ML16071A153

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

ML16071A153
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: ML16071A153 (52)

Text

Vogtle Electric Generating 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 4Vogtle EAL Verification and Validation Documents Vogtle EAL V&V Documentation Index.V&V# Description ,. ,,IC IThresholdRCS Modes/Temperatures -TS Reference (Table 1.1-1) EAL Basis Section 1.51 RCS Cold Shutdown Temperature reference (200 °F) CA3 (1)CU3 (1)Radiation Monitor Calculations: RG 1 (1)RE-12839E RSl (1)RE-12444E RA1 (1)Calc X6CNAJ15Radiation Monitor Calculations: RE-0018 RUI (1) (2)RE-0021RE-0848ARE-00142 ~RE- 12839RE-12442CRE-12444CCaic X6CNAJ15Radiation Monitor Calculation: RE-005 CGI1 (2)bRE-006 CS1 (3)bFCB L3A FCB L3ARCSB L3A RCSB L3ACaic X6CNA15 CB PL3A CB PL3AODCM/TS Reference to Site Boundary RG1 (2) (3)3RS 1 (2) (3)RA1 (2) (3) (4)SFP Level 3 & 2 Indications RG2 (1)4 RS2 (1)RA2 (3)Rad Monitor Ref (ARP): RE-008 RA2 (2)RE-002/0035 ARE-2532 A/BARE-2533 A/BAnnunciator Response Procedure (Control Room) RA3 (1)6

Reference:

RE-001Annunciator Response Procedure (SFP Level) RU2 (1)a7 ReferenceAnnunciator Display: ALB05 E02 (SFP Lo Level)Radiation Monitor Information: RE-008 RU2 (1)bRE-002RE-0038 RE-004RE-005RE-006RE-001 1 ____RVLIS Indications/Displays (RVLIS) CG1 (1)a9CS1 (1)b (2)bCAl (1)Calc X6CNA5 15___Containment Sump/Reactor Coolant Drain Tank CG 1 (2)b10 (RCDT)/Waste Holdup Tank (WHiT) references (FSAR) CS 1 (3)b10CA1 (2)b_____CU1 (2)b2/22/2016Page 1 of 2 Vogtle EAL V&V Documentation IndexV&V# Description IC ThresholdH-2 Concentration (> 6%) -calculation/reference CG 1 (1)b (2)cCalc X6CNA 15 CB PL4B CB PL4BContainment Pressure

Reference:

CG1 (1)b (2)c12 > 13 psig with Containment Closure established> 52 psig with TS Containment Integrity IntactCale X6CNAJ15Emergency Buses Drawing CA2 (1)CU2 (1)aSG1 (1)a13 SG8 (1)aSS1 (1)SA1 (1)a____SU1 (1)DC System Information CU4 (1)14 SG8 (1)b______ ___________________________________ SS58 (1)15 ISFSI TS/Dose Reading Calculation E-HUI1 (1)Caic X6CNA 15CSFST Procedure FCB PL1A FCB PLIARCSB PL1B RCSBPL1 BFCB L2A FCB L2AFCB PL2A FCB PL2AFCB PL2B FCB PL2B16 RCSB PL2A RCSBPL2ACB PL2A CB PL2ACB PL4A CB PL4ACB PL4C.1 CB PL4C.1SG1 (1)bSS5 (1)cSeismic Indications/Alarms (OBE) HU2 (1)17 Seismic Monitoring System indications/Alarm ______Rad Monitor Calculation: RE-48000 SU3 (1)18 Calc X6CNA14 V7 (pg 9)19 RCS Sample Activity SU3 (2)TS 3.4.16RCS Operational LeakageSU(1(220 54()2TS 3.4.1321 Containment Pressure Reference (52 psig) SU7 (2)a2/22/ 20 16Page 2 of 2 VlPage 1 of 1Definitions1.1Table 1.1-1 (page 1 of 1)MODES% RATEDAVERAGEREACTVITY THERMAL REACTOR COOLANTCONDTIO POWER(a) TEMPERATURE(0F)1 Power Operation _> 0.99 > 5 NA2 Startup s 5 NA3 Hot Standby < 0.99 NA > 3504 Hot Shutdown(b) < 0.99 NA 350 > Tavg > 2005 Cold Shutdown(b) < 0.99 NA _< 2006 Ref ueling(C) NA NA NA(a)(b)(c)Excluding decay heat.All reactor vessel head closure bolts fully tensioned.One or more reactor vessel head closure bolts less than fully tensioned.Vogtle Units 1 and 21,.1-7Amendment No. 96 (Unit 1)Amendment No. 74 (Unit 2)

V2See NL-1 5-1 898Enclosure 3SOUTHERN A-L ~ .a I.?Southern Nuclear Design CalculationCalculation Number: )(6cNA1 5Plant:lVocat Electric Generatina Plant Unit: 0] 1 0] 2 ix] 1 & 2 IDisci~line:i MechanicalTitle: NEI 99-01 Rev 6 EAL Calculations

Subject:

EmergencyIAction Level SetpointsPurpose)I Objective: ..... ...,,,...Document Emergency Action Level Values to support conversion to NEI 99-01 Rev 6System or Equipment Tag Numbers:NtAContentsTopic Page Attachments .. .. # of(Computer Printouts. Technical Papers, Sketches. PagesCorrespondence)Purpose .....1 A -SNC EP Concurrence ...1Criteria ........... B B- Reserved 0Conclusion -3 'C -"References' from X6CNAI4 31Design Inputs -6 D -"TEDE and Thyroid CDE Calculations 19Assumptions ..... 18 E -Shielding Calculations 29References 22 F -Evaluation of 52 psig Pressure on Mechanical 14Penetrations____Method of Solutions 26 G -References"'from X6CNA16 22Body of Calculation 31 "H -VEGP 1 EAL Thresholds 7I -VE'GP 2 EAL Thresholds ...7_____J' Reviewer Altern'ate Calculation ...11....K -SNCO024-CALC-:005 Vogtle EALs RA1_____ thresholds to address NEI 99-01 rev 6 1.....______ ___ L -SNC024-CALC-004 VEGP" EAL for IC E-HU1 16Total # of Pagesincluding cover sheet & 22AttachmentsNuclear Quality Level0 [ Safety-Related IXI .. Safety Significant ....03 Non- Safety --Significant 'Version RecordViinOriginator Reviewer Approval 'I "APproval 2INo.t Description j ZW .Io.jMAIIoI I ICalculation of EAL Thresholdsto support NEI 99-01 Rev. 6Guidance.1.0~j4~ADC3~t /2--i i~k.~~1iA4INMP-ES-039-F01 V4,0 M-S-3-ONMP-ES-039-001 V3Page 1 of 1VEGP ODCMFigure 4-1. Terrestrial Stations Near Site Boundary4-164-16 VER 30 V4Page 1 of 3-5-rIn Its letter dated July 17, 2013, the licensee stated, in part, thatLevel 1 Is established as the SFP cooling system low level set paint of 21 T-0",which is above the elevation at the top of the fuel pool cooling system suction linethat is at approximately 21 4-1 1". Two trains supply Unit 1 and Unit 2 spent fuelpool cooling water. When adjusted for saturated steam conditions, the pool levelneeded to meet the NPSH required Is 214"-6" for Train A and 219'-6" for Train Bbut only one train is required for operation. Thus, the two points described in NEI12-02 for loss of NPSH for the VEGP Spent Fuel Pool are 214'-1 1 -and 21 4'-6"and the HIGHER of the two Is 214'-I1 .However, VEGP conservatively selectsLevel 1 as 217'-0" since it is the normal low level set point for the SFP Coolingsystem.The NRC staff notes that Level 1 at 217 ft. 0 in. Is adequate for normal SFP cooling systemoperation; it is also sufficient for Net Positive Suction Head (NPSH) and represents the higher ofthe two points described above.NEi 12-02 states, in part, thatLevel 2 represents the range of water level where any necessary operations inthe vicinity of the spent fuel pool can be completed without significant doseconsequences from direct gamma radiation from the stored spent fuel. Level 2 isbased on either of the following:* 10 feet (+1- 1 foot) above the highest point of any fuel rack seated in thespent fuel pools, or* a designated level that provides adequate radiation shielding to maintainpersonnel radiological dose levels within acceptable limits while performinglocal operations in the vicinity of the pool. ThIs level shall be based on eitherplant-specific or appropriate generic shielding calculations, considering theemergency conditions that may apply at the time and the scope of necessarylocal operations, including installation of portable SFP instrument channelcomponents.FIn its OIP, the licensee stated that Level 2 would be set at a plant elevation 203 ft. 9-1/8 in.,which is approximately 10 ft. above the highest point of the fuel racks for both units at elevation193 ft. 9-1/8 in.In its letter dated July 17, 2013, the licensee provided a sketch depicting elevations Identified asLevel 1,2 and 3, the level measurement range and the top of the tallest fuel storage rack. TheNRC staff notes that Level 2 at an elevation of 20,3 ft. 9-1/8 in. is approximately 10 ft. above thetop of the fuel rack. The staff also notes that the licensee designated Level 2 using the first ofthe two options described in NEI 12-02 for Level 2.NEi 12-02 states, in part, thatLevel 3 corresponds nominally (i.e., +/- 1 foot) to the highest point of any fuelrack seated in the spent fuel pool. Level 3 is defined in this manner to providethe maximum range of information to operators, decision makers and emergencyresponse personnel.

