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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
[Table view] |
Text
_- _
, TABLE 4.3.2.1-1 .
~)
ISOLATION ACTUATION INSTIRSENTATION SURVEILLAACE REQUIREMENTS E CHAfWlEL OPERATICIIAL E CHAf81EL FUNCTIONAL CHA181EL ColeITIONS IN telICH j TRIP FLNICTION CHECK TEST CALIBRATION SURVEILLAIICE RE0tflRED
[ 1. PRISIRRY CONTAINMENT ISOLATION
- a. Reactor Vessel Water Level - l Low Low, Level 2 S M R (c) 1, 2, 3 and # :
- b. Reactor Vessel Water Level- S M R IC) 1, 2, 3 and #
Low Low, Level 2 (ECCS -
Division 3) i
- c. Reactor Vessel Water Level- 5 M R IC) 1, 2, 3 and #'
Low Low Low, Level 1 (ECCS -
Division 1 and Division 2) ,
5 d. Drywell Pressure - High S M R '}
C ' 1, 2, 3 Y e. Drywell Pressure-High (ECCS - S M R IC) 1, 2, 3 o Olvision 1 and Division 2)
- f. Drywell Pressure-High (ECCS - S M R IC) 1, 2, 3 Division 3)
- g. Containment and Drywell
'$0 Ventilation Exhaust 2'y Radiation - High High S M R 1, 2, 3 and *
$3 h. Manual Inf.tiation MA MI ") NA 1, 2, 3 and *f-S3
't m 2. MAIN STEAM LINE ISOLATION 8S a. Reactor Vessel Water Level - [
mgS l'ow Low Low, Level 1 S N R(c)
High 5 M R 1, 2, 3 l c. Main Steam Line Pressure -
Low S M-R (c) 1
- d. Main Steam Line Flow - High S M R (.c) 1 , 2 ,. 3 I
I e. Condenser Vacuum - Low $ M R 1, 2**, 3**
TABLE 4.3.2.1-1(Contireuedi ,
E h ISOLATION ACTUATION INSTNINENTATION SURVEILLANCE REQUIREfENTS E
y, CHANNEL OPERATIONAL
- CHAMEL FUNCTIONAL CHAfWlEL ColeITIONS IN WlICH
- k TRIP FUNCTION CHECK TEST CALIBRATION SURVEILU4 ICE REQUIRED
[ 2. MAIN STEAM LINE ISOLATION (Continued)
I
(. Main Steam Line Tunnel Temperature - High S M -#- A 1,2,3 I g. Main Steam Line Tunnel i
a Temp. - High S M XA 1,2,3
! h. Manual Initiation M MI ") NA 1, 2, 3 l
l 3. SECONDARY CONTAll0IENT ISOLATION 1:
8
- a. Reactor Vessel Water I
- Level - Low Low, Level 2 S M R (c) 1, 2, 3 and #
- b. Drywell Pressure - High S M R 1, 2, 3
. c. Fuel Handling Area Ventilation Exhaust Radiation - High High S M R 1, 2, 3 and
- l d. Fuel Handling Area Pool Sweep i Exhaust Radiation - High High $ M R 1, 2, 3 and *,
- e. Manual Initiation IIA MI *) M 1, 2, 3 and *
- 4. REACTOR WATER CLEANUP SYSTEM ISOLATION
} a. A Flow - High S M R 1,2,3 l
- b. IFlowTimer NA M Q 1, 2, 3
- c. EMipmentAreaTemperature-l High 5 M XA 1,2,3
- d. Equipment Area Ventilation
& Temp. - High S M #A 1, 2, 3
- e. Reactor Vessel Water gey Level - Low Low, Level 2 S M R 1, 2,,3 ,
S
TABLE 4.3.2.1-1 (Continued) ,
- l lEo ISOLATION ACTUATION INSTRtN NTATION SURVEILtANCE REQUIREE NTS 8
4; CHANNEL OPERATIONAL
- CHAISIEL FUNCTIONAL CHANNEL CONDITIONS IN WICH
! TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
) 4. REACTOR M TER CLEANUP SYSTEN ISOLATION (Continued)
- f. Main Steam Line Tunnel Ambient Teeperature - High S M #A 1,2,3 l
- g. Main Steam Line Tunnel l l A Temp. - High S M XA 1,2,3 l 1
l I
- h. SLCS Initiation NA M(b) NA 1, 2, 3
- 1. Manual Initiation MA MI ") NA 1,2,3 )
'w I
lk
. 5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High N R 1, 2, 3 h a. S RCIC Steam Supply Pressure -
b.
