ML20084H497
| ML20084H497 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/01/1984 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20084H477 | List: |
| References | |
| PROC-840501, NUDOCS 8405080079 | |
| Download: ML20084H497 (285) | |
Text
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/ GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 1 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
FLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O '
HATCH NUCLEAR PLANT '
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GEORGIA POWER COMPANY .
HATCH NUCLEAR PLANT PAGE 2 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O TABLE OF CONTENTS SECTION PAGE PREFACE........................................................... 4 INTRODUCTION...................................................... 5 OPERATOR PRECAUTIONS............................................. 16 GENERAL..................................................... 16 SPECIFIC.................................................... 20 RPU CONTROL GUIDELINE............................................ 27 RC/L........................................................ 28 RC/P........................................................ 31 RC/Q........................................................ 36 PRIMARY CONTAINMENT CONTROL GUIDELINE............................ 41 SP/T........................................................42 DW/T........................................................43 PC/P........................................................44 SP/L........................................................46 SECONDARY CONTAINMENT CONTROL GUIDELINE.......................... 50 i
SC/T........................................................52 !
, SC/R........................................................53 i
SC/L........................................................53 RADIOACTIVITY RELEASE CONTROL GUIDELINE.......................... 59 l
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. GEORGIA POWER COMPANY .
-HATCH NUCLEAR PLANT PAGE 3 0F 93 I DOCUMENT-TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 SECTION PAGE CONTINGENCIES 1 - LEVEL RESTORATION....................................... 60 2 - EMERGENCY RPV DEPRESSURIZATION.......................... 65 i
j 3 - STEAM COOLING........................................... 67 I
4 - CORE COOLING WITHOUT LEVEL RESTORATION.................. 68 5 - ALTERNATE SHUTDOWN C00 LING.............................. 69 6 - RPV FLOODING............................................ 71 7 - LEVEL / POWER CONTROL..................................... 77 ATTACHMENTS 1 - NPSH REQUIREMENTS....................................... 83 2 - HEAT CAPACITY TEMPERATURE LIMIT......................... 84 3 - SUPPRESSION POOL LOAD LIMIT............................. 85 4 - REACTOR PRESSURE VESSEL SATURATION LIMIT................ 86 5 - DRYWELL SPRAY INITIATION-PRESSURE LIMIT................. 87 i 6 - PRESSURE SUPPRESSION PRESSURE........................... 89 7 - PRIMARY CONTAINMENT DESIGN PRESSURE..................... 90-8 - PRIMARY CONTAINMENT. PRESSURE LIMIT...................... 91 9 - HEAT CAPACITY LEVEL LIMIT............................... 92 ~
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10 - MAXIMUM CORE UNC0VERY TIME LIMIT........................ 93 TABLES I - ABBREVIATIONS / DEFINITIONS................................ 8 l
II - OPERATING VALUES OF SECONDARY' CONTAINMENT PARAMETERS.... 55 l
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y GEORGIA POWER COMPANY .
HATCH NUCLEAR PLANT PAGE 4 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O PREFACE This Plant Specific Technical Guideline was developed from the Boiling Water Reactor Owner's Group generic Emergency Procedure Guidelines, Revision 3, dated December 8, 1982, by following instructions contained on page I-2 of these generic guidelines. The format of this Plant Specific Technical Guideline is not intended to reflect the format of the Emergency Operating Procedures (EOP) developed from this guideline. Format of the EOP's will follow the instructions of the Plant Specific Writer's Guide.
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GEORGIA-POWER COMPANY .
HATCH NUCLEAR PLANT PAGE 5 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O INTRODUCTION Based on the BWR system design, the following Plant Specific Technical Guidelines have been developed:
RPU Control Guideline Primary Containment Control Guideline Secondary Containment Control Guideline Radioactivity Release Control Guideline The RPV Control Guideline contains instructions to enable the operator to maintain adequate core cooling, shut down the reactor, and cool down the RPV to cold shutdown conditions. This guideline is entered whenever low RPV water level, high RPV pressure, high drywell pressure, or a condition which requires MSIV isolation has occurred, or whenever a condition which requires reactor scram exists and reactor power is above the APRM downscale trip or cannot be determined.
The Primary Containment Control Guideline contains' instructions to i'
enable the operator to maintain primary containment integrity and protect equipment in the primary containment. This guideline is entered whenever suppression pool temperature, drywell temperature, '
containment temperature, drywell pressure, or suppression pool water level is above its high operating limit or suppression pool water i level is below its low operating limit.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 6 OF 93-DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O The Secondary Containment Control Guidelino contains instructions to enable the operator to protect equipment in the secondary containment, limit radioactivity release to the secondary containment, and either maintain secondary containment integrity or limit radioactivity release from the secondary containment. This guideline is entered whenever a secondary containment temperature, radiation level, or water level is above its maximum normal operating value or secondary containment differential pressure reaches zero.
The Radioactivity Release Control Guideline contains instructions to enable the operator to limit radioactivity release into areas outside the primary and secondary containments. This guideline is entered whenever offsite radioactivity release rate is above that which requires an Alert.
Tcble I is a list of abbreviations / definitions used in the guidelines.
Pcrentheses ( ) indicate the source for a plant specific variable.
Illustrated in these guidelines are variables specifically for HNP 1 Unit 1.
At various points throughout these guidelines, cautions are noted by, ,,
for example, the symbol 20 .
The number within the box refers to a numbered " Caution" contained in the Operator Precautions section.
These " Cautions" are brief and succinct red flags for the operator, a__-_-____________-_
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 7 OF 93-DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O Where the basis for the " Caution" or a step is not completely evident
- from the text, a full discussion of the basis is contained in Appendix
- B to the generic Emergency Procedures Guidelines. Other system 1
details which pertain to the guidelines are also included in this appendix.
At various points within these guidelines, limits are specified beyond I
'which certain actions are required. While conservative, these limits are derived from engineering analyses utilizing best-estimate (as opposed to licensing) models. Consequently, these limits are not as 1
conservative as the limits specified in a plant's Technical Specifications. This is not to imply that operation beyond the
! Technical Specifications is recommended in an emergency. Rather, such operation may be required under.certain degraded conditions in order to safely mitiga,te the consequences of those degraded conditions. The limits specified in the guidelines establish the boundaries within i which continued safe operation of the plant can be assured.
Therefore, conformance with the guidelines does not ensure strict conformance with a plant's Technical Specifications or other licensing bases.
The entry conditions for these guidelines are symptomatic of both _ :
cmergencies and events which may degrade into' emergencies. The i
l guidelines specify actions appropriate for both. Therefore, entry.
into procedures developed from these guidelines is not conclusive that I l
l cn emergency has occurred. ;
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. GEORGIA POWER COMPANY HATCH NUCLEAR PLAr!T PAGE 8 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O TABLE I ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION A Amendment 4
Adjust To regulate or bring to a more satisfactory state. Example: " ADJUST Reactor Water Level setpoint to +36 inches."
ADS Automatic Depressurization System.
Align To place a system in proper or desired
'l configuration for an intended purpose. '
Example: " ALIGN Standby Gas Treatment to Reactor Building".
Allow To permit a stated condition to be achieved prior to proceeding. Example: " ALLOW discharge pressure to stabilize".
Alternate Injection Any of: keep fill systems, RHR service Subsystem water, SLC.
Appendix The Appendix to the Plant Specific Technical Guidelines.
APRM Average Power Range Monitor, ,
Available Capable of performing its intended function e.g. adding water to the reactor.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 9 0F 93 -
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION Check To perform a physical action which determines the state of a variable or status of equipment without directing a change in status. Example: " CHECK for satisfactory lube oil level".
Close To change the physical position of a mechanical device to the closed position so that it prevents fluid flow or permits passage of electric current. Example:
"CLOSE valve 2B21-F019'."
Complete To accomplish specific procedural requirements, Example: " COMPLETE value check-off list 3.7.1", " COMPLETE data report QA-1", COMPLETE steps 7 through 9'of Section III".
CRD Control Rod Drive.
CS Core Spray. ,
DW/T Drywell Temperature Control.
ECCS Emergency Core Cooling System.
EPG Emergency Procedure Guideline generated by the BWR owners group with generic application to all BWRs.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 10 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION EOP Emergency Operating Procedures.
Establish To make arrangements for a stated condition. Example: " ESTABLISH communication with control room".
FSAR Final Safety Analysis Report.
ft. Foot or feet.
HCU Hydraulic Control Unit.
HNP Hatch Nuclear Plant.
HPCI High Pressure Coolant Injection.
HUAC Heating, Ventilating and Air Conditioning.
In. Inch or inches.
Injection Subsystem Any of: condensate, LPCI, or CS Isolate To close one or more values in a system for the purpose of separating or setting apart a complete system or a portion of the system from the rest. Example: " ISOLATE _
interruptible instrument air header by shutting value 2P51-F011."
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 11 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION Inspect To measure, observe, or evaluate a feature or characteristic for comparison with specified limits; method of inspection should be included. Example: " visually INSPECT for leaks".
LCO Limiting Condition for Operation.
LOCA Loss of Coolant Accident.
LPCI Low Pressure Coolant Injection.
Maintain To keep in an existing state. Example:
" MAINTAIN the reactor vessel water level between +15 and +55 inches, with one or more of the following systems".
MSIU Main Steamline Isolation Valves.
NDTT Nil-Ductility Transition Temperature.
NE North East.
NPSH Net Positive Suction Head. ,
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 12 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION Open To change the physical position of a mechanical device to the open position so that it allows fluid flow or prevents passage of electrical current. Example:
"OPEN value 2B21-FOl6". Unless specifically directed otherwise, open means fully.open.
P Page.
PC Primary Containment Control.
PC/P Primary Containment Pressure Control.
PC/T Primary Containment Temperature Control.
Place To put in a particular position. Example:
" PLACE mode switch to shutdown".
Press. Pressure.
Primary System Main Steam, HPCI, RCIC, Core Spray, RHR, 3 CRD, Feedwater, RWCU, SLC, Reactor Sampling Systems are the systems designated primary _
systems.
PSIG Pounds per square inch gage.
PSTG Plant Specific Technical Guidelines.
RCIC Reactor Core Isolation Cooling.
R 31 Revision Number 31.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 13 OF 93.
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION RC RPU Control.
RC/L RPU Level Control.
RC/P RPV Pressure Control.
RC/Q RPV Power Control.
Record To document a specified condition or characteristic. Example: " RECORD discharge pressure".
Reduce To cause a parameter to decrease in value.
Example: " REDUCE reactor pressure with bypass value manual ~j ack" .
RFPT Reactor Feed Pump Turbine RHR Residual Heat Removal.
RPS Reactor Protection System. )
RR Radioactivity Release.
RSCS Rod Sequence Control System. f
.- I RWCU Reactor Water Cleanup.
-SDGT Standby Gas Treatment.
SC ' Secondary Containment Control.
SC/L Secondary Containment Level Control.
SC/R Secondary Containment Radiation Control.
UEORGIA POWER COMPANY HATCH NUCLEAR PLANT 'PAGE 14 0F 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS i
WORD / ABBREVIATION MEANING / APPLICATION SC/T Secondary Containment Temperature Control.
SE South East.
Set To physically adjust to a specified value an adjustable feature. Example: " SET diesel speed to... rpm".
SORV Stuck Open Relief Valve.
I SP/L Suppression Pool Level Control.
SP/T Suppression Pool Temperature Control.
, Start To energize an electro-mechanical device by manipulation of a start switch or button. I Example: " START a second CRD pump".
Stop Opposite of_ start. -Example: "STOP admitting steam by shutting value 2B21-F044". i l
j Synchronize To make synchronous in operation. Example:
" SYNCHRONIZE the Diesel Generator to 4160V i
Bus 2E".
Temp. Temperature.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 15 OF 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1)
REVISION:
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TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION Throttle To operate a valve in an intermediate position to obtain a certain flow rate.
Example: " THROTTLE value 2B21-F077 to obtain 2000 l b/hr flow".
Trip To manually activate a semi-automatic feature. Example: " TRIP breaker...".
TS Technical Specification.
Vent To permit a gas or liquid confined under pressure to escape at a vent. ~ Example:
"UENT the Heat Exchanger before placing it in service".
Verify To prove to be true, exact, or accurate by observation of a condition or characteristic for comparison with an original or procedural requirement. Example: " VERIFY discharge pressure". ,
GEORGIA 'WER COMPANY HATCH N: .i:AR PLANT PAGE 16 OF 93 DOCUMENT / ITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O OPERATOR PRECAUTIONS GENERAL This section lists " Cautions" which are generally applicable at all times.
CAUTION 1 l
MONITOR THE GENERAL STATE OF THE PLANT. IF AN ENTRY CONDITION FOR AN EMERGENCY OPERATING PROCEDURE OCCURS, ENTER THAT PROCEDURE. WHEN IT IS DETERMINED THAT AN EMERGENCY NO LONGER EXISTS, ENTER THE APPROPRIATE NORMAL OPERATING PROCEDURE AS DIRECTED BY THE EMERGENCY OPERATING PROCEDURES.
i CAUTION 2
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MONITOR RPV WATER LEVEL AND PRESSURE AND PRIMARY CONTAINMENT TEMPERATURES AND PRESSURE FROM MULTIPLE INDICATIONS.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 17 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CAUTION 3 IF A SAFETY FUNCTION INITIATES AUTOMATICALLY, ASSUME A TRUE INITIATING EVENT HAS OCCURRED UNLESS OTHERWISE CONFIRMED BY AT LEAST TWO INDEPENDENT INDICATIONS.
CAUTION 4 WHENEVER RHR IS IN THE LPCI MODE, INJECT THROUGH THE HEAT EXCHANGERS AS SOON AS POSSIBLE.
CAUTION 5 SUPPRESSION POOL TEMPERATURE IS DETERMINED BY THE HIGHEST ,
READING ON 1H11-P650 1T47-R630, 1H11-P654 1T47-R612 OR IH11-P657 1T47-R611. DRTWELL TEMPERATURE IS DETERMINED BY THE PROCEDURE IN HNP-1-1050, ITEM 10 DATA PACKAGE 1.
f GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 18 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CAUTION 6 WHENEVER TEMPERATURE NEAR THE INSTRUMENT REFERENCE LEG UERTICAL RUN EXCEEDS THE TEMPERATURE SHOWN BELOW AND THE INSTRUMENT READS BELOW THE INDICATED LEVEL IN THE TABLE, THE ACTUAL RPU WATER LEVEL MAY BE ANYWHERE BELOW THE ELEUATION OF THE LOWER INSTRUMENT TAP.
INDICATED TEMPERATURE LEVEL INSTRUMENT Any 95.7 IN. SHUTDOWN RANGE LEVEL
(-17 to +3 8 3 IN.) 1821-R605 127.8 F -107.9 IN. WIDE RANGE LEVEL
(-150 to +60 IN.) 1B21-NO24, NO25, NO26, NO31, R604 303 F (B) 1.8 IN. NARROW RANGE LEVEL
( 0 to +60 IN.) 1C32-R606B 303*F (C,D) 21.5 IN. NARROW RANGE LEVEL
( O to +60 IN.) 1821-N017C,D 303 F (B) 21.4 IN. NARROW RANGE LEVEL
( O to +60 IN.) 1821-N042B 305*F (A,C) 1.8 IN. NARROW RANGE LEVEL
( O to +60 IN.) 1C32-R606A,C !
305*F (A) 20.8 IN. NARROW RANGE LEVEL y
( 0 to +60 IN.) 1821-NO42A ,
305 F (A,B) 20.9 IN. NARROW RANGE LEVEL
( O to +60 IN.) 1821-N017A,8 547 F -330.6 IN. FUEL ZONE LEVEL
(-317 to -17 IN.) IB21-NO36 NO37, R610, R615
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 19 OF 93
. DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CAUTION 7 4
1821-R604A AND R6048 (HEATED REFERENCE LEG INSTRUMENTS)
INDICATED LEVELS ARE NOT RELIABLE DURING RAPID RPU DEPRESSURIZATION BELOW 500 PSIG. FOR THESE CONDITIONS, UTILIZE 1821-R605, R610, AND R615 (COLD REFERENCE LEG i INSTRUMENTS) TO MONITOR RPU WATER LEVEL.
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i CAUTION 8 i
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OBSERVE NPSH REQUIREMENT FOR PUMPS TAKING SUCTION FROM THE SUPPRESSION POOL (SEE ATTACHMENT 1).
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 20 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
l PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CAUTION 9 IF SIGNALS OF HIGH SUPPRESSION POOL WATER LEVEL 150 IN. (HIGH LEVEL SUCTION INTERLOCK) OR LOW CONDENSATE STORAGE TANK WATER LEVEL 0 IN. (LOW LEVEL SUCTION INTERLOCK) OCCUR, CONFIRM AUTOMATIC TRANSFER OF OR MANUALLY TRANSFER HPCI AND RCIC SUCTION FROM THE CONDENSATE STORAGE TANK TO THE SUPPRESSION POOL.
SPECIFIC This section lists " Cautions" which are applicable at one or more specific points within the guidelines. Where a " Caution" is opplicable, it is identified with a symbol, for example: 20 .
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 21 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O l
CAUTION 10 i
DO NOT SECURE OR PLACE AN ECCS IN MANUAL MODE UNLESS, BY AT LEAST l TWO INDEPENDENT INDICATIONS, (1) MISOPERATION IN AUTOMATIC MODE i
! IS CONFIRMED, OR (2) ADEQUATE CORE COOLING IS ASSURED. IF AN
[ AUTOMATICALLY. MAKE FREQUENT CHECKS OF THE INITIATING OR CONTROLLING PARAMETER. WHEN MANUAL OPERATION IS NO LONGER-REQUIRED, RESTORE THE SYSTEM TO AUTOMATIC / STANDBY MODE IF POSSIBLE.
1 CAUTION 11 IF A HIGH DRYWELL PRESSURE ECCS INITIATION SIGNAL 2.0 PSIG (DRYWELL PRESSURE WHICH INITIATES ECCS) OCCURS OR EXISTS WHILE DEPRESSURIZING, PREVENT INJECTION FROM THOSE CS AND LPCILPUMPS NOT REQUIRED TO ASSURE ADEQUATE CORE COOLING PRIOR TO REACHING ~
THEIR MAXIMUM INJECTION PRESSURES. WHEN THE HIGH DRYWELL PRESSURE ECCS INITIATION SIGNAL CLEARS, RESTORE CS AND_LPCI TO J
AUTOMATIC / STANDBY MODE.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 22 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION: l PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0 l CAUTION 12 DO NOT THROTTLE HPCI TURBINE BELOW 2000 RPM OR RCIC TURBINE BELOW 2250 RPM (MINIMUM TURBINE SPEED LIMIT PER TURBINE VENDOR MANUAL).
CAUTION 13 4
1 COOLDOWN RATES ABOVE 100 F/HR (RPV COOLDOWN RATE LCO) MAY BE REQUIRED TO ACCOMPLISH THIS STEP.
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CAUTION 14 w b DO NOT DEPRESSURIZE THE RPV BELOW 100 PSIG (HPCI LOW PRESSURE ISOLATION SETPOINT) UNLESS MOTOR DRIVEN PUMPS SUFFICIFNT TO MAINTAIN RPV WATER LEVEL ARE RUNNING AND AVAILABLE FOR INJECTION.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 23 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CAUTION 15 OPEN SRU'S IN THE FOLLOWING SEQUENCE IF POSSIBLE: G, D, L, H, E, J, C, F. K. USE SRU'S A AND B ONLY IF UNABLE TO MAINTAIN PRESSURE WITH OTHER SRU'S.
CAUTION 16 3YPASSING LOW RPU WATER LEVEL UENTILATION SYSTEM AND MSIV ISOLATION INTERLOCKS MAY BE REQUIRED TO ACCOMPLISH THIS STEP.
4 CAUTION 17 COOLDOWN RATES ABOVE 100 F/HR (RPV COOLDOWN RATE LCO) MAY BE _
REQUIRED TO CONSERVE RPV WATER INVENTORY, PROTECT PRIMARY CONTAINMENT INTEGRITY, OR LIMIT RADIOACTIVE RELEASE TO THE j ENVIRONMENT.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 24 OF 91 DOCUMENT TITLE: ZMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CAUTION 18 IF CONTINUOUS LPCI OPERATION IS REQUIRED TO ASSURE ADEQUATE CORE COOLING, DO NOT DIVERT ALL RHR PUMPS FROM LPCI MODE.
, CAUTION 19 MANUALLY TRIP SLC PUMPS AT 0% IN THE SLC TANK.
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.i CAUTION 20 DEFEATING RSCS AND/OR RWM INTERLOCKS MAY BE REQUIRED TO ACCOMPLISH THIS STEP.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 25 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CAUTION 21 ELEVATED SUPPRESSION CHAMBER PRESSURE MAY TRIP THE RCIC TURBINE ON HIGH EXHAUST PRESSURE.
CAUTION 22 DEFEATING ISOLATION INTERLOCKS MAY BE REQUIRED TO ACCOMPLISH THIS STEP.
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i CAUTION 23 1
DO NOT INITIATE DRYWELL SPRAYS IF SUPPRESSION POOL WATER LEVEL IS ABOVE 198 IN. (ELEVATION OF BOTTOM OF MARK I INTERNAL i
SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKERS LESS VACUUM BREAKER OPENING PRESSURE IN FEET OF WATER).
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 26 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CAUTION 24 BYPASSING HIGH DRYWELL PRESSURE AND LOW RPU WATER LEVEL SECONDARY CONTAINMENT HFAC ISOLATION INTERLOCKS MAY BE REQUT. RED TO ACCOMPLISH THIS STEP.
CAUTION 25
. A RAPID INCREASE IN INJECTION INTO THE RPV MAY INDUCE A LARGE j POWER EXCURSION AND RESULT IN SUBSTANTIAL CORE DAMAGE.
4 CAUTION 26 LARGE REACTOR POWER OSCILLATIONS MAY BE OBSERVED WHILE ,
EXECUTING THIS STEP.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 27 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O RPV CONTROL GUIDELINE PURPOSE The purpose of this guideline is to:
Maintain adequate core cooling, Shut down the reactor, and Cool down the RPV to cold shutdown conditions (RPV temperature between 100 F and 212 F).
ENTRY CONDITIONS The entry conditions for this guideline are any of the following:
RPU water level below +12.5 inches (low level scram setpoint).
RPV pressure above 1045 psig (high RPU pressure scram setpoint).
Drywell pressure above 2 psig (high drywell pressure scram setpoint).
A condition which requires MSIV isolation.
A condition which requires reactor scram, and reactor power above 3% (APRM downscale trip) or cannot be determined.
OPERATOR ACTIONS RC-1 If reactor scram has not been initiated, initiate reactor scram.
Irrespective of the entry condition, execute Steps RC/L, RC/P, and RC/Q concurrently.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 28 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O RC/L Monitor and control RPU water level.
j RC/L-1 Confirm initiation of any of the following:
, - Isolation
- ECCS i
- Emergency diesel generator Initiate any of these which should have initiated but did not.
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If while executing step RC/L-2:
- Boron Injection is required, enter the procedure developed from CONTINGENCY 7.
- RPV water level cannot be determined, RPV FLOODING IS REQUIRED:
1 enter the procedure developed from CONTINGENCY 6.
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- RPV Flooding is required, enter'the procedure developed from 1
i CONTINGENCY 6.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 29 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0 RC/L-2 Restore and maintain RPU water level between +12.5 in. (low level scram setpoint) 9 and +58 in. (high level trip setpoint) 10 with one or more of the following systems: 11
- Condensate system 385-0 psig (RPU pressure range for system operation).
- Condensate /feedwater system 1717-0 psig (RPU pressure range for system operation)
- CRD system 1525-0 psig (RPU pressure range for system operation)
- RCIC system 1120-50 psig (RPU pressure 12 range for system operation)
- HPCI system 1120-150 psig (RPU pressure range for system opera lon)
- CS system 340-0 psig (RPU pressure range for system operations)
- LPCI system 280 -0 psig (RPU pressure range for system operation)
If RPU water level cannot be restored and maintained above
+12.5 inches (Iow level scram setpoint), maintain RPU water ,
level above -164.5 inches (top of active fuel).
If RPU water level can be maintained above -164.5 inches (top of active fuel) and the ADS timer has initiated, prevent automatic RPU depressurization by resetting the ADS timer.
= GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 30 OF 93 DOCUMENT TITLE- EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O If RPU water level cannot be maintained above -164.5 inches (top of active fuel), enter the procedure developed from CONTINGENCY 1.
If Alternate Shutdown Cooling is required, enter the procedure developed from CONTINGENCY 5.
l i
i RC/L-3 Proceed to cold shutdown in accordance with the procedure for cooldown to cold shutdown conditions or as directed by Plant Management.
W t
GEORGIA POWER COMPANY i HATCH NUCLEAR PLANT PAGE 31 OF 93 ,
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION: '
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O RC/P Monitor and control RPU pressure.
If while executing any step in RC/P:
- Emergency RPU Depressurization is anticipated, 13 rapidly depressurize the RPU with the main turbine bypass valves.
- Emergency RPU Depressurization or RPU Flooding is required and less than 7 (number of SRVs dedicated to ADS) SRVs are open, enter the procedure developed from CONTINGENCY 2.
- RPV Flooding is required and at least 7 (number of SRVs dedicated to ADS) SRVs are open, enter the procedure developed from CONTINGENCY 6.
RC/P-1 If any SRU is cycling, manually open SRVs until RPU pressure drops to 927 psig (RPV pressure'at which all turbine bypass valves are fully open).
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT P AGE 32 OF' 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
1
- PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O If while executing steps RC/P-2, RC/P-3, or RC/P-4:
- Suppression pool temperature cannot be maintained 8 below the Heat Capacity Temperature Limit (see 13 Attachment 2), maintain RPU pressure below the Limit. 14
- Suppression pool water level cannot be maintained 13 below the Suppression Pool Load Limit (see 14 Attachment 3) maintain RPU pressure below the Limit.
1 j - Steam Cooling is required, enter the procedure developed from CONTINGENCY 3.
~
O
, .- . -g-
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 33 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0 If while executing steps RC/P-2, RC/P-3, or RC/P-4:
- Boron Inj ection is required, and
- The main condenser is available, and
- There has been no indication of gross fuel failure or steam line break, open MSIVs to re-establish the main condenser as a heat sink. 16 RC/P-2 Control RPU pressure below 1080 psig (lowest SRU 14 lifting pressure) with the main turbine bypass valves.
RPU pressure control may be augmented by one or more of the following systems:
- SRVs only when suppression pool water level 15 is above 63 in. (elevation of top of SRU discharge device). If the continuous SRU _ h pneumatic supply is or becomes unavailable, depressurize with sustained SRU opening.
3
- HPCI 12
- RCIC
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 34 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0
- Reactor Feed Pump Turbines
- RHR Steam Condensing
- Offgas Preheater
- Steam Seal System
- RWCU (recirculation mode) if no boron has been injected into the RPU.
- Main steam line drains
- RWCU (blowdown mode) if no boron has been injected into the RPU. Refer to post accident sampling procedures prior to initiating blowdown.
If while executing steps RC/P-3 or RC/P-4, the reactor is not shutdown, return to Step RC/P-2.
RC/P-3 When either:
- All control rods except one are inserted to position 00
- (maximum subcritical banked withdrawal position), or
- 507 pounds (Cold Shutdown Boron Weight) (occurs at SLC tank i indication of 17%) of boron have been injected into the RPU, or
- The reactor is shutdown and no boron has been injected into _
i the RPV, depressurize the RPV and maintain cooldown 14, 17 rate below I'O F/hr (RPU cooldown rate LCO).
- This is an interim value which will be used until the generic calculation is completed by General Electric Co.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 35 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O RC/P-4 When the RHR shutdown cooling interlocks clear, initiate the shutdown cooling mode of RHR. 18 If the RHR shutdown cooling mode cannot be established and-further cooldown is required, continue to cool down using one or more of the systems used.for depressurization.
If RPU cooldown is required but cannot be accomplished and all control rods except one are inserted to position 00 (maximum subcritical banked withdrawal position),-ALTERNATE SHUTDOWN COOLING IS REQUIRED: enter the procedure developed from CONTINGENCY 5.
RC/P-5 Proceed to cold shutdown in accordance with the procedure for cooldown to cold shutdown conditions or as directed by Plant-Management.
W
/
.~
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 36 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION: !
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O RC/Q Monitor and control reactor power.
If while executing any step in RC/Q:
- All control rods except one are inserted to position 00 4
(maximum subcritical banked withdrawal position),
terminate boron injection and enter the scram procedure.
- The reactor is shutdown and no boron has been injected into the RPV, enter the scram procedure.
< RC/Q-1 Confirm or place the reactor mode switch in SHUTDOWN.
RC/Q-2 If the main turbine-generator is on-line and the MSIVs are
't open, confirm or initiate recirculation flow runback to minimum.
RC/Q-3 If reactor power is above 3% (APRM downscale trip) or cannot be determined, trip the recirculation pumps.
~
Execute Steps RC/Q-4 and RC/Q-5 concurrently.
i
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 37 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O l
1 i
RC/Q-4 If the reactor cannot be shutdown before 19 suppression pool temperature reaches 110 F (Boron Injection Initiation Temperature),
l BORON INJECTION IS REQUIRED; inject boron into the RPU with SLC and prevent automatic initiation of ADS.
If boron cannot be injected with SLC, inject boron into the RPU by one or more of the following alternate methods:
- CRD
- RWCU
- HPCI
- RCIC RC/Q-4.1 If boron is not being injected into the RPV by RWCU, confirm automatic isolation of or_ manually isolate RWCU.
j RC/Q-4.2 Continue to inject boron until %07 pounds (Cold shutdown Boron Weight) (occurs at *" C mr.k indication of-17%) of boron have been inject, ' 3.... '.he RPV. ,
RC/Q-4.3 Enter the scram procedure.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 38 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O RC/Q-5 Insert control rods as follows:
c RC/Q-5.1 If any scram value is not open:
- Remove:
1Hll-P609 1C71-F18A, E, C, G 1H11-P611 1C71-F18B, F, D, H (fuses which de-energize RPS scram solenoids).
- Close 1C11-F095 (scram air header supply value) and open 1Cll-FOO8 (scram air header vent value).
When control rods are not moving inward:
- Replace:
1Hll-P609 1C71-F18A, E, C, G 1H11-P611 1C71-F188, F, D, H (fuses which de-energize RPS scram solenoids).
- Close 1Cll-F008 (scram air header vent value) and open 1Cll-F095 (scram air header supply valve).
b RC/Q-5.2 Reset the reactor scram.
If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, continue at step RC/Q-5.6.1. -
- 2. Close IC11-F034 (HCU accumulator charging water header value).
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 39 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0
- 3. Rapidly insert control rods manually 20 until the reactor scram can be reset
- 4. Reset the reactor scram.
- 5. Open 1Cll-F034 (HCU accumulator charging water header valve).
RC/Q-5.3 If the scram discharge volume vent and drain valves are open, initiate a manual reactor scram.
- 1. If control rods moved inward, return to Step RC/Q-5.2.
- 2. Reset the reactor scram.
If the reactor scram cannot be reset, continue at step RC/Q-5.5.1.
l 3. Open the scram discharge volume vent and drain valves.
RC/Q-5.4 Individually open the scram test switches for control rods not inserted to position 00 (maximum subcritical banked withdrawal position).
When a control rod is not moving inward, close its scram test switch.
RC/Q-5.5 Reset the reactor scram.
If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, continue at step RC/Q-5.6.1.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 40 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0
- 2. Close 1C11-F034 (HCU accumulator charging water header value).
RC/Q-5.6 Rapidly insert control rods manually until all 20 control rods except one are inserted to position 00 (maximum subcritical banked withdrawal position).
If more than one control rod cannot be inserted to position 00 (maximum subcritical banked withdrawal position):
- 1. Individually direct the effluent from 1C11-F102 (CRD withdraw line vent value) to a contained radwaste drain and open 1C11-F102 (CRD withdraw line vent value) for each control rod not inserted to position 00 (maximum subcritical banked withdrawal position).
