ML20235U574
| ML20235U574 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/16/1987 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20235U544 | List: |
| References | |
| NUDOCS 8707220521 | |
| Download: ML20235U574 (45) | |
Text
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ATTACHMENT 1 Proposed Cnanges to Technical Specification Pages Unit 1 Revision Page IV Replace Page VIII Repl ace Page XIV Replace Page 3/4 3-59 Repl ace Page 3/4 3-60 thru Delete Page 3-60a Page 3/4 7-82 Replace Page'3/4 7-83 thru Delete Page 3/4 7-93 Page 3/4 7-94 Replace Page B 3/4 3-4 Replace Page B 3/4 7-6 Replace Page B 3/4 7-7 Replace Page 6-1 Replace Unit 2 Revision Page IV Replace Page VIII Repl ace Page XIV.
Replace Page 3/4 3-59 Replace Page 3/4 3-60 thru Delete Page 3/4 3-60a Page 3/4 7-52 Replace Page 3/4 7-53 thru Delete Page 3/4 7-63 Page 3/4 7-64 Repl ace Page B 3/4 3-4 Replace Page B 3/4 7-6 Repl ace l
Page B 3/4 7-7 Replace Page 6-1 Replace i
8707220521 070716 PDR ADOCK 05000348 P
PDR q
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i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
= = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =
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SECTION-PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE.......................................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R................................
3/4 2-4 3/4.2.3 NUCLEAR E NTHALPY HOT CHANNEL FACT 0R......................... 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RAT 10..........................
,,,,,,,, 3/4 2-11 3/4.2.5 DNB PARAMETERS..............................................
3/4 2-14 l
I 3/4.3 INSTRUMENTATION 3/ 4. 3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.........................
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.............................................
3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring........................................
3/4 3-38 Movabl e Inco re Detect ors.................................... 3/4 3-42 Sei smi c Moni t ori n g I nst rumentati on.......................... 3/4 3-43 Met eorol ogi c al Inst rument at i on..............................
3/4 3-46 Remote Shutdown Instrumentation.............................
3/4 3-49 Chl o ri n e Det ecti on Sy st ems.................................. 3/4 3-52 Hi gh E ne r gy Li ne B re ak S E-n s o rs.............................. 3/4 3-53 Accident Moni tori ng I nst rumentation......................... 3/4 3-56 Fi re Dctcct i on !.;t rument c ti on (Deleted).................... 3/4 3-59 Radioactive Liquid Effluent Monitoring......................
3/4 3-61 Radioacti ve Gaseous Ef fluent Monitori ng..................... 3/4 3-66 3/4.3.4 TURBINE OVERSPEEP PROTECTION...............................
3/4 3-72 FARLEY-UNIT 1 IV AMENDMENT NO.
.P 4
_INDEX LIMITING' CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE.
3/4.7 PLANT SYSTEMS
-3/4.7.1 TURBINE CYCLE Safety Valves...............................................
3/4 7-1
' Au xi l i a ry Fe ed wa t e r Sy s t em.................................. 3/4 7-4 Condensate Storage Tank.....................................
3/4 7-6
-Activity....................................................
3/4 7-7
' Main Steam Li ne I solation Val ves............................ 3/4 7-9 3/4.7.2 STEAM GENER ATOR PRESSURE / TEMPER ATURE LIMITATION............. 3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM..............................
3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM........................................
3/4 7-12 3/4.7.5-n!":R WATER SYSTE" (Deleted)................................
3/4 7-13 3/4.7.6. ULTIMATE HEAT. SINK H+ vee ( D e l e t ed )............................................. 3/4 7-14 Pond........................................................
3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY VENTIL ATION SYSTEM................... 3/4 7-16 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM..........................
3/4 7-18 3/4.7.9 SNUBBERS...................................................,
3/4 7-20 3/4.7.10 SEALED SOURCE CONTAMINATION.................................
3/4 7-80 3/4.7.11 TIME SUPPRESSION SYSTO".S (Deleted)
{
Fi rc Su ppr e;;i cn U;t e r Sy; tem (Del eted)..................... 3/4 7-82 Spr y and/c r Spri r'1 er Sj:t em; (Del eted).................... 3/4 7-85
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S ;t;m; (Deleted).......................................
3/4 7-88 002
/
re 40;; Station; (Deleted)................................
3/4 7-90 rd
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Yard Fi ri Hyd rant; and Hyd rant Mc;c Hou;;; (Deleted)........ 3/4 7-92 I
l 3/4.7.12 f!R: L AJRI ER P h:Td AT IONS (Del eted)......................... 3/4 7-94 i
FARLEY-UNIT 1 Vill AMENDMENT NO.
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'INDEX t
BASES SECTION PAGE l3/4.7 PLANT SYSTEMS.
3/4.7.1 TURBINE CYCLE...............................................
B 3/4 7-1 3/4.7.2' STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.............
B'3/4 7-3
.3/4.7.3 COMPONENT COOLING WATER SYSTEM..............................
B 3/4 7-3
-3/4.7.4 ' SERVICE WATER SYSTEM........................................
B 3/4 7-3 3/4.7.5 R I VE R WAT E R S Y ST EM.......................................... B 3/4 7-3
,.3/4.7.6 ULTIMATE HEAT SINK..........................................
B 3/4 7-4
'3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM...................
B 3/4 7-4 3/4.7.8 ECCS PUMP R0OM EXHAUST AIR FILTRATION SYSTEM................
B 3/4 7-4
'3/4.7.9 SNUBBERS....................................................
B 3/4 7-5 3/4.7.10 SEALED SUURCE CONTAMINATION.................................
B 3/4 7-6 3/4.7.11 T!RC SUrrR:0 ! 0N SY ST:"S (Del eted).......................... B 3/4 7-6 3/4.7.12 TIR SARRI:R PE N:TRATI ONS ( Del et ed )......................... B 3/4 7-7 3/4.8 ELECTRICAL' POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS.........................................
B 3/4 8-1 e
FARLEY-UNIT 1 XIV AMENDMENT NO.
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l PLANT SYSTEMS
- 3/4.7.11 FIRE SUPPRESSION SYSTEMS l^
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This specification deleted. Pages 3/4 7-83 through 3/4 7-93 deleted.
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l F ARLEY-UNIT 1 3/4 7-82 AMENDMENT NO.
PLANT SYSTEMS 3/4.7.12 FIRE BARRIER PENETRATIONS 1
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This specification deleted.
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1 FARLEY-UNIT 1 3/4 7-94 AMENDMENT NO.
.. _...._. _ _ _ _ _ _ _ _ ______ ____ ____ _ ___j
4 INSTRUMENTATION BASES
================================================================================.
3/4.3.3.0 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient -information.is available on selected plant parameters to monitor and assess these variables following an accident.
3/4.3.3.9 FIRE DETECTION INSTRUMENTATION This specification deleted.
3/4.3.3.10 RADIOACTIVE LIQUIU EFFLUENT INSTRUMENTATION The radioactive liquid ef fluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid ef fluents during actual or potential releases of liquid ef fluents. The alarm /
trip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.11 RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm /
trip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this i
instrumentation is consistent with the requirements of General Design Criteria j
60, 63 and 64 of Appendix A to 10 CFR Part 50.
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FARLEY-UNIT 1 B 3/4 3-4 AMEN 0 MENT NO.
