|
|
(2 intermediate revisions by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 02/03/1995 | | | issue date = 02/03/1995 |
| | title = Rev 5 to Att-17.0, Attachment SD-1. W/950203 Ltr | | | title = Rev 5 to Att-17.0, Attachment SD-1. W/950203 Ltr |
| | author name = WIDAY J A | | | author name = Widay J |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = JOHNSON A | | | addressee name = Johnson A |
| | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000244 | | | docket = 05000244 |
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:PRIORITY(ACCELERATED RIDSPROCESSIX REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9502130285 DOC.DATE: | | {{#Wiki_filter:PRIORITY (ACCELERATED RIDS PROCESSIX REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| 95/02/03NOTARIZED: | | ACCESSION NBR:9502130285 DOC.DATE: 95/02/03 NOTARIZED: NO DOCKET FACIL:50-244 RobertEmmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION WYDAY,Z.A. Rochester Ges & Electric Corp. pi RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A. Project Directorate I-3 (PDl-3) (Post 941001) |
| NODOCKETFACIL:50-244 RobertEmmet GinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION WYDAY,Z.A.
| |
| Rochester Ges&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A. | |
| ProjectDirectorate I-3(PDl-3)(Post941001)
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Rev5toAtt-17.0, "Attachment SD-1."W/950203ltr.DISTRIBUTION CODEA045DCOPIESRECEIVED:LTR JENCLSIZE:TITLE:ORSubmittal:
| | Rev 5 to Att-17.0, "Attachment SD-1." W/950203 ltr. |
| Emergency Preparedness,Pla s,Implement'g Procedures, Cpi0NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). | | DISTRIBUTION CODE A045D COPIES RECEIVED:LTR J ENCL SIZE: |
| 05000244RRECIPIENT IDCODE/NAME PD1-3PDINTERNAL~ICECENTERP1~NUDOCSA'BSTRACT EXTERNAL:
| | TITLE: OR Submittal: Emergency Preparedness,Pla s, Implement'g Procedures, C 0 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 R |
| NOACCOPIESLTTRENCL11111111RECIPIENT IDCODE/NAME JOHNSON,A NRR/DRSS/PEPB NRCPDRCOPIESLTTRENCL111111D0UNNOTETOALL"RIDS"RECIPIENTS:
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL ~ICE CENTER P1 1 1 NRR/DRSS/PEPB 1 1 |
| PLEASEHELPUSTOREDUCEiVASTE!CONTACI'THE DOCUMENTCONTROL DESK,ROOMPI-37(EXT.504-2083)TOELlih!INATEYOURNAMEFRO~IDISTRIBUTION LISTSFORDOCI;MENTS YOUDON"I'LED!TOTALNUMBEROFCOPIESREQUIRED:
| | ~NUDOCS A'BSTRACT 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
| LTTR7ENCL7 t<<P,/.<<III<<I
| | 0 U |
| <<<<<<<<<<<<&'J<<<<<<<<<<<<<<<<<<<<I ROCHESTER GASANDELECTRICCORPORATION o89EASTAVENUE,ROCHESTER, N.Y.14649-0001 TELEPHONE AREACOOE71B546-2700February3,1995Mr.AllenJohnsonProjectDirectorate I-3U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555 | | N NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE iVASTE! CONTACI'THE DOCUMENTCONTROL DESK, ROOM PI -37 (EXT. 504-2083 ) TO E Llih!INATE YOUR NAME FRO~I DISTRIBUTION LISTS FOR DOCI;MENTS YOU DON"I'LED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 7 ENCL 7 |
| | |
| | t <<P,/.<<III<<I |
| | <<<<<<<<<<<<&'J<<<<<<<<<<<<<<<<<<<<I ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N. Y. 14649-0001 TELEPHONE AREA COOE 71B 546-2700 February 3, 1995 Mr. Allen Johnson Project Directorate I-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Emergency Operating Procedures R.E.GinnaNuclearPowerPlantDocketNo.50-244 | | Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Johnson:== |
| | |
| | As requested, enclosed are Ginna Station Emergency Operating Procedures. |
| | Very Truly Yours, a.d oseph A. Widay JAW/jdw xc: Mr. Lee Bettenhausen, USNRC, Region 1 Resident Inspector, Ginna Station RG&E Nuclear Safety & Licensing y/,on2S 9502130285 950203 PDR ADOCK 05000244 F PDR |
|
| |
|
| ==DearMr.Johnson:==
| | Page 2 |
| Asrequested, enclosedareGinnaStationEmergency Operating Procedures.