V4Page 2 of 3-6-The licensee stated In its OIP that Level 3 would be set at plant elevation 193 ft. 9-118 in., whichis the nominal level of the highest fuel rack.In its letter dated July 17, 2013, the licensee provided a sketch depicting elevations identified asLevel 1, 2 and 3, the level measurement range and the top of the tallest fuel storage rack. TheNRC staff notes that Level 3 at an elevation of 193 ft. 9-1/8 in. as the highest point of any spentfuel storage rack seatd in the SFP.The licensee's proposed plan, with respect to identification of Levels 1, 2, and 3, appears to beconsistent with NEI 12-02, as endorsed by the ISG.3.3 Design Feature~s: InstrumentsAttachment 2 of Order EA-1 2-051, states, in part, thatThe instrumentation shall consist of a permanent, fixed primary instrumentchannel and a backup instrument channel. The backup instrument channel maybe fixed or portable. Portable instruments shall have capabilities that enhancethe ability of trained personnel to monitor spent fuel pool water level underconditions that restrict direct personnel access to the pool, such as partialstructural damage, high radiation levels, or heat and humidity from a boiling pool.NEI 12-02 states, in part, thatA spent fuel pool level instrument channel is considered reliable when theinstrument channel satisfies the design elements listed in Section 3[instrumentation Design Features] of this guidance and the plant operator hasfully implemented the programmatic features listed in Section 4 [ProgramFeatures].In its OIP, the licensee stated that, for both Unit 1 and Unit 2, the primary and backupinstrument channels will consist of fixed components. The licensee also stated that themeasured range will be continuous fromn the high pool level elevation of 219 ft. 0 in. to thetop of the spent fuel racks at elevation 193 ft. 9-1/8 in.In Its letter dated July 17, 2013, the licensee provided a sketch depicting elevations identified asLevel 1, 2 and 3 and the level measurement range. The NRC staff reviewed this sketch andnotes that there is a slight variation on the measurement range identified in the licensee's OIPand on this sketch. In its OIP, the licensee stated that the measurement range would go frompool elevation of 219 ft. 0 in. to 193 9-118 in. However, the sketch shows the range goes frompool elevation of 219 ft. 3 in. to 194 ft. 1/8 in. The staff has identified this request as:RAl #1Please identify the final SFP level instrumentation measurement range.The licensee's proposed plan, with respect to the number of channels and the range of theinstrumentation for both of its SF Ps, appears to be consistent with NEI 12-02, as endorsed bythe ISG. to NL-1 3-1 460ATTACHMAENT 1SKETCH IN RESPONSE TO RAI ITEM 1 .b---EL. 220'"S= TOP OP SFP OUR ---EL, 216'-6" NOLLVL-EL, 2t7'-O" LOW LEVEL ALARI--*EL. 214-t!1" TOP OP SUTION LIIE-EL. ! 79' 1/2 ! BOu lTTOMkNOTES EILEVATIONIS 40W ARE FOR BOTH UNITS V5Page 1 ofl15Aproe B Pat Procedure VersionS. E. Prewitt .....Elcti. neain 17100-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88ANNUNCIATOR RESPONSE INDEXDETECTOR NO.1 -RE-Q0011 -RE-00021 -RE-0003I -RE-00041 -RE-00051 -RE-0006A-RE-0007AA-RE-0007B1I-RE-0008A-RE-0009AA-RE-0009BA-RE-0009C1-RE-00l111 -RE-0013A-RE-0014A-RE-001 61-RE-0017A1 -RE-001 7B1 -RE-001 81 -RE-001 91 -RE-0020A1 -RE-0020B1 -RE-00211 -RE-0024A1 -RE-0024BA-RE-0025RADIATION MONITOR INDEXUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeRad Chem LabSample RoomFuel Handling BldgDecon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)Seal Table RoomWaste Gas ProcessingWaste Gas ProcessingBoron Recycle LiquidCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected Cubical-RadiogasAux Steam Condensate Return LiquidPAGE9101214**16182022242628313335* Safety Related. Go to 17102-1, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.**Passive collector. No electronic components.Printed February 3, 2016 at 13:02 V5Page 2 of 15AproegBt~6 Gnrating LA Procedure VersionApoeBs. E. Prewitt Vogle Electric Gen Pant 17100-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND jPage Number12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 7 of 88ANNUNCIATOR RESPONSE INDEXRADIATION MONITOR INDEXDETECTOR NO.1 -RE-0039A1 -RE-0039B1 -RE-07241 -RE-081 01 -RE-08481-RE-1 950A-RE-2532AA-RE-2532 BA-RE-2533AA-RE-2533B1 -RE-2562A1 -RE-2562B1 -RE-2562C1 -RE-2565A1 -RE-2565B1 -RE-2565C1-RE-121161-RE-121 171-RE-I12442A1-RE-i12442 B1-RE-i12442CUSEWaste Gas Decay Tank -RadiogasWaste Gas Compressor & Catalytic Recombiner -RadiogasN16 Rad MonitorSJAE Exhaust Rad MonitorTurbine Bldg Drains -LiquidACCW -LiquidFHB -RadiogasFHB -RadiogasFHB -RadiogasFHB -RadiogasContainment -Air ParticulateContainment -Passive Iodine CartridgeContainment Air -RadiogasContainment Vent -ParticulateContainment Vent -IodineContainment Vent -RadiogasControl Room Air In -Train AControl Room Air In -Train BPlant Vent Air Particulate (Low Range)Plant Vent Iodine Particulate (Low Range)Plant Vent Radiogas Particulate (Low Range)PAGE384042454850545658606264* Safety Related. Go to 17102-1, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.**Passive collector. No electronic components.Printed February 3, 2016 at 13:02 V5Page 3 of 15Approved By Votl Electric Geeatn Plant Procedure VersionS. E. Prewitt vog.e ....e..... 171 00-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 14 of 88ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEIncrease in radiation level near Unit 1 Spent Fuel PcBuilding.2.0 AUTOMATIC ACTIONSOn the south wall of the Fuel Handling Building Speldoor:a. Alarm horn on 1-RA-0008 sounds.b. Strobe light on 1-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.1 -RE-0008(High)in the Fuel Handlingnt Fuel Pool Room near thePrinted February 3, 2016 at 13:02 V5Page 4 of 15Approved By VersionJ.B SaneyVogtle Electric Generating Plant 11212.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 8 of 42ANNUNCIATOR RESPONSE INDEXSRDCWIDWN. TITLE PAGEAlA2A3A4A5 1-RE-2562A CNMT AIR -PARTICLES 10A6 1-RE-2562C CNMT AIR -GAS 12A7A8B1 1-RE-13119 MSL Gas 15B2 1-RE-13120 MSL Gas 17B3 1 -RE-0002 AREA 19B4 1-RE-0005 High Range -Area 21B5 1-RE-12116 In-Vent Gas 23B6 A-RE-2532A In-Vent Gas 25B7 A-RE-2532B In-Vent Gas 27B8C1 1-RE-13121 MSL Gas 29C2 1-RE-i131 22 MSL Gas 31C3 1 -RE-0003 AREA 33C4 1-RE-0006 High Range Area 35CS 1-RE-12117 In-Vent Gas 37C6 A-RE-2533A In-Vent Gas 39C7 A-RE-2533B In-Vent Gas 41Printed February 3, 2016 at 13:11 V5Page 5 of 15Approved By "' Electri Geea PlantPrcdeVrsoJ.B. Stanley VogUe Generting Procedure 20.4ioEffective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 19 of 42WINDOW CDCA B3ORIGINContainment LowRange Area Monitor1 -RE-0002SETPOI NTAs determinedby Chemistry(15 mR/hr duringrefueling)1 -RE-0002(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSEi NOTES* During refueling operations indicates a fuel drop accident. EJ* During power operation indicates possible loss of coolant accident. 0]2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 13:11 V5Page 6 of 15Appove ByGeeraing , Procedure VersionJ...tnlyvo .Ele tri ..... -...a.n...... 17102-1 20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY IPage Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 j 25 of 42WINDOW CDCA B6ORIGINFuel HandlingBuilding EffluentRadiogas MonitorARE-2532ASETPOINTAs determinedby ChemistryDepartment(RED LAMP LIT)(HIGH)]1.0PROBABLE CAUSE2.01. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.AUTOMATIC ACTIONSSwitches the Normal Fuel Handling Building Ventilation to Accident ModeVentilation.INITIAL OPERATOR ACTIONS3.0Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5Page 7 of 15Approved By lcti Pat Procedure VersionJ.B. Stanley vgeGnrtn 112I2.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 27 of 42WINDOW CDCA B7ORIGIN SETPOINT_________[A- RE-2532BFuel Handling As determined I(RED LAMP LIT)Building Effluent by Chemistry j(HIGH)Radiogas Monitor DepartmentIARE-2532BL_________NOTEFor other than HIGH conditions see Pages 5 and 6. 0]1.0 PROBABLE CAUSE1. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.2.0 AUTOMATIC ACTIONSSwitches the Normal Fuel Handling Building Ventilation to Accident ModeVentilation.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5Page 8 of 15Approved By ..... E lectric GnrngPlant IPrcdeVrsoJ.B. Stanley Vogtle Generatingre17102.1 Veso20.4Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY IPage Number06/23/20 14 IRELATED DISPLAY CONSOLE QRM2 j 33 of 42WINDOW CDCA C3ORIGINContainment LowRange Area Monitor1 -RE-0003SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)1 -RE-0003(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. EJ* During power operation indicates possible loss of coolant accident. o]2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 13:11 V5Page 9 of 15Approved: 8yiGenerating an Procedure VersionJ.B. Stanley vog,_e ElectricPat-._ 212.Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 39 of 42WINDOW CDCA C6ORIGINFuel HandlingBuilding EffluentRadiogas MonitorARE-2533ASETPOINTAs determinedby ChemistryDepartmentSA-RE-2533A(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSE1. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.AUTOMATIC ACTIONS2.0Switches the Normal Fuel Handling Building Ventilation to Accident ModeVentilation.INITIAL OPERATOR ACTIONS3.0Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5Page 10 of 15Approved By Gene rating anrceueVesoJ.B. Stanley Vogtle Electric Plant I Procedure 20.4ioEffective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY P age Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 41 of 42WINDOW CDCA C7ORIGINFuel HandlingBuilding EffluentRadiogas MonitorARE-2533BSETPOINTAs determinedby ChemistryDepartment(RED LAMP LIT)(HIGH)11.0PROBABLE CAUSE2.01. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.AUTOMATIC ACTIONSSwitches the Normal Fuel Handling Building Ventilation to Accident ModeVentilation.INITIAL OPERATOR ACTIONS3.0Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5Page 11 of 15ApproveVBytle Electric Gnrtg Plant AIProcedure VersionS. E. Prewitt ....g.e.Generat.ng.. 17100-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 77ANNUNCIATOR RESPONSE INDEXRADIATION MONITOR INDEXDETECTOR NO.2-RE-000 12-RE-00022-RE-00032-RE-00042-RE-OD052-RE-00062-RE-00082-RE-DO0112-RE-001 32-RE-001 7A2-RE-D01 7B2-RE-D01 82-RE-DO0192-RE-0020A2-RE-0020B2-RE-002 12-RE-0024A2-RE-0024B2-R E-0039A2-RE-0039B2-RE-0039C2-R E-0 7242-RE-081 02-RE-08482-RE-i19502-R E-2562AUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeFuel Handling BldgSeal Table RoomWaste Gas ProcessingCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air Pa rticu lateSelected CubicaI-RadiogasWaste Gas Decay Tank -RadiogasWaste Gas Compressor -RadiogasCatalytic Recombiner -RadiogasN16 MonitorSJAE Exhaust Rad MonitorTurbine Bldg Drains -LiquidACCW -LiquidContainment -Air ParticulatePAGE891113151719212326283033353739424547* Safety Related. Go to 17102-2, "ARP For The SRDC QRM2"** Not Functional -Detectors Removed.Passive collector. No electronic components.Printed February 3, 2016 at 13:22 V5Page 12 of 15Approved BYs E.Genratigitt Procedure VersionS...E.... ..w... .....t.e Electric..... Plant. ..... 17100-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/10/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 11 of 77ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEIncrease in radiation level near Unit 2 Spent Fuel PcBuilding.2.0 AUTOMATIC ACTIONSOn the south wall of the Fuel Handling Building Speldoor:a. Alarm horn on 2-RA-0008 sounds.b. Strobe light on 2-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.2-RE-0008(High)in the Fuel Handlingnt Fuel Pool Room near thePrinted February 3, 2016 at 13:22 V5Page 13 of 15Approve.By.... Plant Procedure VersionJ. B. Stanley voteEeti ~nrtn in 17102-2 16.3Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 8 of 34ANNUNCIATOR RESPONSE INDEXSRDC TTEPGWINDOW NO. TTEPGAlA2A3A4A5 2-RE-2562A CNMT AIR -PARTICLES 10A6 2-RE-2562C CNMT AIR -GAS 12A7A8B1 2-RE-13119 MSL Gas 15B2 2-RE-I13120 MSL Gas 17B3 2-RE-0002 AREA 19B4 2-RE-0005 High Range -Area 21B5 2-RE-121 16 In-Vent Gas 23B6B7B8Cl 2-RE-13121 MSL Gas 25C2 2-RE-i13122 MSL Gas 27C3 2-RE-0003 AREA 29C4 2-RE-0006 High Range Area 31C5 2-RE-12117 In-Vent Gas 33C6C7Printed February 3, 2016 at 13:28 V5Page 14 of 15Approved By V .. ...... .Procedure VersionJ. B. Stanley v ogtue Electric Generating Plant ~ 17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 19 of 34WINDOW CDCA B3ORIGINContainment LowRange Area Monitor2-RE-0002SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)[2-RE-0002(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. E* During power operation indicates possible loss of coolant accident. [2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 13:28 V5Page 15 of 15Approved By Genrain AIProcedure VersionJ. B. Stanley Vogtle Electric eertn Plant -17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 RELATED DISPLAY CONSOLE QRM2 29 of 34WINDOW CDCA C3ORIGINContainment LowRange Area Monitor2-RE-0003SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)2-RE-0003(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. [L* During power operation indicates possible loss of coolant accident.2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.pt'rinted -ebruary 3, 2016 at 13:28 V6Page 1 of 4Approved By _ ~Procedure VersionS. E. Prewitt Vogtle Elcri enerating Pln1i17100-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88ANNUNCIATOR RESPONSE INDEXDETECTOR NO.1 -RE-00011 -RE-00021 -RE-00031 -RE-00041 -RE-00051 -RE-0006A-RE-0007AA-RE-0007B1 -RE-Q008A-RE-0009AA-RE-0009BA-RE-0009C1-RE-00l111-RE-0013A-R E-001 4A-RE-001 61 -RE-001 7A1-RE-0017B1-RE-001 81-RE-001 91 -RE-0020A1 -RE-0020B1 -RE-00211 -RE-0024A1 -RE-0024BA-RE-0025RADIATION MONITOR INDEXUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeRad Chem LabSample RoomFuel Handling BldgDecon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)Seal Table RoomWaste Gas ProcessingWaste Gas ProcessingBoron Recycle LiquidCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected CubicaI-RadiogasAux Steam Condensate Return LiquidPAGE910121416182022242628313335* Safety Related. Go to 17102-1, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.Passive collector. No electronic components.Printed February 3, 2016 at 14:28 V6Page 2 of 4Approved By Ge ti IProcedure VersionS. E. Prewitt v .g.e Elcti.Gneain.Pat 17100-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 9 of 88ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEDeteriorating radiological conditions in the Control F2.0 AUTOMATIC ACTIONSNONE3.0 INITIAL OPERATOR ACTIONSNONE4.0 SUBSEQUENT OPERATOR ACTIONS1. Request Health Physics to survey Control Rilevel.2. Obtain detector trend data per 13508-1, "Ra3. Refer to NMP-EP-1 10, "Emergency ClassificInstructions".4. Monitor the channel for further changes.5* IF sampling and analysis determine the chanrequest Chemistry to deactivate the channel5.0 COMPENSATORY OPERATOR ACTIONSNONEEND OF SUB-PROCEDURE

