Text

Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 1 of 4
	ML16071A126
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: ML16071A126 (42)
	v • d • e

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant Units 1 and 2;Edwin I. Hatch Nuclear Plant Units 1 and 2;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 2 Deviations and Differences Matrix Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant Units 1 and 2 License Amendment Request for Changes to Emergency Action Level Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant Enclosure 2 Farley Deviations and Differences Matrix NEI 99-01 Rev 6 Deviations and Differences Joseph M. Farley Nuclear Plant -Units I and 2 Table of Contents Generic Differences..............................................................

1 RGI: Initiating Conditions......................................................

2 RG2: Initiating Conditions......................................................

3 RS1: Initiating Conditions.......................................................

4 RS2: Initiating Conditions.......................................................

5 RAl: Initiating Conditions......................................................

6 RA2: Initiating Conditions......................................................

7 RA3: Initiating Conditions......................................................

8 RUl: Initiating Conditions.....................................................

10 RU2: Initiating Conditions.....................................................

12 CGI: Initiating Conditions...................................................13..

CS 1: Initiating Conditions

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16 CAl: Initiating Conditions.....................................................

18 CA2: Initiating Conditions.....................................................

19 CA3: Initiating Conditions.....................................................

20 CA6: Initiating Conditions.....................................................

22 CUl: Initiating Conditions.....................................................

24 CU2: Initiating Conditions.....................................................

25 CU3: Initiating Conditions.....................................................

26 CU4: Initiating Conditions.....................................................

27 CU5: Initiating Conditions.....................................................

28 E-HUI: Initiating Conditions..................................................

29 PWR Fission Product Barriers Matrix -Initiating Conditions/Thresholds

..3 1 1. RCS or SG Tube Leakage.......................................

31 2. Inadequate Heat Removal.......................................

33 3. RCS Activity!/

Containment Radiation

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35 4. Containment Integrity or Bypass ...............................

36 5. Other Indications

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38 6. Emergency Director Judgment .................................

38 HG 1: Initiating Conditions

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40 HG7: Initiating Conditions....................................................

41 HS 1: Initiating Conditions

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42 HS6: Initiating Conditions

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43 HS7: Initiating Conditions

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44 HAl: Initiating Conditions....................................................

45 HA5: Initiating Conditions....................................................

46 HA6: Initiating Conditions....................................................

47 HA7: Initiating Conditions....................................................

48 HUl: Initiating Conditions....................................................

49 HU2: Initiating Conditions....................................................

50 HU3: Initiating Conditions....................................................

51 HU4: Initiating Conditions....................................................

52 HU7: Initiating Conditions....................................................

54 SG1: Initiating Conditions

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55 SG8: Initiating Conditions

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56 SSI1: Initiating Conditions

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57 SS5: Initiating Conditions

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58 SS8: Initiating Conditions

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59 SAl: Initiating Conditions

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60 SA2: Initiating Conditions

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61 SA5: Initiating Conditions

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63 SA9: Initiating Conditions

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64 SUl: Initiating Conditions

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65 SU2: Initiating Conditions

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66 SU3: Initiating Conditions

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67 SU4: Initiating Conditions

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68 SU5: Initiating Conditions

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69 SU6: Initiating Conditions

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70 SU7: Initiating Conditions

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71 Uspesdi A fo theoradoogiale Sieffluentfiradeiaitions leelasaporae L~eleteU 0 wV reIeren1es Uses R for the radiological effluent/radiation level ICs Instrument setpoint readings used as threshold values to determine emergency classifications have been verified by Farley personnel as being within the range of the instrument and clearly and consistently read within the scale of the instrument.

Site specific information is highlighted in yellow.RLPV used instead of common PWR terminology of RCS.ODCM is the controlling:

Radiation Effluent Document.WOG CSFSTs are used for EAL thresholds as allowed by NEI 99-01 Rev 6 Developer Notes.Appendix A -Deleted BWR Acronyms and Abbreviations.

Added additional acronyms as needed.Appendix B -Incorporated Site Specific definitions as appropriate.

ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ICS/EALS RG1: INITIATING CONDITIONS Difference

/ Deviation I Justification None THRESHOLDS NEI199-01 Rev 6 Farley (1) Reading on ANY of the following radiation monitors greater than (1) Reading on ANY of the following radiation monitors greater than the reading shown for 15 minutes or longer: the reading shown for 15 minutes or longer: (site-specific monitor list and threshold values) Steam Jet Air Ejector RE-15C I130 lci/cc (130 R/hr)(2) Dose assessment using actual meteorology indicates doses greater Plant Vent Stack RE-29B (NG) 0.8 lCilcc than 1,000 mrem TEDE or 5,000 mrem thyroid CDE at or beyond (2) Dose assessment using actual meteorology indicates doses greater (site-specific dose receptor point). than 1,000 mrem TEDE or 5,000 mrem thyroid CDE at or beyond (3) Field survey results indicate EITHER of the following at or beyond the site boundary.(site-specific dose receptor point): (3) Field survey results indicate EITHER of the following at or beyond* Closed window dose rates greater than 1,000 mR/hr expected to the site boundary: continue for 60 minutes or longer. 0 Closed window dose rates greater than 1,000 mR/hr expected to* Analyses of field survey samples indicate thyroid CDE greater continue for 60 minutes or longer.than 5,000 mrem for one hour of inhalation.

0 Analyses of field survey samples indicate thyroid CDE greater than 5,000 mrem for one hour of inhalation.

Difference

/ Deviation

/ Justification Difference:

Site specific information provided.

