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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
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. ,* PLANT OPERATI,0NS MANUAL 4 - s -
Volume 05 05-1-02-1-6 Section 02 Revision: 11 Date:
0FF-NORMAL EVENT PROCEDURE STATION BLACKOUT
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A'.* i. SAFETY RELATED
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f Prepared: (t4 d /
Reviewed: / N d /C. M O~. X,I Independent Review Technical Review Approved:
Operations Superintendent
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List of Effective Pages: -
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CRAND GULF NUCLEAR STATION .,
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- OFF-NORMAL EVENT PRCCECWE
Title:
Station Blackout No.: 05-1-02-1-6 Revision: 11 Pace: 1 1.0 PURPOSE / DISCUSSION 1.1 The purpose of this procedure is to provide guidance to the operators in the event all onsite and offsite AC powers are lost, and the estimated time available to restore AC power is 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
1.2 This proc.edure will interface with ONEP 05-1-02-I-1 Reactor Scrarn, ONEP 05-1-02-I-4 Loss of Offsite Power, Emergency Procedures, and the Emergency Plan.
1.3
.a This procedure assumes loss of all three(3) Emergency Diesel Generators,
- concurrent with the loss of all offsite power. -=*
'*f ' '
1.4 -
It l's assumed that all station and non-divisional batteries are availableffy b' in a fully charged status.
1.5 This procedure gives direction for establishing backup Emercency Power I via the Gas Turbine Generator (GTG) system.
j 2.0 SYMPTOMS 3 ~
2.1 Loss of AC Power to all operating equipment E
2.2 Loss of all normal plant lighti.ng
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2.3 Reactor Scram k n? z
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2.4 Turbine trip j'"^ ; "$ '] ":f [- [ ., } f, ' :[
- v. .s .. . e v: t6 a 2.5 MSIV's close on loss of Toliiioid Power j 2.6 Givision I, II & III Emergency Diesel Generators fail to start 3.0 AUTOMATIC ACTIONS 3.1 Main turbine trip upon Main Generator load reject 3.2 Reactor Scram 3.3 MSIV's close (due to loss of solenoid power) 3.4 Safety / Relief valves operate to control reactor pressure 3.5 RCIC initiates on low level in Reactor Vessel 5k . Ni2N d?'ki:;:-::.'952 u_i M' L
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sities s t ,,v.
'v Stcticn Birckout No.:
%:. EiCNT FRCCE0WE 05-1-02-I-6 Rcvision:
11 e)agn 2 I 4.0 i
'I IMMEDIATE OPERATOR ACTIONS .
. 4.1 Carry out actions of ONEP 05-1-02-I-1 Reactor am.
Ser 4.2 Carry out actions of 05-S-01-EP-1 Level Control 4.3 .
respective batteries). Verify that plant DC electrical busses rem v ce (power from their 4.4 Perform Section 5.10 concurrent with 5.0 SUBSEQUENT ACTION procedure. remainder of l
5.1
.- Supervisor / Shift Superintendent.e Proceed y the Shiftto implemen '
NN.. '
5.2
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?+' P the relief valve setpoint and ato suppression pool. n a distribute n pressere belew heat ormly arcund the
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Operate the 12 relief. f,valves 'first," tfien oTe'ra'te 'th 5.2.1 ,, (" C L./ : " , 5. eEDSvalves. J During operation-6f The ielief valve have Control R observe active fuel. all level indications andoommaintain Ocerator eos cf level 5.2.2 Monitor temperatures and pressures in con n and Drywell if
- a. n a ment Centrel.
Drywell pressure +1.73 psig b.
Drywell temperature above 135'F c.
Suppression pool temperature above 95'F d.
Containment temperature above 90*F 5.3 Maintain vessel. maximum RCIC flow to maximize steam dr (approximately two (2) hours) return ofRCIC +35 inches. flow tUpon 5.4 tank to maintain normal Reactor Vessel ,
o the condenscte level stora;e e:
Inform maintenance section to install Nitrogen bottl air receivers prior to six (6) hours). to sustain Safety / Relief Valve es to the operation AOS syste , (
must be es plete 5.5 Monitor Suppression pool level arx1 Leniperatura .
5.5.I thrionily d.m Me '
it r.v.v mnry. v: :t . .a a 2. i . . .e ,: p , it in t 'e u.n.pi ... : p-: .