- 2. When a control rod is not moving inward, close its 1C11-F102 (CRD withdraw line vent value).
1 s
A
,,--,-,w,- - ~ , , , - ,
GEORGIA POWER COMPANY HATCH NUCLEAR-PLANT PAGE 41 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
- PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O PRIMARY CONTAINMENT CONTROL-GUIDELINE i
PURPOSE The purpose of this guideline is to:
- Maintain primary containment integrity, and
- Protect equipment in the primary containment.
ENTRY CONDITIONS The entry conditions for this guideline are any of the following:
- Suppression pool temperature above 95 F (most limiting suppression
- pool temperature LCO)
- Drywell temperature above 148 F (maximum normal operating temperature).
- - Drywell pressure above 2.0 psig (high drywell pressure scram J
setpoint) l --Suppression pool water level above 150 in. (maximum suppression pool l water level LCO)
, - Suppression pool water level below 146 in. (minimum suppression pool water level LCO).
OPERATOR ACTIONS I
(
Irrespective of the entry condition, execute Steps.SP/T, DW/T, t
PC/P, and SP/L concurrently.
4 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 42 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O SP/T Monitor and control suppression pool temperature, i
SP/T-1 Close all SORVs.
I If any SORV cannot be closed scram the reactor.
i SP/T-2 When suppression pool temperature exceeds 18 4
95 F (most limiting sup,araction pool temperature LCO), operate available suppression
, pool cooling.
]
SP/T-3 Before suppression pool temperature reaches 110*F (Boron i
Injection Initiation Temperature), scram the reactor.
1 SP/T-4 If suppression pool temperature cannot be f a
maintained below the Heat Capacity Temperature 13 Limit (see Attachment 2), maintain RPV pressure 14 below the Limit.
l If suppression pool temperature and RPV pressure cannot be restored and maintained.below the Heat Capacity Temperature Limit (see Attachment 2), EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: enter the procedure developed from the RPV Control ~
Guideline at Step RC-1 and execute it concurrently with SP/T.
l I
i i
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7
__ - - .. . . -- . . . .. .- - .-~ .. - -,
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 43 OF 93 DOCUMF.NT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0 1
DW/T Monitor and control drywell temperature.
DW/T-1 When drywell temperature. exceeds 148*F (maximum 6 1
normal operating temperature) operate available drywell cooling.
j i
i t
Execute Steps DW/T-2 and DW/T-3 concurrently, t
k j DW/T-2 If drywell temperature near the cold reference leg instrument vertical runs reaches the RPV Saturation j Temperature (see Attachment 4), RPV FLOODING IS REQUIRED:
i l enter the procedure developed from the RPV Control Guideline 1
- at Step RC-1 and execute it concurrently with DW/T.
l DW/T-3 Before drywell temperature reaches 281*F 18 I
(drywell design temperature), but only if suppression
- chamber temperature and pressure are below the Drywell Spray
- Initiation Pressure Limit and if drywell temperature and pressure are below the Drywell Spray Initiation Pressure l
j Limit (see Attachment 5), shut down recirculation pumps and l
] drywell cooling fans and initiate drywell sprays, ,
If drywell temperature cannot be maintained below 281*F l
(drywell design temperature), EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: enter the procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently
- j. . with DW/T.
3
- - - , , - - , , - , .,-..---,,.,----,Gn,---. , . , - ~ - . - 7, , , ,,-< -. , -.-,., ,, ,.wn,, ~ ,, --.--r , , - -
GEORGIA POWER COMPANY j HATCH NUCLEAR PLANT PAGE 44 OF 93 4
' DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O j PC/P Monitor and control primary containment pressure, i
j PC/P-1 Operate the following system, as required: . 21
- SBGT only when the temperature in the space being evacuated is below 212 F (Maximum Noncondensible Evacuation Temperature). Use SBGT operating procedures, i
i PC/P-2 Before suppression pool pressure reaches 8, 18 17.5 psig (Suppression Pool Spray Initiation Pressure),
but only if suppression pool water level is below 287 in.
(elevation of suppression pool spray nozzles),' initiate i
i suppression pool sprays, i
PC/P-3 If suppression chamber pressure exceeds 17.5 psig 18 i
(Suppression Chamber Spray Initiation Pressure) but only if suppression chamber temperature and pressure are below the Drywell Spray Initiation Pressure Limit and if drywell temperature and pressure
- are below the Drywell Spray Initiation Pressure Limit i
- (see Attachment 5), shut down recirculation pumps and j drywell cooling fand ~ end initiate drywell sprays.
1 PC/P-4 If suppression chamber pressure cannot be maintained below i
the Pressure Suppression Pressure (see Attachment 6),
l EMERGENCY RPU DEPRESSURIZATION IS REQUIRED.
J T
- l 1 .
l l
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 45 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O 4 PC/P-5 If suppression chamber pressure cannot be maintained below the Primary Containment Design Pressure (see Attachment 7),
RPU FLOODING IS REQUIRED.
PC/P-6 If suppression chamber pressure cannot be maintained below the Primary Containment Pressure Limit (sce Attachment 8),
then irrespective of whether adequate core cooling is assured:
- If suppression pool water level is below 287 in.
(elevation of suppression pool spray nozzles), initiate suppression pool sprays.
- If suppression chamber temperature and pressure are below the Drywell Spray Initiation Pressure Limit and if drywell temperature and pressure are below the Drywell Spray I
Initiation Pressure Limit (see Attachment 5), shut down recirculation pumps and drywell cooling fans and initiate drywell sprays.
.i PC/P-7 If suppression chamber pressure exceeds the Primary 22 Containment Pressure Limit, vent the primary containment-in _
l accordance with the Post Accident Venting Procedure to reduce and maintain pressure below the Primary Containment 1
Pressure Limit (see Attachment 8).
4
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 46 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT' SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O SP/L Monitor and control suppression pool water level.
SP/L-1 Maintain suppression pool water level between 8, 9 150 in. (maximum suppression pool water level LCO) and 146 in. (minimum suppression pool water level LCO). Refer to S ppression Pool sampling program prior to discharging water.
If suppression pool water level cannot be maintained above 146 in. (minimum suppression pool water level LCO) execute Step SP/L-2.
If suppression pool water level cannot be maintained below 150 in. (maximum suppression pool water level LCO), execute Stop SP/L-3. 4 SP/L-2 SUPPRESSION POOL WATER LEVEL BELOW 146 in. (minimum suppression pool water level LCO).
i Maintain suppression pool water level above the Heat Capacity Level Limit (see Attachment 9).
If suppression pool water level cannot be maintained above the Heat Capacity Level Limit (see Attachment 9), EMERGENCY RPU DEPRESSURIZATION IS REQUIRED: enter the procedure developed from the RPU Control Guideline at Step RC-1 and execute it concurrently with SP/L.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 47 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O SP/L-3 SUPPRESSION POOL WATER LEVEL ABOVE 150 in. (maximum suppression pool water level LCO).
Execute Steps SP/L-3.1 and SP/L-3.2 concurrently.
SP/L-3.1 Maintain suppression pool water level below the Suppression Pool Load Limit (see Attachment 3).
If suppression pool water level cannot be 13 maintained below the Suppression Pool Load 14 Limit (see Attachment 3), maintain RPU pressure below the limit.
If suppression pool' water level and'RPV pressure cannot be maintained below the Suppression Pool Load Limit (see Attachment 3) but only 1f adequate core cooling is assured, terminate injection into the RPU from sources external to the primary containment except from boron _
injection systems and CRD.
I t
i
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 48 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O If suppression pool water level and RPV pressure cannot be restored and maintained below the Suppression Pool Load Limit (see Attachment 3), EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: enter the procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with SP/L.
SP/L-3.2 Before suppression pool water level reaches 198 in.
(elevation of bottom of Mark I internal suppression pool to drywell vacuum breakers less vacuum breaker opening pressure in feet of water), but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron injection systems and CRD.
- 1. When suppression pool water level reaches 18 198 in. (elevation of bottom of Mark I internal suppression chamber to drywell i vacuum breakers less vacuum breaker opening pressure in feet of water) but only if suppression chamber temperature and pressure are below the Drywell Spray Initiation Pressure Limit and if drywell temperature and pressure are below the Drywell Spray Initiation Pressure Limit (see Attachment 5), shut down recirculation pumps and drywell cooling fans and initiate drywell sprays.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 49 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0
- 2. If suppression pool water level exceeds 23 198 in. (elevation of bottom of Mark I internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water), continue to operate drywell sprays.
- 3. When primary containment water level reaches 104.25 ft. (Maximum Primary Containment Water Level Limit),
terminate injection into the RPU from sources external to the primary containment irrespective of-whether adequate core cooling is assured.
i i
i
-l
- GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT PAGE 50 OF 93 DOCUMENT TITLE:. EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O SECONDARY CONTAINMENT CONTROL GUIDELINE
- PURPOSE The purpose of this guideline is to
- Protect equipment in the secondary containment,
- Limit radioactivity release to the secondary containment, and either:
- Maintain secondary containment integrity, or
- Limit radioactivity release from the secondary containment.
ENTRY CONDITIONS i
! The entry conditions for this guideline are any of the following i
secondary containment conditions (see Table II):
- Differential pressure at or above O in. of water 4
i - An area temperature above the maximum normal operating temperature
- A HUAC cooler differential temperature above the maximum normal i
- operating differential temperature ;
- A HUAC exhaust radiation level above the maximum normal operating radiation level
- An area-radiation level above the maximum normal operating radiation ,
level A floor drain sump water level above the maximum normal operating i
water level An area water level above the maximum normal operating water level
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 51 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O OPERATOR ACTIONS If while executing the following steps secondary containment HVAC exhaust radiation level exceeds 20mr/hr Refuel floor or 15mr/hr Reactor Building (secondary containment HVAC isolation setpoint):
- Confirm or manually initiate isolation of secondary containment HVAC, and
- Confirm initiation of or manually initiate SBGT only when the space being evacuated is below 212"F.
If while executing the following steps:
- Secondary containment HVAC isolates, and
- Secondary containment HUAC exhaust radiation level is below 20mr/hr Refuel floor or 15mr/hr Reactor Building (secondary containment HVAC isolation setpoint),
i restart secondary containment HUAC. 24 Irrespective of the entry condition, execute Steps SC/T, SC/R, and SC/L concurrently.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 52 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O SC/T Monitor and control secondary containment temperatures.
SC/T-1 Operate available area coolers.
SC/T-2 If secondary containment HVAC exhaust radiation level is below 20mr/hr Refuel floor or 15mr/hr Reactor Building (secondary containment HUAC isolation setpoint), operate available secondary containment HUAC.
SC/T-3 If any area temperature exceeds its maximum normal operating temperature, isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire.
SC/T-4 If a primary system is discharging into an area, then before any area temperature reaches its maximum safe operating temperature, enter the procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently.
with SC/T.
SC/T-5 If a primary system is discharging into an area and an area ,
temperature exceeds its maximum safe operating temperature in more than one area, EMERGENCY RPU DEPRESSURIZATION IS REQUIRED.
GEORGIH POWER COMPANY HATCH NUCLEAR PLANT PAGE 53 OF 93 DOCUMENT TITLE: EMERGENCY. OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O SC/R Monitor and control secondary containment radiation levels.
SC/R-1 If any area radiation level exceeds its maximum normal operating radiation level, isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire.
SC/R-2 If a primary system is discharging into an area, then before any area radiation level reaches its maximum safe operating radiation level, enter the procedure developed from the RPU Control Guideline at Step RC-1 and execute it concurrently with SC/R.
SC/R-3 If a primary system is discharging into an area and an area radiation level exceeds its maximum safe operating radiation level in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED, j i
SC/L Monitor and control secondary-containment water levels.
~
i SC/L-1 If any floor drain sump or area water level is above its maximum normal _ operating water level, operate available sump pumps to restore and maintain it below its' maximum normal operating water level, i
i GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 54 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O If any floor drain sump or area water 1? vel cannot be restored and maintained below its maximum normal operating water level, isolate all systems that are discharging water into the sump or area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire.
SC/L-2 If a primary system is discharging into an area, then before j any floor drain sump or area water level reaches its maximum safe operating water level, enter procedure developed from j the RPV Control Guideline at Step RC-1 and execute it concurrently with SC/L.
SC/L-3 If a primary system is discharging into an area and a floor drain sump or area water level exceeds its maximum safe
, operating water level in more than one area, EMERGENCY RPV i
i DEPRESSURIZATION IS REQUIRED.
I
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l
! ' GEORGIA POWER-COMPANY HATCH NUCLEAR PLANT PAGE'55 0F 93
) DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC' TECHNICAL GUIDELINE (UNIT 1) 0
) TABLE II i
j OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS SECONDARY CONTAINMENT MAXIMUM NORMAL MAXIMUM SAFE PARAMETER / LOCATION ALARM OPERATING VALUE OPERATING VALUE Differential pressure on 1H11-P700 (in. water) (in. water) psig
- Reactor Building /outside 0 0 +0.25 ,
air T46-R602A 0 0 +0.25 1 - Refuel Floor /outside air
- T46-R602B or 1H11-P657-R604A or B t
l i Area temperature from 1Hil-P614-R614 (*F) (*F) (*F)
- RWCU "A" pump room 158' G31-N016A 130 150 214 4
- RWCU "B" pump room 158' G31-N016B 130 150 214 2 - RWCU Hx room 158' at Hx,G31-N016C 130 150 214 l
1
- RWCU Hx room 158' disch-H.W.
G31-N016D 130 150 214 i - RWCU phase sep, room 158' 1
G31-N016E 130 150 214 j - RWCU holding pump room 185
{ G31-N016F 130 150 214
} - NF. Diagonal E11-N009A 175 175
- 214
{
- SE Diagonal E11-N0098 175 175
- 214 >
- HPCI room, area A E41-N024 150 175 214
- HPCI room, area B E41-NO30A 150 175 214 l - HPCI room, area C E41-NO308 150 175 214
- Torus room, westwall E51-N025A 150 175 '218
- Torus room, eastwall E51-NO25B 150 175 218 l - Torus room, northwall E51-N025C 150 175 218
{ ~ Torus room, southwall E51-NO250 150 175 218 4
l - Main steam tunnel 821-N014 160 200 300 ,
- SE, Reactor 130 elev., area A I E41-N046A 175 175
- 214
- SE, Reactor 130 elev., area B E41-N046B 175 175
- 214 '
- NW Diagonal, area A E51-N011 150 175 310
- NW Diagonal, area B E51-N023A 150 175 310
- NW Diagonal, area C E51-N0238 150 175 310 1
). Same as alarm setpoint l.
i d
. - _ . _ _ _ _ _ _ . _ _ _ _ - . _ m_. -
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 56 0F 93
- DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
{ PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O t
TABLE II (Continued)
OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS l
i I
SECONDARY CONTAINMENT MAXIMUM NORMAL MAXIMUM SAFE PARAMETER / LOCATION ALARM OPERATING UALUE OPERATING UALUE t Steam Leak Detection System Area (*F) (*F) (*F)
Differential Temperatures
- RWCU "A" Pump room G31-N022/N023A 75 75 98
- RWCU "B" Pump room G31-NO22/N023B 75 75 98
- RWCU Hx Room 158' l at Hxs G31-NO22/N023C 75 75 98 !
1 - RWCU Hx Room 158' ,
i disch. to Hotwell G31-N022/N0230 75 75
- 98 l - RWCU phase i separator room 158'G31-N022/N023E 75 75 98
- - RWCU holding pump i room 185' G31-N022/NO23F 75 75 98
- - Torus Room, i NW/ West E51-NO26/N027A 40 50 102 L
- Torus Room, '
NW/ West E51-N026/N027B 40 50 102 l - Torus Room,
) NW/ West E51-NO26/N027C 40 50 102
- - Torus Room, NW/ West E51-NO26/N027D 40 50 102 i
1
- Same as alarm setpoint I
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b GEORGIA POWER COMPANY
- HATCH NUCLEAR PLANT PAGE 57 0F 93 l DOCUMENT TITLE
- EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O TABLE II (Continued)
OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS l ,
SECONDARY CONTAINMENT MAXIMUM NORMAL MAXIMUM SAFE PARAMETER / LOCATION ALARM OPERATING VALUE OPERATING VALUE HUAC exhaust radiation (mr/hr) (mr/hr) (mr/hr) level above
- Reactor Building 15 50 1250
- Refuel Floor 20 50 1250 Area radiation level
- 158' Southeast Area Ch 9 15 50 1250
- Reactor Water Sample Rack Ch 10 30 50 1250
- 130' Northeast Work Area Ch 7 15 50 1250
- 130' Southwest Work Area Ch 8 15 50 1250
- North CRD Hydraulic Units Ch 13 15 50 1250
- South CR0 Hydraulic Units Ch 12 15 50 1250
- Spent fuel Pool Passageway Ch 11 15 50 1250
- 185' operating Floor Ch 25 30 50 1250
- Spent fuel Pool Ch 3 130 150 1250
- Fuel Pool Demin Panel Area Ch 31 10 50 1250
- Refuel floor Ch 4 15 50 1250
- HPCI Turbine Area Ch 16 100 150 1250
- RCIC Equipment Area Ch 18 20 50 1250
- CRD Pump Room NW Ch 19 20 50 1250
- North Core Spray &
RHR Area Ch 21 20 50 1250 1
- South Core Spray &
RHR Area Ch 14 20 50 1250 I
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l i GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT PAGE 58 OF 93 i DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0 TABLE II (Continued OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS 1 SECONDARY CONTAINMENT MAXIMUM NORMAL MAXIMUM SAFE PARAMETER / LOCATION ALARM OPERATING VALUE OPERATING UALUE Floor drain sump water level .(in.) (in.) (in.)
- Sump A (NE Diagonal) T45-N006 53 62 N/A
, - Sump B (NW Diagonal) T45-N007 53 53 N/A l
Area water level
- CRD Compartment T45-N005 5 11 14
- RCIC Compartment T45-N004 5 11 32
- RB NE Corner RM T45-N0038 5 11 19
- RB SE Corner RM T45-N003A 5 11 14
- HPCI compartment T45-N001 5 11 37 '-
- Torus Compartment NW T45-N002D 5 7 9 1
- Torus Compartment NE T45-N0028 5 7 9
- Torus Compartment SE T45-N002A 5 7 9
- Torus Compartment SW T45-N002C 5 7 9 I
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 59 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O RADIOACTIVITY RELEASE CONTROL GUIDELINE i.
PURPOSE The purpose of this guideline is to limit radioactivity release into creas outside the primary and secondary containments.
ENTRY CONDITIONS The entry condition for this guideline is:
- Offsite radioactivity release rate above 3 C1/sec (release rate ~
which requires an Alert).
OPERATOR ACTIONS RR-1 Isolate all primary systems that are discharging into areas outside the primary and secondary containments except systems required to assure adequate core cooling or shut down the reactor.
RR-2 If offsite radioactivity release rate approaches.or exceeds 91 C1/sec (release rate which requires a General Emergency) and a primary system is discharging into an area outside the primary ,
and secondary containments, EMERGENCY RPU DEPRESSURIZATION-IS REQUIRED; enter the procedure developed from the RPU Control Guideline at Step RC-1 and execute it concurrently with-RR.
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GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT PAGE 60 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O j CONTINGENCY 1 LEVEL RESTORATION If while executing any step in Contingency 1:
3 - Boron Injection is required, enter the procedure developed from CONTINGENCY 7.
- RPV water level cannot be determined, RPV FLOODING IS REQUIRED; enter the procedure developed from CONTINGENCY 6.
- RPV Flooding is required, enter procedure developed from CONTINGENCY 6.
- Cl-1 Line up for injection and start pumps in 2 or more of the following injection subsystems
- Condensate
-GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 61 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O If less than 2 of the injection subsystems can be lined up, commence lining up as many of the following alternate injection subsystems as possible:
- RHR service water crosstie
- ECCS keep-full systems
- SLC (test tank)
Cl-2 Monitor RPU pressure and water level. Continue in this Contingency at the step indicated as follows:
RPU PRESSURE REGION 340 psig I 2 100 psig HIGH INTERMEDIATE LOW-RPV INCREASING Cl-3 Cl-4 Cl-5 LEVEL DECREASING Cl-6 ~Cl-7 1(RPU pressure at which CS shutoff head is reached) 2(HPCI low pressure isolation setpoint).
4 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 62 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O If while executing steps Cl-3, C1-4, Cl-5, Cl-6, or Cl-7:
- The RPU water level trend reverses or RPU pressure changes region, return to Step Cl-2.
- RPU water level drops below -146 inches (ADS initiation setpoint), prevent automatic initiation of ADS.
Cl-3 RPU WATER LEVEL INCREASING, RPU PRESSURE HIGH
- Enter the procedure developed from the RPU Control Guideline at Step RC/L.
Cl-4 RPU WATER LEVEL INCREASING, RPU PRESSURE INTERMEDIATE If HPCI and RCIC are not available and RPU pressure is increasing, EMERGENCY RPU DEPRESSURIZATION IS REQUIRED. When RPU pressure is decreasing, enter the procedure developed from the RPU Control Guideline at Step RC/L.
If HPCI and RCIC are not available and RPU pressure is not increasing, enter the procedure developed from the RPU Control ,
Guideline at Step RC/L.
Otherwise, when RPU water level reaches +12.5 inches (low level scram setpoint), enter the procedure developed from the RPU 1
Control Guideline at Step RC/L.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 63 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O Cl-5 RPU WATER LEVEL INCREASING, RPV PRESSURE LOW If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter the procedure developed from the RPV Control Guideline at Step RC/L.
Otherwise, enter the procedure developed from the RPV Control Guideline at Step RC/L. -
Cl-6 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH OR INTERMEDIATE If HPCI or RCIC is not operating, restart whichever is not operating, s t/
I If no injection subsystem is lined up for injection with at 1,
least one pump running, start pumps in alternate injection ,, '
s subsystems which are lined up for injection.
N When RPV water level drops to -164.5 inches (top of active fuel):
- If no system, injection subsystem or alternate injection ,'
d
(
i subsystem is lined up with at least one pump running, STEAM 7;
- \'
COOLING IS REQUIRED. When any system, injection subsystem or-alternate injection subsystem is lined up with at least one
!; (
- 31 pump running, return to Step Cl-2. ,
- Otherwise, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When I 5-)
i RPU water level is increasing or RPU pressure drops below Ido ' ,1f'b i M /-
psig (HPCI low pressure isolation setpoint), return to , Step " ,- ';, g,-\.(\
[\
Cl-2. \
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 64 OF 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O Cl-7 RPU WATER LEVEL DECREASING, RPU PRESSURE LOW If no CS subsystem is operating, start pumps in alternate injection subsystems which are lined up for injection.
If RPU pressure in increasing, EMERGENCY RPV DEPRESSURIZATION IS I!EQUIRED.
n 1
When RPU water level drops to -164.5 inches (top of active fuel), enter the procedure developed from CONTINGENCY 4.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 65 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CONTINGENCY 2 EMERGENCY RPU DEPRESSURIZATION C2-1 When either: 13, 14
- Boron Injection is required and all injection into the RPU except from boron injection systems and CRD has been terminated and prevented, or
- Boron Inj ection is not required.
C2-1.1 If suppression pool water level is above 63 in. (elevation of top of SRU discharge device):
- Open all ADS valves.
- If any ADS valve cannot be opened, open other SRVs until'.7 (number of SRUs dedicated to ADS) valves are open.
4 C2-1.2 If less than 3 (Minimum Number of SRUs Required for 22 Emergency Depressurization) SRUs are open and RPU pressure is at least 50 psig (minimum SRU re-opening , ,
1 pressure) above suppression chamber pressure, rapidly depressurize the RPU using one or more of the following systems (use in order which-will minimize radioactive release to the environment):
a
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 66 OF 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0 Main condenser RHR (steam condensing mode)
- Steam Jet Air Ejectors Reactor Feed Pump Turbines Main steam line drains
- HPCI steam line
- RCIC steam line Head vent If RPV Flooding is required, enter the procedure developed from CONTINGENCY 6.
C2-2 Fnter the procedure developed from the RPV Control Guideline at-Step RC/P-4.
-- I s
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1 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 67 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CONTINGENCY 3 STEAM ~ COOLING If while executing any step in Contingency 3 Emergency RPV Depressurization is required or any system, inj ection subsystem, or alternate injection subsystem is lined up for injection with at least one pump running, enter the procedure developed from CONTINGENCY 2.
C3-1 When RPV water level drops to -264.5 in. (Minimum Zero-Inj ection RPU Water Level) or if RPV water level cannot be determined, open one SRV.
When RPU pressure drops below 700 psig (Minimum Single SRU Steam Cooling Pressure), enter the procedure developed from CONTINGENCY 2.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 68 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CONTINGENCY 4 CORE COOLING WITHOUT LEVEL RESTORATION C4-1 Open all ADS valves. 13 If any ADS value cannot be opened, open other SRUs until 7 (number of SRVs dedicated to ADS) values are open.
C4-2 Operate CS subsystems with suction from the suppression pool.
When at least one core spray subsystem is operating with suction from the suppression pool and RPU pressure is below 113 psig (RPU pressure for rated CS flow, terminate injection into the RPV from sources external to the primary containment.
C4-3 When RPU water level is restored to -164.5 inches (top of active fuel), enter the procedure developed from the RPU Control Guideline at Step RC/L.
g
i GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 69 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O i
CONTINGENCY 5 ALTERNATE' SHUTDOWN COOLING C5-1 Initiate suppression pool cooling.
C5-2 Close the RPV head vents, MSIVs, main steam line drain valves, and HPCI and RCIC isolation valves.
C5-3 Place the control switch for one (Minimum Number of SRVs Required for Alternate Shutdown Cooling) SRU in the OPEN position.
l CS-4 Slowly raise RPU water level to establish a flow path through the open SRU back to the suppression pool.
C5-5 Start one CS or LPCI pump with suction from the suppression pool.
C5-6 Slowly increase CS or LPCI injection into the RPV to the maximum.
C5-6.1 If RPU pressure does not stabilize at least 108 psig (Minimum Alternate Shutdown Cooling RPV Pressure) above suppression chamber pressure, start another CS or LPCI pump ~.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 70 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHIJICAL GUIDELINE (UNIT 1) O C5-6.2 If RPU pressure does not stabilize below 168 psig (Maximum Alternate Shutdown Cooling RPU Pressure), open another SRU.
C5-6.3 If the cooldown rate exceeds 100 F/hr (maximum RPU cooldown rate LCO), reduce CS or LPCI injection into the RPU until the cooldown rate decreases below 100aF/hr (maximum RPU cooldown rate LCO) or RPU pressure decreases to within 50 psig (Minimum SRU Re-opening Pressure ) of suppression chamber pressure, whichever occurs first.
C5-7 Control suppression pool temperature to maintain RPU water temperature above 70"F (head tensioning limit).
C5-8 Proceed to cold shutdown in accordance with the procedure for cooldown to cold shutdown conditions, or as directed by Plant.
Management.
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l GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 71 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CONTINGENCY 6 RPV FLOODING C6-1 If at least 3 (Minimum Number of SRVs Required for Emergency Depressurization) SRVs can be opened,'close the MSIVs, main steam line drain valves, HPCI, RCIC and RHR steam condensing isolation valves.
C6-2 If two or more control rods are at other than position 00 (maximum subcritical banked withdrawal-position):
C6-2.1 Terminate and prevent all injection into the RPU except from boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPU Flooding Pressure.
Number of Open SRVs Minimum Alternate RPV Flooding Pressure (psig) 7 or more 149 6 177 ,
5 215 4 272 3 368 2 560
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 72 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O If less than 2 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRU lifting pressure) SRVs can be opened, continue in this procedure.
If while executing step C6-2.2, RPV water level can be determined and RPV Flooding is not required, enter the procedure developed from CONTINGENCY 7 and the procedure developed from the RPU Control Guideline at Step RC/P-4 and execute them concurrently.
C6-2.2 Commence and slowly increase injection into the 25 RPV with the following systems until at least 2 (minimum number of SRVs for which the Minimum Alternate RPU Flooding Pressure is below the lowest SRV lifting i
pressure) SRVs are open and RPV pressure is above the Minimum Alternate RPU Flooding Pressure:
- Condensate pumps
- CRD
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- LPCI
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 73 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES- REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0 If at least 2 (minimum number of SRVs for which-the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure) SRVs are not open or RPU pressure cannot be increased to above the Minimum Alternate RPU Flooding Pressure, commence and slowly increase injection into the RPV with the following systems until at least 2 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRU lifting pressure) SRVs are open and RPV pressure is above the Minimum Alternate RPU Flooding Pressure:
- CS
- RHR service water crosstie
- ECCS keep-full systems C6-2.3 Maintain at least 2 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure) SRVs open and RPV pressure above the Minimum Alternate RPU Flooding i' assure by throttling inj ec tion .
C6-2.4 When:
~
- All control rods, except one, are inserted to position 00 (maximum subcritical banked withdrawal position), or
- The reactor is shutdown and no boron has been injected
- into the RPV, continue in this contingency.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 74 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O C6-3 If RPV water level cannot be determined:
C6-3.1 Commence and increase injection into the RPV with the following systems until at least 3 (Minimum Number of SRVs Required for Emergency Depressurization) SRVs are open and RPV pressure is not decreasing and is at least 53 psig (Minimum RPU Flooding Pressure) above suppression chamber pressure.
- CS
- LPCI
- Condensate pumps
- CRD
- RHR service water crosstie
- ECCS keep-full systems
- SLC (test tank)
C6-3.2 Maintain at least 3 (Minimum Number of SRVs Required for Emergency Depressurization) SRVs open and RPV pressure at least 53 psig (Minimum RPU Flooding Pressure)'above suppression chamber pressure by throttling inj ection. ,
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 75 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL. GUIDELINE (UNIT 1) O C6-4 If RPU water level can be determined, commence and increase injection into the RPU with the following systems until RPU water-level is increasing:
- CS
- LPCI
- Condensate pumps
- CRD
- RHR service water crosstie
- ECCS keep-full systems
- SLC (test tank)
C6-5 If RPV water level cannot be determined:
C6-5.1 Fill all RPV water level instrumentation reference columns.
C6-5.2 Continue injecting water into the RPU until the temperature near the cold reference leg instrument vertical runs is below 212 F and RPU water level instrumentation is available.
-~
If while executing steps C6-5.3 or C6-5.4, level can be determined, continue at step C6-6. .
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 76 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLjNT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O C6-5.3 If it can be determined that the RPU is filled or if RPU pressure is at least 53 psig (Minimum RPU Flooding Pressure) above suppression chamber pressure, terminate all injection into the RPU and reduce RPU water level.
C6-5.4 If RPU water level indication is not restored within the Maximum Core Uncovery Time Limit (see Attachment 10) after commencing termination of injection into the RPU, return to Step C6-3.
C6-6 When suppression chamber pressure can be maintained below the Primary Containment Design Pressure (see Attachment 7), enter the procedure developed from the RPU Control Guideline at Steps RC/L and RC/P-4 and execute these steps concurrently.
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l GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 77 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O CONTINGENCY 7 LEVEL / POWER CONTROL If while executing any step in Contingency 7 RPV Flooding is required or RPV water level cannot be determined, control injection into the RPU to maintain reactor power above 8% (Reactor Flow Stagnation Power) but as low as practicable. However, if reactor power cannot be determined or maintained above 8% (Reactor Flow Stagnation Power),
RPU FLOODING IS REQUIRED: enter the procedure developed from CONTINGENCY 6.
C7-1 If:
- Reactor power is above 3% (APRM downscale trip) or cannot be determined, and
- Suppression pool temperature is above 110'F (Boron Injection Initiation Temperature), and
- Either an SRU is open or opens or drywell pressure is above 2.0 ,
psig (high drywell pressure scram setpoint),
lower RPV water level by terminating and preventing 26 all injection into the RPV except from boron injection systems and CRD until either:
-. . 1
l GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 78 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) 0
- Reactor power drops below 3% (APRM downscale trip), or
- RPV water level reaches -164.5 inches (top of active fuel), or
- All SRVs remain closed and drywell pressure remains below 2.0 psig (high drywell pressure scram setpoint).