See V2 Rad Monitor Calculation and V30ODCM Site Boundary Drawing.2 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ICS/EALS RG:IITIATING CONDITIONS Difeece2DeitinI utiiato Difeenfe:

Site specifi ian formationst pretovid ed.t (sie-se iFP Level 3 and2endctife on.lvlcno erstrdt tlat10 et(ee )fr6 descipton) or 0 miute oTHRESHOLDnuts o ogr Difference I Deviation I Justification Difference:

Site specific information provided.

See V4 SFP Level 3 and 2 Indication.

3 ABNOMALRAD EVESI INIRADIOLGICALNEFFLUNTS CEL RS1: INITIATING CONDITIONS Difference

/ Deviation

/ Justification None THRESHOLDS NEI 99-01 Rev 6 Farley (1) Reading on ANY of the following radiation monitors greater than (1) Reading on ANY of the following radiation monitors greater than the reading shown for 15 minutes or longer: the reading shown for 15 minutes or longer: (site-specific monitor list and threshold values) ISteam Jet Air Ejector RE'I15C 13 lCi/cc (13 R/hr)(2) Dose assessment using actual meteorology indicates doses greater Plant Vent Stack RE-29B (NG) 0.08 aCi/cc than 100 mrem TEDE or 500 mrem thyroid CDE at or beyond (site- (2) Dose assessment using actual meteorology indicates doses greater specific dose receptor point). than 100 mrem TEDE or 500 mrem thyroid CDE at or beyond the (3) Field survey results indicate EITHER of the following at or beyond site boundary.(site-specific dose receptor point): (3) Field survey results indicate EITHER of the following at or beyond* Closed window dose rates greater than 100 mR/hr expected to the site boundary: continue for 60 minutes or longer. 0 Closed window dose rates greater than 100 mR/hr expected to* Analyses of field survey samples indicate thyroid CDE greater continue for 60 minutes or longer.than 500 mrem for one hour of inhalation.

0 Analyses of field survey samples indicate thyroid CDE greater than 500 mrem for one hour of inhalation.

Difference I Deviation

/ Justification Difference:

Site specific information provided.

See V2 Rad Monitor Calculation and V30ODCM Site Boundary Drawing.4 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ICS/EALS RS:INITIATING CONDITIONS Difference

/ Deviation

/ Justification Difference:

Site specific information provided.

See V4 SFP Level 3 and 2 Indication.

~~THRESHDHSOLDS Difference

/ Deviation/IJustification Difference:

Site specific information provided.

See V4 SFP Level 3 and 2 Indication.

5 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ICS/EALS RAI: INITIATING CONDITIONS Difference

/ Deviation

/ Justification None THRESHOLDS NE199-01IRev 6 Farley (1) Reading on ANY of the following radiation monitors greater than (1) Reading on ANY of the following radiation monitors greater than the reading shown for 15 minutes or longer: the reading shown for 15 minutes or longer: (site-specific monitor list and threshold values) Steam Jet Air Ejector RE-15C 1.3 tCi/cc (1.3 R/hr)(2) Dose assessment using actual meteorology indicates doses greater Plant Vent Stack RE-29B (NG) 0.008 tCi/cc than 10 mrem TEDE or 50 mrem thyroid CDE at or beyond (site- (2) Dose assessment using actual meteorology indicates doses greater specific dose receptor point). than 10 mrem TEDE or 50 mrem thyroid CDE at or beyond the site (3) Analysis of a liquid effluent sample indicates a concentration or boundary.release rate that would result in doses greater than 10 mrem TEDE (3) Analysis of a liquid effluent sample indicates a concentration or or 50 mrem thyroid CDE at or beyond (site-specific dose receptor release rate that would result in doses greater than 10 mrem TEDE point) for one hour of exposure.

or 50 mrem thyroid CDE at or beyond the site boundary for one (4) Field survey results indicate EITHER of the following at or beyond hour of exposure.(site-specific dose receptor point): (4) Field survey results indicate EITHER of the following at or beyond* Closed window dose rates greater than 10 mR/hr expected to the site boundary: continue for 60 minutes or longer. 0 Closed window dose rates greater than 10 mR/hr expected to* Analyses of field survey samples indicate thyroid CDE greater continue for 60 minutes or longer.than 50 mrem for one hour of inhalation.

S Analyses of field survey samples indicate thyroid CDE greater than 50 mrem for one hour of inhalation.

Difference I Deviation

/ Justification Difference:

Site specific information provided.

See V2 Rad Monitor Calculation and V30ODCM Site Boundary Drawing.6 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ICS/EALS RA2: INITIATING CONDITIONS Difference

/ Deviation

/ Justification None THRESHOLDS NEI 99-01 Rev 6 Farley (1) Uncovery of irradiated fuel in the REFUELING PATHWAY. (1) Uncovery of irradiated fuel in the REFUELING PATHWAY.(2) Damage to irradiated fuel resulting in a release of radioactivity from (2) Damage to irradiated fuel resulting in a release of radioactivity from the fuel as indicated by ANY of the following radiation monitors:

the fuel as indicated by alarms on ANY of the following radiation (site-specific listing of radiation monitors, and the associated monitors: readings, setpoints and/or alarms) I Spent Fuel Pool Ventilation Monitor RE-25A OR B (3) Lowering of spent fuel pool level to (site-specific Level 2 value). Spent Fuel Radiation Monitor RE-5[See Developer Notes] Containment Pur ;e Ventilation Monitor RE-24A OR B!(3) Lowering of spent fuel pool level to 140 feet (Level 2).Difference

/ Deviation

/ Justification Difference:

Farley EAL Threshold (2) specifies that alarms on identified radiation monitors are required to satisfy the EAL threshold.

See V5 FNP-I(2)-ARP-1.6.

