ML18005A899

Revised Tech Specs Re Chlorine Detection Sys

ML18005A899
Person / Time
Site:	Harris
Issue date:	05/03/1989
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18005A898	List: ML18005A897 ML18005A899
References
NUDOCS 8905110333
Download: ML18005A899 (6)

Text

ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RETYPED TECHNICAL SPECIFICATION PAGES 8905110333 890503 PDR ADOCK 05000400 P PDC

F INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 3-3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERAT10NS..................................... 3/4 3-51 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS..................... 3/4 3-54 Movable Incore Detectors................................. 3/4 3-56 Seismic Instrumentation. ~ ................................ 3/4 3-57 TABLE 3.3"7 SEISMIC MONITORING INSTRUMENTATION.................... 3/4 3-58 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................. 3/4 3-59 Meteorological Instrumentation........................... 3/4 3-60 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............. 3/4'-61 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE "

REQUIREMENTS............................................. 3/4 3-62 Remote Shutdown System................................... 3/4 3-63 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM................................ 3/4 3-64 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................eo... 3/4 3-65 Accident Monitoring Instrumentation..... .... ....

~ ~ ~ ~ ~ ~ . ~ ~ 3/4 3-66 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-68 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE-.

REQUIREMENTS........... .............................o... 3/4 3-70 TABLE 3.3"11 (DELETED)........................... 3/4 3-73 Metal Impact Monitoring System........................... 3/4 3-74 INSTRUMENTATION' Radioactive Liquid Effluent Monitoring Instrumentation' ~ 3-75 3/4 TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING

......................................... 3/4 3-76 TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS. 3/4 3-79 Radioactive Gaseous Effluent Monitoring Instrumentation.. 3/4 3-82 TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.o.........eo..... ~ ..................o.... 3/4 3-83 TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................ 3/4 3-86

.3/4 '.4 TURBINE OVERSPEED PROTECTION. ~ ............. -............

~ ~ 3/4 3-89 SHEARON HARRIS UNIT 1 v1 Amendment No.

INSTRUMENTATION CHLORINE DETECTION SYSTEMS Specification 3/4 3.3.7 de1eted.

SHEARON HARRIS UNIT 1 3/4 3-72 Amendment No.

PLANT SYSTEMS CONTROL ROOM EMERGENCY FILTRATION SYSTEM SURVEILLANCE RE UIREMENTS (Continued)

Revisions 2, March 1978, and the system flow rate is 4000 cfm

+ 10X 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 0.175Z when tested at a temperature of 30'C and at a relative humidity of 70X in accordance with ASTM D3803.

C ~ 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 0.175X 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 while operating the system at a flow rate of 4000 cfm

+ 10X;

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; Verifying that the heaters dissipate 14 + 1.4 kW when tested in accordance with ANSI N510"1980; and

5. Deleted.

SHEARON HARRIS UNIT 1 3/4 7-15 Amendment No.

~ '

~

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 information is available on selected plant parameters to monitor and assess these variables following an accidents 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.

3/4.3.3.7 DELETED 3/4.3.3.8 DELETED 3/4.3.3.9 METAL IMPACT MONITORING SYSTEM The OPERABILITY of the Metal Impact Monitoring System ensures that sufficient capability is available to detect loose metallic par'ts in the Reactor System and avoid or mitigate damage to Reactor System components. The allowable 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 MONITORING INSTRUMENTATION'he 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.