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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems ML20095L0231995-12-22022 December 1995 Proposed Improved TS & Bases,Allowing Flexibility to Install Main Stack Rms (Mod 5386) W/O Need for Addl Licensing Actions & Addressing Annotations to Reflect pre- & post-mod Scenarios,Respectively ML20095J1321995-12-21021 December 1995 Proposed Tech Specs,Consisting of Change Request 95-08, Eliminating Outdated Matl from FOLs & Making FOL for Unit 2, Consistent W/Fol for Unit 3 ML20095J7011995-12-19019 December 1995 Proposed Tech Specs Re Administrative Change to Ventilation Filter Testing Program ML20095A1731995-11-30030 November 1995 Proposed Tech Specs,Changing Minimum Allowable Control Rod Scram Accumulator Pressure & Charging Water Header Pressure from Value of 955 Psig to Value of 940 Psig ML20094R2971995-11-22022 November 1995 Revised,Proposed TS Pages 147,157 & 158 Re Early Implementation of Improved TS Section 3.4.3 ML20094Q6801995-11-21021 November 1995 Proposed Tech Specs Re SR for High Pressure Test of HPCI & B 3.5-14 & B 3.5-28.Administrative Change Proposed to Eliminate Ref to Section Previously Eliminated ML20092A2141995-09-0101 September 1995 Proposed Tech Specs,Consisting of Change Request 95-07, Deleting License Condition 2.C ML20092A2841995-08-30030 August 1995 Proposed Tech Specs,Requesting Enforcement Discretion from Portion of FOL Condition 2.C ML20092B9871995-08-28028 August 1995 Proposed Improved Tech Specs ML20087E8881995-08-0404 August 1995 Proposed Tech Specs Re Implementation of New SR Associated W/Conversion to TS 1999-09-27
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems 1999-09-27
[Table view] |
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ATTACHMENT 2 PEACH BOTTON ATOMIC POWER STATION Units 2 and 3 Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 TECHNICAL SPECIFICATION CHANGES List of Attached Pages l
75 '
84 93 97 182 183 (Unit 2, Unit 3) 200 l-l-
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f 1,
9001080067 '891228- -
o fDR ADOCK 05000277 PDC-1
TABLE 3.2.0 .
~
RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS Minimum No.
of Operable No. of Instrument Action Instrument Channels Provided (2)
Channels (1) Trip Function Trip Level Setting by Design g
2 Refuel Area Exhaust Upscale, <16 mr/hr 4 Inst. Channels - A or B Monitor 2 Reactor Building Area Upscale. <16 mr/hr 4 Inst. Channels B Exhaust Monitors 1(3) Main Stack Monitor Upscale, <106 cps 2 Inst. Channels C NOTES FOR TABLE 3.2.D
- 1. Whenever the systems are required to be operable, the specified number of instrument channels shall be operable or y placed in the tripped condition. If this cannot be met, the indicated action shall be taken.
I
- 2. Action A. Cease operation of tSe refueling equipment.
B. Isolate secondary cor.tainment and start the standby gas treatment system.
C. Cease purging of primary containment, and close vent and purge valves greater than 2 inches in diameter.
- 3. The trip function is required to be operable only when the containment is purging through the SGTS and containment integrity is required. If both radiation monitors are out of service, action shall be taken as indicated in Note 2, (C).
i l
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TAB 7T 4.2.D . . .
~ '
MINIMUM TEST & CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS , _
Instrument Functional Instrument Instrument Channels Test Calibration. Check (2)
'1) Refuel Area Exhaust (1) Once/3 months Once/ day Monitors - Upscale
- 2) Reactor Building Area (1) Once/3 months Once/ day
- 3) Main Stack Monitor Once/3 months Once/12 months Once/ day as described in 4.8.C.4.a logic System Functional Test (4) (6) Frequency-In i 1) Reactor Building Isolation Once/6 months
- 2) Standby Gas Treatment Once/6 months System Actuation 0
_ _ _ - , _. .v-- . . - - -,- r ~- , , + - - . . - , - - - . , - - - -- *--we. % . . . - -..e.- v , - - . . .. -- - + ,s-e- o v. ,v
L .*
,. PBAPS
'3.2 BASES (Cont'd)
, Four sets of two radiation monitors are provided which t initiate the Reactor Building Isolation function and operation of
- the standby gas treatment system. Four instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor. Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.
Trip settings of less than 16 mr/hr for the monitors in the refteling area ventilation exhaust ducts are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.
