CNS-16-016, Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/001 and Revision 036 to RP/0/A/5000/001: Difference between revisions
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RP/O/AI5000/00 Page 3 of 4 I..F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/026, Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence of" the event.2.2 Assessment, classification and declaration of any applicable emergency condition should be completed within 15 minutes after the availability of indications or information to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 [F' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1l (Fission Product Barrier M'atrix) OR. refer to [AL wvallboards. | RP/O/AI5000/00 Page 3 of 4 I..F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/026, Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence of" the event.2.2 Assessment, classification and declaration of any applicable emergency condition should be completed within 15 minutes after the availability of indications or information to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 [F' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1l (Fission Product Barrier M'atrix) OR. refer to [AL wvallboards. | ||
2.5 IF a General Emergency is NOT declared in Ste p 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to [AL wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated. | 2.5 IF a General Emergency is NOT declared in Ste p 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to [AL wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated. | ||
2.7 Document the declaration time.___________ | |||
2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERG Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportunity that will not interf'ere with the performance of the crew or the fhow of the Emergency Procedure. | |||
the declaration time.___________ | |||
the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERG Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportunity that will not interf'ere with the performance of the crew or the fhow of the Emergency Procedure. | |||
: 2. 10 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel. | : 2. 10 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel. | ||
RPIOIAI/001001 Page 4 o f 4 2.11 Implemnent the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure. | RPIOIAI/001001 Page 4 o f 4 2.11 Implemnent the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure. | ||
Notification of Unusual Event RP/O/A/5000/O02 Alert RP/0/A/5000/003 Site Area Emergency RP/O/A/5000/004 General Emergency RP/0/A/5000/005 | Notification of Unusual Event RP/O/A/5000/O02 Alert RP/0/A/5000/003 Site Area Emergency RP/O/A/5000/004 General Emergency RP/0/A/5000/005 | ||
: 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures | : 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures 4.1 through 4.7 OR. EAL wallboards. | ||
3.2 Refer to Enclosure 4.8 (Definitions/Acronyms) | |||
4.7 OR. EAL wallboards. | |||
to Enclosure 4.8 (Definitions/Acronyms) | |||
OR 4.9 (Emergency Declaration Guidelines), as needed.3.3 Refer to Section D of the Catawba Emergency Plan for basis information about thle Emergency Classification System as needed.3.4 Refer to RP/0/A/5000/020, "TSC Activation Procedure' concerning the use of 10CFR50.54(x). | OR 4.9 (Emergency Declaration Guidelines), as needed.3.3 Refer to Section D of the Catawba Emergency Plan for basis information about thle Emergency Classification System as needed.3.4 Refer to RP/0/A/5000/020, "TSC Activation Procedure' concerning the use of 10CFR50.54(x). | ||
If the TSC is activated, contact the TSC Emergency Coordinator | If the TSC is activated, contact the TSC Emergency Coordinator | ||
([C)for concurrence when using I10CFR50.54(x). | ([C)for concurrence when using I10CFR50.54(x). | ||
: 4. Enclosures | : 4. Enclosures | ||
: 4. 1 Fission Product Barrier M'atrix 4.2 System Malfunctions | : 4. 1 Fission Product Barrier M'atrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radiological Effluent 4.4l Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.1I0 Radiation Monitor Reading for Enclosure 4.3 EALs S Enclosure 4.1 Fission Product Barrier Matrix RPIOIAI500010011 Page 1 of 5 ission Product Barrier status (,Intact, Potential Loss, or Loss). Add points for all barriers. | ||
Rad Levels/Radiological Effluent 4.4l Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms | |||
Declaration Guidelines 4.1I0 Radiation Monitor Reading for Enclosure 4.3 EALs S Enclosure | |||
Product Barrier Matrix RPIOIAI500010011 Page 1 of 5 ission Product Barrier status (,Intact, Potential Loss, or Loss). Add points for all barriers. | |||
Classify J)W.Ie events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is hours). In this IMMINENT LOSS situation, use judgment and classify as if the thresholds are exceeded.ission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions | Classify J)W.Ie events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is hours). In this IMMINENT LOSS situation, use judgment and classify as if the thresholds are exceeded.ission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions | ||
;or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.ion (C SF) indications are not meant to include transient alarm conditions which may appear during the start-up of ment. A CSF condition is satisfied when the alarmed state is valid and sustained. | ;or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.ion (C SF) indications are not meant to include transient alarm conditions which may appear during the start-up of ment. A CSF condition is satisfied when the alarmed state is valid and sustained. | ||
The STA should be consulted to alidated prior to the CSF being used as a basis to classify an emergency. | The STA should be consulted to alidated prior to the CSF being used as a basis to classify an emergency. | ||
of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-___{ IC jAlert IC f Site Area Emergency | of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-___{ IC jAlert IC f Site Area Emergency | ||
{ IC General Emergency 4. l.A.l Loss OR Potential Loss of Nuclear Coolant System 4.1.S.1 Loss OR Potential Loss of Both Nuclear Coolant System AN I Fuel Clad 4. I.G.I Loss of All Three Barriers 4.l.A.2 4.L.A.3 Loss OR_ Potential Loss of Fuel Clad Loss AND l'otential Loss Combinations of B~oth Nuclear Coolant System ANt)Fuel Clad 4.l.G.2 Loss of Any Two B~arriers AN I Potential Loss of the Third Cot a' t ll mlncolt A N )l~oss of Containmnent A N)ILoss OR Potenthil Loss 0 Enclosure | { IC General Emergency 4. l.A.l Loss OR Potential Loss of Nuclear Coolant System 4.1.S.1 Loss OR Potential Loss of Both Nuclear Coolant System AN I Fuel Clad 4. I.G.I Loss of All Three Barriers 4.l.A.2 4.L.A.3 Loss OR_ Potential Loss of Fuel Clad Loss AND l'otential Loss Combinations of B~oth Nuclear Coolant System ANt)Fuel Clad 4.l.G.2 Loss of Any Two B~arriers AN I Potential Loss of the Third Cot a' t ll mlncolt A N )l~oss of Containmnent A N)ILoss OR Potenthil Loss 0 Enclosure 4.1 Fission Product Barrier Matrix RP/O/A/5000/001I Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based on a "potential loss" or" a "loss." "Not Applicable" is inclu~ded in the table as a place holder only, and has no point v'alue assigned.Barrier IPoints (1-5) Potential Loss (X) Loss (X) Total IPoints Classification Containment 1 3 1 -3 Unusual Event-NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Elmergency Total Points 1 -13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of 5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description. | ||
Product Barrier Matrix RP/O/A/5000/001I Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based on a "potential loss" or" a "loss." "Not Applicable" is inclu~ded in the table as a place holder only, and has no point v'alue assigned.Barrier IPoints (1-5) Potential Loss (X) Loss (X) Total IPoints Classification Containment 1 3 1 -3 Unusual Event-NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Elmergency Total Points 1 -13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of 5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description. | |||
: 3. For each barrier, write the highest single point value applicable for the barrier in the "'Points" column and mark the appropriate | : 3. For each barrier, write the highest single point value applicable for the barrier in the "'Points" column and mark the appropriate | ||
"'loss"~COltllnnl. | "'loss"~COltllnnl. | ||
: 4. Add the points in the lPoints'" column and record the sum as "'Total Points".5. Determine the classilqcation level based on the number of "Total Points".6. In the table on" page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. 1 for Loss of Nuclear Coolant System) that best fits the loss of harrier descriptions. | : 4. Add the points in the lPoints'" column and record the sum as "'Total Points".5. Determine the classilqcation level based on the number of "Total Points".6. In the table on" page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. 1 for Loss of Nuclear Coolant System) that best fits the loss of harrier descriptions. | ||
: 7. Usingt the number (e.g. 4.1 .A. I). select the preprinted notification form OR a blank notification form and complete the required nflornmt ion Ibr Emergency Coordinator approval and transmittal. | : 7. Usingt the number (e.g. 4.1 .A. I). select the preprinted notification form OR a blank notification form and complete the required nflornmt ion Ibr Emergency Coordinator approval and transmittal. | ||
0 Enclosure | 0 Enclosure 4.1 RPIOIA15000100 1 Page 3 of 5 Fission Product Barrier Matrix 4.1.C CONTAINMIENT BARRI,1ER 4.1.N NCS BARRIER 4.I.F FUEL CLAD BARRIER POTENTIAL LOSS -/(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points).....h .. .. ... .. ..I -I -* I 1. Critical Safety Function Status* Containment-RED | ||
1 Page 3 of 5 Fission Product Barrier Matrix 4.1.C CONTAINMIENT BARRI,1ER 4.1.N NCS BARRIER 4.I.F FUEL CLAD BARRIER POTENTIAL LOSS -/(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points).....h .. .. ... .. ..I -I -* I 1. Critical Safety Function Status* Containment-RED | |||
* Not applicable | * Not applicable | ||
* Core cooling-RED Path is indicated for > 15 minutes 2. Containnment Conditions | * Core cooling-RED Path is indicated for > 15 minutes 2. Containnment Conditions | ||
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OIPERATING MODE: ALL 4.2.11.5-1 Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perfonn routine operations. | OIPERATING MODE: ALL 4.2.11.5-1 Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perfonn routine operations. | ||
*4.2.UJ.5-2 Loss of all offsite communications capability (Duke Emergenacy M-anagemtent Network [DE MN El].NR(" ETIS linies, ol'lhite radio system, commcreial phonec system) a llicting the abilitly to commun~icate wvith of'tsite antltori ties.END) | *4.2.UJ.5-2 Loss of all offsite communications capability (Duke Emergenacy M-anagemtent Network [DE MN El].NR(" ETIS linies, ol'lhite radio system, commcreial phonec system) a llicting the abilitly to commun~icate wvith of'tsite antltori ties.END) | ||
Enclosure | Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 of"5 G;ENERAl. | ||
Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 of"5 G;ENERAl. | |||
