Text

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-SNC524602-001I Attachment I ENERCON Calculation for E-HU1 SHEET I-6 v15 Page 1 of 3 CALC NO. SNC024-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0 PAGE NO. Page 6 of 8 5.0 Design Inputs 1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask system technical specification

[2, Table 6.2-3] are provided below in Table 5-1. These source values are scaled to develop the emergency action levels for initiating condition E-HU1.Table 5-1 Technical Specification Dose Rate Limits (Neutron + Gamma) for HI-STORM 100 and HI-TRAC 125 LocaionNumber of 1Technical Specification jMeasurementsj Limit (mrem/hr)HI-TRAC 125 Side -Mid -height T 4 1680.3 Top 1 4 j129.4 HI-STORM 100 Side -60 inches below mid-height 4 171.8 Side -Mid -height 4 177.0 Side -60 inches above mid-height 4 84.7 Top -Center of lid 1 27.1 Top -Radially centered 4 30.0 Inlet duct 4 231.8 Outlet duct 4 82.2 SM-SNC524602-001 Attachment I IPNI::IlNN

(.'l'ml:afinn fnr IF..WI I1 SHEET I-7 v15 Page 2 of 3 CALC NO. SNCO24-CALC-003 FNP DETERMINATION OF ___________

EMERGENCY ACTION LEVEL REV. 0 0I EN ER C ON FORI=NITATNG CONDITION E- _ _______..."' HUl PAGE NO. Page 7 of 8 6.0 Methodology The "on-contact"'

dose rates from the technical specification for the HI-STORM 100 and HI-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-SNC524602-001 Attachment I I:PCANI (%lrdp-mi6*rn fr i::._WI I1 SHEET I-8 v15 Page 3 of 3 CALC NO. SNC024-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0 0 E N E R C 0 N FOR INITAliNG CONDITION E-HUl PAGE NO. Page 8oft8 7.0 Calculations The dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose rate limits. These calculations are presented below in Table 7-1.w Table 7-1 Dose Rate Scaling Calculations for EAL Limits (Neutron + Gamma)Technical LoainSpecification Scaling Calculated Value EAL LoainLimit Factor .(mremn/hr) (mrem/hr)_______________________ (mremlhr)

____________

_____________ ______ ______ ______HI-TRAC 125 _ _ _ _ _ _ _ _ _ _ _ _ _ _Side -Mid -height [ 680.3 j 2 J 1360.6 1360 Top L 129.4 j 2 258.8 260 Side -60 inches below mid-height Side -Mid -height Side -60 inches above mid-height Top -Center of lid Top -Radially centered Inlet duct Outlet duct 171.8 177.0 84.7 27.1 30.0 231.8 82.2 343.6 340 354 350 169.4 170 54.2 50 60 60 463.6 460 164.4 160 8.0 Computer Software Microsoft WORD 2Q13 is used in this calculation for basic multiplication.

V16 LYN I Page 1o of 8 CORE COOLING Revision 17 P S SFIFTH NO HOTTEST I TC LESS i GO TO SAT a Page1 ofI1 V16 N !T 1Page 2 of 8 HEAT SINK Revision 17 FRP4.LI~GO TO FRP-H.2 PRESS IN INOI ALL SG'S L.EBB THAN"" GO TOFRP-H.3 NAR RNG N LVL IN ALL L SO'S LESS '--'THAN 62 1 YESJGOTO r FRP-H.4 PRESS IN N ALL SG'S LESS THAN,,,,, 1075 P8I10YE GO TO-I FRP-4.5 CSF SAT 1 V16 Page 3 of 8 8/29/2007 08:3 3 FNP-I-CSF-O.4 INTEGRIT Revision 17 I-f,' GO TOFRP.P.1 JGO TO inininm m --t a FRP-.2 CSF SAT GO TO GOOT SAT SAT PagI 1 f2

[NI 1Page 4of 8 FP1CSF-0.

COTANMN Geson TO PRESS NO in in, -FRP-Z.1 LESS ri- !THAN 5 YEs At LEAST ONE NOI PUMP RUNNING--

--OT I (FLOW>IODOOGPM)

YES ,. 2 I CTMT ko I S~UMP LVL N CTMT [THAN 7.6 I=: LESS H THAN 27 YsGO TO PSIG FRPZ.SUMP LVL.N LESS THAN 7.6H FT.~GO TO FRP-Z.3 BOTH CTMT RAD N LESS --hrTHAN 2 R/ LY1CS Page 1 of I 1I]IJIT9 Vi16 Page 5 of 8 8/29/2007 08:33 -FNP-2-CSF-0,2 CORE COOLING Revision 12 GOTOo IP I m IIFRP-C.1 HOTTEST NORP.CCORE EXIT THAN YETHANT790TCREXIT---, TC LSSTC HES SUBOO NO GO TOCOR PRP-C.3 0 EXIOT TCS "-iGRTR THAN E i16" F 145"F}Page1 of 1 V1 6!]N IT 2Page 6 of 8 FNP-2-CSF-O0.3 HEAT SINK Revision 12 SGO TO FRP-K.1 miTOTAL AFW NO IiFLOW TO I 1 ALL SG'8 -,-, 395 GPM E GO TO~FRP-HL2 LVL IN AT IN NO LEAST ONE ALL SG'S SG GRTR --'-LESS THAN THAN 31% YES __ _______ 1129PSIG YES ,[ GO TO! f FRP-H.3 MiAR RNG [N]LVL IN ALL SGS8 LESS mmm THAN 52% YES GO TO-I FRP-H.4 PRESS IN NO ALL 5G5S: ILESS THANmmg 1075 P810 YES GO TO I r FRP-H.5 CSF SAT Page 1 of I V16 7 of 8 FNP-2-CSF-O.4 IINTEGRITY Revision 12 COLD LGTMEAUE('F GO TO W FRP-P,1 ALL RCS PRESS- OT CL TEMP (IN m -ine e l RIGHT OF YES ,.,i_AL. RCS CL N OT TEMPS INGOT SLAST 60 MIN -,FRP..P.2 GRTIR THAN--'---- L RCS CL N~ TEMP TEMPNO SA LALATT600MIN LESSR ThAN TEM DCRNN OJ SA LESTRTTAHAN GOT 326' F SAT CSF SAT Page I of 2 Vi16*l Page 8 of 8 8/29/2007 08:33 I NJ J .FNP-2-CSF-0.5 CONTAINMENTReion1 H CTMT TI _O__O PRESS NO R "P .L "I m-~-LESS H-- 11 THAN 5 YES At LEAST ONE NO RUNNING (FLOW1 000GPM)YES FnI *m WRP-Z.2 SUMP LVL OI CTMT- THAN 7.6[PRESS N LESS- S ITHAN 27 YEs GO TO PSIG jjFRP-Z.1 SUMP LVI NO LESS H.-THAN 7.6 YE FT.GO TO FRP-Z.3 1 THAN2RJ [ES T SAT Page 1 of I V1 7Page 1 of 8 07/13/15 09:23:59 LOCATION FiUl SETPOINT:

1. Variable, as per FNP-1-RCP-252 HI RMS ORIGIN: Any of the below listed Area, Process or Gaseous and HI-RAD Particulate Monitors:

R01, R02, R03, R04, RO5, R06, R07, R08,-R1OI RI1, R12, RI3,[T RI5, RI7A ________R17B, RIS8, R-I19, R20A, R20B, R21, R23A or R23B.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 of instrument and/or control power that will result in actuation of associated automatic functions.

AUTOMATIC ACTIONS;I. The following actions will occur if a High Radiation Alarm is actuated on the associated Radiation Monitor.A. R14: (Plant Vent Gas) closes Waste Gas Release Valve I -G WD-HV-0 14.8. R16: None -abandoned in place per MDC 1040589501.

C. R17A or B: (Component Cooling Water) closes QIPIYRCV3028 CCW SRG TANK VENT.D. R18: (Liquid Waste Processing) closes Liquid Waste Release Valve I -L WP-RC V-0 18.E. R19: (Steam Generator Blowdown) isolates Steam Generator Blowdown Sample Lines.F. R23A :( Steam Generator Blowdown Processing) closes 1-BD-FC V-I1152 SIG Blowdown Heat Exchanger Outlet FCV.G. R23B :( Steam Generator Blowdown Processing) closes I-BD-RCV-023B SQ BLOWDOWN PMP DISC.Page 1 of 15 Page 1of 15Version 72.1 V1 7 Page 2 of 8 07/13/15 09:23:59 FNP-I-ARP-I

.6 LOCATION FHI.*RADIATION MONITOR TABLE I -p y p LOCATION DETECTOR FUNCTION ACTIONS R-IA Control Room (Unit I Area G-M (W) Perform Step____ Panel) _ _ _ _ _ __ 4.1 R-I B Technical Support Center Area G-M ( W ) No input to__ _(Unit II Panel) R-IB _______ ____this alarm R-2 Containment (155' elev) Area G3-Mr ( W) Starts IPC dose Perform Steps____ ________integration 4.2 R-3 Radiochemistry Lab (AB Area G-M (W~) Perform Step_ _ _ _ 139') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.3 R-4 #3 Charging Pump (AB Area G-M (_W ) Perform Step I__ _ 00') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.4 R-5* Spent Fuel Pool Room (AB Area G-M (_.W) Perform Steps_ _ _ _ 155') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 4.5 R-6 Sampling Room (AB 139') Area G-M ( _W) Perform Step____ __ ____ ___ ___4.6 R-7 In-core NIS Area (CTMT Area G-M ( W) Starts [PC dose Perform Steps____129', near Seal Table) ___________integration 4.7 R-8 Drumming Station (AB Area G-M (W ) Perform Step_ _ _ _ 155') _ _ _ _ _ _ _ _ _ __4.8 R-9 SG Sample Panel (Unit II Area G-M ( W ) No input to Panel) (AB 139') ___ _____this alarm R-0 Penetration Room Filtration APD Beta Scint Perform Step Discharge (AB 155') ____**(GA-ES) 4.9 R-I 1