Justification:

Use of the alarm indiciations for the radiation monitors provides site personnel with a clear indication that fuel has been damaged and a release of radioactivity is occurring as a result.Difference:

Site specific information provided for Farley EAL Threshold (3). See V4 SFP Level 3 and 2 Indication.

7 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ICS/EALS RA3: INITIATING CONDITIONS THRESHOLDS NEI 99-01 Rev 6 Farley (1) Dose rate greater than 15 mR/hr in ANY of the following areas: (I) Dose rate greater than 15 mR/hr on RE-1IA, Control Room Radiation* Control Room Monitor* Central Alarm Station (2) An UNPLANNED event results in radiation levels that prohibit or* (other site-specific areas/rooms) impede access to any Table Hi plant rooms or areas: (2) An UNPLANNED event results in radiation levels that prohibit or impede access to any of the following plant rooms or areas: Table HI (site-specific list of plant rooms or areas with entry-related mode Mode Room Name Room Number applicability identified)

Electrical Penetration 334,333,347/

Room 2334,2333,2347 Hallway Outside Filter 3 12,332/3 Room 23 12,2332 1A.2A MCC areas Sample Room and 323, 324/Primary CHM labs 2323, 2324 Sample Room and 323, 324/4 Primary CI-M labs 2323, 2324 RHR Hx Room 128/________________________2128 Difference

/ Deviation

/ Justification 8-J ABNORMAL RA) LEVELS / RADIOLOGICAL EFFLUENT ICS/EALS Differences:

Farley Threshold (1) -CAS is located in the CR envelope; no additional areas identified.

See V6 Alarm Response -FNP-I-ARP-1.6 (Control Room Rand Monitor).Justification:

No additional rooms applicable to this EAL threshold.

CAS is included in the Control Room envelope.Difference:

Farley Threshold (2) provides site specific information.

9 ABNORML RADLEVEL INIRADIOLGICALNEFFLUNTS C/EL RUl: INITIATING CONDITIONS NEI 99-01 Rev 6 Farley Release of gaseous or liquid radioactivity greater than 2 times the (site- Release of gaseous or liquid radioactivity greatre than 2 times the ODCM specific effluent release controlling document) limits for 60 minutes or imits for 60 minutes or longer.longer.Difference

/ Deviation

/ Justification None THRESHOLDS NE1 99-0 1 Rev 6 Farley (1) Reading on ANY effluent radiation monitor greater than 2 times the (1) Reading on ANY effluent radiation monitors greater than 2 times the (site-specific effluent release controlling document) limits for 60 ODCM limits for 60 minutes or longer: minutes or longer: Liquid Effluents (site-specific monitor list and threshold values corresponding to 2 Steam Generator Blowdown Effluent Line RE-23B 2.80 x 1 03 cpm times the controlling document limits) Gaseous Effluents (2) Reading on ANY effluent radiation monitor greater than 2 times the Steam Jet Air Ejector RE-15 3.5 X 102 cpm alarm setpoint established by a current radioactivity discharge Plant Vent Gas permit for 60 minutes or longer. R-14 3.2 x 104 cpm (3) Sample analysis for a gaseous or liquid release indicates a RE-22 4.0 x 102 cpm concentration or release rate greater than 2 times the (site-specific RE-29B (NG) 8.90 x 10"4 iiCi/cc effluent release controlling document) limits for 60 minutes or longer. (2) Reading on ANY effluent radiation monitor greater than 2 times the alarm septpoint established by the current radioactivity discharge permit for 60 minutes or longer.(3) Sample analysis for a gaseous or liquid release indicates a concentration or release rate greater than 2 times the ODCM limits for 60 minmutes or longer.10 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ICS/EALS LDifference

/ Deviation

/ Justification Difference:

Site specific information provided.

See V2 Rad Monitor Calculation.

11 ABNORML HADLEVEL INIRADIOLGICOLNEFFLUNTS CEL RU2: INITIATING CONDITIONS Difference

/ Deviation I Justification None THRESHOLDS NE1 99-01 Rev 6 Farley (1) a. UJNPLANNED water level drop in the REFUELING (1) a. UNPLANNED water level drop in the REFUELING PATHWAY as indicated by ANY of the following:

PATHWAY as indicated by ANY of the following: (site-specific level indications).

AND IPersonnel report of low water level b. UNPLANNED rise in area radiation levels as indicated by[ Annunciator EH2 "SFP LVL HIiLO" ANY of the following radiation monitors.(site-specific list of area radiation monitors)

AND b. UNPLANNED rise in area radiation levels as indicated by ANY of the following radiation monitors.RE-5 in the fuel buildin~g RE-2 in containment RE-27A OR B in containment Difference

/ Deviation

/ Justification Difference:

Farley Threshold (1)a -site specific information provided.

See V7 Alarm Response -FNP-I(2)-ARP-I.5 (SFP Level).Difference:

Farley Threshold (l)b -site specific information provided.

See V8 Rad Monitor Information (FSAR).12 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CGI: INITIATING CONDITIONS Difference

/ Deviation

/ Justification Difference:

NEI 99-01 Rev 6 refers to reactor vessel/RCS inventory for PWRs. Farley uses RPV inventory.