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PLANT SYSTEMS BASES Tne service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal I
replaced, spring replaced, in high radiation area, in high temperature area, etc...).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sout ces requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Tnis limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups with surveillance requirements commensurate with the probability of damage to a source in that I
group. Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need 1
not be tested unless they are removed from the shielded mechanism.
l 3/4.7.11 FIRE SUPPRESSION SYSTEMS This specification deleted.
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FARLEY-UNIT 1 B 3/4 7-6 AMENDMENT NO.
L____--_-_-_______.
PLANT SYSTEMS BASES 3/4.7.12 FIRE BARRIER PENETRATIONS This specification deleted, i
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FARLEY-UNIT 1 B 3/4 7-7 AMENDMENT NO.
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1 ADMINISTRATIVE CONTROLS
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6.1 RESPONSIBILITY l
6.1.1 The General Manager - Nuclear Plant shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Supervisor or during his absence from the Control Room a designated individual shall be responsible for the Control Room ccamand function. A management directive to this effect, signed by the Senior Vice President responsible for Nuclear Generation, hereafter referred to as Senior Vice President, shall be reissued on an annual basis.
6.2 ORGANIZATION OFFSITE 1
6.2.1 The offsite organization for facility management and technical support l
shall be as shown on Figure 6.2-1.
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FACILITY STAFF 1
6.2.2 Tne f acility organization shall be as shown on Figure 6.2-2 and:
a.
Each on-duty shif t : hall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor.
In addition, at least one licensed Senior Reactor Operator shall be in the Control Room while the unit is in MODE 1, 2, 3 or 4.
c.
A Health Physics Technician # shall be on site when fuel is in the l
reactor.
1 d.
ALL CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation, e.
(Deleted)
- Tne Health Pnysics Technician may be absent for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected circumstances provided immediate i
action is taken to restore the Health Physics Technician to within the minimum requi rement.
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FARLEY-UNIT 1 6-1 AMENDMENT NO.
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE i
3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1' AXIAL FLUX DIFFERENCE.......................................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R................................
3/42-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACT 0R.........................
3/42-8 f
3/4.2.4 QU ADR ANT P OWE R T I LT R AT I 0................................... 3/4 2-11 3/4.2.5 DNB PARAMETERS..............................................
3/4 2-14 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.........................
3/4 3-1 1
l 3/4.3.2 ENGINEERED SAFE 1Y FEATURE ACTUATION SYSTEM l
INSTRUMENTATION.............................................
3/4 3-15 i
3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring..>.....................................
3/4 3-38 Mo v a b l e I n c o r e D et e ct o r s..................................... 3/4 3-42 Sei smi c Moni tori ng Inst rument at ion..........................
3/4 3-43 Meteorological Instrumentation..............................
3/4 3-46 i
Remote Shutdown Instrumentation.............................
3/4 3-49 Chlorine Detection Systems..................................
3/4 3-52 Hi gh Ene rgy Li ne Break Sensors.............................. 3/4 3-53 Acci dent Moni tori n g I nst rument ation......................... 3/4 3-56 Fi re Octcct i on I,;t rument et i en (Deleted)....................
3/4 3-59
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Radi oacti ve Li qui d Ef fl uent Moni tori ng...................... 3/4 3-61 Radi oacti ve Gaseous Ef fl uent Moni tori ng..................... 3/4 3-66 3/4.3.4 TURBINE OVERSPEED PR0TECTION................................
3/4 3-72 j
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FARLEY-UNIT 2 IV AMENDMENT NO.
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2NDEX-
- LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
~SECTION PAGE-3/4.7 PLANT SYSTEMS
-3/4.7.1-TURBINE CYCLE Safety Va1ves...............................................
3/4. 7-1 1
Auxi l i a ry ' Fee dwate r System.......................,'..........
3/47-4 Condensate Storage Tank.....................................
3/47-6 A c t i v i ty....................................................
3/47-7 Mai n Steam Li ne I sol ati on Va1 ves............................
3/47-9 3/4.7.2 - STE AM GENERATOR PRESSURE / TEMPERATURE LIMITATION.............
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM..............................
3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM.................................'.......
3/4 7-12 3/4.7.5 "4 v e r W:te r Sy;ter ( Del eted )................................
3/4 7-13 i
l 3/4.7.6 ULTIMATE HEAT SINK R4+e*
(Deleted).............................................
3/4 7-14 l
Pond........................................................
3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM...................
3/4 7-16 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM..........................
3/4 7-18 3/4.7.9 SNUBBERS....................................................
3/4 7-20 1
3/4.7.10 SEALED SOURCE CONTAMINATION.................................
3/4 7-50 3/4.7.11 FIRE SUPPRESSION SYSTE"S (Deleted)
Fire Supprc;; ion Water Sy;te: (Del e ted )......................
3/4 7-52 Spr:y :nd/o r Spri nkl er Sy;te=; (Deleted)....................
3/4 7-55 CO2 Sy s t e m; ( D el e te d ).......................................
3/4 7-58 Fire Mc;c St: tion; (Deleted)................................
3/4 7-60 Y:rd F# rc Mydrant; and Hydrant H0;c Hou;c; (Deleted)........
3/4 7-62 3/4.7.12 f! RE CARRIER PENETRATI ONS ( Del eted ).........................
3/4 7-64 l
3/4.7.13 AREA TEMPERATURE MONITORING.................................
3/4 7-64 FARLEY-UNIT 2 VIII AMENDMENT NO.
b n
- lNDEX, BASES
.- -===.........
SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...............................................
B 3/4,7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.............
B 3/4'7-3
~3/4.7.3 COMP 0NENT ' C00 LING WATER SYSTEM........................... e.. B 3/4 7-3.
3/4.7.4 -SERVICE WATER SYSTEM........................................
'3 3/4 7-3 3/4.7.5 RIVER WATER SYSTEM..........................................
B 3/4 7-3 3/4.7.6 ULTIMATE HEAT SINK..........................................
B 3/4 7-4 3/4.7.7 CONTROL' ROOM EMERGENCY. VENTILATION SYSTEM....................
B 3/4 7-4 3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM................
B 3/4 7-4 3/4.7.9 SHUBBERS....................................................
B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION.................................
~ B 3/4 7-6
~
. 3/4.7.11 TIRE SUPPRESSI ON SYST "5 (0el eted).......................... B 3/4 7-6
~
3/4.7.12 f!R: " AP.R: R P:":T R ATI ON S (Del eted )......................... B 3/4 7-7
.g 3/4.7.13 AREA TEMPERATURE MONITORING.................................
B 3/4 7-7 3/4.8 ELECTRICAL POWER' SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS........................................
B 3/4 8-1 3/4.8.3 Electrical Equipment Protection Devices.....................
B 3/4 8-1 l
FARLEY-UNil 2 XIV AMENDMENT NO.
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INSTRUMENTATION l.
3/4.3.3.9 FIRE DETECTION INSTRUMENTATION l
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This specification deleted.
Pages 3/4 3-60 and 3/4 3-60a deleted.
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I FARLEY-UNIT 2 3/4 3-59 AMEN 0 MENT NO.
PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS This specification deleted.
Pages 3/4 7-53 througn 3/4 7-63 deleted.
1
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FARLEY-UNIT 2 3/4 7-62 AMENDMENT NO.
