ML20215F737
| ML20215F737 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/26/1984 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20215F733 | List: |
| References | |
| 40AC-FPX01-0, 40AC-FPX1, TAC-61626, TAC-61627, NUDOCS 8612240048 | |
| Download: ML20215F737 (81) | |
Text
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1 GEORGIA POWER C0!!PANY l HATCH NUCLEAR PLANT I PAGE 1 0F 65
.I DOCUMENT TYPE: 1 DOCU!ENT NU11BER:
ADetINISTRATIVE CONTRCL PROCEDURE I 40AC-FPX01-0 I i DOCUl2NT TITLE: l REVISIO!!: '
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A, FIRE PROTECTION PROGRAM i .1 ,
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_J._. SAFETY RELATED APPROVED DATE: 17 l u ,h 4
_ NON-SAFETY RELATED EFFECTIVE DATE: 17 /cm/F 4-EXPIRATIO!! DATE: N/A REV.l l APPROVED l l APPROVED l NO. I DESCRIPTION I DEPT. FER. I DATE I GENERAL MGR. l DATE I i l l I 0 l Initial Issue l I l l l 1 > / I I o I 1 Proc. Ref. & Att. revised l I I I I l'
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1 I I l l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l' l I I I I I I I I I FER-0002 Rev. 0 8612240048 861209 PDR ADOCK 05000321 p PDR
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- GEORGIA POWER C0l!PA21Y l HATCH I;UCLEAR PLANT l PAGE 2 0F 65 DOCUMENT TYPE: i DOCU!EIIT !!U!!BER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMEET TITLE: l REVISION :
1 FIRE PROTECTION PROGRAM l 1 TABLE OF CONTENTS Section Eggg 1.0 OBJECTIVE ..................................... 5 2.0 APPLICABILITY ................................. 5 3.0 REFERCICES .................................... 5 '.
3.1 DEVELOP!! ENTAL REFERENCES . . . . . . . . . . . . . . . . . . . . 5 3.2 I!!PLEZ ENTING REFERENCES . . . . . . . . . . . . . . . . . . . . . 6 4.0 I1ESPOIISIBILITIES .............................. 7 4.1 G EN E RA L }!Al?AG ER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4.2 ENGI!!EERING DEPARTHENT . . . . . . . . . . . . . . . . . . . . . . 7 4.3 !!AINTENANCE DEPART!ENT . . . . . . . . . . . . . . . . . . . . . . 9 4.4 QUALITY CONTROL SECTION . . . . . . . . . . . . . . . . . . . . . 9 4.5 OPERATION S DEPARTtENT . . . . . . . . . . . . . . . . . . . . . . . 9 4.6 HEALTH PHYSICS AND CHEPIISTRY DEPART 1[ENT .. . . . 10 4.7 ADMINISTEATIVE, FINANCE A!!D HU;IAN REdOURCES D E PA RTMEN T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4.8 TRA IN ING DEPART!ENT . . . . . . . . . . . . . . . . . . . . . . . . . 10 4.9 ALL D E PART1ENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 4.10 ALL PERSONNEL ............................... 11 MGR-0001 Rev. 0
l l l GEORGIA POWER C0!!PANY l HATC11 NUCLEAR PLANT l PAGE 3 0F 65 DOCUMENT TYPE: 1 DOCUMENT NUMBER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 ;
DOCUMENT TITLE: l REVISION:
- l FIRE PROTECTION PROGRAM l 1 TABLE OF CONTENTS Section h 5.0 REOUTREMENTS .................................. 12 5.1 PERS ON!!EL REQUIREMENTS . . . . . . , . . . . . . . . . . . .,. . . 12 5.2 tlATERIAL AND EQUIP!ENT . . . . . . . . . . . . . . . . . . . . . . 12 -
5.3 SPECIAL REQUIREMEllTS ........................ 12 6.0 PRECAUTIONS /LT!!ITATIONS ....................... 13 6.1 PRECAUTI0 tis ................................. 13 6.2 L I t !ITAT IO N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 7.0 PREREOUISITES ................................. 13 S.0 PROCEDURE ..................................... 13 8.1 F IR E PR EV ENT ION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 8.1.1 Control of Transient Fire Loads ......... 14 8.1.2 Control of Flammnble and Cnnbustible Liquids ................................. 18 8.1.3 Control of Hn2nrdous Comoressed Cases ... 23 8.1.4 control of Tenition sources ............. 24 8.1.5 Trninine ................................ 28 MGR-0001 Rev. O
I GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT l PAGE 4 0F 65 DOCUMENT TYPE: l DOCU!IENT I U!IBER:
I .
ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: I REVISION :
1 FIRE PROTECTION PROGRA!! l 1 TABLE OF CONTENTS Section h 8.2 EFFECTIVE HANDLING OF FIRE EMERGENCIES . . . . . . 30 8.2.1 Fire Protection Systens and Ecuinnent ... 30 8.2.2 Fire Bricade and Fire Enercency Sunnart Groun (FESG) ............................ 34 ',
8.2.3 Fire Bricade and FESG Trainine Procran .. 35 8.2.4 Leadershin Traininc Progngg ............. 37 8.2.5 Drills .................................. 37 8.3 !!AINTAINIUG PROGRAtt INTEGRITY . . . . . . . . . . . . . . . 40 8.4 FIRE E![ ERG FN CY OPERATION S . . . . . . . . . . . . . . . . . . . 42 Attachnents 1 Transient Conbustible Permit .................. 45 2 Transient Combustible Permit Log Index......... 48 3 Weekly Fire Inspection Report ................. 50 4 Hot Work Permit ............................... 52 5 Hot Work Permit Log Sheet ..................... 55 6 Organization. Lines of Conmunication and Responsibilities of the Fire Brigade. FESG.
and Local Fire Departments .................... 57 7 Request for Revision to Prefire Plan .......... 58 8 Definitions ................................... 60 -
MGR-0001 Rev. 0
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GEORGIA POUER COMPANY l HATCH NUCLEAR PLANT l PAGE 5 0F 65 DOCUME!IT TYPE: I DOCU!!ENT NU!!BER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCU!!ENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM l 1 1.0 OBJECTIVE This purpose of the Fire Protection Program is to provide a single source document which pulls together all the requirements for fire protection administracive controls and presents them in a cohesive fashion. The objectives of the Fire Protection Program are to minimize the probability and severity of fires throughout the plant. This is achieved using the defense-in-depth concept which employs multiple levels of safety measures to attain the required high degree of safety. The Fire Protection Progran implements the ,
requirements of section 3.0 below.
2.0 APPLICABILITY The measures established by this procedure are applicable to all personnel at Plant Hatch and to those systems and activities covereo by this procedure.
3.0 REFERENCES
3.1 DEVELOP!! ENTAL REFERENCES 3.1.1 10CFR50.48. Fire Protection 3.1.2 10CFR50. Appendix R. Sections G. J and O. 1.5. Appendix A.
Criterion 3 3.1.3 National Fire Protection Association Code - NFPA 27-1975.
Private Fire Brigades 3.1.4 Nuclear Mutual Limited Property Loss Prevention Standards f or -Nuclear Generating Stations - Appendix A.6. Private Fire Brigades - Operating Plant 3.1.5 International Fire Service Training Association (IFSTA)
Volume No. 301 - Fire Department Officer 3.1.6 International Fire Service Training Association (IFSTA)
Volume No. 202 - Fire Service Orientation and Indoctrination MGR-0001 Rev. 0
I GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT l PAGE 6 0F 65 DOCUMENT TYPE: l DOCUMENT NUMBER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
l FIRE PROTECTION PROGRAM l 1 3.1.7 Regulatory Guide 1.120. Fire Protection Guidelines for Nuclear Power Plants and Supplemental Guidelines. Nuclear Plant Fire Protection Functional Responsibilities. Adminis-trative Controls and Quality Assurance - Attach ents 1 - 6 3.1.8 Evaluation of the Hatch Nuclear Plant Fire Protection Pro-gram
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3.1.9 Branch Technical Position 9.5.-l. Rev. 2. 1981. Guidelines for Fire Protection for Nuclear Power Plants ,
3.1.10 Regulatory Guide 1.33 - 1979. Appendix A. Section 1.L 3.1.11 National Fire Protection Association Pamphlet No. 51B-1977.
Oxygen Fuel Gas Systems for Velding and Cutting 3.1.12 Southern Electric Service Property Loss Prevention Standards for Nuclear Generating Stations. Appendix A.8. Uelding and Cutting Safety Procedures - Operating Plant 3.1.13 National Fire Association Famphlet No. 30-1977. Flammable and Combustible Liquids Code 3.1.14 Occupational Safety and Health Acts Standards 29CFR 1910.105-1980. and 1910.144-1980, 1910.155-81. Subpart L 3.1.15 National Fire Protection Association Piaphlet No. 325 H-1977.
Properties of Flanmable Liquids. Gases and Volatile Solids 3.1.16 Natioss). Fire Protection Association Pamphlet No. 803-1983.
Fire Protection for Light Uater Nuclear Power Plants 3.2 IMPLEMENTING REFERENCES 3.2.1 Technical Specifications. Unit 1. 3/4.13 3.2.2 Technical Specifications. Unit 2. 3/4.7.7 and 6.8.1.f 3.2.3 Edwin I. Hatch Nuclear Plant Emergency Plan 3.2.4 FSAR. Unit 2. Section 17.2.2.1. Fire Protection Program 3.2.5 49CFR Chapter 1. Transportation MGR-0001 Rev. O
1 GEORGIA POUER COMPA?iY l HATCH NUCLEAR PLAUT l PAGE 7 0F 65 DOCUMENT TYPE: l DOCUlINT UUMBER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMERT TITLE: 1 REVISIOM:
I FIRE PROTECTION PROGRAM l 1 3.2.6 National Fire Protection Association Pamphlet 386-1981.
Standard for Portable Shipping Tanks 4.0 RESPONSIBTLITIES 4.1 GENERAL MANAGER The General Manager has the overall responsibility for fire protection at Plant Hatch.
4.2 EUGINEERING DEPARTME!!T ,
The Engineering Department. specifically the engineering group with fire protection responsibilities, under the direction of the Manager of Engineering, shall have the following responsibili-ties:
4.2.1 Establishing a fire protection and loss prevention progran and imple2enting that prograu.
4.2.2 Revieuing and evaluating applicability of fire codes and standards to Plant Hatch fire protection systems and pro-grams.
4.2.3 Revicwing and updating the fire protection plan, fire haz-ards analysis report and those procedures used to implement tne fire protection program.
4.2.4 Formulating, reviewing and approving prefire plans, revisions to the plans, and developing Emergency Implenenting Procedures for fire emergencies.
4.2.5 Implementing those adninistrative controls outlined by this procedure for the control of transient combustibles and ignition sources.
4.2.6 Perf orming weekly plant fire safety inspections in accordance with this procedure.
4.2.7 Maintaining an inventory and history of fire fighting equip-ment and controlling the issuance of fire extinguisherr and fire hoses.
tiGR-0001 Rev. O
I GEORGIA POWER COMPANY l HATCil NUCLEAR PLANT l PAGE 8 0F 65 DOCUMENT TYPE: l DOCUMEllT NU!IBER:
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ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMEET TITLE: ( REVISION:
1 FIRE PROTECTION PROGRAM l 1 4.2.8 Establishing the training program for the Fire Brigade.
Emergency Support Group and other plant personnel, and main-taining a roster of those personnel qualified as members ot the Fire Brigade or Emergency Support Group.
4.2.9 Perf orming preventive maintenance on specialized fire fight-ing equipment (nozzles. foam eductors, etc.) and verifying perf ormance of acceptance tests on fire protection systems.
4.2.10 Conducting and evaluating plant fire drills as outlined in ,
this procedure. .
4.2.11 Identifying the need for new fire protection systems or modi-fications to existing system.
4.2.12 Investigating all fires and issuing fire reports as applica-ble.
4.2.13 Reviewing Design Change Requests and Maintenance Work Orders generated that may affect fire protection systems or components, when required.
4.2.14 Perf orming, as necessary, those quality control functions related to surveillance or inspection of fire protection systems, fire barriers and penetration seals, fire doors or other components ot the rire protection systems at Plant Hatch.
4.2.15 Reviewing the saf ety measures taken when hot work activities are to be performed on ttnks that nave contained any combustible, flammable or volatile substance.
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4.2.16 Verifying. cn an annual basis that active members of the Fire Brigade have received a physical examination and pass respirator qualifications.
4.2.17 Providing authorization for hot work activities to be per-formed on previously pressurized systems or tanks that have contained any volatile, fimnmable or combustible substances, based on report from the Health Physics and Chemistry Department.
MGR-0001 Rev. 0
I GEORGIA POWER COMPANY l HATCH NUCLEAR. PLANT l PAGE 9 0F 65 DOCUMENT TYPE: 1 DOCUMENT NUMBER:
I ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT' TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM l 1 4.3 MAINTENANCE DEPARTMENT The Maintenance Department, under the direction of the Manager of Maintenance. has the following responsibilities:
4.3.1 Performing required maintenance and surveillance activities on fire protection systems and components in accordance with approved procedures.
Issuing and controlling Hot Work Permits in accordance with 4.3.2 subsection 8.1.4 of this procedure.
4.3.3 Providing personnel, as required, to participate in training and becoming qualified members of the Fire Emergency Support Group.
4.3.4 Reviewing Hot Work Permit Logs kept by Plant and Contractor Maintenance Foremen.
4.4 QUALITY CONTROL SECTION The Quality Control Section shall be responsible for performing those inspections. tests and audits outlined in 40AC-QCX01-0.
Quality Control Inspection Plan.
4.5 OPERATIONS DEPARTMENT The Operations Department (specifically the Shif t Supervisor not acting as the Fire Brigade Chief and the Operations Supervisor on Shift) are responsible for the following:
4.5.1 Maintaining the plant in a saf e condition during fire emer- -
gencies and keeping the Fire Brigade Chief informed of plant changes and status.
4.5.2 Authorizing removal and return to service of fire protection systems and components and specifying temporary measures to raintain adequate levels of fire protection, and meeting the Limiting Conditions of Operation as specified in plant Tech-nical Specifications. This includes establishing a Fire Watch. ,
HGR-0001 Rev. O
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GEORGIA POUER COMPANY l HATCH NUCLEAR PLANT l PAGE 10 0F 65 DOCUMENT TYPE: l DOCUt!ENT l1 UMBER:
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ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUt[ENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRA!! l 1 4.5.3 Notifying an engineer with fire protection responsibilities when fire protection systems or components are removed from or returned to service.
4.5.4 Authorizing the shutdown and start-up of plant systems and components as necessary to contain a fire or minimize the damage that may be incurred due to a fire.
4.6 HEALTIl PHYSICS AND CHEMISTRY DEPART!!ENT The Health Physics Group, under the direction of the Manager of '.
Health Physics and Chemistry, shall be responsible for:
4.6.1 Surveying work locations and issuance of Radiation Work Penaits (RWP), when required.
4.6.2 Surveying pressurized systems or tanks that have previously contained volatile or cembustible substances to determine the suitability of the systen or tank for the proposed activity.
4.6.3 Responding to fire emergencies to monitor radiation and contamination.
4.7 ADtIINISTRATIVE. FINANCE AND HUI!AN RESOURCES DEPARTIIENT The Administrative. Finance and llucan Resources Department, under the direction of the !!anager of Administrative. Finance and Human Resources, shall be responsible for maintaining and distributing approved copies of Plant Hatch prefire plans in accordance with approved procedures.
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4.8 TRAINING DEPARTMENT The Training Department, under the direction of the flanager of Training. shall be responsible for the following:
, 4.8.1 Maintaining the training records of those plant personnel qualified as members of the Fire Brigade. Fire Emergency Support Group, general plant personnel trained for fire I
watch. " Hot Work" permit issuing training and general '
j employee fire training.
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}0R-0001 Rev. O P
I GEnr.GIA POWER COMPANY l IIATCH NUCLEAR PLANT l PAGE 110F 65 DOCUMENT TYPE: 1 DOCUMENT NUMBER:
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ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: 1 REVISION :
1 FIRE PROTECTION PROGRAM l 1 4.8.2 Reviewing the formal training program established by the engineering group with fire protection responsibilities that provides training for the Fire Brigade and Fire Emergency Support Group members. fire watch. " Hot Work" p rmit and general employee fire training.
4.9 ALL DEPARTMENTS 4.9.1 Personnel frou each department assigned duties as a Fire Watch shall have the following responsibilities: , ,
. I 4.9.1.1 Observing the area where the hot work is being performed and immediate surrounding areas for indications of fire.