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GLLF MJCLEAR STATION OPT 80lMAL CVENT PROCEDURE Titles 5tation pieckout no.: p-1-02-1-6 mvielen: 11 regen J EAli 5.5.2 If there le no activated fuel in the opent fuel pool, Open RHR and LPCI test lines from the opent fuel pool to the suppression pool if necessary.
S.S.3 If the upper containment pool hea been dumped to the suppreseine peel and enticipettee of needing more water etart Diesei driven fire pumps and add water to the suppression pool from the fire water storage tank.
(see 30104-5-01-764-1).
5.6 Prior to esptying the OST l 61/2 hours), shift RCIC suction to the suppreselon pool meantsinang nesieum RCIC and Reactor Vessel level by routing water becu to tne suppression pool wie thru bypees line.
5.7 Ensure the respective OC emergen:y bearing oil seg supplies lubricating oil to the eelm tuttine end Reactor Feoo Ps.mp furbines 4 and 9 during roll-down to zero speed.
5.8 Reduce DC loads to minteam.
S.S.' Secure t9e emergercy oil pump wnen L9e turbine generator sto:e rotetsng.
$.8.2 5ecure w2 su: ply. vomt the generator hydrogen, and secure the seal oil eacwuo pumo onen pressure is bled off.
s 5.8.) Secure L9e RTP emergency lube 311e suppe wnen tne RF8e etcp rotetanq- i l
5.9 upon resteretten :f 4.C. power, croceed to 101 03-1 ')1-3 Plent Shutdown.
l
%E If STS) D/C 11 and 0/G 12 failee to etert ans e:eept its sesociated etvistonal loace, serform steo 5.10 concurrent
.ith the reesinder of this procedure. l-5.*0 Energize t9e sele:ted E$r Sue (creferstly Bus 16a8) t$st is deemer-ized I due to ' salute to etert and load from its roepective STSV 0/3 was t9e Gas furtiae Generator (GTG) system, by taking the following act&one: )
I S.1c.1 Notify tne on-ousy OfG ooeroting crew at Phone =2109 or recto Lae t STBY Di~. 'I enc 12 move fetten to start and tne ".fC is reawsted for emergency comer.
5.10.2 Esten11en coetinous coms%nicatio9e wit" the ".T0 crew en: "ontrol Rooe.
g S.10.3 Disaste* en operator to rockcut breewer 152-1901
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NFO 9 VIATIO \i COPY ON _Y
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.JO M U M H N tl 1g u L P NUCLEMM t' l I.
RAW EAJ WCL, EAR STATION OFFJduWthL tWNT PROCEDtalC utle == &en Eleekout, he.: UD.1-gg-I.s Nov&stens 11 rege: 4
. DRAF" aus 1648 wuld be the preferred bue if NH4 8 and S$W 8 ore eveile61o.
5.10.4 Reckout Breakers 152-1501 and 1521511 if D/G 11 failed to etert and Bue 15AA le to be energized wie the CTG system.
S.10.5 Rechout greekers 152-1411 end 152-1614 if Stby O/G 12 failed to I etert end Sue '646 le to be energized via the GTC system. ,
l (s) To prevent R*NI DJ4pe auto etert, plass rocosctive "RMR I Logic Power Aveileele Norme1/Teet" emitch tu test. I For R*4 A it is MS-M6444 ($444) on 1H13-0629 k for RMp 8 it is H5-MS448 ($448) on 1H13-P618
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(b) Turn of locally the t S$ panel (1H22J331 or 1H224332) for tne 6ue to be energized wie GTG systee by piecing the ,
ESr DC Ney entteh to off. i 1
S.10.6 (152-1904)
Stetton operator with control hoy et the leched open tie breaker '.
close breaker.ene direct soetetor to unlock brecher in properation to
(
s S.10.7 when CTC systom is ready to Iced, close 152-1906 lacelly.
N0tt 5.10.7 will energiae peser circuit to breeker 152-1314 for tus 1SAA, or 1521601 for Bus 16ee.
