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MONTHYEARML20134M6591985-08-23023 August 1985 Proposed Tech Specs 3.8.1.1 & 3.8.1.2,increasing Min Useable Fuel Required for Diesel Generators 11 & 12 from 48,000 to 57,200 Gallons & Changing Standby Svc Water Sys Project stage: Other AECM-85-0258, Application for Amend to License NPF-29,changing Min Useable Fuel Required for Diesel Generators 11 & 12 in Tech Specs 3.8.1.1 & 3.8.1.2 to 57,200 Gallons & Temporarily Allowing Exception to Standby Svc Water Sys.Fee Paid1985-08-23023 August 1985 Application for Amend to License NPF-29,changing Min Useable Fuel Required for Diesel Generators 11 & 12 in Tech Specs 3.8.1.1 & 3.8.1.2 to 57,200 Gallons & Temporarily Allowing Exception to Standby Svc Water Sys.Fee Paid Project stage: Request ML20133A7611985-09-25025 September 1985 Proposed Changes to Tech Specs 6.3.1 & 6.4.1,providing Justification for Exemption from Requirements for Senior Reactor Operator Qualifications Project stage: Request AECM-85-0304, Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications1985-09-25025 September 1985 Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications Project stage: Supplement AECM-85-0317, Forwards Calculational Info to Justify Proposed Increase in Diesel Fuel Oil Storage Requirements in 850823 Proposed Change to Tech Specs 3.8.1.1.b.2.a & 3.8.1.2.b.2.a1985-10-0202 October 1985 Forwards Calculational Info to Justify Proposed Increase in Diesel Fuel Oil Storage Requirements in 850823 Proposed Change to Tech Specs 3.8.1.1.b.2.a & 3.8.1.2.b.2.a Project stage: Request ML20138B0591985-10-0505 October 1985 Proposed Tech Spec 3.7.1.3,supplementing 850823 Request to Support Design Change Scheduled During Planned Outage in Oct 1985 Project stage: Supplement AECM-85-0326, Application for Amend to License NPF-29,supplementing 850823 Request.Amend Supports Design Change Scheduled During Planned Outage in Oct 19851985-10-0505 October 1985 Application for Amend to License NPF-29,supplementing 850823 Request.Amend Supports Design Change Scheduled During Planned Outage in Oct 1985 Project stage: Supplement 1985-10-05
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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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- - - -
= : 2 2.2 2: = :: --
or tha acsockta) SSL<J sJ sysTee sh alI 6e )a.cle 4 i>, op .a n.U<.
. (SSW) system and verification that the design flow can be achieved to all SSW system components. However, should a core offloading be necessary prior to completion of these modifications (scheduled for the first scheduled refueling outage), irradiated fuel may be placed in the spent fuel pool when the RHR system operating in the spent fuel pool cooling mode is available. Until the SSW system is modified, the spent fuel pool cooler s tall be isolated from the SSW system by locked closed valvesr Tie post-s until the tion of these valves shall be verified every 31 day un /4ss fA4.
design flowrate for SSW system is demonstrated lrsMe.*
~
.rysTem ks.* b.n en de.c lo.n d in oy.
i (21) Spent Fuel Pool Ventilation System (Section 9.4.2, SER, $$ER #2) ,
If spent irradiated fuel is placed in the spent fuel pool prior to installation and operability of the safety related backup fuel pool cooling pump room coolers, the plant shall be placed in shutdown condition and remain shutdown with the RHR system dedicated to the fuel pool cooling mode.
(22) Remote Shutdown Panel (Section 9.5.4.1. SER, SSER #2)
Prior to startup following the first refueling outage, MP&L shall install electrical isolation switches between the control room and the Division 1 remote shutdown panel. l (23) Fire Protection Program (Section 9.5.9, SER)
MP&L shall maintain in effect and fully implement all provisions i' of the approved Fire Protection Plan. In addition, MP&L shall maintain the fire protection program to meet the intent of Appendix R to 10 CFR Part 50, except that an oil collection system for the reactor coolant pump is not required.