EMERG ENC\Y[;NUSI!AI, I-\.'ENT ALERT SITE Ai REA E:M ERG EN(CV 4.3.L .1 Any Unplanned Release (of Gaseous or 4.3.A.1 Liquid Radioactivity to the Environment thtat Exceeds Two Tiumes the SL(: Limits for 60 Minutes or Longer.Any I nlplaunnd Release of Gaseous or Liquid Radioactivity to the Eiuvironmcnt thatt Exceeds 200 Times the SLC limits for 15 Minutes or Longer.4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100 mrem TED)E or 500 mrem CDE Adult TIhyroid for the Actual or Projected Duration of the Release.OPERV [TINC MODE: AII OPElRATING MODE: ALL 4.3.Ui.1-1 A valid Tlrip 2 alarm on radiation monitor E~vlF-49L or ENvlF'-57 or > 60 minuteS or will likely continue for >_ 60 minultes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure | EMERG ENC\Y[;NUSI!AI, I-\.'ENT ALERT SITE Ai REA E:M ERG EN(CV 4.3.L .1 Any Unplanned Release (of Gaseous or 4.3.A.1 Liquid Radioactivity to the Environment thtat Exceeds Two Tiumes the SL(: Limits for 60 Minutes or Longer.Any I nlplaunnd Release of Gaseous or Liquid Radioactivity to the Eiuvironmcnt thatt Exceeds 200 Times the SLC limits for 15 Minutes or Longer.4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100 mrem TED)E or 500 mrem CDE Adult TIhyroid for the Actual or Projected Duration of the Release.OPERV [TINC MODE: AII OPElRATING MODE: ALL 4.3.Ui.1-1 A valid Tlrip 2 alarm on radiation monitor E~vlF-49L or ENvlF'-57 or > 60 minuteS or will likely continue for >_ 60 minultes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure | ||
[-IP/0/B/1009/0 14.4I.3.tJ..i-2 A valid indication on radiation monitor EMF- 36L of>_ 3.(0E+t04 cpm for->_ 60)minutes or will likely continue for >- 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AID-HP-ALIL-0202.4..3.A.1-1 A\ valid indication on radiation monitor EMF- 49L or EMvF-57 of> 1.2E+05 cpm lbr> 15 minutes or will likely continue for --15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H-P/0/B3/1009/014.(Continued) | [-IP/0/B/1009/0 14.4I.3.tJ..i-2 A valid indication on radiation monitor EMF- 36L of>_ 3.(0E+t04 cpm for->_ 60)minutes or will likely continue for >- 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AID-HP-ALIL-0202.4..3.A.1-1 A\ valid indication on radiation monitor EMF- 49L or EMvF-57 of> 1.2E+05 cpm lbr> 15 minutes or will likely continue for --15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H-P/0/B3/1009/014.(Continued) | ||
OIPERATING NIOIOE: ALiL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of> 2.7E+06 cpm sustained for> IS1 minmutes.4.3.S.1-2 Dose assessment teamn calculations in~dicate dose consequences greater than 100 mrem "IEDE or 500 mrem CDE Adult Thlyroid at the site houndary.4.3.G.1 Boundary l)ose Resultitng f'rom an Actual or hmnmitent Release of Radioactivity that Exceeds 1000 mrenm TEDE or 5000)onrei CDE Adult Thyroid for the Atuald or Projected Duration of the Release. | OIPERATING NIOIOE: ALiL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of> 2.7E+06 cpm sustained for> IS1 minmutes.4.3.S.1-2 Dose assessment teamn calculations in~dicate dose consequences greater than 100 mrem "IEDE or 500 mrem CDE Adult Thlyroid at the site houndary.4.3.G.1 Boundary l)ose Resultitng f'rom an Actual or hmnmitent Release of Radioactivity that Exceeds 1000 mrenm TEDE or 5000)onrei CDE Adult Thyroid for the Atuald or Projected Duration of the Release. | ||
MODE: ALL 4.3.G.1-1 A valid indication on radiation monitor EMF-36t-of> _8.3E+03 cpm sustained lbr > 15 minutes.4.3.G.1-2 Dose assessment team calculations indicate dose conseqtuences greater than 1000 ,mrem TEDE or 5000 mrcm CDL Adtmh Thyroid at the site boundary.lConmtin ned)(( "ontini, ed) 0 Enclosure | MODE: ALL 4.3.G.1-1 A valid indication on radiation monitor EMF-36t-of> _8.3E+03 cpm sustained lbr > 15 minutes.4.3.G.1-2 Dose assessment team calculations indicate dose conseqtuences greater than 1000 ,mrem TEDE or 5000 mrcm CDL Adtmh Thyroid at the site boundary.lConmtin ned)(( "ontini, ed) 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent R.P/O/A/5000/OO01 Page 2 of 5 GENERA I EM'ERGENCY UNU.SUAL, EVENT ALERT SITE AREA EM1ERGENCY 4.3.12...-3 Gaseous effluent being released exceeds two times SLC 16.1 1-6 for >60 minutes as determined by RP~procedure. | ||
Rad Levels/Radiological Effluent R.P/O/A/5000/OO01 Page 2 of 5 GENERA I EM'ERGENCY UNU.SUAL, EVENT ALERT SITE AREA EM1ERGENCY 4.3.12...-3 Gaseous effluent being released exceeds two times SLC 16.1 1-6 for >60 minutes as determined by RP~procedure. | |||
4,3.U.1-4 Liquid effluent being released exceeds two times SLC 16.11 I- for>60 minutes as determined by RP procedure. | 4,3.U.1-4 Liquid effluent being released exceeds two times SLC 16.11 I- for>60 minutes as determined by RP procedure. | ||
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continued) 4.3.A.1-2 A valid indication on radiation nmonitor EMF- 36L of_>5.4E+05 cpm for> 15 minutes or will likely continue for >-15 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202. | Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continued) 4.3.A.1-2 A valid indication on radiation nmonitor EMF- 36L of_>5.4E+05 cpm for> 15 minutes or will likely continue for >-15 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202. | ||
| Line 235: | Line 203: | ||
Note 2: If dose assessment team calculations cannot be completed in I 5 minutes.then valid monitor reading should be used for emergency classification. | Note 2: If dose assessment team calculations cannot be completed in I 5 minutes.then valid monitor reading should be used for emergency classification. | ||
END) | END) | ||
Enclosure | Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/O/A/5000/001I Page 3 of"5 GENERAL EM'ERGENCY UNLUSI.1AL EVENT ALERT SITE AREA EMERGENCY 41.3. I.2 Uneixpected Increase in Plant Radiation or Airborne Concentration. | ||
Rad Levels/Radiological Effluent RP/O/A/5000/001I Page 3 of"5 GENERAL EM'ERGENCY UNLUSI.1AL EVENT ALERT SITE AREA EMERGENCY 41.3. I.2 Uneixpected Increase in Plant Radiation or Airborne Concentration. | |||
OPERATING MODE: ALL 4.3.U.2-1 Indication of uncontrolled water level decrease of greater than _6 inches inl the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.U.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pool and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.U.2-3 Unplanned valid area EM~F reading increases by a factorof 1,000 over normal levels as shown in Enclosure 4.10.END 4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel.Does not apply to spent fuel in diy cask storage. Refer to EPLAN Section D basis document OPERATING MODE: ALL 4.3.A.2-1 An unplanned valid trip I1 alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge IEMF-15 2EMF-4 Spent Fuel Pool Ventilation I EMIF-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Nlode Only)IEMF-17 2EM lF-2 Containment Noble Gas Monitor (Applies to Mode 6 and No Mode (Jnly)1 EMF-39 2EiNlF-3') | OPERATING MODE: ALL 4.3.U.2-1 Indication of uncontrolled water level decrease of greater than _6 inches inl the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.U.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pool and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.U.2-3 Unplanned valid area EM~F reading increases by a factorof 1,000 over normal levels as shown in Enclosure 4.10.END 4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel.Does not apply to spent fuel in diy cask storage. Refer to EPLAN Section D basis document OPERATING MODE: ALL 4.3.A.2-1 An unplanned valid trip I1 alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge IEMF-15 2EMF-4 Spent Fuel Pool Ventilation I EMIF-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Nlode Only)IEMF-17 2EM lF-2 Containment Noble Gas Monitor (Applies to Mode 6 and No Mode (Jnly)1 EMF-39 2EiNlF-3') | ||
l( " liii ijed I 0 VP Enclosure 4.3 RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 4 of"5 UiNtSUAkL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity. spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any iIradiated fuel will become uncovered. | l( " liii ijed I 0 VP Enclosure 4.3 RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 4 of"5 UiNtSUAkL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity. spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any iIradiated fuel will become uncovered. | ||
| Line 272: | Line 237: | ||
* Spent Fuel Pool level alnd/or" temlperalture showv degraded performlance t(-'ontinulicd) | * Spent Fuel Pool level alnd/or" temlperalture showv degraded performlance t(-'ontinulicd) | ||
Enclosure 4.6 RP/0/A/5 000/001 Fire/Explosion andi Security Events Page 3 of' 3 I)NLISLAL EVENT AILERT SITE AREA EMERGENC'Y GENERAL ENIER(GENCY' Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling.4.6.A.3 HOSTILE ACTION Within tihe OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift Supervision 4.6.A.3-2 A validated notification from NRC of airliner attack threat within 30 minutes of the site.E NI) | Enclosure 4.6 RP/0/A/5 000/001 Fire/Explosion andi Security Events Page 3 of' 3 I)NLISLAL EVENT AILERT SITE AREA EMERGENC'Y GENERAL ENIER(GENCY' Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling.4.6.A.3 HOSTILE ACTION Within tihe OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift Supervision 4.6.A.3-2 A validated notification from NRC of airliner attack threat within 30 minutes of the site.E NI) | ||
Enclosure | Enclosure 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant SafetyEVENT'ALERT SITE AREA EMERGENCY 4.7.1U.1 Natural and Destructive Phenomena Affecting tihe Protected Area.OPERATING MODE: ALL 4.7.U1.1-1 Tremor felt and valid alarm on tihe Syscom Seismic Monitoring Systemn (OAC C 1 D22 52).4.7.U1.1-2 Report by plant personnel of toi-nado striking within protected area botmdary/ISFSI. | ||
Disasters, Hazards, And Other Conditions Affecting Plant SafetyEVENT'ALERT SITE AREA EMERGENCY 4.7.1U.1 Natural and Destructive Phenomena Affecting tihe Protected Area.OPERATING MODE: ALL 4.7.U1.1-1 Tremor felt and valid alarm on tihe Syscom Seismic Monitoring Systemn (OAC C 1 D22 52).4.7.U1.1-2 Report by plant personnel of toi-nado striking within protected area botmdary/ISFSI. | |||
4.7.U1.1-3 Vehicle crash into plant structures or systems within protected area boundary!/ISFSlI. | 4.7.U1.1-3 Vehicle crash into plant structures or systems within protected area boundary!/ISFSlI. | ||
4.7.U1.1-4 Report of turbine Fa~ilure resulting in casing penetration or damage to turbine or generator seals.4.7.1_1.1-5 Independent Spent Fuel Cask tipped over or dr'opped greater than 24 inches.4.7.11..1-6 Uncontrolled Ilooding in the ISFSI area.4.7.11. .1-7 Tornado generatecd missiles(s) impacting the ISFSi.{(C oiitn liicud)4.7.A.!I Natural and Destructive Phenomena Affecting the Plant Vital Area.OPERATING MODE: ALL 4.7.A.1-1 Valid "OBE Exceeded" Alarm on I AD-4.B/8 4.7.AAl-2 | 4.7.U1.1-4 Report of turbine Fa~ilure resulting in casing penetration or damage to turbine or generator seals.4.7.1_1.1-5 Independent Spent Fuel Cask tipped over or dr'opped greater than 24 inches.4.7.11..1-6 Uncontrolled Ilooding in the ISFSI area.4.7.11. .1-7 Tornado generatecd missiles(s) impacting the ISFSi.{(C oiitn liicud)4.7.A.!I Natural and Destructive Phenomena Affecting the Plant Vital Area.OPERATING MODE: ALL 4.7.A.1-1 Valid "OBE Exceeded" Alarm on I AD-4.B/8 4.7.AAl-2 | ||