S.10.8 With tre respective Syne. owiten in the Orr position, elooe the resoective 1648i. offette treeker (152-1514 or III4.1521601 for tus 5.*0.9 dith newer om t%e Bus from the CTG system close in the following loess manually to apcly statt11ainq lood to the 37G systee. 8 CAUTION
- Only (1) CTG eey be powered up et this time 00 N0' attempt to close in the RNR pump l
)
55n pww. Instrument ear compressor, or, err **11 challere, etil oli three GtG's are synchronised, feeding tme ESr bue and are lead balented and ready to accept thre larger leade.
Limit lead to 3.6 set with 2 GTC's runnlag and 3.4 sur with 3 GMe running. }
I lNFORMAWON '
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.mme 31J WCLEAR STATION FF-NGMAL OtNT PRotEDWC utzes m atten stessout we.: U N -c M -e novsesen 11 rego: 3 1
(a) Centrol Asem Eastgency ren (b) Settery thesters (e) sa pump c/A ren (d) saw Cooling Tenor rene (e) RP5 Alternete (r) ECcs Pump Rose Caeler (g) Sefe Guard Seitehgoer and Bettery Rose rene 5.10.10 Verify with the GTC ersw that suffleient lead le en the CF be to syne. the other two GTG's to the b e.
5.10.11 Howe the CTG erew eensonce syneirq and lead baleneirg on the remaining CTC's in preparation fbt large setor starting.
5.10.12 when all three GTGe are syneed and ready, eloos the 59f pump breaker and establish flow path as needed.
5.10.13 Allow GTGe to be stabill ed end be releed balanced.
5.10.1 A Wnen CTCe are ready, elees RNR pump and establish flew path es needed.
5.10.15 Allow GTGe to be etabilized end be releed beloneed.
5.10.16 Apply additional leeds as necessary to establish shutdeun cooling er suppression peel eseling. These lease soy be, but are not limited to the following:
(e) Instrument alt esepresser 2313tw 1
I (b) ECCS Pues rose oesler Siw (c) EF electrieel rose eseler fan 12kw (d) Centrol fees A/C and fan iltniw (e) fuel Pos! Cooling and Recite pug 124kw (f) Bettery shorsers 110kw (g) MOYe se needed 5.10.17 To espeditievely establish eeeling of reeeter, drywell and contatteent smell EF leads (selenoide, Move) er the other CF divisional bue ser be desired.
5.10.18 The lead ehed esquence penel suet be shutdown and the sesseleted SSW and ICCS puepe reelsed out to prevent overleedine the CTCe. (If t e r <,, b . is e ,e on.. i.ee)
' LNFORMATION COPY ON<_Y -
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c4, U4/iu i;;gy rge xuMMMu uuLP NUGLEMM ft 1 EDI WNO SAJ 183 CLEAR STATION F F-JOINAL EVENT PRIX 2DUltt Titles station B eckout No.: ID=1-02-I-6 .Nev&olen 11 Pages 4
] 7f 1 4
(
3.10.19 After Step 5.10.18 cleos the feeder (15 11 It,8 52-1601
, for 16AS) for the escond ESF bus.
5.10.20 Apply only onell loads (solenoid poser, RPS, Novo, etc.)
carefully monitoring GTG systes leading via tte GTG crew.
5.11 Rostoration of offsite to the ESF Bue pouered by the GTG System.
i IdOTE Roetore offeite power to the redundant CSF bus before !
treneferring from the GTC to offsite.
5.11.1 Piece the sync switch for the offeito feeder from either ESF 12 or ESF 21 to be closed into the ESF bus being powered by the GTG system to on. I 5.11.2 Through communication between control roon operator and the GTG crew. adjust the GTGs to obteln elew counter clockwise rotation (20-30 seconde per full scope cycle)'on the control Room Syne Scope by changing governor settinee et CTGo. Adjust voltese et CTC to within +50 volte of offeite voltage.
5.11.3 When syne conditione are established, close tne offeite feeder on
' the E5F bus when the scope is just before 12 o' cloak. This will simultanocuely oute trip the offsite feeder from Esf 11 that the GTG system is feeding the bus through.
5.11.4 Notify the GTG crew to open their sein CXT brookers for each GTG:
GT81. GTB2 and GTB).
5.11.5 Open and lock treeker 152-1906.
5.11.6 hetify GTG crew to shutdown the GTG system.
5.11.7 Recicae 152-1901 if desired.
I INFORMA?OF COPY ON/_Y .