| |
| VeryTrulyYours,a.dosephA.WidayJAW/jdwxc:Mr.LeeBettenhausen, USNRC,Region1ResidentInspector, GinnaStationRG&ENuclearSafety&Licensing y/,on2S9502130285 950203PDRADOCK05000244FPDR Page2
| |
|
| |
|
| ==Enclosures:== | | ==Enclosures:== |
|
| |
|
| ATT-17.0Revision5 EOP:ATT-17.01'ILE:ATTACHMENT SD-1REV:4PAGE1/of2Surintendent Date7Perfmthefollowing localactionstocompletenormalsecondary systeshutdown: | | ATT-17.0 Revision 5 |
| osereheater4thpasstemperature controlvalves:V-2432(SWcorner1AMSR)oV-2433(SWcorner1BMSR)oV-2434(SWcorner2AMSR)o-2435(SWcorner2BMSR)Closerheatersteamchainvalves:oV-350(SWof1BMSR)oV-351(SWof1bMSR)oV-355(NWof1AMSR)oV-3553(NWof1AMSR)0OpenReheatersteamline ventsmiddlefloor):oV-8500oV-8501oV-8502oV-8504oV-8505SWcornerofcondenser, Closeflangehetingsolationvalves:oMOV-3601A (TBidieLvlWestofTURBL.O.Reservoir) oMOV-3602A NOTE:IFeitherS/GpessureiLESSTHANcondensate headerpressure, THENmanualisoationoftheMFWregulating andbypassvalveshouldbecsideredbeforealigningforcooldownreirculation.
| | |
| Opentheollowingvalvestoalignforcondensate feedsystemoldownRECIRC:oV982B(atN5heaterouetheader)o-3983B(atN5heateroutetheader)oV-4363(atN5heateroutleheader)oV-4365(byMFWregulating ives)V-4361(southwest cornerofcondenser, middlefloor)oV-3976AMFPAdischarge valvbypassvalveoV-3977AMFPBdischarge valvebypassvalveSecureall5secondary chemicaladdtionpumpsonTURBBLDGmiddlefloorbyN5heaters.oSecureall3ammoniapumps,TURBBLDGbasementbyMCCA.
| | EOP: 1' ILE: |
| +1QIIAtlt EOP:ATT-17.0ATTACHMENT SD-1REV:4PAGE2of2oIsolateSWfromthefollowing coolers:oMFWPumpOilCoolers(MFWpumproom)oV-4703oV-4704oExciterAirCooler:oV-4679(chainvalvenexttocondensate transferpump)oBusDuctAirCooler(TURBBLDGbasementEastofbusductcooler)oV-4674oV-4674C(minibypassaroundV-4674)oThrottleSWasnecessary fromfollowing coolers:oGenerator SealOilUnitCoolers(H2sideandairside):oV-4674A(minibypassdischvalveinsidesealoilenclosure Bldg.NWcorner)oV-4677A(minibypassdischvalveinsidesealoilenclosure Bldg.NWcorner)oMainLubeOilCoolers(SWcornerofTurbOilReservoir) oV-4691oV-4692oWHENtheturbineshaftstops,THENnotifyControlRoom.ControlRoompersonnel willdetermine ifadequatepoweravailable tostartturninggear.oTransferhouseheatingsteamtohouseheatingboilerifnecessary (refertoT-35H,NUCLEARHOUSEHEATINGSTEAMTOBOILERSTEAMSUPPLYCHANGE).oPerformT-14G,STEAMGENERATOR BLOWDOWNHEATRECOVERYSYSTEMSHUTDOWN. | | REV: 4 ATT-17.0 ATTACHMENT SD-1 PAGE 1/of 2 Su rintendent Date 7 Perf m the following local actions to complete normal secondary syste shutdown: |
| oRestoreMAKEUPtoCSTsasdirectedbyControlRoom.
