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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 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 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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217H6211997-12-15015 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 ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20056C9241993-06-30030 June 1993 GGNS GL 89-10 MOV Program ML20095J9471992-03-31031 March 1992 Quarterly Status Rept for Period Ending 920331 Re Degraded Core Accident Hydrogen Control Program ML20114B8011992-01-23023 January 1992 Rev 13 to Offsite Dose Calculation Manual ML20086A4101991-11-0707 November 1991 Rev 0 to Administrative Procedure 01-S-10-4, Emergency Plan Training & Drills, Reflecting Cancellation of Emergency Plan Procedure 10-S-01-23,Rev 11 ML20043H0541990-06-19019 June 1990 Receipt,Routing & Disposition Form for Procedures S-330, Security Training & Qualification Plan & S-480, Physical Security Plan. ML20043B2501990-05-14014 May 1990 Rev 4 to Spec SERI-M-189.1, Pump & Valve Inservice Testing Program. ML20059C9231990-04-11011 April 1990 Rev 3 to Process Control Program ML20006C0571990-01-18018 January 1990 Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. ML15264A1571990-01-0202 January 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. ML20012A3751990-01-0101 January 1990 Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station. ML20012A3771990-01-0101 January 1990 Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station. ML20012A3791990-01-0101 January 1990 Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station. ML20012A3801990-01-0101 January 1990 Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations. ML20012A3691989-12-0505 December 1989 Rev 8 to, Process Control Program,Mcguire Nuclear Station. ML20011D2441989-12-0101 December 1989 Crisis Mgt Implementing Procedures. ML20012A3721989-11-27027 November 1989 Rev 4 to, Process Control Program,Cawtaba Nuclear Station. ML20012A3731989-11-15015 November 1989 Rev 4 to, Process Control Program Oconee Nuclear Station. ML19325F1931989-11-0101 November 1989 Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations. ML19332C8451989-11-0101 November 1989 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13 ML20247H3371989-09-15015 September 1989 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting .. ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20247M7921989-07-31031 July 1989 Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl ML20247M9151989-07-27027 July 1989 Procedure Generation Package ML20247N0421989-06-19019 June 1989 Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing ML20245C2541989-04-0505 April 1989 Public Version of Rev 29 to Duke Power Co Crisis Mgt Plan for Nuclear Stations ML20247M7801989-04-0404 April 1989 Rev 0 to ST-1 Re Simulators safety-related Valves Stroke W/ Acceptable Time Period Required by ANSI/ANS-3.5-1985 ML20247M8741989-02-0101 February 1989 Rev 1 to 2BEP-0, Reactor Trip or Injection Unit 2 ML20247M8661989-02-0101 February 1989 Rev to 1BEP-0, Reactor Trip or Safety Injection Unit 1 ML20247M8201989-02-0101 February 1989 Rev 1 to 2BWEP-0, Reactor Trip or Safety Injection Unit 2 ML20247M8011989-02-0101 February 1989 Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1 ML20196E9331988-11-30030 November 1988 Cycle 4 Proposed Startup Physics Tests ML20204J1391988-09-0707 September 1988 Temporary Procedure Change 88-504 to Rev 4 to Procedure E-0, Reactor Trip or Safety Injection ML20204J0391988-08-23023 August 1988 Rev 4 to Emergency Operating Procedure EOP 3.1-28, Turbine Overspeed ML20205A3341988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2526, Reactor Trip Recovery ML20205A6281988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2540C, Functional Recovery of RCS Inventory & Pressure ML20205A6111988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2540B, Functional Recovery of Vital Auxiliaries (AC & DC Power) ML20205A4191988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2540A, Functional Recovery of Reactivity Control ML20205A4011988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2537, Loss of All Feedwater ML20205A6651988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2540D, Functional Recovery of Heat Removal ML20205A3941988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2536, Excess Steam Demand ML20205A3831988-08-0303 August 1988 Rev 5 to Emergency Operating Procedure EOP 2534, Steam Generator Tube Rupture ML20205A3181988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2525, Std Post-Trip Actions ML20205A3671988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2532, Loss of Primary Coolant 1997-12-15
[Table view] |
Text
, .