If while executing steps C7-2 or C7-3 Emergency RPV Depressurization is required, continue at step C7-2.1.
i If while executing steps C7-2 or C7-3:
- Reactor power is above 3% (APRM downscale trip) or cannot be determined, and
- RPU water level is above.-164.5 inches (top of active fuel),
and
- Suppression pool temperature is above 110*F (Boron Injection Initiation Temperature), and _
- Either an SRU is open or opens or drywell pressure is above 2.0 psig (high drywell pressure scram setpoint),
return to Step C7-1.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 79 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O C7-2 Maintain RPU water level either: 9, 10, 11, 25
- If RPV water level was deliberately lowered in Step C7-1, at the level to which it was lowered, or
- If RPV water level was not deliberately lowered in Step C7-1, between +12.5 inches (low level scram setpoint) and +58 inches 1
(high level trip setpoint),
with the following systems:
- Condensate System 385-0 psig (RPU pressure range for system operation)
- Condensate /feedwater system 1717-0 psig (RPV pressure range l
for system operation)
- CRD system 1525-0 psig (RPV pressure range for system operation)
- RCIC system 1120-50 psig (RPU pressure range .12 for system operation)
- HPCI system 1120-150 psig (RPU pressure range for system operation)
- LPCI system 280-0 psig (RPV pressure range for system operation)
~
If RPV water level cannot be so maintained, maintain RPV water level above -164.5 inches (top of active fuel).
If RPU water level cannot be maintained above -164.5 inches (top of active fuel). EMERGENCY RPV OEPRESSURIZATION IS REQUIRED.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 80 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O C7-2.1 Terminate and prevent all injection into the RPU except from boron injection systems and CRD until RPU pressure is below the Minimum Alternate RPU Flooding Pressure.
Number of Open SRVs Minimum Alternate RPV Flooding Pressure (psig) i 7 or more 149 6 177 5 215 4 272 3 368 2 560 If less than 2 (minimum number of SRVs for which the Minimum Alternate RPU Flooding Pressure is below the lowest SRV 4
lifting pressure) SRVs can be opened, continue in this Con tingency.
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GEORGIA POWER COMPANY
. HATCH NUCLEAR PLANT PAGE 81 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O C7-2.2 Commence and slowly increase injection into the 25 RPU with the following systems to restore and maintain RPU water level above -164.5 inches (top i of active fuel):
- Condensate /feedwater system
- CRD
- RCIC
! - HPCI
- LPCI i
, If RPU water level cannot be restored and maintained above
-164.5 inches (top of active fuel), commence and slowly
] .
increase injection into the RPU with the following systems to restore and maintain RPU water level above -164.5 inches (top of active fuel):
I - CS
- RHR service water crosstie
- ECCS keep-full systems
, If while executing step C7-3 step reactor power commences and continues to increase, return to Step C7-1.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 82 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION: i PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O i
C7-3 When 262.5 pounds (Hot Shutdown Boron Weight) (occurs at SLC tank indication of 39%) of boron have been injected or all control rods, except one, are inserted to position 00 (maximum subcritical banked withdrawal position), restore and maintain RPU water level between +12.5 inches (low level scram setpoint) and +58 inches (high level trip setpoint).
If RPU water level cannot be restored and maintained above +12.5 inches (low level scram setpoint), maintain RPU water level above -164.5 inches (top of active fuel).
If RPU water level cannot be maintained above -164.5 inches (top of active fuel), EMERGENCY RPU DEPRESSURIZATION IS REQUIRED:
return to Step C7-2.1.
If Alternate Shutdown Cooling is required, enter the procedure developed from CONTINGENCY 5.
C7-4 Proceed to cold shutdown in accordance with the procedure for ~
f cooldown to cold shutdown conditions, or as directed by Plant Management. .
1
ATTACHMENT 1 .
PAGE 83 OF 93 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O ATTACHMENT TITLE:
NPSH REQUIREMENTS 240
' ~~
ONSET OF BOILING:
SUPPIlESSICN # UNSTABLE SUPPRESSION 220' ~
p # --- CHAMBER CONDITIONS CllAM3ER PRESLURE I 210 --- -- -- -- 6PMU 200- - -- -- . - - . . . - l4 P9
_. } ..
E l 99G 100 - -
1 _
g 180- - -- --- -. . -- -
_gg l 3
r: ' ' ' '
' l18.5' CORE SPRAY 0 4720 GPM p 170- . ....
- J . _. , 9. - -l , gp. -- -
15'
' -#:h 20'l21.9' 20.8' '1H R O 7700 CPM
.s ,---- p- g', ,
160 --. . . . . . _ . . _ _ . _ _ . _ .
RCIC o 150- -
s' MINIMUM CREDIBLE _ .j
_ l g / SUPP11ESSICN POC L LEVEL.
y 140 5* . , , . 1P' , . . , 15' ..
20' , . . . 25' . l2s.s HPC
(--- ... .....
'. 4.'
i u0 120 - --
/
~~=
rh^'
. '_ f_. ' ' ' '
'4.'
4._
'J j272'coas sPaav s200 GPM l28' RHR G 10s00 GPM I
no. _ _
i 100 1
90 FIGURE 1 HATCH UNIT 1. MINIMUM SUPPAESSION POOL LEVEt.WHICH MEETS REQUIRED ~
NPSH FOR ECC'S PUMPS TAKING SUCTION FROM TORUS.
ATTACHMENT 2 -
PAGE 84 OF 93 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O ATTACHMENT TITLE:
HEAT CAPACITY TEMPERATURE LIMIT 200 190 180 N \
h N
e h 170 \
s N N
$ is0 N y is0 O
O h 140-U g 130 120 110 -
0 100 200 300 400 500 600 700 000 900 1000 1100 1200 1300 RPV PRESSURE (pois) ,
FIGURE C2-4 HEAT CAPACITY TEMPFRATI;RE LIMIT
ATTACHMENT 3 PAGE 85 OF 93 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1-DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O ATTACHMENT TITLE:
SUPPRESSION POOL LOAD LIMIT
( TO BE PROVIDED LATER )
J
ATTACHMENT 4 .
PAGE 86 OF 93 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O ATTACHMENT TITLE:
REACTOR PRESSURE VESSEL SATURATION LIMIT 550 e b /
s m
500 - /
k V U /
9 9 450- /
i /
=
E 400 b
/
o u
/
b m
O 300- --
m 6
z m 250-E E
H 200-U 100 2(o 300 400 500 600 700 000 900 1000 1100 RPV PRESSURE (psig)
FIGURE C7-1 ,,
RPy CATitD4tinN TFMPf D A Tilpf
l l
ATTACHMENT 5 PAGE 87 OF 93 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 2 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O ATTACHMENT TITLE:
DRYWELL SPRAY INITIATION PRESSURE LIMIT 400 380 360 i
340 320 g 300 1 ?
280 e
$ 260 5 240 s h 220 s
200 \ $
100 \ <
IM \, !i 140 120 100
~
0 5 10 .15 20 25 30 35 40 45 50 55 60 2
DRYWELL PRESSURE (pses) I'* 8 FIGURE C9-1 DRYWELL SPRAY INITIATION PRESSURE LIMIT (C9.I. WETWELL-TO-DRYWELL AP LIMIT)
ATTACHMENT 5 -
GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 2 OF 2 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O ATTACHMENT TITLE:
DRYWELL SPRAY INITIATION PRESSURE LIMIT 360 340 320 =
300 g 280 o-E 260
$ /"
$ 240 h /
220 e <
200 5
$ 180
- g 160 /
140
,20 /
100 I
.0
/
.0 0 5 10 .15 20 25 30 35 40 45 50 55 60 SUPPRESSION CH AM8ER PRESSURE (psig) inni FIGURE C9-2 ORYWELL SPRAY INITIATION PRESSURE LIMIT (C9.II.A. CONTAINMENT-TO-RB & LIMIT FOR RELATED SPRAY)
ATTACHMENT 6 -
PAGE 89 OF 93 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O ATTACHMENT TITLE:
PRESSURE SUPPRESSION PRESSURE 70 60
?
E 6
w E
~
//
)
' ~
f
?fAV/////f##A%%
I- PRESSURE SUPPRESSION PRESSURE 30-0 10 20 30 40 50 60 PRIMARY CONTAINMENT WATER LEVEL (f t) . ~
FIGURE C12-3 perssiipr supporssing enrsciinr
ATTACHMENT 7 PAGE 90 OF 93 '
GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE I OF 1 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O ATTACHMENT TITLE:
PRIMARY CONTAINMENT DESIGN PRESSURE 130 120 110 100 5 90 E
E g 80
$ 70 a
3 60 5 N 5 50 E
N l40 30 20 10 0 10 20 30 40 50 60 70 00 90 100 -'
PRIMARY CONTAINMENT VyATER LEVEL (ft) a n a..
FIGURE C13-2 PRIMARY CONTAltMENT DESIGN PRES $URE i
l I
l l
l j
< i 9
> , I ATTACHMENT 8 . . .
PAGE 'J1 O F 93 GEORGIA POWER COMPANY ATTACHMENT ',
HATCH NUCLEAR PLANT PAGE 110F A t 3
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION: ~s G s %
'*i PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O <-
\x \%
ATTACHMENT TITLE: 's: V PRIMARY CONTAINMENT PRESSURE LIMIT '\'
'/ 5 N
P 6
130 - -
, 3 I A g.
120 s
% l / 8 110 *
\
g, . . n; :- 't
~ '
100
) +- [\
'E 90 ~', s' \
5 y
, , w ' ,! .
g ( l N 'N -
g 80 -- A .
\r
- E , Il s I.
I L,
$70 ' ' '
') '
= J. .
{c 60 v , . 'r
% s t-',
u ,,
g 2 N '
9 N *
$g 'A l <
a:
' -> J b40
'f i 30 ',. .
'% ~,
20 ,
k e- ,, s I v .1 10 \
0 .
O 10 20 30 40 50 60 70 80 90 100 ,,
PRIMARY CONTAINMENT WATER LEVEL (ft) ann; ,
\
FIGURE C14 1 PRIMARY CONTAIN"ENT PRESSURE LIMIT s
e
T :~
v
",n
,g.; 6 i ., ATTACHMENT 9 -
7 -
- PAGE 92 OF 93 GEORGI A 'f 0WER COMP ANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENT % TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
s[ PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O
" ATTACHMENT TITLE:
q flEAT CAPACITY LEVEL LIMIT hs I
{ t lm' i
~% , t
'"s 6 t
240 230-220 210-200- - - - - _ _ 135 PS G __
C
. 190- p g 0
/
y <W
$ 180- gg g- T
$ V /
fLEVEL AT ATh.= 0
/
g 170- e
~
/'
lli 4# (,@9 jG-'
a M i
[ st D
4 S g
- 140- -
er-
-,o*
([
1 0- \ LEVEL. AT AT 3e =/,LL VAL UES FqR 2,T
-3 120- hc F0 1 WHICH l k
LEVELBU A MINIMUM 110- d--
\
, 100 s
s 6 7 8 9 to 11 12 13 14 15 16 17 18 19 20 21 22 SUPPRESSION POOL LEVEL (f t) ~
ATTACHMENT 10 PAGE 93 OF 93 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT' SPECIFIC TECHNICAL GUIDELINE (UNIT 1) O
. ATTACHMENT TITLE:
MAXIMUM CORE UNCOVERY TIME LIMIT 7
so 50 T c b
3
)
j do /
a r
kw r
.J 30 5
a 8
s 20 g E
Q E
10 i e 3 e io - a i. u n ion ... in m .sa 1000 mm un ** 30,000' TIME AFTER REACTOR SHUTDOWN (m.nl sun.:
FIGURE C23 1 .-
MAXIMIN CORE UNC0VERY TIME LIMIT 3;j 3
DRGIA POWER COMPANY
'/.[HATCHNUCLEAR
?
PLANT PAGE 1 OF 93*-
" DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION: - - -
PLnNT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O 3g. ,
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t HATCH NUCLEAR PLANT EMERGENCY OPERATING PROCEDURES-PLANT SPECIFIC TECHNICAL GUIDELINE
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 2 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDFLINE (UNIT 2) 0 TABLE OF CONTENTS SECTION PAGE PREFACE........................................................... 4 INTRODUCTION...................................................... 5 OPERATOR PRECAUTIONS............................................. 16 GENERAL. ................................................... 16 SPECIFIC.................................................... 20 RPV CONTROL GilIDELINE............................................ 27 RC/L.................................. ..................... 28 RC/P........................................................ 31 RC/Q........................................................ 36 PRIMARY CONTAINMENT CONTROL GUIDELINE............................ 41 SP/T........................................................ 42 DW/T................................. ...................... 43 PC/P................................................' ....... 44 SP/L........................................................ 46 SECOND A RY CONT AINMENT CONTROL GUIDE LINE . . . . . . . . . . . . . . . . . . . . . . . . . . 50 SC/1............... ........................................ 52 ,
SC/R..........................-.............................. 53 SC/L......................................................... 53 RADIOACTIVITY RELEASE CONTROL GUIDELINE.......................... 59-
GEORGIA-POWER COMPANY HATCH NUCLEAR PLANT PAGE 3 OF 93 -
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O SECTION PAGE 4
CONTINGENCIES 1 - LEVEL RESTORATION....................................... 60 ,
2 - EMERGENCY RPU DEPRESSURIZATION.......................... 65 3 - STEAM COOLING........................................... 67 4 - CORE COOLING WITHOUT LEVEL RESTORATION.................. 68 5 - ALTERNATE SHUTDOWN C00 LING.............................. 69 6 - RPU FLOODING.......... ................................. 71 7 - LEVEL / POWER CONTROL..................................... 77 ATTACHMENTS 1 - NPSH REQUIREMENTS....................................... 83 2 - HEAT CAPACITY TEMPERATURE LIMIT......................... 84 3 - SUPPRESSION POOL LOAD LIMIT............................. 85
{ 4 - RE ACTOR PRESSURE VESSEL S ATURATION LIMIT. . . . . . . . . . . . . . . . 86 5 - DRYWELL SPRAY INITIATION PRESSURE LIMIT................. 87 6 - PRESSURE SUPPRESSION PRESSURE........................... 89 7 - PRIMARY CONTAINMENT DESIGN PRESSURE..................... 90 8 - PRIMARY CONTAINMENT PRESSURE LIMIT...................... 91 9 - HEAT-CAPACITY LEVEL LIMIT............................... 92 l
10 - MAXIMUM CORE UNCOVERY TIME LIMIT........................ 93 4 i
4 TABLES I - ABBREVIATIONS / DEFINITIONS................................ 8
- . II - OPERATING UALUES OF SECONDARY CONTAINMENT PARAMETERS.... 55
GEORGIA POWER COMPANY
' HATCH NUCLEAR PLANT PAGE 4 OF 93 -
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O PREFACE This Plant Specific Technical Guideline was developed from the Boiling Water Reactor Owner's Group generic Emergency Procedure Guidelines, Revision 3, dated December 8, 1982, by following instructions '
contained on page I-2 of these generic guidelines. The format of this Plant Specific Technical Guideline is not intended to reflect the format of the Emergency Operating Procedures (EOP) developed from this guideline. Format of the EOP's will follow the instructions of the Plant Specific Writer's Guide. '
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE ' S OF 93 -
DOCUMENT TITLE: EMERGENCY-OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O i
INTRODUCTION Based on the BWR system design, the following Plant Specific Technical Guidelines have been developed:
RPU Control Guideline Primary Containment Control Guideline Secondary Containment Control Guideline Radioactivity Release Control Guideline The RPV Control Guideline contains instructions to enable the operator to maintain adequate core cooling, shut down the reactor, and cool
., down the RPV to cold shutdown conditions. This guideline is entered whenever low RPV water level, high RPV pressure, high drywell pressure, or c condition which requires MSIV isolation has occurred, or whenever a condition which requires reactor scram exists and reactor power is above the APRM downscale trip or cannot be determined.
The Primary Containment Control Guideline contains instructions to enable the operator to maintain primary containment integrity and protect equipment in the primary containment. This guideline is entered whenever suppression pool temperature, drywell temperature, ,
containment temperature, drywell pressure, or suppression pool water level is above its high operating limit or suppression pool water level is below its low operating limit.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 6 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REUISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O The Secondary containment Control Guideline contains instructions to enable the operator to protect equipment in the secondary containment, limit radioactivity release to the secondary containment, and either maintain secondary containment integrity or limit radioactivity release from the secondary containment. This guideline is entered whenever a secondary containment temperature, radiation level, or water level is above its maximum normal operating value or secondary containment differential pressure reaches zero.
The Radioactivity Release Control Guideline contains instructions to enable the operator to limit radioactivity release into areas outside the primary and secondary containments. This guideline is entered whenever offsite radioactivity release rate is above that which requires an Alert.
Table I is a list of abbreviations / definitions used in the guidelines.
Parentheses ( ) indicate the source for a plant specific variable.
Illustrated in these guidelines are variables specifically for HNP Unit 2.
At various points throughout these guidelines, cautions are noted by, _
for example, the symbol 20 .
The number within the box refers to a numbered " Caution" contained in the Operator Precautions section.
These " Cautions" are brief and succinct red flags for the operator.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 7 OF 92 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
.PtANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O Where the basis for the " Caution" or a step is not completely evident from the text, a full discussion of the basis is contained in Appendix B to the generic Emergency Procedures Guidelines. Other system details which pertain to the guidelines are.also included in this appendix.
At various points within these guidelines, limits are specified beyond which certain actions are required. While conservative, these limits are derived from engineering analyses utilizing best-estimate (as opposed to licensing) models. Consequently, these limits cre not as conservative as the limits specified in a plant's Technical Specifications. This is not to imply that operation beyond the Technical Specifications is recommended in an emergency. Rather, such operation may be required under certain degraded conditions in order to safely mitigate the consequences of those degraded conditions. The limits specified in the guidelines establish the boundaries within which continued safe operation of the plant can be assured.
Therefore, conformance with the guidelines does not ensure strict conformance with a plant's Technical Specifications or other licensing bases.
The entry conditions for these guidelines are symptomatic of both ,,
emergencies and events which may degrade into emergencies. The guidelines specify actions appropriate for both. Therefore, entry into procedures developed from these guidelines is not conclusive that an emergency has occurred.
[
i s us ,eoG L e a.( v uise n PAGE 8 0F 93 -
)CUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
. ANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O i
TABLE I ABBREVIATIONS / DEFINITIONS
)RD/ ABBREVIATION MEANING / APPLICATION Amendment lj us t To regulate or bring to a more satisfactory state. Example: " ADJUST Reactor Water Level setpoint to +36 inches."
13 Automatic Depressurization System.
Lign To place a system in proper or desired configuration for an intended purr,ose.
Example: " ALIGN Standby Gas Treatment to i
Reactor Building".
Llow To permit a stated condition to be achieved prior to proceeding. Example: " ALLOW discharge pressure to stabilize".
Lternato Injection Any of: keep fill systems, RHR service Subsystem water, SLC.
ipendix The Appendix to the Plant Specific Technical Guidelines.
qui Average Power Range Monitor. ,
ailable capable of performing its intended function e.g. adding water to the reactor.
GEORGIA POWEN COMPANY HATCH NUCLEAR PLANT PAGE 9 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION Check To perform a physical action which determines the state of a variable or status of equipment without directing a change in status. Example: " CHECK for satisfactory lube oil level".
Close To change the physical position of a mechanical device to the closed position so that . pre, vents fluid flow or permits passage of electric current. Example:
"CLOSE valve 2821-F019."
Complete To accomplish specific procedural requirements, Example: " COMPLETE value check-off list 3.7.1", " COMPLETE data report QA-1", " COMPLETE steps 7 through 9 of Section III".
CRD Control Rod Drive.
CS Core Spray. ,
DW/T Drywell Temperature Control.
ECCS Emergency Core Cooling System.
EPG Emergency Procedure Guideline generated by the BWR owners group with generic application to all BWRs.
j
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 10 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION: j PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O i TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION EOP Emergency Operating Procedures.
Establish To make arrangements for a stated condition. Example: " ESTABLISH communication with control room".
FSAR Final Safety Analysis Report.
ft. Foot or feet.
HCU Hydraulic Control Unit.
HNP Hatch Nuclear Plant.
HPCI High Pressure Coolant Injection.
HUAC Heating, Ventilating and Air Conditioning.
In. Inch or inches.
Injection Subsystem Any of: condensate, LPCI, or CS Isolate To close one or more values in a system for the purpose of separating or setting apart a complete system or a portion.of the system from the rest. Example: " ISOLATE _
~;
interruptible instrument air header by
! shutting value 2P51-F011."
I l
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 11 OF 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION Inspect To measure, observe, or evaluate a feature or characteristic for comparison with specified limits; method of inspection should be included. Example: " visually INSPECT for leaks".
LCO Limiting Condition for Operation.
LOCA Loss of Coolant Accident.
LPCI Low' Pressure Coolant Injection.
Maintain To keep in an existing state. Example:
" MAINTAIN the reactor vessel water'1evel between +15 and +55 inches, with one or more of the following systems", i MSIV Main Steam 1dne Isolation Valves, j NDTT Nil-Ductility Transition Temperature.
NE North East.
NPSH Net Positive Suction Head. , ,
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 12 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REUISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT-2) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION Open To change the physical position of a mechanical device to the open position so that it allows fluid flow or prevents passage of electrical current. Example:
"OPEN valve 2B21-FOl6". Unless specifically directed otherwise, open means fully open.
P Page.
PC Primary Containment Control.
PC/P Primary Containment Pressure Control.
PC/T Primary Containment Temperature Control.
Place To put in a particular position. Example:
" PLACE mode switch to shutdown".
Press. Pressure.
Primary System Main Steam, HPCI, RCIC, Core Spray, RHR, CRD, Feedwater, RWCU, SLC, Reactor Sampling Systems are the systems designated primary systems.
~
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PSIG Pounds per square inch 1 gage.
PSTG Plant' Specific Technical Guidelines'..
RCIC Reactor Core Isolation Cooling. ,
R 31 Revision Number 31, 1
1
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 13 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD / ABBREVIATION MEANING / APPLICATION RC RPU Control.
RC/L RPU Level Control.
RC/P RPU Pressure Control.
RC/Q RPU Power Control.
Record To document a specified condition or characteristic. Example: " RECORD discharge pressure".
Reduce To cause a parameter to decrease in value, example: " REDUCE reactor pressure with bypass valve manual jack".
RFPT Reactor Feed Pump Turbine RHR Residual Heat Removal.
RPS Reactor Protection System.
RR Radioactivity Release.
RSCS Rod Sequence Control System.
RWM Rod Worth Minimizer SBGT Standby Gas Treatment.
SC Secondary Containment Control.
SC/L Secondary Containment Level Control.
SC/R Secondary Containment Radiation Control.
L_
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 14 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O TABLE I (Continued)
ABBREUIATIONS/ DEFINITIONS f
WORD /ABBREUIATION MEANING / APPLICATION E
SC/T Secondary Containment Temperature Control.
SE South East.
Set To physically adjust to a specified value an
. adjustable feature. Example: " SET diesel speed to... rpm",
SORU Stuck Open Relief Valve.
! SP/L Suppression' Pool Level Control.
i j SP/T Suppression Pool Temperature Control.
I j SRV Safety Relief Valve.
Start To energize an electro-mechanical device by manipulation of a start switch or button.
- Example: " START a second CRD pump".
i Stop Opposite of start. Example: "STOP admitting i
-l steam by shutting valve 2821-f044".
! Synchronize To make synchronous in operation. Example: ,
" SYNCHRONIZE the Diesel Generator to 4160V Bus 2E".
.i Temp. Temperature.
5 i
e
t.
I GEORGIA POWER COMPANY
! -HATCH NUCLEAR PLANT PAGE 15 OF 93 l DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
l PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O i
l TABLE I (Continued)
ABBREVIATIONS / DEFINITIONS WORD /ABBREUIATION MEANING / APPLICATION Throttle To operate a valve in an intermediate position to obtain a certain flow rate.
i
- Example
- " THROTTLE value 2821-F077 to obtain 2000 lb/hr. flow".
Trip To manually activate a semi-automatic feature. Example: " TRIP breaker...".
IS Technical Specification.
Vent To permit a gas or liquid confined under pressure to escape at a vent. Example:
"UENT the Heat Exchanger before placing it in service".
Verify To prove to be true, exact, or accurate by observation of a condition or characteristic for comparison with an original or procedural requirement. Example: " VERIFY discharge pressure".
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 16 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O OPERATOR PRECAUTIONS GENERAL This section lists " Cautions" which are generally applicable at all times.
CAUTION 1 MONITOR THE' GENERAL STATE OF THE PLANT. IF AN ENTRY CONDITION FOR AN EMERGENCY OPERATING PROCEDURE OCCURS, ENTER THAT PROCEDURE. WHEN IT IS DETERMINED THAT AN EMERGENCY NO LONGER EXISTS, ENTER THE APPROPRIATE NORMAL OPERATING PROCEDURE AS DIRECTED BY THE EMERGENCY OPERATING PROCEDURES.
CAUTION 2 MONITOR RPU WATER LEVEL AND PRESSURE AND PRIMARY CONTAINMENT TEMPERATURES AND PRESSURE FROM MULTIPLE INDICATIONS, a__________________--____-___-_--_---_----- .- _ - -
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 17 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O .
l l
CAUTION 3 IF A SAFETY FUNCTION INITIATES AUTOMATICALLY, ASSUME A TRUE INITIATING EVENT HAS OCCURRED UNLESS OTHERWISE CONFIRMED BY AT LEAST TWO INDEPENDENT INDICATIONS.
CAUTION 4 WHENEVER RHR IS IN THE LPCI MODE, INJECT THROUGH THE HEAT EXCHANGERS AS SOON AS POSSIBLE.
CAUTION 5 SUPPRESSION POOL TEMPERATURE IS DETERMINED BY THE HIGHEST ,,
READING ON 2H11-P650 2T47-R627, 2H11-P657 2T47-R626. DRYWELL TEMPERATURE IS DETERMINED BY THE PROCEDURE IN HNP-2-1050 ITEM 8, DATA PACKAGE 1.
GEORGIA POWEN COMPANY HATCH NUCLEAR PLANT PAGE 18 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O CAUTION 6-WHENEVER TEMPERATURE NEAR THE INSTRUMENT REFERENCE LEG VERTICAL RUN EXCEEDS 1HE TEMPERATURE SHOWN BELOW AND THE INSTRUMENT READS BELOW THE INDICATED LEVEL IN THE TABLE, THE ACTUAL RPU WATER LEVEL MAY BE ANYWHERE BELOW THE ELEVATION OF THE LOWER INSTRUMENT TAP.
INDICATED TEMPERATURE LEVEL INSTRUMENT Any 96.2 IN. SHUTDOWN RANGE LEVEL
(-17 to+383 IN.) 2B21-R605 127.8'F -107.7 IN. WIDE RANGE LEVEL
(-150 to +60 IN.) 2B21-N024, NO25, NO26, NO31, 2C82-ROO5 285.6*F (B) 2.1 IN. NARROW RANGE LEVEL
( 0 to +60 IN.) 2C32-R606B 285.6af (B) 25.54 IN. NARROW RANGE LEVEL
( 0 to +60 IN.) 2B21-N042B 286.7'F (C,D) 2E.54 IN. NARROW RANGE LEVEL
( 0 to +60 IN.) 2821-N017C,D 287.8'F (A,C) 2.2 IN. NARROW RANGE LEVEL
( 0 to +60 IN.) 2C32-R606A,C 287.8af (A) 25.42 IN. NARROW RANGE LEVEL
( 0 to +60 IN.) 2821-N042A ,
287.8af (A,B) 25.42 IN. NARROW RANGE LEVEL
( 0 to +60 IN.) 2B21-NO17A,8 545'F -346.9'1N. FUEL ZONE LEVEL
(-317 to -17 IN.) 2821-NO36 NO37, R610, R615 A,8
l GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT PAGE 19 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC ~TECHNTCAL GUIDELINE (UNIT 2) 0 l
l l
CAUTION 7 2821-R604 A AND B ON P603, 2B21-R623 A AND B ON P601 (HEATED REFERENCE LEG INSTRUMENTS) INDICATED LEVELS ARE NOT RELIABLE DURING RAPID RPV DEPRESSURIZATION BELOW 500 PSIG. FOR THESE CONDITIONS, UTILIZE 2B21-R605 ON P602, 2B21-R610 ON P601, OR 2821-R615 ON P601 (COLD REFERENCE LEG INSTRUMENTS) TO MONITOR RPV WATER LEVEL.
CAUTION 8 OBSERVE NPSH REQUIREMENT FOR PUMPS TAKING SUCTION FROM THE SUPPRESSION POOL (SEE ATTACHMENT 1).
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 20 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O CAUTION 9 IF SIGNALS OF HIGH SUPPRESSION POOL WATER LEVEL 150 IN. (HIGH LEVEL SUCTION INTERLOCK) OR LOW CONDENSATE STORAGE' TANK WATER LEVEL 0 IN. (LOW LEVEL SUCTION INTERLOCK)' OCCUR, CONFIRM -
AUTOMATIC TRANSFER OF OR MANUALLY TRANSFER HPCI AND RCIC SUCTION FROM THE CONDENSATE STORAGE TANK TO THE SUPPRESSION POOL.
SPECIFIC THIS section lists " CAUTIONS" Which are applicable at one or more specific points within the guidelines. Where a " Caution" is applicable, it is identified with a symbol, for example: 20 .
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1 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 21 0F 93 l DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
1 PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 i
CAUTION 10 DO NOT SECURE OR PLACE AN ECCS IN MANUAL MODE UNLESS, BY AT LEAST TWO INDEPENDENT INDICATIONS, (1) MISOPERATION IN AUTOMATIC MODE IS CONFIRMED. OR (2) ADEQUATE CORE COOLING IS ASSURED. IF AN ECCS IS PLACED IN MANUAL MODE, IT WILL NOT INITIATE AUTOMATICALLY. MAKE FREQUENT CHECKS OF THE INITIATING OR CONTROLLING PARAMETER. WHEN MANUAL OPERATION IS NO LONGER REQUIRED, RESTORE THE SYSTEM TO AUTOMATIC / STANDBY MODE IF
- POSSIBLE.
)
4 1
CAUTION 11 1
i IF A HIGH DRYWELL PRESSURE ECCS INITIATION SIGNAL 2.0 PSIG i
(DRYWELL PRESSURE WHICH INITIATES ECCS) OCCURS OR EXISTS WHILE i
- DEPRESSURIZING, PREVENT INJECTION FROM THOSE CS AND LPCI. PUMPS NOT REQUIRED TO ASSURE ADEQUATE CORE COOLING PRIOR TO REACHING ,,
i THEIR MAXIMUM INJECTION PRESSURES. WHEN THE HIGH DRYWELL PRESSURE ECCS INITIATION SIGNAL CLEARS, RESTORE CS AND LPCI TO
]
l Aur0MATIC/ STANDBY MODE.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 22 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O CAUTION 12 DO NOT THROTTLE HPCI TURBINE BELOW 2000 RPM OR RCIC TURBINE BELOW 2250 RPM (MINIMUM TURBINE SPEED LIMIT PER TURBINE VENDOR MANUAL).
CAUTION 13 COOLDOWN RATES ABOVE 100 F/HR (RPV COOLDOWN RATE LCO) MAY BE REQUIRED TO ACCOMPLISH THIS STEP, i
CAUTION 14 l
DO NOT DEPRESSURIZE THE RPV BELOW 100 PSIG (HPCI LOW PRESSURE )
ISOLATION SETPOINT) UNLESS MOTOR DRIVEN PUMPS SUFFICIENT TO MAINTAIN RPU WATER LEVEL ARE RUNNING AND AVAILABLE FOR l INJECTION.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 23 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC' TECHNICAL GUIDELINE (UNIT 2) O
- CAUTION 15 i
OPEN SRU'S IN THE FOLLOWING SEQUENCE If POSSIBLE: M, B , G, F, D, L, K, C, A. USE SRV'S E AND H ONLY IF UNABLE TO MAINTAIN I PRESSURE WITH OTHER SRV'S, I
l CAUTION 16 l
- ISOLATION INTERLOCKS MAY BE REQUIRED TO ACCOMPLISH THIS STEP.