Containment Atmosphere APD Beta Scint Perform Step (AB 121') **__ (GA-ES) _______4.10

Technical Specification related**General Atomics Electronic Systems Page 5 of 15 Vrin7.Version 72.1 V17 Page 3 of 8 07/13/15 09:23:59 FNP-1-.ARP-1

.6 LOCATIONFH RADIATION MONITOR REFERENCE TABLE (cont)RELOCATION TYPE~ DETECTOR FUJNCTION ACTIONS R- 12" Containment Atmosphere Gas Beta Scint Perform Step____(AR 121') ___ **(OA-.ES)

________4.11l R-1 3 Waste Gas Compressor Gas G-M ( _W) Perform Step Suction (AB 100' WGC 4.12 Valve Room) _________________

R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform Step ODCM ________ __4.13 R- i 5A Condenser Air Ejector Gas G-M ....Perform Step ODCM Discharge Header (TB 155') 4.14 R-I 5B* Condenser Air Ejector Gas G-M (Eberline)

Perform Step (Intermediate Range) (T 4.15 R-I 5C* Condenser Air Ejector Gas Ion Chamber Perform Step____(High Range) (TB 189') (berline)

_______4.15 R-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 Step ODCM Discharge (AB 121' at the 4.17______Batching Funnel) _____R-19 Steam Generator Liquid Scint. (YWL) Isolates sample Perform Step Blowdown/Sample (AR lines 3328, 4.1 8____139')

_______3329, 3330 ______R-20A Service Water from Liquid Scint. ( W) Perform Step Containment Coolers A and 4.19 B (AB 121' BTRS Chiller______ Room)__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R-20B Service Water from Liquid Scint. ( _W) Perform Step Containment Coolers C and 4.19______D (AB 121') ____________

__ _____*Technical Specification related**General Atomics Electronic Systems Page 6 of15 Vrin7.Version 72.1 V1 7 Page 4 of 8 07/1 3/15 09:23:59 FNP-I-ARP-1

.6 LOCATION Fill RADIATION MONITOR REFERENCE TABLE (cont)RE LOCATION TYP DIETECTR FUNCTON ACTIONS R-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____ ____________

____(Victoreen) 4.20 R-22 Plant Vent Stack Gas G-M (_W Perform Step ODCM (AB 155') -)_______________

4.21 R-23A SG Blowdown Surge Tank Liquid Scint. (__) Closes Perform Step Inlet (AB 130') ____FCV-1152 4.22 R-23B SG BLOWDOWN PMP Liquid Scint. ( __i) Closes Perform Step ODCM DISC (AB 130') ___ _____RCV-23B 4.22 R-24A* Containment Purge (AB Gas Scint. Closes No input to 155') containment this alarm purge supply &exhaust dampers 2866C & 2867C____________

_______and 3198A &D R-24B* Containment Purge Gas Scint. Closes valves: No input to (AB 155') (Victoreen) 2866D &2867D, this alarm 3196,3197,____________

_______3198B

& C R-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input to R-25B* (AB 184') (Victoreen) supply and this alarm e~xhaust fans;closes SEP H-VAC supply and exhaust dampers; starts associated trains of penetration

_____________

__ _ ________room filtration.

____R-27A* Containment (High Range) Area Ion Chamber No input to_____ _____________

____(Victoreen)

_ ______this alarm Technical Specification related Page 7 of 15 Vrin7.Version 72.1 07/13/15 09:41:15 1F~~i~ NP-2-ARP-1.6 Page 5of 8 LOCATION .Iill SETPOINT:

1. Variable, as per F'NP-2-RCP-252 ORIGIN: Any of the below listed Area, Process or Gaseous and Particulate 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, R224 R23A or R23B PROBABLE CAUSE RMS HI-RAD I. High Radiation Level in the System, Area or at the Component monitored.I

2. The radiation monitors fail to a "'High Radiation-"" condition on loss of instrument and/or control power that will result in actuation of associated automatic functions.

AUTOMATIC ACTION 1. The following actions will occur if a High Radiation Alarm is actuated on the 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 Recycle Evaporator discharge from Reactor Makeup Water System to the Recycle Evaporator Demineralizer.

c) RI7A or B: (Component Cooling Water) closes 2-CC W-RC V-3028 CCWN SRG TANK VENT.d) R I8: (Liquid Waste Processing) closes Liquid Waste Release Valve 2-LWP-RCV-0I18.

e) RI9: (Steam Generator Blowdown) isolates Steam Generator Blowdown Sample Lines.t) R23A: (Steam Generator Blowdown Processing) closes 2-BD--FCV-1 152 S/G Blowdown Heat Exchanger Outlet FCV.g) R23B: (Steam Generator Blowdown Processing) closes 2-BD-RCV-023B SGBD DISCH TO ENVIRONMENT.

Page 1 of 13 Vrin6.Version 61. i SNIT 2 07/13/15 09:41:15 Vi17 FNP-2-ARP-I.6 Page 6 of 8 LOCATION FHil OPERATOR 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 the table do not input into this alarm but are included for reference).

RADIATION MONITOR REFERENCE TABLE C RE LO:CATION TYPE DETECTOR FUNCTION ACTIONS R- 1A Control Room (Unit I Area G-M ( W) No input to Panel) _______this alarm R- lB Technical Support Center Area G-M ( W) Perform Step (Unit 1] Panel) R-l 1B_________

4.1 R-2 Containment (155' elev) Area G-M ( W) Starts IPC dose Perform Steps___ __ ___ __ ___ __ _ _ __ __integration 4.2 R-3 Radiochemistry Lab (AB Area G-M ( W) No input to 139') __________this alarm R-4 #3 Charging Pump (AB Area G-M (W) Perform Step 100') _____ ________4.3 R-5* Spent Fuel Pool Room (AB Area G-M (Wj) Perform Steps 155') _ _ _ _ _ _ _ _ _ _ 4.4 R-6 Sampling Room (AB 139') Area G-M ( W) Perform Step____ ___ ____ ___ ____ ___ ___ ___ ____ ___4.5 R-7 In-core NIS Area (CTMT Area G-M ( W) Starts IPC dose Perform Steps 129', near Seal Table) ____integration 4.6 R-8 Drumming Station (AD Area G-M ( W) Perform Step 155') __ _ _ _______4.7 R-9 SG Sample Panel (Unit II Area G-M (W) Perform Step Panel) (AB 139') 4.8 R- 10 Penetration Room Filtration APD Scint. Perform Step____Discharge (AD 155') (Victoreen) 4.9 R- 11

Containment Atmosphere APD) Scint. Perform Step____(AB 121') ____(Victoreen)

_______4.10

- Technicail Specification related Page 4 of 13 Page 4of 13Version 61.1

~k J. ~'V1 7 FNP-2-ARP-1.6 Page 7 of 8 07/13/15 09:41:15 LOCATION FHil RADIATION MONITOR REFERENCE TABLE (cont)RE. LOCATION TYPE DETECTO FU[NCTION ACTIONS R- 12* Containment Atmosphere Gas G-M ( W) Perform Step (AB 121') _____4.11 R-13 Waste Gas Compressor Gas O-M (W) Perform Step Suction (AB 100' WGC 4.12 Valve Room) ________R-14 Plant Vent Stack (AB Roof) Gas G-M ( W) Closes HCV-14 Perform Step ODCM ___________________

__4.13 R- 15A Condenser Air Ejector Gas G-M Perform Step ODCM Discharge Header (TB 155') 4.14 R-15B* Condenser Air Ejector Gas G-M (Eberline)

Perform Step (Intermediate Range) (TB3 4.15 189') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R .15C* Condenser Air Ejector Gas Ion Chamber Perform Step (High Range) (TB 189') (Eberline) 4.15 R-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 Step ODCM Discharge (AB 121' at the 4.17_______Batching Funnel)R-19 Steam Generator Liquid Scint. ( W) Isolates sample Perform Step Blowdown/Sample (AB lines 3328, 4.18 139') ___ _____ __3329, 3330 R-20A Service Water from Liquid Scint. ( W) Perform Step Containment Coolers A and 4.19 B (AB 121' BTRS Chiller_____Room)

_________________

Technical Specification relaed Page 5 of 13 Vrin6.Version 6 I. 1 UN 1 IT 2 V1 7 FNP-2-ARP-I1.6 Page 8 of 8 07113115 09:41:15 LOCATION .TL RADIATION MON1TOR TABLE (cont)RELOCATION IX DETECTOR FUNCTION ATIOQNS R-20B Service Water from Liquid Scint. ( W) Perform Step Containment Coolers C and 4.19______D (AB 121')______

R-21 Plant Vent Stack (AB 155') APD Scint. Perform Step____(Victoreen) 4.20 R-22 Plant Vent Stack Gas G-M ( W) Perform Step ODCM (AB 155') 4.21 R-23A SG Blowdown Surge Tank Liquid Scint. ( W) Closes Perform Step____Inlet (AD 130') ____ _______FCV-!