4.9.1.2 In the event a fire is discovered:
4.9.1.2.1 Notify the Control Room and provide the type. loca-tion, and size of the fire.
4.9.1.2.2 Sound the fire alarm or instruct personnel in the work area to do so.
4.9.1.2.3 Attempt to extinguish the fire using the hand held extinguishers equipment provided.
4.9.1.2.4 Evacuate the area of personnel should the hand held extinguisher be insufficient to suppress the fire.
4.10 ALL PERSONNEL All personnel who have duties or perform activities at Plant
! Hatch are responsible for:
4.10.1 Being familiar with this procedure, the Emergency Plan and the implementing procedures applicable to them during a fire emergency.
4.10.2 Reporting fires to the Control Room and providing the type.
Location and stze of the fire.
4.10.3 Reporting all potential fire hazards to an engineer with i
fire protection responsibilities or to their immediate -
j supervisor.
MGR-0001 Rev. O L
I GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT l PAGE 12 0F 65 DOCUMENT TYPE: 1 DOCUIENI NUMBER:
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ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION :
1 FIRE PROTECTION PROGRA!! l 1 4.10.4 Reporting the unauthorized use of fire protection equipment or systems, damaged fire protection equipment and missing fire protection equipment to their immediate supervisor and/or an engineer with fire protection responsibilities.
4.10.5 Minimizing fire hazards within their work areas.
5.0 REDUIREMENTS 5.1 PERSONNEL REQUIREMENTS .
5.1.1 Engineering group members with fire protection program responsibilities shall meet the minimum qualifications specified in 10AC-MGR07-0. Personnel Qualification Requirements and be qualified members of the Fire Brigade.
5.1.2 Fire Brigade and Fire Emergency Support Group personnel shall neet the qualifications specified in subsection 8.2.2 and be trained in accordance with subsection 8.2.3 of this proce-dure.
5.1.3 Personnel acting as instructors for classroom training and drill activities shall be individuals qualified and trained as members of the Fire Brigade.
5.1.4 Foremen issuing Hot Work Pensits shall meet the minimum qual-ifications for that position as specified in 10AC-MGR07-0.
Personnel Qualification Requirements and receive the training specified in subsection 8.1.6.
l 5.2 !!ATERIAC AND EQUIPMENT N/A - Not applicable to this procedure.
5.3 SPECIAL REQUIREMENTS When notified by the Control Room that a fire protection system or component has been removed from service for other than scheduled. routine maintenance. or is inoperative and will remain so for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. the Engineering group with fire l
protection responsibilities should notify the insurers of Plant l Hatch. They should also notify the insurers when those systems or components are returned to service.
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l 10R-0001 Rev. 0 1
I GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT l PAGE 13 0F 65 DOCUMENT TYPE: l DOCUliENT tlU!IBER:
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ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION :
l FIRE PROTECTION PROGRAM l 1 6.0 PRECAUTIONS / LIMITATIONS 6.1 PRECAUIIONS N/A - Ilot applicable to this procedure.
, 6.2 LI!!ITATIONS 6.2.1 Fire Brigade and Fire Emergency Support Group members who fail to attend one training session shall be required to ,
attend a make-up session. Two missed sessions in a row .
shall require recertification.
6.2.2 The Fire Brigade shall have no less than five members per shif t who shall have no other duties during a fire than fire fighting.
6.2.3 The Limiting Conditions for Operations as listed in Unit I and Unit 2 Technical Specifications shall be adhered to.
6.2.4 Use of open flame or combustion smoke for leak detection is prohibited.
6.2.5 All wood utilized in saf ety related areas shall be of the fire retardant type or covered with fire retardant material.
7.0 PREREOUISITES N/A - Not applicable to this procedure.
8.0 PROCEDERE The defense-in-depth approach, when applied to achieving the objec-tives of the Fire Protection Program, include: (1) preventing fires, (2) handling fire emergencies, and (3) maintaining program integrity.
8.1 FIRE PREVENTION One of the primary objectives of the Fire Protection Program is to prevent fires from occurring. Administrative controls have been established to control both combustibles and ignition -
sources to the greatest extent possible.
MGR-0001 Rev. 0
I GEORGIA POWER C0!!PANY l HATCH NUCLEAR PLANT l PAGE 14 0F 65 DOCUMENT TYPE: l DOCUMENT NUMBER:
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ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION :
1 FIRE PROTECTION PROGRAM l 1 8.1.1 Control of Trnnaient Fire Londa Transient Fire Loads are those flammable or combustible materials that are not permanently installed as part of a plant structure.
8.1.1.1 Transient Fire Loads are classified in two categories based on the BTU rating per square foot of floor area for control purposes and for determining additional fire protection requirewents to be implemented. .
Low Firo Load: The fire load of an occupancy is clas-sified as " low" if it does not exceed an average of 100.000 B1U per square foot of net floor area of any compartment or an average of 200.000 BTU per square foot in limited, isolated areas. (It is determined that existing extinguishers and hoselines normally provide adequate protection for " low" fire loads.)
Mich Fire Lond: The fire load of an occupancy is clas-sified as "nigh" if it exceeds an average of 100.000 BTU per square-foot of net floor area of any coupartment or an average of 200.000 BTU per square foot in limited.
isolated areas. (It is determined that supplemental por-table and/or hand held fire equipment will be required for that 3TU content above the " low" fire load classification.)
8.1.1.2 Movement of any transient fire load into a saf ety related area or other area designated by the General Manager, is accomplished through the use of a Transient Combustible
'Pe rm it. The format of the report should be similar to that shown in Attachment 1. These areas include, but are not limited to, the following:
Turbine Buildings Control Building Reactor Buildings Intake Structure 1 Diesel Generator Building FER-0001 Rev. O I 1
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I GEORGIA POWER C0tiPA!!Y l HATCH NUCLEAR PLANT l PAGE 15 0F 65 DOCUMENT TYPE: l DOCU!!ENT !! UMBER:
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ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM l 1 8.1.1.3 Personnel wishing to move transient combustibles into a designated area shall have the proposed location and the combustibles inspected and approved by the Engineering group with fire protection responsibilities on a Transient Combustible Permit. (Blocks 3 through 5 on the example permit.)
8.1.1.4 The Engineering group with fire protection responsibili-ties shall determine the need for additional manual fire suppression capabilities during the inapection based on . -
the following:
Fire Load Calculations Rate of Heat Release Potential Spill Areas (for liquids)
Fire Brigade Access Total Combustibles Availability of Fire Suppression Equipment Fire Detection Devices Available 8.1.1.5 General Itanager approval shall be required on Transient Combustible Permits when movement or transient combustibles into a designated ar2 , ccuse tne areas load cla.;;_ ~_ ca co se iacreased cbove the low classi-fication as defined above.
8.1.1.6 Any portable fire extinguishers specified on the Tran-sient Combustible Permit should be in addition to those already available in the area.
8.1.1.7 Approved permits should be maintained by the Engineering group with fire protection responsibilities and a copy should be posted in the area where the transients are to be stored.
10R-0001 Rev. 0
I GEORGIA POWER Col;PANY l HATCH NUCLEAR PLANT I PAGE 16 OF 65 DOCUMENT TYPE: 1 DOCUMENT NUMBER: ,
1 ADMINISTESTIVE CONTROL PROCEDURE I 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM ! 1 8.1.1.8 The Engineerina group with fire protection respons-ibilities will maintain the original peruit in a log book. The log book should have an index page mini 14r to that shown as Attachment 2.
8.1.1.9 The Engineering group with fire protection respons-ibilities will be notified when transient combustibles are removed from the area by returning the posted copy of the Transient Comoustible Permit. . .
8.1.1.10 The Engineering group with tire protection respons-ibilities will inspect the area and verify that transient coueusttoles were removed. This will be be documented on the Transient Combustible Permit.
8.1.1.11 Uhen the Transient Combustible Permit is completed.
the Engineering group with fire protection respons-iotlities ws11 updat. tue Transient Combustible Permit Log Index and forwara the original permit to Document Control for retention in accordance with 20AC-DCn02-0.
Plant Records Management.
8.1.1.12 Tran4ient tire load.. tenporarily stored in safety re-lated areas, shall be posttroned in a manner that nini-mizes the potential hazard to important equipment and components should the area be involved in a fire.
8.1.1.13 Combustioles associated with specific uork activities (such as rass. comoustiole containers, etc.) should be removed at the completion of the activity or at the end of et.ch work shif t. whicnever is sooner.
8.1.1.14 Storage of flammaole or combustible materials in areas where there is reu anu white dragonal striping on floors and caution signs on walls to designate the area as a "N0 STORAGE AREA" is prohibited.
8.1.1.1; Wood utilized in safety related areas shall be of the fire retardant type or covered ottn fire retardant materials.
MGR-0001 Rev. U
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I GEORGIA POUER COMPAt;Y l IIATCH ITUCLEAR PLA!!T I PAGE 17 0F 65 DOCUI1ENT TYPE: l DOCUl'E!;T !!U!IBER:
AD!!I!!ISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
I FIRE PROTECTIO!! PROGRA!! l 1 8.1.1.16 Portable electrical equipment, such as portable temporary electrical heaters, multi-string lights, flood lights 200 watt and above, salamanders. weld rod holding ovens, temporary power connections and temporary trans-formers will be inspected by the Engineering group with fire protection responsibilities on a periodic basis to ensure that the equipment is in good repair and functions properly. !
8.1.1.17 The Engineering group uith fire protection ',
responsibilities will perform a weekly fire inspection of the plant to determine tne status of Transient Combustible Permits, identify areas where transient fire loads have been placed, inspect portable electrical equipnent in use, and ensure the requirements of this procedure are act. Results of the weekly inspection should be documented. The format of tne form should be similar to that shown in Attacnment 3.
S.1.1.18 Weekly fire inspection reports should be maintained by the Engineering group with fire protection responsi-bilities. Discrepancies notea during the inspection should be documented, the corrective actions specified, and a copy of the form fortrarded to the responsible departnent.
8.1.1.19 Re-inspection and confinmation of corrective actions taken will be docunented on the weekly inspection f orm.
MGR-0001 Rev. O
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I GEORGIA POWER COMPANY l HATCH NUCLEAR PLA!!T l PAGE 18 0F 65 DOCUMENT TYPE: l DOCUMENT IiUliBER: '
I ADMINISTRATIVE CONTROL PROCEDURE ! 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM i 1 8.1.2 Control of Finnnnble and Combustible Liouids 8.1.2.1 Finnnnble Liouids are liquids with a flash point below 100 F (37.8*C) and having a vapor pressure not exceeding 40 pounds per square inch (absolute) at 100*F (37.8'C)
These shall be known as a Class I liquid. Class I liquids shall be subdivided as follous:
Class IA shall include those having flash points below '
73*F (22.8*C) and having a boiling point below 100*F "
(37.8*C).
Class IB shall include those having flash points below 73*F (22.S*C) and having a boiling point at or above 100*F (37.8*C).
Class IC shall include those having flash points at or above 73*F (22.8'C) and belov 100*F (37.8*C).
8.1.2.2 Conbustible Liouids are liquids having a flash point at or above 100*F (37.8'C). Conbustible liquids are sub-divided as follows:
Class II liquids shall include those having flash points at or above 100*F (37.8*C) and belov 140*F (60*C).
Class IIIA liquids shall include those having flash points at or above 140*F (60*C) and belou 200*F (93.4*C).
Class IIIB liquids shall include those having flash points at or above 200*F (93.4*C).
MGR-0001 Rev. O
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GEORGIA POWER COMPAMY l HATCH HUCLEAR PLANT l PAGE 19 0F 65 DOCU!!ENT TYPE: l DOCUMENT I:UMSER: '
I ADMINISTRATIVE CONTROL PROCEDURE I 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRAll 1 1 8.1.2.3 Outdoor Container Storage 8.1.2.3.1 Drum storage of flannable liquids shall be located at a niniuun of 75 feet from any plant structure. The naximuu number of druns per lot shall be:
Class IA -
20 Class 13 - 40 Class IC -
80 * '
Class II - 160 ,
Class IIIA - 400 8.1.2.3.2 Storage lots shall be a minimun of 50 feet apart and druns shall not be stacked.
8.1.2.3.3 The lowest naxinun storage of druns per lot by the classifications listed above shall be used when the lot contains two or nore classifications of liquids.
3.1.2.3.4 Class IA drums shall be sheltered fron direct rays of the sun.
8.1.2.3.5 Drun storage areas for flannable liquids shall be graded in such a nanner as to divert possible spills away from buildings and other exposures, or the storage area shall be provided with a curb at least six inches high. Appropriate drains shall be provid-ed. as necessary. to relieve rain water accumu-lations within the curbed area. Drains shall terni-nate at a saf e location and shall be accessible to
. operation under fire conditions.
8.1.2.3.6 The stora; e area shall be kept clear of grass, weeds, and other foreign coubustibles for a distance of 25 feet.
8.1.2.3.7 Smoking or use of open flames shall not be allowed within 50 feet of any storage area.
3.1.2.3.8 Storage areas shall be posted with appropriate caution signs such as " CAUTION - !!O S!!0KIliG"; " KEEP
^
OPEM FLAFES AVAY"; etc.
MCR-0001 Rev. 0
I GEORGIA F0WER C0!!PANY l RATCH NUCLEAR PLANT l PAGE 20 0F 65 DOCUMENT TYPE: 1 DOCUlfENT NU!CER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUllENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM l 1 8.1.2.4 Indoor Container Storage 8.1.2.4.1 Flammable or combustible liquids shall not be stored within safety related areas of the plant.
8.1.2.4.2 Only approved containers and portable tanks shall be used. tietal containers and portabic tanks meeting the requirements of. and containing products autho-rized by. Chapter I. Title 49 of the Code of Federal * '
Regulations (DOT Regulations) or llFPA 386. Standard '
for Portable Shipping Tanks. shall be acceptable.
8.1.2.4.3 Each portable tank or container shall be provided uith one or more devices installed in the top with sufficient emergency venting capacity to limit in-ternal pressure under fire exposure conditions to 10 psig (68.45kPa). or 30 percent of the bursting pres-sure of the tank, whichever is greater and a posi-tive closure mechanisu.
8.1.2.4.4 Drum storage of flammable or combustible liquids shall be in those areas designated as ficumable liquid storage areas by the General llanager and are to be located outside safety related areas.
l 112II I I I I Flammable liquids may be stored in glass containers i l of not more than one pint capacity if the required i i liquid purity would be affected by storage in a i l metal container. I l l 8.1.2.4.5 Containers for storage shall be the original contain-er or a container approved for storage of the flam-mable liquid by an independent testing laboratory such as Underwriters Laboratories. Inc. (UL) or Factory !!utual (FM). These glass containers shall be stored in an approved fireproof metal cabinet. .
IIGR-0001 Rev. O
l GEORGIA POWER COMPANY l
!!ATCH NUCLEAR PLAtlT l PAGE 21 0F 65 DOCUMENT TYPE: 1 DOCUt!ENT UUltBER:
1 ADt!INISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUttENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRA!! l 1 8.1.2.4.6 Flamnable liquids of more than 25 gallons a8gregate capacity whien are not stored within the flamnable liquids storage roon shall be stored within a metal cabinet specifica11/ opproved by UL and/or Fl! as a flaumable liquids storage cabinet. Each cabinet shall contain not nore than 60 gallons of combusti-ble liquids, including not more than 30 gallons of liquids having a flash point below 100 degrees Fahr-enheit. , ,
8.1.2.4.7 Not more than two such cabinets shall be located in any single fire area. Each cabinet shall be con-spicuously labeled "FLA!!!!ABLE - KEEP FIRE AWAY".
8.1.2.4.8 Flammable liquids storage cabinets shall not be used for storage of any material other than flammable liquids.
8.1.2.5 llandling of Flannable Liquids 8.1.2.5.1 Transfer or dispensing of flancable liquids shall be conducted at a designated area a minimun of 25 feet from the drun storage area and 75 feet from plant structures.
8.1.2.5.2 Uhen transferring liquids with a flash point belou 100*F. the containers shall be grounded and electri-cally bonded to eacn other to reduce the possibility of static spark generation.
8 .1. 2 . 5 .-3 During any transfer of flannable liquids, a neans shall be provided to control spills.
8.1.2.5.4 only approved safety containers shall be utilized for the transport of flannable liquids.
9 itGR-0001 Rev. 0
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GEORGIA POUER C0:!PA!!Y l HATCH HUCLEAR PLA!!T l PAGE 22 0F 65 DOCUMENT TYPE: l DOCUI!EUT I; UMBER: '
I ADtlINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCU!iEllT TITLE: l REVISION :
1 FIRE PROTECTION PROGRA!! l 1 S.1.2.5.5 Flannable liquids shall not be lef t unattended in those areas defined below:
Turbine Building Control Building Reactor Building Intake Structure .
