ML20044B965
| ML20044B965 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/09/1993 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20044B964 | List: |
| References | |
| NUDOCS 9303160015 | |
| Download: ML20044B965 (61) | |
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' Y REFERENCE MATERIAL INDEX I
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ATEAODfEFlE A REMEDe[E M121 RIALS 11R JLBE 1993 LTCDGENG FLW Insson Plan No. Tit 1e Revision No. Revision Date 4-1-6 Verhal Camunication 1 August 9,1991 7-11-1 Auxiliary Feedwater 4 January 13, 1992 7-11-2 Chmical and Volum Cbatrol 4 Doc mber 3, 1992 7-11-3 C.tzculating Water 2 June 4, 1990 7-11-4 Condensate 3 November 18, 1990 7-11-5 Candenser Air Rer: oval 3 June 17,1992 7-11-6 Oxponent Cooling Water 4 August 28, 1992 7 7 Cmpressed Air 3 Decmber 18, 1990 7-11-8 Cantain m nt 4 Novmber 18, 1992 June 9, 1992 7-11-11 Feedwater and Fealwater Regulating 7 7-11-12 Fire Pzvtection 4 June 1,1991 7-11-13 Fuel Handling 4 June 5,1992 7-11-1 7 Main Steam Systm 8 June 5,1992 7-11-18 Main Turbine .2 October 9, 1989 7-11-19 Raw Water 4 August 21, 1991 7-11-20 Reactor Coolant Systm (RCIS) 5 September 25, 1992 7 21 Rmctor Vessel and Cam Construction 3 June 15,1990 7-11-22 Safety Injection and Cantainmnt Spray -9 June - 2, 1992 ;
7-11-25 Stmm Generatar Blagicwn 2 Cttober 31, 1989 7-11-29 Turbine Lube Oil 5 June 24,1991 7-11-32 Waste Disposal Liquid Systm 3 Novmber 7,1990 7-12-1 Auxiliary Feed Shutdown Panel AT-179 3 April 1,1992 7-12-2 Alternate Shutdown Panel AI-185 2 March 31, 1988 7-12-3 Am3 and Pzocess Rad Manitors 4 July 16, 1992 A-1
ATinGMM1' A REETREME }MHRIATE Im JimE 1993 IJCDGIMI 200W Lesson P1an No. Title Revisian No. Revieion Date 7-12-11 ESC-Aux Feedwater Actuation (AFAS) 3 March 24,1992 7-12-14 Ebgineezed Safeguanis Canttv1 Systan 4 January 14, 1993 7-12-18 Nacimr Instnments - WR Log Channels 3 June 7,1990 7-12-19 Nuclmr Instturents - Power Range 4 October 15, 1991 Safety 7-12-20 Incom Nuclmr Instnmentation 4 August 21, 1992 7-12-23 Qualified Safety Paraneter Display 2 May 22, 1990 Systan l
7-12-25 Rmctor Pmtective Systan and Diverse 8 Novanber 30, 1992 Scram Systan 7-12-26 Cantml Rcd Drive Systan 3 June 3, 1992 7-12-29 Turbine Electrahydraulic Cantml 4 August 28, 1992 7-1 2-31 Rmctor Ra] and Stmm Bypass 3 May 3, 1991 7-13-1 HV and Grid Systan 5 Decemtur 30, 1991
^
7-13-2 4160V Distribution 6 January 14, 1992 7-13-3 480 VAC Electrical Distribution 3 December 9,1991 7-13-4 125 VDC and 120 VAC Distribution 6 Novanber 18, 1992 '
4 7-13-5 Diergency Diesel Generator 5 September 1, 1992 7-13-6 Main Generator 5 October 5,1992 7-14-1 Auxiliary Building Ventilation 2 January 3, 1991' 7-14-2 Cantairment Air Cbolixx] 5 October 26, 1992 7-14-3 Containrrant Hydtujen Purge 4 June 19,1990 t
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A-2
i ATLA' BFfENT A RFEERDNCE MMERIALS Int JL9E 1993 LTORGING DOW Lesson Plan No. Title Revision No. Revision EUte 7-14-4 Containnent Partje 3 January 4, 1990 7-14-5 CEDY Cooling /Nucimr Lk?tector Well 2 June 22,1992 Cooling 7-14-6 Control Roan Ventilation 7 Septernber 9,1991 7-15-12 Transient and Accident Analysis 2 lbvembcr 10, 1992 7-15-16 Loss of Flow 2 Jan ary 9, 1992 7-15-17 Loss of Fcotwater 2 January 16, 1992 7-15-20 Dccessive Hmt Raroval Events 3 February 27, 1992 7-1 5-21 Loss of Imd 1 April 5,1988 7-15-23 Loss of Coolant Accidents (LOCAs) 4 February 5,1993 7-15-28 Mitigating Coze LMnage 2 March 21,1991 ,
7-1 5-31 Intzoduction to Transient and Accident 0 February 22,'1991 Analysis 7-15-32 Rmctivity Events 0 February 26, 1991 ,
7-15-33 Stmm Generator Tuba Rupture 1 August 14, 1992 7-15-34 Dose Assessnent Overview 0 January 22, 1993 i
7-17-1 AOP-1 Acts of Nature 3 October 21, 1992 7-17-2 AOP-2 CEEN Malfunction 3 October 20, 1992 7-17-3 AOP-3 Diergency Boration 3 Cttoter 21,'1992 7-17-5 AOP-5 Drergency Shutdown 3 October 12, 1992 ,
7-17-6 AOP-6 Drezgency Fire Proacdure 5 Decanber 21, 1992 7-17-7 AOP-7 Forced Evacuation of Control Rocan 3 Decernber 21, 1992 b
F A-3
ATTAC1MXP A REFERDCE MLTERIALB EtR JlNE 1993 IJONSIN3 EXMi Lesson Plan No. Title Revision No. Revision EMte 7-17-8 JDP-8 IDel Handling Accident 2 October 12, 1992 7-17-9 AOP-9 High Radiwctivity 3 October 19, 1992 7-17-10 AOP-10 Lass of Circulating water 3 OctaMr 14, 1992 7-1 7-11 AOP-11 Loss of Canpanent Oooling Water 3 October 23, 1992 7-17-12 ADW12 Loss of Cantainmnt Integrity 3 October 6,1992 ,
7-17-13 AOP-13 Loss of Cbntrol Roctn Air 4 October 20, 1992 Canditioning 7-17-15 AQW15 Loss of Flux Indication 3 LMcember 15, 1992 ,
7-17-16 AOP-16 Loss of Instrumnt Bus PCner 3 October 15, 1992 7-17-17 AOP-17 Loss of Instruncnt Air 4 (L~tober 21, 1992 7-17-18 AOP-18 Ioss of Raw Water 3 October 21, 1992 ;
7-17-19 AOP-19 Loss of Shutdcun 5 January 6,1993 ;
7-17-20 AOP-20 Loss of Turbine Plant Cboling 2 October 21, 1992 Water
- 7-1 7- 21 AQW21 Rwctor Ooolant Systen 2 Lucember 9,1992 l 7-1 7-22 AOW22 Rwctor Coolant Lwk 2 LMcuubea-11, 1992 7-1 7-23 ikOP-23 Reset of Engineered Safeguards 2 LMcentnr 1,1992 7-1 7-24 AOP-24 Steam Generator Tube Rupture 2 DeCETDber 1, 1992 (Rwctor Shutdcun) 7-1 7-26 AOP-26 Turbine Malfunctions 2 Notenber 30, 1992 7-17-27 AOP-27 Generatar Halfunctions 2 Decanber 21, 1992 7-1 7-28 AOP-28 Auxiliary Feedseter 2 LMcGrnber 21, 1992 i
A-4
AT1%QP!ENT A REFERENT FATERTAl$ ItR JERE 1993 IJOKSUG EXMi Lesson Plan No. Title Revision No. Revision IMte 7-17-30 AOP-30 Dmzgency Fill of EFWST 3 Dec w ber 9, 1992 7-1 7-31 ADP-31 All 4160V Buses Fed Frm 22hV 3 Dc &. 14, 1992 7-17-32 ADP-32 Loss of 4160V Bus or 480V Bus 2 Novmter 11, 1992 i
Ptner 7-1 7-34 AOP-34 1 October 8,1992 7-18-10 EQP-00 Intro to H2Ps and Standard 4 July 31, 1992 FDst Trip Actions ,
7-18-11 B2P-01 Rmctor Trip Recovery 2 October 14, 1992 7-18-12 EDP-02 Loss of Offsite Pcwer/ Loss of 3 Cttober 12, 1992 Forcui Circulation 7-18-13 EOP-03 LCCA 4 January 11, 1993 7-18-14 EOP-04 Stwm Generator Tube Rupture 3 January 28, 1993 ;
7-18-15 EOP-05 Uncontrollai Hwt Dctraction 3 January 7,1993 7-18-16 BJP-06 Loss of All Feedwater 3 January 29, 1993 7-18-17 H2P-07 Station Blackout 4 February 2,1993 7-18-18 ECP-20 Functional Recovery 4 February 3, 1993 7-53-2 ERECS 3 July 7,1992 7-62-1 Operating Manual Pzocedures Standing 6 kwie.r 29,1992 Orders 7-62-8 7bchnical Specifications 3 September 25, 1992 2 January 27, 1993 7-62-11 Use of Annunciator Respanse Proceduin ARP-1 8-11-1 100% Pcuer Cperations O April 11,1990 i
I A-5
A7'1MGMN1' A RE2HENCB MA7TRTALS Em JUE 1993 IJGN5ilhG EKMi Iesson Plan No. Title Revision No. Revision Date 8-11-2 Fill and Vent RCS O July 17,1990 8-11-3 RCS 200 PSIA Imk lust 0 July 17,1990 8-11-4 Establish Pressurizer Stwm Bubble 0 July 17,1990 8-11-5 R W Hm tup 130*F to 300*F 0 July 17,1990 8-11-6 RCS Hmtup 3OO*F to 395*F 0 July 17,1990 8-11-7 2100 RCS Isak Tust 0 July 26,1990
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8-11-8 RCS Hmtup 395*F to 532*F 0 July 26,1990 8-11-9 Pzcparation l'or a R ctor Startup 0 July 26,1990 8-11-10 Rmctor Startup - BOD, Cold 7Drbine O April 11,1990 8-11-11 Rmctor Startup - 1RX,, Wann Turbine O April 11,1990 8-11-12 Rmctor Startup - mb, Cold Turbine O April 11,1990 8-11-13 Cdticality to Dilution (OP-7) 0 April 11, 1990 8-11-14 Cdticality to Dilution (OP-7) 0 July 30, 1990 +
8-11-15 Plant Startup - Cbld 7Drbine O April 11, 1990 8-11-16 Plant Startup - Wann Turbine 0 July 30, 1990 8-11-17 Power Inctusse 15% to 50% 0 April 11,1990 8-11-18 Power Incmase 50% to 100's O April 11,1990 8-11-19 100t Stmdy State - Appmsch Xenon 0 July 30, 1990 Ek]uilibrium B-11-20 Imd Decrmse 100% to Mininann Imd 0 July 30, 1990 L
8 21 Plant Shutdown to Hot Standby 0 July 30, 1990 A-6
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.i AT12V1PRN1' A REFERENZ 12L78tTAES ItR JLNH 1993 LTONKUG EKM ,
j Iesson Plan No. Title Revision ib. Revision IMte
- 8-11-22 Rwctor Shutdcnm 0 July 30,1990 8-11-23 Initiate RCS Ocoldcun 532*F to 395 F 1 July 7,1990 8-11-24 Plant Shutdcun - Mininazn L d 7b Off 1 July 9, 1990 Line 8-11-25 RCS Cboldcun 395 to 275 0 July 30,1990 8-11-26 Plant Cooldcun 275 to 120 (OP-6) 0 July 30,1990 8-11-27 EM, Lwd Incxwse 0 July 30,1990 '
8-11-28 Plant Cooldcun Onto Shutdcun Cooling 0 July 30,1990 8 29 Refueling Operations O August 7,1990 8-12-1 Loss of 161hY Due 1b Actions of Nature 1 Septanber 1,1990 8-12-2 Dwrgency Plant Shutdcun After loss 1 October 1,1990 of 161EV ;
8-12-3 Continuous Rcd Insertion During Load 0 August 21, 1990 l Reduction 8-12-4 Inadvertent Rwctor Tcip O August 21, 1990 8-12-5 Manual R wctor Trip O Aix]ust 21, 1990 8-12-6 Rwctor Trip - No Cwplications O August 21, 1990 8-12-7 Waste Gas Der.ay Tank Rupture O August 21, 1990 6-12-8 Loss of Ptuer Range NIs O August 21, 1990 8-12-9 CTA Dzvp at High Pcunt 2 July 31,1991 8-12-10 Dmtgency Plant Shutdcun Fzun Full Lwd 0 August 21, 1990 '
- RCP Swl Failure i
>> 7
ATTAGMENI' A RETHDCB 12MRTAES HR JENe 1993 lim 611G DOW Lesson Plan No. Title Revision No. Revision Ehte :
8-12-11 Rwctor/ Plant Startup With Malfunctions 1 Septanber 16, 1991 t 8-12-12 Rwctor/ Plant Startup With GA 0 July 18,1990 Malfunctions 8-12-13 Rmctor Trip After Cantinuous Rod 0 Atx]ust 21, 1990 Witldrawal 8-12-14 Plant Shutdown Due to Inoperable NIS 0 August 21, 1990 ,
Channel 8-12-15 Loss of a Single Circulating Water Pimp 1 March 14, 1991 8-12-16 Cmplete Loss of Instzurent Air 1 Septanber 25, 1990 8-12-17 9 toke Induced Control Rocin Evacuation 0 August 21, 1990 Due lb Plant Oil Fire 8-12-18 Cbatrol Roctn Fize and Evacuation 0 August 21, 1990 8-12-19 Dnergency Baration Requi. red With 0 August 21, 1990 Rmctat Trip 8-1 2- 21 Loss of Raw Water During Shutdcun 0 August 21, 1990 i 8-12-22 AFW Failum During (boldown O July 18,1990 B-12-23 971R With PPIS Blocked 0 July 18,1990 8-12-24 Loss of Instrument Bus Pcner - 1 DC Bus O August 21, 1990 B-12-25 CW Systen Lwk 0 August 21, 1990 8-12-26 Ccuplete Loss of CCW Due to Systen Lwk 0 August 21, 1991 8-12-27 Loss of Cai to Rwctor Coolant Pungs - 0 August 21, 1990 Natural Circ Requized A-8
ATTAGPENT A RDHU2M MA71 RIALS EtR JU21993 LTG2GIRG EXMi Insson Plan No. Title Revision No. Revision Lbte 8-12-28 RCS High Activity 0 August 21, 1990 -
8-12-29 Loss of Instnrent Bus Pcwr - Single O August 21, 1990 '
120VAC Bus 8-12-30 Plant Shutdcnn With Loss of TPCW D August 21, 1990 8-1 2-31 Inadvertent ECCS Actuation O August 21, 1990 8-12-32 Inadvertent ECCS Actuation in Made 3 0 August 21, 1930 >
8-12-33 LOCA During Cboldown - PPIS Blockel 0 August 21, 1990 8-12-34 ILEA While on Shutdoan Cboling 0 August 21, 1990 8-12-35 Plant Shutdown Due 2b Cbndenser Air 0 August 21, 1990 L mkage 8-12-36 Loss of Turtune Dmring Oil 0 August 21, 1990 8-12-37 Turbine Malfunction - High Vibration 0 August 21, 1990 8-12-38 Generator Malfunctions O August 21, 1990 ,
8-12-39 Loss of Shutdown Cooling - Mode 4 0 August 21, 1990 8-12-40 Loss of Shutdown - RCS Drained 0 August 21, 1990 i 8-1 2-41 RCS Leak Requiring Dreit]ency Shutdown 0 June 4, 1990 8-12-42 SG Tube Lwk With Fuel Ciad Failure O August 21, 1990 8-12-43 01anying Hmder Laak O/S Contallment 0 June 5, 1990 Lwd Inctmse .
B-13-1 Rwctor Trip Folicmng Cmponent 0 April 11,1990 Malfunctians 8-13-2 Rmctor Trip With Minor Cmplimtions O April 11,1990 ;
I A-9 l
ATinCTRfENT A RF2TIDCU MA11 RIALS ItR Jine 1993 I2CEN'iDG FXW f
Insson Plan No. Title Revision No. Revislan Ibte 8-13-3 Ccinplete I.oss of All AC IDwer Souztes 0 June 4, 1990 8-13-4 Loss of Offsite Power 1 July 9, 1990 8-13-5 Rwctor 2 rip Due to IDss of CCH to RCPs O August 17, 1990 8-13-6 RCS Isak - Incmssing to SBEDC4 1 July 9, 1990 8-13-7 ILEA Due to Ejectal GA 0 August 21, 1990 8-13-8 Rwctor Trip With Lwk1ng REV O August 21, 1990 8-13-9 Stwm Generatar 2Dbe Ruptum - At Power 1 July 9, 1990 8-13-10 Significant Stwm Generatar 7ube Inak 0 August 21, 1990 8-13-11 Main Stwm Line Bmak Outside of 0 May 31, 1990 Cbata2n mnt 8-13-12 Main Stwm Line Bmak Inside 0 July 18, 1990 Cantainnent 8-13-13 Main Stwm Camon Hwder Bmak During 0 August 21, 1990 Lwd inamase 8-13-14 Ccrplete Loss of Feoctaater - Condensate O August 21, 1990 Recovery 8-13-15 7Dtal Loss of Feed Capability - Am O Atgust 21, 1990 Recovery 8-13-16 Multiple Failums - Rmctor Trip With 0 August 21, 1990 functional Recovery 8-13-17 Stwm Line Break With 371R 0 August 21, 1990 8-13-18 Main Stmm Line Lwk Inside Cbntainmnt 0 August 21, 1990 B-13-19 Rwcta: Trip With S/G Prossum Control 0 July 18,1990.