| | ose reheater 4th pass temperature control valves: |
| | V-2432 (SW corner 1A MSR) o V-2433 (SW corner 1B MSR) o V-2434 (SW corner 2A MSR) o -2435 (SW corner 2B MSR) |
| | Close r heater steam chain valves: |
| | o V-3 50 (SW of 1B MSR) o V-35 1 (SW of 1b MSR) o V-355 (NW of 1A MSR) o V-3553 (NW of 1A MSR) 0 Open Reheater steamline vents SW corner of condenser, middle floor): |
| | o V-8500 o V-8501 o V-8502 o V-8504 o V-8505 Close flange heting solation valves: |
| | o MOV-3601A (TB i die Lvl West of TURB L.O. Reservoir) o MOV-3602A NOTE: IF either S/G p essure i LESS THAN condensate header pressure, THEN manual iso ation of the MFW regulating and bypass valve should be c sidered before aligning for cooldown re irculation. |
| | Open the ollowing valves to align for condensate feed system oldown RECIRC: |
| | o V 982B (at N5 heater ou et header) o -3983B (at N5 heater out et header) o V-4363 (at N5 heater outle header) o V-4365 (by MFW regulating ives) |
| | V-4361 (southwest corner of condenser, middle floor) o V-3976A MFP A discharge valv bypass valve o V-3977A MFP B discharge valve bypass valve Secure all 5 secondary chemical add tion pumps on TURB BLDG middle floor by N5 heaters. |
| | o Secure all 3 ammonia pumps, TURB BLDG basement by MCC A. |
| | |
| | +1 I Q |
| | I t l A t |
| | |
| | EOP: |
| | REV: 4 ATT-17.0 ATTACHMENT SD-1 PAGE 2 of 2 o Isolate SW from the following coolers: |
| | o MFW Pump Oil Coolers (MFW pump room) o V-4703 o V-4704 o Exciter Air Cooler: |
| | o V-4679 (chain valve next to condensate transfer pump) o Bus Duct Air Cooler (TURB BLDG basement East of bus duct cooler) o V-4674 o V-4674C (mini bypass around V-4674) o Throttle SW as necessary from following coolers: |
| | o Generator Seal Oil Unit Coolers (H2 side and air side): |
| | o V-4674A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o V-4677A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o Main Lube Oil Coolers (SW corner of Turb Oil Reservoir) o V-4691 o V-4692 the turbine shaft stops, THEN notify Control o WHEN Room. Control Room personnel available to start will determine turning gear. |
| | if adequate power o Transfer house heating steam to house heating boiler if necessary (refer to T-35H, NUCLEAR HOUSE HEATING STEAM TO BOILER STEAM SUPPLY CHANGE). |
| | o Perform T-14G, STEAM GENERATOR BLOWDOWN HEAT RECOVERY SYSTEM SHUTDOWN. |
| | o Restore MAKEUP to CSTs as directed by Control Room. |
| | |
| -~}} | | -~}} |
Similar Documents at Ginna |
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999 Proposed Tech Specs,Consisting of 1999 Changes to TS Bases ML17265A6941999-06-28028 June 1999 Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping ML17265A6401999-05-12012 May 1999 Rev 11 to Technical Requirements Manual for Ginna Station. ML17265A6261999-04-18018 April 1999 Rev 10 to Technical Requirements Manual (Trm), for Ginna Station ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17309A6531999-04-13013 April 1999 Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr ML17265A6111999-03-26026 March 1999 Rev 9 to Technical Requirements Manual for Ginna Station. ML17265A5911999-03-0101 March 1999 Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5461999-02-12012 February 1999 0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required. ML17309A6481999-01-25025 January 1999 Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr ML17265A5151999-01-14014 January 1999 Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index ML17265A5081999-01-0808 January 1999 Rev 7 to Technical Requirements Manual, for Ginna Station ML17265A4961998-12-18018 December 1998 Rev 6 to Technical Requirements Manual. ML20198C0361998-12-14014 December 1998 Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required ML20198C0121998-12-14014 December 1998 Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow ML20198C0581998-12-14014 December 1998 Rev 5 to FR-Z.1, Response to High Containment Pressure ML20198C0411998-12-14014 December 1998 Rev 16 to FR-C.1, Response to Inadequate Core Cooling ML20198C0521998-12-14014 December 1998 Rev 13 to FR-S.1, Response to Reactor Restart/Atws ML17265A4661998-11-24024 November 1998 Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR ML20155G0301998-10-30030 October 1998 Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop ML17265A4091998-08-24024 August 1998 Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr ML17265A3721998-07-16016 July 1998 Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr ML17265A3151998-06-0404 June 1998 Proposed Tech Specs Basis Re Main Steam Isolation Setpoint ML17265A2941998-05-21021 May 1998 Tech Specs Consisting of Submittal Changes for 1998 ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A2461998-04-27027 April 1998 Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17264B0671997-10-0808 October 1997 Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements ML17264B0441997-09-29029 September 