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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests ML20059B0351993-10-15015 October 1993 Proposed Tech Specs Converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20057C7281993-09-23023 September 1993 Proposed Tech Specs Removing Surveillance Requirement 4.4.1.2.2 Due to Problems Encountered W/Jet Pump Differential Pressure Instrumentation Measurements ML20056E4511993-08-12012 August 1993 Proposed Tech Specs 3/4 6-3,6-4,6-4a,6-6,6-12 Re Exemption to 10CFR50,App J, Primary Reactor Containment..., for Local Leak Rate ML20056D5621993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.5 Reflecting Relocation of Certain Accident Monitoring Instrumentation to Administrative Control ML20046D2081993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.10, Loose Part Detection Sys, Relocating Loose Part Detection Instrumentation from TS to Administrative Control ML20046D1961993-08-11011 August 1993 Proposed Tech Specs Supporting Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7141993-07-15015 July 1993 Proposed Tech Specs Removing Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve 1999-08-20
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20210F6651997-12-22022 December 1997 Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations ML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6101994-01-14014 January 1994 Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220 ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20029D6451993-11-30030 November 1993 Reactor Containment Bldg 1993 Integrated Leakage Rate Test. ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests 1999-08-20
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GrAo - 95/co D I 7 Endese 1
% cf I .T l CONTAINMENT SYSTEMS 3/4.6.2 DRYWELL DRYWELL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.2.1 DRYWELL INTEGRITY shall be maintained.
APPLICABILITY: OPERATIONAL CONDITIONS 1, nd 3.
ACTION:
Without DRYWELL INTEGRITY, restore DRYWELL INTEGRITY within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REOUIREMENTS ,
I 4.6.2.1 DRYWELL INTEGRITY shall be demonstrated:
- a. At least once per 31 days by verifying that all drywell penetra-tions** not capable of being closed by OPERABLE drywell automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except for valves that are opened under administrative control as permitted by Specification 3.6.4. j
- b. By verifying the drywell air lock is in compliance with the )
requirements of Specification 3.6.2.3.
- c. By verifying the suppression pool is in compliance with the requirements of Specification 3.6.3.1.
- d. By verifying drywell bypass leakage is less than or equal to 10% of the bypass leakage limit at least once per 18 months.
(Not required to be performed until entry into MODE 2 on the first plant startup from the eighth refueling outage.)
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l MS : Sp:: h! Te t E : g tien 3.10. b
- Except valves, blind flanges, and deactivated automatic valves which are located inside the drywell or containment and are locked, sealed or otherwise secured in the clored position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed more often than once per 92 days.
GRAND GULF-UNIT 1 3/4 6-13 Amendment No. M ,102 l 9502240194 950214 1 PDR ADOCK 05000416 W ___ __ __ __ ___ CD
GNRO-95/00017 Enclosure 3 Page 1 of 1 Additional Information Concerning the Pretreatment Radiation Monitor Following the implementation of NEDO-31400,to minimize nuisance alarms GGNS has chosen to use an Offgas Pretreat Hi radiation alarm setpoint of either 2x the normal background radiation at the detector location or 20 mR/hr, whichever is greater. The Offgas Pretreat Radiation Hi and Hi-Hi trips have an alarm only function with no automatic actions. Current Technical Specification section 3.11.2.7 requires "The gross radioactivity (gamma) rate of the noble gases measured at the Offgas recombiner effluent shall be limited to less than or equal to 380 millicuries /second, after 30 minutes decay". If this specification is exceeded, the Specification requires the release rate to be restored to its limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The Offgas Pretreat Radiation Hi-Hi setpoint is calculated using a conservative equation to help ensure this Technical Specification limit is not exceeded. This equation is inversely proportional to the Offgas flowrate. This Hi-Hi alarm setpoint ensures that the NEDO-31400 Section 7 assumptions for the Offgas pretreatment monitor are met, since the NEDO states that a change associated with a noble gas release rate in the range of 1 to 10 Ci/sec would be promptly annunciated. In addition, implementation of Technical Specification Section 4.11.2.7.2.b requires the gross radioactivity release rate of the noble gases from the main condenser air ejector be determined to be within the limits of Specification 3.11.2.7 by performing an isotopic analysis of a representative sample of gases taken at the offgas recombiner effluent fo!!owing a 50% increase in 4 hrs or a 100 mr/hr reading as indicated by the Offgas Pretreatment Monitor. Using conservatively typical values, a Hi setpoint of 2x background would be less than 1% of the Hi-Hi setpoint and 20 mR/hr would be on the order of 0.3% of the Hi-Hi setpoint, both with an assumed offgas flowrate of 50 cfrn.