REFERENCES:

AX4DB206-2, 1X5DS2A02(High)toom.oom area to verify radiationdiation Monitoring System".*ation And Implementingreel has malfunctioned,Printed February 3, 2016 at 14:28 V6Page 3 of 4Approveds EPrwtBY Generating.. ...... Procedure170 .Version2 1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 6 of 77ANNUNCIATOR RESPONSE INDEXDETECTOR NO.2-RE-00012-R E-00022-R E-00032-RE-00042-RE-00052-RE-00062-R E-00082-RE-0011I2-RE-001 32-RE-001 7A2-RE-001 7B2-RE-001 82-RE-001 92-RE-0020A2-RE-0020B2-R E-002 12-R E-0024A2-RE-0024B2-R E-0039A2-RE-0039B2-RE-0039C2-RE-07242-RE-081 02-R E-0 8482-RE-I19502-R E-2562ARADIATION MONITOR INDEXUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeFuel Handling BldgSeal Table RoomWaste Gas ProcessingCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected CubicaI-RadiogasWaste Gas Decay Tank -RadiogasWaste Gas Compressor -RadiogasCatalytic Recombiner -RadiogasN16 MonitorSJAE Exhaust Rad MonitorTurbine Bldg Drains -LiquidACCW -LiquidContainment -Air ParticulatePAGE891113151719212326283033353739424547* Safety Related. Go to 171 02-2, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.Passive collector. No electronic components.Printed February 3, 2016 at 14:32 V6Page 4 of 4Approved By * ...Procedure VersionS. E. Prewitt Vogtle Electri c Generating Plant E. I171 00-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 8 of 77ORIGIN SETPOINT_________2-RE-0001Area Monitor As determined by (High)Chemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5. 0]1.0 PROBABLE CAUSEDeteriorating radiological conditions in the Control Room.2.0 AUTOMATIC ACTIONSNONE3.0 INITIAL OPERATOR ACTIONSNONE4.0 SUBSEQUENT OPERATOR ACTIONS1. Request Health Physics to survey Control Room area to verify radiationlevel.2. Obtain detector trend data per 13508-2, "Radiation Monitoring System".3. Refer to NMP-EP-1 10, "Emergency Classification And ImplementingInstructions".4. Monitor the channel for further changes.5. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.5.0 COMPENSATORY OPERATOR ACTIONSNONEEND OF SUB-PROCEDURE

REFERENCES:

AX4DB206-2, 2X5DS2A02Printed February 3, 2016 at 14:32 V7Page 1 of 6Approved By I e eatn Procedure VersionC. H. Willijams, Jr. j Vogtle Electric GeeaigPlant I10513.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 IPANEL 1A2 ON MCB I 3 of 67(1 )(2'i(3'i(4'lABCDEFLIQUID PROCESS NSSS FHB EXH NIS GROUP 1 SPENT FUELPANEL TROUBLE PROT GR I RAD MONITOR CHANNEL I MONITOR LIGHT PIT HI TEMPBYPASS EQUIP TROUBLE BYPASS COMP OFF NORMGAS PROCESS NSSS INTMD NIS GROUP 2 BYPASS CNMTPANEL TROUBLE PROT GR II RADIATION CHANNEL II MONITOR LIGHT VENT ISOBYPASS ALARM BYPASS COMP OFF NORM HI RAD TESTBORON RECYCLE NSSS HIGH NIS GROUP 3 SAFEGUARDS CABPANEL TROUBLE PROT GR III RADIATION CHANNEL 111 MONITOR LIGHT TRAIN ABYPASS ALARM BYPASS COMP OFF NORM TESTPCS CABINET NSSS NIS GROUP 4 SAFEGUARDS CABDOORS OPEN PROT GR IV CHANNEL IV MONITOR LIGHT TRAIN BBYPASS BYPASS COMP OFF NORM TESTPCS CABINETS SPENT FUEL PIT ANNUNCIATOR AMSAC GROUP 5 PROT SYSTEMPWR SUPPLY LO LEVEL DC SOURCE TROUBLE MONITOR LIGHT TRAIN AFAILURE SUPPLY FAILURE COMP OFF NORM TROUBLEPROCESS PROT SPENT FUEL ANNUNCIATOR ANNUNCIATOR ANNUNCIATOR PROT SYSTEMSET VIOLATED PIT HI LEVEL SYSTEM DC SYSTEM ON SYSTEM TRAIN B>1 DOOR OPEN SUPPLY FAILURE ALTN SUPPLY DC GROUND TROUBLEPrinted February 2, 2016 at 16:24Printed February 2, 2016 at 16:24 V7Page 2 of 6Approved By .............. l l rcGenerating Plroedr VrsoC. H. Williams, Jr. PrtoEecredPanure100- 34.2ioEffective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 PANEL 1A2 ON MCB5of6ANNUNCIATORWINDOW NO.E01E02E03E04EQ5E06F0 1F02F03F04F05F06TITLEPCS CABINETS PWR SUPPLY FAILURESPENT FUEL PIT LO LEVELANNUNCIATOR DC SOURCE SUPPLY FAILUREAMSAC TROUBLEGROUP 5 MONITOR LIGHT COMP OFF NORMPROT SYSTEM TRAIN A TROUBLEPROCESS PROT SET VIOLATED >1 DOOR OPENSPENT FUEL PIT HI LEVELANNUNCIATOR SYSTEM DC SUPPLY FAILUREANNUNCIATOR SYSTEM ON ALTN SUPPLYANNUNCIATOR SYSTEM DC GROUNDPROT SYSTEM TRAIN B TROUBLEPAGE414346475253565761626365Printed February 2, 2016 at 16:24 V7Page 3 of 6Approved By og e ProcedurerVersionC. H. Williams, Jr. Vo e Eetric ~.ireaigPant Pr17005-1 34.2ioEffective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 PANEL 1A2 ON MOB I 43 of 67WINDOW E02ORIGIN SETPOINT_________SPENT FUEL PIT1-LSHL-625 217 feet elevation LO LEVEL1.0 PROBABLE CAUSE1. Insufficient inventory during filling or refueling operation.2. Normal evaporation.3. System leak.4. Loss of air to the Fuel Transfer Canal and/or Cask Loading Pit GateSeals.2.0 AUTOMATIC ACTIONSNONE3.0 INITIAL OPERATOR ACTIONSNONEPrinted February 2, 2016 at 16:24 V7Page 4 of 6Approved BYc H. ElectricPlant I Procedure VersionC. H.W..l.m...J .....e.eneatig 17005-2 28.1Effective Date jANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 IPANEL 2A2 ON MCB I 3 of 65(1)(2)(3)(4)(5)(6)ABCDEFLIQUID PROCESS NSSS NIS GROUP 1 SPENT FUELPANEL TROUBLE PROT GR ! CHANNEL I MONITOR LIGHT PIT HI TEMPBYPASS BYPASS COMP OFF NORMGAS PROCESS NSSS INTMD NIS GROUP 2 BYPASS CNMTPANEL TROUBLE PROT GR II RADIATION CHANNEL II MONITOR LIGHT VENT ISOBYPASS ALARM BYPASS COMP OFF NORM HI RAD TESTNSSS HIGH NIS GROUP 3 SAFEGUARDS CABPROT GR III RADIATION CHANNEL MONITOR LIGHT TRAIN ABYPASS ALARM III BYPASS COMP OFF NORM TESTPCS CABINET NSSS NIS GROUP 4 SAFEGUARDS CABDOORS OPEN PROT GR IV CHANNEL IV MONITOR LIGHT TRAIN BBYPASS BYPASS COMP OFF NORM TESTPCS CABINETS SPENT FUEL PIT ANNUNCIATOR AMSAC GROUP 5 PROT SYSTEMPWR SUPPLY LO LEVEL DC SOURCE TROUBLE MONITOR LIGHT TRAIN AFAILURE SUPPLY FAILURE COMP OFF NORM TROUBLEPROCESS PROT SPENT FUEL ANNUNCIATOR ANNUNCIATOR ANNUNCIATOR PROT SYSTEMSET VIOLATED PIT HI LEVEL SYSTEM DC SYSTEM ON SYSTEM TRAIN B>1 DOOR OPEN SUPPLY FAILURE ALTN SUPPLY DC GROUND TROUBLEPrinted February 2, 2016 at 16:29 V7Page 5 of 6ANNUNCIATORWINDOW NO.E01E02E03E04E05E06F01IF02F03F04F05F06TITLEPCS CABINETS PWR SUPPLY FAILURESPENT FUEL PIT LO LEVELANNUNCIATOR DC SOURCE SUPPLY FAILUREAMSAC TROUBLEGROUP 5 MONITOR LIGHT COMP OFF NORMPROT SYSTEM TRAIN A TROUBLEPROCESS PROT SET VIOLATED >1 DOOR OPENSPENT FUEL PIT HI LEVELANNUNCIATOR SYSTEM DC SUPPLY FAILUREANNUNCIATOR SYSTEM ON ALTN SUPPLYANNUNCIATOR SYSTEM DC GROUNDPROT SYSTEM TRAIN B TROUBLEPAGE394144455051545559606163Printed February 2, 2016 at 16:29 V7Page 6 of 6Apoec. H. Williams,B Jr. i voge Elecltric Pl.. ant Prcdr17005-2 Veso28.1Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 IPANEL 2A2 ON MCB I 41 of 65WINDOW E02ORIGIN SETPOINT_________SPENT FUEL PIT12-LSHL-625 217 feet [LO LEVELelevation [__________1.0 PROBABLE CAUSE1. Insufficient inventory during filling or refueling operation.2. Normal evaporation.3. System leak.4. Loss of air to the Fuel Transfer Canal and/or Cask Loading Pit GateSeals.2.0 AUTOMATIC ACTIONSNONE3.0 INITIAL OPERATOR ACTIONSNONEPrinted February 2, 2016 at 16:29 V8Page 1 of 18ApprvedBygtle Procedure VersionS. E. Prewitt .....e.E..ectric Generating Plant...... ...... .. 171 00-1 26.2....Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88ANNUNCIATOR RESPONSE INDEXDETECTOR NO.1 -RE-00011 -RE-00021 -RE-00031 -RE-00041 -RE-00051 -RE-0006A-RE-0007AA-RE-0007B1 -RE-0008A-RE-0009AA-RE-0009BA-RE-0009C1-R E-0011I1-RE-0013A-RE-001 4A-RE-001 61 -RE-001 7A1 -R E-0017B1 -RE-00181-RE-00191 -RE-0020A1 -RE-0020B1 -RE-00211 -RE-0024A1 -RE-0024BA-R E-0025RADIATION MONITOR INDEXUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeRad Chem LabSample RoomFuel Handling BldgDecon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)Seal Table RoomWaste Gas ProcessingWaste Gas ProcessingBoron Recycle LiquidCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected CubicaI-RadiogasAux Steam Condensate Return LiquidPAGE9101214**k"**161820**k22242628313335* Safety Related. Go to 17102-1, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.Passive collector. No electronic components.Printed February 3, 2016 at 14:52 V8Page 2 of 18Approved By ... W r'lUl VersionS. E. Prewitt vou lcrcPat -171 00-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 10 of 88ORIGIN SETPOINTArea Monitor As determined byChemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5.1 -RE-0004(High)1.02.03.04.0PROBABLE CAUSEIncrease in radiation level in the Containment Personnel Access Hatch.AUTOMATIC ACTIONSOutside the containment near the hatch:a. Alarm horn on 1-RA-0004 sounds,b. Strobe light on 1-RA-0004 blinks.INITIAL OPERATOR ACTIONSNONESUBSEQUENT OPERATOR ACTIONS1. Check for elevated radiation level in containment at 1 -RE-0002 and1-RE-0003 at the SRDC.2. IF alarm is valid, warn personnel in containment to exit by way of theemergency escape hatchway.3. Notify Health Physics of the alarm and request survey of ContainmentPersonnel Access Hatch.4. Obtain detector trend data per 13508-1, "Radiation Monitoring System".5. Monitor the channel for further changes.6. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.Printed February 3, 2016 at 14:52 V8Page 3 of 18AE.Pproedit Byle Electric Geert Plant IProcedure Veso1S.E rwt oge ~ nrugI171 00-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 112/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 14 of 88ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEIncrease in radiation level near Unit 1 Spent Fuel PcBuilding.2.0 AUTOMATIC ACTIONSOn the south wall of the Fuel Handling Building Spedoor:a. Alarm horn on I-RA-0008 sounds.b. Strobe light on I -RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.1 -RE-0008(High))ol in the Fuel Handlingnt Fuel Pool Room near thePrinted February 3, 2016 at 14:52 V8Page 4 of 18Approved By VersionS. E. Prewitt ....Vogtle Electric Generating Plant 11012.Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 16 of 88ORIGIN SETPOINT_________1-RE-001 1Area Monitor As determined by (High)"Chemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5. 0]1.0 PROBABLE CAUSEIncrease in radiation level in the Seal Table Room on Level B Containment.2.0 AUTOMATIC ACTIONSIn the Incore Instrumentation Room:a. Alarm horn on 1 -RA-0011I sounds.b. Strobe light on 1 -RA-Ol11 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Incore Instrumentation Room.4.0 SUBSEQUENT OPERATOR ACTIONS1. Notify Health Physics to determine the cause of the high radioactivitylevel.2. Restrict personnel access to the seal table area until the condition hasbeen corrected.3. Obtain detector trend data per 13508-1, "Radiation Monitoring Systems".4. Monitor the channel for further changes.5. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.Printed February 3, 2016 at 14:52 V8Page 5 of 18Approved By

