ML20203E089

Amends 62 & 53 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements

ML20203E089
Person / Time
Site:	Farley
Issue date:	04/15/1986
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20203E094	List: ML20203E089 ML20203E097
References
TAC-60287, TAC-60288, NUDOCS 8604240099
Download: ML20203E089 (10)

Text

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'o UNITED STATES

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8 NUCLEAR REGULATORY COMMISSION o

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WASHINGTON, D. C. 20655

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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. 62 License No. NPF-2 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendinent by Alabama Power Company (the licensee) dated November 22, 1985, 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 ir 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 Comission's regulations; D.

The issuance of this license amendnint will not be inimical to the common defense and security or to tne health and safety of the public; and i

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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8604240099 860415 i

PDR ADOCK 05000348 p

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(2)TechnicalSpecifications 1

The Technical Specifications contained in Appendices l

A and B, as revised through Amendment No. 62, are hereby incorporated in the license. The licensee I

shall operate the facility in accordance with the j

Technical Specifications, i

3.

This license amendment is effective as of its date of issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION k

l d;I /SkuSbs Lester S. Ru enstein, Director j

PWR Project Directorate #2 j

Division of PWR Licensing-A i

Attachment:

Changes to the Technical Specifications

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Date of Issuance: April 15, 1986 I

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l ATTACHMENT TO LICENSE AMENDMENT i

i AMENDMENT NO. 62 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 1

I Replace the following page of the Appendix "A" Technical Specifications.

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with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change.

1 The corresponding overleaf page is also provided to maintain document i

completeness.

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3/4 3-14 3/4 3-14

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n TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLnNCE REQUIRENENTS

?

E CHANNEL MODES IN WHICH G

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

13. Steam Generator Water Level--

S R

M 1, 2 Low-Low

14. Steam /Feedwater Flow Mismatch and S

R N

1, 2 Low Steam Generator Water Level

15. Undervoltage - Reactor Coolant N.A.

R N

1 Pumps

16. Underfrequency - Reactor Coolant M.A.

R M

1 Pumps w

l 1

17. Turbine Trip A.

Low Auto Stop 011 Pressure N.A.

N.A.

S/U(9)(1)

N.A.

8.

Turbine Throttle Valve Closure N.A.

N.A.

S/U(9)(1)

N.A.

18.

Safety Injection Input from ESF N.A.

N.A.

N(4) 1, 2

19. Reactor Coolant Pump Breaker N.A.

N.A.

R 1

Position Trip 9

20. Reactor Trip System Interlocks N.A.

R S/U(8) 1 3

g

21. Reaqtor Trip Breaker N. A.'

N.A.

N(5) and S/U(1) 1, 2, and

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22. Automatic Trip Logic,

N.A.

N.A.

N(S) 1, 2, and

• 5

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UNITED STATES 8

NUCLEAR REGULATORY COMMISSION n

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a WASHINGTON, D. C. 20665

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ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. NPF-8 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The app 1tcation for amendment by Alabama Power Company (the licensee) dated November 22, 1985, 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: (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 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 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 i

The Technical Specifications contained in Appendices i

A and B, as revised through Amendment No. 53, are j

hereby incorporated in the license. The licensee j

shall operate the facility in accordance with the Technical Specifications.

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3.

This license amendment is effective as of its date of issuance.

i FOR THE NUCLEAR REGULATORY COMMISSION i

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'wd

.. L Lester S~.

ubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuance: April 15, 1986 1

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ATTACHMENT TO LICENSE AMENDMENT 1

l AMENDMENT NO. 53 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 i

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j Replace the following page of the Appendix "A" Technical Specifications I

with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change.

j The corresponding overleaf page is also provided to maintain document completeness.

Remove Page Insert Page j

f 3/4 3-14 3/4 3-14 I

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TABLE 4.3-1 (Centinued) f REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS y

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i CHANNEL MODES IN WHICH I

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

)

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 4

^

13. Steam Generator Water Level--

S R

M 1, 2 L \\

Low-Low

14. Steam /Feedwater Flow Mismatch and S

R M

1, 2 Low Steam Generator Water Level 15.

Undervoltage - Reactor Coolant N.A.

R M

1 i

Pisaps i

16. Underfrequency - Reactor Coolant N.A.

R M

1 Pumps

,s*

17. Turbine Trip j

y A.

Low Auto Stop 011 Pressure N.A.

N.A.

S/U(9)(1)

N.A.

8.

Turbine Throttia Valve Closure M.A.

N.A.

S/U(9)(1)

N.A.

j

18. Safety Injection Input from ESF '

N.A.

N.A.

M(4) 1, 2 3

19.

Reactor Coolant Pump Breaker N.A.

N.A.

R 1

Position Trip i

20.

Reactor Trip System Interlocks N.A.

R S/U(8) 1 l

21.

Reactor Trip Breaker N.A.

N.A.

M(5) and S/U(1) 1, 2, and *

22. Automatic Trip Logic N.A.

N.A.

M(5) 1, 2, and *

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TABLE 4.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers closed and the c6ntrol rod drive system capable of rod withdrawal.

If not performed in previous 7 days.

(1)

Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel (2) if absolute difference greater tnan 2 percent.

Compare incore to excore axial flux difference every 31 EFPD.

(3)

Recalibrate if the absolute difference is greater than or equal to 3 percent.

Manual ESF functional input check every 18 months.

(4)

Each train or logic channel shall be tested at lee every 62 days (5)

P on a STAGGERED TEST BASIS.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(6)

Below the P-6 (Block of Source Range Reactor Trip) setpoint.

(7)

Logic only, if not performed in previous 92 days.

(8)

CHANNEL FUNCTIONAL TEST will consist of verifying that each channel (9) l indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.

(10) - If not performed in the previous 31 days.

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I FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO. 39 53 i