152 4.22 R-23B SGBD DISCH TO Liquid Scint. ( W) Closes Perform Step ODCM ENVIRONMENT RCV-23B 4.22_______ (AB 130')________

________ _ _ _ _ _ _R-24A* Containment Purge (AD Gas Scint. Closes No input to 155') containment this alarm purge supply &exhaust dampers 2866C & 2867C____ ________and 3198A & _____R-24B* Containment Purge Gas Scint. Closes valves: No input to (AD 155') (Victoreen) 2866D &2867D, this alarm 3196, 3197,_____3198B

&C R-25A/ Spent Fuel Pool Ventilation Gas Scint. Trip fuel bldg No input to R-25B* (AD 184') (Victoreen) supply and this alarm exhaust fans;closes SFP HVAC supply and exhaust dampers; starts associated trains of penetration room filtration.

Teehnical Specification related Page 6 of 13 Page6 o 13Version 61I.1I V18 Page 1 of 3 FNP-I-ARP-I.12 07/13/15 08:32:48 -SETPOINT: 1.2.3.0.01lg System Health Relay Alarm Relay 0 LOCATION M~~SEISMIC PANEL ALARM ORIGIN: 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 polling from central controller.

Hardware failure* Recorder high temperature

Failure of recorder(s) to respond to controller during startup.* Communication problem.* DC power loss on alarm panel.* AC power loss on recorder(s).

3. Alarm relay 0 (From channel 1 recorder, used for functional testing only).PROBABLE CAUS 1. Seismic event.12. Operating Basis Earthquake (OBE) exceeded.I 3.4.5.Seismic Panel loss of power.Instrument malfunction.

Seismic finctional testing in progress.AUTOMATIC ACTION 1. The monitoring system remain on at all times continuously monitoring the signals from the acceleration sensors.2. When a setpoint is exceeded, the system' retrieves the time history data from storage and automatically performs the preprogrammed calculations for operator review.3. The system printer provides print and plot copies of the results for record and review.El[]El Page I of 15 Vrin6.Version 63.1 07/13/i5 08:33:15 Vi18 Page 2 of 3 FNP-1-ARP-I1.12 LOCATION MK5 OPERATOR ACTIONS CONTINUED ACTION EXPECTED 3.3 Record and compare the seismic panel printout channel 1, 2 and 3 Spectral Acceleration calculated values, Spectral Velocity calculated values and Computed CAV values to the Spectral Acceleration design values, Spectral Velocity design values and CAV Design Limit Values on Table ! "~Operating Basis Earthquake Exceedance (OBEE)Limit for Determination of Plant Shutdown Requirements".

I RESPONSE NOT OBTAINED 3.4 Check the following:

CAV Design limit value has NOT been exceeded.*Based on operator walkdowns no plant significant damage is found.3.4.1 JF either unit tripped, THEN conduct a post trip review and restart as appropriate.

3.4 IF_ any of the following has occurred:* The Spetral Acceleration design value has been exceeded, o_.R* The Spectral Velocity design value has been exceeded,_OR* Significant plant damage is found during operator walkdowns THEN OBEE Criteria has been exceeded.3.4.1 Generate a Condition Report to refer to FNP- I-ETP-4580 and document the event.3.4.2 Generate a Condition Report to refer to FNP-I-ETP-4580 and document 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-1.1 LOCATION M15 TABLE I OPERATING BASIS EARTHQUAKE EXCEEDANCE (OBEE) LIMIT FOR DETERMINATION OF PLANT SHUTDOWN REQUIREMENTS Resoonse Soectr Analysis for..Free Field Measurement Channel 1: [L"~S1 Computed CAV = * ..g-sec, Limit =0.160 g-sec"PSA Limit = 0.200 g ", OBE SV Limit =15.240 Damping = 0.050 Spectral 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-UP1 Computed CAV -* ....g-sec, CAV Limit = 0.160 g-sec'*OBE PSA Limit -0.200 g**, OBE SV Limit ,,15.240 cm/sec, Damping =0.050 Spectral 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=W1 Computed CAV =

g-sec, CAV Limit = 0.160 g-sec"°OBE PSA Limit =0.200 g"*, OBE SV Limit = 15.240 cm/sec, Damping = 0.050 Spectral 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 setup values 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 of 0.0 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 one value 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 so the Farley Nuclear Plant OBE Spectra would control the OBE system alarm.Page 13 ofI Veson6.Version 63.1 V19 Page 1 of 3 RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.16 RCS Specific Activity LCO 3.4.16 APPLICABILITY:

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 TIME A. DOSE EQUIVALENT----------------Noe-------

1-131 > 0.5 pCi/gm. LCO 3.0.4c is applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I-131 within the acceptable region of Figure 3.4.16-1.AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.B. Gross specific activity of B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months the reactor coolant not Tavg < 500°F.within limit.Farley Units 1 and 2 3.4.16-1 Amendment No. 170 (Unit 1)Amendment No. 163 (Unit 2)

Vi19 Page 2 of 3 RCS Specific Activity 3.4.16 ACTIONS_________

___CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated CompletionTag<50F Time of Condition A notTag<50F met.O._R DOSE EQUIVALENT I-131 in the unacceptable region of Figure 3.4.16-1.SURVEILLANCEREQUIREMENTS

_______SURVEILLANCE FREQUENCY SR 3.4"16.1 Verify reactor coolant gross specific activity I10E .~/g.ten accordance withsrelac Frequency Control Program SR 3.4.16.2 ---NOTE---------------........

Only required to be performed in MODE 1.Verify reactor coolant DOSE EQUIVALENT 1-131 In accordance with specific activity < 0.5 IpCi/gm. the Surveillance Frequency Control Program AND Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of > 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period Farley Units 1 and 2 3.4. 16-2 Amendment No. 185 (Unit 1)Amendment No. 180 (Unit 2)

V19 Page 3 of 3 RCS Specific Activity 3.4.16 E 0 U 275 250 225 200 175 150 125.__'- -Operation_ _ .. +:_::~i-J:1 1_+?[]i. ..E I.N K.. .Acceptable ; ++ 5 -+ -* + -5 75. ... Operatin --50, 2 5 ,. ......0 ..., '. + : + ._ L .+ ' + : + ....20 30 40 5O 00 70 80 90 100 Percent of RATED THERMAL POWER Figure 3.4.16-1 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.5 jiCi/gm DOSE EQUIVALENT 1-131.Farley Units 1 and 2 3.4. 16-4 Amendment No. 147 (Unit 1)Amendment No. 138 (Unit 2)

V20 Page 1 of 1 RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to: a. No pressure boundary LEAKAGE;b. I gpm unidentified LEAKAGE;c. 10 gpm identified LEAKAGE; and d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).APPLICABILITY:

MODES 1, 2, 3, and 4.ACTIONS____________

_____ ___CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within limits within limits.for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.B. Required Action and 8.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AN met.8.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Pressure boundary LEAKAGE exists.Primary to secondary LEAKAGE not within limit.I 1 Farley Units I and 2 3.4.13-1 Amendment No. 163 (Unit 1)Amendment No. 156 (Unit 2)

V21 Page 1 of 1 ESFAS Instrumentation

3.3.2 Table

3.3,2-1 (page 2 of 4)Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT 2. Containment Spray a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.6 NA NA bi. Automatic Actuation 1.2,3,4 2 trains C SR 3.3.2.2 NA NA Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.8 Pressure SR 3.3.2.4 High -3SR 3.3.2.7 SR 3.3.2.9 3. Containment Isolation a. Phase A Isolation (1) Manual Initiation (2) Automatic Actuation Logic and Actuation Relays (3) Safety Injection b. Phase B Isolaton (1) Manual Initiation (2) Automatic Actuatio Logic andAcutn Relays 1,2,3,4 1,2,3,4 2 2 trains B SR 3.32..6 C SR 3.3.2.2 SR 3.3,2.3 SR 3.32.8 NA NA NA NA Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

1,2,3A4 1.2,3,4 2 2 trains B SR 3.3.2.6 C SR 3.32.2 SR 3.3 2.3 SR 3.3 28 E SR 3.3.2.1 SR 3.3.2..4 SR 3.32.7 SR 3.3,2-9 NA NA NA NA (3) Containment Pressure Hlgh -3 1.2,3 4 S 28.3 psig 5 27 psig Fadley Units I and 2 3.3.2-10 Amendment No. 185 (Unit 1) i Amendment No. 180 (Unit 2) I Edwin I. Hatch Nuclear Plant Units 1 and 2 License Amendment Request for Changes to Emergency Action Level Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant Enclosure 4 Hatch EAL Verification and Validation Documents Hatch EAL V&V Documentation Index V&V# ..'Description I' IC [Threshold' RCS Modes/Temperatures

-TS Reference (Table 1.1I-I) EAL Basis Section 1.4 1 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 I RG I (1)RS1 (1)RA1 (1)2 Radiation Monitor Calculations:

1D11-K604 RU1 (1)1D 11-K605 1D11-K619 A(B)1D1 l-K600 A(B)2D1 1I-K604 2D 11-K605 2D1 1-K636 A(B)Ca/c SMNH-13-021 Rev 1 Radiation Monitor Information:

RU2 (1)b 1D21-K601 A 2D21-K601 A 1D11-K601 D 2D21-K601 M 1D21-K601 E 2D21-K601 E 1D21-K601 M 2D21-K611 K 2D21l-K611 L Ca/c SMNH-13-021 Rev 1 _____Radiation Monitor Calculation:

CG1 (1)b DWRRM 1/2D 11-K621 A(B) CS 1 (2)b Ca/c SMNH-13-021 Rev 1 ______Primary Containment Rad Monitor Calculations FCB L4A FCB L4A DWRRM RCSB L4A RCSB L4A Ca/c SMNH-13-021 Rev 1 CB PL4A CB PL4A Offgas Pre-Post Treatment Reading Calculation FCB L5A FCB L5A Ca/c SMNH-13-021 Rev 1I_____Drywell Fission Product Monitor Reading Calculation Ca/c SMNH-13-021 Rev 1 RCSB L5A RCSB L5A ODCMITS 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 M 1D21-K601 B 2D21-K601 E 1D21-K601 D 2D21-K611 K 1D21-K601 E 2D21-K611 L 1D21-K601 M 2D11-K609 A-D IDII-K609 A-D 2D11-K611 A-D 1D1Il-K611 A-D 2D 11-K634 A-D 2D21-K601 A 2D11-K635 A-D Alarm Response Procedure Reference Control Room Rad RA3 (1)Monitor [Annunciator Display: 1D21-K600 B(C)] ____________

Alarm Response Procedure Reference RU2 (1 )a Annunciator Display: Spent Fuel Storage Pool Level Low 6 654-022-1 Spent Fuel Storage Pool 'Level Low 654-022-2

______2/22/20 16 Page 1 of 3 Hatch EAL V&V Documentation Index V&V# *Description

' IlC Threshold RPV Level Indications/Displays

(-155" TAF) CG1 (1)a 7CS1 (2)b FCB PL2A FCB PL2A Caic SMNH-13-021 Rev 1 RCSB L2A RCSB L2A RPV Level Indication/Display

(-35"); Level 2 Actuation CS 1 (1)b 8 setpoint info (required for CA1/CS1 is 6" below setpt) CAl (1)Caic SMNH-13-02I Rev 1 Drywell Floor Drain Sumps; Drywell Equipment Drain CG1 (2)b Sumps; Torus; Torus Room Sumps; RB Floor Drain CS 1 (3)b Sumps; TB Floor Drain Sumps; Rad Waste Tanks CA1 (2)b references cui (2)b H 2 Concentration

(> 6%) and 02 Concentration

(> 5%) -CGI (2)c 10 calculation/reference CB PL1B CB PL1B Cale SMNH-13-021 Rev 1 11 Primary Containment Pressure Reference

(> 56 psig) CG1 (2)c Calc SMNH-13-021 Rev]1 CB PLIA CB PL1A Secondary Containment Rad Monitors > Max Safe values CG1 (2)c 12 34AB-T22-O03-1/2 CBL3A CBL3A Secondary Containment Rad Monitors > Max Normal RCSBPL3A RCSBPL3A Values 34AB-T22-O03-1/2 4160 VAC Essential Buses Description CA2 (1)CU2 (1)a 13 SG1 (1)a SG8 (1)a SS1 (1)SA1 (1)SU1 (1)14 RCS Pressure indications CA3 (2)DC System Information CU4 (1)15 SO8 (1)b SS8 (1)16 ISFSI TS/Dose Reading Calculation E-HU1 (1)SMHN-13-021 Rev 1 17 Primary Containment Pressure > 1.85 psig reference RCSB LIA RCSB L1A 17 Calc SMNH-13-021 Rev 1 Secondary Containment Temps -> Max Normal values RCSBPL3A RCSBPL3A 18 34AB-T22-O03-1/2 Secondary Containment Temps -> Max Safe values CBL3A CBL3A 34AB-T22.-O03-1/2 Seismic Indications (OBE): HU2 (1)19 [Annunciator Display (657-048/657-066)]

12.7 Hz amber light 12.7 Hz red light 20 Table H2 Basis HU4 (1)b (2)b 34AB-X43-O01-1 (2)21 Minimum Steam Cooling RPV Water Level SG1 (1)b SS5 (1)c 22 Heat Capacity Temperature Limit (HCTL) Curve SS5 (1)c Pretreatment Radiation Monitor Reading SU3 (1)23 TS3.7.6 Caic SMNH-13-021 Rev 1 RCS sample activity -Tech Spec Value SU3 (2)24 TS3.4.6 2/22/2016 Page 2 of 3 Hatch EAL V&V Documentation Index IV&V# I> Description I IC IThreshold' RCS Operational Leakage -Tech Spec Values SU4 (1)(2)25 TS3.4.4 2/22/2016 Page 3 of 3 Vl Page 1 of 1 Definitions

1.1 Table

1.1-1 (page 1 of 1)MODES AVERAGE REACTOR COOLANT REACTOR MODE TEMPERATURE MODE TITLE SWITCH POSITION (°F)1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot NA Standby 3 Hot Shutdownl(a)

Shutdown > 212 4 Cold Shutdown(a)

Shutdown < 212 5 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 1 1.1-6 HATC UNI I 11-6Amendment No. 195 5 A~NY Ern~r,,.&'~i.v I~W*d4 V2 Southern Nuclear Design CalculationSeNL1589 Enclosure 3 ICalculation Number: SMNH-13-021 Plant:Hatch Nuclear Plant Unit:O 1 0" 2 0] 1 & 2 Discipllne:Mechanlcal Tlfite:Subject Emergency NEI 99-01 Rev 6 EAL. Calculations Action Level Setpoints Purpose I Objective:

Document Emergency Action Level Values to support conversion to NEI 99-01 Rev 6 System or Equipment Tag Numbers: N/A Contents Topic Page Attachments

of (Computer Printouts, Technical Papers, Pages__________________Sketches, Correspondence)

Purpose 1 A -SNC EP Concurrence 1 Criteria 1 B -Reserved 0 Conclusions 3 C -Fuel Clad' Loss 4.A Threshold Calculation 19 Design Inputs 5 D -Fuel Clad Potential Loss 5.A Threshold 1 Assumptions

,10 Calculation References 14 E -RCS Loss 4.A Threshold calculation

... 16 Method of Solutions 18 F -RCS Loss 5.A Threshold Calculation 6 Body of Calculation

.... ....23 G -containment Potential Loss 4.A 1__________________Threshold Calculation

______________H

-Steam Table Validation 5 I- RS1 Threshold Calculation

______ 25 Toa fPgsicuigJ

-CG1 Threshold Calculation 4 cover sheet & Attachments:

189 K -CG1 Threshold,,,Calculation 15 L -E-HU1 Threshold Calculation 16 M -RA1 Threshold Calculation 18 Nuclear Quality Level 0 -Safety-Related li Safety Significant 0 o-Safety -Significant Version Record Version Originator Reviewer' Approval I Approval 2 I, ~ dui= Name P.*HW 4Name Pri~ed Na. ati Calculation of EAL Thresholds. wb..d l-L to support NEI 99-01 Rev. 6 Notes: Key calculation NMP-ES-039 NMP-E-039NMP-ES-039-001 V3 Page 1 of 2 HNP ODCM d. 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 ,4 3.1.2 Gas eous Effluent Dose Rate Control In accordance with Technical Sp ecif'ication~s 5.5.4.c and 5.5.4.g, the licensee shall conduct o perations so that th e dos e rates due to radioactive materials rel eased in gaseous effluents from the siteto areas at and beyondthe SITE BOUNDARY (see Figure 10-1) are limited as follows: a. For noble gase.-s: Less than or equalto a dose rate of to the total body and less than or equal to a dose rate of 3000 /to the skin, and b. For Iodine-131, Iodine-133, tritum, and forall radionuclides in partioulate forin with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 j~r, j~rn to any organ.3.1.2.1 Applicability This limit applies at all times.3.1.2.2 Actions With a dos e rate due to radioactive material released in gaseous effluents exceeding the limit stated 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 Requirements The dose rates dueto radioactive materials in areas at or beyondth e SITE BOUNDARY due to rel eases of gaseous effluents shall be determinedto be withinthe above limits, in accordance with the methods and procedures in Section 3.4.1, by obtaining representative samples and performing analyses in accordance with the sam pling an d analysis program specifed in Table 3-3.3.1.2..4 Basis This control is provided to ensure that gaseous effluent dose rates will be maintained within the limits that historicallyhave provided reasonable assurance that radioactive material disdiarged in gas eous effluents wilN not result in a d ose to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceedingthe limits specified inAppendix I ofI10CFR Part 50, while allowing operational fl exibiity for effluent releases.

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 any increase in th e atmospheric diffusion factor above that for th e SITE BOUNDARY.3-6 Version 23 213 K eFPLOO PinAI FOUEUT B'mueaTea PFcJif 0)&Co V4 Page 1 of 16 SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) AGE 1 OF 2 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ARP'S FOR CONTROL PANEL 34AR-601-902-1 I 14.4 1H11-P601, ALARM PANEL 1 EXPIRATION APPROVALS:

EFFECTIVE DATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE: 04 15 N/A SSM /PM: N/A DATE: N/A ANNUNCIATOR RESPONSE PROCEDURES FOR IHII-P601 -ALARM PANEL 1 ARP 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 6.2 34AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.2 34AR-601-103-1 6.2 34AR-601-1 15-1 4.1 34AR-601-127-1 6.2 34AR-601-104-1 3.3 34AR-601-1 16-1 5.6 34AR-601-128-1 3.2 34AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.1 34AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.0 34AR-601-107-1 1.1 34AR-601-119-1 1.1 34AR-601-131-1 6.3 34AR-601-1 08-1 2.2 34AR-601-120-1 5.2 34AR-601-1 32-1 3.3 34AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.1 34AR-601-1 10-1 4.2 34AR-601-122-1 4.1 34AR-601-1 34-1 4.3 34AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.5 34AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0 I I NOE Approval signature on this page constitutes approval for all procedures listed above at the NOE revision indicated.

