Text

Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 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)
	v • d • e

Vogtle Electric Generating Plant Units 1 and 2 License Amendment Request for Changes to Emergency Action Level Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant Enclosure 4 Vogtle EAL Verification and Validation Documents Vogtle EAL V&V Documentation Index.V&V# Description

,. ,,IC IThreshold RCS Modes/Temperatures -TS Reference (Table 1.1-1) EAL Basis Section 1.5 1 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 X6CNAJ15 Radiation Monitor Calculations:

RE-0018 RUI (1) (2)RE-0021 RE-0848 ARE-0014 2 ~RE- 12839 RE-12442C RE-12444C Caic X6CNAJ15 Radiation Monitor Calculation:

RE-005 CGI1 (2)b RE-006 CS1 (3)b FCB L3A FCB L3A RCSB L3A RCSB L3A Caic X6CNA15 CB PL3A CB PL3A ODCM/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-002/003 5 ARE-2532 A/B ARE-2533 A/B Annunciator Response Procedure (Control Room) RA3 (1)6

Reference:

RE-001 Annunciator Response Procedure (SFP Level) RU2 (1)a 7 Reference Annunciator Display: ALB05 E02 (SFP Lo Level)Radiation Monitor Information:

RE-008 RU2 (1)b RE-002 RE-003 8 RE-004 RE-005 RE-006 RE-001 1 ____RVLIS Indications/Displays (RVLIS) CG1 (1)a 9CS1 (1)b (2)b CAl (1)Calc X6CNA5 15___Containment Sump/Reactor Coolant Drain Tank CG 1 (2)b 10 (RCDT)/Waste Holdup Tank (WHiT) references (FSAR) CS 1 (3)b 10CA1 (2)b_____CU1 (2)b 2/22/2016 Page 1 of 2 Vogtle EAL V&V Documentation Index V&V# Description IC Threshold H-2 Concentration

(> 6%) -calculation/reference CG 1 (1)b (2)c Calc X6CNA 15 CB PL4B CB PL4B Containment Pressure

Reference:

CG1 (1)b (2)c 12 > 13 psig with Containment Closure established

> 52 psig with TS Containment Integrity Intact Cale X6CNAJ15 Emergency Buses Drawing CA2 (1)CU2 (1)a SG1 (1)a 13 SG8 (1)a SS1 (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 15 CSFST Procedure FCB PL1A FCB PLIA RCSB PL1B RCSB PL1 B FCB L2A FCB L2A FCB PL2A FCB PL2A FCB PL2B FCB PL2B 16 RCSB PL2A RCSB PL2A CB PL2A CB PL2A CB PL4A CB PL4A CB PL4C.1 CB PL4C.1 SG1 (1)b SS5 (1)c Seismic 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 3.4.16 RCS Operational LeakageSU(1(2 20 54()2 TS 3.4.13 21 Containment Pressure Reference (52 psig) SU7 (2)a 2/22/ 20 16 Page 2 of 2 Vl Page 1 of 1 Definitions 1.1 Table 1.1-1 (page 1 of 1)MODES% RATEDAVERAGE REACTVITY THERMAL REACTOR COOLANT CONDTIO POWER(a) TEMPERATURE (0 F)1 Power Operation

_> 0.99 > 5 NA 2 Startup s 5 NA 3 Hot Standby < 0.99 NA > 350 4 Hot Shutdown(b)

< 0.99 NA 350 > Tavg > 200 5 Cold Shutdown(b)

< 0.99 NA _< 200 6 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 2 1,.1-7 Amendment No. 96 (Unit 1)Amendment No. 74 (Unit 2)

V2 See NL-1 5-1 898 Enclosure 3 SOUTHERN A-L ~ .a I.?Southern Nuclear Design Calculation Calculation Number: )(6cNA1 5 Plant:lVocat Electric Generatina Plant Unit: 0] 1 0] 2 ix] 1 & 2 IDisci~line:i Mechanical Title: NEI 99-01 Rev 6 EAL Calculations

Subject:

Emergency IAction Level Setpoints Purpose)I Objective:

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

.. .. # of (Computer Printouts.

Technical Papers, Sketches.

Pages Correspondence)

Purpose .....1 A -SNC EP Concurrence

...1 Criteria ...........

B B- Reserved 0 Conclusion

-3 'C -"References' from X6CNAI4 31 Design Inputs -6 D -"TEDE and Thyroid CDE Calculations 19 Assumptions

..... 18 E -Shielding Calculations 29 References 22 F -Evaluation of 52 psig Pressure on Mechanical 14 Penetrations____

Method of Solutions 26 G -References"'from X6CNA16 22 Body of Calculation 31 "H -VEGP 1 EAL Thresholds 7 I -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 16 Total # of Pages including cover sheet & 22 Attachments Nuclear Quality Level 0 [ Safety-Related IXI .. Safety Significant

....03 Non- Safety --Significant

'Version Record ViinOriginator Reviewer Approval 'I "APproval 2 INo.t Description j ZW .Io.j M AIIoI I I Calculation of EAL Thresholds to support NEI 99-01 Rev. 6 Guidance.1.0~j4~ADC 3~t /2--i i~k.~~1iA4 I NMP-ES-039-F01 V4,0 M-S-3-O NMP-ES-039-001 V3 Page 1 of 1 VEGP ODCM Figure 4-1. Terrestrial Stations Near Site Boundary 4-16 4-16 VER 30 V4 Page 1 of 3-5-rIn Its letter dated July 17, 2013, the licensee stated, in part, that Level 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 line that is at approximately 21 4-1 1". Two trains supply Unit 1 and Unit 2 spent fuel pool cooling water. When adjusted for saturated steam conditions, the pool level needed to meet the NPSH required Is 214"-6" for Train A and 219'-6" for Train B but only one train is required for operation.

Thus, the two points described in NEI 12-02 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 selects Level 1 as 217'-0" since it is the normal low level set point for the SFP Cooling system.The NRC staff notes that Level 1 at 217 ft. 0 in. Is adequate for normal SFP cooling system operation; it is also sufficient for Net Positive Suction Head (NPSH) and represents the higher of the two points described above.NEi 12-02 states, in part, that Level 2 represents the range of water level where any necessary operations in the vicinity of the spent fuel pool can be completed without significant dose consequences from direct gamma radiation from the stored spent fuel. Level 2 is based on either of the following:

10 feet (+1- 1 foot) above the highest point of any fuel rack seated in the spent fuel pools, or* a designated level that provides adequate radiation shielding to maintain personnel radiological dose levels within acceptable limits while performing local operations in the vicinity of the pool. ThIs level shall be based on either plant-specific or appropriate generic shielding calculations, considering the emergency conditions that may apply at the time and the scope of necessary local operations, including installation of portable SFP instrument channel components.

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 elevation 193 ft. 9-1/8 in.In its letter dated July 17, 2013, the licensee provided a sketch depicting elevations Identified as Level 1,2 and 3, the level measurement range and the top of the tallest fuel storage rack. The NRC staff notes that Level 2 at an elevation of 20,3 ft. 9-1/8 in. is approximately 10 ft. above the top of the fuel rack. The staff also notes that the licensee designated Level 2 using the first of the two options described in NEI 12-02 for Level 2.NEi 12-02 states, in part, that Level 3 corresponds nominally (i.e., +/- 1 foot) to the highest point of any fuel rack seated in the spent fuel pool. Level 3 is defined in this manner to provide the maximum range of information to operators, decision makers and emergency response personnel.