Failum +
A-10
AT1701 err A REFERENCE M111 RIALS KR JEN8' 1993 IJJNSDG EDTAM Insson Plan No. Title Revision No. Revision Date 8-13-20 Inss of offsite Pcwz with Inss of C04 0 May 31, 1990 8-13-21 Sequential Loss of All Main Feedwater, O July 18,1990 1DAEW Stmm Idne Imk 8-13-22 Maximum Size IlrA Inside Containrent 2 Septmber 29, 1990 8-13-23 Isolable Feedwater Imk Inside O July 18,1990 Contaizment With IDP 8-13-24 Stmm Generatar Tube Ruptum Follcuity 0 July 18,1990 Imd EXcursian 8-13-25 Station Blackout 0 August 21, 1990 8-13-26 IDCA Without RPSI Purqps 0 July 8,1990 10-70-003 Classification Bases 1 March 24,1992 . .
10-70-005 Pmtective Action Recctmendations 0 Docanber 18, 1990 10-70-06 Dwzgancy Dizaction and Cantml 1 lbvenbar 27, 1991 1 0- 70-09 ERO Pmtective Actions 1 Ncnunber 15, 1991 10-27-13 GET Station Grientation 10 10-27-21 GET II Radiation Worker Trainity 10 19-20-40 Radiation Detection and Mwsururnt 2 June 25,1991 19-23-08 Radiation Survey Instzuwnts 3 Ncnunbar 9,1992 19-24-03B Radiation Pzotection Manual 2 Septanber 7,1989 Fami 1iar-ization 1
A-11
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ATinGHN1' A RFIERENCE MLDETALS RR JUE 1993 LICENIDG MAFi SDI Title Revisian No. Revision Date Alternate Shutdam Panels 3 1/20/92 Auxiliary Building INAC 2 2/1 7/93 Auxiliary Feedwater 6 9/25/92 Auxillazy Steam 0 4/27/92- ,
02emical and Volum Cantivl 5 9/25/92 01emical Feed 0 5/22/92 Chanical Waste Iagoans and Neutralization 0 9/18/92 Circulating Water 3 10/11/91 Cwpanent Cooling Water 5 10/9/92 Cmpressed and Ins +mt Air 3 9/26/91 Cbndensato and Feedwater 5 10/9/92 Condenser Evacuation 1 10/9/92 Cantainnent 1 10/3/91 b
Cantainmnt Hydttgen Analyzer 1 10/9/92 Cantzol Rod Drive 2 1/15/92 Dwuneralized Water 3 10/16/92 Electrical Distribution 5 2/10/93 D:ergency Care Cooling 7 2/18/93 D:ergency Diesel Generators 3 1/16/92 D:cigency Lighting 0 7/2/92 Diczgency Response Facilities Cwputer O 3/18/92 Engineezed Safeguants Cantivls 6 11/10/92 Fire Pzotection 4 2/4/93 Hydzu]en and Nitztgen 0 4/14/92 A-12
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ATEA 09tDff A REFDENQ191HRIAl$ EtR JLNF: 1993 LIGNSDG FJGW .
l S7M Title Revision No. Revision Date .
Main Generatar 3 9/18/92 Main Steam 2 10/16/92 Main 'Ivrbine and Turbine Auxillaries 5 1/10/92 Miscellaneous Plant Water Systars 0 7/2/92 Racimr Instrumentation 3 9/10/92 Plant Canununication 1 4/8/92 Post-Accident Sanpling 0 3/31/92 Radiation Manitoring 1 2/ 21/ 9 2 Raw water 6 10/9/92 RCS Instzunentation and Rmctar Regulating 2 3/ 28/91 Rmctor Coolant Systen 3' 3/28/91 Rwctor Pzotection 1 1/20/92 ,
1 Rmctor Vessel and Com Constraction 3 1/6/92 Refueling 3 3/13/92 Sanpling Systans 0 6/26/92 Saniatory ard Stann Drain 1 11/9/92 Spent Fuel Pool Cooling 1 9/18/92 Turbine Plant Cooling Water 2 2/19/91 '
Vacumn Prinung 0 2/19/92 Vibration and Loose Parts Manitoring 0 4/6/92-Waste Disposal 4 12/11/91 A-13
AT1AmMENT A 183fSD T)LSK 10 7EAINDG M11RTGS RR JE121993 IJCENSDC E;GW Plmse zufer to Book 25 and Book 26 of the June 1992 nailing.
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9 A-14
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./ IROGlXRE REVISIM MMBERS Im JDn21993 IJCDGI2G EKMi The follwing indexes contain the pmcedure mvision numbers to be used far developing the Reactar Operator License Dcams for June 1993.
- 1. Energency Operating Procedures
- 2. Abnaaral Operating Pmcodums
- 3. Operating Procedums
- 4. Operating Instructions
- 5. Standing Onlezs (Adridnistrative Pmcedures)
- 6. 'Ibchnical Data Book
- 7. Ibchnical Specifications
- 8. Radiation Pmtection - Only the follwing Radiation Protection Proccdums are being sent per this nailing. Please discard all other Radiation Pmtection Pmcedures in your possession.
\p~') RP-201 RP-216 RP-202 RP-405 RP-204 RP-602 RP-205 RP-605 RP-206 RPP RP-207
- 9. Drezgency Plan Inglementing Pmcedures
- 10. Annunciator Respanse Pmcedums I
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B-1
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FORT CALHOUN STATION PAGE 1 0F 1 EMERGENCY OPERATING PROCEDURE INDEX ,
PROCEDURE NUMBER TITLE REVISION /DATE ,
[EOP-00] Standard Post Trip Actions R1 09-03-92 E0P-01 Reactor Trip Recovery R0 12-21-92
[EOP-02] Loss of Off-site Power / Loss of Forced R1 12-21-92 Circulation
[EOP-03] Loss of Coolant Accident RI 12-22-92
[E0P-04] Steam Generator Tube Rupture R1 12-21-92
[EOP-05] Uncontrolled Heat Extraction R1 12-21-92 ,
[EOP-06] Loss of All Feedwater R1 12-21-92
[EOP-07] Station Blackout RI 12-21-92
[EOP-20] Functional Recovery Procedure R0 12-21-92 E0P E0P Attachments R0 12-21-92 ATTACHMENTS A
i
[ ] "On Going" Commitments FC/INDEX/KKK 12/22/92 8:49am
FORT CALHOUN STATION PAGE 1 0F'1 ABNORMAL OPERATING PROCEDURE INDEX P RE TULE REVISION /0 ATE A0P-01 Acts of Nature R0 06-17-92 AOP-02 CEA and Control System Malfunctions R0 06-17-92 r A0P-03 Emergency Boration R0 06-17-92 A0P-05 Emergency Shutdown R1 07-29-92
[A0P-06] Fire Emergency R0 12-21-92 A0P-07 Evacuation of Control Room R0 12-21-92 A0P-08 fuel Handling Incident R0 06-17-92 .
A0P-09 Hig.h Radioactivity R0 06-17-92 AOP-10 Loss of Circulating Water R0 06-17-92
[ADP-11] Loss of Component Cooling Water R0 12-21-92 AOP-12 Loss of Containment Integrity R0 06-17-92 AGP-13' Loss of Control Room Air Conditioning R0 06-17-92 A0P-15 Loss of Flux Indication R0 06-17-92 A0P-16 Loss of Instrument Bus Power RO 09-03-92 Loss of Instrument Air RO 06-17-92
[A0P-17]
Loss of Raw Water R0 06-17-92
[AOP-1B]
loss of Shutdown Cooling R0 12-21-92 (A0P-19]
AOP-20 Loss of Bearing Water Cooling R0 06-17-92 A0P-21 Reactor Coolant System High Activity R0 06-17-92 A0P-22 Reactor Coolant Leak R0 12-21-92 A0P-23 Reset of Engineered Safeguards RO 06-17-92 A0P-24 Steam Generator Tube Rupture (Reactor Shutdown) R0 12-21-92 A0P-26 Turbine Malfunctions RO 06-17-92 AOP-27 Generator Halfunctions R0 06-17-92 A0P-28 Auxiliary feedwater System Malfunctions R0 12-21-92 A0P-30 Emergency Fill of Emergency Feedwater Storage Tank R0 06-17-92 AOP-31 All 4160V Buses fed From 22KV R1 12-21-92 A0P-32 Loss of 4160 Volt or 480 Volt Bus Power R0 12-21-92 A0P-34 Loss of the ERF, QSPDS or Security Computer R0 06-17-92 FC/INDEX/KKK 12/17/92 9:08am i
FORT CALHOUN STAT 10N PAGE 1 0F 1 OPERATING PROCEDURE INDEX CEDURE sMBER TITLE REVISION /DATE i
i
[*0P-1] Master Checklist for Start-Up or-Trip Recovery R23 03-01-93
- 0P-2 Plant Startup from Refueling or Cold R4 01-28-93 Shutdown to Hot Shutdown ,
- 0P-3 Plant Startup from Hot Standby to Minimum Load R6 01-28-93'
- 0P-4 Load Change and Normal Power Operation -R6 01-28-93
- 0P-5 Plant Shutdown R8 01-28-93
[*0P-6] Hot Shutdown to a Cold or Refueling Condition R6 01-28-93 'I and Conduct of Shutdown Cooling Operations
- 0P-7 Reactor Startup R7 01-28-93
- 0P-8 Reactor Shutdown R2 01-28-93 OP-9 Reactor Coolant Pump Partial Loop Operation DELETED
' -10 Annunciator Response Procedure, Index (R4. 09-14-89)
SUPERSEDED 04-30-91 uP-10-DG1 LOCAL Annunciator DG-1 Local (R1 01-14-89)-
SUPERSEDED 04-30-91' OP-10-DG2 LOCAL Annunciator DG-1 Local '(R1 03-07-89)-
SUPERSEDED 04-30-91
- 0P-11 Reactor Core Refueling R6 01-28-93 i
i "On Going" Commitments l
- Project 1991 Procedure Upgrade FC/INDEX/MC 02/26/93 11:28am !
FORT CALHOUN' STATION PAGE'1 0F 14
~
. OPERATING INSTRUCTIONS INDEX PROCEDURE NUMBER TITLE REVISION /DATE AB-1 Auxiliary Boiler Normal Operation R5 01-28-93
- AFW-1 Auxiliary Feedwater Actuation System R16 02-16-93 Normal Operation ,
[*AFW-2] Auxiliary Feedwater System Actuation and R1 01-28-93
- Bypass
- AFW-3 Off Normal Auxiliary Feedwater Operation R3 01-28-93
- AFW-4 Auxiliary Feedwater Startup and System RIO 02-19-93 .
Normal Operation >
[*AS-1] Auxiliary Steam System Normal Operation R10 03-01-93~
- BA-1 Boric Acid Treatment of Steam Generators R1 01-28-93 -
- BW-1 Turbine Plant Cooling Water System Normal R5 01-28 Operation 4
- BW-2 Turbine Plant Cooling Water Chemical Addition R1 01-28-93 and Makeup'
- BW-3 Turbine Plant Cooling Water System Startup R1 01-28-93 forbine Plant Cooling Water System Shutdown R1- 01-28-93
- BW-4
- BW-5 Turbine Plant Cooling Water System Operation R2 01-28-93 with the Demineralized Water System Cooling CW-6A/6B
[*CA-1] Compressed Air System Normal Operation R12 01-28-93
- CA-2 Compressed Air System Weekly Checks R4 01-28-93 :
- CA-3 Compressed Air System Auxiliary Building R3 01-28-93 4 and Containment Instrument Air Outage
- CA-4 Compressed Air System, Containment R1 01-28-93 Instrument Air Outage
- CA-5 Compressed Air System Backup Cooling Supply R6 01-28-93 Operation CA-6 Operation of Temporary Air Dryer -(R1 05-01-90)
CANCELLED 09-18-90 !
[ ] "On Going" Commitments Project 1991 Procedures Upgrade FC/INDEX/MC 02/26/93.11:27am -
FORT CALHOUN STATION PAGE 2'0F 14 OPERATING INSTRUCTIONS _INDEX .j PROCEDURE NUMBER TITLE REVISION /DATE i
CA-7 Radwaste Building Compressed Air Normal R1 01-28-93 '
Operation
[*CC-1] Component Cooling System Normal Operation R12 01-28-93 ;
- CC-2 Component Cooling Chemistry Control R4 01-28-93a
- CC-3 Component Cooling Water Special Operations R3 01-28-93
- CC-4 Component Cooling Water Outage for R8 01-28-93 Maintenance System Drain Down
- CC-5 Corrosion Inhibitor Concentration Reduction R3 01-28-93 through Ion Exchange Resin
- CC-6 Component Cooling Water -(CCW) System Cleanup R1 01-28-93
- CE-1 Condenser Evacuation. System Normal Operation R2 01-28-93
- CE-2 Condenser Air In-Leakage Check R1 01-28 *CF-1 Secondary Chemical Feed System Normal R8 01-28-93 Operation
[*CH-1] Chemical and Volume Control System R15 01-28-93 :
Normal Operation
[*CH-2] CVCS Purification System Normal Operation R7 01-28-93 ;
CH-3 Chemical and Volume Control System Normal Operation of the Volume Control Tank R5 01-28-93 9
[*CH-4] Chemical and Volume Control System R12 01-28-93 Makeup Operations
'CH-5 Concentrated Boric Acid System - Normal R5 01-28-93 Operation ,
- CH-6 CVCS Resin Transfer R5 01-28-93
- CH-7 Resin Addition to CVCS Ion Exchangers R4 01-28-93
^
DELETED 12-30-86
[ ] "On Going" Commitments Project 1991 Procedures Upgrade FC/INDEX/MC 02/23/93 2:24pm
i FORT'CALHOUN STATION PAGE 3 0F 14 o OPERATING INSTRUCTIONS.INDEX PROCEDURE NUMBER TITLE REVISION /DATE
- CH-10 Saturating New Resin With Boron R2 01-28-93 l
- CH-11 Boron Concentration in Reactor Coolant System R1 01-28-93 CL-1 Plant Discharge to Chemical Lagoons / (R2 07-07-88)
Neutralization Basin DELETED 06-24 [*CL-2] Chemical Lagoons / Neutralization Basin RIO.01-28-93 Recirculation and Transfer
[*CL-3] Chemical Lagoons Discharge R9 01-28-93
- CL-4 Chemical Lagoons / Neutralization Basin R2 01-28-93 pH Adjustment i CL-5 Caustic Transfer from Bulk Caustic Drum R1 01-28-93 to Bulk Caustic Storage Tank (CL-5)
[*CO-1] Containment Closure R5 01-28-93
- CO-2 Personnel Air Lock R3 01-28-93 .
