-7 11 supprenson chamber pressure cureerts the l'rimary Contamment Pressure Lemet, vent the primary #22 PC/3'-7 11 rontamment pressure eseceds 10 psig, vent the primarv a) A step hv uan contamment m accordance with (procedure for cantamment m accordance with the #22 P'oredure well be contamnent venting) to reArc and nuntain pressure below proce<ture 05-%-Of-CP-3 (Section 3.1.6) to reduce and Proveded to address the Primary Contamment Pressure Limit. maintam pressure helnw 30 psig. CWd8""'ent wenteng.

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE  !

DEVIATION / JUSTIFICATION SP/L Monitor and control suppression pool water level. SP/L M=i'or and control suppression pool water level, e

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GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION !

imavenurm suppression pool mater levet LCC4) and SP/L.) Ab en ta m' P3. f 9 umnressinn tioot water level between 18.88 ft a) Suppression pool levets (12 ft. 2 m. (minm.um suppressum pool mater level LC01). and 13.% f t. Refer to samplant pro- #8 refer to(sampimg procedurelpreor to discharging water. reesrc 04.l.01.Pf l.? (CVD5 RFUEL STOR & #9 found m Tech. Spec. '

(Suppression pool maLeup may be augmented by spats). TRNVR W5) prior to discharging eater. Suppression 3.6.3.1.

pont makeup may be aun nent by SP%tu.

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, R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 34 of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAI. GUIDELINE DEVIATION / JUSTIFICATION f

I l If suppression pool water level cannot be maintained above (12 ft. If suppression pool water level cannot be maintained l 3 in. (minimum suppression pool water level LCO)) esecute (Step above 13.34 it. execute Step SP/L-2.

SP/L 2).

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APPENDIN A i Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 35 ofA8_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVI ATION/ JUSTIFICATION It suppression pool water level cannot be maintained below (12 f t. If suppression pool water level cannot he maintained 6 in.(maximum suppression pool water level LCO))(23 ft. 9 in. below 18.81 ft.,cuecute 5tv SP/L-3. a) 18.81 f t. founct in Tech. '

(SPMU initiation setpoint plus suppression pool water level i ,n- Spec. 3.6.3.I.

crease which results from SPMU operation))if SPMU has been 6nitiated), execute (Step SP/L-3).

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SP/L-2 SUPPRESSION POOL WATER LEVEL BELOW (I2 f t. 2 in. (minimum $P/L-2 SUPPRESSION POOL FATER LEVEL BELOW 18.34 f t. a) 18.34 f t. found in suppression pool water level LCO)). Tech. Spec. 3.6.3.1.

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Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 37 of 48 b BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE 3

GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION ,

Ma ta pression pool water level above the Heat Capacity Maintain suppression pool water level above the Heat Capacity Level Limit.

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FSTG GulDE Rev. O APPENDIX A I Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 38_ of 48  ;

BWR OWNERS GROUP- EMERGENCY PROCEDuitE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE  !

DEVI ATION/ JUSTIFICATION  !

Il suppression pool water level cannot be enaintained above the Heat il suppression pool water level cannot be maintained above the C.pacity Level Limit, EMERGENCY RPV DEPRE55URIZATION IS REQUIRED 3 Heat Capacity Level L6mit, EMERGENCY DEPRE55URIZATION is a) At Grand Gulf the enter Wocedwe developed from the RPV Control Guideline), at Emergency Depres-REQUIRED; enter EP-12 and execute it concurrently with this surization Procedure (Step RC-1) and esecute it concurrently with this procedure, procedure.

is evitered directly when conditions re-quare its use.

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, Rev. O APPEPdDtX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 39 of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION

• d SP/L.) SUPPRE5510N POOL WATER LEVEL ABOVE (12 ft. 6 in. (maximum suppression pool water level LCO))((23 f t. 9 in. (SPM5 SP/L.3 5UPPRESSION POOL WATER LEVEL ABOVE 18.31 ft. f,"c c]. 6. .I*

enatiation setpoint plus suppressaan pool water level increase which results from SPM5 operation))!! SPM5 has l been inst:ated).

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. Res. O APPENDIX A y Rev. O g Mississippi Power & Light Company- Grand Gulf NuclearStation Page 40 of _48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS-' PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/JUSTlFIC ATION Execute (Steps SP/L-3.1 and 5P/L-3.2) concurrently. Execute Steps SP/L-3.1 and SP/L.3.2 concurrently.

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PSTG GulDE h ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 41 of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 5P/L-3,8 Maintain suppression pool water level below the SP/L.3.1 Maintain suppression pool water level below the ,

j Suppression Pool Load Limit. Suppression Pool Load Limit. t 8

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, Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 42 of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 11 suppression pool water level cannot be maintained be- #I1 If suppression pool water level cannot be maintained below low the Suppression Pool Load Limit, maintain RPV #In the Suppression Pool Load Limit, maintain RPV pessure below the Limit. f13 pressure below the Limit. fit 4

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PSTG GulDE Rev. O APPENDfX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 43__ of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 11 suppressson pool water level and RPV pressure cannot be main- If suppression pool water level and RPV pressure cannot be oned below the Suppression Pool Load Limit but only if adequate maintained below the Suppresssion Pool Load Limit but only if core coolang is assured, terminate injection into the RPV from adequate core cooling is assured, terminate injection into sources externaf to the primary contaanment except from boron the RPV from sources external to the primary containment except cmjection systems and CRD. from baron injection systems and CRD.

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, Mississippi Power & Light Company- Grand Gulf NuclearStation Page 44 of _dB_  !

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEvlATION/ JUSTIFICATION It suppression pool water level and RPV pressure cannot be testored if suppression pool water level and R PV pressure cannot be and mamtained below the Suppression Pool Load famit Emergency RPV a) At Grand Gulf the restored and mastained below the Suppression Pool Load Limit. Emergency Depressur.

OLPRE550RIZAT10N 15 REQUIRED: enter (procedure developed from the RPV Control Guadehne) at (Step RC-1) and execute it concurrently EMERGENCY RPV DEPRE55URIZATION 15 REQUIRED: enter EP-12 iration Procedure is '

t and execute it concurrently with this procedure, entered directly with this procedwe, [

when condations re. .

quare its use.

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' Rev. O APPEND 1X A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station. Page__45 of 48 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SP/L-3.2 Before suppression pool water level reaches (17 f t. 2 in. SP/L.3.2 IVfore suppression pool water level reaches 84.73 ft (Maximum Primary Containment Water Level Limit or elevation of bottom of Mark Iinternal suppression but only if adeqwte core cooling is assured, chamber to drywell vacuum breakers less vacuum breaker terminate iniection into the RPV from sources openirig pressure in feet of water, whichever is lower)) external to the vimary containment except from boron injection systems and CRI).

but only if a:lequate core cooling is assured, terminate insection into the RPV from sources external to the primary containment except from boron injection systems and CRD.

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' Rev. O APPE N W M A ,

Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 46 of _48_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLAMT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION  !!

I

1. When suppression pool water level reaches (17 f t. #18 I 2 in. (elevation of bottom of Mark Iinternal suppression a) Grand Guli a.s not '

chamber to drywell vacuurn breakers less vacuum tweaker opening '9U PPed with dry- l pressure an fee of water)) but only it (suppression chamber **""'Y'"

I temperature and drywell presswe are below the Drywell Spray laatsation Pressure Limit),(shut down recirculation pumps and i drywell cooleng fans and) anstaate drywell sprays (restricting flow rate to less than 720 gpm (Masamurn Drywell Spray Flow Rate Limst)).

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,, APPENDIX A Re.. o i Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 47 of 48_ i p BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION

3. It suppression pool water level exceeds (17 ft. 2 in.

(elevatson of bottom of Mark I internal suppression #23 a) Grand Cu:f is not chamber to drywell vacuum breakers less vacuum breaker equipped with drywell Wang pressure in feet of water)). continue to operate g sprays, dry.ets sprays below 723 gym (Mausmum Drywell Spray Flow -

Rate Limit)).

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Mi;sissippi Power & Light Company- Grand Gulf Nucirr St: tion Page 48 of _48 BWR OWNERS GROUP - EMERGENCY PROCEDURE GUIDELINE 6 GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE 3.

Chen primary ccmtammt sater F vel re ches (l% ft.innumum DEVIATION / JUSTIFICATION Premary Contamment 4ater Level Ll r et)). termmate metion mto 1.

1rhen primary centainment water level reaches 34.75 ft.

the RPV from sources enternal to the prsmary contamment irrespecteve of shether adequate core coolmg is assured.

termmate intreten snto the IPV from sources caternal to the primary containment irrespective et whether adequate core cootmg is assured.

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Mis:inippi Power & Light Company- Grand Gulf Nucle r Strtion Page 1 of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE L GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEvlATION/ JUSTIFICATION SECOND AI'Y CONT \fNUCNT CONTirOL ClftDELINE

[ntry C=wfates 50CONnAI'Y eONT AINitCNT C 3NT'tOL r.:rintLINE Entry Conditions The entry comfations for this guidelene are anv of the following secondary contasnment condations:

The entry conditions for this guidtline are any of the following secondary contasnment condations e Dit!rrential pressure at or above 0 bi. of water ,

o Differential pressure at or above 0 in.cf water l, o An area temperature above the maximum normaloperatifg temperature o l

An area temperature temperature above t'ie maximum normaloperating e A HVAC cooler dif ferential temperature above the mavimum normal operating differential temperature o A HVAC cooler differentist temperature above the maximum normal operating dif ferential temperature e

A HV AC radiation operatang cuhaust level radiation level above the maximum normal o A HVAC exhaust radiatio,s le tel above the maximum normal operating radiation level e

An area radiation level above the maximum normal operating o radiation level An area level radiation radiation level above the maximum normal operating e A Floor drain sump water level above the maximum normal operating mater level o A finor drain sump water leval above the maximum normal operating water level e An area water level above the manimum normal operatir? water level o An area water level above th? maximum normal operating water level (Mauimum normal and maulmum safe tables start on next pageJ 3

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9 8*CidDet c Rev. 1 Mississippi Power & Light Company- Grand Gulf Nuclerr St tion -g Page _la_ of _19 BWR OWNERS GROUP- EMERGENCY PROCEDURE Gu1DELINE L GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVit. TION /JUSTlFICATION Wmbry Ccent emnent f.rmtrol Temperature klas Stau Room Normal Sale l

, L I A192 RilP A HX 'toem 105 F 135 F IA103 RHR A Pump Room ISO F 180 F 105 F 133 F IAl04 RCIC 150 F e

180 F '

los F 135 F 150 F 180 F I Al05 RHR D P.smp Room 103 F  !

133 F t

I Al06 RHR B ttX Room 150 F 180 F t 105 F 135 F .

