ML20065S876
| ML20065S876 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/07/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065S877 | List: |
| References | |
| NUDOCS 9012260135 | |
| Download: ML20065S876 (25) | |
Text
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pa nseg'o, UNITED STATES
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,e NUCLE AR REGULATORY COMMISSION I
I I W ASHINGTON, D. C. 20555 g4
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TENNESSEE VALLEY AUTHORITY D_0CKET NO. 50-327 0
SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 149 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated January 22, 1990, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct),
and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i 9012260135 901207 PDR ADOCK 05000327 P
2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendice. A and B, as revised through Amendment No. 14g, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE tiUCLEAR REGULATORY COMMISSION fmkw
}-
Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance; December 7, 1990
_ -. - _ _ = _ _ _ - _ - _ =.
ATTAUiMENT TO LICENSE AMENDMENT NO.149 t
FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages idertified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment nutter and contain marginal lines indicating the area of change.
Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT i
3/4 3-55 3/4 3-55 3/4 3-56 3/4 3-56 3/4 3-50a 3/4 3-56a l
3/4 3-E7 3/4 3-57 3/4 3-57a 3/4 3-57a B3/4 3-3 B3/4 3-3 B3/4 3-4 B3/4 3-4 l.
B3/4 3-5 l
B3/4 6-4 B3/4 6-4 I
INSTRUMENTATION ACCIDENT HONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The accident monitoring instrementation channels shown in Table 3.3-10 shall be OPERAP' r, APPLICABILITY: H0 DES 1, 2 and 3.
ACTION: As shown in Table 3.3-10
$URVEILLANCE REQUIREMENTS 4.3.3.7 Each accident monitoring instrumentation channel shall be demon-strated OPERABLE:
a.
Every 31 days by performance of a CHANNEL CHECK, and b.
Every 18 months by performance of a CHANNEL CALIBRATION.*
- For containment Arca Radiation Monitors, a CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for range decades above 10R/h and a single calibration check of the detector below 10R/h with either an installed or portable gamma source.
SEQUOYAH - UNIT 1 3/4 3-55 Amendment No. 40, 112. 149
~
y, TABLE 3.3-10 a
mS ACCIDENT MONITORING INSTRUMENTATION i
y.
MINIMUM
+
I i
TOTAL NO.
CHANNELS INSTRUMENT OF CHANNELS REQUIRED ACTION 4
c 2-
- 1. Reactor Coolant'THot (Wide Range) 4(1/RCS Loop) 1/RCS Loop 1
l (Instrument Loops68-001,-024,-043,-065) g j
- 2. Reactor Coolant:.TCold (Wide Range).
4(1/RCS Loop) 1/RCS Loop 1
(Instrument Loops68-018,-041,-060,-083) l
- 3. Containment Pressure (Wide Range) 2 2
1 j
(Instrument Loops-30-310,-311) j
- 4. Containment Pressure (Narrow Range) 2 2
1
[
(Instrument Loops30-044,-045) l R
- 5. Refueling Water Storage Tank Level 2
2 1
(Instrument Loops63-050,-051) l
- 6. Reactor Coolant Pressure (Wide Range) 3 3
2 j
(Instrument Loops68-062,-%6 -%9) c' l
- 7. Pressurizer Level (Wide Range) 3 3
2 (Instrument Loops68-320,-335,-339)
- 8. Steam Line Pressure 2/ steam line 2/ steam line 1
(Instrument Loops 1-002A,-002B,-009A,-0098, l
-020A,-0208,-027A,-0278)
- 9. Steam Generator Level - (Wide Range) 1/ steam generator 1/ steam generator 1
t j
g (Instrument Loops 3-043,-056,-098,-111) h
- 10. Steam Generator Level - (Narrow Range) 2/ steam generator 2/ steam generator 1
g (Instrument Loops 3-039,-042, "52,-055,
-094,-097,-107,-110)
[
- 11. Auxiliary Feedwater g
- a. Flow Rate
-1/ steam generator 1/ steam generator 5
(Instrument Loops 3-163 -155,-147,-170) h b.. Valve Pe:ition Indication 3/ steam generator 3/ steam generator 5
h (Instrument Loops 3-164,-164A,-172,-156,
-156A,-173,-148,-148A,-174,-171,-171A,-175) 3 i
4 TABLE 3.3-10 (Continued) mE i
g ACCIDENT MONITORING INSTRUMENTATION l
5 x
MINIMUM e -
TOTAL NO.