Justification:

Site use of terminology differs from NE! guidance.THRESHOLDS NEI 99-01 Rev 6 Fale 13 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS (1) a. (Reactor vesselIRCS

[PWRI or RPV [BWR]) level less than (site-specific level) for 30 minutes or longer.AND b. ANY indication from the Containment Challenge Table (see below).(2) a. (Reactor vessel/RCS

[PWR] or RPV [BWR]) level cannot be monitored for 30 minutes or longer.AND b. Core uncovery is indicated by ANY of the following:

(Site-specific radiation monitor) reading greater than (site-specific value)* Erratic source range monitor indication

[PWR]* UNPLANNED increase in (site-specific sump and/or tank) levels of sufficient magnitude to indicate core uncovery* (Other site-specific indications)

AND c. ANY indication from the Containment Challenge Table (see below).(1)a. Reactor vessel level cannot be monitored for 30 minutes or longer.AND b. Core uncovery is indicated by ANY of the following:

Containment High Range Radiation Monitor RE27A or 27B reading greater than or equal to 100 RIHr* Erratic source range monitor indication

UNPLANNED increase in Containment Sump, or Reactor Coolant Drain Tank (RCDT), or Waste Holdup Tank (WHT) levels of sufficient magnitude to indicate core uncovery AND c. ANY indication from the Containment Challenge Table C1.Containment Challenge Table CI* CONTAINMENT CLOSURE not established*

Greater than or equal to 6 % H 2 exists inside containment

UNPLANNED increase in containment pressure* If CONTAINMENT CLOSURE is re-established prior to exceeding the 30-minute time limit, then declaration of a General Emergency is not required.Containment Challenge Table* CONTAINMENT CLOSURE not established*

(Explosive mixture) exists inside containment

UNPLANNED increase in containment pressure* Secondary containment radiation monitor reading above (site-specific value) [BWR]* If CONTAINMENT CLOSURE is re-established prior to exceeding the 30-minute time limit, then declaration of a General Emergency is not required.Difference

/ Deviation

/ Justification Difference:

NEI 99-01 Rev 6 Threshold (1) is not used at Farley. Remaining threshold renumbered.

Justification:

Site specific design -FNP does not have the ability to accurately measure level at TOAF; per Developer's Note guidance, this threshold can be deleted.14 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS Difference:

Justification:

Difference:

Justification:

Difference:

NEI 99-0 1 Rev 6 Threshold (2)b, last bullet, refers to Other site-specific indications of core uncovery.

No Other site-specific indications are used at Farley.Farley does not use any other site-specific indications of core uncovery than those already identified in FNP Threshold (I)b.Table designator C1 assigned to Containment Challenge Table.Editorial change to clearly identify tables within the document.Site specific information provided.

See V2 Rad Monitor Calculation, Vll Coat Sump-RCDT-WHT FSAR Reference, and VI2 112 Concentration.

15 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CSI: INTIATING CONDITIONS Difference

/ Deviation

/ Justification Difference:

NEI 99-01 Rev 6 refers to reactor vessel/RCS inventory for PWRs. Farley uses RPV inventory.

Justification:

Site use of terminology differs from NEI guidance.THRSHOLDS NEI 99-01 Rev 6 Farley (1) a. CONTAINMENT CLOSURE not established.

(1) a. CONTAINMENT CLOSURE not established.

AND AND b. (Reactor vessel/RCS

[PWR] or RPV [BWRI) level less than b. RVLIS (Mode5) level less than 121'0" (6" below bottom (site-specific level). ID of RCS loop).(2) a. CONTAINMENT CLOSURE established.

(2) a. RPV level cannot be monitored for 30 minutes or longer.AND AND b. (Reactor vesseliRCS

[PWR] or RPV [BWR]) level less than b. Core uncovery is indicated by ANY of the following: (site-specific level). 0 Containment High Range Radiation Monitor RE27A (3) a. (Reactor vessel/RCS

[PWR] or RPV [BWR]) level cannot or 27B reading greater than or equal to 100 R/Hr be monitored for 30 minutes or longer. 0 Erratic source range monitor indication AND 0 UNPLANNED increase Containment Sump, or b. Core uncovery is indicated by ANY of the following:

Reactor Coolant Drain Tank (RCDT), or Waste* (Site-specific radiation monitor) reading greater than Holdup Tank (WHT) levels of sufficient magnitude to (site-specific value) indicate core uncovery* Erratic source range monitor indication

[PWR]* UNPLANNED increase in (site-specific sump and/or tank) levels of sufficient magnitude to indicate core uncovery* (Other site-specific indications)

Difference

/ Deviation

/ Justification 16 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS Difference:

Justification:

Difference:

Justification:

Difference:

Justification:

Difference:

NE! 99-01 Rev 6 Threshold (1)b refers to reactor vesselIRCS level for PWRs. Farley uses RVLIS (Mode 5) level. See V9 RVLISI/RPV Level and VI0 RPV Level Calculation.

RVLIS (Mode 5) level is used since it can be monitored by control room personnel at Farley.NEI 99-01 Rev 6 Threshold (2) is not used at Farley. Remaining threshold renumbered.

Site specific design -FNP does not have the ability to accurately measure level at TOAF; per Developer's Note guidance, this threshold can be deleted.NEI 99-0 1 Rev 6 Threshold (3)b, last bullet, refers to Other site-specific indications of core uncovery.

No Other site-specific indications are used at Farley.Farley does not use any other site-specific indications of core uncovery than those already identified in FNP Threshold (2)b.Site specific information provided for Farley EAL Threshold 2(b). See V2 Rad Monitor Calculation and VI1 Cont Sump-RCDT-WriT FSAR Reference.

17 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CAI: INITIATING CONDITIONS Difference

/ Deviation

/ Justification Difference:

NEI 99-01 Rev 6 refers to reactor vessel/RCS inventory for PWRs. Farley uses RPV inventory.