C0-3 Equipment Hatch Operation (Replaced by DELETED 12-30-86 :
[*C0-4] Refueling Containment Integrity R5 01-28-93
- C0-5 Containment Integrity R6 01-28-93 ;
- CP-1 Plant Communications Normal Operation R1 01-28-93 CRP-1 Normal-Operation of the C/RP Building R2 01-28-93 -
Equipment ,
l CRP-1 Normal Operation of CRP Building HVAC Systems R2 01-28-93 1 SECTION A1 Office Area CRP-1 Normal Operation of CRP Building HVAC Systems R1 01-28-93 SECTION A2 Cafeteria and Office Area CRP-1 Normal Operation of CRP Building HVAC Systems R1 01-28-93 SECTION A3 Locker Rooms CRP-1 Heating, Cooling and Ventilation -- Normal R2 01-28-93 ;
I SECTION A4 Operation Chemistry and Radiation Protection Building - Laboratory Area
[ ] "On Going" Commitments i
Project 1991 Procedures Upgrade )
FC/INDEX/MC 02/23/93 2:24pm
S 1
c FORT CALHOUN STATION PAGE-4 0F=14' OPERATING INSTRUCTIONS INDEX PROCEDURE-NUMBER TITLE REVISION /DATE-
[*CS-1] Containment Spray - Normal Operation R9 01-28-93
- CW-1 Circulating Water System Normal Operation R2. 01-28-93
- CW-2 Screen Wash Sys' tem Normal Operation R4 01-28-93
- DG-1 Diesel Generator No. 1 (DGI) Normal Operation R9 02-24-93
- DG-2 Diesel Generator No. 2 (DG2) Normal Operation R10 02-24-93
- DSS-1 Diverse Scram System Normal Operation R2 01-28 *DW-1 Demineralized Water Pretreatment System R3 01-28-93 Normal Operation
- DW-2 Sand and Carbon Filters Normal Operation R2 01-28-93
- DW-3 Demineralized Water Plant Normal Operation R8 .02-18-93
- DW-4 Deaerated, Water System Normal Operation R3 01-28-93
- DW-5 - Chlorine Gas System Normal Operation R3 01-28-93 DW-6 Chemical Lagoon Recirculation (R1 09-02-83)
DELETED 05-14-85 DW-7 Chemical Lagoon Discharge (R2 09-02-83)
DELETED 05-14-85 DW-8 Chemical Effluent Lagoon Discharges (R0 06-29-79)
DELETED 05-14-85 EE-RWPB-1 Normal Operation of the Radwaste Processing R1 01-28-93 Building Equipment
- EE-TSC-1 Technical Support Center (TSC) Normal 480V, R2 01-28-93 208V and 120V Electrical Alignment
- EE-1 4160 Volt System Normal Operation R7 '01-28-93
- EE-1A 4160 Volt Circuit Breaker and Control Switch R2 01-28-93a Operation
- EE-1B Transfer of In-House Service Between 161KV R1 01-28-93 and 22KV
- EE-2 480 Volt AC System Normal Operation R15 01-28-93a
[ ] "On Going" Commitments Project 1991 Procedures Upgrade FC/INDEX/MC 02/23/93 2:24pm
FORT CALHOUN STATION PAGE 5 0F 14-- ,
OPERATING INSTRUCTIONS INDEX t
PROCEDURE NUMBER TITLE REVISION /DATE
- EE-2A 480. Volt Circuit Breaker and Control Switch R2 01-28 [
Operation j
[*EE-2B] 480 Volt Hot Bus Transfer R6 01-28-93ay
- EE-3 125 VDC System Normal Operation R6 01-28-93
[*EE-4] 120 Volt AC System Normal Operation R12 01-28-93
- EE-5 Station Lighting and Bus Transformer R3 28-93 l Operations
- EG-1 345KV Grid System Normal Operation R3 01-28-93
^
- EG-2 161KV Grid System Normal Operation R2 01-28-93
[*ERFCS-1] Emergency Response Facility Computer System R6 01-28-93a Core Monitoring Systems R1 01-28-93 I
[ERFCS-2]
- ES-1 Engineered Safeguard Controls - Normal R5 01-28-93 Operation j
- ES-2 Engineered Safeguards Controls-Cold Shutdown R2 01-28-93 ,
Operation i
- FH-1 Fuel Handling Equipment Operation R7 01-28-93
- FH-2 Transferring Refueling Water from SIRWT to R3 01-28-93~ r Refueling Pools
+FH-3 Refueling Water Transfer from Refueling R5 01-28-93 Pool to SIRWT .
- FH-4 Refueling Pool Purification R2 01-28-93 FO-1 Emergency Diesel Generator Fuel Oil Shipments R2 01-28-93
[*FP-1] Fire Protection System Water System . R5 01-28-93
- FP-2 Dry Chemical Fire Extinguishers R1 01-28-93
- FP-3 Carbon Dioxide (CO 2
) Fire Extinguishers - R1 01-28-93
- FP-4 Fire Detection Systems R4 '01-28-93 :
FP-5 Fire Protection System Water System Testing DELETED ,
t
[ ] "On Going" Commitments Project 1991 Procedures Upgrade FC/INDEX/MC 02/23/93 2:24pm
.i a
FORT'CALHOUN-STATION PAGE 6 0F 14 OPERATING INSTRUCTIONS INDEX PROCEDURE NUMBER TITLE. REVISION /DATE
[*FP-6] Fire Protection System' Inspection and Test R19 01-28-93a
- FP-7 Emergency Fire Water Supply for Blair Fire R1 01-28-93 Department-
- FP-8 Halon 1211 Fire Extinguishers R1 01-28-93
- FP-9 Aqueous Film Forming Foam (AFFF) Fire R1 01-28-93 Extinguishers
- FW-1 Condensate System Normal Operation R3 01-28-93'
- FW-3 Steam Generator Level Control R4 01-28-93 FW-4 Auxiliary Feedwater Pump Operation and (R42 07-27-89)
Testing Auxiliary Feed Operation REISSUED 11-06-89 SUPERSEDED 03-21-90
- FW-5 Steam Generator Blowdown Normal Operation R2 01-28-93
- FW-6 Steam Generator Draining RIO 01-28-93'
- FW-7 Steam Generator Wet Lay-Up R6 01-28-93
- FW-8 Condenser Fill for Blacklighting R3 01-28-93 ,
- FW-9 Steam Generator Recirculation R5 01-28-93
- FW-10 Condensate System Demineralization R6 01-28-93 HE-1 Normal Operating Hoisting Equipment - (R9 07-24-90)
Polar Crane SUPERSEDED 07-25-91 ;
'5 HE-2 (R9 11-28-90)
.Auxiliary Normal Building Operation Hoisting (Equipment HE-2Previously 01-HE-5) SUPER Crane HE-3 Hoisting Ecuipment HE-3 Drumming Area Crane (R4 09-30-74)
(Normal Operation) DELETED 06-18-87.
HE-3 REINSTATED i Normal Operation Hoisting Equipment HE-3 (R0 09-02-87) .
Turbine Room Crane SUPERSEDED 07-25-91
[ ] "On Going" Commitments :
Project 1991 Procedures Upgrade FC/INDEX/MC 02/23/93 2:24pm y
y
. FORT CALHOUN STATION PAGE 7 0F 14 )
OPERATING INSTRUCTIONS INDEX j I
PROCEDURE NUMBER TITLE REVISION /DATE .
l HE-4 Hoisting Equipment HE-4 Miscellaneous Cranes. (R2 05-25-72) and Hoists (Normal Operation) DELETED 06-18-87 l i
HE-5 Hoisting Equipment HE-5 Turbine Room Crane (R3 10-21-82)
(Normal Operation) (Previously 01-HE-2) DELETED 06-18-87 l HE-8 Normal Operation Hoisting Equipment Drumming (RO 09-02-87)- ..
Area Crane DELETED 04-05-91 j I
HE-MISC-1 Normal Operation Hoisting Equipment (R0 08-27-87)
Miscellaneous Cranes & Hoists DELETED 04-05-91 ;
- HG-1 Primary Plant Hydrogen Normal Operation R2 01-28 l
'MS-1 Main Steam System Normal Operation R5 01-28-93
- MS-2 Main Steam System Cold Startup R6 01-28-93
- MS-3 Main Steam System Shutdown from Hot Shutdown R1 01-28-93 i to Cold Shutdown ;
- MS-4 Steam Dump and Bypass System Normal Operation R2 01-28-93 ;
- MS-5 Calorimeter System' Normal Operation R1 01-28 '
- ST-1 Turbine Generator Normal Operation R3 01-28-93
- ST-2 Turbine Generator Startup R4 01 28-93
- ST-3 Turbine Generator Shutdown R4 01-28-93 ;
- ST-4 Turbine Lube Oil System R1 01-28-93 ,
- ST-5 Steam Seal System Normal Operation R1 01-28-93
- ST-6 Operation of the Generator Gas System R4 01-28-93
- ST-7 Stator Cooling Water Normal Operation R2 01-28-93
- ST-8 Isolated Phase Bus Duct Cooling Normal R1 01-28-93 Operation
- ST-9 Generator Excitation System Generator R4 01-28-93 ,
Synchronization Procedure and Operating Guidelines .
- ST-10 Turbine Generator Tests R7 01-28-93
[ ] "On Going" Commitments !
Project 1991 Procedures Upgrade FC/INDEX/MC 02/23/93 2:24pm i
t
FORT CALHOUN STATION PAGE 8 0F 14-OPERATING INSTRUCTIONS INDEX ,
PROCEDURE NUMBER TITLE REVISION /DATE ST-11 Not Used ---
- ST-12 Turbine Hydraulic Power Unit Operation R2 01-28-93 ST-13 Partial Condenser Operation R1 01-28-93 ND-1 Normal Operat-ion - Steam Generator Nozzle Dams'(RI- 10-31-89)
SUPERSEDED 06-28-91 i
- NG-1 Nitrogen System Normal Operation R6 01-28-93 ,
- NI-1 Nuclear Instrumentation System Normal R5 01-28-93 Operation j
- NZ-1 Steam Generator Nozzle Dams Normal Operation R1 01-28-93 ,
PAP-1 POST ACCIDENT PROCEDURES Post Accident (R6 09-04-84)
Sampling of Primary Coolant SUPERSEDED 08-07-91 :
PAP-2 POST ACCIDENT PROCEDURES Post Accident (R3 09-05-84) ;
Determination of Isotopic Specific Activities SUPERSEDED 08-05-91 .
in Containment Atmosphere and Primary Coolant Gas 1 PAP-3 POST ACCIDENT PROCEDURES Post Accident (R1 01-20-83) 3 Determination of. Hydrogen in Primary Coolant DELETED 10-02-84 ;
Sample and. Containment Atoms.
PAP 4 POST ACCIDENT SAMPLING Backup Grab Sample (R1 06-13-85) 'i Chloride Analysis SUPEP,SEDED 08-07 ;
PAP-5 Backup Grab Sample Baron Analysis -(R3 02-07-90) !
SUPERSEDED 08-07-91 ,
l PAP-7 POST ACCIDENT PROCEDURES Procedure for R8 01-28-93 Monitoring the Gaseous Effluent Releases Via the Auxiliary Building Ventilation Duct Pathway PAP-8 POST ACCIDENT PROCEDURES Procedure for R7 01-28-93 ,
Monitoring the Gaseous Effluent Releases Via the Main Steam Safety Relief Valves, Atmospheric Dump Valve Pathway, and Auxiliary Feed Pump Turbine Exhaust 1 l
[ ] "On Going" Commitments
- Project 1991 Procedures Upgrade l FC/INDEX/MC. 02/23/93 2:24pm
FORT CALHOUN STATION PAGE'9 0F 14
, 4 OPERATING IHSTRUCTIONS INDEX f PROCEDURE NUMBER TITLE REVISION /DATE PAP-9 AIRBORNE RADIOI0 DINE MONITORING SYSTEM R6 01-28-93 i Procedure for Post Accident Monitoring of Radiciodine in Occupied Areas
~
PAP-10 Radioactive Sample Transport to Cooper Nuclear (R1 10-22-87)-
Station DELETED 05-06-91 :
- PAP-11 Control Room Post-Accident Iodine Radiation R1 01-28-93 Monitor Operation PAP-12 Toxic Gas Accidents R8 01-28-93 PC-1 Plant Computer (Normal Operation) (R13 06-22-87) '
DELETED 02-09-89 PC-2 Xe and Samarium Worth Determination (R206-01-76)
DELETED 02-09-89 Incore Detector Analysis Program (R1 04-18-86) .
PC-3 CANCELLED 09-07-90 ,
PS-1 Security Power Distribution System (UPS)' R1 01-28-93_ ,
- PW-1 Potable and Service Water System Normal R4 01-28-93 i Operation
?
- PW-2 Auxiliary Building Electric Water Heater R1 01-28-93 Operation
- QSP-1 Qualified Safety Parameter Display System R2 01-28-93 Operation QSPDS-1 Qualified Safety Parameter Display System (R0 04-30-86) ;
SUPERSEDED 01-18-91 l RC-1 Reactor Coolant System (Normal Operation) (R1901-22-89)
CANCELLED 03-20-90
[*RC-2A] Reactor Coolant System (RCS) Fill for R8 01-28-93 Startup and CEA Coupling and uncoupling RC-2B Reactor Coolant Vent and Leak Test (R5512-16-88)
Instruction DELETED 03-20-89
[*RC-2C] Reactor Coolant System Cold Hydrostatic Test R12 01-28 !
[ ] "On' Going" Commitments Project 1991 Procedures Upgrade ,
FC/INDEX/MC 02/23/93 2:24pm-
l FORT-CALHOUN' STATION PAGE 10 0F l4 l 1
OPERATING INSTRUCTIONS INDEX PROCEDURE NUMBER TITLE REVISION /DATE-
[*RC-2D] Reactor Coolant System (RCS) Fill During R8 01-28-93 Cold / Refueling Shutdown ,
[*RC-3] Reactor Coolant System (RCS) Startup R17 02-05-93
[*RC-4] Reactor Coolant System (RCS) Normal Shutdown R14 01-28-93 -
[*RC-5] Reactor Coolant System Draining For Plant R7 01-28-93 Shutdown
[*RC-5A] Reactor _ Coolant System Draining After Steam R4 01-28-93 Generator Tube Dump
- RC-6 Pressurizer Quench Tank Normal Operation R3 01-28-93. t
- RC-7 Reactor Coolant System Pressure Control R4 01-28-93 ,
Normal Operation ,
- RC-8 Reactor Coolant System Level Control Normal R1 01-28 Operation
- RC-9 Reactor Coolant Pump (RCP) Normal Operation. R11 01-28-93
- RC-10 Reactor Coolant Gas Vent System (RCGVS) R1 01-28-93
[*RC-11] Reactor Coolant System (RCS) Natural R4 02-05-93 Circulation Cooldown RC-12 Post-Accident. Venting of Non-Condensable Gases R1 01-28-93 From the Reactor Coolant System (RCS)
RDW-1 Normal Operation of Radwaste Processing R3 01-28-93 SECTION A-1 Building HVAC Systems
[*RM-1] Radiation Monitoring Normal and Accident R8 01-28-93 Operation
- RPS-1 Reactor Protection System - Normal Operation R3 01-28-93 -
I
- RPS-2 Reactor Protective System-TM/LP COLD CAL R2 01-28-93 Calibration
- RR-1 Reactor Regulating System Normal Operation R4 01-28-93 RR-2 Dropped CEA Recovery (R6 11-26-86)
CANCELLED 01-30-90
['] "On Going" Commitments Project 1991 Procedures Upgrade FC/INDEX/MC 02/23/93 2:24pm i
-_ FORT CALHOUN STATION P'GE 11 0F 14 !
OPERATING INSTRUCTIONS INDEX PROCEDURE NUMBER TITLE REVISION /DATE
- RR-3 CEA Exercising During Cold Shutdown R1 01-28-93
[*RW-1] Raw Water System Normal Operation R16 01-28-93
- RW-2 Raw Water System Outage for Maintenance R2 01-28-93 -:
[*SC-1] Shutdown Cooling Initiation R9 01-28-93
- SC-2 Termination of Shutdown Cooling R2 01-28-93
- SC-3 Alternate Shutdown Cooling Utilizing R6 01-28-93 >
Containment Spray Pumps *
- SC-4 Termination of Alternate Shutdown Cooling R2 01-28-93 '
- SC-5 Shutdown Cooling Purification R8 01-28-93
- SC-6 Shutdown Cooling System Abnormal Operation (R2 12-03-90a)
DELETED 11-24-92 :
- SD-1 Sanitary' System Operation R1 01-28-93
- SD-2 Warehouse Decontamination Shower Retention R1 01-28-93 Tank Operation SF-1 Spent Fuel Pool Cooling Normal Operation (R17 08-15-90)
SUPERSEDED 06-19-91 SF-2 Spent Fuel Pool Cooling Makeup (RIO 08-08-90)
SUPERSEDED 11-19-90:
SF-3A Spent Fuel Pool Cooling Spent Resin (R1812-20-89) >
Sluicing SUPERSEDED 06-19-91 .,
SF-3B Spent Fuel Pool Demineralizer - Resin Addition (R8 07-25-90)
SUPERSEDED 03-11-91 SF-4A Spent Fuel Pool Cooling Emergency Cross Tie (R0 07-21-86) .