CHANNELS g
INSTRUMENT OF CHANNELS REQUIRED ACTION I
g
[
- 12. Reactor' Coolant System Subcooling Margin 2
2 6
l Monitor (Instrument Loops94-101,-102) l
- 13. Containment Water Level (Wide Range) 2-2 1
l (Instrument Loops63-178,-179)
- 14. In Core Thermocouples 65 1/ core quadrant / train 3
- 15. Reactor Vessel Level Instrumentation 2
2 1
i System (Instrument Loops68-367,-368,
-369,-370,-371,-372)
- 16. Containment Area Radiation Monitors E
- a. Upper Compartment 2
1 4
E (Instrument Loops90-271,-272)
- b. Lower Compartment 2
1 4
(Instrument loops90-273,-274)
[
- 17. Neutron Flux
- a. Source Range 2
2 1
i-
.-(Instrument' Loops 92-5001,-5002) 4' i
E
- b. Intermediate Range 2
2 1
]
{
(Instrument Loops 92-5003,-5004)
E5 i
I g
I
- Source Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.
1.'
4 r
H
.Au+i
.--m..
m.2 m
m
f I
TABLE 3.3-10 (Continued)
ACTION STATEMENTS i
ACTION 1 - NOTE:
Also refer to the applicable action requirements from Tables 3.3-1, 3.3-3, and 3.3-9 since they may contain more restrictive actions.
a.
With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT SHU100WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.-
The provisions of Specification 3.0.4 are not applicable.
i ACTION 2 - NOTE:
Also refer to the applicable action requirements from Tables 3.3-1 since it may contain more restrictive actions.
a.
With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
With the number of channels three less than the minimum channels required, restore one channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d.
The provisions of Specification 3.0.4 are'not applicable.
ACTION 3 -
a.
Wit. the number of channels less than the minimum channels re u red, restore the-inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
The provisions of Specification 3.0.4 are not applicable.
JEQUOYAH - UNIT 1 3/4 3-57 Amendment No. 46,149
-. ~. _ _.,,
TABLE 3.3-10 (Continued)
ACTION STATEMENTS (Continued)
ACTION 4 -
a.
With the number of channels less than the minimum channels required, initiate an alternate method of monitoring containment area radiation within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and either restore the inoperable channel (s) to OPERABLE status within 7 days, or prepare and submit a special report to the Commission pursuant to Specification 6.9.2.1 within 14 days that provides actions taken, cause of the inoperability, and plans and schedule for restorinC the channels to OPERABLE status, l
b.
The provisions of Specification 3.0.4 are not applicable.
)
ACTION 5 - NOTE:
Also refer to the applicable action requirements froF Table 3.3-9 since it may contain more restrictive actions.
a.
With the number of channels on one or more steam l
generators less than the minimum channels required for either flow rate or valve position, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
With the number of channels on one or more steam generators less than the minimum channels required for either flow rate or valve position, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.
The provisions of Specification 3.0.4 are not applicable.
ACTION 6 -
a.
With the number of channels less than the minimum channels required, restore the inoperable channel to OPERABLE status within 7 days or increase by one the minimum shift crew per Table 6.2-1.
The additional shift crew member shall be dedicated to and capable of
. determining the subcooling margin during an accident using existing instrumentation, b.
Nith the number of channels two less than the minimum-channels required, restore at least one-inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or increase by one the minimum shift crew per Table 6.2-1.