Justification:

Site use of terminology differs from NEt guidance.THRESHOLDS NE1 99-01 Rev 6 Farley (1) Loss of (reactor vessel/RCS

[PWR] or RPV [BWR]) inventory as (1) Loss of RPV inventory as indicated by level less 122'1 1".indicated by level less than (site-specific level). (2) a. RPV level cannot be monitored for 15 minutes or longer (2) a. (Reactor vessel/RCS

[PWR] or RPV [BWR]) level cannot AND be monitored for 15 minutes or longer b. UNPLANNED increase in Conainment Sump, Reactor AND Coolant Drain Tank (RCDT) or Waste Holdup Tank b. UNPLANNED increase in (site-specific sump and/or tank) (WHT) levels due to a loss of RPV inventory.

levels due to a loss of (reactor vesseliRCS

[PWR] or RPV[BWR]) inventory.

Difference

/ Deviation

/ Justification Difference:

NEI 99-01 Rev 6 refers to reactor vessel/RCS inventory for PWI~s. Farley uses RPV inventory.

Justification:

Site use of terminology (RPV vs RCS) differs from NEI guidance.Difference:

Site specific information provided for Threshold (1). See V9 RVLIS/RPV Level.Justification:

The 122'II" level specified in EAL threshold (1) is the minimum RCS level for RHR operation provided in procedure for mid ioop operations.

Difference:

Site specific information provided for Threshold (2)b. See VI1 Cont Sump-RCDT-WIIT FSAR Reference.

18 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CA2: INITIATING CONDITIONS Difference I Deviation I Justification None THRESHOLDS NEI 99-01 Rev 6 Farley (1) Loss of ALL offsite and ALL onsite AC Power to (site-specific (1) Loss of ALL offsite and ALL onsite AC Power to BOTH 4160V emergency buses) for 15 minutes or longer. ESF busses 1(2)F AND l(2)G for 15 minutes or longer.Table SI Unit 1 Unit 2 Start-up Aux XFMR IA Start-up Aux XFMR 2A Start-up Aux XFMR lB Start-up Aux XFMR 2B Diesel Generator 1 -2A Diesel Generator 1l-2A Diesel Generator 1 B Diesel Generator 2B Diesel Generator 1 C Diesel Generator 1 C Diesel Generator 2C Diesel Generator 2C Difference I Deviation

/ Justification Difference:

Site specific information provided.

See V13 ESF Busses Drawing.19 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CA3: INITIATING CONDITIONS Difference

/ Deviation

/ Justification None THRESHOLDS NEI 99-01 Rev 6 Farley (1) UNPLANNED increase in RCS temperature to greater than (site- (1) UNPLANNED increase in RCS temperature to greater than 200 *F specific Technical Specification cold shutdown temperature limit) for greater than the duration specified in Table C2.for greater than the duration specified in the following table.Table C2: RCS Heat-up Duration Thresholds Table: RCS Heat-up Duration Thresholds RCS Status Containment Closure Heat-up Containment Closure Heat-up Status Duration RCS Status Status I Duration Not intact Not Established 0 minutes Intact (but not at reduced (o1trdcdivntr)Etbihd20 minutes*inventory

[PWR]) Not___applicable__

0 miue*Intact Not intact (or at reduced Established f 20 minutes* (but not at reduced inventory)

Not applicable 60 minutes*inventory

[PWR]) Not Established 0 minutes

If an RCS heat removal system is in operation within this time frame and* If an RCS heat removal system is in operation within this time frame and RCS temperature is being reduced, the EAL is not applicable.

RCS temperature is being reduced, the EAL is not applicable.

(2) UNPLANNED RCS pressure increase greater than 10 psig. (This (2) UNPLANNED RCS pressure increase greater than (site-specific EAL does not apply during water-solid plant conditions.)

pressure reading). (This EAL does not apply during water-solid plant conditions.

[PWR])Difference

/ Deviation

/ Justification Difference:

Table designator C2 assigned to RCS Heat-up Duration Thresholds.

Justification:

Editorial change to clearly identify tables within the document.Difference:

Information included in RCS Heat-up Duration Thresholds Table for Farley is inverted from the presentation in NEI 99-01 Rev 6.Information is the same.20 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS Justification:

Editorial change for Human Factors consideration

-worst case is presented first.Difference:

Site specific information provided.

See VI TS Table 1.1-1 Modes.21 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CA6: INITIATING CONDITIONS Difference

/ Deviation I Justification None THRESHOLDS NE1 99-01 Rev 6 Farley (1) a. The occurrence of ANY of the following hazardous events: (1) a. The occurrence of ANY of the following hazardous events:* Seismic event (earthquake) 0 Seismic event (earthquake)

Internal or external flooding event 0 Internal or external flooding event* High winds or tornado strike 0 High winds or tornado strike* FIRE

FIRE* EXPLOSION 0 EXPLOSION* (site-specific hazards) 0 Other events with similar hazard characteristics as* Other events with similar hazard characteristics as determined by the Shift Manager determined by the Shift Manager AND AND b. EITHER of the following:

b. EITHER of the following:

Event damage has caused indications of degraded 1. Event damage has caused indications of degraded performance in at least one train of a SAFETY performance in at least one train of a SAFETY SYSTEM needed for the current operating mode.SYSTEM needed for the current operating mode.

The event has caused VISIBLE DAMAGE to a OR SAFETY SYSTEM component or structure needed for 2. The event has caused VISIBLE DAMAGE to a the current operating mode.SAFETY SYSTEM component or structure needed for the current operating mode.Difference I Deviation

/ Justification 22 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS Difference:

NEI 99-01 Rev 6 Threshold (1)a, next to the last bullet, refers to site-specific hazards. No additional site specific hazards are identified for Farley.Justification:

Farley has not identified any additional site-specific hazards applicable to this EAL threshold.

23 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CUIi: INITIATING CONDITIONS Difference

/ Deviation

/ Justification Difference:

NEI 99-01 Rev 6 refers to reactor vessel/RCS inventory for PWRs. Farley uses RPV inventory.

