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Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 6
	ML16071A149
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	03/03/2016
From:	; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML16071A108	List: ML16071A110; ML16071A126; ML16071A132; ML16071A136; ML16071A137; ML16071A140; ML16071A144; ML16071A146; ML16071A147; ML16071A149; ML16071A150; ML16071A152; ML16071A153; ML16071A158; ML16071A160; ML16071A166; ML16071A170; ML16071A174; ML16071A176; ML16071A180; ML16071A181; ML16071A184; ML16071A185; ML16071A187; ML16071A188; ML16071A193; ML16071A195; ML16071A198; NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 1 of 4; NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 2 of 4; NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 3 of 4; NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 4 of 4; NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 3; NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 3; NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 3; NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 6; NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 6; NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 6; NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 4 of 6; NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 5 of 6; NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 6 of 6; NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 8; NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 8; NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 3 of 8; NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 4 of 8; NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 5 of 8; NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 6 of 8; NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 7 of 8; NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 8 of 8; NL-15-1898, Enclosure 5: Vogtle Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 4; ... further results
References
	NL-15-1898
	Download: ML16071A149 (54)
	v • d • e

SM-SNC524602-001IAttachment IENERCON Calculation for E-HU1SHEET I-6 v15Page 1 of 3CALC NO. SNC024-CALC-003FNP DETERMINATION OFEMERGENCY ACTION LEVEL REV. 0PAGE NO. Page 6 of 85.0 Design Inputs1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask systemtechnical specification [2, Table 6.2-3] are provided below in Table 5-1. Thesesource values are scaled to develop the emergency action levels for initiatingcondition E-HU1.Table 5-1 Technical Specification Dose Rate Limits (Neutron + Gamma) for HI-STORM100 and HI-TRAC 125LocaionNumber of 1Technical SpecificationjMeasurementsj Limit (mrem/hr)HI-TRAC 125Side -Mid -height T 4 1680.3Top 1 4 j129.4HI-STORM 100Side -60 inches below mid-height 4 171.8Side -Mid -height 4 177.0Side -60 inches above mid-height 4 84.7Top -Center of lid 1 27.1Top -Radially centered 4 30.0Inlet duct 4 231.8Outlet duct 4 82.2 SM-SNC524602-001Attachment IIPNI::IlNN (.'l'ml:afinn fnr IF..WI I1SHEET I-7 v15Page 2 of 3CALC NO. SNCO24-CALC-003FNP DETERMINATION OF ___________EMERGENCY ACTION LEVEL REV. 00I EN ER C ON FORI=NITATNG CONDITION E- _ _______..."' HUl PAGE NO. Page 7 of 86.0 MethodologyThe "on-contact"' dose rates from the technical specification for the HI-STORM 100 andHI-TRAC 125 cask system are scaled by a factor of 2, as specified in NEI 99-01 Rev. 6[1], for use in initiating condition E-HU1.

SM-SNC524602-001Attachment II:PCANI (%lrdp-mi6*rn fr i::._WI I1SHEET I-8 v15Page 3 of 3CALC NO. SNC024-CALC-003FNP DETERMINATION OFEMERGENCY ACTION LEVEL REV. 00 E N E R C 0 N FOR INITAliNG CONDITION E-HUl PAGE NO. Page 8oft87.0 CalculationsThe dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose ratelimits. These calculations are presented below in Table 7-1.wTable 7-1 Dose Rate Scaling Calculations for EAL Limits (Neutron + Gamma)TechnicalLoainSpecification Scaling Calculated Value EALLoainLimit Factor .(mremn/hr) (mrem/hr)_______________________ (mremlhr) ____________ _____________ ______ ______ ______HI-TRAC 125 _ _ _ _ _ _ _ _ _ _ _ _ _ _Side -Mid -height [ 680.3 j 2 J 1360.6 1360Top L 129.4 j 2 258.8 260Side -60 inches below mid-heightSide -Mid -heightSide -60 inches above mid-heightTop -Center of lidTop -Radially centeredInlet ductOutlet duct171.8177.084.727.130.0231.882.2343.6 340354 350169.4 17054.2 5060 60463.6 460164.4 1608.0 Computer SoftwareMicrosoft WORD 2Q13 is used in this calculation for basic multiplication.

V16LYN I Page 1o of 8CORE COOLING Revision 17P SSFIFTH NOHOTTEST ITC LESS iGO TOSATaPage1 ofI1 V16N !T 1Page 2 of 8HEAT SINK Revision 17FRP4.LI~GO TOFRP-H.2PRESS IN INOIALL SG'S L.EBB THAN""GO TOFRP-H.3NAR RNG NLVL IN ALL LSO'S LESS '--'THAN 62 1YESJGOTOr FRP-H.4PRESS IN NALL SG'SLESS THAN,,,,,1075 P8I10YEGO TO-I FRP-4.5CSFSAT 1V16Page 3 of 88/29/2007 08:3 3FNP-I-CSF-O.4 INTEGRIT Revision 17I-f,' GO TOFRP.P.1JGO TOinininm m --t aFRP-.2CSFSATGO TOGOOTSATSATPagI 1 f2

[NI 1Page 4of 8FP1CSF-0. COTANMN Geson TOPRESS NO in in, -FRP-Z.1LESS ri- !THAN 5 YEs At LEAST ONE NOIPUMP RUNNING-- --OTI (FLOW>IODOOGPM) YES ,. 2I CTMT koI S~UMP LVL NCTMT [THAN 7.6 I=:LESS HTHAN 27 YsGO TOPSIG FRPZ.SUMP LVL.NLESSTHAN 7.6HFT.~GO TOFRP-Z.3BOTHCTMT RAD NLESS --hrTHAN 2 R/ LY1CSPage 1 of I 1I]IJIT9Vi16Page 5 of 88/29/2007 08:33 -FNP-2-CSF-0,2 CORE COOLING Revision 12GOTOoIP I m IIFRP-C.1HOTTEST NORP.CCORE EXITTHAN YETHANT790TCREXIT---,TC LSSTC HESSUBOO NO GO TOCOR PRP-C.30 EXIOT TCS "-iGRTR THAN Ei16" F 145"F}Page1 of 1 V1 6!]N IT 2Page 6 of 8FNP-2-CSF-O0.3 HEAT SINK Revision 12SGO TOFRP-K.1miTOTAL AFW NOIiFLOW TO I1 ALL SG'8 -,-,395 GPM EGO TO~FRP-HL2LVL IN AT IN NOLEAST ONE ALL SG'SSG GRTR --'-LESS THANTHAN 31% YES __ _______ 1129PSIG YES,[ GO TO! f FRP-H.3MiAR RNG [N]LVL IN ALLSGS8 LESS mmmTHAN 52% YESGO TO-I FRP-H.4PRESS IN NOALL 5G5S:ILESS THANmmg1075 P810 YESGO TOI r FRP-H.5CSFSATPage 1 of I V167 of 8FNP-2-CSF-O.4 IINTEGRITY Revision 12COLD LGTMEAUE('F GO TOW FRP-P,1ALL RCSPRESS- OTCL TEMP (IN m -ine e lRIGHT OF YES ,.,i_AL. RCS CL N OTTEMPS INGOTSLAST 60 MIN -,FRP..P.2GRTIR THAN--'---- L RCS CL N~ TEMP TEMPNO SALALATT600MINLESSR ThANTEM DCRNN OJ SALESTRTTAHAN GOT326' F SATCSFSATPage I of 2 Vi16*l Page 8 of 88/29/2007 08:33 I NJ J .FNP-2-CSF-0.5 CONTAINMENTReion1H CTMT TI _O__OPRESS NO R "P .L "I m-~-LESS H-- 11THAN 5 YES At LEAST ONE NORUNNING(FLOW1 000GPM)YESFnI *m WRP-Z.2SUMP LVL OICTMT- THAN 7.6[PRESS NLESS- SITHAN 27 YEs GO TOPSIG jjFRP-Z.1SUMP LVI NOLESS H.-THAN 7.6 YEFT.GO TOFRP-Z.31THAN2RJ [EST SATPage 1 of I V1 7Page 1 of 807/13/15 09:23:59 LOCATION FiUlSETPOINT: 1. Variable, as per FNP-1-RCP-252 HIRMSORIGIN: Any of the below listed Area, Process or Gaseous and HI-RADParticulate Monitors: R01, R02, R03, R04, RO5, R06,R07, R08,-R1OI RI1, R12, RI3,[T RI5, RI7A ________R17B, RIS8, R-I19, R20A, R20B, R21, R23A orR23B.PROBABLE 1 .High Radiation Level in the System, Area or at the Component monitored.2. The radiation monitors fail to a "High Radiation" condition on loss ofinstrument and/or control power that will result in actuation of associatedautomatic functions.AUTOMATIC ACTIONS;I. The following actions will occur if a High Radiation Alarm is actuated onthe associated Radiation Monitor.A. R14: (Plant Vent Gas) closes Waste Gas Release ValveI -G WD-HV-0 14.8. R16: None -abandoned in place per MDC 1040589501.C. R17A or B: (Component Cooling Water) closes QIPIYRCV3028CCW SRG TANK VENT.D. R18: (Liquid Waste Processing) closes Liquid Waste Release ValveI -L WP-RC V-0 18.E. R19: (Steam Generator Blowdown) isolates Steam GeneratorBlowdown Sample Lines.F. R23A :( Steam Generator Blowdown Processing) closes1-BD-FC V-I1152 SIG Blowdown Heat Exchanger Outlet FCV.G. R23B :( Steam Generator Blowdown Processing) closesI-BD-RCV-023B SQ BLOWDOWN PMP DISC.Page 1 of 15Page 1of 15Version 72.1 V1 7Page 2 of 807/13/15 09:23:59FNP-I-ARP-I .6LOCATION FHI.*RADIATION MONITOR TABLEI -p y pLOCATIONDETECTORFUNCTIONACTIONSR-IA Control Room (Unit I Area G-M (W) Perform Step____ Panel) _ _ _ _ _ __ 4.1R-I B Technical Support Center Area G-M ( W ) No input to__ _(Unit II Panel) R-IB _______ ____this alarmR-2 Containment (155' elev) Area G3-Mr ( W) Starts IPC dose Perform Steps____ ________integration 4.2R-3 Radiochemistry Lab (AB Area G-M (W~) Perform Step_ _ _ _ 139') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.3R-4 #3 Charging Pump (AB Area G-M (_W ) Perform StepI__ _ 00') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.4R-5* Spent Fuel Pool Room (AB Area G-M (_.W) Perform Steps_ _ _ _ 155') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 4.5R-6 Sampling Room (AB 139') Area G-M ( _W) Perform Step____ __ ____ ___ ___4.6R-7 In-core NIS Area (CTMT Area G-M ( W) Starts [PC dose Perform Steps____129', near Seal Table) ___________integration 4.7R-8 Drumming Station (AB Area G-M (W ) Perform Step_ _ _ _ 155') _ _ _ _ _ _ _ _ _ __4.8R-9 SG Sample Panel (Unit II Area G-M ( W ) No input toPanel) (AB 139') ___ _____this alarmR-0 Penetration Room Filtration APD Beta Scint Perform StepDischarge (AB 155') ____**(GA-ES) 4.9R-I 1

Containment Atmosphere APD Beta Scint Perform Step(AB 121') **__ (GA-ES) _______4.10*Technical Specification related**General Atomics Electronic SystemsPage 5 of 15 Vrin7.Version 72.1 V17Page 3 of 807/13/15 09:23:59FNP-1-.ARP-1 .6LOCATIONFHRADIATION MONITOR REFERENCE TABLE (cont)RELOCATION TYPE~ DETECTOR FUJNCTION ACTIONSR- 12" Containment Atmosphere Gas Beta Scint Perform Step____(AR 121') ___ **(OA-.ES) ________4.11lR-1 3 Waste Gas Compressor Gas G-M ( _W) Perform StepSuction (AB 100' WGC 4.12Valve Room) _________________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform StepODCM ________ __4.13R- i 5A Condenser Air Ejector Gas G-M ....Perform StepODCM Discharge Header (TB 155') 4.14R-I 5B* Condenser Air Ejector Gas G-M (Eberline) Perform Step(Intermediate Range) (T 4.15R-I 5C* Condenser Air Ejector Gas Ion Chamber Perform Step____(High Range) (TB 189') (berline) _______4.15R-1 7A Component Cooling Water Liquid Scint. ( W) Closes CCW Perform Step(CCW H-x Room) surge tank vent 4.16_______ ~~(RCV-3028) ______R-17B Component Cooling Water Liquid Scint. Closes CCW Perform Step(CCW Hx Room) surge tank vent 4.16______ _____ ___________(RCV-3028)R-1 8 Waste Monitor Tank Pump Liquid Scint. ( W) Closes RCV-1 8 Perform StepODCM Discharge (AB 121' at the 4.17______Batching Funnel) _____R-19 Steam Generator Liquid Scint. (YWL) Isolates sample Perform StepBlowdown/Sample (AR lines 3328, 4.1 8____139') _______3329, 3330 ______R-20A Service Water from Liquid Scint. ( W) Perform StepContainment Coolers A and 4.19B (AB 121' BTRS Chiller______ Room)__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R-20B Service Water from Liquid Scint. ( _W) Perform StepContainment Coolers C and 4.19______D (AB 121') ____________ __ _____*Technical Specification related**General Atomics Electronic SystemsPage 6 of15 Vrin7.Version 72.1 V1 7Page 4 of 807/1 3/15 09:23:59FNP-I-ARP-1 .6LOCATION FillRADIATION MONITOR REFERENCE TABLE (cont)RE LOCATION TYP DIETECTR FUNCTON ACTIONSR-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____ ____________ ____(Victoreen) 4.20R-22 Plant Vent Stack Gas G-M (_W Perform StepODCM (AB 155') -)_______________ 4.21R-23A SG Blowdown Surge Tank Liquid Scint. (__) Closes Perform StepInlet (AB 130') ____FCV-1152 4.22R-23B SG BLOWDOWN PMP Liquid Scint. ( __i) Closes Perform StepODCM DISC (AB 130') ___ _____RCV-23B 4.22R-24A* Containment Purge (AB Gas Scint. Closes No input to155') containment this alarmpurge supply &exhaust dampers2866C & 2867C____________ _______and 3198A &DR-24B* Containment Purge Gas Scint. Closes valves: No input to(AB 155') (Victoreen) 2866D &2867D, this alarm3196,3197,____________ _______3198B & CR-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input toR-25B* (AB 184') (Victoreen) supply and this alarme~xhaust fans;closes SEPH-VAC supplyand exhaustdampers; startsassociated trainsof penetration_____________ __ _ ________room filtration. ____R-27A* Containment (High Range) Area Ion Chamber No input to_____ _____________ ____(Victoreen) _ ______this alarmTechnical Specification relatedPage 7 of 15 Vrin7.Version 72.1 07/13/15 09:41:15 1F~~i~ NP-2-ARP-1.6 Page 5of 8LOCATION .IillSETPOINT: 1. Variable, as per F'NP-2-RCP-252ORIGIN: Any of the below listed Area, Process or Gaseous andParticulate Monitors: ROI!B, R02, R04, R05, R06,R07, RO8, R09, RI I, R12, R 13, -R'4 R15,R17A, RI7B, RIB, R19, R20A, R20B[ R21, R224R23A or R23BPROBABLE CAUSERMSHI-RADI. High Radiation Level in the System, Area or at the Component monitored.I2. The radiation monitors fail to a "'High Radiation-"" condition on loss ofinstrument and/or control power that will result in actuation of associatedautomatic functions.AUTOMATIC ACTION1. The following actions will occur if a High Radiation Alarm is actuated onthe associated Radiation Monitor.a) R14: (Plant Vent Gas) closes Waste Gas Release Valve 2-GWD-HV-0 14.b) R16: (Boron Recycle System) diverts 2-C VC-RC V-016 RecycleEvaporator discharge from Reactor Makeup Water System to theRecycle Evaporator Demineralizer.c) RI7A or B: (Component Cooling Water) closes 2-CC W-RC V-3028CCWN SRG TANK VENT.d) R I8: (Liquid Waste Processing) closes Liquid Waste Release Valve2-LWP-RCV-0I18.e) RI9: (Steam Generator Blowdown) isolates Steam GeneratorBlowdown Sample Lines.t) R23A: (Steam Generator Blowdown Processing) closes2-BD--FCV-1 152 S/G Blowdown Heat Exchanger Outlet FCV.g) R23B: (Steam Generator Blowdown Processing) closes2-BD-RCV-023B SGBD DISCH TO ENVIRONMENT.Page 1 of 13 Vrin6.Version 61. i SNIT 207/13/15 09:41:15Vi17FNP-2-ARP-I.6 Page 6 of 8LOCATION FHilOPERATOR ACTION (cont)4. In addition to the general actions perform steps indicated in the "ACTIONS"column of the following table. (Some of the radiation monitors included in thetable do not input into this alarm but are included for reference).RADIATION MONITOR REFERENCE TABLECRE LO:CATION TYPE DETECTOR FUNCTION ACTIONSR- 1A Control Room (Unit I Area G-M ( W) No input toPanel) _______this alarmR- lB Technical Support Center Area G-M ( W) Perform Step(Unit 1] Panel) R-l 1B_________ 4.1R-2 Containment (155' elev) Area G-M ( W) Starts IPC dose Perform Steps___ __ ___ __ ___ __ _ _ __ __integration 4.2R-3 Radiochemistry Lab (AB Area G-M ( W) No input to139') __________this alarmR-4 #3 Charging Pump (AB Area G-M (W) Perform Step100') _____ ________4.3R-5* Spent Fuel Pool Room (AB Area G-M (Wj) Perform Steps155') _ _ _ _ _ _ _ _ _ _ 4.4R-6 Sampling Room (AB 139') Area G-M ( W) Perform Step____ ___ ____ ___ ____ ___ ___ ___ ____ ___4.5R-7 In-core NIS Area (CTMT Area G-M ( W) Starts IPC dose Perform Steps129', near Seal Table) ____integration 4.6R-8 Drumming Station (AD Area G-M ( W) Perform Step155') __ _ _ _______4.7R-9 SG Sample Panel (Unit II Area G-M (W) Perform StepPanel) (AB 139') 4.8R- 10 Penetration Room Filtration APD Scint. Perform Step____Discharge (AD 155') (Victoreen) 4.9R- 11

Containment Atmosphere APD) Scint. Perform Step____(AB 121') ____(Victoreen) _______4.10**Technicail Specification relatedPage 4 of 13Page 4of 13Version 61.1

~k J. ~'V1 7FNP-2-ARP-1.6 Page 7 of 807/13/15 09:41:15LOCATION FHilRADIATION MONITOR REFERENCE TABLE (cont)RE. LOCATION TYPE DETECTO FU[NCTION ACTIONSR- 12* Containment Atmosphere Gas G-M ( W) Perform Step(AB 121') _____4.11R-13 Waste Gas Compressor Gas O-M (W) Perform StepSuction (AB 100' WGC 4.12Valve Room) ________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform StepODCM ___________________ __4.13R- 15A Condenser Air Ejector Gas G-M Perform StepODCM Discharge Header (TB 155') 4.14R-15B* Condenser Air Ejector Gas G-M (Eberline) Perform Step(Intermediate Range) (TB3 4.15189') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R .15C* Condenser Air Ejector Gas Ion Chamber Perform Step(High Range) (TB 189') (Eberline) 4.15R-17A Component Cooling Water Liquid Scint. (W ) Closes CCW Perform Step(CCW H-x Room) surge tank vent 4.16__________________(RCV-3028) _____R-17B Component Cooling Water Liquid Scint. Closes CCW Perform Step(CCW Hix Room) surge tank vent 4.16_________________ _____ _________ RCV-3028)R- 18 Waste Monitor Tank Pump Liquid Scint. (W ) Closes RCV- 18 Perform StepODCM Discharge (AB 121' at the 4.17_______Batching Funnel)R-19 Steam Generator Liquid Scint. ( W) Isolates sample Perform StepBlowdown/Sample (AB lines 3328, 4.18139') ___ _____ __3329, 3330R-20A Service Water from Liquid Scint. ( W) Perform StepContainment Coolers A and 4.19B (AB 121' BTRS Chiller_____Room) _________________*Technical Specification relaedPage 5 of 13 Vrin6.Version 6 I. 1 UN1IT 2V1 7FNP-2-ARP-I1.6 Page 8 of 807113115 09:41:15LOCATION .TLRADIATION MON1TOR TABLE (cont)RELOCATION IX DETECTOR FUNCTION ATIOQNSR-20B Service Water from Liquid Scint. ( W) Perform StepContainment Coolers C and 4.19______D (AB 121')______R-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____(Victoreen) 4.20R-22 Plant Vent Stack Gas G-M ( W) Perform StepODCM (AB 155') 4.21R-23A SG Blowdown Surge Tank Liquid Scint. ( W) Closes Perform Step____Inlet (AD 130') ____ _______FCV-! 152 4.22R-23B SGBD DISCH TO Liquid Scint. ( W) Closes Perform StepODCM ENVIRONMENT RCV-23B 4.22_______ (AB 130')________ ________ _ _ _ _ _ _R-24A* Containment Purge (AD Gas Scint. Closes No input to155') containment this alarmpurge supply &exhaust dampers2866C & 2867C____ ________and 3198A & _____R-24B* Containment Purge Gas Scint. Closes valves: No input to(AD 155') (Victoreen) 2866D &2867D, this alarm3196, 3197,_____3198B &CR-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input toR-25B* (AD 184') (Victoreen) supply and this alarmexhaust fans;closes SFPHVAC supplyand exhaustdampers; startsassociated trainsof penetrationroom filtration.*Teehnical Specification relatedPage 6 of 13Page6 o 13Version 61I.1I V18Page 1 of 3FNP-I-ARP-I.1207/13/15 08:32:48 -SETPOINT:1.2.3.0.01lgSystem Health RelayAlarm Relay 0LOCATION M~~SEISMICPANELALARMORIGIN: 1. SSA-3 Solid State Accelograph(NIH 11NGSI2507G)2. System Health Relay (8 inputs)* Recorder memory usage exceeding 80%* Failure of recorder(s) to respond to pollingfrom central controller.* Hardware failure* Recorder high temperature* Failure of recorder(s) to respond to controllerduring startup.* Communication problem.* DC power loss on alarm panel.* AC power loss on recorder(s).3. Alarm relay 0 (From channel 1 recorder, used forfunctional testing only).PROBABLE CAUS1. Seismic event.12. Operating Basis Earthquake (OBE) exceeded.I3.4.5.Seismic Panel loss of power.Instrument malfunction.Seismic finctional testing in progress.AUTOMATIC ACTION1. The monitoring system remain on at all times continuously monitoringthe signals from the acceleration sensors.2. When a setpoint is exceeded, the system' retrieves the time history datafrom storage and automatically performs the preprogrammed calculationsfor operator review.3. The system printer provides print and plot copies of the results for recordand review.El[]ElPage I of 15 Vrin6.Version 63.1 07/13/i5 08:33:15Vi18Page 2 of 3FNP-1-ARP-I1.12LOCATION MK5OPERATOR ACTIONS CONTINUEDACTION EXPECTED3.3 Record and compare the seismicpanel printout channel 1, 2 and 3Spectral Acceleration calculatedvalues, Spectral Velocity calculatedvalues and Computed CAV values tothe Spectral Acceleration designvalues, Spectral Velocity designvalues and CAV Design Limit Valueson Table ! "~Operating BasisEarthquake Exceedance (OBEE)Limit for Determination of PlantShutdown Requirements".IRESPONSE NOT OBTAINED3.4 Check the following:CAV Design limit value has NOTbeen exceeded.*Based on operator walkdowns noplant significant damage is found.3.4.1 JF either unit tripped, THENconduct a post trip review andrestart as appropriate.3.4 IF_ any of the following has occurred:* The Spetral Acceleration design valuehas been exceeded,o_.R* The Spectral Velocity design value hasbeen exceeded,_OR* Significant plant damage is found duringoperator walkdownsTHEN OBEE Criteria has been exceeded.3.4.1Generate a Condition Report to referto FNP- I-ETP-4580 and documentthe event.3.4.2 Generate a Condition Report torefer to FNP-I-ETP-4580 anddocument the event.3.4.2 Proceed to step 4.3.4.3 Proceed to step 5.Page 4 of 15 Vrin6.Version 63.1 07/13/15 08:34:29 A l 1 NP-I-AP-1.1LOCATION M15TABLE IOPERATING BASIS EARTHQUAKE EXCEEDANCE (OBEE) LIMITFOR DETERMINATION OF PLANT SHUTDOWN REQUIREMENTSResoonse Soectr Analysis for..Free Field MeasurementChannel 1: [L"~S1Computed CAV = * ..g-sec, Limit =0.160 g-sec"PSA Limit = 0.200 g ", OBE SV Limit =15.240 Damping = 0.050Spectral acceleration exceeded OBE Design criteria at

frequencies.Spectral acceleration greater than 2/30OBE Design criteria at

frequencies.Spectral velocity exceeded OBE Design criteria at

frequencies.Channel 2: I'V-UP1Computed CAV -* ....g-sec, CAV Limit = 0.160 g-sec'*OBE PSA Limit -0.200 g**, OBE SV Limit ,,15.240 cm/sec, Damping =0.050Spectral acceleration exceeded OBE Design criteria at

frequencies.Spectral acceleration greater than 2/30OBE Design criteria at.._* frequencies.Spectral velocity exceeded OBE Design criteria at....2* frequencies.Channel 3: FT=W1Computed CAV =

g-sec, CAV Limit = 0.160 g-sec"°OBE PSA Limit =0.200 g"*, OBE SV Limit = 15.240 cm/sec, Damping = 0.050Spectral acceleration exceeded OBE Design criteria at______ frequencies.Spectral acceleration greater than 2/30OBE Design criteria at

frequencies.Spectral velocity exceeded OBE Design criteria at frequencies.Calculated by Seismic Monitor. Any exceedances are exceedances of the system setupvalues per Table 2 and do not necessarily mean OBEE limits have been exceeded.oe The CAV Design Limit is 0.16 g-s but Table 2 -OBE Limit Value shows a limit value of0.0 g-s so the Farley Nuclear Plant OBE Spectra would control the OBE system alarm.O 0.20g is the EPRI OBE Limit Value (OBEE). The monitoring system will accept only onevalue at a time for the OBE limit Value. The recommended monitoring system setup (Ref'.Table 2 -OBE Limit Value) shows a limit value of 0.05g horizontal and 0.033g vertical sothe Farley Nuclear Plant OBE Spectra would control the OBE system alarm.Page 13 ofI Veson6.Version 63.1 V19Page 1 of 3RCS Specific Activity3.4.163.4 REACTOR COOLANT SYSTEM (RCS)3.4.16 RCS Specific ActivityLCO 3.4.16APPLICABILITY:The specific activity of the reactor coolant shall be within limits.MODES 1 and 2,MODE 3 with RCS average temperature (Tavg) > 500°F.ACTIONS ___________ _______CONDITION REQUIRED ACTION COMPLETION TIMEA. DOSE EQUIVALENT----------------Noe-------1-131 > 0.5 pCi/gm. LCO 3.0.4c is applicable.A.1 Verify DOSE Once per 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sEQUIVALENT I-131within the acceptableregion ofFigure 3.4.16-1.ANDA.2 Restore DOSE 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months sEQUIVALENT 1-131 towithin limit.B. Gross specific activity of B.1 Be in MODE 3 with 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sthe reactor coolant not Tavg < 500°F.within limit.Farley Units 1 and 23.4.16-1Amendment No. 170 (Unit 1)Amendment No. 163 (Unit 2)

Vi19Page 2 of 3RCS Specific Activity3.4.16ACTIONS_________ ___CONDITION REQUIRED ACTION COMPLETION TIMEC. Required Action and C.1 Be in MODE 3 with 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sassociated CompletionTag<50FTime of Condition A notTag<50Fmet.O._RDOSE EQUIVALENTI-131 in the unacceptableregion of Figure 3.4.16-1.SURVEILLANCEREQUIREMENTS _______SURVEILLANCE FREQUENCYSR 3.4"16.1 Verify reactor coolant gross specific activity I10E .~/g.ten accordance withsrelacFrequency ControlProgramSR 3.4.16.2 ---NOTE---------------........Only required to be performed in MODE 1.Verify reactor coolant DOSE EQUIVALENT 1-131 In accordance withspecific activity < 0.5 IpCi/gm. the SurveillanceFrequency ControlProgramANDBetween 2 and6 hours after aTHERMALPOWER changeof > 15% RTPwithin a 1 hourperiodFarley Units 1 and 23.4. 16-2Amendment No. 185 (Unit 1)Amendment No. 180 (Unit 2)

V19Page 3 of 3RCS Specific Activity3.4.16E0U275250225200175150125.__'- -Operation_ _ .. +:_::~i- J:1 1_+?[]i. ..EI.NK.. .Acceptable ; ++ 5 -+ -* + -575. ... Operatin --50,2 5 ,. ......0 ..., '. + : + ._ L .+ ' + : + ....20 30 40 5O 0070 80 90 100Percent of RATED THERMAL POWERFigure 3.4.16-1DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit VersusPercent of RATED THERMAL POWER with the Primary Coolant SpecificActivity > 0.5 jiCi/gm DOSE EQUIVALENT 1-131.Farley Units 1 and 23.4. 16-4Amendment No. 147 (Unit 1)Amendment No. 138 (Unit 2)

V20Page 1 of 1RCS Operational LEAKAGE3.4.133.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGELCO 3.4.13RCS operational LEAKAGE shall be limited to:a. No pressure boundary LEAKAGE;b. I gpm unidentified LEAKAGE;c. 10 gpm identified LEAKAGE; andd. 150 gallons per day primary to secondary LEAKAGE through anyone steam generator (SG).APPLICABILITY: MODES 1, 2, 3, and 4.ACTIONS____________ _____ ___CONDITION REQUIRED ACTION COMPLETION TIMEA. RCS operational A.1 Reduce LEAKAGE to 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sLEAKAGE not within limits within limits.for reasons other thanpressure boundaryLEAKAGE or primary tosecondary LEAKAGE.B. Required Action and 8.1 Be in MODE 3. 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sassociated CompletionTime of Condition A not ANmet.8.2 Be in MODE 5. 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months sPressure boundaryLEAKAGE exists.Primary to secondaryLEAKAGE not within limit.I1Farley Units I and 23.4.13-1Amendment No. 163 (Unit 1)Amendment No. 156 (Unit 2)

