ML20080D706
| ML20080D706 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/28/1994 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080D709 | List: |
| References | |
| NUDOCS 9501060077 | |
| Download: ML20080D706 (12) | |
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f 8-4 UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20665I001 s...../
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
i DOCKET NO. 50448 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 License No. NPF-2 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated October 20, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and r
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 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 1
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:
9501060077 941228 DR ADOCK 05000348 PDR
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' (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.111, are hereby incorporated in the license.
Southern Nuclear 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 30 days of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION Af W 111am H. B tema, Director Project Directorate II-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 28, 1994 i
I
t ATTACHMENTTOLICENSEAMENbMENTNO.111 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 Paaes Insert Paaes IV IV 3/4 3-52 3/4 3-52 B 3/4 3-3 B 3/4 3-3 6
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DI FFERENCE................................ 3 / 4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR......................... 3/ 4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR.................. 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO............................ 3 / 4 2-11 i
3/4.2.5 DNB PARAMETERS....................................... 3/4 2-14 r
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM II'STRUMENTATION.................. 3/4 3-1 I
3/4.3.2 E!!GINEERED SAFETY FEATURE ACTUATION SYSTEM i
INSTRUMENTATION...................................... 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring................................. 3/4 3-38 Movable Incore Detectors............................. 3/4 3-42 Seismic Monitoring Instrumentation...................
3/4 3-43 Meteorological Instrumentation....................... 3/4 3-46 Remote Shutdown Instrumentation...................... 3/4 3-49 Chl::in: 0::::ti Sy:t---(Deleted).................. 3/4 3-52 l
High Energy Line Break Sensors....................... 3/4 3-53 Accident Monitoring Instrumentation.................. 3/4 3-56 (Deleted).............. 3/4 3-59 Erfi:::tiv: Liquid Ifflu::: M :it:ri;;(Deleted)...... 3/4 3-61 i
i Radioactive Gaseous Ef fluent Monitoring.............. 3/4 3-66 3/4.3.4 TURBINE OVERS PEED PROTECTION......................... 3/4 3-72 l
l EARLEY-UNIT 1 IV AMENDMENT NO. IIeIIeIIe111
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INSTRUMENTATION CHLORINE DETECTION SYSTEMS i
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I This specification deleted.
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FARLEY-UNIT 1 3/4 3-52 AMENDMENT No. 88. 111
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INSTRUMENTATION i
BASES l
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient l
capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to. permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100. The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes," April 1974.
344.3.3.4 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 generally consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Program," February 1972.
t 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to pecnit shutdown and maintenance of NOT STANDBY of the facility 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 Criteria 19 of 10 CFR 50.
I 3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.
l 3/4.3.3.7 HIGH ENERGY LINE BREAK ISOLATION SENSORS The high energy line break isolation sensors are designed to mitigate the consequences of the discharge of steam and/or water to the affected room and other lines and systems contained therein.
In addition, the sensors will initiate signals that will alert the operator to bring the plant to a shutdown condition.
EARLEY-UNIT 1 B 3/4 3-3 AMENDMENT NO. 20, 111
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UNITED STATES.
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NUCLEAR REGULATORY CQMMISSION f
WASHINGTON, D.C. 20066-4001 4,*****,o SOUTHERN NUCLEAR OPERATING COMPANY. INC.
DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 L
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-8 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated October 20, 1994, 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 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 license amendment will not be inimical to the common defense and security or to the health and safety of the public; and j
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.
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:
' (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.102, are hereby incorporated in the license. Southern Nuclear 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
W 111am H. Ba man, Director
.roject Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 28, 1994
ATTACHMENT TO LICENSE AMEN 6 MENT NO. 102 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes IV IV 3/4 3-52 3/4 3-52 B 3/4 3-3 B 3/4 3-3 1
I
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE................................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R......................... 3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR.................. 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATI0............................ 3/4 2-11 3/4.2.5 DNB PARAMETERS....................................... 3/4 2-14 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.................. 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION...................................... 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring................................. 3/4 3-38 Movable Incore Detectors............................. 3/4 3-42 Seismic Monitoring Instrumentation................... 3/4 3-43 Meteorological Instrumentation....................... 3/4 3-46 Remote Shutdown Instrumentation...................... 3/4 3-49 Chi;;in: Oct::ti;; Sy;t --- (Deleted).................. 3/4 3-52 l
High Energy Line Break Sensors....................... 3/4 3-53 Accident Monitoring Instrumentation.................. 3/4 3-56 i
- ir: 0::::ti:: :::::-- ;t: tic (Deleted)............. 3/ 4 3-5 9 n:di:::ti c; '.iquid Offic::t = it::ing(Deleted)...... 3/4 3-61 Radioactive Gaseous Effluent Monitoring.............. 3/4 3-66 3/4.3.4 TURBINE OVERSPEED PROTECTION......................... 3/4 3-72 AMENDMENT No. gd,91,102 FARLEY-UNIT 2 IV
4 INSTRUMENTATION CHLORINE DETECTION SYSTEMS 4
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This specification deleted.
1 FARLEY-UNIT 2 3/4 3-52 AMENDMENT NO.
102
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INSTRUMENTATION BASES 3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY cf the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event i
and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100. The instrumentation is consistent with the reconenendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes,." April 1974.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERASILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for ertimating 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 generally consistent with the recommendations of Regulatory Guide 1.23; "Onsite Meteorological Program," February 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is i
consistent with General Design criteria 19 of 10 CFR 50.
3/4.3.3.6 CHLORINE DETECTION SYSTEMS This specification deleted.
l 3/4.3.3.7 HIGN ENERGY LINE BREAK ISOLATION SENSORS The high energy line break isolation sensors are designed to mitigate the consequences of the discharge of steam and/or water to the affected room and other lines and systems contained therein.
In addition, the sensors will i
initiate signals that will alert the operator to bring the plant to a shutdown condition.
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102 FARLEY-UNIT 2 5 3/4 3-3 AMENDMENT NO.
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