ML20207D601
| ML20207D601 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/26/1999 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20207D599 | List: |
| References | |
| NUDOCS 9903100023 | |
| Download: ML20207D601 (16) | |
Text
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ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)
UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE 98 MARKED PAGES I.
AFFECTED PAGE LIST Unit 1 Index Page IX 3/4 7-15 3/4.7-16 B 3/4 7-4 Unit 2 Index Page IX 3/4 7-15 3/4 7-16 B 3/4 7-4 II.
MARKED PAGES See attached.
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9903100023 990226
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PDR ADOCK 05000327 l
P pag l
.a E2-1
INDEX
. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE l Insert l
3/4.7.5 ULTIMATE HEAT SIN
............................... 3/4 7-14 3/4.7.6 FLOOD PROTECTION (DELETED).............................. 3/4 7-15 R65 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.................
3/4 7-17 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM...................
3/4 7-19 3/4.7.9 SNUBBERS ( D E LET E D )........................................ 3 / 4 7 - 21 lR239 3/4.7.10 S EALED SOURCE CONTAMINATION............................... 3 / 4 7-2 9 '
3/4'7.11 FIRE SUPPRESSION SYSTEMS (DELETED)........................
3/4 7-31, R231 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED).......................
3/4 7-41 3/4.8 ELECTRICAL POWER SYSTEMS R65 3/4.8.1 A.C.
SOURCES OPERATING.............................
.................... 3/4 8-1 SHUTDOWN.................
................................. 3/4 8-8 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C.
DISTRIBUTION - OPERATING..............................
3/4 8-9 A.C.
DISTRIBUTION - SHUTDOWN..............................
3/4 8-10 D.C.
DISTRIBUTION - OPERATING.............................
3/4 8-11 D.C.
DISTRIBUTION - SHUTDOWN.............................. 3/4 8-14 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES............................................. 3/4 8-15 i
August 28, 1998 SEQUOYAH.- UNIT 1 IX Amendment No. 61, 227, 235 PI ANT l
SYSTEMS
.3/4.7.6 FLOOD PROTECTION LIMITING CONDITION FOR OPERATION 3.7.6 The flood protection plan shall be ready for implementation to maintai the plant in a safe condition.
APPLICABILITY:
When one or more of the following conditions exist:
a.
heavy rainfall conditions in the east Tennessee watershed, b.
an early warning or alert that a critical combination of -lood and/or high headwater levels may or have developed, c.
an early warning or alert involving Fontana Dam, or d.
recognizable seismic activity in the east Tennes ee region.
ACTION:
a.
With a Stage I flood warning issued initi-e and complete within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> the Stage I flood protection p cedure which shall include being in at least HOT STANDBY within 6 Tours, with a SHUTDOWN MARGIN of at least 5% delta k/k and T,y le s than or equal to 350*F within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
If within 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> following the issuance of a Stage I flood warning communi tions between the TVA Division of Water Resources and t'e Sequoy Nuclear Plant cannot be verified, initiate and complete the St e II flood protection procedure within the following 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
W' a Stage II flood warning issued initiate the Stage II flo d protection plan in time to ensure completion before the p dicted flooding of the site and no later j
than 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> prior t the predicted arrival time of the initial critical flood level (703 ft msl winter and summer).
. R26 i
b.
With a seismic ev nt occurring after a critical combination of flood and/or headwate alerts are issued verify and maintain communications between TVA P er Control Center and the Sequoyah Nuclear Plant j
within 6 hot s or initiate and complete the Stage I flood protection plan withi the following 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
If communications have not been establis >d upon completion of the Stage I flood protection plan initia. and complete the Stage II flood protection plan within the l
follo ing 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
l c.
W a Fontana Dam Alert issued verify and maintain communications etween Fontana Dam and the Sequoyah Nuclear Plant with I hour or initiate and complete the Stage I flood protection plan within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
If communications have not been established upon completion of the Stage I flood protection plan initiate and complete the Stage II flood protection plan within the following 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
Delete December 27, 1982 SEQUOYAH - UNIT 1 3/4 7-15 Amendment No. 22
PLANT SYSTEMS 3/4.7.6 FLOOD PROTECTION LIMITING CONDITION FOR OPERATION (Continued) j d.