V4 Page 2 of 3-6-The licensee stated In its OIP that Level 3 would be set at plant elevation 193 ft. 9-118 in., which is the nominal level of the highest fuel rack.In its letter dated July 17, 2013, the licensee provided a sketch depicting elevations identified as Level 1, 2 and 3, the level measurement range and the top of the tallest fuel storage rack. The NRC staff notes that Level 3 at an elevation of 193 ft. 9-1/8 in. as the highest point of any spent fuel storage rack seatd in the SFP.The licensee's proposed plan, with respect to identification of Levels 1, 2, and 3, appears to be consistent with NEI 12-02, as endorsed by the ISG.3.3 Design Feature~s:

Instruments Attachment 2 of Order EA-1 2-051, states, in part, that The instrumentation shall consist of a permanent, fixed primary instrument channel and a backup instrument channel. The backup instrument channel may be fixed or portable.

Portable instruments shall have capabilities that enhance the ability of trained personnel to monitor spent fuel pool water level under conditions that restrict direct personnel access to the pool, such as partial structural damage, high radiation levels, or heat and humidity from a boiling pool.NEI 12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3[instrumentation Design Features]

of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features].

In its OIP, the licensee stated that, for both Unit 1 and Unit 2, the primary and backup instrument channels will consist of fixed components.

The licensee also stated that the measured range will be continuous fromn the high pool level elevation of 219 ft. 0 in. to the top 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 as Level 1, 2 and 3 and the level measurement range. The NRC staff reviewed this sketch and notes that there is a slight variation on the measurement range identified in the licensee's OIP and on this sketch. In its OIP, the licensee stated that the measurement range would go from pool elevation of 219 ft. 0 in. to 193 9-118 in. However, the sketch shows the range goes from pool elevation of 219 ft. 3 in. to 194 ft. 1/8 in. The staff has identified this request as: RAl #1 Please identify the final SFP level instrumentation measurement range.The licensee's proposed plan, with respect to the number of channels and the range of the instrumentation for both of its SF Ps, appears to be consistent with NEI 12-02, as endorsed by the ISG.

Enclosure 2 to NL-1 3-1 460 ATTACHMAENT 1 SKETCH 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 lTTOMk NOTES EILEVATIONIS 40W ARE FOR BOTH UNITS V5 Page 1 ofl15 Aproe B Pat Procedure Version S. E. Prewitt .....Elcti. neain 17100-1 26.2 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number 12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88 ANNUNCIATOR RESPONSE INDEX DETECTOR NO.1 -RE-Q001 1 -RE-0002 1 -RE-0003 I -RE-0004 1 -RE-0005 1 -RE-0006 A-RE-0007A A-RE-0007B 1I-RE-0008 A-RE-0009A A-RE-0009B A-RE-0009C 1-RE-00l11 1 -RE-0013 A-RE-0014 A-RE-001 6 1-RE-0017A 1 -RE-001 7B 1 -RE-001 8 1 -RE-001 9 1 -RE-0020A 1 -RE-0020B 1 -RE-0021 1 -RE-0024A 1 -RE-0024B A-RE-0025 RADIATION MONITOR INDEX USE Control Room Containment

-Low Range Containment

-Low Range Containment Hatch Containment

-High Range Containment

-High Range Rad Chem Lab Sample Room Fuel Handling Bldg Decon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)

Seal Table Room Waste Gas Processing Waste Gas Processing Boron Recycle Liquid CCW Train A CCW Train B Waste Liquid SG Sample Liquid NSCW Train A NSCW Train B SG Blowdown Liquid Selected Cubical-Air Particulate Selected Cubical-Radiogas Aux Steam Condensate Return Liquid PAGE 9 10 12 14**16 18 20 22 24 26 28 31 33 35* 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 V5 Page 2 of 15 AproegBt~6 Gnrating LA Procedure Version ApoeBs. E. Prewitt Vogle Electric Gen Pant 17100-1 26.2 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND jPage Number 12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 7 of 88 ANNUNCIATOR RESPONSE INDEX RADIATION MONITOR INDEX DETECTOR NO.1 -RE-0039A 1 -RE-0039B 1 -RE-0724 1 -RE-081 0 1 -RE-0848 1-RE-1 950 A-RE-2532A A-RE-2532 B A-RE-2533A A-RE-2533B 1 -RE-2562A 1 -RE-2562B 1 -RE-2562C 1 -RE-2565A 1 -RE-2565B 1 -RE-2565C 1-RE-12116 1-RE-121 17 1-RE-I12442A 1-RE-i12442 B 1-RE-i12442C USE Waste Gas Decay Tank -Radiogas Waste Gas Compressor

& Catalytic Recombiner

-Radiogas N16 Rad Monitor SJAE Exhaust Rad Monitor Turbine Bldg Drains -Liquid ACCW -Liquid FHB -Radiogas FHB -Radiogas FHB -Radiogas FHB -Radiogas Containment

-Air Particulate Containment

-Passive Iodine Cartridge Containment Air -Radiogas Containment Vent -Particulate Containment Vent -Iodine Containment Vent -Radiogas Control Room Air In -Train A Control Room Air In -Train B Plant Vent Air Particulate (Low Range)Plant Vent Iodine Particulate (Low Range)Plant Vent Radiogas Particulate (Low Range)PAGE 38 40 42 45 48 50 54 56 58 60 62 64* 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 V5 Page 3 of 15 Approved By Votl Electric Geeatn Plant Procedure Version S. E. Prewitt vog.e ....e..... 171 00-1 26.2 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 14 of 88 ORIGIN SETPOINT Area Monitor As determined by Chemistry Department 1.0 PROBABLE CAUSE Increase in radiation level near Unit 1 Spent Fuel Pc Building.2.0 AUTOMATIC ACTIONS On the south wall of the Fuel Handling Building Spel door: a. Alarm horn on 1-RA-0008 sounds.b. Strobe light on 1-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONS Evacuate the Fuel Handling Building.1 -RE-0008 (High)in the Fuel Handling nt Fuel Pool Room near the Printed February 3, 2016 at 13:02 V5 Page 4 of 15 Approved By Version J.B SaneyVogtle Electric Generating Plant 11212.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 06/23/2014 RELATED DISPLAY CONSOLE QRM2 8 of 42 ANNUNCIATOR RESPONSE INDEX SRDC WIDWN. TITLE PAGE Al A2 A3 A4 A5 1-RE-2562A CNMT AIR -PARTICLES 10 A6 1-RE-2562C CNMT AIR -GAS 12 A7 A8 B1 1-RE-13119 MSL Gas 15 B2 1-RE-13120 MSL Gas 17 B3 1 -RE-0002 AREA 19 B4 1-RE-0005 High Range -Area 21 B5 1-RE-12116 In-Vent Gas 23 B6 A-RE-2532A In-Vent Gas 25 B7 A-RE-2532B In-Vent Gas 27 B8 C1 1-RE-13121 MSL Gas 29 C2 1-RE-i131 22 MSL Gas 31 C3 1 -RE-0003 AREA 33 C4 1-RE-0006 High Range Area 35 CS 1-RE-12117 In-Vent Gas 37 C6 A-RE-2533A In-Vent Gas 39 C7 A-RE-2533B In-Vent Gas 41 Printed February 3, 2016 at 13:11 V5 Page 5 of 15 Approved By "' Electri Geea PlantPrcdeVrso J.B. Stanley VogUe Generting Procedure 20.4io Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 19 of 42 WINDOW CDCA B3 ORIGIN Containment Low Range Area Monitor 1 -RE-0002 SETPOI NT As determined by Chemistry (15 mR/hr during refueling) 1 -RE-0002 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE i NOTES* During refueling operations indicates a fuel drop accident.