(24) Interplant Communication Systems (Section 9.6.1.2, SER, SSER #2, i 55ER #4, 55ER #5) l Tests of the communication systems used to mitigate the con-sequences of an event and attain a safe plant shutdown shall be I completed during preoperational and startup tests. An evaluation l of the test results shall be provided for NRC review within 90 l days after test completion. Any system modifications found l necessary as a result of NRC review shall be completed prior to startup following the first refueling autage.
- (25) Reliability of Diesel-Generators (Sections 8.3.1,9.6.3 through 9.6.7, SER, 55ER #2, 53ER #4, 55ER #6)
- (a) Prior to startup following the first refueling outage, a j heavy duty turbocharger gear drive assembly shall be j B50904020e e30eg3+=11ad an s11 EMO diesel-generators.
PDR ADOCK 05000416
, P pg
~..__ - - _ _ - - . _ _ _ _ _ _ . . _ _ . _ . . _ _ . _ . _ _ . _ _ . _ _ _ . _ . _ . _ _ _ ~ . _ . . _ _ . _
(y1) Prain sI y s sGlrtd a o LCR N L S - 9 C/D ~z on Jul y '3; I ws (A Ecm- er /ou g, n .c) 1 L (b) Provide the second level undervoltage protection for Division 3 power supply (Item No. 373, T.S. Table 3.3.3-2).
! (c) Incorporate a bypass or coincident logic in all Division 1 and 2 diesel generator protective trips, except for trips on diesel engine overspeed and generator differential cur-1 rent (Item No. 808, T.S. 4.8.1.1.2.d.16.d).
(38) Control Room Leak Rate (Section 6.2.6, SSER #6)
MP&L shall operate Grand Gulf Unit I with an allowable control l
i room leak rate not to exceed 590 cfm. Upon restart of construc-tion of Unit 2 control room, MP&L will be permitted to operate at a leak rate of 760 cfm as evaluated in SSER No. 6.
- & zHscar The facility requires exemptions from certain requirements of Appendices l
D.
A and J to 10 CFR Part 50. These include: (a) exemption from General
- Design Criterion 17 of Appendix A until startup following the first refueling outage, for (1) the emergency override of the test mode for the Division 3 diesel engine (2) the second level undervoltage protec-tion for the Division 3 diesel engine, and (3) the generator ground 4 i over current trip function for the Division 1 and 2 diesel generators (Section 8.3.1 of SSER #7) and (b) exemption from the requirements of Paragraph III.D.2(b)(ii) of Appendix J for the containment airlock testing following not required (Section normal 6.2.6 door of SSER opening #7 . These w) hen containment exemptions are integrity is authorized by law and will not endanger life or property or the connon l defense and security and are otherwise in dm ;:ublic interest. There-j fore, these exemptions are hereby granted pursuant to 10 CFR 50.12.
- With the granting of these exemptions, the facility will operate, to l the extent authorized herein, in conformity with the application, as l
}
amended, the provisions of the Act and the rules and regulations of l the Commission. _,
E. MP&L shall maintain in effect and fully implament all the provisions l
of the Connission-approved physical security plan, guard training and qualification plan and safeguards contingency plan, including amend-
' ments made pursuant to the authority of 10 CFR Section 50.54(p). The l
approved plans, which are safeguards information protected under 10 CFR 73.21, are collectively entitled Grand Gulf Nuclear Station
" Physical Security Plan," Revision 1, 2 and 3; the Grand Gulf Nuclear Station " Security Training and Qualification Plan," and the Grand Gulf Nuclear Station " Safeguards Contingency Plan." The identification of vital areas and measures used to control access to these areas, as
' described in the physical security plan, may be subject to amendnents l
in the future based upon a confirmatory evaluation of the plant to determine those areas where acts'of sabotage might cause a release of radionuclides in sufficient quantities to result in dose rates equal l to or exceeding 10 CFR Part 100 guidelines.