Diesel Generator Building 3.1.2.5.6 Uhen activities require the use of combustible liquids in a safety related area, transport of the liquid shall be nade in its original container or a closed approved metal container labeled uith the con-tainer contents. The nininun anount necessary for the task snall be the anount transported.
8.1.2.5.7 During transfer operations, ilmmuable liquids shall be drawn from the bulk supply into approved safety cans only by gravity through a UL and/or Fil approved self-closing valve, or other neans approved by the Engineering group with fire protection responsibili-ties.
8.1.2.5.8 All flannable liquids nust be handled through use of an approved safety can provided with a flane arres-tor in the spout of the can. Under no circunstances
- is the flash arrestor to be renoved fron a safety can. Transfer or use of flannable liquids to or from containers other than approved safety cans is prohibited.
8.1.2.5.9 Each flannable liquid container shall be conspicu-ously labeled to indicate the contents of the can.
The lettering shall be yellow on a red background.
MGR-0001 Rev. 0
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GEORGIA POWER C0!!PANY l lIATCH NUCLEAR PLANT l PAGE 23 0F 65 DOCUMENT TYPE: l DOCUl21 T NU!iBER: ~
I ADtIINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: 1 REVISIO!!:
1 FIRE PROTECTIO!! PROGRAtt l 1 8.1.2.5.10 Flammable liquids shall not be handled within build-ing area where flammable vapors could accumulate unless the area of handling is provided with ade-quate mechanical ventilation to prevent such an ac-cumulation.
8.1.3 Control of Harnrdous Comoressed Cases 8.1.3.1 Control of combustible and oxidizing gases shall be main- '
tained in safety related areas and those other areas ',
designated by the General !!anager. Those gases control-led shall include, but not be limited to, the following:
Hydrogen -
combustible gas
!! app Gas - combustible gas Acetylene - combustible gas
!!etnane -
combustible gas Oxygen - oxidizing gas Chlorine - oxidizing gas 3.1.3.2 Cylinders of hazardous compressed gases shall not be located in an area where they present a fire or ex-plosion hazard to safety related cables or components, regardless of the fire suppressior. provided, unless evaluated and approved using the Transient Conbustible Permit as described in Section 8.1.1 of this procedure.
8.1.3.3 Cylinders shall be located in cool, well ventilated areas identified by use of caution signs. i.e.. "CAUTIO!!
- !!O Stt0 KING".
8.1.3.4 Cylinders shall be valved off. the protective cap in place and be in an upright position when stored.
8.1.3.5 Cylinders of flammable gases shall not be located within 20 feet of cylindera of oxidizing gases. or they shall be separated by a 1/2 hour fire barrier. This does not apply to welding apparatus using fuel gas and oxygen.
8.1.3.6 tio hot work shall be accomplished or combustibles stored within 20 feet of hazardous gas cylinders. .
MGR-0001 Rev. O
a ,
u !
s 1
GEORGIA POUER C011PAHY j l HATCH NUCLEAR PLAllT l PAGE 24 0F 65 DOCUt!ENT TYPE: -
l DOCUl!EllT NU!IBER:
1 ADMINISTRATIVE CONTROL PROCEDURE -
l 40AC-FPX01-0 DOCUMENT TITLE: ), REVISION:
I:
'u l'\ '
- FIRE PROTECTIO!! PROGRAM ,1 s."
\
3.1.3.7 Cylinders shall h,e physically restricted from fallin't by use of saf ety chains or their equivalent. '
8.1.3.8 Acetylene containers shall not be used at container pressures < 35 psig and distribution through systems (hose. piping, etc.) or any utilization of acetylene shall be maintained at pressures < 15 psig. s 8.1.3.9 0xygen regulators, hoses and accessories shall be main- , .
tained free of oil and grease. s .
8.1.4 Control of Icnition Sources /
1 Ignition sources are spark or open flane producing .,
activitier, k such as welding, grinding, flame cutting or use of portable furnaces. These activities are referred to as ILot Work '
activities. S -'-s ,
, 's 8.1.4.1 Hot Work activities shall be *sontrolled through the use of Hot flork Permits. The f ormat should be similar tog that shown in Attachment 4. Each responsible forcuan l qualified in accordance with subsectic'n 8.1.6 to issue Ilot Uork Permits shall maintain a Jog of those permits 4
(an example log page is shown as Attachment 5). The log i ,
should contain, as a nininun, the'follouing information: '
s Hot Work Permit Number Issuc Date Work Area Responsible Foreman Type of Hot Work Expiration Date -
Final Closeout Date s.
I l
ItGR-0001 Rev. 0
a I
GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT I PAGE 25 0F 65 DOCUMENT TYPE: 1 DOCU!:ENT NUMBER:
1 ADMINISTRATIVE CONTROL PROCEDURE I 40AC-FPX01-0 DOCUMENT TITLE: l REVIS TJN :
1 FIRE PROTECTION PROGRAM l 1 8.1.4.2 Each Hot Uork Permit should be assigned a unique number by the responsible Foreman and entered in the Log.
8.1.4.3 Logs established by outside contractor foremen should be reviewed once per month by the Superintendent of Retro-fit or by the Maintenance Supervisor the contractor foreman is working for.
8.1.4.4 Completed log sheets are reviewed by the appropriate , ,
supervisor, signed and dated and forwarded to Docucent ,
Control in accordance with 20AC-DCX02-0. Records Manage-ment.
8.1.4.5 A Hot Uork Permit' is only valid for one hot work activ-icy at one location.
8.1.4.6 During operational conditions, a Ho, uork Peruit may exceed a one snif t duration. if approved !v the respon-sible foreman, but shall not exceed a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duration.
2.1.4.7 During shutdown conditions, a Hot Work Peruit may be issued for the duration of a job. However, if startup commences prior to job completion, then the anximum duration shall be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as stated above.
8.1.4.8 A copy of the Hot Work permit shall be poste.d at the job activity site in a conspicuous manner and the original shal' be maintained by the responsible foreman.
8.1.4.9 Hot Uork activities being conducted in areas covered by an RUP shall have the permit posted at the access to the RWP area in a conspicuous manner.
8.1.4.10 A Fire Watch shall be provided whenever Hot Work activities are perf ormed in areas where a high potential for fire and vulnerability of plant property or equip-ment exists, and whenever fire protection systems are out of service or inoperative as required by plant Technical Specifications.
HGR-0001 Rev. O
l CEORGIA POWER COMPANY l RATCH NUCLEAR PLANT l PAGE 26 0F 65 DOCUMENT TYPE: l DOCU!IENT NUMBER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCU!IENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM l 1 8.1.4.11 A Fire Watch shall be assigned whenever Hot Work activi-ties are to be performed within 35 feet of any open cables. open cable trays, scaffold boards, papers, rags, or other flammable objects.
8.1.4.12 Fire Watches should have no other duties while assigned that duty and remain on station a minimum of 30 minutes af ter the completion of Hot Work activities to ensure no fires begin. , .
8.1.4.13 The Control Roon shall be notified prior to the start of any llot Work activities and given the location and type of activity taking place.
8.1.4.14 At the completior, of Hot Work activities, the Hot Work Permit shall be returned to the responsible foreman.
The responsible foreman vill update his log. check that all fire hazards have been removed and ensure that the Fire Uatch remains on station the required time. At the end of the required time, the Fire Ustch shall return any portable fire extinguishers to the responsible foreman for return to its proper storage location.
8.1.4.15 Uhen a Hot Work Permit is issued as part of a Mainte-nance Work Order (MWO) a copy of the permit should remain with the Inf0 package. All other copies uay be destroyed after being retained for 30 days after the completion of the Hot Work activity.
8.1.4.16 At the completion of l'o't Work activities, the Control Room shall be notified.
8.1.4.17 An inspection shall be performed by the Health Physics and Chemistry Department prior to perf orming Hot Work activities on previously pressurized systems or tanks that have contained combustible, flammable or volatile substances to ensure a safe work environment exists. Authorization. based on the survey. for work to begin will be given by a member of the Engineering group with fire protection responsibilities on the Hot Work Permit. .
HGR-0001 Rev. 0
s l
GEORGIA POUER C0!!PANY l itATCH NUCLEAR PLANT l PAGE 27 0F 65 DOCUl:ENT TYPE: l DOCU![ENT NUMBER: '
I ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: 6 REVISION:
1 FIRE PROTECTION PROGRAM l 1 8.1.4.18 Ilot Uork activities shall be controlled in all build-ings on site except for those areas designated as llot Uork Areas. Those areas are:
Service Building !!aintenance Shop Service Building Test Shop "llot" !!achine Shop , ,
Ueld Test Shop (Bldg. 10)
- Cooling Tower Repair Shop Contractor Building (UKI)
Building 15 Building & Grounds Tire Shop 3.1.4.19 A menber of the Engineering group with fire protection responsibilities. Quality Control Section or a Supervisor qualified as a Fire Brigade nenber shall confirm and countersign all llot Uork Permits when an authorized forenan determines a Fire Uatch is not required.
8.1.4.20 Measures shall be established to ensure that the debris f rom welding, cutting and grinding is contained within the work area by covering all openings. equipment, and the floor.
8.1.4.21 Additional personnel may be required in adjoining areas if sparks and debris can spread through open grating or other similar openings.
MGR-0001 Rev. 0
1 GEORGIA POW'ER C0!!PA!!Y l IIATCH NUCLEAR PLAIiT I PAGE 28 0F 65 DOCUMENT TYPE: l DOCU!'ENT hUllBER:
I ADMINISTRATIVE CONTROL PROCEDifRE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISIO!!:
1 FIRE PROTECTION PROGRAM l 1 8.1.4.22 Fire barriers may be necessary in some cases to reduce the possibility of fire.
8.1.4.23 Hot Work activities performed uithin 50 feet of any com-bustible structure (Cooling Towers. etc.) flammable or combustible gas or liquid storage areas, oil filled transf ormers or exposed electrical cables, shall be con-trolled and a Fire Uatch established in accordance with this procedure. , ,
8.1.4.24 Combustible materials below or within 35 feet of the work area shall be renoved. If removal is impossible, then adequate protection shall be provided. i.e. fire retardant curtains. metal guards, flameproof covers, etc.
8.1.5 Traininc Plant personnel assigned as Fire Uatches shall receive the training specified in this subsecticn or have received training necessary to be a member of the Fire Brigade or Fire Emergency Support Group.
8.1.5.1 Hot Work Permits 8.1.5.1.1 Foremen required to issue Hot Uork Permits shall receive classroom training covering, but not liutted to the following areas:
Fire Hazard Recogniton
. Identification of Class A. B or C fires Proper selection, use and operation of portable fire extinguishers Fire theory Issuance of Hot Works Permit 1
MGR-0001 Rev. 0
a I
GEORGIA POUER COMPAMY l 11ATCH NUCLEAR PLA3T l PAGE 29 0F 65 DOCUMENT TYPE: l 00CULENT !!UCDER: -
I ADt!INISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: 1 REVISIOU:
1 FIRE PROTECTIOM PROGRAM l 1 0.1.5.1.2 The instructor vill maintain a record of trained per so nne l .
3.1.5.2 Fire Watch S.I.5.2.1 Classroon instruction shall be provided on, but not limited to the following:
Identification of Class A. 3 and C fires - -
3 Types and uses of pcrtable fire extin;uishers and -
their locations Procedures for soundin; fire alarms Evacuatica of personnel G.I .5.2.2 Hands-on training shall be provided to instruct personnel in the proper use of hand held fire extinguishers.
8.1.5.2.3 A record of trained personnel uill be naintained by tne fire ustch instructor.
i UCR-0001 Rev. O
GLORGIA POUER C0!!PANY l HATC11 NUCLEAR PLA!!T I PAGE 30 CF 65 LOCUIEllT TYPE: ! DOCU!E T I!IJ:3 E". : -
I ADI!IlilSTRATIVE COIITROL ? ROC"OULE i 40AC-FPX01-0 DOCUt:E!!T TITLE: i OVISIOU:
I FF.C Pit 0 TECTI 0ii PROGRA'! l 1 C.2 EFFECTIVE iiX!DLI; C OF FIRE EllERG5i.CIES Effective handlin3 of fire ener3cncies is also an objective or tr.e Fire Protection Prc3ran. This objective is accouplished through fire ;er tection systens and equipment, or;anizing and traiutug a fire bricace and preplanning for fire energencies.
3.?.1 Fire Prctection Systens and Enuinment T..e active fire protection systens and the passive fire -
- arriers installed at Plant listch provide addicional levels of safety required in order to achieve tne fire protection necessary for cae naintenance of public nealth and safety.
G.2.1.1 Automatic suppression systeus snall be providea in all areas or the plant as retiuired by the fire ianard safety analysis.
b.2.1.2 The extin5;uishing systens chosen shall be based upon the desi;n para:..eters required as a result of the fire ha:-
arc. an.41yais. Uhen the rire uanard analysis shous that a tixed extinguisning syste:. is needed, the require::.ents of :TPA-803 and 10CFt:50 Appanui:: t., criterion 3 shall be used in selecting the type of systen or couaiantion of systen:s to be installed.
MGR-0001 Rev. 0
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GEORGIA POWER COMPANY l IIATCl! NUCLEAR PLANT l PAGE 31 0F 65 DOCUMENT TYPE: l DOCUMENT NUMBER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
I FIRE PROTECTION PROGRAlt l 1 8.2.1.3 Selection of extinguishing agents shall be based on the following:
Type or class of hazard Effect of agent discharge on equipment in area Health hazards to personnel in discharge area 8.2.1.4 Each fire suppression system shall be equipped with .
approved alarm devices which alarm in the Control Room.
if required.
8.2.1.5 All shut-off valves controlling fire suppression systems shall be supervised by one of the following methods:
Electrical supervision with audible signal Locking mechanisms for maintaining valves in the open position 8.2.1.6 All fire protection systems and components are removed from service for maintenance and repair in accordance with-30AC-OPS 01-0. Control of Clearances and Tags.
8.2.1.7 Surveillances on fire protection systems and components shall be performed in accordance with the Technical Spec-ifications for Units 1 and 2 and as described in 40AC-REG 01-0. Technical Specifications Surveillance Pro-l gram.
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I
- 8.2.1.8 All modifications to plant systems or components shall be reviewed by the Engineering group with fire protection
~
responsibilities to ensure that adequate levels of fire protection are maintained. Modifications shall be performeu in accordance with 40AC-ENG03-0. Design Control.
8.2.1.9 }bintenance on fire protection systens shall be per-formed as described in 50AC-MNT01-0. Maintenance Program.
Personnel who perform maintenance on fire protection systems or equipment shall be trained in accordance wiqh 70AC-TRN01-0. Plant Training Program.
}ER-0001 Rev. 0
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l GEORGIA POUER C0KPANY l HATCH NUCLEAR PLANT l PAGE 32 0F 65 DOCUMENT TYPE: l DOCUMENT NUMBER: '
I ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION :
1 FIRE PROTECTION PROGRAM l 1 8.2.1.10 Fire barriers shall be installed, as necessary, to per-form as a minimum the following functions:
To separate redundant trains of safety shutdown equipment To isolate safety related systems from fire hazards in non-safety related areas To prevent the spread of fires , ,
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8.2.1.11 Breaching of fire barriers or penetration seals shall require alternate forms of fire protection and a Fire Watch to be established as required by the Technical Specifications.
8.2.1.12 Active fire protection systens at Plant Hatch consist of the following:
8.2.1.12.1 Uater Supply - water is provided through looped underground piping to all fixed water suppression systems. hose stations and yard hydrants by three 2.500 gallon per minute fire pumps (one electric and two diesel driven) and two 300.000 gallon ground level storage tanks.
8.2.1.12.2 Fire hydrants and standpipes are spaced along the yard main at approximately 250 foot intervals.
Hose houses have been erected at key locations on the site grounds and standpipes are located at strategic points throughout the plant interior in-
. side normally occupied areas and at or near the entrance to normally unoccupied areas.
8.2.1.12.3 Spray / sprinkler systems are used to protect against hazards involving combustible liquids and/or group-ed electrical cables.
ItGR-0001 Rev. 0
U l
GEORGIA F0WER COHPANY l HATCH NUCLEAR PLANT l PAGE 33 0F 65 DOCUMENT TYPE: l DOCUtENT NUMBER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: 1 REVISION:
_ l FIRE PROTECTION PROGRAM l 1 8.2.1.12.4 Carbon dioxide (CO2) total flooding systems have been provided in each diesel generator room and fuel tank roon. These systens are automatically actuated by thermal detectors or manually. Manual-ly operated total flooding CO2 is provided in the Cable Spreading and Computer roons in the Control Building. Manually operated CO2 hose reels are also provided at strategic locations throughout the plant.