V21Page 1 of 1ESFAS Instrumentation3.3.2Table 3.3,2-1 (page 2 of 4)Engineered Safety Feature Actuation System InstrumentationAPPLICABLEMODES OROTHERSPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIPFUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT2. Containment Spraya. Manual Initiation 1,2,3,4 2 B SR 3.3.2.6 NA NAbi. Automatic Actuation 1.2,3,4 2 trains C SR 3.3.2.2 NA NALogic and Actuation SR 3.3.2.3Relays SR 3.3.2.8Pressure SR 3.3.2.4High -3SR 3.3.2.7SR 3.3.2.93. Containment Isolationa. Phase A Isolation(1) ManualInitiation(2) AutomaticActuation Logicand ActuationRelays(3) Safety Injectionb. Phase B Isolaton(1) ManualInitiation(2) AutomaticActuatio LogicandAcutnRelays1,2,3,41,2,3,422 trainsB SR 3.32..6C SR 3.3.2.2SR 3.3,2.3SR 3.32.8NANANANARefer to Function 1 (Safety Injection) for all initiation functions and requirements.1,2,3A41.2,3,422 trainsB SR 3.3.2.6C SR 3.32.2SR 3.3 2.3SR 3.3 28E SR 3.3.2.1SR 3.3.2..4SR 3.32.7SR 3.3,2-9NANANANA(3) ContainmentPressureHlgh -31.2,34S 28.3 psig 5 27 psigFadley Units I and 23.3.2-10Amendment No. 185 (Unit 1) iAmendment No. 180 (Unit 2) I Edwin I. Hatch Nuclear Plant Units 1 and 2License Amendment Request for Changes toEmergency Action Level Schemes to Adopt NEI 99-01 Rev. 6and to Modify Radiation Monitors at Farley Nuclear PlantEnclosure 4Hatch EAL Verification and Validation Documents Hatch EAL V&V Documentation IndexV&V# ..'Description I' IC [Threshold'RCS Modes/Temperatures -TS Reference (Table 1.1I-I) EAL Basis Section 1.41 RCS Cold Shutdown Temperature reference (212 OF) t CA3 (1)___tj CU3 J (1)Radiation Monitor Calculations:1/2D1 1-P601 (feeding 1/2D 11-R63 1)1D11l-P007 (feeding 1D11-R631)Calc SMiNH-13-021 Rev IRG I(1)RS1 (1)RA1(1)2Radiation Monitor Calculations: 1D11-K604 RU1 (1)1D 11-K6051D11-K619 A(B)1D1 l-K600 A(B)2D1 1I-K6042D 11-K6052D1 1-K636 A(B)Ca/c SMNH-13-021 Rev 1Radiation Monitor Information: RU2 (1)b1D21-K601 A 2D21-K601 A1D11-K601 D 2D21-K601 M1D21-K601 E 2D21-K601 E1D21-K601 M 2D21-K611 K2D21l-K611 LCa/c SMNH-13-021 Rev 1 _____Radiation Monitor Calculation: CG1 (1)bDWRRM 1/2D 11-K621 A(B) CS 1 (2)bCa/c SMNH-13-021 Rev 1 ______Primary Containment Rad Monitor Calculations FCB L4A FCB L4ADWRRM RCSB L4A RCSB L4ACa/c SMNH-13-021 Rev 1 CB PL4A CB PL4AOffgas Pre-Post Treatment Reading Calculation FCB L5A FCB L5ACa/c SMNH-13-021 Rev 1I_____Drywell Fission Product Monitor Reading CalculationCa/c SMNH-13-021 Rev 1RCSB L5ARCSB L5AODCMITS Reference to Site Boundary RG1 (2)(3)3RS1 (2)(3)RAl (2)(3)(4)Alarm Response Procedure Reference RA2 (2)Annunciator Displays:1D21-K601 A 2D21-K601 M1D21-K601 B 2D21-K601 E1D21-K601 D 2D21-K611 K1D21-K601 E 2D21-K611 L1D21-K601 M 2D11-K609 A-DIDII-K609 A-D 2D11-K611 A-D1D1Il-K611 A-D 2D 11-K634 A-D2D21-K601 A 2D11-K635 A-DAlarm Response Procedure Reference Control Room Rad RA3 (1)Monitor [Annunciator Display: 1D21-K600 B(C)] ____________Alarm Response Procedure Reference RU2 (1 )aAnnunciator Display: Spent Fuel Storage Pool Level Low6 654-022-1Spent Fuel Storage Pool 'Level Low654-022-2 ______2/22/20 16Page 1 of 3 Hatch EAL V&V Documentation IndexV&V# *Description ' IlC ThresholdRPV Level Indications/Displays (-155" TAF) CG1 (1)a7CS1 (2)bFCB PL2A FCB PL2ACaic SMNH-13-021 Rev 1 RCSB L2A RCSB L2ARPV Level Indication/Display (-35"); Level 2 Actuation CS 1 (1)b8 setpoint info (required for CA1/CS1 is 6" below setpt) CAl (1)Caic SMNH-13-02I Rev 1Drywell Floor Drain Sumps; Drywell Equipment Drain CG1 (2)bSumps; Torus; Torus Room Sumps; RB Floor Drain CS 1 (3)bSumps; TB Floor Drain Sumps; Rad Waste Tanks CA1 (2)breferences cui (2)bH2 Concentration (> 6%) and 02 Concentration (> 5%) -CGI (2)c10 calculation/reference CB PL1B CB PL1BCale SMNH-13-021 Rev 111 Primary Containment Pressure Reference (> 56 psig) CG1 (2)cCalc SMNH-13-021 Rev]1 CB PLIA CB PL1ASecondary Containment Rad Monitors > Max Safe values CG1 (2)c12 34AB-T22-O03-1/2 CBL3A CBL3ASecondary Containment Rad Monitors > Max Normal RCSBPL3A RCSBPL3AValues 34AB-T22-O03-1/24160 VAC Essential Buses Description CA2 (1)CU2 (1)a13 SG1 (1)aSG8 (1)aSS1 (1)SA1 (1)SU1 (1)14 RCS Pressure indications CA3 (2)DC System Information CU4 (1)15 SO8 (1)bSS8 (1)16 ISFSI TS/Dose Reading Calculation E-HU1 (1)SMHN-13-021 Rev 117 Primary Containment Pressure > 1.85 psig reference RCSB LIA RCSB L1A17 Calc SMNH-13-021 Rev 1Secondary Containment Temps -> Max Normal values RCSBPL3A RCSBPL3A18 34AB-T22-O03-1/2Secondary Containment Temps -> Max Safe values CBL3A CBL3A34AB-T22.-O03-1/2Seismic Indications (OBE): HU2 (1)19 [Annunciator Display (657-048/657-066)]12.7 Hz amber light12.7 Hz red light20 Table H2 Basis HU4 (1)b (2)b34AB-X43-O01-1 (2)21 Minimum Steam Cooling RPV Water Level SG1 (1)bSS5 (1)c22 Heat Capacity Temperature Limit (HCTL) Curve SS5 (1)cPretreatment Radiation Monitor Reading SU3 (1)23 TS3.7.6Caic SMNH-13-021 Rev 1RCS sample activity -Tech Spec Value SU3 (2)24 TS3.4.62/22/2016Page 2 of 3 Hatch EAL V&V Documentation IndexIV&V# I> Description I IC IThreshold'RCS Operational Leakage -Tech Spec Values SU4 (1)(2)25 TS3.4.42/22/2016Page 3 of 3 VlPage 1 of 1Definitions1.1Table 1.1-1 (page 1 of 1)MODESAVERAGE REACTORCOOLANTREACTOR MODE TEMPERATUREMODE TITLE SWITCH POSITION (°F)1 Power Operation Run NA2 Startup Refuel(a) or Startup/Hot NAStandby3 Hot Shutdownl(a) Shutdown > 2124 Cold Shutdown(a) Shutdown < 2125 Refueling(b) Shutdown or Refuel NA(a)(b)All reactor vessel head closure bolts fully tensioned.One or more reactor vessel head closure bolts less than fully tensioned.HATCH UNIT 11.1-6HATC UNI I 11-6Amendment No. 195 5A~NYErn~r,,.&'~i.v I~W*d4V2Southern Nuclear Design CalculationSeNL1589Enclosure 3ICalculation Number: SMNH-13-021Plant:Hatch Nuclear Plant Unit:O 1 0" 2 0] 1 & 2 Discipllne:MechanlcalTlfite:Subject EmergencyNEI 99-01 Rev 6 EAL. Calculations Action Level SetpointsPurpose I Objective:Document Emergency Action Level Values to support conversion to NEI 99-01 Rev 6System or Equipment Tag Numbers:N/AContentsTopic Page Attachments # of(Computer Printouts, Technical Papers, Pages__________________Sketches, Correspondence)Purpose 1 A -SNC EP Concurrence 1Criteria 1 B -Reserved 0Conclusions 3 C -Fuel Clad' Loss 4.A Threshold Calculation 19Design Inputs 5 D -Fuel Clad Potential Loss 5.A Threshold 1Assumptions ,10 CalculationReferences 14 E -RCS Loss 4.A Threshold calculation ... 16Method of Solutions 18 F -RCS Loss 5.A Threshold Calculation 6Body of Calculation .... ....23 G -containment Potential Loss 4.A 1__________________Threshold Calculation______________H -Steam Table Validation 5I- RS1 Threshold Calculation ______ 25Toa fPgsicuigJ -CG1 Threshold Calculation 4cover sheet & Attachments: 189 K -CG1 Threshold,,,Calculation 15L -E-HU1 Threshold Calculation 16M -RA1 Threshold Calculation 18Nuclear Quality Level0 -Safety-Related li Safety Significant 0 o-Safety -SignificantVersion RecordVersion Originator Reviewer' Approval I Approval 2I, ~ dui= Name P.*HW 4Name Pri~ed Na. atiCalculation of EAL Thresholds. wb..d l-Lto support NEI 99-01 Rev. 6Notes: Key calculationNMP-ES-039NMP-E-039NMP-ES-039-001 V3Page 1 of 2HNP ODCMd. The CHAN4NEL CHECK s hall consist of verifying sampler flow an d the presence ofthe*collection device (i.e., partic~ulate filteror charcoal cartridge, etc.) at the weekly o ,43.1.2 Gas eous Effluent Dose Rate ControlIn accordance with Technical Sp ecif'ication~s 5.5.4.c and 5.5.4.g, the licensee shall conducto perations so that th e dos e rates due to radioactive materials rel eased in gaseous effluentsfrom the siteto areas at and beyondthe SITE BOUNDARY (see Figure 10-1) are limited asfollows:a. For noble gase.-s: Less than or equalto a dose rate of to the total body andless than or equal to a dose rate of 3000 /to the skin, andb. For Iodine-131, Iodine-133, tritum, and forall radionuclides in partioulate forin withhalf-lives greater than 8 days: Less than or equal to a dose rate of 1500 j~r, j~rn to anyorgan.3.1.2.1 ApplicabilityThis limit applies at all times.3.1.2.2 ActionsWith a dos e rate due to radioactive material released in gaseous effluents exceeding the limitstated in Section 3.1.2, immediatelydecrea~se the relea~se rate to within the stated limit.Entry into an Operational Mode or other specified COM)ITION shall be made if, as a minimum,the requirements ofTedinical Sp eafications LCO03.0.4 are met.3.1.2.3 Surveillance RequirementsThe dose rates dueto radioactive materials in areas at or beyondth e SITE BOUNDARY due torel eases of gaseous effluents shall be determinedto be withinthe above limits, in accordancewith the methods and procedures in Section 3.4.1, by obtaining representative samples andperforming analyses in accordance with the sam pling an d analysis program specifed inTable 3-3.3.1.2..4 BasisThis control is provided to ensure that gaseous effluent dose rates will be maintained within thelimits that historicallyhave provided reasonable assurance that radioactive material disdiargedin gas eous effluents wilN not result in a d ose to a MEMBER OF THE PUBLIC in anUNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceedingthe limitsspecified inAppendix I ofI10CFR Part 50, while allowing operational fl exibiity for effluentreleases. For MEBROFTH-E PUBLIC who may at times be withinthe SITE BOUNDARY,the occupancy ofth e MEBE OFTHE PUBLIC will be sufficiently low to compensate for anyincrease in th e atmospheric diffusion factor above that for th e SITE BOUNDARY.3-6 Version 23 213 KeFPLOO PinAI FOUEUTB'mueaTeaPFcJif0)&Co V4Page 1 of 16SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) AGE 1 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 34AR-601-902-1 I 14.41H11-P601, ALARM PANEL 1EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE:04 15N/A SSM /PM: N/A DATE: N/AANNUNCIATOR RESPONSE PROCEDURES FOR IHII-P601 -ALARM PANEL 1ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-101-1 5.1 34AR-601-113-1 2.1 34AR-601-125-1 6.234AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.234AR-601-103-1 6.2 34AR-601-1 15-1 4.1 34AR-601-127-1 6.234AR-601-104-1 3.3 34AR-601-1 16-1 5.6 34AR-601-128-1 3.234AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.134AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.034AR-601-107-1 1.1 34AR-601-119-1 1.1 34AR-601-131-1 6.334AR-601-1 08-1 2.2 34AR-601-120-1 5.2 34AR-601-1 32-1 3.334AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.134AR-601-1 10-1 4.2 34AR-601-122-1 4.1 34AR-601-1 34-1 4.334AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.534AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0II NOE Approval signature on this page constitutes approval for all procedures listed above at theNOE revision indicated. Tab numbers in the back correspond to procedure sequence number.ILevel Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneN MP-AP-002 V4Page 2 of 16PAGE 2 OF 2SOUTHERN NUCLEARPLANT E.I. HATCHDOCUMENT TITLE:ARP'S FOR CONTROL PANEL 1H11-P601,ALARM PANEL 1DOCUMENT NUMBER: VERSION NO:34AR-601-902-1 I 14.4UNIT 11H 11-P601 -1601-101 601-102 601-103

601-104 601-105 601-106601-107 601-108

601-109

601-110 601-111 601-112601-113 601-114 601-115 601-116 601-117 601-118601-119 601-120 601-121 601-122 601-123 601-124601-125 601-126 *60-2 60-2 6119 6113601-125 601-1326 601-127 601-128 601-125 601-130RECORDSThere are no records generated from this procedure.COMMITMENTSNone* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on TRIP UNIT Label(s) at 1D21-P600 to provide across-reference for locating the device(s) in Abnormal and/or EOP Tables.Refer to 34AB-T22-003-1, Secondary Containment Control.NMP-AP-002 v.2.0 V4Page 3 of 161.0 IDENTIFICATION:ALARM PANE L 601-1_____ ___RX BLDG___ __ ___RADIATION___ __ _ _ __ ___HIGHDEVICE: SETPOINT:1D21-K601A, E, F, G, H, K, L, N, P, R, S, T, U, V, W, X, Y See 64C1-CAL-002-05.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED amber upscale light and high reading on individual indicator/trip units,on 1D21-P600, Area Radiation Monitoring Panel.5.1.1 Attempt to reset Trip Unit.5.2 IF Trip Unit will NOT reset, perform the following:5.2.1 Confirm monitor reading,by checking 1D21-R600, Area Radiation Monitor Recorder, panel 1~ H1-P600. (see channels below).5.2.2 Contact Health Physics to confirm radiological condition.5.2.3 REFER to 73EP-RAD-001-0, Radiological Event.5.2.4 Periodically monitor panel 1D21-P600,to ensure that no other channels in the Reactor Building are indicating high OR in alarm.5.2.5 Enter 34AB-T22-003-1, Secondary Containment Control.5.2.6 IF a radioactive release outside the Reactor Building is occurring, OR has occurred,enter 34AB-D1 1-001-1, Radioactive Release Control.LiLILiLiLiLiLiLi6.0 CAUSES:6.1 High radiation Trip on one or more of the following indicator/trip units:1 D21 R600CHANNEL TRIP UNIT LOCATION01 1 D21-K601A Reactor Head Laydown05 1D21-K601E Drywell Shield Plug06 1D21-K601F Tip Area07 1D21-K601G 130' NE Working Area08 1 D21-K601H 130' SW Working Area09 1 D21-K601K 158' SW Working Area10 1D21-K601L Rx Wtr Smpl Rack Area 158'12 1D21-K601N South CR0 Hydraulic Units13 1 D21-K601P North CR0 Hydraulic Units14 1D21-K601R CS & RHR S-E Diag.15 1 D21 -K601 S Equipment Access Airlock16 1 D21-K601T HPCI Turbine Area17 1 D21-K601U TIP Probe Drive Area18 1D21-K601V RCIC Equipment Area SW19 1D21-K601W CR0 Pump Room NW20 1 D21-K601X RB 203' Working Area21 1D21-K601Y CS & RHR N-E Diag.6.2 Malfunctions of one or more trio unitsSENSOR1D021-N002-11 D21-N002-51021 -N002-61021 -N002-71021 -N002-81 D21-N002-91021 -N002-1 01 D21-N002-121021 -N002-1 31 D21-N002-141021 -N002-1 51021 -N002-1 61 D21-N002-171021 -N002-1 81021 -N002-1 91 D21-N002-201 D21-N002-2134AB-T22-003-1ITEM NUMBER14111416910171221152213181962

07.0 REFERENCES

8.0 TECH. SPEC./TRM/ODCMIFHA:7.1 H-17854 -H-17859, H-19598 & H-i19599, ARM Sys. 021 Elem. N/A -Not applicable to this procedure34AR-601 -104-1Ver. 3.3MGR-0048 Ver. 5 V4Page 4 of 161.0 IDENTIFICATION:ALARM PANEL 601-1________REFUELING FLOORAREA RADIATION___ __ __ ___HIGHDEVICE: SETPOINT:1 D21 -K601 B, 1 D21 -K601 D See 64C1-CAL-002-02.0 CONDITION: 3.0 CLASSIFICATION:EQUIPMENT STATUSOne OR both of the Refueling Floor Area Radiation Monitors has 4.0 LOCATION:exceeded its setpoint.1H-P0Pae6015.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/trip unitson panel 1D21-P600. Li5.1.1 Attempt to reset trip unit. LI5.2 Confirm Control Room ventilation shifted to pressurization (Mode II),per 34SO-Z41-001-1, Control Room Air Conditioning System. LI5.3 IF trip unit will NOT reset, perform the following:5.3.1 Confirm monitor reading by checking 1D21-R600, Area Radiation Monitor Recorder,panel 1Hi11-P600. (see channels below) Li5.3.2 Contact Health Physics to confirm radiological condition in the affected area,evacuate area IF required. LI5.3.3 Periodically monitor panel 1D21-P600,to ensure that no other channels on the Refueling Floor are indicating high OR~ in alarm. Li5.3.4 Enter 34AB-T22-003-1, Secondary Containment Control. Li5.3.5 Refer to 73EP-RAD-001-0, Radiological Event. Li5.3.6 IF a radioactive release outside the Refueling Floor is occurring, OR has occurred,enter 34AB-D1 1-001-1, Radioactivity Release Control. Li6.0 CAUSES:6.1 High radiation causing one OR both of the following indicator/trip units:MONITOR CHANNEL TRIP UNIT LOCATION SENSOR02 1D21-K601B Refueling Floor Stairway 1D21-N002-204 1D21-K601D Refueling Floor 1D21-N002-46.2 Malfunction of trip unit.

7.0 REFERENCES

8.0 TECH. SPEC./TRMIODCM/FHA:7.1 H-17854 thru H-17859, H-19598 and H-19599, AreaRadiation Monitoring Sys. D21 Elem Diag N/A -Not applicable to this procedure34AR-601-1 10-1Ver. 4.2MGR-0048 Ver. 5 V4Page 5 of 161.0 IDENTIFICATION:__ALARMPANEL 601-1 __________ __ __ ___NEW FUEL__ __STORAGE AREA__ __ __RADIATION HIGHDEVICE: SETPOINT:1 D21-K601C 64CI-CAL-002-01 D21-K601M2.0 CONDITION: 3.0 CLASSIFICATION:2.1 Radiation level in vicinity of Spent Fuel Pool Demineralizer EQUIPMENT STATUSEquipment ARM has exceeded its setpoint 4.0 LOCATION:2.2 Radiation level in vicinity of Spent Fuel Pool & New Fuel Storage 1H11-P601 Panel 601-1ARM has exceeded its setpoint2.3 Loss of power to either of the above listed ARMs5.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/tripunits on panel 1D21-P600. LI5.1.1 Attempt to reset trip unit. LI!5.2 IF trip unit will NOT reset, perform the following:5.2.1 Confirm monitor reading by checking 1D21-R600, Area Radiation Monitor Recorder,on panel 1H1 1-P600. (see channels below) LI5.2.2 Contact Health Physics to confirm radiological condition in the affected area ANDevacuate area IF required. LI5.2.3 Periodically monitor 1D21-P600, panel, to ensure that no other channels on theRefueling Floor are indicating high OR in alarm. 135.2.4 Enter 34AB-T22-003-1, Secondary Containment Control. LI5.2.5 Refer to 73EP-RAD-001-0, Radiological Event. III5.3 If neither ARM is reading high, then at 1 R25-S064, confirm BRKR 9 is CLOSED. El5.4 IF an abnormal radioactive release is occurring OR has occurred,enter 34AB-D1 1-001-1, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation causing one or both of the following indicator/trip units to alarm:1D21-R600 POINT TRIP UNIT LOCATIONNUMBER SENSOR3 1D21-K601C, Spent Fuel Pool Demin Equip 1D21-N002C11 1D21-K601 M, Spent Fuel Pool & New Fuel Storage 1D21-NO02M6.2 Loss of power to ARM's

7.0 REFERENCES

8.0 TECH. SPEC./TRMIODCMIFHA:7.1 H-17854 & H-17856, ARM Sys. D21 Elem. Diag. N/A -Not applicable to this procedure34AR-601-127-1Ver. 6.2MGR-0048 Ver. 5 V4Page 6 of 16DOCUMNT TTLE:DOCUMENT NUMBER: VERSION NO:ARP'SALRFOR PAECONTROL4 PANEL 1H11-P601, 34AR-601-901-1 12.4EXPIATIN APROVLS:EFFECTIVEDATE: DEPARTMENT MANAGER DAK for Keith D. Lonq DATE 5-9-13 DATE:N/A SSM/PM N/A DATE N/A 5-15-15ANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601 -ALARM PANEL 4ARP NO. Ver, NO. ARP NO. Ver.NO. ARP NO. Ver. NO.34AR-601-401-1 0.4 34AR-601-413-1 0.4 34AR-601-425-1 4.434AR-601-402-1 3.4 34AR-601-414-1 3.3 34AR-601-426-1 3.534AR-601-403-1 3.5 34AR-601-415-1 1.5 34AR-601-427-1 1.334AR-601 -404-1 0.2 34AR-60 1-416-1 1.3 34AR-601 -428-1 4.634AR-601-405-1 7.1 34AR-601-417-1 4.6 34AR-601-429-1 2.234AR-601-406-1 7.3 34AR-601-418-1 3.3 34AR-601-430-1 0.234AR-601-407-1 1.5 34AR-601-41 9-1 0.2 34AR-601-431-1 1.134AR-601 -408-1 1.5 34AR-601 -420-1 4.5 34AR-601 -432-1 4.334AR-60 1-409-1 5.5 34AR-60 1-421-1 4.3 34AR-601 -433-1 0.134AR-601-410-1 2.2 34AR-601-422-1 3.5 34AR-601-434-1 2.134AR-601-411-1 3.6 34AR-601-423-1 3.6 34AR-601-435-1 034AR-60 1-412-1 4.5 34AR-60 1-424-1 2.5 34AR-601 -436-1 0INOTE Approval signature on this page constitutes approval for all procedures listed above at the IVersion indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneI V4Page 7 of 16UNIT 11H11-P601-4601-401 601-402 601-403 601-404 601-405 601-406601-407 601-408 601-409 601-410 601-411 601-412601-413 601-414 601-415 601-416 601-417 601-418601-419 601-420 601-421 601-422 601-423 601-424601-425 601-426 601-427 601-428 601-429 601-430601-431 601-432 601-433 601-434 601-435 601-436RECORDSNo Records are generated by this procedure.COMMITMENTSSNC1 9472, SNC5027 V4Page 8 of 161.0 IDENTIFICATION:ALARM PANEL 601-4 __________REFUELING FLOOR___ __ __ ___VENT EXHAUST___ __ __ __ ___RADIATION HI-HIDEVICE: SETPOINT:1D11-K611A thru D 18 mr/hr2.0 CONDITION: 3.0 CLASSIFICATION:EMERGENCYRadiation levels in the Refueling Floor Exhaust Duct exceed the 4.LOAINsetpoint.1H11-P601 Panel 60 1-45.0 OPERATOR ACTIONS:5.1 Confirm the annunciator by monitoring 1 D11-R607, Recorder, panel 1H11-P600. D]5.1.1 Monitor the R/F VENT EXHAUST RAD MON, 1 HI1-P606; IF only one trip unit is affected,attempt to reset the affected trip unit. Eli5.2 IF only one trip unit is alarmed, AND the unit is not malfunctioning,determine and correct the cause of the high high radiation. LI5.3 IF" the A AND B, OR the C AND D OR all channels of trip unit 1 D11-K61 1 are tripped,enter 31EO-EOP-014-1, SC-Secondary Containment Control, andperform concurrently with this procedure. Eli5.4 IF refueling is in progress, STOP refueling operations, andif possible, insert any withdrawn Control Rods. LI5.5 Evacuate personnel from the Refueling Floor. LI5.6 IF: refueling or fuel handling was in progress,ENTER 34AB-J11-001-1, Irradiated Fuel Damage During Handling. LII5.7 IF" an abnormal radioactive release is occurring,ENTER 34AB-D1 1-001-1, Radioactive Release Control. LI6.0 CAUSES:6.1 High radiation levels in the vent duct6.2 Trip unit failure, upscale or downscale

7.0 REFERENCES

8.0 TECH. SPECS./TRMIODCM/FHA:7.1 H-19551 through H-19566, H19578, H19584, & H19596, 8.1 Secondary ContainmentProcess Radiation Monitoring System Elem Diag Isolation Instr Table 3.3.6.2-134AR-601 -403-1Ver. 3.5 V4Page 9 of 161.0 IDENTIFICATION:ALARM PANEL 601-4 ___________ __ ___RX BLDG POT___ __ __ __ ___CONTAM AREA______-VENT RADN HI-HIDEVICE: SETPOINT:1 D11-K609A 1ID11-K609B 18 mr/hr1D1 1-K609C, 1 D1 1-K609D5.0 OPERATOR ACTIONS:5.1 Confirm annunciator by monitoring the radiation level on 1D11-R605, recorder, 1H11-P600. LI5.1.1 Monitor 1 D11-K609A, ID11-K609B, 1ID11-K609C, 1D1I-K609D, Reactor BuildingPotential Contaminate Area Rad Monitors, 1Hi 11-P606.IF only one trip unit is affected, attempt to reset the affected trip unit. Eli5.2 IF only one trip unit is alarmed AND the unit is not malfunctioning,determine and correct the cause of the high high radiation. LI5.3 IF the A AND B, OR the C AND_ D OR all channels of trip unit 1 D11-K609, are tripped,ENTER 31EO-EOP-014-1, SC-Secondary Containment Control. III5.4 IF an abnormal radioactive release is occurring,ENTER 34AB-D1 1-001-1, Radioactivity Release Control. LI6.0 CAUSES:6.1 Primary leakage

7.0 REFERENCES

8.0 TECH. SPECS./TRM/ODCM/FHA:7.1 H-19561, H-19564, H-19563, & H-19566, Process 8.1 Unit 1 T.S. 3.3.6.1Radiation Monitoring System Elem Diag 8.2 Unit 1 T.S. 3.3.6.27.2 H-16005, Reactor Building Vent System P&ID34AR-60 1-426-1Ver. 3.5 V4Page 10 of 16SOUTHERN NUCLEAR IDOCUMENT TYPE:IPLANT ElI. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) PAGE 1 OF 2DOCUMENT TITLE: NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 2H1 1-P601, ALARM PANEL 3 l 34AR-601-904-2 12.18EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER G. L. Johnson DATE 04/19/00 DATE:8/31/15N/A SSM /PM N/A DATE N/A _____ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601 -ALARM PANEL 3ARP NO VER. NO. ARP NO. VER. NO. ARP NO VER. NO.34AR-601 -301-2 3.1 34AR-601 -31 3-2 3.5 34AR-60 1-325-2 2.334AR-60 1-302-2 3.2 34AR-60 1-314-2 2.4 34AR-60 1-326-2 0.534AR-601-303-2 3.3 34AR-601-315-2 1.2 34AR-601-327-2 5.234AR-601 -304-2 3.2 34AR-60 1-316-2 0.2 34AR-60 1-328-2 2.234AR-601 -305-2 0.3 34AR-601 -317-2 2.1 34AR-601 -329-2 1.334AR-60 1-306-2 3.3 34AR-601 -318 SPARE 34AR-60 1-330-2 2.234AR-601-307-2 2.4 34AR-601-319-2 0.3 34AR-601-331-2 2.334AR-601-308-2 2.3 34AR-601-320-2 1.2 34AR-601-332-2 0.334AR-601-309-2 1.2 34AR-601-321-2 4.2 34AR-601-333-2 0.334AR-601-310-2 0.4 34AR-601-322-2 0.6 34AR-601-334 SPARE34AR60131 12 03 3AR-61-33-2 .3 4AR601 4.34AR-601-311-2 4.3 34AR-601-323-2 2.4 34AR-601-335-2 04.SNT:IApproval signature on this page constitutes approval for all procedures listed above at the !NOErevision indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneMGR-0002 VER. 8.1 V4of 16UNIT 22H11-P601 -3601-301 601-302 601-303 601-304 601-305

601-306601-307 601-308 601-309 601-310 601-311

601-312601-313 601-314 601-315 601-316 601-317 601-318601-319 601-320 601-321 601-322

601-323 601-324601-325 601-326 601-327 601-328 601-329 601-330601-331 601-332 601-333 601-334 601-335 601-336* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on Trip Unit Label(s) at 2D21-P600 to provide across reference for locating the device(s) in ABNORMAL AND/OR EOP Tables.Refer to 34AB-T22-003-2, Secondary Containment Control.RECORDSNo records are generated from this procedure.COMMITMENTSNONEMGR-0001 VER. 4 V4Page 12 of 161.0 IDENTIFICATION:ALARM PANEL 601-3-II--IIrREFUELING FLOORAREA RADIATIONHIGHDEVICE: SETPOINT:2D21-K601-A,E,M See 64CI-CAL-002-02D21-K61 1-K,L5.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light AND~ high reading on individual indicator/tripunits on panel 2D21-P600. LI5.1.1 Attempt to reset Trip Unit. LI5.2 IF 2D21-K601 A O._R M Tripped,THEN confirm Control Room ventilation shifted to pressurization (Mode II) per34SO-Z41-001-1, Control Room Ventilation System. LI5.3 IF Trip Unit will NOT reset, perform the following:5.3.1 Confirm monitor reading by checking 2D21-R600A, Area Radn Monitor Recorder,panel 2H1 1-P600 (see channel below) Lii5.3.2 Contact Health Physics to confirm radiological condition in the affected area,evacuate area IFrequired. LI5.3.3 Periodically monitor panel 2D21-P600 to ensure no other channels on the RefuelingFloor are indicating high OR in alarm. LI5.3.4 Enter 34AB-T22-003-2, Secondary Containment Control. LI5.3.5 IF a radioactive release outside the Reactor Building is occurring, OR has occurred,enter 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation causing a trip of one ORR more of the following indicator trip unitsMONITOR CHANNEL LOCATION SENSOR TRIP UNIT1 Reactor Head Layout Area 2D21-N002-A K601-A5 Dryer/Separator Pool 2D21-N002-E K601-E10 Spent Fuel/Fuel Pool Areas 2D21-N002-M K601-M21 Reactor Vessel Refueling Area 2D21-N012-K K61 1-K22 Reactor Vessel Refueling Area 2D21-N012-L K61 1-L6.2 Malfunction of trip unit

7.0 REFERENCES

8.0 TECH. SPECS./TRMIODCMIFHA:7.1 H-27805 thru H-27810 and H-27992, Area RadiationMonitoring Sys 2D21 Elementary Diagram 8.1 TRM Table T3.3.7-134AR-60 1-312-2Ver. 4.3MGR-0048 Ver. 5.0 A-GR7- 0AG-MGR-75-1101 V4Page 13 of 16SOUTHERN NUCLEAR )OCUMENT TYPE:PLANT ElI. HATCH lANNUNCIATOR RESPONSE PROCEDURE (ARP PAGE 1 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO:ARP'S FOR CONTROL PANEL 2HI11-P601, 34AR-601-901-2 l 12.1ALARM PANEL 4/EXPIRATION APPROVALS: IEFFECTIVEDATE: DEPARTMENT MANAGER DAK for Keith D. Long DATE 5-9-13 I DATE:N/A SSM/PM N/A DATE N/A 5-i5-I5ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601 -ALARM PANEL 4ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-401-2 0.3 34AR-601-413-2 1.2 34AR-601-425-2 3.434AR-60 1-402-2 4.1 34AR-60 1-414 Spare 34AR-60 1-426-2 6.334AR-601-403-2 5.4 34AR-601-415-2 1.0 34AR-601-427-2 2.334AR-60 1-404-2 0.3 34AR-60 1-416-2 0.5 34AR-60 1-428-2 5.534AR-60 1-405-2 8.1 34AR-60 1-417-2 4.3 34AR-60 1-429-2 3.134AR-60 1-406-2 8.3 34AR-60 1-418-2 1.2 34AR-60 1-430-2 0.334AR-60 1-407-2 3.6 34AR-60 1-419-2 1.1 34AR-60 1-431-2 2.134AR-601-408-2 1.0 34AR-601-420-2 6.3 34AR-601-432-2 4.334AR-601-409-2 5.3 34AR-601-421-2 4.3 34AR-601-433-2 1.434AR-601-410-2 2.3 34AR-601-422-2 5.4 34AR-601-434-2 3.034AR-601-411-2 4.5 34AR-601-423-2 4.4 34AR-601-435-2 1.134AR-601-412-2 0.4 34AR-601-424-2 2.3 34AR-601-436-2 0.1IINOTE Approval signature on this page constitutes approval for all procedures listed above at theI Version indicated. Tab numbers in the back correspond to procedure sequence number.FILevel Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO None V4Page 14 of 162 OF2SOUTHERN NUCLEARPLANT E.I. HATCHDOCUMENT TITLE: 'DOCUMENT NUMBER: VERSION NO:ARP'SALRFORpAECONTROL4 PANEL 2H11-P601, 34AR-601-901-2 1 12.1UNIT 22H1 1-P601 -4601-401 601-402 601-403 601-404 601-405 601-406601-401 601-408 601-409 601-410 601-411 601-412601-413 601-414 601-415 601-416 601-417 601-418601-419 601-420 601-421 601-422 601-423 601-424601-425 601.426 601-427 601-428 601-429 601-430601-431 601-432 601-433 601-434 601-435 601-436RECORDSThere are no records generated from this procedure.COMMITMENTSSNC5027 V4Page 15 of 161.0 IDENTIFICATION:ALARM PANEL 601-4T 11 T T -1-4-1REFUELING FLOORVENT EXHAUSTRADIATION HI-HIDEVICE:2D11-K611 A thru D2D11-K634 Athru D2D11-K635 Athru DSETPOINT:18 mr/hrPER 64Cl-CAL-002-0PER 64CI-CAL-002-02.0 CONDITION: 3.0 CLASSIFICATION:Radiation levels in the. Refueling Floor Exhaust Duct exceed EMERGENCYthe setpoint. 4.0 LOCATION:2H11-P601 panel 601-45.0 OPERATOR ACTIONS:5.1 Confirm the annunciator by monitoring recorders on panel 2H1 1-P600:* 2D11-R615 for 2D11-K611A &2D11-K611 B, and 2D11-K634A -D LI* 2D11-R616 for 2D11-K611C &2D11-K611D, and 2D11-K635A- D Lii5.1.1 Monitor the R/F Vent Exhaust Rad Mon on 2H11-P606;IF only one trip unit is affected, attempt to reset the affected trip unit. LI5.2 IF only one trip unit is alarmed, AND the unit is NOT malfunctioning,determine AND correct the cause of the high high radiation. Eli5.3 IF refueling operations are in progress,STOP refueling operations ANDIF possible, insert any withdrawn Control Rods. LI5.4 Evacuate personnel from the Refueling Floor. LII5.5 IF refueling OR fuel handling was in progress,enter 34AB-J1 1-001-2, Irradiated Fuel Damage During Handling. LI5.6 For valid alarm conditions, enter 31EO-EOP-014-2, SC-Secondary ContainmentControl AND 34AB-T22-003-2, Secondary Containment Control. LI5.7 IF an abnormal radioactive release is occurring OR has occurred,ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation levels in the vent duct6.2 Trip unit failure, upscale OR downscale ___________________

7.0 REFERENCES

8.0 TECH. SPECS./TRMIODCMIFHA:7.1 H-27629 and H-27631, Process RadiationMonitoring Diagram, Sheets 10 and 12 8.1 U2 TS 3.3.6.1 Table 3.3.6.1-17.2 H-27596 thru H-27600, Primary ContainmentIsolation System, Sheets 1 through 5 8.2 U2 TS 3.3.6.2 Table 3.3.6.2-134AR-60 1-403-2VER. 5.4 V4Page 16 of 161.0 IDENTIFICATION:ALARM PANEL 601-4________RX BLDG POT___ CONTAM AREAVENT RADN HI-HIDEVICE: SETPOINT:2011l-K609A through 0, Per 64CI-OCB-006-2, Form HPX-1 252, from ChemistryTrip Indicator Unit2.0 CONDITION: 3.0 CLASSIFICATION:Radiation levels on the inlet to 2T41-D005, Reactor Building EMERGENCYExhaust Filter Train, exceeds the setpoint. 4.0 LOCATION:2H11-P601 panel 601-45.0 OPERATOR ACTIONS:5.1 On panel 2H1 1-P600, confirm annunciator by monitoring the radiation level on2D1 1-K609A/2D1 1-K609B/2D11l-K609C/2D1 1-K609D on 2D1 1-R605 recorder. El5.1 .1 Monitor 2011 -K609A through D, Reactor Building Potential Contaminated AreaRad Monitors, on 2H11-P606.IF only one trip unit is affected, attempt to RESET the affected trip unit. LI5.2 IF only one trip unit is alarmed AND the trip unit is NOT malfunctioning,determine AND correct the cause of the high high radiation. El5.3 IF the A & B, O._R the C & D O__R all channels of trip unit 2D1 1-K609 are tripped,THEN enter 31EO-EOP-014-2, SC-Secondary Containment Control ANDconfirm Automatic Actions per 34AB-T22-003-2, Secondary Containment Control,Attachment 7. LI5.4 IF an abnormal radioactive release is occurring OR has occurred,ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 Steam leaks

7.0 REFERENCES

8.0 TECH. SPECS./TRM/ODCMIFHA:7.1 H-27629, H-27631, H-27632, & H-27634, Process 8.1 U2 TS 3.3.6.1Radiation Monitoring System Elem. Diag.7.2 H-26067 Reactor Zone Ventilation System P&ID34AR-601 -420-2VER. 6.3 VSPage 1 of 3SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE ('ARP' AGE 1 OF 2V5Page 1 of 3DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 34AR-601-902-1 ] 14.41H11-P601, ALARM PANEL 1EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE:04-30-15N/A SSM /PM: N/A DATE: N/AANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601 -ALARM PANEL 1ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-101-1 5.1 34AR-601-113-1 2.1 34AR-601-125-1 6.234AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.234AR-601-103-1 6.2 34AR-601-115-1 4.1 34AR-601-127-1 6.234AR-601-104-1 3.3 34AR-601-116-1 5.6 34AR-601-128-1 3.234AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.134AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.034AR-601-107-1 1.1 34AR-601-1 19-1 1.1 34AR-601-1 31-1 6.334AR-601 -108-1 2.2 34AR-601 -120-1 5.2 34AR-601-1 32-1 3.334AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.134AR-601-110-1 4.2 34AR-601-122-1 4.1 34AR-601-134-1 4.334AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.534AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0NOTE:______ Approval signature on this page constitutes approval for all procedures listed above at the~ NOTE:revision indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneNMP-AP-002I V5Page 2 of 3SOUTHERN NUCLEARPLANT E.I. HATCHPAGE 2 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO:ARP'S FOR CONTROL PANEL 1H11-P601, 34AR-601-902-1 1 14.4ALARM PANEL 1UNIT 11H11-P601 -1601-101 601-102 601-103 *601-104 601-105 601-106601-107 601-108

601-109

601-110 601-111 601-112601-113 601-114 601-115 601-116 601-117 601-118601-119 601-120 601-121 601-122 601-123 601-124601 -1 25 601 -1 26 601-1 27 601-1 28 601-1 29 601 -130601-131 601-132 601-133 601-134 601-135 601-136RECORDSThere are no records generated from this procedure.COMMITMENTSNone* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on TRIP UNIT Label(s) at 1D21-P600 to provide across-reference for locating the device(s) in Abnormal and/or EOP Tables.Refer to 34AB-T22-003-1, Secondary Containment Control.NMP-AP-002 v.2.0 V5Page 3 of 31.0 IDENTIFICATION:ALARMPANEL_601-1 ___________ __ ___TURBINE BLDG__RADIATION___ __ ___HIGHDEVICE: SETPOINT:SEE SECTION 6.0 AS PER THE CHEMISTRY CONTROLLED SETPOINT RECORD5.0 COPERATIOR: ACTIONS:FCATON5.1 At 1D21-P600, monitor ARMs listed in Section 6.0,to determine which monitor(s) indicates high, to assess the severity, and monitor for trends. LI5.1.1 Attempt to reset the trip unit. Iii5.2 Notify Health Physics to determine the validity of the alarm. LI5.3 IF the alarm is valid,enter 73EP-RAD-001-0, Radiological Event. LI5.4 Refer to 34AB-U22-001-1, Pipe Break in Turbine Building, for possible entry conditions. LI5.5 IF a radiation release to outside the Turbine Building has occurred OR is occurring,enter 34AB-D1 1-001-1, Radioactivity Release Control. LI5.6 IF a Fuel Element Failure is confirmed,Initiate Turbine Building Purge per 34SO-U41-001-1 radiation. LI5.7 Monitor other ARM's that are associated with this annunciator for increasing radiation. LI6.0 CAUSES:High radiation, as indicated by one of the following ARM's:1D21-R600 POINT NUMBER MONITOR AREA22 1D21-K600A Main Turbine Front Standard23 1D21-K600B Control Room24 1 D21-K600C Control Room25 1D21-K600D T/B 164' North End Operating Floor26 1D21-K600E Turbine Bldg Feedwater Area27 121-K01ZCondensate Demin Area34AR-601-1 16-1Ver. 5.6MGR-0048 Ver. 5 SM-SNC524602-001IAttachment IENERCON Calculation for E-HU1SHEET I-6 v15Page 1 of 3CALC NO. SNC024-CALC-003FNP DETERMINATION OFEMERGENCY ACTION LEVEL REV. 0PAGE NO. Page 6 of 85.0 Design Inputs1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask systemtechnical specification [2, Table 6.2-3] are provided below in Table 5-1. Thesesource values are scaled to develop the emergency action levels for initiatingcondition E-HU1.Table 5-1 Technical Specification Dose Rate Limits (Neutron + Gamma) for HI-STORM100 and HI-TRAC 125LocaionNumber of 1Technical SpecificationjMeasurementsj Limit (mrem/hr)HI-TRAC 125Side -Mid -height T 4 1680.3Top 1 4 j129.4HI-STORM 100Side -60 inches below mid-height 4 171.8Side -Mid -height 4 177.0Side -60 inches above mid-height 4 84.7Top -Center of lid 1 27.1Top -Radially centered 4 30.0Inlet duct 4 231.8Outlet duct 4 82.2 SM-SNC524602-001Attachment IIPNI::IlNN (.'l'ml:afinn fnr IF..WI I1SHEET I-7 v15Page 2 of 3CALC NO. SNCO24-CALC-003FNP DETERMINATION OF ___________EMERGENCY ACTION LEVEL REV. 00I EN ER C ON FORI=NITATNG CONDITION E- _ _______..."' HUl PAGE NO. Page 7 of 86.0 MethodologyThe "on-contact"' dose rates from the technical specification for the HI-STORM 100 andHI-TRAC 125 cask system are scaled by a factor of 2, as specified in NEI 99-01 Rev. 6[1], for use in initiating condition E-HU1.

