ML20247A842
| ML20247A842 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/04/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247A845 | List: |
| References | |
| NUDOCS 8905230294 | |
| Download: ML20247A842 (18) | |
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ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. NPF-8 1.
The Nuclear Regulatory Commission (the Comission) has found that:-
A.-
The application for amendment by Alabama Power Company (the licensee), dated December 14, 1988, as supplemented April 6,1989, complies 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Comiss Ion; 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 Comission's regulations;-
O.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the i
public; and 1
(.
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 Y
of the Commission's regulations and all applicable requirements have been satisfied.
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. NPF-8 is hereby amended to read as follows:
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.e 2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B. as revised through Amendment No. 72, are hereby incorporated in the' license. Alabama Power Company 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 prior to startup from the refueling outage for Cycle 7.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects.;,1 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 4, 1989 l
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. 48 ATTACHMENT TO LICENSE AMENDMENT NO. 72 l
TO FACILITY OPERATING LICENSE N0. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendfx A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57 3/4 3-57a 3/4 3-58 3/4 3-58 8 3/4 3-4 B 3/4 3-4 8 3/4 3-5 8 3/4 3-5 1
.)
INSTRUMENTATION ACCIDENT NONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The accident monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
As shown in Table 3.3-11.
The provisions of Specification 3.0.4 are not l
applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL T,ALIBRATION operations at the frequencies shown in Table 4.3-7.-
FARLEY-UNIT 2 3/4 3-56 Amendment No. 72
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Table 3.3-11 (Continued)
ACTION STATEMENTS ACTION 1 -
Vith the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-11, 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 />.
ACTION 2 -
Vith the number of OPERABLE accident monitoring channels less than the Minimum Channcis OPERABLE requirements of Table 3.3-11, 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 80T SHUTD0VN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 3 -
Vith the number of OPERABLE channels one less than the Required Number of Channels shovn in Table 3.3-11, restore the inoperable channel to OPERABLE status within 7 days.
If repairs are not feasible without shutting down, prepare and submit a Special Report to the Commission pursuant to the Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.
ACTION 4 -
Vith the number of OPERABLE channels less than the Minimum Channels OPERABLE requirements of Table 3.3-11, restore the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. If repairs are not feasible without shutting down:
1.
Initiate an alternate method of monitoring the reactor vessel inventory; and 2.
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status; and 3.
Restore at least one channel to OPERABLE status at the next scheduled refueling outage.
l PARLEY-UNIT 2 3/4 3-57a Amendment No. 72 l
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1 INSTRUMENTATION BASES 3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATI0ti The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
In the event more than four sensors in a reactor vessel level indicating system channel are inoperable, repairs may only be possible during the next refueling outage. This is because the sensors are accessible only after the missile shield is removed. If only one channel is inoperable, it shall be restored to OPERABLE status as soon as reasonably possible. If both channels are iroperable, at least one channel should be restored to OPERABLE status no later than by the end of the next refueling outage.
Vith the number of OPERABLE RVLIS channels less than the minimum channels required to be OPERABLE, the inoperable channels must be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or an alternate method of monitoring the reactor vessel level must be initiated. Monitoring pressurizer level and upperhead subcooling is an acceptable alternative to the RVLIS since the RVLIS is primarily used to detect the formation of a void in the reactor vessel head.
A channel check of the RVLIS is a comparison of each valid sensor with its corresponding rensor in the opposite train to verify they display the same state (i.e. covered or uncovered). If the corresponding sensor in the opposite train is invalid then the level at that location can be determined based upon the state of the next highest sensor, pressurizer level, and upperhead subcooling.
A channel calibration of the RVLIS involves the calibration of the digital to analog and analog to digital converters, the cold reference
" junction, and the power supplies.
3/4.3.3.9 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 in order to detect and locate fires in their early stages.
Prompt detection of fires vill 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.