I AIO9 HPCS ISO F 180 F 103 F- 135 F I All8 RHR C 150 F ISO F 105 F 135 F '

j I AII9 LPCS ISO F 330 p l 103 F 333 p  ;

I A207 EL SWCR Room ISO F 180 F I

104 F 134 F i I A208 EL SWCR Room 104 F 134 F I I A219 EL 5WGR Room 104 F I 134 F I A221 EL SWGR Room 104 F 134 F i I A101 Rtain Steam Tunnel 123 F 133 F b

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE L GGNS- PLANT SPECIFIC TECHNICA1. GulDELINE

~

D/ VIATION/JUSTlFICATION l kta Atas floom Normal Safe i AMS EL Pen Room 104 F  !)4 F '

I A109 EL Pee Room 104 F 134 F

• l All3 EL T'en Room 104 F 134 F I A120 EL Pen Room 104 F 134 F '

I A123 SCTS 103 F 133 F IA326 SGTS 103 F 133 F I A407 MCC Room lot F 134 F I A410 MCC Room 104 F 134 F Secondary Containment Control dadiation Room hiau Alan Normal Safe I A102 Ri1R A HX Room 13 mr/hr 100K rem /hr I AIO) RHR A Pump Room 30 mrAr 13 mr/hr 200K remAr t AIO4 RCIC 13 mr/hr 100K rem /hr 30 mr/hr

! AIDS RHR R Pump Room 13 mr/hr 100K rem /hr I A106 RHR B 30 mr/hr i

85 mr/hr 100K rem /hr I A105 Main Steam Tunnel 30 mr/hr i A323 SGTS 3,000 mr/hr 100K rem /hr l e I mr/hr IK rem /hr l

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SWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION l Secondary Containment Water Level Mat Man Rooni Normal Safe r I AID) RHR A Pump Room 3 9'-3* i 93'4' 1 AIDS RHR R Pump Room 3 9'-3* 93'4" IA104 BCIC 90'4* 93'4 ' '

I A109 HPCS 90'-6" 93'4 ' I 1 Al19 LPC5 90'4' 93'4 " I l Al13 RHR C 90'4' 93'4 " i l'

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' Rev. O APPENDIM A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation f, Page _ _ 2 of 19 .

BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDEUNE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Operator Actions Operator Actinns

a. 3.6 mr/hr and 30 mr/hr 11 while esecuttr; the following steps secondary containment HVAC are from Tech. Spec.

exhaust radiation level exceeds (20 mr/hr (secondary containment  !! while executing the followly steps fuel hantfling area exhaust Table 3.3.2-2 HVAC isolation setpoint)h radiation exceeds 3.6 enr/hr OR fuel handling area pool sweep exhaust radiation exceeds 30 mr/hr

b. The Fuel Handling e Confirm or manually initiate isolation of secondary containment Area, Auxiliary HV AC, and o Confirm or manually initiste isolation of the Fuel Handling Area, bildmg and Fuel Auxiliary Nilding Ventilation Systems and Fuel Handling Area Pool Handling Area Pool

'e Sweep Ventilation System.

Confirm initiation of or manually initiate 58CT(only when the Sweep Ventilation i space bemg evacuated is below 212'F). Systems are the sys.

o Confirm initiation of or manualty initiate SGT5 i

tems used to main-tain the Secondary Containment at a negative pressure

, during normal plant opera tions.

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, Rev. O APPE NDeX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page=3= of 19 b] BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELlHE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If while cuecuting the following steps: If while cuecuting the following Steps:

o Secondary containment HVAC isolates, and o Fuel Handling Are* Auuiliary Nilding and Fuel Handling Area o Pool Sweep Vents. aion % stems isolate and Secondary containment HVAC exhaust radiadon L.mel!s below (20 mr.'.ar (secondary containment HVAC isolation setpoint)), o Fuel Handling Area Erhaust fladiation levelis below 34 rnr/hr restar secondary containment HVAC and Fuel Handling Area Pool Sweep cuhaust radiation is below

1. 24 30 mr/hr restart pefuel Handling Area, Aviliary Nilding and Fuel Handline Area Pool Sweep Ventilation Systems. #24 4

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APPE PdDIN A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station d

Page -4 of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION /JUSTlFICATION trrespective of entry condition, esecute (5teps SC/T, SC/R, and SC/L) concurrently. krespective of the entry condition, esecute Steps SC/T, SC/R and SC/L concurrently.

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PSTG GUIDE Dev. O APPE NDt X A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _-5_ of 19 l

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SC/T Monitor and control secondary containment temperatwes. SC/T Monitor and control secondary containment temperatures, i

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SC/T-t Oprate available area coolers, g fy,g g,,, ,,,g,g C

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PS*G GUIDE R ev . O APFENDIN A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station O. Page -7 of 19_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SC/T-2 If secondary containment HVAC exhaust radiation level is be.

low (20 mrlhr (secondary containment HV AC isolation set- SC/T.2 If Fuel Hand!!nst area Exhaust Radiation levelis below point)), operate available secondary containment HVAC. 34 mr/hr and Fuel Handling Area Pool Sweep Exhaust Radiation is beksw 30 mr/br operate Refuel Handling Area, Auulliary Asikfing and fuel Handling Area Pool 5 vecp Ventilation Systems L

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PSTG GUIDE Rev. O APPCteOfM A Res. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 9 of 19-1 P

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SC/T-4 Il a primary system is discharging into an area, then before SC/T.4 If a primary system is discharging into an area, then any area temperature reaches ats manimum safe operating temp. before any area temperature reaches its maximum safe a) At Gram Gulf a crature, enter lprocedure developed from the RPV Centrol operating temperature, enter EP-I and execute it con- Separate scram Guidehne) at (5tep RC-1) and execute it concurrently with currently with this procedure. n this procedwe. ,{d ,

be entered in this situation anstead of the RPV Control Pro-Cedure.

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PS Ta GUIDE R ev. O APPENDIE A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 10_ of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SC/T-5 Il a primary system is discharging into an area and an area SC/T-3 11 a primary system Is discharging into an area and temperatwe exceeds its manmum safe operating temperatwe an area temperatwe exceeds it maximum safe operating in enore than one area, EMERGENCY RPV DEPRE55URIZATION temperatwe in more than one area, EMERGENCY 15 REQUIRED. DEPRE55URIZ ATION 15 REQUIRED.

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PSTG GulDE APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 41 of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SC/R Monskor a.aJ contret secondary containment radiation levels.

SC/R Monitor and control secondary containment radiation levels, e

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PSTG GulCE Rev. O APPENOlX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 12 of 19 BWR OWNERS GRCUP- EMIRGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION SC/R-1 If,any area radiation level exceeds it maximum normal SC/R.I If any area radiation level exceeds Lts maulmum operating radiation level, isolate all systems that are normal operating radiation level, isolate all systems dischargmg onto the area except systems required to shut. that are v.scharging into the area except systems required down the reactor, assure adequate core coohng, or suppress to shut down the reactor, assure adequate core cooling, or a working tare. suppress a working fire.

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j PSTG GUIDE

Feev. O APPENDtX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _13 of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION SC/R-2 If a primary system is discharging into an area, then before SC/R-2 If a primary system is discharging into an area, then before a) At Grand Gulf a any area radiation level reaches its maximum safe operating any area radiation level reaches kts maximum safe operating radiation level, enter (procedure developed from the RPV separate SCitAM Control Guideline) at (5tep RC-l) and execute it concurrently radsation level, enter EP-1 and execute it concurrently with Procedure has been this procedure. developed and is with this procedure, entered at this time iristead of the RPV Control Procedure, s

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b Page 14 of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION SC/R-3 If a primary system is discharging into an area and an area SC/R-3 If a primary system is discharging into an area and an area radiatuxs level exceeds its maximum safe operating radiation levelin more than one area, EMERGENCY RPV DEPRE55URIZATION radiation level exceeds its maximum safe operating 15 REQUIRED. radiation levelin more than one area, EMERGENCY RPV DEPRE55URIZATION 15 REQUIRED.

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h ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_15_ of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION SC/L Monitor and control secondary containment water levels.

SC/L Monitor and contro? ncondary containment water levels.

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PSTG GUIDL H ev. O APPENDtx A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _16_ of 19 '

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SC/L-l if any fluor drain sump or area water level is above its man- SC/L.I !! any floor drain sump or area water level is above its 1

imum normal operating water level, operate available sump maximum normal operating water level, operate available pumps to restore and maintain it below its manimum normal sump pumps to restore and maintain it below its maximum operatang water level, normal operating water level.

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PSTG GutDE Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page -17 of 19 r BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Il any floor drain sump or area water level cannot be restored and if any floor drain sump or area water levelcannot be restored maintained below its maximum normal operating water level, isolate and maintained below its maximum normal operating water level, all systems that are discharging water into the sump or area except isolate all systems that are discharging water into the sump

' systems requared to shut down the reactor, assure adequate core or area except systems required to shut down the reactor, cooli.ig, or suppress a working fre.

assure adequate core coohng, or suppress a working fire.

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PSTG GUIDE

' Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_18_ of __19_

i Fv e BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEylATION/ JUSTIFICATION SC/L-2 li a primary system is discharging into an area, then before any floor drain sump or area water level reaches its maulmum SC/L.2 If a primary system is discharging into an area, then ") AI Of*"d b"II

• safe operating water level, enter (procedure developed from before any floor drain sump or area water level reaches Separate krarn h the RPV Control Guideline) at (Step RC-1) and en rute it its maximum safe operating water level, enter EP-1 and cedure has been concurrently with this procedure. execute it concurrently with this procedure.

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v ev. O APPENDER A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_19_of 19 T')

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION SC/L-) If a primary system is discharging into an area and a floor SC/L.) !! a primary system is discharging into an area and a floor drain sump of area water level exceeds its maximum safe drain Sump or area water level exceeds its maximum safe operating water level in more than one area, EMERGENCY operating water level in more thr.n one area, EMERCENCY RPV DEPRE55URIZATION 15 REQUIRED. DEPRE550RIZATION 15 REQUIRED.

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, PSTG GUIDE R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 1 of 3 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEYlATION/ JUSTIFICATION RADIOACTIVITY RELEASE CONTROL GUIDELINE

_p ADIOACTIVITY PFL E ASE C 3NTROt. Cliff 1FLivF Entry Conditions Entry Conditions The entry condition for this guideline is:

The entry condition for this guideline ist o OfIsite radioactivity release rate above O Cl/sec (release rate which requires an Alert) o of fsite radioactivity release rate above 0.571 mr/hr at the Site Boundary.

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. PSTG GUIDE Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _ 2 of 3 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Operator Actions Operator Actions RR-l isolate all primary systems that are discharging into R R.I Isolate all primary systerns that are discharting into areas areas outside the primary and secondary containments except systems required to assure adequate core cooling outside the primsry and secondary containments eteect or shut down the reactor. systems required to assure ademsate core cooling or shut down the reactor.

R R-2 Operate Feedwater and M51V Leakare Control Systems as needed.

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i PSTG GUIDE Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_G o f __3____

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUfDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION R R-2 11 of filte radioactivity release rate approaches or exceeds R R-3 If offsite radicactivity release rate approaches or (91 Ci/sec (release rate which requires a General Emergency)) a) At Grand Gulf, the and a primary system is discharging into an area outside the exceeds the offsite release rate which requires a General primary and secondary containments, EMERGENCY R PV DEPREb Emergency and a primarv system is discharring into an area Emergency Depressuri-SURIZATION 15 REOUIRED: enter (procedure devekred from outside the primar r and secondary containments, ration Procedure is the RPV Control Guideline) at (Step RC-l) and execute it EMFRCENCY RPY DFPREMURIZATION 15 REDIHRFDt entered without tra-concurrently with this procedure, enter EP-12 and execute it concurrently with this versing through the or redure, RPV retrol lYocedure.

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e o::: aa fiev. O APPE tJ DIE A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 1 of 24 P 6 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CONTINGENCY di Level Restoration a) To maximize injection Level Restoration flow, Emergency If while executing the following stepse Depressurization if while executine the following steps: is performed prior o Baron injection is required, enter (procedure ileveloped from to RPV Flooding.

o noron injection is required or boron has been injected into CONTINGENCY #7). the RPV, enter EP.I4 o RPV water level cannot be determined, RPV FLOODING IS o RPV water level cannot be determined. R PV FLOOfilNG f5 HEQUlitED; enter (procedure developed from CONTINGENCY #6).