With either the Norris, Cherokee, Douglas, Fort Loudon, Fontana, Hiwassee, Apalachia, Blue Ridge or Tellico dam failed seismicall,
t after a critical combination of flood and/or beadwater alerts 1-issued initiate and complete the Stage I floor. protection p n within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
Upon completion of the Stage I flood protectic plan initiate and complete the Stage II flood protection pla within the following 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
Both the Stage I and the Stage flood protection plans will be terminated if it is deter.ned that the I
potential for flooding the site does not exist.
SURVEILLANCE-REQUIREMENTS 4.7.6.1 The water level in the forebay shal be determined at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the water level is less than equal to 693 feet Mean Sea Level R26 USGS datum and at least once per 15 min" es when the water level is above these limits.
)
I 4.7.6.2 Communications between equoyah Nuclear Plant:
a.
and TVA Division o Water Resources shall be maintained every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during heavy ra. all condition in the east Tennessee watershed.
I b.
and TVA Pow Control Center shall be maintained every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> followin. a recognizable seismic event that has occurred when a critic-combination of flood and/or headwater alert is issued.
Ccr - tications shall be maintained until it has been determined that t
potential for flooding the site does not exist.
c.
and Fontana Dam shall be maintained every hour when an alert involving Fontana Dam has been issued by TVA Division of Water Resources.
Delete December 27, 1982 SEQUOYAH - UNIT 1 3/4 7-16 Amendment No. 22
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3 1
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PLANT SYSTEMS
. BASES.
3/4.7.5' ULTIMATE HEAT SINK (UHS) l
.The. limitations on UHS water level and temperature ensure that sufficient R83?
cooling capacity is available-to either 1) prcvide normal cooldown.of the-facility, or 2):to' mitigate the effects of accident conditions within i
acceptable limits.
The limitation on the maximum temperature is based on providing a 30-day.
R12 cooling water' supply to safety related equipment without ( <ceeding their design
-basis temperature and is consistent with the recommendations of Regulatory
?
Guide 1.27, " Ultimate Heat Sink for Nuclear Plants", March 1974.
l
-The limitations on minimum water level are based on providing sufficient flow to the ERCW serviced heat loads af ter a postulated event assum;ng a time-i dependent drawdown of reservoir level.
Flow to the major transient heat' loads R83 (CCS and.CS heat exchangers) is balanced assuming a reservoir level,of elevation 670.
The time-independent heat loads (ESF room coolers, etc.) are i
' balanced assuming a reservoir level of elevation 639.
lBR-10
_3/4.7.6 FLOOD PROTECTION.
[
]
{
/-actionswillbetakenandoperationwillbeterminatedintheeventofflood The requirements for flood protection ensures that facility protective conditions. A f:tage 1 flood warning is issued when the water in the forebay is predicted to exceed 697 feet Mean Sea Level USGS datum during Octobor 1 through April 15,-or.703 Feet Mean Sea Level USGS datum during April 15 through j
\\ September 30.
A Stage II flood warning is issued when the water in the forebay fis predicted to exceed 703 feet Mean Sea Level USGS datum. 'A maximum allowed water level of 703 Mean Sea' Level USGS datum provides sufficient margin to ensure. waves due to high winds cannot disrupt the flood mode preparation. A Stage I~or Stage II flood warning requires the implementation of procedures which include plant shutdown.
Further, in the event of a loss of communications simultaneous with a critical combination flood, headwaters, and/or seismically induced dam failure the' plant will be shutdown and flood on measures impleme 3/4.7.7 CONTROL ROOM' EMERGENCY VENTILATION SYSTEM
)
The OPERABILITY of the control room ventilation system ensures that 1) the-ambient. air temperature does not exceed the allowable temperature for j
. continuous duty rating for the equipment and instrumentation cooled by this system and 2) the. control room will remain habitable for operations personnel during'and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting
,-the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the
- requirements of General Design Criteria 19 of Appendix "A",
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
Amendment No. 8, 79
'SEQUOYAH - UNIT-1~
B 3/4 7-4 September 13, 1996
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i i
INDEX j
l i
' LIMITING COND1TIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS y
i 1
3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM........................