SM-SNC524602-001Attachment II:PCANI (%lrdp-mi6*rn fr i::._WI I1SHEET I-8 v15Page 3 of 3CALC NO. SNC024-CALC-003FNP DETERMINATION OFEMERGENCY ACTION LEVEL REV. 00 E N E R C 0 N FOR INITAliNG CONDITION E-HUl PAGE NO. Page 8oft87.0 CalculationsThe dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose ratelimits. These calculations are presented below in Table 7-1.wTable 7-1 Dose Rate Scaling Calculations for EAL Limits (Neutron + Gamma)TechnicalLoainSpecification Scaling Calculated Value EALLoainLimit Factor .(mremn/hr) (mrem/hr)_______________________ (mremlhr) ____________ _____________ ______ ______ ______HI-TRAC 125 _ _ _ _ _ _ _ _ _ _ _ _ _ _Side -Mid -height [ 680.3 j 2 J 1360.6 1360Top L 129.4 j 2 258.8 260Side -60 inches below mid-heightSide -Mid -heightSide -60 inches above mid-heightTop -Center of lidTop -Radially centeredInlet ductOutlet duct171.8177.084.727.130.0231.882.2343.6 340354 350169.4 17054.2 5060 60463.6 460164.4 1608.0 Computer SoftwareMicrosoft WORD 2Q13 is used in this calculation for basic multiplication.

V16LYN I Page 1o of 8CORE COOLING Revision 17P SSFIFTH NOHOTTEST ITC LESS iGO TOSATaPage1 ofI1 V16N !T 1Page 2 of 8HEAT SINK Revision 17FRP4.LI~GO TOFRP-H.2PRESS IN INOIALL SG'S L.EBB THAN""GO TOFRP-H.3NAR RNG NLVL IN ALL LSO'S LESS '--'THAN 62 1YESJGOTOr FRP-H.4PRESS IN NALL SG'SLESS THAN,,,,,1075 P8I10YEGO TO-I FRP-4.5CSFSAT 1V16Page 3 of 88/29/2007 08:3 3FNP-I-CSF-O.4 INTEGRIT Revision 17I-f,' GO TOFRP.P.1JGO TOinininm m --t aFRP-.2CSFSATGO TOGOOTSATSATPagI 1 f2

[NI 1Page 4of 8FP1CSF-0. COTANMN Geson TOPRESS NO in in, -FRP-Z.1LESS ri- !THAN 5 YEs At LEAST ONE NOIPUMP RUNNING-- --OTI (FLOW>IODOOGPM) YES ,. 2I CTMT koI S~UMP LVL NCTMT [THAN 7.6 I=:LESS HTHAN 27 YsGO TOPSIG FRPZ.SUMP LVL.NLESSTHAN 7.6HFT.~GO TOFRP-Z.3BOTHCTMT RAD NLESS --hrTHAN 2 R/ LY1CSPage 1 of I 1I]IJIT9Vi16Page 5 of 88/29/2007 08:33 -FNP-2-CSF-0,2 CORE COOLING Revision 12GOTOoIP I m IIFRP-C.1HOTTEST NORP.CCORE EXITTHAN YETHANT790TCREXIT---,TC LSSTC HESSUBOO NO GO TOCOR PRP-C.30 EXIOT TCS "-iGRTR THAN Ei16" F 145"F}Page1 of 1 V1 6!]N IT 2Page 6 of 8FNP-2-CSF-O0.3 HEAT SINK Revision 12SGO TOFRP-K.1miTOTAL AFW NOIiFLOW TO I1 ALL SG'8 -,-,395 GPM EGO TO~FRP-HL2LVL IN AT IN NOLEAST ONE ALL SG'SSG GRTR --'-LESS THANTHAN 31% YES __ _______ 1129PSIG YES,[ GO TO! f FRP-H.3MiAR RNG [N]LVL IN ALLSGS8 LESS mmmTHAN 52% YESGO TO-I FRP-H.4PRESS IN NOALL 5G5S:ILESS THANmmg1075 P810 YESGO TOI r FRP-H.5CSFSATPage 1 of I V167 of 8FNP-2-CSF-O.4 IINTEGRITY Revision 12COLD LGTMEAUE('F GO TOW FRP-P,1ALL RCSPRESS- OTCL TEMP (IN m -ine e lRIGHT OF YES ,.,i_AL. RCS CL N OTTEMPS INGOTSLAST 60 MIN -,FRP..P.2GRTIR THAN--'---- L RCS CL N~ TEMP TEMPNO SALALATT600MINLESSR ThANTEM DCRNN OJ SALESTRTTAHAN GOT326' F SATCSFSATPage I of 2 Vi16*l Page 8 of 88/29/2007 08:33 I NJ J .FNP-2-CSF-0.5 CONTAINMENTReion1H CTMT TI _O__OPRESS NO R "P .L "I m-~-LESS H-- 11THAN 5 YES At LEAST ONE NORUNNING(FLOW1 000GPM)YESFnI *m WRP-Z.2SUMP LVL OICTMT- THAN 7.6[PRESS NLESS- SITHAN 27 YEs GO TOPSIG jjFRP-Z.1SUMP LVI NOLESS H.-THAN 7.6 YEFT.GO TOFRP-Z.31THAN2RJ [EST SATPage 1 of I V1 7Page 1 of 807/13/15 09:23:59 LOCATION FiUlSETPOINT: 1. Variable, as per FNP-1-RCP-252 HIRMSORIGIN: Any of the below listed Area, Process or Gaseous and HI-RADParticulate Monitors: R01, R02, R03, R04, RO5, R06,R07, R08,-R1OI RI1, R12, RI3,[T RI5, RI7A ________R17B, RIS8, R-I19, R20A, R20B, R21, R23A orR23B.PROBABLE 1 .High Radiation Level in the System, Area or at the Component monitored.2. The radiation monitors fail to a "High Radiation" condition on loss ofinstrument and/or control power that will result in actuation of associatedautomatic functions.AUTOMATIC ACTIONS;I. The following actions will occur if a High Radiation Alarm is actuated onthe associated Radiation Monitor.A. R14: (Plant Vent Gas) closes Waste Gas Release ValveI -G WD-HV-0 14.8. R16: None -abandoned in place per MDC 1040589501.C. R17A or B: (Component Cooling Water) closes QIPIYRCV3028CCW SRG TANK VENT.D. R18: (Liquid Waste Processing) closes Liquid Waste Release ValveI -L WP-RC V-0 18.E. R19: (Steam Generator Blowdown) isolates Steam GeneratorBlowdown Sample Lines.F. R23A :( Steam Generator Blowdown Processing) closes1-BD-FC V-I1152 SIG Blowdown Heat Exchanger Outlet FCV.G. R23B :( Steam Generator Blowdown Processing) closesI-BD-RCV-023B SQ BLOWDOWN PMP DISC.Page 1 of 15Page 1of 15Version 72.1 V1 7Page 2 of 807/13/15 09:23:59FNP-I-ARP-I .6LOCATION FHI.*RADIATION MONITOR TABLEI -p y pLOCATIONDETECTORFUNCTIONACTIONSR-IA Control Room (Unit I Area G-M (W) Perform Step____ Panel) _ _ _ _ _ __ 4.1R-I B Technical Support Center Area G-M ( W ) No input to__ _(Unit II Panel) R-IB _______ ____this alarmR-2 Containment (155' elev) Area G3-Mr ( W) Starts IPC dose Perform Steps____ ________integration 4.2R-3 Radiochemistry Lab (AB Area G-M (W~) Perform Step_ _ _ _ 139') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.3R-4 #3 Charging Pump (AB Area G-M (_W ) Perform StepI__ _ 00') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.4R-5* Spent Fuel Pool Room (AB Area G-M (_.W) Perform Steps_ _ _ _ 155') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 4.5R-6 Sampling Room (AB 139') Area G-M ( _W) Perform Step____ __ ____ ___ ___4.6R-7 In-core NIS Area (CTMT Area G-M ( W) Starts [PC dose Perform Steps____129', near Seal Table) ___________integration 4.7R-8 Drumming Station (AB Area G-M (W ) Perform Step_ _ _ _ 155') _ _ _ _ _ _ _ _ _ __4.8R-9 SG Sample Panel (Unit II Area G-M ( W ) No input toPanel) (AB 139') ___ _____this alarmR-0 Penetration Room Filtration APD Beta Scint Perform StepDischarge (AB 155') ____**(GA-ES) 4.9R-I 1

Containment Atmosphere APD Beta Scint Perform Step(AB 121') **__ (GA-ES) _______4.10*Technical Specification related**General Atomics Electronic SystemsPage 5 of 15 Vrin7.Version 72.1 V17Page 3 of 807/13/15 09:23:59FNP-1-.ARP-1 .6LOCATIONFHRADIATION MONITOR REFERENCE TABLE (cont)RELOCATION TYPE~ DETECTOR FUJNCTION ACTIONSR- 12" Containment Atmosphere Gas Beta Scint Perform Step____(AR 121') ___ **(OA-.ES) ________4.11lR-1 3 Waste Gas Compressor Gas G-M ( _W) Perform StepSuction (AB 100' WGC 4.12Valve Room) _________________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform StepODCM ________ __4.13R- i 5A Condenser Air Ejector Gas G-M ....Perform StepODCM Discharge Header (TB 155') 4.14R-I 5B* Condenser Air Ejector Gas G-M (Eberline) Perform Step(Intermediate Range) (T 4.15R-I 5C* Condenser Air Ejector Gas Ion Chamber Perform Step____(High Range) (TB 189') (berline) _______4.15R-1 7A Component Cooling Water Liquid Scint. ( W) Closes CCW Perform Step(CCW H-x Room) surge tank vent 4.16_______ ~~(RCV-3028) ______R-17B Component Cooling Water Liquid Scint. Closes CCW Perform Step(CCW Hx Room) surge tank vent 4.16______ _____ ___________(RCV-3028)R-1 8 Waste Monitor Tank Pump Liquid Scint. ( W) Closes RCV-1 8 Perform StepODCM Discharge (AB 121' at the 4.17______Batching Funnel) _____R-19 Steam Generator Liquid Scint. (YWL) Isolates sample Perform StepBlowdown/Sample (AR lines 3328, 4.1 8____139') _______3329, 3330 ______R-20A Service Water from Liquid Scint. ( W) Perform StepContainment Coolers A and 4.19B (AB 121' BTRS Chiller______ Room)__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R-20B Service Water from Liquid Scint. ( _W) Perform StepContainment Coolers C and 4.19______D (AB 121') ____________ __ _____*Technical Specification related**General Atomics Electronic SystemsPage 6 of15 Vrin7.Version 72.1 V1 7Page 4 of 807/1 3/15 09:23:59FNP-I-ARP-1 .6LOCATION FillRADIATION MONITOR REFERENCE TABLE (cont)RE LOCATION TYP DIETECTR FUNCTON ACTIONSR-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____ ____________ ____(Victoreen) 4.20R-22 Plant Vent Stack Gas G-M (_W Perform StepODCM (AB 155') -)_______________ 4.21R-23A SG Blowdown Surge Tank Liquid Scint. (__) Closes Perform StepInlet (AB 130') ____FCV-1152 4.22R-23B SG BLOWDOWN PMP Liquid Scint. ( __i) Closes Perform StepODCM DISC (AB 130') ___ _____RCV-23B 4.22R-24A* Containment Purge (AB Gas Scint. Closes No input to155') containment this alarmpurge supply &exhaust dampers2866C & 2867C____________ _______and 3198A &DR-24B* Containment Purge Gas Scint. Closes valves: No input to(AB 155') (Victoreen) 2866D &2867D, this alarm3196,3197,____________ _______3198B & CR-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input toR-25B* (AB 184') (Victoreen) supply and this alarme~xhaust fans;closes SEPH-VAC supplyand exhaustdampers; startsassociated trainsof penetration_____________ __ _ ________room filtration. ____R-27A* Containment (High Range) Area Ion Chamber No input to_____ _____________ ____(Victoreen) _ ______this alarmTechnical Specification relatedPage 7 of 15 Vrin7.Version 72.1 07/13/15 09:41:15 1F~~i~ NP-2-ARP-1.6 Page 5of 8LOCATION .IillSETPOINT: 1. Variable, as per F'NP-2-RCP-252ORIGIN: Any of the below listed Area, Process or Gaseous andParticulate Monitors: ROI!B, R02, R04, R05, R06,R07, RO8, R09, RI I, R12, R 13, -R'4 R15,R17A, RI7B, RIB, R19, R20A, R20B[ R21, R224R23A or R23BPROBABLE CAUSERMSHI-RADI. High Radiation Level in the System, Area or at the Component monitored.I2. The radiation monitors fail to a "'High Radiation-"" condition on loss ofinstrument and/or control power that will result in actuation of associatedautomatic functions.AUTOMATIC ACTION1. The following actions will occur if a High Radiation Alarm is actuated onthe associated Radiation Monitor.a) R14: (Plant Vent Gas) closes Waste Gas Release Valve 2-GWD-HV-0 14.b) R16: (Boron Recycle System) diverts 2-C VC-RC V-016 RecycleEvaporator discharge from Reactor Makeup Water System to theRecycle Evaporator Demineralizer.c) RI7A or B: (Component Cooling Water) closes 2-CC W-RC V-3028CCWN SRG TANK VENT.d) R I8: (Liquid Waste Processing) closes Liquid Waste Release Valve2-LWP-RCV-0I18.e) RI9: (Steam Generator Blowdown) isolates Steam GeneratorBlowdown Sample Lines.t) R23A: (Steam Generator Blowdown Processing) closes2-BD--FCV-1 152 S/G Blowdown Heat Exchanger Outlet FCV.g) R23B: (Steam Generator Blowdown Processing) closes2-BD-RCV-023B SGBD DISCH TO ENVIRONMENT.Page 1 of 13 Vrin6.Version 61. i SNIT 207/13/15 09:41:15Vi17FNP-2-ARP-I.6 Page 6 of 8LOCATION FHilOPERATOR ACTION (cont)4. In addition to the general actions perform steps indicated in the "ACTIONS"column of the following table. (Some of the radiation monitors included in thetable do not input into this alarm but are included for reference).RADIATION MONITOR REFERENCE TABLECRE LO:CATION TYPE DETECTOR FUNCTION ACTIONSR- 1A Control Room (Unit I Area G-M ( W) No input toPanel) _______this alarmR- lB Technical Support Center Area G-M ( W) Perform Step(Unit 1] Panel) R-l 1B_________ 4.1R-2 Containment (155' elev) Area G-M ( W) Starts IPC dose Perform Steps___ __ ___ __ ___ __ _ _ __ __integration 4.2R-3 Radiochemistry Lab (AB Area G-M ( W) No input to139') __________this alarmR-4 #3 Charging Pump (AB Area G-M (W) Perform Step100') _____ ________4.3R-5* Spent Fuel Pool Room (AB Area G-M (Wj) Perform Steps155') _ _ _ _ _ _ _ _ _ _ 4.4R-6 Sampling Room (AB 139') Area G-M ( W) Perform Step____ ___ ____ ___ ____ ___ ___ ___ ____ ___4.5R-7 In-core NIS Area (CTMT Area G-M ( W) Starts IPC dose Perform Steps129', near Seal Table) ____integration 4.6R-8 Drumming Station (AD Area G-M ( W) Perform Step155') __ _ _ _______4.7R-9 SG Sample Panel (Unit II Area G-M (W) Perform StepPanel) (AB 139') 4.8R- 10 Penetration Room Filtration APD Scint. Perform Step____Discharge (AD 155') (Victoreen) 4.9R- 11

Containment Atmosphere APD) Scint. Perform Step____(AB 121') ____(Victoreen) _______4.10**Technicail Specification relatedPage 4 of 13Page 4of 13Version 61.1

~k J. ~'V1 7FNP-2-ARP-1.6 Page 7 of 807/13/15 09:41:15LOCATION FHilRADIATION MONITOR REFERENCE TABLE (cont)RE. LOCATION TYPE DETECTO FU[NCTION ACTIONSR- 12* Containment Atmosphere Gas G-M ( W) Perform Step(AB 121') _____4.11R-13 Waste Gas Compressor Gas O-M (W) Perform StepSuction (AB 100' WGC 4.12Valve Room) ________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform StepODCM ___________________ __4.13R- 15A Condenser Air Ejector Gas G-M Perform StepODCM Discharge Header (TB 155') 4.14R-15B* Condenser Air Ejector Gas G-M (Eberline) Perform Step(Intermediate Range) (TB3 4.15189') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R .15C* Condenser Air Ejector Gas Ion Chamber Perform Step(High Range) (TB 189') (Eberline) 4.15R-17A Component Cooling Water Liquid Scint. (W ) Closes CCW Perform Step(CCW H-x Room) surge tank vent 4.16__________________(RCV-3028) _____R-17B Component Cooling Water Liquid Scint. Closes CCW Perform Step(CCW Hix Room) surge tank vent 4.16_________________ _____ _________ RCV-3028)R- 18 Waste Monitor Tank Pump Liquid Scint. (W ) Closes RCV- 18 Perform StepODCM Discharge (AB 121' at the 4.17_______Batching Funnel)R-19 Steam Generator Liquid Scint. ( W) Isolates sample Perform StepBlowdown/Sample (AB lines 3328, 4.18139') ___ _____ __3329, 3330R-20A Service Water from Liquid Scint. ( W) Perform StepContainment Coolers A and 4.19B (AB 121' BTRS Chiller_____Room) _________________*Technical Specification relaedPage 5 of 13 Vrin6.Version 6 I. 1 UN1IT 2V1 7FNP-2-ARP-I1.6 Page 8 of 807113115 09:41:15LOCATION .TLRADIATION MON1TOR TABLE (cont)RELOCATION IX DETECTOR FUNCTION ATIOQNSR-20B Service Water from Liquid Scint. ( W) Perform StepContainment Coolers C and 4.19______D (AB 121')______R-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____(Victoreen) 4.20R-22 Plant Vent Stack Gas G-M ( W) Perform StepODCM (AB 155') 4.21R-23A SG Blowdown Surge Tank Liquid Scint. ( W) Closes Perform Step____Inlet (AD 130') ____ _______FCV-! 152 4.22R-23B SGBD DISCH TO Liquid Scint. ( W) Closes Perform StepODCM ENVIRONMENT RCV-23B 4.22_______ (AB 130')________ ________ _ _ _ _ _ _R-24A* Containment Purge (AD Gas Scint. Closes No input to155') containment this alarmpurge supply &exhaust dampers2866C & 2867C____ ________and 3198A & _____R-24B* Containment Purge Gas Scint. Closes valves: No input to(AD 155') (Victoreen) 2866D &2867D, this alarm3196, 3197,_____3198B &CR-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input toR-25B* (AD 184') (Victoreen) supply and this alarmexhaust fans;closes SFPHVAC supplyand exhaustdampers; startsassociated trainsof penetrationroom filtration.*Teehnical Specification relatedPage 6 of 13Page6 o 13Version 61I.1I V18Page 1 of 3FNP-I-ARP-I.1207/13/15 08:32:48 -SETPOINT:1.2.3.0.01lgSystem Health RelayAlarm Relay 0LOCATION M~~SEISMICPANELALARMORIGIN: 1. SSA-3 Solid State Accelograph(NIH 11NGSI2507G)2. System Health Relay (8 inputs)* Recorder memory usage exceeding 80%* Failure of recorder(s) to respond to pollingfrom central controller.* Hardware failure* Recorder high temperature* Failure of recorder(s) to respond to controllerduring startup.* Communication problem.* DC power loss on alarm panel.* AC power loss on recorder(s).3. Alarm relay 0 (From channel 1 recorder, used forfunctional testing only).PROBABLE CAUS1. Seismic event.12. Operating Basis Earthquake (OBE) exceeded.I3.4.5.Seismic Panel loss of power.Instrument malfunction.Seismic finctional testing in progress.AUTOMATIC ACTION1. The monitoring system remain on at all times continuously monitoringthe signals from the acceleration sensors.2. When a setpoint is exceeded, the system' retrieves the time history datafrom storage and automatically performs the preprogrammed calculationsfor operator review.3. The system printer provides print and plot copies of the results for recordand review.El[]ElPage I of 15 Vrin6.Version 63.1 07/13/i5 08:33:15Vi18Page 2 of 3FNP-1-ARP-I1.12LOCATION MK5OPERATOR ACTIONS CONTINUEDACTION EXPECTED3.3 Record and compare the seismicpanel printout channel 1, 2 and 3Spectral Acceleration calculatedvalues, Spectral Velocity calculatedvalues and Computed CAV values tothe Spectral Acceleration designvalues, Spectral Velocity designvalues and CAV Design Limit Valueson Table ! "~Operating BasisEarthquake Exceedance (OBEE)Limit for Determination of PlantShutdown Requirements".IRESPONSE NOT OBTAINED3.4 Check the following:CAV Design limit value has NOTbeen exceeded.*Based on operator walkdowns noplant significant damage is found.3.4.1 JF either unit tripped, THENconduct a post trip review andrestart as appropriate.3.4 IF_ any of the following has occurred:* The Spetral Acceleration design valuehas been exceeded,o_.R* The Spectral Velocity design value hasbeen exceeded,_OR* Significant plant damage is found duringoperator walkdownsTHEN OBEE Criteria has been exceeded.3.4.1Generate a Condition Report to referto FNP- I-ETP-4580 and documentthe event.3.4.2 Generate a Condition Report torefer to FNP-I-ETP-4580 anddocument the event.3.4.2 Proceed to step 4.3.4.3 Proceed to step 5.Page 4 of 15 Vrin6.Version 63.1 07/13/15 08:34:29 A l 1 NP-I-AP-1.1LOCATION M15TABLE IOPERATING BASIS EARTHQUAKE EXCEEDANCE (OBEE) LIMITFOR DETERMINATION OF PLANT SHUTDOWN REQUIREMENTSResoonse Soectr Analysis for..Free Field MeasurementChannel 1: [L"~S1Computed CAV = * ..g-sec, Limit =0.160 g-sec"PSA Limit = 0.200 g ", OBE SV Limit =15.240 Damping = 0.050Spectral acceleration exceeded OBE Design criteria at

frequencies.Spectral acceleration greater than 2/30OBE Design criteria at

frequencies.Spectral velocity exceeded OBE Design criteria at

frequencies.Channel 2: I'V-UP1Computed CAV -* ....g-sec, CAV Limit = 0.160 g-sec'*OBE PSA Limit -0.200 g**, OBE SV Limit ,,15.240 cm/sec, Damping =0.050Spectral acceleration exceeded OBE Design criteria at

frequencies.Spectral acceleration greater than 2/30OBE Design criteria at.._* frequencies.Spectral velocity exceeded OBE Design criteria at....2* frequencies.Channel 3: FT=W1Computed CAV =

g-sec, CAV Limit = 0.160 g-sec"°OBE PSA Limit =0.200 g"*, OBE SV Limit = 15.240 cm/sec, Damping = 0.050Spectral acceleration exceeded OBE Design criteria at______ frequencies.Spectral acceleration greater than 2/30OBE Design criteria at

frequencies.Spectral velocity exceeded OBE Design criteria at frequencies.Calculated by Seismic Monitor. Any exceedances are exceedances of the system setupvalues per Table 2 and do not necessarily mean OBEE limits have been exceeded.oe The CAV Design Limit is 0.16 g-s but Table 2 -OBE Limit Value shows a limit value of0.0 g-s so the Farley Nuclear Plant OBE Spectra would control the OBE system alarm.O 0.20g is the EPRI OBE Limit Value (OBEE). The monitoring system will accept only onevalue at a time for the OBE limit Value. The recommended monitoring system setup (Ref'.Table 2 -OBE Limit Value) shows a limit value of 0.05g horizontal and 0.033g vertical sothe Farley Nuclear Plant OBE Spectra would control the OBE system alarm.Page 13 ofI Veson6.Version 63.1 V19Page 1 of 3RCS Specific Activity3.4.163.4 REACTOR COOLANT SYSTEM (RCS)3.4.16 RCS Specific ActivityLCO 3.4.16APPLICABILITY:The specific activity of the reactor coolant shall be within limits.MODES 1 and 2,MODE 3 with RCS average temperature (Tavg) > 500°F.ACTIONS ___________ _______CONDITION REQUIRED ACTION COMPLETION TIMEA. DOSE EQUIVALENT----------------Noe-------1-131 > 0.5 pCi/gm. LCO 3.0.4c is applicable.A.1 Verify DOSE Once per 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sEQUIVALENT I-131within the acceptableregion ofFigure 3.4.16-1.ANDA.2 Restore DOSE 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months sEQUIVALENT 1-131 towithin limit.B. Gross specific activity of B.1 Be in MODE 3 with 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sthe reactor coolant not Tavg < 500°F.within limit.Farley Units 1 and 23.4.16-1Amendment No. 170 (Unit 1)Amendment No. 163 (Unit 2)

Vi19Page 2 of 3RCS Specific Activity3.4.16ACTIONS_________ ___CONDITION REQUIRED ACTION COMPLETION TIMEC. Required Action and C.1 Be in MODE 3 with 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sassociated CompletionTag<50FTime of Condition A notTag<50Fmet.O._RDOSE EQUIVALENTI-131 in the unacceptableregion of Figure 3.4.16-1.SURVEILLANCEREQUIREMENTS _______SURVEILLANCE FREQUENCYSR 3.4"16.1 Verify reactor coolant gross specific activity I10E .~/g.ten accordance withsrelacFrequency ControlProgramSR 3.4.16.2 ---NOTE---------------........Only required to be performed in MODE 1.Verify reactor coolant DOSE EQUIVALENT 1-131 In accordance withspecific activity < 0.5 IpCi/gm. the SurveillanceFrequency ControlProgramANDBetween 2 and6 hours after aTHERMALPOWER changeof > 15% RTPwithin a 1 hourperiodFarley Units 1 and 23.4. 16-2Amendment No. 185 (Unit 1)Amendment No. 180 (Unit 2)

V19Page 3 of 3RCS Specific Activity3.4.16E0U275250225200175150125.__'- -Operation_ _ .. +:_::~i- J:1 1_+?[]i. ..EI.NK.. .Acceptable ; ++ 5 -+ -* + -575. ... Operatin --50,2 5 ,. ......0 ..., '. + : + ._ L .+ ' + : + ....20 30 40 5O 0070 80 90 100Percent of RATED THERMAL POWERFigure 3.4.16-1DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit VersusPercent of RATED THERMAL POWER with the Primary Coolant SpecificActivity > 0.5 jiCi/gm DOSE EQUIVALENT 1-131.Farley Units 1 and 23.4. 16-4Amendment No. 147 (Unit 1)Amendment No. 138 (Unit 2)

V20Page 1 of 1RCS Operational LEAKAGE3.4.133.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGELCO 3.4.13RCS operational LEAKAGE shall be limited to:a. No pressure boundary LEAKAGE;b. I gpm unidentified LEAKAGE;c. 10 gpm identified LEAKAGE; andd. 150 gallons per day primary to secondary LEAKAGE through anyone steam generator (SG).APPLICABILITY: MODES 1, 2, 3, and 4.ACTIONS____________ _____ ___CONDITION REQUIRED ACTION COMPLETION TIMEA. RCS operational A.1 Reduce LEAKAGE to 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sLEAKAGE not within limits within limits.for reasons other thanpressure boundaryLEAKAGE or primary tosecondary LEAKAGE.B. Required Action and 8.1 Be in MODE 3. 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sassociated CompletionTime of Condition A not ANmet.8.2 Be in MODE 5. 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months sPressure boundaryLEAKAGE exists.Primary to secondaryLEAKAGE not within limit.I1Farley Units I and 23.4.13-1Amendment No. 163 (Unit 1)Amendment No. 156 (Unit 2)

