Letter Sequence Other |
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Results
Other: AECM-86-0264, Submits Addendum 2 to 860815 Proposed Amend to License NPF-29 Cycle 2 Core Stability, ML20207G736, ML20207G753, ML20207G761, ML20207G773, ML20209G546, ML20211A296, ML20212M728, ML20212M732, ML20212M735
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MONTHYEARAECM-86-0085, Provides Summary of Property Insurance Coverage That Will Be in Effect on 860401.Certificates of Coverage Encl1986-03-31031 March 1986 Provides Summary of Property Insurance Coverage That Will Be in Effect on 860401.Certificates of Coverage Encl Project stage: Request ML20207G7731986-05-31031 May 1986 LOCA Analysis Project stage: Other ML20207G7611986-06-30030 June 1986 Rev 2 to Grand Gulf Unit 1 Cycle 2 Plant Transient Analysis Project stage: Other ML20207G7531986-06-30030 June 1986 Rev 2 to Grand Gulf Unit 1 Cycle 2 Reload Analysis Project stage: Other ML20207G7361986-07-14014 July 1986 Proposed Tech Specs Re Cycle 2 Reload Project stage: Other AECM-86-0214, Application for Amend to License NPF-29,consisting of Proposed Change 86-15,revising Tech Specs Re Cycle 2 Reload. Fee Paid1986-07-14014 July 1986 Application for Amend to License NPF-29,consisting of Proposed Change 86-15,revising Tech Specs Re Cycle 2 Reload. Fee Paid Project stage: Request ML20212M7351986-08-0909 August 1986 Rev 3 to Grand Gulf Unit 1 Cycle 2 Plant Transient Analysis Project stage: Other ML20212M7321986-08-0909 August 1986 Rev 3 to Grand Gulf Unit 1 Cycle 2 Reload Analysis Project stage: Other ML20212M7281986-08-15015 August 1986 Proposed Tech Specs,Establishing Detect & Suppress Region of Potential thermal-hydraulic Instability to Be Applied to Mixed Core of Cycle 2 Project stage: Other AECM-86-0255, Addendum to 860714 Application for Amend to License NPF-29, Forwarding Rev 3 to XN-NF-86-35, Cycle 2 Reload Analysis & Rev 3 to XN-NF-86-36, Cycle 2 Plant Transient Analysis. Proposed Tech Specs Re Detect & Suppress Region Also Encl1986-08-15015 August 1986 Addendum to 860714 Application for Amend to License NPF-29, Forwarding Rev 3 to XN-NF-86-35, Cycle 2 Reload Analysis & Rev 3 to XN-NF-86-36, Cycle 2 Plant Transient Analysis. Proposed Tech Specs Re Detect & Suppress Region Also Encl Project stage: Request ML20209G5461986-09-0404 September 1986 Proposed Tech Specs Supporting Detect & Suppress Stability Surveillance Region for Cycle 2 Project stage: Other AECM-86-0264, Submits Addendum 2 to 860815 Proposed Amend to License NPF-29 Cycle 2 Core Stability1986-09-0404 September 1986 Submits Addendum 2 to 860815 Proposed Amend to License NPF-29 Cycle 2 Core Stability Project stage: Other AECM-86-0273, Responds to NRC 860829 Request for Addl Info Supporting Util 860714 Application for Amend to License NPF-29 Re Cycle 2 Reload.Supporting Info Encl1986-09-0505 September 1986 Responds to NRC 860829 Request for Addl Info Supporting Util 860714 Application for Amend to License NPF-29 Re Cycle 2 Reload.Supporting Info Encl Project stage: Request ML20211A2961986-10-0303 October 1986 Proposed Tech Specs Re Cycle 2 Reload,Editing Inserts & Clarifying Text Project stage: Other AECM-86-0299, Suppls 860714 Application for Proposed Amend to License NPF-29,consisting of Proposed Change 86-15,changing Tech Specs to Support Cycle 2 Operation,Per NRC Concerns. Justification for Changes & Proposed Tech Specs Encl1986-10-0303 October 1986 Suppls 860714 Application for Proposed Amend to License NPF-29,consisting of Proposed Change 86-15,changing Tech Specs to Support Cycle 2 Operation,Per NRC Concerns. Justification for Changes & Proposed Tech Specs Encl Project stage: Request ML20235F9341987-06-23023 June 1987 Trip Rept of 870130-31 Visit to Jackson,Ms Re Safety Evaluation of Plant Reactor Core for Fuel Cycle 2,addressing thermal-hydraulic Stability Tests During Startup.Summary of Meetings Before & After Tests Also Encl Project stage: Approval 1986-07-14
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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
. - _ - - _ _ -
(
DEFINITIONS J
e CORE ALTERATION 1.7 CORE ALTERATION shall be the addition, removal, relocation or movement of fuel, sources, incore instruments or reactivity controls within the reactor o pressure vessel with the vessel head removed and fuel in the vessel. 3 Suspension of CORE ALTERATIONS shall not preclude completion of the movement 2-of a component to a safe conservative position.
{
CRITICAL POWER RATIO .
_ ,.7 ,_ _. _n _. .a _ t .W') h 1.8 The CRITICAL POWER RATIO (CPR) shall be the ratiofof that power in the assembly which is calculated by application of the-6Ent correlation to cause
/
l some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
DOSE EQUIVALENT I-131 1.9 00SE EQUIVALENT I-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, I-133,1-134, and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those I.. listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
DRYWELL INTEGRITY 1.10 DRYWELL INTEGRITY shall exist when:
- a. All drywell penetrations required to be closed during accident conditions are either:
- 1. Capable of being closed by an OPERABLE drywell automatic isolation system, or
- 2. Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, L
nm except as provided in Table 3.6.4-1 of Specification 3.6.4.
i 8 b. The drywell equipment hatch is closed and sealed.
$$ c. The drywell airlock is in compliance with the requirements of ne Specification 3.6.2.3.
m 88 d. The drywell leakage rates are within the Itaits of Specification g4 3.6.2.2.
o g e. The suppression pool is in compliance with the requirements of am. a- Specification 3.6.3.1.