Two channels of nonsafety-related radiation monitors are provided in the main stack. Trip signals from these monitors are required only when purging the containment through the SGTS and containment integrity is required. The trip signals isolate primary containment vent and purge valves greater than 2 inches in diameter to prevent accidental releases of radioactivity offsite when the valves are open. This signal is added to fulfill the requirements of item II.E.4.2(7) of NUREG-0737.
I Flow integrators are used to record the. integrated flow of liquid from the drywell sumps. The integrated flow is indicative of reactor coolant leakage. A Drywell Atmosphere Radioactivity Monitor is provided to give supporting information to that supplied by the reactor coolant leakage monitoring system. (See Bases for 3.6.C and 4.6.C)
Some of the surveillance instrumentation listed in Table 3.2.F are required to meet the accident monitoring requirements of NUREG-0737, Clarification of TMI Action Plan Requirements. >
This instrumentation and the applicable 11UREG-0737 requirements are:
- 1. Wide range drywell pressure (II.F.1.4)
- 2. Subatmospheric drywell pressure (II.F.1.4)
- 3. Wide range suppression chamber water level (II.F.1.5)
- 4. Main stack high range radiation monitor (II.F.1.1)
- 5. Reactor building roof vent high range radiation monitor (II.F.1.1)
- 6. Drywell hydrogen concentration analyzer and monitor (II.F.1.6) ;
- 7. Drywell high range radiation monitors (II.F.1.3) 8.
Reactor Water Level - wide and fuel range (II.F.2)
- 9. Safety-Relief Valve position indication (II.D.3) .
t PBAPS F
'4.2 BASES (Cont'd)
The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment ;
operation are arranged in a 1 out of 2 twice logic system. The ,
bases given above for the rod blocks apply here also and were used to arrive at the functional testing frequency. The air ejector off-gas monitors are connected in a 2 out of 2 logic I arrangement. Based on the experience with instruments of similar '
design, a testing interval of once every three months has been found adequate.
Radiation monitors in the main stack which initiate containment isolation are not safety-related and are required
, only during containment purging through the SGTS and when containment integrity is required, an activity which occurs ,
infrequently. Therefore, a twelve (12) month calibration interval is appropriate.
The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.
l i
. PBAPS :
, NOTES FOR TABLE NO. 3.7.1
C = Closed SC = Stays Closed '
GC = Goes Closed Note: Isolation groupings are as follows: !
GROUP'lt The valves in Group 1 are actuated by any one of the I following conditions: '
- l. Reactor vessel low-low-low water level. {
- 2. Main steam line high radiation.
- 3. Main steam line high flow.
4.. Main steam line space high temperature.
- 5. Main steam line low pressure (RUN mode only).
GROUP 2A: The valves in Group 2A are actuated by any one of the -
following conditions:
- 1. Reactor vessel low water level.
- 2. Reactor water cleanup system heat exchanger discharge high temperature.
- 3. Reactor water cleanup system suction line break.
- 4. Standby liquid control system actuation.
GROUP 2B: The valves in Group 2B are actuated by any one of the following conditions:
- 1. Reactor vessel low water level.
- 2. High drywell pressure, i
- 3. Reactor high pressure of shutdown mode.
GROUP 2C: The valves in Group 2C are actuated by any one of the following conditions:
- 1. Reactor low water level.
- 2. High reactor vessel pressure. (600 PSIG)
- 3. High drywell pressure.
GROUP 2D: The valves in Group 2D are actuated by the following -
conditions: .
- 1. High drywell pressure.
- 2. Reactor low water level.
-182-1
c ..
. PBAPS 1 NOTES POR TABLE NO. 3.7.1 (Cont'd) '
GROUP 3: The valves in Group 3 are actuated by any one of the following i conditions:
- 1. Reactor vessel low water level. I
- 2. High drywell pressure.
- 3. Reactor building ventilation exhaust high radiation.
- 4. Refuel floor ventilation exhaust high radiation.
- 5. Main stack high-high radiation during containment purging ,
through SGTS (vent and purge valves greater than two inches in diameter only). i
{
GROUP 4: :
The valves in Group 4 are actuated by any one of the following '
conditions:
- 1. HPCI steam line high flow. !
- 2. HPCI steam line space high temperature. i
- 3. HPCI steam line low pressure. (except for HPCI steam line '
exhaust drain valve AO-4247)
C100P 4A: The valves in Group 4A are actuated by either of the following conditions:
- 1. Reactor vessel low-low water level. *
- 2. High drywell pressure.
