ML20072R532

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Proposed Tech Specs Re Loose Parts Detection Sys Relocation
ML20072R532
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 08/30/1994
From:
Public Service Enterprise Group
To:
Shared Package
ML20072R517 List:
References
NUDOCS 9409130224
Download: ML20072R532 (5)
v • d • e


Text

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l TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this License Amendment Request:

Technical Soecifications Paces Index ix and xviii 3/4.3.7.9 3/4 3-90 B 3/4.3.7.9 B 3/4 3-6 l

l 9409130224 940830 PDR ADOCK 05000354 P PDR

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87 I INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l SECTION L

i PAGE Tab.le 3.3.7.4-1 Remote Shutdown Monitoring Instrumentation. ... . . .. . . . 3/4 3-75 Table 3.3.7.4-2 Remote Shutdown Systems Controls. . . 3/4 3-77 Table 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Surveillance Requirements.. ............ . ...... 3/4 3-53 j Accicent Monitoring Instrumentation.. ... . ..... . ... 3/4 3-E4-Table 3.3,7.5-1 Accident Monitoring Instrumentation.. . 3/4 3-25 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements. . .., . . .. 3/4 3-67 ,

Source Range Monitors..... . . ..... ....... . . . . 3/4 3-8e g Tra.ersing In-Core Probe System. ......... .. .. ...

3/4 3.-89 Loose-Part Detection Sys D ........ ......... ...... ... ~

3/4 3-90

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Radioactive Liquid Effluent Monitoring Instrumentation. .

3/4 3-91 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation........ ... 3/4 3-92 Table 4.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance l Requirements............................ 3/4 3-94 Radioactive Gaseous Effluent Monitoring Instrumentation... 3/4 3-96 Table 3.3.7.10-1 Radicactive Gaseous Effluent Monitoring Instrumentation.......... . 3/4 3-97 Table 4.3.7.10-1 Radioactive Gaseous Effluent Monitor'ing

. Instrumentation Surveillance Requirements...................... ... '3/4 3-100 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM.... .................. 3/4 3-103 3/4.3.9 TEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................... 3/4 3-105 Table 3.3.9-1 Feedwater/ Main Turbine Trip System Actuation Instrumentation................. 3/4 3-106.

HOPE-CREEK ix-

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. INDEX I BASES I

SEC?!ON PAGE INSTRUMENTATICN (Continued) i Seismic Mnnitoring Instrumentation.. ....... ... B 3/4 3-4 Meteorological Monitoring Instrumentation. . . . ...

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B 3/4 3-4 l Remote Shutdown Monitoring Instrumentation ,

and Controls... .......... .... .. . .. .

B 3/* 3-5 Accident Monitoring Instrumentation.. .. . . .. ... B 3/4 3-5

. ,- Source Range Monitors.. . ......... . . . .

..... B 3/4 3-5 Dek Traversing In-Core Probe Sy" stem.

. . . .. . .. B 3/4 3-5  !

Loose-Part Cetection System... . . ..... . ... .. B 3/4 3-6  :

Radioactive Liquid Effluent Monitoring 1 Instrumentation..... . ... ... ............. .. B 3/4 3-6 Radioactive Gaseous Effluent Monitoring Instrumentation. . .. .

.................. . . .. B 3/4 3-6 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM. .. ...... ..... B 3/4 3-7  :

3/4.3.9 FEE 0 WATER /MiIN TURBINE TRIP SYSTEM ACTUAT*0N .

INSTRUMEN(ATION... . ... ............ .... .. .. B 3/4 3-7 Figure B1/4 3-1 Reactor Vessel Water Level. . '.. B 3/4 3-8  ;

3/4.4 #EACTOR COOLANT SYSTEM '

3/4.4.1 RECIRCULATION SYSTEM. ... . ... ... . .. . B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.... .. . . . .. . .. B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.... .. . . ..... .. .. . B 3/4 4-3 Operational Leakage.... .......... . ..... ........ B 3/4 4-3 3/4.4.4 CHEMISTRY,........... .

... . ................... B 3/4 4-3 P

3/4.4.5 SPECIFIC ACTIVITY. . .. .... ...... ......... ... B 3/4 4-4 I 3/4.4.6 PRESSURE / TEMPERATURE LIMITS. ........ ... ... .. . B 3/4 4-5 Table B3/4.4.6-1 Reactor Vessel Toughness. . B 3/4 4-7 Figure B3/4.4.6-1 Fast Neutron Fluence - ~ ~"

(E>1Mev) at (1/4)T as a Function of Service Life.. . . B 3/4 4-8 e HOPE CREEK xviii Amendment No. 3 l

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM i LIMITING CONDITION FOR OPERATION 3.3.7.9 The loose part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION: .

a. With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commiss'On pursuant to Specification 6.9.2 within the next 10 days cutlining t*e cause of the malfunction and the plans for restoring the channel /s) to OPERABLE status.
b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.9 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of a:

a. CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
c. CHANNEL CALIBRATION at least once per 18 months.

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Tars pmE. ImmTI.tu ALLM LEFT MR HOPE CREEK 3/4 3-90 Amendment,No.,19 , ,. ._.. ,

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]NSTRUMENTATION BASES MONITOR]NG INSTRUMENTATION (Continued) 3/4.3.7.8 The material originally contained in Section 3/4.3.7.8 was deleted with the issua'nce of the Full Power License, ilowever, to maintain numerical con-  ;

tinuity between the succeeding sections aid existing station procedural references to those Technical Specifications Sections, 3/4.3.7.8 has been

' intentionally left blank.

3/4.3.7.9 LOOSE-PART DETECTION SYSTEM ( DEtETEM l f_

The OPERABILITY of the loose part detection system ensures that sufficient capabiitty is available to detect loose metallic parts in the primary systern and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recorr- l mendations of Regulatory Guide 1.133. " Loose-Part Detection Program for the System of Light- ater-Cooled Reactors," May 1981. g 3/4.3.7.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluen't monitoring instrumentation is provided to monitor and control, as applicable, the. releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarn/ trip setpoints for these instruments shall be calculated and adjusted in 1 accordance with the methodology and parameters in the 00CM to ensure that the alare/ trip will occur prior to eFr9eding the limits of 10 CFR Part 20.. The OPERA 8ILITY and use of this instramentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. ,

i 3/4.3.7.11 RADI0 ACTIVE GASE0US EFFLUENT DONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual er potential releases of gaseous' effluents. The alare/ trip setpoints for these lastruments shall be calculated and adjusted in accordance with the methodology and parameters in the 00CM. This will ensure the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

i This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially amplosive gas mixtures in the mein condenser offees treatment system. The OPERABILITY and use of this instrumentation 4s consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

i lePE CREEK t 3/4 3-6 Amendment 2o. 30 .

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