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GNRO-95/00017 Enclosure 4 Page 1 of 6 Discussions of Changes: i LA.2 The details of the methods and acceptance values for these tests are relocated from the Technical Specifications to the UFSAR and Technical Specification Bases and the control of 10CFR50.59. The v:.iues are system design values which are additional control by design change procedures and regulations. l LA.3 These motor operated valves are required to be cycled in accordance with the ASME Section XI Inservice Testing (IST) Program as specified in the Administrative Controls Section of the proposed Technical Specifications. Consistent with the BWR Standard Technical Specifications, NUREG-1434, these IST details are not repeated in the proposed Technical Specifications. The requirement for this testing is relocated from the Technical Specifications to the UFSAR and Technical Specification Bases and the control of 10CFR50.59. ;
LA.4 The MSIV-LCS is a manually actuated system. The instrumentation being tested by the existing surveillance provides operational interlocks and automatic system shutdown for .
the system at various conditions. Many systems specified in the Technical Specifications l have system-internal operational functions that are not detailed within the Specification itself. The OPERABILITY of the system and of these controls is considered part of the system functional testing. Proposed SR 3.6.1.8.3 will inherently perform a functional test of the instruments, and confirms the proper calibration of the channels. These requirements are relocated from the Technical Specifications to the UFSAR and Technical Specification Bases and the control of 10CFR50.59.
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CONTAINMENT SYSTEMS LCo 3. 6. l. 6 MSIV LEAKAGE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION ;
LCO 3.6.1.4 Two6ndepende_r(M leakage control system (LCS) subsystems shall be 3.lel- OPERABLE.
,Ai I
APPLICABILITY: OPERATIONAL C0 ONS 1, 2 and 3.
ACTION: MS d C =^ D eakage control system subsystem inoperable, restore the inoperable ,
- c. g With one MSIVsubsystem to OPERABLE status within 30 days or be in at least HOT SH!
C_eNO4 the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. f SURVEILLANCE REQUIREMENTS l
4.6.1.4 Each MSIV leakage control system subsystem shall be demonstrated OPERABLE
- a. At least once per 31 days by verifying.
S e, 7,< . f .'3 4 1. Blower OPERABILITY by starting the blowers from the control room and operating the blowers for at least 15 minutes.
Inboard heater OPERABILITY by demonstrating electrical l
$ R 3.02.1.T. 2 2.
continuityoftheheatingelement_circuitryfl~byverifying}
Og ,] -ithe inocard heater draws 5.b31 10% amperes per_ phase, During each COLD SHUTDOWN, if not performed within the previous Og,3 , N(b.92 days, 1
by cycling each motor operated valve through at least one (complete cycle of full travel. y
- c. At least once per 18 months by:
$# h 'A 3 1. hich includes simulated Performanceofafunctionaltes[houtitsoperatingsequence, actuation of the subsystem T.nroug and verifying that each automatic valve actuates to its correct ,
I position, the blowers start and the inboard heater draws l
8.65 1 10% amperes per phase. 1 LA2 2. Verifying that the blower developed at least the below required vacuum at the rated capacity.*
a) Inboard subsystem,10" t 1" H O 2 vacuum at > 100 scfm.