Halon 1301 total flooding systems are used in areas 8.2.1.12.5 such as the warehouse storing Quality Assurance (QA) records and in the Service Building area housing QA records. Each systen has reserve capacity for a second discharge.
8.2.1.13 Portable fire extinguishers that contain water, water / antifreeze or foan should not be used on ener-gized electrical equipment.
8.2.1.14 Multipurpo *e dry chemical is not recommended for installation in locations having sensitive electronic equipment due to the potential for damage from the dry chenical and its decomposition products on that type of equipuent.
8.2.1.15 002 units equipped with netal horns should not be used on fires in energized ciectrical equipment.
8.2.1.16 Carbon dioxide hand hoselines shall not be used in
~
normally inhabited enclosures unless provisions for evacuation (alarm annunciation. etc.) are nade before use.
8.2.1.17 Where sensitive electrical control equipment is in-volved, due consideration shall be given to the effects of thermal shock on the operability of this equipment when using carbon dioxide hand hoselines.
FER-0001 Rev. O
V l
GEORGIA POUER C0!!PANY l KATCH NUCLEAR PLANT l PAGE 34 0F 65 DOCUIENT TYPE: l DOCUfEt:T I; UMBER:
I ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION :
1 FIRE PROTECTION PROGRA!! l 1 8.2.1.18 The use of hand hoselines involving water or energized
~
electrical equipment shall take into consideration:
The voltage of the equipment.
The type of water stream used i.e. solid vs. spray.
The effect of electrically conductive water on the operability of the equipment. -
The most probable distance between the fire fighter and -
the energized electrical equipment.
The location of energized electrical equipment in the drainage path that is likely to be encountered when water is used.
8.2.1.19 Equipment purchased for fire protection measures shall only be used for those purposes. These include items such as water hose, spanner wrenches, nozzles. ladders, portable foam equipment, and protective clothing.
8.2.1.20 Portable extinguishers will be labeled indicating the type of fire for which it is intended. "
8.2.1.21 Persons t,orking in the area of any portable er.tinguishers shall be f eniliar with the location and use of such equipment and the equipment's limitations.
8.2.2 Fire Briande and Fire Emercency Suonort Groun (FESG)
A ch' art showing the organization, lines of communication and general responsibilities is provided as Attachment 6.
8.2.2.1 The Fire Brigade shall consist of Shift Supervisors and Plant Equipment Operators who are qualified in accord-ance with this procedure.
I 11GR-0001 Rev. 0
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l GEORGIA POWER COMPANY I RATCH NUCLEAR PLANT l PAGE 35 0F 65 DOCUMENT TYPE: 1 DOCUllEt;T NUi1BER:
I ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMEtfT TITLE: 1 REVISION:
1 FIRE PROTECTION PROGRAM l 1 8.2.2.2 The Fire Brigade shall consist of a minimum of five qualified persons. A minimum of three of these persons shall have competent knowledge of safety related systems and components. One of these should be the Fire Brigade Chief. Personnel assigned to the Fire Brigade shall not be necessary to fulfill the minimum shif t crew composi-tion requirements.
8.2.2.3 The Unit 2 Shift Supervisor shall act as Fire Brigade Chief during a fire, provided he is a qualified Fire Brigade member. If he is not qualified. then he shall be replaced by the Unit 1 Shift Supervisor.
8.2.2.4 The FESG shall be comprised of personnel selected from other Plant Hatch departments outside the Operations Departuent.
8.2.2.5 The purpose of the. Fire Emergency Support Group is to support the Fire Brigade as necessary with additional manpower and equipment.
8.2.2.6 Fire Brigade and FESG members shall meet the following minimum qualifications:
8.7.2.6.1 Each member shall be subjected to an annual physical examination and respirator qualification.
8.2.2.6.2 Members shall complete a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> initial training program and retraining classes as scheduled.
8.2.2.6.3
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Members shall participate in scheduled and un-scheduled drills and practices.
8.2.3 Fire Bricade and FESG Trainine Procram This program will be composed of an initial instruction program followed by classroom retraining and live fire practice sessions.
The initial instruction program provides approximately 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> of classroom training and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of field practice.
FER-0001 Rev. O
o I
GEORGIA POUER COMPAtlY I HATCH NUCLEAR PLANT l PAGE 36 0F 65 DOCUMENT TYPE: 1 DOCUMENT UUMBER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: 1 REVISION:
1 FIRE PROTECTION PROGRAM l 1 8.2.3.1 Classroom lectures shall include, but not be limited to.
the following areas:
Fire protection organization Fire behavior Fire extinguishers Fire hoses, hose stations and equipment Foam equipment Automatic suppression systems Fire fighting methods and agents - -
Emergency breathing devices Ventilation and lighting Forcible entries Emergency exits and first aid
- Communications Emergency implementing procedures Storage, use and hazards of flammable gases and combustible liquids Salvage operations Personal protective clothing S.2.3.2 Field practice includes, but is not limited to eight hours or training in hose handling techniques, fire fighting equipment use and extinguishing live Class A and B fires and simulated Class C fires.
8.2.3.3 Quarterly classroom retraining shall be conducted such that all lectures covered in initial training are repeated over a two year cycle.
8.2.3.4 ;An annual practice session snail be conducted that provides brigade and support group members with hands-on experience in hose handling techniques. fire fighting equipment use and breathing apparatus use in heavy smoke concentrations. This training shall be conducted on live Class A and B fires and on simulated Class C fires.
All members shall attend a mininum of one of these sessions per year.
FCR-0001 Rev. 0
U l
GEORGLA PtWER C0tlPANY l HATCH :"JCLEAR PLANT l PAGE 37 0F 65 DOCUhENT TYPE: l DOCU! INT flUllBER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUfEN'T TITLE: l REVISION:
1 FIRE PROTECTI0t! PROGRAM i 1 8.2.4 Leadershin Trainine Procram Leadership training shall provide the Fire Brigade Chiefs and the Fire Emergency Support Group leaders with the fundamentals necessary to command their personnel and to eff ectively control fire incidents. Fire Brigade and Fire Emergency Support Group Leadership Training includes, but is not limited to, the following:
Critical Factor Analysis Fire Fighting Systems ttodel -
Time Constraints Fire Incident Command Tactics for Fire Control General Tactical Principles Special Hazards Tactics 8.2.5 Drills 8.2.5.1 Drills should, as a minimum, include the following:
Assessment of fire alaro effectiveness, time required to notify and assenble Fire Brigade, and selection, place-ment, and use of equipment and fire fighting strategies.
Assessment of each brigade member's knowledge of their role in the fire fighting strategy for the area assumed to contain the fire. Assessment ot the brigade menber's confidence with established plant fire fighting equipment, including self-contained emergency breathing apparatus,
, communication equipment, and ventilation equipment, to the extent practicable.
PER-0001 Rev. O
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l GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT l PAGE 38 0F 65 DOCUMENT TYPE: 1 DOCUl:ENT UUMBER:
I ADMINISTRATIVE CONTROL PROCEDURE I 40AC-FPx01-0 DOCUMENT TITLE: l REVISION :
1 FIRE PROTECTION PROGRAM l 1 The simulated use of fire fighting equipment required to cope with the situation and type of fire selected for the drill. The area and type of fire chosen for the drill should dif fer from those used in the previous drills so that brigade members are trained in fighting fires in various plant areas. The situation selected should simulate the size and arrangement of a fire that could ceasonably occur in the area selected, allowing for fire development due to the time required to respond, to obtain equipment, and organize for the fire, assuming
- loss of automatic suppression capability.
Assessment of brigade leader's direction of the fire fighting ef fort as to thoroughness. accuracy, and ef fec-tivene s s.
8.2.5.2 Drills shall be preplanned, the objectives documented, and a critique held at drill completion documenting the results in terms of the preplanned objectives.
8.2.5.3 The types of drills held at Plant Hatch are:
Preannounced Drills - drills performed on a random basis to evaluate the ef fectiveness of plant prefire plans. Fire 3rigade and Fire Emergency Support Group.
Walk-thru Drills - drills perturmed on a random basis to f amiliarize brigade and FESG members uith fire suppression equipment activation, operation and location.
Hazards that may be encountered during a fire of the
, type being simulated should also be addressed.
Unannounced Drills - drills that are performed for each shift at least once per year and are used to evaluate the readiness and effectiveness of Fire Brigade and FESG response. These drills are to be as realistic as possible and the use of charged hoselines, full protective gear and self-contained breathing apparatus should be applied where possible.
8.2.5.4 Unsatisfactory drill performance should be followed by a repeat drill within 30 days.
IGR-0001 Rev. O
l l GEORGIA POWER C0hPANY l l HATCH NUCLEAR PLANT l PAGE 39 0F 65 l DOCUMENT TYPE: 1 DOCUlIENT NUtIBER:
1 ADt!INISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0
~
DOCUMENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM l 1 Drills should provide for local fire department partici-
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8.2.5.5 pation periodically (at least annually).
8.2.5.6 At 3-year intervals, a randomly selected unannounced drill shall be critiqued by qualified individuals independent of the licensee's staff. A copy of the written report from such individuals will be available for review.
8.2.6 On an annual basis, local fire departments will be of fered -
orientation in radiation safety and security. Members of these departments receiving radiation safety and security training will also be given a tour of the f acility with emphasis on special hazards associated with a nuclear power plant.
3.2.7 Instruction shall be provided by qualified individuals trained in fighting the types of fires that could occur in a nuclear power plant. and in using the types of equipment available at Plant Hatch.
8.2.8 Prefire plans shall be written for fires that may occur in specific areas of the plant. Prefire plans shall address the following subjects as a minimum:
Fire hazards in the area Fire extinguishing agents to control fires involving those hazards and the location of those agents Most favorable direction from which to attack a fire in that area considering ventilation direction access hall-ways, stairs and doors Access and exit routes, especially those involving locked doors. should be identified and the appropriate methods and precautions specified Plant systems that should be managed to reduce the damage potential during a local fire and the location of remote and local control stations .
}ER-0001 Rev. O
s i
GEORGIA POWER C0!!PANY l HATCH NUCLEAR PLANT l PAGE 40 0F 65 DOCUMENT TYPE: l DOCU!IENT NUf!BER:
1 ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMEN'T TITLE: l REVISION:
1 FIRE PROTECTION PROGRAM l 1 Vital heat-sensitive equipment that must be kept coo l, particularly hazardous combustibles Organizational duties of Fire Brigade members and the FESG should they be needed Radiological and toxic hazards in the area Ventilation system operation that ensures desired plant air distribution when flow is modified to contain the -
fire Instructions for Fire Brigade personnel and Fire Emergency Support Group .
8.2.9 The Engineering Group with fire protection responsibilities shall prepare the prefire plans in accordance with Engineer-ing Department instructions.
8.2.10 Revisions to prefire plans shall be requested on a form similar to that shown in Attachment 7. Revision requests shall be reviewed by the Engineering Group uith fire pro-tection responsibilities and changes to prefire plans that result will be made by that group in accordance with Engi-neering Department instructions. Disapproved requests shall be returned to the requestor with an explanation.
8.2.11 Prefire plans shall be maintained and distributed by the Document Control group in accordance with 20AC-DCX01-0.
Document Distribution.
8.3 MAINTAIli1NG PROGRAll INTEGRITY The intent of this section is to outline those measures which are established to ensure that all aspects of the Fire Protec-tion Program are effectively maintained. These measures in-clude the control of plant modifications which could af fect the fire protection designed into the plant and the control of fire protection systems and equipment, including system impairments and outages. test, inspection, surveillance, and maintenance.
FER-0001 Rev. 0
a I
GEURGIA POWER COMPAliY l RATCH NUCLEAR PLANT l PAGE 41 0F 65 DOCUMENT TYPE: 1 DOCUMENT MUISER:
1 ADMINISTRATIVE CONTROL PROCEDURE I 40AC-FPX01-0 DOCUMENT TITLE: l REVISION :
1 FIRE PROTECTION PROGRA!! l 1 8.3.1 Control of plant modifications is accomp? ! . d tarough the use or .
.e control procedure 40AC-ENG03-0. Design Control.
8.3.1.1 Modifications made to facility structures. component s , y or systens shall be evaluated by the Engineering group g for fire protection to assess changes in the degree of 'z fire hazard in the affected area. The evaluation should 1 consider. but not'be limited to, the following: \
\-
Obstructions to fire detection or suppression systems Breached fire barriers (doors, ducts, cable penetrations, i etc.) y New fire protection system requirenents including single failure criteria Impact on fire brigade prefire plans Separation criteria as defined in Section III.G of 10CFR50.48. Appendix R 8.3.1.2 Completed nodifications shall be analyzed for their impact on the Fire Hazards Analysis perforced for Plant Hatch and the analysis updated if appropriate.
8.3.2 Fire protection systems and components are removed f rom service in accordance with 30AC-0PS01-0. Control of Clear-ances and Tags.
8.3.2.1 "The Limiting Conditions of Operations specified in plant Technical Specifications shall be adhered to whenever a fire protection system or component is removed fron service for repair or modification.
!%R-0001 Rev. 0
a l
GEORGIA POWER C0!!PANY I RAICH hUCLEAR PLAllT l PAGE 42 0F 65 DOCU!ENT TYPE: l DOCU!!Et4T !!Ut:BER:
I ADt11!!ISTRATIVE CONTROL PROCEDURE i 40AC-FPX01-0 l REVISI0li:
~
DOCUMENT TITLE:
1 FIRE PROTECTION PROGRAll l 1 8.3.2.2 Temporary protection to cover those areas r'emoved f rom service is provided in accordance with the applicable Technical Specifications. These temporary protection measures include, but are not limited to, the following:
Portable fire extinguishers Live hoselines Establishing a Fire Watch Curtailing hazardous operations 8.3.3 Surveillance activities on fire protection systems cr components shall be conducted in accordance with 40AC-REG 01-0. Technical Specifications Surveillance Program, and the Final Saf ety Analysis Report (FSAR).
8.3.4 ltaintenance activities shall be performed by persons trainea in the repair and maintenance of fire protection components in accordance with 50AC-II!!T01-0. !!aintenance Program.
3.4 FIRE ElIERGEllCY OPERATIO!!S Control Room operators can become aware of a fire in their unit tnrough several sources. If a fire actuates fire detection or suppression systems alarms will be received automatically in the Control Room. The decision to call for the assistance of local fire departments lies with the Fire Brigade Leader.
8.4.1 Plant personnel discovering a fire shall call the Control Room and provide the following information:
Type fire - Class A. B. or C Location of fire - As specifically as possible
!!easures taken to contain the fire 8.4.2 Control Room personnel receiving notification of a fire within the plant area shall take the following action: .
MGR-0001 Rev. 0
U l
GEORGIA POUER COMPA:1Y l HATCH NUCLEAR PLANT l PAGE 43 0F 65 DOCUMENT TYPE: l DOCU!IEllT NUMBER:
I ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
_ l FIRE PROTECTION PROGRAM i 1 8.4.2.1 Sound the fire alaru (SIREN) over the plant' PA system and announce:
ATTENTION. THERE IS A FIRE IN (here specify exact location, such as; unit number, building name. floor elevation and equipment affected). FIRE BRIGADE RESPOND.
Repeat the announcement two more times.
8.4.2.2 t;otify the Operations Supervisor on Shift'or Shift Super- -
visor that a fire has been reported. Specify type and exact location.
8.4.3 Notify the Health Physics section.
8.4.4 If tne fire situation warrants inititate the appropriate Emergency Impleaenting Procedure.
8.4.5 One individual should be assigned to perform the following functions:
Establish and maintain two-way coumunications between the
! bin Control Room and the Fire Brigade.
If the fire occurs on a backshif t. ueekend or holiday, no-tify Security Headquarters to initiate the Emergency Call List, if necessary.
tionitor fire status and notify the Operations Supervisor on Shift or Shift Supervisor of changes that might affect plant or unit operations.
8.4.6 Onerator Actions 8.4.6.1 If the fire involves an area or equipnent that could affect plant operations, the Unit 1 and Unit 2 Control Room operators shall monitor unit / plant parmaeters and shall notify the Operations Supervisor on Shif t or Shif t Supervisor of any unusual or abnormal indications which might occur.
FER-0001 Rev. O
I I
GEORGIA POUER C0!IPANY l HATCH NUCLEAR PLANT l PAGE 44 0F 65 DOCUMENT TYPE: 1 DOCUMENT i;U!BER:
I ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
1 FIRE PROTECTION PROGRA!! l 1 8.4.6.2 If the fire occurs inside a nain poverblock' building. the Radwaste System Operators shall ensure that floor drain sump pumps for the affected building are in automatic and notify the IIain Control Room when the action is con-pleted.
