ML18106A309

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Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation
ML18106A309
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/02/1998
From:
Public Service Enterprise Group
To:
Shared Package
ML18106A303 List:
References
NUDOCS 9802130022
Download: ML18106A309 (5)
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Text

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LR-N980055 ATTACHMENT 1 SALEM GENERATING STATION UNIT NO. 1 FACILITY OPERATING LICENSE DPR-70 DOCKET NO. 50-272 CHANGE TO TECHNICAL SPECIFICATION BASES RADIATION MONITOR TECHNICAL SPECIFICATION BASES PAGES WITH PROPOSED CHANGES The following Technical Specification Bases pages for Facility Operating License No.

DPR-70 are affected by this supplement:

Technical Specification Page B 3/4.3.3.1 3/4 3-2 (double sided includes 3/4 3-2a)

B 3/4.3.3.8 3/4 3-3 B 3/4.3.3.9 3/4 3-3a 1:-----;;;~~:-=-::-=--=-------

i! 9802130022 980202 '

r; PD.R ADOCK 05000272

, p . PDR

INSTRUMEN,TATION BASf.S

~

3/4.3.3.l RADIATION MONITORING INSTRUMENTATION (Continued)

CROSS REFERENCE - TABLES 3.3-6 AND 4.3-3 T/S Tab1e :Instrumen*t Description Acceptab1e RMs

Item No. Channe1s la Fuel Storage Area lRS or 1R9 lb Containment Area 1R44A and B 2ala Containment Gaseous Activity Purge & 1Rl2A or 1R41A, Pressure/Vacuum Reli~f Isolation and D< 1 > <2 >

2alb Containment Gaseous Activity RCS Leakage 1Rl2A Detection 2a2a Containment Air Particulate Activity Purge & lRllA Pressure/Vacuum Relief Isolation 2a2b Containment Air Particulate Activity RCS lRllA Leakage Detection 2bl Noble Gas Effluent Medium Range Auxiliary 1R41B Building Exhaust System (Plant Vent) (1) (3) (5)

.& D 2b2 Noble Gas Effluent High Range Auxiliary 1R41C &D ( 1 > ' 4 > ' 5 >

Building Exhaust System (Plant Vent) 2b3 Noble Gas Effluent Main Steamline Discharge - 1R46 Safety Valves and Atmospheric Steam Dumps 2B4 Noble Gas Effluent Condenser Exhaust System 1Rl5 3a Unit 1 Control Room Intake Channel 1 (to Unit lRlB-1 1 Monitor)

Unit 1 Control Room Intake Channel 2 (to Unit 2RlB-2 2 Monitor)

Unit 2 Control Room Intake Channel 1 (to Unit 2R1B-1

. ~ ,l-toni tor)

-.gllit 2 Control Room Intake Channel 2 (to Unit lRlB-2

. :f--Monitor)

Immediate action{s), in accordance with the LCO Action Statements, means that the required action should be pursued without delay and in a controlled manner.

(1) The channels listed are required to be operable to meet a single operable channel for the Technical Specificiation's "Minimum Channels Operable" requirement.

(2) The setpoint applies to 1R41D. The measurement range applies to 1R41A and B which display in uCi/cc using the appropriate channel conversion factor form cpm to uCi/cc.

SALEM - UNIT 1 B 3/4 3-2 Amendment No. January 28, 1998

INSTRUMENTATION BASES (3) 1R41D is the setpoint channel; 1R41B is the measurement channel.

(4) 1R41D is the setpoint channel; 1R41C is the measurement channel.

(5) The new release rate channel 1R41D setpoint value of 2E4 uCi/sec is within the bounds of the concentration setpoint values listed in Table 3.3-6 (originally for 1R45) for normal a*nd accident plant vent flow rates.

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector used and normalizing its respective output.

3/4.3.3.3 THIS SECTION DELETED 3/4.3.3.4 THIS SECTION DELETED SALEM - UNIT 1 B 3/4 3-2a Amendment No. January 28, 1998

==================================================================

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

3/4.3.3.6 THIS SECTION DELETED 3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is 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, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975.

3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent 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 alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures 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 i s consistent with the requirements of General Design 1

Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

CROSS REFERENCE - TABLES 3.3-12 and 4.3-12 T/S Table Item No. Instrument Description Acceptable ~ Channels la Liquid Radwaste Effluent 1Rl8 Line Gross Activity lb Steam Generator Blowdown 1Rl9A, B, c, and D Line Gross Activity 2a Containment Fan Coolers 1Rl3 A, B, c, D and E Service Water Line Discharqe Gross Activity SALEM - UNIT 1 B 3/4 3-3 Amendment No. January 28, 1998

INSTRUMENTATION BASES

==============================================~~===================

3/4.3.3.9 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 du~ing actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures 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 waste gas holdup 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.

CROSS REFERENCE - TABLES 3.3-13 and 4.3-13 T/S Table Item No. Instrument Description Acceptable :ElMS Channels la Waste Gas Holdup System 1R41A and D (1) (2) "'

Noble Gas Ativity 2a Containment Purge and 1R12A Pressure - Vacuum Relief or (1) (2)

Noble Gas Activity 1R41A and D 3a Plant Vent Header System 1R16 Noble Gas Activity or 1R41A and D (1) (2) 3b Plant Vent Header System lRME 4, 5 (1R41)

Iodine Sampler (3) or 1XT8911 (1R45) 3c Plant Vent Header System lRME 4, 5 (1R41)

(3)

Particular Sampler or 1XT8911 (1R45)

(1) The channels listed are required to be operable to meet a single operable

  • cham:iel for the Technical Specification's "Minimum Channels Operable" requirement.

(2) 1R41D is the setpoint channel. 1R41A is the measurement channel.

(3) Laboratory analysis of the sampler filters ensures that the limits of

.Specification 3.11.2.1 are not exceeded. Alarm/trip setpoints do not apply to these passive components.

SALEM - UNIT 1 B 3/4 3-3a Amendment No. January 28, 1998

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