V21Page 1 of 1ESFAS Instrumentation3.3.2Table 3.3,2-1 (page 2 of 4)Engineered Safety Feature Actuation System InstrumentationAPPLICABLEMODES OROTHERSPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIPFUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT2. Containment Spraya. Manual Initiation 1,2,3,4 2 B SR 3.3.2.6 NA NAbi. Automatic Actuation 1.2,3,4 2 trains C SR 3.3.2.2 NA NALogic and Actuation SR 3.3.2.3Relays SR 3.3.2.8Pressure SR 3.3.2.4High -3SR 3.3.2.7SR 3.3.2.93. Containment Isolationa. Phase A Isolation(1) ManualInitiation(2) AutomaticActuation Logicand ActuationRelays(3) Safety Injectionb. Phase B Isolaton(1) ManualInitiation(2) AutomaticActuatio LogicandAcutnRelays1,2,3,41,2,3,422 trainsB SR 3.32..6C SR 3.3.2.2SR 3.3,2.3SR 3.32.8NANANANARefer to Function 1 (Safety Injection) for all initiation functions and requirements.1,2,3A41.2,3,422 trainsB SR 3.3.2.6C SR 3.32.2SR 3.3 2.3SR 3.3 28E SR 3.3.2.1SR 3.3.2..4SR 3.32.7SR 3.3,2-9NANANANA(3) ContainmentPressureHlgh -31.2,34S 28.3 psig 5 27 psigFadley Units I and 23.3.2-10Amendment No. 185 (Unit 1) iAmendment No. 180 (Unit 2) I Edwin I. Hatch Nuclear Plant Units 1 and 2License Amendment Request for Changes toEmergency Action Level Schemes to Adopt NEI 99-01 Rev. 6and to Modify Radiation Monitors at Farley Nuclear PlantEnclosure 4Hatch EAL Verification and Validation Documents Hatch EAL V&V Documentation IndexV&V# ..'Description I' IC [Threshold'RCS Modes/Temperatures -TS Reference (Table 1.1I-I) EAL Basis Section 1.41 RCS Cold Shutdown Temperature reference (212 OF) t CA3 (1)___tj CU3 J (1)Radiation Monitor Calculations:1/2D1 1-P601 (feeding 1/2D 11-R63 1)1D11l-P007 (feeding 1D11-R631)Calc SMiNH-13-021 Rev IRG I(1)RS1 (1)RA1(1)2Radiation Monitor Calculations: 1D11-K604 RU1 (1)1D 11-K6051D11-K619 A(B)1D1 l-K600 A(B)2D1 1I-K6042D 11-K6052D1 1-K636 A(B)Ca/c SMNH-13-021 Rev 1Radiation Monitor Information: RU2 (1)b1D21-K601 A 2D21-K601 A1D11-K601 D 2D21-K601 M1D21-K601 E 2D21-K601 E1D21-K601 M 2D21-K611 K2D21l-K611 LCa/c SMNH-13-021 Rev 1 _____Radiation Monitor Calculation: CG1 (1)bDWRRM 1/2D 11-K621 A(B) CS 1 (2)bCa/c SMNH-13-021 Rev 1 ______Primary Containment Rad Monitor Calculations FCB L4A FCB L4ADWRRM RCSB L4A RCSB L4ACa/c SMNH-13-021 Rev 1 CB PL4A CB PL4AOffgas Pre-Post Treatment Reading Calculation FCB L5A FCB L5ACa/c SMNH-13-021 Rev 1I_____Drywell Fission Product Monitor Reading CalculationCa/c SMNH-13-021 Rev 1RCSB L5ARCSB L5AODCMITS Reference to Site Boundary RG1 (2)(3)3RS1 (2)(3)RAl (2)(3)(4)Alarm Response Procedure Reference RA2 (2)Annunciator Displays:1D21-K601 A 2D21-K601 M1D21-K601 B 2D21-K601 E1D21-K601 D 2D21-K611 K1D21-K601 E 2D21-K611 L1D21-K601 M 2D11-K609 A-DIDII-K609 A-D 2D11-K611 A-D1D1Il-K611 A-D 2D 11-K634 A-D2D21-K601 A 2D11-K635 A-DAlarm Response Procedure Reference Control Room Rad RA3 (1)Monitor [Annunciator Display: 1D21-K600 B(C)] ____________Alarm Response Procedure Reference RU2 (1 )aAnnunciator Display: Spent Fuel Storage Pool Level Low6 654-022-1Spent Fuel Storage Pool 'Level Low654-022-2 ______2/22/20 16Page 1 of 3 Hatch EAL V&V Documentation IndexV&V# *Description ' IlC ThresholdRPV Level Indications/Displays (-155" TAF) CG1 (1)a7CS1 (2)bFCB PL2A FCB PL2ACaic SMNH-13-021 Rev 1 RCSB L2A RCSB L2ARPV Level Indication/Display (-35"); Level 2 Actuation CS 1 (1)b8 setpoint info (required for CA1/CS1 is 6" below setpt) CAl (1)Caic SMNH-13-02I Rev 1Drywell Floor Drain Sumps; Drywell Equipment Drain CG1 (2)bSumps; Torus; Torus Room Sumps; RB Floor Drain CS 1 (3)bSumps; TB Floor Drain Sumps; Rad Waste Tanks CA1 (2)breferences cui (2)bH2 Concentration (> 6%) and 02 Concentration (> 5%) -CGI (2)c10 calculation/reference CB PL1B CB PL1BCale SMNH-13-021 Rev 111 Primary Containment Pressure Reference (> 56 psig) CG1 (2)cCalc SMNH-13-021 Rev]1 CB PLIA CB PL1ASecondary Containment Rad Monitors > Max Safe values CG1 (2)c12 34AB-T22-O03-1/2 CBL3A CBL3ASecondary Containment Rad Monitors > Max Normal RCSBPL3A RCSBPL3AValues 34AB-T22-O03-1/24160 VAC Essential Buses Description CA2 (1)CU2 (1)a13 SG1 (1)aSG8 (1)aSS1 (1)SA1 (1)SU1 (1)14 RCS Pressure indications CA3 (2)DC System Information CU4 (1)15 SO8 (1)bSS8 (1)16 ISFSI TS/Dose Reading Calculation E-HU1 (1)SMHN-13-021 Rev 117 Primary Containment Pressure > 1.85 psig reference RCSB LIA RCSB L1A17 Calc SMNH-13-021 Rev 1Secondary Containment Temps -> Max Normal values RCSBPL3A RCSBPL3A18 34AB-T22-O03-1/2Secondary Containment Temps -> Max Safe values CBL3A CBL3A34AB-T22.-O03-1/2Seismic Indications (OBE): HU2 (1)19 [Annunciator Display (657-048/657-066)]12.7 Hz amber light12.7 Hz red light20 Table H2 Basis HU4 (1)b (2)b34AB-X43-O01-1 (2)21 Minimum Steam Cooling RPV Water Level SG1 (1)bSS5 (1)c22 Heat Capacity Temperature Limit (HCTL) Curve SS5 (1)cPretreatment Radiation Monitor Reading SU3 (1)23 TS3.7.6Caic SMNH-13-021 Rev 1RCS sample activity -Tech Spec Value SU3 (2)24 TS3.4.62/22/2016Page 2 of 3 Hatch EAL V&V Documentation IndexIV&V# I> Description I IC IThreshold'RCS Operational Leakage -Tech Spec Values SU4 (1)(2)25 TS3.4.42/22/2016Page 3 of 3 VlPage 1 of 1Definitions1.1Table 1.1-1 (page 1 of 1)MODESAVERAGE REACTORCOOLANTREACTOR MODE TEMPERATUREMODE TITLE SWITCH POSITION (°F)1 Power Operation Run NA2 Startup Refuel(a) or Startup/Hot NAStandby3 Hot Shutdownl(a) Shutdown > 2124 Cold Shutdown(a) Shutdown < 2125 Refueling(b) Shutdown or Refuel NA(a)(b)All reactor vessel head closure bolts fully tensioned.One or more reactor vessel head closure bolts less than fully tensioned.HATCH UNIT 11.1-6HATC UNI I 11-6Amendment No. 195 5A~NYErn~r,,.&'~i.v I~W*d4V2Southern Nuclear Design CalculationSeNL1589Enclosure 3ICalculation Number: SMNH-13-021Plant:Hatch Nuclear Plant Unit:O 1 0" 2 0] 1 & 2 Discipllne:MechanlcalTlfite:Subject EmergencyNEI 99-01 Rev 6 EAL. Calculations Action Level SetpointsPurpose I Objective:Document Emergency Action Level Values to support conversion to NEI 99-01 Rev 6System or Equipment Tag Numbers:N/AContentsTopic Page Attachments # of(Computer Printouts, Technical Papers, Pages__________________Sketches, Correspondence)Purpose 1 A -SNC EP Concurrence 1Criteria 1 B -Reserved 0Conclusions 3 C -Fuel Clad' Loss 4.A Threshold Calculation 19Design Inputs 5 D -Fuel Clad Potential Loss 5.A Threshold 1Assumptions ,10 CalculationReferences 14 E -RCS Loss 4.A Threshold calculation ... 16Method of Solutions 18 F -RCS Loss 5.A Threshold Calculation 6Body of Calculation .... ....23 G -containment Potential Loss 4.A 1__________________Threshold Calculation______________H -Steam Table Validation 5I- RS1 Threshold Calculation ______ 25Toa fPgsicuigJ -CG1 Threshold Calculation 4cover sheet & Attachments: 189 K -CG1 Threshold,,,Calculation 15L -E-HU1 Threshold Calculation 16M -RA1 Threshold Calculation 18Nuclear Quality Level0 -Safety-Related li Safety Significant 0 o-Safety -SignificantVersion RecordVersion Originator Reviewer' Approval I Approval 2I, ~ dui= Name P.*HW 4Name Pri~ed Na. atiCalculation of EAL Thresholds. wb..d l-Lto support NEI 99-01 Rev. 6Notes: Key calculationNMP-ES-039NMP-E-039NMP-ES-039-001 V3Page 1 of 2HNP ODCMd. The CHAN4NEL CHECK s hall consist of verifying sampler flow an d the presence ofthe*collection device (i.e., partic~ulate filteror charcoal cartridge, etc.) at the weekly o ,43.1.2 Gas eous Effluent Dose Rate ControlIn accordance with Technical Sp ecif'ication~s 5.5.4.c and 5.5.4.g, the licensee shall conducto perations so that th e dos e rates due to radioactive materials rel eased in gaseous effluentsfrom the siteto areas at and beyondthe SITE BOUNDARY (see Figure 10-1) are limited asfollows:a. For noble gase.-s: Less than or equalto a dose rate of to the total body andless than or equal to a dose rate of 3000 /to the skin, andb. For Iodine-131, Iodine-133, tritum, and forall radionuclides in partioulate forin withhalf-lives greater than 8 days: Less than or equal to a dose rate of 1500 j~r, j~rn to anyorgan.3.1.2.1 ApplicabilityThis limit applies at all times.3.1.2.2 ActionsWith a dos e rate due to radioactive material released in gaseous effluents exceeding the limitstated in Section 3.1.2, immediatelydecrea~se the relea~se rate to within the stated limit.Entry into an Operational Mode or other specified COM)ITION shall be made if, as a minimum,the requirements ofTedinical Sp eafications LCO03.0.4 are met.3.1.2.3 Surveillance RequirementsThe dose rates dueto radioactive materials in areas at or beyondth e SITE BOUNDARY due torel eases of gaseous effluents shall be determinedto be withinthe above limits, in accordancewith the methods and procedures in Section 3.4.1, by obtaining representative samples andperforming analyses in accordance with the sam pling an d analysis program specifed inTable 3-3.3.1.2..4 BasisThis control is provided to ensure that gaseous effluent dose rates will be maintained within thelimits that historicallyhave provided reasonable assurance that radioactive material disdiargedin gas eous effluents wilN not result in a d ose to a MEMBER OF THE PUBLIC in anUNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceedingthe limitsspecified inAppendix I ofI10CFR Part 50, while allowing operational fl exibiity for effluentreleases. For MEBROFTH-E PUBLIC who may at times be withinthe SITE BOUNDARY,the occupancy ofth e MEBE OFTHE PUBLIC will be sufficiently low to compensate for anyincrease in th e atmospheric diffusion factor above that for th e SITE BOUNDARY.3-6 Version 23 213 KeFPLOO PinAI FOUEUTB'mueaTeaPFcJif0)&Co V4Page 1 of 16SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) AGE 1 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 34AR-601-902-1 I 14.41H11-P601, ALARM PANEL 1EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE:04 15N/A SSM /PM: N/A DATE: N/AANNUNCIATOR RESPONSE PROCEDURES FOR IHII-P601 -ALARM PANEL 1ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-101-1 5.1 34AR-601-113-1 2.1 34AR-601-125-1 6.234AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.234AR-601-103-1 6.2 34AR-601-1 15-1 4.1 34AR-601-127-1 6.234AR-601-104-1 3.3 34AR-601-1 16-1 5.6 34AR-601-128-1 3.234AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.134AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.034AR-601-107-1 1.1 34AR-601-119-1 1.1 34AR-601-131-1 6.334AR-601-1 08-1 2.2 34AR-601-120-1 5.2 34AR-601-1 32-1 3.334AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.134AR-601-1 10-1 4.2 34AR-601-122-1 4.1 34AR-601-1 34-1 4.334AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.534AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0II NOE Approval signature on this page constitutes approval for all procedures listed above at theNOE revision indicated. Tab numbers in the back correspond to procedure sequence number.ILevel Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneN MP-AP-002 V4Page 2 of 16PAGE 2 OF 2SOUTHERN NUCLEARPLANT E.I. HATCHDOCUMENT TITLE:ARP'S FOR CONTROL PANEL 1H11-P601,ALARM PANEL 1DOCUMENT NUMBER: VERSION NO:34AR-601-902-1 I 14.4UNIT 11H 11-P601 -1601-101 601-102 601-103

601-104 601-105 601-106601-107 601-108

601-109

601-110 601-111 601-112601-113 601-114 601-115 601-116 601-117 601-118601-119 601-120 601-121 601-122 601-123 601-124601-125 601-126 *60-2 60-2 6119 6113601-125 601-1326 601-127 601-128 601-125 601-130RECORDSThere are no records generated from this procedure.COMMITMENTSNone* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on TRIP UNIT Label(s) at 1D21-P600 to provide across-reference for locating the device(s) in Abnormal and/or EOP Tables.Refer to 34AB-T22-003-1, Secondary Containment Control.NMP-AP-002 v.2.0 V4Page 3 of 161.0 IDENTIFICATION:ALARM PANE L 601-1_____ ___RX BLDG___ __ ___RADIATION___ __ _ _ __ ___HIGHDEVICE: SETPOINT:1D21-K601A, E, F, G, H, K, L, N, P, R, S, T, U, V, W, X, Y See 64C1-CAL-002-05.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED amber upscale light and high reading on individual indicator/trip units,on 1D21-P600, Area Radiation Monitoring Panel.5.1.1 Attempt to reset Trip Unit.5.2 IF Trip Unit will NOT reset, perform the following:5.2.1 Confirm monitor reading,by checking 1D21-R600, Area Radiation Monitor Recorder, panel 1~ H1-P600. (see channels below).5.2.2 Contact Health Physics to confirm radiological condition.5.2.3 REFER to 73EP-RAD-001-0, Radiological Event.5.2.4 Periodically monitor panel 1D21-P600,to ensure that no other channels in the Reactor Building are indicating high OR in alarm.5.2.5 Enter 34AB-T22-003-1, Secondary Containment Control.5.2.6 IF a radioactive release outside the Reactor Building is occurring, OR has occurred,enter 34AB-D1 1-001-1, Radioactive Release Control.LiLILiLiLiLiLiLi6.0 CAUSES:6.1 High radiation Trip on one or more of the following indicator/trip units:1 D21 R600CHANNEL TRIP UNIT LOCATION01 1 D21-K601A Reactor Head Laydown05 1D21-K601E Drywell Shield Plug06 1D21-K601F Tip Area07 1D21-K601G 130' NE Working Area08 1 D21-K601H 130' SW Working Area09 1 D21-K601K 158' SW Working Area10 1D21-K601L Rx Wtr Smpl Rack Area 158'12 1D21-K601N South CR0 Hydraulic Units13 1 D21-K601P North CR0 Hydraulic Units14 1D21-K601R CS & RHR S-E Diag.15 1 D21 -K601 S Equipment Access Airlock16 1 D21-K601T HPCI Turbine Area17 1 D21-K601U TIP Probe Drive Area18 1D21-K601V RCIC Equipment Area SW19 1D21-K601W CR0 Pump Room NW20 1 D21-K601X RB 203' Working Area21 1D21-K601Y CS & RHR N-E Diag.6.2 Malfunctions of one or more trio unitsSENSOR1D021-N002-11 D21-N002-51021 -N002-61021 -N002-71021 -N002-81 D21-N002-91021 -N002-1 01 D21-N002-121021 -N002-1 31 D21-N002-141021 -N002-1 51021 -N002-1 61 D21-N002-171021 -N002-1 81021 -N002-1 91 D21-N002-201 D21-N002-2134AB-T22-003-1ITEM NUMBER14111416910171221152213181962

07.0 REFERENCES

8.0 TECH. SPEC./TRM/ODCMIFHA:7.1 H-17854 -H-17859, H-19598 & H-i19599, ARM Sys. 021 Elem. N/A -Not applicable to this procedure34AR-601 -104-1Ver. 3.3MGR-0048 Ver. 5 V4Page 4 of 161.0 IDENTIFICATION:ALARM PANEL 601-1________REFUELING FLOORAREA RADIATION___ __ __ ___HIGHDEVICE: SETPOINT:1 D21 -K601 B, 1 D21 -K601 D See 64C1-CAL-002-02.0 CONDITION: 3.0 CLASSIFICATION:EQUIPMENT STATUSOne OR both of the Refueling Floor Area Radiation Monitors has 4.0 LOCATION:exceeded its setpoint.1H-P0Pae6015.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/trip unitson panel 1D21-P600. Li5.1.1 Attempt to reset trip unit. LI5.2 Confirm Control Room ventilation shifted to pressurization (Mode II),per 34SO-Z41-001-1, Control Room Air Conditioning System. LI5.3 IF trip unit will NOT reset, perform the following:5.3.1 Confirm monitor reading by checking 1D21-R600, Area Radiation Monitor Recorder,panel 1Hi11-P600. (see channels below) Li5.3.2 Contact Health Physics to confirm radiological condition in the affected area,evacuate area IF required. LI5.3.3 Periodically monitor panel 1D21-P600,to ensure that no other channels on the Refueling Floor are indicating high OR~ in alarm. Li5.3.4 Enter 34AB-T22-003-1, Secondary Containment Control. Li5.3.5 Refer to 73EP-RAD-001-0, Radiological Event. Li5.3.6 IF a radioactive release outside the Refueling Floor is occurring, OR has occurred,enter 34AB-D1 1-001-1, Radioactivity Release Control. Li6.0 CAUSES:6.1 High radiation causing one OR both of the following indicator/trip units:MONITOR CHANNEL TRIP UNIT LOCATION SENSOR02 1D21-K601B Refueling Floor Stairway 1D21-N002-204 1D21-K601D Refueling Floor 1D21-N002-46.2 Malfunction of trip unit.

7.0 REFERENCES

8.0 TECH. SPEC./TRMIODCM/FHA:7.1 H-17854 thru H-17859, H-19598 and H-19599, AreaRadiation Monitoring Sys. D21 Elem Diag N/A -Not applicable to this procedure34AR-601-1 10-1Ver. 4.2MGR-0048 Ver. 5 V4Page 5 of 161.0 IDENTIFICATION:__ALARMPANEL 601-1 __________ __ __ ___NEW FUEL__ __STORAGE AREA__ __ __RADIATION HIGHDEVICE: SETPOINT:1 D21-K601C 64CI-CAL-002-01 D21-K601M2.0 CONDITION: 3.0 CLASSIFICATION:2.1 Radiation level in vicinity of Spent Fuel Pool Demineralizer EQUIPMENT STATUSEquipment ARM has exceeded its setpoint 4.0 LOCATION:2.2 Radiation level in vicinity of Spent Fuel Pool & New Fuel Storage 1H11-P601 Panel 601-1ARM has exceeded its setpoint2.3 Loss of power to either of the above listed ARMs5.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/tripunits on panel 1D21-P600. LI5.1.1 Attempt to reset trip unit. LI!5.2 IF trip unit will NOT reset, perform the following:5.2.1 Confirm monitor reading by checking 1D21-R600, Area Radiation Monitor Recorder,on panel 1H1 1-P600. (see channels below) LI5.2.2 Contact Health Physics to confirm radiological condition in the affected area ANDevacuate area IF required. LI5.2.3 Periodically monitor 1D21-P600, panel, to ensure that no other channels on theRefueling Floor are indicating high OR in alarm. 135.2.4 Enter 34AB-T22-003-1, Secondary Containment Control. LI5.2.5 Refer to 73EP-RAD-001-0, Radiological Event. III5.3 If neither ARM is reading high, then at 1 R25-S064, confirm BRKR 9 is CLOSED. El5.4 IF an abnormal radioactive release is occurring OR has occurred,enter 34AB-D1 1-001-1, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation causing one or both of the following indicator/trip units to alarm:1D21-R600 POINT TRIP UNIT LOCATIONNUMBER SENSOR3 1D21-K601C, Spent Fuel Pool Demin Equip 1D21-N002C11 1D21-K601 M, Spent Fuel Pool & New Fuel Storage 1D21-NO02M6.2 Loss of power to ARM's

7.0 REFERENCES

8.0 TECH. SPEC./TRMIODCMIFHA:7.1 H-17854 & H-17856, ARM Sys. D21 Elem. Diag. N/A -Not applicable to this procedure34AR-601-127-1Ver. 6.2MGR-0048 Ver. 5 V4Page 6 of 16DOCUMNT TTLE:DOCUMENT NUMBER: VERSION NO:ARP'SALRFOR PAECONTROL4 PANEL 1H11-P601, 34AR-601-901-1 12.4EXPIATIN APROVLS:EFFECTIVEDATE: DEPARTMENT MANAGER DAK for Keith D. Lonq DATE 5-9-13 DATE:N/A SSM/PM N/A DATE N/A 5-15-15ANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601 -ALARM PANEL 4ARP NO. Ver, NO. ARP NO. Ver.NO. ARP NO. Ver. NO.34AR-601-401-1 0.4 34AR-601-413-1 0.4 34AR-601-425-1 4.434AR-601-402-1 3.4 34AR-601-414-1 3.3 34AR-601-426-1 3.534AR-601-403-1 3.5 34AR-601-415-1 1.5 34AR-601-427-1 1.334AR-601 -404-1 0.2 34AR-60 1-416-1 1.3 34AR-601 -428-1 4.634AR-601-405-1 7.1 34AR-601-417-1 4.6 34AR-601-429-1 2.234AR-601-406-1 7.3 34AR-601-418-1 3.3 34AR-601-430-1 0.234AR-601-407-1 1.5 34AR-601-41 9-1 0.2 34AR-601-431-1 1.134AR-601 -408-1 1.5 34AR-601 -420-1 4.5 34AR-601 -432-1 4.334AR-60 1-409-1 5.5 34AR-60 1-421-1 4.3 34AR-601 -433-1 0.134AR-601-410-1 2.2 34AR-601-422-1 3.5 34AR-601-434-1 2.134AR-601-411-1 3.6 34AR-601-423-1 3.6 34AR-601-435-1 034AR-60 1-412-1 4.5 34AR-60 1-424-1 2.5 34AR-601 -436-1 0INOTE Approval signature on this page constitutes approval for all procedures listed above at the IVersion indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneI V4Page 7 of 16UNIT 11H11-P601-4601-401 601-402 601-403 601-404 601-405 601-406601-407 601-408 601-409 601-410 601-411 601-412601-413 601-414 601-415 601-416 601-417 601-418601-419 601-420 601-421 601-422 601-423 601-424601-425 601-426 601-427 601-428 601-429 601-430601-431 601-432 601-433 601-434 601-435 601-436RECORDSNo Records are generated by this procedure.COMMITMENTSSNC1 9472, SNC5027 V4Page 8 of 161.0 IDENTIFICATION:ALARM PANEL 601-4 __________REFUELING FLOOR___ __ __ ___VENT EXHAUST___ __ __ __ ___RADIATION HI-HIDEVICE: SETPOINT:1D11-K611A thru D 18 mr/hr2.0 CONDITION: 3.0 CLASSIFICATION:EMERGENCYRadiation levels in the Refueling Floor Exhaust Duct exceed the 4.LOAINsetpoint.1H11-P601 Panel 60 1-45.0 OPERATOR ACTIONS:5.1 Confirm the annunciator by monitoring 1 D11-R607, Recorder, panel 1H11-P600. D]5.1.1 Monitor the R/F VENT EXHAUST RAD MON, 1 HI1-P606; IF only one trip unit is affected,attempt to reset the affected trip unit. Eli5.2 IF only one trip unit is alarmed, AND the unit is not malfunctioning,determine and correct the cause of the high high radiation. LI5.3 IF" the A AND B, OR the C AND D OR all channels of trip unit 1 D11-K61 1 are tripped,enter 31EO-EOP-014-1, SC-Secondary Containment Control, andperform concurrently with this procedure. Eli5.4 IF refueling is in progress, STOP refueling operations, andif possible, insert any withdrawn Control Rods. LI5.5 Evacuate personnel from the Refueling Floor. LI5.6 IF: refueling or fuel handling was in progress,ENTER 34AB-J11-001-1, Irradiated Fuel Damage During Handling. LII5.7 IF" an abnormal radioactive release is occurring,ENTER 34AB-D1 1-001-1, Radioactive Release Control. LI6.0 CAUSES:6.1 High radiation levels in the vent duct6.2 Trip unit failure, upscale or downscale

7.0 REFERENCES

8.0 TECH. SPECS./TRMIODCM/FHA:7.1 H-19551 through H-19566, H19578, H19584, & H19596, 8.1 Secondary ContainmentProcess Radiation Monitoring System Elem Diag Isolation Instr Table 3.3.6.2-134AR-601 -403-1Ver. 3.5 V4Page 9 of 161.0 IDENTIFICATION:ALARM PANEL 601-4 ___________ __ ___RX BLDG POT___ __ __ __ ___CONTAM AREA______-VENT RADN HI-HIDEVICE: SETPOINT:1 D11-K609A 1ID11-K609B 18 mr/hr1D1 1-K609C, 1 D1 1-K609D5.0 OPERATOR ACTIONS:5.1 Confirm annunciator by monitoring the radiation level on 1D11-R605, recorder, 1H11-P600. LI5.1.1 Monitor 1 D11-K609A, ID11-K609B, 1ID11-K609C, 1D1I-K609D, Reactor BuildingPotential Contaminate Area Rad Monitors, 1Hi 11-P606.IF only one trip unit is affected, attempt to reset the affected trip unit. Eli5.2 IF only one trip unit is alarmed AND the unit is not malfunctioning,determine and correct the cause of the high high radiation. LI5.3 IF the A AND B, OR the C AND_ D OR all channels of trip unit 1 D11-K609, are tripped,ENTER 31EO-EOP-014-1, SC-Secondary Containment Control. III5.4 IF an abnormal radioactive release is occurring,ENTER 34AB-D1 1-001-1, Radioactivity Release Control. LI6.0 CAUSES:6.1 Primary leakage

7.0 REFERENCES

8.0 TECH. SPECS./TRM/ODCM/FHA:7.1 H-19561, H-19564, H-19563, & H-19566, Process 8.1 Unit 1 T.S. 3.3.6.1Radiation Monitoring System Elem Diag 8.2 Unit 1 T.S. 3.3.6.27.2 H-16005, Reactor Building Vent System P&ID34AR-60 1-426-1Ver. 3.5 V4Page 10 of 16SOUTHERN NUCLEAR IDOCUMENT TYPE:IPLANT ElI. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) PAGE 1 OF 2DOCUMENT TITLE: NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 2H1 1-P601, ALARM PANEL 3 l 34AR-601-904-2 12.18EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER G. L. Johnson DATE 04/19/00 DATE:8/31/15N/A SSM /PM N/A DATE N/A _____ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601 -ALARM PANEL 3ARP NO VER. NO. ARP NO. VER. NO. ARP NO VER. NO.34AR-601 -301-2 3.1 34AR-601 -31 3-2 3.5 34AR-60 1-325-2 2.334AR-60 1-302-2 3.2 34AR-60 1-314-2 2.4 34AR-60 1-326-2 0.534AR-601-303-2 3.3 34AR-601-315-2 1.2 34AR-601-327-2 5.234AR-601 -304-2 3.2 34AR-60 1-316-2 0.2 34AR-60 1-328-2 2.234AR-601 -305-2 0.3 34AR-601 -317-2 2.1 34AR-601 -329-2 1.334AR-60 1-306-2 3.3 34AR-601 -318 SPARE 34AR-60 1-330-2 2.234AR-601-307-2 2.4 34AR-601-319-2 0.3 34AR-601-331-2 2.334AR-601-308-2 2.3 34AR-601-320-2 1.2 34AR-601-332-2 0.334AR-601-309-2 1.2 34AR-601-321-2 4.2 34AR-601-333-2 0.334AR-601-310-2 0.4 34AR-601-322-2 0.6 34AR-601-334 SPARE34AR60131 12 03 3AR-61-33-2 .3 4AR601 4.34AR-601-311-2 4.3 34AR-601-323-2 2.4 34AR-601-335-2 04.SNT:IApproval signature on this page constitutes approval for all procedures listed above at the !NOErevision indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneMGR-0002 VER. 8.1 V4of 16UNIT 22H11-P601 -3601-301 601-302 601-303 601-304 601-305

601-306601-307 601-308 601-309 601-310 601-311

601-312601-313 601-314 601-315 601-316 601-317 601-318601-319 601-320 601-321 601-322

601-323 601-324601-325 601-326 601-327 601-328 601-329 601-330601-331 601-332 601-333 601-334 601-335 601-336* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on Trip Unit Label(s) at 2D21-P600 to provide across reference for locating the device(s) in ABNORMAL AND/OR EOP Tables.Refer to 34AB-T22-003-2, Secondary Containment Control.RECORDSNo records are generated from this procedure.COMMITMENTSNONEMGR-0001 VER. 4 V4Page 12 of 161.0 IDENTIFICATION:ALARM PANEL 601-3-II--IIrREFUELING FLOORAREA RADIATIONHIGHDEVICE: SETPOINT:2D21-K601-A,E,M See 64CI-CAL-002-02D21-K61 1-K,L5.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light AND~ high reading on individual indicator/tripunits on panel 2D21-P600. LI5.1.1 Attempt to reset Trip Unit. LI5.2 IF 2D21-K601 A O._R M Tripped,THEN confirm Control Room ventilation shifted to pressurization (Mode II) per34SO-Z41-001-1, Control Room Ventilation System. LI5.3 IF Trip Unit will NOT reset, perform the following:5.3.1 Confirm monitor reading by checking 2D21-R600A, Area Radn Monitor Recorder,panel 2H1 1-P600 (see channel below) Lii5.3.2 Contact Health Physics to confirm radiological condition in the affected area,evacuate area IFrequired. LI5.3.3 Periodically monitor panel 2D21-P600 to ensure no other channels on the RefuelingFloor are indicating high OR in alarm. LI5.3.4 Enter 34AB-T22-003-2, Secondary Containment Control. LI5.3.5 IF a radioactive release outside the Reactor Building is occurring, OR has occurred,enter 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation causing a trip of one ORR more of the following indicator trip unitsMONITOR CHANNEL LOCATION SENSOR TRIP UNIT1 Reactor Head Layout Area 2D21-N002-A K601-A5 Dryer/Separator Pool 2D21-N002-E K601-E10 Spent Fuel/Fuel Pool Areas 2D21-N002-M K601-M21 Reactor Vessel Refueling Area 2D21-N012-K K61 1-K22 Reactor Vessel Refueling Area 2D21-N012-L K61 1-L6.2 Malfunction of trip unit

7.0 REFERENCES

8.0 TECH. SPECS./TRMIODCMIFHA:7.1 H-27805 thru H-27810 and H-27992, Area RadiationMonitoring Sys 2D21 Elementary Diagram 8.1 TRM Table T3.3.7-134AR-60 1-312-2Ver. 4.3MGR-0048 Ver. 5.0 A-GR7- 0AG-MGR-75-1101 V4Page 13 of 16SOUTHERN NUCLEAR )OCUMENT TYPE:PLANT ElI. HATCH lANNUNCIATOR RESPONSE PROCEDURE (ARP PAGE 1 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO:ARP'S FOR CONTROL PANEL 2HI11-P601, 34AR-601-901-2 l 12.1ALARM PANEL 4/EXPIRATION APPROVALS: IEFFECTIVEDATE: DEPARTMENT MANAGER DAK for Keith D. Long DATE 5-9-13 I DATE:N/A SSM/PM N/A DATE N/A 5-i5-I5ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601 -ALARM PANEL 4ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-401-2 0.3 34AR-601-413-2 1.2 34AR-601-425-2 3.434AR-60 1-402-2 4.1 34AR-60 1-414 Spare 34AR-60 1-426-2 6.334AR-601-403-2 5.4 34AR-601-415-2 1.0 34AR-601-427-2 2.334AR-60 1-404-2 0.3 34AR-60 1-416-2 0.5 34AR-60 1-428-2 5.534AR-60 1-405-2 8.1 34AR-60 1-417-2 4.3 34AR-60 1-429-2 3.134AR-60 1-406-2 8.3 34AR-60 1-418-2 1.2 34AR-60 1-430-2 0.334AR-60 1-407-2 3.6 34AR-60 1-419-2 1.1 34AR-60 1-431-2 2.134AR-601-408-2 1.0 34AR-601-420-2 6.3 34AR-601-432-2 4.334AR-601-409-2 5.3 34AR-601-421-2 4.3 34AR-601-433-2 1.434AR-601-410-2 2.3 34AR-601-422-2 5.4 34AR-601-434-2 3.034AR-601-411-2 4.5 34AR-601-423-2 4.4 34AR-601-435-2 1.134AR-601-412-2 0.4 34AR-601-424-2 2.3 34AR-601-436-2 0.1IINOTE Approval signature on this page constitutes approval for all procedures listed above at theI Version indicated. Tab numbers in the back correspond to procedure sequence number.FILevel Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO None V4Page 14 of 162 OF2SOUTHERN NUCLEARPLANT E.I. HATCHDOCUMENT TITLE: 'DOCUMENT NUMBER: VERSION NO:ARP'SALRFORpAECONTROL4 PANEL 2H11-P601, 34AR-601-901-2 1 12.1UNIT 22H1 1-P601 -4601-401 601-402 601-403 601-404 601-405 601-406601-401 601-408 601-409 601-410 601-411 601-412601-413 601-414 601-415 601-416 601-417 601-418601-419 601-420 601-421 601-422 601-423 601-424601-425 601.426 601-427 601-428 601-429 601-430601-431 601-432 601-433 601-434 601-435 601-436RECORDSThere are no records generated from this procedure.COMMITMENTSSNC5027 V4Page 15 of 161.0 IDENTIFICATION:ALARM PANEL 601-4T 11 T T -1-4-1REFUELING FLOORVENT EXHAUSTRADIATION HI-HIDEVICE:2D11-K611 A thru D2D11-K634 Athru D2D11-K635 Athru DSETPOINT:18 mr/hrPER 64Cl-CAL-002-0PER 64CI-CAL-002-02.0 CONDITION: 3.0 CLASSIFICATION:Radiation levels in the. Refueling Floor Exhaust Duct exceed EMERGENCYthe setpoint. 4.0 LOCATION:2H11-P601 panel 601-45.0 OPERATOR ACTIONS:5.1 Confirm the annunciator by monitoring recorders on panel 2H1 1-P600:* 2D11-R615 for 2D11-K611A &2D11-K611 B, and 2D11-K634A -D LI* 2D11-R616 for 2D11-K611C &2D11-K611D, and 2D11-K635A- D Lii5.1.1 Monitor the R/F Vent Exhaust Rad Mon on 2H11-P606;IF only one trip unit is affected, attempt to reset the affected trip unit. LI5.2 IF only one trip unit is alarmed, AND the unit is NOT malfunctioning,determine AND correct the cause of the high high radiation. Eli5.3 IF refueling operations are in progress,STOP refueling operations ANDIF possible, insert any withdrawn Control Rods. LI5.4 Evacuate personnel from the Refueling Floor. LII5.5 IF refueling OR fuel handling was in progress,enter 34AB-J1 1-001-2, Irradiated Fuel Damage During Handling. LI5.6 For valid alarm conditions, enter 31EO-EOP-014-2, SC-Secondary ContainmentControl AND 34AB-T22-003-2, Secondary Containment Control. LI5.7 IF an abnormal radioactive release is occurring OR has occurred,ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation levels in the vent duct6.2 Trip unit failure, upscale OR downscale ___________________

7.0 REFERENCES

8.0 TECH. SPECS./TRMIODCMIFHA:7.1 H-27629 and H-27631, Process RadiationMonitoring Diagram, Sheets 10 and 12 8.1 U2 TS 3.3.6.1 Table 3.3.6.1-17.2 H-27596 thru H-27600, Primary ContainmentIsolation System, Sheets 1 through 5 8.2 U2 TS 3.3.6.2 Table 3.3.6.2-134AR-60 1-403-2VER. 5.4 V4Page 16 of 161.0 IDENTIFICATION:ALARM PANEL 601-4________RX BLDG POT___ CONTAM AREAVENT RADN HI-HIDEVICE: SETPOINT:2011l-K609A through 0, Per 64CI-OCB-006-2, Form HPX-1 252, from ChemistryTrip Indicator Unit2.0 CONDITION: 3.0 CLASSIFICATION:Radiation levels on the inlet to 2T41-D005, Reactor Building EMERGENCYExhaust Filter Train, exceeds the setpoint. 4.0 LOCATION:2H11-P601 panel 601-45.0 OPERATOR ACTIONS:5.1 On panel 2H1 1-P600, confirm annunciator by monitoring the radiation level on2D1 1-K609A/2D1 1-K609B/2D11l-K609C/2D1 1-K609D on 2D1 1-R605 recorder. El5.1 .1 Monitor 2011 -K609A through D, Reactor Building Potential Contaminated AreaRad Monitors, on 2H11-P606.IF only one trip unit is affected, attempt to RESET the affected trip unit. LI5.2 IF only one trip unit is alarmed AND the trip unit is NOT malfunctioning,determine AND correct the cause of the high high radiation. El5.3 IF the A & B, O._R the C & D O__R all channels of trip unit 2D1 1-K609 are tripped,THEN enter 31EO-EOP-014-2, SC-Secondary Containment Control ANDconfirm Automatic Actions per 34AB-T22-003-2, Secondary Containment Control,Attachment 7. LI5.4 IF an abnormal radioactive release is occurring OR has occurred,ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 Steam leaks

7.0 REFERENCES

8.0 TECH. SPECS./TRM/ODCMIFHA:7.1 H-27629, H-27631, H-27632, & H-27634, Process 8.1 U2 TS 3.3.6.1Radiation Monitoring System Elem. Diag.7.2 H-26067 Reactor Zone Ventilation System P&ID34AR-601 -420-2VER. 6.3 VSPage 1 of 3SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE ('ARP' AGE 1 OF 2V5Page 1 of 3DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 34AR-601-902-1 ] 14.41H11-P601, ALARM PANEL 1EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE:04-30-15N/A SSM /PM: N/A DATE: N/AANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601 -ALARM PANEL 1ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-101-1 5.1 34AR-601-113-1 2.1 34AR-601-125-1 6.234AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.234AR-601-103-1 6.2 34AR-601-115-1 4.1 34AR-601-127-1 6.234AR-601-104-1 3.3 34AR-601-116-1 5.6 34AR-601-128-1 3.234AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.134AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.034AR-601-107-1 1.1 34AR-601-1 19-1 1.1 34AR-601-1 31-1 6.334AR-601 -108-1 2.2 34AR-601 -120-1 5.2 34AR-601-1 32-1 3.334AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.134AR-601-110-1 4.2 34AR-601-122-1 4.1 34AR-601-134-1 4.334AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.534AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0NOTE:______ Approval signature on this page constitutes approval for all procedures listed above at the~ NOTE:revision indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneNMP-AP-002I V5Page 2 of 3SOUTHERN NUCLEARPLANT E.I. HATCHPAGE 2 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO:ARP'S FOR CONTROL PANEL 1H11-P601, 34AR-601-902-1 1 14.4ALARM PANEL 1UNIT 11H11-P601 -1601-101 601-102 601-103 *601-104 601-105 601-106601-107 601-108

601-109

601-110 601-111 601-112601-113 601-114 601-115 601-116 601-117 601-118601-119 601-120 601-121 601-122 601-123 601-124601 -1 25 601 -1 26 601-1 27 601-1 28 601-1 29 601 -130601-131 601-132 601-133 601-134 601-135 601-136RECORDSThere are no records generated from this procedure.COMMITMENTSNone* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on TRIP UNIT Label(s) at 1D21-P600 to provide across-reference for locating the device(s) in Abnormal and/or EOP Tables.Refer to 34AB-T22-003-1, Secondary Containment Control.NMP-AP-002 v.2.0 V5Page 3 of 31.0 IDENTIFICATION:ALARMPANEL_601-1 ___________ __ ___TURBINE BLDG__RADIATION___ __ ___HIGHDEVICE: SETPOINT:SEE SECTION 6.0 AS PER THE CHEMISTRY CONTROLLED SETPOINT RECORD5.0 COPERATIOR: ACTIONS:FCATON5.1 At 1D21-P600, monitor ARMs listed in Section 6.0,to determine which monitor(s) indicates high, to assess the severity, and monitor for trends. LI5.1.1 Attempt to reset the trip unit. Iii5.2 Notify Health Physics to determine the validity of the alarm. LI5.3 IF the alarm is valid,enter 73EP-RAD-001-0, Radiological Event. LI5.4 Refer to 34AB-U22-001-1, Pipe Break in Turbine Building, for possible entry conditions. LI5.5 IF a radiation release to outside the Turbine Building has occurred OR is occurring,enter 34AB-D1 1-001-1, Radioactivity Release Control. LI5.6 IF a Fuel Element Failure is confirmed,Initiate Turbine Building Purge per 34SO-U41-001-1 radiation. LI5.7 Monitor other ARM's that are associated with this annunciator for increasing radiation. LI6.0 CAUSES:High radiation, as indicated by one of the following ARM's:1D21-R600 POINT NUMBER MONITOR AREA22 1D21-K600A Main Turbine Front Standard23 1D21-K600B Control Room24 1 D21-K600C Control Room25 1D21-K600D T/B 164' North End Operating Floor26 1D21-K600E Turbine Bldg Feedwater Area27 121-K01ZCondensate Demin Area34AR-601-1 16-1Ver. 5.6MGR-0048 Ver. 5