REOIflRED: enter EP.1211 preparation for RPV Finorfing o RPV Flooding is required, enter (procedure developed fr3m o PPV Finortsnr is required, anter FP l? in preparation for CONTINGENCY #6). RPV Flooding.

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PTTG GuiOE h ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page___2_ of _24 F

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELIN8E DEVIATION / JUSTIFICATION C l.1 Initiate IC.

a) This step is deleted because an IC is not installed at Grand Gulf.

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' feev. O APPEt4Dik A Rev, O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page ___3 of 24 P

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINL GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Cl-2 Line up for injection and start pumps in 2 or more of the Cl-2 Line up for injection and start pumps in 2 or more of the a) Grand Gulf has only oew followinh wbsystems: following injection subsystems: LPC5 pump installed.

o Condensate o Condensate o HPCS o HPCS o LPCI-A o L PCI- A o L PCI-B o LI'Cl-D o LPCI-C o LPCI C o LPC5-A o LPC5 o LPC5-B t

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p;tG GulLE R ev. O APP E NDIX A Rev. O Mississipp! Power & Light Company- Grand Gulf Nuclear Station Page 4 of 24_

P BWR OWNERS GROUP- EMERGENCY PROCEDURE GulCELINE GGNS- PLANT SPECIFIC TECHNICAL GUICELINE DEVIATION / JUSTIFICATION If less than 2 of the injection subsystems can be lined up, commence if less than 2 of the injectio1 sihsystems can he lined laning up as many of the following alternate injection subsystems as a) At this time Grand possibles up, commence lining up as many of the following alternate Gulf is a single injection subsystems as possihIer unit; therefore, o ItHR service water crosstle interconnections o Fire system o RHR service water crosstie with otter units o Fi.e system o hterconnections with other units was deleted.

o ECCS keep-full systems o ECC5 keep-futt systems o SLC(test tank) o SLC (test tank) o %LC (bornn tank) o SLC (boron tarA)

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P.13 CUIDE kes O Ac ENDix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_5 of_24 D '

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGN3- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/ JUSTIFICATION Cl .3 Monitor RPV pressse and water level. Continue an this Cl.3 Yonitor RPV prasswe and water level. Continue in this a) 40 psig from Tech.

procedure at the step indicated in the following table. procedure at the step indicated in the following table. Spec. Table 3.3.2.2 RPV PRESSURE REGION RPV PPESSIIRE REGION b) 289 psig from FSAR (425 psig)I (100 psig)2 289 60 osig HIGH INTERMEDIATE LOW HIGH INTE R MEDI ATE Lnw INCREASING CIA Cl.3 Cl4 INCR E A%ING Cl4 Cf.5 (*I .(.

DECREA5ING Cl .7 C18 DECR E A%ING C 8.7 C l .t I (RPV pressure at which LPCS shutof f her.d is reached) e .

2 (HPCI or PCIC low pressure isolation setpoint, whichever is higher)

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P *, T G GUIDE h ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 6 of 24 P

BWR OWNERS GROUF- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION l

If shik esecuting the following steps: It while executing the following steps: a) -150.3 from Tech.

o Spec. Table 3.3.3-2 The RPV water level trend reverses of ItPV pressure changes o The RPV water level trend reverses or RPV pressure region, return to (Step Cl-3). changes region, return to Step Cl-3.

o R PV water level drc,ps below (-l% in. (ADS initiation setpoint)), o RPV water level drops beton -150.3 inches prevent automatic prevent autornatic initiation of ADS. initiation of ADS.

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PSTG guide R ev. O APPENDtX A Rev. O D Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 7 of_24 BWR OWNERS GROUP - EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/ JUSTIFICATION C l-4 RPV W ATER LEVEL INCREASING, RPV PRES 5URE HIGH C l.4 RPV WATER LEVEL INCREA5tNG, RPV PRES 5URE HIGH Enter (procedure developed from the RPV Control Guidelme) Enter EP-2 at Step RC/L.

at (Step RC/L).

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' PSTG GUIDE Rev. O APPENDIX A Rev. O F Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 8 of_24 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEvl ATION/ JUSTIFICATION Cl-5 RPV W ATER LEVEL INCREA5lNG, RPV PRES 5URE INTERMEDI ATE Cl-5 RPV WATER LEVEL INCREASING, RPV PRE 55URg INTERMEDIATE a) HPCIis not installed at Grand Gulf II HPCI and RCIC are not available and RPV pressure is increasmg, EMERGENCY RPV DEPRE55URl:ATION 15 REQUIRED.

5 hen HPV pressure is decreasing, enter (procedure developed If RCIC is not available and RPY pressure is increasing, fran the RPV Control Guidelme) at (Step RC/L). EMERGENCY RPV DEPRE55URIZATION IS REQUIRED.

When RPV pressure is decreasing, enter EP-2 at Step RC/L.

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• =,TG OusD; 9 h e, O APPENDIE A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 9 of 24 F

BWR OWNERS GROUP- EMCRGENCY PROCEDURE GUIDELINE GGNS- PLANT SDECIFIC TECHNICAL GUIDELINE 4

DEVIATION / JUSTIFICATION af HPCI and RCIC are not available and RPY pressure is not a) HPCI is not installed j increasing, enter Qrocedure developed froen the RPV Control Guide- il RCIC is not available and RPV pressure is not increasing, enter EP-2 at Step RC/L. at Grand Gulf.

Ime) at Step RC/L).

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S'- 0 CU:LE Sem e, ApcEt40tx A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 10 of_23_

P BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Otherwiw, when R PV water level reaches (+12 in. (Iow level scram setpoent)), er *er (procedure developed from the RPV Control Guideline) at (5tep RC/L). a) The operator is per-mitted to exit this procedure prfor to RPV level being

/ raised to the scram setpoint because when EP-2 is entered, direction is given to raiw level to the normal range.

Therefore this step is deleted.

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PSTG GutDE h ev 0 APPENDIX A Res. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 11 of _23_

C BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Cl4 RPV W ATI'R LEVEL INCREASING, RPV PRESSURE LOW Cl-( RPY WATER LEVEL IN"REASING, RPV PRESSURE LOW 1

If RPV pres.sure is increasing, EMERGENCY RPV DEPRE55URl:ATioN 15 REQUIRED. then RPV pressure is decreasing, enter If pressure is increasing, EMERGENCY RPY (procedure developed frorn the RPV Control Guideline) at DEPRE55URIZATION 15 REQUIRED. When RPV pressure is (5tep RC/L) decreasing, enter EP-2 at Step RC/L.

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• APPENCth A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 12 of 24 F

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATI ON/ JUSTIFICATION Otherwise, enter (procedure developed from the RPV Control Guide- Otherwise, enter EP 2 at Step RC/L.

Isne) at (Step RC/L).

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PSTG CulDL

• Rev. O AoPENDtX A Rev. O Mississippi Power & Lig'1 Company- Grand Gulf Nuclear Station Page 13_ of _24 F

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGMS- PLANT S=ECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Cl-F RPV WATER LEVEL DECREASING, RPV PRE 55URE HIGH OR Cl-7 RPV WATER LEVEL DECREASING,RPV PRE 55URE HIGH a) HPCI is not installed INTERMEDIATE . OR INTERMEDIATE at Grand Gulf.

11 HPCI or RCIC is not operating, restarI whichever  !! CRD or RCIC is not operating, restart whichever is not b) CRD is a source of is not operating. opera ting. hg essure fore, should be consadcred.

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• TTG Gut D E h ev . O APPENOtx A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 14 of _24__

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT S*ECIFIC TECHNICAL GUIDELINE I

DEVIATION / JUSTIFICATION 18 no insection subsystem is lined up for insection with at least if no injection subsystem is lined up for injection with at one pump running, start pumps in alternate insection subsystems least one pump running, start pumps in alternate injection ehsde are lined up for enjection. subsysteins ubich are hned up for injection, e

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-.o s'Cr4Diz a nes. 1 Mississippi Pow r & Light Cempany- Gr:nd Gulf NucI::rStctisn Page _15_ of _21.

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE L GGNS- PLANT SPECIFIC TECHNICAt. GUIDELINE DEvlATION/ JUSTIFICATION t hews PPV mater lavel strnns to (-144 m.f arm of active fuell):

Whewi ItPV water level drons to -167 inches: 3I '

• e 11 no system inrection subsystem or alternate injection sub-o k

svstam is kned up with at least one pump running. STE AM if no system, inject en subsystem or alternate injection sub-COOLING 85 REQUlitED. Ehen any svstem. inrection s.6wstem wstem is lined up with at least one pump running STE AM or alternate intaction M/1 system is isnad up wqth at least COOLING 15. REOtflRED. E'sen any system,inrection sghsystem one pump runnina,. return to 15tep Cl-31. or alternate iryectirtn subsyst?m is lined up with at least one pump runnine,, return to Step Cl-3 .

o Otherwise. EMERGENCY RPV DEPRES5URCATION 15 REQUIRED. When o RPV water level is increasing or RPV pressure drops below (100 Otherwise. EMERGENCY RPV DEPRE550Rf2ATION IS psig OlPCI or RCIC low pressure isolation serpoint, whichever REQUIRED. When RPV water levelis increasing or RPV ,

is higher)), return to (step Cl-31. pressure drops below 60 psig return to Step Cl.). e L

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' PSTG GutDE R*v. O APPENDtM A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station r Page 16 of 24__

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If while executing the following s'eps Emergency RPV Depressuriza-tion as requred or any system, injection subsystem or alternate g gg, ,, g, g,,

iniection subsystem is laned up for infection with at least one I

• pump running, enter EP-12. .)

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PSTG GUIDE E ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 17 of_2_4_

P BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/JUSTIFICA flON Then RPV water level drons to -276.56 inches or if DPV a) This step is from water level Cannot be determinwl, open one SRV.

Contingency 83 (Steam Cooling) e e

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PSTG GUIDE R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 18 _ of _24 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION ,

Then RPV pressure drops below 700 psig, enter EP-12. 8) NS Step is from Contingency 83 (5 team Cooling)

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P3TG GulDE R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 19_ of _23_

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Cl-8 RPV W ATER LEVEL DECREASING, RPV PRESSURE LOW C l-8 RPV WATER LEVEL DICREA5lNG, RPV PRES $URE LOW (11 no HPC5 or LPC5 subsystem is operating,) star pumps in alternate entection subsystems which are lined up for If no HPCS or LPCS su5 system is operating, start pumps in injec tson. alternate enjection subs; stems which are hned up for injec tion.

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{ Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 20 of 24 I BWR OWNERS GROUP- EMERGENCY PROdEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDEl.lNE DEVIATION / JUSTIFICATION i

If RPV pressure is increasing, EMERGENCY RPV DEPRE55URl:ATION If RPV pressure is increasing, EMERGENCY RPV 15 REQUIRED.

DEPRE550RIZATION 85 REQUIRED.

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".es 1 Mississippi Power & Light C:mpany- Grand Gulf Nucl ar Station Page _21_ of _24 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE Ehce. I:IT mater level drops to (-164 n. f tco of a-teve fuel)). DEVIATION / JUSTIFICATION enter (procedure deveinred from CONTINGENCY N. Elm ItPV water Feel drops to -867 inches, enter EP-12 and cuecute "' 'T '

concurrentiv.

','{* ,, "'g h irrorporated here.