The additional shift crew member shall be dedicated to and capable of determining the subcooling margin during an accident using e d sting instrumentation.
c.
The provisions of Specification 3.0.4 are not applicable.
l SEQUOYAH - UNIT 1 3/4 3-57a Amendment No. 112. 149
s_
f*
INSTRUMENTATION O
BASES design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100. All specified measurement ranges represent the minimum ranges of the instruments.
This instrumentation is i
consistent with the recommendations of Regulatory Guide 1.12. " Instrumentation for Earthquakes," April 1974.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the ublic and is consistent with the recommendations of Regulatory Guide 1.23, p'Onsite Meteorological Programs," Feb wy 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMFNTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility and the potential capability for subsequent cold shut-down from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50.
3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.
3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitorirg instrumentation ensures that sufficient information-is available on selecd.ed plant parameters to monitor
.and assess-these variables following an accident.- This capability is consistent i
_ with the recommendations of Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980.
For Sequoyah, the redundant channel capability-for Auxiliary Feedwater (AFW) flow consists of a single AFW flow channel for each Steam Generator with the second channel consisting;of three AFW valve position indicators (two level control valves for the motor driven AFW flowpath and one level control valve
'for the turbine dH ven AFW flowpath) for each steam generator.
Two containment hydrogen monitoring channels are designated as accident monitoring instrumenta-tion (Type A, Category 1) in accordance with Regulatory Guide 1.97.
Operability and Surveillance Requirements for the purpose of accident monitoring is governed by Specification 3.6.4.1 for containment hydrogen monitors.
4 Revised 08/18/87 SEQUOYAH - UNIT 1 B 3/4 3-3 Amendment No. 62, 81. 149
INSTRUMENTATION l
I BASES j
3/4.3.3.8 FIRE DETECTION INSTRUMENTATION l
OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This capability is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas l
1s required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
3/4.3.3.9 This Specification is deleted.
3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The L. ER-ABILITY and use of this in.trumentation is consistent with the requirements for monitoring potentially explosive gas mixtures.
SEQUOYAH - UNIT 1 8 3/4 3-4 Amendment No. 43, 148, 149 Revised 08/18/87 l
d CONTAINMENT SYSTEMS BASES
)
3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit or the hydrogen i
mitigation system, consisting of 68 hydrogen ignitions per unit, is capable of I
controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water and 3) corrosion of metals within containment. These hydrogen control systems are designed to mitigate the effects of an accident as described in Regulatory Guide 1.7,
" Control of Combustible Gas Concentrations in Containment Following a LOCA",
Revision 2 dated November 19#
The hydrogen monitors of Specification 3.6.4.1 are part of the accident monitoring instrumentation in Specification 3.3.3.7 and are designated as Type A, Category 1 in accordance with Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980.
The hydrogen mixing systems are provided to ensure adequate mixing of the
- i containment atmosphere following a LOCA.
This mixing action will prevent localized accumulations of hydrogen from exceeding the flammable limit.
The operability of at least 66 of 68 ignitors in the hydrogen mitigation system will maintain an effective coverage throughout the containment.
This i
system of ignitors will initiate combustion of any significant amount of hydrogen released after a degraded core accident.
This system is to ensure burning in a controlled manner as the hydrogen is released instead of allowing it to be ignited at high concentrations by a random ignition source.
3/4.6.5 ICE CONDENSER Trw requirements associated with each of the components of the ice con-denser ensure that the overall system will be available to provide sufficient pressure suppression capability to limit the containment peak pressure tran-sient to less than 12 psig during LOCA conditions.
3/4.6.5.1 ICE BED The OPERABILITY of the ice bed ensures that the required ice inventory will 1) be distributed evenly through the containment bays, 2) contain suffi-cient boron to preclude dilution of the containment sump following the LOCA and 3) contain sufficient heat removal capability to condense the reactor system volume released during a LOCA.
