ML20212K953

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Amends 144 & 135 to Licenses NPF-2 & NPF-8,respectively, Revising TS Nis SRs to Adjust Nis Pr Channels Only When calorimetric-calculated Power Greater than Pr Indicated Power by More than +2% RTP
ML20212K953
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 10/01/1999
From: Emch R
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20212K958 List:
References
NUDOCS 9910070113
Download: ML20212K953 (8)
v • d • e


Text

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y UNITED STATES 3

g NUCLEAR REGULATORY COMMISSION

'2 WASHINGTON, D.C. 20666 4001

%...../

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. j 44 License No. NPF-2

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southern Nuclear), dated November 6,1998, 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 (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 Operating License No. NPF-2 is hereby amended to read as follows:

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9910070113 991001 PDR ADOCK 05000348 l

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(2) Technical Soecifications 1

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 144, 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 l

Richard L. Emch, Jr., Chief, Section 1 Project Directorate il l

Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical j

Specifications Date of issuance: October 1,1999 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 144 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348

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Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3/4 3-14 3/4 3-14 i

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Tamrm a_s-1 s ena+ 4 mi..a s l

T&RT.E MOTaTTnM With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

(1)

If not performed in previous 7 days.

(2)

Heat balance only, above.15% of RATED THERMAL POWER (RTP). Adjust NIS channel if calorimetric calculated power exceeds NIS indicated power by more than +2% RTP.

(3)

Compare incore to excore axial flux difference every 31 EFPD.

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

(4)

Manual ESF functional !nput check overy 18 months.

(5)

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below the P-6 (Block of Source Range Reactor Trip) setpoint. Upon reaching P-6 from MODE 2 the CHANNEL CHECK must be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Logic only, if not performed in previous 92 days.

(8)

(9)

CHANNEL FUNCTIONAL TEST will consist of verifying that each channel 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.

(11)

Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.

Verify reactor trip breaker and reactor trip bypass breaker open upon j

(12) actuation of each Main control Board handswitch.

(13)

Local manual shunt trip prior to placing breaker in service. Local manual undervoltage trip prior to placing breaker in service.

Undervoltage trip via Reactor Protection System.

(14)

(15)

Local manual shunt trip.

1 FARLEY-UNIT 1 3/4 3-14 AMENDMENT NO. 144 l

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UNITED STATES

+-j j

NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20566-0001

'+9.....,o SOUTHERN NUCLEAR OPERATING COMPANY. INCs ALABAMA POWER COMPANY DOCKET NO. 50-36_4 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.135 License No. NPF-8

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southern Nuclear), dated November 6,1998, 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 (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 Operating License No. NPF-8 is hereby amended to read as follows:

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. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.135. 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

(

Richard L. Emch, Jr., Chief, Section 1 i

Project Directorate II Division of Licensing Project Management i

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 1, 1999

r-i ATTACHMENT TO LICENSE AMENDMENT NO.135 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50 364 Replace the following pages of the Appendix A Technical Specifications with the attached

(

revised pages. - The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 3-14 3/4 3-14 i

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1

, mar 4.2.s s ewn+. t...m 2&RLE,,MOTaTTfM With the reactor trip system breakers closed and the control rod

' drive system capable of rod withdrawal.

(1)

If not performed in previous 7 days.

(2)

Heat balance only, above 15% of RATED THERMAL POWER (RTP). Adjust NIS channel if calorimetric calculated power exceeds NIS indicated power by more than +2% RTP.

(3)

Compare incore to encore axial flux difference every 31 EFPD.

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

(4)

Manual ESF functional input check every 18 months.

(5)

Each. train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below the P-6 (Block of Source Range Reactor Trip) setpoint. Upon reaching P-6 from NODE 2 the CHANNEL CHECK must be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

(8)

Logic only, if not performed in previous 92 days.

(9)

CHANNEL FUNCTIONAL TEST will consist of verifying that each channel 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.

(11)

Independently verify OPERABILITY of the undervoltage and shunt trip circuitry for the Manual Reactor Trip Function.

(12)

Verify reactor trip breaker and reactor trip bypass breaker open upon actuation of each Main Control Board handswitch.

(13)

Local manual shunt trip prior to placing breaker in service.

l Local manual undervoltage trip prior to placing breaker in service.

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(14)

Undervoltage trip via Reactor Protection System.

(15)

Local manual shunt trip.

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FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO.135

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