____________-__a
PLANT-SYSTEMS 3/4.7.12 FIRE BARRIER PENETRATIONS This specification deleted.
)
FARLEY-UNIT 2 3/4 7-64 AMENDMENT NO.
I glNSTRUMENTATI0ii BASES 3/4.3.3.8 ' ACCIDENT MONITORING INSTRUMENTATION' The OPERABILITY of the accident monitoring instrumentation ensures that
.sufficent information is available on selected plant parameters-to monitor and.
assess these variables following.an accident.
3/4.3.3.9' FIRE DETECTION INSTRUMENTATION This specification deleted.
3/4.3.3.10 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The' radioactive liquid effluent instrumentation is provided.-to monitor and and control, as applicable,.the releases of radioactive materials in liquid effluents during actual.or potential releases.of liquid effluentt,.The alarm / trip setpoints for these instruments shall be calculated in.accordance with the methods in the ODCM to ensure that the alarm / trip-will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation ~is consistent with the requirements of General Design Criteria 60,'63'and 64.of Appendix A to'10 CFR Part 50.
3/4.3.3.11 'RADI0 ACTIVE GASE0US EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor _
and control, as applicable, the releases of radioactive materials in gaseous
' effluents during actual or potential releases of gaseous'ef fluents. The alarm /
trip setpoints'for these instruments shall be calculated in accordance with the methods in the ODCM to' ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for
. monitoring-(and controlling) the concentrations of potentially explosive gas I
mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria J
60, 63 and 64 'of Appendix A to 10 CFR Part 60.
1 FARLEY-UNIT 2 B 3/4 3-4 AMENDMENT NO.
D
PLANT SYSTEMS'
- i1 i
BASES
.....-=======================a============================================
.The service life of a snubber is evaluated via manufacturer input and Information through' consideration of the snubber service conditions and associated. installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in -high radiation area, in high temperature area, etc...).
The requirement to monitor the snubber service life is included to ensure.that the snubbers periodically undergo a performance evaluation in view
]
of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not Lintended to affect plant operation.
3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources-requiring leak testing, including-alpha emitters, is based on 10 CFR 70.39(c) limits for pl utonium. Tnis limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a' shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless.they are removed from the shielded mechanism.
3/4.7.11 FIRE SUPPRESSION SYSTEMS Tnis specification deleted.
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'FARLEY-UNIT 2 B 3/4 7-6 AMEN 0 MENT NO.
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. P'LANTL SYSTEMS '
BASES L
-3/4.7.12 FIRE ~ BARRIER PENETRATIONS p
.This specification deleted.
- c.,
3/4.7.13 AREA TEMPERATURE MONITORING
'The areaf emperature limitations. ensure that safety-related equipment t
will not be. subjected to temperatures in excess' of their environmental
- qualification temperatures. Exposure' to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY. The temperature limits 4'
- include an allowance for instrument error of 2*F.
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FARLEY-UNIT 2 B 3/4 7-7 AMENDMENT NO.
ADMINISTRATIVE CONTROLS
=
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- _.=========,o
,====.
6.1 RESPONSIBILITY 6.1.1 The General Manager - Nuclear Plant shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Supervisor or during his absence from the Control Room a designated individual shall be responsible for the Control Room command function. A management directive to this effect, signed by the Senior Vice President responsible for Nuclear Generation, hereafter referred to as Senior Vice President, shall be reissued on an annual basis.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 Tne facility organization shall be as shown on Figure 6.2-2 and:
a.
Each on-duty shift shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor.
in addition, at least one licensed Senior Reactor Operator shall be in the Control Room while the unit is in MODE 1, 2, 3 or 4 c.
A Health Physics Technician # shall be on site when fuel is in the reactor.
d.
ALL CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other conccrrent responsibilities during this operation.
e.
(Deleted)
- The Health Physics Technician may be absent for a period of time not to exceed i
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected circumstances provided immediate action is taken to restore the Health Physics Technician to within the minimum requirement.
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l FARLEY-UNIT 2 6-1 AMENDMENT NO.
' Attachment 2 Proposed Changes to Operating License Pages Unit 1 Revision License Condition 2.C(4)
Replace Unit 2 Revision License Condition 2.C(6)
Replace i
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Unit 1 Operating License No. NPF-2 2.C(4) Fire Protection Program Alabama Power Company shall implement 6nd maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility.
Alabama Power Company may make changes to the approved fire protection program without prior approval of the Commission only under the provisions of 10CFR50.59,
~
which will ensure changes made to the fire protection program will not adversely affect the ability to achieve and maintain safe shutdown, i
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Unit 2 Operating License No. NPF-8 2.C(6)
Fire Protection Program Alabama Power Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the f acility. Alabama Power Company may make changes to the approved fire protection program without prior approval of the Commission only under the provisions of 10CFR50.59, which will ensure changes made to the Fire Protection Program will not adversely affect the ability to achieve and maintain safe shutdown.
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- Attachment 3 Significant' Hazards Evaluation Pursuant to 10CFR50.92 for the Proposed Changes to the Fire Protection Technical Specifications and License Conditions Proposed Changes Revise'the fire protection license conditions (license condition 2.C(4) for Unit 1 and 2.C(6) for Unit 2) to provide consistency with the standard fire protection license condition contained in the'NRC Generic Letter 86-10.
' Delete' Unit 1.and Unit 2 fire protection Technical. Specifications 3/4.3.3.9, 3/4'.7.11.1, 3/4.7.11.2, 3/4.'7.11.3, 3/4.7.11.4, 3/4.7.11.5, 3/4.7.12, and associated bases. Delete the minimum Fire Brigade staffing-requirement, Technical Specification 6,2.2(e) for both Units 1 and 2, and revise the footnote for the exception to the Health Physics Technician requirement.
1 Background
Nuclear Regulatory Commission (NRC) Generic Letter 86-10, " Implementation of. Fire Protection Requirements," dated April 24, 1986 requested licensees include, in the FSAR update required by 10CFR50.71(e) that falls due more than 6 months after the date of the letter, the incorporation of the ' fire
)rotection program that has been approved by the NRC, including the fire lazards analysis and. major commitments that form the basis for the. fire protection program. Generic Letter 86-10 -states, "In this manner, the fire protection program, including the systems, the administrative and technical controls, the organization, and other plant features associated with fire protection would be on a consistent status with other plant features described in the FSAR. Also, the provisions of 10CFR50.59 would then apply directly for changes the. licensee desires to make in the fire protection program that would not adversely affect the ability to achieve and maintain safe shutdown." Generic Letter 86-10 also states that, upon completion of this effort, the licensee may apply for an amendment to the operating i
license which amends any current license conditions regarding fire protection and substitutes a standard condition. As a result of the license condition and the placement of the fire protection program in the FSAR where it is controlled via 10CFR50.59, Generic Letter 86-10 states that licensees may request an amendment to delete the technical specifications that will now be unnecessary.
In accordance with Generic Letter 86-10, Alabama Power Company has incorporated the fire protection program into Revision 5 of the FSAR Update as Appendix 98. This appendix documents the evaluation of the Farley Nuclear Plant fire protection program against Appendix A to BTP APCSB 9.5-1 and Appendix R to 10CFR50, and contains the fire hazards analysis and the major commitments that form the basis for the program.