Tab numbers in the back correspond to procedure sequence number.I Level Of Use ARPs CONTINUOUS ALL REFERENCE None INFO None N MP-AP-002 V4 Page 2 of 16 PAGE 2 OF 2 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE: ARP'S FOR CONTROL PANEL 1H11-P601, ALARM PANEL 1 DOCUMENT NUMBER: VERSION NO: 34AR-601-902-1 I 14.4 UNIT 1 1H 11-P601 -1 601-101 601-102 601-103

601-104 601-105 601-106 601-107 601-108

601-109

601-110 601-111 601-112 601-113 601-114 601-115 601-116 601-117 601-118 601-119 601-120 601-121 601-122 601-123 601-124 601-125 601-126 *60-2 60-2 6119 6113 601-125 601-1326 601-127 601-128 601-125 601-130 RECORDS There are no records generated from this procedure.

COMMITMENTS None* 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 a cross-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 V4 Page 3 of 16 1.0 IDENTIFICATION:

ALARM PANE L 601-1_____ ___RX BLDG___ __ ___RADIATION

___ __ _ _ __ ___HIGH DEVICE: SETPOINT: 1D21-K601A, E, F, G, H, K, L, N, P, R, S, T, U, V, W, X, Y See 64C1-CAL-002-0

5.0 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.Li LI Li Li Li Li Li Li 6.0 CAUSES: 6.1 High radiation Trip on one or more of the following indicator/trip units: 1 D21 R600 CHANNEL TRIP UNIT LOCATION 01 1 D21-K601A Reactor Head Laydown 05 1D21-K601E Drywell Shield Plug 06 1D21-K601F Tip Area 07 1D21-K601G 130' NE Working Area 08 1 D21-K601H 130' SW Working Area 09 1 D21-K601K 158' SW Working Area 10 1D21-K601L Rx Wtr Smpl Rack Area 158'12 1D21-K601N South CR0 Hydraulic Units 13 1 D21-K601P North CR0 Hydraulic Units 14 1D21-K601R CS & RHR S-E Diag.15 1 D21 -K601 S Equipment Access Airlock 16 1 D21-K601T HPCI Turbine Area 17 1 D21-K601U TIP Probe Drive Area 18 1D21-K601V RCIC Equipment Area SW 19 1D21-K601W CR0 Pump Room NW 20 1 D21-K601X RB 203' Working Area 21 1D21-K601Y CS & RHR N-E Diag.6.2 Malfunctions of one or more trio units SENSOR 1D021-N002-1 1 D21-N002-5 1021 -N002-6 1021 -N002-7 1021 -N002-8 1 D21-N002-9 1021 -N002-1 0 1 D21-N002-12 1021 -N002-1 3 1 D21-N002-14 1021 -N002-1 5 1021 -N002-1 6 1 D21-N002-17 1021 -N002-1 8 1021 -N002-1 9 1 D21-N002-20 1 D21-N002-21 34AB-T22-003-1 ITEM NUMBER 1 4 11 14 16 9 10 17 12 21 15 22 13 18 19 6 20

7.0 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 procedure 34AR-601 -104-1 Ver. 3.3 MGR-0048 Ver. 5 V4 Page 4 of 16 1.0 IDENTIFICATION:

ALARM PANEL 601-1________

REFUELING FLOOR AREA RADIATION___ __ __ ___HIGH DEVICE: SETPOINT: 1 D21 -K601 B, 1 D21 -K601 D See 64C1-CAL-002-0

2.0 CONDITION

3.0 CLASSIFICATION

EQUIPMENT STATUS One OR both of the Refueling Floor Area Radiation Monitors has 4.0 LOCATION: exceeded its setpoint.1H-P0Pae601

5.0 OPERATOR

ACTIONS: 5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/trip units on panel 1D21-P600.

Li 5.1.1 Attempt to reset trip unit. LI 5.2 Confirm Control Room ventilation shifted to pressurization (Mode II), per 34SO-Z41-001-1, Control Room Air Conditioning System. LI 5.3 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) Li 5.3.2 Contact Health Physics to confirm radiological condition in the affected area, evacuate area IF required.

LI 5.3.3 Periodically monitor panel 1D21-P600, to ensure that no other channels on the Refueling Floor are indicating high OR~ in alarm. Li 5.3.4 Enter 34AB-T22-003-1, Secondary Containment Control. Li 5.3.5 Refer to 73EP-RAD-001-0, Radiological Event. Li 5.3.6 IF a radioactive release outside the Refueling Floor is occurring, OR has occurred, enter 34AB-D1 1-001-1, Radioactivity Release Control. Li 6.0 CAUSES: 6.1 High radiation causing one OR both of the following indicator/trip units: MONITOR CHANNEL TRIP UNIT LOCATION SENSOR 02 1D21-K601B Refueling Floor Stairway 1D21-N002-2 04 1D21-K601D Refueling Floor 1D21-N002-4

6.2 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, Area Radiation Monitoring Sys. D21 Elem Diag N/A -Not applicable to this procedure 34AR-601-1 10-1 Ver. 4.2 MGR-0048 Ver. 5 V4 Page 5 of 16 1.0 IDENTIFICATION:

__ALARMPANEL 601-1 __________ __ __ ___NEW FUEL__ __STORAGE AREA__ __ __RADIATION HIGH DEVICE: SETPOINT: 1 D21-K601C 64CI-CAL-002-0 1 D21-K601M 2.0 CONDITION:

3.0 CLASSIFICATION

2.1 Radiation

level in vicinity of Spent Fuel Pool Demineralizer EQUIPMENT STATUS Equipment ARM has exceeded its setpoint 4.0 LOCATION: 2.2 Radiation level in vicinity of Spent Fuel Pool & New Fuel Storage 1H11-P601 Panel 601-1 ARM has exceeded its setpoint 2.3 Loss of power to either of the above listed ARMs 5.0 OPERATOR ACTIONS: 5.1 Check for ILLUMINATED red upscale light and high reading on individual indicator/trip units on panel 1D21-P600.

LI 5.1.1 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) LI 5.2.2 Contact Health Physics to confirm radiological condition in the affected area AND evacuate area IF required.

LI 5.2.3 Periodically monitor 1D21-P600, panel, to ensure that no other channels on the Refueling Floor are indicating high OR in alarm. 13 5.2.4 Enter 34AB-T22-003-1, Secondary Containment Control. LI 5.2.5 Refer to 73EP-RAD-001-0, Radiological Event. III 5.3 If neither ARM is reading high, then at 1 R25-S064, confirm BRKR 9 is CLOSED. El 5.4 IF an abnormal radioactive release is occurring OR has occurred, enter 34AB-D1 1-001-1, Radioactivity Release Control. LI 6.0 CAUSES: 6.1 High radiation causing one or both of the following indicator/trip units to alarm: 1D21-R600 POINT TRIP UNIT LOCATION NUMBER SENSOR 3 1D21-K601C, Spent Fuel Pool Demin Equip 1D21-N002C 11 1D21-K601 M, Spent Fuel Pool & New Fuel Storage 1D21-NO02M 6.2 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 procedure 34AR-601-127-1 Ver. 6.2 MGR-0048 Ver. 5 V4 Page 6 of 16 DOCUMNT TTLE:DOCUMENT NUMBER: VERSION NO: ARP'SALRFOR PAECONTROL4 PANEL 1H11-P601, 34AR-601-901-1 12.4 EXPIATIN APROVLS:EFFECTIVE DATE: DEPARTMENT MANAGER DAK for Keith D. Lonq DATE 5-9-13 DATE: N/A SSM/PM N/A DATE N/A 5-15-15 ANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601

-ALARM PANEL 4 ARP 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 4.4 34AR-601-402-1 3.4 34AR-601-414-1 3.3 34AR-601-426-1 3.5 34AR-601-403-1 3.5 34AR-601-415-1 1.5 34AR-601-427-1 1.3 34AR-601 -404-1 0.2 34AR-60 1-416-1 1.3 34AR-601 -428-1 4.6 34AR-601-405-1 7.1 34AR-601-417-1 4.6 34AR-601-429-1 2.2 34AR-601-406-1 7.3 34AR-601-418-1 3.3 34AR-601-430-1 0.2 34AR-601-407-1 1.5 34AR-601-41 9-1 0.2 34AR-601-431-1 1.1 34AR-601 -408-1 1.5 34AR-601 -420-1 4.5 34AR-601 -432-1 4.3 34AR-60 1-409-1 5.5 34AR-60 1-421-1 4.3 34AR-601 -433-1 0.1 34AR-601-410-1 2.2 34AR-601-422-1 3.5 34AR-601-434-1 2.1 34AR-601-411-1 3.6 34AR-601-423-1 3.6 34AR-601-435-1 0 34AR-60 1-412-1 4.5 34AR-60 1-424-1 2.5 34AR-601 -436-1 0 INOTE Approval signature on this page constitutes approval for all procedures listed above at the I Version indicated.

Tab numbers in the back correspond to procedure sequence number.Level Of Use ARPs CONTINUOUS ALL REFERENCE None INFO None I V4 Page 7 of 16 UNIT 1 1H11-P601-4 601-401 601-402 601-403 601-404 601-405 601-406 601-407 601-408 601-409 601-410 601-411 601-412 601-413 601-414 601-415 601-416 601-417 601-418 601-419 601-420 601-421 601-422 601-423 601-424 601-425 601-426 601-427 601-428 601-429 601-430 601-431 601-432 601-433 601-434 601-435 601-436 RECORDS No Records are generated by this procedure.