8.4.7 Plant Enuinnent Onerators Upon hearing the fire alarm and announcement over the PA system. Plant Equipment Operators shati: - -
8.4.7.1 Inmediately report to the nearest available Fire Equip-ment Emergency Locker.
S.4.7.2 Don his/her turnout gear and self-contained breathing apparatus.
3.4.7.3 Secure appropriate fire equipment.
8.4.7.4 Proceed to the fire area and nake contact with the Fire Brigade Chief for further instructions.
tiGR-0001 Rev. O
.'.TTACE!:CI.T ,,l_, i
! Pi.ch 45 cr r.5 1 __
c:,Ont;1A twLn CD:.in;;y l ..TTACO:2.i *. :
~: *n CH . U CL*.1.it PL!.i:T l Pl.Gli 1 OP 3 i__
PCCUhE: ~1 TTP * * ' CU: D.1:Y . U:'.ir..l:
AD:ll :leTEl.TIVE CO'! TROL PROCEDURE i M. AC-FP::61-0 1
DOCUhEi:T TITLE: 1 REVISIO!;:
PICE Pn0TECTIO;! Ph0GRA11 l 1 I
ATTACE:!EI.T TITLE:
TRA!:SIEi:T C01.nUSTI3LE PEnl:IT INSTRUCTIOHS 31ock 1 - The date the permit will expire - assigned by the Engineering Group uith fire protection responsibilitics.
Block 2 - The permit number - assigned by the Engineering Group '
with fire protection responsibilities. ',
Block 3 - List the materials to be stored. Provide cny additional information t~nat nay be useful such as flash point of
=aterial or-boiling point.
Block 4 - List the quantities of each material to be stored.
Block 5 - Provide an accurate description of the location uhere the unterials are to be stored.
Block 6 - A nenber of the Engineering Group with fire protection responsibilities will calculate the fire load using a departmental instruction.
Block 7 - !! ember of Engineering Group with fire protection responsibilities - perform fire load calculations check appropriate block.
Block 8 - Check appropriate block i
Block 9 - Engineering group with fire protection responsibilities -
list any additional. extinguishing equipnent necessary.
Block 10 - Fleuber of Engineering Group with fire protection responsibilities - complete permit. sign and date.
i Block 11 - General !!anager sign and date, if required.
Block 12 - Date individual returns posted copy of permit and notifics Engineering Group with fire protection responsibilities that area is clear of trcnsient combustibics brought in, under that permit.
!:GR-0009 Rev. O
ATTACHIENT l___ l l PAGE 46 0F 65 ,
I GEORGIA POWER COMPANY l ATTACHIE!!T: ~
HATCH NUCLEAR PLAllT l PAGE 2 0F 3 .
I DOCU)ENT TYPE: l DOCU!ENT NUllBER:
ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 l
DOCUIEllT TITLE: l REVIS10ti:
FIRE PROTECTION PROGRAMS l 1 l
ATTACH}ENT TITLE: ..
TRANSIENT COMBUSTI3LE PERMIT Block 13 - Signature of member of Engineering Group with fire protection responsibilities confirming removal of transient combustibles covered by this permit and date of verifica-tion.
4 i
MGR-0009 Rev. O i
I
i ATTACH!!ENT __1 l l PAGE 47 0F 65
HATCH NUCLEAR PLANT l PAGE~3 0F 3 -
I DOCU!ENT TYPE: 1 DOCUMENT NU!IBER:
ADI:INISTRATIVE CONTROL PROCEDURE I 40AC-FPX01-0 i
DOCUIINT TITLE: l REVISIO!!:
FIRE PROTECTION PROGRAM l 1 l
ATTACHMENT TITLE:
TRA!!SIENT COMBUSTIBLE PERitIT GEORCIA F0VER CD:' Patly l RATCit NUCLEAR FLA:lf l PACE 1 0F 1 I
FOR t TITLE:
TRANS1ENT Cott&UST13LE PERIIIT EXF1'AT10tl DATE b Peruit fle. b Material to be stored b ,
Quantity to be stored b Specific location of storage b Fire Lead Calculations h
@ireLoadClassification lav 0, , sisb**O
@af sty Related-drea'1'aiot Tes**Q uo 0
@ al rio E shis EkulpaegtEquired ys .
(OSCompl 8y Detet J J
% a
- tt0TE: If the hasard is la a safety related area of the plant and is calculated above a low f are load classification. General Manager approvat mast be obtained to asistain the basardous esterial in that area.
b General Manager Approval Date Original copy of this pemit is maintained by the Engineering group with fire .otection reponsibilities. The copy of this per: sit post-ed at tb aark area is to be returned when no lon;er needed to the Engineersag group with fire protection respoesi'silities. af ter re-moval of materials.
Permit copy returned on Date Q Area inspected and confimation of renoval I of transnent conbustible By Date E!:C-9002 MGR-0009 Rev. 0
e ATTACH!ENT _.2_ l l PAGE 48 0F 65 l
GEORGIA POWER COMPANY l ATTACHMENT:
RATCH NUCLEAR PLANT l PAGE 1 0F 2 I
DOCUMENT TYPE: l DOCUIE!IT NUl!BER:
AD!!iNISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 l
DOCUIEllT TITLE: l REVISION:
FIRE PROTECTIO!! PROGRA!! l 1 l
ATTACHMEllT TITLE:
TRA!!SIENT COMBUSTIBLE PERllIT LOG INDEX INSTRUCTIONS Block 1 - Permit number assigned ,
Block 2 - Name of person permit issued to . -
Block 3 - Location of transient combustibles Block 4 - Name of person t' rom Engineering Group with fire protection responsibilities issuing permit.
Block 5 - Date permit issued Block 6 - Date posted copy of permit returned to Engineering Group with fire protection responsibilities.
Block 7 - Name of person from Engineering Group with fire protection responsibilities inspecting area for removal of transient combustibles.
Block 8 - Date area inspected.
Block 9 - Any pertinent remarks deemed necessary or helpful.
1 MGR-0009 Rev. 0
a i
l ATTACit:IIIT _.2_. l l PAGE 49 0F 65 l I
GE0 NGL \ PO!!En C0;:PA!!Y l ATTAC1'II:!T: .
!!ATC!i IUCLEAR PLA;iT l PAGE 2 0F 2 1
DOCU:iE::T.._ TYPE : l DOCU:.E?;T liUliBER:
AD;1IIIIST2ATIVE C0?iTROL PROCEDURE I 40AC-FPX01-0 l
DOCU:II!T TITLE: l REVISIOll:
FIRE PROTECTIO:1 PROGRA!! l 1 1
ATTACHMEliT TITLE:
TRA;!SIENT C0:1!iUSTI3LE PER!!IT LOG II;DEX CE0tC!.i PO'l;; CO JA: Y l IL\TC:! .1JCLLU; FUJ:T l FACE 1 0F 1 t
FLA:1 TITLE:
T LJ SIC:t COPSUSTISLE FIR :IT LOG 1:DEX FEA:!IT 210 1 ISSr!3 !O l LOC.T103 I ISSLID 3Y l DATC I DAT; RET. I 1:'SF. 8Y I DATE 1 K C' \.".;3 f f f f f f ' !
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C C-drVs l
- CR-0009 liev. O
i
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ATTACHIENT _,3_ l l PAGE 50 0F 65 '
l p GEORGIA POWER CollPANY l ATTAClllENT:
HATCH NUCLEAR PLANT l PAGE 1 0F 2 -
I DOCUIENT TYPE: l DOCUMENT NUMBER:
ADt!INISTRATIVE CONTROL PROCEDURE I 40AC-FPX01-0 i
DOCUMENT TITLE: l REVISION:
FIRE PROTECTION PROGRAM l 1 l
ATTACHMENT TITLE:
WEEKLY FIRE INSPECTION REPORT INSTRUCTIONS Block 1 - Inspector checks appropriate hazard found.
Block 2 - Describe location of hazard. . -
Block 3 - Identify the responsible department. section or group.
'41ock 4 - Inspector should note any hazards or discrepancies found on his tour of a general nature pertaining to fire pro-tection.
Block 5 - Specify actions taken or proposed to correct problems identified, such as clean the area move blockage, or initiate a Deficiency Report.
Block 6 - Inspector confirming that corrective actions have been completed sign and date.
Block 7 - Inspector sign and date inspection report.
1 l
l l
- l l !
4 i
!!CR-0009 Rev. 0 1
B l
l ATTACH!!ENT _3_ l l l PAGE 51 0F 65 '
I .
GEORGIA POUER C0!!PANY l ATTACH!ENT: '
HATCH NUCLEAR PLANT - l PAGE 2 0F 2 - l DOCUMENT TYPE: l DOCUIENT NUMBER:
ADt!INISTEATIVE CONTROL PROCEDURE l 40AC-FPX01-0 i l
DOCUMENT TITLE: 1. REVISION: l FIRE PROTECTION PROGRAM i 1 i
ATTACllt!ENT TITLE:
WEEKLY FIRE INSPECTION REPORT GEORCIA F0WER CoitFANY l RATCH NUCL*.Aa PLANT l FACE 1 0F 1 t
FORM TITLE:
WEEKLY FIRE INSFECTION REPORT FIRE RAZARD IDENTIFIED @ 1OCATIO!! RE5FC:fS13tLITY , ,
Cutties. grindias. welding 0 b 'b -
Electrical agulpoest 0 Flammable 11guid 0 Combustible liguid 0 Foor housekeeping 0 Seeking La unauthorised area O Blocked or impaired fire doors 0 Blocked or impaired '0 extinguishing equipment stations taproper use or storage of 0 safety cans or containers for flaneable and combustible 11guids .
m m eq . - - ,
Proyama est,1fi&d (General)
'g 6 a Cochtio#A.st-. c, ed., J, altlake's@
Corrective Actions Coefirmed Couplete b I Date laspection Performed By: b Date Forward a ccpy of this report to the af fected department, section or i group. The original as to reasia on file with the Engineering group having f 8re protection responsi'uilities.
ENC-0013 ,
!!GP.-0009 Rev. O
t ATTACH 12NT _,4_, -l l PAGE 52 0F 65 1
GEORGIA POWER CutIPANY l ATTACH!ENT:
- HATCH ?!UCLEAR Pk1NT l PAGE 1 0F 2 -
l DOCUMENT TYPE: l DOCUMENT NUMBER:
AD!!INISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 l
DOCUtENT TITLE: l REVISION:
4 FIRE PROTECTION PROGRAM i 1 1
4 ATTACHNENT TITLE: .
HOT WORK PERMIT INSTRUCTIONS Block 1 - Permit number.
Block 2 - The effective date and expiration date.
Block 3 - Shift work is to be started on.
, Block 4 - The name of the person the permit is being issued to. -
Block 5 - Issuing foreman's name.
Block 6 - Description of location where work will be performed.
Block 7 - Type of hot work activity to be performed.
Block 8 - Fire watch required. If Yes print Fire Watch's name and provide him with the proper portable extinguishing equipment.
Block 9 - If a Fire Watch is not required, a supervisor qualified as a member of the Fire Brigade, a Quality Control Specialist, or a member of the Engineering Group with fire protection responsibilities must evaluate the work and concur with the foreman's evaluation by signing and dating the form.
Block 10 - Special precautions necessary such as fire barriers or fire retardant cloths or equipment to be moved.
Block 11 - Exti~nguisher required? If portable fire extinguish-i ers are provided to the Fire Watch, list the quantity and type provided.
. Block 12 - Inspecting foreman's signature and date. Notify Control Room that work is to begin. A member of the Engineering Group with fire protection responsibilities will sign.
authorizing work to begin on previously pressurized systems t i
that have contained combustible, flaneable or volatile i liquids. ,
IIGR-0009 Rev. 0
I i
ATIt.CitLIT _,4_ l l PACE 53 or 65 l -
GL01;GIA POUER C01:PA!;Y l ATTisClllIIlT:
- 1;ATC11 1:UCLEAR PLA!:T ! Pt.GE 2 0F 3 1
LOCUl!E;iT TYPE: 1 LOCUlli:T 1:UhDTR:
AIXIII:ISTRATIVE C0llTROL PROCEDURE I LOAC-FP;:01-0 1
- LOCU:1!!T TITLE: l REVISIO!!:
FIRE PROTECTION PROGRA}l l 1 i
ATTACll!!E!1T TITLE:
HOT WORK PERIIIT Llock 13 - Foreman taking charge and accepting responsibility for hot work activity sign date, time and shift after notifying Control Room. if extended past one shift.
Block 14 - Fire Watch's signature and date. #
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i I:GR-0009 Rev. 0
i ATTACi!!I:iT _4 l l PAGE 54 Ol' 6 5 l .
GEORGIA POWER COUPA::Y l ATTACi!!T.:!T:
IIATC11 NUCLEAR PLA1;T l PAGE 3 0F 3 l
DOCU ZNT TYPE: 1 DOCUI'E:IT :!UI-13E2 :
ADi!UlISTRATIVE COI: TROL PROCEDURE l 407C-FPX01-0 l
DOCU:1ENT TITLE: l REVISI0li:
FIRE PROTECTI0l! PROGRA:I i 1 i
ATTAC:0ZIIT TITLE:
110T WO.",1; PER!!IT CECACIA FO'iCA C3:1FANT l MATCM h1/CI.F.AR PLMT l FACC 1 0F 1 .
t FCL't TIT *.Es EDT WORE PER' TIT Expiration Date
- Permit No. Effective Date 12F shift b Issued for b ~
Issued By: b tocation of Activity b hype of Activityt )ielding O Cuttla; C Grinding G Open F1me O Rest Treating Q hireWatchNecessary?*TesQ **No G
- fire Watch Name Provide necessary F.F. egul;sent
- Muallfled Supervisor /Q.C./Eng. Group sign and date below
@ h @
Nas.e Dept./Sec./ Croup Date hSpecial' Fr's autions
- 5. . ' : , .
h!atrai entf shenh.' ,a deM ? N N.. .G', Bo' O *Q tyi, Type hTheI ad f nece pr utions listed are i Contr a d n ted t @ nd the For e: san /!as pector Date Eag. Croup With T.F. Resp. Date Qtgquest for extension of permit past one shif t. (two shifts /24'r a ass.)
Shift Date Time Foreman
$htft Date Time Forecan flotify the Control Raon at the beginnin; of each shif t GFtre Watch Follow-Up InspectLos The work area and all adjacent ares where sparks oight have spread were inspected at least 30 minutes af ter each werk period and no fire condattons s. ore noted. The portable fire extin;uishers have been re-turr.ed to their storage location.
Fire tratch Si;nsture Date Return f orm to originatta; foressa unen conpleted. Ort.anstan; f orenan
- update 104 File ori;inal for 30 days and destrop those c6pi.s not j re,uired to be attached to 0330 packr;e.
l C:C-COO L -
l l
- .GR-0009 nev. O
~^O~
ATTACH!2NT _5_ l l PAGE 55 0F 65 I
GEORGIA POUER C0;;PA!:Y l ATTACll!IEliT:
IIATCl! !;UCLEAR PLANT l PAGE 1 0F 2 l
DOCUZIENT TYPE: l DOCUl;E!!T tiUlir.ER:
ADIIIIIISTRATIVE COI: TROL PROCEDURE l 40AC-FPX01-0 1
DOCUtiE!1T TITLE: 1 REVISION:
FIRE PROTECTION PROGRAM l 0 i
ATTACH!!EliT TITLE:
HOT WORK PERMIT LOG SHEET INSTRUCTIONS (Please Print)
Block 1 - Foreman's name Block 2 - Enter name of department. section or group foreman works * '
for. Contractor foreman should also supply company name.
Block 3 - Enter permit number. Permit numbers are established by the year. month day, and numeric order.
Example: 83-04-15-1 Where: 83 is the year 04 is the month 15 is the day 1 is the number of the first permit written that day Block 4 - Enter the type of work to be performed such as welding.
grinding. open flame, etc.
Block 5 - Print the name of the person the permit is being issued to.
Block 6 - Enter the date of issue Block 7 - Enter the expected date of expiration Block 8 - Provide a brief description of the work location and build-ing number.
Block 9 - Enter the actual date permit terminated.