With Shutdown Cooling Already in Service SUPERSEDED 06-12-91 SF-4B Spent Fuel Pool Cooling Emergency Cross Tie (R1 04-27-89)
(Shutdown Cooling Not in Service) SUPERSEDED 06-19 :
1 i
l j
[ ] "On Going" Commitments i I
Project 1991 Procedures Upgrade j FC/INDEX/MC 02/23/93 2:24pm
FORT CALHOUN STATION PAGE 12 0F 14 ,
OPERATING INSTRUCTIONS INDEX i PROCEDURE NUMBER TITLE REVISION /0 ATE SF-5 Alternate Spent Fuel Pool Cooling (R2 12-17-90a)
SUPERSEDED 03-06-92
- SFP-1 Spent Fuel Pool Cooling Normal Operation R4 01-28-93
- SFP-2 Spent Fuel Pool Cooling Makeup R1 01-28-93
- SFP-3A Spent Fuel Pool Cooling Spent Resin Sluicing R2 01-28-93
- SFP-3B Spent Fuel Pool Cooling Demineralizer Resin R2 01-28-93 Addition ,
- SFP-4A Spent Fuel Pool Cooling Emergency Cross Tie R1 01-28 -
With Shutdown Cooling Already in Service
- SFP-4B Spent Fuel Pool Cooling Emergency Cross Tie R1 01-28-93 with Shutdown Cooling Not in Service SFP-5 Alternate Spent Fuel Pool Cooling (R0 03-06-92a)
DELETED 09-08-92 SFP-6 Spent Fuel Pool Heat-Up Rate R3 01-28-93
[*SI-1] Safety Injection - Normal Operation R19 01-28-93 -
- SL-1 Primary Sampling System Alignment R1 01-28-93 ,
- SL-2 Post Accident Sampling System Alignment R2 02-19-93 SL-3 Safety Injection and Containment Spray DELETED 12-20-76 Recirculation SL-SP General Sampling Procedure - Normal Operation (R2 05-28-75)
DELETED 06-17-91
- SM-1 Seismic Monitoring R1 01-28-93
- SPDS-1 Safety Parameter Display System Operation R2 01-28-93a
- SS-1 Secondary Sampling System Start-up Valve R1 01-28-93 :
Alignment
[ ] "On Going" Commitments >
Project 1991 Procedures Upgrade FC/INDEX/MC 02/23/93 2:24pm
FORT CALHOUN STATION PAGE 13 0F 14 OPERATING INSTRUCTIONS INDEX PROCEDURE NUMBER TITLE REVISION /DATE j
- SS-2 Steam Generator Blowdown Sampling System R2 02-26-93 Operation. j SS/DG-1 Site Security System Diesel Generator (R1 09-26-86)-
' DELETED 01-18-91
- TGM-1 Toxic Gas Monitoring System R1. 01-28-93 TSC/DG-1 TSC/ Security Diesel Generator - Normal R2 01-28-93 Operation
- TSC/UPS-1 Technical Support Center (TSC) Uninterruptible R1 01-28-93 Power Supply (UPS) Operation
[*VA-1] Containment Heating, Cooling and Ventilation R6 02-11-93 Systems Normal Operation >
- VA-2 Auxiliary Building Ventilation System Normal R2 01-28-93 ,
Operation
- VA-3 Control Room Ventilation System Normal R1 01-28-93 ,
Operation *
- VA-4 Heating, Cooling, and Ventilation Turbine R1 01-28-93 Room and Intake Structure Normal Operation
- VA-S Heating, Cooling, and Ventilation R2 01-28 i Service Building Normal Operation i
- VA-6 Containment Hydrogen Analyzer Operation R2 l01-28-93 VA-6-2 Containment Hydrogen Analyzer Normal (R1 03-30-82)
Operation DELETED 07-22-82 .
- VA-7 Technical Support Center Heating, Cooling and R2 01-28-93 Ventilating Systems Operation -
VA-8 Heating, Cooling and Ventilation-Normal R2 01-28-93 Operation, Warehouse VA-9 Heating Cooling and Ventilation -- Normal R1 01-28-93 Operation Maintenance Shop Facility l
'[ ] "On Going" Commitments Project 1991 Procedures Upgrade FC/INDEX/MC 02/26/93 8:10am l t
i
i FORT CALHDUN STATION PAGE 14 0F 14 .
OPERATING INSTRUCTIONS INDEX
' PROCEDURE.
NUMBER TITLE REVISION /DATE
- VD-1 Feedwater Heater Vents and Drains Normal R4 01-28-93 ,
Operation
- VP-1 Vacuum Priming System Normal Operation R2 01-28 [WDG-1] Waste Gas Disposal System Normal Operation R4 01-28-93 '
- WDG-2 Waste Gas Disposal System Release R3 01-28-93a
[WDG-3] Waste Gas Sampling System (AI-110) Normal R4 01-28-93 Operation ,
- WDL-1 Collection and Transfer of Liquid Waste R8 .02-19-93
- WDL-2 Waste Holdup Tank Desludging R1 01-28-93
- WDL-3 Liquid Waste Disposal Release R3 01-28-93
- WDL-4 Liquid Waste Disposal N2 Purging R1 01-28-93 WDS-1 Solids Waste Disposal System Concentrate l(R13 04-11-88)
Collection DELETED 06-10-91 .
WDS-2 Waste Solids Baler Operation (R12 04-16-84)
DELETED 01-21-87 WDS-3 Solids Waste Disposal System Cement (R0 09-08-81)
Loading DELETED 02-05-85 j WDS-4 Automatic Mode - Solidification Processing (R2 09-11-84) ,
of Concentrates / Resin DELETED 02-05-85 WDS-5 Solidification Processing of Waste (R5 04-04-88) :
Concentrates DELETED 07-19-91 ;
l.
I
[ ] "On Going" Commitments .
Project 1991 Procedures Upgrade FC/INDEX/MC 02/23/93 2:24pm l
FORT CALHOUN STATION PAGE 1 OF 14 I STANDING ORDER INDEX ,
PROCEDURE NUMBER TITLE REVISION /DATE G-1 Standing Orders R3 02-25-93 G-2 Special Orders R2 _07-04-90a Special Procedures R22 11-23-92
[G-3]
G-5 Fort Calhoun Station Plant Review Committee R94 02-04-93 Housekeeping R45 12-17-92
[G-6]
Operating Manual R22 01-13-93
[G-7]
G-8 Radiological Emergency Response Plan (R5 07-25-88) . l DELETED 04-12-90 l
G-9 Authority of Licensed Personnel (R4 01-09-89)
SUPERSEDED 02-26-90 G-10 Technical Specifications R6- 12-01-92 >
G-12 Special Process Control (R20 02-25 87)
DELETED 02-22-88 J-12A Welding and Weld Control (R9 11-03-87)
DELETED 02-22-88 -
G-13 Personnel Conduct (R1 03-24-88)
DELETED 04-24-90 G-14 Accident Reporting Procedures (R5 12-23-88)
DELETED 05-15-89 G-15 Backshift/ Weekend / Holiday Visits and Duty R12 12-03-92 Assignments G-16 Bomb Threat Action Guide R3 06-05-90 G-17 Maintenance Work Order (Pages 1 thru 34) (R57 09-27-89)
DELETED 02-16-90 G-17A Electrical Equipment in a Harsh Environment (R3 07-28-88)
DELETED 01-13-89 G-18 Nonconformance Control R19 02-18-92 G-19 Test Control (R7 07-07-90)
DELETED 08-22-90 ;
[ ] "On Going" Commitments FC/INDEX/MC 02/24/93 1:36pm;
FORT CALHOUN STATION PAGE 2 OF 14 STANDING ORDER INDEX PROCEDURE NUMBER TITLE REVISION /DATE ;
G-19A Qualification and Certification of Test (R1 .04-13-90) . ';
Personnel DELETED 08-22-90 G-20 Departmental Budgets (R1 01-14-80)
DELETED 11-17-81 ..!
Modification Control R48 12-22-92
[G-21] ,
G-22 Transfer, Storage and Handling of Critical (R41 07-14-90)- ;
Quality Elements, Fire Protection Material, DELETED 01-11-91 Radwaste Packaging, and Limited COE Material REINSTATED Following Withdrawal of Materials from the R43 06-18-92 Warehouse Surveillance Test Program R38 01-14-93
[G-23]
G-24 Receipt Control of CQE Material (R18'12-10-86)-
DELETED 10-01-87 G-25 Stores Control (R17 04-21-87)
DELETED'10-01-87 G-26] Maintenance Personnel Certification Program R29 01-13-92 G-26A Quality Control Program -(R27 07-27-88)
DELETED 07-28-88 G-27 Training (R7 07-18-88) ,
DELETED 11-09-90 '!
R25 12-07-92
[G-28] Station Fire Plan G-29 Flood Plan (R3 02-27-90)
DELETED 10-07-92 Setpoint/ Procedure Changes and Generation R50 02-16-93
[G-30]
G-31 Posting of Notice to Workers (R3 04-17-90)
DELETED 07-17-90 G-32 Design Change Request Initiating Instructions (R1 09-11-75)
DELETED 01-20-78 G-33 Facility License Change Initiating (R6 11-30-88)
Instructions DELETED 02-16-93 ;
[ ] "On Going" Commitments FC/INDEX/MC 02/16/93 10:55am .
s FORT CALHOUN STATION PAGE 3'OF 14 STANDING ORDER INDEX PROCEDURE NUMBER TITLE REVISION /DATE -i G-34 Engineering Evaluative/ Assistance Request (R0 01-22-74) <
DELETED 07-06-78 G-35 Recorder Annotation (Pages 1 thru 2) R1 07-05-84
[G-36] Biennial Reviews R25 10-07-92 .
G-37 Petty Cash (R2 01-07-88)
DELETED 05-09-88 'i G-38 Miscellaneous Inspection, Report and Test (R2 10-07-77)
Requirement DELETEDL11-19 G-39 Security Instructions (R24 10-28-89)
DELETED 12-21-89 !
10-19-76)
G-40 Quality Control Personnel Qualification (R1 and Certification DELETED 03-08-79 e G-41 Fort Calhoun Station First Aid R14 12-23-92 G-42 Reporting of Defects and Non-Compliance (R9 09-02-88) to the Nuclear Regulatory Commission DELETED 06-24-92
[G-43] Shift Technical Advisor (STA) (R9 10-27-89)
SUPERSEDED 02-26 G-44' Shock Suppressor List R12 06-09-92 G-45 Confined Space Entry R7 11-04-91 G-46 Evaluation of Procedures, Procedure Changes, R7 07-25-88 Tests and Experiments for Safety Evaluations and Status as an Unreviewed Safety Question (Page 1 Only)
G-47 Control Room Drawings R6 11-26-91 G-48 Station Equipment Labeling R8 02-04-93 G-49 Protection of Safeguards Information (R7 07-25-88)
DELETED 12-21-89 G-50 ALARA Radiation Exposure Program (R10 10-18-89) l SUPERSEDED 10-18-89 G-51 Forms Management and Control R6 09-27-91a
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~
' FORT CALHOUN STATION STANDING ORDER INDEX ~
~ PROCEDURE NUMBER TITLE REVISION /DATE l
G-52 Plant Staff Working Hours 22 '07-25-88a r
G-53 Personnel Certification - Technical (RS. 09-29-88)-
Specification Section 5.3 DELETED 10-30-90 G-55 Operating Experience Review (R6' 10-01-88)
DELETED 04-04-89
-[G-56] Qualified Life Program R13 09-08-92 G-57 Installation of Temporary Lead Shielding (R6 10-18-89)
DELETED 11-20 [G-58] Control of Fire Protection System Impairments R18 10-28-92 G-61 Rigging Inspection Program at Fort Calhoun R19 02-08 93 Station
[G-62] Control of Vendor Manuals R9 01-08-92 G-63 volume Reduction of Radioactive Waste (R1 10-01-88)
SUPERSEDED 10-26 ~
.[G-64] Medical Examination Program for Worker R19 03-18-92 Qualification G-65 Nuclear Contractor Access Authorization Program (R10 07-21-89)
DELETED 08-28 1 G-66 Control of Key Card Badges (R4 05-12-89).
DELETED 07-13-90 G-69 Fort Calhoun Station Asbestos Abatement R9 02-06-92 j G-70 Chemical Control R9 .09-09-91 G-71 Champs Database Updates (R1 07-28-88') !
DELETED 08-03-90 '
6 j
b Special Process Control R8 11-24-92
[G-72]
G-72A Welding and Weld Control (R8 02-22-89)
DELETED 10-30-89 .
G-72B- Qualifications of Welders (R1 07-25-88) l DELETED' 10-30-89 !
[ ] -"On Going" Commitments FC/INDEX/MC 02/05/93.12:26pm
I i
pAGE'5'OF.14 FORT CALHOUN STATION STANDING ORDER INDEX PROCEDURE NUMBER TITLE REVISION /DATE Fort Calhoun Station Writer's Guide R13 02-17-93
[G-73]
'G-74 Fort Calhoun Station EOP/AOP Generation R5 06-23-92a Program G-75 Annunciator Response Procedure (ARP) Writer's R1 05-12-92 Guide R2 04-24-92'
[G-76] Use of Portal Monitors G-78 Observation Program R7 12-02-92 G-79 Signature / Initial Form R3 04-05-91 G-61 Fort Calhoun Warehouse Operations R10 11-06-92 i
Engineering Assistance Requests R1 11-19-90
[G-82]
G-85 Central Processing (Initial, Requalification, R4 01-11-93 and Termination)
G-86 Fort Calhoun Heat Stress Program (R0 01-05-90)
DELETED 07-21-90 i
G-87 Non-Routine Activities Requiring Formalized R1 05-22-92 Plans G-92 Conduct of Infrequently Performed Procedures R0 02-08-92' t
G-93 NRC Licensed Operator Physicals R0 02-27-92 l
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[ ] "On Going" Commitments FC/INDEX/MC 02/17/93 8:42am i
FORT CALHOUN STATION PAGE 6 OF 14 STANDING ORDER INDEX PROCEDURE NUMBER TITLE- REVISION /DATE
[0-1] Conduct of Operations R10 01-28-93b O-2 Requirements for Criticality (Pages 1 thru 2) R2 10-23-75 i
0-3 Requirements for Raising Power 10"% (R2 10-23-75)-
DELETED 01-11-79 O-4 Requirements for Changing Power (R2 08-24-87)
SUPERSEDED- 02-26-90 0-5 Shift Supervisors Duties (R5 11-21-89)
SUPERSEDED 02-26-90 ,
0-6 Licensed Senior Operator Duties (R4 02-29-88)
SUPERSEDED 02-26-90 0-7 Licensed Operator (Lo) Duties (R3 08-15-89)
SUPERSEDED 02-26-90 /
O-8 Equipment Operator Nuclear Duties (R3 06-06-88)
(Turbine and Auxiliary) SUPERSEDED 02-26-90 3-9 Auxiliary Operator Nuclear (AON) Duties (R3 06-06-88) and Responsibilities SUPERSEDED 02-26-90 0-10 Helpers' Duties and Responsibiliti1s (R2 05-31-88)
SUPERSEDED 02-26 !
O-11 Control Room Access (R8 01-24-89) ,
SUPERSEDED 02-26-90 O-12 Control Room Operations (R2 08-06-86) l SUPERSEDED 02-26-90
.s 0-13 Operations Memorandums R10 02-20 .l O-14 Work Schedules - Operations (Page 1 Only) R3 08-14-87' O-15 Night Notes (R3 08-27-87) ,
DELETED 02-08-93 ,
I 0-16' ' Operating Procedures R8 05-06-91 i
R0 06-04-92 i 0-16A Annunciator Response Procedures ,
0-17 Operating Instructions R7 12-28-89
[ ] "On Going" Commitments. ;
FC/INDEX/MC 02/17/93 8:42am- .
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. FORT CALHOUN STATION PAGE 7 OF 14 STANDING ORDER INDEX PROCEDURE NUMBER TITLE REVISION /DATE i'
0-18 Emergency. Operating Procedures and Technical. R6 12-15-90 Basis Documents 0-18A Abnormal Operating Procedures R2 06-17-92 !
(Pages 1 thru 2) .l O-19 Systems Descriptions (Pages 1 thru 2) R6 01-05-89 Equipment Tagging Procedure R31'02-19-93
[0-20] >
O-22 Containment Access and Egress R15 02-11-93 O-23 Systems and Equipment Usage Data R6 05-23-91 i
O-24 Log. Entries (R7 12-14-89)~
' SUPERSEDED 02-26-90. I Temporary Modification Control R41 01-13-93
[0-25]
0-25A Independent Verification Sheet Control RO 07-12-89 R23 11-05-92 l
[0-26] Plant Keys O-27 Technical Data Book (Page 1 Only) RS 05-30-87 r
O-28 Requirements for Administratively Bypassing RS 09-23-88 Reactor Protective System (RPS) Trip Units (Page 1 Only) .
0-29 Conduct of Operations (R14 01-09-90)- '
SUPERSEDED 02-26-90 Testing of Safety Related Equipment R5 09-14-89 O-30 ,
(Pages 1 thru 3) 0-31 DELETED ,
Plant Computers R9 06-30-92 O-32 Control of Software R7 11-02-92 0-32A Definition of Channel of Heat Tracing to (R1 10-28-75) 0-33 Satisfy Tech. Spec. 2.2.(2)e. DELETED 06-09-90 j O-34 Cable Spreading Room (R1 03-23-78)
DELETED 08-28-80 'i i
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I FORT CALHOUN STATION PAGE 8 OF 14 l STANDING ORDER INDEX PROCEDURE
. NUMBER TITLE REVISION /DATE O-35 Reactor Cavity Tool Accountability (R1 ~11-20-76)
DELETED 04-27-82
[0-36] Annual Review of Shift Supervisor R4 06-19-91 Responsibilities
[O-37] Independent Verification of Critical Systems R11 02-05-93 Component Positioning ,
'[0-38] Fire Watch Duties and Turnover Procedures R9 06-21-91 I
0-39 Procedures for Feedback of Operating (R5 07-25-88)
Experience to Plant Staff DELETED- 04-04-89
[0-40] Annunciator Status Change R6 01-17-90
-[0-41] Control of Operator Aids and Emergency R46 12-22-92 Equipment 0-42 Notification to the NRC of Licensed R1 05-30-87 Personnel Disability (Pages 1 thru 2)
- -43 Fuel Reliability Action Plan R3 02-18-93 (U-44] Administrative Controls for the Locking of R24 02-26-93 !
Components O-45 Maximum / Nominal Power Level Definition and (R3 05-01-92)
Guidelines DELETED 10-01-92
[0-46] Post Trip Reviews R3 03-01-93 0-47 Spent Fuel Pool Inventory Control R1 07-12-91a ;
O-48 Requirements for Administratively R0 12-28-92 ,
Bypassing the Diverse Scram System (DSS) !
