ML18005A893
| ML18005A893 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/03/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18005A895 | List: |
| References | |
| NPF-63-A-010 NUDOCS 8905110112 | |
| Download: ML18005A893 (7) | |
Text
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Cy 4+*+4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER 8 LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POMER PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 10 License No.
NPF-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power 5 Light Company (the licensee),
dated January 4, 1989, 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.
C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; I
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 (fi) that such activities will be conducted in compliance with the COIINIission's regulations; D.
The issuance of this 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 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-63 is hereby amended to read as follows:
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(2)
Technical S ecifications and Environmental 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. 10, are hereby incorporated into this license.
Carolina Power 5 Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 3, 1989 Original Signed By:
Elinor G. Adensam, Director Project Directorate II-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation a~ma
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OFFICIAL RECORD COPY
ATTACHMENT TO LICENSE AMENDMENT NO. 10 FACILITY OPERATING LICENSE NO.
NPF>>63 DOCKET 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 V1 3/4 3-72 3/4 7-15 B3/4 3-5 Insert Pa es V1 3/4 7-15 B3/4 3-5
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION TABLE 3-3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
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TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLAhT OPERATIONS SURVEILLANCE REQUIREMENTS' ....................
Movable Incore Detectors.................................
Seismic Instrumentation..................................
TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION....................
TABLE 4.3-4 SEISHIC HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS....o..oo.....os'...o.oo
~....N.NN.NN.....N.NN Meteorological Instrumentation.............,.............
TABLE 3.3-8 HETEOROLOGICAL HONITORING INSTRUMENTATION.............
TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUHENTATION SURVEILLANCE REQUIREMENTS.....s..
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Remote Shutdown System...................................
TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM...............
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TABLE 4.3"6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........
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Accident Monitoring Instrumentation..
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TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.N..~.............
TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS'
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TABLE 3.3-11 (DELETED) ~......
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Metal Impact Monitoring System....
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Radioactive Liquid Effluent Monitoring Instrumentation.
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TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.~ ~ o..s.
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TABLE 4N3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMKNTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
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Radioactive Gaseous Effluent Monitoring Instrumentation.
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TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.~ ~. ~ ~ ~ ~... ~......
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~.......N TABLE 4.3-9 RADIOACTIVE GASKOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
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3/4'.4 TURBINE OVERSPEED PROTECTION. ~.. ~....
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PAGE 3/4 3-51 3/4 3-54 3/4 3-56 3/4 3-57 3/4 3-58 3/4 3-59 3/4 3-60 3/4 3"61 3/4 3-62 3/4 3"63 3/4 3"64 3/4 3-65 3/4 3-66 3/4 3-68 3/4 3-70 3/4 3"73 3/4 3"74 3/4 3"75 3/4 3-76 3/4 3-79
.3/4 3-82 3/4 3-83 3/4 3-86 3/4 3-89 SHEARON HARRIS - UNIT 1
v1 Amendment No.
10
INSTRUMENTATION CHLORINB'DETECTION SYSTEMS Specification 3/4 3.3.7 de1eted.
SHEARON HARRIS - VNIT 1 3/4 3-72 Amendment No. 5>
10
PLANT SYSTEMS CONTROL ROOM EMERGENCY FILTRATION SYSTEM SURVEIf.LANCE RE UIREMENTS (Continued)
Revisions 2, March 1978, and the system flow rate is 4000 cfm
+
LOZ during system operation when tested in accordance with ANSI N510-1980; and 2.
Verifying, within 31 days after removaL, that a Laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the Laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revi-sion 2, March 1978, by showing a methyl iodide penetration of less than 0.175X when tested at a temperature of 30'C and at a
relative humidity of 70X in accordance with ASTM D3803.
Co After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, within 31 days after removaL, that a Laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Posi-tion C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position.C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, by showing a methyL iodide penetration of less than 0.175Z when tested at a temperature of 30'C and at a relative humidity of 70X in accordance with ASTM D3803.
d.
At Least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA fil-ters and charcoal adsorber banks is less than 5.1 inches water gauge awhile operating the system at a flow rate of 4000 cfm
+
LOZ 2.
Verifying that, on either a Safety Injection or a High Radiation test signal, the system automatically switches into an isolation with recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks',
3 ~
Verifying that the system maintains the control room at a
positive pressure of greater than or equal to 1/8 inch Water Gauge at less than or equaL to a pressurization flow of 315 cfm relative to adjacent areas during system operation; 4.
Verifying that the heaters dissipate 14
+ 1.4 kW when tested in accordance with ANSI N510-1980>
and S.
Deleted.
SHEARON HARRIS - UNIT 1 3/4 7-15 Amendment No.
10
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INSTRUMENTATION BASES REMOTE SHUTDOWN SYSTEM (Continued)
This capability is consistent with General Design Criterion 3 and Appendix R
to 10 CFR Part 50.
3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that suffi-cient informatio~'s available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 3, "Instrumentation for Light-Water-CooLed Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG-0737, "Clarification of TMI Action Plan Requirements.,"
November 1980
'/4.3.3.7 DELETED 3/4 '.3.8 DELETED 3/4.3.3.9 METAL IMPACT MONITORING SYSTEH The OPERABILITY of the Metal Impact Monitoring System ensures that sufficient capability is available to detect loose metallic parts'n the Reactor System and avoid or mitigate damage to Reactor System components.
The allo~able out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Guide 1. 133, "Loose-Part Detection Program for the Primary System of Light"Water-Cooled Reactors,"
May 1981.
3/4.3.3.10 RADIOACTIVE LI UID EFFLUENT HONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and con" trol, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The Alarm/Trip Set-points 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.
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.
SHEARON HARRIS - UNIT 1
B 3/4 3-5 Amendment No.
10