COMMITMENTS SNC1 9472, SNC5027 V4 Page 8 of 16 1.0 IDENTIFICATION:

ALARM PANEL 601-4 __________

REFUELING FLOOR___ __ __ ___VENT EXHAUST___ __ __ __ ___RADIATION HI-HI DEVICE: SETPOINT: 1D11-K611A thru D 18 mr/hr 2.0 CONDITION:

3.0 CLASSIFICATION

EMERGENCY Radiation levels in the Refueling Floor Exhaust Duct exceed the 4.LOAIN setpoint.1H11-P601 Panel 60 1-4 5.0 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. Eli 5.2 IF only one trip unit is alarmed, AND the unit is not malfunctioning, determine and correct the cause of the high high radiation.

LI 5.3 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, and perform concurrently with this procedure.

Eli 5.4 IF refueling is in progress, STOP refueling operations, and if possible, insert any withdrawn Control Rods. LI 5.5 Evacuate personnel from the Refueling Floor. LI 5.6 IF: refueling or fuel handling was in progress, ENTER 34AB-J11-001-1, Irradiated Fuel Damage During Handling.

LII 5.7 IF" an abnormal radioactive release is occurring, ENTER 34AB-D1 1-001-1, Radioactive Release Control. LI 6.0 CAUSES: 6.1 High radiation levels in the vent duct 6.2 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 Containment Process Radiation Monitoring System Elem Diag Isolation Instr Table 3.3.6.2-1 34AR-601 -403-1 Ver. 3.5 V4 Page 9 of 16 1.0 IDENTIFICATION:

ALARM PANEL 601-4 ___________ __ ___RX BLDG POT___ __ __ __ ___CONTAM AREA______-VENT RADN HI-HI DEVICE: SETPOINT: 1 D11-K609A 1ID11-K609B 18 mr/hr 1D1 1-K609C, 1 D1 1-K609D 5.0 OPERATOR ACTIONS: 5.1 Confirm annunciator by monitoring the radiation level on 1D11-R605, recorder, 1H11-P600.

LI 5.1.1 Monitor 1 D11-K609A, ID11-K609B, 1ID11-K609C, 1D1I-K609D, Reactor Building Potential Contaminate Area Rad Monitors, 1Hi 11-P606.IF only one trip unit is affected, attempt to reset the affected trip unit. Eli 5.2 IF only one trip unit is alarmed AND the unit is not malfunctioning, determine and correct the cause of the high high radiation.

LI 5.3 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. III 5.4 IF an abnormal radioactive release is occurring, ENTER 34AB-D1 1-001-1, Radioactivity Release Control. LI 6.0 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. 3.3.6.1 Radiation Monitoring System Elem Diag 8.2 Unit 1 T.S. 3.3.6.2 7.2 H-16005, Reactor Building Vent System P&ID 34AR-60 1-426-1 Ver. 3.5 V4 Page 10 of 16 SOUTHERN NUCLEAR IDOCUMENT TYPE:I PLANT ElI. HATCH ANNUNCIATOR RESPONSE PROCEDURE (ARP) PAGE 1 OF 2 DOCUMENT TITLE: NUMBER: VERSION NO: ARP'S FOR CONTROL PANEL 2H1 1-P601, ALARM PANEL 3 l 34AR-601-904-2 12.18 EXPIRATION APPROVALS:

EFFECTIVE DATE: DEPARTMENT MANAGER G. L. Johnson DATE 04/19/00 DATE: 8/31/15 N/A SSM /PM N/A DATE N/A _____ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601

-ALARM PANEL 3 ARP 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 2.3 34AR-60 1-302-2 3.2 34AR-60 1-314-2 2.4 34AR-60 1-326-2 0.5 34AR-601-303-2 3.3 34AR-601-315-2 1.2 34AR-601-327-2 5.2 34AR-601 -304-2 3.2 34AR-60 1-316-2 0.2 34AR-60 1-328-2 2.2 34AR-601 -305-2 0.3 34AR-601 -317-2 2.1 34AR-601 -329-2 1.3 34AR-60 1-306-2 3.3 34AR-601 -318 SPARE 34AR-60 1-330-2 2.2 34AR-601-307-2 2.4 34AR-601-319-2 0.3 34AR-601-331-2 2.3 34AR-601-308-2 2.3 34AR-601-320-2 1.2 34AR-601-332-2 0.3 34AR-601-309-2 1.2 34AR-601-321-2 4.2 34AR-601-333-2 0.3 34AR-601-310-2 0.4 34AR-601-322-2 0.6 34AR-601-334 SPARE 34AR60131 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 ARPs CONTINUOUS ALL REFERENCE None INFO None MGR-0002 VER. 8.1 V4 of 16 UNIT 2 2H11-P601

-3 601-301 601-302 601-303 601-304 601-305

601-306 601-307 601-308 601-309 601-310 601-311

601-312 601-313 601-314 601-315 601-316 601-317 601-318 601-319 601-320 601-321 601-322

601-323 601-324 601-325 601-326 601-327 601-328 601-329 601-330 601-331 601-332 601-333 601-334 601-335 601-336* 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 a cross reference for locating the device(s) in ABNORMAL AND/OR EOP Tables.Refer to 34AB-T22-003-2, Secondary Containment Control.RECORDS No records are generated from this procedure.

COMMITMENTS NONE MGR-0001 VER. 4 V4 Page 12 of 16 1.0 IDENTIFICATION:

ALARM PANEL 601-3-II--II r REFUELING FLOOR AREA RADIATION HIGH DEVICE: SETPOINT: 2D21-K601-A,E,M See 64CI-CAL-002-0 2D21-K61 1-K,L 5.0 OPERATOR ACTIONS: 5.1 Check for ILLUMINATED red upscale light AND~ high reading on individual indicator/trip units on panel 2D21-P600.

LI 5.1.1 Attempt to reset Trip Unit. LI 5.2 IF 2D21-K601 A O._R M Tripped, THEN confirm Control Room ventilation shifted to pressurization (Mode II) per 34SO-Z41-001-1, Control Room Ventilation System. LI 5.3 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) Lii 5.3.2 Contact Health Physics to confirm radiological condition in the affected area, evacuate area IFrequired.

LI 5.3.3 Periodically monitor panel 2D21-P600 to ensure no other channels on the Refueling Floor are indicating high OR in alarm. LI 5.3.4 Enter 34AB-T22-003-2, Secondary Containment Control. LI 5.3.5 IF a radioactive release outside the Reactor Building is occurring, OR has occurred, enter 34AB-D1 1-001-2, Radioactivity Release Control. LI 6.0 CAUSES: 6.1 High radiation causing a trip of one ORR more of the following indicator trip units MONITOR CHANNEL LOCATION SENSOR TRIP UNIT 1 Reactor Head Layout Area 2D21-N002-A K601-A 5 Dryer/Separator Pool 2D21-N002-E K601-E 10 Spent Fuel/Fuel Pool Areas 2D21-N002-M K601-M 21 Reactor Vessel Refueling Area 2D21-N012-K K61 1-K 22 Reactor Vessel Refueling Area 2D21-N012-L K61 1-L 6.2 Malfunction of trip unit

7.0 REFERENCES

8.0 TECH. SPECS./TRMIODCMIFHA:

7.1 H-27805 thru H-27810 and H-27992, Area Radiation Monitoring Sys 2D21 Elementary Diagram 8.1 TRM Table T3.3.7-1 34AR-60 1-312-2 Ver. 4.3 MGR-0048 Ver. 5.0 A-GR7- 0 AG-MGR-75-1101 V4 Page 13 of 16 SOUTHERN NUCLEAR )OCUMENT TYPE: PLANT ElI. HATCH lANNUNCIATOR RESPONSE PROCEDURE (ARP PAGE 1 OF 2 DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO: ARP'S FOR CONTROL PANEL 2HI11-P601, 34AR-601-901-2 l 12.1 ALARM PANEL 4/EXPIRATION APPROVALS:

IEFFECTIVE DATE: DEPARTMENT MANAGER DAK for Keith D. Long DATE 5-9-13 I DATE: N/A SSM/PM N/A DATE N/A 5-i5-I5 ANNUNCIATOR RESPONSE PROCEDURES FOR 2H11-P601

-ALARM PANEL 4 ARP 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 3.4 34AR-60 1-402-2 4.1 34AR-60 1-414 Spare 34AR-60 1-426-2 6.3 34AR-601-403-2 5.4 34AR-601-415-2 1.0 34AR-601-427-2 2.3 34AR-60 1-404-2 0.3 34AR-60 1-416-2 0.5 34AR-60 1-428-2 5.5 34AR-60 1-405-2 8.1 34AR-60 1-417-2 4.3 34AR-60 1-429-2 3.1 34AR-60 1-406-2 8.3 34AR-60 1-418-2 1.2 34AR-60 1-430-2 0.3 34AR-60 1-407-2 3.6 34AR-60 1-419-2 1.1 34AR-60 1-431-2 2.1 34AR-601-408-2 1.0 34AR-601-420-2 6.3 34AR-601-432-2 4.3 34AR-601-409-2 5.3 34AR-601-421-2 4.3 34AR-601-433-2 1.4 34AR-601-410-2 2.3 34AR-601-422-2 5.4 34AR-601-434-2 3.0 34AR-601-411-2 4.5 34AR-601-423-2 4.4 34AR-601-435-2 1.1 34AR-601-412-2 0.4 34AR-601-424-2 2.3 34AR-601-436-2 0.1 I INOTE Approval signature on this page constitutes approval for all procedures listed above at the I Version indicated.