IIGR-0009 Rev. 0
a ATTAC!!IIE!!T .) _ l l PAGE 56 0F 65 i
GE01;GIA PO'..'ER C0;!PA!!Y l ATTAC111E!!T:
!!ATCi! 11UCLEAR PLAT!T l PAGE 2 0F 2 '
l DOCUIE!!T TYPE: l DOCU::EllT liUMBER:
ADMI!!ISTRATIVE COI! TROL PROCEDURE l 40AC-FPX01-0 l
DOCUIEtIT TITLE: l REVISIO!I:
FIRE PROTECTI0t PROGRA!! l 1 i
ATTACHIE!IT TITLE:
HOT UORK PERMIT LOG SHEET Cto d' . PWtt ConPA::Y l Kt.TCI! l1 ;L*4 r!./07 l FAC: 1 0F 1 Fs'.i II!*.;I h77 '. c7. r!':::IT !ssUL LOC , , ,
Responsible Forena Depa rt:2 cat /section/ Croup I i 1 ~Issus it:FruTrosi ICdN$T
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- 1C-0023 -
MGR-0009 Rev. O
0 ATTACillEi:T _ G_ l l PAGC 57 0F 65 i
CEORGIA POUER CO:!PA:7f l ATTACIDE::T: -
HATCH 11UCLEAR PLA:IT l PAGE 1 0F 1 I
DOCUliE!!T TYPE: l DCCUI1EIiT IlUI' .DER:
ADl!I!!ISTRATIVE CO: TROL PP.0CEDURE l 40AC-FPX01-0 l
DOCUliENT TITLE: l REVISIOU:
FIRE PROTECTIO!! PRCGRAll l 1 I
ATTACHlI::T TITLE:
ORGA lIZATIO!! LINES OF COI11:UIIICATION AND RESP 0'ISIBILITIES OF THE FIRE BRIGADE. FESG. A!!D LOCAL FIRE DEPARTMENT
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!!CR-0009 Rev. O
ATTACIIIII T _7_ l l PAGE 50 07 65 i
CEORGIA POUER CO 'PA!!Y l ATTACICII;T:
I'J,TCII I;UCLEl.R PLA!!T l PAGE 1 OF 2 l
DOCU121;T TYPE: l DOCUlII!T ;!Uii!ER:
AIXIII;I.STRATIVE C0!! TROL PEOCEDURE l 40AC-FF::01-0 DOCUl;E::T TITLE: l REVISI0ll:
FIRE PROTECTION PROGRA!! l 1 i
ATTACiCIEliT TITLE:
REQUEST FOR REVISION TO PREFIRE PLAll I!!STRUCTI0llS Block 1 - Date of Revision Request Block 2 - Requestor's name Block 3 - Requestor's department Block 4 - !!ethod used to identify requested revision Block 5 - Explanation of reason for revision Block 6 - Check appropriate block. if disapproved provide explanation of reason Block 7 - Signature and date of Engineering Group with fire protection responsibility approval Block 8 - Signature and date of !!anager of Engineering approval
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!;GR-0009 Rev. 0
a ATTect'l:E :I _7_ l l pac:: 59 or 65 l
CEcncIA PO'..~ER CO::PA::Y l ATT.' c'.r.3;;;T :
!iATCr. :lUCL~AR PLA :T l PAGE 2 Or 2 1
DOCU;.E:!T TYPC: 1 1,CCUI.E :T 1.U:..: :'.:
Aili;I::ISTEATIVE CO::YROL PROC ~: DURE I 40.T-FPX01-0 I
DOCUI:E;:T TITLE: l REVISIO:::
FIRE PROTECTIO!! PROG'idt I i i
ATTACF.:fE:iT TITLE:
REQUEST FOR REVISIO!! TO PREFIRE PLAII G?. COG Li PC-.~.2. Cot:7. !Y l IL*.TCH ::CCLI.'.E FRJ:T I PAC: 1 0F 1 f
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IICR-0009 Rev. 0
g ATTAC;tiIllT _C I l PAGE 60 0F 65 I
GEORGIA P0"ER CO?IPAIIY ! ATTACHHEt!T:
- l!ATCII NUCLEAR PLA!!T l PAGE 1 0F 6 1
DOCU:IENT TYPE: 1 DOCUIIEllT 1:UIIBER:
ADIiIIIISTRATIVE C0 ! TROL PROCEDURE l 40AC-FPF.01-0 l
DOCUt!ENT TITLE: l REVISION:
FIRE PROTECTION PROGRAM i 1 l
ATTACHI{E!!T TITLE:
DEFINITIONS ANI - American Nuclear Insurers ANSI - American National Standards Institute Approved - signifies devices or assemblies having been tested and accepted for a specific purpose or application by a nationally recognized testing laboratory.
Automatic - self-acting, operating by its own mechanism when actuated by
- some impersonal influence; for example, a change in current strength, pressure. temperature. or mechanical configuration.
Combustible Liquid - a liquid having a flash point at or above 100*F (37.8aC). Combustible liquids are furthe subdivided as follows:
Class II liquids are those having flash points at or above 100*F (37.8*C) and below 140*F (60*C).
Class IIIA liquids include those having flash points at or above 140*F (60 C) and below 20,0*F (93.4*C).
Class IIIB liquids include those having flash points at or above 200*F (93.4*C).
Combustible !bterial - any material which burns or sustains the com-l bustion process whether or not it exhibits flame under exposure fire conditions that can exist at.the point of application.
Concealed - if sgace containing combustible material is inaccessible to the extinguishing agent. the combustibles are considered to be l
concealed.
Design Bases Fires - are those that are considered to cause most damage and are fires that may develop in local areas assuming no manual.
automatic, or other fire fighting action has been initiated.
Electrical Conduit - rigid or ficxible tubing, usually either steel or aluminum in which electrical cables are run.
t1GR-G009 Rev. 0
ATTACHIIUT __3 l l PAGE 61 0F 65 I
GEORGIA POUER C0iiPA!!Y l ATTACH *ENT:
IIATCH 1:UCLEAR PLA :T l PAGE 20F 6 l
DOCUME:T TYPE: l EOCUI2NT GU;iLER:
ADMI!!ISTP.ATIVE CO ! TROL PROCCDURE l 40AC-FPF.01-0 g
DOCUMENT TITLE: l REVISION:
FIRE PROTECTION PROGRAM l 1 l
ATTACHt!ENT TITLE:
DEFINITIONS Enclosed - surrounded by a case which will prevent a person from acci-
~
dentally contacting live electrical parts. Can also apply to fissmable liquids uhich are contained or encased in fire resistive materials or buildings.
Fire Area - that portion of a building or plant that is separated from other areas by fire barriers (walls. floors. ceilings. or roofs) with any openings or penetrations protected with seals or closures having a -
~
fire resistive rating equivalent to that of the barrier.
Fire Barrier - those components of construction (walls, floors. ceilings.
and roof s) that are rated by approving laboratories in hours for resis-tance to a standard time / temperature curve to prevent the spread of fire.
Fire Break - a feature of construction which prevents fire propagation along the length of cable (s) or prevents spreading of fire to nearby combustibles within a given fire area of fire zone.
Fire Brigade - the five man team of plant personnel assigned to fire fighting and uho are trained in the fighting of fires according to an established training program.
Fire Detectors - a fire detector is a device designed to automatically detect the presence of fire and iniciate an alarm system. Typical fire detectors are classified as follows:
Heat Detector - a device which detects abnormally high temperature or rate-of-temperature rise.
Smoke Detector - a device which detects the visible or invisible particles of combustion.
Flame Detector - a device which detects the infrared. ultraviolet.
or visible radiation produced by a fire.
Products-of-Combustion Detector - a detector uhose actuation mechanism depends upon pyrolysis or combustion products.
(For further definitions, see NFPA 72E. " Automatic Fire Detectors.")
- MGR-0009 Rev. O
U ATTACHMENT 8_ l l PAGE 62 0F 65 I
GEORGIA POWER COMPANY l ATTACHMENT:
HATCH NUCLEAR PLANT l PAGE 3 0F 6 ~
i DOCUMENT TYPE: l DOCUMENT NUMBER:
ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 l
DOCUMENT TITLE: l REVISION:
FIRE PROTECTION PROGRAM l 1 l
ATTACHMENT TITLE:
DEFINITIONS Fire Protection Plan - encompasses the components, procedures.and per-sonnel utilized in carrying out all activities of fire protection and includes such items as fire prevention, detection. administrative proce-dures, fire brigade organization, inspection and maintenance. equipment surveillance, training. quality assurance, and testing.
Fire Rating - refers to the endurance period of fire barrier or struc-ture and defines the period of resistance to a standard fire exposure (
elapsing before the first critical point in behavior is observed (Refer to NFPA 251).
Fire Suppression - refers to capability for control and extinguishing of fires (fire fighting). Manual fire suppression activities refer to the use of C02 hose reels, standpipes and/or portable extinguishers. Auto-matic fire suppression refers to fixed systems such as water spray, sprinklers, halon, or carbon dioxide.
Fire Zones - subdivisions of fire areas in which the fire suppression systems are designed to combat particular types of fires. The concept of fire zone aids in defining to the fire fighter the fire paramenters and the actions which would be necessary in a fire situation.
Flame Spread Rating - refers to ratings obtained according to the Method of Test of Surface Burning Characteristics of Buidling Materials. NFPA No. 255; Underwriters Laboratories No. U.L. 723; ASTM No. E-84 and ANSI No. A.25.
Flammable Liquids - a liquid having a flash point below 100aF and having a vapor pressure.not exceeding 40 pounds per square inch absolute at 100*F shall be known as a flammable liquid (Class I). Flammable liquids (Class I) are further subdivided as follows:
Class IA liquids shall include those having flash points below 73*F(22.8+C) and having a boiling point below 100*F (37.8eC).
Class IB liquids shall include those having flash points below 73*F(22.8*C) and having a boiling point at or above 100*F (37.8*C).
Class IC liquids shall include those having flash points at or ab'ove 73*F(22.8eC) and below 100*F(37.8*C).
MGR-0009 Rev. O
l ATTACHIENT _S__ l l l PAGE 63 0F 65 l l l GEORGIA POWER COMPANY l ATTACHtENT:
HATCH NUCLEAR PLANT l PAGE 4 0F ~
6 l l .
DOCUMENT TYPE: l DOCU:ENT NUMBER:
ADMINISTRATIVE CGiTROL PROCEDURE l 40AC-FPX01-0 DOCUMENT TITLE: l REVISION:
FIRE PROTECTION PROGRAM l 1 l
ATTACHMENT TITLE:
DEFINITIONS F.M. - Factory Hutual Engineering Corporation and Factory Mutual Research Corporation.
Hydraulic Designed Sprinkler System - a fixed water suppression system
- in which sprinkler spacing and pipesizing is, within limits, determined by hydraulic calculations rather than a standard schedule of allowable pipe sizes..
NEIL - Nuclear Enery Insurance Limited. -
NFPA - National Fire Protection Association NHL - Nuclear Hutual Limited Noncombustible - materials no part of which will ignite and burn when subjected to fire.
j Private Protection - all fire protection systems, equipment (fixed or portable). and facilities or methods owned by or made available through the electric genersting station. (The private Fire Brigade would be an example of private protection.)
. Public Protection - fire fighting aid and/or assistance which is avail-able from nearby governmental installations or municipalities (fire departments in Lyons. Baxley or Vidalia, etc.) and would include man-power. fire department mobile apparatus. fire hose, water supply, pumping facilities.
Raceway - any channel for holding wires, cables, or bus-bars which is designed expressly *for and used solely for this purpose. -
r Restricted Area - any area to which accesc is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
Safety Related Systems and Components - systems and components required to shut down the reactor and mitigate the consequences of postulated accidents and maintain it in a safe shutdown condition .
i MGR-0009 Rev. 0
--e< -
--m--.,-,-,- - , - -
a ATTACHMENT _,,8___ l l PAGE 64 0F 65 .
I GEORGIA POUER COMPANY l ATTACHMENT:
- HATCH NUCLEAR PLANT l PAGE 5 or 6 I
DOCUMENT TYPE: l DOCUMENT NUMBER:
ADMINISTRATIVE CONTROL PROCEDURE l 40AC-FPX01-0 i
DOCUMENT TITLE: l REVISION:
FIRE PROTECTION PROGRAM l 1 1
ATTACHMENT TITLE:
DEFINITIONS Sprinkler System - a system of overhead piping and components from the supply valve to the point where water discharges from the system in the fire area. The system is usually activated by heat or smoke from a fire. The system sometimes ~ includes a controlling and/or a section-alizing valve which is activated by a fire detection system and a device '
for actuating an alarm when the system is in operation. ,
Sprinkler System Classification - water suppression system consisting of piping and discharge devices. These systems can be further subdivided into four system types:
Wet Pipe - a system employing automatic closed head (fusible link operated) sprinklers and/or nozzles attached to a fixed piping system containing water and co- ted to a water supply so that water dischargee immedia*,ely i :prinkler heads operated by a fire.
Dry pipe - a system employing automatic closed head sprinklers attached to a piping system containing air under pressure, the release of which from the opening of a sprinkler permits the water to open a valve known as a dry pipe valve. The water then flows into the piping system and out the opened sprinklers as the air pressure drops.
Pre-Action - a system employing automatic closed head sprinkler and/or nozzles attached to a piping system containing air that may l
or may not be under pressure, with a fire detection system installed l
in the same areas as the sprinklers. Actuation of the fire detection l
system open a valve which permits water to flow into the sprinkler i piping system and to be discharged from any sprinklers which have been opened by the fire.
l Deluge - a system employing open head sprinklers attached to a j piping system connected to a water supply through a valve which is
- opened upon operation of a fire detection system in the same areas l as the sprinklers and/or nozzles. When this valve opens, water flous into the piping system and discharges from all open sprinklers simultaneously. ,
MGR-0009 Rev. O t
ATTAC1:IE!!T 8___ l l PAGE 65 0F 65 I
CEORGIA PO!!ER CO IPA 1:Y l ATTACII:EliT:
HATCH ;;UCLEAR PLAI;T l PAGE 6 0F 6 I
DOCUt:ENT TYPE: l DOCU:IEl!T 11Ut1BER :
ADIINLETRATIVE C01: TROL PROCEDURE l 40AC-FP;;01-0 l
DOCUt'EllT TITLE: 1 REVISION:
FIRE PROTECTION PROGRAM l 1 1 -
ATTACHIENT TITLE:
DEFINITIO!!S Standpipe and Hose Systems - a fixed piping system connected to a water supply to provide ef fective fire hose streams for manual use by the Fire Brigade.
U.L. - Underwriters Laboratories. Inc.
Water Spray - water suppression system utilizing directional spray nozzles , ,
generally of the open type, which may be actuated either automatically ,
or manually.
IlGR-0009 Rev. t
- - - .. ,_. =_, . - _ _ . . . _ - _ _ _ , . -..,.-- ,.. .---.,._- - _ __ .-. . .,_ --,
d5 l GEORGIA POWER COMPANY l DOCUMENT TYPE: l PLANT E.I. HATCH l ABNORMAL OPERATING PROCEDURE I PAGE 10F 44 DOCUMENT TITLE: RESTORATION OF l DOCUMENT NUMBER: l REVISION N0:
SAFE SHUTDOWN LOADS FOLLOWING A FIRE I 34AB-0PS-056-1S l 0 p
t ; EXPIRATION DATE: l APPROVALS:
V' DEPT. MGR. ._./h- . DATE//-39 d ll EFFECTIVEb DATE:
N/A l
l
~
tis ,:, l /2 d l GEN. MGR. .OM '..DATE! # M I 1.0 CONDITIONS d% 04f fi/ N ggg 1.1 An electrical bus has been lost and the effort to reenergize it has failed and 1.2 A fire is involved in the event.
2.0 AUTOMATIC ACTIONS A Bus, Motor Control Center, or Distribution Cabinet listed in Attachments 1, 2 or 3 has been deenergized.
3.0 IMMEDIATE OPERATOR ACTION 3.1. If a Reactor SCRAM occurs or a SCRAM is required by plant conditions, ENTER 31E0-E0P-001-lS, Emergency Operating Procedures and perform concurrently with this procedure.
3.2 Determine the location of the fire and what Safe Shutdown Path (1 or 2) is protected per 34AB-FPX-053-15 or Remote Shutdown if the Control Room is not
,/N available.
V ___________________________
l NOTE l 1 l l If an individual Safe Shutdown Load is to be left l l deenergized per this procedure, alternate equipment l l must be selected as defined in the E0Ps End Path l l Manual and/or another shutdown path selected. l
' C\
V MGR-0002 Rev. 2
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 2 0F 44 DOCUMENT TITLE: RESTORATION OF l DOCUMENT NUMBER: l REVISION NO:
SAFE SHUTDOWN LOADS FOLLOWING A FIRE l 34AB-0PS-056-1S I O 7- s i) s_/
4.0 SUBSEQUENT OPERATOR ACTION l NOTE l l
- l-l No attempt is made by this procedure to remove the l l ability of Operations to determine how the plant l l will be operated. Additional loads may be placed l l on buses at shift Supervisors discretion to ensure l l proper system operation. l CAUTION WHEN RESTORING BREAKERS, MONITOR THE SYSTEM OF THE COMPONENT BEING RESTORED AND CONFIRM THAT PROPER SYSTEM OPERATION CONTINUES.