1997 Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept ML17264B0391997-09-29029 September 1997 Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264B0031997-08-19019 August 1997 Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3 ML17264A9991997-08-19019 August 1997 Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. ML17264A9391997-07-0707 July 1997 Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev ML17264A9341997-07-0101 July 1997 to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624 ML17264A9461997-06-20020 June 1997 to Inservice Insp (ISI) Program. ML17264A9241997-06-0303 June 1997 Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection ML17311A0471997-05-22022 May 1997 Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr ML17264A8671997-04-24024 April 1997 Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements 1999-06-28
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17265A6401999-05-12012 May 1999 Rev 11 to Technical Requirements Manual for Ginna Station. ML17265A6261999-04-18018 April 1999 Rev 10 to Technical Requirements Manual (Trm), for Ginna Station ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. ML17309A6531999-04-13013 April 1999 Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr ML17265A6111999-03-26026 March 1999 Rev 9 to Technical Requirements Manual for Ginna Station. ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. ML17265A5461999-02-12012 February 1999 0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required. ML17309A6481999-01-25025 January 1999 Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr ML17265A5151999-01-14014 January 1999 Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index ML17265A5081999-01-0808 January 1999 Rev 7 to Technical Requirements Manual, for Ginna Station ML17265A4961998-12-18018 December 1998 Rev 6 to Technical Requirements Manual. ML20198C0581998-12-14014 December 1998 Rev 5 to FR-Z.1, Response to High Containment Pressure ML20198C0361998-12-14014 December 1998 Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required ML20198C0521998-12-14014 December 1998 Rev 13 to FR-S.1, Response to Reactor Restart/Atws ML20198C0411998-12-14014 December 1998 Rev 16 to FR-C.1, Response to Inadequate Core Cooling ML20198C0121998-12-14014 December 1998 Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow ML20155G0301998-10-30030 October 1998 Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop ML17265A4091998-08-24024 August 1998 Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr ML17265A3721998-07-16016 July 1998 Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. ML17264A9391997-07-0707 July 1997 Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev ML17264A9341997-07-0101 July 1997 to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624 ML17264A9461997-06-20020 June 1997 to Inservice Insp (ISI) Program. ML17311A0471997-05-22022 May 1997 Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr ML20140B8291997-03-24024 March 1997 Rev 3 to EOP ATT-12.0, Attachment N2 Porvs ML17264A8221997-02-0606 February 1997 Rev 15 to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition. ML17264A8201997-02-0606 February 1997 Rev 7 to AP-RCC.2, Rcc/Rpi Malfunction. ML17264A8081997-01-23023 January 1997 Revised Emergency Operating Procedures,Including Rev 14 to E-1,Rev 19 to E-3,Rev 14 to ECA-2.1,Rev ECA-3.3,Rev 20 to ES-1.3,Rev 13 to FR-C.1,Rev 12 to FR-C.2 & Rev 14 to FR-P.1 ML20133N3351997-01-10010 January 1997 Rev 7 to FR-C.3, Response to Saturated Core Cooling ML17264A8881996-10-10010 October 1996 Rev 9 to ODCM for Ginna Station. ML20128N0681996-10-0303 October 1996 Revised Emergency Operating Procedures,Including Rev 5 to Att-10.0, Attachment Faulted S/G & Rev 6 to Att-16.0, Attachment Ruptured S/G ML17264A5311996-05-31031 May 1996 Revised Emergency Operating Procedures,Including Rev 10 to AP-RCP.1,Rev 12 to ECA-0.1,Rev 12 to ECA-2.1,Rev 3 to FR-H.2,Rev 3 to FR-H.4,Rev 7 to FR-I.1,Rev 12 to FR-P.1,Rev 10 to FR-S-1 & Rev 6 to FR-S.2 ML17264A5161996-05-22022 May 1996 Rev 2 to Technical Requirements Manual (TRM) ML17264A4581996-04-0808 April 1996 Rev 7 to ODCM for Ginna Station. ML17264A4371996-04-0101 April 1996 Rev 1 to Technical Requirements Manual (TRM) ML17264A4391996-04-0101 April 1996 Rev 1 to Updated Technical Requirements Manual (TRM) ML17264A4191996-02-24024 February 1996 Rev 0 to Technical Requirements Manual (Trm). ML17264A6901996-02-23023 February 1996 Rev 0 to Inservice Testing Program. 1999-05-12
[Table view] |
Text
PRIORITY (ACCELERATED RIDS PROCESSIX REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9502130285 DOC.DATE: 95/02/03 NOTARIZED: NO DOCKET FACIL:50-244 RobertEmmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION WYDAY,Z.A. Rochester Ges & Electric Corp. pi RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A. Project Directorate I-3 (PDl-3) (Post 941001)
SUBJECT:
Rev 5 to Att-17.0, "Attachment SD-1." W/950203 ltr.