Justification:

Site use of terminology differs from NE! guidance.THRESHOLDS NEI 99-01 Rev 6 Farley (1) UNPLANNED loss of reactor coolant results in (reactor vessei/RCS (1) UNPLANNED loss of reactor coolant results in RPV level less than[PWR] or RPV [BWR]) level less than a required lower limit for 15 a required lower limit for 15 minutes or longer.minutes or longer. (2) a. RPV level cannot be monitored.

(2) a. (Reactor vessel/RCS

[PWRI or RPV [BWR]) level cannot AND be monitored.

b. UNPLANNED increase in Containment Sump, Reactor AND Coolant Drain Tank, or Waste Holdup Tank levels.b. UNPLANNED increase in (site-specific sump and/or tank)levels.Difference

/ Deviation

/ Justification Difference:

NEI 99-01 Rev 6 refers to reactor vessel/RCS level for PWRs. Farley uses RPV level.Justification:

Site use of terminology (RPV vs RCS) differs from NE! guidance.Difference:

Site specific information provided.

See VII Cont Sump-RCDT-WHT FSAR Reference.

24 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CU2: INITIATING CONDITIONS NE1 99-01 Rev 6 Farley Loss of all but one AC power source to emergency buses for 15 minutes or Loss of all but one AC power source to emergency buses for 15 minutes or longer. longer.Difference

/ Deviation

/ Justification None THRESHOLDS NEI 99-01 Rev 6 Farley (1) a. AC power capability to (site-specific emergency buses) is reduced to a single power source for 15 minutes or longer.AND b. Any additional single power source failure will result in loss of all AC power to SAFETY SYSTEMS.(1)a. AC power capability to BOTH 41 60V ESF busses 1l(2)F AN 1l(2)G is reduced to a single power source for 15 minutes or longer.AND b. Any additional single power source failure will result in loss of all AC power to SAFETY SYSTEMS.Table S1 Unit 1 Unit 2 Start-up Aux XFMR 1A Start-up Aux XFMR 2A Start-up Aux XFMR lB Start-up Aux XFMR 2B Diesel Generator 1-2A Diesel Generator 1-2A Diesel Generator 1 B Diesel Generator 2B Diesel Generator 1C Diesel Generator IC Diesel Generator 2C Diesel Generator 2C Difference:

Seiatio /Jspeific ifrationprvd.SeV1EFBussDaig Difference:

Site specific information provided.

See V13 ESF Busses Drawing.25 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS~CU3: INITIATING CONDITIONS Difference!/

Deviation I Justification None~THRESHOLDS NEI 99-01 Rev 6 Farley (1) UNPLANNED increase in RCS temperature to greater than (site- (1) UNPLANNED increase in RCS temperature to greater than 200 °F.specific Technical Specification cold shutdown temperature limit). (2) Loss of ALL RCS temperature and RPV level indication for 15 (2) Loss of ALL RCS temperature and (reactor vessel/RCS

[P WR] or minutes or longer.RPV [BWR]) level indication for 15 minutes or longer.Difference I Deviation

/ Justification Difference:

NEI 99-01 Rev 6 EAL Threshold (2) refers to reactor vessel/RCS level for PWRs. Farley uses RPV level.Justification:

Site use of terminology (RPV vs RCS) differs from NEt guidance.Difference:

Site specific information provided.

See V1 TS Table 1.1-1 Modes.26 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CUJ4: INITIATING CONDITIONS Difference

/ Deviation I Justification None THRESHOLDS NE1 99-01 Rev 6 Farley (1) Indicated voltage is less than (site-specific bus voltage value) on (1) Indicated voltage is less than 105VDC on Technical Specification required Vital DC buses for 15 minutes or longer, required 125 VDC vital busses for 15 minutes or longer.Difference I Deviation

/ Justification Difference:

Site specific information provided.

See V14 DC Voltage Reference.

27 COLD SHUTDOWN/REFUELING SYSTME MALFUNCTION ICS/EALS CUJ5: INITIATING CONDITIONS Difference

/ Deviation I Justification None THRESHOLDS NE1 99-01 Rev 6 Farley (1) Loss of ALL of the .following onsite communication methods: (1) Loss of ALL of the following onsite communication methods: (site-specific list of communications methods) IIn plant telephones (2) Loss of ALL of the following ORO communications methods: Public address system (site-specific list of communications methods) Plant radio systems (3) Loss of ALL of the following NRC communications methods: (site-specific list of communications methods) (2) Loss of ALL of the following ORO communications methods: SENN (Emer gency Notification Network)Commercial phones (3) Loss of ALL of the following NRC communications methods: rENS on Federal Telecommunications System (FTS)Commercial phones Difference

/ Deviation

/ Justification Difference:

Site specific information provided.28 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) ICS/EALS E-HUIJ: INITIATING CONDITIONS Difference I Deviation

/ Justification None THRESHOLDS NEI 99-01 Rev 6 Farley (1) Damage to a loaded cask CONFINEMENT BOUNDARY as (1) Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by an on-contact radiation reading greater than (2 times the indicated by an on-contact radiation reading greater than ANY of the site-specific cask specific technical specification allowable radiation values listed in Table El.level) on the surface of the spent fuel cask.Table El HI-TRAC 125 Side -Mid height [1360 Top [260 HI-STORM 100 Side -60 inches below mid-height 340 Side -Mid- height 350 Side -60 inches above mid-height 170 Center of lid 50 Middel of top lid 60 Top (outlet) duct 160 Bottom (inlet) duct 460 29 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) ICS/EALS Difference

/ Deviation

/ Justification Difference:

Added new Table El to Farley EAL Threshold (1). Site specific information provided.