3/4 7-13 3/4.7.5 ULT'. STE HEAT SINK.....................
............. 3/4 7-14 (DELETED). f....
insert 3/4.7.6 FLOOD PROTECTION PLAN
............. 3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATICr1 SYSTEM.............
... 3/4 7-17 l
3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM...................
3/4 7-19 3/4.7.9 SNUBBERS (DELETED).......................................
.3/4 7-21 lR225 3/4.7.10 SEALED SOURCE CONTAMINATION..............................
.3/4 7-41 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED)........
............... 3/4 7-43 j
R218 3/4.7.12 FIRE BARRIER PENETRATIONS (DELETED).........
............. 3/4 7-52 3/4.8 ELECidICAL POWER SYSTEMS i
3/4.8.1 A.C.
SOURCES Operating........................
................... 3/4 8-1 Shutdown..........
........................................ 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS I
A.C. Distribution - Operating............................. 3/4 8-10 A.C.
Distribution - Shutdown.............................. 3/4 8-11 D.C.
Distribution - Operating.............................
3/4 8-12 D.C.
Distribution - Shutdown...........
.................. 3/4 8-15 i
August 28, 1998 SEQUOYAH - UNIT 2 IX Amendment No. 218, 225 1
PLANT SYSTEMS
,3/4.7.6 FLOOD PROTECTION PLAN LIMITING CONDITION FOR OPERATION 3.7.6 The flood protection plan shall be ready for implementation to maint n the plant in a safe condition.
APPLICABILITY: When one or more of the following conditions exist:
a.
heavy rainfall ;onditions in the east Tennessee watershe,
b.
an early warning er alert that a critical combination of flood and/or high headwater levels may or have developed,'
c.
an early warning or alert involving Fontana Dam, or d.
recognizable seismic activity in the east Te lessee region.
ACTION:
a.
With a Stage I flood warning issued i tiate and complete within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> the Stage I flood protecti plan which shall include being in at least HOT STANDBY within 6 ars, with a SHUTDONN MARGIN of at s
least 5% delta k/k and T/ avg ler than or equal to 350*F within the
)
following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
If within J hours following the issuance of a j
Stage I flood warning commun';ations between the TVA Division of 1
Water Resources and the Se oyah Nuclear Plant cannot be verified, initiate and complete the Stage II flood protection procedure within i
the following 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
With a Stage II flood warning issued initiate the Stage II lood protection plan in time to ensure completion before th e predicted flooding of the site and no later l
than 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> pri to the predicted arrival time of the initial R12 critical flood 1 /e1 (703 f t ms1 winter and summer).
b.
With a seism' event occurring after a critical combination of flood and/or hea <ater alerts are issued verify and maintain communications between T'a Power Control Center and the Sequoyah Nuclear Plant within hours or initiate and complete the Stage I flood protection plan v thin the following 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
If communications have not been este _lished upon completion of the Stage I flood protection plan 1
late and complete the Stage II flood protection plan within the allowing 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
Delete December 27, 1982 SEQUOYAH - UNIT 2 3/4 7-15 Amendment No. 12
PLANT SYSTEMS ACTION:
(Continued) c.
With a Fontana Dam Alert issued verify and maintain communications between Fontana Dam and the Sequoyah Nuclear Plant with 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> o initiate and complete the Stage I flood protection plan within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
If communications have not been established upon completion of the Stage I flood prot ection plan initiate an complete the Stage II flood protection plan within the following 17 iours.
d.
With either the Norris, Cherokee, Douglas, Fort Loudon Fontana, Hiwassee, Apalachia, Blue Ridge or Tellico dam failed seismically after a critical combination of flood and/or headwa
>r alerts is issued initiate and complete the Stage I flood pr ection plan within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
Upon completion of the Stage I flood rotection plan initiate and complete the Stage II flood prote ion plan within the following 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
Both the Stage I and the Stage II flood protection plans will be terminted if it ie determined that the potential for flooding the site does not ist.