,, j ,, PLANT OPERATIONS MANUAL
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volume 05 05-142-I-A
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Section 02 1 I'
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0FF-NORMAL EVENT PROCEDURE LOSS OF OFFSITE POWER SAFETY RELATED .
Prepared: _ .b '.. - d+ - - ~a ,
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Reviewed: / j'/. d. }; / f. ff Nuclear Plant Quality Superintendent Tecnnical Review Approved:
7 Operattons Superintendent i
List of Effective Pages:
Pace:
1-4 List of TCN's Incorporated: ?
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1.0 PURPOSE / DISCUSSION ,,
__ , 1 1.1 To provide instructions.for.the.Yp'erator -in thh' e. vent 500' KV power is lost, or two or more offsite power s'upplies'are lost .
1.2 This procedure may interface with ONEP 05-1-02-I-1, Reactor Scran, and with the Emeroency Procedure and the Emeroency Plan.
1.3 Unit service power, when being supplied from the 500 KV Switchyard and the 115 KV Offsite circuit, normally feeds 4 KV ESF Busces 15AA, 16A5 1 and 17AC from ESF Transformer 11,12 or 21. Each 'ESF Transformer has been sized to handle the power recuired to start the ESF loads of one unit due to a LOCA and run the ESF loads of the other tnit required for safe shutdown.
Should offsite power become totally unavailable, three (3) enercency diesel cenerators are provided for each unit. Two of the three ciesels in each unit can provide the necessary power for a plant ccolaown er far ESF system requirements. A Gas Turbine Generator (GTG) System is available, should both STBY D/G' and 0/G12 diesel generators fail to sucply t: eir <
respective buses.
2.0 SYMPTOMS
- 2.1 Loss of AC power to running equipment 2.2 Loss of normal lighting 2.3 Reactor Scram 2.4 Turbine Trip 2.5 Division I, II, and III, emergency diesel generators auto-start and energize their respective busses, unless ESF Power is beino appliwi fra-the 115 KV line (ESF transformer 12).
2.6 Load dispatcher or other indications define a degraded offsite power '
condition.
i 3.0 AUTOMATIC ACTIONS 3.1 Main Generator load reject, causing a turbine trip f
- 3.2 Reactor Scram j
3.3 MSIV's trip closed (due to loss of so'lenoid power) 3.4 Condensate Pump, Condensate Booster Pump, and Reactor Feed Puma !.arbine Trip 3.5 Reactor Recire Pumps trip O
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^ ' GRAND GUlr NUCLEAR STATZON , OFF-NORMAL E\ENT Po"*E2*EE Iitie: Loss of Offsite Power No.: 05-1-02-14 Revision: 13 , Page: 2 7 t .
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3.6 Cire Water Pumps trip (Turbine Bypass System operation' blocked on decreasing Main Condenser;vacuumhv c
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. ; 1 3.7 Safety / Relief Valves operate to control rea'clor pressure.
3.8 Reactor water level decreases to low-Icw water level 2, initiating "PCS and RCIC.
3.9 LSS system sheds loads from ESF 4 KV buses 15AA and 16AB and Emeroency Diesel Generator 11,12 and 13 auto-start and enercize ESF 4 KV Busses 15AA,16AB and 17AC (unless supplied for ESF Transformer 12).
3.10 Group I, II, III, VI, VII, VIII and X Isolations.
3.11 Turbine-Generator emergency oil pump, Generator emergency seal oil et.co.
and RFP Turbine A and B emeroency bearino oil punos auto-start on decreasing oil pressure (250 V DC bus 110r .
3.12 Both diesel-driven Fire Pumps A and B auto-start en Icss of caarcer power.
3.13 120V AC UPS system remains ir ervice.
3.14 Plant DC electrical busses remain in service (powered from their J
respective batteries or battery charcers), suoplyino emeroencv lic :irx2 and communications, RCIC system, and critical plant instrumentation.