See V15 ISFSI TS/Dose Reading Calculation.

Justification:

Utilized table to display ISFS! technical specification radiation levels for the different ISFS! modules, Intent of NEI 99-01 Rev 6 EAL threshold remains satisfied.

30 FISSION PRODUCT BARRIER ICS/EALS PWR FISSION PRODUCT BARRERS MATRIX,- INITIATING CONDITIONS/THRESHOLDS NEI 99-01 Rev 6 FA1 -Any Loss or any Potential Loss of either FS1 -Loss or Potential Loss of any two barriers.

FG1 -Loss of any two barriers and Loss or Potential Loss the Fuel Clad or RCS barrier, of the third barrier.,:~ : ' k¢: 777Do 7 iii i: )i77:t5 :'i i" 777,1 177 2t217; ;:f 7 "7 2 2 2 711+ ;7{7;:' -7 :777) g:)' L :Y 7" 7 # ;22 ]I,:W[1if FGI -LOSS of any tWO barriers and Loss or FS1 I LOSS or Potential Loss of any two barriers.

FA1 -Any Loss or any Potential Loss of either the Fuel Potential Loss of the third barrier. Clad or RCS barrier.Difference

/ Deviation

/ Justification Difference:

IC's listed in descending order (GE -Alert) instead of ascending order used by NEI 99-01 Rev 6.Fuel Clad Barrier RCS Barrier Containment Barrier Loss Potential LossLosPtnilLsLssoetalos NEI 99-01 Rev 6 1. RCS or SG Tube Leakage 1. RCS or SG Tube Leakage 1. RCS or SG Tube Leakage Not Applicable A. RCS/reactor A. An automatic or A. Operation of a standby A. A leaking or Not Applicable vessel level less manual ECCS (SI) charging (makeup) RUPTURED SG is than (site-specific actuation is required pump is required by FAULTED outside of level), by EITHER of the EITHER of the containment.

following:

UNISOLABLE

1. UNISOLABLE RCS leakage RCS leakage OR OR* SG tube 2. SG tube leakage.RUPTURE. OR B. RCS cooldown rate greater than (site-specific pressurized thermal shock 31 FISSION PRODUCT BARRIER ICS/EALS criteria/limits defined by site-specific indications).

Not Applicable A. CORE COOLING A. An automatic or A. Operation of a standby A. A leaking or Not Applicable CSF -ORANGE manual ECCS charging pump is RUPTURED SG is entry conditions actuation is required required by EITHER FAULTED outside of met by EITHER of the of the following:

containment.

following:

UNISOLABLE

UNISOLABLE RCS leakage RCS leakage

SG tube leakage.* SG tube OR RUPTURE. B. RCS INTEGRITY CSF-RED entry conditions met Difference

/ Deviation

/ Justification Difference:

RCS Barrier Loss EAL Threshold 1.A -NEI 99-01 Rev 6 includes (SI) as clarifier for ECCS. Farley threshold I.A does not include this clarifier.

Justification:

Terminology difference Difference:

RCS Barrier Potential Loss EAL Threshold 1.A -NEI 99-01 Rev 6 clarifies a charging pump as a makeup pump. Farley threshold 1.A does not include this clarifier.

Justification:

Terminology difference

-Farley does not refer to charging pumps as makeup pumps.Difference:

Site Specific information provided.

See V16 CSFST Information.

32 FISSION PRODUCT BARRIER ICS/EALS NEI 99-01 Rev 6 2. Inadequate Heat Removal J2. Inadequate Heat Removal j2. Inadequate Heat Removal A. Core exit thermocouple readings greater than (site-specific temperature value).A. Core exit thermocouple readings greater than (site-specific temperature value).OR B. Inadequate RCS heat removal capability via steam generators as indicated by (site-specific indications).

Not Applicable A. Inadequate RCS heat removal capability via steam generators as indicated by (site-specific indications).

Not Applicable A. 1. (Site-specific criteria for entry into core cooling restoration procedure)

AND 2. Restoration procedure not effective within 15 minutes.33 FISSION PRODUCT BARRIER ICS/EALS A. CORE COOLING CSF -RED entry conditions met.A. CORE COOLING CSF -ORANGE entry conditions met OR B. HEAT SINK CSF-RED entry conditions met.NOTE: Heat Sink CSF should not be considered RED if total AFW flow is less than 395 gpm due to operator action.Not Applicable A. HEAT SINK CSF -RED entry condition met.NOTE: Heat Sink CSF should not be considered RED if total AFW flow is less than 395 gpm due to operator action.Not Applicable A. CORE COOLING CSF -RED entry conditions met for 15 minutes or longer.C ________________________

L ________________________

I. ______________________

Difference

/ Deviation

/ Justification Difference:

Site specific information provided.

See V16 CSFST Information.

Added NOTE to Fuel Clad and RCS Potential Loss EAL Thresholds related to validity of HEAT SINK CSF indications.

Justification:

Site specific difference/consideration.

FNP has determined that Hleat Sink CSF Red is not applicable if AFW flow is less than 395 gpm due to operator action.NE1 99-01 Rev 6 34 FISSION PRODUCT BARRIER ICS/EALS 3. RCS Activity / Containment Radiation

3. RCS Activity / Containment Radiation

3. RCS Activity / Containment Radiation A. Containment Not Applicable A. Containment radiation Not Applicable Not Applicable A. Containment radiation monitor monitor reading radiation monitor reading greater greater than (site- reading greater than than (site-specific specific value). (site-specific value).value).OR B. (Site-specific indications that reactor coolant activity is greater than 300 jtCi/gm dose equivalent 1-131).A. Containment Not Applicable A. Containment radiation Not Applicable Not Applicable A. Containment radiation monitor monitor RE-2 greater radiation monitor RE-27A or B than 1 R/hr OR RE-27 A or B greater greater than 60)0 Containment radiation than 81000 R/hr.R/hr. monitor RE-7 greater OR than 500 mR/hr.B. Indications that reactor coolant activity is greater than 300 pCi/gm dose equivalent 1-131.Difference

/ Deviation

/ Justification Difference:

Fuel Clad Barrier Loss EAL Threshold 3.B -NEI 99-01 Rev 6 directs use of site specific indiciations of dose equivalent 1-131. Farley threshold uses the term Indications.