- b) Outboard subsystem, > 15" H,0 vacuum at > cf L A. d. By verifying the inboard flow, inboard and outboard pressure, cod .
- inboard temperature instrumentation to be OPERABLE by perforur;ce of a:
- 1. CHANNEL CHECK st least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- 2. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
- 3. CHANNEL CALIBRATION at least once per 18 months.,
LAA s [ '
- Thesubsystemsarenotlineduptothemainsteamlinesduringtheperformance) of this test.
GRAND GULF-UNIT 1 3/4 6-7
G n R> 1S/*an E ., et. sore V i P-5' 3 5 b MSIV LCS 3.6.1.9 1
3.6 CONTAINMENT SYSTEMS 3.6.1.9 Main Steam Isolation Valve (MSIV) Leakage Control System (LCS)
LCO 3.6.1.9 Two MSIV LCS subsystems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV LCS subsystem A.1 Restore MSIV LCS 30 days inoperable. subsystem to OPERABLE status.
B. Two MSIV LCS B.1 Restore one MSIV LCS 7 days subsystems inoperable. subsystem to OPERABLE status.
C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met. M C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.9.1 Operate each MSIV LCS blower 31 days G157 minutes.
(continued) i l
BWR/6 STS 3.6-27 Rev. O, 09/28/92 !
l
G AG O~ASfoo 00 (n el wee 4 i fag 4 o f G l MSIV LCS 3.6.1.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY l
SR 3.6.1.9.2 Verify electrical continuity of each 31 days
]
inboard MSIV LCS subsystem heater element ,
ci rcui try.
SR 3.6.1.9.3 Perform a system functional test of each 118fmonths MSIV LCS subsystem.
l BWR/6 STS 3.6-28 Rev. O, 09/28/92
q,# o -95/ o ool 1 g..,ef s a n s4
@ ## MSIV LCS B 3.6.1.9 BASES ACTIONS C.1 and C.2 (continued) l If the MSIV LCS subsystem cannot be restored to OPERABLE i status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.1.9.1 REQUIREMENTS Each MSIV LCS blower is operated for til5[ minutes to verify OPERABILITY. The 31 day Frequency was developed considering the known reliability of the LCS blower and controls, the two subsystem redundancy, and the low probability of a significant degradation of the MSIV LCS subsystem occurring between surveillances and has been shown to be acceptable through operating experience.
SR 3.6.1.9.2 The electrical continuity of each inboard MSIV LCS subsystem
.: eater is verified by a resistance check, by verifying the rate of temperature increase meets specifications, or by verifying the current or wattage draw meets specifications.
The 31 day Frequency is based on operating experience that has shown that these components usually pass this Surveillance when performed at this Frequency.
SR 3.6.1.9.3 A system functional test is performed to ensure that the MSIV LCS will operate through its operating sequence. This includes verifying that the automatic positioning of the valves and the operation of each interlock and timer are correct, that the blowers start'and develop the required flow rate and the necessary vacuum, and the upstream heaters meet current or wattage draw requirements (if not used to verify electrical continuity in SR 3.6.1.9.2). The 18 month (continued)
BWR/6 STS B 3.6-52 Rev. O, 09/28/92 1
t GNA 3 -Woost 7 cac c5uce 4
, 9 684 MSIV LCS B 3.6.1.9 BASES SURVEILLANCE SR 3.6.1.9.3 (continued)
REQUIREMENTS Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance wer performed with the reactor at power.fgating x ience has n that thes onents usua pass the C2 '
Survei nce when formed at t ] month Fre ncy.
efore, the Frequen was conclu to be accepta from a re bilit standpoint.J REFERENCES @ @ l. (AFSAR,Sectiob6.7[.i.
- 2. ns.w, = :.r.,s...-:= m >
( uFSAR, SectioN15.6.5[ !
e e '
t l
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I BWR/6 "TS B 3.6-53 Rev. O, 09/28/92
.