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, h ev. O J.pPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 22 of 24 =

DWR OWNEPS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLAPIT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION Operate HPC% and LPC% mAsystems with suction from a) This step was step C4-2 the suppression pool. (Core Coohng without Level Restoration) e 1

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• n ew. O APPEt: DIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 23 of 24_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL. GUIDELINE DEVIATION / JUSTIFICATION There at least one core spray subsystem is operating with suction a) 128 psig from FSAR fr3m the suppres; ion pool and RPV pressure is below 128 psle. Table 6.3-8.

terminate iniectinr. Into the RPV from sources enternal to the primary containment, eveept lRft b) CRD flow is small and should be main-tained for possible rod insertx>n efforts.

c) This step is step C4-2 from Core Coot.ng without Leve! Restoration.

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. set 1 Mississippi Power & Light Compcny- Grcnd Gulf Nuclur Stati:n i Pag 2. 24 ef 24 l BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE b GGNS- PLANT SPE0lFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION <

5Phen RPY water levelis restored to -I67 whes. enter EP-2 at ten RC/L. a) Thn step es step 04-) from Core Cooling without Level Restoration.

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PSTG GulDE

• R ev. O APPErdDix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station '

W BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE Page 1 of 7 GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION

• CONTINCENrY #2 Emerrency RPV nenressurization This procedure may be entered with the reactor stilleritical. Since if the reactor is not scramme 1, manually scram, enter depressurization would EP.1 and execute concurrentir, be very dif ficult with the reactor still at power, the operator is instructed to scram the reactor.

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, Rev. O APPENOlx A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 2 of 7 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGHS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CONTINGENCY #2 Emergency RPV (Wpressurization C3-1 When either: #13.#14 C21 Men eithers #11,#1e o Ibron Injection is required and all injection into the o Ibron injection is required and all in}ection H PV except from boron injection systems and CR!1 has been terminated and prevented, or into the RPV eece1t from boron inicetion systems and CRD has been terminated and prevented, or o Ibron Injection is not required n Ibron InHetion is wt requirect f

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f4ev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station r Page 3 of 7 BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C2-I.I initiate IC.

a) This step is deleted since Gr.snd Gull is rut equspped with an J IC.

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Eev 0 AF F Er.Dik A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 4 of_ 7 BWR OWlJERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELilJE DEVIATION / JUSTIFICATION C2 1.2 If wppression pool water levet is above (4 ft. 9 in. C2 1.2 (elevaren of top of SRV discharge devecelh If sunnression onni watar level is above 6.5 f t. a) 8 SRVs are dedicated to An$ at Grand Guit.

o Open att ADS valves. , pp,, ,gg gng ,,,,,,,

o If any ADS valve cannot be opened, open other SRVs until o if any ADS valve rannnt be onened, onen other SRVs (7 (nurnber of SRVs dedicated to ADS)) valves are open. until 8 valves are onen, e

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A ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 5 of 7 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE

• GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVI ATIONfJUSTIFICATION C2-1.3 11 less than O (Minimum Number of SRVs Required for C2-1.3 If less than 3 SRVs are open and RPV pressure is at Emergemy Depressurization)) 5R Vs are open (and RPV #22 #22 pressure is at least 30 psig (Manimum SRV Re-openinr, least 0 psig aftove cretainment pressure, rapidly a) liPC1 and IC are not

• Pressure) above suppression chamber pressure), rapWy depressurire the RPV ming one or more of the installed at Grand depressurize the RPV using one or more of the following following systems use in order which wijg Gutt.

systems (use in order which will minimize radioactive minimise radsoactive release to the environments release to the environment): b) RiiR steain condens.ing o \tain condemer is not currently o Main condenser o prPTs i

o tremed f.w use o ItHR (steam condensing mode) ttain steam line drains at Grand Gulf.

o (Other steam driven epipment) o $1Ars o Mam steam Inne drains o PCIC steam line o ifPCI steam lane o ifcad vent o RCIC steam line o Itcad vent j o IC tube sade vent e

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Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 6 of 7 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE i DEVI ATI ON/ JUSTIFICATION If RPV Flooding is required, enter (procedure developed from If RPV Flooding is required, enter EP.13.

CONTINGENCY H).

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PSTG guide PE OtX A Res. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 7 of 7 BWR OWNERS GROUP- EMERGENOY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION C2-2 Enter (procedure developed from the RPV Control Guideline) at C2-2 Enter EP-2 at Stei RC/P-1 a) RC/P-4 is covered (Step RC/P-4).

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Rev 0 APPENCIX A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page _2 F of a BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTIFfCATION If while cueruting the following steps Emergency RPV Deprewri. a) Tius step is inchaded zation is required or any system, injection subsystem,or alternate in EP.II (Level ingection subs

• stem is lined up for injection with at least one Restwation),

pump running, enter (procedure developed from CONTINGENCY #2),

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Rev. O APPENDtX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station P Page _3 of 4 BWR OWNERS GROUP- EMERGENCY P ROCEDURE GUIDELINE GGilS- P'. ANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION It IC cannot be initiated:

a) M IC is not muaWd When RPV water level drops to (-272 in.(Minimum Zero-Injection at Grand Gulf.

RPV water Leve 0) or if RPY mater level c.arnot be determined, open b) This step is included meSRV.

b EP-Il hvd Restora tion).

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Rev 0 APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 4 of 4 P

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION When RPV pressure drops below (700 psig (Mirimum Single SRV Steam Cooling Pressure)), enter (procedure develope 1 from CONTINGENCY #2). a) This step is included i

in EP-il (Level Restoration).

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' Rev. O APPENDtX A Rew. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 1 of 5

-F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CONTINGENCY M This step is celeted Core CoolmR Wsthout Level Restoration '

due to concurrent execution of CP-12 C4-1 Open all ADS valvet. pl3 (RPV Emergency Depreswriza ion).

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,m new. O AFPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station F Page ___2 _ of _5_

BWR OWNERS GROUP- EMERGENCY PROCE3URE GUIDELINE GGNS PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If any ADS valve cannot be opened, open other SRVs antil(7 (number of SRVs dedicated to ADM) valves are open, a) This step is deleted due to concurrent execution of EP.!2 (RPV Emergency De-pressurization).

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8v ev. O APPENDIX 4 Rev. O F Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 3 of 5 BWR OWNERS GROUP - EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAI. GUIDELINE DEVIATION / JUSTIFICATION C4-2 Operata Iff'C5 arut .PCS sukystems with suction .? vei the suppressson pool.

2) This step is in-cluded an EP-3I (Level Resforation).

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A P', T G GUIDE R ev. O j APPEN0ix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 4 of 5 t

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION then at least one core spray subsystem is operating with suction from the suppressun pool and RPV pressure is below 010 psig (RPV a) This step is in-pressure for rated LPC5 or HPCS, whichever pressure is lower)), ciuded in EP-II terminate intection into the RPV from sources enternal to the (Level Restoration).

primary containment.

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R ee- O APPENDin A Rev. O F Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 5 of=_5 BWR OWNERS GROUP- EMERGENCY PROCEDURE GutDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C4.) When RPV water level is restored to (-164 in. (top of active fue0), enter (procedure developed from the RPV Control a) Ns step is b Guideline) at (5tep RC/L).

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~ ~' ""'"'"#"" ' ' " ' ' " " as "sLis pro cu re w iii .e incorporated sn .sn Jal'.

C3-1 Imtlate suppression poolcooling.

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l. FEY N0lu a Rev 0 Mississippi Power & Light Company- Grand Gulf Nuclear Station P Page_2_ cf 11 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C5-2 Close the (RPV head vents), MSIVs main steam line drain valves, and HPCI and RCIC isolation valves. C3 2 Clow the RPV head vents, M51Vs main steam line drain valves, and RCIC isolation valves. a) HPCI is not hstalled at Grand Gulf.

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'f APPENots A Res O Mississippi Power & Light Cornpany- Grand Gulf Nuclear Station P Page __.3 of 11 BWR OWNERS GROUP- EMERGENCY PRDCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C3-3 Place the control switch for (one (Manimurn Number of SRVs C3 3 Place the control switch for Required for Alternate Shutdown Coolina)) SRV(s)in the OPEN positson. 5RVs in the OPEN position.

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Rev. O Mississippi Power & Light Company- Grand Gulf NuClearSlatIOn Page 4 of 11 C BWR OWNERS GRCUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT :PECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C3-4 Slowly raise RPV water level to establish a flow path through C3e Slowly raise RPV water level to establish a flow the open SRV back to the suppression pool. path through the open SRV back to the suppresssion pool.

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• PSTG Gs .C E Rev. O APPENDIX A Rev. O Mississippi Power & Light Corsaany- Grand Gulf Nuclear Station C Page _ 5 _ of 11 BWP OWNERS GROUP- EMERGENCY PFOCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUICELINE DE'/lATION/ JUSTIFICATION C5.5 5:are one LPC5 nr LPCI pin) watti suctson froen the c5.5 St irt .w= '.PCS or '. Sri pumn wit's a setion fa 3m tv en.

suppression pool, pression r>nnt and secure all other injection excent CRD. 3J C suppression pool level from contenuously rising.

b) CRD flow is not secured because it may be needed for rod inserteon etforts.

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, PSTG GL.;i R ev. O APPENDIE A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page __ 6 of 11

' I BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE .

GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CS4 Sb tv increase LPC5 or LPCI enrection into the R PV to the ma um.em.

C5-6 hly increase LP ice f.Prline ction inn the "PV to the mani'num.

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Ree. C Mississippi Power & Light Corrpany- Grand Gulf Nuclear Station Page 7 of_11.

BWR OWNERS GROUS- EMERGENCY Pt0CEDURE GutDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDILINE DEVIATION /JUSTlF!Ct. TION .

C3-4.8 If NPV presswe h s not statnl.se at least (94 pse l

('twwman Atternate %tdoen Cooteng NPY preww-il above C34.1 If RPY prestre dnes wt sta5ilire .it least 44.11 asi? a5nwe l suppressson chamber pressure, start another LPC5.w LPCI cnntairunent presswe, start another LPC5 or LVI nurm, pump.

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• PSTG G J. C R ew. O APPENClX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 8 of 11 F

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PL TNT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION C5-6.2 If HPV pressse does not stabitare below (5 72 psig (muimism c.1 4.2 If 9PV veterre does ent stabiliza heb* 202 osi*,nnen Alterrute %urdown cooling RPV Pressure)) open another SRV. another ERV.

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apFENtex A Rtw. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 9 of 11 I ( BWR OWNERS GROUP- EMERGENW PROCIDuf?E SUIDELINE GG*lS- PLANT SPECIFIC TECHNICAL GUf0ELINE DEVI ATION/JUSTIFIC.tTION C3-6.3 It the roothmn rate enceeds (8 )PI'/hr (enaui men P

'V cool. 1-4.1 If the real4own rate ewreeds e9er jse,, car. t r*M or down rate LCOl),redace LPCS or LPCIinprction into the PPV LPCIinjection into the 4 f* emtil the cooldown rate

,0 3 fi n4' treen Tech, gn c.

until the cooldown rate decreaws below (1000 F/hr (marimum 3.4.6. l .

1. 9erreases below I00*"/hr or RPY pressure decreases to RPV cookfown rate LCOB)(or RPV pressure decreases to withwi within 0 psig af co stainment pressure, whichever occurs M pshg (Umireuen SRV Rem Pressure) of suppressinn first.

chamber pressure, whschever occurs f asth

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B'*tR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C3 7 Control suppresson pool trnocratwe to maintain RPV water Cb7 Conernt wenressinn pnit temnerature to me intain tempera ture above (70*F ti;PY NDTT or head tensioneng limit. RPY water temneratur t above 73T.