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OPERATING MIODE: ALL 4.7.S.2-l Other conditions exist which in the Judgement of the Emergency Coordinator!EGF Director indicate actual or likely major f~itilures ol plant functions needed lor protection of the~ public.END RP/O/A/5 000/001 Page 1 of 4 GENERAL EM'ERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency. | OPERATING MIODE: ALL 4.7.S.2-l Other conditions exist which in the Judgement of the Emergency Coordinator!EGF Director indicate actual or likely major f~itilures ol plant functions needed lor protection of the~ public.END RP/O/A/5 000/001 Page 1 of 4 GENERAL EM'ERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency. | ||
OPERATING MODE: ALL 4.7.G.1-I Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (1) actual or imminent substantial core degradation with potential for loss of containmaent OR (2) potential for uncontrolled radionuclide releases. | OPERATING MODE: ALL 4.7.G.1-I Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (1) actual or imminent substantial core degradation with potential for loss of containmaent OR (2) potential for uncontrolled radionuclide releases. | ||
These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.En __)OR sustained winds >_ 74 mph for> 15 minutes.(Continued) 0 Enclosure | These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.En __)OR sustained winds >_ 74 mph for> 15 minutes.(Continued) 0 Enclosure 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety RPIO/AI/500I/O01 Page 2 o1"4 GFNERAL EMERGENCY IJNUSUJAL EVENT ALERT SITE AREA 4.7.1_1.2 Release of Toxic or Flanmnable Gases D~eemed Detrimental to Safe Operation or the Plant.OPERALTING MODE: ALL 4.7.U.2-l Report or detection of'toxic or flammable gases that could enter within the site boundary in amounts that can aff'ect safe operation of the plant.4.7.U.2-2 Report by Local. County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgeinent of the Emergency Coordiziator/EOF Director Warrant Declaration of an Unusual Event.OPERATING MODE: AILL 4.7. U.3-1I Other conditions exist which in the j udgcmlcnt o f thte Emcrgency Coordinazor/ELOF D)irector indic'ate a potential degradatlion ofth lt evel of Siitct\' of'thlw plaint.4.7.A. 1-3 Visible structural damage caused by either:* Vehicle crashes OR*Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures: | ||
Disasters, Hazards, And Other Conditions Affecting Plant Safety RPIO/AI/500I/O01 Page 2 o1"4 GFNERAL EMERGENCY IJNUSUJAL EVENT ALERT SITE AREA 4.7.1_1.2 Release of Toxic or Flanmnable Gases D~eemed Detrimental to Safe Operation or the Plant.OPERALTING MODE: ALL 4.7.U.2-l Report or detection of'toxic or flammable gases that could enter within the site boundary in amounts that can aff'ect safe operation of the plant.4.7.U.2-2 Report by Local. County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgeinent of the Emergency Coordiziator/EOF Director Warrant Declaration of an Unusual Event.OPERATING MODE: AILL 4.7. U.3-1I Other conditions exist which in the j udgcmlcnt o f thte Emcrgency Coordinazor/ELOF D)irector indic'ate a potential degradatlion ofth lt evel of Siitct\' of'thlw plaint.4.7.A. 1-3 Visible structural damage caused by either:* Vehicle crashes OR*Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures: | |||
* Reactor Building* Auxiliary Building* FWST* Diesel Generator Rooms SControl Room* RN Pump 1-ouse* SSF* Doghouses* CAS* SAS (Continued) | * Reactor Building* Auxiliary Building* FWST* Diesel Generator Rooms SControl Room* RN Pump 1-ouse* SSF* Doghouses* CAS* SAS (Continued) | ||
[NI) | [NI) | ||
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Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence or" the event.2.2 Assessment, classification and declaration of any applicable emergency condition shouild be completed within 15 minutes after the availability of indications or inf'ormation to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 IF the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix) OR refer to EAL wvallboards. | Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence or" the event.2.2 Assessment, classification and declaration of any applicable emergency condition shouild be completed within 15 minutes after the availability of indications or inf'ormation to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 IF the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix) OR refer to EAL wvallboards. | ||
__2.5 IF a General Emergency is NOT declared in Step 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to EA\L wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated. | __2.5 IF a General Emergency is NOT declared in Step 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to EA\L wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated. | ||
2.7 Document the declaration time. __________ | |||
2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERO Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportuinity that will not intert'ere with the performance of the crew or the flow of the Emergency Procedure. | |||
the declaration time. __________ | |||
the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERO Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportuinity that will not intert'ere with the performance of the crew or the flow of the Emergency Procedure. | |||
: 2. 1 0 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel. | : 2. 1 0 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel. | ||
RP/O/A/5000/00 I Page 4 o t"4 2.1!1 Implement the applicable Emergency Response Procedure (RP) f~or that classification and continue with subsequent steps of this procedure. | RP/O/A/5000/00 I Page 4 o t"4 2.1!1 Implement the applicable Emergency Response Procedure (RP) f~or that classification and continue with subsequent steps of this procedure. | ||
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If the TSC is activated, contact the TSC Emergency Coordinator (EC)for concurrence when using IOCFR5O.54(x). | If the TSC is activated, contact the TSC Emergency Coordinator (EC)for concurrence when using IOCFR5O.54(x). | ||
: 4. Enclosures | : 4. Enclosures | ||
: 4. 1 Fission Product Barrier Matrix 4.2 System Malfunctions | : 4. 1 Fission Product Barrier Matrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radio logical Effluent 4.4 Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.10 Radiation Monitor Reading for Enclosure 4.3 EALs 0 0 Enclosure 4.1 RPIOIA!5000/001I Page 1 of'5 Fission lProduct Barrier Matrix 1.Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all barriers. | ||
Rad Levels/Radio logical Effluent 4.4 Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms | |||
Declaration Guidelines 4.10 Radiation Monitor Reading for Enclosure 4.3 EALs 0 0 Enclosure 4.1 RPIOIA!5000/001I Page 1 of'5 Fission lProduct Barrier Matrix 1.Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all barriers. | |||
Classify according to the table below.Note 1 : An event (or multiple events) could occur which results in the conclusion that exceeding thle Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT LOSS situation, use judgment and classify' as if the thresholds are exceeded.Note 2: When determining Fission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions for the Fuel Clad Barrier loss or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.Note 3: Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the stait-up of engineered safeguards equipment. | Classify according to the table below.Note 1 : An event (or multiple events) could occur which results in the conclusion that exceeding thle Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT LOSS situation, use judgment and classify' as if the thresholds are exceeded.Note 2: When determining Fission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions for the Fuel Clad Barrier loss or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.Note 3: Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the stait-up of engineered safeguards equipment. | ||
A CSF condition is satisfied when the alamred state is valid and sustained. | A CSF condition is satisfied when the alamred state is valid and sustained. | ||
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Example: If ECA-0.0, Loss of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF should be used as the basis to classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-O.O.IC Unusual Event IC Alert IC Site Area Emergency IC General Emergency LossOR Ptenial ossLoss OR Potential Loss Potential Loss of of 41 1of Both Loss of 4.1nU.aI4.1ent. | Example: If ECA-0.0, Loss of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF should be used as the basis to classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-O.O.IC Unusual Event IC Alert IC Site Area Emergency IC General Emergency LossOR Ptenial ossLoss OR Potential Loss Potential Loss of of 41 1of Both Loss of 4.1nU.aI4.1ent. | ||
Nuclear Coolant System Nuclear Coolant System AND 4. G otimn ___All Three Barriers Fuel Clad Loss AND Loss OR P~otential Loss Potential Loss CombinationsLosf | Nuclear Coolant System Nuclear Coolant System AND 4. G otimn ___All Three Barriers Fuel Clad Loss AND Loss OR P~otential Loss Potential Loss CombinationsLosf | ||
: 4. U2 Loss ofl .A2o .S2o oh41.. Any Two Barriers AN D 4IU Containment 4... f4lS2o oh4102 Potential Loss of the Fuel Clad Nuclear Coolant System ANDThr Fuel CladThr Potentia Losssofof Containment ANI)4. Conaimet.3t 4.1.S.3 Loss Ok Potential Loss of I .A.~ Loss OR Potential LossAnOtrBrie Aof OteyBare Any Other Barrier 0l Enclosure | : 4. U2 Loss ofl .A2o .S2o oh41.. Any Two Barriers AN D 4IU Containment 4... f4lS2o oh4102 Potential Loss of the Fuel Clad Nuclear Coolant System ANDThr Fuel CladThr Potentia Losssofof Containment ANI)4. Conaimet.3t 4.1.S.3 Loss Ok Potential Loss of I .A.~ Loss OR Potential LossAnOtrBrie Aof OteyBare Any Other Barrier 0l Enclosure 4.1 Fission Product Barrier Matrix RPlO I AI50 00/001 Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based onl a "potential loss" or a "loss." "Not Applicable" is included in thle table as a place holder only, and has no point value assigned.Barrier Points (1-5) Potential Loss (X) Loss (X) Total Points Classification Containmenat 1 3 1 -3 Unusual Event NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Emergency Total Points | ||
Product Barrier Matrix RPlO I AI50 00/001 Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based onl a "potential loss" or a "loss." "Not Applicable" is included in thle table as a place holder only, and has no point value assigned.Barrier Points (1-5) Potential Loss (X) Loss (X) Total Points Classification Containmenat 1 3 1 -3 Unusual Event NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Emergency Total Points | |||
-13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of"5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description. | -13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of"5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description. | ||
