ML20235P027

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Proposed Tech Specs Reflecting Installation of Reactor Vessel Level Monitoring Sys
ML20235P027
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/10/1987
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20235P009 List:
References
NUDOCS 8707200310
Download: ML20235P027 (10)
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Text

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j TABLE 3.3-10 (Continued) ACTION STATEMENTS I ACTION 31 - With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inoperable channel" to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours. ACTION 32 - With the number of OPERABLE post-accident monitoring channels j one lets. than the minimum channel operable requirement in Table 3.3-10, operation may proceed provided the inoperable channel is restored to OPERABLE status at the next outage of sufficient duration. ACTION 33 - With the number of OPERABLE post-accident monitoring channels two less than required by Table 3.3-10, either restore one inoperable channel to OPERABLE status within 30. days or be in HOT SHUTDOWN within the next 12 hours. 9.,. m~- w p r~ ./ ACTION 34 - With the number of OPERABLE Post-Accident Monitoring Channels one less than the minimum Channel OPERABLE requirement in Table 3.3-10, either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days ) ~ following the event, outlining the action taken, the cause of the inoper-Q ability and the plans and schedule for restoring the system to OPERABLE status. ACTION 35 - With the number of OPERABLE Channels two less than required by Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48 hours if repairs are feasible without shutting down or: f I' 1. Initiate an alternate method of monitoring for core and reactor N I coolant system voiding; L -) 2. Prepare and submit a Special Report to the Commission pursuant / to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and 5 3. Restore at least one channel to OPERABLE status at the next scheduled refueling, ^ k v ) / CALVERT CLIFFS - UNIT 1 3/4 3-41a AmendmentNo.,Ilf

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r j. 1 INSTRUMENTATION ~ BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION q l ? The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor i and assess these variables following an accident. This capability is j R consistent with the recommendations of Regulatory Guide 1.97, "Instrumen-tation for Light-Water-Cooled' Noclear Plants ^to' Assess PlantMCoriditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations." D ( 3/4.3.3.7 FIRE DETECTION INSTRUMENTATION ~ ~. i -\\ OPERABIt.ITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of I fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the poten-i- tial for damage to safety related equipment and is an integral element in the overall facility fire protection program. I In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability. W/y- ~ r 8 The Subcooled Margin Monitor (SMM), the Heated Junction Thermocouple (HJTC), and the i [ Core Exit Thermocouple (CET) comprise the Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post TMI-2 Action Plan. The function of the ICC / it. instrumentation is to enhance the ability of the plant operator to diagnose the approach 3 [I to, and recovery from. ICC. Additionally, they aid in tracking reactor coolant if inventory. These instruments are included in the Technical Specifications at the request of NRC Generic Letter 83-37. These instruments are not required by the accident h y analysis, nor to bring the plant to HOT STANDBY or COLD SHUTDOWN. s In the event more than four sensors in a Reactor Vessel Level channel are inoperable, ( repairs may only be possible during an extended COLD SHUTDOWN. This is because the sensors are accessible only after the plant has been cooled down and drained, and the ( missile shield has been moved. If only one channel is inoperable, it should be restored A to OPERABLE status in accordance with the schedule outlined in a Special Report. If / both channels are inoperable, at least one channel shall be restored to OPERABLE status } in the next refueling outage. (NOTE: Repairs to b.01h channels shall be attempted during the refueling outage.) \\ VD^ / CAtvERT CtIFr5 - UNIT 1 B 3/4 3-3 AmendmentNo.25,53,Bef,$)}g' ~. - - __ -_. 7

ADMINISTRATIVE CONTROLS a. ECCS Actuation, Specifications 3.5.2 and 3.5.3. i b. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3. Inoperable Meteorological Monitoring Instrumentation, Specification c. 3.3.3.4. d. Seismic event analysis, Specification 4.3.3.3.2. l d. Core Barrel Movement Specification 3.4.11. f. Fire Detection Instrumentation, Specification 3.3.3.7. ~ g. Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4, and 3.7.11.5. h. Penetration F. ire Barriers, Specification 3.7.12. 1. Steam Generator Tube Inspection Results, Specification 4.4.5.5.a and c. j. Specific Activity of Primary Coolant, Specification 3.4.8. k. Containment Structural Integrity, Specification 4.6.1.6. 3 1. Radioactive Effluents - Ct.lculated Dose and Total Dose, Specifica-tions 3.11.1.2, 3.11.2.2, 3.11.2.3, and 3.11.4. m. Radioactive Effluents - Liquid Radwaste, Gaseous Radwaste and Ventilation Exhaust Treatment Systems Discharges, Specifications 3.11.1.3 and 3.11.2.4. Radiological Environmental Monitoring Program, Specification 3.12.1. n. Radiation Monitoring Instrumentation, Specification 3.3.3.1 o. (Table 3.3-6). p. Overpressure Protection Systems, Specification 3.4.9.3. q. Hydrogen Analyzers, Specification 3.6.5.1. Y. %c - Ace. cans Ssnwam A, Spae,r,es s su L*B 3 G f CALVERT CLIFFS - UNIT 1 6-18a AmendmentNo.,29,#,M5,g*/[