,) 7)or fro n Tech.

whschever as higher)L g 3,g,3, l

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s = .: .:. x s,.. a Mississippi Power & Light Company- Grand Gulf NuclearStation Page _11__ of 11 C BWR OWNERS GROUP - EMERGENCY 'ROCEDURE GUIDELINE GGNS PLANT SPECIFIC TECHNICAL GUIDELINE DEvt ATIOr */JUSTIFICATIOra C 3-3 BYorced to cold shutdown in accordance with (prot edire fu ri-t Prcreed to rnH Vmed)wn in accordance wit 5 Pf 1 cooldown to cold shutdown conditions).

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CONTINCENCy #6

_CONTfvCENcY #4 a) IC, HPCI and motor driven W1't Fkwxime RPV FlWM feedpumps are not in-(6-I If at least (1(Minimum Number of SRVs Required for C61 If at least 1 %RVs can he opened or if HPCS is available for stalled at Grand Gulf.

Emergency ITepressurizat.on)) SRVs can be opened or it iniection,close the M%IVs, main steam line drain valves, HPCS or motor drsven feedwater pumps are available for and RCIC. b) HHR ste-am condensing is snpection, close the MSIVs, enain steam Ime draan valves. not currently licensed IC. HPCI. RCIC and RHR steam condensing isolation valves. for use at Grand Gulf.

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, E ev. D APPErsDix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 2 of 20 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTIFICATloN CM If any control rod as not inserted beyond position (M C6 2 (mauemum suberitacal barned withdrawal positeordh If any control rod is not inserved to or beyorwt position 02 a) Slight wording change for clarity e

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, Rev. O APPE W'fx A Ree. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 3 of 20 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C6-2.1 Termmate and prevent all biection bte the RPV except from C6-2-1 Terminate and prevent all injection into the RPV baron msection systems and CRD until RPV pressure is below escept from boron iniecteon systems and CRD until the Mnemuen Afternate RPV Flooding Pressse. RPV presusre is below the Meimum Alternate RPV Flooding Pressure.

Mmimum Alternate RPV Number of open SRVs Floodeg Pres ure (psiK)

Minimum Afternate RPV Number of open SRVs Flooding Pressure (psig) 7 or more ISS 6 151 3 98 1 221 a

? Ilt 231 6 3 835 331 3 2 165 535 4 209 3 233 2 431 3 874 r

PSTG GUIDE

• R ev . O APPEr4 DIM A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 4 of _2_Q_

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS - Pt. ANT SPECIFIC TECHNICAL GUIDELINE DEvlATION/ JUSTIFICATION

!! less than (2 (minimum rusmber of SRVs for which the Minimum 18 at least i 5RV cannot te opewd, continue in this procedure.

Alternate RPV Floodang Pressure is below the lowest SRV litt'q Slight wordsng change pressare)) 5RVs can be opened, continue in this pracake. for chrity, e

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• Rev. O APPENDIX A Rew. O

, Mississippi Power & Light Company- Grand Gulf NuclearStation Page __ 5_ of _2O

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT S*ECl:lC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If shale cuecuting the following step, RPV water level can he If while cuccuting the followW st9 '?PV water levelcan he determsned and RPV Floodeng is not required, enter (procedure determined and RPV Flonding is not reepsired, enter EP-14 and a) RC/P-4 is addressed droeloped from CONTINGENCY #U and (praredure developed from the in Plant Restoration.

RPV Control Custeline) at (Step RC/P-4) and esecute thew EP-2 at Sten RC/P.) an<f esecute these crocedures concurrenttv.

peoredures rancurrently.

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) Mississippi Power & Light Company- Grand Gulf NuclearStation '

Page 6 _ of _2O_

O SWR OWNERS group- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C6 2.2 C_.--- e and slowly increase iniection into the RPV #23 1 2.7 Commence and slowly increaw injet? ion into the with the fallowsng systems untal at least (2 (minsmum i

number of SRVs for whsch the afinimum Alternate RPV RPY with the followant srstems untilat least I SRV is open and RPV presusre is above #73 Fanodmg Pressure is below the lowest SRV liftsag pressse)) SRVs are open and R PV presusre is above the winimum Alternate PPV Flwwfmt Prestsret the ntanamum Alternate RPV Flandsng Pressures g gg gg g g o Condensate %vstem o Llotor driven feedwater pumps

• o CRI)

" P"*PS b) The systems listed

• for use here inject outsede the shroud.

LPCIat Grand Gulf injects inside the shroud.

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' R ev. O APPE NDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 7- of_20 BWR OWt3ERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If at kast (2 (mwumum number of 5RVs for which the Maimum If at kast I %PY is nat armi er RPV presore cannot he in-Alternate RPV Flooding Prestre is below the lowest SRV liftwig creased to above the Heimum Alternate RPY Floorfing Pressure, pressurel) 5RVs are not open or R PV presore cannot he increased commence arvt sinwk increaw inpectinn inta the RPV with the to above the um mum Alternate RPV Flooding Presusre,etwnmence folleming systems amtil at least I %RY is opers anaf RPY nres. N N II*' O'8 and sloely sncreaw anpectaan into t*ic R"Y with the followrig are is above the 'tiniemem %! ternate tt*V Flooding Presseret A'af is a one unit systems until at least f 2 imensmum msmher of SRVs for which the facahtya therefore, Mwumum Alternate RPV Floodang Pressse is bebw the lowest SRV o HPCg "intercewinections httang pressure)) 5RVs are open and RPV prestre as above the o LPf3 with other assits' Mmamum Afternate RPV Flooding Preswer o FCC% Ireep-full systeves was deleted.

o LPet o HPC5 o '" ire % tem b) LPCI added to inside o LPCS o RHP servsee water crosstie 'h' 5h*'d sniec tson o RHR Servate Water Crosstie SY SI'"'S' o Fre Systam o hverconnections with other units o ECCS keep. full systeves e

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1. ev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 8 of _20__

DWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS - PLANT SPECIFIC TECHNICAL GUIDELINE DIVIATION/ JUSTIFICATION CM.3 Atawitam at least (2 (mmimum senber of SRVs for which the G-2.3 vaintam at least I %RV cren and RPV pres ure above the Menemum Alternate RPV Floodeng Pressure is below the lowest Minemum Afternate R W Flooding Pressure but as low as SRV latt mg pressne)) 5RVs open and RPV pressne above the practicable by throttling inWtion.

Mansmime Alternate RPV Floodmg Presmae by throttling mpPctaan.

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APPENDIX &

Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 9 of 20 F

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SDECIFIC TECHNICAL GUIDELINE DEVI ATION[ JUSTIFICATION C6-2.4 then: C614 whent a) The wording "to or e Att control rods are insrrted beyond positen (06 beyond"is added to o All control forfs are inserted to or beyontf positinn C', or clarify the intent of (ananmum subcratical bar&ed withdrawal position)), or the tiep.

o The reactor i; shutdown and no baron has been injected o The reactor is shutdown anrf no horon has been injected snto the RPV. into the RPY, I contsnue an this procedure. contimse in this proce kwe.

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PSTG GUIDE R ee. O APPENOtX A Rew. O I

Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_10 _ of 20

' O BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVI ATION/ JUSTIFICATION C6.) If RPV water level cannot be determined: C6.) If RPV watn level cannot be determined.

If hydrogen igniters have not already been started, then start the hydrogen igniters en P870 in accordance with 501-4-01 1.E61-1 e

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8e ev. O APPENDin A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 11 of _2O_

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECTFlc TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C6-1.1 Commence and increase injection into the RPV with the CK.1.1 Commence and increase injection into the RPV wit 5 the following systems until at least ()(Minimum Number of a) Grand Gull is not 5RVs Requwed for Emergency Depressurization)) SRVs are following systems until at least 3 SRV are apen anef equipped with rnotor open and RPV pressure is not decreasing and is at least RPV pressire is nat ferreasinr anti is at least t r)0 psig driven feedpumps or or mnre above containment presswer interconnections with (77 psig (Minimum RPV Flooding Presstyre)) above suppression chamber prese.ure. other units.

o HPC%

o HPCS o LPC%

o L PCI o Motor driven feedwater pumps n Condensata onmis o LPCS o CRO o L PCI o ECC% Ireco-full systems o Condensate pumps o CRD o SLC(test tant) o dHR service water crosstie o %LC (horon ta+)

o fire System e PHD service water crosstie a Fire system o Interconnections with othar units o ECCS keep-full systems o 5LC (test tank) '

o 5LC (boron tank) r

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' PSTG GUIDE s Rew. O APPEf4 DIX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _12__ of _2O_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVlATION/ JUSTIFICATION C6- 3.2 Maintain at least ()(Minimum Number of SRVs Required for 06-3.2 Vaintain at least I SPVs open and RPY pressure at Emergency Depressurization)) $RVs open and RPV pressura at least 100 psig sho re enntainment pressure hut as least (77 psig (Minimum RPV Flooding Presserell above inw as practicable hv throttling injection, suppression chamber pressure by theottling injection.

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PCTG GJil e h et . O ASPENDix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_13 of _2O_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION C64  !! RPV water level can be determined. commence ancf C64 If RPY water level ran be rietarmined, commence and increase inrection into the RPV with the following systems increase injectinn int i the RPV with the followlM a) Grand Gulf is not until water level is increasing: svstems until RPV water level is increasing equipped with motor driven feed.

o HPCS o itPCS '"

o Motor driven feedwater pumps o LPC% '

o LPCS o LPCI n o LPCI n Condensa te c Condensate pumps o com o CHO n Ff'C% beep-fiell s= stems o RitR servics water crosstie o %LC(test tank) o fire system n %Lf'(%oron tar *)

o hierconnections with other units o P8f9 servire watN creastic o ECC5 keep-full systems o Fire %vstem o SLC(test tank) o SLC (boron tank)

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APPEfCIM A Rev. O

Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 14 -- of _2O_

P BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT S"E0lHO TEOHNICAL GUIDELINE DEVlATION/JuSTlFl0ATION C6 5 11 RPV water level cannot be determined: C6-5 11 RPV erater level carmut be determined:

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{ R ev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_15__of.2O_

P BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION C6 5.1 Fill all RPV water level instrumentation reference columns. Reference IcR filling may be reydred.

a) Since filhng tfie Reference kgs enay not always be necesury, ttus step is ad<treswd as an operator note at Grand Gulf.

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r BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELlHE DEVIATION / JUSTIFICATION i

C6 5.2 Continue insecting water into the RPV until(temperature C6-3.1 Continue injecting water into the RPY until temperature near the cold reference leg instrument vertical runs)is near the cold reference leg instrument vertical runs is below 212 F and RPV water level instrumentation is available. below 212 F and RPV water level instrumentation is available.

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PGTG GuiDI Rev. O APPEN0tX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 17 of 20 C BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVlATION/ JUSTIFICATION 11 whale cuecutang the following steps, RPV water level can be !! while cuecuting the following steps, RPV water level can be determined, continue in stus procedure at (Step C6-6L determined, continue in this procedure at Step C6-6.

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PSTG GUIDE R ev. O APPENDIM A Ree. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 18 of_20 BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/ JUSTIFICATION C6-5.3 If it can be determined that the RPV is filled or if RPV C6-3.2 If it can be determin-d that the RPV is filled or if RPV pressure is at least (77 psig (Minimum RPV Flooding Pressure)) pressure is at least 100 psig above containment pressure, above suppression chamber pressure, terminate all enjection terminate allinjection into the RPV and rerbre RPV water into the RPV and reduce RPV water level. level.

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PSTC . JIDE R ev. O APPEN0ix A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 19 - of_2O_

P BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C6 5.6  !! RPV water level indication is not restored within the C6 3.) If RPV water level indication is not restored within tne Maximum Core Uncovery Time Limit af ter commencing termina. Maximum Core Uncovery Time Limit atter commencing tson of snjection into the RPV, return to (Step C6.D. termination of injection into the RPV, return to Step C6-3.