: 3. For each barrier, write the highest single point value applicable for the barrier in the "Points" column and mark the appropriate "loss" column.4. Add the points in the "'Points" column and record the sum as "Total Points".5. Determine the classification level based on thle number of "Total Points".6. In thle table on page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. I for Loss of Nuclear Coolant S,,ystem) that best fits thle loss of barrier descriptions. | : 3. For each barrier, write the highest single point value applicable for the barrier in the "Points" column and mark the appropriate "loss" column.4. Add the points in the "'Points" column and record the sum as "Total Points".5. Determine the classification level based on thle number of "Total Points".6. In thle table on page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. I for Loss of Nuclear Coolant S,,ystem) that best fits thle loss of barrier descriptions. | ||
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* Not applicable | * Not applicable | ||
* Coolant Activity* GREATER THAN 300 p~i/cc Dose Equivalent Iodine (DEl) 1-131 CONTINtJEI) | * Coolant Activity* GREATER THAN 300 p~i/cc Dose Equivalent Iodine (DEl) 1-131 CONTINtJEI) | ||
()TNJI N NtEI (-'ONTIN I)ED ('ONTINIIED Enclosure | ()TNJI N NtEI (-'ONTIN I)ED ('ONTINIIED Enclosure 4.1 RPIOIAIS001001 Page 4 of 5 Fission Product Barrier Matrix 4.!.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4. I.F FUEL CLAI) BARRIER POTENTIAL LOSS -( I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)lil r... ... .. .I I I I 3. Containment lsolation Valves Status After Containment Isolationi Actuation 3. SC Tube Rupt ire ItI BIB tlhtl tIi tiIUl J RTU lllfl B lURB .Not applicable | ||
Page 4 of 5 Fission Product Barrier Matrix 4.!.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4. I.F FUEL CLAI) BARRIER POTENTIAL LOSS -( I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)lil r... ... .. .I I I I 3. Containment lsolation Valves Status After Containment Isolationi Actuation 3. SC Tube Rupt ire ItI BIB tlhtl tIi tiIUl J RTU lllfl B lURB .Not applicable | |||
.Containment isolation is incomplete and a direct release path lioin containment exists to the environment Pri mary-to-Secondary leak rate exceeds the capacity of one charging pump in the normal charging mode with letdown isolated.* Indication that a SG is Ruptured and has a Non-Isolable secondary line fault* Indication that a SG is ruptured and a prolonged release of contaminated secondary coolant is occurring from the affected SG to the environmnent Not applicable | .Containment isolation is incomplete and a direct release path lioin containment exists to the environment Pri mary-to-Secondary leak rate exceeds the capacity of one charging pump in the normal charging mode with letdown isolated.* Indication that a SG is Ruptured and has a Non-Isolable secondary line fault* Indication that a SG is ruptured and a prolonged release of contaminated secondary coolant is occurring from the affected SG to the environmnent Not applicable | ||
* Containment radiation monitor 53 A or 53 B Reading at time since Shutdown.0-0.5 hrs > 99 R/hr 0.5-2 hrs > 43 R/hr 2-4 hrs > 31 R/hr 4-8 hrs > 22 R/hr>8 hrs > 13 R/hr 4. Emereencv Coordinator/EOF Director 4. SC Secondary Side Release With Primary-to-Secondary Leakagle* Not applicable | * Containment radiation monitor 53 A or 53 B Reading at time since Shutdown.0-0.5 hrs > 99 R/hr 0.5-2 hrs > 43 R/hr 2-4 hrs > 31 R/hr 4-8 hrs > 22 R/hr>8 hrs > 13 R/hr 4. Emereencv Coordinator/EOF Director 4. SC Secondary Side Release With Primary-to-Secondary Leakagle* Not applicable | ||
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4.2.1I.5-2 Loss of all offsite communications capabi Iity (Duke Emergency Mianagemenit Network {DI-rv.NI | 4.2.1I.5-2 Loss of all offsite communications capabi Iity (Duke Emergency Mianagemenit Network {DI-rv.NI | ||
'li.NR(" ETS lines. of'fsite radio system, commercial phone system) affecting! | 'li.NR(" ETS lines. of'fsite radio system, commercial phone system) affecting! | ||
the ability to communicate wvith ol'lsite authl ori ties.ENI) 0 Enclosure | the ability to communicate wvith ol'lsite authl ori ties.ENI) 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 o1'5 GENERtAI. | ||
Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 o1'5 GENERtAI. | |||
EMER(GENCTY IJNIJSI IAl, E:VENTI ALERT'SlITE AREA EM EIRGENC\: 4.3.ti.1 Any lUnplanned Release of(Gaseous or -t.3.A.1 Liquid Radioactivity to the Environment that Exceeds Two Times the SLC Limits fo~r 60 Minutes or Longer.Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environnment that Exceeds 200 Times the SLC limits for 15 Mlinutes or Longer.OPERA ITIN(; MODE: ALL OPERATING MODE.ALL 4t.3.UAt-t A vatid '[rip 2 alarm on radiation monitor EMIF-49L or EMF-57 for > 60 minutes or oil! likely continue obr > 601 minutes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H- P/0/B3/1009/0 14.4.3.1U.1-2 A valid indication on radiation monitor EMF- 36L of_> 3.00E+04 cpm lbr > 60 minutes or will likely' continue tbr _> 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD)-EI'-ALL-0202.4.3.A.l-1 A valid indication on radiation monitor EMF- 49L or EMF-57 of_ 1.2E+05 cpm lbr > 15 mfinutes or will likely continue for >15 mtnutes, which indicates that the releatse may have exceeded the initiating condition and indicates the need to assess the release with procedure ItP/0/B/ 1009/014.(Continued) 4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100l mirem TED)E or 500 anrem CDE Adult Thyroid for the Aetual or Projected Duration of the Release.OPERATING NMODE: ALL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of">_ 2.7E+06 cpm sustained for > 15 minutes.4.3.S.1-2 Dose assessment temn~calculations indicate dose consequences greater than 100 mrem T1EDE or 500 turen CDE Adult Thyroid at the site boundary.{(Continued) 4.3.G.1 Boundary l)ose Resulting from an Actual or Inmminent Release of Radioactivity that Exceeds 1000 wrenm ITEDE or 5000 mrema CDE Adult Thyroid fo~r the Actual or Projected Duration of the Release.OPERATING MIODE: ALL 4.3.G.t-1 A valid indication on radiation monitor EMF-36H]of">_ 8.3 E+03 cpm sustained tbr > I5 tminutes.4.3.G.1-2 Dose assessment team calculations indicate dose consequences greater than 1000 mrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.I Continued) t( 'ontinued) | EMER(GENCTY IJNIJSI IAl, E:VENTI ALERT'SlITE AREA EM EIRGENC\: 4.3.ti.1 Any lUnplanned Release of(Gaseous or -t.3.A.1 Liquid Radioactivity to the Environment that Exceeds Two Times the SLC Limits fo~r 60 Minutes or Longer.Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environnment that Exceeds 200 Times the SLC limits for 15 Mlinutes or Longer.OPERA ITIN(; MODE: ALL OPERATING MODE.ALL 4t.3.UAt-t A vatid '[rip 2 alarm on radiation monitor EMIF-49L or EMF-57 for > 60 minutes or oil! likely continue obr > 601 minutes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H- P/0/B3/1009/0 14.4.3.1U.1-2 A valid indication on radiation monitor EMF- 36L of_> 3.00E+04 cpm lbr > 60 minutes or will likely' continue tbr _> 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD)-EI'-ALL-0202.4.3.A.l-1 A valid indication on radiation monitor EMF- 49L or EMF-57 of_ 1.2E+05 cpm lbr > 15 mfinutes or will likely continue for >15 mtnutes, which indicates that the releatse may have exceeded the initiating condition and indicates the need to assess the release with procedure ItP/0/B/ 1009/014.(Continued) 4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100l mirem TED)E or 500 anrem CDE Adult Thyroid for the Aetual or Projected Duration of the Release.OPERATING NMODE: ALL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of">_ 2.7E+06 cpm sustained for > 15 minutes.4.3.S.1-2 Dose assessment temn~calculations indicate dose consequences greater than 100 mrem T1EDE or 500 turen CDE Adult Thyroid at the site boundary.{(Continued) 4.3.G.1 Boundary l)ose Resulting from an Actual or Inmminent Release of Radioactivity that Exceeds 1000 wrenm ITEDE or 5000 mrema CDE Adult Thyroid fo~r the Actual or Projected Duration of the Release.OPERATING MIODE: ALL 4.3.G.t-1 A valid indication on radiation monitor EMF-36H]of">_ 8.3 E+03 cpm sustained tbr > I5 tminutes.4.3.G.1-2 Dose assessment team calculations indicate dose consequences greater than 1000 mrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.I Continued) t( 'ontinued) | ||
Enclosure | Enclosure 4.3 Abnormal Rad Levels/Radiologicai Effluent RP/O/A/5000/001 Page 2 ot'5 GENERAL EMERGENCY UNulSUAL EVENT ALERT SITE AREA EMERGENCY 4.3.U.1-3 Gaseous effluent being released exceeds two times SLC 16.11-6 lbr >60 minutes as determined by RP procedure. | ||
Rad Levels/Radiologicai Effluent RP/O/A/5000/001 Page 2 ot'5 GENERAL EMERGENCY UNulSUAL EVENT ALERT SITE AREA EMERGENCY 4.3.U.1-3 Gaseous effluent being released exceeds two times SLC 16.11-6 lbr >60 minutes as determined by RP procedure. | |||
4.3.U.I-4 Liquid effluent being released exceeds two times SLC 16.11-I for>60 minutes as determined by RP procedure. | 4.3.U.I-4 Liquid effluent being released exceeds two times SLC 16.11-I for>60 minutes as determined by RP procedure. | ||
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continuemd) 4.3.A.i-2 A valid indication on radiation monitor EMF- 36L of>_5.4E+05 cpm for > 15 minutes or will likely continue for >15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202. | Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continuemd) 4.3.A.i-2 A valid indication on radiation monitor EMF- 36L of>_5.4E+05 cpm for > 15 minutes or will likely continue for >15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202. | ||
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ENDI 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 1000 inrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.Note I : These EMF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available. | ENDI 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 1000 inrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.Note I : These EMF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available. | ||
Note 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid monitor reading should be used for emergency classification. | Note 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid monitor reading should be used for emergency classification. | ||
E NI 0 Enclosure | E NI 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 3 of 5.GENERAL EMERGENCY UNUSIJAL EVENT ALERT SITE AREA EM'ERGENCV: | ||
Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 3 of 5.GENERAL EMERGENCY UNUSIJAL EVENT ALERT SITE AREA EM'ERGENCV: | |||
4.3.U.2 Unexpected increase iin Plant Radiation or Airborne Concentration. | 4.3.U.2 Unexpected increase iin Plant Radiation or Airborne Concentration. | ||
