ML20046D208

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Proposed Tech Specs Section 3/4.3.7.10, Loose Part Detection Sys, Relocating Loose Part Detection Instrumentation from TS to Administrative Control
ML20046D208
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/11/1993
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20046D205 List:
References
GNRO-93-00088, GNRO-93-88, NUDOCS 9308160330
Download: ML20046D208 (8)
v • d • e


Text

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Attachment 3 to GNRO-93/00088 l

. Page 1 of 4 W

MARKED-UP TECHNICAL SPECIFICATION PAGES LOOSE PART DETECTION SYSTEM (GGNS PCOL-93/07) i

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Attachment 3 to GNRO-93/00088

, Page 2 of 4

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INSTRUMENTATION

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LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FdR OPERATION pttMED 3.3.7.10 7 he. loose part detection systed 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 Commis-sion pursuant to Specification 6.9.2 within the next 10 days outlining the 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.

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SURVEILLANCE REQUIREMENTS 96LETED 4.3.7.10 sEach channel of the loose part detection system shall be demons ~trated 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 i c. CHANNEL CALIBRATION at least once per 18 months.

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GRAND GULF-UNIT 1 3/4 3-90 Amendment No. 69 l:

i INSTRUMENTATION Attachment 3 to GNRO-93/00088 Page 3 of I BASES

'p5LETE D 3/4.3.7.10 LOOSE-PART DETECTIC4 SYSTEM

-> The OPERABILITY of the loose-part detection system ensures that sufficient l capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The system consists of 16 sensors, of which only 8 are selected and need to be OPERABLE at a time, to provide the inputs to the 8 monitoring channels. The remaining 8 sensors may be used as replacement sensor inputs for-failed sensors or to provide a ,

change in location of the area being monitored. Thn allowacle out-of-service times and surveillance requirements are consistent sith the reccmendations of Regulatory Guide 1.133, " Loose-Part Detection Progran for the Primary System of Light-Water-Cooled Reactors," May 1981. ~~- ~

3/4.3.7.12 MAIN CONDENSER OFFGAS TREATMENT SYSTEM - EXPLOSIVE GAS MUNITORING SYSTEM INSTRUMENTATION The explosive gas monitoring system instrume.itation af the main c'.sndenser off-gas treatment system is provided to monitor the conceM rations cf potentially explosive gas mixtures in the main condenser offgas treatment system. This instrumentation is calibrated in accordance with plant procedures.

3/4.3.8 PLANT SYSTEMS ACTUATION INSTRUMENTATION The plant systems actuation instrumentation is provided to initiate action to mitigate the consequences of accidents that are beyond the ability of the operator to control. The LPCI mode of the RHR system is automatically initiated on a high drywell pressure signal and/or a low reactor water level, 1 level 1, signal. The containment spray system will then actuate automatically following high drywell and high containment pressure signals. Negative ,

barometric pressure fluctuations are accounted for in the trip setpoints and )

allowable values specified for drywell and containment pressure-high. A 10-  !

minute minimum, 13-minute maximum time delay exists between initiation of LPCI and containment spray actuation. A high reactor water level, level 8, signal will actuate the feedwater system / main turbine trip system. The suppression i pool makeup system is automatically initiated on a low low suppression pool I water level signal with a concurrant LOCA signal or following a specified time  !

delay after receipt of a LOCA signal. The low low suppression pool water level  !

Trip Setpoint and Allowable Value are relative to the surface floor of the I suppression pool (93'01" above mean sea level).

Specified surveillance intervals and surveillance end maintenance outage times have been determined in accordance with General Electric Report GENE-770-06-1, " Bases for Changes to Surveillance Test and Allowed Out-of- 1 Service Times for Selected Instrumentation Technical Specifications", February  !

1991.

Amendment No. 60, sit, 105 GRAND GULF-UNIT I B 3/4 3 .. . . . .. ..

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Attachment 3 to GNRO-93/00088 Page 4 of 4 INDEX i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION................... 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION...................... .. 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION..... 3/4 3-27 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation......... 3/4 3-37 End-of-Cycle Recirculation Pump Trip System  ;

Instrumentation............................................. 3/4 3-41 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION............................................. 3/4 3-47 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION........................... 3/4 3-52 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...................... . 3/4 3-58 Seismic Monitoring Instrumentation.......................... 3/4 3-63 Meteorological Monitoring Instrumentation................... 3/4 3-66 Remote Shutdown System Instrumentation and Controls......... 3/4 3-69 Accident Monitoring Instrumentation......................... 3/4 3-73 Source Range Monitors....................................... 3/4 3-77 Traversing In-Core Probe System............................. 3/4 3-78 Chlorine Detection System................................... 3/4 3-79 Fire Detection Instrumentation (DELETED)... ................. 3/4 3-80 '

Loose-Part Detection System.