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Rev. 1 Mississippi Pow:r & Light Ccmpany- Grcnd Gulf Nucisar Statirn Page 20_ of _20=

owr OWNERS GROUP- EMERGENCY PROCEDURE GUIDEUNE t C6-6 GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATI t hen wppresuon e hamber preswre ran he nuentamed helm tte Pronury Contaannent tbsern Precure, enter forocedure C6 6 when rantainerent pressure can be maintained below 11 psig develnped froen the RPV Control Gewtelinel at (%teps IRC/L and enter EP-7 at %teps it C/L amt RC/P.1 and esecute these stens reneurrently.

RC/P-4) and esecute thew steps retrurrently.

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PSTG GUIDC Rev. O APPE NDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 1 of 19 b BWR OWNERS G't0UP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION a) Emergency Depressurtra-CONTINGENCY 87~ CONTINGENCY #7 tion is perforrned prior level / Power Control Level / Power rnneral " '" i n I 11 while executing the following steps RPV Flooding is required or If while executine the following steps HPV water level cannot be c'etermined. control injection into the b) It has been determined HPV to mamtain reactor power above (8% (Reactor Flew Stagnation o RPV water level cannot determined, DPV FLOODINC. by the 13WR owners group PowerD but as low as paracticable. However,it reactor power 1% REOUIRE'11 enter EP-12 in preparation for R PV ttiat a specific power cannot be determined or maintained above (5% (Reactor flow Wint le vel cannot be stated

- Stagnation Power)l, RPV FLOODING IS REQUIRED: enter (procedure in advance. Therefore, developed froen CONTINGENCY #6) o Flow Stagnation Power RPV rione4ine is requirei, enter EP-l? in preparation for RPV FlondinC has been deleted in later EPG revisions and the concept of 1%w Stagnation Water Level is used. I i

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PSTG GutDE e Rev. O APPEN0tX A Rev. O N Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 2 of _19_._

I ', BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C7 8 If:

C7-1 Ifr o

a) 4% is from Tech. Spec.

Peactor power is above (3% (APR M downscale trip)) or o Table 3.3.6-2.

4 cannot be determined, and Reactor power is above 4% or cannot be determlwd, and o b) Il0*F is from Tech.

Suppression pool terriperature is above (I10*r (Boron o suppression pool temperature is above 1800F and * *

• Ins etion initiation Temperature)), and o o Either an srtV is open or opens or drywell pressure is c) 1.23 psig is from Either an $RV is open or opens or drywell pressure is Tech. h>ec. Table above 12.3 psig (high drywell pressure scram setpoint)) above 1.21 osit 2.2.11.

If any "%IV is onen, bynass low 'iPV water level instrument d) If an AtSIV is open air and V%IV isolati wi interlocks anti restore instnnnent it is advantagerms to air to the containment n.amtain is nien en order to keep tlee Hwin condenser as a heat sink. Only the itPV tow level isolation is bypassed to maintain protection against steam line breaks and fuel element failures.

b Instrument air is restored to prevent the anboard MSIVs from draltang Sut.

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nex 1 Mississippi Pow;r & Light Company- Grand Gulf Nucts:r Stati::n BWR OWNERS group - EMERGENCY PROCEDURE GUIDELINE Page_3= of 19

( Lower RPV mater levelin teemmating and preventmg all mie*tenn GGNS- PLANT SPECIFIC TECHNICAL GuiOELINE DEVIATION / JUSTIFICATION mte the RPV except from boron ing tion wstems and CRD Lower RPV water 1. velby terninatine. and oreventmr all snie: tion until etthers ( 24 f2(. al 4*. from Tech. Spec.

into the RPV cucept from boros inte:tson systems and CRD until Table 3,14-2.

eithers o Reacto* power deops below (3% ( APRM dowes ale tripi), or o Reactor nower deoos below 4% or td I.23 psig from Tech.

e RPV water levelreaches(-164 in.(too of active fuel)),or Spec. Tatsle 2.2.1-1.

o RPV water levelreaches -167 inches e A!! SRVs remain closed and drywell pressure remains below .

QA psig thigh drywell peessure scram setpointl).

e All SRVs remain closed and drywell pressure remains below t.21 psig ,

1 if RPV water level reaches or roes below -167 inches, then start hydrogen igniters on P870 in accordance with SOI-441.I-E61.t.

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APPENDIX t-Rew. O ,

Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 4 of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If while esecuting the following steps Emergency RPV Depressuri. If while executing the following steps Emergency RPV zation is reqaired, continue in this procedure at (Step C12.1) Depressurization is required, continue in this procedure at Step C7 2.1 i

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.1 O Mis iscippi Pow r & Light Company- Grcnd Gulf Nucirr St; tion Page__5 of _19  !

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE b If shel- cie utenr, the folliming step:

GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION If while escrutirer, the followanc step: as 4. grun, lecte. Spec.

c fleactor power is above 1*. (Arft41 downseale trip)) or cannot he Table 3.1.t. 2.

n Reactor power is above 4*a or cannot he determined, and h) Il0"r fron. Tech.

o o ItPV water levelis a%cve .3 57 inches AN[1 RPV water level is above (-164 in.(top of active fueD), and * **

• o O (Boeon Insecteon o Sunpression pool temperature is above ll0*r. and c) 1.23 psig from Tech.

Suppression pool temperature is above (llO F Insteation Temperature)), and Spec. Table 2.2.1 1.

o Either an SRV is open or opens or drywell pressure is o Either an SRV is open or opens or drywe!! pressure is above (2.0 psig (high drywell prev. ore scram setpoint)), I return to Step C71.

return to Step (C7.ll L

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. Rev. O aPPENOlx A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _ 6_ __ of 19 P CWR OWNERS GROUP - EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION C7-2 Maintain RPV water level either t7.f10,#11,#25 C7-2 Maintain RPV water level either: #9,#10,#11,#23 al

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• and + 53.5 " Ireen Tech. 56 ec. Table 2.2.I-l.

o If RPV wate* level was deliberately lowered in o 11 RPV water level was deliberately lowered in Step (Step C7-l), at the level to which it was lowered, C1 1, at the level to which it was lowered, or or o If RPV water level was not deliberately lowered in o  !! RPV water level was not deliberJtely lowered 5tep C7 I,between ell,4 in and 4)).) in, I

in (Step C7-l), beIween ( 12 en. (Iow level scram wtpoint)) and (.55 an. thigh level trip setpoint))

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PSTG GUIDE R ev. O APPENDen A Rev. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 7 of 19 r BWR OWNERS GROUP- EMERGENCY PROCEF.;ME GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION With the following systems: With the following systems: if PCI is not installed at Grand Gulf, o Condensate /feedwater system (1810 - O psig (RPV pressure range o Condensate /feedwater system #12 for system operation)) b) LPCI injects inside o CRD system the shroud and tiere.

{ o CRD system (Illo -O psig(PPY pressure range for system #12 fore is omitted from operation)) o RCIC system this step.

o dCIC system (18 80 - 50 psig (RPV pressure range for systeen operation))

o HPCI system (1110 - 100 psig (RPV pressure ran6e for system oper aison))

o LPCI systern (250 - O psig (RPV pressure range for sys' tem operation))

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Mississippi Pow:r & Light Ccmpany- Grcnd Gulf Nuclerr Stelion Pago 8 et _19 I BWM OWNET.S GRO'JP - EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE i If RPV water kvel cannet be so maintained, maintain RPY ester DEVIATION / JUSTIFICATION l e j level a5ove bl4 m. Itop of arteve luc 0). If Rrv water Evel cannot he si maint.imed, mamtam R"Y water l

level above -167 enches with thew systemw k'

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v.. ~,a es. 0 8'PEpeOlu A Geo. 1 Mississippi Pow r & Light Crmpany- Grcnd Gulf Nuclear Station Page 9 of 19 BWR OWNERS GROUP - EMERGENCY PROCEDURE GulDELINE L 11121% war-r We t r enews: he m,sent.orw d .i'enve f.f(4 m. han rif GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEvlATION/ JUSTIFICATION

.e- t eve ! r lH. f.\tESPt.!.N N lif4 (IEl'It?;$4t te.'t:4TI.W 8% IFI,0till:EI) !! lif'Y w.st~ level r.vvet he mamtained ahnve -f(.7 pe%cs, EttiftC.ENCY 1 T*V 11ET'Itt$%tlRIZATION I5 REQtIIRED

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PSIG uUeUL Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_10 _ of 19 O BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDILlHE DIVIATION/JUSTIFICATIOil C7 2.1 Terminate and prevent all injection into the RPV except C 7-2.1 Terminate and prevent allinjectlan into the RPV except from baron injection systems and CRD until PPV pressure from boron injection systems and CRD until RPV pressure as below tha Minimum Alternate RPV Floodmg Pressure. is below the Minimum Alternate RPV Tlooding Preswre.

Minimum Alternate RPY Minimum Alternate RPV Nurnbc. of open SRVs Floodmg Pressure (psig) Number of open SRVs flooding Pressure (psig) 7 or more 155 8 6 93

!$5 7 114 1 225 6 115 4 235 5 f r,5 3 135 4 209 2 535 3 231 2 til I 874 e

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Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 11 of 19 b BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION

, If less than (2 (minimum number of $RVs for which the Minimum Mternate itPV Floodmg Pressure is below the lowest SRV hiting  !! at least i SRV cannot be opened, continue in this procedure l pressure)) 5R Vs can be opened, continue in this procedure.

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. . of ND:EA 8e M. 1 Mississippi Pow;r & Light Company- Grcnd Gulf Nuclur Stction Page 12-- of 19 BwR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE t C7 2.2 GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / ' JUSTIFICAT Con.nw re arwt slow tv wrraw ser. ten mio tt c I?PV f24 C7-2.2 Comn.e,we arwl slowlr increase injection into the m ath it.c tollon ey systems to restore and mantan a) IIPCI es een installed RPV water icvelahove f lp us.Itop of active fuell): itPY with the inflowi y, systems to restore #25 at Grand Gulf.

arm enamtain RPV water level above .3 67 inches.

o Cordnute/feedwater srstem o Corweenute b) LPCI n deleted be.

o CHD cause it injects in-o RCIC o CHD sede the shroud.

o 64PCI

• o LPCI c) RCIC and reedwater are deleted because they are steem driven L

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.w.n!NDit i 0 Mis:issippi Power & Light Company- Gr:nd Gulf Nucisar Stetion Page 13 of_19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE L l GGNS- PLANT SPECIFIC TECHNICAL GUIDE.'.lNE If stIn mat- b v-l r.wwns h- r-st.wed and ensintaineet a%nvc DEvl ATION/ JUSTIFICATIO

(-18.6 w.. tem nt e-tree f.enl. commance an1 slou 4 entraaw 11 itPY watar level cannot be restwed and maintained above -167 *I E#d"d Id'E 8' * '@

enretuwe anto the RPV e sth the follon eng weten,s to restore ir.rsies romn,,w e a,,d slowly increase ente:tenn ento tie ""I' 'D' a,wi nimtan. I f'Y m.ater I wel above I-164 wi.(top of active fisc01: IIPY u ith tha folk www systems in restore and maintap Rf4' water l vel ahnvc -1(,7 ieu-hen o HPC%

o LI*C% o IIPCS o R?f R service water crosstie o LPC5 o rerc srstem o LI'CI o interconnections = ith other units o ECC51reep-full wstems n LCC% keep-full systems o Corwiensate Transfer ,

o I!!!R service water crosstic t o f" ire system ff lif%* water level reaches or goes below .867 inches, then start hydrrven igniters on P8r0 in acrordance with 501 f6-01-1-L61-1.