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+{{#Wiki_filter:SM-SNC524602-001IAttachment IENERCON Calculation for E-HU1SHEET I-6 v15Page 1 of 3CALC NO. SNC024-CALC-003FNP DETERMINATION OFEMERGENCY ACTION LEVEL REV. 0PAGE NO. Page 6 of 85.0 Design Inputs1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask systemtechnical specification [2, Table 6.2-3] are provided below in Table 5-1. Thesesource values are scaled to develop the emergency action levels for initiatingcondition E-HU1.Table 5-1 Technical Specification Dose Rate Limits (Neutron + Gamma) for HI-STORM100 and HI-TRAC 125LocaionNumber of 1Technical SpecificationjMeasurementsj Limit (mrem/hr)HI-TRAC 125Side -Mid -height T 4 1680.3Top 1 4 j129.4HI-STORM 100Side -60 inches below mid-height 4 171.8Side -Mid -height 4 177.0Side -60 inches above mid-height 4 84.7Top -Center of lid 1 27.1Top -Radially centered 4 30.0Inlet duct 4 231.8Outlet duct 4 82.2 SM-SNC524602-001Attachment IIPNI::IlNN (.'l'ml:afinn fnr IF..WI I1SHEET I-7 v15Page 2 of 3CALC NO. SNCO24-CALC-003FNP DETERMINATION OF ___________EMERGENCY ACTION LEVEL REV. 00I EN ER C ON FORI=NITATNG CONDITION E- _ _______..."' HUl PAGE NO. Page 7 of 86.0 MethodologyThe "on-contact"' dose rates from the technical specification for the HI-STORM 100 andHI-TRAC 125 cask system are scaled by a factor of 2, as specified in NEI 99-01 Rev. 6[1], for use in initiating condition E-HU1.
+SM-SNC524602-001Attachment II:PCANI (%lrdp-mi6*rn fr i::._WI I1SHEET I-8 v15Page 3 of 3CALC NO. SNC024-CALC-003FNP DETERMINATION OFEMERGENCY ACTION LEVEL REV. 00 E N E R C 0 N FOR INITAliNG CONDITION E-HUl PAGE NO. Page 8oft87.0 CalculationsThe dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose ratelimits. These calculations are presented below in Table 7-1.wTable 7-1 Dose Rate Scaling Calculations for EAL Limits (Neutron + Gamma)TechnicalLoainSpecification Scaling Calculated Value EALLoainLimit Factor .(mremn/hr) (mrem/hr)_______________________ (mremlhr) ____________ _____________ ______ ______ ______HI-TRAC 125 _ _ _ _ _ _ _ _ _ _ _ _ _ _Side -Mid -height [ 680.3 j 2 J 1360.6 1360Top L 129.4 j 2 258.8 260Side -60 inches below mid-heightSide -Mid -heightSide -60 inches above mid-heightTop -Center of lidTop -Radially centeredInlet ductOutlet duct171.8177.084.727.130.0231.882.2343.6 340354 350169.4 17054.2 5060 60463.6 460164.4 1608.0 Computer SoftwareMicrosoft WORD 2Q13 is used in this calculation for basic multiplication.
+V16LYN I Page 1o of 8CORE COOLING Revision 17P SSFIFTH NOHOTTEST ITC LESS iGO TOSATaPage1 ofI1 V16N !T 1Page 2 of 8HEAT SINK Revision 17FRP4.LI~GO TOFRP-H.2PRESS IN INOIALL SG'S L.EBB THAN""GO TOFRP-H.3NAR RNG NLVL IN ALL LSO'S LESS '--'THAN 62 1YESJGOTOr FRP-H.4PRESS IN NALL SG'SLESS THAN,,,,,1075 P8I10YEGO TO-I FRP-4.5CSFSAT 1V16Page 3 of 88/29/2007 08:3 3FNP-I-CSF-O.4 INTEGRIT Revision 17I-f,' GO TOFRP.P.1JGO TOinininm m --t aFRP-.2CSFSATGO TOGOOTSATSATPagI 1 f2
+[NI 1Page 4of 8FP1CSF-0. COTANMN Geson TOPRESS NO in in, -FRP-Z.1LESS ri- !THAN 5 YEs At LEAST ONE NOIPUMP RUNNING-- --OTI (FLOW>IODOOGPM) YES ,. 2I CTMT koI S~UMP LVL NCTMT [THAN 7.6 I=:LESS HTHAN 27 YsGO TOPSIG FRPZ.SUMP LVL.NLESSTHAN 7.6HFT.~GO TOFRP-Z.3BOTHCTMT RAD NLESS --hrTHAN 2 R/ LY1CSPage 1 of I 1I]IJIT9Vi16Page 5 of 88/29/2007 08:33 -FNP-2-CSF-0,2 CORE COOLING Revision 12GOTOoIP I m IIFRP-C.1HOTTEST NORP.CCORE EXITTHAN YETHANT790TCREXIT---,TC LSSTC HESSUBOO NO GO TOCOR PRP-C.30 EXIOT TCS "-iGRTR THAN Ei16" F 145"F}Page1 of 1 V1 6!]N IT 2Page 6 of 8FNP-2-CSF-O0.3 HEAT SINK Revision 12SGO TOFRP-K.1miTOTAL AFW NOIiFLOW TO I1 ALL SG'8 -,-,395 GPM EGO TO~FRP-HL2LVL IN AT IN NOLEAST ONE ALL SG'SSG GRTR --'-LESS THANTHAN 31% YES __ _______ 1129PSIG YES,[ GO TO! f FRP-H.3MiAR RNG [N]LVL IN ALLSGS8 LESS mmmTHAN 52% YESGO TO-I FRP-H.4PRESS IN NOALL 5G5S:ILESS THANmmg1075 P810 YESGO TOI r FRP-H.5CSFSATPage 1 of I V167 of 8FNP-2-CSF-O.4 IINTEGRITY Revision 12COLD LGTMEAUE('F GO TOW FRP-P,1ALL RCSPRESS- OTCL TEMP (IN m -ine e lRIGHT OF YES ,.,i_AL. RCS CL N OTTEMPS INGOTSLAST 60 MIN -,FRP..P.2GRTIR THAN--'---- L RCS CL N~ TEMP TEMPNO SALALATT600MINLESSR ThANTEM DCRNN OJ SALESTRTTAHAN GOT326' F SATCSFSATPage I of 2 Vi16*l Page 8 of 88/29/2007 08:33 I NJ J .FNP-2-CSF-0.5 CONTAINMENTReion1H CTMT TI _O__OPRESS NO R "P .L "I m-~-LESS H-- 11THAN 5 YES At LEAST ONE NORUNNING(FLOW1 000GPM)YESFnI *m WRP-Z.2SUMP LVL OICTMT- THAN 7.6[PRESS NLESS- SITHAN 27 YEs GO TOPSIG jjFRP-Z.1SUMP LVI NOLESS H.-THAN 7.6 YEFT.GO TOFRP-Z.31THAN2RJ [EST SATPage 1 of I V1 7Page 1 of 807/13/15 09:23:59 LOCATION FiUlSETPOINT: 1. Variable, as per FNP-1-RCP-252 HIRMSORIGIN: Any of the below listed Area, Process or Gaseous and HI-RADParticulate Monitors: R01, R02, R03, R04, RO5, R06,R07, R08,-R1OI RI1, R12, RI3,[T RI5, RI7A ________R17B, RIS8, R-I19, R20A, R20B, R21, R23A orR23B.PROBABLE 1 .High Radiation Level in the System, Area or at the Component monitored.2. The radiation monitors fail to a "High Radiation" condition on loss ofinstrument and/or control power that will result in actuation of associatedautomatic functions.AUTOMATIC ACTIONS;I. The following actions will occur if a High Radiation Alarm is actuated onthe associated Radiation Monitor.A. R14: (Plant Vent Gas) closes Waste Gas Release ValveI -G WD-HV-0 14.8. R16: None -abandoned in place per MDC 1040589501.C. R17A or B: (Component Cooling Water) closes QIPIYRCV3028CCW SRG TANK VENT.D. R18: (Liquid Waste Processing) closes Liquid Waste Release ValveI -L WP-RC V-0 18.E. R19: (Steam Generator Blowdown) isolates Steam GeneratorBlowdown Sample Lines.F. R23A :( Steam Generator Blowdown Processing) closes1-BD-FC V-I1152 SIG Blowdown Heat Exchanger Outlet FCV.G. R23B :( Steam Generator Blowdown Processing) closesI-BD-RCV-023B SQ BLOWDOWN PMP DISC.Page 1 of 15Page 1of 15Version 72.1 V1 7Page 2 of 807/13/15 09:23:59FNP-I-ARP-I .6LOCATION FHI.*RADIATION MONITOR TABLEI -p y pLOCATIONDETECTORFUNCTIONACTIONSR-IA Control Room (Unit I Area G-M (W) Perform Step____ Panel) _ _ _ _ _ __ 4.1R-I B Technical Support Center Area G-M ( W ) No input to__ _(Unit II Panel) R-IB _______ ____this alarmR-2 Containment (155' elev) Area G3-Mr ( W) Starts IPC dose Perform Steps____ ________integration 4.2R-3 Radiochemistry Lab (AB Area G-M (W~) Perform Step_ _ _ _ 139') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.3R-4 #3 Charging Pump (AB Area G-M (_W ) Perform StepI__ _ 00') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.4R-5* Spent Fuel Pool Room (AB Area G-M (_.W) Perform Steps_ _ _ _ 155') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 4.5R-6 Sampling Room (AB 139') Area G-M ( _W) Perform Step____ __ ____ ___ ___4.6R-7 In-core NIS Area (CTMT Area G-M ( W) Starts [PC dose Perform Steps____129', near Seal Table) ___________integration 4.7R-8 Drumming Station (AB Area G-M (W ) Perform Step_ _ _ _ 155') _ _ _ _ _ _ _ _ _ __4.8R-9 SG Sample Panel (Unit II Area G-M ( W ) No input toPanel) (AB 139') ___ _____this alarmR-0 Penetration Room Filtration APD Beta Scint Perform StepDischarge (AB 155') ____**(GA-ES) 4.9R-I 1
+* Containment Atmosphere APD Beta Scint Perform Step(AB 121') **__ (GA-ES) _______4.10*Technical Specification related**General Atomics Electronic SystemsPage 5 of 15 Vrin7.Version 72.1 V17Page 3 of 807/13/15 09:23:59FNP-1-.ARP-1 .6LOCATIONFHRADIATION MONITOR REFERENCE TABLE (cont)RELOCATION TYPE~ DETECTOR FUJNCTION ACTIONSR- 12" Containment Atmosphere Gas Beta Scint Perform Step____(AR 121') ___ **(OA-.ES) ________4.11lR-1 3 Waste Gas Compressor Gas G-M ( _W) Perform StepSuction (AB 100' WGC 4.12Valve Room) _________________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform StepODCM ________ __4.13R- i 5A Condenser Air Ejector Gas G-M ....Perform StepODCM Discharge Header (TB 155') 4.14R-I 5B* Condenser Air Ejector Gas G-M (Eberline) Perform Step(Intermediate Range) (T 4.15R-I 5C* Condenser Air Ejector Gas Ion Chamber Perform Step____(High Range) (TB 189') (berline) _______4.15R-1 7A Component Cooling Water Liquid Scint. ( W) Closes CCW Perform Step(CCW H-x Room) surge tank vent 4.16_______ ~~(RCV-3028) ______R-17B Component Cooling Water Liquid Scint. Closes CCW Perform Step(CCW Hx Room) surge tank vent 4.16______ _____ ___________(RCV-3028)R-1 8 Waste Monitor Tank Pump Liquid Scint. ( W) Closes RCV-1 8 Perform StepODCM Discharge (AB 121' at the 4.17______Batching Funnel) _____R-19 Steam Generator Liquid Scint. (YWL) Isolates sample Perform StepBlowdown/Sample (AR lines 3328, 4.1 8____139') _______3329, 3330 ______R-20A Service Water from Liquid Scint. ( W) Perform StepContainment Coolers A and 4.19B (AB 121' BTRS Chiller______ Room)__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R-20B Service Water from Liquid Scint. ( _W) Perform StepContainment Coolers C and 4.19______D (AB 121') ____________ __ _____*Technical Specification related**General Atomics Electronic SystemsPage 6 of15 Vrin7.Version 72.1 V1 7Page 4 of 807/1 3/15 09:23:59FNP-I-ARP-1 .6LOCATION FillRADIATION MONITOR REFERENCE TABLE (cont)RE LOCATION TYP DIETECTR FUNCTON ACTIONSR-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____ ____________ ____(Victoreen) 4.20R-22 Plant Vent Stack Gas G-M (_W Perform StepODCM (AB 155') -)_______________ 4.21R-23A SG Blowdown Surge Tank Liquid Scint. (__) Closes Perform StepInlet (AB 130') ____FCV-1152 4.22R-23B SG BLOWDOWN PMP Liquid Scint. ( __i) Closes Perform StepODCM DISC (AB 130') ___ _____RCV-23B 4.22R-24A* Containment Purge (AB Gas Scint. Closes No input to155') containment this alarmpurge supply &exhaust dampers2866C & 2867C____________ _______and 3198A &DR-24B* Containment Purge Gas Scint. Closes valves: No input to(AB 155') (Victoreen) 2866D &2867D, this alarm3196,3197,____________ _______3198B & CR-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input toR-25B* (AB 184') (Victoreen) supply and this alarme~xhaust fans;closes SEPH-VAC supplyand exhaustdampers; startsassociated trainsof penetration_____________ __ _ ________room filtration. ____R-27A* Containment (High Range) Area Ion Chamber No input to_____ _____________ ____(Victoreen) _ ______this alarmTechnical Specification relatedPage 7 of 15 Vrin7.Version 72.1 07/13/15 09:41:15 1F~~i~ NP-2-ARP-1.6 Page 5of 8LOCATION .IillSETPOINT: 1. Variable, as per F'NP-2-RCP-252ORIGIN: Any of the below listed Area, Process or Gaseous andParticulate Monitors: ROI!B, R02, R04, R05, R06,R07, RO8, R09, RI I, R12, R 13, -R'4 R15,R17A, RI7B, RIB, R19, R20A, R20B[ R21, R224R23A or R23BPROBABLE CAUSERMSHI-RADI. High Radiation Level in the System, Area or at the Component monitored.I2. The radiation monitors fail to a "'High Radiation-"" condition on loss ofinstrument and/or control power that will result in actuation of associatedautomatic functions.AUTOMATIC ACTION1. The following actions will occur if a High Radiation Alarm is actuated onthe associated Radiation Monitor.a) R14: (Plant Vent Gas) closes Waste Gas Release Valve 2-GWD-HV-0 14.b) R16: (Boron Recycle System) diverts 2-C VC-RC V-016 RecycleEvaporator discharge from Reactor Makeup Water System to theRecycle Evaporator Demineralizer.c) RI7A or B: (Component Cooling Water) closes 2-CC W-RC V-3028CCWN SRG TANK VENT.d) R I8: (Liquid Waste Processing) closes Liquid Waste Release Valve2-LWP-RCV-0I18.e) RI9: (Steam Generator Blowdown) isolates Steam GeneratorBlowdown Sample Lines.t) R23A: (Steam Generator Blowdown Processing) closes2-BD--FCV-1 152 S/G Blowdown Heat Exchanger Outlet FCV.g) R23B: (Steam Generator Blowdown Processing) closes2-BD-RCV-023B SGBD DISCH TO ENVIRONMENT.Page 1 of 13 Vrin6.Version 61. i SNIT 207/13/15 09:41:15Vi17FNP-2-ARP-I.6 Page 6 of 8LOCATION FHilOPERATOR ACTION (cont)4. In addition to the general actions perform steps indicated in the "ACTIONS"column of the following table. (Some of the radiation monitors included in thetable do not input into this alarm but are included for reference).RADIATION MONITOR REFERENCE TABLECRE LO:CATION TYPE DETECTOR FUNCTION ACTIONSR- 1A Control Room (Unit I Area G-M ( W) No input toPanel) _______this alarmR- lB Technical Support Center Area G-M ( W) Perform Step(Unit 1] Panel) R-l 1B_________ 4.1R-2 Containment (155' elev) Area G-M ( W) Starts IPC dose Perform Steps___ __ ___ __ ___ __ _ _ __ __integration 4.2R-3 Radiochemistry Lab (AB Area G-M ( W) No input to139') __________this alarmR-4 #3 Charging Pump (AB Area G-M (W) Perform Step100') _____ ________4.3R-5* Spent Fuel Pool Room (AB Area G-M (Wj) Perform Steps155') _ _ _ _ _ _ _ _ _ _ 4.4R-6 Sampling Room (AB 139') Area G-M ( W) Perform Step____ ___ ____ ___ ____ ___ ___ ___ ____ ___4.5R-7 In-core NIS Area (CTMT Area G-M ( W) Starts IPC dose Perform Steps129', near Seal Table) ____integration 4.6R-8 Drumming Station (AD Area G-M ( W) Perform Step155') __ _ _ _______4.7R-9 SG Sample Panel (Unit II Area G-M (W) Perform StepPanel) (AB 139') 4.8R- 10 Penetration Room Filtration APD Scint. Perform Step____Discharge (AD 155') (Victoreen) 4.9R- 11
+* Containment Atmosphere APD) Scint. Perform Step____(AB 121') ____(Victoreen) _______4.10**Technicail Specification relatedPage 4 of 13Page 4of 13Version 61.1
+~k J. ~'V1 7FNP-2-ARP-1.6 Page 7 of 807/13/15 09:41:15LOCATION FHilRADIATION MONITOR REFERENCE TABLE (cont)RE. LOCATION TYPE DETECTO FU[NCTION ACTIONSR- 12* Containment Atmosphere Gas G-M ( W) Perform Step(AB 121') _____4.11R-13 Waste Gas Compressor Gas O-M (W) Perform StepSuction (AB 100' WGC 4.12Valve Room) ________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform StepODCM ___________________ __4.13R- 15A Condenser Air Ejector Gas G-M Perform StepODCM Discharge Header (TB 155') 4.14R-15B* Condenser Air Ejector Gas G-M (Eberline) Perform Step(Intermediate Range) (TB3 4.15189') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R .15C* Condenser Air Ejector Gas Ion Chamber Perform Step(High Range) (TB 189') (Eberline) 4.15R-17A Component Cooling Water Liquid Scint. (W ) Closes CCW Perform Step(CCW H-x Room) surge tank vent 4.16__________________(RCV-3028) _____R-17B Component Cooling Water Liquid Scint. Closes CCW Perform Step(CCW Hix Room) surge tank vent 4.16_________________ _____ _________ RCV-3028)R- 18 Waste Monitor Tank Pump Liquid Scint. (W ) Closes RCV- 18 Perform StepODCM Discharge (AB 121' at the 4.17_______Batching Funnel)R-19 Steam Generator Liquid Scint. ( W) Isolates sample Perform StepBlowdown/Sample (AB lines 3328, 4.18139') ___ _____ __3329, 3330R-20A Service Water from Liquid Scint. ( W) Perform StepContainment Coolers A and 4.19B (AB 121' BTRS Chiller_____Room) _________________*Technical Specification relaedPage 5 of 13 Vrin6.Version 6 I. 1 UN1IT 2V1 7FNP-2-ARP-I1.6 Page 8 of 807113115 09:41:15LOCATION .TLRADIATION MON1TOR TABLE (cont)RELOCATION IX DETECTOR FUNCTION ATIOQNSR-20B Service Water from Liquid Scint. ( W) Perform StepContainment Coolers C and 4.19______D (AB 121')______R-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____(Victoreen) 4.20R-22 Plant Vent Stack Gas G-M ( W) Perform StepODCM (AB 155') 4.21R-23A SG Blowdown Surge Tank Liquid Scint. ( W) Closes Perform Step____Inlet (AD 130') ____ _______FCV-! 152 4.22R-23B SGBD DISCH TO Liquid Scint. ( W) Closes Perform StepODCM ENVIRONMENT RCV-23B 4.22_______ (AB 130')________ ________ _ _ _ _ _ _R-24A* Containment Purge (AD Gas Scint. Closes No input to155') containment this alarmpurge supply &exhaust dampers2866C & 2867C____ ________and 3198A & _____R-24B* Containment Purge Gas Scint. Closes valves: No input to(AD 155') (Victoreen) 2866D &2867D, this alarm3196, 3197,_____3198B &CR-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input toR-25B* (AD 184') (Victoreen) supply and this alarmexhaust fans;closes SFPHVAC supplyand exhaustdampers; startsassociated trainsof penetrationroom filtration.*Teehnical Specification relatedPage 6 of 13Page6 o 13Version 61I.1I V18Page 1 of 3FNP-I-ARP-I.1207/13/15 08:32:48 -SETPOINT:1.2.3.0.01lgSystem Health RelayAlarm Relay 0LOCATION M~~SEISMICPANELALARMORIGIN: 1. SSA-3 Solid State Accelograph(NIH 11NGSI2507G)2. System Health Relay (8 inputs)* Recorder memory usage exceeding 80%* Failure of recorder(s) to respond to pollingfrom central controller.* Hardware failure* Recorder high temperature* Failure of recorder(s) to respond to controllerduring startup.* Communication problem.* DC power loss on alarm panel.* AC power loss on recorder(s).3. Alarm relay 0 (From channel 1 recorder, used forfunctional testing only).PROBABLE CAUS1. Seismic event.12. Operating Basis Earthquake (OBE) exceeded.I3.4.5.Seismic Panel loss of power.Instrument malfunction.Seismic finctional testing in progress.AUTOMATIC ACTION1. The monitoring system remain on at all times continuously monitoringthe signals from the acceleration sensors.2. When a setpoint is exceeded, the system' retrieves the time history datafrom storage and automatically performs the preprogrammed calculationsfor operator review.3. The system printer provides print and plot copies of the results for recordand review.El[]ElPage I of 15 Vrin6.Version 63.1 07/13/i5 08:33:15Vi18Page 2 of 3FNP-1-ARP-I1.12LOCATION MK5OPERATOR ACTIONS CONTINUEDACTION EXPECTED3.3 Record and compare the seismicpanel printout channel 1, 2 and 3Spectral Acceleration calculatedvalues, Spectral Velocity calculatedvalues and Computed CAV values tothe Spectral Acceleration designvalues, Spectral Velocity designvalues and CAV Design Limit Valueson Table ! "~Operating BasisEarthquake Exceedance (OBEE)Limit for Determination of PlantShutdown Requirements".IRESPONSE NOT OBTAINED3.4 Check the following:CAV Design limit value has NOTbeen exceeded.*Based on operator walkdowns noplant significant damage is found.3.4.1 JF either unit tripped, THENconduct a post trip review andrestart as appropriate.3.4 IF_ any of the following has occurred:* The Spetral Acceleration design valuehas been exceeded,o_.R* The Spectral Velocity design value hasbeen exceeded,_OR* Significant plant damage is found duringoperator walkdownsTHEN OBEE Criteria has been exceeded.3.4.1Generate a Condition Report to referto FNP- I-ETP-4580 and documentthe event.3.4.2 Generate a Condition Report torefer to FNP-I-ETP-4580 anddocument the event.3.4.2 Proceed to step 4.3.4.3 Proceed to step 5.Page 4 of 15 Vrin6.Version 63.1 07/13/15 08:34:29 A l 1 NP-I-AP-1.1LOCATION M15TABLE IOPERATING BASIS EARTHQUAKE EXCEEDANCE (OBEE) LIMITFOR DETERMINATION OF PLANT SHUTDOWN REQUIREMENTSResoonse Soectr Analysis for..Free Field MeasurementChannel 1: [L"~S1Computed CAV = * ..g-sec, Limit =0.160 g-sec"PSA Limit = 0.200 g ", OBE SV Limit =15.240 Damping = 0.050Spectral acceleration exceeded OBE Design criteria at
+* frequencies.Spectral acceleration greater than 2/30OBE Design criteria at
+* frequencies.Spectral velocity exceeded OBE Design criteria at
+* frequencies.Channel 2: I'V-UP1Computed CAV -* ....g-sec, CAV Limit = 0.160 g-sec'*OBE PSA Limit -0.200 g**, OBE SV Limit ,,15.240 cm/sec, Damping =0.050Spectral acceleration exceeded OBE Design criteria at
+* frequencies.Spectral acceleration greater than 2/30OBE Design criteria at.._* frequencies.Spectral velocity exceeded OBE Design criteria at....2* frequencies.Channel 3: FT=W1Computed CAV =
+* g-sec, CAV Limit = 0.160 g-sec"&deg;OBE PSA Limit =0.200 g"*, OBE SV Limit = 15.240 cm/sec, Damping = 0.050Spectral acceleration exceeded OBE Design criteria at______ frequencies.Spectral acceleration greater than 2/30OBE Design criteria at
+* frequencies.Spectral velocity exceeded OBE Design criteria at frequencies.Calculated by Seismic Monitor. Any exceedances are exceedances of the system setupvalues per Table 2 and do not necessarily mean OBEE limits have been exceeded.oe The CAV Design Limit is 0.16 g-s but Table 2 -OBE Limit Value shows a limit value of0.0 g-s so the Farley Nuclear Plant OBE Spectra would control the OBE system alarm.O 0.20g is the EPRI OBE Limit Value (OBEE). The monitoring system will accept only onevalue at a time for the OBE limit Value. The recommended monitoring system setup (Ref'.Table 2 -OBE Limit Value) shows a limit value of 0.05g horizontal and 0.033g vertical sothe Farley Nuclear Plant OBE Spectra would control the OBE system alarm.Page 13 ofI Veson6.Version 63.1 V19Page 1 of 3RCS Specific Activity3.4.163.4 REACTOR COOLANT SYSTEM (RCS)3.4.16 RCS Specific ActivityLCO 3.4.16APPLICABILITY:The specific activity of the reactor coolant shall be within limits.MODES 1 and 2,MODE 3 with RCS average temperature (Tavg) > 500&deg;F.ACTIONS ___________ _______CONDITION REQUIRED ACTION COMPLETION TIMEA. DOSE EQUIVALENT----------------Noe-------1-131 > 0.5 pCi/gm. LCO 3.0.4c is applicable.A.1 Verify DOSE Once per 4 hoursEQUIVALENT I-131within the acceptableregion ofFigure 3.4.16-1.ANDA.2 Restore DOSE 48 hoursEQUIVALENT 1-131 towithin limit.B. Gross specific activity of B.1 Be in MODE 3 with 6 hoursthe reactor coolant not Tavg < 500&deg;F.within limit.Farley Units 1 and 23.4.16-1Amendment No. 170 (Unit 1)Amendment No. 163 (Unit 2)
+Vi19Page 2 of 3RCS Specific Activity3.4.16ACTIONS_________ ___CONDITION REQUIRED ACTION COMPLETION TIMEC. Required Action and C.1 Be in MODE 3 with 6 hoursassociated CompletionTag<50FTime of Condition A notTag<50Fmet.O._RDOSE EQUIVALENTI-131 in the unacceptableregion of Figure 3.4.16-1.SURVEILLANCEREQUIREMENTS _______SURVEILLANCE FREQUENCYSR 3.4"16.1 Verify reactor coolant gross specific activity I10E .~/g.ten accordance withsrelacFrequency ControlProgramSR 3.4.16.2 ---NOTE---------------........Only required to be performed in MODE 1.Verify reactor coolant DOSE EQUIVALENT 1-131 In accordance withspecific activity < 0.5 IpCi/gm. the SurveillanceFrequency ControlProgramANDBetween 2 and6 hours after aTHERMALPOWER changeof > 15% RTPwithin a 1 hourperiodFarley Units 1 and 23.4. 16-2Amendment No. 185 (Unit 1)Amendment No. 180 (Unit 2)
+V19Page 3 of 3RCS Specific Activity3.4.16E0U275250225200175150125.__'- -Operation_ _ .. +:_::~i- J:1 1_+?[]i. ..EI.NK.. .Acceptable ; ++ 5 -+ -* + -575. ... Operatin --50,2 5 ,. ......0 ..., '. + : + ._ L .+ ' + : + ....20 30 40 5O 0070 80 90 100Percent of RATED THERMAL POWERFigure 3.4.16-1DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit VersusPercent of RATED THERMAL POWER with the Primary Coolant SpecificActivity > 0.5 jiCi/gm DOSE EQUIVALENT 1-131.Farley Units 1 and 23.4. 16-4Amendment No. 147 (Unit 1)Amendment No. 138 (Unit 2)
+V20Page 1 of 1RCS Operational LEAKAGE3.4.133.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGELCO 3.4.13RCS operational LEAKAGE shall be limited to:a. No pressure boundary LEAKAGE;b. I gpm unidentified LEAKAGE;c. 10 gpm identified LEAKAGE; andd. 150 gallons per day primary to secondary LEAKAGE through anyone steam generator (SG).APPLICABILITY: MODES 1, 2, 3, and 4.ACTIONS____________ _____ ___CONDITION REQUIRED ACTION COMPLETION TIMEA. RCS operational A.1 Reduce LEAKAGE to 4 hoursLEAKAGE not within limits within limits.for reasons other thanpressure boundaryLEAKAGE or primary tosecondary LEAKAGE.B. Required Action and 8.1 Be in MODE 3. 6 hoursassociated CompletionTime of Condition A not ANmet.8.2 Be in MODE 5. 36 hoursPressure boundaryLEAKAGE exists.Primary to secondaryLEAKAGE not within limit.I1Farley Units I and 23.4.13-1Amendment No. 163 (Unit 1)Amendment No. 156 (Unit 2)
+V21Page 1 of 1ESFAS Instrumentation3.3.2Table 3.3,2-1 (page 2 of 4)Engineered Safety Feature Actuation System InstrumentationAPPLICABLEMODES OROTHERSPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIPFUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT2. Containment Spraya. Manual Initiation 1,2,3,4 2 B SR 3.3.2.6 NA NAbi. Automatic Actuation 1.2,3,4 2 trains C SR 3.3.2.2 NA NALogic and Actuation SR 3.3.2.3Relays SR 3.3.2.8Pressure SR 3.3.2.4High -3SR 3.3.2.7SR 3.3.2.93. Containment Isolationa. Phase A Isolation(1) ManualInitiation(2) AutomaticActuation Logicand ActuationRelays(3) Safety Injectionb. Phase B Isolaton(1) ManualInitiation(2) AutomaticActuatio LogicandAcutnRelays1,2,3,41,2,3,422 trainsB SR 3.32..6C SR 3.3.2.2SR 3.3,2.3SR 3.32.8NANANANARefer to Function 1 (Safety Injection) for all initiation functions and requirements.1,2,3A41.2,3,422 trainsB SR 3.3.2.6C SR 3.32.2SR 3.3 2.3SR 3.3 28E SR 3.3.2.1SR 3.3.2..4SR 3.32.7SR 3.3,2-9NANANANA(3) ContainmentPressureHlgh -31.2,34S 28.3 psig 5 27 psigFadley Units I and 23.3.2-10Amendment No. 185 (Unit 1) iAmendment No. 180 (Unit 2) I Edwin I. Hatch Nuclear Plant Units 1 and 2License Amendment Request for Changes toEmergency Action Level Schemes to Adopt NEI 99-01 Rev. 6and to Modify Radiation Monitors at Farley Nuclear PlantEnclosure 4Hatch EAL Verification and Validation Documents Hatch EAL V&V Documentation IndexV&V# ..'Description I' IC [Threshold'RCS Modes/Temperatures -TS Reference (Table 1.1I-I) EAL Basis Section 1.41 RCS Cold Shutdown Temperature reference (212 OF) t CA3 (1)___tj CU3 J (1)Radiation Monitor Calculations:1/2D1 1-P601 (feeding 1/2D 11-R63 1)1D11l-P007 (feeding 1D11-R631)Calc SMiNH-13-021 Rev IRG I(1)RS1 (1)RA1(1)2Radiation Monitor Calculations: 1D11-K604 RU1 (1)1D 11-K6051D11-K619 A(B)1D1 l-K600 A(B)2D1 1I-K6042D 11-K6052D1 1-K636 A(B)Ca/c SMNH-13-021 Rev 1Radiation Monitor Information: RU2 (1)b1D21-K601 A 2D21-K601 A1D11-K601 D 2D21-K601 M1D21-K601 E 2D21-K601 E1D21-K601 M 2D21-K611 K2D21l-K611 LCa/c SMNH-13-021 Rev 1 _____Radiation Monitor Calculation: CG1 (1)bDWRRM 1/2D 11-K621 A(B) CS 1 (2)bCa/c SMNH-13-021 Rev 1 ______Primary Containment Rad Monitor Calculations FCB L4A FCB L4ADWRRM RCSB L4A RCSB L4ACa/c SMNH-13-021 Rev 1 CB PL4A CB PL4AOffgas Pre-Post Treatment Reading Calculation FCB L5A FCB L5ACa/c SMNH-13-021 Rev 1I_____Drywell Fission Product Monitor Reading CalculationCa/c SMNH-13-021 Rev 1RCSB L5ARCSB L5AODCMITS Reference to Site Boundary RG1 (2)(3)3RS1 (2)(3)RAl (2)(3)(4)Alarm Response Procedure Reference RA2 (2)Annunciator Displays:1D21-K601 A 2D21-K601 M1D21-K601 B 2D21-K601 E1D21-K601 D 2D21-K611 K1D21-K601 E 2D21-K611 L1D21-K601 M 2D11-K609 A-DIDII-K609 A-D 2D11-K611 A-D1D1Il-K611 A-D 2D 11-K634 A-D2D21-K601 A 2D11-K635 A-DAlarm Response Procedure Reference Control Room Rad RA3 (1)Monitor [Annunciator Display: 1D21-K600 B(C)] ____________Alarm Response Procedure Reference RU2 (1 )aAnnunciator Display: Spent Fuel Storage Pool Level Low6 654-022-1Spent Fuel Storage Pool 'Level Low654-022-2 ______2/22/20 16Page 1 of 3 Hatch EAL V&V Documentation IndexV&V# *Description ' IlC ThresholdRPV Level Indications/Displays (-155" TAF) CG1 (1)a7CS1 (2)bFCB PL2A FCB PL2ACaic SMNH-13-021 Rev 1 RCSB L2A RCSB L2ARPV Level Indication/Display (-35"); Level 2 Actuation CS 1 (1)b8 setpoint info (required for CA1/CS1 is 6" below setpt) CAl (1)Caic SMNH-13-02I Rev 1Drywell Floor Drain Sumps; Drywell Equipment Drain CG1 (2)bSumps; Torus; Torus Room Sumps; RB Floor Drain CS 1 (3)bSumps; TB Floor Drain Sumps; Rad Waste Tanks CA1 (2)breferences cui (2)bH2 Concentration (> 6%) and 02 Concentration (> 5%) -CGI (2)c10 calculation/reference CB PL1B CB PL1BCale SMNH-13-021 Rev 111 Primary Containment Pressure Reference (> 56 psig) CG1 (2)cCalc SMNH-13-021 Rev]1 CB PLIA CB PL1ASecondary Containment Rad Monitors > Max Safe values CG1 (2)c12 34AB-T22-O03-1/2 CBL3A CBL3ASecondary Containment Rad Monitors > Max Normal RCSBPL3A RCSBPL3AValues 34AB-T22-O03-1/24160 VAC Essential Buses Description CA2 (1)CU2 (1)a13 SG1 (1)aSG8 (1)aSS1 (1)SA1 (1)SU1 (1)14 RCS Pressure indications CA3 (2)DC System Information CU4 (1)15 SO8 (1)bSS8 (1)16 ISFSI TS/Dose Reading Calculation E-HU1 (1)SMHN-13-021 Rev 117 Primary Containment Pressure > 1.85 psig reference RCSB LIA RCSB L1A17 Calc SMNH-13-021 Rev 1Secondary Containment Temps -> Max Normal values RCSBPL3A RCSBPL3A18 34AB-T22-O03-1/2Secondary Containment Temps -> Max Safe values CBL3A CBL3A34AB-T22.-O03-1/2Seismic Indications (OBE): HU2 (1)19 [Annunciator Display (657-048/657-066)]12.7 Hz amber light12.7 Hz red light20 Table H2 Basis HU4 (1)b (2)b34AB-X43-O01-1 (2)21 Minimum Steam Cooling RPV Water Level SG1 (1)bSS5 (1)c22 Heat Capacity Temperature Limit (HCTL) Curve SS5 (1)cPretreatment Radiation Monitor Reading SU3 (1)23 TS3.7.6Caic SMNH-13-021 Rev 1RCS sample activity -Tech Spec Value SU3 (2)24 TS3.4.62/22/2016Page 2 of 3 Hatch EAL V&V Documentation IndexIV&V# I> Description I IC IThreshold'RCS Operational Leakage -Tech Spec Values SU4 (1)(2)25 TS3.4.42/22/2016Page 3 of 3 VlPage 1 of 1Definitions1.1Table 1.1-1 (page 1 of 1)MODESAVERAGE REACTORCOOLANTREACTOR MODE TEMPERATUREMODE TITLE SWITCH POSITION (&deg;F)1 Power Operation Run NA2 Startup Refuel(a) or Startup/Hot NAStandby3 Hot Shutdownl(a) Shutdown > 2124 Cold Shutdown(a) Shutdown < 2125 Refueling(b) Shutdown or Refuel NA(a)(b)All reactor vessel head closure bolts fully tensioned.One or more reactor vessel head closure bolts less than fully tensioned.HATCH UNIT 11.1-6HATC UNI I 11-6Amendment No. 195 5A~NYErn~r,,.