These conditions are consistent with the assumptions used in the accident analyses.
The mi-imum weight figure-of 1155 pounds of ice per basket contains a 15%
conservative allowance for ice loss through sublimation which is a factor of 15 highet than assumed for the ice condenser design.
The minimum weight i
figure of 2,245,320 pounds of ice also contains an additional 1% conservative allowance to account for systematic error in weighing instruments.
In the Amendment No. 4, 5, 131, 149 SEQUOYAH - UNIT 1 B 3/4 6-4 Revised 08/18/87
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I TEhhESSEE VAL}.,E,Y, Al'THORITY DOCKET NO,._50-328 SEQUOYAHy,UCLEARPLANT,_ UNIT 2 AliENDMENT TO FACILITY OFERATING LICENSE Anendment No.- 135 License No. DFR-79 1.
The Fuc1 cat Rtgblatory. Cctritt. ion (the Comission) has found-that:
A.-
The applicaticn fcr atenda nt hy Tcnnessee Yality Authority (the liccrsce) dated January 22, 1990, con. plies with the standards and reovirenents of the Atoric Erergy Act of 1954, as amended (the Act),
and the Corrission's rules and reEulations set forth in 10 CFR Chapter It B.
The facility will operate in cerformity with the application, the Frovisicns of the Act, and the rules and regulations of the Comission;-
C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby this anendrent can be ccnducttd without endangering the health and sefety of the public, and (ii) that such activities will be conducted in compliarce with the Comission's regulations; D.
The issuance of this amctdrent will nct be inimical to the comon j-defense and security or to the health and safety of the public; and L
E.
The issuarte of this amendment is in accordance with 10 CFR Part 51 of the Cornission's regulations-and all applicable requirements have been satisfied.
V 1
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Accordingly, tbc lictose is an.trded by changes to the Technical Specifications as indicated in ttt. attacht.ient to this lictnse amendt..er.t and paragraph 2.C.(P) of facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical F 7 cificatiot.s contained in Appendices A and E, as rcvised throurn Araendment No.135, are hertby incorporated it, tht.
license.
The lict r.see shall operate the facility in accordance with the Technical @ er.ifications.
2.
This lictr,st ar.er.dr:ent is cffectivc t s cf its date of issuancc.
FOR THL i:UCLEAT REGULATORY C0FFISSION 1
k,,&
. l$
Trcdcrick J. i8 fdon, Dircctor t
Project Directorate 11 a i
Divisicr. of Reactor pro.iects - 1/11 Office of i:oclear Reactor Regulation Attachnient:
Cherges to tFL Technical Specifications Date of issuance: December 7, 1990
l i
ATTACHMENT TO LICENSE AMENDMENT NO. 135 rACILITY OPERATING LICENSE NO. OPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified bv the captioned amendment number and contain marginal lines indicating the area of change. Overleaf and spillover pages which do not har any material being changed by this amendment are marked with an
"** and provided to maintain document completeness, l
REMOVE INSERT 3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57 1
3/4 3-57a 3/4 3-57a 3/4 3-58 3/4 3-58 3/4 3-58a 3/4 3-58a B3/4 3-3 B3/4 3-3 B3/4 3-4 B3/4 3-4*
B3/4 6-3 B3/4 6-3*
B3/4 6-4 B3/4 6-4 B3/4 6-5 B3/4 6-5*
B3/4 6-6 B3/4 6-6*
INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The accident monitoring instrumentation channels shown in (able 3.3-10
-shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
As shown in Table 3.3-10 SURVEILLANCE REQUIREMENTS 4.3.3.7 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE:
a.
Every 31 days by performance of a CHANNEL CHECK, and b.
Every IB months by performance of a CHANNEL CALIBRATION.*
"For Containment Area Radiation Monitors, a CHANNEL CALIBRATION may consist of an electronic calibration of the-channel, not including the detector, for range decades above 10R/h and a single point calibration of the detector below 10R/h with either an installed or portable gamma source.
l SEQUOYAH - UNIT 2 3/4 3-56 Amendment No. 32, 102, 135
n
~
TABLE 3.3-10 ACCIDENT MONITORING INSTRlHENTATION MINIMUM h
TOTAL NO.