EJ* During power operation indicates possible loss of coolant accident.

0]2.0 High radiation in the Containment Building.AUTOMATIC ACTIONS Initiates Containment Building Ventilation Isolation.

INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm. If required, initiate evacuation of Containment.

Printed February 3, 2016 at 13:11 V5 Page 6 of 15 Appove ByGeeraing , Procedure Version J...tnlyvo

.Ele tri ..... -...a.n......

17102-1 20.4 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY IPage Number 06/23/2014 RELATED DISPLAY CONSOLE QRM2 j 25 of 42 WINDOW CDCA B6 ORIGIN Fuel Handling Building Effluent Radiogas Monitor ARE-2532A SETPOINT As determined by Chemistry Department (RED LAMP LIT)(HIGH)]1.0 PROBABLE CAUSE 2.0 1. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.

AUTOMATIC ACTIONS Switches the Normal Fuel Handling Building Ventilation to Accident Mode Ventilation.

INITIAL OPERATOR ACTIONS 3.0 Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5 Page 7 of 15 Approved By lcti Pat Procedure Version J.B. Stanley vgeGnrtn 112I2.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 06/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 27 of 42 WINDOW CDCA B7 ORIGIN SETPOINT_________

[A- RE-2532B Fuel Handling As determined I(RED LAMP LIT)Building Effluent by Chemistry j(HIGH)Radiogas Monitor DepartmentI ARE-2532BL_________

NOTE For other than HIGH conditions see Pages 5 and 6. 0]1.0 PROBABLE CAUSE 1. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.

2.0 AUTOMATIC ACTIONS Switches the Normal Fuel Handling Building Ventilation to Accident Mode Ventilation.

3.0 INITIAL OPERATOR ACTIONS Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5 Page 8 of 15 Approved By ..... E lectric GnrngPlant IPrcdeVrso J.B. Stanley Vogtle Generatingre17102.1 Veso20.4 Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY IPage Number 06/23/20 14 IRELATED DISPLAY CONSOLE QRM2 j 33 of 42 WINDOW CDCA C3 ORIGIN Containment Low Range Area Monitor 1 -RE-0003 SETPOINT As determined by Chemistry (15 mR/hr during refueling) 1 -RE-0003 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE NOTES* During refueling operations indicates a fuel drop accident.

EJ* During power operation indicates possible loss of coolant accident.

o]2.0 High radiation in the Containment Building.AUTOMATIC ACTIONS Initiates Containment Building Ventilation isolation.

INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm. If required, initiate evacuation of Containment.

Printed February 3, 2016 at 13:11 V5 Page 9 of 15 Approved:

8yiGenerating an Procedure Version J.B. Stanley vog,_e ElectricPat-._

212.Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 06/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 39 of 42 WINDOW CDCA C6 ORIGIN Fuel Handling Building Effluent Radiogas Monitor ARE-2533A SETPOINT As determined by Chemistry Department SA-RE-2533A (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE 1. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.

AUTOMATIC ACTIONS 2.0 Switches the Normal Fuel Handling Building Ventilation to Accident Mode Ventilation.

INITIAL OPERATOR ACTIONS 3.0 Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5 Page 10 of 15 Approved By Gene rating anrceueVeso J.B. Stanley Vogtle Electric Plant I Procedure 20.4io Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY P age Number 06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 41 of 42 WINDOW CDCA C7 ORIGIN Fuel Handling Building Effluent Radiogas Monitor ARE-2533B SETPOINT As determined by Chemistry Department (RED LAMP LIT)(HIGH)1 1.0 PROBABLE CAUSE 2.0 1. High airborne radioactivity in the Fuel Handling Building.2. Equipment malfunction.

AUTOMATIC ACTIONS Switches the Normal Fuel Handling Building Ventilation to Accident Mode Ventilation.

INITIAL OPERATOR ACTIONS 3.0 Evacuate the Fuel Handling Building.Printed February 3, 2016 at 13:11 V5 Page 11 of 15 ApproveVBytle Electric Gnrtg Plant AIProcedure Version S. E. Prewitt ....g.e.Generat.ng..

17100-2 20.1 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number 12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 77 ANNUNCIATOR RESPONSE INDEX RADIATION MONITOR INDEX DETECTOR NO.2-RE-000 1 2-RE-0002 2-RE-0003 2-RE-0004 2-RE-OD05 2-RE-0006 2-RE-0008 2-RE-DO011 2-RE-001 3 2-RE-001 7A 2-RE-D01 7B 2-RE-D01 8 2-RE-DO019 2-RE-0020A 2-RE-0020B 2-RE-002 1 2-RE-0024A 2-RE-0024B 2-R E-0039A 2-RE-0039B 2-RE-0039C 2-R E-0 724 2-RE-081 0 2-RE-0848 2-RE-i1950 2-R E-2562A USE Control Room Containment

-Low Range Containment

-Low Range Containment Hatch Containment

-High Range Containment

-High Range Fuel Handling Bldg Seal Table Room Waste Gas Processing CCW Train A CCW Train B Waste Liquid SG Sample Liquid NSCW Train A NSCW Train B SG Blowdown Liquid Selected Cubical-Air Pa rticu late Selected CubicaI-Radiogas Waste Gas Decay Tank -Radiogas Waste Gas Compressor

-Radiogas Catalytic Recombiner

-Radiogas N16 Monitor SJAE Exhaust Rad Monitor Turbine Bldg Drains -Liquid ACCW -Liquid Containment

-Air Particulate PAGE 8 9 11 13 15 17 19 21 23 26 28 30 33 35 37 39 42 45 47* 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 V5 Page 12 of 15 Approved BYs E.Genratigitt Procedure Version S...E....

..w... .....t.e Electric.....

Plant. ..... 17100-2 20.1 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/10/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 11 of 77 ORIGIN SETPOINT Area Monitor As determined by Chemistry Department 1.0 PROBABLE CAUSE Increase in radiation level near Unit 2 Spent Fuel Pc Building.2.0 AUTOMATIC ACTIONS On the south wall of the Fuel Handling Building Spel door: a. Alarm horn on 2-RA-0008 sounds.b. Strobe light on 2-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONS Evacuate the Fuel Handling Building.2-RE-0008 (High)in the Fuel Handling nt Fuel Pool Room near the Printed February 3, 2016 at 13:22 V5 Page 13 of 15 Approve.By....

Plant Procedure Version J. B. Stanley voteEeti ~nrtn in 17102-2 16.3 Effective Date I ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 8 of 34 ANNUNCIATOR RESPONSE INDEX SRDC TTEPG WINDOW NO. TTEPG Al A2 A3 A4 A5 2-RE-2562A CNMT AIR -PARTICLES 10 A6 2-RE-2562C CNMT AIR -GAS 12 A7 A8 B1 2-RE-13119 MSL Gas 15 B2 2-RE-I13120 MSL Gas 17 B3 2-RE-0002 AREA 19 B4 2-RE-0005 High Range -Area 21 B5 2-RE-121 16 In-Vent Gas 23 B6 B7 B8 Cl 2-RE-13121 MSL Gas 25 C2 2-RE-i13122 MSL Gas 27 C3 2-RE-0003 AREA 29 C4 2-RE-0006 High Range Area 31 C5 2-RE-12117 In-Vent Gas 33 C6 C7 Printed February 3, 2016 at 13:28 V5 Page 14 of 15 Approved By V .. ...... .Procedure Version J. B. Stanley v ogtue Electric Generating Plant ~ 17102-2 16.3 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 19 of 34 WINDOW CDCA B3 ORIGIN Containment Low Range Area Monitor 2-RE-0002 SETPOINT As determined by Chemistry (15 mR/hr during refueling)

[2-RE-0002 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE NOTES* During refueling operations indicates a fuel drop accident.