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9 TABLE 3.3-10 (Continued) A ACTION STATEMENTS a ACTION 31 - With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours. ACTION 32 - With the number of OPERABLE post-accident monitoring channels one less than the minimum channel operable requirement in Table 3.3-10, operation may proceed provided the inoperable channel is restored to OPERABLE status at the next outage of sufficient duration. ACTION 33 - With the nuinber of OPERABLE post-accident monitoring channelt two less than required by Table 3.3-10, either restore one inoperable channel to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours. / ., g /- .., j ~ .m \\ ACTION 34 - With the number of OPERABLE Post-Accident Monitoring Channels one less than the minimum Channel OPERABLE requirement in Table 3.3-10, either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the system to i. OPERABLE status. ) ACTION 35 - With the nmber of OPERABLE Channels two less than required by i Table 3.3-10, either restore the inoperable channel (s) to OPERABLE i status within 48 hours if repairs are feasible without shutting down or: \\ 1. Initiate an alternate method of monitoring for core and reactor l l ( coolant system voiding; / j 2. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and \\ 3. Restore at least one channel to OPERABLE status at the next (', scheduled refueling. j / \\ ,I } ~ q, -f^- W "_ l CALVERT CLIFFS - UNIT 2 3/4 3-41a AmendmentNo.h i 1 L_-___-_ \\

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\\. .i \\. t INSTRUMENTATION BASES ~~ j 3/4.3.3.6 POSI-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that 6~ 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, "Instru-mentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 ~ Lessons Learned Task Force Status Report and Short-Term Recommendations." N 3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERA 5ILITY of the fire detection instrtunentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the poten-tial for damage to safety related equipment and is an integral element in the overall facility fire protection program. -{ In the event that a portion of the fire detection instrumentation' is inoperable, the establishment of frequent fire patrols in the affected t. areas'is required to provide detection capability until the inoperable instrumentation is restored to coerability. y-_. -f m_ ~ The Subcooled Margin Monitor (SMM), the Heated Junction Thermocouple (HJTC), and the, Core Exit Thermocouple (CET) comprise the Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post TMI-2 Action Plan. The function of the'ICC instrumentation is to enhance the ability of the plant operator to diagnose the approach to, and recovery from, ICC. Additionally, they aid in tracking reactor ecolant inventory. These instruments are included in the Technical Specifications at the i request of NRC Generic Letter 83-37. These instruments are not required by the accident d analysis, nor to bring the plant to HOT STANDBY or COLD SHUTDOWN. In the event more than four sensors in a Reactor Vessel Level channel are incperable, s l repairs may only be possible during an extended COLD SHUTDOWN. This is because the l sensors are accessible only after the plant has been cooled down and drained, and the missile shield has been moved. If only one channel is inoperable, it should be restored to OPERABLE status in accordance with the schedule outlined in a Special Report. If both channels are inoperable, at least one channel shall be restored to OPERABLE status in the next refueling outage. (NOTE: Repairs to bath channels shall be attempted during the refueling outage.) w w _. m .-/ CALVERT CLIFFS - UNIT 2 S 3/4 3-3 knendment No. 77, 36,E i I c

ADMINISTRATIVE CONTROLS i~h a. ECCS Actuation, Specifications 3.5.2 and 3.5.3. b. . Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3. c. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.44 d. Seismic event analysis, Specification 4.3.3.3.2. e. Core Barrel Movement, Specification 3.4.11. f. Fire Detection Instrumentation, Specification 3.3.3.7. g. Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4, and 3.7.11.5. h. Penetration Fire Barriers, Specification 3.7.12. 1. Steam Generator Tube Inspection Results, Specification 4.4.5.5.a and c. j. . Specific Activity of Primary Coolant, Specification 3.4.8. k. Containment Structural Integrity, Specification 4.6.1.6. i 1. Radioactive Effluents - Calculated Dose and Total Dose, Specifica-tions 3.11.1.2, 3.11.2.2, 3.11.2.3, and 3.11.4. m. Radioactive Effluents -- Liquid Radwaste, Gaseous Radwaste and Ventilation Exhaust Treatment Systems Discharges, Specifications 3.11.1.3 and 3.11.2.4. n. Radiological Environmental Mcnitoring Program, Specification 3.12.1. o. Radiation Monitoring Instrumentation, Specification 3.3.3.1 (Table 3.3-6). p. Overpressure Protection Systems, Specification 3.4.9.3. q. Hydrogen Analyzers, Specification 3.6.5.1. Dem^" H***>*6 c. 7.g Aamn x~wwe-w,.n, AmendmentNo.U,75,E6,g CALVERT CLIFFS - UNIT 2 6-18a - - - -}}

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