CHANNELS m
OF CHANNELS REQUIRED ACTION INSTRUMENT
- 1. Reactor Coolant THot (Wide Range) 4(1/RCS Loop) 1/RCS Loop 1
g (Instrument Loops68-001,-024,-043,-06S) m
- 2. Reactor Coolant TCold (Wide Range) 4(1/RCS Loop) 1/RCS Loop 1
(Instrument Loops68-018,-041,-060,-083)
- 3. Containment Pressure (Wide Range) 2 2
1 (Instrument Loops30-310,-311)
- 4. Containment Pressure (Narrow Range) 2 2
1 (Instrument Loops30-044,-045) q
- 5. Refueling Water Storage Tank Level 2
2 1
(Instrument Loops63-050,-051)
- 6. Reactor Coolant Pressure (Wide Range) 3 3
2 (Instrument Loops68-062,-066,-069) w
- 7. Pressurizer Level (Wide Range) 3 3
2 (Instrument Leops68-320,-335,-339) 2/ steam line 2/ steam line 1
R. Steam Line Pressure l
(Instrument Loops 1-002A,-002B,-009A,-0098, l
-020A,-0208,-027A,-0278)
- 9. Steam Generator Level - (Wide Rarr e) 1/ steam generator 1/ steam generator 1
l p
g (Instruent Loops 3-043,-056,-098,-111) l
- 10. Steam Generator Level - (Narrow Range) 2/ steam generator 2/ steam generator 1
j E
(Instruraent Loops 3-039,-042,-052,-055,
[
-094,-097,-107,-110) 8
- 11. Auxiliary Feedwater w
- a. Flow Rate 1/ steam generator 1/ steam generator 5
(Instrument Loops 3-163,-155,-147,-170) y
- b. Valve Position Indication 3/ steam generator 3/ steam generator 5
(Inftrument Loops 3-164,-164A,-172,-156,
'J"
-156A,-173,-148,-148A,-174,-171,-171A,-175) w
u-TABLE 3.3-10 (Continued)
M ACCIDENT MONITORING INSTRUMENTATION s
MINIMUM
- L TOTAL NO.
CHANNELS OF CHANNELS REQUIRED ACTION INSTRUMENT Z
- 12. Reacter Coolant System Subcooling Margin 2
2 6
ro Monitor (Instrument Loops94-101,-102)
- 13. Containment Water Level (Wide Range) 2 2
1 (Instrument Loops63-178,-179) 65 1/ core quadrant / train 3
- 14. In Core Thermocouples
- 15. Reactor Vessel Level Instrumentation 2
2 1
System (Instrument Loops68-367,-368,
-369,-370,-371,-372)
- 16. Containment Area Radiation Monitors to 2
1 4
h
- a. Upper Compartment (Instrument Loops90-271,-272)
=
2 1
4
- b. Lower Compartment (Instrument Loops90-273,-274)
- 17. Neutron Flux 2
2 1
l
- a. Source Range (Inctrument Loops 92-5001,-5002) 2 2
1
[
- b. Intermediate Range g
(Instrument Loops 92-5003,-5004)
Po
?.
E
- 5ource Range outputs may be disabled above the P-6 (Block of Source Range Reactor Trip) setpoint.
o v,
l
TABLE 3.3-10 (Continued) l t'
ACTION STATEMENTS ACTION 1 - NOTE:
Also refer to the apt
.:able action requirements from Tables 3.3-1, 3.3-3, and 3.3-9 since they maylcontain-more restrictive actions.
a.
With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b.
With the number of channels two less than the minimum channels required, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in 40T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.
The provisions of Specification 3.0.4 are not applicable.
