ML20033G688
| ML20033G688 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/02/1990 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033G689 | List: |
| References | |
| NUDOCS 9004110203 | |
| Download: ML20033G688 (14) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION W ABHINGT ON, o, C. 20666
_ TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQU0YAH NUCLEAR PLANT, UNIT 1 AMENDM:NT TO FACILITY OPERATING LICENSE
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Amendment No. 134 License No. DPR-77 1.
The Nuclear Regehtory Commission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated January 12, 1990, and its supplements dated February 9 and March 1,1990, comply with the standards and requirements 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 applicatisn the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authori.'.ed by 1
this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in e mpliance 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 Commission's regulations and all applicable requirements have l
been satisfied.
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' 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment and paragraph 2.C.(2) of facility Operating License No. OPR-77 is hereby amended to read as follows:
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(2) Technical Specifications
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The Technical Specifications contained in Appendices A and B, as revised through Amendment No.134, 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.
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FOR THE NUCLEAR REGULATORY COMMISSION of Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 2, 1990
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s ATTACHMENT TO LICENSE AMENDMENT NO.134 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 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 3/4 9-8 3/4 9-8 B3/4 9-1 B3/4 9-1*
B3/4 9-2 B3/4 9-2 B3/4 9-3 B3/4 9-3
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REFUELING OPERATIONS 3/4.9.8 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION ALL WATER LEVELS LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal (RHR) loop shall be in operation.
APPLICABILITY:
MODE 6.
ACTION:
With less than one residual heat removal loop in operation, except a.
as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, The residual heat removal loop may be removed from operation for up b.
to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.
The provisions of Specification 3.0.3 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.9.8.1 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 2000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i
e SEQUOYAH - UNIT 1 3/4 9-8 Amendment No.134 1
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
- 1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
Maintaining the listed vaives in the closed position precludes an uncontrolled boron dilution accident s
by closing the flow paths for possible sources of unborated water.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel as:,emblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.
This decay time is consistent with the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling i
station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.
SEQUOYAH - UNIT 1 B 3/4 9-1
REFUELING OPERATIONS
^
BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:
- 1) manipulator cranes will be used for movement of drive rods and fuel assemblies.
- 2) each crane has suf ficient load capacity to lift a drive rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped:
- 1) the activity release will be limited to that contained in a single fuel assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array.
This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residud heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F es required durh,3 the REFUELING MODE, and 2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
The minimum required flow rate of 2000 gpm ensures decay heat removal, minimizes the probability of losing an RHR pump by air-entrainment from pump vortexing, and minimizes the potential for valve damage due to cavitation or chatter.
Losing an RHR pump is a particular concern during reduced RCS inventory operation.
The 2000 gpm value is limited by the potential for cavitation in the control valve and chattering in the 10-inch check valve.
i The requirement to have two RHR loops OPERABLE when there is less than I
23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability.
With the reactor vessel head removed and i
23 feet of water above the reactor pressure vessel flange, a large heat sink i
is available for core cotsling.
Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
i SEQUOYAH - UNIT 1 B 3/4 9-2 Amendment No.
134 j
REFUELING OPERATIONS BASES 3/4 9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the containment.
The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL PIT The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.
The minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.12 AUXILIARY BUILDING GAS TREATMENT SYSTEM The limitations on the auxiliary building gas treatment system ensure that all racioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.
Cumulative operation of the system with the heater 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 adsorbers and HEPA filters.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
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l SEQUOYAH - UNIT 1 B 3/4 9-3 Amendment No. 134
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NUCLEAR REGULATORY COMMISSION a
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%,.,...l TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated January 12. 1990, and its supplements dated February 9, and March 1,1990, comply with the standards and requirements of the Atomic 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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, j
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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.121, 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 C0tWISSION Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical Specifications Date of Issuance: April 2, 1990 l
I i
J i
ATTACHMENT TO LICENSE AMENDMENT NO. 121 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pa9es.
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 j
3/4 9-9 3/4 9-9 3/4 9-10 3/4 9-10*
B3/4 9-1 B3/4 9-1*
B3/4 9-2 B3/4 9-2 B3/4 9-3 B3/4 9-3 I
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REFUELING OPERATIONS 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ALL WATER LEVELS LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal (RHR) loop shall be in operation.
APPLICABILITY:
MODE 6.
ACTION:
With less than one residual heat removal loop in operation, except a.
as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, b.
The residual heat removal loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs, The provisions of Specification 3.0.3 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.9.8.1 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 2000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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l SEQUOYAH - UNIT 2 3/4 9-9 Amendment No. 121 l
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3/4.9 REFUELING OPERATIONS BASES l
3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
- 1) the reactor will remain suberitical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
Maintaining the listed valves in the closed position precludes an uncontrolled boron dilution accident by closing the flow paths for possible sources of unborated water.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
l 3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
l 3/4.9.3 DECAY TIME l
The minimum requirement for reactor suberiticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.
This decay time is consistent with the assumptions used in the accident analyses.
l 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.
SEQUOYAH - UNIT 2 B 3/4 9-1 Amendment No.
4 REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:
- 1) manipulator cranes will be used for movement of drive rods and fuel assemblies,
- 2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, assembly, and 3) the core internals and pressure vessel are protected from excessive lif ting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped
- 1) the activity release will be limited to that contained in a single fuel assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array.
This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION i
The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F as required during the REFUELING MODE, and 2) sufficient coolant circulation is maintained thru the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
The minimum required flow rate of 2000 gpm ensures decay heat removal, minimizes the probability of losing an RHR pump by air-entrainment from pump vortexing, and minimizes the potential for valve damage due to cavitation or chatter.
Losing an RHR pump is a l
particular concern during reduced RCS inventory operation.
The 2000 gpm value is limited by the potential for cavitation in the control valve and chattering in the 10-inch check valve.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is avai'.rele for core cooling.
Thus, in the event of a failure of the operating i
RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
j l
SEQUOYAH - UNIT 2 B 3/4 9-2 Amendment No. 121
REFUELING OPERATIONS BASES 3/4.9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the containment.
The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL PIT The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.
The minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.12 AUXLIARY BUILDING GAS TRFATMENT SYSTEM The limitations on the auxiliary building gas treatment system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters anu charcoal adsorber prior to discharge to the atmosphere.
Cumulative operation of the system with the heater 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 adsorbers and HEPA filters.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
F I
SEQUOYAH
' NIT 2 B 3/4 9-3 Amendment No. 121 U
i
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