)
i CAUTION 17 COOLDOWN RATES ABOVE 100 F/HR (RPV COOLDOWN RATE LCO) MAY BE ,,
REQUIRED TO CONSERVE RPV WATER. INVENTORY, PROTECT PRIMARY CONTAINMENT INTEGRITY, OR LIMIT RADIOACTIVE RELEASE TO THE f
ENVIRONMENT.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 24 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REUISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O
,i f
4 CAUTION 18 IF CONTINUOUS LPCI OPERATION IS REQUIRED TO ASSURE ADEQUATE
, CORE COOLING, DO NOT DIVERT ALL RHR PUMPS FROM LPCI MODE.
CAUTION 19 a
MANUALLY TRIP SLC PUMPS AT 0% IN THE SLC TANK.
I 3
i CAUTION 20 DEFEATING RSCS AND/OR RWM INTERLOCKS MAY BE REQUIRED TO ACCOMPLISH THIS STEP. ~
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GEONGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 25 OF 93 1' DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O 4
1 CAUTION 21 ELEVATED SUPPRESSION CHAMBER PRESSURE MAY TRIP THE RCIC TURBINE ON HIGH EXHAUST PRESSURE.
.f j CAUTION 22 1
DEFEATING ISOLATION INTERLOCKS MAY BE REQUIRED TO ACCOMPLISH
! THIS STEP.
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f CAUTION 23 i
DO NOT INITIATE DRYWELL SPRAYS IF SUPPRESSION POOL WATER LEVEL IS ABOVE 216 IN. (ELEVATION OF BOTTOM OF MARK I INTERNAL ,
SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKERS LESS VACUUM
! BREAKER OPENING PRESSURE IN FEET OF WATER),
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GEORGIA POWER COMPANY.
HATCH NUCLEAR PLANT PAGE 26 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O CAUTION 24 ,
s s BYPASSING HIGH DRYWELL PRESSURE AND LOW RPV WATER LEVEL- ,
SECONDARY CONTAINMENT HVAC ISOLATION INTERLOCKS MAY BE ,
REQUIRED TO ACCOMPLISH THIS STEP. '
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i CAUTION 25 A RAPID INCREASE IN INJECTION INTO THE RPV MAY INDUCE A LARGE- -
s.
3 POWER EXCURSION AND RESULT IN SUBSTANTIAL CORE DAMAGE. D.' .
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. I t'sG ly CAUTION 26 ; .'5 y \"o ,i
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.E LARGE REACTOR POWER OSCILLATIONS MAY BE OBSERVED WHILE . b'N i t - g,
.Ay .r '
EXECUTING THIS STEP. - e l., ' -
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 27 OF 93 DOCUMENT-TITLE: EMERGENCY OPERATING PROCEDURES- REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O f RPU CONTROL GUIDELINE ig-t PURPOSE The purpose of this guideline is to:
Maintain adequate core cooling, Shut down the reactor, and Cool down the RPU to cold shutdown conditions (RPU temperature between 100 F and 212*F).
ENTRY CONDITIONS The entry conditions for this guideline are any of the following:
RPV water level below +12.5 inches (Iow level scram setpoint).
RPU pressure above 1045 psig (high RPU pressure scram setpoint).
Drywell pressure above 2 psig (high drywell pressure scram setpoint).
A condition which requires MSIU isolation.
A condition which requires reactor scram, and reactor power above
\
3% (APRM downscale trip) or cannot be determined.
1 '
OPERATOR ACTIONS
' , RC J1 If reactor scram has not been initiated, initiate reactor scram.
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Irrespective of the entry condition, execute Steps RC/L, RC/P, and RC/Q concurrently.
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GEORGIA POWER COMPANY '
HATCH NUCLEAR PLANT PAGE 28 OF 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O l
1 RC/L Monitor and control RPU water level.
s RC/L-1 Confirm initiation of any of the following:
- Isolation ,
- ECCS
- Emergency diesel generator -
Initiate any of these which should have initiated but did not.
a If while executing step RC/L-2:
- Boron Injection is required, enter the procedure developed from CONTINGENCY 7.
- RPU water level cannot be determined, RPV FLOODING I;S REQUIRED enter the procedure developed from CONTINGENCY 6. #
- RPU Flooding is required, enter the. procedure developed from J' r ,
CONTINGENCY 6.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 29 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 RC/L-2 Restore and maintain RPV water level between +12.5 in. (low level scram setpoint) 9 and +58 in. (high level trip setpoint) 10 with one or more of the following systems: 11
- Condensate system 650-0 psig (RPU pressure range for system operation).
- Condensate /feedwater system 1717-0 psig (RPU pressure range for system operation)
- CRD system 1507.-0 psig (RPV pressure range for system operation)
- RCIC system 1120-50 psig (RPV pressure 12 range for system operation)
- HPCI system 1120-150 psig (RPU pressure range for system operation)
- CS system 435-0 psig (RPV pressure range for system opsrmtions)
- LPCI system 225-0 psig (RPU pressure range for system operation)
If RPU water level cannot be restored and maintained above
+12.5 inches (low level scram setpoint), maintain RPV water _
level above -164.5 inches (top of active fuel).
If RPU water level can be maintained above -164.5 inches (top of active fuel) and the ADS timer has initiated, prevent automatic RPU depressurization by resetting the ADS timer. <
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 30 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 -
If RPV water level cannot be maintained above -164.5 inches (top of active fuel), enter the procedure developed from CONTINGENCY 1.
If Alternate Shutdown Cooling is required, enter the procedure 1
developed from CONTINGENCY 5.
RC/L-3 Proceed to cold shutdown in accordance with the procedure for cooldown to cold shutdown conditions or as directed by Plant Management.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 31 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O RC/P Monitor and control RPU pressure.
If while executing any step in RC/P:
- Emergency RPU Depressurization is anticipated, 13 rapidly depressurize the RPU with the main turbine bypass valves.
- Emergency RPU Depressurization or RPU Flooding is required and less than 7 (number of SRVs dedicated to ADS) SRVs are open, enter the procedure developed from CONTINGENCY 2.
- RPU Flooding is required and at least 7 (number of SRUs dedicated to ADS) SRVs are open, enter the procedure developed from CONTINGENCY 6.
RC/P-1 If any SRU is cycling, manually open SRVs until RPU pressure drops to 927 psig (RPU pressure at which all turbine bypass valves are fully open).
l I
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 32 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O If while executing steps RC/P-2, RC/P-3, or RC/P-4:
- Suppression pool temperature cannot be maintained 8 below the Heat Capacity Temperature Limit (see 13 Attachment 2), maintain RPU pressure below the Limit. 14
- Suppression pool water level cannot be maintained 13 below the Suppression Pool Load Limit (see 14 Attachment 3) maintain RPU pressure below the Limit.
- Steam Cooling is required, enter the procedure developed from CONTINGENCY 3.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 33 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O If while executing steps RC/P-2, RC/P-3, or RC/P-4:
- Boron Injection is required, and
- The main condenser is available, and
- There has been no indication of gross fuel failure or steam line break, open MSIVs to re-establish the main condenser as a heat sink. 16 RC/P-2 Control RPU pressure below 1090 psig (lowest SRU 14 lifting pressure) with the main turbine bypass values.
RPU pressure control may be augmented by one or more of the following systems:
- SRVs only when suppression pool water level 15 is above 58 in. (elevation of top of SRU discharge device). If the continuous SRV ,
j pneumatic supply is or becomes unavailable, depressurize with sustained SRU opening.
- HPCI 12
- RCIC
i GEORGIA POWER COMPANY HATCH ~ NUCLEAR PLANT PAGE 34 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0
- Reactor Feed Pump Turbines
- RHR Steam Condensing
- Offgas Preheater ,
- Steam Seal System
- RWCU (recirculation mode) if no boron has been injected into the RPU.
- Main steam line drains
- RWCU (blowdown mode) if no boron has been injected into the RPU. Refer to post accident sampling procedures prior to initiating blowdown.
If while executing steps RC/P-3 or RC/P-4, the reactor is not shutdown, return to Step RC/P-2.
RC/P-3 When either:
- All control rods except one are inserted to position 00
- (maximum subcritical banked withdrawal position), or
- 551.1 pounds (Cold Shutdown Boron Weight) (occurs at SLC tank indication of 19%) of boron have been injected into the RPV, or
- The reactor is shutdown and no boron has been injected into _
the RPV, depressurize the RPU and maintain cooldown 14, 17 rate below 100 F/hr (RPV cooldown rate _LCO).
- This is an interim value which will be used until the generic calculation is completed by General Electric Co.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 35 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O RC/P-4 When the RHR shutdown cooling interlocks clear, initiate the shutdown cooling mode of RHR. 18 If the RHR shutdown cooling mode cannot be established and further cooldown is required, continue to cool down using one or more of the systems used for depressurization.
If RPV cooldown is required but cannot be accomplished and all control rods except one are inserted to position 00 (maximum subcritical banked withdrawal position), ALTERNATE SHUTDOWN COOLING IS REQUIRED: enter the procedure developed from CONTINGENCY 5.
t i
1 RC/P-5 Proceed to cold shutdown in accordance with the procedure for cooldown to cold shutdown conditions or as' directed by Plant Management.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 36 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O RC/Q Monitor and control reactor power.
If while executing any step in RC/Q:
- All control rods except one are inserted to position 00 (maximum subcritical banked withdrawal position),
terminate boron injection and enter the scram procedure.
- The reactor is shutdown and no boron has been injected into the RPU, enter the scram procedure.
RC/Q-1 Confirm or place the reactor mode switch in SHUTDOWN.
RC/Q-2 If the main turbine-generator is on-line.and the MSIVs are-open, confirm or initiate' recirculation flow runback to minimum.
RC/Q-3 If reactor power is above 3% (APRM downscale trip) or cannot be determined, trip the recirculation pumps.
~
Execute Steps RC/Q-4 and RC/Q-5 concurrently.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 37 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 RC/Q-4 If the reactor cannot be shutdown before 19 suppression pool temperature reaches 110 F (Boron Injection Initiation Temperature),
BORON INJECTION IS REQUIRED; inject boron into the RPU with SLC and prevent automatic initiation of ADS.
If boron cannot be injected with SLC, inject boron into the RPU by one or more of the following alternate methods:
- CRD
- RWCU
- HPCI
- RCIC J
RC/Q-4.1 If boron is not being injected into the RPU by RWCU, confirm automatic isolation.of or manually isolate RWCU.
RC/Q-4.2 Continue to inj ect boron until 551.1 pounds (Cold Shutdown Boron Weight) (occurs at SLC tank indication of 19%) of boron have been injected into the RPU. ,
RC/Q-4.3 Enter the scram procedure.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 38 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O RC/Q-5 Insert control rods as follows:
RC/Q-5.1 If any scram valve is not open:
- Remove:
2H11-P609 2C71-F18A, E, C, G 2H11-P611 2C71-F18B, F, D, H (fuses which de-energize RPS scram solenoids).
- Close 2Cll-F095 (scram air header supply value) and open 2Cll-F008 (scram air header vent value).
When control rods are not moving inward:
- Replace:
2H11-P609 2C71-F18A, E, C, G 2H11-P611 2C71-F188, F, D, H (fuses which de-energize RPS scram solenoids)'.
- Close 2C11-F008 (scram air header vent value) and open 2Cll-F095 (scram air header supply value).
RC/Q-5.2 Reset the reactor. scram.
If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, continue at step RC/Q-5.6.1,
- 2. Close 2Cll-F034 (HCU accumulator charging water header value).
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 39 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O
- 3. Rapidly insert control rods manually 20 until the reactor scram can be reset
- 4. Reset the reactor scram.
s
- 5. Open 2C11-F034 (HCU accumulator charging w'ater header value). -
RC/Q-5.3 If the scram discharge volume vent and drain values are open, initiate a manual reactor scram.
- 1. If control rods moved inward, return to Step RC/Q-5.2.
- 2. Reset the reactor scram.
If the reactor scram cannot be reset, continue at step RC/Q-5.5.1.
- 3. Open the scram discharge volume vent and drain valves. ,
RC/Q-5.4 Individually open the scram test switches for control rods not inserted to position 00 (maximum subcritical banked withdrawal position).
.j When a control rod is not moving inward, close its scram test switch.
~
4 Reset the reactor scram.
RC/Q-5.5 If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, continue -
at step RC/Q-5.6.1.
GEORGIA POWER COMPANY 1 HATCH NUCLEAR PLANT PAGE 40 OF 93 '
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0
- 2. Close 2C11-F034 (HCU accumulator charging water i
. header value).
RC/Q-5.6 Rapidly insert control rods manually until all 20 control rods except one are inserted to position 00 (maximum subcritical banked withdrawal position). -
V'
) If more than one control rod cannot be inserted to Position 00 (maximum subcritical banked withdrawal position):
- 1. Individually direct the effluent from 2C11-F102 (CRD withdraw line vent valve) to a contained radwaste drain and open 2C11-F102 (CRD withdraw line vent value) for each control rod not inserted to position 00 (maximum suberitical banked withdrawal position).
- 2. When a control rod is not moving inward, close its 2C11-F102 (CRD withdraw line vent value).
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 41 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O PRIMARY CONTAINMENT CONTROL GUIDELINE PURPOSE _
The purpose of this guideline is to:
~
- Maintain primary containment integrity, and
- Protect equipment in the primary containment.
ENTRY CONDITIONS The entry conditions for this guideline are any of the following:
- Suppression pool temperature above 95 F (most limiting suppression pool temperature LCO)
- Drywell temperature above 135 F (drywell temperature LCO)
- Drywell pressure above 2.0 psig (high drywell pressure scram setpoint)
- Suppression pool water level above 150 in. (maximum suppression pool water level LCO)
- Suppression pool water level below 146 in. (minimum suppression pool water level LCO).
OPERATOR ACTIONS
~
Irrespective of the entry condition, execute Steps SP/T, DW/T, PC/P, and SP/L concurrently.
GEORGIA POWER COMPANY j HATCH NUCLEAR PLANT PAGE 42 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O l SP/T Monitor and control suppression pool temperature.
SP/T-1 Close all SORVs.
If any SORU cannot be closed scram the reactor.
SP/T-2 When suppression pool temperature exceeds 18 95 F (most limiting suppression pool temperature LCO), operate available suppression pool cooling.
SP/T-3 Before suppression pool temperature reaches 110'F (Boron Inj ection Initiation Temperature), scram the reactor.
SP/T-4 If suppression pool temperature cannot be 8 ,
maintained below the Heat Capacity Temperature 13 Limit (see Attachment 2), maintain RPV pressure 14 below the Limit.
If suppression pool temperature and RPU pressure cannot be restored and maintained below the Heat Capacity Temperature Limit (see Attachment 2), EMERGENCY RPV DEPRESSURIZATION IS
, REQUIRED; enter the procedure developed from the RPV Control ,
Guideline at Step RC-1 and execute it concurrently with SP/T.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 43 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O DW/T Monitor and control drywell temperature.
DW/T-1 When drywell temperature exceeds 135*F (drywell 6 temperature LCO) operate available drywell cooling.
Execute Steps DW/T-2 and DW/T-3 concurrently.
DW/T-2 If drywell temperature near the cold reference leg instrument vertical runs reaches the RPU Saturation Temperature (see Attachment 4), RPU FLOODING IS REQtlIRED:
enter the procedure developed from the RPU Control Guideline at Step RC-1 and execute it concurrently with DW/T.
t DW/T-3 Before drywell temperature reaches 340*F 18 (drywell design temperature), but only if suppression chamber temperature and pressure are below the Drywell Spray Initiation Pressure Limit and if'drywell temperature and pressure are below the Drywell spray Initiation Pressure Limit (see Attachment 5), shut down recirculation pumps and drywell cooling fans and initiate drywell sprays. .,
If drywell temperature cannot be maintained below 340 F (drywell design temperature), EMERGENCY RPU DEPRESSURIZATION IS REQUIRED: enter the procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with DW/T.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 44 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
-PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O PC/P Monitor and control primary containment pressure.
PC/P-1 Operate the following system, as required: 21
- SBGT only when the temperature in the space being evacuated is below 212 F (Maximum Noncondensible Evacuation Temperature). Use SBGT operating procedures.
PC/P-2 Before suppression pool pressure reaches 8, 18 17.1 psig (Suppression Pool Spray Initiation Pressure),
but only if suppression pool water level is below 287 in.
(elevation of suppression pool spray nozzles), initiate
- suppression pool sprays.
PC/P-3 If suppression chamber pressure exceeds 17.1 psig 18 (Suppression Chamber Spray Initiation Pressure) but only if suppression chamber temperature and pressure are below the Drywell Spray Initiation Pressure Limit and if drywell temperature and pressure are below the Drywell Spray Initiation Pressure Limit (see l Attachment 5), shut down recirculation pumps and drywell cooling fans and_ initiate drywell sprays.
~
2 PC/P-4 If suppression chamber pressure cannot be maintained below the Pressure Suppression Pressure (see Attachment 6),
EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 45 OF 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O PC/P-5 If suppression chamber pressure cannot be maintained below the Primary Containment Design Pressure (see Attachment 7),
RPV FLOODING IS REQUIRED.
PC/P-6 If suppression chamber pressure cannot be maintained below the Primary Containment Pressure Limit (see Attachment 8),
then irrespective of whether adequate core cooling is assured:
- If suppression pool water level is below 287 in.
(elevation of suppression pool spray nozzles), initiate suppression pool sprays.
- If suppression chamber temperature and pressure are below l
the Drywell Spray Initiation Pressure Limit and if drywell temperature and pressure are below the Drywell Spray
] Initiation Pressure Limit (see Attachment 5), shut down recirculation pumps and drywell cooling fans and initiate
! drywell sprays.
PC/P-7 If suppression chamber pressure exceeds the Primary 22 Containment Pressure Limit, vent tne primary containment in
~
- accordance with the Post Accident Venting Procedure to
$ reduce and maintain pressure below the Primary Containment Pressure Limit (see Attachment 8).
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 46 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O SP/L Monitor and control suppression pool water level.
SP/L-1 Maintain suppression pool water level between 8, 9 150 in. (maximum suppression pool water level e
LCO) and 146 in. (minimum suppression pool water level LCO). Refer to Suppression Pool sampling program prior to discharging water.
If suppression pool water level cannot be maintained above 146 in. (minimum suppression pool water level LCO) execute Step SP/L-2.
l If suppression pool water level cannot be maintained below
] 150 in. (maximum suppression pool water level LCO), execute
, Step SP/L-3.
SP/L-2 SUPPRESSION POOL WATER LEVEL BELOW 146 in. (minimum suppression pool water level LCO).
Maintain suppression pool water level above the Heat Capacity Level Limit (see Attachment 9).
~
If suppression pool water level cannot be maintained above the Heat Capacity Level Limit (see Attachment 9), EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter the procedure-developed from the RPU Control Guideline at Step RC-1 and execute it concurrently with SP/L.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 47 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O SP/L-3 SUPPRESSION POOL WATER LEVEL ABOVE 150 in. (maximum suppression pool water level LCO).
Execute Steps SP/L-3.1 and SP/L-3.2 concurrently.
SP/L-3.1 Maintain suppression pool water level below the Suppression Pool Load Limit (see Attachment 3).
If suppression pool water level cannot be 13 I
maintained below the Suppression Pool Load 14 Limit (see Attachment 3), maintain RPV pressure below
, the limit.
l If suppression pool water level and RPU pressure cannot be maintained below the Suppression Pool Load Limit (see Attachment 3) but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary _ containment _except from boron ,
inj ection systems and CRD.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 48 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O I If suppression pool water level and RPU pressure cannot be restored and maintained below the Guppression Pool Load Limit (see Attachment 3), EMERGENCY RPU DEPRESSURIiATION IS REQUIRED: enter the procedure developed from the RPU Control Guideline at Step RC-1 and execute it concurrently with SP/L.
SP/L-3.2 Before suppression pool water level reaches 216 in.
(elevation of bottom of Mark I_ internal suppression pool to drywell vacuum breakers less vacuum breaker opening pressure in feet of water), but only if-adequate core cooling is assured, terminate injection into the RPU from sources external to the primary containment except from boron injection systems and CRD.
- 1. When suppression pool water level reaches 18 216 in. (elevation of bottom of Mark'I internal suppression chamber to drywell vacuum breakers less vacuum breaker opening -
pressure in feet of water) but only if suppression chamber temperature and pressure are below the , ]
Drywell Spray Initiation Pressure Limit and if '
drywell temperature and pressure are below the I Drywell Spray Initiation Pressure' Limit'(see '
. Attachment 5), shut down recirculation _ pumps and drywell cooling fans and initiate drywell sprays. .
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 49 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O
- 2. If suppression pool water level exceeds 23 216 in. (elevation of bottom of Mark I internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water), continue to operate drywell sprays.
- 3. When primary containment water level reaches 103.5 ft. (Maximum Primary Containment Water Level Limit),
terminate injection into the RPU from sources external to the primary containment irrespective of whether adequate core cooling is assured.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 50 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O SECONDARY CONTAINMENT CONTROL GUIDELINE PURPOSE The purpose of this guideline is to:
- Protect equipment in the secondary containment,
- Limit radioactivity release to the secondary containment, and either:
- Maintain secondary containment integrity, or
- Limit radioactivity release from the secondary containment.
ENTRY CONDITIONS The entry conditions for this guideline are any of the following secondary containment conditions (see Table II):
- Differential pressure at or above O in, of water
- An area temperature above the maximum normal operating temperature
- A HUAC cooler differential temperature above the maximum normal operating differential temperature
- A HUAC exhaust radiation level above the maximum normal operating radiation level
- An area radiation level above the maximum normal operating radiation , j level
- A floor drain sump water level above the maximum normal operating water level
- An area water level above the maximum normal operating water level
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 51 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O OPERATOR ACTIONS If while executing the following steps secondary containment HVAC exhaust radiation level exceeds 15mr/hr Refuel floor or 50mr/hr Reactor Building (secondary containment HUAC isolation setpoint):
- Confirm or manually initiate isolation of secondary containment HVAC, and
- Confirm initiation of or manually initiate SBGT only when the space being evacuated is below 212 F.
If while executing the following steps:
- Secondary containment HUAC isolates, and
- Secondary containment HUAC exhaust radiation level is below 15mr/hr Refuel floor or 50mr/hr Reactor Building (secondary containment HVAC isolation setpoint), s restart secondary containment HVAC. 24 l
Irrespective of the entry condition, execute Steps SC/T,_SC/R, and SC/L concurrently.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 52 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O SC/T Monitor and control secondary containment temperatures.
SC/T-1 Operate available area coolers.
SC/T-2 If secondary containment HVAC exhaust radiation level is below 15mr/hr Refuel floor or 50mr/hr Reactor Building (secondary containment HUAC isolation setpoint), operate available secondary containment HUAC.
SC/T-3 If any area temperature exceeds its maximum normal operating temperature, isolate all systems that are discharging into the area except systems required to shut down the reactor',
assure adequate core cooling, or suppress a working fire.
SC/T-4 If a primary system is discharging into an area, then before any area temperature reaches its maximum safe operating temperature, enter the procedure developed from the.RPU Control Guideline at Step RC-1 and execute it concurrently with SC/T. I SC/T-5 If a primary system is discharging into an area and an area
_ )
temperature exceeds its maximum safe operating temperature in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 53 OF 93
~ DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O SC/R Monitor and control secondary containment radiation levels.
SC/R-1 If any area radiation level exceeds its maximum normal I
operating radiation level, isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire.
SC/R-2 If a primary system is discharging into an area, then before any area radiation level reaches its maximum safe operating i radiation level, enter the procedure developed from the RPU Control Guideline at Step RC-1 and execute it concurrently with SC/R. ,
SC/R-3 If a primary system is discharging into an area and an area j radiation level exceeds its maximum safe _ operating radiation level in more than one area, EMERGENCY RPV DEPRESSURIZATION j IS REQUIRED.
i SC/L Monitor and control secondary containment water levels.
~
SC/L-1 If any floor drain sump or area water level is above its maximum normal operating water level, operate available sump pumps to restore and maintain it below its maximum normal operating water level.
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GEORGIA POWER COMPANY T HATCH NUCLEAR PLANT PAGE 54 OF 93__
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION: y,,
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O .
__,___ \_
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If any floor drain sump or area water level cannot, be
- \
restored and maintained below its maximum normal oper'a'tipg s water level, isolate all systems that are discharging water into the sump or area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire. *%
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SC/L-2 If a primary system is discharging into an area, the nibaf or'e .' ; ,
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any floor drain sump or area water level reaches its maximum safe operating water level, enter procedure developed fr0mc' ~
the RPV Control Guideline at Step RC-1 and execute it concurrently with SC/L.
N SC/L-3 If a primary system is discharging into an area and a' floor drain sump or area water level exceeds its maximum safe, operating water level in more than one area, EMERGENCY RPV -
DEPRESSURIZATION IS REQUIRED.
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GEORGIA POWER COMPANY H,f70H NUCLEAR PLANT PAGE 55 OF 93 DOEUMENT. TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O
., TABLE II
), OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS SECONDARY C0flTAINMENT MAXIMUM NORMAL MAXIMUM SAFE PARAMETER / LOCATION ALARM OPERATING UALUE OPERATING UALUE Differential pressure T on 2Hll-P700-R604 (in. water) (in. water) psig
- ReactorT8uilding/outside air 0 0 +0.25
- Refuel Floor /outside air O O +0.25
\ ' \'
Area temperature from 2Hll-PS14-R614 ( F) ( F) ( F)
- RWCU "A" pump room 158' 2G31-N016A 120 130 215
- RWCU "B" p' ump room 158' 2G31-N0168 120 130 215
- RWCU,Hx room 158' at Hx.2G31-N016C 120 130 215
- - RWC: Nix room 158' disch-H.W.
2G31-N016D 120 130 215
- RWCU' phase sep. room 158' 2G31-N016E 120 130 215
- RWCU holding pump room 185
.i 2G31-N016F 120 130 215
- NE Diagonal 2E11-N009A 175 175
- 214
- SE Diagonal 2E11-N009B 175 175
- 214
- HPCI room, area A 2E41-N024 150 175 214
- HPCI room, area B 2E41-NO30A 150 175 214
- HPCI, room, area C 2E41-NO308 150 175 214
- Torus room, westwall 2E51-N025A 150 175 214
- Torus. room, eastwall 2E51-N025B 150 175 214
- Torus room, northwall 2E51-NO25C 150 175 214
- Torus room, southwall 2E51-N025D 150 175 214
- Main' steam tunnel 2B21-N014 160 200 215
- SE, Reactor 130 elev., area A 2E41-NO46A 150 150
- 214
- SE, Reactor 130 eleu., area B 2E41-NO46B 150 150
- 214 ~
^
- NW Diagonal, area A 2E51-N011 150- 175 310
- NW Diagonal, area B 2E51-N023A 150 175 310
- NW Diagonal, area C 2E51-N023B 150 175 310
- Same as alarm setpoint.
i GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 56 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) s 0
TABLE II (Continued)
OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS SECONDARY CONTAINMENT MAXIMUM NORMAL MAXIMUM SAFE PARAMETER / LOCATION ALARM OPERATING UALUE OPERATING UALUE Steam Leak Detection System Area (*F) ( F) ( F)
Differential Temperatures 2Hll-P614
- RWCU "A" Pump room 2G31-NO22/N023A 50 -
75 1 99
- RWCU "B" Pump room 2G31-NO22/N0238 50 ,
75 99
- RWCU Hx Room 158' ';
at Hxs 2G31-N022/N023C 50 75 '99
- RWCU Hx Room 158' disch. to Hotwell 2G31-N022/N023D 50 75 99
- RWCU phase separator room 158'2G31-NO22/NO23E 50 75 99
- RWCU holding pump room 185' 2G31-N022/N023F 50 75 99
- Torus Room, NW/ West 2E51-N026/N027A 40 50 98
- Torus Room, f' NW/ West 2E51-N026/N027B 40 50 98
- Torus Room, ,
NW/ West 2E51-NO26/N027C 40 50 98
- Torus Room, NW/ West 2E51-N026/NO27D 40 50 102
- Same as alarm setpoint a z
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 57 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 TABLE II (Continued)
OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS SECONDARY CONTAINMENT MAXIMUM NORMAL MAXIMUM SAFE PARAMETER / LOCATION ALARM OPERATING UALUE OPERATING UALUT HUAC exhaust radiation (mr/hr) (mr/hr) (mr/hr) level above
- Reactor Building 50 50 1250
- Refuel Floor 15 50 1250 Area radiation level
- 158' Southeast Area Ch 2 15 50 1250
- 158' Northeast Area Ch 3 15 50 1250
- 158' Northwest Area Ch 4 15 50 1250
- 130' Northeast Work Area Ch 7 15 50 1250
- 130' Southwest Work Arca Ch 8 15 50
- Decant Pump & 1250 Equipment Room Ch 9 15 50
- Souch CRD Hydraulic 1250 Urits Ch 11 15 50 1250
- Spent Fuel Pool Passageway Ch 12 25 50 1250
- 185' Operating Floor Ch 13 15 50
- 185 Sar,1ple Panel Area Ch 3 4 1250 30 50 1250
- 185' RWCU Control Panel Area Ch 16 10 50 1250
- Fuel Pool Denim Panel Area Ch 23 10 50 1250
- CRD Repair Area Ch 15 15 50 1250
- RCIC Equipment Area Ch 17 20 50 1250
- CRD Pump Room SW Ch 18 20 50 1250 ,
- RHR & Core Spray ~
Room Northeast Ch 19 20 50 1250 RHR & Core Spray Room Southeast Ch 20 100 150 1250 i
GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT PAGE 58 0F 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 TABLE II (Continued)
OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS SECONDARY CONTAINMENT MAXIMUM NORMAL MAXIMUM SAFE PARAMETER / LOCATION ALARM OPERATING VALUE OPERATING VALUE Floor drain sump water level (in.) (in.) (in.)
- Sump A (NE Diagonal) T45-N006 38 47 N/A
- Sump B (NW Diagonal) T45-N007 52 52 N/A Aren water level
- CRD Compartment 2T45-N005 5 7 260
- RCIC Compartment 2T45-N004 5 7 22
- RD NE Corner RM 2T45-N003B 5 7 14
- RB SE Corner RM 2T45-N003A 5 7 15
- HPCI Compartment 2T45-N001 5 7 14
- Torus Compartment NW 2T45-N002D 5 7 11
- Torus Compartment NE 2T45-N002B 5 7 11
- Torus Compartment SE 2T45-N002A 5 7 11
- Torus Compartment SW 2T45-N002C 5 7 11 i
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GEORGIA POWER COMPANY '
HATCH NUCLEAR PLANT PAGE 59 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O RADIOACTIVITY RELEASE CONTROL GUIDELINE PURPOSE The purpose of this guideline is to limit radioactivity release into areas outside the primary and secondary containments.
ENTRY CONDITIONS The entry condition for this guideline is:
- Offsite radioactivity release rate above 3 C1/sec (release rate which requires an Alert).
OPERATOR ACTIONS RR-1 Isolate all primary systems that are discharging into-areas outside the primary and secondary containments except' systems required to assure adequate core cooling or shut down the reactor, i
RR-2 If offsite radioactivity release rate approaches or exceeds 91 C1/sec (release rate which requires a General Emergency) and a primary system is discharging into an area outside the primary .
and secondary containments, EMERGENCY RPU DEPRESSURIZATION IS REQUIRED: enter the procedure. developed from the RPU Control Guideline at Step RC-1 and execute it concurrently 'with ~ RR.
GEORGIA. POWER COMPANY HATCH NUCLEAR PLANT PAGE 60 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O '
CONTINGENCY 1 LEVEL RESTORATION If while executing any step in Contingency 1:
- Boron Injection is required, enter the procedure developed from CONTINGENCY 7.
- RPU water level cannot be determined, RPU FLOODING IS REQUIRED:
enter the procedure developed from CONTINGENCY 6.