In addition, Sections 9B.2.2.5, 9B.2.3.2, and Attachment C to Appendix 9B of the FSAR i
l Page 2 contain the requirements that replace those that have been proposed for deletion from the Technical Specifications. discusses in detail the replacement of the fire protection Technical Specification requirements with the requirements which now appear in Sections 9B.2.2.5, 98.2.3.2, and Attachment C to Appendix 98 of the FSAR.
1 Analysis Alabama Power Company has reviewed the requirements of 10CiR50.92 as they relate to the proposed changes to the fire protection Technical Specifications and license conditions and considers these changes not to involve a significant' hazards consideration.
In support of this I
conclusion, the following analyses are provided.
1.
Deletion of Technical Specification 3/4.3.3.9, " Fire Detection Instrumentation" and associated bases:
a.
The proposed change will not increase the probability or conse-quences of an accident previously evaluated because the Technical Specification requirements to maintain fire detection instruments-i tion will be replaced with the requirements which appear in I
Attachment C to Appendix 9B to the FSAR. The following changes to these Technical Specification requirements have been made to the requirements which appear in Attachment C to Appendix 9B to the FSAR:
(1) The special reporting requirement was deleted; (2) The reference to Specifications 3.0.3 and 3.0.4 was deleted; and (3) l The lists of fire detection instrumentation were updated to reflect Appendix R commitments. Each of these changes and the appropriate justifications are discussed in Attachment 4.
The operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made l
to the FSAR without prior NRC approval. Changes to the fire I
protection program in the FSAR may be made only if the changes will i
not adversely affect the ability to achieve and maintain safe shutdown. Per Technical Specifications 6.5.1.6(b) and 6.5.1.7(a),
the Plant Operations Review Committee (PORC) will continue to i
i review safety evaluations prepared in accordance with the provisions of 10CFR50.59 for changes to the fire protection program implementation and recommend in writing approval or disapproval of such safety evaluations to the General Manager-Nuclear Plant.
i Additionally, Technical Specification 6.8.1(f) requires that written procedures be established, implemented and maintained covering the fire protection program implementation. These administrative controls will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve an increase in the probability or consequences of an accident or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the
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. 3 Page 3 deletion -of. Technical Specification 3/4.3.3.9 and the placement of the same operability and -surveillance' requirements into the FSAR will not increase the probability or consequences of an accident previously evaluated.
b.
This change does' not create the possibility. of a new or different -
kind of accident from any accident previously evaluated. The requirement to maintain operability of the detection instrumentation and to perform surveillance requirements to ensure 1
l operability of the. detectors is retained; these requirements have simply been moved from the Technical Specifications to the FSAR.
l Plant procedures will be developed from the existing procedures that implement this Technical Specification to provide specific
. instructions for implementing the operability and surveillance requirements. Therefore, the possibility of a new or different-kind of accident from any accident previously evaluated will not be created by this change.
i l
c.
The proposed change will not involve a reduction in the margin of safety because the operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to theFSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made'only.if the changes will not adversely affect the ability to achieve and maintain safe shutdown. Additionally, the administrative controls discussed in item (a) above will ensure that changes to these operability.and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve a reduction in the margin of' safety or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of this technical specification and the placement of the same operability and l
surveillance requirements into the FSAR will not involve a reduction in the margin of safety.
2.
Deletion of Technical Specification 3/4.7.11.1, " Fire Suppression Water System" and associated bases:
a.
The proposed change will not increase the probability or consequences of an accident previously evaluated because the Technical Specification requirements to maintain the fire suppression water system will be replaced with the requirements that appear in Attachment C to Appendix 9B to the FSAR. The following changes to the Technical Specification requirements have j
been made to the requirements which now appear in Attachment C to Appendix 9B to the FSAR:
(1) The special reporting requirement was deleted; (2) The requirement to provide an alternate backup pump or supply in the event that a backup pump or supply is not available was added; (3) The reference to Specifications 3.0.3 and 3.0.4 was i
deleted; and (4) The requirement that each fire pump develop at least 2500 gpm at a system head of 125 psi was revised to specify 4
_ _ _____ _- _A
F
' Attachment 3
'Page 4 at least 2500 gpm at a differential head of 125 psi. Each of these changes'and the appropriate justifications are provided in.
The operability and surveillance requirements will' be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made '
to.the FSAR without prior NRC approval. Changes to the. fire
. protection program in the FSAR may be 'made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown.
Per Technical Specifications 6.5.1.6(b) and 6.5.1.7(a),
the PORC will continue to review safety evaluations prepared in accordance with the provisions of 10CFR50.59 for changes to the fire' protection program implementation and recommend in writing
. approval or disapproval of such safety evaluations' to the General Manager-Nuclear Plant. Additionally, Technical Specification 6.8.1(f) requires that written procedures be established, I
implemented and maintained covering the fire protection program impl ementation. These administrative controls will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not-involve an increase in the probability'or consequences of an accident or adversely affect the ability 'to achieve and maintain safe shutdown. Therefore, the deletion of Technical Specification 3/4.7.11.1 and the placement of the same operability and surveillance requirements into the FSAR will not increase the probability or consequences of an accident previously evaluated.
b.
This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The requirement to maintain operability of the fire suppression water system and to perform surveillance requirements to ensure operability of the system is retained; these requirements have simply been moved from the Technical Specifications to the FSAR.
Plant procedures will be developed from existing procedures that implement this Technical Specification' to provide specific instructions for implementing the operability and surveillance requi rements. Therefore, the possibility of a new or different kind of accident from any accident previously evaluated will not be created by this change.
c.
The proposed change will not involve a reduction in the margin of safety because the operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown. Additionally, the administrative controls discussed in item (a) above will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve a reduction in the a
u Page 5 margin of safety or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of this technical specification and the placement of the same operability and surveillance requirements into the FSAR will not involve;a reduction in the margin of safety.
3.
Deletion of Technical Specification 3/4.7.11.2, " Spray and/or Sprinkler Systems" and associated bases:
a.
The proposed change will not increase the probability or conse-quences of an' accident previously evaluated because the Technical Specification requirements to maintain the spray and/or sprinkler systems will be replaced with the requirements that appear in Attachment C to Appendix 9B to the FSAR. The following changes to the Technical Specification requirements have been made to the requirements which now appear in Attachment C to Appendix 9B to the FSAR:
(1) The-'special reporting requirement was deleted; (2) The reference to Specification 3.0.3 and 3.0.4 was deleted; and (3) The lists of sprinkler systems were updated to reflect Appendix R commitments. Each 'of these' changes and the appropriate justifications are provided in Attachment 4.
The operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accordance' with 10CFR50.59. The provisions of 10CFR50.59 allow changes' to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes will not' adversely affect the ability. to achieve and maintain safe shutdown.- Per Technical Specifications 6.5.1.6(b) and 6.5.1.7(a),
the PORC will continue to review safety evaluations prepared in accordance with the provisions of 10CFR50.59 for changes to the fire protection program implementation and recommend in writing approval or disapproval of such safety evaluations to the General Manager-Nuclear Plant. Additionally, Technical Specification 6.8.1(f) requires that written procedures be established, implemented and maintained covering the fire protection' program implementation. These administrative controls will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve an increase in the probability or consequences of an accident or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of Technical Specification 3/4.7.11.2 and the placement of the same operability and surveillance requirements into the FSAR will not increase the probability or consequences of an accident previously evaluated.
