ML20149H784
| ML20149H784 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/11/1988 |
| From: | Zech G NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20149H758 | List: |
| References | |
| NUDOCS 8802220103 | |
| Download: ML20149H784 (16) | |
Text
d'ps ury'o, UNITED STATES
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g NUCLEAR REG,ULATORY COMMISSION wAssiNa ton. o. c. roess
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0VOYAH NUCLEAR PLANT, UNIT 1 i
AMENDMENT TO FACillTY OPERATING LICENSE Amendment No. 67 License No. OPR-77 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 16, 1987, complies with the standards and I
reouirements of the Atomic Energy Act of 1954, as amended (the Act).
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is, reasonable assurance (i) that the activities authorized by this arrendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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 Comission's regulations and all applicable requirements have been satisfied.
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8802220103 880211 FDR ADOCK 05000327 P
PDR 1
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.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 Appendices A and B, as revised through Amendment No. 67 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 NUCLEAR REGULATORY COMMISSION 4
L Gary lG.Zech, hstant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical i
j Specifications Date of issuance: February 11, 1988 l
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 67 FACILITY OPERATING LICENSE NO. OpR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the Dages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment rurber and contair margiral lines indicating the area of change. Overleaf pagas* are provided to maintain document corpleteress.
PEMOVE INSERT VII VII VIII Vill
- 3/4 6-16a B 3/4 6-3 R 3/4 6-3 8 3/4 6-3a B 3/4 6-3a*
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5.2 ECCS SUBSYSTEMS - T,yg greater than or equal to 350*F.....
3/4 5-5 3/4.5.3 ECCS SUBSYSTEMS - T, g less than 350*F....................
3/4 5-9 3/4.5.4 BORON INJECTION SYSTEM Boron Injection Tank...............
3/4 5-11 Heat Tracing........
3/4 5-12 3/4.5.5 REFUELING WATER STORAGE TANK..............
3/4 5-13 3/4.6 CONTAINMENT SYSTEMS k
3/4.6.1 PRIMARY CONTAINMENT Containment Integrity....
3/4 6-1 Containment Ieakage..........
3/4 6-2 Containment Air Locks................................
3/4 6-7 Internal Pressure....
3/4 6-9 Air Temperature..................
3/4 6-10 Containment Vessel Structural Integrity...
3/4 6-11 Shield Building Structural Integrity.....
3/4 6-12 Emergency Gas Treatxtnt Systen (Cleanup Subsystem)..
3/4 6-13 Containment Ventilation System...
3/4 6-15 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System...
,3/4 6-16 Containment Cooling Fans........................
3/4 6-ISb l
3/4.6.3 CONTAINMENT ISOLATION VALVdS.......................... ' 3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers....................................
3/4 6-24 Electric Hydrogen Recombiners..........
3/4 6-25 SEQUOYAH - UNIT 1 VII Amendment No.67
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS y
SECTION PAGE i
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3/4.6.5 ICE CONDENSER Ice Bed...................................................
3/4 6-26 Ice Bed Temperature Monitoring System.....................
3/4 6-28:
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Ice Condenser 0oors..................................
3/4 6-29 l
t Inlet Door Position Monitoring System.....................
3/4 6-31 Divider Barrier Personnel Access Doors and l
Equipment Hatches.......................................
.3/4 6-32 i
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Containment Air Return Fans...............................
3/4 6-33 I
l Floor Drains...
3/4 6-34 j
Refueling Canal 0 rains....................................
3/4 6-35 i
l Divider Barrier Sea 1......................................
3/4 6-36 3/4.6.6 VACUUM RELIEF VALVES......................................
3/4 6-38 3/4.7 PLANT SYSTEMS 3/4. 7. K TL'RBINE CYCLE s
t e Safety Va1ves.............................................
3/4 7-1 y
Auxiliaey Feedwater System................................
3/4 7-5 4
Condensate Storage Tank....................................
3/4 7-7 Activity..................................................
3/4 7-8 Main Steam ).ine Isolation Va1ves..........................
3/4 7-10 1
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........
3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SY5 TEM.......................
3/4 7-12 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM I
Essential Raw Cooling Water System.......................
3/4 7-13 1
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SEQUOYAH - UNIT 1 VIII i
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CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS LOWER CONTAINMENT VENT COOLERS f
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LIMITING CONDITION FOR OPERATION
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i 3.6.2.2 Two independent trains of lower containment vent coolers shall be OPERABLE with two coolers to each train.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one of the above required lower containment vent coolers l
a.
inoperable, restore to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hou's and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With two lower containment vent coolers of the se.me train inoperable, restore to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 Each lower containment vent cooler shall be demonstrated OPERABLE At least once per 31 days by verifying that each fan operates for at a.
least 15 minutes.
l b.
At least once per 18 months by.
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Verifying from the control room that each fan starts.
3 2.
Verifying a cooling water flow rate of greater than or equal to 200 gpm to each cooler.
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SEQUOYAH - UNIT 1 3/4 6-16a Amendment No.
C
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 cf 10 CFR 100 during LOCA conditions.
Cumulative operation of the system with the heate s 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 and 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 i
24 inch inlet line and a 24 inch outlet line), a pre existing iodine spike in the reactor coolant ana four second valve closure times.
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 depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses, j
i 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-term cooling following a non-LOCA avent.
Postaccident use of these coolers ensures containment tem-1 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 valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
By letters dated March 3, 1981, and April 2, 1981, TVA will submit a report on the operating experience of the plant no later than startup after the first refueling.
This information will be used to provide a basis to re-evaluate the adequacy of the purge and vent time limits.