- RPU Flooding is required, enter procedure developed from CONTINGENCY 6.
Cl-1 Line up for injection and start pumps in 2 or more of the.
Following injection subsystems:
- Condensate
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 61 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 1
-If less than 2 of the injection subsystems can be lined up, commence lining up as many of the following alternate injection subsystems as possible: -
- RHR service water crosstie
- ECCS keep-full systems
- SLC (test tank)
Cl-2 Monitor RPV pressure and water level. Continue in this Contingency at the step indicated as follows:
RPV PRESSURE REGION i
435 psig I 100 psig 2 d
HIGH INTERMEDIATE LOW RPV INCREASING Cl-3 Cl-4 Cl-5 LEVEL DECREASING Cl-6 - I Cl-7 ;
I(RPV pressure at which CS shutoff head is reached) 2(HPCI low pressure isolation setpoint).
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GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT PAGE 62 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O If while executing steps Cl-3, Cl-4, Cl-5, Cl-6, or Cl-7:
- The RPV water level trend reverses or RPU pressure changes region, return to Step Cl-2.
- RPV water level drops below -146 inches (ADS initiation setpoint), prevent automatic initiation of ADS.
Cl-3 RPV WATER LEVEL INCREASING, RPU PRESSURE HIGH Enter the procedure developed from the RPV Control Guideline at Step RC/L.
Cl-4 RPV WATER LEVEL INCREASING, RPV PRESSURE INTERMEDIATE If HPCI and RCIC are not available and RPU pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter the procedure developed from the RPV Control Guideline at Step RC/L.
If HPCI and RCIC are not available and RPU pressure is not increasing, enter the procedure developed from the RPV Control ~
Guideline at Step RC/L.
f Otherwise, when RPV water level reaches +12.5 inches (Iow level scram setpoint), enter the procedure developed from the RPV Control Guideline at Step RC/L.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 63 OF 93.
DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O Cl-5 RPV WATER LEVEL INCREASING, RPV PRESSURE LOW If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter the procedure developed from the RPV Control Guideline at Step RC/L.
Otherwise, enter the procedure developed from the RPU Control Guideline at Step RC/L.
Cl-6 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH OR INTERMEDIATE If HPCI or RCIC is not operating, restart whichever is not operating.
If no injection subsystem is lined up for injection with at least one pump running, start pumps in alternate injection subsystems which are lined up for injection.
When RPV water level drops to -164.5 inches (top-of active fuel):
- If no system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, STEAM COOLING IS REQUIRED. When any system, injection subsystem or alternate injection subsystem is lined up with at least one "
pump running, return to Step Cl-2.
i
- Otherwise, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. -When-RPV water level is increasing or RPU pressure. drops below 100 psig (HPCI low pressure isolation setpoint),. return to Step :
Cl-2.
GEORGIA POWER COMPANY i HATCH NUCLEAR PLANT t DOCUMENT TITLE: PAGE 64 OF 93.
EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O Cl-7 RPV WATER LEVEL DECREASING, RPV PRESSURE LOW If no CS subsystem is operating, start pumps in alternate injection subsystems which are lined up for infection .
If RPV pressure in increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED, When RPV water level drops to -164.5 inches (top of active fuel),
enter the procedure developed from CONTINGENCY 4.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 65 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O CONTINGENCY 2 EMERGENCY RPU DEPRESSURIZATION C2-1 When either: 13, 14
- Boron Injection is required and all injection into the RPU except from boron injection systems and CRD has been terminated and prevented, or 1
- Boron Injection is not required, C2-1.1 If suppression pool water level is above 58 in. (elevation of top of SRU discharge device):
- Open all ADS valves.
- If any ADS Valve cannot be opened, open other SRVs until 7 (number of SRVs dedicated to ADS) valves are open.
C2-1.2 If less than 3 (Minimum Number of SRVs Required for 22 Emergency Depressurization) SRVs are open and
~
RPV pressure is at least 50 psig (minimum SRV re-opening ,
{
pressure) above suppression chamber pressure, rapidly depressurize the RPU using one or more of the following systems (use in order which will minimize radioactive ,
release to the environment): l
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I GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 66 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O
- RHR (steam condensing mode)
- Reactor Feed Pump Turbines
- Main steam line drains.
- HPCI steam line
- RCIC steam line
- Head vent If RPV Flooding is required, enter the procedure developed from CONTINGENCY 6.
C2-2 Enter the procedure developed from the RPU Control Guideline at' Step RC/P-4.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 67 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURESREVISION:
PLANT SPECIFIC TECHNICAL GilIDELINE (UNIT 2) O CONTINGENCY 3 STEAM COOLING If while executing any step in Contingency 3 Emergency RPV Depressurization is required or any system, injection subsystem, or alternate injection subsystem is lined up for injection with at least one pump running, enter the procedure developed from CONTINGENCY 2.
C3-1 When RPV water level drops to -265.5 in. (Minimum Zero-Inj ection RPV Water Level) or if RPU water level cannot be determined, '
open one SRV.
I When RPV pressure drops below 700 psig (Minimum Single SRU Steam i Cooling Pressure), enter the procedure developed from CONTINGENCY 2.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT DOCUMENT TITLE: PAGE 68 OF 93 EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE(UNIT 2) O CONTINGENCY 4 CORE COOLING WITHOUT LEVEL RESTORATION C4-1 Open all ADS values.
13 If any ADS valve cannot be opened, open other SRUs until 7 (number of SRVs dedicated to ADS) valves are open.
C4-2 Operate CS subsystems with suction from the suppression pool ..
When at least one core spray subsystem is operating with suction from the suppression pool and RPV pressure is below 113 psig (RPV pressure for rated CS flow) terminate injection into the RPV from sources external to the primary containment.
C4-3 :
When RPU water level is restored to -164.5 inches (top of active i
fuel),
enter the procedure developed from the RPV Control Guideline at Step RC/L.
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GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT PAGE 69 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REUISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O CONTINGENCY 5 ALTERNATE SHUTDOWN COOLING C5-1 Initiate suppression pool cooling.
C5-2 Close the RPU head vents, MSIVs, main steam line drain valves, and HPCI and RCIC isolation valves, C5-3 Place the control switch for one (Minimum Number of SRUs Required for Alternate Shutdown Cooling) SRV in the OPEN position.
C5-4 Slowly raise RPV water level to establish a flow path through the open SRU back to the suppression pool.
C5-5 Start one CS or LPCI pump with suction from the suppression pool, C5-6 Slowly increase CS or LPCI injection into the RPV to the maximum.
~
r C5-6,1 If RPV pressure does not stabilize at least 94.6 psig ;
I (Minimum Alternate Shutdown Cooling RPV Pressure) above suppression chamber pressure, start another CS or LPCI pump.
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GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT PAGE 70 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O C5-6.2 If RPU pressure does not stabilize below 193 psig (Maximum Alternate Shutdown Cooling RPV Pressure), open another SRU.
C5-6.3 If the cooldown rate exceeds 100 F/hr (maximum RPU cooldown rate LCO), reduce CS or LPCI injection into the RPU until the cooldown rate decreases below 100*F/hr (maximum R'PU cooldown rate LCO) or RPU pressure decreases to within 50 psig (Minimum SRU Re-opening Pressure ) of suppression chamber pressure, whichever occurs first.
C5-7 Control suppression pool temperature to maintain RPV water temperature above 70af (head tensioning limit),
C5-8 Proceed to cold shutdown in accordance with the procedure for cooldown to cold shutdown conditions, or as directed by Plant Management.
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1 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT P AGE 71 OF 91 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O CONTINGENCY 6 RPU FLOODING C6-1 If at least 3 (Minimum Number of SRVs Required for Emergency -
Depressurization) SRUs can be opened, close the MSIVs, main steam line drain values, HPCI, RCIC and RHR steam condensing isolation valves.
C6-2 If two or more control rods are at other than position 00 (maximum subcritical banked withdrawal position):
C6-2.1 Terminate and prevent all injection into the RPU except from boron injection systems and CRD until RPU pressure is below the Minimum Alternate RPU Flooding Pressure.
Number of Open SRVs Minimum Alternate RPU Flooding Pressure (psig) 1 7 or more 134 6 159 ~
5 194 ,
4 246 3 333 2 506 y 1 1027 p
1 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 72 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O If less than 1 (minimum number of SRVs for which the Minimum Alternate RPU Flooding Pressure is below the lowest SRU lifting pressure) SRV can be opened, continue in this procedure.
If while executing step C6-2.2, RPV water level can be determined and RPU Flooding is not required, enter the procedure developed from CONTINGENCY 7 and the procedure developed from the RPU Control Guideline at Step RC/P-4 and execute them concurrently.
C6-2,2 Commence and slowly increase injection into the 25 RPU with the following systems until at least 1 (minimum number of SRVs for which the Minimum Alternate RPU Flooding Pressure is below the lowest SRV lifting <
pressure) SRV is open and RPU pressure is above the Minimum Alternate RPU Flooding Pressure:
- Condensate pumps
- CRD '
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- LPCI k
GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT PAGE 73 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O If at least 1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRU lifting pressure) SRU is not open or RPU pressure cannot be increased to above the Minimum Alternate RPU Flooding Pressure, commence and slowly increase injection into the RPV with the following systems until at least 1 (minimum number of SRVs for which the Minimum Alternate RPU Flooding Pressure is below the lowest SRV lifting pressure) SRU is open and RPV pressure is above the Minimum Alternate RPU Flooding Pressure:
- CS
- RHR service water crosstie
- ECCS keep-full systems C6-2.3 Maintain at least 1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure) SRU open and RPV pressure above the Minimum Alternate RPV Flooding Pressure by throttling injection.
C6-2.4 When: '
- All control rods, except one, are inserted to position 00 (maximum subcritical banked withdrawal position), or
- The reactor is shutdown and no boron has been injected I
into the RPV, continue in this contingency.
GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT PAGE 74 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES .3EVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O C6-3 If RPU water level cannot be determined:
C6-3.1 Commence and increase injection into the RPV with the following systems until at least 3 (Minimum Number of SRVs Required for Emergency Depressurization) SRVs are open and
- RPV pressure is not decreasing and is at least 68 psig l
(Minimum RPV Flooding Pressure) above suppression chamber pressure.
- CS
- LPCI
- Condensate pumps 1 - CRD I
- RHR service water crosstie j - ECCS keep-full systems i
- SLC (test tank) l
)
j C6-3.2 Maintain at least 3 (Minimum Number of SRVs Required for Emergency Depressurization) SRVs open and RPV pressure at least 68 psig (Minimum RPV Flooding Pressure) above suppression chamber pressure by throttling injection. '
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 75 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O C6-4 If RPV water level can be determined, commence and increase injection into the RPV with the following systems until RPV water level is increasing:
- CS
- LPCI
- Condensate pumps
- CRD
- RHR service water crosstie
- ECCS keep-full systems
- SLC (test tank)
C6-5 If RPU water level cannot be determined:
C6-5.1 Fill all RPV water level instrumentation reference columns.
C6-5.2 Continue injecting water into the RPU until the temperature near the cold reference leg instrument vertical runs is below 212*F and RPV water level instrumentation is available.
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If while executing steps C6-5.3 or C6-5.4, RPV water level can be determined, continue at step C6-6.
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GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT PAGE 76 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O C6-5.3 If it can be determined that the RPV is filled or if RPV pressure is at least 68 psig (Minimum RPV Flooding Pressure) ,
above suppression chamber pressure, terminate all injection -
into the RPV and reduce RPV water level.
C6-5.4 If RPU water level indication is not restored within the Maximum Core Uncovery Time Limit (see Attachment 10) after commencing termination of injection into the RPV, return to Step C6-3.
C6-6 When suppression chamber pressure can be maintained below the Primary Containment Design Pressure (see Attachment 7), enter the procedure developed from the RPV Control Guideline at Steps RC/L and RC/P-4 and execute these steps concurrently.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 77 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O CONTINGENCY 7 LEVEL / POWER CONTROL If while executing any step in Contingency 7 RPV Flooding is required or RPV water level cannot be determined, control injection into the RPV to maintain reactor power above 8% (Reactor Flow Stagnation Powe.r) _but as low as practicable. However, if reactor power cannot be determined or maintained above 8% (Reactor Flow Stagnation Power),
RPV FLOODING IS REQUIRED; enter the procedure developed from CONTINGENCY 6.
C7-1 If:
- Reactor power is above 3% (APRM downscale trip) or cannot be determined, and
- Suppression pool temperature is above 110'F (Boron Injection Initiation Temperature), and
- Either an SRV is open or opens or drywell pressure is above 2.0 ,
psig (high drywell pressure scram setpoint),
lower RPV water level by terminating and preventing 26 4
all injection into the RPV except from boron injection ,
systems'and CRD until either:
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GEORGIA POWER COMPANY '
HATCH NUCLEAR PLANT PAGE 78 OF 93 DOCUMENT TITLE: EMERGENCY OPERATING PROCEDURES REVISION:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0
- Reactor power drops below 3% (APRM downscale trip), or
- RPU water level reaches -164.5 inches (top of active fuel), or
- All SRVs remain closed and drywell pressure remains below 2.0 psig (high drywell pressure scram setpoint).
If while executing steps C7-2 or C7-3 Emergency RPV Depressurization is required, continue at step C7-2.1.
If while executing steps C7-2 or C7-3:
- Reactor power is above 3% (APRM downscale trip) or cannot be determined, and
- RPV water level is above -164.5 inches (top of active fuel),
and
- Suppression pool temperature is above 110'F (Boron Inj ection Initiation Temperature), and 1
- Either an SRV is open or opens or drywell pressure is above l
2.0 psig (high drywell pressure scram setpoint),
return to Step C7-1.
q 0
-1 e
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT DOCUMENT TITLE: PAGE 79 OF 93 PLANT SPECIFIC TECHNICAL REVISION:
(UNIT GUIDELINEEMERGENCY
- 2) O OPERATIN C7-2 Maintain RPV water level either: 9, 10, 11, 25
- If RPV water level was deliberately lowered in Step C7-1, at the level to which it was lowered, or
- If RPU water level was not deliberately lowered in Step C7-1 i'
between +12.5 inches (Iow level scram setpoint) and +58 inches (high level trip setpoint),
with the following systems:
- Condensate System 650-0 psig (RPV pressure range for system operation)
- Condensate /feedwater system 1717-0 psig (RPU pressure range for system operation)
- CRD system 1507-0 psig (RPV pressure range for system operation)
- RCIC system 1120-50 psig (RPV pressure range, 12 for system operation) l
- HPCI system 1120-150 psig (RPV pressure range for system operation)
- LPCI system 225-0 psig (RPV pressure range for system ~
operation)
~
I If RPV water level cannot be so maintained, maintain RPV water level above -164.5 inches (top of active fuel) . ..
If RPU of active water fuel), level cannot be maintained above
-164 5 inche s (top ,;
EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
GEOHGIA POWER COMPANY HATCH NUCLEAR PLANT DOCUMENT TITLE: PAGE 80 OF 93 EMERGENCY OPERATING PROCEDURES REVISION:
_ PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2)O C7-2.1 Terminate and prevent all injection into the RPV except from boron injection systems and CR0 until RPV pressure is below the Minimum Alternate RPV Flooding Pressure.
Number of Open SRVs Minimun, Alternate RPV Flooding Pressure (psig) 7 or more 134 6
159 5
194 4
246 3
333 2 .
506 1
1027 If less than 1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV
. ~
lifting pressure) SRV can be opened, continue in this Contingency, ,
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT ~
DOCUMENT TITLE: PAGE 81 OF 93 PLANT SPECIFIC TECHNICAL REVISION:
GUIDELINEEMERGENCY OPER (UNIT 2) O
~
C7-2.2 Commence and slowly increase injection into the 25 RPV with the following systems to restore and maintain RPU water level above -164.5 inches (top of active fuel):
- Condensate /feedwater system
- CRD
- RCIC
- HPCI
- LPCI If RPV water level cannot be restored and maintained abo
-164.5 inches (top of active fuel), commence and slowly increase injection into the RPU with the following systems to restore and maintain RPU water level above -164 5 inc .
(top of active fuel):
- CS 1 i
- RHR service water crosstie
- ECCS keep-full systems
~
l
- t If while executing step C7-3 . reactor power commences I
and continues to increase, return to Step C7-1.
.i al j
I GEORGIA POWER COMPANY
_ HATCH NUCLEAR PLANT DOCllMENT TITLE:
PAGE 82 OF 93 PLANT SPECIFIC TECHNICAL GUIDELINE REVISION:
0 (UNIT _
C7-3 When 262.1 pounds (Hot Shutdown Boron Weight)
(occurs at SLC tank indicatic.* of 45%)
of boron have been injected or all control rods, except one, are inserted to position 00 (maximum subcritical banked withdrawal position) ,l restore and maintain RPV water level between +12.5 inches
)
and +58 inches (Iow level scram setpoint) J (high level trip setpoint).
If RPV water level cannot be restored n a nedand abovemai ti
+12.5 inches (Iow level scram setpoint)
, maintain RPV water level above -164.5 inches (top of active fuel) .
If RPV water level cannot be maintained of active fuel), -164.5above inches (top return to EMERGENCY Step C7-2.1. RPU DEPRESSURIZATION(f I ,
,i If Alternate Shutdown Cooling is required , enter
. t the procedure developed from CONTINGENCY 5 .
i
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C7 4 ?
Proceed to cold shutdown in accordance withforth e procedure cooldown to cold shutdown conditions, or as directed Management. y Plant b ,
il
A I I ACt1 MEN I i '
PAGE 83 ' 0F 93 GEOHGIA POWER CUMPANY ATTACHMtNT HATCH NUCLEAR PLANT PAGE 1 UF 1 DUCUMENT TITLE: EMF.HGENCY UPEHATING PHUCLUUHEd _ HEVidluN:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O HiIACHHtiNT TITLE:
NPSH REQUIREMENTS f
t 4 0 I '
230 - - t I ONSET OF BOILING SU RES ON IUNSTABLE SUPPRESSION 220 Cil DEI
~
p W #7-p d CHAMBER CONDITIONS
" g ,
110 - - - - - - - - -- "h- - gn p l
200- -- - -- -- -
-- f, 99G
-l p ---.. - - .: * ' '
'9.2' RHR 0 7700 GPM a:
i , ---
- . ,'. '_.'92.1'
!.8' COR E SPR AY O 5600 GPM
\
190 -
- - - - ---(99G --
l -: ---- . g,
- -_ f.
' ' .g CORE SPRAY @ 5900 GPM
~~~~~~
i $ 180- ~
il5.4 RCIC
/-- -- l-- fg?Oo E ..
"5 ' MINIMUM CREtllBLE l
17]- -- - - - - - -.
,SUPP lESSidN POC L LEVEL.
g
,8
.: s '
140\ - -S- -----t 5' ' ' ' 10' ' ' ' ' If' ' ' '
,_20',_
a.
, -- , l 'l23.1' RHR 910600 GPM
$ 150- --
S. ' " . - IC
- 1,5' 25 20' .
. . . . i e ,
i e e i ' ' ' '
- i i 26 !
g 140- ! .7'HPCI i
& I g 130- -
I i (
120 - - - -
l
{
110 - l t g
100- __ ._._ - _ . _
1 I
90 I
)
' FIGURE 2 HATCH UNIT 2. MINIMUM SUPPRESSION POOL LEVEL WHICH MEETS REQUIRED ~
NPSH FOR ECC'S PUMPS TAKING SUCTION FROM TORUS. ,,
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t 5
0 l
AIIACHMtNI 2 ~'
PAGE 84. OF 9'3 UEUHGIA PUWEH COMPANY AlTACHMENT HATCH NUCLEAR PLANT PAGE 10F 1 UUCUMENT IIILL: EMtLGENCY UPLHATING PHUCEUUHth HtVid1UN:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 A I I ACfiMENT TITLE: -
HEAT CAPACITY TEMPERATURE LIMIT 200 ,
190 N '
180 w
C 170 N
E N N 160- '
y N a 150 E
h 140 t 130 3
110 0 100 .200 300 400 500 603 700 800 900 1000 1100 1200 1300 RPV PRESSURE (psig)
, j FIGURE C3-4 HEAT CAPACfTV TEMPERATURE LIMIT s
ATTACHMENT 3 -
PAGE 85 OF 93
. GEORGIA POWER COMPANY -
ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 1 DOCUMENI TITLE: EMERGENCY OPERATING PROCEDURES REVISION: l PLANT SPECIFIC TECHNICAL GUT.DELINE (UNIT 2) O l ATTACHMENT TITLE:
SUPPRESSION POOL LOAD LIMIT l
f i
( TO BE PROVIDED LATER )
i 4 ,
.. J h
a 1
AIIACHMcNT 4 ,
PAGE 86 0F 93 GEUHGIA PUWER CUMPANY ATTACHMENI HATCH NUCLEAR PLANT PAGE 1 UF 1 UUCUMENT TITLE: EMEHGENCY UPEHATING PHUCEUUHEb HtViblUN:
PLANT SPECIFIC TECHNICAL GUIUELINE (UNIT 2) O AIIACHMEMI TITLE: ~
RE ACTUR PHESSURE VESSEL SATURATION LIMIT 550 C -
- /
E
/
e
.2 500 #
/ '
f '
9 g 450 / ,
W 2 da f
/
S a
y '
w 350 -
g b
e O
{300 -
e Y ,
- z 250 -
[
1 0 100 200 300 400 500 600 700 800 900 1000 1100 RPV PRESSURE (psig)
FIGURE C7-1 '
RPV SATURATION TEMPERATURE i
'l i
4
. 4
ATTAtiiRENT 5 -
PAGE 87 UF 93 UEUHGIA POWEH COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 UF 2 _
UUCUMLNI TITLt: EMtHGENCY UPLHMIING PHUCLUUHtb HLVIbluN:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O MTTRUT1RENI firEE:
ORYWELL SPHAY INITIATION PRESSURE LIMIT 400 380 -
360 !
5 340 .
320 g 300-l
$ 280 3
h260
!H 240 \ l g 120- \-
X 200 180 N '
ia Nx . !
140 120 100
, ~
g t' O 5 10 15 20 25 30 35 40 45 50 55 60 DRYWELL PRESSURE (psig) inn a 1
FIGURE C9-1 ORYWELL SPRAY INITIAt10N PRES 5URE LIMIT (C9.1, WETWELL-TO.DRYWELL AP LIMlf)
I i.
14 i
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AITHCHMtNT b PAGE 88 0F h3 GEUHGIA POWEH COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 2 0F 2 DOCUMENT TITLE: EMERGENCY UPEHA11NU PHUCEDUHES HtVISIUN:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 Ai i ACHMERT TTTLE:
ORYWELL SPRAY INITIATION PRESSURE LIMIT 300 340 320 300
, o g 280 ;
c E 260
$ / '
$ 240 [
H 220 #
/
E f 200 ,
5 y 180 ,
/
R E 160 ,
/
s.
" 140
/ '
i 120 /
100 ,
80 / :
60
, ~.
l ' ';
O 5 10 15 20 25 30 35 40 45 50 55 60 SUPPRESSION CHAMBER PRESSURE (psig)
I ssens
. FIGURE C9-2 DRYWELL SPRAY INITIATION PRESSURE LIMIT (C9.II.A. CONTAINMENT-TO-RB AP LIMIT FOR RELATED SPRAY)
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AIiACIIMt.N1 6 GEURGIA POWEH CUMPANY P AGE 89 0F 93-ATTACHMENT HATCH NUCLEAR PLANT PAGE 10F 1 UUCUMENT TITLE: EEhMLENCY UPEHAllNG PHUCEUUML5 MtV1510N:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) O HiIACHMENT TITLE:
PRESSURE SUPPREdSION PRESSURE 70 60 3
E s
g 50 /
E
/
l~ "
lWhVMAVfMA E
h
( ~ PRESSURE SUPPRESSION
.. PR ESSUR E.
30 0
0 10 20 30 40 50 60 .-
PRIMARY CONTAINMENT WATER LE'/EL (ft) .
~
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FIGURE C12-3 PRESSURE SUPPRESSION PRESSURE
~
's
~" :
41 y
- 9
A I I ACHMtiNT ~7 -
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PAGE 90 0F93 GEUNGIA POWEH COMPANY HTIACHMbHT HATCH NUCLEAR PLANT PAGE 1 UF 1 DOCUMENT TITLE: EMEHGENCY UPEHATING PHUCEDUHE5 HEViblON:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2) 0 ATTACTiMEN i TITLE: ~~
PRIMARY CONTAINMENT DESIGN PRESSURE 130
'i 120 110 100 I 90 E
80 E
$ 70 m
5 xa u
5 g* N N
40 M
30 r . ..
20 10 O
0 10 20 30 40 60 60 70 00 90 100 'f PRIMARY CONTAINMENT WATER LEVEL (ft) ann.s FIGURE C13 2 PRIMARY CONTAINMENT DESIGN PRESSURE 9
AIIACHMtNI 6 PAGE 91 0F 93 GEORGIA POWER COMPANY ATTACHMtNT HATCH NUCLEAR PLANT PAGE 1 0F 1 DOCUMENT TITLE: EMERGENCY UPbHA11NG PHUCLUUHbb HEVIblUN:
PLANT SPECIFIC TECHNICAL GUIUELINE (UNIT 2) 0 AiintHMENI firth:
PRIMARY CONTAINMENT PRESSURE LIMIT 130 120 110 100 I 90 E
g 80 E
e 70 I
zo 60 2 %
N x gM t
g 40 30 l
20 10 0 10 20 30 40 50 60 70 80 90 100 ' '
PRIMARY CONTAINMENT WATER LEVEL {tt) 128 M-3 FIGURE C14-1
-1 PRIMARY C0'iTAINMENT PRESSt%E LIMIT '
AiIACHMENI 9 ~
GEURGIA PUWER COMPANY PAGE 92 0F 93 HATCH NUCLEAR PLANT ATTHCHMtNT PAGE 1 0F 1 DUCUMENT TITLE: EMLHGENCY UPERATING PHUCLOUktb HtVI510N:
PLANT SPECIFIC TECHNICAL GUIDELINE (UNIT 2)
RIIACHf,ENT TITU: 0
~~~
HEAT CAPACITY LEVEL LIMIT 240 230-220-210-200 135 PS in 0 190-E 4#
g 170-
[ /
160- -8 8 /
e iso 2 ,
// \
\ LEVEL OF AT,, = 0 140- -- '
, 130- -
t 120-
\ LEVEL ATAT,c= ALL VALUES FO1 WHICH 110 LEVEL IS A MINIWUM 100-90 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22, SUPPRESSION POOL LEVEL (ft) ' 3 FIGURE 4 HATCH UNIT 2 '
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AllACHMtNI lo PAGE 93 UF 9a UEUHGIA POWEH COMPANY ~
HATCH NUCLEAR PLANT ATTACHMtNT PAGE 1 0F 1 i DUCUMENT TITLE: EMERGENCY UPEHATING PRUCEUUKEb HEVib10N:
PLANT SPECIFIC TECHNICAL ATTACHREMI GUIDELINE (UNIT 2) O siitt:
~
~
l MAXIMUM COHE UNCOVERY TIME LIMIT 1
I l
60 f
50 1 t-E )
j 40 /
a N
so 30 5
E 8
3 20 .
h a .
4 2
10 .
O I * * ' '
10 ** u u n 100 au see see no 1000 sees use "" 10,000 T!ME AFTER REACTOR SHUTDOWN (min) ,,,3.,
~
FIGURE C23-1 MAXIMUM CORE UNC0VERY TIME LIMIT
UEURCIA-' POWER CURPANY- ._
i / HATCH NUCLEAR PLANT _
PAGE 1 OF'- 70 UUCUREHT TITte: Endn6ENcy UFEnATinu aEvidiuN: . -- i-PROCEDURES PLANT-SPECI _FIC- WHI.TER'S
- - - ._- - - GUIuE.-- -
O i
i HATCH NUCLEAH PLANT EMERGENCY OPERATING PROCEDURES PLANT-SPECIFIC WHITER'S GUIDE
'1$
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.,kUHG14 PUQEH COMPANY U
HATCH NUCLLAH PLANT PAGE 2 UF'70 UUCUMENI TITEE: EMERGENLY uFEHA11NG HEV1510N:
PROCEUUREb PLANT-SPECIFIC WHITER'S GUIUE O TABLE OF CONTENTS
_SE C T ION PAGE 1.0 OBJECTIVE .................................................... 5 1.1 $C0PE...................................................... 5 1.2 RELATIONSHIP OF EUPs TO OTHEN PLANT PROCEDURES............. 6 1.3 WHAT CON 5TITUTES AN EUP..................................... 6 1.4 THE INTRODUCTION TO THE FLOW CHAKTS PHUCEOURE (COVEH PH0CEUUKE)...................................... 7 1.5 THE FLOW CHARTS............................................ 7 1.6 THE END PATH MANUAL 5........................................ 8 2.0 APPLICABILITY................................................. 8 3.0 HEFEHENCES.................................................... 8 3.1 DEVELUPMENTAL HEFERENCES.................................... 8 3.2 IMPLEMENTING REFERENCEb..................................... 9 4.0 HESPONSIBILITIES.............................................. 9 5.0 REQUIHEMENTb................................................. 10 5.1 PERSONNEL REQUIREMENTS..................................... 10 5 . 2 M A T E R I A L A N D E Q U I PN E N T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 5.3 SPECIAL REQUIREMENTS....................................... 10 ,
1 i
l E UNGIA PUE RT UMPANY HATCH NUCLEAR PLANT PAGE 3 0F-70 00CUMENT TITLE: LMtHGtNLY UPLHAIANL HtVlbluN:
PROCEDURES PLANT-SPECIFIC WHITEH'5 GUIUE 0, TABLE UF CONTENTS SE C TION PAGE 6.0 PHECAUTIONS/LIMITATIUNS...................................... 11 6.1 PHECAUTI0NS................................................ 11 6.2 LIMITATIONS................................................ 11 7.0 PREHEQUISITES................................................ 11 8.0 PR0CEUURE......................................... ........ 12 8.1 O R G AN I Z A T ION U F A N E 0P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 8.2 OHGANIZATION OF FLOW CHARTS................................ 15 8.3 END PATH MANUAL PHOCEUURE PREPARATION...................... 2) 8.4 USE OF E0PS................................................ 56 8.5 USE OF OPEHATOH A105....................................... 57-8.6 EXCEPTIONS................................................. 57
~
.GEUHGIA PU3EH LUMPEEV ~
HATCH NUCLEAR PLANT PAGE 4 0F'70 UUCUREMT TITLE: EstnGENCV~UPtHA11Nu REVIb10N:
PROCEOURES PL ANT-SPECIFIC WHITER 'S GUIDE O j _
TABLE UF CUNTENIS i
ATTACHMENTS PAGE I RELATIONSHIP UF EOPS TO OTHEH PLANT PRUCEDURES...... 58 2 ENTRY CONDITIONS ANU INTEHRELATIUNbHIP UF E0P FLOW CHARTS AND END P ATH M ANUALS. . . . . . . . . . . . . . . . 59 3 IITLE PAGE FORMAT FUM E0P'S......................... 60 4 DESIGNATION AND NUMBERING UF FLOW CHARTS............ 62-5 FLUW CHANT LUGIC bYMB0LS............................ 63 2 6 EXAMPLE DECISIUN THEE UTILIZING S T ANU AHO LOG I C S Y MUUL S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4 7 EXANPLE UUAL COLUMN PAGE F0kMAT..................... 65 8 SAMPLE ACTION VEHb lib 1............................. 66 P
. ee l.
EEUNG1A PocER CURPERV HATCH NUCLEAH PLANT PAGE 5 0F '70 UUUUMLNT Ti1LE: EMEHGENCY UPENATING HEVid1UN:
PROCEDURES PLANT-SPECIFIC WHITEH'd GUIOE O 1.0 OBJECTIVE lhis Procedure outlines the content ana format necessary to implement the requirements set fortn in NUREG 0899, Guiaelines for the Preparation of Emergency Operating Procedures, and result in
~
stand-alone, user-orientea procedures. Tne purpose of this Proceaure is to provice administrative ana technical guidance on the preparation of Emergency Operating Proceaures, and to serve as a Writer's Guice.