OPERATING MODE: ALL 4.3.UJ.2-1I Indication of uncontrolled water level decrease of greater than 6_inches in the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.11.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pooi and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.11.2-3 Unplanned valid area EMF reading increases by a factor of 1 ,000 over normal levels as shown in Enclosure 4.10.EN I)4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that tlas or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor V'essel.SDoes not apply to spent fuel in dry cask storage. Refer to EPLAN Section D basis document OPERATING MIODE: ALL 4.3.A.2-1 An unplanned valid trip II alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge 1IEMF- 15 2EMF-4 Spent Fuel Pool Ventilation 1EM F-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Mode Only)l EMF-17 2EMF-2 Containment Noble Gas Monitor (Applies to Mode 6 andMode Only)I EM F-39 21N'lF-39 C(oniliiniud) | OPERATING MODE: ALL 4.3.UJ.2-1I Indication of uncontrolled water level decrease of greater than 6_inches in the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.11.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pooi and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.11.2-3 Unplanned valid area EMF reading increases by a factor of 1 ,000 over normal levels as shown in Enclosure 4.10.EN I)4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that tlas or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor V'essel.SDoes not apply to spent fuel in dry cask storage. Refer to EPLAN Section D basis document OPERATING MIODE: ALL 4.3.A.2-1 An unplanned valid trip II alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge 1IEMF- 15 2EMF-4 Spent Fuel Pool Ventilation 1EM F-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Mode Only)l EMF-17 2EMF-2 Containment Noble Gas Monitor (Applies to Mode 6 andMode Only)I EM F-39 21N'lF-39 C(oniliiniud) | ||
Enclosure | Enclosure 4.3 RPIOIAI5 000/001 Abnormal Rad Levels/Radiological Eftluent Page 4 of 5 UNUSUAL EVENTI ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any irradiated fiuel will become uncovered. | ||
000/001 Abnormal Rad Levels/Radiological Eftluent Page 4 of 5 UNUSUAL EVENTI ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any irradiated fiuel will become uncovered. | |||
4.3.A.2-3 NC system wide range level <95% after initiation ofhNC system make-up.AN.__D_Anly irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.4.3.A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.ANDI Any irradiated fuel assembly not capable of being fully lowered inb the spent fuel pool racks or transfer canal fuel transfer system basket.(Colnlinlued) | 4.3.A.2-3 NC system wide range level <95% after initiation ofhNC system make-up.AN.__D_Anly irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.4.3.A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.ANDI Any irradiated fuel assembly not capable of being fully lowered inb the spent fuel pool racks or transfer canal fuel transfer system basket.(Colnlinlued) | ||
Enclosure 4.3 RP/0/A/5000/00 Abnormial Rad Levels/Radiological Effluent Page 5 of 5 IUNtJSUAI EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases inl Radiation Levels Within the Facility That Inmpedes Operation of Systems Required to Mlaintain Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.3.A.3-1 V'alid reading on IEMF-12 greater than 1 5 mremihr in the Control Room.4.3.A.3-2 Valid indication of radiation levels greater than 15 nmremihr in the Central Alarm Station (_CAS) or Secondary Alarm Station (SAS).4.3.A.3-3 | Enclosure 4.3 RP/0/A/5000/00 Abnormial Rad Levels/Radiological Effluent Page 5 of 5 IUNtJSUAI EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases inl Radiation Levels Within the Facility That Inmpedes Operation of Systems Required to Mlaintain Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.3.A.3-1 V'alid reading on IEMF-12 greater than 1 5 mremihr in the Control Room.4.3.A.3-2 Valid indication of radiation levels greater than 15 nmremihr in the Central Alarm Station (_CAS) or Secondary Alarm Station (SAS).4.3.A.3-3 | ||
| Line 589: | Line 519: | ||
* Spent Fuel Pool level anld/or tempeC~llratr sho~v degraded pcrlbrmance | * Spent Fuel Pool level anld/or tempeC~llratr sho~v degraded pcrlbrmance | ||
!('on tin ued) | !('on tin ued) | ||
Enclosure 4.6 RP/0/A/5000/001 Fire/Explosion and Security Events Page 3 of 3 UJNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling~.4.6.A.3 IIOSTILE ACTION Within the OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift. Supervision 4.6.A.3-2 A validated notification from*NRC of airliner attack threat wiihin 30 minutes of the site.END Enclosure | Enclosure 4.6 RP/0/A/5000/001 Fire/Explosion and Security Events Page 3 of 3 UJNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling~.4.6.A.3 IIOSTILE ACTION Within the OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift. Supervision 4.6.A.3-2 A validated notification from*NRC of airliner attack threat wiihin 30 minutes of the site.END Enclosure 4.7 Natural Disasters, Iltazards, And Other Conditions Affecting Piant Safety UNUSUAL EVENT ALERT SITE AREA EMIERGENCY 4.7.U.1 Natural and Destructive Phenomena Affectinig tihe Protected Area. | ||
Disasters, Iltazards, And Other Conditions Affecting Piant Safety UNUSUAL EVENT ALERT SITE AREA EMIERGENCY 4.7.U.1 Natural and Destructive Phenomena Affectinig tihe Protected Area. | |||
MIODE: ALL 4.7.U.l-1 Tremor felt and valid alarm on the Syscom Seismic Monitoring System (OAC C 1D225 2).4.7.U.I-2 Report by plant personnel of tor'nado striking within protected area boundary/ISFSl. | MIODE: ALL 4.7.U.l-1 Tremor felt and valid alarm on the Syscom Seismic Monitoring System (OAC C 1D225 2).4.7.U.I-2 Report by plant personnel of tor'nado striking within protected area boundary/ISFSl. | ||
4.7.U.I-3 Vehicle crash into phlan structures or systems within protected area boundary/ISFSI. | 4.7.U.I-3 Vehicle crash into phlan structures or systems within protected area boundary/ISFSI. | ||
| Line 600: | Line 527: | ||
OPERATING MODE: ALL 4.7.S.2-1 Other conditions exist which in the J udgemient of the Emergency Coordinator/EOF-Director indicate actual or likely ma~jor lhuilures ofplant functions needed lbr protection of the public.I"N I)RP/0/A/5000/001I P~age I of 4 GENERAL EMIERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency. | OPERATING MODE: ALL 4.7.S.2-1 Other conditions exist which in the J udgemient of the Emergency Coordinator/EOF-Director indicate actual or likely ma~jor lhuilures ofplant functions needed lbr protection of the public.I"N I)RP/0/A/5000/001I P~age I of 4 GENERAL EMIERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency. | ||
OPERATING MODE: ALL 4.7.G.1-1 Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (I) actual or imminent substantial core degradation with potential for loss of containment OR (2) potential for uncontrolled radionuclide releases. | OPERATING MODE: ALL 4.7.G.1-1 Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (I) actual or imminent substantial core degradation with potential for loss of containment OR (2) potential for uncontrolled radionuclide releases. | ||
These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.L-NI)OR sustained winds >_ 74 mph lbr-" I5 minutes.t(oinllliuiedl 0 Enclosure | These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.L-NI)OR sustained winds >_ 74 mph lbr-" I5 minutes.t(oinllliuiedl 0 Enclosure 4.7 Natural Disasters, Hazards, Andi Other Conditions Affe~cting Plant Safety RP/0/A/5 000/001 Page 2 of 4 GENERAL EMERGENCY UNUSUAL EVENT ALERT SITE AREA EMERGENCY 4.7.11.2 Release of toxic or Fininniable Gases Deemed Detrimental to Safe Operation of the FPlant.O IPERATING MODE: ALL 4.7.U1.2-I Report or detection of toxic or flammable gases that could enter within the site boundary in amounts that can affect safe operation of the phlan.4.7.U1.2-2 Report by Local, County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgemtent of the Emergency Coordinator/EOF Dir-ector Warrant Declaraition of art Unusual Event.OIPERATING MODE: ALL 4.7.11.3-1 Other conditions exist which in thle juidg~eicnt of, the Emergency Coord ilnatoriLOF-lirector indicate a potei ti al dcegradation of the level of satet o~t' " theU p3tlant.4.7.A.1-3 Visible structural damage caused by cither:* Vehicle crashes OR* Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures: | ||
Disasters, Hazards, Andi Other Conditions Affe~cting Plant Safety RP/0/A/5 000/001 Page 2 of 4 GENERAL EMERGENCY UNUSUAL EVENT ALERT SITE AREA EMERGENCY 4.7.11.2 Release of toxic or Fininniable Gases Deemed Detrimental to Safe Operation of the FPlant.O IPERATING MODE: ALL 4.7.U1.2-I Report or detection of toxic or flammable gases that could enter within the site boundary in amounts that can affect safe operation of the phlan.4.7.U1.2-2 Report by Local, County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgemtent of the Emergency Coordinator/EOF Dir-ector Warrant Declaraition of art Unusual Event.OIPERATING MODE: ALL 4.7.11.3-1 Other conditions exist which in thle juidg~eicnt of, the Emergency Coord ilnatoriLOF-lirector indicate a potei ti al dcegradation of the level of satet o~t' " theU p3tlant.4.7.A.1-3 Visible structural damage caused by cither:* Vehicle crashes OR* Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures: | |||
* Reactor Building* Auxiliary Building* FW'ST* Diesel Generator Rooms* Control Room* RN Pump I-ouse* SSF* Doghouses* CAS* SAS V NI | * Reactor Building* Auxiliary Building* FW'ST* Diesel Generator Rooms* Control Room* RN Pump I-ouse* SSF* Doghouses* CAS* SAS V NI | ||
* | * | ||
| Line 799: | Line 723: | ||
RP/O/AI5000/00 Page 3 of 4 I..F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/026, Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence of" the event.2.2 Assessment, classification and declaration of any applicable emergency condition should be completed within 15 minutes after the availability of indications or information to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 [F' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1l (Fission Product Barrier M'atrix) OR. refer to [AL wvallboards. | RP/O/AI5000/00 Page 3 of 4 I..F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/026, Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence of" the event.2.2 Assessment, classification and declaration of any applicable emergency condition should be completed within 15 minutes after the availability of indications or information to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 [F' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1l (Fission Product Barrier M'atrix) OR. refer to [AL wvallboards. | ||
2.5 IF a General Emergency is NOT declared in Ste p 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to [AL wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated. | 2.5 IF a General Emergency is NOT declared in Ste p 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to [AL wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated. | ||
2.7 Document the declaration time.___________ | |||
2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERG Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportunity that will not interf'ere with the performance of the crew or the fhow of the Emergency Procedure. | |||
the declaration time.___________ | |||
the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERG Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportunity that will not interf'ere with the performance of the crew or the fhow of the Emergency Procedure. | |||
: 2. 10 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel. | : 2. 10 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel. | ||
RPIOIAI/001001 Page 4 o f 4 2.11 Implemnent the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure. | RPIOIAI/001001 Page 4 o f 4 2.11 Implemnent the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure. | ||
Notification of Unusual Event RP/O/A/5000/O02 Alert RP/0/A/5000/003 Site Area Emergency RP/O/A/5000/004 General Emergency RP/0/A/5000/005 | Notification of Unusual Event RP/O/A/5000/O02 Alert RP/0/A/5000/003 Site Area Emergency RP/O/A/5000/004 General Emergency RP/0/A/5000/005 | ||