. ACTION 2 - NOTE:
Also refer-to the applicable action requirements from Tables 3.3-1 since it may contain more restrictive
- actions, a.
With the number of channels one less than the minimum channels required, restore the inoperable channel to OPERABLE status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With-the number of channels two less than the minimum channels required, restore at least one inoperable channel _
to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
With the number of channels three less than the minimum channels' required, restore one channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN'within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d.-
The provisions of Specification 2.0.4 are not applicable.
ACTION 3 -
a.
With the number of channels less than.the minimum channels-required, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
t-
.b.
.The provisions of Specification 3.0.4=are not applicable.
L t
SJ0t!0YAH - UNIT 2 3/4 3-58 Amendment No. 38,135
TABLE 3.3-1,0 (Continued)
ACTION STATEMENTS (Continued)
ACTION 4 -
a.-
With the number of channels less than the minimum channels required, initiate an alternate method tf monitoring containment area radiation within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and either restore the inoperable channel (s) to OPERABLE status within 7 days, or prepare and submit a special report to tht: Commission pursuant to Specification 6.9.2.1 within 14 days that provides actions taken, cause of the inoperability, and plans _ and schedule for restoring the channels to OPERABLE status.
b.
The provisions of Specification 3.0.4 are not applicable.
ACTION 5 - NOTE:
Also refer to the applicable action requireents from Table 3.3-9 since it may contain more restrictive
- actions, a.
Wit 1 the number of channels on one or more steam gr.erators less than the minimum channels required for
,ther flow rate or valve position, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
With the number of channels on one or more steam genefators less than the minimum channels required ~for either flow rate or valve position, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at
-least HOT SHUTOOWN within the next ).2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable, ACTION 6=-
a-With the number of channels less than the minimum i
L channels required, restore the inoperable channel to OPERABLE status within 7 days or increase by one the l
minimum shift crew per Table 6.2-1.
The additional shift.
L crew member shall be dedicated to_and capable of determining the subcooling margin during an accident ucing l
existing instrumentation.
(
b.
With the number of channels two less than the minimum channels required, restore at least one troperable channel
.to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or incr*
s 'y one the l
minimum shift crew per Table 6.2 ~i. The o -
t tal_ shift crew member _shall be dedicated to and capab'le of determining the subcooling margin during an accident usin; existing' instrumentation.
c.
The provisions of Specification 3.0.4 are not applicable.
SEQUOYAH - UNIT 2-3/4 3-58a Amendment No. 102, 135
1NSTRUMENTAT10N BASES 3/4.3.3.3 SEISMIC INSTRUMENTATION (Continued) design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100.
All specified measurement ranges represent the minimum ranges of the instruments.
The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes," April 1974.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown it.strumentation ensures that suf-ficient capability is available to permit shutdo m -nd maintenance of HOT STANDBY of the facility and the potential capabii.ty for subsequent cold shut-down from locations outside of the control room.
Ihis capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50.
3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.
3/4.3.3.7 ACCIDENT MONITORING INSTRUMENfATION The OPERABILITY of the accident monitoring instrumentation ensures that suf ficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980.
For Sequoyah, the redundant channel capability for Auxiliary Feedwater (AFW) flow consists of a single AFW flow channel for each Steam Generator with the second channel consisting of three AFW valve position indicators (two level control valves for the motor driven AFW flowpath and one level control valve for the turbine drive AFW flowpath) for each steam generator.
Two containment hydrogen monitoring channels are designated as accident monitoring instrumenta-tion (Type A, Category 1) in accordance with Regulatory Guide 1.97.
Operabil-ity and Surveillance Requirements for the purpose of accident monitoring is governed by Specification 3.6.4.1 for containment hydrogen monitors.
1 Revised 08/18/S' SEQUOYAH - UNIT 2 B 3/4 3-3 Amendment Nos. 35,46,54,72,135
-_.__.._._._.-~.~.m.._
.._m..._
INSTRUMENTATION BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This capability is required 13 order to detect and locate fires in their early stages.- Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that'a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection-capability until the inoperable instrumentation is restored to OPERABILITY.