&'~i.v I~W*d4V2Southern Nuclear Design CalculationSeNL1589Enclosure 3ICalculation Number: SMNH-13-021Plant:Hatch Nuclear Plant Unit:O 1 0" 2 0] 1 & 2 Discipllne:MechanlcalTlfite:Subject EmergencyNEI 99-01 Rev 6 EAL. Calculations Action Level SetpointsPurpose I Objective:Document Emergency Action Level Values to support conversion to NEI 99-01 Rev 6System or Equipment Tag Numbers:N/AContentsTopic Page Attachments # of(Computer Printouts, Technical Papers, Pages__________________Sketches, Correspondence)Purpose 1 A -SNC EP Concurrence 1Criteria 1 B -Reserved 0Conclusions 3 C -Fuel Clad' Loss 4.A Threshold Calculation 19Design Inputs 5 D -Fuel Clad Potential Loss 5.A Threshold 1Assumptions ,10 CalculationReferences 14 E -RCS Loss 4.A Threshold calculation ... 16Method of Solutions 18 F -RCS Loss 5.A Threshold Calculation 6Body of Calculation .... ....23 G -containment Potential Loss 4.A 1__________________Threshold Calculation______________H -Steam Table Validation 5I- RS1 Threshold Calculation ______ 25Toa fPgsicuigJ -CG1 Threshold Calculation 4cover sheet & Attachments: 189 K -CG1 Threshold,,,Calculation 15L -E-HU1 Threshold Calculation 16M -RA1 Threshold Calculation 18Nuclear Quality Level0 -Safety-Related li Safety Significant 0 o-Safety -SignificantVersion RecordVersion Originator Reviewer' Approval I Approval 2I, ~ dui= Name P.*HW 4Name Pri~ed Na. atiCalculation of EAL Thresholds. wb..d l-Lto support NEI 99-01 Rev. 6Notes: Key calculationNMP-ES-039NMP-E-039NMP-ES-039-001 V3Page 1 of 2HNP ODCMd. The CHAN4NEL CHECK s hall consist of verifying sampler flow an d the presence ofthe*collection device (i.e., partic~ulate filteror charcoal cartridge, etc.) at the weekly o ,43.1.2 Gas eous Effluent Dose Rate ControlIn accordance with Technical Sp ecif'ication~s 5.5.4.c and 5.5.4.g, the licensee shall conducto perations so that th e dos e rates due to radioactive materials rel eased in gaseous effluentsfrom the siteto areas at and beyondthe SITE BOUNDARY (see Figure 10-1) are limited asfollows:a. For noble gase.-s: Less than or equalto a dose rate of to the total body andless than or equal to a dose rate of 3000 /to the skin, andb. For Iodine-131, Iodine-133, tritum, and forall radionuclides in partioulate forin withhalf-lives greater than 8 days: Less than or equal to a dose rate of 1500 j~r, j~rn to anyorgan.3.1.2.1 ApplicabilityThis limit applies at all times.3.1.2.2 ActionsWith a dos e rate due to radioactive material released in gaseous effluents exceeding the limitstated in Section 3.1.2, immediatelydecrea~se the relea~se rate to within the stated limit.Entry into an Operational Mode or other specified COM)ITION shall be made if, as a minimum,the requirements ofTedinical Sp eafications LCO03.0.4 are met.3.1.2.3 Surveillance RequirementsThe dose rates dueto radioactive materials in areas at or beyondth e SITE BOUNDARY due torel eases of gaseous effluents shall be determinedto be withinthe above limits, in accordancewith the methods and procedures in Section 3.4.1, by obtaining representative samples andperforming analyses in accordance with the sam pling an d analysis program specifed inTable 3-3.3.1.2..4 BasisThis control is provided to ensure that gaseous effluent dose rates will be maintained within thelimits that historicallyhave provided reasonable assurance that radioactive material disdiargedin gas eous effluents wilN not result in a d ose to a MEMBER OF THE PUBLIC in anUNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceedingthe limitsspecified inAppendix I ofI10CFR Part 50, while allowing operational fl exibiity for effluentreleases. For MEBROFTH-E PUBLIC who may at times be withinthe SITE BOUNDARY,the occupancy ofth e MEBE OFTHE PUBLIC will be sufficiently low to compensate for anyincrease in th e atmospheric diffusion factor above that for th e SITE BOUNDARY.3-6 Version 23 213 KeFPLOO PinAI FOUEUTB'mueaTeaPFcJif0)&Co V4Page 1 of 16SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) AGE 1 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 34AR-601-902-1 I 14.41H11-P601, ALARM PANEL 1EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE:04 15N/A SSM /PM: N/A DATE: N/AANNUNCIATOR RESPONSE PROCEDURES FOR IHII-P601 -ALARM PANEL 1ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-101-1 5.1 34AR-601-113-1 2.1 34AR-601-125-1 6.234AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.234AR-601-103-1 6.2 34AR-601-1 15-1 4.1 34AR-601-127-1 6.234AR-601-104-1 3.3 34AR-601-1 16-1 5.6 34AR-601-128-1 3.234AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.134AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.034AR-601-107-1 1.1 34AR-601-119-1 1.1 34AR-601-131-1 6.334AR-601-1 08-1 2.2 34AR-601-120-1 5.2 34AR-601-1 32-1 3.334AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.134AR-601-1 10-1 4.2 34AR-601-122-1 4.1 34AR-601-1 34-1 4.334AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.534AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0II NOE Approval signature on this page constitutes approval for all procedures listed above at theNOE revision indicated. Tab numbers in the back correspond to procedure sequence number.ILevel Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneN MP-AP-002 V4Page 2 of 16PAGE 2 OF 2SOUTHERN NUCLEARPLANT E.I. HATCHDOCUMENT TITLE:ARP'S FOR CONTROL PANEL 1H11-P601,ALARM PANEL 1DOCUMENT NUMBER: VERSION NO:34AR-601-902-1 I 14.4UNIT 11H 11-P601 -1601-101 601-102 601-103
+* 601-104 601-105 601-106601-107 601-108
+* 601-109
+* 601-110 601-111 601-112601-113 601-114 601-115 601-116 601-117 601-118601-119 601-120 601-121 601-122 601-123 601-124601-125 601-126 *60-2 60-2 6119 6113601-125 601-1326 601-127 601-128 601-125 601-130RECORDSThere are no records generated from this procedure.COMMITMENTSNone* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on TRIP UNIT Label(s) at 1D21-P600 to provide across-reference for locating the device(s) in Abnormal and/or EOP Tables.Refer to 34AB-T22-003-1, Secondary Containment Control.NMP-AP-002 v.2.0 V4Page 3 of 161.0 IDENTIFICATION:ALARM PANE L 601-1_____ ___RX BLDG___ __ ___RADIATION___ __ _ _ __ ___HIGHDEVICE: SETPOINT:1D21-K601A, E, F, G, H, K, L, N, P, R, S, T, U, V, W, X, Y See 64C1-CAL-002-05.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED amber upscale light and high reading on individual indicator/trip units,on 1D21-P600, Area Radiation Monitoring Panel.5.1.1 Attempt to reset Trip Unit.5.2 IF Trip Unit will NOT reset, perform the following:5.2.1 Confirm monitor reading,by checking 1D21-R600, Area Radiation Monitor Recorder, panel 1~ H1-P600. (see channels below).5.2.2 Contact Health Physics to confirm radiological condition.5.2.3 REFER to 73EP-RAD-001-0, Radiological Event.5.2.4 Periodically monitor panel 1D21-P600,to ensure that no other channels in the Reactor Building are indicating high OR in alarm.5.2.5 Enter 34AB-T22-003-1, Secondary Containment Control.5.2.6 IF a radioactive release outside the Reactor Building is occurring, OR has occurred,enter 34AB-D1 1-001-1, Radioactive Release Control.LiLILiLiLiLiLiLi6.0 CAUSES:6.1 High radiation Trip on one or more of the following indicator/trip units:1 D21 R600CHANNEL TRIP UNIT LOCATION01 1 D21-K601A Reactor Head Laydown05 1D21-K601E Drywell Shield Plug06 1D21-K601F Tip Area07 1D21-K601G 130' NE Working Area08 1 D21-K601H 130' SW Working Area09 1 D21-K601K 158' SW Working Area10 1D21-K601L Rx Wtr Smpl Rack Area 158'12 1D21-K601N South CR0 Hydraulic Units13 1 D21-K601P North CR0 Hydraulic Units14 1D21-K601R CS & RHR S-E Diag.15 1 D21 -K601 S Equipment Access Airlock16 1 D21-K601T HPCI Turbine Area17 1 D21-K601U TIP Probe Drive Area18 1D21-K601V RCIC Equipment Area SW19 1D21-K601W CR0 Pump Room NW20 1 D21-K601X RB 203' Working Area21 1D21-K601Y CS & RHR N-E Diag.6.2 Malfunctions of one or more trio unitsSENSOR1D021-N002-11 D21-N002-51021 -N002-61021 -N002-71021 -N002-81 D21-N002-91021 -N002-1 01 D21-N002-121021 -N002-1 31 D21-N002-141021 -N002-1 51021 -N002-1 61 D21-N002-171021 -N002-1 81021 -N002-1 91 D21-N002-201 D21-N002-2134AB-T22-003-1ITEM NUMBER14111416910171221152213181962
+==07.0 REFERENCES==
+: 8.0 TECH. SPEC./TRM/ODCMIFHA:7.1 H-17854 -H-17859, H-19598 & H-i19599, ARM Sys. 021 Elem. N/A -Not applicable to this procedure34AR-601 -104-1Ver. 3.3MGR-0048 Ver. 5 V4Page 4 of 161.0 IDENTIFICATION:ALARM PANEL 601-1________REFUELING FLOORAREA RADIATION___ __ __ ___HIGHDEVICE: SETPOINT:1 D21 -K601 B, 1 D21 -K601 D See 64C1-CAL-002-02.0 CONDITION: 3.0 CLASSIFICATION:EQUIPMENT STATUSOne OR both of the Refueling Floor Area Radiation Monitors has 4.0 LOCATION:exceeded its setpoint.1H-P0Pae6015.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/trip unitson panel 1D21-P600. Li5.1.1 Attempt to reset trip unit. LI5.2 Confirm Control Room ventilation shifted to pressurization (Mode II),per 34SO-Z41-001-1, Control Room Air Conditioning System. LI5.3 IF trip unit will NOT reset, perform the following:5.3.1 Confirm monitor reading by checking 1D21-R600, Area Radiation Monitor Recorder,panel 1Hi11-P600. (see channels below) Li5.3.2 Contact Health Physics to confirm radiological condition in the affected area,evacuate area IF required. LI5.3.3 Periodically monitor panel 1D21-P600,to ensure that no other channels on the Refueling Floor are indicating high OR~ in alarm. Li5.3.4 Enter 34AB-T22-003-1, Secondary Containment Control. Li5.3.5 Refer to 73EP-RAD-001-0, Radiological Event. Li5.3.6 IF a radioactive release outside the Refueling Floor is occurring, OR has occurred,enter 34AB-D1 1-001-1, Radioactivity Release Control. Li6.0 CAUSES:6.1 High radiation causing one OR both of the following indicator/trip units:MONITOR CHANNEL TRIP UNIT LOCATION SENSOR02 1D21-K601B Refueling Floor Stairway 1D21-N002-204 1D21-K601D Refueling Floor 1D21-N002-46.2 Malfunction of trip unit.
+==7.0 REFERENCES==
+: 8.0 TECH. SPEC./TRMIODCM/FHA:7.1 H-17854 thru H-17859, H-19598 and H-19599, AreaRadiation Monitoring Sys. D21 Elem Diag N/A -Not applicable to this procedure34AR-601-1 10-1Ver. 4.2MGR-0048 Ver. 5 V4Page 5 of 161.0 IDENTIFICATION:__ALARMPANEL 601-1 __________ __ __ ___NEW FUEL__ __STORAGE AREA__ __ __RADIATION HIGHDEVICE: SETPOINT:1 D21-K601C 64CI-CAL-002-01 D21-K601M2.0 CONDITION: 3.0 CLASSIFICATION:2.1 Radiation level in vicinity of Spent Fuel Pool Demineralizer EQUIPMENT STATUSEquipment ARM has exceeded its setpoint 4.0 LOCATION:2.2 Radiation level in vicinity of Spent Fuel Pool & New Fuel Storage 1H11-P601 Panel 601-1ARM has exceeded its setpoint2.3 Loss of power to either of the above listed ARMs5.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/tripunits on panel 1D21-P600. LI5.1.1 Attempt to reset trip unit. LI!5.2 IF trip unit will NOT reset, perform the following:5.2.1 Confirm monitor reading by checking 1D21-R600, Area Radiation Monitor Recorder,on panel 1H1 1-P600. (see channels below) LI5.2.2 Contact Health Physics to confirm radiological condition in the affected area ANDevacuate area IF required. LI5.2.3 Periodically monitor 1D21-P600, panel, to ensure that no other channels on theRefueling Floor are indicating high OR in alarm. 135.2.4 Enter 34AB-T22-003-1, Secondary Containment Control. LI5.2.5 Refer to 73EP-RAD-001-0, Radiological Event. III5.3 If neither ARM is reading high, then at 1 R25-S064, confirm BRKR 9 is CLOSED. El5.4 IF an abnormal radioactive release is occurring OR has occurred,enter 34AB-D1 1-001-1, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation causing one or both of the following indicator/trip units to alarm:1D21-R600 POINT TRIP UNIT LOCATIONNUMBER SENSOR3 1D21-K601C, Spent Fuel Pool Demin Equip 1D21-N002C11 1D21-K601 M, Spent Fuel Pool & New Fuel Storage 1D21-NO02M6.2 Loss of power to ARM's
+==7.0 REFERENCES==
+: 8.0 TECH. SPEC./TRMIODCMIFHA:7.1 H-17854 & H-17856, ARM Sys. D21 Elem. Diag. N/A -Not applicable to this procedure34AR-601-127-1Ver. 6.2MGR-0048 Ver. 5 V4Page 6 of 16DOCUMNT TTLE:DOCUMENT NUMBER: VERSION NO:ARP'SALRFOR PAECONTROL4 PANEL 1H11-P601, 34AR-601-901-1 12.4EXPIATIN APROVLS:EFFECTIVEDATE: DEPARTMENT MANAGER DAK for Keith D. Lonq DATE 5-9-13 DATE:N/A SSM/PM N/A DATE N/A 5-15-15ANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601 -ALARM PANEL 4ARP NO. Ver, NO. ARP NO. Ver.NO. ARP NO. Ver. NO.34AR-601-401-1 0.4 34AR-601-413-1 0.4 34AR-601-425-1 4.434AR-601-402-1 3.4 34AR-601-414-1 3.3 34AR-601-426-1 3.534AR-601-403-1 3.5 34AR-601-415-1 1.5 34AR-601-427-1 1.334AR-601 -404-1 0.2 34AR-60 1-416-1 1.3 34AR-601 -428-1 4.634AR-601-405-1 7.1 34AR-601-417-1 4.6 34AR-601-429-1 2.234AR-601-406-1 7.3 34AR-601-418-1 3.3 34AR-601-430-1 0.234AR-601-407-1 1.5 34AR-601-41 9-1 0.2 34AR-601-431-1 1.134AR-601 -408-1 1.5 34AR-601 -420-1 4.5 34AR-601 -432-1 4.334AR-60 1-409-1 5.5 34AR-60 1-421-1 4.3 34AR-601 -433-1 0.134AR-601-410-1 2.2 34AR-601-422-1 3.5 34AR-601-434-1 2.134AR-601-411-1 3.6 34AR-601-423-1 3.6 34AR-601-435-1 034AR-60 1-412-1 4.5 34AR-60 1-424-1 2.5 34AR-601 -436-1 0INOTE Approval signature on this page constitutes approval for all procedures listed above at the IVersion indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneI V4Page 7 of 16UNIT 11H11-P601-4601-401 601-402 601-403 601-404 601-405 601-406601-407 601-408 601-409 601-410 601-411 601-412601-413 601-414 601-415 601-416 601-417 601-418601-419 601-420 601-421 601-422 601-423 601-424601-425 601-426 601-427 601-428 601-429 601-430601-431 601-432 601-433 601-434 601-435 601-436RECORDSNo Records are generated by this procedure.COMMITMENTSSNC1 9472, SNC5027 V4Page 8 of 161.0 IDENTIFICATION:ALARM PANEL 601-4 __________REFUELING FLOOR___ __ __ ___VENT EXHAUST___ __ __ __ ___RADIATION HI-HIDEVICE: SETPOINT:1D11-K611A thru D 18 mr/hr2.0 CONDITION: 3.0 CLASSIFICATION:EMERGENCYRadiation levels in the Refueling Floor Exhaust Duct exceed the 4.LOAINsetpoint.1H11-P601 Panel 60 1-45.0 OPERATOR ACTIONS:5.1 Confirm the annunciator by monitoring 1 D11-R607, Recorder, panel 1H11-P600. D]5.1.1 Monitor the R/F VENT EXHAUST RAD MON, 1 HI1-P606; IF only one trip unit is affected,attempt to reset the affected trip unit. Eli5.2 IF only one trip unit is alarmed, AND the unit is not malfunctioning,determine and correct the cause of the high high radiation. LI5.3 IF" the A AND B, OR the C AND D OR all channels of trip unit 1 D11-K61 1 are tripped,enter 31EO-EOP-014-1, SC-Secondary Containment Control, andperform concurrently with this procedure. Eli5.4 IF refueling is in progress, STOP refueling operations, andif possible, insert any withdrawn Control Rods. LI5.5 Evacuate personnel from the Refueling Floor. LI5.6 IF: refueling or fuel handling was in progress,ENTER 34AB-J11-001-1, Irradiated Fuel Damage During Handling. LII5.7 IF" an abnormal radioactive release is occurring,ENTER 34AB-D1 1-001-1, Radioactive Release Control. LI6.0 CAUSES:6.1 High radiation levels in the vent duct6.2 Trip unit failure, upscale or downscale
+==7.0 REFERENCES==
+: 8.0 TECH. SPECS./TRMIODCM/FHA:7.1 H-19551 through H-19566, H19578, H19584, & H19596, 8.1 Secondary ContainmentProcess Radiation Monitoring System Elem Diag Isolation Instr Table 3.3.6.2-134AR-601 -403-1Ver. 3.5 V4Page 9 of 161.0 IDENTIFICATION:ALARM PANEL 601-4 ___________ __ ___RX BLDG POT___ __ __ __ ___CONTAM AREA______-VENT RADN HI-HIDEVICE: SETPOINT:1 D11-K609A 1ID11-K609B 18 mr/hr1D1 1-K609C, 1 D1 1-K609D5.0 OPERATOR ACTIONS:5.1 Confirm annunciator by monitoring the radiation level on 1D11-R605, recorder, 1H11-P600. LI5.1.1 Monitor 1 D11-K609A, ID11-K609B, 1ID11-K609C, 1D1I-K609D, Reactor BuildingPotential Contaminate Area Rad Monitors, 1Hi 11-P606.IF only one trip unit is affected, attempt to reset the affected trip unit. Eli5.2 IF only one trip unit is alarmed AND the unit is not malfunctioning,determine and correct the cause of the high high radiation. LI5.3 IF the A AND B, OR the C AND_ D OR all channels of trip unit 1 D11-K609, are tripped,ENTER 31EO-EOP-014-1, SC-Secondary Containment Control. III5.4 IF an abnormal radioactive release is occurring,ENTER 34AB-D1 1-001-1, Radioactivity Release Control. LI6.0 CAUSES:6.1 Primary leakage
+==7.0 REFERENCES==
+: 8.0 TECH. SPECS./TRM/ODCM/FHA:7.1 H-19561, H-19564, H-19563, & H-19566, Process 8.1 Unit 1 T.S. 3.3.6.1Radiation Monitoring System Elem Diag 8.2 Unit 1 T.S. 3.3.6.27.2 H-16005, Reactor Building Vent System P&ID34AR-60 1-426-1Ver. 3.5 V4Page 10 of 16SOUTHERN NUCLEAR IDOCUMENT TYPE:IPLANT ElI. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) PAGE 1 OF 2DOCUMENT TITLE: NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 2H1 1-P601, ALARM PANEL 3 l 34AR-601-904-2 12.18EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER G. L. Johnson DATE 04/19/00 DATE:8/31/15N/A SSM /PM N/A DATE N/A _____ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601 -ALARM PANEL 3ARP NO VER. NO. ARP NO. VER. NO. ARP NO VER. NO.34AR-601 -301-2 3.1 34AR-601 -31 3-2 3.5 34AR-60 1-325-2 2.334AR-60 1-302-2 3.2 34AR-60 1-314-2 2.4 34AR-60 1-326-2 0.534AR-601-303-2 3.3 34AR-601-315-2 1.2 34AR-601-327-2 5.234AR-601 -304-2 3.2 34AR-60 1-316-2 0.2 34AR-60 1-328-2 2.234AR-601 -305-2 0.3 34AR-601 -317-2 2.1 34AR-601 -329-2 1.334AR-60 1-306-2 3.3 34AR-601 -318 SPARE 34AR-60 1-330-2 2.234AR-601-307-2 2.4 34AR-601-319-2 0.3 34AR-601-331-2 2.334AR-601-308-2 2.3 34AR-601-320-2 1.2 34AR-601-332-2 0.334AR-601-309-2 1.2 34AR-601-321-2 4.2 34AR-601-333-2 0.334AR-601-310-2 0.4 34AR-601-322-2 0.6 34AR-601-334 SPARE34AR60131 12 03 3AR-61-33-2 .3 4AR601 4.34AR-601-311-2 4.3 34AR-601-323-2 2.4 34AR-601-335-2 04.SNT:IApproval signature on this page constitutes approval for all procedures listed above at the !NOErevision indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneMGR-0002 VER. 8.1 V4of 16UNIT 22H11-P601 -3601-301 601-302 601-303 601-304 601-305
+* 601-306601-307 601-308 601-309 601-310 601-311
+* 601-312601-313 601-314 601-315 601-316 601-317 601-318601-319 601-320 601-321 601-322
+* 601-323 601-324601-325 601-326 601-327 601-328 601-329 601-330601-331 601-332 601-333 601-334 601-335 601-336* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on Trip Unit Label(s) at 2D21-P600 to provide across reference for locating the device(s) in ABNORMAL AND/OR EOP Tables.Refer to 34AB-T22-003-2, Secondary Containment Control.RECORDSNo records are generated from this procedure.COMMITMENTSNONEMGR-0001 VER. 4 V4Page 12 of 161.0 IDENTIFICATION:ALARM PANEL 601-3-II--IIrREFUELING FLOORAREA RADIATIONHIGHDEVICE: SETPOINT:2D21-K601-A,E,M See 64CI-CAL-002-02D21-K61 1-K,L5.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light AND~ high reading on individual indicator/tripunits on panel 2D21-P600. LI5.1.1 Attempt to reset Trip Unit. LI5.2 IF 2D21-K601 A O._R M Tripped,THEN confirm Control Room ventilation shifted to pressurization (Mode II) per34SO-Z41-001-1, Control Room Ventilation System. LI5.3 IF Trip Unit will NOT reset, perform the following:5.3.1 Confirm monitor reading by checking 2D21-R600A, Area Radn Monitor Recorder,panel 2H1 1-P600 (see channel below) Lii5.3.2 Contact Health Physics to confirm radiological condition in the affected area,evacuate area IFrequired. LI5.3.3 Periodically monitor panel 2D21-P600 to ensure no other channels on the RefuelingFloor are indicating high OR in alarm. LI5.3.4 Enter 34AB-T22-003-2, Secondary Containment Control. LI5.3.5 IF a radioactive release outside the Reactor Building is occurring, OR has occurred,enter 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation causing a trip of one ORR more of the following indicator trip unitsMONITOR CHANNEL LOCATION SENSOR TRIP UNIT1 Reactor Head Layout Area 2D21-N002-A K601-A5 Dryer/Separator Pool 2D21-N002-E K601-E10 Spent Fuel/Fuel Pool Areas 2D21-N002-M K601-M21 Reactor Vessel Refueling Area 2D21-N012-K K61 1-K22 Reactor Vessel Refueling Area 2D21-N012-L K61 1-L6.2 Malfunction of trip unit
+==7.0 REFERENCES==
+.0 TECH. SPECS./TRMIODCMIFHA:7.1 H-27805 thru H-27810 and H-27992, Area RadiationMonitoring Sys 2D21 Elementary Diagram 8.1 TRM Table T3.3.7-134AR-60 1-312-2Ver. 4.3MGR-0048 Ver. 5.0 A-GR7- 0AG-MGR-75-1101 V4Page 13 of 16SOUTHERN NUCLEAR )OCUMENT TYPE:PLANT ElI. HATCH lANNUNCIATOR RESPONSE PROCEDURE (ARP PAGE 1 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO:ARP'S FOR CONTROL PANEL 2HI11-P601, 34AR-601-901-2 l 12.1ALARM PANEL 4/EXPIRATION APPROVALS: IEFFECTIVEDATE: DEPARTMENT MANAGER DAK for Keith D. Long DATE 5-9-13 I DATE:N/A SSM/PM N/A DATE N/A 5-i5-I5ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601 -ALARM PANEL 4ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-401-2 0.3 34AR-601-413-2 1.2 34AR-601-425-2 3.434AR-60 1-402-2 4.1 34AR-60 1-414 Spare 34AR-60 1-426-2 6.334AR-601-403-2 5.4 34AR-601-415-2 1.0 34AR-601-427-2 2.334AR-60 1-404-2 0.3 34AR-60 1-416-2 0.5 34AR-60 1-428-2 5.534AR-60 1-405-2 8.1 34AR-60 1-417-2 4.3 34AR-60 1-429-2 3.134AR-60 1-406-2 8.3 34AR-60 1-418-2 1.2 34AR-60 1-430-2 0.334AR-60 1-407-2 3.6 34AR-60 1-419-2 1.1 34AR-60 1-431-2 2.134AR-601-408-2 1.0 34AR-601-420-2 6.3 34AR-601-432-2 4.334AR-601-409-2 5.3 34AR-601-421-2 4.3 34AR-601-433-2 1.434AR-601-410-2 2.3 34AR-601-422-2 5.4 34AR-601-434-2 3.034AR-601-411-2 4.5 34AR-601-423-2 4.4 34AR-601-435-2 1.134AR-601-412-2 0.4 34AR-601-424-2 2.3 34AR-601-436-2 0.1IINOTE Approval signature on this page constitutes approval for all procedures listed above at theI Version indicated. Tab numbers in the back correspond to procedure sequence number.FILevel Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO None V4Page 14 of 162 OF2SOUTHERN NUCLEARPLANT E.I. HATCHDOCUMENT TITLE: 'DOCUMENT NUMBER: VERSION NO:ARP'SALRFORpAECONTROL4 PANEL 2H11-P601, 34AR-601-901-2 1 12.1UNIT 22H1 1-P601 -4601-401 601-402 601-403 601-404 601-405 601-406601-401 601-408 601-409 601-410 601-411 601-412601-413 601-414 601-415 601-416 601-417 601-418601-419 601-420 601-421 601-422 601-423 601-424601-425 601.426 601-427 601-428 601-429 601-430601-431 601-432 601-433 601-434 601-435 601-436RECORDSThere are no records generated from this procedure.COMMITMENTSSNC5027 V4Page 15 of 161.0 IDENTIFICATION:ALARM PANEL 601-4T 11 T T -1-4-1REFUELING FLOORVENT EXHAUSTRADIATION HI-HIDEVICE:2D11-K611 A thru D2D11-K634 Athru D2D11-K635 Athru DSETPOINT:18 mr/hrPER 64Cl-CAL-002-0PER 64CI-CAL-002-02.0 CONDITION: 3.0 CLASSIFICATION:Radiation levels in the. Refueling Floor Exhaust Duct exceed EMERGENCYthe setpoint. 4.0 LOCATION:2H11-P601 panel 601-45.0 OPERATOR ACTIONS:5.1 Confirm the annunciator by monitoring recorders on panel 2H1 1-P600:* 2D11-R615 for 2D11-K611A &2D11-K611 B, and 2D11-K634A -D LI* 2D11-R616 for 2D11-K611C &2D11-K611D, and 2D11-K635A- D Lii5.1.1 Monitor the R/F Vent Exhaust Rad Mon on 2H11-P606;IF only one trip unit is affected, attempt to reset the affected trip unit. LI5.2 IF only one trip unit is alarmed, AND the unit is NOT malfunctioning,determine AND correct the cause of the high high radiation. Eli5.3 IF refueling operations are in progress,STOP refueling operations ANDIF possible, insert any withdrawn Control Rods. LI5.4 Evacuate personnel from the Refueling Floor. LII5.5 IF refueling OR fuel handling was in progress,enter 34AB-J1 1-001-2, Irradiated Fuel Damage During Handling. LI5.6 For valid alarm conditions, enter 31EO-EOP-014-2, SC-Secondary ContainmentControl AND 34AB-T22-003-2, Secondary Containment Control. LI5.7 IF an abnormal radioactive release is occurring OR has occurred,ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation levels in the vent duct6.2 Trip unit failure, upscale OR downscale ___________________
+==7.0 REFERENCES==
+: 8.0 TECH. SPECS./TRMIODCMIFHA:7.1 H-27629 and H-27631, Process RadiationMonitoring Diagram, Sheets 10 and 12 8.1 U2 TS 3.3.6.1 Table 3.3.6.1-17.2 H-27596 thru H-27600, Primary ContainmentIsolation System, Sheets 1 through 5 8.2 U2 TS 3.3.6.2 Table 3.3.6.2-134AR-60 1-403-2VER. 5.4 V4Page 16 of 161.0 IDENTIFICATION:ALARM PANEL 601-4________RX BLDG POT___ CONTAM AREAVENT RADN HI-HIDEVICE: SETPOINT:2011l-K609A through 0, Per 64CI-OCB-006-2, Form HPX-1 252, from ChemistryTrip Indicator Unit2.0 CONDITION: 3.0 CLASSIFICATION:Radiation levels on the inlet to 2T41-D005, Reactor Building EMERGENCYExhaust Filter Train, exceeds the setpoint. 4.0 LOCATION:2H11-P601 panel 601-45.0 OPERATOR ACTIONS:5.1 On panel 2H1 1-P600, confirm annunciator by monitoring the radiation level on2D1 1-K609A/2D1 1-K609B/2D11l-K609C/2D1 1-K609D on 2D1 1-R605 recorder. El5.1 .1 Monitor 2011 -K609A through D, Reactor Building Potential Contaminated AreaRad Monitors, on 2H11-P606.IF only one trip unit is affected, attempt to RESET the affected trip unit. LI5.2 IF only one trip unit is alarmed AND the trip unit is NOT malfunctioning,determine AND correct the cause of the high high radiation. El5.3 IF the A & B, O._R the C & D O__R all channels of trip unit 2D1 1-K609 are tripped,THEN enter 31EO-EOP-014-2, SC-Secondary Containment Control ANDconfirm Automatic Actions per 34AB-T22-003-2, Secondary Containment Control,Attachment 7. LI5.4 IF an abnormal radioactive release is occurring OR has occurred,ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 Steam leaks
+==7.0 REFERENCES==
+: 8.0 TECH. SPECS./TRM/ODCMIFHA:7.1 H-27629, H-27631, H-27632, & H-27634, Process 8.1 U2 TS 3.3.6.1Radiation Monitoring System Elem. Diag.7.2 H-26067 Reactor Zone Ventilation System P&ID34AR-601 -420-2VER. 6.3 VSPage 1 of 3SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE ('ARP' AGE 1 OF 2V5Page 1 of 3DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 34AR-601-902-1 ] 14.41H11-P601, ALARM PANEL 1EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE:04-30-15N/A SSM /PM: N/A DATE: N/AANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601 -ALARM PANEL 1ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-101-1 5.1 34AR-601-113-1 2.1 34AR-601-125-1 6.234AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.234AR-601-103-1 6.2 34AR-601-115-1 4.1 34AR-601-127-1 6.234AR-601-104-1 3.3 34AR-601-116-1 5.6 34AR-601-128-1 3.234AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.134AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.034AR-601-107-1 1.1 34AR-601-1 19-1 1.1 34AR-601-1 31-1 6.334AR-601 -108-1 2.2 34AR-601 -120-1 5.2 34AR-601-1 32-1 3.334AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.134AR-601-110-1 4.2 34AR-601-122-1 4.1 34AR-601-134-1 4.334AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.534AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0NOTE:______ Approval signature on this page constitutes approval for all procedures listed above at the~ NOTE:revision indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneNMP-AP-002I V5Page 2 of 3SOUTHERN NUCLEARPLANT E.I. HATCHPAGE 2 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO:ARP'S FOR CONTROL PANEL 1H11-P601, 34AR-601-902-1 1 14.4ALARM PANEL 1UNIT 11H11-P601 -1601-101 601-102 601-103 *601-104 601-105 601-106601-107 601-108
+* 601-109
+* 601-110 601-111 601-112601-113 601-114 601-115 601-116 601-117 601-118601-119 601-120 601-121 601-122 601-123 601-124601 -1 25 601 -1 26 601-1 27 601-1 28 601-1 29 601 -130601-131 601-132 601-133 601-134 601-135 601-136RECORDSThere are no records generated from this procedure.COMMITMENTSNone* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on TRIP UNIT Label(s) at 1D21-P600 to provide across-reference for locating the device(s) in Abnormal and/or EOP Tables.Refer to 34AB-T22-003-1, Secondary Containment Control.NMP-AP-002 v.2.0 V5Page 3 of 31.0 IDENTIFICATION:ALARMPANEL_601-1 ___________ __ ___TURBINE BLDG__RADIATION___ __ ___HIGHDEVICE: SETPOINT:SEE SECTION 6.0 AS PER THE CHEMISTRY CONTROLLED SETPOINT RECORD5.0 COPERATIOR: ACTIONS:FCATON5.1 At 1D21-P600, monitor ARMs listed in Section 6.0,to determine which monitor(s) indicates high, to assess the severity, and monitor for trends. LI5.1.1 Attempt to reset the trip unit. Iii5.2 Notify Health Physics to determine the validity of the alarm. LI5.3 IF the alarm is valid,enter 73EP-RAD-001-0, Radiological Event. LI5.4 Refer to 34AB-U22-001-1, Pipe Break in Turbine Building, for possible entry conditions. LI5.5 IF a radiation release to outside the Turbine Building has occurred OR is occurring,enter 34AB-D1 1-001-1, Radioactivity Release Control. LI5.6 IF a Fuel Element Failure is confirmed,Initiate Turbine Building Purge per 34SO-U41-001-1 radiation. LI5.7 Monitor other ARM's that are associated with this annunciator for increasing radiation. LI6.0 CAUSES:High radiation, as indicated by one of the following ARM's:1D21-R600 POINT NUMBER MONITOR AREA22 1D21-K600A Main Turbine Front Standard23 1D21-K600B Control Room24 1 D21-K600C Control Room25 1D21-K600D T/B 164' North End Operating Floor26 1D21-K600E Turbine Bldg Feedwater Area27 121-K01ZCondensate Demin Area34AR-601-1 16-1Ver. 5.6MGR-0048 Ver. 5 SM-SNC524602-001IAttachment IENERCON Calculation for E-HU1SHEET I-6 v15Page 1 of 3CALC NO. SNC024-CALC-003FNP DETERMINATION OFEMERGENCY ACTION LEVEL REV. 0PAGE NO. Page 6 of 85.0 Design Inputs1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask systemtechnical specification [2, Table 6.2-3] are provided below in Table 5-1. Thesesource values are scaled to develop the emergency action levels for initiatingcondition E-HU1.Table 5-1 Technical Specification Dose Rate Limits (Neutron + Gamma) for HI-STORM100 and HI-TRAC 125LocaionNumber of 1Technical SpecificationjMeasurementsj Limit (mrem/hr)HI-TRAC 125Side -Mid -height T 4 1680.3Top 1 4 j129.4HI-STORM 100Side -60 inches below mid-height 4 171.8Side -Mid -height 4 177.0Side -60 inches above mid-height 4 84.7Top -Center of lid 1 27.1Top -Radially centered 4 30.0Inlet duct 4 231.8Outlet duct 4 82.2 SM-SNC524602-001Attachment IIPNI::IlNN (.'l'ml:afinn fnr IF..WI I1SHEET I-7 v15Page 2 of 3CALC NO. SNCO24-CALC-003FNP DETERMINATION OF ___________EMERGENCY ACTION LEVEL REV. 00I EN ER C ON FORI=NITATNG CONDITION E- _ _______..."' HUl PAGE NO. Page 7 of 86.0 MethodologyThe "on-contact"' dose rates from the technical specification for the HI-STORM 100 andHI-TRAC 125 cask system are scaled by a factor of 2, as specified in NEI 99-01 Rev. 6[1], for use in initiating condition E-HU1.