. During Testing or inoperability e
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[ ] "On Going" Commitments FC/INDEX/MC 02/26/93 11:32am i
FORT.CALHOUN STATION PAGE 9 OF 14' STANDING ORDER INDE -
PROCEDURE-
- NUMBER TITLE REVISION /DATE ,
M-0 Conduct of Maintenance (R0 12-12-88)
DELETED 02-23-89 ,
M-1 Maintenance Procedures (R9 07-25-88)
DELETED 03-06-89 Preventive Maintenance Program R21 09-08-92 s
[M-2]
M-3 Maintenance Equipment History Records (R2 05-13-82)
DELETED 05-21-85 (R0 05-76)
M-4 Maintenance Tool Room Procedure DELETED 03-06-89 M-5 Failure Reports (Instrumentation (R0 10-25-74) ;
and Control and Electrical) DELETED 12-29-77 M-6 Nuclear Plant Reliability Data Systems DELETED 04-11-77 ,
(N.P.R.D.S.) Reports M-7 Calibration of Mechanical Gauging Equipment R31 01-11-93 ,
9 Control of Crane Operations R12 02-13-90 7
1d-9] Fire Prevention During Flame Cutting, R18 03-28-92 Grinding and Welding Operations M-10 Foreign Material Exclusion R11 06-03-92 '
M-11 Floor Drain Plugging in Rooms Containing DELETED 09-22-88 Safety-Related Equipment ,
[M-26] Calibration Procedures (Formerly T-26) R22 03-01-93 -l
[M-28] Issuance, Control and Calibration of R41 05-31-91 Measuring and Test Equipment ERF Maintenance and Availability (Pages 1-4) R3 06-22-89
[M-29]
M-30 System Cleanliness (R0 09-24-88)_ l DELETED 03-06-89 Scaffolding Installation Control R3 07-22-92 ,
~[M-35]
M-36' Outage and Maintenance Planning (R0 12-17-88)
DELETED 03-06-89 ,
t
'M-100] Conduct of Maintenance R18 01-06 ,
I
[ ] "On Going" Commitments FC/INDEX/MC 02/26/93 11:33am
FORT CALHOUN STATIOli PAGE 10 OF 14 STANDING ORDER INDEX PROCEDURE '
NUMBER TITLE REVISION /DATE M-101 Maintenance Work Control R23 01-19-93 M-102 Post-Maintenance Testing R6 12-22-92. ,
M-103 System Cleanliness R1 09-27-91 M-104 Outage Planning and Execution R1 10-05-92 ~;
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[] "On Going" Commitments FC/INDEX/CM 01/18/93 11:34am ;
PAGE 12 OF 14 FORT CALHOUN STATION STANDING ORDER INDEI PROCEDURE REVISION /DATE ITUMBER TITLE Emergency Diesel Generator Fuel Monitoring R10 02-10-93 T-16 Program T-17 Bulk Acid and Bulk Caustic Unloading R3 03-30-89 (1 Page Only)
T-18 Cleaning Agents for Use in the Auxiliary (R2 06-25-85)
Building DELETED 03-17-89 T-25 Quality Control Progran for Evaluating R6 10-02-91 Chemistry Laboratory Performance T-26 Calibration Procedures (See M-26) (R1 08-16-74)
DELETED Calibration Procedures R5 02-15-91 T-27 T-28 Calibration of Test Equipment (R4 07-22-76)
DELETED-l I
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a
-FORT CALHOUN STATION PAGE 13 OF 14 STANDING ORDER INDEX PROCEDURE NUMBER TITLE REVISION /DATE R-3 Reportable Occurrences R10 12-02-92 Station Incident Reports R37 01-06-93
[R-4]
R-8 EPA Hazardous / Radioactive Material Spills R11 11-09-92 and Releases and NPDES Violations ,
R-9 Plant Outage Report (Pages 1 thru 2) R5 02-09-78 R-10 Power Reduction Report (Pages 1 thru 2) R2 02-07-78 R-11 Notification of Significant Events R24 02-04-93 R-12 Reporting of Physical Security Events R5 12-09-88 (Pages 1 thru 2)
R-13 Plant Startup Report R1- 11-15-83a R-14 NPRDS Failure Reporting R4 01-28 l R-15 Reporting Alert Notification System R0 10-29-91b Accidental Activation R-16 FAA Notification of Weather Tower Light -
R0 01-17-92 Problems
'l 4
[ ] "On-Going" Commitments FC/INDEX/MC 02/03/93 9:57am
i FORT CALHOUN. STATION PAGE 14 OF 14 STANDING ORDER INDEX PROCEDURE NUMBER TITLE REVISION /DATE
'C-1 Fort Calhoun Office Files (Pages 1 thru 2) R5 07-06-89 C-2 Fort Calhoun Station Quality Assurance R69 10-15-92 (QA) Records C-3 Fort Calhoun Station Quality Assurance (QA) (R8 08-05-82)
- Records (Chem. and Rad. Protection ONLY) DELETED 01-24-84
.C-4 Distribution of Reports, Procedures, (R2 07-26-88)
Memorandums, etc. DELETED 06-26-90 Fort Calhoun Station Drawing Files R15 11-24-92
[C-5]
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.[ - ] "On Going" Commitments 11/23/92'3:27pm FC/INDEX/CM i
FORT CALHOUN' STATION- PAGE 1 0F 10 ,
TECHNICAL DATA BOOK INDEX
'ROCEDURE NUMBER TITLE REVISION /DATE .
'I. Values obtained from Low Power. Physics Test Results R7 03-18-82 A. Core Maps I.A.1 Core Location Designation and CECOR Mimic Numbers R2 08-27-86 (1 Page Only) ,
I.A.2 Fuel Assembly, CEA, Flow Plug, and Source Locations R12-04-29-92b- $
.i I.A.3 CEDM Locations R6 05-06-91 I.A.4 Cycle 1-Control ~ Rod, Flow Plug, and Source (R5 1 82 )L-Locations by Serial Number DELETED 04-26-83 1.A.5 CEA's by Core Mimic Numbers and Group Numbers (R2 04-04-87)- l DELETED 04-10-91 I.A.6 In-Core Instrumentation Location (1 Page Only) R4' 09-02-88 1.A.7.a In-Core Instrumentation Mimic Numbers and Serial R4 12-14-87 :
Numbers (1 Page Only) i.A.7.B Cecor Octant and Reference Octant Numbers in RS 06-21-91 Full Core .
I.A.7.c Failed Incore Detector Status 'R46 08 ,
I.A.7.d Operable Incore Detectors (R17 04-29-82)
DELETED 10-05-82 1.A.8 Source Location by Serial Number '(R2.12-17-85)
DELETED 12-19 ,
l.A.9 Es-Core Instrumentation Location R2 12-17-92 -
1.A.9.a Core Location and Nuclear Instrumentation R3 17-92 Designations-and Orientations JI.A.10 Flow Plugs by Serial Number (R1 11-17-77)
DELETED 12-11-78 B. Spent Fuel Pool I.B.1- Spent Fuel Rack -R26.05-22 I.B.2 Spent Fuel Storage CEA'S by Serial Number '(R6: 11-08-91) .
DELETED 02-17-93
[ ] "On Going" Commitments ;
FC/INDEX/MCX 02/17/93 9:13am T' '
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-FORT CALHOUN STATION PAGE 2'0F 10- .
i TECHNICAL DATA BOOK INDEX ;
iROCEDURE NUMBER TITLE REVISION /0 ATE j I.B.3 Spent Fuel Storage Sources by Serial Number (R3 12-17-85) ,
DELETED 02-17-93 -
I.B.4 Spent Fuel Storage Flow Plugs by Serial Number (R6 12-14-87) l DELETED 02-17-93 !
i C. New Fuel Storage Area I.C.1 New Fuel Storage Rack R19 04-29-92: .
1.C.2 CEA's by Serial Number (R11 09-28-87) ,
DELETED 12.-03-90 i
D. Miscellaneous I.D.1 AI and CB Panel List R2 09-16-92
- 11. Reactivity Curves R18 04-27-92 l II.A.1.a. 1. Cycle 14 Critical Boron Concentration !
-vs. Burnup II.A.1.b. 2. Cycle 14 Critical Boron Concentration j vs. Burnup l II.A.2.a. 3. Cycle 14 Critical Boron Concentration -
vs. Power 1 i
II.A.2.b. 4. Cycle 14 Boron Concentration vs. Power
]
II.A.2.c. 5. Cycle 14 Critical Baron Concentration vs. Power i 1
II.A.2.d 6. Cycle 14 Critical Boron Concentration i vs. Power j i
II.A.3.a 7. Cycle _14 Minimum Boron Concentration for 4% Shutdown Margin vs. Burnup 532*F II.A.3.b. 8. ' Cycle 14 Boron Concentration for 4%
Shutdown Margin vs. Burnup 515 F I I .. A . 3. c . 9. Cycle _14 Boron Concentration for 4%-
Shutdown Margin vs'. Burnup 500*F II.A.3.d. 10. Cycle 14 Boron Concentration for 4%
Shutdown Margin vs. Burnup 475*F ;
l
[ ] "On Going" Commitments -
FC/INDEX/MCK 02/17/93 9:13am !
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FORT CALHOUN STATION .PAGE 3 0F 10 .
TECHNICAL DATA BOOK INDEX PROCEDURE '
NUMBER TITLE REVISION /DATE II.A.3.e. 11. Cycle.14 Boron . Concentration for 4%
Shutdown Margin vs. Burnup 450*F II.A.3.f 12. Cycle 14 Boron Concentration for 4%
Shutdown Margin vs. Burnup 400*F II.A.3.g 13. Cycle 14 Boron Concentration for.4%
Shutdown Margin vs. Burnup 350*F II.A.3.h. 14. Cycle 14 Boron Concentration for 4%
Shutdown Margin vs. Burnup 210*F II.A.3.i 15. Cycle 14 Boron Concentration for 3%
Shutdown Margin vs. Burnup 210*F II.A.3.j 16. Cycle 14 Boron Concentration for 3%
Shutdown Margin vs. Burnup 68aF ,
II.A.4 17. Cycle 14 Inverse Boron Worth vs. Burnup II.B.I.a 18. Cycle 14 CEA Group Worths at HZP l in %Ap when Inserted Sequentially !
II.B.I.b 19. Cycle 14 Reduction in Shutdown !
Margin or Stuck CEA(s) Worth II.B.2.a 20. Cycle 14 Sequential Rod Worth vs. d i
Rod Position at 0_ MWD /MTV II.B.2.b 21. Cycle 14 Sequential Rod Worth vs.
Rod Position at 7,000 MWD /MTU II.B.2.c 22. Cycle 14 Sequential Rod Worth vs. '
Rod Position at 15,000 MWD /MTU II.B.3.a 23. Cycle 14 Group 4 Integral Rod Worth .
O MWD /MTV II.B.3.b 24. Cycle 14 Group 4 Integral Rod Worth ;
7,000 MWD /MTU II.B.3.c 25. Cycle 14 Group 4 Integral Rod Worth 15,000 MWD /MTV 9
II.C.1 26. Cycle 14 Excess Reactivity vs. Burnup
[ ] "On Going" Commitments-FC/INDEX/CM 09/17/92 1:00pm
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^
f-. l FORT:CALHOUN STATION PAGE 4 0F 10 l
TECHNICAL DATA BOOK INDEX j PROCEDURE NUMBER TITLE REVISION /DATE
\
II.C.2.a 27. Cycle 14' Total. Power Defect vs. Power j 0 to 6,000 MWD /MTU II.C.2.b 28. Cycle 14 Total Power Defect vs. Power 6,000 to 11,000 MWD /MTU
]
II.C.2.c 29. Cycle 14 Total Power Defect vs. Power 11,000 to 15,000 MWD /MTV
]
II.C.3 30. Cycle 14 Moderator Temperature i Coefficient vs. Burnup ,
II.D.1.a 31. Cycle 14 Equilibrium Xenon Reactivity Vs. Percent Power II.D.1.b 32. Cycle 14 Xenon Reactivity Worth vs. Burnup II.D.2 33. Cycle 14 Xenon Worth After Trip III. Operating Characteristics
[III.1) Tave Program R9 09-14-92 .[
[III.I.a] Temperature Correction for Pressurizer Level R3 09-14-92 ,
Indicators LI-101 X/Y !
[III.1.b] Pressurizer Level Correction (Density Effects R3 09-14-92' i Correction = 120*F.)
[III.1.c] Pressurizer Level Correction (Density Effects R3 09-14 !'
Correction = 200*F.)
[III.1.d] Pressurizer Level Correction (Density Effects R3 09-14-92 l Correction - 250*F.) !
[III.I.e] Pressurizer Level Correction (Density Effects R3 09-14-92 Correction = 300*F.)
[III.2) Actual Level in Pressurizer vs. Indicated R3 09-14-92 i Level in Pressurizer t III.3 Steam Generator-Level Actual vs.-Steam R1 12-22-86 !
Generator Level -Indicated (1. Page Only) l III.3.a Steam Generator Level Correction (Ambient R2 09-08-87 h Temperature = 120*F.) (1 Page Only)
-[ ] "On Going" Commitments'
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'i FORT CALHOUN STATION PAGE 5 0F 10 TECHNICAL DATA BOOK INDEX PROCEDURE NUMBER TITLE REVISION /DATE III.3.b Steam Generator Level Correction (Ambient R2 09-08-87 Temperature = 200af.) (1 Page Only)
III.3.c Steam Generator Level :.orrection (Ambient R2 09-08-87 Temperature = 250*F.) (1 Page Only)
III.3.d Steam Generator Level Correction (Ambient .R2 09-08-87 Temperature - 300aF.) (1 Page Only)
III.3.e Steam Generator Level Correction (Ambient R2 09-08-87 Temperature = 350*F.) (1 Page Only)
III.3.f Steam Generator Level Correction (Ambient R2 09-08-87 .
Temperature - 400aF.) (1 Page Only)
- 111.3 9 Steam Generator Level Correction (Ambient R2 09-08-87 Temperature - 450aF.) (1 Page Only) i III.3.h Wide Range to Narrow Range Conversion (1 Page Only) R1 11-30-82 III.3.i Wide Range Steam Gen. Level Correction (Ambient R2 09-08 Temperature = 120*F.) (1 Page Only)
III.3.j Wide Range Steam Gen. Level Correction (Ambient R1 09-08-87 Temperature = 200*F.) (1 Page Only)
III.3.k Wide Range Steam Gen. Level Correction _(Ambient R1- 09-08-87 Temperature = 250aF.) (I Page Only) ,
111.3.1 Wide Range Steam Gen. Level Correction (Ambient R1 09-08-87 Temperature - 300af.) (1 Page Only) 1 III.3.m Wide Range Steam Gen. Level Correction,(Ambient
~
R1 09-08-87 !
Temperature = 350aF.) (1 Page Only)
III.3.n Wide Range Steam Gen. Level Correction (Ambient R1 09-08-87 Temp = 400aF)- (1 Page Only)
III.3.o; Wide Range Steam Gen. Level Correction.(Ambient R1 09-08-87 Temp = 450*F) (1 Page Only) ,
'III.3.p Steam Generator Component Elevations R0 03-24-88 III.4 Steam Generator Pressure vs. Power Level R1 10-05-87 111.5 Pressurizer Level Control Program (1 Page Only) R1 03-06-86 j
[ ] "On Going" Commitmento 09/17/92 1:00pm.
FC/INDEX/CM
FORT CALHOUN STATION PAGE 6 0F-10 TECHNICAL DATA BOOK INDEX PROCEDURE NUMBER TITLE REVISION /DATE III.6 Pressure Control Program R3 09-03-92 III.7.a Reactor Coolant System Pressure-Temperature Limits R13 07-25-88 Heatup (Reactor Not Critical) (1 Page Only)
III.7.b Reactor Coolant System Pressure-Temperature Limits R13 07-25-88 Cooldown (Reactor Not Critical) (1 Page Only)
F III.7.c Reactor Coolant System Pressure-Temperature (R0 6-21-76)
Limitations for 10 to 40 Years of Full Power DELETED 11-11-77 Operation III.8 Reactor Coolant System Mass vs. Reactor Coolant R1 10-15-86 i System Temperature (1 Page Only)
III.8.b RCS Inventory Based on Pressurizer Level R0 09-10-88 (1 Page Only)
III.8.c Reactor Vessel Volumes (1 Page Only) R0 09-10-88 :
III.8.D Steam Generator and Primary System Piping Volumes R0 09-10-88 (Pages 1 thru 2)
III.8.e Volume of RCS at Centerline of Hot Leg (1 Page Only)R0 09-10-88 III.9 Feedwater Temperature vs. Power Level R3 10-31-89 111.10 Deleted III.11 Deleted :
III.12 First Stage Shell Steam Temperature vs. Percent LoadR1 12-22-86 i (1 Page Only) i T
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[ ] "On Going" Commitments FC/INDEX/CM 09/17/92 1:00pm 1
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f FORT CALHOUN STATION PAGE 7 0F 10~
TECHNICAL DATA BOOK INDEX PROCEDURE NUMBER TITLE REVISION /DATE Recommended Startup and Loading Times for Turbine III.13.a a. Cold Turbine (1 Page Only) R1 12-22-86 III.13.b b. Warm Turbine (1 Page Only) R1 12-22-86 III.13.c c. Hot Turbine (1 Page Only) R1 12-22-86 III.14 Load Changing Recommendations for Turbine R1 12-22-86 (1 Page Only).