FARLEY-UNIT 2 B 3/4 3-4 Amendment No. 72
INSTRUMENTATION P' Pt 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarritrip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip vill occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.11 RADI0 ACTIVE CASEOUS EFFLUEIR INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip vill occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the vaste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
'3 /4. 3. 4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and vill protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.
FARLEY-UNIT 2 B 3/4 3-5 Amendment No. 72 l
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DOCKET NO. 50-348 1
i JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. NPF-2 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee),
dated December 14, 1988, as supplemented April 6,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amereded (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 (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 Comission's regulations; D.
The issuance of this license 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.
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. NPF-2 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical-Specifications contained in Appendices A and B, as revised through Amendment No. 80, are hereby it.corporated 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 prior to startup from the refueling outage for Cycle 10.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Elinor G. Adensam Director Project Directorate II-1 Division of Reactor Projects I/II Office of-Nuclear Reactor Regulation
Attachment:
. Changes to the Technical Specifications Date of Issuance: May 4, 1989 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 80 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57 3/4 3-57a 3/4 3-58 3/4 3-58 B 3/4 3-4 8 3/4 3-4 8 3/4 3-5 B 3/4 3-5
INSTRUMENTATION t
ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The accident monitoring instrumentation channels shown in Table-3.3-11 shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
As shown in Table 3.3-11.
The provisions of Specification 3.0.4 are not l
applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL
-CALIBRATION operations at the frequencies shown in Table 4.3-7.
FARLEY-UNIT 1 3/4 3-56 Amendment No. M, 80
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Table 3.3-11 (Continued) j ACTION STATEMENTS ACTION 1 -
Vith the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-11, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the
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next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 2 -
Vith the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirements of Table 3.3-11, 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 vithin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 3 -
With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11, restore the inoperable channel to OPERABLE status within 7 days. If repairs are not feasible without shutting down, prepare and submit a Special Report to the Commission pursuant to the Specification 6.9.2 within 30 days following the event.
outlining the action taken, the.cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.
ACTION 4 -
With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirements of Table 3.3-11, restore the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. If 1
repairs are not feasible without shutting down:
1.
Initiate an alternate method of monitorin.c the reactor vessel inventory; and 2.
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperebility, and the plans and schedule for restoring the system to OPERABLE status; and 3.
Restore at least one channel to OPERABLE status at the next scheduled refueling outage.
FARLEY-UNIT 1 3/4 3-57a Amendment No. 80 l
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INSTRUMENTATION BASES 3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
In the event more than four sensors in a reactor vessel level indicating system channel are inoperable, repairs may only be possible during the next refueling outage. This is because the sensors are accessible only after the missile shield is removed.
If only one channel is inoperable, it shall be restored to OPERABLE status as soon as reasonably possible.
If both channels are inoperable, at least one channel should be restored to OPERABLE status no later than by the end of the next refueling outage.
With the number of OPERABLE RVLIS channels less than the minimum channels required to be OPERABLE, the inoperable channels must be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or an alternate method of monitoring the reactor vessel level must be initiated. Monitoring pressurizer level and upperhead subcooling is an acceptable alternative to the RVLIS since the RVLIS is primarily used to detect the formation of a void in the reactor vessel head.
A channel check of the RVLIS is a comparison of each valid sensor with its corresponding sensor in the opposite train to verify they display the same state (i.e. covered or uncovered).
If the corresponding sensor in the opposite train is invalid then the level at that location can be determined based upon the state of the next highest sencor, pressurizer level, and upperhead subcooling.
A channel calibration of the RVLIS involves the calibration of the digital to analog and analog to digital converters, the cold reference
-junction, and the power supplies.
3/4.3.3.9 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate varning 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 vill reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
1 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.
FARLEY-UNIT 1 B 3/4 3-4 Amendment No. 76, 80
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I INSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT INSTRUMElfrATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip vill occur prior to exceeding the limits of 10 CFR Part 20.'
This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the vasta gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.4 TURBINE OVERSPEED FROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and vill protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, e,2ipment or structures.
i FARLEY-UNIT 1 B 3/4 3-5 Amendment No. 97, 80 l
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