E* During power operation indicates possible loss of coolant accident.

[2.0 High radiation in the Containment Building.AUTOMATIC ACTIONS Initiates Containment Building Ventilation Isolation.

INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm. If required, initiate evacuation of Containment.

Printed February 3, 2016 at 13:28 V5 Page 15 of 15 Approved By Genrain AIProcedure Version J. B. Stanley Vogtle Electric eertn Plant -17102-2 16.3 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 11/4/13 RELATED DISPLAY CONSOLE QRM2 29 of 34 WINDOW CDCA C3 ORIGIN Containment Low Range Area Monitor 2-RE-0003 SETPOINT As determined by Chemistry (15 mR/hr during refueling) 2-RE-0003 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE NOTES* During refueling operations indicates a fuel drop accident.

[L* During power operation indicates possible loss of coolant accident.2.0 High radiation in the Containment Building.AUTOMATIC ACTIONS Initiates Containment Building Ventilation Isolation.

INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm. If required, initiate evacuation of Containment.

p t'rinted -ebruary 3, 2016 at 13:28 V6 Page 1 of 4 Approved By _

~Procedure Version S. E. Prewitt Vogtle Elcri enerating Pln1i17100-1 26.2 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number 12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88 ANNUNCIATOR RESPONSE INDEX DETECTOR NO.1 -RE-0001 1 -RE-0002 1 -RE-0003 1 -RE-0004 1 -RE-0005 1 -RE-0006 A-RE-0007A A-RE-0007B 1 -RE-Q008 A-RE-0009A A-RE-0009B A-RE-0009C 1-RE-00l11 1-RE-0013 A-R E-001 4 A-RE-001 6 1 -RE-001 7A 1-RE-0017B 1-RE-001 8 1-RE-001 9 1 -RE-0020A 1 -RE-0020B 1 -RE-0021 1 -RE-0024A 1 -RE-0024B A-RE-0025 RADIATION MONITOR INDEX USE Control Room Containment

-Low Range Containment

-Low Range Containment Hatch Containment

-High Range Containment

-High Range Rad Chem Lab Sample Room Fuel Handling Bldg Decon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)

Seal Table Room Waste Gas Processing Waste Gas Processing Boron Recycle Liquid CCW Train A CCW Train B Waste Liquid SG Sample Liquid NSCW Train A NSCW Train B SG Blowdown Liquid Selected Cubical-Air Particulate Selected CubicaI-Radiogas Aux Steam Condensate Return Liquid PAGE 9 10 12 14 16 18 20 22 24 26 28 31 33 35* 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 V6 Page 2 of 4 Approved By Ge ti IProcedure Version S. E. Prewitt v .g.e Elcti.Gneain.Pat 17100-1 26.2 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 9 of 88 ORIGIN SETPOINT Area Monitor As determined by Chemistry Department 1.0 PROBABLE CAUSE Deteriorating radiological conditions in the Control F 2.0 AUTOMATIC ACTIONS NONE 3.0 INITIAL OPERATOR ACTIONS NONE 4.0 SUBSEQUENT OPERATOR ACTIONS 1. Request Health Physics to survey Control Ri level.2. Obtain detector trend data per 13508-1, "Ra 3. Refer to NMP-EP-1 10, "Emergency Classific Instructions".

4. Monitor the channel for further changes.5* IF sampling and analysis determine the chan request Chemistry to deactivate the channel 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE

REFERENCES:

AX4DB206-2, 1X5DS2A02 (High)toom.oom area to verify radiation diation Monitoring System".*ation And Implementing reel has malfunctioned, Printed February 3, 2016 at 14:28 V6 Page 3 of 4 Approveds EPrwtBY Generating..

...... Procedure170

.Version2 1 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 6 of 77 ANNUNCIATOR RESPONSE INDEX DETECTOR NO.2-RE-0001 2-R E-0002 2-R E-0003 2-RE-0004 2-RE-0005 2-RE-0006 2-R E-0008 2-RE-0011I 2-RE-001 3 2-RE-001 7A 2-RE-001 7B 2-RE-001 8 2-RE-001 9 2-RE-0020A 2-RE-0020B 2-R E-002 1 2-R E-0024A 2-RE-0024B 2-R E-0039A 2-RE-0039B 2-RE-0039C 2-RE-0724 2-RE-081 0 2-R E-0 848 2-RE-I1950 2-R E-2562A RADIATION MONITOR INDEX USE Control Room Containment

-Low Range Containment

-Low Range Containment Hatch Containment

-High Range Containment

-High Range Fuel Handling Bldg Seal Table Room Waste Gas Processing CCW Train A CCW Train B Waste Liquid SG Sample Liquid NSCW Train A NSCW Train B SG Blowdown Liquid Selected Cubical-Air Particulate Selected CubicaI-Radiogas Waste Gas Decay Tank -Radiogas Waste Gas Compressor

-Radiogas Catalytic Recombiner

-Radiogas N16 Monitor SJAE Exhaust Rad Monitor Turbine Bldg Drains -Liquid ACCW -Liquid Containment

-Air Particulate PAGE 8 9 11 13 15 17 19 21 23 26 28 30 33 35 37 39 42 45 47* 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 V6 Page 4 of 4 Approved By * ...Procedure Version S. E. Prewitt Vogtle Electri c Generating Plant E. I171 00-2 20.1 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 8 of 77 ORIGIN SETPOINT_________

2-RE-0001 Area Monitor As determined by (High)Chemistry Department NOTE For other than HIGH conditions see Pages 4 and 5. 0]1.0 PROBABLE CAUSE Deteriorating radiological conditions in the Control Room.2.0 AUTOMATIC ACTIONS NONE 3.0 INITIAL OPERATOR ACTIONS NONE 4.0 SUBSEQUENT OPERATOR ACTIONS 1. Request Health Physics to survey Control Room area to verify radiation level.2. Obtain detector trend data per 13508-2, "Radiation Monitoring System".3. Refer to NMP-EP-1 10, "Emergency Classification And Implementing Instructions".

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 ACTIONS NONE END OF SUB-PROCEDURE

REFERENCES:

AX4DB206-2, 2X5DS2A02 Printed February 3, 2016 at 14:32 V7 Page 1 of 6 Approved By I e eatn Procedure Version C. H. Willijams, Jr. j Vogtle Electric GeeaigPlant I10513.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number 6/21/13 IPANEL 1A2 ON MCB I 3 of 67 (1 )(2'i (3'i (4'lA B C D E F LIQUID PROCESS NSSS FHB EXH NIS GROUP 1 SPENT FUEL PANEL TROUBLE PROT GR I RAD MONITOR CHANNEL I MONITOR LIGHT PIT HI TEMP BYPASS EQUIP TROUBLE BYPASS COMP OFF NORM GAS PROCESS NSSS INTMD NIS GROUP 2 BYPASS CNMT PANEL TROUBLE PROT GR II RADIATION CHANNEL II MONITOR LIGHT VENT ISO BYPASS ALARM BYPASS COMP OFF NORM HI RAD TEST BORON RECYCLE NSSS HIGH NIS GROUP 3 SAFEGUARDS CAB PANEL TROUBLE PROT GR III RADIATION CHANNEL 111 MONITOR LIGHT TRAIN A BYPASS ALARM BYPASS COMP OFF NORM TEST PCS CABINET NSSS NIS GROUP 4 SAFEGUARDS CAB DOORS OPEN PROT GR IV CHANNEL IV MONITOR LIGHT TRAIN B BYPASS BYPASS COMP OFF NORM TEST PCS CABINETS SPENT FUEL PIT ANNUNCIATOR AMSAC GROUP 5 PROT SYSTEM PWR SUPPLY LO LEVEL DC SOURCE TROUBLE MONITOR LIGHT TRAIN A FAILURE SUPPLY FAILURE COMP OFF NORM TROUBLE PROCESS PROT SPENT FUEL ANNUNCIATOR ANNUNCIATOR ANNUNCIATOR PROT SYSTEM SET VIOLATED PIT HI LEVEL SYSTEM DC SYSTEM ON SYSTEM TRAIN B>1 DOOR OPEN SUPPLY FAILURE ALTN SUPPLY DC GROUND TROUBLE Printed February 2, 2016 at 16:24 Printed February 2, 2016 at 16:24 V7 Page 2 of 6 Approved By .............. l l rcGenerating Plroedr Vrso C. H. Williams, Jr. PrtoEecredPanure100-34.2io Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number 6/21/13 PANEL 1A2 ON MCB5of6 ANNUNCIATOR WINDOW NO.E01 E02 E03 E04 EQ5 E06 F0 1 F02 F03 F04 F05 F06 TITLE PCS CABINETS PWR SUPPLY FAILURE SPENT FUEL PIT LO LEVEL ANNUNCIATOR DC SOURCE SUPPLY FAILURE AMSAC TROUBLE GROUP 5 MONITOR LIGHT COMP OFF NORM PROT SYSTEM TRAIN A TROUBLE PROCESS PROT SET VIOLATED >1 DOOR OPEN SPENT FUEL PIT HI LEVEL ANNUNCIATOR SYSTEM DC SUPPLY FAILURE ANNUNCIATOR SYSTEM ON ALTN SUPPLY ANNUNCIATOR SYSTEM DC GROUND PROT SYSTEM TRAIN B TROUBLE PAGE 41 43 46 47 52 53 56 57 61 62 63 65 Printed February 2, 2016 at 16:24 V7 Page 3 of 6 Approved By og e ProcedurerVersion C. H. Williams, Jr. Vo e Eetric ~.ireaigPant Pr17005-1 34.2io Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number 6/21/13 PANEL 1A2 ON MOB I 43 of 67 WINDOW E02 ORIGIN SETPOINT_________

SPENT FUEL PIT 1-LSHL-625 217 feet elevation LO LEVEL 1.0 PROBABLE CAUSE 1. 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 Gate Seals.2.0 AUTOMATIC ACTIONS NONE 3.0 INITIAL OPERATOR ACTIONS NONE Printed February 2, 2016 at 16:24 V7 Page 4 of 6 Approved BYc H. ElectricPlant I Procedure Version C. H.W..l.m...J

.....e.eneatig 17005-2 28.1 Effective Date jANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number 6/21/13 IPANEL 2A2 ON MCB I 3 of 65 (1)(2)(3)(4)(5)(6)A B C D E F LIQUID PROCESS NSSS NIS GROUP 1 SPENT FUEL PANEL TROUBLE PROT GR ! CHANNEL I MONITOR LIGHT PIT HI TEMP BYPASS BYPASS COMP OFF NORM GAS PROCESS NSSS INTMD NIS GROUP 2 BYPASS CNMT PANEL TROUBLE PROT GR II RADIATION CHANNEL II MONITOR LIGHT VENT ISO BYPASS ALARM BYPASS COMP OFF NORM HI RAD TEST NSSS HIGH NIS GROUP 3 SAFEGUARDS CAB PROT GR III RADIATION CHANNEL MONITOR LIGHT TRAIN A BYPASS ALARM III BYPASS COMP OFF NORM TEST PCS CABINET NSSS NIS GROUP 4 SAFEGUARDS CAB DOORS OPEN PROT GR IV CHANNEL IV MONITOR LIGHT TRAIN B BYPASS BYPASS COMP OFF NORM TEST PCS CABINETS SPENT FUEL PIT ANNUNCIATOR AMSAC GROUP 5 PROT SYSTEM PWR SUPPLY LO LEVEL DC SOURCE TROUBLE MONITOR LIGHT TRAIN A FAILURE SUPPLY FAILURE COMP OFF NORM TROUBLE PROCESS PROT SPENT FUEL ANNUNCIATOR ANNUNCIATOR ANNUNCIATOR PROT SYSTEM SET VIOLATED PIT HI LEVEL SYSTEM DC SYSTEM ON SYSTEM TRAIN B>1 DOOR OPEN SUPPLY FAILURE ALTN SUPPLY DC GROUND TROUBLE Printed February 2, 2016 at 16:29 V7 Page 5 of 6 ANNUNCIATOR WINDOW NO.E01 E02 E03 E04 E05 E06 F01I F02 F03 F04 F05 F06 TITLE PCS CABINETS PWR SUPPLY FAILURE SPENT FUEL PIT LO LEVEL ANNUNCIATOR DC SOURCE SUPPLY FAILURE AMSAC TROUBLE GROUP 5 MONITOR LIGHT COMP OFF NORM PROT SYSTEM TRAIN A TROUBLE PROCESS PROT SET VIOLATED >1 DOOR OPEN SPENT FUEL PIT HI LEVEL ANNUNCIATOR SYSTEM DC SUPPLY FAILURE ANNUNCIATOR SYSTEM ON ALTN SUPPLY ANNUNCIATOR SYSTEM DC GROUND PROT SYSTEM TRAIN B TROUBLE PAGE 39 41 44 45 50 51 54 55 59 60 61 63 Printed February 2, 2016 at 16:29 V7 Page 6 of 6 Apoec. H. Williams,B Jr. i voge Elecltric Pl.. ant Prcdr17005-2 Veso28.1 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 05 ON Page Number 6/21/13 IPANEL 2A2 ON MCB I 41 of 65 WINDOW E02 ORIGIN SETPOINT_________

SPENT FUEL PIT1 2-LSHL-625 217 feet [LO LEVEL elevation

[__________

1.0 PROBABLE CAUSE 1. 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 Gate Seals.2.0 AUTOMATIC ACTIONS NONE 3.0 INITIAL OPERATOR ACTIONS NONE Printed February 2, 2016 at 16:29 V8 Page 1 of 18 ApprvedBygtle Procedure Version S. E. Prewitt .....e.E..ectric Generating Plant......