III.15 Specific Volume vs. Temperature (1 Page Only) R1 10-15-86 III.15a Specific Volume vs Temperature (35 deg.F. to R0 03-13-87 200 deg.F.) (1 Page Only)
III.16.a Power Ratio Re' corder Setpoints DNBR Monitoring R18 06-04-92 III.16.a.1 Coefficient Settings for Power Ratio Calculator- R18 06-04-92 DNBR Monitoring III.16.a.2 Power Ratio Recorder Limits for Excore Monitoring R6 06-04-92 of DNBR COLR Figure 5 III.16.b Power Ratio Recorder Setpoints KW/FT Excore R19 06-04-92 Monitoring III.16.b.1 Coefficient Settings for Power Ratio Calculator R19 06-04-92 KW/FT Monitoring III.16.b.2 Power Ratio Recorder Limits for Excore Monitoring R7 06-04-92 of KW/FT COLR Figure 4 ;
III.16.c Cycle 14 Axial Power Distribution Limits - 4 Pump R20 06-04-92 Operation III.17.a RCS-Pressure Temperature Limitations During (R1 4-04-77)
Heatup - 2 to 5 years Reactor Not Critical, DELETED 11-11-77 '
NDTT Shifted Tech. Spec. Figure 2-1 III.17.b RCS-Pressure Temperature' Limitations During (R0 6-21-76) l Cooldown - 2 to 5 years Reactor Not Critical, DELETED 11-11-77 NDTT Shifted Tech. Spec. Figure 2-1 j 111.18 Deleted I
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{-] "On Going" Commitments )
'l FC/INDEX/CM 09/17/921:00pm '
i 1
~
FORT CALHOUN STATION PAGE 8 0F 10 TECHNICAL DATA BOOK INDEX I
/ROCEDURE NUMBER TITLE REVISION /DATE 111.19 Conversions of RPS Channel A Voltage to % Flow R1 10-15-86 i for Computer Point F0 114A (1 Page Only) '
111.20 RCS Elevations vs. LI-106, LI-199, LI-197 and R7 09-01-90 LIS-119 III.21.a Thermal Margin / Low Pressure Calc of PVAR R12 06-04-92 ,
at Tc = 543"F ASI=- 0.06 III.21.b Thermal Margin / Low Pressure Calc of PVAR R12 06-04-92 at Tc = 543*F ASI= 0.0 III.21.c Thermal Margin / Low Pressure Calc of PVAR R12 06-04-92 at Tc = 543*F ASla 0.10 III.21.d Thermal Margin / Low Pressure Calc of PVAR R1 06-04-92 100% Power 111.22 Limitation on Power Level Increases and Rod R9 08-11-92 -
Movements at Power s III.23 Axial Xenon Transient Control Decision FlowSheet R1 10-15 (1 Page Only)
III.23.a Transient Power ASI Control Band (1 Page Only) R3 12-22-86 III.23.b Equilibrium Power ASI Control Band (1 Page Only) R2 12-22-86 111.24' Detector Well Temperature vs. Highest Concrete R4 01-05-89' Temperature (1 Page Only)
]
111.25 RCS Press-Temp Limits R6 09-03-92 III.26 Diesel Generator Capability Curve (1 Page Only) R1- 12-22-86 l III.26.A Diesel Generator Loading Curve R5 09-03-92 1 III.27 Decay Heat vs. Time After Shutdown Heatup Rate ~R2 03-04-89 :
Due to Decay Heat (Page 1 thru 2) !
III.28 ReactorVesselLevelMonitoringSystem(RVLMS) RI 10-01-91 ,
III.29 Maximum River Water Temperature vs. Raw Water R0 '02-10 f Flow Rate.
III.30 Circulating Water Pump Cell and River Levels from R1 10-23-92 Pressure Gauge LI-1900 l
[-] "On Going" Commitments j FC/INDEX/MC 11/13/92 12:55pm-q
FORT CALHOUN STATION lPAGE 9 0F 10.
TECHNICAL DATA BOOK INDEX
'ROCEDURE
' NUMBER TITLE REVISION /DATE -
l III.31 AC-10A Pump Curve R0 08-14-92 ,
.111.32 AC-108 Pump Curve RO 08-14-92a
~III.33 AC-10C Pump Curve R1 12-28 III.34 AC-10D Pump Curve -R0. 08-14-92 IV. Chemistry ,
IV.1 Boration - Dilution Tables (a-u) (R110-15-86)
DELETED. 06-15-90' .
IV.2.a Total G:'icns "c Time Boration or Dilution R1 12-22-86 (with One Charging Pump) (1 Page Only)
-IV.2.b Total Gallons vs. Time Boration or Dilution R1 .12-22-86 l (1 Page Only)
IV.3 Deleted IV.4 CB in Makeup Stream vs Required Flow of 6.25% (R1 12-22-86)
Weight Boric Acid DELETED 06-15-90 IV.5 Baronometer Correction for Sample Temperature R1- 12-22-86 ;
(1 Page Only)
IV.6 Boric' Acid Solubility vs. Temperature Process Monitor (R2 ~ 12-22-86)
Setpoints DELETED 06-15-90 ..
IV.7 Process Monitor Setpoints R129 08-17-92 IV.8 Area Monitoring Setpoints R25 01-20-93 ;
V. Work Sheets and Calculation Procedures '{
V.1 Estimated Critical Position Work Sheet (R6 .04-04-87) >
DELETED 08-31-89'
]
-V.1.b Estimated Critical Conditions WorkSheet R13 11-16-92a' ,
V.2 Deleted V.3 Manual Group Mode Guide' Table (Pages 1 thru 3) R1. 04-04-87 .i
' V . '4 Boration-Dilution Tables and Work Sheet (R1 04-04-87)
DELETED 06-15-90 4
.h
[.] "On Going" Commitments .l FC/INDEX/MCK- 02/23/93 8:45am ..,
me. - yra
FORT CALHOUN STATION PAGE 10 0F 10 TECHNICAL DATA BOOK INDEX
'ROCEDURE NUMBER TITLE REVISION /DATE V.5 Deleted V.6 Indication of Reactor Power Based on AT R4 07-29-91 V.7 Reactor Power Based on Steam Flow (R2 06-06-89)
DELETED 10-22-91 V.8 Leak Rate Data and Calculation for Steady State (R1 04-04-87)
Reactor Coolant System Conditions DELETED 05-06-91 V.9 Shutdown Margin Worksheet R22 11-16-92 Part I - Instantaneous Shutdown Margin for a ,
Part II - Hot Shutdown Condition (No Rod Movement Planned)
Part III - Cold Shutdown Condition ;
i Part IV - Shutdown Margin After the Reactor is Shutdown (With Possible Rod Movement or Inoperable CEA's) :
V.10 Cold Shutdown Procedures (Pages 1 thru 3) R4 05-09-89 ,
V.11- Instrument Bus Loads and Failure Modes R21 04-25-92a '
V.12 Misc. Formula Sheet R3 10-12-92 VI Core Operating Limit Report R4 12-17-92 I
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[-] "On Going" Commitments FC/INDEX/MCK 02/18/93.12:30pm. i 4
OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION UNIT NO. 1 OPERATING LICENSE NO. DPR-40 APPENDIX A PAGE STATUS
SUMMARY
SUBJECT, PAGE ORIGINAL OR MATTER NUMBER CHANGE NUMBER QA,If Table of Contents i Amend. 146 06/16/92 ,
Table of Contents ii Amend. 136 12/12/90 -
Table of Contents iii Amend. 141 03/06/92 I Table of Contents iv Amend. 136 12/12/90 Table of contents v Amend. 145 04/23/92 ,
Table of Contents vi Amend. 142 03/19/92
~
Table of Contents vii Amend. 145 04/23/92 Table of Contents viii Amend. 141 03/06/92 ,
Definition 1 Amend. 50 08/15/80 Definition 2 Amend. 141 03/06/92 t Definition 3 Amend. 32 11/21/77 Definition 4 Amend. 86 04/03/85 Definition 5 Amend. 109 05/04/87 Definition 6 Amend. 109 05/04/87 Definition 7 Amend. 141 03/06/92 Definition 8 Amend. 141 03/06/92 Technical Specification 1-1 Amend. 70 03/15/83-Technical Specification 1-2 Amend. 141 03/06/92 .j Deleted 1-3 Amend. 5 04/30/75 Figure 1-1 Amend. 92 11/29/85 Figure 1-2 Amend. 70 03/15/83 Deleted - Figure 1-3 Amend. 141 03/06/92
]
Deleted - Figure 1-4 Amend. 47 04/01/80 !
Technical Specification 1-4 0 08/09/73 Technical Specification 5 Amend. 117 12/14/88 Technical Specification 1-6 Amend. 32 11/21/77- l Page 1 of 12 11/05/92 l
SUBJECT PAGE ORIGINAL OR MATTER NUMBER CHANGE NUMBER QATE Technical Specification 1-7 Amend. 92 11/29/85 Technical Specification 1-8 Amend. 141 03/06/92 Technical Specification 1-8a Change 11 04/30/75 Technical Specification 1-9 Amend. 109 05/04/87 Technical Specification 1-10 Amend. 141 03/06/92 Technical Specification 1-10a Amend. 32 11/21/77 Technical Specification 2-0 Amend. 52 10/14/80 Technical Specification 2-Oa Amend. 52 10/14/80 Technical Specification 2-Ob Amend. 52 10/14/80 Technical Specification 2-1 Amend. 56 02/10/81 Technical Specification 2-2 Amend. 136 12/12/90 Technical Specification 2-2a Amend. 136 12/12/90 ,
Technical Specification 2-2b Amend. 92 11/29/85 Technical Specification 2-2c Amend. 136 12/12/90 -
Technical Specification 2-2d Amend. 136 12/12/90 Technical Specification 2-2e Amend. 136 12/12/90 Technical Specification 2-3 Amend. 74 06/20/83 j Technical Specification 2-4 Amend. 114 06/28/88 t Technical Specification 5 Amend. 114- 06/28/88 ;
Technical Specification 2-6 Amend. 121 04/26/89 Figure 2-1A Amend. 114 06/28/88 Figure 2-18 Amend. 114 06/28/88 Deleted 2-2A Amend. 74 06/20/83 Deleted 2-2B Amend. 74 06/20/83 Figure 2-3 Amend. 121 04/26/89 -
Technical Specification 2-7 Amend. 100 09/08/86 Page 2 of 12 11/05/92 ,
SUBJECT PAGE ORIGINAL OR MATTER NUMBER CHANGE NUMBER DATI Technical Specification 2-7a Amend. 100 '09/08/86 Technical Specification 2-8 Amend. 102 01/20/87 Technical Specification 2-9 Amend. 119 02/14/89 Deleted 2-10 Amend. 67 02/23/83 Technical Specification 2-11 Amend. 32 11/21/77 Technical Specification 2-12 Amend. 32 11/21/77 Technical Specification 2-12a Amend. 32 11/21/77 Technical Specification 2-13 0 08/09/73 Technical Specification 2-14 0 08/09/73 Technical Specification 2-15 Amend. 146 06/16/92-Technical Specification 2-15a Amend. 146 06/16/92 Technical Specification 2-16 Amend. 146 06/16/92 Technical Specification 2-16a Amend. 76 01/26/84 Technical Specification 2-16b Amend. 80 07/09/84 Technical Specification 2-17 Amend. 131 05/18/90 Technical Specification 2-18 Amend. 131 05/18/90 ,
Technical Specification 2-19 Amend. 131 05/18/90 Figure 2-11 Amend. 131 05/18/90 Figure 2-12 Amend. 131 05/18/90 Technical Specification 2-20 Amend. 141 03/06/96 Technical Specification 2-20a Amend. 17 09/07/76 Technical Specification 2-21 Amend. 49 07/25/80 Technical Specification 2-22 Amend. 141 03/06/92 Technical Specification 2-23 Amend. 74 06/20/83 Technical Specification 2-23a Amend. 100 09/08/86 Technical Specification 2-23b Amend. 74 06/20/83 Page 3 of 12 11/05/92
l SUBJECT PAGE ORIGINAL OR MATTER NUMBER CHANGE NUMBER QATE Technical Specification 2-24 Amend. 120 04/14/89 Technical Specification 2-25 Amend. 120 04/14/89 Technical Specification 2-25a Amend. 120 04/14/89 Technical Specification 2-26 Amend. Ill- 09/24/87 ,
Technical Specification 2-27 Ltr. Dated 06/10/87 Technical Specification 2-28 Amend. 127 04/09/90 Technical Specification 2-29 Amend. 127 04/09/90 Technical Specification 2-30 Amend. 138 05/18/91 Technical Specification 2-31 Amend. 138 05/18/91 Technical Specification 2-31a Amend. 138 05/18/91 ;
Technical Specification 2-32 Amend. 147 08/03/92 Technical Specification 2-33 Amend. 25 06/06/77 Technical Specification 2-34 Amend. 147 08/03/92 Technical Specification 2-35 Amend. 147 08/02/92 Technical Specification 2-36 Amend. 147 08/03/92 Technical Specification 2-37 Amend. 133 10/12/90 Technical Specification 2-38 Amend. 133 10/12/90 Figure 2-10 2-38a Amend. 133 10/12/90 Technical Specification 2-39 Amend. 141 03/06/92 ,
Technical Specification 2-40 Amend. 113 05/04/88 i
Technical Specification 2-41 Amend. 113 05/04/88 Technical Specification 2-42 Amend. 86 04/03/85 Technical Specification 2-43 Amend. 113 05/04/88 :
Technical Specification 2-44 Amend. 137 06/05/91 i Technical Specification 2-45 Amend. 137 06/05/91 l Technical Specification 2-45a Amend. 137 06/05/91-Technical Specification 2-46 Amend. 46 07/02/79 Technical Specification 2-47 Amend. 137 06/05/91 ;
i Page 4 of 12 11/05/92 i
SUBJECT PAGE ORIGINAL OR MATTER NUMBER CHANGE NUMBER DAIX Technical Specification 2-47a Amend. 86 04/03/85 Technical Specification 2-48 Amend. 109 05/04/87 Technical Specification 2-49 Amend. 32 11/21/77 Technical Specification 2-50 Amend. 143 04/02/92 Technical Specification 2-50a Amend. 148 11/05/92 Technical Specification 2-50b Amend. 141 03/06/92 Technical Specification 2-50c Amend. 148 11/05/92 Technical Specification 2-50d Amend. 148 11/05/92 Technical Specification 2-50e Amend. 148 11/05/92 Technical Sp6cification 2-50f Amend. 148 11/05/92 Technical Specification 2-51 Amend. 62 09/22/81 Technical Specification 2-52 Amend. 32 11/21/77 Technical Specification 2-53 Amend. 32 11/21/77 Deleted - Figure 2-4 Amend. 141 03/06/92 Deleted - Figure 2-5 Amend. 141 03/06/92 Deleted - Figure 2-6 Amend. 141 03/06/92 Deleted - Figure 2-7 Amend. 141 03/06/92 Figure 2-8 Amend. 109 05/04/87 Deleted - Figure 2-9 Amend. 141 03/06/92 Technical Specification 2-54 Amend. 141 03/06/92 Technical Specification 2-55 Amend. 141 03/06/92 Technical - Specification 2-56 Amend. 141 03/06/92 Technical Specification 2-57 Amend. 141 03/06/92 Technical Specification 2-57a Amend. 141- 03/06/92 Technical Specification 2-57b Amend. 141 03/06/92 Technical Specification 2-57c Amend. 141 03/06/92 Page 5 of 12 11/05/92
P SUBJECT PAGE ORIGINAL MATTER NUMBER CHANGE NUMBER QATE Technical Specification 2-57d Amend. 141 03/06/92 Technical Specification 2-57e Amend. 141 03/06/92 Technical Specification 2-58 0 08/09/73 Technical Specification 2-59 Amend. 130 04/27/90 Technical Specification 2-60 0 08/09/73 Technical Specification 2-61 Amend. 108 04/28/87 Technical Specification 2-62 Amend. 141 03/06/92 ,
Technical Specification 2-63 Amend. 108 04/28/87 Technical Specification 2-64 Amend. 108 04/28/87 Technical Specification 2-64a Amend. 86 04/03/85 Technical Specification 2-65 Amend. 108 04/28/87 Technical Specification 2-66 Amend. 125 03/19/90 Technical Specification 2-66a Amend. 125 03/19/90 Technical Specification 2-6Gb Amend. 125 03/19/90 Technical Specification 2-67 Amend. 88 05/09/85 i
Technical Specification 2-67a Amend. 88 05/09/85 l Technical Specification 2-68 Amend. 88 05/09/85 Technical Specification 2-68a Amend. 88 05/09/85 ,
Technical Specification 2-68b Amend. 88 05/09/85 Technical Specification 2-69 Amend. 108 04/28/87 Technical Specification 2-69a Amend. 108 04/28/87 Technical Specification 2-70 Amend. 110 08/31/87 i
Deleted 2-70a Amend. 65 06/18/82 Technical Specification 2-71 0 08/09/73 !
Technical Specification 2-72 Amend. 11 02/04/76 .