DISTRIBUTION CODE A045D COPIES RECEIVED:LTR J ENCL SIZE:
TITLE: OR Submittal: Emergency Preparedness,Pla s, Implement'g Procedures, C 0 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 R
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL ~ICE CENTER P1 1 1 NRR/DRSS/PEPB 1 1
~NUDOCS A'BSTRACT 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
0 U
N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACI'THE DOCUMENTCONTROL DESK, ROOM PI -37 (EXT. 504-2083 ) TO E Llih!INATE YOUR NAME FRO~I DISTRIBUTION LISTS FOR DOCI;MENTS YOU DON"I'LED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 7 ENCL 7
t <<P,/.<<III<<I
<<<<<<<<<<<<&'J<<<<<<<<<<<<<<<<<<<<I ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N. Y. 14649-0001 TELEPHONE AREA COOE 71B 546-2700 February 3, 1995 Mr. Allen Johnson Project Directorate I-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very Truly Yours, a.d oseph A. Widay JAW/jdw xc: Mr. Lee Bettenhausen, USNRC, Region 1 Resident Inspector, Ginna Station RG&E Nuclear Safety & Licensing y/,on2S 9502130285 950203 PDR ADOCK 05000244 F PDR
Page 2
Enclosures:
ATT-17.0 Revision 5
EOP: 1' ILE:
REV: 4 ATT-17.0 ATTACHMENT SD-1 PAGE 1/of 2 Su rintendent Date 7 Perf m the following local actions to complete normal secondary syste shutdown:
ose reheater 4th pass temperature control valves:
V-2432 (SW corner 1A MSR) o V-2433 (SW corner 1B MSR) o V-2434 (SW corner 2A MSR) o -2435 (SW corner 2B MSR)
Close r heater steam chain valves:
o V-3 50 (SW of 1B MSR) o V-35 1 (SW of 1b MSR) o V-355 (NW of 1A MSR) o V-3553 (NW of 1A MSR) 0 Open Reheater steamline vents SW corner of condenser, middle floor):
o V-8500 o V-8501 o V-8502 o V-8504 o V-8505 Close flange heting solation valves:
o MOV-3601A (TB i die Lvl West of TURB L.O. Reservoir) o MOV-3602A NOTE: IF either S/G p essure i LESS THAN condensate header pressure, THEN manual iso ation of the MFW regulating and bypass valve should be c sidered before aligning for cooldown re irculation.
Open the ollowing valves to align for condensate feed system oldown RECIRC:
o V 982B (at N5 heater ou et header) o -3983B (at N5 heater out et header) o V-4363 (at N5 heater outle header) o V-4365 (by MFW regulating ives)
V-4361 (southwest corner of condenser, middle floor) o V-3976A MFP A discharge valv bypass valve o V-3977A MFP B discharge valve bypass valve Secure all 5 secondary chemical add tion pumps on TURB BLDG middle floor by N5 heaters.
o Secure all 3 ammonia pumps, TURB BLDG basement by MCC A.
+1 I Q
I t l A t
EOP:
REV: 4 ATT-17.0 ATTACHMENT SD-1 PAGE 2 of 2 o Isolate SW from the following coolers:
o MFW Pump Oil Coolers (MFW pump room) o V-4703 o V-4704 o Exciter Air Cooler:
o V-4679 (chain valve next to condensate transfer pump) o Bus Duct Air Cooler (TURB BLDG basement East of bus duct cooler) o V-4674 o V-4674C (mini bypass around V-4674) o Throttle SW as necessary from following coolers:
o Generator Seal Oil Unit Coolers (H2 side and air side):
o V-4674A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o V-4677A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o Main Lube Oil Coolers (SW corner of Turb Oil Reservoir) o V-4691 o V-4692 the turbine shaft stops, THEN notify Control o WHEN Room. Control Room personnel available to start will determine turning gear.
if adequate power o Transfer house heating steam to house heating boiler if necessary (refer to T-35H, NUCLEAR HOUSE HEATING STEAM TO BOILER STEAM SUPPLY CHANGE).
o Perform T-14G, STEAM GENERATOR BLOWDOWN HEAT RECOVERY SYSTEM SHUTDOWN.
o Restore MAKEUP to CSTs as directed by Control Room.
-~