...... .. 171 00-1 26.2....Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/9/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 6 of 88 ANNUNCIATOR RESPONSE INDEX DETECTOR NO.1 -RE-0001 1 -RE-0002 1 -RE-0003 1 -RE-0004 1 -RE-0005 1 -RE-0006 A-RE-0007A A-RE-0007B 1 -RE-0008 A-RE-0009A A-RE-0009B A-RE-0009C 1-R E-0011I 1-RE-0013 A-RE-001 4 A-RE-001 6 1 -RE-001 7A 1 -R E-0017B 1 -RE-0018 1-RE-0019 1 -RE-0020A 1 -RE-0020B 1 -RE-0021 1 -RE-0024A 1 -RE-0024B A-R E-0025 RADIATION MONITOR INDEX USE Control Room Containment

-Low Range Containment

-Low Range Containment Hatch Containment

-High Range Containment

-High Range Rad Chem Lab Sample Room Fuel Handling Bldg Decon Station (Large Parts)Decon Station (Small Parts)Decon Station (Instruments)

Seal Table Room Waste Gas Processing Waste Gas Processing Boron Recycle Liquid CCW Train A CCW Train B Waste Liquid SG Sample Liquid NSCW Train A NSCW Train B SG Blowdown Liquid Selected Cubical-Air Particulate Selected CubicaI-Radiogas Aux Steam Condensate Return Liquid PAGE 9 10 12 14**k"**16 18 20**k 22 24 26 28 31 33 35* 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 V8 Page 2 of 18 Approved By ... W r'lUl Version S. E. Prewitt vou lcrcPat -171 00-1 26.2 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 10 of 88 ORIGIN SETPOINT Area Monitor As determined by Chemistry Department NOTE For other than HIGH conditions see Pages 4 and 5.1 -RE-0004 (High)1.0 2.0 3.0 4.0 PROBABLE CAUSE Increase in radiation level in the Containment Personnel Access Hatch.AUTOMATIC ACTIONS Outside the containment near the hatch: a. Alarm horn on 1-RA-0004 sounds, b. Strobe light on 1-RA-0004 blinks.INITIAL OPERATOR ACTIONS NONE SUBSEQUENT OPERATOR ACTIONS 1. Check for elevated radiation level in containment at 1 -RE-0002 and 1-RE-0003 at the SRDC.2. IF alarm is valid, warn personnel in containment to exit by way of the emergency escape hatchway.3. Notify Health Physics of the alarm and request survey of Containment Personnel 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 V8 Page 3 of 18 AE.Pproedit Byle Electric Geert Plant IProcedure Veso1 S.E rwt oge ~ nrugI171 00-1 26.2 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 1 12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 14 of 88 ORIGIN SETPOINT Area Monitor As determined by Chemistry Department 1.0 PROBABLE CAUSE Increase in radiation level near Unit 1 Spent Fuel Pc Building.2.0 AUTOMATIC ACTIONS On the south wall of the Fuel Handling Building Spe door: a. Alarm horn on I-RA-0008 sounds.b. Strobe light on I -RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONS Evacuate the Fuel Handling Building.1 -RE-0008 (High))ol in the Fuel Handling nt Fuel Pool Room near the Printed February 3, 2016 at 14:52 V8 Page 4 of 18 Approved By Version S. E. Prewitt ....Vogtle Electric Generating Plant 11012.Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/9/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 16 of 88 ORIGIN SETPOINT_________

1-RE-001 1 Area Monitor As determined by (High)" Chemistry Department NOTE For other than HIGH conditions see Pages 4 and 5. 0]1.0 PROBABLE CAUSE Increase in radiation level in the Seal Table Room on Level B Containment.

2.0 AUTOMATIC ACTIONS In the Incore Instrumentation Room: a. Alarm horn on 1 -RA-0011I sounds.b. Strobe light on 1 -RA-Ol11 blinks.3.0 INITIAL OPERATOR ACTIONS Evacuate the Incore Instrumentation Room.4.0 SUBSEQUENT OPERATOR ACTIONS 1. Notify Health Physics to determine the cause of the high radioactivity level.2. Restrict personnel access to the seal table area until the condition has been 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 V8 Page 5 of 18 Approved By

lcri ln Procedure Version J.B. Stanley , Vogtle EetcGenerating Plnt17102-1 20.4 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETW Page Number 06/23/20 14 RELATED DISPLAY CONSOLE QRM2 8 of 42 ANNUNCIATOR RESPONSE INDEX SRDC WINDOW NO.Al A2 A3 TITLE PAGE A4 A5 A6 A7 A8 B1 B2 83 B4 B5 B6 B7 B88 Cl C2 C3 C4 C5 C6 C7 1-RE-2562A CNMT AIR -PARTICLES 1-RE-2562C CNMT AIR -GAS 10 12 1-RE-I13119 MSL Gas 1-RE-I131 20 MSL Gas 1 -RE-0002 AREA 1-RE-0005 High Range -Area 1-RE-12116 In-Vent Gas A-RE-2532A In-Vent Gas A-RE-2532B In-Vent Gas 1-RE-i13121 MSL Gas 1-RE-I131 22 MSL Gas 1 -RE-0003 AREA 1-RE-0006 High Range Area 1-RE-i12117 In-Vent Gas A-RE-2533A In-Vent Gas A-RE-2533B In-Vent Gas 15 17 19 21 23 25 27 29 31 33 35 37 39 41 Printed February 3, 2016 at 15:08 V8 Page 6 of 18 AprvdB lcti ln rocedure Version J.B. Stanley I vge ~ nrin 112I2.Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 06/23/2014 RELATED DISPLAY CONSOLE QRM2 I 19 of 42 WINDOW CDCA B3 ORIGIN Containment Low Range Area Monitor 1 -RE-0002 SETPOINT As determined by Chemistry (15 mR/hr during refueling) 1 -RE-0002 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE NOTES* During refueling operations indicates a fuel drop accident.

0* During power operation indicates possible loss of coolant accident.

[]2.0 High radiation in the Containment Building.AUTOMATIC ACTIONS Initiates Containment Building Ventilation Isolation.

INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR, IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm. If required, initiate evacuation of Containment.

Printed February 3, 2016 at 15:08 V8 Page 7 of 18 Approved By ElcrcPat AProcedure Version J.B. Stanley .... ...g.....e. Generating.

..... .... .. ...17102-1 20.4 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 06/23/2014 RELATED DISPLAY CONSOLE QRM2 33 of 42 ORIGIN Containment Low Range Area Monitor 1 -RE-0003 SETPOINT As determined by Chemistry (15 mR/hr during refueling)

WINDOW CDCA C3 1 -RE-0003 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE NOTES* 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 ACTIONS 2.0 Initiates Containment Building Ventilation isolation.

INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm. If required, initiate evacuation of Containment.

Printed February 3, 2016 at 15:08 V8 Page 8 of 18 AprvdBj.B.

Stanley ....Vogtle Electric nraigPlant Prceur171 02-1 Veso20.4 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 06/23/20 14 RELATED DISPLAY CONSOLE QRM2 I 21 of 42 WINDOW CDCA B4 ORIGIN Containment High Range Area Monitor 1 -RE-0005 SETPOINT 100 R/hr 1 -RE-0005 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE 2.0 High radiation in Containment.

AUTOMATIC ACTIONS NONE INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm and sample Containment atmosphere.

if required, initiate evacuation of Containment.

Printed February 3, 2016 at 15:08 V8 Page 9 of 18 Approved BY.B GeneraingyA P rc~edure Version1 J.B...Stanley..vogt.e Electric Plant....

...... ...17102-1 20.4 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 1 06/23/2014 IRELATED DISPLAY CONSOLE QRM2 I 35 of 42 WINDOW CDCA C4 ORIGIN SETPOINT Containment High Range Area Monitor 1 -RE-0006 100 R/hr 1 -RE-0006 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE 2.0 High radiation in the Containment.

AUTOMATIC ACTIONS NONE INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm and sample Containment atmosphere.

if required, initiate evacuation of Containment.