Technical Specification 2-73 Amend. 105 03/26/87 :
i
'Page 6 of 12 11/05/92-
SUBJECT PAGE ORIGINAL OR MIJffL NUMBER CHANGE NUMBER MT1 Technical Specification 2-74 Amend. 105 03/26/87 l
Technical Specification 2-89 Amend. 133 10/12/90 Technical Specification 2-90 Amend. 128 04/12/90
-l Technical Specification 2-90a Amend. 60 07/29/81 Technical Specification 2-91 Amend. 133 10/12/90 Technical Specification 2-92 Amend. 133 10/12/90 Technical Specification 2-93 Amend. 53 11/17/80 j Technical Specification 2-94 Amend. 60 07/29/81 l Technical Specification 2-95 Amend. 60 07/29/81 Technical Specification 2-96 Amend. 67 02/23/83 Technical Specification 2-97 Amend. 110 08/31/87 Technical Specification 2-97a Amend. 110 08/31/87 Technical Specification 2-98 Amend. 147 08/03/92 Technical Specification 2-98a Amend. 147 08/03/92 Technical Specification 2-98b Amend. 110 08/31/87 Technical Specification 2-99 Amend. 87 04/29/85 Technical Specification 2-100 Amend. 107 03/30/87 Technical Specification 3-Oa Amend. 129 04/27/90 Technical Specification 3-Ob Amend. 129 04/27/90 Technical Specification 3-Oc Amend. 122 06/02/89 Technical Specification 3-1 Amend. 125 03/19/90 Technical Specification 3-2 0 08/09/73 Technical Specification 3-3 Amend. 60 07/29/81 Technical Specification 3-4 0 08/09/73 Technical Specification 3-5 Amend. 77 04/26/84 Technical Specification 3-6 Amend. 122 06/02/89 Page 7 of 12 11/05/92
SUBJECT PAGE ORIGINAL OR MATTER NUMBER CHANGE NUMBER DMI Technical Specification 3-7 Amend. 54 01/19/81 Technical Specification 3-8 0 08/09/73 Technical Specification 3-9 Amend. 111 09/24/87 Technical Specification 3-10 Amend. 111 09/24/87 Technical Specification 3-11 Amend. 131 05/18/90 Technical Specification 3-12 Amend. 41 .11/27/78 Technical Specification 3-12a Amend. 122 06/02/89 Technical Specification 3-13 Amend. 137 06/05/91 Technical Specification 3-14 0 08/09/73 Technical Sp6cification 3-15 Amend. 123 11/06/89 Technical Specification 3-16 Amend. 96 04/24/86 Technical Specification 3-16a Amend. 110 08/31/87 i Technical Specification 3-16b Amend. 107 03/30/87 2 Technical Specification 3-16c Amend. 122 06/02/89 -
Technical Specification 3-16d Amend. 125 03/19/90 Technical Specification 3-16e Amend. 125 03/19/90 Technical Specification 3-17 Amend. 128 04/12/90 Technical Specification 3-17a Amend. 138 05/18/91 !
4 Technical Specification 3-18 Amend. 133 10/12/90 Technical Specification 3-19 Amend. 133 10/12/90 Deleted 3-19a Amend. 67 02/23/83 Technical Specification 3-20 Amend. 128 04/12/90
. Technical Specification 3-20a Amend. 128 04/12/90 ,
Technical Specification 3-20b Amend. 128 04/12/90 l Technical Specification 3-20c Amend. 128 04/12/90 Technical Specification 3-20d Amend. 80 07/9/84 Technical Specification 3-20e Amend. 138 05/18/91 Page 8 of 12 11/05/92
SUBJECT- PAiC ORIGINAL MATTER NUMBER CHANGE NUMBER RAI[
A Technical Specification 3-21 Amend. 142 03/19/02 Technical Specification 3-22 Amend. 104 03/26/87 Technical Specification 3-27 Amend. 142 03/19/92 Technical Specification 3-36 0 08/09/73 Technical Specification 3-37 Amend. 95 02/03/86 Technical Specification 3-38 Amend. 95 02/03/86 Technical Specification 3-39 Amend. 95 02/03/86 Technical Specification 3-40 Amend. 95 02/03/86 Technical Specification 3-41 Amend. 95 02/03/86 Technical Specification 3-42 Amend. 95 02/03/86 :
Technical Specification 3-43 Amend. 95 02/03/86 ;
Technical Specification 3-44 Amend. 97 _06/03/86
- f. - Technical Specification 3-45 Amend. 139 10/31/91 Technical Specification 3-46 Amend. 139 10/31/91 Deleted 3-47 Amend. 139 10/31/91
?
Deleted 3-48 Amend. 139 10/31/91 Technical Specification 3-49 Amend. 139 10/31/91 Technical Specification 3-50 Amend. 139 10/31/91 Technical Specification 3-51 Amend. 139 10/31/91 Technical Specification 3-52 Amend. 139 ~10/31/91 Technical Specification 3-53 Amend. 139 10/31/91 Technical Specification 3-53a Amend. 95 02/03/86 Technical Specification 3-54 Amend. 121 04/26/89 Technical Specification 3-54a Amend. 44 03/22/79 Technical Specification 3-55 Amend. 135 12/03/90 Technical Specification 3-56 Amend. 24 06/06/77 Page 9 of 12 11/05/92
$b ' a . ~
SUBJECT PAGE ORIGINAL OR MATTER NUMBER CHANGE NUMBER RAJ1 Technical Specification 3-57 Amend. 121 04/26/89 Technical Specification 3-57a Amend. 121 04/26/89 Technical Specification 3-58 Amend. 140 12/23/91 :
Technical Specification 3-59 Amend. 112 04/19/88' Technical Specification 3-60 Amend. 111 09/24/87 Technical Specification 3-61 Amend. 24 06/06/77 Technical Specification 3-62 Amend. 90 08/19/85 Technical Specification 3-62a Amend. 134 11/19/90 Technical Specification 3-63 Amend. 122 06/02/89 .
~
Technical Specification 3-63a Amend. 141 03/06/92 Technical Specification 3-63b Amend. 92 11/29/85 Technical Specification 3-64 Amend. 86 04/03/85 ,
Technical Specification 3-65 Amend. 86 04/03/85 Technical Specification 3-66 Amend. 86 04/03/85 Technical Specification 3-67 Amend. 86 04/03/85 ,.
Deleted 3-68 Amend. 86 04/03/85 Technical Specification 3-69 Amend. 122 06/02/89 Technical Specification 3-70 Amend. 137 06/05/91 Technical Specification 3-70a Amend. 137 06/05/91~
Technical Caecification 3-71 Amend. 122 06/02/89 Technical Specification 3-71a Amend. 91 08/22/85 Technical Specification 3-72 Amend. 122 06/02/89 Technical Specification 3-73 Amend. 122 06/02/89 ,
Technical Specification 3-74 Amend. 137 06/05/91 ,
. Technical Specification 3-75 Amend. 86 04/03/85 Technical Specification 3-76 Amend. 122 06/02/89 Page 10 of 12 11/05/92-
, ., __ .~ ._ . . . _ _.
l SUBJECT' PAGE ORIG'INAL OR -
MATTER NUMBER CHANGE NUMBER QME '
Technical ' Specification 3-77 Amend. 145L 04/23/92- -
1 Technical. Specification 3-78 Amend. 105 03/26/87 j Technical Specification 3-79 Amend. - 145 - 04/23/92- .
Technical Specification 3-79a Amend. 145 04/23/92 {
Technical Spectfication 3-79b . Amend. 145 04/23/92- ;
1 Technical Specification 3-79c Amend. 145. 04/23/92 Technical Specification 3-80 Amend. 122. 06/02/89 ] ,
Technical Specification 3-81 Amend. 98 07/01/86 [
Technical Specification 3-82 Amend. 53 11/17/80 Technical Specification 3-83 Amend. 98~ 07/01/86: I Technical Specification 3-84 Amend. 136 12/12/90 Technical Specification 3-85 Amend. 136 12/12/90 ;
Technical. Specification 3-86 Amend. 104- '03/26/87: l
-Technical Specification 3-87 Amend. 104 03/26/87.
Technical Specification .3-88 Amend. 104 03/26/87-
.t Technical Specification 3-89 Amend.-104 03/26/87- l Technical Specification 3-90 Amend. 104- 03/26/87 Technical Specification 3-91 Amend. 104 03/26/87- q Technical Specification 4-1 Amend. 36- 01/20/78 i Technical Specification 4-2 0 08/09/73.
Technical Specification 4-3 Amend. 109 05/04/87
^
Technical-Specification 4-4 Amend. 141 03/06/92 j
-i .
Technical Specification 4-5 0 -08/09/73 Technical Specification 5-1 Amend. 132 07/26/90-Technical Specification 5-la Amend. 115 07/01/88 ,
Technical . Specification' 5-lb- Amend. 115 07/01/88.
1 Deleted - Figure 5-1 Amend. 115 07/01/88- ;
Deleted - Figure 5 Amend. 115 07/01/88- f
- Page 11 of 12 11/05/92
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SUBJECT 'PAGE ORIGINAL OR' -
MATTER NUMBER CHANGE NUMBER DME i
-Technical Specification 5-2 Amend. 78 05/16/84 Technical Specification 5-3 Amend. 134 11/19/90 Technical Specification 5-4 Amend. 141 03/06/92 Technical Specification 5-5 Amend. 141 03/06/92 Technical Specification 5-6 Amend. 60 07/29/81 Technical Specification 5-7 Amend. 99 08/13/86 ;
Technical Specification 5-8 Amend. 132 07/26/90 Technical Specification 5-8a Amend. 86 04/03/85 Technical Specification 5-9 Amend. 115 07/01/8S +
Technical Sp6cification 5-10 Amend. 75 09/09/83 '
Technical Specification 5-11 Amend. 75 '09/09/83 Technical Specification 5-12 Amend. 119 02/14/89 Technical Specification 5-15 Amend. 147 08/03/92 Technical Specification 5-16 Amend. 102 01/20/87 Technical Specification 5-17 _ Amend. 102 01/20/87 Technical Specification 5-17a Amend. 144 04/22/92 Technical Specification 5-18 Amend. 99 08/13/86 Technical Specification 5-19 Amend. 105 03/26/87 Technical Specification 5-19a Amend. 132 07/26/90 Technical Specification 5-20 Amend. 93 ~12/06/85 Technical Specification 5-21 Amend. 89 5/24/85 Technical Specification 6-1 Amend. 73 04/11/83 t
Page 12 of 12 11/05/92 b
~ FORT CALHOUN $TATION 'PAGE.1:0F,3 EMERGENCY PLAN IMPLEMENTIN
G. PROCEDURE
S INDEX .
(EPIP)
. PROCEDURE ,
NUMBER TITLE REVISION /DATE a
EPIP-0SC-1 Emergency Classification R21 07-08-92
[EPIP-0SC-2] Notifications 'R26 02-05-93 ,
EPIP-OSC-9 Emergency Team Briefings R4 01-18-93 EPIP-OSC-12 Accidental Actuation of Early Warning Siren System (R8 04-05-91) -
DELETED 10-29-91' !
i
[EPIP-0SC-14] Shift Supervisor Actions (R18 12-30-91)-
- SUPERSEDED 02-05-93 EPIP-0SC-15 Communicator Actions R11 02-03-93 t 1
[EPIP-05C-20] Site Population Exposure Estimates R4- 11-09-92 ,
n EPIP-05C-21 Activation of the Operations Support Center R3 02-03-93 EPIP-TSC-1 Activation of the Technical Support Center R16 01-18 '
EPIP-TSC-8 Core Damage Assessment R7 07-13-92 EPIP-EOF-1 Activation of the-Emergency Operations Facility R8 05-22-92 EPIP-EOF-3 Offsite Monitoring R12 09-05-91
[EPIP-EOF-6] Manual Dose Assessment R21 01-13-93 l EPIP-EOF-7 Protective Action Guidelines R9 02-03-93 EPIP-EOF-10 Warehouse Personnel Decontamination Station R9 11-01-90 '
Operation EPIP-EOF-Il Dosimetry Records, Exposure Extensions and R13 09-05-91 Habitability EPIP-EOF-13 Emergency Direction and Control Transition (R7 05-22-92).
SUPERSEDED 02-05-93 EPIP-EOF-19 Downgrading and Termination of the Emergency R6 02-03-93 Classification, and Recovery EPIP-E0F-20 Imminent / Projected Release Calculations (R1 11-01-90)
SUPERSEDED 02-05-93 EPIP-EOF-21 Potassium Iodide Issuance RI- 11-01-90
{ ] '"On Going" Commitments
.FC/INDEX/MC 02/23/93 2:25pm
- I t
' FORT CALHOUN STATION PAGE 2 0F 3 !
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX (EPIP) .
PROCEDURE !
NUMBER TITLE REVISION /DATE :
'EPIP-E0F-22 Computerized Dose. Assessment (R3 '05-17-91c)- i SUPERSEDED.02-05-93 EPIP-EOF-23 Emergency Response Message System R2 07-30 ;
EPIP-E0F-24 E0F Backup Alert Notification System Activation R0 11-01-90 !
[EPIP-RR-10] Emergency Director Actions (R13 10-31-91) .
SUPERSEDED 02-05 .
[EPIP-RR-11] Technical Support Center Director Actions R11 02-08 t
[EPIP-RR-13] Reactor Safety Coordinator Actions R9 01-14-93.
EPIP-RR-17 TSC Security Coordinator Actions R10 11-01-90.
EPIP-RR-17A TSC Administrative-Logistics Coordinator Actions. R6 11-14-91~
[EPIP-RR-18] Site. Director Actions (RIO 10-31-91) .
SUPERSEDED 02-05-93 J EPIP-RR-19 Control Room Coordinator Actions (R11 12-18-91)-
SUPERSEDED 02-05-93 EPIP-RR-19A Operations Liaison Actions R2 02-03-93
[EPIP-RR-21] Operations Support Center Director Actions R9 11-08-91 EPIP-RR-21A Maintenance Coordinator Actions R1 11-01 ,
[EPIP-RR-22] Protective Mt;asures Coordinator Actions R12 02-03-93 ;
EPIP-RR-22A Chemistry Coordinator Actions R2 01-09-92
-[EPIP-RR-24] EOF Protective Measures Manager Actions 'R12 02-03-93 .;
[EPIP-RR-25] EOF Dose Assessment Coordinator Actions R14 02-24-93 EPIP-RR OSC Accountability and Dosimetry Technical Actions R6 11-01-90
-)
EPIP-RR-29 EOF Administrative Logistics Manager Actions R10 04-24-92 l EPIP-RR-63 EOF Dose Assessment Assistant Actions R6 02-03-93 EPIP-RR-65 EOF Communicator Actions (R3 11-01-90)~
SUPERSEDED 02-03-93 ;
[.] "On Going". Commitments FC/INDEX/MC 02/23/93 2:25pm ,
i e
FORT CALHOUN STATION PAGEi3 OF 3 !
EHERGENCY PLAN IMPLEMEN11NG PROCEDURES INDEX-(EPIP)
PROCEDURE NUMBER TITLE REVISION /DATE EPIP-RR-66 Communication Specialist Actions R5 11-01-90._
[EPIP-RR-69] EOF Dose Assessment Specialist Actions R8 02-24-93 l EPIP-RR-70 EOF Operations Liaison Actions (R4 09-05-91)
SUPERSEDED 04-24-92 EPIP-RR-72 EOF Field Team Specialist Actions R8 11-01-90 EPIP-RR-84 TSC Operations Liaison Actions (R2 09-05-91)
SUPERSEDED 04-24 [EPIP-RR-85] TSC Dose Assessment Coordinator Actions R4 02-24-93 :
EPIP-RR-87 Radiation Protection Coordinator Actions R3 09-27-91 .
[EPIP-RR-94) TSC Dose Assessment Specialist Actions R3 02-24-93 EPIP-RR-95 TSC Field Team Specialist Actions R0 11-01-90 EPIP-RR TSC Communicator Actions (R0 11-01-90) ,
SUPERSEDED 02-03-93
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[-] "06 Going" Commitments
'FC/INDEX/MC 02/23/93 2:25pm i
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- FORT CALHOUN 5TATION . PAGE :110F-~ 5 ; j l
n ANNUNCIATOR RESPONSE-INDEX 1
$ ARP. ]
' Annunciator Response Procedures are in order according to the Annunciator Number.
PROCEDURE NUMBER TITLE REVISION / DATER j ARP-1 ARP-1-Annunciator Response Procedure R1- 06-03-92 !
ARP-CB-1,2,3/A1 Annunciator Response Procedure Al Control R6.L12-07-92a-Room Annunciator A1 ARP-CB-1,2,3/A2 Annunciator Response Procedure.A2 Control R4 : 04-14-92a1 :
Room Annunciator A2 ARP-CB-1,2,3/A4 Annunciator Response Procedure A4 Control R1 06-07-91c- !
Room Annunciator A4 ,
ARP-CB-1,2,3/A6 Annunciator Response Procedure A6 Control --R0 .04-30-91 .