: 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures | : 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures 4.1 through 4.7 OR. EAL wallboards. | ||
3.2 Refer to Enclosure 4.8 (Definitions/Acronyms) | |||
4.7 OR. EAL wallboards. | |||
to Enclosure 4.8 (Definitions/Acronyms) | |||
OR 4.9 (Emergency Declaration Guidelines), as needed.3.3 Refer to Section D of the Catawba Emergency Plan for basis information about thle Emergency Classification System as needed.3.4 Refer to RP/0/A/5000/020, "TSC Activation Procedure' concerning the use of 10CFR50.54(x). | OR 4.9 (Emergency Declaration Guidelines), as needed.3.3 Refer to Section D of the Catawba Emergency Plan for basis information about thle Emergency Classification System as needed.3.4 Refer to RP/0/A/5000/020, "TSC Activation Procedure' concerning the use of 10CFR50.54(x). | ||
If the TSC is activated, contact the TSC Emergency Coordinator | If the TSC is activated, contact the TSC Emergency Coordinator | ||
([C)for concurrence when using I10CFR50.54(x). | ([C)for concurrence when using I10CFR50.54(x). | ||
: 4. Enclosures | : 4. Enclosures | ||
: 4. 1 Fission Product Barrier M'atrix 4.2 System Malfunctions | : 4. 1 Fission Product Barrier M'atrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radiological Effluent 4.4l Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.1I0 Radiation Monitor Reading for Enclosure 4.3 EALs S Enclosure 4.1 Fission Product Barrier Matrix RPIOIAI500010011 Page 1 of 5 ission Product Barrier status (,Intact, Potential Loss, or Loss). Add points for all barriers. | ||
Rad Levels/Radiological Effluent 4.4l Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms | |||
Declaration Guidelines 4.1I0 Radiation Monitor Reading for Enclosure 4.3 EALs S Enclosure | |||
Product Barrier Matrix RPIOIAI500010011 Page 1 of 5 ission Product Barrier status (,Intact, Potential Loss, or Loss). Add points for all barriers. | |||
Classify J)W.Ie events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is hours). In this IMMINENT LOSS situation, use judgment and classify as if the thresholds are exceeded.ission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions | Classify J)W.Ie events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is hours). In this IMMINENT LOSS situation, use judgment and classify as if the thresholds are exceeded.ission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions | ||
;or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.ion (C SF) indications are not meant to include transient alarm conditions which may appear during the start-up of ment. A CSF condition is satisfied when the alarmed state is valid and sustained. | ;or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.ion (C SF) indications are not meant to include transient alarm conditions which may appear during the start-up of ment. A CSF condition is satisfied when the alarmed state is valid and sustained. | ||
The STA should be consulted to alidated prior to the CSF being used as a basis to classify an emergency. | The STA should be consulted to alidated prior to the CSF being used as a basis to classify an emergency. | ||
of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-___{ IC jAlert IC f Site Area Emergency | of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-___{ IC jAlert IC f Site Area Emergency | ||
{ IC General Emergency 4. l.A.l Loss OR Potential Loss of Nuclear Coolant System 4.1.S.1 Loss OR Potential Loss of Both Nuclear Coolant System AN I Fuel Clad 4. I.G.I Loss of All Three Barriers 4.l.A.2 4.L.A.3 Loss OR_ Potential Loss of Fuel Clad Loss AND l'otential Loss Combinations of B~oth Nuclear Coolant System ANt)Fuel Clad 4.l.G.2 Loss of Any Two B~arriers AN I Potential Loss of the Third Cot a' t ll mlncolt A N )l~oss of Containmnent A N)ILoss OR Potenthil Loss 0 Enclosure | { IC General Emergency 4. l.A.l Loss OR Potential Loss of Nuclear Coolant System 4.1.S.1 Loss OR Potential Loss of Both Nuclear Coolant System AN I Fuel Clad 4. I.G.I Loss of All Three Barriers 4.l.A.2 4.L.A.3 Loss OR_ Potential Loss of Fuel Clad Loss AND l'otential Loss Combinations of B~oth Nuclear Coolant System ANt)Fuel Clad 4.l.G.2 Loss of Any Two B~arriers AN I Potential Loss of the Third Cot a' t ll mlncolt A N )l~oss of Containmnent A N)ILoss OR Potenthil Loss 0 Enclosure 4.1 Fission Product Barrier Matrix RP/O/A/5000/001I Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based on a "potential loss" or" a "loss." "Not Applicable" is inclu~ded in the table as a place holder only, and has no point v'alue assigned.Barrier IPoints (1-5) Potential Loss (X) Loss (X) Total IPoints Classification Containment 1 3 1 -3 Unusual Event-NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Elmergency Total Points 1 -13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of 5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description. | ||
Product Barrier Matrix RP/O/A/5000/001I Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based on a "potential loss" or" a "loss." "Not Applicable" is inclu~ded in the table as a place holder only, and has no point v'alue assigned.Barrier IPoints (1-5) Potential Loss (X) Loss (X) Total IPoints Classification Containment 1 3 1 -3 Unusual Event-NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Elmergency Total Points 1 -13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of 5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description. | |||
: 3. For each barrier, write the highest single point value applicable for the barrier in the "'Points" column and mark the appropriate | : 3. For each barrier, write the highest single point value applicable for the barrier in the "'Points" column and mark the appropriate | ||
"'loss"~COltllnnl. | "'loss"~COltllnnl. | ||
: 4. Add the points in the lPoints'" column and record the sum as "'Total Points".5. Determine the classilqcation level based on the number of "Total Points".6. In the table on" page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. 1 for Loss of Nuclear Coolant System) that best fits the loss of harrier descriptions. | : 4. Add the points in the lPoints'" column and record the sum as "'Total Points".5. Determine the classilqcation level based on the number of "Total Points".6. In the table on" page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. 1 for Loss of Nuclear Coolant System) that best fits the loss of harrier descriptions. | ||
: 7. Usingt the number (e.g. 4.1 .A. I). select the preprinted notification form OR a blank notification form and complete the required nflornmt ion Ibr Emergency Coordinator approval and transmittal. | : 7. Usingt the number (e.g. 4.1 .A. I). select the preprinted notification form OR a blank notification form and complete the required nflornmt ion Ibr Emergency Coordinator approval and transmittal. | ||
0 Enclosure | 0 Enclosure 4.1 RPIOIA15000100 1 Page 3 of 5 Fission Product Barrier Matrix 4.1.C CONTAINMIENT BARRI,1ER 4.1.N NCS BARRIER 4.I.F FUEL CLAD BARRIER POTENTIAL LOSS -/(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points).....h .. .. ... .. ..I -I -* I 1. Critical Safety Function Status* Containment-RED | ||
1 Page 3 of 5 Fission Product Barrier Matrix 4.1.C CONTAINMIENT BARRI,1ER 4.1.N NCS BARRIER 4.I.F FUEL CLAD BARRIER POTENTIAL LOSS -/(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points).....h .. .. ... .. ..I -I -* I 1. Critical Safety Function Status* Containment-RED | |||
* Not applicable | * Not applicable | ||
* Core cooling-RED Path is indicated for > 15 minutes 2. Containnment Conditions | * Core cooling-RED Path is indicated for > 15 minutes 2. Containnment Conditions | ||
| Line 880: | Line 778: | ||
OIPERATING MODE: ALL 4.2.11.5-1 Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perfonn routine operations. | OIPERATING MODE: ALL 4.2.11.5-1 Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perfonn routine operations. | ||
*4.2.UJ.5-2 Loss of all offsite communications capability (Duke Emergenacy M-anagemtent Network [DE MN El].NR(" ETIS linies, ol'lhite radio system, commcreial phonec system) a llicting the abilitly to commun~icate wvith of'tsite antltori ties.END) | *4.2.UJ.5-2 Loss of all offsite communications capability (Duke Emergenacy M-anagemtent Network [DE MN El].NR(" ETIS linies, ol'lhite radio system, commcreial phonec system) a llicting the abilitly to commun~icate wvith of'tsite antltori ties.END) | ||
Enclosure | Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 of"5 G;ENERAl. | ||
Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 of"5 G;ENERAl. | |||
EMERG ENC\Y[;NUSI!AI, I-\.'ENT ALERT SITE Ai REA E:M ERG EN(CV 4.3.L .1 Any Unplanned Release (of Gaseous or 4.3.A.1 Liquid Radioactivity to the Environment thtat Exceeds Two Tiumes the SL(: Limits for 60 Minutes or Longer.Any I nlplaunnd Release of Gaseous or Liquid Radioactivity to the Eiuvironmcnt thatt Exceeds 200 Times the SLC limits for 15 Minutes or Longer.4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100 mrem TED)E or 500 mrem CDE Adult TIhyroid for the Actual or Projected Duration of the Release.OPERV [TINC MODE: AII OPElRATING MODE: ALL 4.3.Ui.1-1 A valid Tlrip 2 alarm on radiation monitor E~vlF-49L or ENvlF'-57 or > 60 minuteS or will likely continue for >_ 60 minultes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure | EMERG ENC\Y[;NUSI!AI, I-\.'ENT ALERT SITE Ai REA E:M ERG EN(CV 4.3.L .1 Any Unplanned Release (of Gaseous or 4.3.A.1 Liquid Radioactivity to the Environment thtat Exceeds Two Tiumes the SL(: Limits for 60 Minutes or Longer.Any I nlplaunnd Release of Gaseous or Liquid Radioactivity to the Eiuvironmcnt thatt Exceeds 200 Times the SLC limits for 15 Minutes or Longer.4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100 mrem TED)E or 500 mrem CDE Adult TIhyroid for the Actual or Projected Duration of the Release.OPERV [TINC MODE: AII OPElRATING MODE: ALL 4.3.Ui.1-1 A valid Tlrip 2 alarm on radiation monitor E~vlF-49L or ENvlF'-57 or > 60 minuteS or will likely continue for >_ 60 minultes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure | ||
[-IP/0/B/1009/0 14.4I.3.tJ..i-2 A valid indication on radiation monitor EMF- 36L of>_ 3.(0E+t04 cpm for->_ 60)minutes or will likely continue for >- 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AID-HP-ALIL-0202.4..3.A.1-1 A\ valid indication on radiation monitor EMF- 49L or EMvF-57 of> 1.2E+05 cpm lbr> 15 minutes or will likely continue for --15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H-P/0/B3/1009/014.(Continued) | [-IP/0/B/1009/0 14.4I.3.tJ..i-2 A valid indication on radiation monitor EMF- 36L of>_ 3.(0E+t04 cpm for->_ 60)minutes or will likely continue for >- 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AID-HP-ALIL-0202.4..3.A.1-1 A\ valid indication on radiation monitor EMF- 49L or EMvF-57 of> 1.2E+05 cpm lbr> 15 minutes or will likely continue for --15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H-P/0/B3/1009/014.(Continued) | ||