• lcri ln Procedure VersionJ.B. Stanley , Vogtle EetcGenerating Plnt17102-1 20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETW Page Number06/23/20 14 RELATED DISPLAY CONSOLE QRM2 8 of 42ANNUNCIATOR RESPONSE INDEXSRDCWINDOW NO.AlA2A3TITLEPAGEA4A5A6A7A8B1B283B4B5B6B7B88ClC2C3C4C5C6C71-RE-2562A CNMT AIR -PARTICLES1-RE-2562C CNMT AIR -GAS10121-RE-I13119 MSL Gas1-RE-I131 20 MSL Gas1 -RE-0002 AREA1-RE-0005 High Range -Area1-RE-12116 In-Vent GasA-RE-2532A In-Vent GasA-RE-2532B In-Vent Gas1-RE-i13121 MSL Gas1-RE-I131 22 MSL Gas1 -RE-0003 AREA1-RE-0006 High Range Area1-RE-i12117 In-Vent GasA-RE-2533A In-Vent GasA-RE-2533B In-Vent Gas1517192123252729313335373941Printed February 3, 2016 at 15:08 V8Page 6 of 18AprvdB lcti ln rocedure VersionJ.B. Stanley I vge ~ nrin 112I2.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 19 of 42WINDOW CDCA B3ORIGINContainment LowRange Area Monitor1 -RE-0002SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)1 -RE-0002(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. 0* During power operation indicates possible loss of coolant accident. []2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR, IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 15:08 V8Page 7 of 18Approved By ElcrcPat AProcedure VersionJ.B. Stanley .... ...g.....e. Generating. ..... .... .. ...17102-1 20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 33 of 42ORIGINContainment LowRange Area Monitor1 -RE-0003SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)WINDOW CDCA C31 -RE-0003(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. 0]* During power operation indicates possible loss of coolant accident. 0]High radiation in the Containment Building.AUTOMATIC ACTIONS2.0Initiates Containment Building Ventilation isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 15:08 V8Page 8 of 18AprvdBj.B. Stanley ....Vogtle Electric nraigPlant Prceur171 02-1 Veso20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/20 14 RELATED DISPLAY CONSOLE QRM2 I 21 of 42WINDOW CDCA B4ORIGINContainment HighRange Area Monitor1 -RE-0005SETPOINT100 R/hr1 -RE-0005(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSE2.0High radiation in Containment.AUTOMATIC ACTIONSNONEINITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm and sample Containmentatmosphere. if required, initiate evacuation of Containment.Printed February 3, 2016 at 15:08 V8Page 9 of 18Approved BY.B GeneraingyA P rc~edure Version1J.B...Stanley..vogt.e Electric Plant.... ...... ...17102-1 20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 106/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 35 of 42WINDOW CDCA C4ORIGINSETPOINTContainment HighRange Area Monitor1 -RE-0006100 R/hr1 -RE-0006(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSE2.0High radiation in the Containment.AUTOMATIC ACTIONSNONEINITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm and sample Containmentatmosphere. if required, initiate evacuation of Containment.Printed February 3, 2016 at 15:08 V8Page 10 of 18Procedure Version17100-2 20.1nber6 of 77ANNUNCIATOR RESPONSE INDEXRADIATION MONITOR INDEXDETECTOR NO.2-R E-000 12-RE-00022-RE-00032-RE-00042-RE-00052-R E-00062-RE-00082-RE-0011I2-RE-001 32-RE-001 7A2-RE-001 7B2-RE-001 82-RE-001 92-R E-0020A2-R E-0020 B2-R E-002 12-R E-0024A2-RE-0024B2-RE-0039A2-RE-0039B2-RE-0039C2-RE-07242-RE-081 02-RE-08482-RE-I19502-R E-2562AUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeFuel Handling BldgSeal Table RoomWaste Gas ProcessingCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected CubicaI-RadiogasWaste Gas Decay Tank -RadiogasWaste Gas Compressor -RadiogasCatalytic Recombiner -RadiogasN16 MonitorSJAE Exhaust Rad MonitorTurbine Bldg Drains -LiquidACCW -LiquidContainment -Air ParticulatePAGE891113151719212326283033353739424547* Safety Related. Go to 171 02-2, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.*** Passive collector. No electronic components.Printed February 3, 2016 at 14:58 V8Page 11 of 18Procedure Version17100-2 20.1Page Number9 of 77ORIGIN SETPOINTArea Monitor As determined byChemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5.2-RE-0004(High)1.02.03.04.0PROBABLE CAUSEIncrease in radiation level in the Containment Personnel Access Hatch.AUTOMATIC ACTIONSOutside the containment near the hatch:a. Alarm horn on 2-RA-0004 sounds.b. Strobe light on 2-RA-0004 blinks.INITIAL OPERATOR ACTIONSNONESUBSEQUENT OPERATOR ACTIONS1. Check for elevated radiation level in containment at 2-RE-0002 and2-RE-0003 at the SRDC.2. IF alarm is valid, warn personnel in containment to exit by way of theemergency escape hatchway.3. Notify Health Physics of the alarm and request survey of ContainmentPersonnel Access Hatch.4. Obtain detector trend data per 13508-2, "Radiation Monitoring System".5. Monitor the channel for further changes.6. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.Printed February 3, 2016 at 14:58 V8Page 12 of 18Approveds EPrwtBY 'og Elect$ric ln Procedure VersionS.E rwt ogi eeaig17100-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 11 of 77ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEIncrease in radiation level near Unit 2 Spent Fuel PcBuilding.2.0 AUTOMATIC ACTIONSOn the south wall of the Fuel Handling Building Spedoor:a. Alarm horn on 2-RA-0008 sounds.b. Strobe light on 2-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.2-RE-0008(High))ol in the Fuel Handlingnt Fuel Pool Room near thePrinted February 3, 2016 at 14:58 V8Page 13 of 18Approveds EPrwtBY .... Gen Procedure VersionS. EPr.......t..Eletr. Generatin Plant ...... 171 00-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number12/10/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 13 of 77ORIGIN SETPOINTArea Monitor As determined byChemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5.2-RE-00l11(High)1.02.03.04.0PROBABLE CAUSEIncrease in radiation level in the Seal Table Room on Level B Containment.AUTOMATIC ACTIONSIn the Incore Instrumentation Room:a. Alarm horn on 2-RA-0011 sounds.b. Strobe light on 2-RA-011I blinks.INITIAL OPERATOR ACTIONSEvacuate the Incore Instrumentation Room.SUBSEQUENT OPERATOR ACTIONS1. Notify Health Physics to determine the cause of the high radioactivitylevel.2. Restrict personnel access to the seal table area until the condition hasbeen corrected.3. Obtain detector trend data per 13508-2, "Radiation Monitoring Systems".4. Monitor the channel for further changes.5. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.Printed February 3, 2016 at 14:58 V8Page 14 of 18Approved By Vogtl Electric GeeaigPlant & Procedure VersionJ. B. Stanley ...eGeertig 17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 RELATED DISPLAY CONSOLE QRM2 I 8 of 34ANNUNCIATOR RESPONSE INDEXSRDC TTEPGWINDOW NO. TTEPGAlA2A3A4A5 2-RE-2562A CNMT AIR -PARTICLES 10A6 2-RE-2562C CNMT AIR -GAS 12A7A881 2-RE-13119 MSL Gas 15B2 2-RE-13120 MSL Gas 17B3 2-RE-0002 AREA 19B4 2-RE-0005 High Range -Area 21B5 2-RE-12116 In-Vent Gas 23B687B88Cl 2-RE-13121 MSL Gas 25C2 2-RE-I131 22 MSL Gas 27C3 2-RE-0003 AREA 29C4 2-RE-0006 High Range Area 31C5 2-RE-12117 In-Vent Gas 33C6C7Printed February 3, 2016 at 15:18 V8Page 15 of 18ApprovedBytric Generating Pln IProcedure VersionJ.pBpStanedy I Vogtle EetiPln -17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 19 of 34WINDOW CDCA B3ORIGINContainment LowRange Area Monitor2-RE-0002SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)2-RE-0002(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident.* During power operation indicates possible loss of coolant accident. LI2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 15:18 V8Page 16 of 18Approved By " 'Eectric GeeaigPlant & Procedure VersionJ. B. Stanley , Vogtle Geertig,17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 RELATED DISPLAY CONSOLE QRM2 29 of 34ORIGINContainment LowRange Area Monitor2-RE-0003SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)WINDOW CDCA C32-RE-0003(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. L* During power operation indicates possible loss of coolant accident. [2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 15:18 V8Page 17 of 18Approvedgtle Electric G~eaigPlantPrcde VrsoApoeJ. B. Stanleyy vog..Geeratng 17102-2Prcr Veso16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 21 of 34WINDOW CDCA B4ORIGINContainment HighRange Area Monitor2-RE-0005SETPOINT100 R/hr2-RE-0005(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSE2.0High radiation in Containment,AUTOMATIC ACTIONSNONEINITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplan nedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm and sample Containmentatmosphere. If required, initiate evacuation of Containment.Printed February 3, 2016 at 15:18 V8Page 18 of 18Approved By vogtle Geneirating nt....17102-2 Verson3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 31 of 34WINDOW CDCA C4ORIGINContainment HighRange Area Monitor2-RE-0006SETPOINT100 R/hr2-RE-0006(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSEHigh radiation in the Containment.AUTOMATIC ACTIONS2.0NONEINITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR if appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm and sample Containmentatmosphere. if required, initiate evacuation of Containment.Printed February 3, 2016 at 15:18 Vogtle Electric Generating 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 4Vogtle EAL Verification and Validation Documents Vogtle EAL V&V Documentation Index.V&V# Description ,. ,,IC IThresholdRCS Modes/Temperatures -TS Reference (Table 1.1-1) EAL Basis Section 1.51 RCS Cold Shutdown Temperature reference (200 °F) CA3 (1)CU3 (1)Radiation Monitor Calculations: RG 1 (1)RE-12839E RSl (1)RE-12444E RA1 (1)Calc X6CNAJ15Radiation Monitor Calculations: RE-0018 RUI (1) (2)RE-0021RE-0848ARE-00142 ~RE- 12839RE-12442CRE-12444CCaic X6CNAJ15Radiation Monitor Calculation: RE-005 CGI1 (2)bRE-006 CS1 (3)bFCB L3A FCB L3ARCSB L3A RCSB L3ACaic X6CNA15 CB PL3A CB PL3AODCM/TS Reference to Site Boundary RG1 (2) (3)3RS 1 (2) (3)RA1 (2) (3) (4)SFP Level 3 & 2 Indications RG2 (1)4 RS2 (1)RA2 (3)Rad Monitor Ref (ARP): RE-008 RA2 (2)RE-002/0035 ARE-2532 A/BARE-2533 A/BAnnunciator Response Procedure (Control Room) RA3 (1)6

