ML20006C148
| ML20006C148 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/30/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006C149 | List: |
| References | |
| NUDOCS 9002060386 | |
| Download: ML20006C148 (14) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION
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j PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY f
DOCKET NO. 50-272 SALEM GENERATING STATION, UNIT NO. 1 O
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 i
License No. DPR-70 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated September 11, 1989 and November 6, 1989 complies 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 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 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon i
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 i
the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by chances to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
9002060386 900f30 PDR ADOCK 05000272 P
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2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.109. 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 and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY C0911SSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/11
Attachment:
Changes to the Technical Specifications Date of Issuance: January 30, 1990
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 109. 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 and shall be impicmented within 60 days of the date of issuance.
i FOR THF NUCLEAR REGULATORY COPMISSION l'f.L a
G Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance: Jardary 30, 1990 t
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.'s ATTACHMENT TO LICENSE AMENDMENT NO.109 I
FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 j
Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 1-4 3/4 1-4 3/4 9-8 3/4 9-B B 3/4 1-1 B 3/4 1-1 B-3/4.9-2 f.
B 3/4 9-2 i
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THIS PAGE LEFT INTENTIONALLY BLAgg l
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t SALEM - UNIT 1 3/4 1-4 Amendment No.109 i
REFUELING OPERATIONS.
y' CODIANT C2RCU1ATION 4
LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual. heat removal loop shall be in operation.
l APPLICABILITY:
MODE 6.
ACTION
- With less than one residual heat removal loop in operation,except a.
as provided in b. below, suspend all operctions involving an increase in the reactor decay heat load or a reduction in boren
. 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.
SURVEILIANCE REQUIREMETS AtleastonceperlhhoursoneRHRloopshallbeverifiedin 4.9.8.1 operation and circulating coolant at a flow rate of:
greater than or equal to 1000 gpm, and a.
b.
sufficient to maintain the RCS temperature at less than or equal to 140 F.
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.l 1-SAbEM - UNIT 1 3/4 96 Amendment No. 109 1
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3/4 1 ' REACTIVITY CONTROL SYSTE11 BASES 3/4.1.1 B0 RATION CONTROL 3/4.1.1.1 and 3 /4.1.1. 2 SMUTDOVN KARCIN A sufficient SHUTDOWN MARCIN ensures that 1) the reactor can be made suberitical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within I
acceptable limits, and 3). the reactor will be maintained sufficiently suberitical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel dapletion, RCS boron concentration, and RCS Tavg.
The most restrictive condition occurs at EOL, with Tavg at no load operating temperaturs, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown.
In the analysis of this accident, j
a minimum SHUTDOVN MARGIN of 1.6% 6k/k is initially required to control the reactivity transient. Accordingly, the SHUTDOVN MARCIN requirement is j
based upon this limiting condition and is consistent with FSAR safety analysis assumptions. Vith Tavgf 200'F, the reactivity transients resulting from a postulated steam line break cooldown are minimal and a 14 6k/k shutdown margin provides adequate protection, 3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) i The limitations on MTC are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the accident and transient analyses, i
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SALEM UNIT 1 8 3/4 1 1 Amendment No. 109 i
c REFUELING OPERATIONS t
9; BASES 3/4.9.6 MANIPUIATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:
- 1) manipulator cranes will be used for movement of control rods and fuel assemblies. 2) each crane has sufficient load capacity to lift a control 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 STORACE BUILDING 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 requirements that at least one residual heat removal 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 through the reactor core to minimize the
- effects of a boron dilution incident and prevent boron stratification. A minimum flow rate of 1000 gpm is required, Additional flow limitations are s
specified in plant procedures, with the design basis documented in the Salem UFSAR. These flow limitations address the concerns related to vortexing and air entrapment in the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time after shutdown.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. The provisions of Sections 3.4.1.4 and 3.9.8.2 (paragraph (b) of footnote (*)] which permit one service water header to be out of service, are based on the following; 1.
The ptriod of time during which plant operations rely upon the p ovisions of this footnote shall be limited to a cumulative 45 days for any single outage, and 2.
The Gas Turbine shall be operable, as a backup to the diesel generators, in the event of a loss of offsite poser, to supply the applicable loads.
The basis for OPERABILITY is one successful startup of the Gas Turbine no more than 14 days prior to the beginning of the Unit outage.
With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the Core.
SkLEM UNIT 1 B 3/4 9 2 Amendment No.109
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PUBLIC SERVICE ELECTRIC & GAS COMPANY L
PHILADELPHIA ELECTRIC COMPANY i-DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 5,ALEM GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that.
t A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company,(Delmarva Power and Light Company and Atlantic City Electric Company the licensees) dated September 11, 1989 and November 6, 1989 complies 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 application, the provisions of the Act, and the rules and regulations of the Comissien; 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Cownission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
c'
- (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B as revised through Amendment No. 87,areherebyincorporatedInthe 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 and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects I/11
Attachment:
Changes to the Technical Specifications Date of Issuance: January 30, 1990
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.(?) Technical Specifications'and Environmental Protection Plan U
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87,.are hereby incorporated in the'
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license. The licensee shall o the Technical Specifications. perate the facility in accordance with-3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.-
P FOR THE NUCLEAR REGULATORY COMMISSION-t i
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v Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance: January 30, 1990 i
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i-by ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO 50-311 1
Revise Appendix A as follows:-
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Remove Pages.
Insert Pages 3/4 9-8 3/4 9-8 B 3/4 9-2 B 3/4 9-2 s
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. REFUELING OPERATIONS-3 /4 ~. 9. 8 RESIDUAL HEAT REMOVAL COOLANT CIRCULATION s
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31 ALL WATER LEVELS.
LIMITINC CONDITION FOR OPERATION L
3.9.8J1 At least'one residual heat removal loop shall be in operation.
I APPLICABILITY:
MODE 6.
ACTION:
With less than one residual heat removal loop in operation, a...
except as provided in b. below, suspend all operations involvin6 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 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 previsions of Specification 3.0.3 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.9.8.l' At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> one RHR loop shall be verffied in F
operation and circulating coolant at a flow rate of:
greater.than or equal to 1000 gpm, and a.
b.
sufficient to maintain the RCS temperature at less than or equal-to 140 F.
n SALEM - UNIT 2 3/4 9-8 Amendment No. 87
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.f REFUELINC OPERATION,1 x
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BASES
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3/4.9.6 HANIPULATOR CRANE 4
The OPERABILITY requirements for the manipulator cranes ensure that: 1)
O manipulator cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control 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 STORACE BUILDING The restriction on movement of loads in excess of the nominal weight' of a-fue1~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 sin 61e 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 requirements that at least one residual heat removal 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'T as required during 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. A minimum flow rate of 1000 gpm.is required. Additional flow limitations are specified in plant procedures, with the design basis documented in the Salem UFSAR.
These flow limitations address the concerns related to vortexing and air entrapment in 4
the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time af ter shutdown. The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability.
The provisions of Sections 3.4.1.4 and 3.9.8.2-(paragraph (b) of footnote (*)]
which permit one service water header to be out of service, are based on the following:
1.
The period of time during which plant operations rely upon the provisions of this footnote shall be limited to a cumulative 45 days for any single outage, and 2.
The Gas Turbine shall be operable, as a backup to the diesel generators, in the event of a loss of offsite power, to supply the applicable loads.
The basis for OPERABILITY is one uccessful startup of the Cas Turbine no more than 14 days prior s
to-the beginning of the Unit outage.
With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
t SALEM - UNIT 2 B 3/4 9-2 Amendment No. 87