OIPERATING NIOIOE: ALiL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of> 2.7E+06 cpm sustained for> IS1 minmutes.4.3.S.1-2 Dose assessment teamn calculations in~dicate dose consequences greater than 100 mrem "IEDE or 500 mrem CDE Adult Thlyroid at the site houndary.4.3.G.1 Boundary l)ose Resultitng f'rom an Actual or hmnmitent Release of Radioactivity that Exceeds 1000 mrenm TEDE or 5000)onrei CDE Adult Thyroid for the Atuald or Projected Duration of the Release. | OIPERATING NIOIOE: ALiL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of> 2.7E+06 cpm sustained for> IS1 minmutes.4.3.S.1-2 Dose assessment teamn calculations in~dicate dose consequences greater than 100 mrem "IEDE or 500 mrem CDE Adult Thlyroid at the site houndary.4.3.G.1 Boundary l)ose Resultitng f'rom an Actual or hmnmitent Release of Radioactivity that Exceeds 1000 mrenm TEDE or 5000)onrei CDE Adult Thyroid for the Atuald or Projected Duration of the Release. | ||
MODE: ALL 4.3.G.1-1 A valid indication on radiation monitor EMF-36t-of> _8.3E+03 cpm sustained lbr > 15 minutes.4.3.G.1-2 Dose assessment team calculations indicate dose conseqtuences greater than 1000 ,mrem TEDE or 5000 mrcm CDL Adtmh Thyroid at the site boundary.lConmtin ned)(( "ontini, ed) 0 Enclosure | MODE: ALL 4.3.G.1-1 A valid indication on radiation monitor EMF-36t-of> _8.3E+03 cpm sustained lbr > 15 minutes.4.3.G.1-2 Dose assessment team calculations indicate dose conseqtuences greater than 1000 ,mrem TEDE or 5000 mrcm CDL Adtmh Thyroid at the site boundary.lConmtin ned)(( "ontini, ed) 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent R.P/O/A/5000/OO01 Page 2 of 5 GENERA I EM'ERGENCY UNU.SUAL, EVENT ALERT SITE AREA EM1ERGENCY 4.3.12...-3 Gaseous effluent being released exceeds two times SLC 16.1 1-6 for >60 minutes as determined by RP~procedure. | ||
Rad Levels/Radiological Effluent R.P/O/A/5000/OO01 Page 2 of 5 GENERA I EM'ERGENCY UNU.SUAL, EVENT ALERT SITE AREA EM1ERGENCY 4.3.12...-3 Gaseous effluent being released exceeds two times SLC 16.1 1-6 for >60 minutes as determined by RP~procedure. | |||
4,3.U.1-4 Liquid effluent being released exceeds two times SLC 16.11 I- for>60 minutes as determined by RP procedure. | 4,3.U.1-4 Liquid effluent being released exceeds two times SLC 16.11 I- for>60 minutes as determined by RP procedure. | ||
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continued) 4.3.A.1-2 A valid indication on radiation nmonitor EMF- 36L of_>5.4E+05 cpm for> 15 minutes or will likely continue for >-15 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202. | Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continued) 4.3.A.1-2 A valid indication on radiation nmonitor EMF- 36L of_>5.4E+05 cpm for> 15 minutes or will likely continue for >-15 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202. | ||
| Line 900: | Line 792: | ||
Note 2: If dose assessment team calculations cannot be completed in I 5 minutes.then valid monitor reading should be used for emergency classification. | Note 2: If dose assessment team calculations cannot be completed in I 5 minutes.then valid monitor reading should be used for emergency classification. | ||
END) | END) | ||
Enclosure | Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/O/A/5000/001I Page 3 of"5 GENERAL EM'ERGENCY UNLUSI.1AL EVENT ALERT SITE AREA EMERGENCY 41.3. I.2 Uneixpected Increase in Plant Radiation or Airborne Concentration. | ||
Rad Levels/Radiological Effluent RP/O/A/5000/001I Page 3 of"5 GENERAL EM'ERGENCY UNLUSI.1AL EVENT ALERT SITE AREA EMERGENCY 41.3. I.2 Uneixpected Increase in Plant Radiation or Airborne Concentration. | |||
OPERATING MODE: ALL 4.3.U.2-1 Indication of uncontrolled water level decrease of greater than _6 inches inl the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.U.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pool and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.U.2-3 Unplanned valid area EM~F reading increases by a factorof 1,000 over normal levels as shown in Enclosure 4.10.END 4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel.Does not apply to spent fuel in diy cask storage. Refer to EPLAN Section D basis document OPERATING MODE: ALL 4.3.A.2-1 An unplanned valid trip I1 alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge IEMF-15 2EMF-4 Spent Fuel Pool Ventilation I EMIF-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Nlode Only)IEMF-17 2EM lF-2 Containment Noble Gas Monitor (Applies to Mode 6 and No Mode (Jnly)1 EMF-39 2EiNlF-3') | OPERATING MODE: ALL 4.3.U.2-1 Indication of uncontrolled water level decrease of greater than _6 inches inl the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.U.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pool and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.U.2-3 Unplanned valid area EM~F reading increases by a factorof 1,000 over normal levels as shown in Enclosure 4.10.END 4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel.Does not apply to spent fuel in diy cask storage. Refer to EPLAN Section D basis document OPERATING MODE: ALL 4.3.A.2-1 An unplanned valid trip I1 alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge IEMF-15 2EMF-4 Spent Fuel Pool Ventilation I EMIF-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Nlode Only)IEMF-17 2EM lF-2 Containment Noble Gas Monitor (Applies to Mode 6 and No Mode (Jnly)1 EMF-39 2EiNlF-3') | ||
l( " liii ijed I 0 VP Enclosure 4.3 RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 4 of"5 UiNtSUAkL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity. spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any iIradiated fuel will become uncovered. | l( " liii ijed I 0 VP Enclosure 4.3 RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 4 of"5 UiNtSUAkL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity. spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any iIradiated fuel will become uncovered. | ||
| Line 937: | Line 826: | ||
* Spent Fuel Pool level alnd/or" temlperalture showv degraded performlance t(-'ontinulicd) | * Spent Fuel Pool level alnd/or" temlperalture showv degraded performlance t(-'ontinulicd) | ||
Enclosure 4.6 RP/0/A/5 000/001 Fire/Explosion andi Security Events Page 3 of' 3 I)NLISLAL EVENT AILERT SITE AREA EMERGENC'Y GENERAL ENIER(GENCY' Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling.4.6.A.3 HOSTILE ACTION Within tihe OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift Supervision 4.6.A.3-2 A validated notification from NRC of airliner attack threat within 30 minutes of the site.E NI) | Enclosure 4.6 RP/0/A/5 000/001 Fire/Explosion andi Security Events Page 3 of' 3 I)NLISLAL EVENT AILERT SITE AREA EMERGENC'Y GENERAL ENIER(GENCY' Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling.4.6.A.3 HOSTILE ACTION Within tihe OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift Supervision 4.6.A.3-2 A validated notification from NRC of airliner attack threat within 30 minutes of the site.E NI) | ||
Enclosure | Enclosure 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant SafetyEVENT'ALERT SITE AREA EMERGENCY 4.7.1U.1 Natural and Destructive Phenomena Affecting tihe Protected Area.OPERATING MODE: ALL 4.7.U1.1-1 Tremor felt and valid alarm on tihe Syscom Seismic Monitoring Systemn (OAC C 1 D22 52).4.7.U1.1-2 Report by plant personnel of toi-nado striking within protected area botmdary/ISFSI. | ||
Disasters, Hazards, And Other Conditions Affecting Plant SafetyEVENT'ALERT SITE AREA EMERGENCY 4.7.1U.1 Natural and Destructive Phenomena Affecting tihe Protected Area.OPERATING MODE: ALL 4.7.U1.1-1 Tremor felt and valid alarm on tihe Syscom Seismic Monitoring Systemn (OAC C 1 D22 52).4.7.U1.1-2 Report by plant personnel of toi-nado striking within protected area botmdary/ISFSI. | |||
4.7.U1.1-3 Vehicle crash into plant structures or systems within protected area boundary!/ISFSlI. | 4.7.U1.1-3 Vehicle crash into plant structures or systems within protected area boundary!/ISFSlI. | ||
4.7.U1.1-4 Report of turbine Fa~ilure resulting in casing penetration or damage to turbine or generator seals.4.7.1_1.1-5 Independent Spent Fuel Cask tipped over or dr'opped greater than 24 inches.4.7.11..1-6 Uncontrolled Ilooding in the ISFSI area.4.7.11. .1-7 Tornado generatecd missiles(s) impacting the ISFSi.{(C oiitn liicud)4.7.A.!I Natural and Destructive Phenomena Affecting the Plant Vital Area.OPERATING MODE: ALL 4.7.A.1-1 Valid "OBE Exceeded" Alarm on I AD-4.B/8 4.7.AAl-2 | 4.7.U1.1-4 Report of turbine Fa~ilure resulting in casing penetration or damage to turbine or generator seals.4.7.1_1.1-5 Independent Spent Fuel Cask tipped over or dr'opped greater than 24 inches.4.7.11..1-6 Uncontrolled Ilooding in the ISFSI area.4.7.11. .1-7 Tornado generatecd missiles(s) impacting the ISFSi.{(C oiitn liicud)4.7.A.!I Natural and Destructive Phenomena Affecting the Plant Vital Area.OPERATING MODE: ALL 4.7.A.1-1 Valid "OBE Exceeded" Alarm on I AD-4.B/8 4.7.AAl-2 | ||
| Line 947: | Line 833: | ||
OPERATING MIODE: ALL 4.7.S.2-l Other conditions exist which in the Judgement of the Emergency Coordinator!EGF Director indicate actual or likely major f~itilures ol plant functions needed lor protection of the~ public.END RP/O/A/5 000/001 Page 1 of 4 GENERAL EM'ERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency. | OPERATING MIODE: ALL 4.7.S.2-l Other conditions exist which in the Judgement of the Emergency Coordinator!EGF Director indicate actual or likely major f~itilures ol plant functions needed lor protection of the~ public.END RP/O/A/5 000/001 Page 1 of 4 GENERAL EM'ERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency. | ||
OPERATING MODE: ALL 4.7.G.1-I Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (1) actual or imminent substantial core degradation with potential for loss of containmaent OR (2) potential for uncontrolled radionuclide releases. | OPERATING MODE: ALL 4.7.G.1-I Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (1) actual or imminent substantial core degradation with potential for loss of containmaent OR (2) potential for uncontrolled radionuclide releases. | ||
These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.En __)OR sustained winds >_ 74 mph for> 15 minutes.(Continued) 0 Enclosure | These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.En __)OR sustained winds >_ 74 mph for> 15 minutes.(Continued) 0 Enclosure 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety RPIO/AI/500I/O01 Page 2 o1"4 GFNERAL EMERGENCY IJNUSUJAL EVENT ALERT SITE AREA 4.7.1_1.2 Release of Toxic or Flanmnable Gases D~eemed Detrimental to Safe Operation or the Plant.OPERALTING MODE: ALL 4.7.U.2-l Report or detection of'toxic or flammable gases that could enter within the site boundary in amounts that can aff'ect safe operation of the plant.4.7.U.2-2 Report by Local. County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgeinent of the Emergency Coordiziator/EOF Director Warrant Declaration of an Unusual Event.OPERATING MODE: AILL 4.7. U.3-1I Other conditions exist which in the j udgcmlcnt o f thte Emcrgency Coordinazor/ELOF D)irector indic'ate a potential degradatlion ofth lt evel of Siitct\' of'thlw plaint.4.7.A. 1-3 Visible structural damage caused by either:* Vehicle crashes OR*Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures: | ||