1.1 SCOPE i by broad definition, Emergency Operating Proceaures (EOPs) are i those procedures that airect actions necessary to mitigate the 1
consequences of transients ano accidents that have caused plant parameters to exceea reactor protection system set points, engineereo safety feature set points, or other established limits. As specifically applied to Plant hatch procedures, Abnormal Operating Procecures contain pre-scram actions and Emergency Operating Proceaures contain post-scram actions. This Proceaure pertains only to the Emergency Uperating Procedures, with ADnormal Operating Procedures coverea Oy 10AC-MGkO3-0, Preparation ano Control of Procedures. ,,
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I GEUHGIA POWEH COMPANY l HATCH NUCLEAR PLANT PAGE 6 OP 70 ~
UUCUMENT T1TLE: EMEHbbNCY UPtHATING HbVib10N:
PRUCEDURES PLANT-5PECIFIC WRITEH'S GUIuE U l.2 RELATIONSHIP OF E0PS TO OTHEH PLANT PROCEDUHES The information contained in the EUPs should be compatible with tne information contained in other plant procedures that support the EUPs. Folmat for EUPs differs slightly from the format specified for other procedures as outlineo in 10AC-MGR03-0. The format of the E0Ps, with Flow Charts for symptoms ano immediate operator actions, and Eno Patn Manuals for subsequent operator actions, makes the EUPs uniquely identifiaole.
Attachment 1 ano Attachment 2 depict the overall relationship of the EUPs to other plant procedures. Ho w e ve r , all instances are not covereo by the attachments since the intent is to show that procedural riow is accomplisheo tnroughout tne proceoure structure to ensure safety function knowleoge ano ultimately plant safety and recovery.
1.3 WHAT CONSTITUTES AN EUP 1.3.1 An EUP shall consist of a cover proceoure, five symptom-orienteo procedures which are to De in Flow Chart format, and End Path Manuals which are to oe in the written or prose format.
1.3.2 There is nothing else that constitutes an EOP.
~
, , , e- .e - , - - - - - - , -..
..n4
GEOHG1A POWEfi CUT ER
~
HATCH NUCLEAH PLANT PAGE 7 UF -70 UUCUMENT IITLL: EMERGE LY UELMATING HEV151UN:
PRUCEUUHES PLANT-SPECIFIC WHITER'S GUIUE O 1.4 THE INTRUUUCTION TU FLOW CHART 5 PMUCEUURE (COVER PRUCEDURE)
The cover proceaure provioes tne operator with the general cautions and ties the cautions to the EUP Flow Cnarts ano End Path Manual.
The cover proceaure will contain the oojective ana entry conditions for the Flow Cha rt s . The cover proceoure's proceaure section will contain an introduction to the Flow Cnart methodology, an explanation of Flow Cha rt ties to the End Patn Manual, ano an overall methoa to use the Flow Cnarts witn the Eno Patn Manual.
1.5 THE FLOW CHANTS Tne Flow Charts provice the operator with a systematic and explicit means for cetermining the safety status of the plant for emergency situations triggered by any automatic or required manual scram regardless of tne combination of initiating events. The Flow charts contain the immediate operator actions to effectively couna multiple-event sequences and bring the plant to a known stacle state. Restoration of reactor and containment parameters anu systems recovery can be accomplisheo via the End Path Manuals. The una Path Manuals, entereo from the Flow Charts, proviae the guioance to complete the safe recovery of the plant and provice conditions from wnich repairs and return to power operation can be accomplisneo.
Regardless of tne event-specific initiating sequences, the symptom-based tiow charts have built into them numerous " verification of action" steps to assist the operator in diagnosis of the initiating events.
.= .. .. . .
1 UEURGIA~PUOtH CUMPANY HATCH NUCLEAR PLANT ~
PAGE-8 UF-70 OucuMENT TITLE: EMEHGENCY UPthaTINu HEVIS1UN:
PROCEDURES PLANT-SPECIFIC WHITER'S GUIUE O 1.6 THE END PATH MANUALS The End Path Manuals are entered from the Flow Charts when the 1
operator has completea a particular patn on the Flow Chart he is utilizing. Each Flow Chart will inaicate which Ena Path Manual and contained proceaure are to be enterea. The End Patn proceaures are made up of information aerivea fIom the previous event specific procedures (e.g. , HNP 1900 Series), contingency action, emergency procedure guiaelines, system recovery proceaures, primary and secondary containment control proceaures, reactivity control guidelines, Heactor Pressure Vessel (RPV) control guidelines, ana
- radioactivity release control guicelines.
4 2.0 APPLICABILITY
, This Proceaure (writer's Guide) applies to the writing of all Plant Hatch Emergency Operating Proceaures, consisting of Flow Charts and End Path Manuals.
3.0 REFERENCES
3.1 DEVELOPMENTAL HEFEHENCES 3.1.1 10CFH50 Appena1x B, Criterion-V, Instructions,_ Procedures and Drawings 3.1.2 luCFHSU.34, Contents of Applications: Technical Information 3.1.3 ANbl-N18.7-1976, Administrative Controls ana Quality Assurance
, for the Operational Phase of Nuclear Power Plants _
3.1.4 Hegulato ry Gulae 1.33, Hevision 2, Appencix A, Quality Assurance Program Hequirements (Operation)
GEORGIA POWEH COMFANY HATCH NUCLEAR PLANT PAGE 9 OF-70 UUCuMENT TITLE: EMEMGtNGY UPLHATING MtViblUN:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 3.2 IMPLEMENTING REFERENCES 3.2.1 INPO 82-017 Emergency Operating Procedures Writing Guideline, July 1982 3.2.2 BWH Emergency Proceoure Guicelines, 6WH1-6, kevision 3, j
Decemoer 8, 1962 3.2.3 NHC Safety Evaluation Report cated November 23, 1983.
3.2.4 NUREG-0899, August 1982, Guidelines for the Preparation of Emergency Operating Proceoures 3.2. 5 10 AC-MGH03 -0, Revision 0, Preparation ano Control of Proceoures 4.0 RESPONSIBILITIES The review ano approval requirements for Emergency Operating Procedures are to be in accordance witn the requirements of Hatch Nuclear Plant's Aaministrative Control Procedure, Preparation ano Control of Procedures (10AC-MGh03-0). The Manager of Operations has primary responsioliity for the procedures generateo as Emergency OpeIating Proceoures.
09 b
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GE0HGIA PODEN LUMPANY HATCH NUCLEAR PLANT PAGE 10 0F 7U DOCURERI TITLE: EMEHGENCY UPEHATING HEvi51UN:
PROCEDURES PLANT-SPECIFIC WHITER'S Gul0E O S.0 REQUIREMENTS 5.1 PERSONNEL REQUIREMENTS Personnel developing or performing reviews of the EUP's sna11 be knowledgeable in the disciplines and bases of the Emergency Procedure Guiaelines (EPG's). Because of the vast areas of information and expertise involveo, writing a successful E0P is a team effort. The team shoula include, but not be limitea to, people who are skilled in the areas of technical writing, power plant operations, operator training, engineering design and human factors.
5.2 MATEHIAL AND EQUIPMENT N/A - Not applicaole to this proceaure.
5.3 $PECIAL REQUIREMENTS 5.3.1 Generic bWR Emergency Procedure Guidelines The background information shall consist of appendices to the Generic bWH Emergency Proceaure Guidelines and shall be documenteo both as a learning tool ano as an ala for verification of actions / analyses performed to achieve the level of accuracy in the technical guicelines.- This documentation shall incluce, but not be limitea to the following: assumptions mace, references to information, references to results of analyses, anc information leacing ,
to the adaptation of generic technical guicelines.
UEURGIA POWEH CUMPANY HATCH NUCLEAH PLANT ~
PAGE 11 UP 70 UUCUREET TITLE: tMthGENCY UPERATINU HEVIb10N:
PROCEDURES PL ANT-SPECIFIC WHITER'S GUIDE O
$.3.2 Plant Specific Tecnnical Guidelines 5.3.2.1 The plant specific technical guidelines will De identical to the generic emergency procedure guidelines except that Hatch Plant specific cata will De used in the various limits, ta01es, ano grapns; references to systems not found at Plant hatch will be deleted.
5.3.2.2 The generic and plant specific guidelines are orienteo so that emergency operating proceaures written from them can be useo by an operator to mitigate the consequences of an emergency without first having to diagnose the event or event combination causing the emergency. The generic and plant specific-guidelines are cased upon the requirements of NUREG-0737, Clarification of TMI Action Plan Requirements, ano will be the latest revision approved by the NHC.
6.0 PRECAUTIONS / LIMITATIONS 6.1 PRECAUTIONS N/A - Not applicaDie to tnis procedure.
6.2 LIMITATIONb N/A - Not applicable to this procedure.
7.0 PREREQUISITES N/A - Not applicaDie to this procedure. ,
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GEORGIA PODEH CUMPANY HATCH NUCLEAR PLANT PAGE 12 UF 70 UUCUMENT TITLE: EMtHGENLY UPEHATINb HLVib10N:
PROCEDURES PLANT-SPECIFIC WHITEH'S GUIDE O 8.0 PROCEDURE 8.1 ORGANIZATION OF AN EOP 8.1.1 The EOPs will be organized in the following general sections:
Title Page (h Objective of E0P (2)
EntryCondition(h Proceoure booy (h 8.1.2 The three parts of the EOP will contain the sections from the list above, as follows:
E0P PART SECTIONS CONTAINED Cover Proceoure h @, @, @
Flow Charts (h* , ()*
End Path Manual Procedures @, @ @ @
- As modified for Flow Chart methodology and implementation 8.1.3 Title Page The title page of an EUP will be ioentical to that shown in Attachment 3 of this Writer's Guide. ,
l UEUMUTA FUDER CURFnNY l HATCH NUCLEAR PLANT -
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l UUCUREMT TTTEET- ERERCERCV UPERATInc REVISTuRT-l PRUCEDURES PLANT-bPECIFIC WHITEh'S GuluE O l
8.1.4 Objective o f an EOP The objective of an EOP (which is the purpose of the EPG) will be a precise and simply stated paragraph of what the 4
i E0P is to accomplish.
8.1.5 Entry Conditions Tne single entry condition for all Flow Charts sna11 be "Any Scram".
8.1.6 Proceoure body 8.1.6.1 The cover proceoure is intendeo to introouce the flow.
chart methodology and general cautions. It also explains the ties between the cover proceoure, Flow Cha rts, ano End Patn Manuals, anc contains the objective and entry conditions for the Flow Charts.
8.1.6.2 The Flow Charts oody shall contain operator immediate actions ano-verification and check' statements to ensure that the indicated automatic system' action is accomplished.
8.1.6.3 The End Path Manual shall contain End Path Procedures which have subsequent action steps that the operator tuKes to return _the plant to a normal steaoy-state condition or to provide for a safe extended shutoown period. Additionally, the End Path Manual will contain ..
the following:
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UE'ORGIA PUDEN COMPANY HATCH NUCLEAR PLANT ~
PAGE 14 0F 70 UUUUREET TITLE: EMERUENCY UPERAl1NG REVIblON:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 6.1.6737I Cover ProceouTe The cover placedure will be placea at the front of the End Path Manual, for convenience to the operator.
8.1.6.3.2 Contingencies This section of the End Path Manual shall contain the contingency actions of the BWR Emergency Proceoure Guidelines.
8.1.6.3.3 System Recovery Procedures This section of the End Patn Manual shall contain the procedural guioance to recover systems that were lost either during the initiating event sequence or as a result of the initiating event sequence.
8.1.6.3.4 Containment Control Procedures Tnis section of the Eno Path Manual shall contain the bulk of the eWR tmergency Procedure Guidelines dealing with primary and secondary containment control.
8.1. 6.3.5 Heactivity Control Procedures 4
This section of the End Path Manual shall contain reactivity control guidance of the bWR Emergency Procedure Guioelines.
8.1.6.3.6 Radioactivity Release Control Guidance Tnose uWR Emergency Proceour,e Guideline actions not amenable to Deing placed in the Hatch Nuclear Plant ..
Emergency Plan will be incorporated into the Containment Control Procedure section.
GE0HGIA POWER CUMPANY HATCH NUCLEAR PLANT ~
PAGE 15 0F 70 UUCUREMT TITLE: EMENUENCY OPtHATING HEVld10N:
PROCEOURES PLANT-SPECIFIC WHITEH'S GU10E O l 8.2 ORGANIZATION OF FLOW CHAHTS The Flow Charts sna11 consist of 5 symptom-oriented oecision tree action paths. The Cover Procedure shall contain tne objective and introouction to the Flow Charts and shall describe now these instructions are to be usea by the plant operators to handle emergency or potential emergency situations.
8.2.1 uesignation ano Numbering 8.2.1.1 The Flow Charts are the procedures that govern the plant operation auring emergency conditions ano specif y immediate operator actions to be taken to bound the problem and to return the plant to a stable condition.
4 Each Flow Chart shall be uniquely.icentified (see Attachment 4). This identification (acting as the title page) permits easy administration of the process of procedure revision, distribution, and operator use.
UEURGlA PUWEN COM R NY HATCH NUCLEAR PLANT ~
PAGE 16 OF 70 UUCUREHT TITLL: EMEHGENCY UPtHATING HEVIb10N:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.2.1.2 The various Paths will have some overlapping information on tnem as required to ensure eacn can stand alone, but they can be generally described as follows:
Path 1 - Malfunction of reactivity control system Path 2 - Reactor transients or failure of vital equipment (from low reactor power)
Path 3 - Heactor transients or failure of vital equipment (from high reactor power)
Path 4 - High steam line radiation, loss of vital power, failure of vital equipment, or loss of coolant (unoer degraded conoitions)
Path 5 - High radiation, loss of coolant, and control of primary containment integrity (under degradeo conoitions)
The Flow Charts shall not have identifying titles. The philosophy is for the operator to immediately enter any Flow Chart when the entry condition occurs. Once the operator enters the Flow Chart, it will leau .to the proper proceoural steps.
8.2.2 Revision and Au tho rization Each Flow Chart shall incluoe tne current' revision number ano authorizing signatures. This information shall De located at_
the upper right of each Flow Chart (see Attachment 4).
GEUHGIA PUCEN COMPANY HATCH NUCLEAR PLANT PAGE 17 0F 70 UUUUMENT TITLE: EMEHEENCY UPEHATING HEViblON:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIUE O 8.2.3 Identification for Flow Charts There shall be site identification and unit identification for the Flow Charts as shown on Attachment 4. The icentification I
block shall De printed black-on-white for Unit 1 and white-on-black for Unit 2 to allow easy laentification.
8.2.4 Page Identification There shall De no page identification on the Flow Charts, since each Flow Chart shall be contained on a single page. The Flow Charts will oe laentified by Path (i.e. Path 1, Path 2, etc.).
(See suosection 8.2.1.)
8.2.5 Format The Flow Charts shall utilize logic symbols as specified on Attachment 5. These symbols shall be arrangeo in a decision tree type Flow Chart that provices the operator with guicance intended to bound the problem and get the plant into a safe condition quickly, systematically and consistently (see Attachment 6). Information in the logic symbols shall be of typewriter quality and all CAPb so that reacability is maintained on the reduced charts.
8.2.6 Uecision Symool 8.2.6.1 This symbol sna11 contain a question which the operator is to answer YES or NO. The question shall pertain to a plant parameter, setpoint, switen position, or system condition.
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GEORGIA PUCEH CUMPENY HATCH NUCLEAR PLANT PAGE 18 0F 70 UUCUEERT TITLt: EMEHGENCY UPEHAl1Nb HEVid10N:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.2.6.2 If the particular step is cesignated as a " key" or " path specific a parameter, it shall have an action symbol superimposed over the stanoard decision symbol and the decision symool sna11 be in bold lines. This identifies steps which require the operator to return to the top of the chart and restart in the event this " key" parameter changes state after having been passed. A normal decision block changing state after having Deen passeo only requires the operator return to that one cecision block and continue from there.
8.2.7 Action Step Symbol (Sequence Sensitive)
Tnis symbol shall contain a specific action or command which the operator performs, and must be performed in the sequence indicated.
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- 8.2.8 Action Step Symbol (dequence Insensitive)
This symbol shall contain a specific action or_commana which the operator performs, and may be performed at tne operator's i
option prior to reaching the step on the Flow Chart.
8.2.9 Inf ormation Symbol This symbol shall contain information wnich may be useful to assist the operator in diagnosing plant conoitions. The symbol is also used to provide operator cautions (as shown on Attachment 5) -
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GEORGIA PUWEH CUMPANY HATCH NUCLEAR PLANT PAGE 19 0F 70-UUCUMENT TITLE: EMEnLENCY OPERATINb MtVlblUN:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 6.2.10 Arrow Symools There shall be two basic types of arrow symbols used on the Flow Charts (see Attachment $). Tne path-to-path arrows guice the operator from one Flow Chart to another. The path-to-end-path arrows shall guide the operator from the Flow Chart Immediate Action Steps to End Path Proceoures. Attachment 6 snows how the path-to-path arrows are individually modified to key the operator to a specific corresponding arrow on the new path, anc how the grid locations are noted (see subsection 8.2.17).
8.2.11 Connecting Lines There shall oe two casic line widths used to guice the operator through the Flow Cnart. Tne operator should follow these lines always entering the symbols at the top and exiting the symbols at the side or cottom.
The wioe line represents the expected plant response for each Flow Cha rt for normal plant recovery. All lines are equally important. Tney represent possible response of the plant for many situations on each Flow Chart. No lines shall Cross or intersect on the Flow Cnarts, except wnere two or more enter the same symbol.
8.2.12 Entry Condition The entry conoition for each Flow Chart is identical (see Attachment 6) and is ioentifieo in the cover procedure. The ..
entry condition snall be "Any 5 cram", and is contained in an information symool.
UFJHGI A POWEN COMPANY HATCH NUCLEAR PLANT PAGE 20 OF 70-DOCURENI TITLE: EMENGENCY UPEHATING MtViblON:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.2.14 Flow Chart initial Format Each Flow Chart snail have an ioentical initial series of symbols as shown on Attachment 6. The placement of YES/NO and type of connecting line will vary according to individual path requirements. This initial sequence establishes priority of actions and guides the operator to the appropriate Flow Chart.
8.2.14 Automatic Actions important safety systems automatic initiation verifications i
I shall be incluoed in the Flow Charts. The following statement enclosed within an action symbol is an example of operator verification of automatic actions: " Verify Auto or Manually Start HPCI".
8.2.15 Immediate Operator Actions Tne initial steps on the Flow Charts are the Immediate Operator Action Steps. These operator actions are taken to stop further degradation of existing conditions and to mitigate their consequences or to bound tne problem. The immediate operator actions shall be visiole at all times to the operator; therefore, tnere is no need for the operator to memorize these actions.
8.2.16 Operator Cautions Operator cautions may be included on the Flow Charts where appropriate. The caution will preceoe the procedural step to ,,
i which it applies, ano shall De highlighted as shown in Attachment 5.
GEORGIA PUWE R UMPT4NY HATCH tJUCLEAR PLANT PAGE 21 OF 70-DUCuMENT TITLE: EMERGENCY OPEHATING HEV151UN:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.2.17 Grio system Each Flow Chart shall have a series of letters along the sides and araolc numerals along the top and bottom to act as a gric locator system (see Attachment 6). Tne grid snall not be drawn on the chart as a series of lines. The resulting intersecting areas (18 for example) snould be arranged to encompass approximately 3 Flow Chart symbols. The grid system is used for path-to-path arrows anu to allow operators to indicate to other personnel where they currently are in the chart. EXAMPLE: to allow the managers in the Technical Support Center to follow progress on the Flow Charts.
d 8.2.18 Preparing and Mounting Flow Charts The Flow Charts will require off-site assistance to prepare since the are extensively color-coceu and may De computer-generated. The completed enarts snall De reduced to approximately 20" x 35" (as appropriate for use in the control room) anc mounted on lightweight ocards such as styrofoam. Each ocuro will then be laminateo with a thin, transparent plastic material. Each Flow Chart board may be framed with lightweight aluminum for auditional strength.
The Control Hoom Flow Charts shall have at least a one half inch blank border on all sides to increase readanility. _
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UtUHU1A FO5ER C'JRFAf Y HATCH NUCLEAH PLANT PAGE 22 0F 70 UUCUMENT TITLE: EMEHLENCY uFennTINu nEv1SIuN:
PROCEDURES PLANT-SPECIFIC WHITER'd GuiUE O 8.2.19 Heproduction of Flow Charts Heproduction of the Flow Cnarts may be done on a standard blueprint copier. Reduced Flow Charts on film (mylar) may be used for the original. Computer-generated or coloreo charts may require more aovance tecnniques (i.e.
photographic reproouction).
8.2.20 Revisions to Flow Charts The revision process for the Flow Charts requires the same administrative controis as all other procedures, in accoroance with 10AC-MGR03-0.
The current revision or eacn Flow Chart snall be maintained in accordance with Hatch procedures for control of procedures.
8.2.21 Color Coding On any given Path 1 through S, yellow indicates the expected, tnough unverified response-path, and is used exclusively for the mainpath down the chart. Green is a deviation, but is otherwise normal.- Orange is-also a deviation; however, a oegradeo plant response may De involved. Red is a deviation with aefinite degracation of plant equipment. The color of a logic symbol indicates the degradation associated with that specific sequence of-
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actions. Connecting lines snoula be the same color as the I
logic symool from which they originate. l I
UEDHGIA PUwEN tuMPANY HATCH NUCLEAR PLANT PAGE 23 0F 70 OUCUMENT TITLL: EMEHGENCY UPEHA11NU HLViblUN:
PROCEDURES PLANT-SPECIFIC WHITEH'S GUIDE O 8.3 ENU PATH MANUAL AND COVER PRUCEDURE PREPARATION 8.3.1 Purpose Tnis section assembles a set of general criteria for preparing and reviewing EUPs assigneo to nuclear facility Plant OpeIating Manuals, subject to some specific qualifications and exemptions for indiviaual types of procecures as aescribeo herein. These criteria sna11 ensure continuing incorporation of the results of human factors stuales in the design of procedures.
8.3.2 Procedure Identification Proper icentirication of proceoures is necessary to avoid errors in selection ano implementation. Complete identification of a procedure incluaes its title, numoer, facility (i . e . , H NP) , revision and type.
8.3.2.1 Proceoure Title Each procedure will oe given a title which accurately reflects its intended purpose. Within this constraint, procedure titles sna11 be kept as short and concise as possible.
6.3.2.2 Procedure Designation The ten significant cnaracter alphanumeric cesignator for the Emergency Operating Procecures shall oe in
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accordance with 10AC-MGR03-0.
UEORGIA FonEn coMFANY HATCH NUCLEAR PLANT PAGE 24 OF 70 UUCUMtNI IIILE: tMEEDEUCY OFERATING aevisluN:
PROCEDURES PLANT-SPECIFIC WRITEH'S GUIDE O 8.3.2.3 Procecure Numoers 8.3.2.3.1 Each procedure will oe assigned'a unique and permanent number within its associated Path and Section of the Ena Path Manual. Whenever a i
procedure is deleteo, the associated procecure numoer will not normally be reassignea for the ensuing 2-year perico. If reassignment is~maoe within this perica, consideration should De given_to user retraining to avolo confusion or error.
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CEURCDUSER LuMF7iN Y HATCH NUCLEAR PLANT PAGE 25 UF 70 U0CoMENT TITLE: EMERGENCY OPERATING MtV1510N:
PROCEDURES PLANT-SPECIFIC WRITER'd GUIDE O 8.3.2.3.2 Procedure numbering shall De controlled as follows:
Sections 1.10-1.19 - Eno Path Manual Procedures from Flow Cna rts - Path 1, 10-19 Sections 2.20-2.29 - Eno Patn Manual Procedures from Flow Charts - Patn 2, 20-29 Sections 3.30-3.39 - Eno Patn Manual Procedures from Flow Charts - Patn 3, 30-39 Sections 4.40-4.49 - End Patn Manual Procedures from Flow Charts - Patn 4, 40-49 Sections 5.50-5.59 - End Patn Manual Procedures from Flow Charts - Patn 5, 50-59 I--------------------- l-I NOTE I I i i I l"X" in Section Number inoicates the End Path Manual numoer (i.e. I I
Iwhicn Flow Chart was exited). 1 I .
Sections X.00-X.09 - Cover Procedures Sections X.60-X.79 - Generic System Hecovery Proceoures Sections A.bO-X.99 - Contingency Procedures Sections X.lu0-X.119 - ATwS Recovery Procedures Sections X.120-X.139 - Containment Control Guice i
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ULOHGIA PUDER COMPANY HATCH NUCLEAR PLANT PAGE 26 0F 70.
DUCUMENI IIILE: ERERGENCY OPERATING RtV15 ION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 6.3.3 Page Identification Beginning with the Title Page, the top of each page of each procedure will bear the procedure designation, current revision numoer and page number as an alc to validation by the user. Each procedure shall oegin with a new page.
The title page format will be as shown in Attachment 3.
8.3.3.1 Revision Number Tne revision number snail be a one or two digit numoer i .
indicating tne current approveo revision.
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GEORGln PU;EH COMPAN'S HATCH NUCLEAR PLANT PAGE 27 0F 70 DOCUMENT TITLE- EMEHGENCY UPEHATING NtVibluN:
PROCEDURES PLANT-SPECIFIC WRITEH'S GUIDE O 8.3.4 Page Numbering Each page of eacn procecure shall be numcereo sequentially beginning with the Title Page. If pages are aaded to a procedure, complete renumbering of all pages shalt ce pe rfo rmed .
The page number shall appear in the following format:
PAGE OF Likewise, wnen pages are deleteo by revision, the proceoure pages sna11 De renumoereo.
8.3.5 loentification of Reviseo Material Reviseo material shall oe icentified witn a vertical line in the right-hand margin opposite the revised text. Vertical lines from any previous revision shall be celeteo.
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GEURGIA POGER'TDMP ANY
' HATCH NUCLEAR PLANT -
PAGE 26 0F 70 .
UUCOMENT' TITLE: EMERGENCY UFERATING RevisTON:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O l
8.3.6 General Writing Techniques The following section provices a set of standaros wnich shall be considered in the preparation ana review of all E0Ps. In considering these guidelines, writers shall keep in mind that some are more important than others for different sections of procedures. The writer snall always-consider the conditions under wnich the proceoure will be implementeo, the time availaole for its implementation, and the possioie consequences of errors in implementation.
8.3.6.1 Multiple-unit Procedures Procedures whicn contain multiple sets of equipment ioentifications for use with more than one unit are more difficult to reaa anc comprehend than proceaures dedicatea to a single unit. Inerefore, a unique set of procedures for each unit shall be developeo. To ease identification, color cooing may be useo wherever appropriate.
ULOHGAA PubEn LUMPANY HATCH NUCLEAR PLANT PAGE 29 0F 70 DOCUMENT TITLE: EMERUEMCV UPERATING MtViblUN:
PROCEDURES PLANT-SPECIFIC WRITER'S GU10E O 8.3.6.2 Page Format A single or cual column format may be used, however, the procedure shall oe in one format only, either all single or all cual. If tne cual column format is to De useo, then the left-hano column shall De designated for operator actions, and tne right-hano column shall be designated for contingency actions to De taken when the expected response is not ootained. A sample cual column page format is presented in Attachment 7. In either format, the general appearance of procedural pages contributes significantly to comprehension and the elimination of confusion and error. Information on pages shall De displayed with minimum clutter, sufficient spacing between lines ano adequate margins.
Margins shall be sufficient to ensure that binding will not interfere with reading the text and that subsequent reproduction will not cut off any of the procedure content or page ioentification.
EEORGIA PowEH CUMPANY HATCH NUCLEAR PLANT PAGE 30 0F 70 UUCURENT. TITLE: EMERCERCV UPERRTING HEVISION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.3.6.3 Step NumDering, Incenting , and Checkoffs Instructional steps must be readily identifiable by the user. Step numoe ring , indenting , ano checkoffs are used to assist proceoure users in keeping track of step sequence and subordination. The following guidelines apply:
Only Araoic numerals sna11 be useo in step numoering.
The same step numoering and incenting scheme will be applied consistently to all procedures.
The acceptable numbering scheme is as follows with the optional cneckof f spaces shown:
1.0 1.1 _
l .1.1 __
1.1.1.1 1.1.1.1.1 ____
Numbering ano incenting beyond the section of the example above shall not ce used. If necessary, procedures shoulo be reorganized to produce an acceptable number of subsections. Subsection numbers should be indented two spaces from the preceding section or suosection number ma rgin.
Checkoff spaces shall De placed as shown for all steps requiring an operator action, and may be used elsewhere if it will enhance the operator's aoility_to keep track of his place in the proceoure.
ULURGIA POWER ~ COMPANY HATCH NUCLEAR PLANT PAGE 31 0F 70 UUCUMENT IIILt: EMtHGENCY UPtHAIING MtVid1UN:
PRUCEUURES PLANT-SPECIFIC WHITER'S GUIUE O 8.3.6.4 Step Sequencing Instructional steps will be presenteo in the sequence most appropriate for the situation. Instructional steps which can be performed concurrently shall be listed in order o f relative importance. When the sequence of actions is critical, the phrase "in the order given" or similar phrase shall be used in tne step introducing the actions. On the flow charts, all steps are understooo to be performed "In tne order given", except those contained in the special symbol wnich allows out of sequence performance.
8.3.6.5 Caution 5tatements 8.3.6.S.1 Cautionary information can be considereo in two funoamental categories, those that apply to the entire proceoure and those that apply to a portion or a specific step of the procedure. Those that apply to the entire proceoure are calleo " General Cautions" ano will be containeo in the cover procedure. Tnose that apply to a portion of a procedure are calleo " CAUTIONS" and are placeo immeaiately oefore the procecural steps to which tney apply.
GEURGIA PUCEH LUMPANY HATCH NUCLEAR PLANT PAGE 32 0F 70 UUCUMENT 11ILE: EMcRGENCY OPERETIRL ncvidion:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O i
8.3. 6. 5.2 Cau tions shall extena across the entire page ano shall ce nighlighted as snown in the Example CAUTION. This placement of cautions helps ensure that the procecure user auserves~the caution Lefore performing the step. A caution cannot ce useo insteaa of an instructional step. It shoulo be useo to cenote a potential hazaro to equipment or personnel associated witn or consequent to the suusequent instructional step. The caution shall be capitalized with the word CAUTION underlined.
Caution statements sna11 De written so tnat they can be read completely without int'erruption by page
, turning.
EXAMPLE:
CAUTION CAUT10N5 SHALL Bd TYPEu IN ALL CAPITAL LETTERS ONLY MM J
CE0HGIA FUEEN COMPANY HATCH NUCLEAR PLANT PAGE 33 0F 70 UUCUMENT-TITLE: EMEHGENCY UPtHATING HEVIS1UN:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.3.6.6 Notes A note provides descriptive or explanatory information intenced to aid personnel in performing an instructional step. Notes shall not contain action steps. Notes shall be as close to the applicaole instruction as possible. If dual column format is usea, the note snall be located in the right-hand column. If single column format is used, tne note shall be approximately aligned with the text of the applicable instruction step as shown in tne Example. The word NOTE shall be capita 11zeo and underlinea, ano shall be nighlighteo as shown in the Example.
Example:
I I l l l NOTE l
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! Notes shall De typeo in structured sentences. 1 I l l I ..
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CEORGIA P0hER CUMPANY HATCH NUCLEAR PLANT PAGE 34 0F 70 UUCUMENT TITLE: EMERGENCY OPEHATING HEVISluN:
PROCEDURES PLANT-SPECIFIC WHITER'S GUIDE O 8.3. 6. 7 Calcula tions Mathematical calculations shoula be avoidea in EOPs. If a value has to be determined in order to perform a procecural step, a cnart or graph should be used whenever possible.
When calculations are requirea, they shall De as simple as possible, and space shall be provided for the calculations.