Tab numbers in the back correspond to procedure sequence number.FI Level Of Use ARPs CONTINUOUS ALL REFERENCE None INFO None V4 Page 14 of 162 OF2 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE: 'DOCUMENT NUMBER: VERSION NO: ARP'SALRFORpAECONTROL4 PANEL 2H11-P601, 34AR-601-901-2 1 12.1 UNIT 2 2H1 1-P601 -4 601-401 601-402 601-403 601-404 601-405 601-406 601-401 601-408 601-409 601-410 601-411 601-412 601-413 601-414 601-415 601-416 601-417 601-418 601-419 601-420 601-421 601-422 601-423 601-424 601-425 601.426 601-427 601-428 601-429 601-430 601-431 601-432 601-433 601-434 601-435 601-436 RECORDS There are no records generated from this procedure.

COMMITMENTS SNC5027 V4 Page 15 of 16 1.0 IDENTIFICATION:

ALARM PANEL 601-4 T 11 T T -1-4-1 REFUELING FLOOR VENT EXHAUST RADIATION HI-HI DEVICE: 2D11-K611 A thru D 2D11-K634 Athru D 2D11-K635 Athru D SETPOINT: 18 mr/hr PER 64Cl-CAL-002-0 PER 64CI-CAL-002-0

2.0 CONDITION

3.0 CLASSIFICATION

Radiation levels in the. Refueling Floor Exhaust Duct exceed EMERGENCY the setpoint.

4.0 LOCATION

2H11-P601 panel 601-4 5.0 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 Lii 5.1.1 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. LI 5.2 IF only one trip unit is alarmed, AND the unit is NOT malfunctioning, determine AND correct the cause of the high high radiation.

Eli 5.3 IF refueling operations are in progress, STOP refueling operations AND IF possible, insert any withdrawn Control Rods. LI 5.4 Evacuate personnel from the Refueling Floor. LII 5.5 IF refueling OR fuel handling was in progress, enter 34AB-J1 1-001-2, Irradiated Fuel Damage During Handling.

LI 5.6 For valid alarm conditions, enter 31EO-EOP-014-2, SC-Secondary Containment Control AND 34AB-T22-003-2, Secondary Containment Control. LI 5.7 IF an abnormal radioactive release is occurring OR has occurred, ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI 6.0 CAUSES: 6.1 High radiation levels in the vent duct 6.2 Trip unit failure, upscale OR downscale

___________________

7.0 REFERENCES

8.0 TECH. SPECS./TRMIODCMIFHA:

7.1 H-27629 and H-27631, Process Radiation Monitoring Diagram, Sheets 10 and 12 8.1 U2 TS 3.3.6.1 Table 3.3.6.1-1 7.2 H-27596 thru H-27600, Primary Containment Isolation System, Sheets 1 through 5 8.2 U2 TS 3.3.6.2 Table 3.3.6.2-1 34AR-60 1-403-2 VER. 5.4 V4 Page 16 of 16 1.0 IDENTIFICATION:

ALARM PANEL 601-4________

RX BLDG POT___ CONTAM AREA VENT RADN HI-HI DEVICE: SETPOINT: 2011l-K609A through 0, Per 64CI-OCB-006-2, Form HPX-1 252, from Chemistry Trip Indicator Unit 2.0 CONDITION:

3.0 CLASSIFICATION

Radiation levels on the inlet to 2T41-D005, Reactor Building EMERGENCY Exhaust Filter Train, exceeds the setpoint.

4.0 LOCATION

2H11-P601 panel 601-4 5.0 OPERATOR ACTIONS: 5.1 On panel 2H1 1-P600, confirm annunciator by monitoring the radiation level on 2D1 1-K609A/2D1 1-K609B/2D11l-K609C/2D1 1-K609D on 2D1 1-R605 recorder.

El 5.1 .1 Monitor 2011 -K609A through D, Reactor Building Potential Contaminated Area Rad Monitors, on 2H11-P606.

IF only one trip unit is affected, attempt to RESET the affected trip unit. LI 5.2 IF only one trip unit is alarmed AND the trip unit is NOT malfunctioning, determine AND correct the cause of the high high radiation.

El 5.3 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 AND confirm Automatic Actions per 34AB-T22-003-2, Secondary Containment Control, Attachment

7. LI 5.4 IF an abnormal radioactive release is occurring OR has occurred, ENTER 34AB-D1 1-001-2, Radioactivity Release Control. LI 6.0 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 3.3.6.1 Radiation Monitoring System Elem. Diag.7.2 H-26067 Reactor Zone Ventilation System P&ID 34AR-601 -420-2 VER. 6.3 VS Page 1 of 3 SOUTHERN NUCLEAR DOCUMENT TYPE: PLANT E.I. HATCH ANNUNCIATOR RESPONSE PROCEDURE

('ARP' AGE 1 OF 2 V5 Page 1 of 3 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION NO: ARP'S FOR CONTROL PANEL 34AR-601-902-1

] 14.4 1H11-P601, ALARM PANEL 1 EXPIRATION APPROVALS:

EFFECTIVE DATE: DEPARTMENT MANAGER: KEH for REV DATE: 03-19-12 DATE: 04-30-15 N/A SSM /PM: N/A DATE: N/A ANNUNCIATOR RESPONSE PROCEDURES FOR 1H11-P601

-ALARM PANEL 1 ARP 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 6.2 34AR-601-102-1 3.2 34AR-601-114-1 3.2 34AR-601-126-1 2.2 34AR-601-103-1 6.2 34AR-601-115-1 4.1 34AR-601-127-1 6.2 34AR-601-104-1 3.3 34AR-601-116-1 5.6 34AR-601-128-1 3.2 34AR-601-105-1 2.2 34AR-601-117-1 2.1 34AR-601-129-1 6.1 34AR-601-1 06-1 4.2 34AR-601-1 18-1 2.2 34AR-601-1 30-1 5.0 34AR-601-107-1 1.1 34AR-601-1 19-1 1.1 34AR-601-1 31-1 6.3 34AR-601 -108-1 2.2 34AR-601 -120-1 5.2 34AR-601-1 32-1 3.3 34AR-601-109-1 4.1 34AR-601-121-1 4.1 34AR-601-133-1 4.1 34AR-601-110-1 4.2 34AR-601-122-1 4.1 34AR-601-134-1 4.3 34AR-601-111-1 2.3 34AR-601-123-1 2.1 34AR-601-135-1 6.5 34AR-601-112-1 5.1 34AR-601-124-1 2.1 34AR-601-136-1 4.0 NOTE:______

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 ARPs CONTINUOUS ALL REFERENCE None INFO None NMP-AP-002 I

V5 Page 2 of 3 SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 2 OF 2 DOCUMENT TITLE: DOCUMENT NUMBER: lVERSION NO: ARP'S FOR CONTROL PANEL 1H11-P601, 34AR-601-902-1 1 14.4 ALARM PANEL 1 UNIT 1 1H11-P601

-1 601-101 601-102 601-103 *601-104 601-105 601-106 601-107 601-108

601-109

601-110 601-111 601-112 601-113 601-114 601-115 601-116 601-117 601-118 601-119 601-120 601-121 601-122 601-123 601-124 601 -1 25 601 -1 26 601-1 27 601-1 28 601-1 29 601 -130 601-131 601-132 601-133 601-134 601-135 601-136 RECORDS There are no records generated from this procedure.

COMMITMENTS None* 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 a cross-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 V5 Page 3 of 3 1.0 IDENTIFICATION:

ALARMPANEL_601-1

___________ __ ___TURBINE BLDG__RADIATION

___ __ ___HIGH DEVICE: SETPOINT: SEE SECTION 6.0 AS PER THE CHEMISTRY CONTROLLED SETPOINT RECORD 5.0 COPERATIOR:

ACTIONS:FCATON 5.1 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. LI 5.1.1 Attempt to reset the trip unit. Iii 5.2 Notify Health Physics to determine the validity of the alarm. LI 5.3 IF the alarm is valid, enter 73EP-RAD-001-0, Radiological Event. LI 5.4 Refer to 34AB-U22-001-1, Pipe Break in Turbine Building, for possible entry conditions.

LI 5.5 IF a radiation release to outside the Turbine Building has occurred OR is occurring, enter 34AB-D1 1-001-1, Radioactivity Release Control. LI 5.6 IF a Fuel Element Failure is confirmed, Initiate Turbine Building Purge per 34SO-U41-001-1 radiation.

LI 5.7 Monitor other ARM's that are associated with this annunciator for increasing radiation.