Reference:

RE-001Annunciator Response Procedure (SFP Level) RU2 (1)a7 ReferenceAnnunciator Display: ALB05 E02 (SFP Lo Level)Radiation Monitor Information: RE-008 RU2 (1)bRE-002RE-0038 RE-004RE-005RE-006RE-001 1 ____RVLIS Indications/Displays (RVLIS) CG1 (1)a9CS1 (1)b (2)bCAl (1)Calc X6CNA5 15___Containment Sump/Reactor Coolant Drain Tank CG 1 (2)b10 (RCDT)/Waste Holdup Tank (WHiT) references (FSAR) CS 1 (3)b10CA1 (2)b_____CU1 (2)b2/22/2016Page 1 of 2 Vogtle EAL V&V Documentation IndexV&V# Description IC ThresholdH-2 Concentration (> 6%) -calculation/reference CG 1 (1)b (2)cCalc X6CNA 15 CB PL4B CB PL4BContainment Pressure

Reference:

CG1 (1)b (2)c12 > 13 psig with Containment Closure established> 52 psig with TS Containment Integrity IntactCale X6CNAJ15Emergency Buses Drawing CA2 (1)CU2 (1)aSG1 (1)a13 SG8 (1)aSS1 (1)SA1 (1)a____SU1 (1)DC System Information CU4 (1)14 SG8 (1)b______ ___________________________________ SS58 (1)15 ISFSI TS/Dose Reading Calculation E-HUI1 (1)Caic X6CNA 15CSFST Procedure FCB PL1A FCB PLIARCSB PL1B RCSBPL1 BFCB L2A FCB L2AFCB PL2A FCB PL2AFCB PL2B FCB PL2B16 RCSB PL2A RCSBPL2ACB PL2A CB PL2ACB PL4A CB PL4ACB PL4C.1 CB PL4C.1SG1 (1)bSS5 (1)cSeismic Indications/Alarms (OBE) HU2 (1)17 Seismic Monitoring System indications/Alarm ______Rad Monitor Calculation: RE-48000 SU3 (1)18 Calc X6CNA14 V7 (pg 9)19 RCS Sample Activity SU3 (2)TS 3.4.16RCS Operational LeakageSU(1(220 54()2TS 3.4.1321 Containment Pressure Reference (52 psig) SU7 (2)a2/22/ 20 16Page 2 of 2 VlPage 1 of 1Definitions1.1Table 1.1-1 (page 1 of 1)MODES% RATEDAVERAGEREACTVITY THERMAL REACTOR COOLANTCONDTIO POWER(a) TEMPERATURE(0F)1 Power Operation _> 0.99 > 5 NA2 Startup s 5 NA3 Hot Standby < 0.99 NA > 3504 Hot Shutdown(b) < 0.99 NA 350 > Tavg > 2005 Cold Shutdown(b) < 0.99 NA _< 2006 Ref ueling(C) NA NA NA(a)(b)(c)Excluding decay heat.All reactor vessel head closure bolts fully tensioned.One or more reactor vessel head closure bolts less than fully tensioned.Vogtle Units 1 and 21,.1-7Amendment No. 96 (Unit 1)Amendment No. 74 (Unit 2)

V2See NL-1 5-1 898Enclosure 3SOUTHERN A-L ~ .a I.?Southern Nuclear Design CalculationCalculation Number: )(6cNA1 5Plant:lVocat Electric Generatina Plant Unit: 0] 1 0] 2 ix] 1 & 2 IDisci~line:i MechanicalTitle: NEI 99-01 Rev 6 EAL Calculations

Subject:

EmergencyIAction Level SetpointsPurpose)I Objective: ..... ...,,,...Document Emergency Action Level Values to support conversion to NEI 99-01 Rev 6System or Equipment Tag Numbers:NtAContentsTopic Page Attachments .. .. # of(Computer Printouts. Technical Papers, Sketches. PagesCorrespondence)Purpose .....1 A -SNC EP Concurrence ...1Criteria ........... B B- Reserved 0Conclusion -3 'C -"References' from X6CNAI4 31Design Inputs -6 D -"TEDE and Thyroid CDE Calculations 19Assumptions ..... 18 E -Shielding Calculations 29References 22 F -Evaluation of 52 psig Pressure on Mechanical 14Penetrations____Method of Solutions 26 G -References"'from X6CNA16 22Body of Calculation 31 "H -VEGP 1 EAL Thresholds 7I -VE'GP 2 EAL Thresholds ...7_____J' Reviewer Altern'ate Calculation ...11....K -SNCO024-CALC-:005 Vogtle EALs RA1_____ thresholds to address NEI 99-01 rev 6 1.....______ ___ L -SNC024-CALC-004 VEGP" EAL for IC E-HU1 16Total # of Pagesincluding cover sheet & 22AttachmentsNuclear Quality Level0 [ Safety-Related IXI .. Safety Significant ....03 Non- Safety --Significant 'Version RecordViinOriginator Reviewer Approval 'I "APproval 2INo.t Description j ZW .Io.jMAIIoI I ICalculation of EAL Thresholdsto support NEI 99-01 Rev. 6Guidance.1.0~j4~ADC3~t /2--i i~k.~~1iA4INMP-ES-039-F01 V4,0 M-S-3-ONMP-ES-039-001 V3Page 1 of 1VEGP ODCMFigure 4-1. Terrestrial Stations Near Site Boundary4-164-16 VER 30 V4Page 1 of 3-5-rIn Its letter dated July 17, 2013, the licensee stated, in part, thatLevel 1 Is established as the SFP cooling system low level set paint of 21 T-0",which is above the elevation at the top of the fuel pool cooling system suction linethat is at approximately 21 4-1 1". Two trains supply Unit 1 and Unit 2 spent fuelpool cooling water. When adjusted for saturated steam conditions, the pool levelneeded to meet the NPSH required Is 214"-6" for Train A and 219'-6" for Train Bbut only one train is required for operation. Thus, the two points described in NEI12-02 for loss of NPSH for the VEGP Spent Fuel Pool are 214'-1 1 -and 21 4'-6"and the HIGHER of the two Is 214'-I1 .However, VEGP conservatively selectsLevel 1 as 217'-0" since it is the normal low level set point for the SFP Coolingsystem.The NRC staff notes that Level 1 at 217 ft. 0 in. Is adequate for normal SFP cooling systemoperation; it is also sufficient for Net Positive Suction Head (NPSH) and represents the higher ofthe two points described above.NEi 12-02 states, in part, thatLevel 2 represents the range of water level where any necessary operations inthe vicinity of the spent fuel pool can be completed without significant doseconsequences from direct gamma radiation from the stored spent fuel. Level 2 isbased on either of the following:* 10 feet (+1- 1 foot) above the highest point of any fuel rack seated in thespent fuel pools, or* a designated level that provides adequate radiation shielding to maintainpersonnel radiological dose levels within acceptable limits while performinglocal operations in the vicinity of the pool. ThIs level shall be based on eitherplant-specific or appropriate generic shielding calculations, considering theemergency conditions that may apply at the time and the scope of necessarylocal operations, including installation of portable SFP instrument channelcomponents.FIn its OIP, the licensee stated that Level 2 would be set at a plant elevation 203 ft. 9-1/8 in.,which is approximately 10 ft. above the highest point of the fuel racks for both units at elevation193 ft. 9-1/8 in.In its letter dated July 17, 2013, the licensee provided a sketch depicting elevations Identified asLevel 1,2 and 3, the level measurement range and the top of the tallest fuel storage rack. TheNRC staff notes that Level 2 at an elevation of 20,3 ft. 9-1/8 in. is approximately 10 ft. above thetop of the fuel rack. The staff also notes that the licensee designated Level 2 using the first ofthe two options described in NEI 12-02 for Level 2.NEi 12-02 states, in part, thatLevel 3 corresponds nominally (i.e., +/- 1 foot) to the highest point of any fuelrack seated in the spent fuel pool. Level 3 is defined in this manner to providethe maximum range of information to operators, decision makers and emergencyresponse personnel.