+SM-SNC524602-001Attachment II:PCANI (%lrdp-mi6*rn fr i::._WI I1SHEET I-8 v15Page 3 of 3CALC NO. SNC024-CALC-003FNP DETERMINATION OFEMERGENCY ACTION LEVEL REV. 00 E N E R C 0 N FOR INITAliNG CONDITION E-HUl PAGE NO. Page 8oft87.0 CalculationsThe dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose ratelimits. These calculations are presented below in Table 7-1.wTable 7-1 Dose Rate Scaling Calculations for EAL Limits (Neutron + Gamma)TechnicalLoainSpecification Scaling Calculated Value EALLoainLimit Factor .(mremn/hr) (mrem/hr)_______________________ (mremlhr) ____________ _____________ ______ ______ ______HI-TRAC 125 _ _ _ _ _ _ _ _ _ _ _ _ _ _Side -Mid -height [ 680.3 j 2 J 1360.6 1360Top L 129.4 j 2 258.8 260Side -60 inches below mid-heightSide -Mid -heightSide -60 inches above mid-heightTop -Center of lidTop -Radially centeredInlet ductOutlet duct171.8177.084.727.130.0231.882.2343.6 340354 350169.4 17054.2 5060 60463.6 460164.4 1608.0 Computer SoftwareMicrosoft WORD 2Q13 is used in this calculation for basic multiplication.
+V16LYN I Page 1o of 8CORE COOLING Revision 17P SSFIFTH NOHOTTEST ITC LESS iGO TOSATaPage1 ofI1 V16N !T 1Page 2 of 8HEAT SINK Revision 17FRP4.LI~GO TOFRP-H.2PRESS IN INOIALL SG'S L.EBB THAN""GO TOFRP-H.3NAR RNG NLVL IN ALL LSO'S LESS '--'THAN 62 1YESJGOTOr FRP-H.4PRESS IN NALL SG'SLESS THAN,,,,,1075 P8I10YEGO TO-I FRP-4.5CSFSAT 1V16Page 3 of 88/29/2007 08:3 3FNP-I-CSF-O.4 INTEGRIT Revision 17I-f,' GO TOFRP.P.1JGO TOinininm m --t aFRP-.2CSFSATGO TOGOOTSATSATPagI 1 f2
+[NI 1Page 4of 8FP1CSF-0. COTANMN Geson TOPRESS NO in in, -FRP-Z.1LESS ri- !THAN 5 YEs At LEAST ONE NOIPUMP RUNNING-- --OTI (FLOW>IODOOGPM) YES ,. 2I CTMT koI S~UMP LVL NCTMT [THAN 7.6 I=:LESS HTHAN 27 YsGO TOPSIG FRPZ.SUMP LVL.NLESSTHAN 7.6HFT.~GO TOFRP-Z.3BOTHCTMT RAD NLESS --hrTHAN 2 R/ LY1CSPage 1 of I 1I]IJIT9Vi16Page 5 of 88/29/2007 08:33 -FNP-2-CSF-0,2 CORE COOLING Revision 12GOTOoIP I m IIFRP-C.1HOTTEST NORP.CCORE EXITTHAN YETHANT790TCREXIT---,TC LSSTC HESSUBOO NO GO TOCOR PRP-C.30 EXIOT TCS "-iGRTR THAN Ei16" F 145"F}Page1 of 1 V1 6!]N IT 2Page 6 of 8FNP-2-CSF-O0.3 HEAT SINK Revision 12SGO TOFRP-K.1miTOTAL AFW NOIiFLOW TO I1 ALL SG'8 -,-,395 GPM EGO TO~FRP-HL2LVL IN AT IN NOLEAST ONE ALL SG'SSG GRTR --'-LESS THANTHAN 31% YES __ _______ 1129PSIG YES,[ GO TO! f FRP-H.3MiAR RNG [N]LVL IN ALLSGS8 LESS mmmTHAN 52% YESGO TO-I FRP-H.4PRESS IN NOALL 5G5S:ILESS THANmmg1075 P810 YESGO TOI r FRP-H.5CSFSATPage 1 of I V167 of 8FNP-2-CSF-O.4 IINTEGRITY Revision 12COLD LGTMEAUE('F GO TOW FRP-P,1ALL RCSPRESS- OTCL TEMP (IN m -ine e lRIGHT OF YES ,.,i_AL. RCS CL N OTTEMPS INGOTSLAST 60 MIN -,FRP..P.2GRTIR THAN--'---- L RCS CL N~ TEMP TEMPNO SALALATT600MINLESSR ThANTEM DCRNN OJ SALESTRTTAHAN GOT326' F SATCSFSATPage I of 2 Vi16*l Page 8 of 88/29/2007 08:33 I NJ J .FNP-2-CSF-0.5 CONTAINMENTReion1H CTMT TI _O__OPRESS NO R "P .L "I m-~-LESS H-- 11THAN 5 YES At LEAST ONE NORUNNING(FLOW1 000GPM)YESFnI *m WRP-Z.2SUMP LVL OICTMT- THAN 7.6[PRESS NLESS- SITHAN 27 YEs GO TOPSIG jjFRP-Z.1SUMP LVI NOLESS H.-THAN 7.6 YEFT.GO TOFRP-Z.31THAN2RJ [EST SATPage 1 of I V1 7Page 1 of 807/13/15 09:23:59 LOCATION FiUlSETPOINT: 1. Variable, as per FNP-1-RCP-252 HIRMSORIGIN: Any of the below listed Area, Process or Gaseous and HI-RADParticulate Monitors: R01, R02, R03, R04, RO5, R06,R07, R08,-R1OI RI1, R12, RI3,[T RI5, RI7A ________R17B, RIS8, R-I19, R20A, R20B, R21, R23A orR23B.PROBABLE 1 .High Radiation Level in the System, Area or at the Component monitored.2. The radiation monitors fail to a "High Radiation" condition on loss ofinstrument and/or control power that will result in actuation of associatedautomatic functions.AUTOMATIC ACTIONS;I. The following actions will occur if a High Radiation Alarm is actuated onthe associated Radiation Monitor.A. R14: (Plant Vent Gas) closes Waste Gas Release ValveI -G WD-HV-0 14.8. R16: None -abandoned in place per MDC 1040589501.C. R17A or B: (Component Cooling Water) closes QIPIYRCV3028CCW SRG TANK VENT.D. R18: (Liquid Waste Processing) closes Liquid Waste Release ValveI -L WP-RC V-0 18.E. R19: (Steam Generator Blowdown) isolates Steam GeneratorBlowdown Sample Lines.F. R23A :( Steam Generator Blowdown Processing) closes1-BD-FC V-I1152 SIG Blowdown Heat Exchanger Outlet FCV.G. R23B :( Steam Generator Blowdown Processing) closesI-BD-RCV-023B SQ BLOWDOWN PMP DISC.Page 1 of 15Page 1of 15Version 72.1 V1 7Page 2 of 807/13/15 09:23:59FNP-I-ARP-I .6LOCATION FHI.*RADIATION MONITOR TABLEI -p y pLOCATIONDETECTORFUNCTIONACTIONSR-IA Control Room (Unit I Area G-M (W) Perform Step____ Panel) _ _ _ _ _ __ 4.1R-I B Technical Support Center Area G-M ( W ) No input to__ _(Unit II Panel) R-IB _______ ____this alarmR-2 Containment (155' elev) Area G3-Mr ( W) Starts IPC dose Perform Steps____ ________integration 4.2R-3 Radiochemistry Lab (AB Area G-M (W~) Perform Step_ _ _ _ 139') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.3R-4 #3 Charging Pump (AB Area G-M (_W ) Perform StepI__ _ 00') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.4R-5* Spent Fuel Pool Room (AB Area G-M (_.W) Perform Steps_ _ _ _ 155') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 4.5R-6 Sampling Room (AB 139') Area G-M ( _W) Perform Step____ __ ____ ___ ___4.6R-7 In-core NIS Area (CTMT Area G-M ( W) Starts [PC dose Perform Steps____129', near Seal Table) ___________integration 4.7R-8 Drumming Station (AB Area G-M (W ) Perform Step_ _ _ _ 155') _ _ _ _ _ _ _ _ _ __4.8R-9 SG Sample Panel (Unit II Area G-M ( W ) No input toPanel) (AB 139') ___ _____this alarmR-0 Penetration Room Filtration APD Beta Scint Perform StepDischarge (AB 155') ____**(GA-ES) 4.9R-I 1
+* Containment Atmosphere APD Beta Scint Perform Step(AB 121') **__ (GA-ES) _______4.10*Technical Specification related**General Atomics Electronic SystemsPage 5 of 15 Vrin7.Version 72.1 V17Page 3 of 807/13/15 09:23:59FNP-1-.ARP-1 .6LOCATIONFHRADIATION MONITOR REFERENCE TABLE (cont)RELOCATION TYPE~ DETECTOR FUJNCTION ACTIONSR- 12" Containment Atmosphere Gas Beta Scint Perform Step____(AR 121') ___ **(OA-.ES) ________4.11lR-1 3 Waste Gas Compressor Gas G-M ( _W) Perform StepSuction (AB 100' WGC 4.12Valve Room) _________________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform StepODCM ________ __4.13R- i 5A Condenser Air Ejector Gas G-M ....Perform StepODCM Discharge Header (TB 155') 4.14R-I 5B* Condenser Air Ejector Gas G-M (Eberline) Perform Step(Intermediate Range) (T 4.15R-I 5C* Condenser Air Ejector Gas Ion Chamber Perform Step____(High Range) (TB 189') (berline) _______4.15R-1 7A Component Cooling Water Liquid Scint. ( W) Closes CCW Perform Step(CCW H-x Room) surge tank vent 4.16_______ ~~(RCV-3028) ______R-17B Component Cooling Water Liquid Scint. Closes CCW Perform Step(CCW Hx Room) surge tank vent 4.16______ _____ ___________(RCV-3028)R-1 8 Waste Monitor Tank Pump Liquid Scint. ( W) Closes RCV-1 8 Perform StepODCM Discharge (AB 121' at the 4.17______Batching Funnel) _____R-19 Steam Generator Liquid Scint. (YWL) Isolates sample Perform StepBlowdown/Sample (AR lines 3328, 4.1 8____139') _______3329, 3330 ______R-20A Service Water from Liquid Scint. ( W) Perform StepContainment Coolers A and 4.19B (AB 121' BTRS Chiller______ Room)__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R-20B Service Water from Liquid Scint. ( _W) Perform StepContainment Coolers C and 4.19______D (AB 121') ____________ __ _____*Technical Specification related**General Atomics Electronic SystemsPage 6 of15 Vrin7.Version 72.1 V1 7Page 4 of 807/1 3/15 09:23:59FNP-I-ARP-1 .6LOCATION FillRADIATION MONITOR REFERENCE TABLE (cont)RE LOCATION TYP DIETECTR FUNCTON ACTIONSR-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____ ____________ ____(Victoreen) 4.20R-22 Plant Vent Stack Gas G-M (_W Perform StepODCM (AB 155') -)_______________ 4.21R-23A SG Blowdown Surge Tank Liquid Scint. (__) Closes Perform StepInlet (AB 130') ____FCV-1152 4.22R-23B SG BLOWDOWN PMP Liquid Scint. ( __i) Closes Perform StepODCM DISC (AB 130') ___ _____RCV-23B 4.22R-24A* Containment Purge (AB Gas Scint. Closes No input to155') containment this alarmpurge supply &exhaust dampers2866C & 2867C____________ _______and 3198A &DR-24B* Containment Purge Gas Scint. Closes valves: No input to(AB 155') (Victoreen) 2866D &2867D, this alarm3196,3197,____________ _______3198B & CR-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input toR-25B* (AB 184') (Victoreen) supply and this alarme~xhaust fans;closes SEPH-VAC supplyand exhaustdampers; startsassociated trainsof penetration_____________ __ _ ________room filtration. ____R-27A* Containment (High Range) Area Ion Chamber No input to_____ _____________ ____(Victoreen) _ ______this alarmTechnical Specification relatedPage 7 of 15 Vrin7.Version 72.1 07/13/15 09:41:15 1F~~i~ NP-2-ARP-1.6 Page 5of 8LOCATION .IillSETPOINT: 1. Variable, as per F'NP-2-RCP-252ORIGIN: Any of the below listed Area, Process or Gaseous andParticulate Monitors: ROI!B, R02, R04, R05, R06,R07, RO8, R09, RI I, R12, R 13, -R'4 R15,R17A, RI7B, RIB, R19, R20A, R20B[ R21, R224R23A or R23BPROBABLE CAUSERMSHI-RADI. High Radiation Level in the System, Area or at the Component monitored.I2. The radiation monitors fail to a "'High Radiation-"" condition on loss ofinstrument and/or control power that will result in actuation of associatedautomatic functions.AUTOMATIC ACTION1. The following actions will occur if a High Radiation Alarm is actuated onthe associated Radiation Monitor.a) R14: (Plant Vent Gas) closes Waste Gas Release Valve 2-GWD-HV-0 14.b) R16: (Boron Recycle System) diverts 2-C VC-RC V-016 RecycleEvaporator discharge from Reactor Makeup Water System to theRecycle Evaporator Demineralizer.c) RI7A or B: (Component Cooling Water) closes 2-CC W-RC V-3028CCWN SRG TANK VENT.d) R I8: (Liquid Waste Processing) closes Liquid Waste Release Valve2-LWP-RCV-0I18.e) RI9: (Steam Generator Blowdown) isolates Steam GeneratorBlowdown Sample Lines.t) R23A: (Steam Generator Blowdown Processing) closes2-BD--FCV-1 152 S/G Blowdown Heat Exchanger Outlet FCV.g) R23B: (Steam Generator Blowdown Processing) closes2-BD-RCV-023B SGBD DISCH TO ENVIRONMENT.Page 1 of 13 Vrin6.Version 61. i SNIT 207/13/15 09:41:15Vi17FNP-2-ARP-I.6 Page 6 of 8LOCATION FHilOPERATOR ACTION (cont)4. In addition to the general actions perform steps indicated in the "ACTIONS"column of the following table. (Some of the radiation monitors included in thetable do not input into this alarm but are included for reference).RADIATION MONITOR REFERENCE TABLECRE LO:CATION TYPE DETECTOR FUNCTION ACTIONSR- 1A Control Room (Unit I Area G-M ( W) No input toPanel) _______this alarmR- lB Technical Support Center Area G-M ( W) Perform Step(Unit 1] Panel) R-l 1B_________ 4.1R-2 Containment (155' elev) Area G-M ( W) Starts IPC dose Perform Steps___ __ ___ __ ___ __ _ _ __ __integration 4.2R-3 Radiochemistry Lab (AB Area G-M ( W) No input to139') __________this alarmR-4 #3 Charging Pump (AB Area G-M (W) Perform Step100') _____ ________4.3R-5* Spent Fuel Pool Room (AB Area G-M (Wj) Perform Steps155') _ _ _ _ _ _ _ _ _ _ 4.4R-6 Sampling Room (AB 139') Area G-M ( W) Perform Step____ ___ ____ ___ ____ ___ ___ ___ ____ ___4.5R-7 In-core NIS Area (CTMT Area G-M ( W) Starts IPC dose Perform Steps129', near Seal Table) ____integration 4.6R-8 Drumming Station (AD Area G-M ( W) Perform Step155') __ _ _ _______4.7R-9 SG Sample Panel (Unit II Area G-M (W) Perform StepPanel) (AB 139') 4.8R- 10 Penetration Room Filtration APD Scint. Perform Step____Discharge (AD 155') (Victoreen) 4.9R- 11
+* Containment Atmosphere APD) Scint. Perform Step____(AB 121') ____(Victoreen) _______4.10**Technicail Specification relatedPage 4 of 13Page 4of 13Version 61.1
+~k J. ~'V1 7FNP-2-ARP-1.6 Page 7 of 807/13/15 09:41:15LOCATION FHilRADIATION MONITOR REFERENCE TABLE (cont)RE. LOCATION TYPE DETECTO FU[NCTION ACTIONSR- 12* Containment Atmosphere Gas G-M ( W) Perform Step(AB 121') _____4.11R-13 Waste Gas Compressor Gas O-M (W) Perform StepSuction (AB 100' WGC 4.12Valve Room) ________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform StepODCM ___________________ __4.13R- 15A Condenser Air Ejector Gas G-M Perform StepODCM Discharge Header (TB 155') 4.14R-15B* Condenser Air Ejector Gas G-M (Eberline) Perform Step(Intermediate Range) (TB3 4.15189') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R .15C* Condenser Air Ejector Gas Ion Chamber Perform Step(High Range) (TB 189') (Eberline) 4.15R-17A Component Cooling Water Liquid Scint. (W ) Closes CCW Perform Step(CCW H-x Room) surge tank vent 4.16__________________(RCV-3028) _____R-17B Component Cooling Water Liquid Scint. Closes CCW Perform Step(CCW Hix Room) surge tank vent 4.16_________________ _____ _________ RCV-3028)R- 18 Waste Monitor Tank Pump Liquid Scint. (W ) Closes RCV- 18 Perform StepODCM Discharge (AB 121' at the 4.17_______Batching Funnel)R-19 Steam Generator Liquid Scint. ( W) Isolates sample Perform StepBlowdown/Sample (AB lines 3328, 4.18139') ___ _____ __3329, 3330R-20A Service Water from Liquid Scint. ( W) Perform StepContainment Coolers A and 4.19B (AB 121' BTRS Chiller_____Room) _________________*Technical Specification relaedPage 5 of 13 Vrin6.Version 6 I. 1 UN1IT 2V1 7FNP-2-ARP-I1.6 Page 8 of 807113115 09:41:15LOCATION .TLRADIATION MON1TOR TABLE (cont)RELOCATION IX DETECTOR FUNCTION ATIOQNSR-20B Service Water from Liquid Scint. ( W) Perform StepContainment Coolers C and 4.19______D (AB 121')______R-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____(Victoreen) 4.20R-22 Plant Vent Stack Gas G-M ( W) Perform StepODCM (AB 155') 4.21R-23A SG Blowdown Surge Tank Liquid Scint. ( W) Closes Perform Step____Inlet (AD 130') ____ _______FCV-! 152 4.22R-23B SGBD DISCH TO Liquid Scint. ( W) Closes Perform StepODCM ENVIRONMENT RCV-23B 4.22_______ (AB 130')________ ________ _ _ _ _ _ _R-24A* Containment Purge (AD Gas Scint. Closes No input to155') containment this alarmpurge supply &exhaust dampers2866C & 2867C____ ________and 3198A & _____R-24B* Containment Purge Gas Scint. Closes valves: No input to(AD 155') (Victoreen) 2866D &2867D, this alarm3196, 3197,_____3198B &CR-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input toR-25B* (AD 184') (Victoreen) supply and this alarmexhaust fans;closes SFPHVAC supplyand exhaustdampers; startsassociated trainsof penetrationroom filtration.*Teehnical Specification relatedPage 6 of 13Page6 o 13Version 61I.1I V18Page 1 of 3FNP-I-ARP-I.1207/13/15 08:32:48 -SETPOINT:1.2.3.0.01lgSystem Health RelayAlarm Relay 0LOCATION M~~SEISMICPANELALARMORIGIN: 1. SSA-3 Solid State Accelograph(NIH 11NGSI2507G)2. System Health Relay (8 inputs)* Recorder memory usage exceeding 80%* Failure of recorder(s) to respond to pollingfrom central controller.* Hardware failure* Recorder high temperature* Failure of recorder(s) to respond to controllerduring startup.* Communication problem.* DC power loss on alarm panel.* AC power loss on recorder(s).3. Alarm relay 0 (From channel 1 recorder, used forfunctional testing only).PROBABLE CAUS1. Seismic event.12. Operating Basis Earthquake (OBE) exceeded.I3.4.5.Seismic Panel loss of power.Instrument malfunction.Seismic finctional testing in progress.AUTOMATIC ACTION1. The monitoring system remain on at all times continuously monitoringthe signals from the acceleration sensors.2. When a setpoint is exceeded, the system' retrieves the time history datafrom storage and automatically performs the preprogrammed calculationsfor operator review.3. The system printer provides print and plot copies of the results for recordand review.El[]ElPage I of 15 Vrin6.Version 63.1 07/13/i5 08:33:15Vi18Page 2 of 3FNP-1-ARP-I1.12LOCATION MK5OPERATOR ACTIONS CONTINUEDACTION EXPECTED3.3 Record and compare the seismicpanel printout channel 1, 2 and 3Spectral Acceleration calculatedvalues, Spectral Velocity calculatedvalues and Computed CAV values tothe Spectral Acceleration designvalues, Spectral Velocity designvalues and CAV Design Limit Valueson Table ! "~Operating BasisEarthquake Exceedance (OBEE)Limit for Determination of PlantShutdown Requirements".IRESPONSE NOT OBTAINED3.4 Check the following:CAV Design limit value has NOTbeen exceeded.*Based on operator walkdowns noplant significant damage is found.3.4.1 JF either unit tripped, THENconduct a post trip review andrestart as appropriate.3.4 IF_ any of the following has occurred:* The Spetral Acceleration design valuehas been exceeded,o_.R* The Spectral Velocity design value hasbeen exceeded,_OR* Significant plant damage is found duringoperator walkdownsTHEN OBEE Criteria has been exceeded.3.4.1Generate a Condition Report to referto FNP- I-ETP-4580 and documentthe event.3.4.2 Generate a Condition Report torefer to FNP-I-ETP-4580 anddocument the event.3.4.2 Proceed to step 4.3.4.3 Proceed to step 5.Page 4 of 15 Vrin6.Version 63.1 07/13/15 08:34:29 A l 1 NP-I-AP-1.1LOCATION M15TABLE IOPERATING BASIS EARTHQUAKE EXCEEDANCE (OBEE) LIMITFOR DETERMINATION OF PLANT SHUTDOWN REQUIREMENTSResoonse Soectr Analysis for..Free Field MeasurementChannel 1: [L"~S1Computed CAV = * ..g-sec, Limit =0.160 g-sec"PSA Limit = 0.200 g ", OBE SV Limit =15.240 Damping = 0.050Spectral acceleration exceeded OBE Design criteria at
+* frequencies.Spectral acceleration greater than 2/30OBE Design criteria at
+* frequencies.Spectral velocity exceeded OBE Design criteria at
+* frequencies.Channel 2: I'V-UP1Computed CAV -* ....g-sec, CAV Limit = 0.160 g-sec'*OBE PSA Limit -0.200 g**, OBE SV Limit ,,15.240 cm/sec, Damping =0.050Spectral acceleration exceeded OBE Design criteria at
+* frequencies.Spectral acceleration greater than 2/30OBE Design criteria at.._* frequencies.Spectral velocity exceeded OBE Design criteria at....2* frequencies.Channel 3: FT=W1Computed CAV =
+* g-sec, CAV Limit = 0.160 g-sec"&deg;OBE PSA Limit =0.200 g"*, OBE SV Limit = 15.240 cm/sec, Damping = 0.050Spectral acceleration exceeded OBE Design criteria at______ frequencies.Spectral acceleration greater than 2/30OBE Design criteria at
+* frequencies.Spectral velocity exceeded OBE Design criteria at frequencies.Calculated by Seismic Monitor. Any exceedances are exceedances of the system setupvalues per Table 2 and do not necessarily mean OBEE limits have been exceeded.oe The CAV Design Limit is 0.16 g-s but Table 2 -OBE Limit Value shows a limit value of0.0 g-s so the Farley Nuclear Plant OBE Spectra would control the OBE system alarm.O 0.20g is the EPRI OBE Limit Value (OBEE). The monitoring system will accept only onevalue at a time for the OBE limit Value. The recommended monitoring system setup (Ref'.Table 2 -OBE Limit Value) shows a limit value of 0.05g horizontal and 0.033g vertical sothe Farley Nuclear Plant OBE Spectra would control the OBE system alarm.Page 13 ofI Veson6.Version 63.1 V19Page 1 of 3RCS Specific Activity3.4.163.4 REACTOR COOLANT SYSTEM (RCS)3.4.16 RCS Specific ActivityLCO 3.4.16APPLICABILITY:The specific activity of the reactor coolant shall be within limits.MODES 1 and 2,MODE 3 with RCS average temperature (Tavg) > 500&deg;F.ACTIONS ___________ _______CONDITION REQUIRED ACTION COMPLETION TIMEA. DOSE EQUIVALENT----------------Noe-------1-131 > 0.5 pCi/gm. LCO 3.0.4c is applicable.A.1 Verify DOSE Once per 4 hoursEQUIVALENT I-131within the acceptableregion ofFigure 3.4.16-1.ANDA.2 Restore DOSE 48 hoursEQUIVALENT 1-131 towithin limit.B. Gross specific activity of B.1 Be in MODE 3 with 6 hoursthe reactor coolant not Tavg < 500&deg;F.within limit.Farley Units 1 and 23.4.16-1Amendment No. 170 (Unit 1)Amendment No. 163 (Unit 2)
+Vi19Page 2 of 3RCS Specific Activity3.4.16ACTIONS_________ ___CONDITION REQUIRED ACTION COMPLETION TIMEC. Required Action and C.1 Be in MODE 3 with 6 hoursassociated CompletionTag<50FTime of Condition A notTag<50Fmet.O._RDOSE EQUIVALENTI-131 in the unacceptableregion of Figure 3.4.16-1.SURVEILLANCEREQUIREMENTS _______SURVEILLANCE FREQUENCYSR 3.4"16.1 Verify reactor coolant gross specific activity I10E .~/g.ten accordance withsrelacFrequency ControlProgramSR 3.4.16.2 ---NOTE---------------........Only required to be performed in MODE 1.Verify reactor coolant DOSE EQUIVALENT 1-131 In accordance withspecific activity < 0.5 IpCi/gm. the SurveillanceFrequency ControlProgramANDBetween 2 and6 hours after aTHERMALPOWER changeof > 15% RTPwithin a 1 hourperiodFarley Units 1 and 23.4. 16-2Amendment No. 185 (Unit 1)Amendment No. 180 (Unit 2)
+V19Page 3 of 3RCS Specific Activity3.4.16E0U275250225200175150125.__'- -Operation_ _ .. +:_::~i- J:1 1_+?[]i. ..EI.NK.. .Acceptable ; ++ 5 -+ -* + -575. ... Operatin --50,2 5 ,. ......0 ..., '. + : + ._ L .+ ' + : + ....20 30 40 5O 0070 80 90 100Percent of RATED THERMAL POWERFigure 3.4.16-1DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit VersusPercent of RATED THERMAL POWER with the Primary Coolant SpecificActivity > 0.5 jiCi/gm DOSE EQUIVALENT 1-131.Farley Units 1 and 23.4. 16-4Amendment No. 147 (Unit 1)Amendment No. 138 (Unit 2)
+V20Page 1 of 1RCS Operational LEAKAGE3.4.133.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGELCO 3.4.13RCS operational LEAKAGE shall be limited to:a. No pressure boundary LEAKAGE;b. I gpm unidentified LEAKAGE;c. 10 gpm identified LEAKAGE; andd. 150 gallons per day primary to secondary LEAKAGE through anyone steam generator (SG).APPLICABILITY: MODES 1, 2, 3, and 4.ACTIONS____________ _____ ___CONDITION REQUIRED ACTION COMPLETION TIMEA. RCS operational A.1 Reduce LEAKAGE to 4 hoursLEAKAGE not within limits within limits.for reasons other thanpressure boundaryLEAKAGE or primary tosecondary LEAKAGE.B. Required Action and 8.1 Be in MODE 3. 6 hoursassociated CompletionTime of Condition A not ANmet.8.2 Be in MODE 5. 36 hoursPressure boundaryLEAKAGE exists.Primary to secondaryLEAKAGE not within limit.I1Farley Units I and 23.4.13-1Amendment No. 163 (Unit 1)Amendment No. 156 (Unit 2)
+V21Page 1 of 1ESFAS Instrumentation3.3.2Table 3.3,2-1 (page 2 of 4)Engineered Safety Feature Actuation System InstrumentationAPPLICABLEMODES OROTHERSPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIPFUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT2. Containment Spraya. Manual Initiation 1,2,3,4 2 B SR 3.3.2.6 NA NAbi. Automatic Actuation 1.2,3,4 2 trains C SR 3.3.2.2 NA NALogic and Actuation SR 3.3.2.3Relays SR 3.3.2.8Pressure SR 3.3.2.4High -3SR 3.3.2.7SR 3.3.2.93. Containment Isolationa. Phase A Isolation(1) ManualInitiation(2) AutomaticActuation Logicand ActuationRelays(3) Safety Injectionb. Phase B Isolaton(1) ManualInitiation(2) AutomaticActuatio LogicandAcutnRelays1,2,3,41,2,3,422 trainsB SR 3.32..6C SR 3.3.2.2SR 3.3,2.3SR 3.32.8NANANANARefer to Function 1 (Safety Injection) for all initiation functions and requirements.1,2,3A41.2,3,422 trainsB SR 3.3.2.6C SR 3.32.2SR 3.3 2.3SR 3.3 28E SR 3.3.2.1SR 3.3.2..4SR 3.32.7SR 3.3,2-9NANANANA(3) ContainmentPressureHlgh -31.2,34S 28.3 psig 5 27 psigFadley Units I and 23.3.2-10Amendment No. 185 (Unit 1) iAmendment No. 180 (Unit 2) I Edwin I. Hatch Nuclear Plant Units 1 and 2License Amendment Request for Changes toEmergency Action Level Schemes to Adopt NEI 99-01 Rev. 6and to Modify Radiation Monitors at Farley Nuclear PlantEnclosure 4Hatch EAL Verification and Validation Documents Hatch EAL V&V Documentation IndexV&V# ..'Description I' IC [Threshold'RCS Modes/Temperatures -TS Reference (Table 1.1I-I) EAL Basis Section 1.41 RCS Cold Shutdown Temperature reference (212 OF) t CA3 (1)___tj CU3 J (1)Radiation Monitor Calculations:1/2D1 1-P601 (feeding 1/2D 11-R63 1)1D11l-P007 (feeding 1D11-R631)Calc SMiNH-13-021 Rev IRG I(1)RS1 (1)RA1(1)2Radiation Monitor Calculations: 1D11-K604 RU1 (1)1D 11-K6051D11-K619 A(B)1D1 l-K600 A(B)2D1 1I-K6042D 11-K6052D1 1-K636 A(B)Ca/c SMNH-13-021 Rev 1Radiation Monitor Information: RU2 (1)b1D21-K601 A 2D21-K601 A1D11-K601 D 2D21-K601 M1D21-K601 E 2D21-K601 E1D21-K601 M 2D21-K611 K2D21l-K611 LCa/c SMNH-13-021 Rev 1 _____Radiation Monitor Calculation: CG1 (1)bDWRRM 1/2D 11-K621 A(B) CS 1 (2)bCa/c SMNH-13-021 Rev 1 ______Primary Containment Rad Monitor Calculations FCB L4A FCB L4ADWRRM RCSB L4A RCSB L4ACa/c SMNH-13-021 Rev 1 CB PL4A CB PL4AOffgas Pre-Post Treatment Reading Calculation FCB L5A FCB L5ACa/c SMNH-13-021 Rev 1I_____Drywell Fission Product Monitor Reading CalculationCa/c SMNH-13-021 Rev 1RCSB L5ARCSB L5AODCMITS Reference to Site Boundary RG1 (2)(3)3RS1 (2)(3)RAl (2)(3)(4)Alarm Response Procedure Reference RA2 (2)Annunciator Displays:1D21-K601 A 2D21-K601 M1D21-K601 B 2D21-K601 E1D21-K601 D 2D21-K611 K1D21-K601 E 2D21-K611 L1D21-K601 M 2D11-K609 A-DIDII-K609 A-D 2D11-K611 A-D1D1Il-K611 A-D 2D 11-K634 A-D2D21-K601 A 2D11-K635 A-DAlarm Response Procedure Reference Control Room Rad RA3 (1)Monitor [Annunciator Display: 1D21-K600 B(C)] ____________Alarm Response Procedure Reference RU2 (1 )aAnnunciator Display: Spent Fuel Storage Pool Level Low6 654-022-1Spent Fuel Storage Pool 'Level Low654-022-2 ______2/22/20 16Page 1 of 3 Hatch EAL V&V Documentation IndexV&V# *Description ' IlC ThresholdRPV Level Indications/Displays (-155" TAF) CG1 (1)a7CS1 (2)bFCB PL2A FCB PL2ACaic SMNH-13-021 Rev 1 RCSB L2A RCSB L2ARPV Level Indication/Display (-35"); Level 2 Actuation CS 1 (1)b8 setpoint info (required for CA1/CS1 is 6" below setpt) CAl (1)Caic SMNH-13-02I Rev 1Drywell Floor Drain Sumps; Drywell Equipment Drain CG1 (2)bSumps; Torus; Torus Room Sumps; RB Floor Drain CS 1 (3)bSumps; TB Floor Drain Sumps; Rad Waste Tanks CA1 (2)breferences cui (2)bH2 Concentration (> 6%) and 02 Concentration (> 5%) -CGI (2)c10 calculation/reference CB PL1B CB PL1BCale SMNH-13-021 Rev 111 Primary Containment Pressure Reference (> 56 psig) CG1 (2)cCalc SMNH-13-021 Rev]1 CB PLIA CB PL1ASecondary Containment Rad Monitors > Max Safe values CG1 (2)c12 34AB-T22-O03-1/2 CBL3A CBL3ASecondary Containment Rad Monitors > Max Normal RCSBPL3A RCSBPL3AValues 34AB-T22-O03-1/24160 VAC Essential Buses Description CA2 (1)CU2 (1)a13 SG1 (1)aSG8 (1)aSS1 (1)SA1 (1)SU1 (1)14 RCS Pressure indications CA3 (2)DC System Information CU4 (1)15 SO8 (1)bSS8 (1)16 ISFSI TS/Dose Reading Calculation E-HU1 (1)SMHN-13-021 Rev 117 Primary Containment Pressure > 1.85 psig reference RCSB LIA RCSB L1A17 Calc SMNH-13-021 Rev 1Secondary Containment Temps -> Max Normal values RCSBPL3A RCSBPL3A18 34AB-T22-O03-1/2Secondary Containment Temps -> Max Safe values CBL3A CBL3A34AB-T22.-O03-1/2Seismic Indications (OBE): HU2 (1)19 [Annunciator Display (657-048/657-066)]12.7 Hz amber light12.7 Hz red light20 Table H2 Basis HU4 (1)b (2)b34AB-X43-O01-1 (2)21 Minimum Steam Cooling RPV Water Level SG1 (1)bSS5 (1)c22 Heat Capacity Temperature Limit (HCTL) Curve SS5 (1)cPretreatment Radiation Monitor Reading SU3 (1)23 TS3.7.6Caic SMNH-13-021 Rev 1RCS sample activity -Tech Spec Value SU3 (2)24 TS3.4.62/22/2016Page 2 of 3 Hatch EAL V&V Documentation IndexIV&V# I> Description I IC IThreshold'RCS Operational Leakage -Tech Spec Values SU4 (1)(2)25 TS3.4.42/22/2016Page 3 of 3 VlPage 1 of 1Definitions1.1Table 1.1-1 (page 1 of 1)MODESAVERAGE REACTORCOOLANTREACTOR MODE TEMPERATUREMODE TITLE SWITCH POSITION (&deg;F)1 Power Operation Run NA2 Startup Refuel(a) or Startup/Hot NAStandby3 Hot Shutdownl(a) Shutdown > 2124 Cold Shutdown(a) Shutdown < 2125 Refueling(b) Shutdown or Refuel NA(a)(b)All reactor vessel head closure bolts fully tensioned.One or more reactor vessel head closure bolts less than fully tensioned.HATCH UNIT 11.1-6HATC UNI I 11-6Amendment No. 195 5A~NYErn~r,,.