LI 6.0 CAUSES: High radiation, as indicated by one of the following ARM's: 1D21-R600 POINT NUMBER MONITOR AREA 22 1D21-K600A Main Turbine Front Standard 23 1D21-K600B Control Room 24 1 D21-K600C Control Room 25 1D21-K600D T/B 164' North End Operating Floor 26 1D21-K600E Turbine Bldg Feedwater Area 27 121-K01ZCondensate Demin Area 34AR-601-1 16-1 Ver. 5.6 MGR-0048 Ver. 5 SM-SNC524602-001I Attachment I ENERCON Calculation for E-HU1 SHEET I-6 v15 Page 1 of 3 CALC NO. SNC024-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0 PAGE NO. Page 6 of 8 5.0 Design Inputs 1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask system technical specification

[2, Table 6.2-3] are provided below in Table 5-1. These source values are scaled to develop the emergency action levels for initiating condition E-HU1.Table 5-1 Technical Specification Dose Rate Limits (Neutron + Gamma) for HI-STORM 100 and HI-TRAC 125 LocaionNumber of 1Technical Specification jMeasurementsj Limit (mrem/hr)HI-TRAC 125 Side -Mid -height T 4 1680.3 Top 1 4 j129.4 HI-STORM 100 Side -60 inches below mid-height 4 171.8 Side -Mid -height 4 177.0 Side -60 inches above mid-height 4 84.7 Top -Center of lid 1 27.1 Top -Radially centered 4 30.0 Inlet duct 4 231.8 Outlet duct 4 82.2 SM-SNC524602-001 Attachment I IPNI::IlNN

(.'l'ml:afinn fnr IF..WI I1 SHEET I-7 v15 Page 2 of 3 CALC NO. SNCO24-CALC-003 FNP DETERMINATION OF ___________

EMERGENCY ACTION LEVEL REV. 0 0I EN ER C ON FORI=NITATNG CONDITION E- _ _______..."' HUl PAGE NO. Page 7 of 8 6.0 Methodology The "on-contact"'

dose rates from the technical specification for the HI-STORM 100 and HI-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-SNC524602-001 Attachment I I:PCANI (%lrdp-mi6*rn fr i::._WI I1 SHEET I-8 v15 Page 3 of 3 CALC NO. SNC024-CALC-003 FNP DETERMINATION OF EMERGENCY ACTION LEVEL REV. 0 0 E N E R C 0 N FOR INITAliNG CONDITION E-HUl PAGE NO. Page 8oft8 7.0 Calculations The dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose rate limits. These calculations are presented below in Table 7-1.w Table 7-1 Dose Rate Scaling Calculations for EAL Limits (Neutron + Gamma)Technical LoainSpecification Scaling Calculated Value EAL LoainLimit Factor .(mremn/hr) (mrem/hr)_______________________ (mremlhr)

____________

_____________ ______ ______ ______HI-TRAC 125 _ _ _ _ _ _ _ _ _ _ _ _ _ _Side -Mid -height [ 680.3 j 2 J 1360.6 1360 Top L 129.4 j 2 258.8 260 Side -60 inches below mid-height Side -Mid -height Side -60 inches above mid-height Top -Center of lid Top -Radially centered Inlet duct Outlet duct 171.8 177.0 84.7 27.1 30.0 231.8 82.2 343.6 340 354 350 169.4 170 54.2 50 60 60 463.6 460 164.4 160 8.0 Computer Software Microsoft WORD 2Q13 is used in this calculation for basic multiplication.

V16 LYN I Page 1o of 8 CORE COOLING Revision 17 P S SFIFTH NO HOTTEST I TC LESS i GO TO SAT a Page1 ofI1 V16 N !T 1Page 2 of 8 HEAT SINK Revision 17 FRP4.LI~GO TO FRP-H.2 PRESS IN INOI ALL SG'S L.EBB THAN"" GO TOFRP-H.3 NAR RNG N LVL IN ALL L SO'S LESS '--'THAN 62 1 YESJGOTO r FRP-H.4 PRESS IN N ALL SG'S LESS THAN,,,,, 1075 P8I10YE GO TO-I FRP-4.5 CSF SAT 1 V16 Page 3 of 8 8/29/2007 08:3 3 FNP-I-CSF-O.4 INTEGRIT Revision 17 I-f,' GO TOFRP.P.1 JGO TO inininm m --t a FRP-.2 CSF SAT GO TO GOOT SAT SAT PagI 1 f2

[NI 1Page 4of 8 FP1CSF-0.

COTANMN Geson TO PRESS NO in in, -FRP-Z.1 LESS ri- !THAN 5 YEs At LEAST ONE NOI PUMP RUNNING--

--OT I (FLOW>IODOOGPM)

YES ,. 2 I CTMT ko I S~UMP LVL N CTMT [THAN 7.6 I=: LESS H THAN 27 YsGO TO PSIG FRPZ.SUMP LVL.N LESS THAN 7.6H FT.~GO TO FRP-Z.3 BOTH CTMT RAD N LESS --hrTHAN 2 R/ LY1CS Page 1 of I 1I]IJIT9 Vi16 Page 5 of 8 8/29/2007 08:33 -FNP-2-CSF-0,2 CORE COOLING Revision 12 GOTOo IP I m IIFRP-C.1 HOTTEST NORP.CCORE EXIT THAN YETHANT790TCREXIT---, TC LSSTC HES SUBOO NO GO TOCOR PRP-C.3 0 EXIOT TCS "-iGRTR THAN E i16" F 145"F}Page1 of 1 V1 6!]N IT 2Page 6 of 8 FNP-2-CSF-O0.3 HEAT SINK Revision 12 SGO TO FRP-K.1 miTOTAL AFW NO IiFLOW TO I 1 ALL SG'8 -,-, 395 GPM E GO TO~FRP-HL2 LVL IN AT IN NO LEAST ONE ALL SG'S SG GRTR --'-LESS THAN THAN 31% YES __ _______ 1129PSIG YES ,[ GO TO! f FRP-H.3 MiAR RNG [N]LVL IN ALL SGS8 LESS mmm THAN 52% YES GO TO-I FRP-H.4 PRESS IN NO ALL 5G5S: ILESS THANmmg 1075 P810 YES GO TO I r FRP-H.5 CSF SAT Page 1 of I V16 7 of 8 FNP-2-CSF-O.4 IINTEGRITY Revision 12 COLD LGTMEAUE('F GO TO W FRP-P,1 ALL RCS PRESS- OT CL TEMP (IN m -ine e l RIGHT OF YES ,.,i_AL. RCS CL N OT TEMPS INGOT SLAST 60 MIN -,FRP..P.2 GRTIR THAN--'---- L RCS CL N~ TEMP TEMPNO SA LALATT600MIN LESSR ThAN TEM DCRNN OJ SA LESTRTTAHAN GOT 326' F SAT CSF SAT Page I of 2 Vi16*l Page 8 of 8 8/29/2007 08:33 I NJ J .FNP-2-CSF-0.5 CONTAINMENTReion1 H CTMT TI _O__O PRESS NO R "P .L "I m-~-LESS H-- 11 THAN 5 YES At LEAST ONE NO RUNNING (FLOW1 000GPM)YES FnI *m WRP-Z.2 SUMP LVL OI CTMT- THAN 7.6[PRESS N LESS- S ITHAN 27 YEs GO TO PSIG jjFRP-Z.1 SUMP LVI NO LESS H.-THAN 7.6 YE FT.GO TO FRP-Z.3 1 THAN2RJ [ES T SAT Page 1 of I V1 7Page 1 of 8 07/13/15 09:23:59 LOCATION FiUl SETPOINT:

1. Variable, as per FNP-1-RCP-252 HI RMS ORIGIN: Any of the below listed Area, Process or Gaseous and HI-RAD Particulate Monitors:

R01, R02, R03, R04, RO5, R06, R07, R08,-R1OI RI1, R12, RI3,[T RI5, RI7A ________R17B, RIS8, R-I19, R20A, R20B, R21, R23A or R23B.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 of instrument and/or control power that will result in actuation of associated automatic functions.

AUTOMATIC ACTIONS;I. The following actions will occur if a High Radiation Alarm is actuated on the associated Radiation Monitor.A. R14: (Plant Vent Gas) closes Waste Gas Release Valve I -G WD-HV-0 14.8. R16: None -abandoned in place per MDC 1040589501.

C. R17A or B: (Component Cooling Water) closes QIPIYRCV3028 CCW SRG TANK VENT.D. R18: (Liquid Waste Processing) closes Liquid Waste Release Valve I -L WP-RC V-0 18.E. R19: (Steam Generator Blowdown) isolates Steam Generator Blowdown Sample Lines.F. R23A :( Steam Generator Blowdown Processing) closes 1-BD-FC V-I1152 SIG Blowdown Heat Exchanger Outlet FCV.G. R23B :( Steam Generator Blowdown Processing) closes I-BD-RCV-023B SQ BLOWDOWN PMP DISC.Page 1 of 15 Page 1of 15Version 72.1 V1 7 Page 2 of 8 07/13/15 09:23:59 FNP-I-ARP-I

.6 LOCATION FHI.*RADIATION MONITOR TABLE I -p y p LOCATION DETECTOR FUNCTION ACTIONS R-IA Control Room (Unit I Area G-M (W) Perform Step____ Panel) _ _ _ _ _ __ 4.1 R-I B Technical Support Center Area G-M ( W ) No input to__ _(Unit II Panel) R-IB _______ ____this alarm R-2 Containment (155' elev) Area G3-Mr ( W) Starts IPC dose Perform Steps____ ________integration 4.2 R-3 Radiochemistry Lab (AB Area G-M (W~) Perform Step_ _ _ _ 139') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.3 R-4 #3 Charging Pump (AB Area G-M (_W ) Perform Step I__ _ 00') _ _ _ _ _ _ _ _ _ _ _ _ _ 4.4 R-5* Spent Fuel Pool Room (AB Area G-M (_.W) Perform Steps_ _ _ _ 155') _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 4.5 R-6 Sampling Room (AB 139') Area G-M ( _W) Perform Step____ __ ____ ___ ___4.6 R-7 In-core NIS Area (CTMT Area G-M ( W) Starts [PC dose Perform Steps____129', near Seal Table) ___________integration 4.7 R-8 Drumming Station (AB Area G-M (W ) Perform Step_ _ _ _ 155') _ _ _ _ _ _ _ _ _ __4.8 R-9 SG Sample Panel (Unit II Area G-M ( W ) No input to Panel) (AB 139') ___ _____this alarm R-0 Penetration Room Filtration APD Beta Scint Perform Step Discharge (AB 155') ____**(GA-ES) 4.9 R-I 1

Containment Atmosphere APD Beta Scint Perform Step (AB 121') **__ (GA-ES) _______4.10

Technical Specification related**General Atomics Electronic Systems Page 5 of 15 Vrin7.Version 72.1 V17 Page 3 of 8 07/13/15 09:23:59 FNP-1-.ARP-1