V4Page 2 of 3-6-The licensee stated In its OIP that Level 3 would be set at plant elevation 193 ft. 9-118 in., whichis the nominal level of the highest fuel rack.In its letter dated July 17, 2013, the licensee provided a sketch depicting elevations identified asLevel 1, 2 and 3, the level measurement range and the top of the tallest fuel storage rack. TheNRC staff notes that Level 3 at an elevation of 193 ft. 9-1/8 in. as the highest point of any spentfuel storage rack seatd in the SFP.The licensee's proposed plan, with respect to identification of Levels 1, 2, and 3, appears to beconsistent with NEI 12-02, as endorsed by the ISG.3.3 Design Feature~s: InstrumentsAttachment 2 of Order EA-1 2-051, states, in part, thatThe instrumentation shall consist of a permanent, fixed primary instrumentchannel and a backup instrument channel. The backup instrument channel maybe fixed or portable. Portable instruments shall have capabilities that enhancethe ability of trained personnel to monitor spent fuel pool water level underconditions that restrict direct personnel access to the pool, such as partialstructural damage, high radiation levels, or heat and humidity from a boiling pool.NEI 12-02 states, in part, thatA spent fuel pool level instrument channel is considered reliable when theinstrument channel satisfies the design elements listed in Section 3[instrumentation Design Features] of this guidance and the plant operator hasfully implemented the programmatic features listed in Section 4 [ProgramFeatures].In its OIP, the licensee stated that, for both Unit 1 and Unit 2, the primary and backupinstrument channels will consist of fixed components. The licensee also stated that themeasured range will be continuous fromn the high pool level elevation of 219 ft. 0 in. to thetop of the spent fuel racks at elevation 193 ft. 9-1/8 in.In Its letter dated July 17, 2013, the licensee provided a sketch depicting elevations identified asLevel 1, 2 and 3 and the level measurement range. The NRC staff reviewed this sketch andnotes that there is a slight variation on the measurement range identified in the licensee's OIPand on this sketch. In its OIP, the licensee stated that the measurement range would go frompool elevation of 219 ft. 0 in. to 193 9-118 in. However, the sketch shows the range goes frompool elevation of 219 ft. 3 in. to 194 ft. 1/8 in. The staff has identified this request as:RAl #1Please identify the final SFP level instrumentation measurement range.The licensee's proposed plan, with respect to the number of channels and the range of theinstrumentation for both of its SF Ps, appears to be consistent with NEI 12-02, as endorsed bythe ISG. to NL-1 3-1 460ATTACHMAENT 1SKETCH IN RESPONSE TO RAI ITEM 1 .b---EL. 220'"S= TOP OP SFP OUR ---EL, 216'-6" NOLLVL-EL, 2t7'-O" LOW LEVEL ALARI--*EL. 214-t!1" TOP OP SUTION LIIE-EL. ! 79' 1/2 ! BOu lTTOMkNOTES EILEVATIONIS 40W ARE FOR BOTH UNITS V5Page 1 ofl15Aproe B Pat Procedure VersionS. E. Prewitt .....Elcti. neain 17100-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88ANNUNCIATOR RESPONSE INDEXDETECTOR NO.1 -RE-Q0011 -RE-00021 -RE-0003I -RE-00041 -RE-00051 -RE-0006A-RE-0007AA-RE-0007B1I-RE-0008A-RE-0009AA-RE-0009BA-RE-0009C1-RE-00l111 -RE-0013A-RE-0014A-RE-001 61-RE-0017A1 -RE-001 7B1 -RE-001 81 -RE-001 91 -RE-0020A1 -RE-0020B1 -RE-00211 -RE-0024A1 -RE-0024BA-RE-0025RADIATION MONITOR INDEXUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeRad Chem LabSample RoomFuel Handling BldgDecon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)Seal Table RoomWaste Gas ProcessingWaste Gas ProcessingBoron Recycle LiquidCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected Cubical-RadiogasAux Steam Condensate Return LiquidPAGE9101214**16182022242628313335* Safety Related. Go to 17102-1, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.**Passive collector. No electronic components.Printed February 3, 2016 at 13:02 V5Page 2 of 15AproegBt~6 Gnrating LA Procedure VersionApoeBs. E. Prewitt Vogle Electric Gen Pant 17100-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND jPage Number12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 7 of 88ANNUNCIATOR RESPONSE INDEXRADIATION MONITOR INDEXDETECTOR NO.1 -RE-0039A1 -RE-0039B1 -RE-07241 -RE-081 01 -RE-08481-RE-1 950A-RE-2532AA-RE-2532 BA-RE-2533AA-RE-2533B1 -RE-2562A1 -RE-2562B1 -RE-2562C1 -RE-2565A1 -RE-2565B1 -RE-2565C1-RE-121161-RE-121 171-RE-I12442A1-RE-i12442 B1-RE-i12442CUSEWaste Gas Decay Tank -RadiogasWaste Gas Compressor & Catalytic Recombiner -RadiogasN16 Rad MonitorSJAE Exhaust Rad MonitorTurbine Bldg Drains -LiquidACCW -LiquidFHB -RadiogasFHB -RadiogasFHB -RadiogasFHB -RadiogasContainment -Air ParticulateContainment -Passive Iodine CartridgeContainment Air -RadiogasContainment Vent -ParticulateContainment Vent -IodineContainment Vent -RadiogasControl Room Air In -Train AControl Room Air In -Train BPlant Vent Air Particulate (Low Range)Plant Vent Iodine Particulate (Low Range)Plant Vent Radiogas Particulate (Low Range)PAGE384042454850545658606264* Safety Related. Go to 17102-1, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.**Passive collector. No electronic components.Printed February 3, 2016 at 13:02 V5Page 3 of 15Approved By Votl Electric Geeatn Plant Procedure VersionS. E. Prewitt vog.e ....e..... 171 00-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 14 of 88ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEIncrease in radiation level near Unit 1 Spent Fuel PcBuilding.2.0 AUTOMATIC ACTIONSOn the south wall of the Fuel Handling Building Speldoor:a. Alarm horn on 1-RA-0008 sounds.b. Strobe light on 1-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.1 -RE-0008(High)in the Fuel Handlingnt Fuel Pool Room near thePrinted February 3, 2016 at 13:02 V5Page 4 of 15Approved By VersionJ.B SaneyVogtle Electric Generating Plant 11212.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 8 of 42ANNUNCIATOR RESPONSE INDEXSRDCWIDWN. TITLE PAGEAlA2A3A4A5 1-RE-2562A CNMT AIR -PARTICLES 10A6 1-RE-2562C CNMT AIR -GAS 12A7A8B1 1-RE-13119 MSL Gas 15B2 1-RE-13120 MSL Gas 17B3 1 -RE-0002 AREA 19B4 1-RE-0005 High Range -Area 21B5 1-RE-12116 In-Vent Gas 23B6 A-RE-2532A In-Vent Gas 25B7 A-RE-2532B In-Vent Gas 27B8C1 1-RE-13121 MSL Gas 29C2 1-RE-i131 22 MSL Gas 31C3 1 -RE-0003 AREA 33C4 1-RE-0006 High Range Area 35CS 1-RE-12117 In-Vent Gas 37C6 A-RE-2533A In-Vent Gas 39C7 A-RE-2533B In-Vent Gas 41Printed February 3, 2016 at 13:11 V5Page 5 of 15Approved By "' Electri Geea PlantPrcdeVrsoJ.B. Stanley VogUe Generting Procedure 20.4ioEffective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 19 of 42WINDOW CDCA B3ORIGINContainment LowRange Area Monitor1 -RE-0002SETPOI NTAs determinedby Chemistry(15 mR/hr duringrefueling)1 -RE-0002(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSEi NOTES* During refueling operations indicates a fuel drop accident. EJ* During power operation indicates possible loss of coolant accident. 0]2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 13:11 V5Page 6 of 15Appove ByGeeraing , Procedure VersionJ...tnlyvo .Ele tri ..... -...a.n...... 17102-1 20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY IPage Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 j 25 of 42WINDOW CDCA B6ORIGINFuel HandlingBuilding EffluentRadiogas MonitorARE-2532ASETPOINTAs determinedby ChemistryDepartment(RED LAMP LIT)(HIGH)]1.0PROBABLE CAUSE2.01. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.AUTOMATIC ACTIONSSwitches the Normal Fuel Handling Building Ventilation to Accident ModeVentilation.INITIAL OPERATOR ACTIONS3.0Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5Page 7 of 15Approved By lcti Pat Procedure VersionJ.B. Stanley vgeGnrtn 112I2.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 27 of 42WINDOW CDCA B7ORIGIN SETPOINT_________[A- RE-2532BFuel Handling As determined I(RED LAMP LIT)Building Effluent by Chemistry j(HIGH)Radiogas Monitor DepartmentIARE-2532BL_________NOTEFor other than HIGH conditions see Pages 5 and 6. 0]1.0 PROBABLE CAUSE1. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.2.0 AUTOMATIC ACTIONSSwitches the Normal Fuel Handling Building Ventilation to Accident ModeVentilation.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5Page 8 of 15Approved By ..... E lectric GnrngPlant IPrcdeVrsoJ.B. Stanley Vogtle Generatingre17102.1 Veso20.4Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY IPage Number06/23/20 14 IRELATED DISPLAY CONSOLE QRM2 j 33 of 42WINDOW CDCA C3ORIGINContainment LowRange Area Monitor1 -RE-0003SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)1 -RE-0003(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. EJ* During power operation indicates possible loss of coolant accident. o]2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 13:11 V5Page 9 of 15Approved: 8yiGenerating an Procedure VersionJ.B. Stanley vog,_e ElectricPat-._ 212.Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 39 of 42WINDOW CDCA C6ORIGINFuel HandlingBuilding EffluentRadiogas MonitorARE-2533ASETPOINTAs determinedby ChemistryDepartmentSA-RE-2533A(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSE1. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.AUTOMATIC ACTIONS2.0Switches the Normal Fuel Handling Building Ventilation to Accident ModeVentilation.INITIAL OPERATOR ACTIONS3.0Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5Page 10 of 15Approved By Gene rating anrceueVesoJ.B. Stanley Vogtle Electric Plant I Procedure 20.4ioEffective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY P age Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 41 of 42WINDOW CDCA C7ORIGINFuel HandlingBuilding EffluentRadiogas MonitorARE-2533BSETPOINTAs determinedby ChemistryDepartment(RED LAMP LIT)(HIGH)11.0PROBABLE CAUSE2.01. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.AUTOMATIC ACTIONSSwitches the Normal Fuel Handling Building Ventilation to Accident ModeVentilation.INITIAL OPERATOR ACTIONS3.0Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5Page 11 of 15ApproveVBytle Electric Gnrtg Plant AIProcedure VersionS. E. Prewitt ....g.e.Generat.ng.. 17100-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 77ANNUNCIATOR RESPONSE INDEXRADIATION MONITOR INDEXDETECTOR NO.2-RE-000 12-RE-00022-RE-00032-RE-00042-RE-OD052-RE-00062-RE-00082-RE-DO0112-RE-001 32-RE-001 7A2-RE-D01 7B2-RE-D01 82-RE-DO0192-RE-0020A2-RE-0020B2-RE-002 12-RE-0024A2-RE-0024B2-R E-0039A2-RE-0039B2-RE-0039C2-R E-0 7242-RE-081 02-RE-08482-RE-i19502-R E-2562AUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeFuel Handling BldgSeal Table RoomWaste Gas ProcessingCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air Pa rticu lateSelected CubicaI-RadiogasWaste Gas Decay Tank -RadiogasWaste Gas Compressor -RadiogasCatalytic Recombiner -RadiogasN16 MonitorSJAE Exhaust Rad MonitorTurbine Bldg Drains -LiquidACCW -LiquidContainment -Air ParticulatePAGE891113151719212326283033353739424547* Safety Related. Go to 17102-2, "ARP For The SRDC QRM2"** Not Functional -Detectors Removed.Passive collector. No electronic components.Printed February 3, 2016 at 13:22 V5Page 12 of 15Approved BYs E.Genratigitt Procedure VersionS...E.... ..w... .....t.e Electric..... Plant. ..... 17100-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/10/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 11 of 77ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEIncrease in radiation level near Unit 2 Spent Fuel PcBuilding.2.0 AUTOMATIC ACTIONSOn the south wall of the Fuel Handling Building Speldoor:a. Alarm horn on 2-RA-0008 sounds.b. Strobe light on 2-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.2-RE-0008(High)in the Fuel Handlingnt Fuel Pool Room near thePrinted February 3, 2016 at 13:22 V5Page 13 of 15Approve.By.... Plant Procedure VersionJ. B. Stanley voteEeti ~nrtn in 17102-2 16.3Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 8 of 34ANNUNCIATOR RESPONSE INDEXSRDC TTEPGWINDOW NO. TTEPGAlA2A3A4A5 2-RE-2562A CNMT AIR -PARTICLES 10A6 2-RE-2562C CNMT AIR -GAS 12A7A8B1 2-RE-13119 MSL Gas 15B2 2-RE-I13120 MSL Gas 17B3 2-RE-0002 AREA 19B4 2-RE-0005 High Range -Area 21B5 2-RE-121 16 In-Vent Gas 23B6B7B8Cl 2-RE-13121 MSL Gas 25C2 2-RE-i13122 MSL Gas 27C3 2-RE-0003 AREA 29C4 2-RE-0006 High Range Area 31C5 2-RE-12117 In-Vent Gas 33C6C7Printed February 3, 2016 at 13:28 V5Page 14 of 15Approved By V .. ...... .Procedure VersionJ. B. Stanley v ogtue Electric Generating Plant ~ 17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 19 of 34WINDOW CDCA B3ORIGINContainment LowRange Area Monitor2-RE-0002SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)[2-RE-0002(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. E* During power operation indicates possible loss of coolant accident. [2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 13:28 V5Page 15 of 15Approved By Genrain AIProcedure VersionJ. B. Stanley Vogtle Electric eertn Plant -17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 RELATED DISPLAY CONSOLE QRM2 29 of 34WINDOW CDCA C3ORIGINContainment LowRange Area Monitor2-RE-0003SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)2-RE-0003(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. [L* During power operation indicates possible loss of coolant accident.2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.pt'rinted -ebruary 3, 2016 at 13:28 V6Page 1 of 4Approved By _ ~Procedure VersionS. E. Prewitt Vogtle Elcri enerating Pln1i17100-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88ANNUNCIATOR RESPONSE INDEXDETECTOR NO.1 -RE-00011 -RE-00021 -RE-00031 -RE-00041 -RE-00051 -RE-0006A-RE-0007AA-RE-0007B1 -RE-Q008A-RE-0009AA-RE-0009BA-RE-0009C1-RE-00l111-RE-0013A-R E-001 4A-RE-001 61 -RE-001 7A1-RE-0017B1-RE-001 81-RE-001 91 -RE-0020A1 -RE-0020B1 -RE-00211 -RE-0024A1 -RE-0024BA-RE-0025RADIATION MONITOR INDEXUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeRad Chem LabSample RoomFuel Handling BldgDecon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)Seal Table RoomWaste Gas ProcessingWaste Gas ProcessingBoron Recycle LiquidCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected CubicaI-RadiogasAux Steam Condensate Return LiquidPAGE910121416182022242628313335* Safety Related. Go to 17102-1, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.Passive collector. No electronic components.Printed February 3, 2016 at 14:28 V6Page 2 of 4Approved By Ge ti IProcedure VersionS. E. Prewitt v .g.e Elcti.Gneain.Pat 17100-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 9 of 88ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEDeteriorating radiological conditions in the Control F2.0 AUTOMATIC ACTIONSNONE3.0 INITIAL OPERATOR ACTIONSNONE4.0 SUBSEQUENT OPERATOR ACTIONS1. Request Health Physics to survey Control Rilevel.2. Obtain detector trend data per 13508-1, "Ra3. Refer to NMP-EP-1 10, "Emergency ClassificInstructions".4. Monitor the channel for further changes.5* IF sampling and analysis determine the chanrequest Chemistry to deactivate the channel5.0 COMPENSATORY OPERATOR ACTIONSNONEEND OF SUB-PROCEDURE