8.3.6.8 Referencing and uranching 8.3.6.8.1 Heferencing implies that an additional procedure or acaitional steps will De used as a supplement to the procedure presently Deing used. Referencing other steps within the procedure being useo, eitner future steps or completea steps, should be minimized. When only a few steps are involvea in tne referencing, the steps should be stated in the proceaure wherever they are needed.
8.3.6.6.2 To minimize potential opergtor confusion, oranching will be usea when tne operator is to leave one i
procedure or step and use another proceaure or step.
Use the key words "go to". Therefore, the operator v:111 know to leave the present step and not return until directea. Use quotation marks to emphasize the title of the referenced or branched procedure; examples: Go to E-1, " Loss of Reactor Coolant". Go to Step 20.
UEUIIGITPUWER CUMFANY HATCH NUCLEAR PLANT PAGE 35 UF 70 UUUUMENT TITLE: EMEHubNCY UPLHA11NG HbV1blUN:
PROCEDURES PLANT-SPECIFIC WRITER'S GU10E O 8.3.6.9 Style of Expression Style of expression refers to tne way in wnich instruction steps are written. Steps will oe written in a style tnat presents information in a simple, familiar and clear manner. Tne following guioance shall be followed:
8.3.6.9.1 Use words tnut are common in oroinary conversation.
8.3.6.9.2 Use terms personnel are trained to use and which are standard in the industry.
8.3.6.9.3 Use action veros tnut descrioe exactly what the user is to do. Ensure that these verbs are understooo ano useo consistently throughout procedures.
Samples of action verbs are given in Attachment 6.
8.3.6.9.4 When there are more than two oojects of an action verb, list them below the instruction step rather than in tne step.
EXAMPLE: USE 3.2.9 open the following valves:
2B21-F016 2b21-F019 2 b21 -F03 8 EXAMPLE: UO NUT USE 3.2.9 open valves 2821-F016, 2621-FU19 and 2621-F036 1
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CEURCIA POWER CUMPANY HATCH NUCLEAR PLANT PAGE 36 0F 70 UUCURENI TITLE: ERERDENCV OPEMATING REVI5 ION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIuE O 8.3. 6. 9. 5 Us e sho rt , direct sentences. Estaoiish a style of sentence construction suitable for the procedure type ano use it consistently.
8.3.6.9.6 Number of actions per step shall be minimized, and limited to one action wnere possible. Where two actions are incluoed in one step, use the connective AND rather tnan two sentences.
8.3.6.9.7 Avoid adveros that have imprecise meanings.
Example: Use " eve ry 5 minu tes until. . . . "
rather than " frequently until.."
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I UEORGIA PUWEH COMPANY HATCH NUCLEAR PLANT PAGE 37 0F 70 l DOCUMENT TITLE: EMERGENCY UPEHATING HEVISION:
1 PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 1
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9.3.6.10 Instrumentation Values When specifying instlumentation values, an appropriate i range, tolerance or limit will be used rather tnan a single
! point value. Avolo tne use of mathematical symbols (<[;)>)
4 in specifying these ranges. 'Instead, use phrases sucn as i "greate r than", "less than", "between", " greater than or i equal to", "less tnan or equal to", etc.
8.3.6.11 Equipment, Controls, and Display l Nomenclature useo shall assist personnel in quick location i
i or identification of equipment, controls, and displays. Use lo a consistent system of identification which corresponds 1 precisely with component identifications' posted on equipment and control panels. Location information will also be included as follows:
For shutoown outside the control room, location inf ormation will be provioed for every valve, switch, pump, panel, etc.
i For snutcown insice the control room, location information j will be provideo for those components not.normally used by the operator.
, EXAMPLE:
2.22.7 Open condensate cemineralizer bypass valve at panel i 2H21-P216 4
Adequacy of tnis information will De checked during the j procecure validation program.
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EEURUTA FuWER CuMPAriY HATCH' NUCLEAR' PLANT PAGE 38 0F 70 UUCUREMT TITEE: EMERGEMCY OPERATING REVIslON:
PROCEUURES PLANT-dPELIFIC WRITER'S GUIDE O 8.3.6.12 Aubreviations, Letter bymbols, ano Acronyms 8.3.6.12.1 Aooreviations may be useo where necessary to save time and space, and when tneir meaning is unquestionably clear to the intended reader.
Write in the full meaning of the abbreviation before the first use of the aobreviation ano whenever in couot. Maintain consistency throughout the procedure, incluoing use of capitalization in tne acoreviations. If the abbreviation is comprised of lower case letters, it shoulo appear in lower case in a title or heading. Omit tne period in abbreviations except in cases where the omission would result in f confusion. Where an abbreviation is not currently used in plant proceoures, the abbreviation will be discussed in the training program.
8.3.6.12.2 Letter symbols may De used to represent operations, quantities, elements, relations, and qualities.
8.3.6.12.3 An acronym is a type of symbol formed by tne initial letter or letters of each of the successive parts or major parts of a compound term. Acronyms may De used it they are defined or commonly used.
UEORGIA PU::EH CUMPANY HATCH NUCLEAR PLANT PAGE 39 0F 70 UUCUMENT IITLE: EMEHGENCY OPtHATING REVIS1UN:
PROCEDURES PLANT-SPECIFIC WRITER'S GulDE O 8.3.6.12.4 Abbreviations, symbols, and acronyms should not be overuseo. Their use should be for the Denefit of the reaaer. They can De beneficial by saving reading time, ensuring clarity wnen space is limited, ano communicating matnematical ideas.
8.3.6.13 Level of Detail 8.3.6.13.1 Too much detail in EOPs should be avoiced in the interest of being aole to effectively execute- the instructions in a timely manner. The level of detail required is the detail that a newly trained i
and licensed operator would desire during an eme rgency condition. To assist in aetermining the level of E0P detail, the following general rules apply: For each control with a numoer engraved on the control panel placard, the numoer may be
- included in parentheses within tne instructional step where necessary for clarity. . EXAMPLE
- " Start HCIC Water Leg Pump (S33)." For control circuitry that executes an entire function upon actuation of the control switch, the action vero appropriate-to the component suffices without further amplification or how to manipulate the control
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device. EXAMPLE: "Close FEED PUMP A SUCTION VALVE (F028A)".
CEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 40 0F 70 UUCUMENT TITLE: EMENGENCY uPEHATING HEVI510N:
PROCEUURES PLANT-SPECIFIC WRITER'S GU10E O 8.3.6.13.2 Hecommended action verbs are as follows:
For power-driven rotating equipment, use Start, Stop.
For valves, use open, Close, Tnrottle Open, Throttle Cl os e , Throttle.
For power distribution breakers, use Synchronize and Close, Cl os e , and Trip.
For control switches with a positional placement that establishes a standby readiness condition, the verb
" Set" should be used, along with the engraved name of the desired position. Positional placements are typically associated with establishing readiness of automatic functions and are typically named AUTO or NURMAL; for example, " Set the GLAND SEAL AIR COMPHESSOR Control Switch (515) in AUT0".
For multiposition control switches that have more than one position for a similar function, placement to the desired position should be specified; for example,
" Place DIESEL FIRE pump selector switch to TEST No. 2".
8.3.6.13.3 Standard practices for observing abnormal results need not be prescrioeo within procedural steps. For example, observation of noise, vibration, erratic flow, or discharge pressure need not be specified by steps that start pumps.
CEURUIA PUWER COMPANY HATCH NUCLEAR PLANT PAGE 41 0F 70 DOCUMENT TITLE: EMERGENCY UPERATING REvibluN:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE 0-8.3.6.14 Equipment Status Equipment status should be denoted as follows:
8.3.6.14.1 Operaule/ operability - See definition contained in Unit 2 Technical Specifications, section 1.0, Amendment 14.
8.3.6.14.2 Operating - This word means that a system, suosystem, train, component, or Uevice is in operation and is performing its specified function (s), and that "Uut of Service Caros" or other concitions do not prevent it from maintaining that service.
8.3.6.14.3 Available - This woro means that a system, subsystem, train component, or device is capable of performing its specified function (s) in the intenaea manner, but does NOT necessarily imply that all redundant support systems are in service.
EXAMPLE: If RFPT A OC oil pumps are out-of service but the RFPT is otherwise normal, RFPT A would not be considered operable, but would be considered available.
UEURGIA POWE M URFAMY HATCH NUCLEAR PLANT PAGE 42 0F 70 UUCUREMT TITLE: EMERUENCY OPERATING HEVI51UN:
PROCEDURES PLANT-SPECIFIC WRITEH'S GUIDE O 8.3.7 Instructional Steps 8.3.7.1 Instruction Step Length and Content 8.3.7.1.1 Instruction steps shall De concise and precite.
Conciseness denotes brevity; preciseness means exactly oefinea. Tnus, instructions snall oe short and exact.
8.3.7.1.2 Instruction steps shall deal with only one idea.
Short, simple, sentences snail oe used in preference to long, compound, or complex sentences. Complex evolutions shall De prescribeo in a series of steps, with each step made as simple as practicable.
8.3.7.1.3 Uojects of operator actions shall be specifically stated. Tnis includes ioentification of exactly what is to be done ano to what.
8.3.7.1.4 Eacn action step shall be wholly contained on a single page.
8.3.7.1.5 For instructional steps that involve an action verb, relating to three or more ODjects, the objects shall
. be listea with space provided for operator checkoff.
8.3.7.1.6 Limits shall be expressed quantitatively whenever possiole (see Subsection 8.3.6.10).
8.3.7.1.7 Identification of components and parts shall De
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complete.
UEURGIA PuWEN COMPANY HATCH NUCLEAR PLANT PAGE 43 UF 70 DOCUMENT TITLE: EMENGENCY UPEHATING HtVib10N:
PROCEDURES PLANT-SPECIFIC WHITER'S GUIDE O 8.3.7.1.8 When system response dictates a time frame witnin whicn the instruction must be accomplished, prescribe sucn time frame. If possible, however, avoid using time to initiate operator actions; operator actions shall be, where possiole, related to plant parameters.
8.3.7.1.9 When actions are required basea upon receipt of an annunciated alarm, list the setpoint of the alarm for ease of verification. Wnen requiring resetting or restoration of an alarm or trip, list the expected results immediately following the resetting or restoration if it woulo be beneficial to the operator.
8.3.7.1.10 Expected results of routine tasks need not be stated.
When considered beneficial to the user for proper
- understanding and performance, aescribe tne system response time associated with performance of the instruction. When anticipated system response may adversely affect instrument indications, describe the conditions that will likely introduce instrument error and means of oetermining if instrument error has occurred by using a NOTE.
8.3.7.1.11 When additional confirmation of system response is i consioereo necessary, prescrice the backup readings to be made.
GEURGTR'TDRETCDRPRNY HATCH NUCLEAR PLANT PAGE 44 0F 70 UUCURENI TITLE: EMERUENCY OPERATING REVISIOt4:
PROCEDURES PLAtlT-SPECIFIC WR1TER'S GUIDE O 8.3.7.2 Instruction Columns When the dual-column format is used, the left-nand column of the dual-column format will contain the operator instructional steps. The following rules are established for this left-nand column, in adoition to the general rules above. Operator actions in the left-hand column should be appropriate for the expected indications.
Expecteo indications shall be presented in the left-hand column.
8.3.7.3 Contingency Actions When the dual-column format is used, contingency actions will be presented in the right-hand column of the dual-column format. Contingency actions are operator actions that should be taken in the event a stateo condition, event, or task does not represent or achieve the expected results. The need for contingency action occurs in conjunction with tasks involving verification, observation, confirmation, and monitoring. Contingency i
actions will be specified for each circumstance in wnich the expected results or actions might not be achieved.
The contingency actions shall identify, as appropriate, directions to override automatic controls and to initiate manually what is normally automatically initiated.
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CEORcIA PUWER COMPRNY HATCH NUCLEAR PLANT PAGE 45 0F 70 UUCUMENT TITLE: EMEHGENCY UPERATING REVIblON:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.3. 7.4 Use of Logic Te rms 6.3.7.4.1 The logic terms AND, UR, NOT, IF, IF NOT, WHEN, and THEN are often necessary to describe precisely a set of conditions or sequence of actions. When logic statements are used, logic terms will be highlighted by capitalization and underlining so that all the conditions are clear to the operator.
8.3.7.4.2 Tne use of AND and OR within the same action snall be avoided. When AND and OR are used togetne r, the logic can be very ambiguous.
8.3.7.4.3 The cual-column format, when useo, equates to the logic: IF NOT tne action in the left-hand column, THEN follow the action specified in the right-hand column.
I 8.3.7.4.4 Wnen attention should be called to combinations of conditions, the word ANU snall De placed between the description of each condition. The word AND shall not be used to join more tnan three conditions. If four or more conditions need to be joinea, a list format shall be useu.
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ut0HGIA PUDER CUMPANT HATCH NUCLEAR PLANT PAGE 46 0F 70.
UUCUMENT TITLE: EMEHGENCY OPERATING REVIbION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.3.7.4.5 The word OH shall be used when calling attention to alternative combinations of conditions. The use of the word OH sna11 always be in the inclusive sense.
To specify the exclusive "0R", the following may oe used: "either A OR 8 but NUT both." When action steps are contingent upon certain conditions or combinations of conditions, the step shall begin with the words IF or WHEN followed by a description of the condition or conditions, a comma, the word THEN, followed by the action to be taken. WHEN is used for an expected condition. IF is used for an unexpected but possible condition. Use of IF NOT should be limiteo to those cases in which the operator must respond to the second of two possible conditions. IF snould be usea to specify the first condition. THEN shall not be used at the end of an action step to instruct the operator to perform the next step because it runs actions together.
8.3.7.5 use of Underlining Underlining will be used for emphasis of logic terms ana CAUTION and NUTE.
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GEOMGIA POWEk CuMPANY HATCH NUCLEAR PLANT PAGE 47 0F 70 U0CuMENT TITLE: EMERGENCY UPEHATING HEVISIUN:
PROCEDURES PLANT-5PECIFIC WRITER'S GUIDE O <
8.3.7.6 Component Identification With respect to identification of components, tne following rules are to oe followed:
8.3.7.6.1 Equipment, Controls, and Displays will be identified in specific terms. These terms shall always match engraved names on panels. When the engravec names and numbers on panel placaras and alarm windows are specifically the item of concern in the procedure, the engraving snail be quoted verbatim and emphasized by using all capitals.
8.3.7.6.2 The names of plant system titles are also empnasized by capitalization. When the word " system" is deletea j from the title oecause of brevity and is unoerstoo,d because of tne context, the title is also emphasized by capitalization.
8.3.7.6.3 If the component is seldom used or it is felt that 4
the component would be difficult to find, location information shall be given in parentheses following*
the identification.
8.3.8 Printed Operator Aios When information is presented using graphs, charts, tables, ano figures, these aios must be self-explanatory, legible, and readable unoer the expecteo conditions of use and within the reading precision of the operator.
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l GE0HGlA PUQLH CUMPANY HATCH NUCLEAR PLANT PAGE 48 UF 70 UUCUREHT TITLE: EMERGENCY OPERATING REVI5IUN:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIUE O 8.3.8.1 Units of Measure Units of measure on figures, taoles, and attachments shall be given for numerical values that represent observed data or calculated results. A virgule (slant line) should be used insteaa of "per".
EXAMPLES: ft/sec, lbs/nr.
8.3.8.2 Titles ano Headings Capitalization of first letter shall be used for references to specific taoles and figures, titles of tables and figures within text materials, and column neadings within a table.
EXAMPLES: Re fe r to Figu re 201 fo r. . . . . . . . . .
as shown in T&ble 201, Equipment Power Supplies, tne .....
8.3.8.3 Figure, Table, and Attachment Numbering 8.3.8.3.1 Sequential aracic numerdis shall be assigned to figures, tables, and attachments in separate series. Tne sequence shall correspond with the order of their reference in the text. The symbol "#" and abbreviation "No." are a unnecessary ano snali not be used.
8.3.8.3.2 Page identification for attachments shall consist of a block of information that identifies (1) procedure number, (2) attachment number, (3) page number, and (4)
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3 revision number. Page numoering of attachments shall meet the requirements of Subsection 8.3.4.
l UEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 49 0F 70 UUCUMENT TITLE: EMERGENCY UPEHATING HEV1bluN:
PROCEUURES PLANT-SPECIFIC WHITER'S GUIDE O B.3.8.3.3 Where standard forms are used from other procedures, they should be referenced and used in preference to complete duplication, where possible.
8.3.9 Mechanics of Style 8.3.9.1 Spelling Spelling shoula be consistent with modern usage.
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i UEORGIA PuuER COMPANY HATCH NUCLEAR PLANT PAGE 50 0F 70 UUUURENT TITLE: ERERUENCY OPERATING - REVI5 TUN:
- PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O i
i 8.3.9.2 Hyphenation Hyphens are useo oetween elements of a compound word when usage calls for it. The following rules shall be i followea for hyphenation. When doubt exists, the l compound word shall be restructured to avoid hyphenation, i
- j. Hyphens shall be used in the following circumstances:
! In fractions, examples: one-half, two-thirds; In compound numerals from twenty-one to ninety-nine, example: one hundred thirty-four;
{
j To separate chemical elements and their atomic weight,
- examples
- Uranium-235, U-235; 1
- When a letter is linked with a noun, examples
- x-ray, i
0-ring, U-bolt, 1-beam; 4
i In compounds with "self", examples: self-contained, l
l s el f-lub rica ted ;
When misleading or awkward consonants would result Dy 1
] joining the words, example: bell-like;
, To avoid confusion with another word, examples: re-cover
, to prevent confusion with recover, pre-position to avoid i t confusion with preposition.
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i UEURGIA POWER c5NFARY HATCH NUCLEAR PLANT PAGE $1 0F 70 -
( DOCUMENT TITLd: EMENGENCY OPEHATING HEV1610N:
l PROCEUURES PLANT-SPECIFIC WRITEH'S GUIDE O i
j 8.3.9.3 Punctuation Punctuation should be used only as necessary to aid reading and prevent misuncerstanaing. Wora order shall i be selected to require a minimum of punctuation. When
, extensive punctuation is necessary for clarity, the l l !
] sentence should be rewritten and possibly made into
)
l several sentences. Punctuation shall be in accordance 4 with the following rules : i Brackets - 00 not use brackets.
1 j Colon - use a colon to indicate that a list of items is j to follow.
1 l Comma - use of many commas is a sign the instruction is i
- too complex and needs to be rewritten. The re fo re ,
1 '
evaluate the number of commas to ensure the instruction
]: <
l is not too complex. Use a comma after conaitional '
i j phrases for clarity and ease of reaaing. EXAMPLE: WHEN 1
] level oecreases to 60 inches, THEN start pump.... <
i i Parentheses - parentheses shall oe used to indicate I
J j alternative items in a procedure, instruction, or 4
, equipment number. .
Period - use a perloo at the end of complete sentences f
and for indicating the decimal place in numbers.
Dasn - may be usea to set of f items in a list. ,.
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CEURGIA PUWER CUMFARY HATCH NUCLEAR PLANT PAGE 52 0F 70 ~~
UUCUMENT TITLE: EMERGERUY uPExaTING REVISTUN:
PROCEDURES PLANT-SPECIFIC WHITER'd GUIDE O 6.3.9.4 Vocabula ry use simple words. Simple woros are usually short words of few syllables. Simple woras are generally common woros. Woros used in procedures shall ce selected to convey precise understanding to the trainea person.
8.3.9.5 Numerical Values The use of numerical values should be consistent with the following rules:
Hrabic numerals shall be used.
For numbers less than one, tne decimal point shall be preceded by a zero. EXAMPLE: 0.1.
The number of significant digits should oe equal to the number of significant algits available from the oisplay and the reading precision of the operator.
Engineering units should always be specified for numerical values of process variables. They should be the same as those used on the control room displays. EXAMPLE: psig instead of psi.
Acceptance values snould be specified in such a way that addition and subtraction by the user are avoiced if possible.
This can generally be cone by stating acceptance values as limits. EXAMPLES: 5100F maximum, 300 psig minimum, 5800 to 6000F. For callaration points, statement of the midpoint and its lower ano upper limits for eacn data cell would accomplis the same purpose; for example,10 mil 11 amperes (9.5 to 10.5).
Avoid using +.
If
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UEORGIA POWEH COMPANY HATCH NUCLEAR PLANT PAGE S3 0F 70 00CUMENT TITLET EMERGENCY OPERATTRU HEVIETUMT PROCEDURES PLANT-SPECIFIC WRITER'S GUIUE O 8.3.10 Typing Format 3.3.10.1 Page Arrangement Page margins shall be such as to facilitate readability, approximately one-half to one inch in wioth on all sides.
8.3.10.2 Heading and Text Arrangement Block style, as illustrated in Attachment 7, is to be used with the dual-column format. Otherwise, the expanded block style used herein is to be used.
8.3.10.3 Breaking of Words Breaking of words shall be avoided to facilitate operator reading.
8.3.10.4 Rotation of Pages Pages should not be rotated. Tables ano figures should be reaoable with the page arranged vertically.
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UEURGIA POWER COMPANY
- i HATCH NUCLEAR PLANT PAGE 54 0F 70 l i UUUURENT TITLE: EMERGENCY OPEHATING REVISION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.3.10.5 Printed Operator Aios (graphs, drawings, diagrams, tables and illustrations) 8.3.10.5.1 The figure field must not violate specified page margins. The essential message shall be clear; simple presentations are preferred. The figure
, number and its title are placed below the figure field (refer to Subsection 8.3.8).
8.3.10.5.2 The figure fielo shall be of suf ficient size to i
offer good readability.
8.3.10.5.3 In general, items within the figure shall be i
l labeled. Typeo labels shall be useo, where possible. Handwritten labels shall be printeo, using all capitals, with letters and numbers at i
least 1/8 inch high. Labeling of items within the figure shall be accompanied by arrows pointing to the item.
8.3.10.5.4 Grid lines of graphs shall be at least 1/8 inch apart.
]
8.3.10.5.5 The items within the figure shall be oriented
- naturally insofar as possible. For example,
- height on a graph should be along the vertical i
- axis.
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GE0HGIA PODEH COMPANY HATCH NUCLEAR PLANT PAGE 55 0F 70 DOCUMENT TITLE: EMERGENCY OPEHATING HEViblUN:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.3.10.5.6 Tables shall be typec using the following rules:
Type style and size shall be the same as that for the rest of the procedure. A heading shall be entered for each column and centered within the column; the first letter of woros in the column headings snall be capitalized. The table number and title snall be located above.the table field.
8.3.10.5.7 Tabular headings shall oe aligned as follows:
Horizontally oy related entries, vertically ~ by decimal point for numerical entries, aled vertically by first letter for word entries.
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! However, run-over lines shall be indented.
8.3.10.5.8 There shall not be a vacant cell in the table. If no entry is necessary, "N.A." shall be entered to indicate not applicable.
8.3.10.5.9 Double spacing between horizontal entries suffices
- to segregate such entries, althougn horizontal lines may also be used if desireo.
8.3.10.6 Cautions and Notes The applicable heading " NOTE" ano " CAUTION" shall be capitalized and centered. The text of the note or
- caution shall be block format, double spaced. All words in cautions snail be capitalized. Examples are presented in Subsections 8.3.6.5 and 8.3.6.6.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 56 OF 76 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O 8.3.10.7 Use of Foldout Pages When used, a foldout page is treated as a single page. It i
- shall follow the same format as a standard page as described .
j in this procedure except the width is different. The page j shall be folded so that a small margin exists between the i
fold and the right-hand edge of standard pages, to reduce wear of the fold. Foldout pages shall not be used if the
! foldout section will cover any other procedures as placed in the End Path Manual.
8.3.10.8 Reverse Page Printing i Reverse page printing may be beneficial in order to keep
! certain curves or limits associated with the procedural 1
text. If this is-the case, the curve or limit shall be-
]
printed on the reverse side of the previous page in the-same
, orientation as the text page so that it is directly readable by the operator. No text will be placed on the reverse side of a figure so printed, except for standard page header-j information and the statement-"[ figure name] printed on reverse side - turn page".
8.4 USE OF EOPs The EOPs are to be utilized as a set with the Flow Charts as the
" entering" media. If no automatic or manual scram signal is present, l
i the operator will' utilize his abnormal, annunciator, or normal -
l operating procedures For guidance. l If, at any time, the entry i l condition exists, the operator is directed to utilize'the EOPs.
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 57 OF 7d DOCUMENT TITLE: EMERGENCY OPERATING REVISION:
, PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O l
l 8.5 ,;I OF OPERATOR AIDS Operator aids (such as Flow Charts and Checkoffs) will be used to assist the operator in returning the plant to a controlled condition.
8.5.1 Flow Charts Flow Charts will be used as a job performance aid for immediate operator actions in place of written procedures. They will be
! plastic coated so that a grease pencil or marker can be used to track progress. Reduced, paper copies of Flow Charts can then be marked up to include in a post scram report.
8.5.2 Check Offs The End Path Manuals will have places for operator initials to track position in the procedure, as specified in section 8.3.6.3. I 8.6 EXCEPTIONS l
This procedure, a Writer's Guide for the development of Emergency
- Operating Procedures, should be considered as a guide. Minor i
variations from these requirements are allowed, such as margins less than one-half inch, caution box not precisely. centered, or figure name above the figure vice below. All procedures or revisions written in accordance with this procedure must be individually reviewed and' approved by the Plant Review Board, thus >
- ensuring that exceptions will be reasonable.
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. _ . =- .
AITAChMENT 1 PAGE 58 0F 70 GEORGIA POWEN CUMPANY ATTACHMtNT
. HATCH NUCLEAH PLANT PAGE 1 OF 1 OUCUMENT TITLE: EMEHGENCY UPEHATING HEV1dIUN:
! PROCEDUREd PLANT-SPECIFIC WRITEH'S GUIDE O t
ATTACHMENT TITLE:
RELATIONSHIP OF E0Ps TO UTHER PLANT PROCEDURES SO i.
1 4
/
GM/SV AB
\
f 1 AR i
l' SO -
SYSTEM OPERATING PROCEDURES i
Ad - ABNORMAL UPERATING PHUCEDURES 1
EM -
EMERGENCY OPERATING PROCEDURES I
l AR -
ANNUNCIATOR RE5PONSE PHUCEDURES GM/SV- GENERAL MAINTENANCE OR SURVEILLANCE PHOCEDUHES ..
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ATTHCHMENT 2 .
PAGE 59 UF 70 GE0HGIA POWEn GUMPMNY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 UF 1 DUCUMENT TITLE: EMENGENCY UPEHATING HEVib10N:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O ~
ATTACHMtNT TITLE: ENiMY CUNullIUNd ANU INTEHHELAT1UNbHIP OF EUP FLOW CHARTS AND ENU PATH MANUALS
! REACTOR FAILURE '0SS OF ABNORMALLY TRANSIENTS OF VITAL VITAL POWER HIGH EQUIPMENT SOURCE HADIATION
, LOSS OF EXCESSIVE COOLANT HA010 ACTIVE HELEASE AUTOMATIC I LOSS OF 08 MALFUNCTION CONTAINMENT REQUIRED OF REACTIVITY i
INTEGRITY MANUAL CONTROL SYSTEM SCRAM i
V IMMEDIATE ACTION
- FLOW CHARTS
- - SHORT TIME RESPONSE l END PATH MANUALS
- LONG TIME HESPONSE i
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ATTACHMENl 3 PAGE 60 0F 7 _ _ _ _ ,
GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 0F 2 DOCUMENT TITLE: EMERGtNCY OPERATING REVISION:
fROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O ATTACHMENT TITLE:
TITLE PAGE FORMAT FOR E0P'S INSTRUCTIONS Block 1 - Procedure page identifier: Page (what) of (how many)
Block 2 - Type of procedure Block 3 - Complete procedure title Block 4 - Procedure number
, Block 5 - Revision Number (0 for original; 1,2,3, etc. for revisions) 1 (2 locations)
Block 6 - Safety related classification i
Block 7 - Approved date Block 8 - Effective date Block 9 - Expiration date. If not applicable, enter N/A Block 10 - General description of the revision Block 11 - Responsible department manager's signature Block 12 - Date approved by department manager Block 13 - General Manager's signature, indicating approval. If not applicable, enter N/A Block 14 - Date approved. If not applicable, enter N/A Block 15 - Path number and section number -
i e
MTIMCHMENT 3 PAGE 61 0F 70 ULOHGIA P0ndR CUMPANY MTTACHMENT HATCH NUCLEAR PLANT PAGE 2 UF 2 00CUMENT TITLE: EMERGENCY UPbHATING HEVibl0N:
PROCEDURES PLANT-SPECIFIC WRITEH'S GUIDE O MITACHMENT TATLE:
TITLE PAGE FORMAT FOR E0P'S C J E PL T P ACE OF b DOCUMEN T IVFE g DOCUMENT NUMBE OCCUME N T TI TLE : g Mty&>4bNs g
END P ATH M ANU AL , SE CTION h
$AFE f Y RELATED APPROWD DATE '
NON.$AFETY REL ATED EFFECT!W DATE: @
EXPIR Af!ON DATE @
RE V. APPROW D APPRO W D
. f!CN DE Pt. MCR. DAtt OgN. MCR. DA tt Nd5 CESC$R @ @ O @
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ATTACHMENT 4
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PAGE 62 UF 70 GLUHGIA PUWEH CUMPaNY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 UF 1 UUCUMENI TITLE: tMthutNCY UPthailNb ntVISTUN:
PHUCEUUHEb PLANT-bPECIFlC WHITER'S GUIDE O ATTACFiRENT 7TTEt:
DESIGNATIUN AND NUMbEHING UF FLuW CHANTd HtVib10N UAIL APPHUVtu tsY UATt
_UtPT. MLH.
__G E N . Muk.
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HIIACHMtNT 5 PAGE 63 OF 7~0 GEORGIA PUWEK CUMPANY ATTACHMtNT HATCH NUCLEAR PLANT PAGE 1 0F 1 DOCUMENT TITLt: EMERGENCY UPERATING REVIbI0N:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O ATTMCHMENT TITLE:
FLOW CHART LOGIC SYMBOLS SYMBOL USED FOR KEY AND PATH SPECIFIC PARAMETERS DECISION SYMBOL ACTION STEP SYMBOL i (SEQUENCE SENSITIVE)
L J INFORMATION SYMBOL ACTION STEP SYMBOL >
(SEQUENCE INSENSITIVE)
- f ] '
- hh!kk)*h$!Ob* PATH TO END PATH k j PATH T0 2O I PATH I I I I
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HIIALhMENT 6 PAGE 64 OF 7'O GEOHGIA PUWEK CUMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 0F 1 DOCUMENT TITLE: EMERGENCY UPtHHilNG HEVib10N:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O ATTACHMENT TITLE: EXAMPLE DECiblON THEE UTILIZING STANDARD LOGIC SYMBOLS d 1 I 2 1 3 ) 4 L A ,
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AliACnMENT 7 PAGE 65 UF 70 GbuRGIA POWEH CuMPANY HTTHLHMENT HATCH NUCLEAR PLANT PAGE 1 0F 1 DUCUMENT TITLE: LMtHGLNCY UPEHHIING HEVib10N:
PROCEDUHES PLANT-SPECIFIC WHITEH'5 GUIDE O ATTACHMENT IITLL:
EXAMPLE DUAL COLUMN PAGE FORMAT __
Left hand column
-basic action sequence
- STEP ACTION / EXPECTED RESPONSE NUT RESPONSE OBTAINED Right hand colur
-contingencies CAUTION: and transitions MONITUK PanAMETERS CLOSELY Caution -
critical and
' precautionary information 1.0 Check RCS Average Temperature
- a. Temperature - DECHEASING a. Dump steam to F 1. Manually open condenser steam dump valves
- b. Temperature - less than of
- 1. Verify feedwater flow control valves CLOSED c. Stop dumping
- c. Temperature - STABILIZES steam. IF qu,, Contingency at of cooldown action when continues, THEN expected respont close main not obtained steamline valve 2.0 Establish AFW Flows
- a. Start AFW. pumps Transition to
- b. Aligr. AFW valves -another guide 11r.
