ML18011A855

Amend 55 to License NPF-63,revising TS 3/4.3.3.4, Turbine Overspeed Protection & Associated Bases IAW New STS

ML18011A855
Person / Time
Site:	Harris
Issue date:	03/22/1995
From:	Bateman W Office of Nuclear Reactor Regulation
To:
Shared Package
ML18011A856	List: ML18011A855
References
NPF-63-A-055 NUDOCS 9503280079
Download: ML18011A855 (13)

Text

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+p*4k UNITED STATES NUCLEAR REGULATORY COMMISSION WASH,INGTON, D.C. 2055&4001 CAROLIN OWER 5 IGHT COMPANY et al.

DOCKET NO. 50-400 SHEARON HARRI NUC 0

P UNI 1

ENDHENT TO FACI ITY OPERATING LICENSE Amendment No. 55 License No. NPF-63 2.

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

A.

The application for amendment by Carolina Power L Light Company, (the licensee),

dated October 24,

1994, as supplemented December 6,

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 (i) that the activities authorized by

.'his 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 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.

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-63 is hereby amended to read as follows:

9503280079 950322 PDR ADOCK 05000400 PDR

J

3.

(2) Tech ical S ecifications and nvironmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached

hereto, as revised through Amendment No.

55

, are hereby incorporated into this license.

Carolina Power' Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

This license amendment is effective as of the date of its issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION W

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~z>qWilliam H. Bateman, 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:

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. NPF-63 OOCKET NO. 50-400 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Pa es viXiii 3/4 3-89 B 3/4 3-6 Insert Pa es vi X111 3/4 3-89 B 3/4 3-6

0 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONSo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~

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TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS....................

PAGE 3/4 3-51 3/4 3-54 Movable Incore Detectors................................

Seismic Instrumentation.................................

TABLE 3.3-7 SEISMIC HONITORING INSTRUMENTATION................

3/4 3/4 3/4 3-56 3-57 3-58 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

Meteorological Instrumentation..........................

3/4 3/4 3-59 3-60 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.........

3/4 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-61 3-62 TABLE Remote Shutdown System.....................

3.3-9 REMOTE SHUTDOWN SYSTEM............................

3/4 3/4 3-63 3-64 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................

Accident Monitoring Instrumentation.....................

TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.............

TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE

.REQUIREMENTS............................................

3/4 3/4 3/4 3/4 3-65 3-66 3-68 3-70 TABLE TABLE 3.3-11 (DELETED)...................................

Metal Impact Monitoring System..........................

Radioactive Liquid Effluent Monitoring Instrumentation..

3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.........................................

3/4 3/4 3/4 3/4 3-73 3-74 3-75 3-76 TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............

3/4 3-79 TABLE Radioactive Gaseous Effluent Monitoring Instrumentation.

3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.........................................

3/4 3/4 3-82 3-83 TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............

3/4 3-86 3/4.3.4 (DELETED) ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~

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3/4 3-89 I

SHEARON HARRIS - UNIT 1

vi Amendment No. yg,g5

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3.0/4.0 BASES SECTION INDEX PAGE 3 4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINEERED FEATURES ACTUATION SYSTEM INSTRUMENTATION......

SAFETY 3/4.3. 3 MONITORING INSTRUMENTATION...............................

3/4.3.4 (DELETED)...............'.................................

3 4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION............

3/4.4.2 SAFETY VALVES............................................

3/4.4.3 PRESSURIZER...................................-....-.....

3/4.4.4 RELIEF VALVES............................-......

3/4.4.5 STEAM GENERATORS.........................................

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE...........................

3/4.4.7 HEMISTRY................................................

C 3/4.4.8 SPECIFIC ACTIVITY........................

3/4.4. 9 PRESSURE/TEMPERATURE LIMITS........

3 4.0 APPLICABILITY..............................................

3 4.1 REACTIVITY CONTROL SYSTEMS-3/4.1. 1 BORATION CONTROL.........................................

3/4.1.2 BORATION SYSTEMS.........................................

3/4.1.3 MOVABLE CONTROL ASSEMBLIES...............................

3 4. 2 POWER DISTRIBUTION LIMITS..................................

3/4.2.1 AXIAL FLUX DIFFERENCE....................................

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.......

FIGURE 8 3/4.2-1 (DELETED).......................................

3/4.2.4 QUADRANT POWER TILT RATIO.......................

3/4.2.5 DNB PARAMETERS...........................................

8 3/4 0-1 8 3/4 1-1 8 3/4 1-2 8 3/4 1-3 8 3/4 2-1 8 3/4 2-1 8 3/4 2-2 8 3/4 2-3 8 3/4 2-5 8 3/4 2-6 8 3/4 3-1 8 3/4 3-3 8 3/4 3-6 I

8 3/4 4-1 8 3/4 4-1 8 3/4 4-2 8 3/4 4-2 8 3/4 4-2 8 3/4 4-3 8 3/4 4-4 8 3/4 4-5 8 3/4 4-6 SHEARON HARRIS

'- UNIT 1 X111 Amendment No. 7 55

INSTRUHENTATION 3 4.3.4 TURBINE OVERSPEED PROTECTION - DELETED SHEARON HARRIS - UNIT I 3/4 3-89 Amendment No.

INSTRUMENTATION BASES 3 4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING 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 and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will 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 GASEOUS RADWASTE TREATMENT 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.

The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent release requirements of Specification 3.11.2.2 shall be such that concentrations as low as 1 x 10'Ci/ml are measurable.

3 4.3.4 DELETED SHEARON HARRIS - UNIT 1 B 3/4 3-6 Amendment No. gg