Printed February 3, 2016 at 15:08 V8 Page 10 of 18 Procedure Version 17100-2 20.1 nber 6 of 77 ANNUNCIATOR RESPONSE INDEX RADIATION MONITOR INDEX DETECTOR NO.2-R E-000 1 2-RE-0002 2-RE-0003 2-RE-0004 2-RE-0005 2-R E-0006 2-RE-0008 2-RE-0011I 2-RE-001 3 2-RE-001 7A 2-RE-001 7B 2-RE-001 8 2-RE-001 9 2-R E-0020A 2-R E-0020 B 2-R E-002 1 2-R E-0024A 2-RE-0024B 2-RE-0039A 2-RE-0039B 2-RE-0039C 2-RE-0724 2-RE-081 0 2-RE-0848 2-RE-I1950 2-R E-2562A USE Control Room Containment

-Low Range Containment

-Low Range Containment Hatch Containment

-High Range Containment

-High Range Fuel Handling Bldg Seal Table Room Waste Gas Processing CCW Train A CCW Train B Waste Liquid SG Sample Liquid NSCW Train A NSCW Train B SG Blowdown Liquid Selected Cubical-Air Particulate Selected CubicaI-Radiogas Waste Gas Decay Tank -Radiogas Waste Gas Compressor

-Radiogas Catalytic Recombiner

-Radiogas N16 Monitor SJAE Exhaust Rad Monitor Turbine Bldg Drains -Liquid ACCW -Liquid Containment

-Air Particulate PAGE 8 9 11 13 15 17 19 21 23 26 28 30 33 35 37 39 42 45 47* 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 V8 Page 11 of 18 Procedure Version 17100-2 20.1 Page Number 9 of 77 ORIGIN SETPOINT Area Monitor As determined by Chemistry Department NOTE For other than HIGH conditions see Pages 4 and 5.2-RE-0004 (High)1.0 2.0 3.0 4.0 PROBABLE CAUSE Increase in radiation level in the Containment Personnel Access Hatch.AUTOMATIC ACTIONS Outside the containment near the hatch: a. Alarm horn on 2-RA-0004 sounds.b. Strobe light on 2-RA-0004 blinks.INITIAL OPERATOR ACTIONS NONE SUBSEQUENT OPERATOR ACTIONS 1. Check for elevated radiation level in containment at 2-RE-0002 and 2-RE-0003 at the SRDC.2. IF alarm is valid, warn personnel in containment to exit by way of the emergency escape hatchway.3. Notify Health Physics of the alarm and request survey of Containment Personnel 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 V8 Page 12 of 18 Approveds EPrwtBY 'og Elect$ric ln Procedure Version S.E rwt ogi eeaig17100-2 20.1 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND Page Number 12/10/12 EFFLUENT RADIATION MONITORING SYSTEM (RMS) 11 of 77 ORIGIN SETPOINT Area Monitor As determined by Chemistry Department 1.0 PROBABLE CAUSE Increase in radiation level near Unit 2 Spent Fuel Pc Building.2.0 AUTOMATIC ACTIONS On the south wall of the Fuel Handling Building Spe door: a. Alarm horn on 2-RA-0008 sounds.b. Strobe light on 2-RA-0008 blinks.3.0 INITIAL OPERATOR ACTIONS Evacuate the Fuel Handling Building.2-RE-0008 (High))ol in the Fuel Handling nt Fuel Pool Room near the Printed February 3, 2016 at 14:58 V8 Page 13 of 18 Approveds EPrwtBY .... Gen Procedure Version S. EPr.......t..Eletr.

Generatin Plant ...... 171 00-2 20.1 Effective Date ANNUNCIATOR RESPONSE PROCEDURE FOR THE PROCESS AND IPage Number 12/10/12 I EFFLUENT RADIATION MONITORING SYSTEM (RMS) I 13 of 77 ORIGIN SETPOINT Area Monitor As determined by Chemistry Department NOTE For other than HIGH conditions see Pages 4 and 5.2-RE-00l11 (High)1.0 2.0 3.0 4.0 PROBABLE CAUSE Increase in radiation level in the Seal Table Room on Level B Containment.

AUTOMATIC ACTIONS In the Incore Instrumentation Room: a. Alarm horn on 2-RA-0011 sounds.b. Strobe light on 2-RA-011I blinks.INITIAL OPERATOR ACTIONS Evacuate the Incore Instrumentation Room.SUBSEQUENT OPERATOR ACTIONS 1. Notify Health Physics to determine the cause of the high radioactivity level.2. Restrict personnel access to the seal table area until the condition has been 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 V8 Page 14 of 18 Approved By Vogtl Electric GeeaigPlant

& Procedure Version J. B. Stanley ...eGeertig 17102-2 16.3 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 11/4/13 RELATED DISPLAY CONSOLE QRM2 I 8 of 34 ANNUNCIATOR RESPONSE INDEX SRDC TTEPG WINDOW NO. TTEPG Al A2 A3 A4 A5 2-RE-2562A CNMT AIR -PARTICLES 10 A6 2-RE-2562C CNMT AIR -GAS 12 A7 A8 81 2-RE-13119 MSL Gas 15 B2 2-RE-13120 MSL Gas 17 B3 2-RE-0002 AREA 19 B4 2-RE-0005 High Range -Area 21 B5 2-RE-12116 In-Vent Gas 23 B6 87 B88 Cl 2-RE-13121 MSL Gas 25 C2 2-RE-I131 22 MSL Gas 27 C3 2-RE-0003 AREA 29 C4 2-RE-0006 High Range Area 31 C5 2-RE-12117 In-Vent Gas 33 C6 C7 Printed February 3, 2016 at 15:18 V8 Page 15 of 18 ApprovedBytric Generating Pln IProcedure Version J.pBpStanedy I Vogtle EetiPln -17102-2 16.3 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 19 of 34 WINDOW CDCA B3 ORIGIN Containment Low Range Area Monitor 2-RE-0002 SETPOINT As determined by Chemistry (15 mR/hr during refueling) 2-RE-0002 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE NOTES* During refueling operations indicates a fuel drop accident.* During power operation indicates possible loss of coolant accident.

LI 2.0 High radiation in the Containment Building.AUTOMATIC ACTIONS Initiates Containment Building Ventilation Isolation.

INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm. If required, initiate evacuation of Containment.

Printed February 3, 2016 at 15:18 V8 Page 16 of 18 Approved By " 'Eectric GeeaigPlant

& Procedure Version J. B. Stanley , Vogtle Geertig,17102-2 16.3 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 11/4/13 RELATED DISPLAY CONSOLE QRM2 29 of 34 ORIGIN Containment Low Range Area Monitor 2-RE-0003 SETPOINT As determined by Chemistry (15 mR/hr during refueling)

WINDOW CDCA C3 2-RE-0003 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE NOTES* During refueling operations indicates a fuel drop accident.

L* During power operation indicates possible loss of coolant accident.

[2.0 High radiation in the Containment Building.AUTOMATIC ACTIONS Initiates Containment Building Ventilation Isolation.

INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm. If required, initiate evacuation of Containment.

Printed February 3, 2016 at 15:18 V8 Page 17 of 18 Approvedgtle Electric G~eaigPlantPrcde Vrso ApoeJ. B. Stanleyy vog..Geeratng 17102-2Prcr Veso16.3 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 11/4/13 IRELATED DISPLAY CONSOLE QRM2 I 21 of 34 WINDOW CDCA B4 ORIGIN Containment High Range Area Monitor 2-RE-0005 SETPOINT 100 R/hr 2-RE-0005 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE 2.0 High radiation in Containment, AUTOMATIC ACTIONS NONE INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR IF appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplan ned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm and sample Containment atmosphere.

If required, initiate evacuation of Containment.

Printed February 3, 2016 at 15:18 V8 Page 18 of 18 Approved By vogtle Geneirating nt....17102-2 Verson3 Effective Date ANNUNCIATOR RESPONSE PROCEDURES FOR THE SAFETY Page Number 11/4/13 IRELATED DISPLAY CONSOLE QRM2 31 of 34 WINDOW CDCA C4 ORIGIN Containment High Range Area Monitor 2-RE-0006 SETPOINT 100 R/hr 2-RE-0006 (RED LAMP LIT)(HIGH)1.0 PROBABLE CAUSE High radiation in the Containment.