SURVEILLANCE REQUIREMENTS 4.7.6.1 The water level in the forebay s.all be determined at least once per B hours when the water level is less th=a or equal to 693 feet Mean Sea Level USGS datum and at least once per 15 m utes when the water level is above these R12 limits.
4.7.6.2 Communications between equoyah Nuclear Plant:
c a.
and TVA Division of dater Resources shall be maintained every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during heavy rainfall condition in the east Tennessee watershed.
b.
and TVA Power ontrol Center shall be maintained every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> following a
> cognizable seismic event that has occurred when a critical ccc.bination of flood and/or headwater alert is issued.
Communica lons shall be maintained until it has been determined that the pot itial for flooding the site does not exist, c.
and ontana Dam shall be maintained every hour when an alert in lying Fontana Dam has been issued by TVA Division of Water F : sources.
- Delete December 27, 1982 SEQUOYAH - UNIT 2 3/4 7-16 Amendment No. 12
1 l
PLANT SYSTEMS J
. BASES l
i I
3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink water level and temperature R70 ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
The limitation on maximum temperature is based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guido 1.27, " Ultimate Heac Sink fo-Nuclear Plants", March 1974.
The limitations on minimum sater level are based on providing sufficient flow to the ERCW serviced heat loads after a postulated event assuming a time dependent drawdown of reservoir level.
Flow to the major transient heat loads R70 (CCS and CS heat exchangers) is balanced assuming a reservoir level of el. 670.
The time independent heat loads (ESF room coolers, etc.) are balanced assuming a reservoir level of el. 639.
lBR-ll i
i 3/4.7.6 FLOOD PROTECTION e requirements for flood protection ensures that facility protective actions will be taken and operation will be terminated in the event of flood i
conditions.
A Stage 1 flood warning is issued when the water in the forebay is predicted to exceed 697 feet Mean Sea Level USGS datum during October 1 through April 15, or 703 Feet Mean Sea Level USGS datum during April 15 through September 30.
A Stage II flood warning is issued when the water in the forebay is predicted to exceed'703 feet Mean Sea Level USGS datum. A maximum allowed water level of 703 Mean Sea Level USGS datum provides sufficient margin to ensure waves due to high winds cannot disrupt the flood mode preparation.
A Stage I or Stage II flood warning requires the implementation of procedures I
which include plant shutdown.
Further, in the event of a loss of communications simultaneous with a critical combination flood, headwaters, and/or seismically induced dam failure the plant will be shutdown and flood l
rotection measures implemented.
i l
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that 1 the ambient air temperaturc does not exceed the allowable temperature for Delete continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
1
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l September 13, 1996 j
SEQUOYAH - UNIT 2 B 3/4 7-4 Amendment No. 70 i
l.
ENCLOSURE 3 TENNESSEE VALLEY. AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE 98-08 REVISED PAGES I.
AFFECTED PAGE LIST Unit 1 Index Page IX 3/4 7-15 3/4 7-16 B 3/4 7-4 Unit 2 Index Page IX 3/4 7-15 3/4 7-16 B 3/4 7-4 II.
REVISED PAGES See attached.
i E3-1
i b
)
1 1
INDEX I
l
. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i
SECTION PAGE 3/4.7.5 ULTIMATE HEAT SINK.......................................
3/4 7-14 R65 3/4.7.6 FLOOD PROTECTION (DELETED)................................
3/4 7-15 l
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................. 3/4 7-17 R65 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM..................
3/4 7 '9 i
3/4.7.9 SHUBBERS (DELETED)........................................ 3/4 7-21 lR239
)
3/4,7.10 SEALED SOURCE CONTAMINATION..............................
3/4 7-29 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED)........................ 3/4 7-31 R231 3/4.7.12 FI RE BARRIER PENETRATIONS ' ( DELETED)....................... 3/4 7-41 3/4.8 ELECTRICAL POWER SYSTEMS R65
-r f 3/4.8.1
-L C. SOURCES OPERATING..................................................
3/4 8-1 SHUTD0WN..................................................
3/4 8-8 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING.............................. 3/4 8-9 A.C. DISTRIBUTION - SHUTDOWN............
................ 3/4 8-10 D.C. DISTRIBUTI ON - OPERATING............................ 3 / 4 8-11 1
D.C.