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' R ev. O APPENDIX 4.

Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 14 of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION It while esecuting the following step reactor power Commences If while executing the following step reactor power Commences and continues to increase, return to (Step C7-1). and continues to increase, returnto Step C7-I.

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Rew. O APPENDIN A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 15 of 19 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C7 3 when (204 pounds (Hot Shutdown Baron Weight)) of boron have C7 3 When 37847 pounds of boron have been in)ccted or all been inkcted or all control rods are inserted beyond a) 11.4in,and33.5 h control rods are inserted to or beyond position 02, from Tech. Spec. [able position (06 (maulmum suberitical barked withdrawal restore and maintain RPV water level between +11.4 in.and ition)), restore and maintain RPV water level between +3 3.5 in. 2J*1 1*

F+12 in. (low level scram setpoint)) and (+38 in. (high level trip setpoint)).

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~ BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE i

b GGNS- PLANT SPE01FIC TECHNICAL GulDELINE If RPY mater levelcannot t$e restored and maintamad a**ove I.12 DEVIATION / JUSTIFICATIO in. (Inv lavel cran, wtponti), mantam RP\ w.ater kvel aSove Iff!PY wa:M b rel cannot he restored and mamtamed ahnvr a) *ll.4 an. f rom Tects.

(.144 ar,. feop of acteve fuelu. Spec. Table 2.7.I-l.

+11.4 in maintam HPV water bel above -10 inches.

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auc coit,t n o apptNotz a A Ps. 1 Mississippi Power & Light Ccmprny- Grrnd Gulf Nucinar Ste. tion Page 17 of _19 ~

BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE L GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVlt.TIONj' JUSTIFICATION !

If RM ust- k vet r.rww$t er nuent eened a%m e f.f 6& wi. (ton of acteve to (St pf C7-2.Il r 01. DtreG.I.NCY 1:"V DCf'l:0%8 fRI:TTI.*N 1% 1:EOl' IRED: returee If I'"Y was r > val rannnt Se mailtained ahnve .367 andies

[11ERi;ENG I:PV FV.PRC55URl:ATl3N15 51EOUll'CD return to 5:en C7.7-l.

If RPY water level reaches or rnes belou -167 inches, then start hydrogen igniters in accordanew with5014-01 1-E6 8 1.

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• APPENmx A Rev. O Page 18 of 19 Mississippi Power & Light Company- Grand Gulf Nuclear Station '

BWR OWNERS GF!OUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE ' DEVI ATION/ JUSTIFICATION If Alternate Shutdown CoolEg h required, enter (procedure

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g) At Grand Gulf when developed from CONTINGENCY #M. conditions permit shutdown coolmg to be established, the operator is directed to do so from the Fiant Restora-tion Procedure. If r

shutdewn cw!ong t cannot be established, the operator is directeo '

to an ONEP. From there performance of Altery nate Shutdown Coohng willbe conducted 6f neceswry.

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BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C7-4 Proceed to cold shutdown in accordance with (procedure for When the conditions to C7-4 Enter EP-7 at Step RC/P.), exit this procedure enast, cooldown to cold shutdown conditions).

the operator is instructed to enter the Reactor Control Procedure prior to entering the Plant Hestoratum Procedure and f snally the normal cooldown procedure.

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, Res. O APPENDEM A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 1 of 9 --

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION REACTOR SCR Ant ppocrtyJRE Entry Conditions a) A separate scram procedure was Any scram condition. developed to address 1 the routine scram.

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PSTG GUIDE Rev. O APPENDtx A fiev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 2 of 9 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTIFICATIO S-1 If while cuecuting the foll> wing steps on entry condition for Should conditions degrade EP-2 esists, cult this proc-dure and enter EP-2. and an entry condition to EP-2 esist, it is i

approprlate to direct the operator to that pro-Cedure.

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, Rev. O APPENDtX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 3 of 9 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION [ JUSTIFICATION 5-2 Arm and depress Manual Scram pushbuttons This action will insert 5-3 Place the mode switch to SHUTDOWN. a 'back up" scram signal in the RPS logic. Taking tSe mode switch out of this "RUN" position may also preclude an isolation of the MSIVs on low steam line pressure.

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PSTG 4,UIDL Res. O APPEN0lX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 4 of 9 F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEvl ATION/JUSTIFICATIOil 5-4 Verify the scram.

With a scram condition present, it is appropeiate to verify that the scram has actually occurred.

5-5 Verify SDV vent and drain valves closed. To prevent a direct g path from developing [

between the RpV and the suppression pool.

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. Rev. O APPENDtX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 5 of 9 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 5-6 Insert the SRM's and IR*A's and switch IRM/APRM LYL recorders to IRM's The IR M's and SR M's are inserted to allow the operator to track the expected power decrease.

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PSTG GulDE Rev. O APPENDtX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 6 of 9 b BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION 5-12 Maintain RPV water level between .II.4 in, and +33.5 in.

This step defines the preferred range in which to maintain RPV water level. The upper and lower limits are the RPV level scram setpoints and are found in Tech. Spec.

5-l) Verify setpoint set down. Table 2.2.5-1.

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PSTG GUIDE Rev. O APPENDtX A Res. O Mississippi Power & Light Company- Grand Gulf NuclearStation Page 7 of 9 b BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIAT10N/JUSTlFICATION 5-14 Control RPV pressure hebw 1064.7 psig, a) To prevent entry into EP-2 the operator should main.

tain RPV pressure below the high pressure scram setpoint.

b) 1064.7 psig is found in Tech. Spec. Table 2.2.I-l.

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PSTG GulDE Rev. O APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 8 of 9 F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL CUIDELINE DEVIATION /JUSTIFICAT10fl S-15 Maintain condenser vacwm. The main condenser is the preferred heat sink under most reactor operating conditions. It is there-fore appropriate to take the actions required to f maintain the condenser available.

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' APPENDIX A Rew,O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 9 of 9

' f BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATloN/ JUSTIFICATION l 5.I6 Exit EP-1 and enter 301-4 a) then the actions of the scram procedure are completed the operator is directed to the Restoration I

Procedure.

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l p5TG ' u,C E h ev. D APPEt; Dix A 8tes. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 1 of _5_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/J.ssTIFICATION i

a.

I PLANT RESTOR ATION PROCEDURE The ac' ions for restoring botti RPy level and level j It while executing the following steps: RPV water level cannot be maintained above top of active luet or cannot be determined then bdacation, are addressed enter EP-2. in EP-2.

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PSTG GulDE e Rev. O g APPENDIX A J:

Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 2__ _ of 5 Ib BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION l If while cuecutmg the following steps the reactor is not shutdown, If while executing the followin; steps the reactor is not shutdown.

return to (Step RC/P.2) return to EP-2. With the reactor not shutdown it is not appropriate to continue

> in 101-4 where posative l reactivity may oc added

'j via a plant cooljown.

The Reactor Control Procedure (EP-2) t aeWesses .alterna te methods of reactor shutdown and is there-fore entered.

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PSTG GUIDE

• feev. O APPENDIX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 3 __ of 5 b BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS DLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION R C/P-4 Shen the RHR shutdown cooling interlocks clear. #IS Then the R HR shutdown cooling interlocks cleae, initiate initiate the shutdown cooling mode of RHR. If the RHR #12 the shutiown cooling mode of IHtt, opratM bto IOI4 shutdown cochng mode cannot be established and f.!rther coo:Jown is required, continue to cookf 3w , If the RHP shutdown cooling mode cannot he established and using one or more of the system used for depresswaation, further cooldown is required, cantime to cool down using one or more of the systems used for depressurizatum.

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PSTG GUIDE

' Rev. O APPENDEM A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 4 of 5 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS PLANT SPEClelC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION If RPV cooldown is reqused Iput cannot be accomplished and all If 9PV cooldown is reaisired Net cannot be accomplished and all controf rods are inwrted beyond positaan 106 (maximum suberitical banked withdrawal positson)), ALTERNATE SHUTDOWN COOLING IS RE-control rods are inserted to or beyond position 02 N NS SP #"*

enter ONEP 051-02.Ilf-l.

• Mili'Y ** F**

QUIRED; enter (procedure developed from CONTINGENCY #1). "' "

d the operater to the hinequate Decay Heat Removal Proredure. If conditions warrant the est.abisshenent of Alteriute hedown Conhng the operator will be given

~ [* thss direction in ONEl' 05-1 Ill-l .

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) BWR OVINERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVI ATION/JUSTIFIC ATION R C/P-1 Proceed to cold shutdown in accordance with (procedure Proceed to cold shutetown in accoretance with 1011.I.08 3.

for c ooldown to cold dwtdown conditions). "

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• . un IIPEP DIN A Rev. O Mississippi Power & Light Company- Grand Gulf NucleatStation Page 1 P of _29_

BWR CWNER3 GROUP- EMERGENCY FRCCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVlATION/ JUSTIFICATION OPER ATOR PRECAUTIONS This caution is not used as GENERAL a) . It is not " flagged

• ire tie Guide-This sectson lasts "Cautaans' which are generally applicable at all times, lanes,and b) operators are trained to con-CAUTION 81 tanuously monitor the general state of the plant.

Monator the general state of the plant. If an entry condition for a tprocedure developed from the Emergency Procedure Guidehnes) occurs, enter that procedure, then it is determined that an emergency no long er enests, enter Enormal operatang procedurel. -

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.aPPEN0ax A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Fage 2_ of _29 F

BWR OWNERS GROUP - EMERCENCY PROCEDURE GUIDE' - lilE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEV ATION/ JUSTIFICATION CAUTION #2 This caution is not used as Monitor RPV water level and prestare and primary containment a) it is not " flagged"in the Guide-temperatures amt pressure from multiple indacations. IFws, and b) operators are trained to use multspie indecations.

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' PCTG GJIC C hev 0 2PFENDix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 3 _ of _2JL F -

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CAUTK)N H This caution is not used as:

If a safety function initiates autornatically, assume a true anatstang event has suurred unless otherwise confirmed by a) it is not " flagged

• in the Guide-at least two independent indications. lines, and b) operators are trained to assume initiations are valid unless otherwise confirmed by more than one independent source.

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h ev . O APPEN0ix A Rew. O Mississippi Power & Light Company- Grand Gulf Huclear Station r Page 4 of _29_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION This caution is not used as Thenever RHR is in the LPCI mode inject through the heat a) it is not "Itagged" in the Guide.

enchangers as soon as possible. lines, and b) operators are trained to insect thru the heat exchangers as seen as possible.

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' P!*C ,J CE 3 Re 0 APPErJCIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station P Page 5 of 29 BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION cy,g g This caution is not used ass Suppression pool temperature is determined by (procedure for a) it is not " flagged"in the Guide-determaning buk suppression pool water temperature). Drywell gines.

temperature is determaned by (procedure for determining drywell atmoWe average temperature). Containment temperature is

', determined by (procedure for determming Mark !!!contamment atmosphere average temperature).

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R es. L APPENClK A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page __6 P of _2.9_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPE lFIC TECHNICI.L GUIDELINE q DEVIATION / JUSTIFICATION CAtfTION #6 CAllTinM #6 The wording of this caution has thenever (temperature near the instrufnent reference leg ver tical runs) been changed for raw of operator Drywett and containtnent tamparatures af feet D"Y water level use and only two of the GG 4N eucceds the temperature in the table and the instrument te eds below irvfecation.

the indscated level en the table, the actual RPV =ater level may be instruments ($lusadown and 'Jpset anywhere below the elevation of the lower instrument tap. Ranges) showed a tendency toward error. Also flw R-OG App. C cal-bwficated culations do rot take ento acemmt Tempera ture(*) Levet bwernment the elevation of M ark til "( ont. sin-rnent"(not drywelli te.nperatures.