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Attachment'3 Page 6 b.
This changa does not create the possibility of a new or different kind of acc ient from any accident previously evaluated. The requirement ;, maintain operability of the spray and/or sprinkler systems and ts cerform surveillance requirements to ensure operability of Dese systems is retained; these requirements have simply been moved from the Technical Specifications to the FSAR.
Plant procedures will be developed from the existing procedures that implement this Technical Specification to provide specific instructions for implementing the operability and surveillance requirements. Therefore, the possibility of a new or different kind of accident from any accident previously evaluated will not be created by this change, c.
The proposed change will not involve a reduction in the margin of safety. because the operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow.
changes to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown. Additionally, the administrative controls discussed in item (a) above will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve a reduction in the margin of. safety or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of this technical specification and the placement of the same operability and surveillance requirements into the FSAR will not involve a reduction in the margin of safety.
4.
Deletion of Technical Specification 3/4.7.11.3, "CO2 Systems" and associated bases:
a.
The proposed change will not increase the probability or conse-quences of an accident previously evaluated because the Technical Specification requirements to maintain the CO2 systems will be replaced with the requirements that appear in Attachment C to Appendix 9B to the FSAR. The following changes to the Technical Specification requirements have been made to the requirements which now appear in Attachment C to Appendix 9B to the FSAR:
(1) The special' reporting requirement was deleted; and (2) The reference to Specifications 3.0.3 and 3.0.4 was deleted. Each of these changes 1
and the appropriate justifications are provided in Attachment 4.
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Page 7 The operability and surveillance ' requirements will be maintained in l
the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR60.59 allow changes to be made l
to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown. Per Technical Specifications 6.5.1.6(b) and 6.5.1.7(a),
i the PORC will continue to review safety evaluations prepared in accordance with the provisions of 10CFR50.59 for changes to the fire protection program implementation and recommend in writing approval or disapproval of such safety evaluations to the General Manager-Nuclear Plant. Additionally, Technical Specification 6.8.1(f) requires that written procedures be established, implemented and naintained covering the fire protection program implementation. These administrative controls will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve an increase in the probability or consequences of an accident or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of Technical Specification 3/4.7.11.3 and the placement of the same operability and surveillance requirements into the FSAR will not increase the probability or consequences of an accident previously evaluated.
b.
This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The requirement to maintain operability of the CO2 systems and to perform surveillance requirements to ensure operability of the CO2 systems is retained; these requirements have simply been moved from the Technical Specifications to the FSAR.
Plant procedures will be developed from the existing procedures that implement this Technical Specification to provide specific instructions for implementing the operability and surveillance requirements.
Therefore, the possibility of a new or different kind of accident from any accident previously evaluated will not be created by this change.
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Page 8
- c..The proposed change will not involve.a reduction in the margin' of safety beciuse the operability and surveillance requirements will
)
be maintained,in the FSAR where changes must be evaluated in accor-1 dance with 10CFR50.59. The provisions of 10CFR50.59 allow changes
.I to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown. Additionally, the administrative controls. discussed in item (a) above will ensure. that changes to these operability and surveillance requirements are. performed in accordance with 10CFR50.59 and will not involve 'a reduction. in the margin of safety cr adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of this. technical specification and the placement of the same operability and surveillance requirements into the FSAR will not involve a reduction in the.
margin of safety.
5.. Deletion of Technical Specification 3/4.7.11.4, " Fire Hose Stations" and associated bases:
a.
The proposed change will not increase the probability. or conse-quences of an accident previously evaluated because the Technical Specification requirements to maintain the fire hose stations will be' replaced with the requirements that appear in Attachment C to Appendix 9B to the FSAR. The following changes to the Technical Specification requirements have been made to the requirements which now appear in Attachment C to Appendix 9B to the FSAR:
(1) The special reporting requirement was deleted; and (2) The reference to Specifications 3.0.3 and 3.0.4 was deleted. Each of these changes and the appropriate justifications are provided in Attachment 4.
The' operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes 'will not adversely affect the ability to achieve and maintain safe shutdown.
Per. Technical Specifications 6.5.1.6(b) and 6.5.1.7(a),
the PORC will continue to review safety evaluations prepared 'in accordance with the provisions of 10CFR50.59 for changes to the fire protection program implementation and recommend in writing approval or disapproval of sucn safety evaluations to the General Manager-Nuclear Plant. Additionally, Technical Specification 6.8.1(f) requires that written procedures be established, implemented and maintained covering the fire protection program implementation. These administrative controls will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve an l
Page 9 increase in the probability or consequences oof an accident or adversely affect the ability to achieve and maintain ' safe shutdown. Therefore,' the deletion of Technical Specification 3/4.7.11.4 and the placement of the same operability and
' surveillance requirements into the FSAR will not increase the probability' or consequences of an accident previously evaluated.
b.
This change does not create the' possibility of a new or different-kind of accident from any accident previously evaluated. The requirement to maintain operability of the fire hose stations and to perform surveillance requirements to ensure operability of the fire hose stations is retained; these requiremer.ts have simply been moved from the Technical Specifications to the FSAR.. Plant procedures will be developed from the' existing procedures 'that implenent this Technical Specification to provide specific instructions for implementing the operability and surveillance requirements..Therefore, the possibility of a new or different kind of accident from any accident previously evaluated will not be created by this change.
c.
The proposed change will not involve a reduction.in the margin of safety because the operability and surveillance requirements will be maintained in the FSAR where changes must be ' evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown. Additionally, the administrative controls discussed in item (a) above udll ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve a reduction in the margin of safety or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of this technical specification and the placement of the same operability and surveillance requirements into the FSAR will not involve a reduction in the margin of safety.
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Page 10 6.
Deletion of Technical Specification 3/4.7.11.5, " Yard Fire Hydran^s and Hydrant Hose Houses" and associated bases:
The proposed change will not increase the probability or conse-a.
quences of an accident previously evaluated because the Technical Specification requirements to maintain the yard fire hydrants and hydrant hose houses will be replaced with the requirements that appear in Attachment C to Appendix 9B to the FSAR. The following changes to the Technical Specification requirements have been made to the requirements which now appear in Attachment C to Appendix 9B to the FSAR:
(1) The special reporting requirement was deleted; and (2) The reference to Specifications 3.0.3 and 3.0.4 was deleted. Each of these changes and the appropriate justifications are provided in Attachment 4.
The operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be rcade only if the changes will not adversely affect the ability to achieve and maintain safe shutdown.
Per Technical Specifications 6.5.1.6(b) and 6.5.1.7(a),
the PORC will continue to review safety evaluations prepared in accordance with the provisions of 10CFR50.59 for changes to the fire protection program implementation and recommend in writing approval or disapproval of such safety evaluations to the General Manager-Nuclear Plant. Additionally, Technical Specification 6.8.1(f) requires that written procedures be established, implemented and maintained covering the fire protection program impl ementation. These administrative controls will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve an increase in the probability or consequences of an accident or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of Technical Specification 3/4.7.11.5 and the placement of the same operability and surveillance requirements into the FSAR will not increase the probability or consequences of an accident previously evaluated, b.