REFERENCES:

AX4DB206-2, 1X5DS2A02(High)toom.oom area to verify radiationdiation Monitoring System".*ation And Implementingreel has malfunctioned,Printed February 3, 2016 at 14:28 V6Page 3 of 4Approveds EPrwtBY Generating.. ...... Procedure170 .Version2 1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 6 of 77ANNUNCIATOR RESPONSE INDEXDETECTOR NO.2-RE-00012-R E-00022-R E-00032-RE-00042-RE-00052-RE-00062-R E-00082-RE-0011I2-RE-001 32-RE-001 7A2-RE-001 7B2-RE-001 82-RE-001 92-RE-0020A2-RE-0020B2-R E-002 12-R E-0024A2-RE-0024B2-R E-0039A2-RE-0039B2-RE-0039C2-RE-07242-RE-081 02-R E-0 8482-RE-I19502-R E-2562ARADIATION MONITOR INDEXUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeFuel Handling BldgSeal Table RoomWaste Gas ProcessingCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected CubicaI-RadiogasWaste Gas Decay Tank -RadiogasWaste Gas Compressor -RadiogasCatalytic Recombiner -RadiogasN16 MonitorSJAE Exhaust Rad MonitorTurbine Bldg Drains -LiquidACCW -LiquidContainment -Air ParticulatePAGE891113151719212326283033353739424547* Safety Related. Go to 171 02-2, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.Passive collector. No electronic components.Printed February 3, 2016 at 14:32 V6Page 4 of 4Approved By * ...Procedure VersionS. E. Prewitt Vogtle Electri c Generating Plant E. I171 00-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 8 of 77ORIGIN SETPOINT_________2-RE-0001Area Monitor As determined by (High)Chemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5. 0]1.0 PROBABLE CAUSEDeteriorating radiological conditions in the Control Room.2.0 AUTOMATIC ACTIONSNONE3.0 INITIAL OPERATOR ACTIONSNONE4.0 SUBSEQUENT OPERATOR ACTIONS1. Request Health Physics to survey Control Room area to verify radiationlevel.2. Obtain detector trend data per 13508-2, "Radiation Monitoring System".3. Refer to NMP-EP-1 10, "Emergency Classification And ImplementingInstructions".4. Monitor the channel for further changes.5. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.5.0 COMPENSATORY OPERATOR ACTIONSNONEEND OF SUB-PROCEDURE

REFERENCES:

AX4DB206-2, 2X5DS2A02Printed February 3, 2016 at 14:32 V7Page 1 of 6Approved By I e eatn Procedure VersionC. H. Willijams, Jr. j Vogtle Electric GeeaigPlant I10513.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 IPANEL 1A2 ON MCB I 3 of 67(1 )(2'i(3'i(4'lABCDEFLIQUID PROCESS NSSS FHB EXH NIS GROUP 1 SPENT FUELPANEL TROUBLE PROT GR I RAD MONITOR CHANNEL I MONITOR LIGHT PIT HI TEMPBYPASS EQUIP TROUBLE BYPASS COMP OFF NORMGAS PROCESS NSSS INTMD NIS GROUP 2 BYPASS CNMTPANEL TROUBLE PROT GR II RADIATION CHANNEL II MONITOR LIGHT VENT ISOBYPASS ALARM BYPASS COMP OFF NORM HI RAD TESTBORON RECYCLE NSSS HIGH NIS GROUP 3 SAFEGUARDS CABPANEL TROUBLE PROT GR III RADIATION CHANNEL 111 MONITOR LIGHT TRAIN ABYPASS ALARM BYPASS COMP OFF NORM TESTPCS CABINET NSSS NIS GROUP 4 SAFEGUARDS CABDOORS OPEN PROT GR IV CHANNEL IV MONITOR LIGHT TRAIN BBYPASS BYPASS COMP OFF NORM TESTPCS CABINETS SPENT FUEL PIT ANNUNCIATOR AMSAC GROUP 5 PROT SYSTEMPWR SUPPLY LO LEVEL DC SOURCE TROUBLE MONITOR LIGHT TRAIN AFAILURE SUPPLY FAILURE COMP OFF NORM TROUBLEPROCESS PROT SPENT FUEL ANNUNCIATOR ANNUNCIATOR ANNUNCIATOR PROT SYSTEMSET VIOLATED PIT HI LEVEL SYSTEM DC SYSTEM ON SYSTEM TRAIN B>1 DOOR OPEN SUPPLY FAILURE ALTN SUPPLY DC GROUND TROUBLEPrinted February 2, 2016 at 16:24Printed February 2, 2016 at 16:24 V7Page 2 of 6Approved By .............. l l rcGenerating Plroedr VrsoC. H. Williams, Jr. PrtoEecredPanure100- 34.2ioEffective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 PANEL 1A2 ON MCB5of6ANNUNCIATORWINDOW NO.E01E02E03E04EQ5E06F0 1F02F03F04F05F06TITLEPCS CABINETS PWR SUPPLY FAILURESPENT FUEL PIT LO LEVELANNUNCIATOR DC SOURCE SUPPLY FAILUREAMSAC TROUBLEGROUP 5 MONITOR LIGHT COMP OFF NORMPROT SYSTEM TRAIN A TROUBLEPROCESS PROT SET VIOLATED >1 DOOR OPENSPENT FUEL PIT HI LEVELANNUNCIATOR SYSTEM DC SUPPLY FAILUREANNUNCIATOR SYSTEM ON ALTN SUPPLYANNUNCIATOR SYSTEM DC GROUNDPROT SYSTEM TRAIN B TROUBLEPAGE414346475253565761626365Printed February 2, 2016 at 16:24 V7Page 3 of 6Approved By og e ProcedurerVersionC. H. Williams, Jr. Vo e Eetric ~.ireaigPant Pr17005-1 34.2ioEffective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 PANEL 1A2 ON MOB I 43 of 67WINDOW E02ORIGIN SETPOINT_________SPENT FUEL PIT1-LSHL-625 217 feet elevation LO LEVEL1.0 PROBABLE CAUSE1. Insufficient inventory during filling or refueling operation.2. Normal evaporation.3. System leak.4. Loss of air to the Fuel Transfer Canal and/or Cask Loading Pit GateSeals.2.0 AUTOMATIC ACTIONSNONE3.0 INITIAL OPERATOR ACTIONSNONEPrinted February 2, 2016 at 16:24 V7Page 4 of 6Approved BYc H. ElectricPlant I Procedure VersionC. H.W..l.m...J .....e.eneatig 17005-2 28.1Effective Date jANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 IPANEL 2A2 ON MCB I 3 of 65(1)(2)(3)(4)(5)(6)ABCDEFLIQUID PROCESS NSSS NIS GROUP 1 SPENT FUELPANEL TROUBLE PROT GR ! CHANNEL I MONITOR LIGHT PIT HI TEMPBYPASS BYPASS COMP OFF NORMGAS PROCESS NSSS INTMD NIS GROUP 2 BYPASS CNMTPANEL TROUBLE PROT GR II RADIATION CHANNEL II MONITOR LIGHT VENT ISOBYPASS ALARM BYPASS COMP OFF NORM HI RAD TESTNSSS HIGH NIS GROUP 3 SAFEGUARDS CABPROT GR III RADIATION CHANNEL MONITOR LIGHT TRAIN ABYPASS ALARM III BYPASS COMP OFF NORM TESTPCS CABINET NSSS NIS GROUP 4 SAFEGUARDS CABDOORS OPEN PROT GR IV CHANNEL IV MONITOR LIGHT TRAIN BBYPASS BYPASS COMP OFF NORM TESTPCS CABINETS SPENT FUEL PIT ANNUNCIATOR AMSAC GROUP 5 PROT SYSTEMPWR SUPPLY LO LEVEL DC SOURCE TROUBLE MONITOR LIGHT TRAIN AFAILURE SUPPLY FAILURE COMP OFF NORM TROUBLEPROCESS PROT SPENT FUEL ANNUNCIATOR ANNUNCIATOR ANNUNCIATOR PROT SYSTEMSET VIOLATED PIT HI LEVEL SYSTEM DC SYSTEM ON SYSTEM TRAIN B>1 DOOR OPEN SUPPLY FAILURE ALTN SUPPLY DC GROUND TROUBLEPrinted February 2, 2016 at 16:29 V7Page 5 of 6ANNUNCIATORWINDOW NO.E01E02E03E04E05E06F01IF02F03F04F05F06TITLEPCS CABINETS PWR SUPPLY FAILURESPENT FUEL PIT LO LEVELANNUNCIATOR DC SOURCE SUPPLY FAILUREAMSAC TROUBLEGROUP 5 MONITOR LIGHT COMP OFF NORMPROT SYSTEM TRAIN A TROUBLEPROCESS PROT SET VIOLATED >1 DOOR OPENSPENT FUEL PIT HI LEVELANNUNCIATOR SYSTEM DC SUPPLY FAILUREANNUNCIATOR SYSTEM ON ALTN SUPPLYANNUNCIATOR SYSTEM DC GROUNDPROT SYSTEM TRAIN B TROUBLEPAGE394144455051545559606163Printed February 2, 2016 at 16:29 V7Page 6 of 6Apoec. H. Williams,B Jr. i voge Elecltric Pl.. ant Prcdr17005-2 Veso28.1Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number6/21/13 IPANEL 2A2 ON MCB I 41 of 65WINDOW E02ORIGIN SETPOINT_________SPENT FUEL PIT12-LSHL-625 217 feet [LO LEVELelevation [__________1.0 PROBABLE CAUSE1. Insufficient inventory during filling or refueling operation.2. Normal evaporation.3. System leak.4. Loss of air to the Fuel Transfer Canal and/or Cask Loading Pit GateSeals.2.0 AUTOMATIC ACTIONSNONE3.0 INITIAL OPERATOR ACTIONSNONEPrinted February 2, 2016 at 16:29 V8Page 1 of 18ApprvedBygtle Procedure VersionS. E. Prewitt .....e.E..ectric Generating Plant...... ...... .. 171 00-1 26.2....Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88ANNUNCIATOR RESPONSE INDEXDETECTOR NO.1 -RE-00011 -RE-00021 -RE-00031 -RE-00041 -RE-00051 -RE-0006A-RE-0007AA-RE-0007B1 -RE-0008A-RE-0009AA-RE-0009BA-RE-0009C1-R E-0011I1-RE-0013A-RE-001 4A-RE-001 61 -RE-001 7A1 -R E-0017B1 -RE-00181-RE-00191 -RE-0020A1 -RE-0020B1 -RE-00211 -RE-0024A1 -RE-0024BA-R E-0025RADIATION MONITOR INDEXUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeRad Chem LabSample RoomFuel Handling BldgDecon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)Seal Table RoomWaste Gas ProcessingWaste Gas ProcessingBoron Recycle LiquidCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected CubicaI-RadiogasAux Steam Condensate Return LiquidPAGE9101214**k"**161820**k22242628313335* Safety Related. Go to 17102-1, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.Passive collector. No electronic components.Printed February 3, 2016 at 14:52 V8Page 2 of 18Approved By ... W r'lUl VersionS. E. Prewitt vou lcrcPat -171 00-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 10 of 88ORIGIN SETPOINTArea Monitor As determined byChemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5.1 -RE-0004(High)1.02.03.04.0PROBABLE CAUSEIncrease in radiation level in the Containment Personnel Access Hatch.AUTOMATIC ACTIONSOutside the containment near the hatch:a. Alarm horn on 1-RA-0004 sounds,b. Strobe light on 1-RA-0004 blinks.INITIAL OPERATOR ACTIONSNONESUBSEQUENT OPERATOR ACTIONS1. Check for elevated radiation level in containment at 1 -RE-0002 and1-RE-0003 at the SRDC.2. IF alarm is valid, warn personnel in containment to exit by way of theemergency escape hatchway.3. Notify Health Physics of the alarm and request survey of ContainmentPersonnel Access Hatch.4. Obtain detector trend data per 13508-1, "Radiation Monitoring System".5. Monitor the channel for further changes.6. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.Printed February 3, 2016 at 14:52 V8Page 3 of 18AE.Pproedit Byle Electric Geert Plant IProcedure Veso1S.E rwt oge ~ nrugI171 00-1 26.2Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 112/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 14 of 88ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEIncrease in radiation level near Unit 1 Spent Fuel PcBuilding.2.0 AUTOMATIC ACTIONSOn the south wall of the Fuel Handling Building Spedoor:a. Alarm horn on I-RA-0008 sounds.b. Strobe light on I -RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.1 -RE-0008(High))ol in the Fuel Handlingnt Fuel Pool Room near thePrinted February 3, 2016 at 14:52 V8Page 4 of 18Approved By VersionS. E. Prewitt ....Vogtle Electric Generating Plant 11012.Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 16 of 88ORIGIN SETPOINT_________1-RE-001 1Area Monitor As determined by (High)"Chemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5. 0]1.0 PROBABLE CAUSEIncrease in radiation level in the Seal Table Room on Level B Containment.2.0 AUTOMATIC ACTIONSIn the Incore Instrumentation Room:a. Alarm horn on 1 -RA-0011I sounds.b. Strobe light on 1 -RA-Ol11 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Incore Instrumentation Room.4.0 SUBSEQUENT OPERATOR ACTIONS1. Notify Health Physics to determine the cause of the high radioactivitylevel.2. Restrict personnel access to the seal table area until the condition hasbeen corrected.3. Obtain detector trend data per 13508-1, "Radiation Monitoring Systems".4. Monitor the channel for further changes.5. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.Printed February 3, 2016 at 14:52 V8Page 5 of 18Approved By