&'~i.v I~W*d4V2Southern Nuclear Design CalculationSeNL1589Enclosure 3ICalculation Number: SMNH-13-021Plant:Hatch Nuclear Plant Unit:O 1 0" 2 0] 1 & 2 Discipllne:MechanlcalTlfite:Subject EmergencyNEI 99-01 Rev 6 EAL. Calculations Action Level SetpointsPurpose I Objective:Document Emergency Action Level Values to support conversion to NEI 99-01 Rev 6System or Equipment Tag Numbers:N/AContentsTopic Page Attachments # of(Computer Printouts, Technical Papers, Pages__________________Sketches, Correspondence)Purpose 1 A -SNC EP Concurrence 1Criteria 1 B -Reserved 0Conclusions 3 C -Fuel Clad' Loss 4.A Threshold Calculation 19Design Inputs 5 D -Fuel Clad Potential Loss 5.A Threshold 1Assumptions ,10 CalculationReferences 14 E -RCS Loss 4.A Threshold calculation ... 16Method of Solutions 18 F -RCS Loss 5.A Threshold Calculation 6Body of Calculation .... ....23 G -containment Potential Loss 4.A 1__________________Threshold Calculation______________H -Steam Table Validation 5I- RS1 Threshold Calculation ______ 25Toa fPgsicuigJ -CG1 Threshold Calculation 4cover sheet & Attachments: 189 K -CG1 Threshold,,,Calculation 15L -E-HU1 Threshold Calculation 16M -RA1 Threshold Calculation 18Nuclear Quality Level0 -Safety-Related li Safety Significant 0 o-Safety -SignificantVersion RecordVersion Originator Reviewer' Approval I Approval 2I, ~ dui= Name P.*HW 4Name Pri~ed Na. atiCalculation of EAL Thresholds. wb..d l-Lto support NEI 99-01 Rev. 6Notes: Key calculationNMP-ES-039NMP-E-039NMP-ES-039-001 V3Page 1 of 2HNP ODCMd. The CHAN4NEL CHECK s hall consist of verifying sampler flow an d the presence ofthe*collection device (i.e., partic~ulate filteror charcoal cartridge, etc.) at the weekly o ,43.1.2 Gas eous Effluent Dose Rate ControlIn accordance with Technical Sp ecif'ication~s 5.5.4.c and 5.5.4.g, the licensee shall conducto perations so that th e dos e rates due to radioactive materials rel eased in gaseous effluentsfrom the siteto areas at and beyondthe SITE BOUNDARY (see Figure 10-1) are limited asfollows:a. For noble gase.-s: Less than or equalto a dose rate of to the total body andless than or equal to a dose rate of 3000 /to the skin, andb. For Iodine-131, Iodine-133, tritum, and forall radionuclides in partioulate forin withhalf-lives greater than 8 days: Less than or equal to a dose rate of 1500 j~r, j~rn to anyorgan.3.1.2.1 ApplicabilityThis limit applies at all times.3.1.2.2 ActionsWith a dos e rate due to radioactive material released in gaseous effluents exceeding the limitstated in Section 3.1.2, immediatelydecrea~se the relea~se rate to within the stated limit.Entry into an Operational Mode or other specified COM)ITION shall be made if, as a minimum,the requirements ofTedinical Sp eafications LCO03.0.4 are met.3.1.2.3 Surveillance RequirementsThe dose rates dueto radioactive materials in areas at or beyondth e SITE BOUNDARY due torel eases of gaseous effluents shall be determinedto be withinthe above limits, in accordancewith the methods and procedures in Section 3.4.1, by obtaining representative samples andperforming analyses in accordance with the sam pling an d analysis program specifed inTable 3-3.3.1.2..4 BasisThis control is provided to ensure that gaseous effluent dose rates will be maintained within thelimits that historicallyhave provided reasonable assurance that radioactive material disdiargedin gas eous effluents wilN not result in a d ose to a MEMBER OF THE PUBLIC in anUNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceedingthe limitsspecified inAppendix I ofI10CFR Part 50, while allowing operational fl exibiity for effluentreleases. For MEBROFTH-E PUBLIC who may at times be withinthe SITE BOUNDARY,the occupancy ofth e MEBE OFTHE PUBLIC will be sufficiently low to compensate for anyincrease in th e atmospheric diffusion factor above that for th e SITE BOUNDARY.3-6 Version 23 213 KeFPLOO PinAI FOUEUTB'mueaTeaPFcJif0)&Co V4Page 1 of 16SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) AGE 1 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 34AR-601-902-1 I 14.41H11-P601, ALARM PANEL 1EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE:04 15N/A SSM /PM: N/A DATE: N/AANNUNCIATOR RESPONSE PROCEDURES FOR IHII-P601 -ALARM PANEL 1ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-101-1 5.1 34AR-601-113-1 2.1 34AR-601-125-1 6.234AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.234AR-601-103-1 6.2 34AR-601-1 15-1 4.1 34AR-601-127-1 6.234AR-601-104-1 3.3 34AR-601-1 16-1 5.6 34AR-601-128-1 3.234AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.134AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.034AR-601-107-1 1.1 34AR-601-119-1 1.1 34AR-601-131-1 6.334AR-601-1 08-1 2.2 34AR-601-120-1 5.2 34AR-601-1 32-1 3.334AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.134AR-601-1 10-1 4.2 34AR-601-122-1 4.1 34AR-601-1 34-1 4.334AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.534AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0II NOE Approval signature on this page constitutes approval for all procedures listed above at theNOE revision indicated. Tab numbers in the back correspond to procedure sequence number.ILevel Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneN MP-AP-002 V4Page 2 of 16PAGE 2 OF 2SOUTHERN NUCLEARPLANT E.I. HATCHDOCUMENT TITLE:ARP'S FOR CONTROL PANEL 1H11-P601,ALARM PANEL 1DOCUMENT NUMBER: VERSION NO:34AR-601-902-1 I 14.4UNIT 11H 11-P601 -1601-101 601-102 601-103
+* 601-104 601-105 601-106601-107 601-108
+* 601-109
+* 601-110 601-111 601-112601-113 601-114 601-115 601-116 601-117 601-118601-119 601-120 601-121 601-122 601-123 601-124601-125 601-126 *60-2 60-2 6119 6113601-125 601-1326 601-127 601-128 601-125 601-130RECORDSThere are no records generated from this procedure.COMMITMENTSNone* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on TRIP UNIT Label(s) at 1D21-P600 to provide across-reference for locating the device(s) in Abnormal and/or EOP Tables.Refer to 34AB-T22-003-1, Secondary Containment Control.NMP-AP-002 v.2.0 V4Page 3 of 161.0 IDENTIFICATION:ALARM PANE L 601-1_____ ___RX BLDG___ __ ___RADIATION___ __ _ _ __ ___HIGHDEVICE: SETPOINT:1D21-K601A, E, F, G, H, K, L, N, P, R, S, T, U, V, W, X, Y See 64C1-CAL-002-05.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED amber upscale light and high reading on individual indicator/trip units,on 1D21-P600, Area Radiation Monitoring Panel.5.1.1 Attempt to reset Trip Unit.5.2 IF Trip Unit will NOT reset, perform the following:5.2.1 Confirm monitor reading,by checking 1D21-R600, Area Radiation Monitor Recorder, panel 1~ H1-P600. (see channels below).5.2.2 Contact Health Physics to confirm radiological condition.5.2.3 REFER to 73EP-RAD-001-0, Radiological Event.5.2.4 Periodically monitor panel 1D21-P600,to ensure that no other channels in the Reactor Building are indicating high OR in alarm.5.2.5 Enter 34AB-T22-003-1, Secondary Containment Control.5.2.6 IF a radioactive release outside the Reactor Building is occurring, OR has occurred,enter 34AB-D1 1-001-1, Radioactive Release Control.LiLILiLiLiLiLiLi6.0 CAUSES:6.1 High radiation Trip on one or more of the following indicator/trip units:1 D21 R600CHANNEL TRIP UNIT LOCATION01 1 D21-K601A Reactor Head Laydown05 1D21-K601E Drywell Shield Plug06 1D21-K601F Tip Area07 1D21-K601G 130' NE Working Area08 1 D21-K601H 130' SW Working Area09 1 D21-K601K 158' SW Working Area10 1D21-K601L Rx Wtr Smpl Rack Area 158'12 1D21-K601N South CR0 Hydraulic Units13 1 D21-K601P North CR0 Hydraulic Units14 1D21-K601R CS & RHR S-E Diag.15 1 D21 -K601 S Equipment Access Airlock16 1 D21-K601T HPCI Turbine Area17 1 D21-K601U TIP Probe Drive Area18 1D21-K601V RCIC Equipment Area SW19 1D21-K601W CR0 Pump Room NW20 1 D21-K601X RB 203' Working Area21 1D21-K601Y CS & RHR N-E Diag.6.2 Malfunctions of one or more trio unitsSENSOR1D021-N002-11 D21-N002-51021 -N002-61021 -N002-71021 -N002-81 D21-N002-91021 -N002-1 01 D21-N002-121021 -N002-1 31 D21-N002-141021 -N002-1 51021 -N002-1 61 D21-N002-171021 -N002-1 81021 -N002-1 91 D21-N002-201 D21-N002-2134AB-T22-003-1ITEM NUMBER14111416910171221152213181962
+==07.0 REFERENCES==
+: 8.0 TECH. SPEC./TRM/ODCMIFHA:7.1 H-17854 -H-17859, H-19598 & H-i19599, ARM Sys. 021 Elem. N/A -Not applicable to this procedure34AR-601 -104-1Ver. 3.3MGR-0048 Ver. 5 V4Page 4 of 161.0 IDENTIFICATION:ALARM PANEL 601-1________REFUELING FLOORAREA RADIATION___ __ __ ___HIGHDEVICE: SETPOINT:1 D21 -K601 B, 1 D21 -K601 D See 64C1-CAL-002-02.0 CONDITION: 3.0 CLASSIFICATION:EQUIPMENT STATUSOne OR both of the Refueling Floor Area Radiation Monitors has 4.0 LOCATION:exceeded its setpoint.1H-P0Pae6015.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/trip unitson panel 1D21-P600. Li5.1.1 Attempt to reset trip unit. LI5.2 Confirm Control Room ventilation shifted to pressurization (Mode II),per 34SO-Z41-001-1, Control Room Air Conditioning System. LI5.3 IF trip unit will NOT reset, perform the following:5.3.1 Confirm monitor reading by checking 1D21-R600, Area Radiation Monitor Recorder,panel 1Hi11-P600. (see channels below) Li5.3.2 Contact Health Physics to confirm radiological condition in the affected area,evacuate area IF required. LI5.3.3 Periodically monitor panel 1D21-P600,to ensure that no other channels on the Refueling Floor are indicating high OR~ in alarm. Li5.3.4 Enter 34AB-T22-003-1, Secondary Containment Control. Li5.3.5 Refer to 73EP-RAD-001-0, Radiological Event. Li5.3.6 IF a radioactive release outside the Refueling Floor is occurring, OR has occurred,enter 34AB-D1 1-001-1, Radioactivity Release Control. Li6.0 CAUSES:6.1 High radiation causing one OR both of the following indicator/trip units:MONITOR CHANNEL TRIP UNIT LOCATION SENSOR02 1D21-K601B Refueling Floor Stairway 1D21-N002-204 1D21-K601D Refueling Floor 1D21-N002-46.2 Malfunction of trip unit.
+==7.0 REFERENCES==
+: 8.0 TECH. SPEC./TRMIODCM/FHA:7.1 H-17854 thru H-17859, H-19598 and H-19599, AreaRadiation Monitoring Sys. D21 Elem Diag N/A -Not applicable to this procedure34AR-601-1 10-1Ver. 4.2MGR-0048 Ver. 5 V4Page 5 of 161.0 IDENTIFICATION:__ALARMPANEL 601-1 __________ __ __ ___NEW FUEL__ __STORAGE AREA__ __ __RADIATION HIGHDEVICE: SETPOINT:1 D21-K601C 64CI-CAL-002-01 D21-K601M2.0 CONDITION: 3.0 CLASSIFICATION:2.1 Radiation level in vicinity of Spent Fuel Pool Demineralizer EQUIPMENT STATUSEquipment ARM has exceeded its setpoint 4.0 LOCATION:2.2 Radiation level in vicinity of Spent Fuel Pool & New Fuel Storage 1H11-P601 Panel 601-1ARM has exceeded its setpoint2.3 Loss of power to either of the above listed ARMs5.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/tripunits on panel 1D21-P600. LI5.1.1 Attempt to reset trip unit. LI!5.2 IF trip unit will NOT reset, perform the following:5.2.1 Confirm monitor reading by checking 1D21-R600, Area Radiation Monitor Recorder,on panel 1H1 1-P600. (see channels below) LI5.2.2 Contact Health Physics to confirm radiological condition in the affected area ANDevacuate area IF required. LI5.2.3 Periodically monitor 1D21-P600, panel, to ensure that no other channels on theRefueling Floor are indicating high OR in alarm. 135.2.4 Enter 34AB-T22-003-1, Secondary Containment Control. LI5.2.5 Refer to 73EP-RAD-001-0, Radiological Event. III5.3 If neither ARM is reading high, then at 1 R25-S064, confirm BRKR 9 is CLOSED. El5.4 IF an abnormal radioactive release is occurring OR has occurred,enter 34AB-D1 1-001-1, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation causing one or both of the following indicator/trip units to alarm:1D21-R600 POINT TRIP UNIT LOCATIONNUMBER SENSOR3 1D21-K601C, Spent Fuel Pool Demin Equip 1D21-N002C11 1D21-K601 M, Spent Fuel Pool & New Fuel Storage 1D21-NO02M6.2 Loss of power to ARM's
+==7.0 REFERENCES==
+: 8.0 TECH. SPEC./TRMIODCMIFHA:7.1 H-17854 & H-17856, ARM Sys. D21 Elem. Diag. N/A -Not applicable to this procedure34AR-601-127-1Ver. 6.2MGR-0048 Ver. 5 V4Page 6 of 16DOCUMNT TTLE:DOCUMENT NUMBER: VERSION NO:ARP'SALRFOR PAECONTROL4 PANEL 1H11-P601, 34AR-601-901-1 12.4EXPIATIN APROVLS:EFFECTIVEDATE: DEPARTMENT MANAGER DAK for Keith D. Lonq DATE 5-9-13 DATE:N/A SSM/PM N/A DATE N/A 5-15-15ANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601 -ALARM PANEL 4ARP NO. Ver, NO. ARP NO. Ver.NO. ARP NO. Ver. NO.34AR-601-401-1 0.4 34AR-601-413-1 0.4 34AR-601-425-1 4.434AR-601-402-1 3.4 34AR-601-414-1 3.3 34AR-601-426-1 3.534AR-601-403-1 3.5 34AR-601-415-1 1.5 34AR-601-427-1 1.334AR-601 -404-1 0.2 34AR-60 1-416-1 1.3 34AR-601 -428-1 4.634AR-601-405-1 7.1 34AR-601-417-1 4.6 34AR-601-429-1 2.234AR-601-406-1 7.3 34AR-601-418-1 3.3 34AR-601-430-1 0.234AR-601-407-1 1.5 34AR-601-41 9-1 0.2 34AR-601-431-1 1.134AR-601 -408-1 1.5 34AR-601 -420-1 4.5 34AR-601 -432-1 4.334AR-60 1-409-1 5.5 34AR-60 1-421-1 4.3 34AR-601 -433-1 0.134AR-601-410-1 2.2 34AR-601-422-1 3.5 34AR-601-434-1 2.134AR-601-411-1 3.6 34AR-601-423-1 3.6 34AR-601-435-1 034AR-60 1-412-1 4.5 34AR-60 1-424-1 2.5 34AR-601 -436-1 0INOTE Approval signature on this page constitutes approval for all procedures listed above at the IVersion indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneI V4Page 7 of 16UNIT 11H11-P601-4601-401 601-402 601-403 601-404 601-405 601-406601-407 601-408 601-409 601-410 601-411 601-412601-413 601-414 601-415 601-416 601-417 601-418601-419 601-420 601-421 601-422 601-423 601-424601-425 601-426 601-427 601-428 601-429 601-430601-431 601-432 601-433 601-434 601-435 601-436RECORDSNo Records are generated by this procedure.COMMITMENTSSNC1 9472, SNC5027 V4Page 8 of 161.0 IDENTIFICATION:ALARM PANEL 601-4 __________REFUELING FLOOR___ __ __ ___VENT EXHAUST___ __ __ __ ___RADIATION HI-HIDEVICE: SETPOINT:1D11-K611A thru D 18 mr/hr2.0 CONDITION: 3.0 CLASSIFICATION:EMERGENCYRadiation levels in the Refueling Floor Exhaust Duct exceed the 4.LOAINsetpoint.1H11-P601 Panel 60 1-45.0 OPERATOR ACTIONS:5.1 Confirm the annunciator by monitoring 1 D11-R607, Recorder, panel 1H11-P600. D]5.1.1 Monitor the R/F VENT EXHAUST RAD MON, 1 HI1-P606; IF only one trip unit is affected,attempt to reset the affected trip unit. Eli5.2 IF only one trip unit is alarmed, AND the unit is not malfunctioning,determine and correct the cause of the high high radiation. LI5.3 IF" the A AND B, OR the C AND D OR all channels of trip unit 1 D11-K61 1 are tripped,enter 31EO-EOP-014-1, SC-Secondary Containment Control, andperform concurrently with this procedure. Eli5.4 IF refueling is in progress, STOP refueling operations, andif possible, insert any withdrawn Control Rods. LI5.5 Evacuate personnel from the Refueling Floor. LI5.6 IF: refueling or fuel handling was in progress,ENTER 34AB-J11-001-1, Irradiated Fuel Damage During Handling. LII5.7 IF" an abnormal radioactive release is occurring,ENTER 34AB-D1 1-001-1, Radioactive Release Control. LI6.0 CAUSES:6.1 High radiation levels in the vent duct6.2 Trip unit failure, upscale or downscale
+==7.0 REFERENCES==
+: 8.0 TECH. SPECS./TRMIODCM/FHA:7.1 H-19551 through H-19566, H19578, H19584, & H19596, 8.1 Secondary ContainmentProcess Radiation Monitoring System Elem Diag Isolation Instr Table 3.3.6.2-134AR-601 -403-1Ver. 3.5 V4Page 9 of 161.0 IDENTIFICATION:ALARM PANEL 601-4 ___________ __ ___RX BLDG POT___ __ __ __ ___CONTAM AREA______-VENT RADN HI-HIDEVICE: SETPOINT:1 D11-K609A 1ID11-K609B 18 mr/hr1D1 1-K609C, 1 D1 1-K609D5.0 OPERATOR ACTIONS:5.1 Confirm annunciator by monitoring the radiation level on 1D11-R605, recorder, 1H11-P600. LI5.1.1 Monitor 1 D11-K609A, ID11-K609B, 1ID11-K609C, 1D1I-K609D, Reactor BuildingPotential Contaminate Area Rad Monitors, 1Hi 11-P606.IF only one trip unit is affected, attempt to reset the affected trip unit. Eli5.2 IF only one trip unit is alarmed AND the unit is not malfunctioning,determine and correct the cause of the high high radiation. LI5.3 IF the A AND B, OR the C AND_ D OR all channels of trip unit 1 D11-K609, are tripped,ENTER 31EO-EOP-014-1, SC-Secondary Containment Control. III5.4 IF an abnormal radioactive release is occurring,ENTER 34AB-D1 1-001-1, Radioactivity Release Control. LI6.0 CAUSES:6.1 Primary leakage
+==7.0 REFERENCES==
+: 8.0 TECH. SPECS./TRM/ODCM/FHA:7.1 H-19561, H-19564, H-19563, & H-19566, Process 8.1 Unit 1 T.S. 3.3.6.1Radiation Monitoring System Elem Diag 8.2 Unit 1 T.S. 3.3.6.27.2 H-16005, Reactor Building Vent System P&ID34AR-60 1-426-1Ver. 3.5 V4Page 10 of 16SOUTHERN NUCLEAR IDOCUMENT TYPE:IPLANT ElI. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) PAGE 1 OF 2DOCUMENT TITLE: NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 2H1 1-P601, ALARM PANEL 3 l 34AR-601-904-2 12.18EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER G. L. Johnson DATE 04/19/00 DATE:8/31/15N/A SSM /PM N/A DATE N/A _____ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601 -ALARM PANEL 3ARP NO VER. NO. ARP NO. VER. NO. ARP NO VER. NO.34AR-601 -301-2 3.1 34AR-601 -31 3-2 3.5 34AR-60 1-325-2 2.334AR-60 1-302-2 3.2 34AR-60 1-314-2 2.4 34AR-60 1-326-2 0.534AR-601-303-2 3.3 34AR-601-315-2 1.2 34AR-601-327-2 5.234AR-601 -304-2 3.2 34AR-60 1-316-2 0.2 34AR-60 1-328-2 2.234AR-601 -305-2 0.3 34AR-601 -317-2 2.1 34AR-601 -329-2 1.334AR-60 1-306-2 3.3 34AR-601 -318 SPARE 34AR-60 1-330-2 2.234AR-601-307-2 2.4 34AR-601-319-2 0.3 34AR-601-331-2 2.334AR-601-308-2 2.3 34AR-601-320-2 1.2 34AR-601-332-2 0.334AR-601-309-2 1.2 34AR-601-321-2 4.2 34AR-601-333-2 0.334AR-601-310-2 0.4 34AR-601-322-2 0.6 34AR-601-334 SPARE34AR60131 12 03 3AR-61-33-2 .3 4AR601 4.34AR-601-311-2 4.3 34AR-601-323-2 2.4 34AR-601-335-2 04.SNT:IApproval signature on this page constitutes approval for all procedures listed above at the !NOErevision indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneMGR-0002 VER. 8.1 V4of 16UNIT 22H11-P601 -3601-301 601-302 601-303 601-304 601-305
+* 601-306601-307 601-308 601-309 601-310 601-311
+* 601-312601-313 601-314 601-315 601-316 601-317 601-318601-319 601-320 601-321 601-322
+* 601-323 601-324601-325 601-326 601-327 601-328 601-329 601-330601-331 601-332 601-333 601-334 601-335 601-336* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on Trip Unit Label(s) at 2D21-P600 to provide across reference for locating the device(s) in ABNORMAL AND/OR EOP Tables.Refer to 34AB-T22-003-2, Secondary Containment Control.RECORDSNo records are generated from this procedure.COMMITMENTSNONEMGR-0001 VER. 4 V4Page 12 of 161.0 IDENTIFICATION:ALARM PANEL 601-3-II--IIrREFUELING FLOORAREA RADIATIONHIGHDEVICE: SETPOINT:2D21-K601-A,E,M See 64CI-CAL-002-02D21-K61 1-K,L5.0 OPERATOR ACTIONS:5.1 Check for ILLUMINATED red upscale light AND~ high reading on individual indicator/tripunits on panel 2D21-P600. LI5.1.1 Attempt to reset Trip Unit. LI5.2 IF 2D21-K601 A O._R M Tripped,THEN confirm Control Room ventilation shifted to pressurization (Mode II) per34SO-Z41-001-1, Control Room Ventilation System. LI5.3 IF Trip Unit will NOT reset, perform the following:5.3.1 Confirm monitor reading by checking 2D21-R600A, Area Radn Monitor Recorder,panel 2H1 1-P600 (see channel below) Lii5.3.2 Contact Health Physics to confirm radiological condition in the affected area,evacuate area IFrequired. LI5.3.3 Periodically monitor panel 2D21-P600 to ensure no other channels on the RefuelingFloor are indicating high OR in alarm. LI5.3.4 Enter 34AB-T22-003-2, Secondary Containment Control. LI5.3.5 IF a radioactive release outside the Reactor Building is occurring, OR has occurred,enter 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation causing a trip of one ORR more of the following indicator trip unitsMONITOR CHANNEL LOCATION SENSOR TRIP UNIT1 Reactor Head Layout Area 2D21-N002-A K601-A5 Dryer/Separator Pool 2D21-N002-E K601-E10 Spent Fuel/Fuel Pool Areas 2D21-N002-M K601-M21 Reactor Vessel Refueling Area 2D21-N012-K K61 1-K22 Reactor Vessel Refueling Area 2D21-N012-L K61 1-L6.2 Malfunction of trip unit
+==7.0 REFERENCES==
+.0 TECH. SPECS./TRMIODCMIFHA:7.1 H-27805 thru H-27810 and H-27992, Area RadiationMonitoring Sys 2D21 Elementary Diagram 8.1 TRM Table T3.3.7-134AR-60 1-312-2Ver. 4.3MGR-0048 Ver. 5.0 A-GR7- 0AG-MGR-75-1101 V4Page 13 of 16SOUTHERN NUCLEAR )OCUMENT TYPE:PLANT ElI. HATCH lANNUNCIATOR RESPONSE PROCEDURE (ARP PAGE 1 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO:ARP'S FOR CONTROL PANEL 2HI11-P601, 34AR-601-901-2 l 12.1ALARM PANEL 4/EXPIRATION APPROVALS: IEFFECTIVEDATE: DEPARTMENT MANAGER DAK for Keith D. Long DATE 5-9-13 I DATE:N/A SSM/PM N/A DATE N/A 5-i5-I5ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601 -ALARM PANEL 4ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-401-2 0.3 34AR-601-413-2 1.2 34AR-601-425-2 3.434AR-60 1-402-2 4.1 34AR-60 1-414 Spare 34AR-60 1-426-2 6.334AR-601-403-2 5.4 34AR-601-415-2 1.0 34AR-601-427-2 2.334AR-60 1-404-2 0.3 34AR-60 1-416-2 0.5 34AR-60 1-428-2 5.534AR-60 1-405-2 8.1 34AR-60 1-417-2 4.3 34AR-60 1-429-2 3.134AR-60 1-406-2 8.3 34AR-60 1-418-2 1.2 34AR-60 1-430-2 0.334AR-60 1-407-2 3.6 34AR-60 1-419-2 1.1 34AR-60 1-431-2 2.134AR-601-408-2 1.0 34AR-601-420-2 6.3 34AR-601-432-2 4.334AR-601-409-2 5.3 34AR-601-421-2 4.3 34AR-601-433-2 1.434AR-601-410-2 2.3 34AR-601-422-2 5.4 34AR-601-434-2 3.034AR-601-411-2 4.5 34AR-601-423-2 4.4 34AR-601-435-2 1.134AR-601-412-2 0.4 34AR-601-424-2 2.3 34AR-601-436-2 0.1IINOTE Approval signature on this page constitutes approval for all procedures listed above at theI Version indicated. Tab numbers in the back correspond to procedure sequence number.FILevel Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO None V4Page 14 of 162 OF2SOUTHERN NUCLEARPLANT E.I. HATCHDOCUMENT TITLE: 'DOCUMENT NUMBER: VERSION NO:ARP'SALRFORpAECONTROL4 PANEL 2H11-P601, 34AR-601-901-2 1 12.1UNIT 22H1 1-P601 -4601-401 601-402 601-403 601-404 601-405 601-406601-401 601-408 601-409 601-410 601-411 601-412601-413 601-414 601-415 601-416 601-417 601-418601-419 601-420 601-421 601-422 601-423 601-424601-425 601.426 601-427 601-428 601-429 601-430601-431 601-432 601-433 601-434 601-435 601-436RECORDSThere are no records generated from this procedure.COMMITMENTSSNC5027 V4Page 15 of 161.0 IDENTIFICATION:ALARM PANEL 601-4T 11 T T -1-4-1REFUELING FLOORVENT EXHAUSTRADIATION HI-HIDEVICE:2D11-K611 A thru D2D11-K634 Athru D2D11-K635 Athru DSETPOINT:18 mr/hrPER 64Cl-CAL-002-0PER 64CI-CAL-002-02.0 CONDITION: 3.0 CLASSIFICATION:Radiation levels in the. Refueling Floor Exhaust Duct exceed EMERGENCYthe setpoint. 4.0 LOCATION:2H11-P601 panel 601-45.0 OPERATOR ACTIONS:5.1 Confirm the annunciator by monitoring recorders on panel 2H1 1-P600:* 2D11-R615 for 2D11-K611A &2D11-K611 B, and 2D11-K634A -D LI* 2D11-R616 for 2D11-K611C &2D11-K611D, and 2D11-K635A- D Lii5.1.1 Monitor the R/F Vent Exhaust Rad Mon on 2H11-P606;IF only one trip unit is affected, attempt to reset the affected trip unit. LI5.2 IF only one trip unit is alarmed, AND the unit is NOT malfunctioning,determine AND correct the cause of the high high radiation. Eli5.3 IF refueling operations are in progress,STOP refueling operations ANDIF possible, insert any withdrawn Control Rods. LI5.4 Evacuate personnel from the Refueling Floor. LII5.5 IF refueling OR fuel handling was in progress,enter 34AB-J1 1-001-2, Irradiated Fuel Damage During Handling. LI5.6 For valid alarm conditions, enter 31EO-EOP-014-2, SC-Secondary ContainmentControl AND 34AB-T22-003-2, Secondary Containment Control. LI5.7 IF an abnormal radioactive release is occurring OR has occurred,ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 High radiation levels in the vent duct6.2 Trip unit failure, upscale OR downscale ___________________
+==7.0 REFERENCES==
+: 8.0 TECH. SPECS./TRMIODCMIFHA:7.1 H-27629 and H-27631, Process RadiationMonitoring Diagram, Sheets 10 and 12 8.1 U2 TS 3.3.6.1 Table 3.3.6.1-17.2 H-27596 thru H-27600, Primary ContainmentIsolation System, Sheets 1 through 5 8.2 U2 TS 3.3.6.2 Table 3.3.6.2-134AR-60 1-403-2VER. 5.4 V4Page 16 of 161.0 IDENTIFICATION:ALARM PANEL 601-4________RX BLDG POT___ CONTAM AREAVENT RADN HI-HIDEVICE: SETPOINT:2011l-K609A through 0, Per 64CI-OCB-006-2, Form HPX-1 252, from ChemistryTrip Indicator Unit2.0 CONDITION: 3.0 CLASSIFICATION:Radiation levels on the inlet to 2T41-D005, Reactor Building EMERGENCYExhaust Filter Train, exceeds the setpoint. 4.0 LOCATION:2H11-P601 panel 601-45.0 OPERATOR ACTIONS:5.1 On panel 2H1 1-P600, confirm annunciator by monitoring the radiation level on2D1 1-K609A/2D1 1-K609B/2D11l-K609C/2D1 1-K609D on 2D1 1-R605 recorder. El5.1 .1 Monitor 2011 -K609A through D, Reactor Building Potential Contaminated AreaRad Monitors, on 2H11-P606.IF only one trip unit is affected, attempt to RESET the affected trip unit. LI5.2 IF only one trip unit is alarmed AND the trip unit is NOT malfunctioning,determine AND correct the cause of the high high radiation. El5.3 IF the A & B, O._R the C & D O__R all channels of trip unit 2D1 1-K609 are tripped,THEN enter 31EO-EOP-014-2, SC-Secondary Containment Control ANDconfirm Automatic Actions per 34AB-T22-003-2, Secondary Containment Control,Attachment 7. LI5.4 IF an abnormal radioactive release is occurring OR has occurred,ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI6.0 CAUSES:6.1 Steam leaks
+==7.0 REFERENCES==
+: 8.0 TECH. SPECS./TRM/ODCMIFHA:7.1 H-27629, H-27631, H-27632, & H-27634, Process 8.1 U2 TS 3.3.6.1Radiation Monitoring System Elem. Diag.7.2 H-26067 Reactor Zone Ventilation System P&ID34AR-601 -420-2VER. 6.3 VSPage 1 of 3SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE ('ARP' AGE 1 OF 2V5Page 1 of 3DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO:ARP'S FOR CONTROL PANEL 34AR-601-902-1 ] 14.41H11-P601, ALARM PANEL 1EXPIRATION APPROVALS: EFFECTIVEDATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE:04-30-15N/A SSM /PM: N/A DATE: N/AANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601 -ALARM PANEL 1ARP NO. VER. NO. ARP NO. VER. NO. ARP NO. VER. NO.34AR-601-101-1 5.1 34AR-601-113-1 2.1 34AR-601-125-1 6.234AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.234AR-601-103-1 6.2 34AR-601-115-1 4.1 34AR-601-127-1 6.234AR-601-104-1 3.3 34AR-601-116-1 5.6 34AR-601-128-1 3.234AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.134AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.034AR-601-107-1 1.1 34AR-601-1 19-1 1.1 34AR-601-1 31-1 6.334AR-601 -108-1 2.2 34AR-601 -120-1 5.2 34AR-601-1 32-1 3.334AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.134AR-601-110-1 4.2 34AR-601-122-1 4.1 34AR-601-134-1 4.334AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.534AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0NOTE:______ Approval signature on this page constitutes approval for all procedures listed above at the~ NOTE:revision indicated. Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPsCONTINUOUS ALLREFERENCE NoneINFO NoneNMP-AP-002I V5Page 2 of 3SOUTHERN NUCLEARPLANT E.I. HATCHPAGE 2 OF 2DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO:ARP'S FOR CONTROL PANEL 1H11-P601, 34AR-601-902-1 1 14.4ALARM PANEL 1UNIT 11H11-P601 -1601-101 601-102 601-103 *601-104 601-105 601-106601-107 601-108
+* 601-109
+* 601-110 601-111 601-112601-113 601-114 601-115 601-116 601-117 601-118601-119 601-120 601-121 601-122 601-123 601-124601 -1 25 601 -1 26 601-1 27 601-1 28 601-1 29 601 -130601-131 601-132 601-133 601-134 601-135 601-136RECORDSThere are no records generated from this procedure.COMMITMENTSNone* Identified as an Area Radiation Level that may require Secondary Containment Control actions.Information similar to "SCIR-X" is contained on TRIP UNIT Label(s) at 1D21-P600 to provide across-reference for locating the device(s) in Abnormal and/or EOP Tables.Refer to 34AB-T22-003-1, Secondary Containment Control.NMP-AP-002 v.2.0 V5Page 3 of 31.0 IDENTIFICATION:ALARMPANEL_601-1 ___________ __ ___TURBINE BLDG__RADIATION___ __ ___HIGHDEVICE: SETPOINT:SEE SECTION 6.0 AS PER THE CHEMISTRY CONTROLLED SETPOINT RECORD5.0 COPERATIOR: ACTIONS:FCATON5.1 At 1D21-P600, monitor ARMs listed in Section 6.0,to determine which monitor(s) indicates high, to assess the severity, and monitor for trends. LI5.1.1 Attempt to reset the trip unit. Iii5.2 Notify Health Physics to determine the validity of the alarm. LI5.3 IF the alarm is valid,enter 73EP-RAD-001-0, Radiological Event. LI5.4 Refer to 34AB-U22-001-1, Pipe Break in Turbine Building, for possible entry conditions. LI5.5 IF a radiation release to outside the Turbine Building has occurred OR is occurring,enter 34AB-D1 1-001-1, Radioactivity Release Control. LI5.6 IF a Fuel Element Failure is confirmed,Initiate Turbine Building Purge per 34SO-U41-001-1 radiation. LI5.7 Monitor other ARM's that are associated with this annunciator for increasing radiation. LI6.0 CAUSES:High radiation, as indicated by one of the following ARM's:1D21-R600 POINT NUMBER MONITOR AREA22 1D21-K600A Main Turbine Front Standard23 1D21-K600B Control Room24 1 D21-K600C Control Room25 1D21-K600D T/B 164' North End Operating Floor26 1D21-K600E Turbine Bldg Feedwater Area27 121-K01ZCondensate Demin Area34AR-601-1 16-1Ver. 5.6MGR-0048 Ver. 5}}

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ML16071A149: Difference between revisions

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