- GROUP 4B: The valve in Group 4B is actuated when both of the following conditions are present: l
" 1. High drywell pressure.
- 2. HPCI steam line low pressure.
GROUP 5: The valves in Group 5 are actuated by any one of the following conditions: '
- l. RCIC steam line high flow. '
- 2. RCIC steam line space high temperature. !
- 3. RCIC steam line low pressure.
GROUP SA: The valves in Group SA are actuated by the following condition:
- 1. Reactor vessel low-low water level. -
GROUP SB: The valve in Group SB is actuated when both of the following '
conditions are present:
- 1. High drywell pressure.
- 2. RCIC steam line low pressure.
-183-
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o NOTES POR TABLE NO. 3.7.1 (Cont'd) ;
l GROUP 3: The valves in Group 3 are actuated by any one of the following conditions: '
i
- 1. Reactor vessel low water level, i
- 2. High drywell pressure.
- 3. Reactor building ventilation exhaust high radiation. ;
- 4. Refuel floor ventilation exhaust high radiation.
- 5. Main stack high-high radiation during containment purging
.through SGTS (vent and purge valves greater than two inches in diameter only).
GROUP 4:
The' valves in Group 4 are actuated by any one of the following l conditions:
- 1. HPCI steam line high flow. :'
- 2. HPCI steam line space high temperature.
- 3. HPCI steam line low pressure. (except for HPCI steam line exhaust drain valve AO-5247)
GROUP 4A The valves in Group 4A are actuated by either of the following ;
conditions: "
- 1. Reactor vessel low-low water level.
- 2. High drywell pressure. l l
GROUP 4B: The valve in Group 4B is actuated when both of the following conditions are present:
- 1. High drywell pressure.
- 2. HPCI steam line low pressure.
GROUP 5: The valves in Group 5 are actuated by any one of the following i conditions: j '
- l. RCIC steam line high flow.
- j. 2. RCIC steam line space high temperature.
1
- 3. RCIC steam line low pressure.
GROUP SAs- The valves in Group 5A are actuated 5y the following condition:
- 1. Reactor vessel low-low water level.
GROUP SB: The valve in Group SB is actuated when both of the following conditions are present:
- 1. High drywell pressure.
- 2. RCIC steam line low pressure.
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PBAPS
- Group 2D - line (traveling in-core probe) is isolated on high drywell pressure or reactor low water level (538"). This is to ,
assure that this line does not provide a leakage path when containment pressure indicates a possible accident condition.
Group 3: Actuation for isolation of valves and dampers associated with the ventilation systems. Group 3 lines are connected to the primary containment but not directly to the reactor vessel. These ,
valves are isolated on reactor low water level (538"), high drywell pressure, reactor building ventilation high radiation which would indicate a possible accident and necessitate primary containment isolation, or refueling floor ventilation high radiation which would indicate a possible refueling accident or main stack high-high radiation (a nonsafety-related signal) during containment purging -
thrcugh SGTS in accordance with Section 3.8.C.8a. The group 3 '
isolation signals, with the exception of main stack high-high radiation, also " isolate" the reactor building and start the Standby Gas Treatment System. It is not desirable to actuate the group 3 1 isolation signal by a transient or spurious signal. ,
The main stack high-high radiation signal (which is nonsafety-related in accordance with NUREG-0737) will isolate only those vent and purge valves which are greater than two inches in diameter during containment purging.
Groups 4 and 5: Actuation associated with process lines that are designed to remain operable and mitigate the consequences of an accident which results in the isolation of other process lines. The signals which initiate isolation of Group 4 and 5 process lines are therefore indicative of a condition which would render them inoperable. Groups 4 and 5 are subdivided as follows: '
Group 4A: - process lines are closed on reactor low water level (490") or high drywell pressure. These close on the same signal that initiates HPCIS to ensure that the valves are not open when HPCIS action is required.
Group 4B - line is isolated on high drywell pressure if the EPCI System has been rendered inoperable by low steam line pressure.
Group SA process lines are closed only on reactor low water level (490"). These close on the same signal that initiates RCICS to ensure that the valves are not open when RCICS action is required.
Group SB - line is isolated on high drywell pressure if the RCIC !
system has been rendered inoperable by low steam line pressure. I i
The maximum closure times for the automatic isolation valves of the I primary containment and reactor vessel isolation control system have ;
been selected in consideration of the design intent to prevent core uncovering following pipe breaks outside the primary containment and the need to contain released fission products following pipe breaks inside the primary containment.
-200-