Low S M R (c) 1, 2, 3
- c. RCIC Tuttine Exhaust Diaphragm ge)
Pressure - High S M R 1, 2, 3
- d. RCIC Equipment Room Ambient Temperature - High 5 M WA 1,2,3
- e. RCIC Fquipment Room a Temp. -
High S M XA 1,2,3
- f. Mai'n Steam f.ine Tunnel Ambient Topperature - High S M XA 1, 2, 3
- g. Main Steam Line Tunnel a Temp. - High S M XA 1,2,3 O
~
l . l l , _TADLE 4.3.2.1-1 (Continued) ,
E o
, ISOLATION ACTUATION INSTMBENTATION SURVEILLANCE REQUIREfENTS i 8 ^
) y CHAISIEL OPEMTICIIAL i i
CHAISIEL FUNCTIONAL CHAISIEL COISITIINIS IN ISIICM 1 !'
-4 TRIP FIRICTIlRI CHECK TEST CALIBRATION SURVEILLAIICE REQUIED g 5. REACTCR CORE ISOLATION COOLING SYSTEM ISOLATI0H (Continued) l .
t j h. Main Steam Line Tunnel
) Temperature Timer NA M Q 1, 2, 3
) 1. RHR Equipment Room Ambient j Temperature - High 5 M XA 1,2,3
- j. IIHR Equipmeht Room & Temp. - -
High . 5 M XA 1, 2, 3 ,
4 1
w k. RHR/RCIC Steam Line Flow - t M High 5 M R 1,2,3 Manual Initiation MI *)
, 1. MA IIA 1, 2, 3
. m. Drywell Pressure-High S M R ICI 1,2,3
! (ECCS Division 1 and 1
Division 2) l 3
- 6. ItHR SYSTEM ISOLATION
- a. IIHR Equipment Room Ambient Temperature - High S M XA 1, 2, 3
- b. RHR Equipment Room l .A Temp. - High 5 M XA 1,2,3 -
l
- c. Reqctor Vessel Water Level - ge)
Low, Level 3 S M R 1,2,3
- d. Reactor Vessel (RNR Cut-in g Permissive) Pressure - High S M R 1, 2, 3 e
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRISENTATION SURVEILCANCE REQUIREENTS
,8
- CHAMEL OPEMTIOML G CHAf81EL CON 0lTIONS IN tRIICH CHAMEL FUNCTIONAL g CHECK TEST CALIBRATION SURVEILLANCE REQUIRE 0 q TRIP FUNCTION g 6. R M SYSTEM ISOLATION (Continued)
Dryuell Pressure - High 5 N R 1, 2, 3 e.
- f. Manual Initiation NA MI 'I MA 1,2,3
When handling irradiated fuel in the primary or secondary containnent and during CONE ALTERATIONS and w operations with a potential for draining the reactor vessel. ~
) **When reactor steam pressure i 1945 psig and/or any tudine stop valve is open.
,w #During CORE ALTERATION and operations with a potential for straining the reactor vessel.
l4 (a) Manual initiation switches shall be tested at least once per 18 nonths during shutdoun. All other l N' circuitry associated with manual initiation shall receive a CHAf01EL FUNCTIONAL TEST at least once per 31 days as part of circuitry required to be tested for automatic system isolation.
(b) Each train or logic channel shall be tested at least every other 31 days.
(c) Calibrate trip unit at least once per 31 days.
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