SEQUOYAH - UNIT 1 B 3/4 6-3 Amendment No. 67 m
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CONTAINMENT SYSTEMS s
BASES 3/4.6.4 COM8USTIBLE GAS CONTROL The OPERABILITY cf the equipment and system required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below it flammable limit during post-LOCA conditions.
Either recombiner unit or the purge system t
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j SEQUOYAH - UNIT 1 B 3/4 6-3a
[p ucy'%,j UNITED STATES
! " 3 7, NUCLEAR REGULATORY COMMISSION j
W ASHINGTON, D. C. 20555
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s TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0V0YAH NUCLEAR PLANT, UNIT 2 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No.59 License No. OPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 16, 1987, complies with the standards and reouirements of the Atoric Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provicions of the Act, and the rules ana 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 Connission's regulations; D.
The issuance of this arandment will not be inimical to the enmmon 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.
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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-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, 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 NUCLEAR REGULATORY COMNISSION O
c
(
Gar G. Zech, Ass stant rector r Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of issuance: February 11, 1988
ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY 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 by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT VII VII VIII Vill
- 3/4 6-16a B 3/4 6-3 8 3/4 6-3 B 3/4 6-4 8 3/4 6-4*
1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Cold Leg Injection Accumulators...........................
3/4 5-1 Upper Head Injection Accumulators.........................
3/4 5,
3/4.5.2 ECCS SUBSYSTEMS - T,yg greater than or equal to 350 F.....
3/4 5-5 3/4.5.3 ECCS SUBSYSTEMS - T,yg less than 350 F....................
3/4 5-9 3/4.5.4 BORON INJECTION SYSTEM Boron Injection Tank......................................
3/4 5-11 Heat Tracing..............................................
3/4 5-12 3/4.5.5 REFUELING WATER STORAGE TANK..............................
3/4 5-13 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity..........
3/4 6-1 Containment Leakage.................
3/4 6-2 Containment Air Locks.....................................
3/4 6-7 Internal Pressure.........................................
3/4 6-9 Air Temperature..................................
3/4 6-10 Containment Vessel Structural Integrity...................
3/4 6-11 Shield Building Structural Integrity......................
3/4 6-12 Emergency Gas Treatment System (Cleanup Subsystem)........
3/4 6-13 Containment Ventilation System............................
3/4 6-15 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System..................................
3/4 6-16 Containment Cooling Fans..................................
3/4 6-16b l
SEQUOYAH - UNIT 2 VII Amendment No. 59
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INDEX LIMITING CONDITIONS-FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PaGE 3/4.6.3 CONTAINMENT ISOLATION VALVES...........
3/4 6-17 3/4.6.4, COMBUSTIBLE GAS CONTROL Hydrogen Monitors.........................................
3/4 6-24 Electric Hydrogen Recombiners...........
3/4 6-25 Hydrogen Control Interim Distributed Ignition System.....
3/4 6-26 3/4.6.5 ICE CONDENSER Ice Bed..........
3/4 6-27 Ice Bed Temperature Monitoring System.....................
3/4 6-29 Ice Condenser Doors.............
3/4 6-30 Inlet Door Position Monitoring System.....................
3/4 6--32 Divider Barrier Personnel Access Doors and Equipment Hatches...........
3/4 6-33 Containment Air Return Fans........
3/4 6-34 Floor Drains.........
3/4 6-35 Refueling Canal 0 rains....................
3/4 6-36 Divider Barrier Seal.............
3/4 6-37 3/4.6.6 VACUUM RELIEF VALVES..............
3/4 6-39 3/4.7 PLANT SYSTEMS 3/4.7.i TURBINE CYCLE Safety Valves.............................................
3/4 7-1 Auxiliary Feedwater System................................
3/4 7-5 Condensate Storage Tank...................................
3/4 7-7 Activity..................................................
3/4 7-8 Main Steam Line Isolation Valves..........................
3/4 7-10 3/4.7.2 STEAMGENERAT0itPRESSURE/TEMPERATURELIMITATION...........
3/4 7-i 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................
3/4 7-12 SEQUOYAH - UNIT 2 VIII
CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS LOWER CONTAINMENT VEffT COOLERS l
LIMITING CONDITION FOR ODERATION 3.6.2.2 Two independent trains of lower containment vent coolers shall be OPERABLE with two coolaars to each train.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one of the above required lower containment vent coolers a.
inoperable, restore to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With two lower containment vent coolers of the same train inoperable, restore to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 Each lower containment vent cooler shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each fan operates for at a.
least 15 minutes.
b.
At least once per 18 months by:
1.
Verifying from the control room that each fan starts.
2.
Verifying a cooling water flow rate of greater than or equal to 200 gpm to each cooler.
SEQUOYAH - UNIT 2 3/4 6-16a Amendment No. 59 l
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9 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 heatcrs 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 and 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.
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 depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
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-term 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 valves ensures that the containment atmosphere will be isolated from the outside environment in the j
event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
Cor tainment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analysr.s for a LOCA.
SEQUOYAH - UNIT 2 8 3/4 6-3 Amendment No. 59
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 anit or the hydrogen mitigation system, consisting of 68 hydrogen igniters per unit, ir capable of 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 Concentratici in Containment Following a LOCA," Revision 2, dated November 1978.
The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphera 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 igniters in the hydrogen control distributed ignitica 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 snurce.
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 i
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 minimun weight figure of 1200 pounds of ice per basket contains a 10%
conservative allowance for ice less through sublimation which is a factor of 10 higher than assumed for the ice condenser design.
The minimum weight figure of 2,333,100 pounds of ice also contains an additional 1% conservative allowance to account for systematic error in weighing instruments.
In the event that observed sublimation rates are equal to or Icwer than design predictions after three years 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.
SEQUOYAH - UNIT 2 8 3/4 6-4 Amendment No. 21
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