ML20080F237
| ML20080F237 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/27/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080F239 | List: |
| References | |
| TAC-48973, TAC-52539, TAC-52540, TAC-53434, NUDOCS 8402100397 | |
| Download: ML20080F237 (10) | |
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ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT.TO FACILITY OPERATING LICENSE Amendment No.41 License No. NPF-2 1.
The Nuclear Regulatory Commission (the Commissien) has found that:
A.
The application for amendment by Alabama Power Cetpany (the licensee) dated October 6, 1983, supplemented November 28, 1983, 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;
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B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 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 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 Op'erating License No. NPF-2 is hereby amended to read as follows:
8402100397 840127 PDR ADOCK 05000348 P_
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. (2) Technical Specifications The Technical Specifications centained in Appendices A and B, as revised through Amendment No. 41, 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 cate of issuance.
FOR THE NUCLEAR REGULATORY COMM!SSION
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Attachment:
Changes to the Technical Specifications Date of Issuance: January 27, 1984 a
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ATTACHMENT TO LICENSE AMENDMENT N0.41 AMENDMENT NO :41 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Revised Appendix A as follows:
Remove Pages Insert Pages IV IV 3/4 3-72 B 3/4 3-5 e
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS l
3/4.2.1 AXIAL FLUX DIFFERENCE................................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R...........,..s..........
3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACT 0R..................
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 ACTUATIO.N SYSTEM INSTRUMENTATION....................................
3/4 3-15 3/4.3.3 ' MONITORING INSTRUMENTATION R a d i a t i U n M o n i t o ri n g.................................
3/4 3-38 Movable Incore Detectors.............................
3/4 3-42 Sei smi c Moni tori n g Inst rumentati on...................
3/4 3-43 Meteorol ogi cal I nst rumentat i on.......................
3/4 3-46 Remote Shutdown Instrumentation......................
3/4 3-49 C h l o ri n e D et e ct i o n Sy st ems...........................
3/4 3-52 Hi gn E ner gy Li ne B reak Senso rs.......................
3/4 3-53 Acci dent Moni tori n g Instrumentati on..................
3/4 3-56 F i re Detecti on Inst rumentati on.......................
3/4 3-59 R adi oacti ve Liqui d Ef fluent Moni to ri ng...............
3/4 3-61 Radi oacti ve Gaseous Ef fluent Moni tori ng..............
3/4 3-66 3/4.3.4 TURBINE OVERSPEED PROTECTION.........................
3/4 3-72 l
FARLEY-UNIT 1 IV Amendment No. 41 i
INSTRUMENTATION 3 /4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
NODES 1, 2 and 3 ACTION:
a.
With one stop valve or one governor valve per high pressure turbine steam line inoperable and/or with one reheat stop. valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) 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 close at least one valve in the af fected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With'the above required turbine overspeed protection system otherwise inoperable. within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine f ron the steam sucoly.
c.
The provisions of Speci fication 3.0.4 a re not apolicaole.
SURVE!LLANCE REQUIREMENTS S
4.3.4.1 The provisions of Speci fic.ation'4.0.4 are not applicable.
- Specification not applicable with all main steam isolation valves and associated bypass valves in the closed position and all other steam flow paths to the turbine isolated.
FARLEY - UNIT 1 3/4 3-72 Amendment No. 41
INSTRUMENTATION BASES 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 will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is "equired since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.
FARLEY-UNIT 1 B 3/4 3-5 Amendment No. 41 i
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ALABAMA POWER C0'MPANY DOCKET N0. 50-364 JOSEPH fl. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.32 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 October 6, 1983, supplemented November 28, 1983, 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, as amended, the provisions of the Act, and the 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; 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 m.
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:
j (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.32, 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 COMM!SSION L
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/arga Operating Reactor' anch #1 Division of Licens1
Attachment:
Changes to the Technical Specifications Date of Issuance: January 27, 1984 I
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.a ATTACHMENT TO LICENSE AMENDMENT fl0.32 AMENDMENT NO. 32 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revised Appendix A as follows:
Remcve Pages Insert Pages 3/4 3 3/4 3-72 3/4 3-73 t
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4 INSTRUNENTATION 3 /4.3.4 TURBINE 0VERSPEED PROTECTION a
LIMITING CONDITION FOR OPERATION 3.3.4 At lea.st one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
MODES 1, 2*
and 3'.
ACTION:
a.
With one stop valve or one governor valve per high pressure turbine steam line inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) 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 close at least o.e valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
C.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.
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" Specification not applicable with all main steam isolation valves and associated bypass valves in the closed position and all other steam flow paths to the turbine isolated.
FARLEY - UNIT 2 3/4 3-72 Amendment No. 32