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3/4 3-90 Main Condenser Offgas Treatment System - Explosive Gas Monitoring System Instrumentation........................... 3/4 3-91 3/4.3.8 PLANT SYSTEMS ACTUATION INSTRUMENTATION...................... 3/4 3-92 3/4.3.9 TURBINE OVERSPEED PROTECTION SYSTEM.......................... 3/4 3-97 1

i GRAND GULF-UNIT 1 v Amendment No. ' 52, 52.17

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Attachment 4 to GNRO-93/00088 -

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t INFORMATIONAL COPY OF PROPOSED TECHNICAL SPECIFICATION PAGES ,

LOOSE PART DETECTION SYSTEM .-

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-(GGNS PCOL-93/07) .,

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Attachment 4 to GNRO-93/00088 Page 2 of 4 'l 1

. j INSTRUMENTATION j J

LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.10 (Deleted)

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1-i SURVEILLANCE REOUIREMENTS j

4.3.7.10 (Deleted) i l

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i Grand Gulf-Unit 1 '3/4 3-90 Amendment No. 69, t.

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7 Attachment 4 to GNRO-93/00088 Page 3 of 4-INSTRUMENTATION BASES i l

l 3/4.3.7.10 LOOSE-PART DETECTION SYSTEM i l

(Deleted) i 3/4.3.7.12 MAIN CONDENSER OFFGAS TREATMENT SYSTEM - EXPLOSIVE GAS MONITORING SYSTEM INSTR" MENTATION The explosive gas monitoring system instrumentation of the main condenser .

offgas treat- snt system is provided to monitor the concentrations of potentially -

'ocive gas mixtures in the main condenser offgas treatment system. .: Instrumentation is calibrated in accordance with plant j procedures.

3/4.3.8 PLANT ACTUATION INSTRUMENTATION The plant systems actuation instrumentation is provided to initiate action to mitigate the consequences of accidents that are beyond the ability of the. '

operator to control. The LPCI mode of the RHR system is automatically ,

initiated on a high drywell pressure signal and/or a low reactor water level, ,

level ~ 1, signal. The containment spray will then actuate automatically following high drywell and high containment pressure . signals. Negative barometric pressure fluctuations are accounted for in the trip setpoints and- l' allowable values specified for drywell and containment pressure-high. A 10-minute minimum, 13-minute maximum time delay exists between initiation of .

LPCI and containment spray actuation. A high reactor water level,'. level'8,  !

signal will actuate the feedwater system / main - turbine trip system. The. i suppression pool makeup system is automatically initiated on a low low suppression pool water level signal with a concurrent - LOCA signalor

  • following a specified time delay after receipt of a LOCA signal. The low . low suppression pool water level Trip Setpoint and Allowable Value are relative ,

to the surface floor of the suppression pool (93' 01" above mean seaLlevel).

Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with General Electric Report GENE- ,

770-06-1, " Bases for Changes to Surveillance Test and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications", February.1991. ,

. GRAND GULF-UNIT 1 B 3/4.3-6 AMENDMENT NO. 60, 87,:105, ,

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h, Attachment 4 to GNRO-93/00088  ;

- Page 4 of 4 j l

l INDEX -

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS i I

-8ECTION PAGE j 3/4.3 Instrumentation 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION................... 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION......................... 3/4 3-9 i 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.... 3/4 3-27 3.4.3.4 RECIRCULATION' PUMP TRIP ACTUATION' INSTRUMENTATION  !

ATWS Recirculation Pump Trip System Instrumentation....... 3/4 3-37 v

End-of-Cycle Recirculation Pump Trip System Instrumentation.3/4 3-41 l l

3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION............ 3/4 3-47 ~ +

INSTRUMENTATION 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION.......................... 3/4 3-52 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....................... 3/4 3-58 Seismic Monitoring Instrumentation......................... 3/4 3-63 Meteorological Monitoring Instrumentation.................. 3/4 3-66

.i Remote Shutdown System Instrumentation and Controls........ 3/4 3-69 '

Accident Monitoring Instrumentation........................ 3/4 3-73 Source Range Monitors...................................... 3/4 3-77 Traversing In-Core Probe System......... .................. 3/4 3-78 Chlorine Detection System.................................. 3/4 3-79  ;

Fire Detection Instrumentation (DELETED) . . . . . . . . . . . . . . . . . . . 3/4 3-80 Loose-Part Detection System (DELETED) . . . . . . . . . . . . . . . . . . . . . . 3/4 '3-90 Main Condenser Offgas Treatment. System - Explosive Gas Monitoring System Instrumentation.......................... 3/4 3-91  ;

3/4. 3. 8 PLANT SYSTEMS ACTUATION INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . 3/4 3-92.

1 3/4. 3. 9 TURBINE OVERSPEED PROTECTION SYSTEM , . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-97 l GRAND GULF-UNIT 1 v Amendment No. 62, 82, 87, 3,

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