OPEN or CLOSE
[ number ano titla 1 viiri fie d , THEN go to FR-H-1. LUSS OF SECONDARY HEAT SINK Logic statementt 3.0 Verify all control , emphasized rods fully inserted IF two or more Ar "' IF..THEN control rods NOT fully inserteo, THEN emergency Dorate 5 ppm for each control rod not fully inserted
ATTACHMENT 8 PAGE 66 OF 76
- GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 1 OF 5 DOCUMENT TITLE: EMERGENCY OPERATING REVISION: ,
PROCEDURES PLANT-SPECIFIC WRITER'S CUIDE O ATTACHMENT TITLE:
SAMPLE ACTION VERB LIST VERB MEANING / APPLICATION Adjust To regulate or bring to a more satisfactory state. EXAMPLE: " Adjust Reactor Water Lovel setpoint to +36 inches".
Align To place a system in proper or desired .
configuration for an intended purpose.
EXAMPLE: " Align CAD vaporized to Re' actor Building" Allow To permit a stated condition to be achieved prior to proceeding. EXAMPLE: " allow discharge pressure to stabilize" Check To perform a physical action which determines the state of a variable or statur of-equipment without directing a change in status. EXAMPLE:
" check for satisfactory lube oil level" I
u_________.____________.______.__
A TTACHMENT 8 PAGE 67 OF 70 GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 2 OF 5 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O ATTACHMENT TITLE:
SAMPLE ACTION VERB LIST VERB MEANING / APPLICATION Close To change the physical position of a mechanical device to the closed position so that it prevents fluid flow or permits passage of electric current.
EXAMPLE: "close valve 2821-F019" Complete To accomplish specific procedural requirements.
EXAMPLE: " complete valve check-off list 3.7.1",
" complete data report QA-1", " complete steps 7 through 9 of Section III" Establish To make arrangements for a stated condition.
EXAMPLE: " establish communication with control room" Isolate To close one or more valves in a system for the purpose of separating or setting apart a complete system or a portion of the system from the rest of the system or plant. EXAMPLE: " isolate interruptible instrument air header by shutting value 2P51-F011" -
-.~ _ _ . . - . . - . - . _ . - -. ._ - - _ . - - - - - . . - .
! 'i ATTACHMENT 8 PAGE 68 0F 70
.; GEORGIA POWER COMPANY ATTACHMENT i - HATCH NUCLEAR PLANT PAGE 3 0F 5 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:
! PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O i ATTACHMENT TITLE:
SAMPLE ACTION VERB LIST i
i VERB MEANING /APPLICATON I
i Inspect To measure, observe, or evaluate a feature or I characteristic for comparison with specified limits; ;
! method of inspection should be included.- EXAMPLE:
. i j " visually inspect for leaks" ,
f i,
Maintain To keep in an existing state. EXAMPLE: " maintain the reactor vessel water ]evel between +15 and +55 i
f inches, with one or more of the following systems...." '
1 !
l I
1 Open To change the physical position of a mechanical i
j device to the open position so that it allows fluid i
flow or prevents passage of electrical current,
- EXAMPLE: "open valve 2821-F016".- Unless i
i specifically directed otherwise, open means fully ;
i
)
open.
.j Place To put in a particular position. EXAMPLE: " place -
f mode switch to Shutdown"
) #
i i
s i i
i
r v ATTACHMENT 8 PAGE 69 OF 7d GEORGIA POWER COMPANY ATTACHMENT HATCH NUCLEAR PLANT PAGE 4 OF 5 DOCUMENT TITLE: EMERGENCY OPENATING REVISION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O ATTACHMENT TITLE:
SAMPLE ACTION VERB LIST UERB MEANING /APPLICATON Record To document specified condition or characteristic.
EXAMPLE: " record discharge pressure" Roduce To cause a parameter to decrease in value. EXAMPLE:
" reduce reactor pressure with bypass valve manual jack" Set To physically adjust to a specified value on adjustable feature. EXAMPLE: " set diesel speed to
.... rpm" Start To energize an electro-mechanical device by manipulation of a start switch or button. EXAMPLE:
" start a second CRD pump" Stop Opposite of start. EXAMPLE: "stop admitting steam by shutting valve 2821-F044" Synchronize To make synchronous in operation. EXAMPLE:
" Synchronize the Diosol Generator to 41600 Bus 2E" l
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ATTACllMENT 8 PAGE 70 0F.7 GEORGIA POWER COMPANY A T T ACitMENT HATCH NUCLEAR PLANT PAGE 5 0F 5 DOCUMENT TITLE: EMERGENCY OPERATING REVISION:
PROCEDURES PLANT-SPECIFIC WRITER'S GUIDE O ATT ACliMENT TITLE:
SAMPLE ACTION VERB LIST UERB MEANING /APPLICATON Throttle To operate a valve in an inter. diate position to obtain a certain flow rate. EXAMPLE: " throttle value 2821-F077 to obtain 2000 lb/hr flow" Trip To manually activate a semi-automatic feature.
EXAMPLE: " trip breaker..."
Vent To permit a gas or liquid confined under pressure to escape at a vent. EXAMPLE: " vent the heat exchanger before placing it in service" Verify To prove to be true, exact, or accurate by observation of a condition or characteristic for comparison with an ori5inal or procedural requirement. EXAMPLE: " verify discharge pressure" i
4
___.______.__.__._________________.__.______________._..____________._________.________._._.._.___.m..
GE0HGIA P0;ER COMPANY
_H_A T CH NU_CL EA_R_ __PL A N T
- DOCUMENT TITLE: E0P IMPLEMENTA TION PLAN FOR PAG _E_1_0F 79 -
REVISION:
EMERGENCY RESPONSE CAPADILITY PROJECT 0 -
HATCH NUCLEAR PLANT EMERGENCY OPERATING PROCEDURES
, PROCEDURES GENERATION PACKAGE ATTACHHENTS: 1) PLANT-SPECIFIC WRITER'S GUIDE .
- 2) PLANT-SPECIFIC TECHNICAL GUIDELINES UNIT 1
- 3) , PLANT-SPECIFIC TECHNICAL GUIDELINES UNIT 2 a
GEORGI 4 POWER COMPANI HATCH NUCLEAR PLANT PAGE ? 0F 29 -
DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR HEVf5IdNt EMECGENCY RESPONSE CAPARILITY PROJECT 0 TABLE OF CONTENTS SECTION PAGE
1.0 INTRODUCTION
...............................".'................. 3 l
2.0 DEFINITIONS..................................'................ 3 1 3.0 I MP L EME N T A T I ON ELEME N T S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 l 3.1 ORGANIZATION OF IMPLEMENTATION ELEMENTS..................... 7 3.2 CREW AND SHIFT POLICY CHARACTERISTICS..................... 8 3.3 PROCEDURESSYSTEMANhNETW0RK.............................10 3.4 TECHNICAL GUIDELINE USE................................... 12 3.5 WRITERS GUIDE FOR E0Ps.................................... 13 3.6. E0P VERIFICATION.......................................... 14 3.7 E0P VALIDAT!0N............................................ 16 3.8 E0P TRAINING.............................................. 17 3.9 REVISION, REVIEW, AND APPROVAL PROCESS.................... 28 l 3.10 E0P CONTR0L.............................................. 28 l 3.11 SUPPORTING DOCUMENTATION CONTR0L......................... 28 l
3.12 EXPERIENCE FEE 00ACK...................................... 29 3.13 UPDATING E0Ps............................................ 29 t
M 5
5 l , .
ULUNUL A VUWtM LUMVANT
- _H A T C H _ N U C L E A R P L A_N _T_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ __ ____P A CE___ 3 0F 29 DOCUMENT TITLE: E0P INPLEMENTAlION PLAN FOR REVISION;
_EMERGENC_Y_ RESPONSE _CAPARILITY_ PROJECT _ 0 l 1.0 Introduction This implementation plan describes the elements of the Hatch l Nuclear Plant program for implementing the new symptom-based Emergency Operating Procedures, based upon the generic guidelines for Emergency Operating Procedures, and addresses the concerns
. Identified in NUREG 0899 and Supplement I to NUREG 0737. These elements were identified and evaluated by the Emergency Operating Procedures Implementation Assistance (EOPIA) Review Group in accordance with the Activity Network described in the E0PI A Prooram Description (!NPO 82-013). The elements presented are not l
to be construed as an exhaustive list and are considered to be generic to most plants and organizations. The elements have been reviewed by Coorgio Power and are presented herein specifically for Hatch Nuclear Plant Units 1 and 2.
i e
This plan also gets as the cover document for the Hatch Procedures l Generation Package reautred by NUREG 0899, section 7.0. A description of the Validation, Verifiention, and Operator Training Programs are contained herein, while the Plant Specific Technical Culdelines and Writer's Guide are attached as separate documents.
2.0 Definitions '
~
! 2.1 Activity Network The system by which products resulting from the COPIA Review Group are developed and reviewed by the representatives of the nucionr industry. ' .
4 0
6 0
GEORGIA P0MER COMPANY
_ HATCH NUCLEAR PLANT _
PAGE 4 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
i
_ EMERGENCY RESPONSE CAPABILITY PROJECT 0 2.2 Emergency Operating Procedures (EOPs) l Plant procedures directing operator actions necessary to mitigate the consequences of transients and accidents that cause plant carameters to exceed reactor protection system setpoints, engineered safety feature setpoints, or other appropriate technical limits. As implemented at Hatch, E0P's will be post-scram procedures, and will be supplemented by Abnormal Operating Procedures for pre-scram emergency conditions.
2.3 E0 PIA Review Group Representatives from the four owners group subcommittees chartered with the development of Emergency Procedure Guidelines (EPGs), as well as representatives from NSSS vendors, and INPO. See the E0 PIA Program (INPO 82-013) for further information.
2.4 Safety Function A safety function is a function specifically required to keep the plant in a safe condition so that public health and safety will not be endangered.
2.5 Event-Oriented E0Ps Event-oriented E0Ps require that the operator diagnose the specific event causing the transient or accident in order to mitigate the conseauences of that transient or accident.
2.6 Symptom-Oriented EOPs Symptom-oriented E0Ps provide the coerator guidance on how to verify the adequacy of critical safety functions and how to restore and maintain these functions when they are degraded.
Symptom-oriented emergency operating procedures are written in a way that the operator need not diagnose an event, such as a LOCA, to maintain a plant in a safe condition.
~
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT _ PAGE 5 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY _ RESPONSE CAPABILITY PROJECT 0 2.7 Writer's Guide The writer's guide provides detailed instructions on how to prepare text and visual aids for Emergency Operating Procedures so that they will be complete, accurate, convenient, and readable to control room personnel. Its recommendations address all aspects of writing these procedures from a human factors standpoint.
2.8 Technical Guidelines Technical guidelines are documents that identify the equipment or systems to be operated and list the steps necessary to mitigate the consequences of transients and accidents'and restore safety functions. Technical guidelines represent the translation of engineering data derived from transient and accident analyses into information presented in such a way that it can be used to write EOPs. There are two types of technical guidelines, as defined below.
2.9 Generic Technical Guidelines Generic technical guidelines are . guidelines prepared .for a group of plants with a similar design.
2.10 Plant-Specific Technical Guidelines (PSTG)
Prepared from the~ Generic Guidelines but' reflecting Hatch Nuclear Plent' Units-l'and 2 p'lant. specific data, limits, operations and systems.- . s. -
s 9 1 q
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.n ' .*7 > 3:-/
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 6 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITIES 0 2.11 HNP Hatch Nuclear Plant 2.12 Verification The process / procedure used to verify that:
- The E0Ps are technically correct and accurately reflect the 4
technical guidelines
- The EOPs are written correctly and accurately reflect the writer's guide requirements
- The controls and instrumentation called out in the E0Ps actually exist and verbatim nomenclature has been used This process will be performed prior to implementation.
2.13 Validation The process / procedure used to determine that:
- The E0Ps are usable in that they can be understood and followed without confusion, delays, errors, etc.
- The operations called out in the E0Ps can be. performed
- The language and level of information presented in the EOPs is compatible with the minimum number, qualification, training, and experience of the operating staff
- There is a high level of assurance that the procedures will M
provide the operator the guidance he needs to mitigate the effects of transients and accidents This process will be performed in parallel with operator training and during EOP development.
GEORGIA POWER COMPANY
( HATCH NUCLEAR PLANT PAGE 7 0F 29.
DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT O 3.0 Implementation Elements 3.1 Organization of Implementation Elements HNP IMPLEMENTATION
- PLAN if V GENERIC HNP SPECIFIC
- TECHNICAL WRITER'S GUIDELINE GUIDE V
HNP SPECIFIC
- TECHNICAL GUIDELINE I r i U if if VERIFICATION WRITE E0Ps OTHER PLANT PROCEDURE PROCEDURE DESCRIPTION CHANGES I
l f if f VERIFICATION y VERIFY E0Ps w6--
PROCEDURE TRAINING
- PROGRAM.
, DESCRIPTION VALIDATION
- Y PROCEDURE TRAINING DESCRIPTION PROGRAM y 1r i f VALIDATION m VALIDATE TRAIN m F ' '
PROCEDURE EOPs OPERATORS I I i'1r IMPLEMENT EOPs AND OTHER PROCEDURE -
CHANGES l
- In Procedures '
Generating Package
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 8 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.2 Crew and Shift Policy Characteristics The scope and structure of the E0Ps must be compatible with the crew and shift staffing levels, the crew and shift composition, and the control room layout.
3.2.1 Control Room Staffing and Division of Responsibilities The division of responsibility and leadership among the control room personnel, differing staff capabilities between shifts, and the turnover in control room shift crews, make the goals of this section difficult to achieve. However, the following guidelines are important to the efficient and accurate development and execution of EOPs, and have been followed to the extent possible.
3.2.2 Division of Responsibility During an emergency, it is vital that the actions of the control room staff be carried out efficiently and accurately. This will be determined in part by the quality of the E0Ps and the training of the operators. However, for the benefit of good procedures and training to be realized, it is important that control room personnel operate as a team with pre-established leadership roles and divisions of responsibility.
~ t i
1
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT _ _
PAGE 9 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.2.3 Sta ffing of the Control Room The number and qualifications of personnel available in the control room will determine the number of secuential actions, concurrent actions and other responsibilities that can be carried out, and the efficiency with which they can be carried out. The following goals have been considered in writing the EOPs.
- Minimizing physical conflicts between personnel (carrying out actions at the same locations at the same time, or crossing paths)
- Avoiding unintentional duplication of tasks by control room perso nn el
- Ensuring that the control room supervisor is able to keep.
up with staff actions and plant status 3.2.4 Consistency Between Staffing and Procedures The E0Ps have been structured so that the number of people required to carry out sequential actions, concurrent actions, and other responsibilities, does not exceed the minimum shift staffing required by the Technical Specifications.
l l
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 10 0F 29 DOCUMENT TlTLE: EOP IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.3 Procedures System and Network E0Ps are but one of many types of procedures within the plant procedures system. Their relationship to other plant procedures is the procedure network-(shown pictorially below).
This network has oeen considered during EOP development to ensure continuity of the E0Ps and other plant procedures.
3.3.1 General Procedure Interaction S0 s
?
SO - System Operating Procedures AB - Abnormal Operating Procedures
'AR - Annunciator Response Procedures GM/SV-General Maintenance or Surveillance Procedures EM - Emergency Operating Procedures
(_
GEORGIA POWER COMPANV HATCH NUCLEAR PLANT PAGE 11 0F 29 DOCUMENT VITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.3.2 E0P Entry Conditions and Interrelationship of E0P Flow Charts and End Path Manuals.
REACTOR FAILURE LOSS OF ABNORMAL TRANSIENTS OF VITAL VITAL POWER HIGH EQUIPMENT SOURCE RADIATION LOSS OF , EXCESSIVE COOLANT RADIOACTIVE RELEASE AUTOMATIC LOSS OF OR MALFUNCTION CONTAINMENT E REQUIRED 4 0F REACTIVITY INTEGRITY MANUAL CONTRnL SYSTEM SCRAM if IMMEDIATE ACTION f
FLOW CHARTS
- SHORT TIME
RESPONSE
~
1 r i END PATH MANUALS j
- LONG TIME
RESPONSE
GEORUIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 12 0F 29' DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.3.3 Existing Event Procedures and EOP Support Procedures A review of existing HNP procedures series 1000, 1100-1700, 1900 and 2000 will be made with the following objectives:
- Identification and development of plant procedure revisions essential to support implementation of the E0Ps
- Identification and review of plant procedures referenced by the E0Ps that must be changed prior to E0P implementation
- Identification and reclassification of existing procedures within the procedure system network 3.4 Technical Guideline Use To effectively use the information provided by technical guidelines, the methodology used to convert this material into EOPs must be adequately detailed in describing how the technical guidelines will be used.
Plant Hatch will use the two types of technical guidelines (generic and plant-specific) as follows:
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e
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 13 0F 29' i DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.4.1 Generic Technical Guidelines Technical guidelines prepared by a group of plants or by owners groups for plants with a similar design. These guidelines, validated and supported by extensive engineering analysis, will be the document from which the plant-specific technical guidelines are derived. The Georgia Power QA Program will be utilized to verify that the plant-specific technical guidelines are true to the generic technical guidelines.
3.4.2 Plant-Specific Technical Guidelines (PSTG)
Technical guidelines will be prepared for Plant Hatch from the generic technical guidelines formulated by the BWR Owners Emergency Procedure Subgroup. These generic guidelines (Revision 3) have been reviewed and approved by the NRC in SER dated November 23, 1983. The Plant-Specific Technical Guideline will be used to develop the E0Ps and other support procedures. This process will be verified and validated per section 3.6 and 3.7.
3.5 Writer's Guide for E0Ps This document is part'.of the Procedures Generation Package, '
prepared in accordance with the guidance provided by INPO and
- NUREG 0899, and will be' controlled as a Hatch procedure 30AC-OPSO4-0.
6
UtOMb H FUWLM LUMPNNY HATCH NUCLEAR PLANT PAGE 14 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.6 E0P Verification E0P Verification will consist of ensuring that the EOF's are technically correct (accurately reflecting the plant-specific technical guidelines), that they are written correctly (accurately reflecting the plant-specific writer's guide requirements), and that controls and instrumentation called out in the E0P's actually exist and verbatim nomenclature has been used. E0P verification will be performed prior to the start of operator training, and will be performed in accordance with supplement 1 of NUREG 0737 (and NUREG 0899 and INPO guidelines for EOP verification as they apply). This process will identify any deviation from the PSTG, and describe any analysis performed to determine the safety significance of the deviation, and provide a technical justification to the plant specific approach, as required. Note that the generic EPG's identify all available BWR equipment, regardless of plant model. The EPG instructions specify that for any equipment so identified, but not existing in the plant of
[ interest, the reference to it should simply be deleted. For example, EPG step RC/L-2 requires the operator to restore and maintain Reactor Water level with one or more of the following systems: condensate / feed, CRD, RCIC, HPCI, HPCS, LPCS, and LPCI.
Plant Hatch does not have a HPCS, and deleting it from the PSTG in '
accordance with EPG instruction on page I-2 (Rev. 3) does not alter the safety significance of the step, and no additional plant unioue analysis is necessary. ,
1 l
I GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT- PAGE 15 0F 29 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION: --;
i EMERGENCY RESPONSE CAPABILITY PROJECT 0 i
Additionally, during the development of the E0P's using the EPG's, plant specific information will be inserted between ;
guideline steps to enable the operator to perform the steps I properly. For example, to feed the Reactor vessel with the
} condensate / feed system following a scram from high power, the '
j startup level control valve needs to be put into service to j ensure that, should an SRV stick open and reactor pressure fall i below the shutoff head of the condensate booster pumps, the ,
i vessel and steam lines will not be flooded, preventing thermal i
shock to the vessel and damage due to water hammer. Therefore, the 5 sps necessary to put the startup level control valve in
! service to meet RC/L-2 will be inserted into the Emergency
- Operating Procedures with step RC/L-2. Since these types of i
j additions do not change the sequence of steps or the intent of 1
j a
the generic EPG's as reflected in the PSTG, additional analysis
- or technical justification need not be provided. The actual
! verification process will be performed by Plant Hatch Shift Technical Advisors, and will be fully documented by writing a Plant Review Board-approved procedure and executing the procedure. This will also support efforts at implementation of 1
l future NRC-approved revisions:to the EPG and subsequent J . .
re-verification of subsequent EOP revisions.
I
- ( i 1
GEORGIA POWER COMPANY -
HATCH NUCLEAR PLANT PAGE 16 0F 29 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 Since verification will be completed prior to initial E0P implementation at Plant Hatch, any discrepancies found during verification will also be completely resolved prior to approval and implementation of Rev 0 of the E0P's. Note that verification is a two-phase process. Phase 1 is performed prior to start of operator training and covers the entire set of E0P's. Phase 2 is the verification of individual revisions entered during training resulting from the validation program.
3.7 EOP Validation E0P Validation will consist of ensuring that the language and 1evel of information presentation in the E0Ps are compatible with the qualifications, training and experience of the operating staff,and that there is a high level of assurance that the procedures will work, i.e., the procedures guide the operator in mitigating transients and accidents. E0P Validation will be performed in parallel with operator training, and will be performed in accordance with supplement 1 of NUREG 0737 (and NUREG 0899 and INPO guidelines for E0P validation as they apply).
An estimated 20 man-weeks will be spent in the Hatch plant-specific simulator, with participation by Hatch STA's and reactor operators, deveJoping and validating the E0P's (utilizing multiple-event scenarios extensively) before operator training begins. This work will be fully documented including a list of scenarios run and significant results. During operator training (approximately 1 year period), ~ many additional man-weeks will be spent in the simulator with evaluation of operator response and l operator feedback included in the validation.
1
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 17 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 Actual plant walk-throughs will be conducted on a case basis to ensure that the simulator represents the plant correctly and that in-plant name plates are used for proper nomenclature of eouipment. Extensive table-top reviews will be performed during development, especially utilizing the STA/ reactor operator member of the development team, and a record of problems and resolution will be kept. Additionally, initial operator training will be in-classroom table-top use of the E0P's, and operator feedback will be recorded. Note that simulator scenarios will be chosen randomly until all possible paths down the E0P Flow Charts are followed, thus ensuring complete coverage.
Documentation will include records of operator comments, changes made as a result, exam results, simulator recurds, and operator simulator performance records, i
3.8 EOP Train'ing -
The following elements will be included in the E0P Training Program:
- Type of operator training (initial, refresher) i
- Method of operator training (simulator, self-study, classroom)
- Operator knowledge and skill-level requirements ,
- Procedure limitations requiring operator decision-makinp
- Training material needed
- Method for operator feedback into the training prcgram and E0P development 1
~1
- Consideration of,the effect on current plant operation while j training operators on * 's not yet in place at the plant '
4
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 18 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.8.1 Course Description 3.8.1.1 Course
Title:
Initial Training Course for Symptomatic Emergency Operating Procedures at Hatch Nuclear Plant.
3.8.1.2
Description:
An introduction to the new concept of Symptomatic Emergency Operating Procedures which are to replace the current Emergency Operating Procedures.
During this course, the background for the new type procedures will be discussed including the events that l 1ed up to the' changes and why it was necessary to make these changes.
The course will be conducted in the classroom and at the simulator.
3.8.1.3 Duration: Approximately 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> 3.8.1.4 Objectives: upon satisfactory completion of this course, the participant will be able to:
- Explain the background that led up to the development of the new procedures and why the change was made from
" Event Based" Procedures to " Symptom Based" Procedures.
- Demonstrate an acceptable level of skill in the use of -
the new procedures during simulated emergency _
conditions.
- Understand basis for and be able to use the various new graphs and limits in the new EOPs.
O O
9
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 19 0F 29.
DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION: l EMERGENCY RESPONSE CAPABILITV PROJECT 0 3.8.1.5 Prerequisites : Should have Reactor Operator (RO) level of knowledge of GE-BWR plant operation for Module 1. Modules must be taken in order given here, since each module assumes the information of previous modules.
3.8.1.6 Participant Eligibility: This course is aporopriate for licensed Reactor Operators (RO), Senior Reactor Operators (SRO), individuals who are in training for an operator's license and other plant personnel who are familiar with plant operat' ion and frequently monitor or review operational events.
3.8.1.7 Materials Required:
- Instructional Handout for this Course
- Chalkboard
- Overhead Projector
- Current HNP P'ocedures r
- New Symptomatic Emergency Operating Procedures Including Flowcharts and End Path Manuals
- Generic Emergency Procedure Guidelines
- HNP Specific Technical Guidelines
- All changed HNP Procedures .
- Appendices to Emergency Procedure Guidelines that _
contain bases.
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EMERGENCY RESPONSE CAPABILTIY PROJECT 0 l
3.8.2 Module 1 BACKGROUND ANS STANDARDS FOR EMERGENCY PROCEDURES ANS 3.2 THREE MILE ISLAND ACCIDENT NRC GUIDANCE FOLLOWING THE TMI ACCIDENT ESSEX CORPORATIONS REVIEW OF TMI BWR (GE) OWNERS' GROUP STUDY QUIZ ,
TIME MODULE -
A hours STUDY -
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> QUIZ -
1/2 hour .
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 21 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.8.3 Module 2 EXISTING EVENT ORIENTED PROCEDURES REVIEW INSTRUCTIONS CURRENTLY USED BY OPERATIONS PERSONNEL PHILOSOPHY OF EMERGENCY INSTRUCTIONS - WHAT ACTUALLY CONSTITUTES AN' EMERGENCY SYMPTOM ORIENTED VERSUS EVENT ORIENTED EMERGENCY INSTRUCTIONS USE OF CURRENT EMERGENCY INSTRUCTION IN THE EVENT OF MULTIPLE FAILURES DISADVANTAGES OF CURRENT EMERGENCY INSTRUCTIONS
SUMMARY
STUDY QUIZ TIME MODULE -
A hoprs STUDY -
I hour QUIZ -
1/2 hour
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 22 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.8.4 Module 3 BWR (GE) OWNERS' GROUP GUIDELINES AND HNP SPECIFIC GUIDELINE INTRODUCTION TO GUIDELINES
- HNP SPECIFIC GUIDELINE
- HNP SPECIFIC GUIDELINE APPENDIX OPERATOR CAUTIONS REACTOR PRESSURE VESSEL CONTROL GUIDELINES PRIMARY CONTAINMENT CONTROL GUIDELINES SECONDARY CONTAINMENT CONTROL GUIDELINES RADI0 ACTIVITY RELEASE CONTROL GUIDELINE CONTINGENCIES
SUMMARY
STUDY QUIZ
~
TIME MODULE -
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> STUDY -
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> QUIZ -
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> I
GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT PAGE 23 0F 29 )
DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.8.5 Module 4 BASES FOR E0P GUIDELINES, CURVES, LIMITS
- BASIS FOR GENERAL CAUTIONS. -
HOW GENERAL CAUTIONS ARE USED
- BASIS FOR SPECIFIC CAUTIONS HOW SPECIFIC CAUTIONS ARE USED
- BASIS FOR GUIDELINE STEPS
- BASIS FOR ALL CURVES AND LIMITS HOW TO READ, INTERPRET AND USE
SUMMARY
- STUDY
- QUIZ TIME MODULE -
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> STUDY -
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> QUIZ -
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> e
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 24 0F 29 l DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION: 1 EMERGENCY RESPONSE CAPABILITY PROJECT 0 l l
3.8.6 Module 5 APPROACH TO BWR OWNERS' GROUP GUIDELINES AND NEW E0Ps FLOWCHARTS END PATH PROCEDURES SYSTEM RECOVERY CONTINGENCIES CONTAINMENT CONTROL GUIDE ANTICIPATED TRANSIENT WITHOUT SCRAM - ATWS HOW EXISTING PROCEDURES ARE TO BE MODIFIED
SUMMARY
STUDY QUIZ TIME MODULE - 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />
~
i STUDY -
A hours QUIZ -
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> I
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EMERGENCY RESPONSE CAPABILITY PROJECT 0 )
3.8.7 Module 6 USE OF NEW EMERGENCY PROCEDURES
- SYMBOLS USED ON FLOWCHARTS
- GENERAL DESCRIPTION OF THE FIVE FLOWCHARTS - PATHS
- TECHNIQUES FOR CHART AND END PATH PROCEDURE USE
- SINGLE FAILURE EVENT - CHART AND END PATH EXERCISE
- MULTIPLE FAILURE EVENT - CHART AND END PATH EXERCISE
- ADVANTAGES OF NEW PROCEDURES
SUMMARY
- STUDY
- QUIZ TIME l
MODULE -
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> STUDY -
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> QUIZ -
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1
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l GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 26 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.8.8 Module 7 l
SIMULATOR TRAINING USING NEW SYMPTOMATIC EMERGENCY PROCEDURES
- ENTRY CONDITION - REACTOR SCRAM
- SYMPTOMS
- IMMEDIATE ACTIONS
- END PATH MANUALS
- PATH CHANGES
- FLOWCHART EXERCISES
- SINGLE EVENT
- MULTIPLE EVENT
- CONTINGENCIES
- SIMULATOR EVALUATION OF EACH TRAINEE TIME MODULE - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> i
i
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 27 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.8.9 Module 8 COURSE REVIEW
SUMMARY
OF MODIFIED PROCEDURES
SUMMARY
OF FLOW CHARTS
SUMMARY
OF END PATH MANUALS
- RESPONSE TO QUESTIONS / COMMENTS FRnM ATTENDEES THROUGHOUT COURSE
SUMMARY
OF. CURVES / LIMITS
- STUDY
- FINAL EXAM
_ TIME MODULE -
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> STUDY -
I hour i FINAL EXAM -
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 28 0F 29 DOCUMENT TITLE: E0P IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 3.9 Revision, Review and Approval Process Revision, review and approval of the E0Ps and new support procedures will be in accordance with the existing Plant Hatch procedure " Preparation and Control of Procedures" (10AC-MGR03-0).
3.10 E0P Control 3
E0Ps will be controlled within the existing plant document control system and in accordance with the Hatch procedure
" Preparation and Control of Procedures" (10AC-MGR03-0) and
" Emergency Operating Procedures Program (Writer's Guide)"
(30AC-0PSO4-0).
3.11 Supporting Documentation Control The process used to develop the Plant Specific Technical Guidelines will be documented in sufficient detail to show the flow of information from its analytical base to its use in the development of technical guidelines, thereby providing a complete documentation package. The development process includes documentation of the assumptions, references to the results of the analysis, and a description of the actual process used to generate the technical guidelines. This information, to be incorporated into an appendix to the HNP Specific Technical Guideline, will become, along with the guidelines themselves (Generic and Plant Specific), controlled documents subject to the existing plant procedures for control of these types of documents.
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GEORGIA POWER-COMPANY HATCH NUCLEAR PLANT PAGE 29 0F 29 DOCUMENT TITLE: EOP IMPLEMENTATION PLAN FOR REVISION:
EMERGENCY RESPONSE CAPABILITY PROJECT 0 l
3.12 Experience Feedback To ensure that the E0Ps are maintained in a manner that is l
responsive to operating experience, the existing HNP procedures
! will be used to incorporate applicable recommendations derived from review of operating experiences and operator comments. Procedure change recommendations may be provided by plant operators, NSSS vendors, owners groups, other utility groups, industry groups, utilities and the NRC. Plant Hatch assesses these recommendations and makes appropriate changes in accordance with administrative ,
procedures for control of changes to procedures (see section 3.9).
In addition, feedback from operator training and from plant audits will be considered as potential input for procedure modifications.
b 3.12.1 On-Going Evaluation The E0P's will be subject to the normal periodic review of all Hatch procedures in accordance with 10AC-MGR03-0.
3.13 Updating E0P's When changes occur in the plant design, Technical Specifications, Technical Guidelines, Writer's Guide, other plant procedures or control room that will affect the E0Ps, the E0Ps will be revised on a timely basis to reflect these changes. In addition, when j operating and training experience, simulator exercises, control room walk-throughs, or other information indicate that incorrect or, incomplete information exists in the E0Ps, the FO*s should be.
revised on a timely basis. These changes should be reviewed to ensure consistency with the Technical Guidelines and the Writer's
. Guide. Operators.have been encouraged to suggest improvements to E0Ps.
.