i 1
a Insert to Facility Operating License NPF-29 Page 14 (40) With the plant in OPERATIONAL condition 4, SSW cooling tower basin A may be considered OPERABLE in accordance with Technical Specification 3.7.1.3 with less than a 30 day supply of water (without makeup) during the time that
' SSW basin B is drained to replace its associated service water pump provided:
a) SSW basin A water level is maintained greater than or equal to 87".
b) At least two sources of water (other than normal makeup with one source not dependent on offsite power) are available for makeup to SSW basin A.
This license condition may remain in effect until plant startup following the outage scheduled for fall 1985.
4 T
t 1
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4 5
i t
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J14PMI85071201 - 8
i .
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. - SOURCES A.C. SOURCES - OPERATING LIMITING CONDITION FOR OPERATION
., 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, and
- b. Three separate and independent diesel generators, each with:
. 1. -Separate day fuel tanks containing a minimum of 220 gallons of ,
- fuel.
- 2. A separate fuel storage system containing'a minimum of:
5 7,2 d o M 00,000 gallons of fuel each for diesel generators 11 and l 12, and b) 39,000 gallons of fuel for diesel generator 13.
- 3. A separate fuel transfer pump.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
- a. With either one offsite circuit or diesel generator 11 or 12 of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveil-lance Requirements 4.8.1.1.1.a within one hour and 4.8.1.1.2.a.4,*
for one diesel generator at a time, within two hours and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least two offsite circuits and diesel generators 11 and 12 to OPERABLE status 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 />.
- b. With one offsite circuit and diesel generator 11 or 12 of the above required A.C. electrical power sources inoperable, demonstrate the i OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a within one hour and 4.8.1.1.2.a.4,* for one diesel generator at a time, within two hours e.nd at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least one of the inoperable A.C.
sources to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT SHUT-DOWN 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 i 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore at least two offsite circuits and diesel genera-tors 11 and 12 to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss 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 />.
" Specification 4.8.1.1.2.a.4 must be performed for diesel generator 13 only when the !{PCS system is OPERABLE.
GRAND GULF-UNIT 1 3/4 8-1 M' **
- ELECTRICAL POWER SYSTEMS A.C. SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
One circuit between the offsite transmission network and the onsite Class lE distribution system, and
- b. Diesel generator 11 or 12, and diesel generator 13 when the HPCS system is required to be OPERABLE, with each diesel generator having:
- 1. A day tank containing a minimum of 220 gallons of fuel.
- 2. A fuel storage system containing a minimum of:
.f'f 200M'",^^^ gallons of fuel for each OPERABLE diesel generator 11 or 12.
b) 39,000 gallons of fuel for diesel generator 13.
- 3. A fuel transfer pump.
APPLICABILITY: OPERATIONAL CONDITIONS 4, 5 and *.
ACTION:
- a. With all offsite circuits inoperable and/or with diesel generators 11 and 12 inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary or secondary containment, operations with a potential for draining the reactor vessel and crane operations over the spent fuel storage pool and the upper containment pool when fuel assemblies are stored therein. In addition, when in OPERATIONAL CONDITION 5 with the water level less than 22 feet 8 inches above the reactor pressure vessel flange, immediately initiate corrective action to restore the required power sources to OPERABLE status as soon as practical.
- b. With diesel generator 13 inoperable, restore the inoperable diesel ;
generator 13 to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the HPCS i
system inoperable and take the ACTION required by Specification 3.5.2 l and 3.5.3.
- c. The previsions of Specification 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.8.1.2 At least the above required A.C. electrical power sources shall be demonstrated OPERABLE per Surveillance Requirements 4.8.1.1.1, 4.8.1.1.2 and 4.8.1.1.3, except for the requirement of 4.8.1.1.2.a.5.
GRAND GULF-UNIT 1 3/4 8-9 M an h ent~ Nd.
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