Any 617 an. Shutine n Range Level (511 to 901 &n.)

IJ7'F 137 en. Wide Range Level (-150 to +63 in.)

3100 F 19 in. ' Narrow Range Level (3 to .60 in.)

543*F 161 in. Fuel 'one Level (200 to 303 in.)

(*Last en order of increasing temperature.)

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j , as s .:t Rev. O APPE ND4 R A Rev. O t Mississippi Power & Light Company- Grand Gulf Nu::learStation Page 7 of _29_.

D BWR OWNERS GROUF- EMERGENCY PROCEDURE GutDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDILINE DEVIATION / JUSTIFICATION

.l CAtJTION #7 This cautim is deleted as CGNS h (Heated reference leg instrument) indicated levels are not rehable *" # #

durang rewt Ill'V depressurization below 100 pug. For thew con. E'

dst om, utshae (cold reference leg instruments) to econator RI'V water level.

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bur OWNERS GROUP- EMERGEilCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION

, C AtiTION #3 l

NOTE #s This caution is changed to a Observe N5H regarements for pumps taking suctenn from the suppression NOTE due to incorporatson of poet. Observe NPSH requirements for pumns taking a suction from the tha intent of CAUTION AS ento simession pnot, the steps of the Emergency Depressuri2atBOfb 6

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Rev 0 APPEN0lx a Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 9 of_21.

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGHS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CAUTION 39 NOTE #9 This caution is changed to a NOTE li signals of high suppression pool water level 112 ft. 7 in. (high as operators are tramed to emtre

!! sirnals of high suppression pool water level or low cont iensate level suction mterkk)) or low condemate storage tara water level storage tank level neror, confirm automatic transfer of or manually the autom.t:( transfer occurs, D en llow level suctim enterlock)) occur. confarm automatic trans- transfer HPCS and PCIC suction from the condensate storage terk fer of or manually transfer HPCI, and RCIC suction ftom the condensate to the suppression pool.

storage tardc to the suppression pool.

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Rev O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _10_ of . 29 I -

BWR OWNERS GROUP- EMERGEilCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C AllTION AIS CAtITION #10 Do not secure or place an ECC5 in M ANUAL made unless, by at least The last sentence is deleted as the twe a r. 6.t med. cations,(Il misnperation in ALIT (%t ATIC mode is Do not secure or plee an ECr% in manual mode unless, by at least restoration lineup is an Auto /5tandby conf armed,er (D adequate core cooling as assured. If an ECCS two S,f ;,;/, r.t indicatiam,(li misnperation in At tTrws ATIC me+ 1s lineup, ronfirened, or (M adaquate core rooting es assured if an ECCS is is placed a M ANUAL mode,it will not putaate automatically. Make placed in '4 ANtIAL mode, it will not operate automatically.

frequent checks of the inariatang or controlling parameter. When manual operation is no longer required, restore the system to AtITO.

41ATIC/STANDO) mnde it possible.

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, P!TC guide hev 0 APPENDIE A Ree. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 11 of_29 F

BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CAUTION #II NOTE #11 This caution is changed to a NOTE as the operators are trained to

!! a high drymeti pressure ECCS initiation signal (2.0 psig (drywett It a high drywell pressur ECCS initiation sienal(1.39 osid necurs or control anrection while depres-pressure shach snetsates ECCS) eccurs or esists whale depressurizing, suri2 sng. Tw last sentence as prevent sniection from those LPC5 and LPCI pumps not required to esists while depressurine, prevent injection from those core soray and LPC1 pismps not required to assu-c adequate core cooling prior to '

ensure adequate core coolang prior to reachang their maximum iniection reaching their madmum insertin i pressures.

d'I'"'d isan Auto85 ** "e'y#*"

/$ tan lancup.

pressures. Ehen the hech drywell pressure f CCS initiation sis:nal clears, restore LPC5 and LPCI to AUTouATIC/ST \NDBY we.

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Rev 0 Mississippi Power & Light Company- Grand Gulf Nuclear Station r Page 12 of _29_

BWR OWNERS GROUP- Eh8ERGEf8CY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTIFIC.4 TION CAUTION #I2 cat fTON #12 HPCIis not an installed system Do not twotsie HPCI or RCIC Systems below (2200 rpm (msimum turbine no not operate RFIC below 21M rpm.

speed hmet per turbane vendor manua0L r

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,s s :. u Rew. O APPENO4X A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 13__ of 29__

F BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GJiDELINE DEVIATION /suSTIFICATION CAUTION #11 ~ NOTE 813 This caution is changed to a NOTE as operators are trasned to espect Cooldown rates above 100*F/hr (RPV cooldown rate LCO) may be re- Cooittown rates above 800'F/hr may be requireef to accornplish this high cooldown rates dureng Emergent, quired to accomphsh this step. step. Depressurizatson.

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he. s 0 AF 8 E rdDt h A Res O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 14 of _29_

F BWR OWNERS GRCUP - EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE

~

DEVI ATION/ JUSTlFICATION CAUTION #ilt CAllTION #it Caiste rnodifsed fw the lolbweng reasons:

Do not depressurlie the RPV beLw (100 psig (HPCI or HCIC low pressure tN not depressewire the PPY 5? low ni osie unless motor driven mimos isolation setpoint, whschever is higher) unless motor driven ptemps ineffecient to assise adetaata rare cooline are running and avail #la a) 60 psig is RCIC isolatmn set.

sufIscaent to mantan RPV water level are running and available for  !!or injection. Pont.

M'iO"*

b) tording changed should RPV level nat be rnaintaened tmt Merpsate

( cre ( ABOltitg* 8% asMNtd.

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, P T, T C 5U 00 Re.. O APPENOtX A Rew. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page_15_ of _29_

F BWR OWNERS GROUP- CMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C AUTION #15 CAtTTION fl1 Oren SRVs in the following sequence if possibies (SRV opening seqience). Open SRVs in a sequance which will distribute heat uniformtv throomhoist the suppression pont le possible.

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( APPENDIX A Rev. O Mississippi Power & Light Company- Grard Gulf Nuclear Station Page 16 of _29_

I BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS - PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C AUTION #16 This caution is deleted as the Bypassing low RrV water level (ventilation system and) MSIV isolation intent of the caestan is met by interlocks may be required to accomplish this step. CAUTION 822.

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APFEN0ls A Rev. O g Mississippi Power & Light Cornpany- Grand Gulf Nuclear Station Page 17 of _29__

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHdlCAL GUIDELINE DEVIATION / JUSTIFICATION CMITION O!?

This caution is deleted as the Cooldawn rates above (100*F/hr (RPV cooldown r.ite LCO)) may be intent of the caution is met by requred to conserve RPY mater inventory, protect primary con- NO TE #13.

tainment antegrary, or famit radioactive release to the environment.

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Rev. O p Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 18_ of _29_

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUjCELINE GGNS- PLANT SDECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION CAUTION #18 CAtITION #18

!! continuous LPCI operation is required to assure adequate core  !! contimanus L PCI operatioi ls required to assure adequate core cooling, do not divert all RHR pumps from LPCI mode, coolinr, do not divert RHR wmps from LPCI mode, e

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' PSTG Gt'iDE R ev. O APPENDlK A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 19 of _29._

BWP OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CAtlTION fl9 CAUTI(W #19 Confirm automatic trip or manually trip SLC pumps at (0% (Iow level Manually trip %LC pumps at approximately 230 G ALLONS trip)) in the 5LC tank, in the 5LC tank.

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, R ev. O APPENDIE A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 20 of _29_

I BWR OWNERS GRCUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CAUTION #20 CAtITION #20 RCIS is the equipment equivalent Defeatlng R5C5 interlocks may be required to accomplish this step. of R$C5.

Defeatint RCl% interiorirs may be required to accomplish this step.

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n,e.ia o cu.ot apotheim S Res. 1 Mississippi Pow r & Light Company- Grand Gulf Nucl::r Sttti n Page_21 of_2_9 SWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE U cuman nu GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION cumon en ti,vated suppression chamber pressure may trip the Reic turbiae en high exhaust pressure. tievated containment pressure may trip the Rcic turbine on high exhaust pressure.

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e : a, .u.a APPENDIX A Res. O Mississippi Power & Light Company- Grand Gulf Nuclear. Station F Page _22__ of _29_

BWR OWNERS GdOUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CAUTroN #22 CAUTION #22 .

Defeating isolation interlocks may be required to accomplish this Defeating isolation interlocks nay be required to accomplish this step.

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i P5TG GulDE Rev. O APPENOix A Rev. O P Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _ 23 of 29 BWR OWNERS GROUP- EMERGENCY PROCEDURE GulDELINE GGNS- PLANT SPECIFIC TECHNICAL GulDELINE DEVIATION / JUSTIFICATION CAUTION #21 This caution is deleted as GCNS Do not initiate drywell sprays !! suppression pool water level is does not have the capability to above ( (elevation of bottom of Mark Iinternal suppression spray the drywell.

chamber to drymell vacuum breakers less vacuum breaker opening pressure in feet of water)).

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r PSTL GUIDE i Rew. D APPENDIX A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page __24 of 29 O

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION I CAUTION #24 NOTE #74 This caution is changed to a NOTE Bypassing high drywell pressure and low RPV water level secondary in that operators will be able to Bypassing high drywell pressure and low RPV water level HVAC accomphsh the step !! the iwla-containment HVAC isolation interlocks may be required to accomplish isolation interiorks may be reepsired to accomplish this step.

this step. tions have not occurred and will have to bypass the interlocl.s if the isolations have occurred.

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s P;TO GQ!OE R ev O APPEN0lx A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page _ 25 of -. 29 P

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION C AUTION 825 CAUTfoN #25 A rapid increase in injection into the RPV may induce a large power A rapid increase in infectio n into the RPY may induce a large excursion and result in substantial core damage. power excursion and result in substantial core damara.

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Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 26_ of 29 F BWR OWNERS GROUP- EMERGENCY PROCEDURE GulCELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DE7iATION/ JUSTIFICATION CAUTION #26 CAUTION #76 Large reactor power oscillations may be observed while executing large reactor power owillations enay be observed 'while executing this this step. Step.

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' 85 3 GU.CE R ev. O AFPENDix A Rev. O Mississippi Power & Light Company- Grand Gulf Nuclear Station

8. Page_27 of _29 BWR OWNERS GROUP- EMERGENCY PROCEDbRE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION /JUSTlFICATION This note is added to aid the operator in maintaining accurate R PV water level instrumentation reference legs may require fi!Iinit RPV water level indecation.

to ensure accurate level indicatio1 1

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' 75TG 3.J.C E R es. O APPENDIX A R e v. O

' Mississippi Power & Light Company- Grand Gulf Nuclear Station P Page_2_8_c _29_ a BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION CAllTION #78 This caution is added to aid the operator in which of the suppression If suporession pool level is belo w 18.14 f t., TAH.L601 C&f) may he poci levelinstruments may be avail-uncovered able at lower pool le--ats.

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l PITG GJICE PE DIX A Res. O Mississippi Power & Light Company- Grand Gulf Nuclear Station Page 29 of 29 F

BWR OWNERS GROUP- EMERGENCY PROCEDURE GUIDELINE GGNS- PLANT SPECIFIC TECHNICAL GUIDELINE DEVIATION / JUSTIFICATION NOTE #29 This note is added to clarify where the operator is to obtain As determined by both cent ninment high rante radiation monitors. the necessary information.

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