3.15 SSW pump will auto start, along with associated sed cooling tcwer 'ans.
4.0 IMMEDIATE OPERATOR ACTION 4.1 Verify emergency diesel generators have started and energized ESF W.'
Busses 15AA, 16AB, and 17AC.
4.1.1 If both SIBY D/G11 and STBY D/G12 fail to energize their I respective busses, notify the GTG System Crew (Phone S0-2iC; or Radio) to start and make ready to load the GTG's. ?.e fe r :,:
Station Blackout Proc. 405-1-02-I-6 for enercizing tusses fem twe GTG's. L 4.2 Carry out the ar.tions of EP-1, Level Control.
4.3 Carry out the actions of ONEP 05-1-02-III-2, Loss o# Cne of Sa:n '25 Busses.
4.3.1 If a scram should have occ'trred, but did not, enter E: 70.
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,. GBAND GULF NUCLEAR STATION (FF-NCRMAL EVENT PROCE'TE Titist Losa of Offsite-Power Ns.: 05-1-02-I-4 Revision: 13 Paga 3
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4.4 Recover from Containment,'Drywell,IIind Auxiliary:8uilding isolations in i
accordance with ONEP 05-1-02-III-5,' Automatic:.Isolations and SOI 04-1-01-M71-1, Containment and Drywell Instrumentation .and Control.
. . . .: ,, ~ m- -
4.4.1 Check containment
- parameters and enter EP-3,; as ' required.
% n 5.0 SUBSEQUENT ACTION f.4 2, /T ./ A JE A I 5.ty_ Proceed to implement the Emergency Plan as directed by the Shift Supervisor / Shift Superintendent. .
Sg3 Monitor the emergency diesel generators locally.
5.J' Refer to SOI 04-1-01-R21-1, Load Shedding and Sequencing System, to determine the systems wtich will auto start, and for the systers, whic7 must be started manually.
5.g3 Attempt to locate and correct the power failure. When correctec. re-eneraize the plant as follows:
C 5.t.1 Reset the LSS Panel per SOI 04-1-01-R21-1 as soon as t.,e offsite power is restored.
/ S J.2 Re-energize major busses.
- 5. 3 Insure all large motors have a stop signal.
5.h.4 Reset the bus undervoltage lockout relays. I 5.f.5 Re-start systems per the respective SOI's as needed.
5.f.6 Return ESF busses from the diesel / generators to normal power per SOI 04-1-01-P75-1 and 04-1-01-P81-1.
5.4 Ensure t"' Main Turbine DC emergency oil pump supplies lubricating oil'
- during tne roll-down to zero speed and for at least 15 minutes thereafter. ,
? I 5.,f Ensure the Reactor Feed Pump Turbine A and B DC emergency bearing oil pumps supply lubricating oil during roll-down to zero speed eN for at least 15 minutes thereafter.
5.7 I If power outage appears to be of long duration (greater than approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), the following additional actions should be taken:
5
- 5. 7.1 Place the Reactor in a Cold Shutdown condition in accordance with 101 03-1-01-3, Plant Shutdown.
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Title:
Losa of Offsits Pcwer No.: 05-1-02-I-4 Rcvision: 13 Paga r a j j
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5./.2 Each ESF battery bank 11DA,1108, and 11DC is sized to supply the required DC loads for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, after a loss of AC power to both battery chargers. Return both battery chargers to service for eacn ESF battery bus 11DA and 1108 and one charger for bus 11DC.
T 5.//.3 Each BOP battery bank is sized to supply all connected loads (including bus 110F) for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after a loss of AC power to b:1-battery chargers. Return both battery chargers to service for esen BOP battery bank.
5 .,1. 4 Notify the GTG System crew to start the Gas Turbines and place them in standby.
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SUBJECT:
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\ J. P. McGAUGHY hDN' C.
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\ JUDY HUG S Y Information Signature Action
\T. M. J SON Comments File Approval C. L. ONE REMARKS / REPLY:
LYN SUD.ECK MARCIA SMITH J. RI SON fy W b.$r'cf Q_r p~ ROOits ah (Oc~o c e euS LINd MILLER \
P. . RICHARDSON /,c[,"c k d re re f p:e n nln
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