AUTOMATIC ACTIONS 2.0 NONE INITIAL OPERATOR ACTIONS 3.0 1. Initiate evacuation of Containment IF the alarm is due to unexpected or unexplained radiation increases, OR if appropriate HP controls are NOT in place for the radiological conditions indicated.

2. IF the alarm is due to expected radiation increases from preplanned evolutions AND appropriate HP controls are in place, THEN request HP and Chemistry to investigate the cause of alarm and sample Containment atmosphere.

if required, initiate evacuation of Containment.

Printed February 3, 2016 at 15:18 Vogtle Electric Generating Plant Units 1 and 2 License Amendment Request for Changes to Emergency Action Level Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant Enclosure 4 Vogtle EAL Verification and Validation Documents Vogtle EAL V&V Documentation Index.V&V# Description

,. ,,IC IThreshold RCS Modes/Temperatures -TS Reference (Table 1.1-1) EAL Basis Section 1.5 1 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 X6CNAJ15 Radiation Monitor Calculations:

RE-0018 RUI (1) (2)RE-0021 RE-0848 ARE-0014 2 ~RE- 12839 RE-12442C RE-12444C Caic X6CNAJ15 Radiation Monitor Calculation:

RE-005 CGI1 (2)b RE-006 CS1 (3)b FCB L3A FCB L3A RCSB L3A RCSB L3A Caic X6CNA15 CB PL3A CB PL3A ODCM/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-002/003 5 ARE-2532 A/B ARE-2533 A/B Annunciator Response Procedure (Control Room) RA3 (1)6

Reference:

RE-001 Annunciator Response Procedure (SFP Level) RU2 (1)a 7 Reference Annunciator Display: ALB05 E02 (SFP Lo Level)Radiation Monitor Information:

RE-008 RU2 (1)b RE-002 RE-003 8 RE-004 RE-005 RE-006 RE-001 1 ____RVLIS Indications/Displays (RVLIS) CG1 (1)a 9CS1 (1)b (2)b CAl (1)Calc X6CNA5 15___Containment Sump/Reactor Coolant Drain Tank CG 1 (2)b 10 (RCDT)/Waste Holdup Tank (WHiT) references (FSAR) CS 1 (3)b 10CA1 (2)b_____CU1 (2)b 2/22/2016 Page 1 of 2 Vogtle EAL V&V Documentation Index V&V# Description IC Threshold H-2 Concentration

(> 6%) -calculation/reference CG 1 (1)b (2)c Calc X6CNA 15 CB PL4B CB PL4B Containment Pressure

Reference:

CG1 (1)b (2)c 12 > 13 psig with Containment Closure established

> 52 psig with TS Containment Integrity Intact Cale X6CNAJ15 Emergency Buses Drawing CA2 (1)CU2 (1)a SG1 (1)a 13 SG8 (1)a SS1 (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 15 CSFST Procedure FCB PL1A FCB PLIA RCSB PL1B RCSB PL1 B FCB L2A FCB L2A FCB PL2A FCB PL2A FCB PL2B FCB PL2B 16 RCSB PL2A RCSB PL2A CB PL2A CB PL2A CB PL4A CB PL4A CB PL4C.1 CB PL4C.1 SG1 (1)b SS5 (1)c Seismic 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 3.4.16 RCS Operational LeakageSU(1(2 20 54()2 TS 3.4.13 21 Containment Pressure Reference (52 psig) SU7 (2)a 2/22/ 20 16 Page 2 of 2 Vl Page 1 of 1 Definitions 1.1 Table 1.1-1 (page 1 of 1)MODES% RATEDAVERAGE REACTVITY THERMAL REACTOR COOLANT CONDTIO POWER(a) TEMPERATURE (0 F)1 Power Operation

_> 0.99 > 5 NA 2 Startup s 5 NA 3 Hot Standby < 0.99 NA > 350 4 Hot Shutdown(b)

< 0.99 NA 350 > Tavg > 200 5 Cold Shutdown(b)

< 0.99 NA _< 200 6 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 2 1,.1-7 Amendment No. 96 (Unit 1)Amendment No. 74 (Unit 2)

V2 See NL-1 5-1 898 Enclosure 3 SOUTHERN A-L ~ .a I.?Southern Nuclear Design Calculation Calculation Number: )(6cNA1 5 Plant:lVocat Electric Generatina Plant Unit: 0] 1 0] 2 ix] 1 & 2 IDisci~line:i Mechanical Title: NEI 99-01 Rev 6 EAL Calculations

Subject:

Emergency IAction Level Setpoints Purpose)I Objective:

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

.. .. # of (Computer Printouts.

Technical Papers, Sketches.

Pages Correspondence)

Purpose .....1 A -SNC EP Concurrence

...1 Criteria ...........

B B- Reserved 0 Conclusion

-3 'C -"References' from X6CNAI4 31 Design Inputs -6 D -"TEDE and Thyroid CDE Calculations 19 Assumptions

..... 18 E -Shielding Calculations 29 References 22 F -Evaluation of 52 psig Pressure on Mechanical 14 Penetrations____

Method of Solutions 26 G -References"'from X6CNA16 22 Body of Calculation 31 "H -VEGP 1 EAL Thresholds 7 I -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 16 Total # of Pages including cover sheet & 22 Attachments Nuclear Quality Level 0 [ Safety-Related IXI .. Safety Significant

....03 Non- Safety --Significant

'Version Record ViinOriginator Reviewer Approval 'I "APproval 2 INo.t Description j ZW .Io.j M AIIoI I I Calculation of EAL Thresholds to support NEI 99-01 Rev. 6 Guidance.1.0~j4~ADC 3~t /2--i i~k.~~1iA4 I NMP-ES-039-F01 V4,0 M-S-3-O NMP-ES-039-001 V3 Page 1 of 1 VEGP ODCM Figure 4-1. Terrestrial Stations Near Site Boundary 4-16 4-16 VER 30 V4 Page 1 of 3-5-rIn Its letter dated July 17, 2013, the licensee stated, in part, that Level 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 line that is at approximately 21 4-1 1". Two trains supply Unit 1 and Unit 2 spent fuel pool cooling water. When adjusted for saturated steam conditions, the pool level needed to meet the NPSH required Is 214"-6" for Train A and 219'-6" for Train B but only one train is required for operation.

Thus, the two points described in NEI 12-02 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 selects Level 1 as 217'-0" since it is the normal low level set point for the SFP Cooling system.The NRC staff notes that Level 1 at 217 ft. 0 in. Is adequate for normal SFP cooling system operation; it is also sufficient for Net Positive Suction Head (NPSH) and represents the higher of the two points described above.NEi 12-02 states, in part, that Level 2 represents the range of water level where any necessary operations in the vicinity of the spent fuel pool can be completed without significant dose consequences from direct gamma radiation from the stored spent fuel. Level 2 is based on either of the following:

10 feet (+1- 1 foot) above the highest point of any fuel rack seated in the spent fuel pools, or* a designated level that provides adequate radiation shielding to maintain personnel radiological dose levels within acceptable limits while performing local operations in the vicinity of the pool. ThIs level shall be based on either plant-specific or appropriate generic shielding calculations, considering the emergency conditions that may apply at the time and the scope of necessary local operations, including installation of portable SFP instrument channel components.