DISTRIBUTION -
SHUTDOWN.............................
3/4 8-34 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES............................................. 3/4 8-15
)
SEQUOYAH - UNIT 1 IX Amendment No. 61, 227, 235,
)
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PLANT SYSTEMS
~ 3/4.7.6: FLOOD PROTECTION i
- LIMITING CONDITIONS FOR OPERATION l
j 3.7.6 This specification is deleted.
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(Pages 3/4 7-15 and 3/4 7-16 are deleted) l e
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i SEQUOYAH - UNIT 1 3/4 7-15 Amendment No. 22, I
1 PLANT SYSTEMS-BASES 3/4.7.5 ULTIMATE HEAT SINK (UHS)
The limitations on UHS water level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the R83 facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
The limitations on the maximum temperature are based on providing a 30 R12 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants", March 1974.
The limitations on minimum water level are based on providing sufficient
~
flow to the ERCW serviced heat loads after a postulated event assuming a time-dependent drawdown of reservoir level.
Flow to the major transient heat loads (CCS and CS heat exchangers) is balanced. assuming a reservoir level of R83 elevation 670.
The time-independent heat loads (ESF room coolers, etc.) are balanced assuming a reservoir level of elevation 639.
lBR-10 3/4.7.6 FLOOD PROTECTION This specification is deleted.
]
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
l t-l i
l i
SEQUOYAH UNIT 1 B 3/4 7-4 Amendment No.
8, 79, i
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.4 ES SENTIAL RAW COOLING WATER SYSTEM....................... 3 / 4 7-13 3/4.7.5 ULTIMATE HEAT SINK........................................ 3/4 7-14 3/4.7.6 FLOOD PROTECTION PLAN (DELETED)........................... 3/4 7-15 l
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................ 3/4 7-17 i
3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM..................
3/4 7-19 3/4.7.9 SNUBBERS (DELETED)........................................ 3/4 7-21 lR225 3/4.7.10 SEALED SOURCE CONTAMINATION..............................
3/4 7-41 3/4.7.11 FIRE SUPPRESSION SYSTEMS (DELETED)........................ 3/4 7-43 R218 3/4.7.12 FIRE RARRIER PENETRATIONS (DELETED)......................
3/4 7-52 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.
SOURCES Operating...........................................
3/4 8-1 Shutdown..................................................
3/4 8-9 3/4.B.2 ONCITE POWER DISTRIBUTION SYSTEMS A.C.
Distribution - Operating.......
.................... 3/4 8-10 A.C. Dis t ribu tion - Shutd own............................. 3 / 4 8-11 D.C.
Distribution - Operating............................
3/4 8-12 D.C. Dis t ribution - Shutdown............................. 3/ 4 8-15 e
i SEQUOYAH - UNIT 2 IX Amendment No. 218, 225,
1 e
i PLANT SYSTEMS 3/4.7.6 FLOOD PROTECTION PLAN LIMITING CONDITION FOR OPERATION l
3.7.6 This specification is delet.ed.
l i
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(Pages 3/4 7-15 and 3/4 7-16 are deleted) i i
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I
)
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SEQUOYAH - UNIT 2 3/4 7-15 Amendment No. 12, i
4
e I
j p1&UT SYSTEMS l
BASES l
3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink water level and temperature
. R70 ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
The limitation on maximum temperature is based on providing a 30 day l
cooling water supply to safety related equipment without exceeding their design basis temperature sind is consistent with the recommendations of Regulatory Guide 1.27,
" Ultimate Heat Sink for Nuclear Plants", March 1974.
The limitations on minimum water level are based on providing sufficient flow to the ERCW serviced heat loads after a postulated event assuming a time dependent drawdown of reservoir level.
Flow to the major transient heat loads R70 (CCS and CS heat exchangers) is balanced assuming a reservoir level of el. 670.
The time independent heat loads (ESF room coolers, etc.) are balanced assuming a reservoir level of el. 639.
lBR-11 3/4.7.6 FLOOD PROTECTION This specification is deleted.
l 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
SEQUOYAH - UNIT 2 B 3/4 7-4 Amendment No. 70,