Justification:

Various methods for determining when this EAL threshold is met.Difference:

Site specific information provided.

See V2 Rad Monitor Calculation.

35 FISSION PRODUCT BARRIER ICS/EALS NEI 99-01 Rev 6 4. Containment Integrity or Bypass 4.Containment Integrity or Bypass 4. Containment Integrity or Bypass Not Applicable Not Applicable Not Applicable Not Applicable A. Containment isolation is required AND EITHER of the following:

1. Containment integrity has been lost based on Emergency Director judgment.OR 2. UNISOLABLE pathway from the containment to the environment exists.OR B. Indications of RCS leakage outside of containment.

A. Containment pressure greater than (site-specific value)OR B. Explosive mixture exists inside containment OR C. 1. Containment pressure greater than (site-specific pressure setpoint)AND 2. Less than one frull train of (site-specific system or equipment) is operating per design for 15 minutes or longer.36 FISSION PRODUCT BARRIER ICS/EALS Not Applicable Not Applicable Not Applicable Not Applicable A. Containment isolation is required AND EITHER of the following:

Containment integrity has been lost based on Emergency Director judgmnent.

UNISOLABLE pathway from the containment to the environment exists.OR B. Indications of RCS leakage outside of containment as indicated by alarms on any of the following:

RE-10* RE-14* RE-21* RE-22 A. CONTAINMENT CSF -RED entry condtions met OR B. Containment Hydrogen concentration greater than 5.5%OR C. 1. CONTAINMENT CSF -ORANGE conditions met AND 2. Less than one CTMT fan coolers and one full train of CTMT spray is operating per design for 15 minutes or longer.Difference I Deviation

/ Justification Difference:

Justification:

Difference:

Justification:

Difference:

Justification:

Difference:

Loss EAL Threshold 4.B -NEI 99-01 Rev 6 refers to generic indications of RCS leakage outside containment.

Farley threshold specifics specific indications using identified rad monitors.

See VI7 Rad Monitor Reference (ARP).Human factors consideration, use of specific measurable and recognizable indications facilitates the determination that EAL threshold has been met.Potential Loss EAL Threshold 4.B -NEI 99-01 Rev 6 refers to Explosive mixture exists inside containment.

Farley threshold specifies the hydrogen concentration that is considered an explosive mixture in containment.

See V12 112 Concentration.

Human factors consideration, use of a specific measurable and recognizable concentration facilitates the determination that EAL threshold has been met.Potential Loss EAL Threshold 4.C.2 -NEI 99-01 Rev 6 refers to only one train of a site specific system. Farley threshold includes additional components (one CTMT fan coolers) that support CTMT spray to meet this entry condition.

Plant design difference.

Site specific information provided.

See VI6 CSFST Information.

37 FISSIONPRODUC BA01RReRvIS/6L NEI 99-01 Rev 6 5. Other Indications

5. Other Indications

5. Other Indications A. (site-specific as A. (site-specific as A. (site-specific as A. (site-specific as A. (site-specific as A. (site-specific as applicable) applicable) applicable) applicable) applicable) applicable)

Not Applicable

[Not Applicable

[Not Applicable Not Applicable Not Applicable Not Applicable Difference

/ Deviation

/ Justification Difference:

No additional EAL Thresholds identified for Farley.Justification:

No additional EAL Thresholds identified.

NEI 99-01 Rev 6 6. Emergency Director Judgment 6. Emergency Director Judgment 6. Emergency Director Judgment A. ANY condition in A. ANY condition in A. ANY condition in the A. ANY condition in the A. ANY condition in the A. ANY condition in the the opinion of the the opinion of the opinion of the opinion of the opinion of the opinion of the Emergency Emergency Emergency Director Emergency Director Emergency Director Emergency Director Director that Director that that indicates Loss of that indicates Potential that indicates Loss of that indicates indicates Loss of indicates Potential the RCS Barrier. Loss of the RCS the Containment Potential Loss of the the Fuel Clad Loss of the Fuel Barrier. Barrier. Containment Barrier.Barrier. Clad Barrier.A. ANY condition in A. ANY condition in A. ANY condition in the A. ANY condition in the A. ANY condition in the A. ANY condition in the the opinion of the the opinion of the opinion of the opinion of the opinion of the opinion of the emergency emergency emergency director emergency director that emergency director that emergency director director that director that that indicates loss of indicates potential loss indicates loss of the that indicates indicates loss of indicates potential the RCS Barrier, of the RCS Barrier, containment barrier, potential loss of the the fuel clad loss of the fuel containment barrier.barrier, clad barrier.Difference

/ Deviation

/ Justification 38 Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant Units 1 and 2;Edwin I. Hatch Nuclear Plant Units 1 and 2;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 2 Deviations and Differences Matrix Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant Units 1 and 2 License Amendment Request for Changes to Emergency Action Level Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant Enclosure 2 Farley Deviations and Differences Matrix NEI 99-01 Rev 6 Deviations and Differences Joseph M. Farley Nuclear Plant -Units I and 2 Table of Contents Generic Differences..............................................................