This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The requirement to maintain operability of the yard fire hydrants and hydrant hose houses and to perform surveillance requirements to ensure operability of the hydrants and hose houses is retained; these requirements have simply been moved from the Technical Specifications to the FSAR.
Plant procedures will be developed from the existing procedures that implement this Technical Specification to provide specific instructions for implementing the operability and surveillance requirements. Therefore, the possibility of a new or different kind of accident from any accident previously evaluated will not be created by this change.
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i c.
The proposed' change will-not involve a reduction in the margin of safety because the operability and surveillance requirements will be maintained in the FSAR.where changes must be evaluated in accor-dance with 10CFR50.59.- The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC approval.- Changes to the fire protection program in the FSAR may be made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown. Additionally, the administrative controls discussed in i
i item (a) above will ensure that changes to these operability and surveillance requirements are performed in accordance with 1
10CFR50.59 and will not involve a reduction in the margin of safety or adversely affect the ability to achieve and maintain safe shutdown.. Therefore - the deletion of this technical specification and the placement of the same operability and surveillance requirements into the FSAR will not involve a reduction in the margin of safety.
7.
Deletion of Technical Specification 3/4.7.12, " Fire Barrier Penetrations" and associated bases:
a.
The proposed change will not increase the probability or conse-quences of an accident previously evaluated becau e the Technical Specification requirements to maintain the fire barrier penetra-l tions will be replaced with the requirements that appear in h
Attachment C to Appendix 9B to the FSAR. The following changes to i
the Technical Specification requirements have been made to the l
requirements which now appear in Attachment C to Appendix 9B to the FSAR:
(1) The special reporting requirement was deleted; and (2)
The reference to Specifications 3.0.3 and 3.0.4 was deleted. Each l
of these changes and the appropriate justifications are provided in.
The operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes will j
not adversely affect the ability to achieve and maintain safe shutdown.
Per Technical Specifications 6.5.1.6(o) and 6.5.1.7(a),
the PORC will continue to review safety evaluations prepared in accordance with the provisions of 10CFR50.59 for changes to the fire protection program implementation and recomend in writing approval or disapproval of such safety evaluations to the General Manager-Nuclear Plant. Additionally, Technical Specification 6.8.1(f) requires that written procedures be established, implemented and maintained covering the fire protection program impl ementation. These administrative controls will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not involve an increase in the probability or consequences of an accident or adversely affect the ability to achieve and maintain safe n
Page 12 shutdown. Therefore, the deletion of Technical Specification 3/4.7.12 and the placement of the. same operability and surveillance requirements' into the FSAR will not increase the probability or consequences of an accident previously evaluated.
b.
This change does not create the possibility of a new or different kind of. accident from any accident previously evaluated. The requirement to maintain operability of the fire barrier penetra-tions and to perform surveillance requirements to ensure operability of. the penetrations is retained;. these requirements have simply been moved from the Technical Specifications to the FSAR. Plant procedures will be developed from the existing procedures that implement this Technical Specification to provide specific instructions for implementing the operability and surveillance requirements. Therefore, 'the possibility of a new or different kind of accident from any accident previously evaluated will not be created by this change.
c.
The proposed change will not involve.a reduction in the nargin of safety because the operability and surveillance requirements will be maintained in the FSAR where changes must be evaluated in accor-dance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC approval. Changes to the fire protection program in the FSAR may be made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown. Additionally, the administrative controls discussed in item (a) above will ensure that changes to these operability and surveillance requirements are performed in accordance with 10CFR50.59 and will not invcive a reduction in the margin of safety or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of this technical specification and the placement of the same operability and surveillance requirements into the FSAR ud11 not involve a reduction in the margin of safety.
8.
Deletion of the Fire Brigade Minimum Staffing Requirement, Technical Specification 6.2.2(e):
a.
The proposed change will not increase the probability or conse-quences of an accident previously evaluated because the Technical Specification requirements to naintain the Fire Brigade staffing will be replaced by the requirements which are discussed in detail in Section 9B.2.3.2 of Appendix 9B to the FSAR.
This administrative control will be maintained in the FSAR where changes must be evaluated in accordance with 10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC approval.
Changes to the fire protection program in the FSAR may be made only if the changes will not adversely affect the ability to achieve and maintain safe shutdown.
Per Technical Specifications 6.5.1.6(b) and 6.5.1.7(a), the PORC will continue to
I i-Attachment'3 1
Page'13 4
review safety evaluations-prepared in accordance with the
- provisions of 10CFR50.59' for changes to the. fire protection program.
implementation and recommend. in writing approval' or disapproval of such safety evaluations to the General Manager-Nuclear Plant.
Additionally, Technical Specification 6.8.1(f) requires that written procedures' be established,' implemented and maintained covering the fire protection program implementation. These administrative controls will ensure.that changes to this.
requirement are performed in accordance-with 10CFR50.59 and will not involve an increase in the probability or consequences of an -
accident or adversely affect the ability to achieve and maintain safe shutdown. Therefore, the deletion of Technical Specification 6.2.2(e) and the placement of the same requirement into the FSAR will not increase.the probability or consequences. of an accident previously evaluated, b.
This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The I.
requirement to maintain minimum fire brigade staffing is retained; this requirement has simply been moved from the Technical Specifications to the FSAR. Therefore, the possibility of a new or different kind of accident from any accident previously evaluated will not be created by this change.
c.
The proposed change will not-involve a reduction in the margin of safety because this administrative control will be maintained in the FSAR where changes must be evaluated in accordance with l
10CFR50.59. The provisions of 10CFR50.59 allow changes to be made to the FSAR without prior NRC tmproval. Changes to the fire i
i protection program in the FSAk my be made only if the changes will i
not adversely affect the ability to achieve and maintain safe shutdown. Additionally, the Technical Specification administrative 1
controls discussed in item (a) above will ensure that changes to this requirement are performed in accordance with 10CFR50.59 and will not involve a reduction in the margin of safety or adversely l-affect the ability to achieve and maintain safe shutdown.
l Therefore, the deletion of this technical specification and the l
placement of this requirement into the FSAR will not involve a reduction in the margin of safety.
9.
Revision of Minimum Staffing Requirements Footnote on Technical Specification Page 6-1:
a.
The proposed change will not increase the probability or consequences of an accident previously evaluated because the change is an editorial clarification. The footnote provides an exception to the minimum staffing requirements for the fire brigade and the health physics technician. The exception to the minimum staffing requirements for the fire brigade has been replaced by the requirements which are discussed in Section 9B.2.3.2 of Appendix 98 l
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l Attachment' 3 i
Page 14
-to the.FSAR, along the minimum fire brigade staffing requirements.
The changes to the exception to the health physics technician staffing requirements (footnote on.Page 6-1)'are necessary as a result of the. removal of the fire brigade from the footnote. These changes are strictly editorial. Therefore, this proposed change will not increase the probability or consequences of an accident.
previously evaluated.
b.
This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The i
requirements -have been, retained, but partially relocated and L
partially edited. Therefore, the. possibility of a new or different kind of accident -from any accident previously evaluated will not be created by these changes.
The proposed change will not involve a reduction in the margin of c.
safety because the requirements are retained; they have been partially relocated and partially edited. ' Thus, the proposed change will not involve a reduction in the margin of safety.
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- 10. Revision of Unit 1 license condition 2.C(4):
a.