CAUTION O)
(_, IF A BUS OR LOAD IS REENERGIZED FOLLOWING A TRIP, A FAULT MAY STILL EXIST, BUT BE HIDDEN AND NOT REAPPEAR UNTIL ANOTHER CONTROL ACTION OF THAT COMPONENT IS REQUIRED. THE PHYSICAL CONDITION OF RESTORED COMPONENTS AS WELL AS LIGHT, FUSE, AND ANNUNCIATOR STATUS ARE TO BE CHECKED TO INSURE THAT LOADS AND BUSES ARE BEING RETURNED TO OPERABLE STATUS.
4.1 IF the bus lost was DC, proceed to Step 4.8.
l NOTE l l l l l This step is written to reenergize 1R23-S003. To l l
l reenergize 1R23-S004, utilize component numbers in l l parentheses. l
___________________________ j l
4.2 When power is not available at 600V Switchgear 1C, (10),1R23-5003 (S004), j RESTORE power as follows:
4.2.1 With power available at 4160V AC Switchgear lE (lG) 1R22-5005 (S007), OPEN -
all circuit breakers on 1R23-S003 (S004). I O 4.2.2 CLOSE 1R22-S005 (S007) Frame 10(9) and 1R23-5003 (S004) Frame 2M (9M) to reenergize the bus.
MGR-0001 Rev. 1
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 3 0F 44 DOCUMENT TITLE: RESTORATION OF l DOCUMENT NUMBER: l REVISION NO:
g SAFE SHUTDOWN LOADS FOLLOWING A FIRE l 34AB-0PS-056-lS l 0 i
i D 4.2.3 CLOSE the Safe Shutdown breakers listed for 1R23-S003 (S004) for the Path Available listed in Attachment 1(2) or 3.
4.2.4 If any feeder breakers for buses listed in Table 4.1 or 4.2 trip OPEN, leave.
them OPEN and proceed to Step 4.4 for Table 4.1 Buses or 4.9 for Table 4.2 Buses. e ~ - -
4.3 IF the Bus lost is listed on Table 4.2, proceed to Step 4.4.
4.3.1 IF the feeder breaker on 1R23-S003 listed on Table 4.1 for the deenergized bus is CLOSED, TRIP all breakers on the deenergized bus.
IF the feeder breaker on 1R23-S003 listed on Table 4.1 for deenergized bus
~
4.3.2 is TRIPPED, proceed as follows:
4.3.2.1 OPEN all breakers on deenergized bus.
4.3.2.2 OPEN OTHER FEEDERS listed for bus, if applicable.
4.3.2.3 'CLOSE feeder breaker for deenergized bus on 1R23-S003 (Table 4.1).
4.3.3 CLOSE OTHER FEEDERS listed for bus on Table 4.1.
4.3.4 For the Safe Shutdown Path Available as defined by 34A8-FPX-053-lS, CLOSE
(
(
safe shutdown breakers listed in Attachment 1 (Path 1), Attachment 2 (Path
- 2) or Attachment 3 (Remote Shutdown) one' by one until all safe shutdown loads on the previously deenergized bus are energized.
4.3.5 IF a Safe Shutdown Load is faulted, leave its circuit breaker tripped and restore all other Safe Shutdown Loads for the Path available.
4.4 IF_ the deenergized bus is listed on Table 4.2, proceed as follows:
4.4.1 IF the feeder breaker on 1R23-S004 listed on Table 4.2 for the deenergized bus is CLOSED, TRIP all breakers on the deenergized bus.
4.4.2 If the 1R23-S004 feeder breaker is OPEN, proceed as follows:
4.4.2.1 OPEN all breakers on deenergized bus 4.4.2.2 OPEN OTHER FEEDERS listed for bus, if applicable.
4.4.2.3 CLOSE feeder breaker for deenergized bus on IR23-5004 (Table 4.2).
l 4.4.3 CLOSE OTHER FEEDERS listed for bus on Table 4.2.
1 4.4.4 For the Safe Shutdown Path Available as defined by 34AB-FPX-053-lS, CLOSE l
Safe Shutdown breakers listed in Attachment 1 (Path 1), Attachment 2 (Path 2) or Attachment 3 (Remote Shutdown) one by one for the affected bus (es) until all are energized.
- 4.4.5 IF a Safe Shutdown Load is faulted, leave its circuit breaker tripped and restore all others.
l l MGR-0001 Rev. 1 1
\
GEORGIA POWER COMPANY l l 1 PLANT E.I. HATCH l l PAGE 4 0F 44 DOCUMENT TITLE: RESTORATION OF l DOCUMENT NUMBER: l REVISION NO:
q SAFE SHUTDOWN LOADS FOLLOWING A FIRE l 34AB-0PS-056-lS l 0 ,
4.5 I_F a faulted load TRIPS a feeder breaker from 1R23-S003 or 1R23-5004, REPEAT steps 4.3.2 through 4.3.5 or 4.4.2 through 4.4.4, as applicable, leaving the faulted load circuit breaker OPEN.
4.6 IF power cannot be restored to either 1R25-5064 or 1R25-5065 (but not both),
refer to 34AB-0PS-014-lS, Loss of Instrument Buses, for the procedure to reenergize 5064 from 5065 OR S065 from S064. Reenergize only the Safe Shutdown Loads on the affected bus.
4.7 IF RPS Power Bus 1C71-P001 cannot be reenergized. TRANSFER the affected bus to Alternate Power Source per 34S0-C71-001-1S,120V AC RPS Power Supply System.
l NOTE l l l l l The following steps are used to reenergize Safe l l Shutdown Loads on IR25-S004. To reenergize l l 1R25-S005 or S006, use component numbers in l l parentheses (S005) or brackets [S006]. l 4.8 IF 1R25-S004 (S005) [S006],125V DC Distribution Panel 10 (lE) [lF] is deenergized, proceed as follows:
4.8.1 OPEN all circuit breakers on the deenergized Panel.
4.8.2 IF BATTERY LOW VOLTS OR FUSE TROUBLE, 652-119, (219) [319] is alarmed, perform the following:
4.8.2.1 Confirm or CLOSE Battery Charger Feed, Breaker 30 in Cabinet 10 (1E)
[lF], 1R25-S004 (S005) [S006].
4.8.2.2 Confirm battery voltage is less than ll7V DC on Voltmeter 1R42-R606 (R607) [R608] on Panel lHll-P652.
4.8.2.3 Confirm Battery Charger 1R42-5032A(B)[C] or S032E(D)[F] is in service as follows:
4.8.2.3.1 AC Input Switch is ON.
4.8.2.3.2 DC Output Switch is ON.
O MGR-0001 Rev. 1
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 5 0F 44 DOCUMENT TITLE: RESTORATION OF l DOCUMENT NUMBER: l REVISION N0:
n SAFE SHUT 00WN LOADS FOLLOWING A FIRE l 34AB-0PS-056-lS l 0 4.8.2.3.3 AC Input light is ILLUMINATED. IF not, check charger power supply.
- Charger 1R42-S032A - 600/208V MCC 1 A,1R24-5025 breaker ICR
- Charger 1R42-S032E - 600/208V MCC 1 A, 4R24-5025 breaker 3AR
- (Charger 1R42-50328 - 600/208V MCC 1B,1R24-S026 breaker 28R) i
- (Charger 1R42-S0320 - 600/208V MCC 18,1R24-S026 breaker 3AR)
- [ Charger 1R42-5032C - 600/208V MCC 1C,1R24-S027 breaker 1CR]
- [ Charger 1R42-S032F - 600/208V MCC 1C,1R24-S027 breaker 3AR]
4.8.2.3.4 Throwover Switch 1R26-M032A(B)[C] is up for charger 1R42-S032A(B)[C]
or down for charger 1R42-S032E(D)[F].
4.8.2.3.5 Float and equalizing voltage set per nameplate data.
4.8.2.3.6 Greater than 125V DC reading on charger voltmeter.
4.8.2.3.7 Greater than 1 amp reading on charger ammeter.
4.8.2.3.8 Repit.ce tur s as necessary in Battery 1A(18)[lC) fuse box lH21-P291
.( (P292)[P29:-
4.8.3 If Panel 10(lE)[lf reenergizes, ADD all Safe Shutdown Loads on the affected bus from Attachmen- 1 (Path 1), Attachment 2 (Path 2) or Attachment 3 (Remote Shutdown) .v.e at a time.
4.8.4 E one of the loads trips its individual breaker or the power to cabinet 10 (1E)[lF], perform the following:
4.8.4.1 E the individual breaker trips, leave it in the TRIPPED position.
4.8.4.2 E the load removes power to Cabinet ID(IE)[lF], reopen all previously closed breakers and REENERGIZE Cabinet 1D(lE)[lF] and Reclose all breakers opened to that point leaving the faulted breaker OPEN.
4.8.4.3 Continue adding loads until all possible Safe Shutdown Loads for the protected path (s) are energized.
O MGR-0001 Rev. 1
l j GEORGIA POWER COMPANY l PLANT E.I. HATCH l l PAGE 6 0F 44 DOCUMENT TITLE: RESTORATION OF l DOCUMENT NUMBER: l REVISION NO:
SAFE SHUTDOWN LOADS FOLLOWING A FIRE l 34AB-0PS-056-1S l O t i - .
l NOTE l l l l The following steps are written to reenergize Safe l l Shutdown Loads from 125/250V DC Switchgea? 1A. l-l Switchgear 1B can be reenergized by using the l l component numbers in parentheses. l 4.9 E power is not available to 125/250V DC Switchgear 1A, 1R22-S016 (18, 1R22-S017) perform the following:
4.9.1 TRANSFER Reactor Bldg MCC 1E-A (1E-8), 1R24-S018A(B) to alternate power supply per 3450-R24-003-IS, 600 Volt Essential 1E-A/B (1R24-5018A/B)
Operation.
4.9.2 Attempt to restore power to Bus 1A (18), 1R22-S016 (5017).
4.9.2.1 OPEN all breakers on Bus 1A (18).
4.9.2.2 REPLACE battery fuses as necessary in battery fuse boxes 1H21-P285 (P288), P286 (P289) and P287 (P290).
/7 4.9.2.3 Confirm that battery chargers 1R42-5026, S027 and S028 (1R42-5029, 5030, V and 5031) are in service per 34S0-R42-001-lN,125/250V DC Station Service Charger Rotation and Breaker Racking.
4.9.2.4 CLOSE breaker 4T on Bus 1 A (1B).
4.9.2.5 E Breaker 4T TRIPS, leave DEENERGIZED until cause of fault is determined.
4.9.2.6 IF Bus 1A (18) remains energized, perform the follouing:
4.9.2.6.1 ADD all Safe Shutdown Loads for the Path indicted one at a time until all loads are added.
4.9.2.6.2 IF one load is faulted, leave its circuit breaker OPEN. Reclose l
breaker 4T and perform the steps below indicated for loss of the appropriate bus.
4.10 E 125V DC Cabinet 1 A or 18,1R25-S001 or S002 OR 250V DC Reactor Building Essential MCC 1 A or 18,1R24-S021 or S022 are deenergized by the fire, perform the following for the bus (es) lost:
4.10.1 Determine the feeder breaker from 1R22-5016 or S017 f rom Attachment 1 or 2.
4.10.2 Confirm feeder breaker is OPEN and OPEN all breakers on the deenergized bus.
4.10.3 CLOSE the feeder breaker identified in Step 4.10.1.
4.10.4 E breaker TRIPS, leave the bus deenergized.
MGR-0001 Rev. 1
GEORGIA POWER COMPANY l l PLANT E.I. HATCH I l PAGE 7 0F 44 DOCUMENT TITLE: RESTORATION OF l DOCUMENT NUMBER: l REVISION N0:
- SAFE SHUTDOWN LOADS FOLLOWING A FIRE l 34AB-0PS-056-1S I O
'G 4.10.5 IF bus remains energized, ADD Safe Shutdown Loads listed in the Attachments for that bus one at a time.
4.10.6 IE a load is faulted, proceed as follows:
c -
4.10.6.1 IF the individual load circuit breaker TRIPS, leave it OPEN and RESTORE all others.
4.10.6.2 IF the 5016 or S017 feeder breaker to the af fected bus TRIPS, Repeat Steps 4.10.3 through 4.10.6 leaving the faulted breaker OPEN.
4.11 For any Safe Shutdown Loads which cannot be energized, evaluate their impact on the Shutdown Path Available.
e TABLE *4.1 1R23-S003 POWER AVAILABLE 1R23-S003 OTHER FEEDER DEENERGIZED BUS FEEDER BREAKER BREAKERS 1R25-S064 3M 1R25-5036 Ckt 15 1R25-5036 3M
/'"3 1R25-5029 38 1R24-S025 Fr. ICL
( _) 1R24-S025 (208) 38 1R25-S029 Ckt 41 1R24-5025 (600) 38 1R24-S011 7M 1R24-S011A 7M Power Panel in 1R24-5011 7M 1R24-S011 Ckt 20A 1R24-5009 4B 1C71-P001A BM 1C71-P003A,C TABLE 4.2 1R23-S004 POWER AVAILABLE 1R23-S004 OTHER FEEDER DEENERGIZED BUS FEEDER BREAKER BREAKERS 1R25-S065 3M 1R25-5037 Ckt 14 1R25-5037 3M 1R25-5031 3B 1R24-5027 Fr. 1BL 1R24-S027 (208) 38 1R25-5031 Ckt 41 1R24-5027 (600) 3B 1R24-5012 6M 1R24-50128 6M Power Panel in 1R24-5012 6M 1R24-5012 Fr 20A 1R24-5010
- 1C71-P0018 28 1C71-P0038, D l
MGR-0001 Rev. 1
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 8 0F 44 I
DOCUMENT TITLE: RESTORATION OF l DOCUMENT NUMBER: l REVISION NO:
g SAFE SHUTDOWN LOADS FOLLOWING A FIRE I 34AB-0PS-056-1S I O
5.0 REFERENCES
5.1 EI Hatch Nuclear Plant - Unit 1 List of Appendix R Required Breakers Mr. William.
F Garner (SCS) to Mr. P.E. Fornel (GPCo) 10/13/86.
e .
5.2 EI Hatch Nuclear Plant - Unit 1 List of Appendix R Required Breakers Mr. William F. Garner (SCS) to Mr. P.E. Fornel (GPCo) 9/19/86 5.3 PLANT PROCEDURES 5.3.1 34AB-0PS-013-1S, Loss of DC Buses 5.3.2 34AB-0PS-014-1S, Loss of Instrument Buses 5.3.3 34AB-0PS-016-1S, Loss of Essential AC Distribution Buses 5.4 PLANT DRAWINGS 5.4.1 H13369 Single Line Diagram 120/208V Essential A.C. System 5.4.2 H13370 Single Line Diagram 125/250V DC Station Service 5.4.3 H13356 Single Line Diagram 4160V Bus lE & 1F 5.4.4 H13357 Single Line Diagram 4160V Bus 1G 5.4.5 H13361 Single Line Diagram 600V Bus 1C & 1D 5.4.6 H13647 Single Line Diagram Diesel Bld 600-208V MCC-1A 5.4.7 H13648 Single Line Diagram Diesel Bld 600-208V MCC R24-5026 1B & R2a-SO48 1D 5.4.8 H13649 Single Line Diagram Diesel Bldg 600-208V MCC-1C 5.4.9 H17012 Single Line Diagram Reactor Building 600V Essential MCC "1E-A" &
"1E-B" 5.4.10 H17011 Single Line Diagram Reactor Building 600V Essential MCC "18" Sht.1 5.4.11 H17010 Single Line Diagram Reactor Building 600VAC Essential MCC "1C" Sht.1 5.4.12 H17022 Single Line Diagram Reactor Building 250V DC Essential MCC "1 A" &
"1A-1" 5.4.13 H17023 Single Line Diagram Reactor Building 250V DC Essential MCC "1B" 5.4.14 H17155 Reactor Protection System MG Set Control C71 Elementary Diagram Sh.1 of 3.
5.4.15 H13371 Single Line Diagram 125V DC Emergency Station Service MGR-0001 Rev. 1
GEORGIA POWER COMPANY l DOCUMENT TYPE:
PLANT E.I. HATCH I ABNORMAL OPERATING PROCEDURE l
I PAGE 1 0F 27
[
DOCUMENT TITLE: RESTORATION l DOCUMENT NUMBER: l REVISION NO:
OF SAFE SHUTDOWN 8.0 ADS FOLLOWING A FIRE I 34AB-0PS-056-2S I 0
/ EXPIRATION DATE: l APPROVALS: s EFFECTIVE DATE:
U l DEPT. M . , ,wo-im DATE///6-/6 l $M.