• lcri ln Procedure VersionJ.B. Stanley , Vogtle EetcGenerating Plnt17102-1 20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETW Page Number06/23/20 14 RELATED DISPLAY CONSOLE QRM2 8 of 42ANNUNCIATOR RESPONSE INDEXSRDCWINDOW NO.AlA2A3TITLEPAGEA4A5A6A7A8B1B283B4B5B6B7B88ClC2C3C4C5C6C71-RE-2562A CNMT AIR -PARTICLES1-RE-2562C CNMT AIR -GAS10121-RE-I13119 MSL Gas1-RE-I131 20 MSL Gas1 -RE-0002 AREA1-RE-0005 High Range -Area1-RE-12116 In-Vent GasA-RE-2532A In-Vent GasA-RE-2532B In-Vent Gas1-RE-i13121 MSL Gas1-RE-I131 22 MSL Gas1 -RE-0003 AREA1-RE-0006 High Range Area1-RE-i12117 In-Vent GasA-RE-2533A In-Vent GasA-RE-2533B In-Vent Gas1517192123252729313335373941Printed February 3, 2016 at 15:08 V8Page 6 of 18AprvdB lcti ln rocedure VersionJ.B. Stanley I vge ~ nrin 112I2.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 19 of 42WINDOW CDCA B3ORIGINContainment LowRange Area Monitor1 -RE-0002SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)1 -RE-0002(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. 0* During power operation indicates possible loss of coolant accident. []2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR, IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 15:08 V8Page 7 of 18Approved By ElcrcPat AProcedure VersionJ.B. Stanley .... ...g.....e. Generating. ..... .... .. ...17102-1 20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/2014 RELATED DISPLAY CONSOLE QRM2 33 of 42ORIGINContainment LowRange Area Monitor1 -RE-0003SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)WINDOW CDCA C31 -RE-0003(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. 0]* During power operation indicates possible loss of coolant accident. 0]High radiation in the Containment Building.AUTOMATIC ACTIONS2.0Initiates Containment Building Ventilation isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 15:08 V8Page 8 of 18AprvdBj.B. Stanley ....Vogtle Electric nraigPlant Prceur171 02-1 Veso20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number06/23/20 14 RELATED DISPLAY CONSOLE QRM2 I 21 of 42WINDOW CDCA B4ORIGINContainment HighRange Area Monitor1 -RE-0005SETPOINT100 R/hr1 -RE-0005(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSE2.0High radiation in Containment.AUTOMATIC ACTIONSNONEINITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm and sample Containmentatmosphere. if required, initiate evacuation of Containment.Printed February 3, 2016 at 15:08 V8Page 9 of 18Approved BY.B GeneraingyA P rc~edure Version1J.B...Stanley..vogt.e Electric Plant.... ...... ...17102-1 20.4Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 106/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 35 of 42WINDOW CDCA C4ORIGINSETPOINTContainment HighRange Area Monitor1 -RE-0006100 R/hr1 -RE-0006(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSE2.0High radiation in the Containment.AUTOMATIC ACTIONSNONEINITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm and sample Containmentatmosphere. if required, initiate evacuation of Containment.Printed February 3, 2016 at 15:08 V8Page 10 of 18Procedure Version17100-2 20.1nber6 of 77ANNUNCIATOR RESPONSE INDEXRADIATION MONITOR INDEXDETECTOR NO.2-R E-000 12-RE-00022-RE-00032-RE-00042-RE-00052-R E-00062-RE-00082-RE-0011I2-RE-001 32-RE-001 7A2-RE-001 7B2-RE-001 82-RE-001 92-R E-0020A2-R E-0020 B2-R E-002 12-R E-0024A2-RE-0024B2-RE-0039A2-RE-0039B2-RE-0039C2-RE-07242-RE-081 02-RE-08482-RE-I19502-R E-2562AUSEControl RoomContainment -Low RangeContainment -Low RangeContainment HatchContainment -High RangeContainment -High RangeFuel Handling BldgSeal Table RoomWaste Gas ProcessingCCW Train ACCW Train BWaste LiquidSG Sample LiquidNSCW Train ANSCW Train BSG Blowdown LiquidSelected Cubical-Air ParticulateSelected CubicaI-RadiogasWaste Gas Decay Tank -RadiogasWaste Gas Compressor -RadiogasCatalytic Recombiner -RadiogasN16 MonitorSJAE Exhaust Rad MonitorTurbine Bldg Drains -LiquidACCW -LiquidContainment -Air ParticulatePAGE891113151719212326283033353739424547* Safety Related. Go to 171 02-2, "ARP For The SRDC QRM2".** Not Functional -Detectors Removed.*** Passive collector. No electronic components.Printed February 3, 2016 at 14:58 V8Page 11 of 18Procedure Version17100-2 20.1Page Number9 of 77ORIGIN SETPOINTArea Monitor As determined byChemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5.2-RE-0004(High)1.02.03.04.0PROBABLE CAUSEIncrease in radiation level in the Containment Personnel Access Hatch.AUTOMATIC ACTIONSOutside the containment near the hatch:a. Alarm horn on 2-RA-0004 sounds.b. Strobe light on 2-RA-0004 blinks.INITIAL OPERATOR ACTIONSNONESUBSEQUENT OPERATOR ACTIONS1. Check for elevated radiation level in containment at 2-RE-0002 and2-RE-0003 at the SRDC.2. IF alarm is valid, warn personnel in containment to exit by way of theemergency escape hatchway.3. Notify Health Physics of the alarm and request survey of ContainmentPersonnel Access Hatch.4. Obtain detector trend data per 13508-2, "Radiation Monitoring System".5. Monitor the channel for further changes.6. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.Printed February 3, 2016 at 14:58 V8Page 12 of 18Approveds EPrwtBY 'og Elect$ric ln Procedure VersionS.E rwt ogi eeaig17100-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 11 of 77ORIGIN SETPOINTArea Monitor As determined byChemistry Department1.0 PROBABLE CAUSEIncrease in radiation level near Unit 2 Spent Fuel PcBuilding.2.0 AUTOMATIC ACTIONSOn the south wall of the Fuel Handling Building Spedoor:a. Alarm horn on 2-RA-0008 sounds.b. Strobe light on 2-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONSEvacuate the Fuel Handling Building.2-RE-0008(High))ol in the Fuel Handlingnt Fuel Pool Room near thePrinted February 3, 2016 at 14:58 V8Page 13 of 18Approveds EPrwtBY .... Gen Procedure VersionS. EPr.......t..Eletr. Generatin Plant ...... 171 00-2 20.1Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number12/10/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 13 of 77ORIGIN SETPOINTArea Monitor As determined byChemistry DepartmentNOTEFor other than HIGH conditions see Pages 4 and 5.2-RE-00l11(High)1.02.03.04.0PROBABLE CAUSEIncrease in radiation level in the Seal Table Room on Level B Containment.AUTOMATIC ACTIONSIn the Incore Instrumentation Room:a. Alarm horn on 2-RA-0011 sounds.b. Strobe light on 2-RA-011I blinks.INITIAL OPERATOR ACTIONSEvacuate the Incore Instrumentation Room.SUBSEQUENT OPERATOR ACTIONS1. Notify Health Physics to determine the cause of the high radioactivitylevel.2. Restrict personnel access to the seal table area until the condition hasbeen corrected.3. Obtain detector trend data per 13508-2, "Radiation Monitoring Systems".4. Monitor the channel for further changes.5. IF sampling and analysis determine the channel has malfunctioned,request Chemistry to deactivate the channel.Printed February 3, 2016 at 14:58 V8Page 14 of 18Approved By Vogtl Electric GeeaigPlant & Procedure VersionJ. B. Stanley ...eGeertig 17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 RELATED DISPLAY CONSOLE QRM2 I 8 of 34ANNUNCIATOR RESPONSE INDEXSRDC TTEPGWINDOW NO. TTEPGAlA2A3A4A5 2-RE-2562A CNMT AIR -PARTICLES 10A6 2-RE-2562C CNMT AIR -GAS 12A7A881 2-RE-13119 MSL Gas 15B2 2-RE-13120 MSL Gas 17B3 2-RE-0002 AREA 19B4 2-RE-0005 High Range -Area 21B5 2-RE-12116 In-Vent Gas 23B687B88Cl 2-RE-13121 MSL Gas 25C2 2-RE-I131 22 MSL Gas 27C3 2-RE-0003 AREA 29C4 2-RE-0006 High Range Area 31C5 2-RE-12117 In-Vent Gas 33C6C7Printed February 3, 2016 at 15:18 V8Page 15 of 18ApprovedBytric Generating Pln IProcedure VersionJ.pBpStanedy I Vogtle EetiPln -17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 19 of 34WINDOW CDCA B3ORIGINContainment LowRange Area Monitor2-RE-0002SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)2-RE-0002(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident.* During power operation indicates possible loss of coolant accident. LI2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 15:18 V8Page 16 of 18Approved By " 'Eectric GeeaigPlant & Procedure VersionJ. B. Stanley , Vogtle Geertig,17102-2 16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 RELATED DISPLAY CONSOLE QRM2 29 of 34ORIGINContainment LowRange Area Monitor2-RE-0003SETPOINTAs determinedby Chemistry(15 mR/hr duringrefueling)WINDOW CDCA C32-RE-0003(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSENOTES* During refueling operations indicates a fuel drop accident. L* During power operation indicates possible loss of coolant accident. [2.0High radiation in the Containment Building.AUTOMATIC ACTIONSInitiates Containment Building Ventilation Isolation.INITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm. If required, initiateevacuation of Containment.Printed February 3, 2016 at 15:18 V8Page 17 of 18Approvedgtle Electric G~eaigPlantPrcde VrsoApoeJ. B. Stanleyy vog..Geeratng 17102-2Prcr Veso16.3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 21 of 34WINDOW CDCA B4ORIGINContainment HighRange Area Monitor2-RE-0005SETPOINT100 R/hr2-RE-0005(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSE2.0High radiation in Containment,AUTOMATIC ACTIONSNONEINITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR IF appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplan nedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm and sample Containmentatmosphere. If required, initiate evacuation of Containment.Printed February 3, 2016 at 15:18 V8Page 18 of 18Approved By vogtle Geneirating nt....17102-2 Verson3Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number11/4/13 IRELATED DISPLAY CONSOLE QRM2 31 of 34WINDOW CDCA C4ORIGINContainment HighRange Area Monitor2-RE-0006SETPOINT100 R/hr2-RE-0006(RED LAMP LIT)(HIGH)1.0PROBABLE CAUSEHigh radiation in the Containment.AUTOMATIC ACTIONS2.0NONEINITIAL OPERATOR ACTIONS3.01. Initiate evacuation of Containment IF the alarm is due to unexpected orunexplained radiation increases, OR if appropriate HP controls are NOTin place for the radiological conditions indicated.2. IF the alarm is due to expected radiation increases from preplannedevolutions AND appropriate HP controls are in place, THEN request HPand Chemistry to investigate the cause of alarm and sample Containmentatmosphere. if required, initiate evacuation of Containment.Printed February 3, 2016 at 15:18