The proposed change will not increase the probability or consequences of an accident previously evaluated. The existing license condition requires all provisions of the approved fire protection program to be maintained in effect, and that any changes which would decrease the effectiveness of the fire protection program receive prior Commission approval. The new license condition requires all provisions of the approved fire protection program to be maintained in effect, and that changes to the fire protection prograt will be made under the provisions of 10CFR50.59 only if the changes will not adversely affect the ability to achieve and maintdin safe shutdown. The new license condition simply changes the criterion by which Alabama Power Company is authorized to make changes to the program without prior NRC approval. This new criterion preserves the ability to achieve and maintain safe shutdown of the plant. The overall objective of the existing fire protection program and license condition is to ensure safe shutdown of the plant. Therefore, the new license condition is consistent with the objective of the existing license condition and NRC Generic Letter 86-10. Consequently, this change will not increase the probability or consequences of an accident previously evaluated.
4 b.
This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The new license condition will ensure that the ability to achieve and l
i maintain safe shutdown is preserved. Since this new license t
condition is consistent with the objective of the old license condition, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
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Page 15 c.
The proposed change will not involve a reduction in the margin of safety., All modifications identified in Tables 1, 2 and 3 of the NRC's Joseph M. Farley Safety Evaluation Report, Fire Protection Review, Unit Nos. I and 2 dated February 12, 1979 have been completed. Administrative control changes and procedure revisions discussed in the February 12, 1979 SER have been' completed and Commission approval 'of design modifications which would allow the
' reactor to be taken to cold shutdown without ' reliance on the cable spreading room or control room was obtained as required by the existing license condition. Therefore, all provisions of acceptance:in the existing license condition have been completed and the only change between the existing license condition and the proposed license condition is the criterion by which Alabama Power Company is authorized to make changes to the approved program. As discussed in item (a) above,'the new license condition is consistent with the objective of.the existing license condition.
Accordingly, this proposed change will not involve a reduction in the margin of safety.
- 11. Revision of Unit 2 license condition 2.C(6):
a.
The proposed' change will not increase the probability or consequences of an' accident previously evaluated. The existing license condition requires all provisions of the approved fire protection program to be maintained in effect, and that any changes which would decrease the effectiveness of the fire protection program receive prior Commission approval.
The new license condition requires all provisions of the approved fire protection program to be maintained in effect, and that changes to the fire protection program will be made under the provisions of 10CFR50.59 only if the changes will not adversely affect the ability to achieve and maintain safe shutdown. The new license condition simply changes the criterion by which Alabama Power Company is authorized to make changes to the program without prior NRC approval.
This new criterion preserves the ability to achieve and maintain safe shutdown of the plant.
The overall objective of the.
existing fire protection program and license condition is to ensure safe shutdown of the plant. Therefore, the new license condition is consistent with the objective of the existing license condition and NRC Generic Letter 86-10. Consequently, this change will not L
increase the probability or consequences of an accident previously evaluated.
b.
This change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The new license condition will ensure that the ability to achieve and maintain safe shutdown is preserved.
Since this new license condition is consistent with the objective of the old license condition, this change will not create the possibility of a new or i
different kind of accident from any accident previously evaluated.
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Page 16 c.
The proposed change will not involve a reduction in the margin of safety. All administrative control changes and procedure revisions discussed in the February 12, 1979 NRC Safety Evaluation Report I
have been implemented. Appendix 9B to the FSAR documents Alabama Power Company's compliance with the fire protection program set forth in Appendix R to 10CFR50 in accordance with the requirements of paragraph 50.48 of 10CFR Part 50. Therefore, the only change between the existing license condition and the proposed license condition is the criterion by which Alabama Power Company is authorized to make changes to the approved program. As discussed in item (a) above, the new license condition is consistent with the objective of the existing license condition. Accordingly, this proposed change will not involve a reduction in the margin of safety.
Conclusion Based upon the analysis provided herein, Alabama Power Company has determined that the proposed changes to the Technical Specifications and license conditions will not increase the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a reduction in a margin of safety. Therefore, Alabama Power Company has determined that these proposed changes meet the requirements of 10CFR50.92(c) and do not involve a significant hazards consideration.
D-65
Discussion of FSAR Requirements Which Replace
~ the Requirements Which Have Been Proposed for Deletion ~ from the Technical Specification The following paragraphs discuss the replacement of each fire protection Technical: Specification with a corresponding requirement which appears in Appendix 9B of the FSAR.
In addition, justification is provided for any changes-I which.were made to the content.of those requirements.
In general, each requirement was given a new format based upon the Technical Specification format but more consistent with the existing FSAR format.. This change _in format has no effect on the technical content of each requirement.
1.
Technical' Specification 3/4.3.3.9, " Fire Detection Instrumentation":
Unit 1 and Unit 2 Specification 3.3.3.9 will be replaced with Operability Requirement 9B.C.1.1 for Unit 1 and 9B.C.8.1 for Unit 2.
These Operability Requirements appear in Attachment C to Appendix _9B to the FSAR. The only changes which were made to the content of these Operability Requirements -
were the deletion of the special reporting requirement (Action Statement b);
the deletion of reference to Technical Specifications 3.0.3 and 3.0.4 (Action Statement c); reference to Specification 4.6.1.5 in Action Statement a was replaced with the list of temperature sensors which should be monitored, and the lists of fire detection instrumentation (Table 9B.C-1 for Unit 1 and Table 9B.C-5 for Unit 2) were updated to reflect Appendix R commi tments.
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The special reporting requirement was deleted on the basis that current Standard Technical Specifications and recent NT0L Technical Specifications I
L no longer require special reports in the event of inoperable fire protection
{
l equipment.
Action Statement c was deleted on the basis that these Operability j
l Requirements are no longer Technical Specification requirements and reference to Specifications 3.0.3 and 3.0.4 is no longer appropriate.
Similarly, reference to Specification 4.6.1.5 is no longer appropriate and so the list of sensors (from Specification 4.6.1.5) was inserted.
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Tables 9B.C-1 and 9B.C-5 were updated to reflect the analyses performed to demonstrate compliance with Section III.G of 10CFR50 Appendix R.
In this.
regard, these tables reflect the fire detection instrumentation required to i
protect safe shutdown equipment and cabling as defined in Appendix 9B of the l
FSAR.
In most cases, rooms were added to these tables. However, the l
following rooms were deleted on the basis that there is either no safe snutdown cabling or equipment located in the rooms or the rooms contain no l
fire hazards which would require detection to protect against the hazards:
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. kttachment' 4 4 '
Page 2 Table 98.C-l' Room / Fire Total Min.
Zone Description Elevation Detection Operable 188*
~ Boric Acid Tanks 121' - 0" 2
1 316 Corridor 139' - 0" 1-1 440,456 Laundry & Drying' 155' - 0" 21 1
Areas Table 98.C-5 Room / Fire Total Min.
Zone Description Elevation Detection Operable 2188*
Boric Acid Tanks 121' - 0" 2
1 2309 Hatch Area 139' - 0" 1
1 Unit'l and Unit 2' Technical Specification Surveillance Requirement 4.3.3.9 will be replaced with Surveillance Requirement 9B.C.1.2 for Unit 1 and 9B.C.8.2 for Unit 2 in Attachment C to Appendix 9B to the FSAR. The only changes that were made to these requirements are the format changes already discussed.
2.