~
N/A l l GEN. MGR.
~
H M M';\\ '
DATE / M l
i l2.'hh 1.0 CONDITIONS 1.1 An electrical bus has'beehlldsttEn'd2the iffort to reenergize it has failed and 1.2 A fire caused the loss of the bus.
2.0 AUTOMATIC tiCTIONS A Bus, Motor Control Center, or Distribution Cabinet listed in Attachments 1, 2 or 3 has been deenergized.
3.0 IMMEDIATE OPERATOR ACTIONS 3.1 If a Reactor SCRAM occurs or a SCRAM is required by plant conditions, ENTER 31E0-EOP-001-25, Emergency Operating Procedures and perform concurrently with this procedure.
3.2 Determine the location of the fire and what Safe Shutdown Path (1 or 2) is protected per 34AB-FPX-053-2S or Reri.ote Shutdown if the Control Room is unavailable.
Y Q t h fr+.e n s y o
<f El d. 'k',
MGR-0002 Rev. 2
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 2 0F 27 DOCUMENT TITLE: RESTORATION l DOCUMENT NUMBER: l REVISION NO:
jT OF SAFE SHUTDOWN LOADS FOLLOWING A FIRE l 34A8-0PS-056-2S l 0 N ,) -
4.0 _ SUBSEQUENT OPERATOR ACTION l NOTE ,,
l No attempt is made by this procedure to remove l l the ability of Operations to determine how the l l plant should be operated. Additional loads may l l be placed on buses at Shift Supervisors discretion l l to ensure proper system operation. l CAUTION WHEN RESTORING BREAKERS, MONITOR THE SYSTEM OF THE COMPONENT BEING RESTORED AND CONFIRM THAT PROPER SYSTEM OPERATION CONTINUES.
CAUTION O
\- ' IF A BUS OR LOAD IS REENERGIZED FOLLOWING A TRIP, A FAULT MAY STILL EXIST, BUT BE HIDDEN AND NOT REAPPEAR UNTIL ANOTHER CONTROL ACTION OF THAT COMPONENT IS REQUIRED. THE PHYSICAL CONDITION OF RESTORED COMPONENTS AS WELL AS LIGHT, FUSE, Af;D ANNUNCIATOR STATUS ARE TO BE CHECKED TO INSURE THAT LOADS AND BUSES ARE BEING RETURNED TO OPERABLE STATUS.
4.1 If the bus lost was DC, proceed to Step 4.7.
l NOTE l l
- l l
! l This step is written to reenergize 2R23-S003. To l l l reenergize 2R23-S004, use component numbers in l l parentheses. l 4.2 If power is not available at 600V Switchgear 2C, (20), 2R23-S003 (S004), restore power as follows:
4.2.1 With power available at 4160 V AC Switchgear 2E (2G) 2R22-5005 (S007), OPEN all circuit breakers on 2R23-S003 (S004).
( J 4.2.2 CLOSE 2R22-S005 (S007) Frame 2 and 2R23-5003 (S004) Frame 8M (2M) to l reenergize the bus.
i MGR-0001 Rev. 1
~
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 3 0F 27 DOCUMENT TITLE: RESTORATION- l DOCUMENT NUM8ER: l REVISION NO:
l 34AB-0PS-056-25 1 0 p -0F SAFE SHUTDOWN LOADS FOLLOWING A FIRE v -
4.2.3 CLOSE the Safe Shutdown breakers listed for 2R23-S003 '(S004) for the Path Available. See Attachments 1 and 2.
~l--
l NOTE l- l l Tables 4.1 and 4.2 are on page 7 af ter step 4.10. l 4.2.4 If any feeder breakers for buses listed in Table 4.1.or 4.2 trip OPEN, leave them OPEN and proceed to Step 4.4 for Table 4.1 Buses or 4.4 for Table 4.2 Buses.
4.3 If the Bus lost is listed on Table 4.2, proceed to Step 4.4.
4.3.1 If the feeder breaker on 2R23-S003 listed on Table 4.1 for the deenergized bus is CLOSED, TRIP all breakers on the deenergized bus.
4.3.2 If the feeder breaker on 2R23-S003 listed on Table 4.1 for deenergized, bus-is TRIPPED, proceed as follows:
4.3.2.1 OPEN all breakers on deenergized bus.
4.3.2.2 OPEN OTHER FEEDERS listed for bus, if applicable.
4.3.2.3 CLOSE feeder breaker for deenergized bus on 2R23-5003 (Table 4.1).
4.3.3 CLOSE OTHER FEEDERS listed for bus on Table 1.
4.3.4 For the Safe Shutdown Path Available as defined by 34AB-FPX-053-2S, CLOSE safe shutdown breakers listed in Attachment 1 (Path 1) or Attachment 2 (Path
- 2) or Attachment 3 (Remote Shutdown) one by one until all safe shutdown loads on the affected bus are energized.
4.3.5 If a Safe Shutdown load is faulted leave its circuit breaker tripped and restore all other Safe Shutdown loads for the Path available, i
li- 4.4 I_F,the deenergized bus is listed on Table 4.2, proceed as follows:
i 4.4.1 If the feeder breaker on 2R23-5004 listed on Table 4.2 for the deenergized bus is CLOSED, TRIP all breakers on the deenergized bus.
4.4.2 If the 2R23-5004 feeder breaker is OPEN, proceed as follows:
4.4.2.1 OPEN all breakers on deenergized bus 4.4.2.2 OPEN OTHER FEEDERS listed for bus, if applicable.
4.4.2.3 CLOSE feeder breaker for deenergized bus on 2R23-S004 (Table 4.2).
l I
i 4.4.3 CLOSE OTHER FEEDERS listed for bus on Table 4.2.
l MGR-0001 Rev. 1
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 4 0F 27 DOCUMENT TITLE: RESTORATION l DOCUMENT NUMBER: l REVISION NO:
l 34AB-0PS-056-2S O p 0F SAFE SHUTDOWN LOADS FOLLOWING A FIRE l V
4.4.4 Hhen the bys is reenergized for the Safe Shutdown Path Available as defined by 34AB-FPX-053-2S, CLOSE Safe Shutdown breakers listed in Attachment 1 (Path 1), Attachment 2 (Path 2) or Attachment 3 (Remote Shutdown) one by one for the affected bus (es) until all are energized. ,
4.4.5 E a Safe Shutdown Load is faulted, leave its circuit breaker tripped and restore all others.
4.5 E a faulted load TRIPS a feeder breaker from 2R23-S003 or 2R23-S004, REPEAT steps 4.3.2 through 4.3.5 or 4.4.2 through 4.4.4 as applicable, leaving the faulted load circuit breaker OPEN.
4.6 IF, either 2R25-S064 or 2R25-5065 but not both cannot be reenergized, refer to 34AB-0PS-014-2S, Loss of Instrument Buses, for a procedure to energize 5064 from S065 or S065 f rom 5064 and only reenergize the Safe Shutdown Loads on these buses.
l NOTE l
! l l The following steps are used to reenergize Safe l l Shutdown Loads on 2R25-S004. To reenergize l l 2R25-S006, use component numbers in parentheses. l
('}
V 4.7 If 2R25-S004 (S006), 125V DC Distribution Panel 20 (2F) is deenergized, proceed as follows:
4.7.1 OPEN all circuit breakers on the deenergized Panel.
4.7.2 IF BATTERY LOW VOLTS OR FUSE TROUBLE, 652-119, (319) is alarmed, perform the following:
4.7.2.1 Confirm or CLOSE Battery Charger Feed, Breaker 29 (30) in Cabinet 2D (2F), 2R25-S004 (S006).
4.7.2.2 Confirm battery voltage is less than ll?VDC on Voltmeter 2R42-R606 (R608) on Panel 2Hil-P652.
4.7.2.3 Confirm Battery Charger 2R42-S032A(C) or 2R42-50320 is in service as follows:
4.7.2.3.1 AC Input Switch in ON.
4.7.2.3.2 DC Output Switch is ON.
MGR-0001 Rev. 1
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 5 0F 27 DOCUMENT TITLE: RESTORATION l DOCUMENT NUMBER: l REVISION NO:
OF SAFE SHUTDOWN LOADS FOLLOWING A FIRE l 34AB-0PS-056-2S l O 4.7.2.3.3 AC Input light is ILLUMINATED IF not, check charger power supply.
- Charger 2R42-S032A - 600/208V MCC 2A, 2R24-S025 breaker 1CR
- Charger 2R42-S032D - 600/208V MCC 2A, 2R24-S025 breaker 1BR y --
- (Charger 2R42-S032B - 600/208V MCC 2C, 2R24-S027 breaker ICL)
- (Charger 2R42-S0320 - 600/208V MCC 2C, 2R24-S027 breaker 1BR) 4.7.2.3.4 Throwover Switch 2R26-M032A(C) is up for charger 2R42-S032A(C) or down for charger 2R42-50320.
4.7.2.3.5 Float and equalizing voltage set per nameplate data.
4.7.2.3.6 Greater than 125V DC reading on charger voltmeter.
4.7.2.3.7 Greater than 1 ampere reading on charger ammeter.
4.7.2.3.8 Replace fuses as necessary in Battery 2A(2C) fuse box 2H21-P291 (P293).
4.7.3 If Panel 20 (2F) reenergizes, ADD Safe Shutdown Loads on the affected bus f rom Attachment 1, Path 1; Attachment 2, Path 2; or Attachment 3, Remote Shutdown one at a time.
D 4.7.4 E one of the loads trips its individual breaker or the power to cabinet 2D (2F), perform the following:
4.7.4.1 E the individual breaker trips, leave it in the TRIPPED position.
4.7.4.2 E the load removes power to Cabinet 20 (2F), REOPEN all previously closed breakers and reenergize Cabinet 2D (2F), THEN RECLOSE all breakers opened to that point leaving the faulted breaker OPEN.
4.7.4.3 Continue adding loads until all possible Safe Shutdown Loads for the protected path (s) are energized.
l NOTE l l l l The following steps are written to reenergize Safe l l Shutdown loads from 125/250 VDC, Switchgear 2A. l l Switchgear 28 can be reenergized by using the l l component numbers in parentheses. l 4.8 E power is not available to 125/250V DC Switchgear 2A 2R22-5016 (28, 2R22-S017) perform the following:
4.8.1 TRANSFER Reactor Bldg MCC 2E-A (2E-B), 2R24-5018A (B) to alternate power l
supply per 34GO-0PS-067-25, 250V DC Inverter System and Reactor Bldg MCC's 2E-A & 2E-B.
MGR-0001 Rev. 1
T GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 6 0F 27 DOCUMENT TITLE: RESTORATION l DOCUMENT NUMBER: l REVISION NO:
0F SAFE SHUTDOWN LOADS FOLLOWING A FIRE- l 34AB-0PS-056-2S l 0
(/
g
(, -
4.8.2 Attempt to restore power to Bus 2A (28), 2R22-S016 (5017).
4.8.2.1 OPEN all breakers on Bus 2A (28).
4.8.2.2 REPLACE battery fuses as necessary in battery fuse boxes ~2H21-P285' (P288), P286 (P289) and P287 (P290).
4.8.2.3 Confirm that battery chargers 2R42-S026, S027 and 5028 (2R42-S029, S030, and S031', are in service with throwover switches properly aligned per 34S0-R42-001-25, 125/250 VOC Station Service Charger Rotation and Breaker Racking.
4.8.2.4 CLOSE breaker 2T on Bus 2A (28).
4.8.2.5 IE Breaker 2T TRIPS, leave DEENERGIZED until cause of fault is determined.
4.8.2.6 IF Bus 2A (28) remains energized, perform the following:
4.8.2.6.1 Add all Safe Shutdown Loads for the Path indicted one at a time until all loads are added.
4.8.2.6.2 1E one load is faulted, leave its circuit breaker OPEN. Reclose breaker 2T and perform the steps below indicated for loss of the O- appropriate bus.
4.9 IE 125V DC Cabinet 2A or 28, 2R25-S001 or S002 OR 250V DC Reactor Building Essential MCC 2A or 28, 2R24-5021 or S022 are deenergized by the fire, perform the following for the bus (es) lost:
l NOTE l 1 l l Bus Feeder Breaker l l 2R25-S001 2R22-S016 Fr. IT l l 2R25-S002 2R22-S017 Fr. IT l l 2R25-5021 2R22-S016 Fr. 2B l l 2R25-5022 2R22-S017 Fr. 3M l 4.9.1 Determine the feeder breaker from 2R22-5016 or S017 listed above.
4.9.2 Confirm feeder breaker is OPEN and OPEN all breakers on the deenergized bus.
4.9.3 CLOSE the feeder breaker identified in Step 4.9.1.
4.9.4 IE breaker TRIPS, leave the bus deenergized.
4.9.5 IE bus remains energized, A00 Safe shutdown Loads listed in the Attachments for that bus one at a time.
4.9.6 IE a load is faulted, proceed as follows:
MGR-0001 Rev. 1
GEORGIA POWER COMPANY l 0 l PLANT E.I. HATCH l l PAGE 7 0F 27 DOCUMENT TITLE: RESTORATION l DOCUMENT NUMBER: l REVISION NO:
f- x 0F SAFE SHUTDOWN LOADS FOLLOWING A FIRE I 34AB-0PS-056-2S I O N,_,) -
4.9.6.1 If the individual load circuit breaker TRIPS, leave it OPEN and RESTORE all others.
4.9.6.2 IF the S016 or S017 feeder breaker to the affected bus TRIPS, Repeat Steps 4.9.3 through 4.9.6 leaving the faulte'J breaker OPEN.
4.10 For any Safe Shutdown Loads which cannot be energized, evaluate their impact on the Shutdown Path Available.
TABLE 4.1 2R23-S003 POWER AVAILABLE 2R23-S003 OTHER FEEDER DEENERGIZED BUS FEEDER BREAKER
- BREAKERS 2R25-S064 2M 29.25-S036 CKT 15 2R25-5036 2M 2R25-5029 68 2R24-S025 CKT 1BL 2R24-S025 (208) 68 2R25-5029 CKT 43 2R24-5025 (600) 6B 2R24-5011 (600) 3M 2R24-S011A 3T
( 2R24-5011 (208) 3M 2R24-5011 CKT20A (s- 2R25-S101 3M 2R24-5011 CKT21A TABLE 4.2 e 2R23-S004 POWER AVAILABLE 2R23-S004 OTHER FEEDER DEENERGIZED BUS FE.EDER BREAKER BREAKERS 2R25-S065 7M 2R25-5037 CKT 16 2R25-S037 7M 2R25-5031 7B 2R24-5027 Fr. 1BL 2R25-5031 CKT 43 2R24-5027 (208) 78 2R24-5027 (600) 78 2R24-5012 (600) 4T 2R24-50128 4T 2R24-S012 (208) 4T 2R24-5012 Fr 21A 2R25-S102 4T 2R24-S012 Fr 22A
5.0 REFERENCES
.O 5.1 10CFRSO Appendix R Breaker and starter list, Bechtel to GPCo letter File:
A29. 3/7010/B-GP-14696 10/3/86.
5.2 PLANT PROCEDURES 5.2.1 34AB-0PS-013-2S Loss of DC Buses.
MGR-0001 Rev. 1
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 8 0F 27 DOCUMENT TITLE: RESTORATION l DOCUMENT NUMBER: l REVISION NO:
OF SAFE SHUTDOWN LOADS FOLLOWING A FIRE l 34AB-0PS-056-2S l 0 O
5.2.2 34AB-0PS-014-2S Loss of Instrument Buses.
5.2.3 34AB-0PS-016-2S Loss of Essential AC Distribution Buses.
5.3 PLANT DRAWINGS C -
5.3.1 H27013 Single Line Diagram Reactor and Bldg. 600/208V AC Essential H27014 MCC 28 (2R24-S012) Sh. 1 and 2 of 2.
5.3.2 H27011 Single Line Diagram Reactor and Bldg. 600/208V AC Essential H27012 MCC 2C (2R24-5011) Sheet 1 and 2 of 2.
5.3.3 H23362 Single Line Diagram 600V Bus 2C and 20.
5.3.4 H27021 Single Line Diagram Reactor Bldg. 600V AC Essential MCC 2E-A and MCC 2E-R.
5.3.5 H23390 Single Line Diagram Sh. 1 125/250V DC Station Service - Sys 2R42A 5.1.6 H23358 Single Line Diagram 4160V Bus 2G v
5.3.7 H23357 Single Line Diagram.4160V Bus 2E and 2F 5.3.8 H24436 Single Line Diagram DC Dist. Cab. 2R25-S129 and 2R25-S130 O
MGR-0001 Rev. 1