- f. The sealing mechanism arsociated with each drywell penetration; e.g. , welds, bellows or 0-cings, is OPERABLE.
GRAND GULF- 1 1-2 $DOMENT NO-
d 3/4.2 POWER DISTRIBUTION LIMITS h h
3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION $
4 Duringfwo loop opm# ion all
- 3.2.1(-AM AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figure 3.2.1-1 as multiplied by the smaller of either the flow-dependent MAPLHGR factor (MAPFAC f
) of Figure 3.2.1-2, or the power-dependent MAPLHGR factor (MAPFAC ) of Figure 3.2.1-3.
p N W it.T 3.21 APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
ACTION:
r" 1N4LET 1 "ith :: f'"""" :::::dia; th: ;;;15::51: licit:, initiate corrective action l within 15 minutes and restore APLHGR to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
t SURVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the :;;1icabh limits: g ,rg )g
- a. 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. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and
- c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LIMITING CONTROL ROD PATTERN for APLHGR.
- d. The provisions of Specification 4.0.4 are not applicable.
GRAND GULF-UNIT 1 3/4 2-1 Amendment No. l
Insert 3.2.1 During single loop operation, the APLHGR for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits as determined below:
a) for fuel types 8CR210 and 8CR160 - the limit shewn in figure 3.2.1-1 as multiplied by the smaller of either MAPFAC(f), MAPFAC(p) or 0.86; and b) for fuel type XN-1 the Ifmit determined in "a" above for fuel type 8CR210.
Insert 1 During two loop operation or single loop operation, with an APLHGR exceeding the limits of Figure 3.2.1-1, as corrected by the appropriate multiplication factor for each type of fuel, J13 MISC 86092302 - 3 J
a e 6 0 m
( .
seWM &M.sk bE Lt l E ')
k I ..I i i g a 3 3 2 E g .g, g.p .
I Eth N
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i sa
( " 4il 8
$w o EB"
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O Wy5 m_
w"O nl gg I:*
, a EWs
__ EA E E.I e
ts-m > m
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l $ El l 1 o =
x c .
n = 9 e e (w/m4 ELW NOuYWElm IV3H inFAM wrond Emaar nnnixyn I
I
( GRAND GULF-UNIT 1 3/4 2-2 AMENW# 80.
1 L >
9 I I I I I CURVE FUR TYPE E A 8CR210 l o $ 443.1,I4.2 8, 72514.14.24 8 8CRl60 C) 9071.8,14.12 C XN-l 1 F wi I4 - -
3628.7,0.99 l _ 13607.7,13.78 E N 1814 .4 ,13.3 4 q 9072 IM S 18143.4.13.3 0
. .. . ,g, m72.3,i3.03 A 22679.s,12.9s -
e o,,3 g I
W 12.6 \ 12 6 12, 6 13042.4.12.94 q, g
1 k 12.4 y
o l2 -
20 120 12.4 12.4 12.1 12 I
~
{~
~
g B
$ o 27215.4,11.77 p
.i g i1.7 ,,, h 4 13 2
- 11. 3 o II . - -
- a i
?W 'E 10.4 31761.5.10.4 8 g
! X 80.2 p 5l'
\1 l U 88 I C l g 36tSZ2Als ,
l D 9
- 5 38101.6 ,8.61 1 g l r I i Q 8 j " O 5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 g AVERAGE PLANAR EXPOSURE (mwd /ST)
) FIGURE 3.2.1-1 MAXIMUM AVERAGE PLArJAR LINEAR HEAT GENERATION RATE (MAPI.HGR)
, VERSUS AVERAGE PLAtlAR EXPOSURE '^^ "^"' " "^ ~^^ ~'N-l CORE FUEL TYPES 8CR2iO,8CRl60, AND XN-l i
(
J 8
t POWER DISTRIBITTION LIMITS y 3/4.2.4 LINEAR HEAT GENERATION RATE , g LIMITING CONDITION FOR OPERATION t
r m
3.2.4.1 The LINEAR REAT GENERATION RATE (IJIGR) for GE fuel shall not exceed D 13.4 kw/ft. U
'Ibe LINEAR HEAT GENERATION RATE (LHGR) for ENC fuel shall not exceed the .W"*i lisi: de e. gd f
. Figu 3.2.4-1.
APPLICABILITY: OPERATIONAL CONDITION 1, when 'DIERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
.In +ser 2 ACTION'
" ENC. -of Rgore 3. 2A-l Vith the LHGR"of any" fuel rod exceeding the limit , initiate corrective action within 15 minutes and restore the LHGR to within the limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or
( reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS of M 6.G. fuel W ENC 848 4.2.4.1 LHGR's(shall be determined to be equal or less than th lici::g-Weir- allewdle UmM 4o/
- a. 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. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER,
- c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating on a LIMITING C0!frROL ROD PATIIRN for LHGR, and
- d. The provisions of Specification 4.0.4 are not applicable.
GRAND GULF-UNIT 1 3/4 2-7 MENDMEN1- No.
J38 MISC 86070704 - 1
F
~
J_
Insert 2 of any GE fuel rod exceeding the 13.4 Kw/ft limit or with the LHGR J13 MISC 86092302 - 4 1