Technical Specification 3/4.7.11.1, " Fire Suppression Water System":
Unit 1 and Unit 2 Specification 3.7.11.1 will be replaced with Operability Requirement 98.C.2.1. for Unit 1 and 9B.C.9.1 for Unit 2 in Attachment C to Appendix 9B to the FSAR. The only changes made to these requirements were the deletion of the special reporting requirement from Action Statements (a) and (b); the addition of the requirement to establish an alternate pump or supply if a backup pump or supply is not available to Action Statement (a);
and deletion of the reference to Technical Specifications 3.0.3 and 3.0.4.
l The deletion of the special reporting requirement is consistent with the current Standard Technical Specifications and recent NT0L Technical Specifications. The requirement in Action Statement (a) to establish an alternate backup pump or supply in the event of an inoperable backup pump or supply is consistent with current Standard Technical Specifications and recent NT0L Technical Specifications. The deletion of the reference to 1
Technical Specifications 3.0.3 and 3.0.4 is based on these Operability j
Requirements no longer being technical specification requirements, and the reference to Specifications 3.0.3 and 3.0.4 is not appropriate.
Unit 1 and Unit 2 Surveillance Requirements 4.7.11.1.1, 4.7.11.1.2, and
)
4.7.11.1.3 will be replaced by Surveillance Requirements 98.C.2.2.A, B and C l
for Unit 1 and 9B.C.9.2. A, B and C for Unit 2, respectively, in Attachment C I
to Appendix 9B to the FSAR. The only change made to these requirements is associated with fire pump testing. At least once per 18 months, it will be These rooms contain only the tanks and no safe shutdown cabling or electrically-actuated equipment which could be affected by a fire in the room.
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kttachment4 Page 3 verified that each pump develops at least 2500 gpm at a differential head of 125 psi as opposed to a system head of 125 psi. NFPA 20 requires a total head across a pump for performance tests to be the differential between the suction head and the discharge head. To be consistent with NFPA 20, these surveillance requirements have been changed to require a differential head, instead of a total system head, for verification of pump operability.
l 3.
Technical Specification 3/4.7.11.2, " Spray and/or Sprinkler Systems":
Unit 1 and Unit 2 Specification 3.7.11.2 will be replaced with Operability Requirement 98,C.3.1 for Unit 1 and 9B.C.10.1 for Unit 2 in Attachment C to Appendix 9B to the FSAR.
The only changes made to these requirements were the deletion of the special reporting requirement and deletion of reference to Technical Specifications 3.0.3 and 3.0.4.
The basis for these changes has been discussed under items 1 and 2 above.
In addition, the lists of sprinkler systems (Table 9B.C-2 for Unit 1 and Table 9B.C-6 for Unit 2) have been updated to reflect the analyses performed to demonstrate compliance with Section III.G of 10CFR50 Appendix R.
In general, sprinkler systems were added to the lists. However, there was one deletion based on the f act that no safe shutdown equipment is located in the room. The following room has been deleted from Table 9B.C-2:
Table 9B.C-2 Room / Fire Sprinkler Zone Description Elevation System 316 North Corridor 139' - 0" 1A-48 Unit 1 and Unit 2 Surveillance Requirement 4.7.11.2 will be replaced with Surveillance Requirements 98.C.3.2 for Unit 1 and 9B.C.10.2 for Unit 2 in Attachment C to Appendix 9B to the FSAR. The only changes that were made to these requirements are the format changes already discussed.
4.
Technical Specification 3/4.7.11.3, "C02 Systems":
Unit 1 and Unit 2 Specification 3.7.11.3 will be replaced with Operability Requirements 9B.C.4.1 for Unit I and 9B.C.11.1 for Unit 2 in Attachment C to Appendix 9B to the FSAR. The only changes made to these requirements were the deletion of the special reporting requirement and deletion of reference to Specifications 3.0.3 and 3.0.4.
The basis for these changes is discussed in items 1 and 2 above.
Unit 1 and Unit 2 Surveillance Requirements 4.7.11.3.1, 4.7.11.3.2 and 4.7.11.3.3 will be replaced with Surveillance Requirements 98.C.4.2.A, B and C for Unit 1 and 9B.C.11.2. A. B and C for Unit 2, respectively, in Attachment C to Appendix 9B to the FSAR. The only changes that were made to these requirements are the format changes already discussed.
I Page 4 5.
Technical Specification 3/4.7.11.4, " Fire Hose Stations":
Unit 1 and Unit 2 Specification 3.7.11.4 will be replaced with Operability i
Requirement 9B.C.5.1 for Unit 1 and 9B.C.12.1 for Unit 2 in Attachment C to Appendix 9B. The only changes made to these requirements were the deletion of the special reporting requirement and deletion of reference to Specifications 3.0.3 and 3.0.4.
The basis for these changes has been discussed in items 1 and 2 above.
Unit 1 and Unit 2 Surveillance Requirement 4.7.11.4 will be replaced with Surveillance Requirement 9B.C.5.2 for Unit 1 and 9B.C.12.2 for Unit 2 in Attachment C to Appendix 9B to the FSAR. The only changes that were made to these requirements are the format changes already discussed.
6.
Technical Specification 3/4.7.11.5, " Yard Fire Hydrants and Hydrant Hose Houses":
l Unit 1 and Unit 2 Specification 3.7.11.5 will be replaced by Operability Requirement 9B.C.6.1 for Unit 1 and 9B.C.13.1 for Unit 2 in Attachment C to Appendix 9B to the FSAR.
The only changes made to these requirements were the deletion of the special reporting requirement and deletion of reference to Specifications 3.0.3 and 3.0.4.
The basis for these changes has been discussed under items 1 and 2 above.
Unit 1 and Unit 2 Surveillance Requirement 4.7.11.5 will be replaced with Surveillance Requirement 9B.C.6.2 for Unit 1 and 9B.C.13.2 for Unit 2 in Attachment C to Appendix 98 to the FSAR. The only changes that were made to these requirements are the format changes already discussed.
7.
Technical Specification 3/4.7.12, " Fire Barrier Penetrations":
Unit I and Unit 2 Specification 3.7.12 will be replaced by Operability Requirement 98.C.7.1 for Unit 1 and 98.C.14.1 for Unit 2 in Attachment C to Appendix 9B to the FSAR. The only changes made to these requirements were the deletion of the special reporting requirement and deletion of reference to Specifications 3.0.3 and 3.0.4.
The basis for these changes has been discussed under items 1 and 2 above.
Unit 1 and Unit 2 Surveillance Requirement 4.7.12 will be replaced by Surveillance Requirement 98.C.7.2 for Unit 1 and 9B.C.14.2 for Unit 2 in Attachment C to Appendix 9B to the FSAR. The only changes that were made to these requirements are the format changes already discussed.
8.
Bases for the foregoing Technical Specifications:
Section 98.2.2.5 of Appendix 9B to the FSAR contains the appropriate
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information from the Technical Specification bases for the requirements which appear in Attachment C to Appendix 9B.
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' Attachment 4 '
Page.5 9.
Technical-Specification 6.2.2(e), " Minimum Staffing Requirements for the Fire Brigade":.
These.' requirements will'.be. replaced by Section 98.2.3.2'of Appendix 9B to the FSAR.. All'. of the requirements of this. Technical Specification.'are included in' Section 98.2.3.2.of. Appendix 9B to the FSAR.
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