3/4.3.3.9 This Specification is deleted.
3/4.3.3.10 EXPLOSIVE GAS HONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERA-BILITY and use of this instrumentation is consistent with the requirements for monitoring potentially explosive-gas mixtures.
l.
l I'
l' I-SEQUOYAH - UNIT 2 B 3/4 3-4 Amendment Nos. 35, 46, 134
~ _ __ _
CONTAINMENT SYSTEMS BASES 3/4.6.1.8 EMERGENCY GAS TREATMENT SYSTEM (EGTS)
The OPERABILITY of the EGTS cleanup subsystem ensures that during LOCA conditions, containment vessel leakage into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere.
This requirement is necessary to meet the assumptions used in the accident analyses and limit the site boundary radiation doses to within the limits of 10 CFR 100 during LOCA conditions.
Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the absorbers and HEPA filters.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.6.1.9 CONTAINMENT VENTILATION SYSTEM Use of the containment purge lines is restricted to only one pair (one supply line a.d one exhaust line) of purge system lines at a time to ensure that the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss of coolant accident during purging operations.
The analysis of this accident assumed purging through the largest pair of lines (a 24 inch inlet line and'a 24 inch outlet line), a pre-existing iodine spike in the reactor coolant and four second valve closure times.
l 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment i
depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower contain'
.t leakage rate are
-consistent with the assumptions used in the accident analy>es.
l 3/4.6.2.2 CONTAINMENT COOLING FANS The OPERABILITY of the lower containment vent coolers ensures that ade-quate heat removal capacity is available to provide long-ter.n cooling following a non-LOCA event.
Postaccident use of these coolers ensures containment tem-
- peratures remain within environmental qualification limits for all safety-related equipment required to remain functional.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valm ensures that the containment atmosphere will be isolated from the o m b environment in the l
event of a release of radioactive material to the cce rment atmosphere or I
pressurization of the containment.- Containment isolauon within the time limits specified ensures that the release of radioactive. material to the j
environment will be consistent with the assumptions used in the analyses for a LOCA.
SEQUOYAH - UNIT 2 B 3/4 6-3 Amendment No. 59 i
6 CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit or the hydrogen mitigation system, consisting of 68 hydrogen igniters per unit, is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water and 3) corrosion of metals wi_ thin containment. These hydrogen control systems are designed to mitigate the effects of an accident as described in Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment following a LOCI.," Revision 2, dated November 1978.
The hydrogen monitors of Specification 3.6.4.1 are part of the accident monitoring instrumentation in Specification 3.3.3.7 and are designated as Type A, Category 1 in accordance with Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants, to Assess Plant Conditions During and Following an Accident," Decembe r 1980.
The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA.
This mixing action will prevent localized accumulations of hydrogen from exceeding the flam.:ble limit.
The operability of at least 66 of 68 igniters in the hydrogen control distributed ignition system will maintain an effective coverage throughout the containment.
This system of ignitors will initiate combustion of any signifi-cant amount of hydrogen released after a degraded core accident.
This system is to ensure burning in a controlled manner as the hydrogen is released instead of allowing it to be ignited at high concentrations by a random ignition source.
3/4.6.5 ICE CONDENSER The requirements associated with each of the components of the ice condenser ensure that the overall system will be available to provide sufficient pressure suppression capability to limit the containment peak pressure transient to
- less than 12 psig during LOCA conditions.
3/4.6.5.1 ~ ICE BED The OPERABILITY _ of the. ice bed ensures that the rNuired ice inventory will 1) be_ distributed evenly through the containment bays, 2) contain suffi-cient boron to preclude dilution of the containment sump following the LOCA and 3) contain sufficient heat removal capability to condense the reactor system volume released during a LOCA.
These conditions are consistent with the assumptions used in the accident analyses.