Room Annunciator A6 .l l
ARP-CB-4/A7 Annunciator Response Procedure A7 Control R2 '.04-09 ~l Room Annunciator A7
. 1 Annunciator Response Procedure A8 Control R3.-02-05-93 $
ARP-CB-4/A8 Room Annunciator A8 l 1
ARP-CB-10,11/A9 Annunciator Response Procedure A9 Control' R3 07-21-92a ,
Room Annunciator A9 <t
- i ARP-CB-10,11/A10 Annunciator Response Procedure A10 Control' RI 11-04-92 Room Annunciator-A10 q 1
ARP-CB-10,11/A11 Annunciator Response Procedure All Control R0 04-30-91 :l i
Room' Annunciator.A11 ARP-CB-10,11/A12 Annunciator Response Procedure A12 Control R0 04-30 -
Room Annunciator A12 i
Annunciator Response Procedure A13 Control R1 02-01 1 ARP-CBi10,11/A13 Room Annunciator A13 -l
[ARP-CB-20/A14] Annunciator Response Procedure.A14 Control. R4 04-08-92a' 1 Room Annunciator A14
. Annunciator Response Procedure A15 Control 'R4 .03-25-92b-j ARP-CB-20/A15 Room Annunciator.-A15 ARP-CB-20/A16]- Annunciator-Response Procedure.A16 Control RI 04-22-92a" '1 Room-Annunciator A16 q i
--F /INDEX/MC: 02/05/93L12:16pm !
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FORT CALHOUN STATION PAGE 2 0F S ANNUNCIATOR RESPONSE INDEX ARP Annunciator Response Procedures are in order according to the Annunciator Number.
PROCEDURE NUMBER TITLE REVISION /DATE
[ARP-CB-20/A17] Annunciator Response Procedure A17 Control R1 04-22-92a Room Annunciator A17
[ARP-CB-20/A18] Annunciator Response Procedure A18 Control R1 04-22-92a Room Annunciator A18
[ARP-CB-20/A19] Annunciator Response Procedure A19 Control R1 04-22-92a Room Annunciator A19 ARP-CB-4/A20 Annunciator Response Procedure A20 Control RS 09-02-92b Room Annunciator A20 ARP-CB-10,11/A21 Annunciator Response Procedure A21 Control R2 10-28-92 Room Annunciator A21 ARP-Al-30A/A30 Annunciator Response Procedure A30 Control R6 10-07-92 Room Annunciator A30. Engineered Safeguards (DG-1)
ARP-Al-134/A30-1 Annunciator Response Procedure A30-1 Local R0 04-30-91 Annunciator Panel A30-1 Generator Hydrogen Panel ARP-Al-134/A30-2 Annunciator Response Procedure A30-2 Local R0 04-30-91a Annunciator A30-2, Generator. Stator Cooling Panel ARP-Al-30A/A31 Annunciator Response Procedure A31 Control R1 04-09-92 Room Annunciator A31, Engineered Safeguards, D.C. Sequencers (51-1)
RRP-Al-30A/A32 Annunciator Response Procedure A32 Control R1 01-18-93 Room Annunciator A32, Engineered Safeguards, A.C. Sequencers (S1-2)
ARP-Al-33C/A33-C Annunciator Response Procedure A33C R2 03-24-92 Control Room Annunciator A33C Radiation ,
Monitor Panel ARP-AI-30A/A33-1 Annunciator Response Procedure A33-1 R1 04-09-92 Control Room Annun'ciator A33-1 Engineered Safeguards ,
01/15/93 1:20pm FC/INDEX/MC
FORT CALHOUN STATION PAGE 3 0F 5 ANNUNCIATOR RESPONSE INDEX ARP Annunciator Resoonse Procedures are in order according to the Annunciator Number.
PROCEDURE NUMBER TITLE REVISION /DATE ARP-Al-30A/A33-2 Annunciator Response Procedure A33-2 R3 04-22-92 Control Room Annunciator A33-2 Engineered Safeguards ARP-AI-301;/A34-1 Annunciator Response Procedure A34-1 R1 04-09-92a Control Room Annunciator A34-1 Engineered Safeguards :
ARP-Al-30B/A34-2 Annunciator Response Procedure A34-2 R3 04-22-92 Control Room Annunciator A34-2 Engineered Safeguards ARP-AI-308/A35 Annunciator Response Procedure A35 Control R1 04-09-92 Room Annunciator A35, Engineered Safeguards, A.C. Sequencers (S2-2)
ARP-Al-308/A36 Annunciator Response Procedure A36 Control R1 04-09-92 Room Annunciator A36, Engineered Safeguards, D.C. Sequencers (52-1)
ARP-AI-30B/A37 Annunciator Response Procedure A37 Control RS 10-08-92 Room Annunciator A37, Engineered Safeguards (DG-2)
ARP-Al-44/A38 Annunciator Response Procedure A38 Control R1 06-26-91 Room Annunciator A38, Auxiliary Building and Containment Ventilation ARP-Al-44/A39 Annunciator Resaonse Procedure A39 Control R1 06-26-91a Room Annunciator A39, Auxiliary Building and Containment Ventilation ARP-Al-43A/A40 Annunciator Response Procedure A40 Control R1 02-29-92 Room Annunciator A40, Containment Isolation
-ARP-Al-438/A41 Annunciator Response Procedure A41 Control R1 02-29-92a Room Annunciator A41, Containment Isolation ARP-Al-107/A42 Annunciator Response Procedure A42 Local R1 06-07-91 Annunciator A42, Steam Generator Secondary Sample Panel FC/1NDEX/MC 01/06/93 8:18am
FORT CALHOUN STATION PAGE 4 0F 5 ANNUNCIATOR RESPONSE INDEX ARP Annunciator Response Procedures are in order according to the Annunciator Number.
PROCEDURE NUMBER TITLE REVISION /DATE-ARP-AI-100/A50 Annunciator Response Procedure A50 Local R0 04-30i91 Annunciator A50, Waste Disposal ARP-Al-100/A51 Annunciator Response Procedure ASI Local R0 04-30-91a Annunciator A51, Waste Disposal ARP-Al-100/A52 Annunciator Response Procedure A52 Local R0 04-30-91 Annunciator A52, Waste Disposal RRP-AI-101/A53 Annunciator Response Procedure A53 Loc R0 04-30-91a Annunciator A53, Waste Disposal, Spent Resin Tank
[ARP-AI-54A/AS4) Annunciator Response Procedure A54 Control R1 05-06-91 Room Annunciator A54, Fire Detection Panel >
Annunciator Response Procedure A65A - R1 11-19-91a ARP-AI-65A/A65-A Control Room Annunciator A65-A Containment /RCGVS ARP-Al-65B/A65-B Annunciator Response Procedure A65B R0 04-30-91a Control Room Annunciator A65-B Containment /RCGVS ARP-AI-66A/A66-A Annunciator Response Procedure A66A R1 04-08-92a Control Room Annunciator A66-A, AFWAS/ DSS e
ARP-Al-66B/A66-B Annunciator Response Procedure A66B R2 09-29-92 Control Room Annur.ciator A66-B, AFWAS/ DSS Annunciator Response Procedure A79 Local R1 02-01-93 ARP-Al-79/A79 Annunciator A79, Air Dryer Panel ARP-Al- Annunciator Response Procedure A102, 103 R0 04-30-91 102.103/A102,A103 Local Annunciator A102,103, Waste Disposal, Waste Evaporator Annunciator Response Procedure A104 Local R3 10-28-92 ARP-AI-104/A104 Annunciator A104, Water Plant
-Annunciator Response Procedure A106A R0 04-30-91a
'ARP-Al-106A/A106-A Control Room Annunciator A106-A Control Room Ventilation 01/29/93 3:02pm FC/INDEX/CM
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. . FORT;CALHOUN: STATION .PAGE SLOF.5
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ANNUNCIATOR-RESPONSE INDEX ARP L
F .AnnunciatoriesponseProceduresareinorder.
according to the Annunciator Number.
PROCEDURE NUMBER TITLE REVISION /DATE:
ARP-A'l-106B/A106-B Annunciator Response Procedure ~A106B .
.R0 04-30-91a-Control Room-Annunciator A106-B Control.
Room Ventilation ARP-AI-125/A125 Annunciator Response Procedure A125 Local R2 .01-05-93.
Annunciator A125 ARP-AI-187/A187 Annunciator Response Procedure A187 Local R0 04-30-91
' Annunciator A187, Switchgear. Ventilation ARP-Al-201/A201- ' Annunciator Response Procedure =A201 Local ;RO '04-30-91 Annunciator A201:TSC Ventilation.
-ARP-DGE/DI-L Annunciator Response Procedure DG1-Local R3 '09-21-92' Annunciator DI-L Local Control Panel (D-1).
aRP-DG2/D2-L Annunciator Response Procedure DG2-Local -R3 10-08-92 Annunciator 02-L Local Control' Panel D-2
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FC/INDEX/MC. 01/22/93 2:06pm.
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P AT130MMT C ,
1993 MlC JI9f I2ST RR 1761DE 1M QN1110G RC3i JPM No. JPM Title importance 0001 Cantinuous Rod Withdrawal 4.3 0008 Diergency Boration fztra the Cantzal Roam 4.4 0010 Loss of CG4 4.1 0014 Loss of Pwer Range Instrurrentation 3.4 0015 Fuel Handling Incident 4.0 0026 Restoration of Offsite Electrical Pwer 4.4 0027 Waste Gas Incident 4. 6 >
0042 Cross-cannect Inst. Buses and Rcstove Inverter frun 3.3 Service 0105 Feed Stmm Generators via the Main FeedWater Ring 3.8 Using an Aux. FeedWater Pimp and then Secure Feeding 01051 Initiate Aux. Feedwater Flow to the Stearn Generators 3. 8 via the AMi Nozzles Using H4-6 0119 Initiate Charging and Letdown 3. 7 0119A Inctmsing Charging and Letdown Flows 3. 7 01 21 Perfoon Baron Change Calculatlan 3. 7 0124 Dilution of RCS, Nannal Flowpath 3.8 0125 Baration of RCS, Nantal Flcspath 3. 7 0136 knidnate Charging and Letdown with RCS in Nooral 3.5 Operaticv1s 0138 Operate CVCS to Makeup to S1RWT 3.4 0156 Operate Cbntaintient Hg Analyzer 3.3 0290 Shift 4160V Buses Between Urlit Aux. and House 3.4 Service Trans.
0293 Backfeed 345KV to 22KV 3.6 0312 Hot Bus Transfer of 480V Buses 3. 3 0312A Hot Bus Transfer of 480V Buses to Nantal Lineup 3.3-0323 maninate SDC 3.3 0329 Fill Safety Injection Tanks 3. 6 0335 Cbntaintient Spray Purip Operability %st 3. 6 0335A ILw Pmssum Safety Injection Pung Operability 3. 6 hst 0338 Initiation of Long kan Care Cooling 4.1 0344 Parallel and Irad a Diesel Generator (&l) 4. 0 0347 Unlcad a Diesel Generator (&l) 3.6 0348 Hanual Startup and Shutdown of Diesel Generator 3. 7 (51) 0355 Diesel Auto Start Initiatirx] Circuit 01eck 3.5 0366 Block PP1B 3. 7 0367 Perfonn SIAS Surveillance %st an Channel A 3.5 0369 Reset CSAS 3.8 0370 Perfoon CSAS Sunni11ance %st 3.6 0373 Perfaan RAS Surveillance %st 3. 6
-0384 Block SES 3. 7 0392 Perfaan ESP Sequencer Suneillance %st 3.5 0397 Reset Engineetal Safeguanis (AOP-23) 3. 7 C-1
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AT17iGHW1' C 1993 NRC JIM IJSP Im I1GIM 112 ON1TlOG TGN JPM No. JPM T1t1e Imaartance 0571 Adjust Narmw Range Safety 01annel Instrurnantation 3. 6 0584B Place RMO50/51 in Oparation 3.6 0607 Calculate RW Imkrate 3. 6 0612 Start a Rwctor Cbolant Purrp 3. 8 0613 Shutdown a Rmctor Coolant Pung 3.6 0621 Manual Cantzol of RCS Pmssum with a Bubble in PER 3.8 0623 Transfer PER Pressure Ox2tw1 fran Manual to Auto 3.6 0625 &]ualize Bomn Concentration with PER Pressure 3. 4 Cbntml in Autmatic 0629 Perfann Imv 14w-tenperatum Ovar-pmssum lust 3.5 0637A Shift HC-101 frctn Manual to Auto 3. 5 0637D Transfer Cbntrol of IRC-101 fran Auto to Manual 3.5 0646 Perfann RPS th11t Startup Otecklist 3. 6 0654 Petfann RPS Manual Trip Q1ecks 3.4 0659 Perfonn Stmm Dung Systan Tust 3.4 0664 Recover Arcin Rod Block 3.4 0666 Withdraw Shutdown Group Rods 3.8 0668 Operate OJntrol Rod Drive to Shutdcun the Rmctor 4.1 0717 Perfann Lineups of Cantainnent Ventilation Systan 3.8 0718 Place Cbatainnent Cooling Unit In-sczvico 3. 7 '
0719 Startup Cbatainnent Hy Purge 3. 8 0720 Shutdown Contairment H, Purge 3. 5 0723 Cparate the Contml Ra3 Drive Fans 3. 3 0724A Operate Nacimr Detector Well Cboling iklits 3.6 0721B Startup Detector Well Cooling 3. 6 0724C Shutdcun Detector Well Cboling 3.6 0778 Adjust 1rold Cal. 3. 6 C-2
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Al'130MX1' C 1993 NC JIM LIS1' KR OUTS 1TE '11E GN11XL IGN JPM No. JPM Title I1noortance 0092B Perfonn Lineup of AEW fzun the Plant 4.4 0096 Local Start of EW-6 3. 6 0098 Operate EW-10 fzun AI-179 3. 7 0099 Stop EW-10 fzun AT-179 and Transfer Control to the 3.4 Cantzol Roan 0100 Local Slow Start of EW-10 - 3. 9 0102 Operate AEW Systan fzun AI-179 3.9 0107 Respond to a Stmm Bound AEW Paap 4.1 0153 Dnergency Borate fzun Outside the Control Rocin 4.4 0214 Shift Inservicc Air Gnpressors 3.1 0295 SWtch Inverter Pcuer Supply fzun Bypass to Nozmsl 3. 6 .
0305 Place Battery Charger Inservice 3.5 0306 Alternate and Secuze Bsttery Chargers 3. 3 0340A Partial Lineup of Diesel Generator 4.0 0340B Partial Inneup of Diesel Generator Systens 4.0 0356 Perfoon Local Manual Start of DG-2 3. 8 0450 Diergency Start of Diesel Fire Pung 3.1 0719 Startup Contalment Hy Puzge 3.8 0720 Shutdcun Containnent Hg Purge 3.5 P
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AT1%7HX1'C 1993 RED (1%IFIQ1TICN DYMULTC S1 MEA 7th FL@ilNATIONS i
Title SSG#
- 1. LOCA Caused By KEY Failure 08-41-01 e
- 2. LOCA 08-41-02
- 3. SC71R Cbincidwt with a Lms of Offaite Power 08-41-03
- 4. Steam Gwerator Tube Rupture 08-41-04
- 5. Uncontrolled Hmt Extraction Event 08-41-06
- 6. Dynamic Simulator Examination 08-41-08
- 7. Loss of JW with Stmm Lwk Inside Cantaincrent 08-41-09
- 8. lbtal Loss of Feafnater 08-41-10
- 9. LOCA in PER 08-41-11
- 10. Simultaneous Sl71R and Feed Line Break 08-41-12
.11. 7btal Blackout with 345 EV Recovery 08-41-13
- 12. Plant Shutdown with SGTR and Loss of 1B4C 08-41-14
- 13. Raw Water System Lwk with Loss of Bus 1A3 08-41-15
- 14. Steam Line Brmk with Featanter Problans 08-41-16
- 15. A7h5 with SI Baration Required 08-41-17 f
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1993 S1MLWtR 1NITIN> CDNDITICNS The follcw1m initi.al condition sets have bcm rewritten:.
IC-1: Mid Icop Ops-S/G's @ 76%
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IC-3: RCS H/U In Pzu]ress Bubble in Pzr IC-4: RW 24% Pcwr-Rmdy to Xfer ET4 Reg IC-5: RCS Cooldcun in Prcx]ress, Rmdy IC-6: Rx Startup (All Rods Inserted) ,
IC-9: 10% Power - Rmay to Sync Gen IC-10: 100% Pcwr Q.Xe 7000 AMD/M Qcle 14 IC-11: 30% Pcwr Q.Xe 250 5D/M Cycle 14 IC-12: 50% Pcwr Q.Xe 250 AD/M Cycle 14 IC-13: 80% power M.Xe 250 DD/1m] Qcle 14 IC-14: 100% pcwr Q.Xe 250 MD/M Qtle 14 IC-15: RX S/U In Pzoyress Pcuer-Trip Qcle 14 IC-18: 3Oh Pcwr Q.Xe 7000 DD/M Cycle 14 IC-20: 501 Pcwr Q.Xe 7000 5D/M Qcle 14 IC-24: 100% Pcuer Q.Xe 13,000 nD/MlTJ Cycle 14 IC-34: Cri S22 - Stmm Generators Drained IC-36: RX Startup (SD/NT Rcds Withdraun) ,
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ATin091NT C 1993 SIMEA1M PAT 2TMCTIW OwW AND arru;i P1mse refer to Book 30 of the June 1992 nailing.
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