The minimum weight figure of 1155 pounds of ice per basket contains a 15%
conservative allowance -tor ice loss through sublimation which is a factor of
- 15. higher than assumed for the ice condenser design.
The minimum weight figure.of 2,245,320 pounds of ice also contains an additional 1% conservative allowance to account for systematic error in weighing instruments.
In the SEQUOYAH - UNIT 2 8 3/4 6-4 Amendment No. 21, 118, 135
l CONTAINMENT SYSTEMS BASES event that observed sublimation rates are equal to or lower than design predictions after three year, of operation, the minimum ice baskets weight may be adjusted downward.
In addition, the number of ice baskets required to be weighed each 9 months may be reduced after 3 years of operation if such a reduction is supported by observed sublimation data.
3/4.6.5.2 ICE BED TEMPERATURE MONITOPING SYSTEM The OPERABILITY of the ice bed terperature monitoring system ensures that the capability is available for monitoring the ice temperature.
In the event the monitoring system is inoperable, the ACTION requirements provide assurance that the ice bed heat removal capacity will be retained within the specified time limits.
3/4.6.5.3 ICE CONDENSER DOORS The OPERABILITY of the ice condenser doors ensures that these doors will open because of the differential pressure between upper and lower containment resulting from the blowdown of reactor coolant during a LOCA and that the blow-down will be diverted through the ice condenser bays for heat removal and thus containment pressure control.
The requirement that the doors be maintained closed during normal operation ensures that excessive sublimation of the ice will not occur because of warm air intrusion from the lower containment.
3/4.6.5.4 INLET 000R POSITION MONITORING SYSTEM The OPERABILITY of the inlet door position monitoring system ensures that the capability is available for monitoring the individual inlet door position.
In the event the monitoring system is inoperable, the ACTION requirements provide assurance that the ice bed heat removal capacity will be retained within the specified time limits.
3/4.6.5.5 DIVIDER BARRIER PERSONNEL ACCESS DOORS AND EQUIPMENT HATCHES The requirements for the divider barrier personnel access doors and equipment hatches being closed and OPERABLE ensure that a minimum bypass steam flow will occur from the lower to the upper containment compartments during a LOCA.
This condition ensures a diversion of the steam through the ice condenser bays that is consistent with the LOCA analyses.
3/4.6.5.6 CONTAINMENT AIR RETURN FANS The OPERABILITY of the containment air return fans ensures that following a LOCA 1) the containment atmosphere is circulated for cooling by the spray system and 2) the accumulation of hydrogen in localized portions of the contain-ment structure is minimized.
I SEQUOYAH - UNIT 2 B 3/4 6-5 Rev' n 08/18/87 l
.s_
_,. _.. ~..
. CONTAINMENT SYSTEMS.
BASES 3/4.6.5.7 gnd 3/4.6.5.8 FLOOR AND REFUELING CANAL DRAINS The OPERABILITY of the ice condenser floor and refueling canal drains ensures that following a LOCA, the water from the melted ice and containment spray system has access for drainage back'to the containment lower compartment i
and subsequently to the sump.
This condition ensures the availability of the.
l
. water for long term coolirg of the reactor during the post accident phase.
3/4.6.5.9 DIVIDER BARRIER SEAL The requirement for-the divider barrier seal ~ to be OPERABLE ensures that a minimum bypass steam flow will occur from the lower to the upper containment compartments during a LOCA.
This condition ensures a diversion of steam through the ice condenser bays that is consistent with the LOCA analyses.
D 3/4.6.6 VACUUM RELIEF VALVES The OPERABILITY of the primary containment to atmosphere vacuum
- relief valves ensures that the containment internal pressure does not become more negative than.0.1 psid.
This condition'is necessary to prevent exceeding -
the containment design _ limit.for internal vacuum of 0.5 psid.
c e.
l SEQUOYAH -UNIT'2' B 3/4 6-6 Revised 08/18/87
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