Disasters, Hazards, And Other Conditions Affecting Plant Safety RPIO/AI/500I/O01 Page 2 o1"4 GFNERAL EMERGENCY IJNUSUJAL EVENT ALERT SITE AREA 4.7.1_1.2 Release of Toxic or Flanmnable Gases D~eemed Detrimental to Safe Operation or the Plant.OPERALTING MODE: ALL 4.7.U.2-l Report or detection of'toxic or flammable gases that could enter within the site boundary in amounts that can aff'ect safe operation of the plant.4.7.U.2-2 Report by Local. County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgeinent of the Emergency Coordiziator/EOF Director Warrant Declaration of an Unusual Event.OPERATING MODE: AILL 4.7. U.3-1I Other conditions exist which in the j udgcmlcnt o f thte Emcrgency Coordinazor/ELOF D)irector indic'ate a potential degradatlion ofth lt evel of Siitct\' of'thlw plaint.4.7.A. 1-3 Visible structural damage caused by either:* Vehicle crashes OR*Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures: | |||
* Reactor Building* Auxiliary Building* FWST* Diesel Generator Rooms SControl Room* RN Pump 1-ouse* SSF* Doghouses* CAS* SAS (Continued) | * Reactor Building* Auxiliary Building* FWST* Diesel Generator Rooms SControl Room* RN Pump 1-ouse* SSF* Doghouses* CAS* SAS (Continued) | ||
[NI) | [NI) | ||
| Line 1,127: | Line 1,010: | ||
Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence or" the event.2.2 Assessment, classification and declaration of any applicable emergency condition shouild be completed within 15 minutes after the availability of indications or inf'ormation to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 IF the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix) OR refer to EAL wvallboards. | Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence or" the event.2.2 Assessment, classification and declaration of any applicable emergency condition shouild be completed within 15 minutes after the availability of indications or inf'ormation to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 IF the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix) OR refer to EAL wvallboards. | ||
__2.5 IF a General Emergency is NOT declared in Step 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to EA\L wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated. | __2.5 IF a General Emergency is NOT declared in Step 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to EA\L wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated. | ||
2.7 Document the declaration time. __________ | |||
2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERO Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportuinity that will not intert'ere with the performance of the crew or the flow of the Emergency Procedure. | |||
the declaration time. __________ | |||
the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERO Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportuinity that will not intert'ere with the performance of the crew or the flow of the Emergency Procedure. | |||
: 2. 1 0 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel. | : 2. 1 0 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel. | ||
RP/O/A/5000/00 I Page 4 o t"4 2.1!1 Implement the applicable Emergency Response Procedure (RP) f~or that classification and continue with subsequent steps of this procedure. | RP/O/A/5000/00 I Page 4 o t"4 2.1!1 Implement the applicable Emergency Response Procedure (RP) f~or that classification and continue with subsequent steps of this procedure. | ||
| Line 1,141: | Line 1,020: | ||
If the TSC is activated, contact the TSC Emergency Coordinator (EC)for concurrence when using IOCFR5O.54(x). | If the TSC is activated, contact the TSC Emergency Coordinator (EC)for concurrence when using IOCFR5O.54(x). | ||
: 4. Enclosures | : 4. Enclosures | ||
: 4. 1 Fission Product Barrier Matrix 4.2 System Malfunctions | : 4. 1 Fission Product Barrier Matrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radio logical Effluent 4.4 Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.10 Radiation Monitor Reading for Enclosure 4.3 EALs 0 0 Enclosure 4.1 RPIOIA!5000/001I Page 1 of'5 Fission lProduct Barrier Matrix 1.Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all barriers. | ||
Rad Levels/Radio logical Effluent 4.4 Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms | |||
Declaration Guidelines 4.10 Radiation Monitor Reading for Enclosure 4.3 EALs 0 0 Enclosure 4.1 RPIOIA!5000/001I Page 1 of'5 Fission lProduct Barrier Matrix 1.Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all barriers. | |||
Classify according to the table below.Note 1 : An event (or multiple events) could occur which results in the conclusion that exceeding thle Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT LOSS situation, use judgment and classify' as if the thresholds are exceeded.Note 2: When determining Fission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions for the Fuel Clad Barrier loss or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.Note 3: Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the stait-up of engineered safeguards equipment. | Classify according to the table below.Note 1 : An event (or multiple events) could occur which results in the conclusion that exceeding thle Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT LOSS situation, use judgment and classify' as if the thresholds are exceeded.Note 2: When determining Fission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions for the Fuel Clad Barrier loss or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.Note 3: Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the stait-up of engineered safeguards equipment. | ||
A CSF condition is satisfied when the alamred state is valid and sustained. | A CSF condition is satisfied when the alamred state is valid and sustained. | ||
| Line 1,154: | Line 1,026: | ||
Example: If ECA-0.0, Loss of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF should be used as the basis to classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-O.O.IC Unusual Event IC Alert IC Site Area Emergency IC General Emergency LossOR Ptenial ossLoss OR Potential Loss Potential Loss of of 41 1of Both Loss of 4.1nU.aI4.1ent. | Example: If ECA-0.0, Loss of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF should be used as the basis to classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-O.O.IC Unusual Event IC Alert IC Site Area Emergency IC General Emergency LossOR Ptenial ossLoss OR Potential Loss Potential Loss of of 41 1of Both Loss of 4.1nU.aI4.1ent. | ||
Nuclear Coolant System Nuclear Coolant System AND 4. G otimn ___All Three Barriers Fuel Clad Loss AND Loss OR P~otential Loss Potential Loss CombinationsLosf | Nuclear Coolant System Nuclear Coolant System AND 4. G otimn ___All Three Barriers Fuel Clad Loss AND Loss OR P~otential Loss Potential Loss CombinationsLosf | ||
: 4. U2 Loss ofl .A2o .S2o oh41.. Any Two Barriers AN D 4IU Containment 4... f4lS2o oh4102 Potential Loss of the Fuel Clad Nuclear Coolant System ANDThr Fuel CladThr Potentia Losssofof Containment ANI)4. Conaimet.3t 4.1.S.3 Loss Ok Potential Loss of I .A.~ Loss OR Potential LossAnOtrBrie Aof OteyBare Any Other Barrier 0l Enclosure | : 4. U2 Loss ofl .A2o .S2o oh41.. Any Two Barriers AN D 4IU Containment 4... f4lS2o oh4102 Potential Loss of the Fuel Clad Nuclear Coolant System ANDThr Fuel CladThr Potentia Losssofof Containment ANI)4. Conaimet.3t 4.1.S.3 Loss Ok Potential Loss of I .A.~ Loss OR Potential LossAnOtrBrie Aof OteyBare Any Other Barrier 0l Enclosure 4.1 Fission Product Barrier Matrix RPlO I AI50 00/001 Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based onl a "potential loss" or a "loss." "Not Applicable" is included in thle table as a place holder only, and has no point value assigned.Barrier Points (1-5) Potential Loss (X) Loss (X) Total Points Classification Containmenat 1 3 1 -3 Unusual Event NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Emergency Total Points | ||
Product Barrier Matrix RPlO I AI50 00/001 Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based onl a "potential loss" or a "loss." "Not Applicable" is included in thle table as a place holder only, and has no point value assigned.Barrier Points (1-5) Potential Loss (X) Loss (X) Total Points Classification Containmenat 1 3 1 -3 Unusual Event NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Emergency Total Points | |||
-13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of"5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description. | -13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of"5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description. | ||
: 3. For each barrier, write the highest single point value applicable for the barrier in the "Points" column and mark the appropriate "loss" column.4. Add the points in the "'Points" column and record the sum as "Total Points".5. Determine the classification level based on thle number of "Total Points".6. In thle table on page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. I for Loss of Nuclear Coolant S,,ystem) that best fits thle loss of barrier descriptions. | : 3. For each barrier, write the highest single point value applicable for the barrier in the "Points" column and mark the appropriate "loss" column.4. Add the points in the "'Points" column and record the sum as "Total Points".5. Determine the classification level based on thle number of "Total Points".6. In thle table on page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. I for Loss of Nuclear Coolant S,,ystem) that best fits thle loss of barrier descriptions. | ||
| Line 1,174: | Line 1,043: | ||
* Not applicable | * Not applicable | ||
* Coolant Activity* GREATER THAN 300 p~i/cc Dose Equivalent Iodine (DEl) 1-131 CONTINtJEI) | * Coolant Activity* GREATER THAN 300 p~i/cc Dose Equivalent Iodine (DEl) 1-131 CONTINtJEI) | ||
()TNJI N NtEI (-'ONTIN I)ED ('ONTINIIED Enclosure | ()TNJI N NtEI (-'ONTIN I)ED ('ONTINIIED Enclosure 4.1 RPIOIAIS001001 Page 4 of 5 Fission Product Barrier Matrix 4.!.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4. I.F FUEL CLAI) BARRIER POTENTIAL LOSS -( I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)lil r... ... .. .I I I I 3. Containment lsolation Valves Status After Containment Isolationi Actuation 3. SC Tube Rupt ire ItI BIB tlhtl tIi tiIUl J RTU lllfl B lURB .Not applicable | ||
Page 4 of 5 Fission Product Barrier Matrix 4.!.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4. I.F FUEL CLAI) BARRIER POTENTIAL LOSS -( I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)lil r... ... .. .I I I I 3. Containment lsolation Valves Status After Containment Isolationi Actuation 3. SC Tube Rupt ire ItI BIB tlhtl tIi tiIUl J RTU lllfl B lURB .Not applicable | |||
.Containment isolation is incomplete and a direct release path lioin containment exists to the environment Pri mary-to-Secondary leak rate exceeds the capacity of one charging pump in the normal charging mode with letdown isolated.* Indication that a SG is Ruptured and has a Non-Isolable secondary line fault* Indication that a SG is ruptured and a prolonged release of contaminated secondary coolant is occurring from the affected SG to the environmnent Not applicable | .Containment isolation is incomplete and a direct release path lioin containment exists to the environment Pri mary-to-Secondary leak rate exceeds the capacity of one charging pump in the normal charging mode with letdown isolated.* Indication that a SG is Ruptured and has a Non-Isolable secondary line fault* Indication that a SG is ruptured and a prolonged release of contaminated secondary coolant is occurring from the affected SG to the environmnent Not applicable | ||
* Containment radiation monitor 53 A or 53 B Reading at time since Shutdown.0-0.5 hrs > 99 R/hr 0.5-2 hrs > 43 R/hr 2-4 hrs > 31 R/hr 4-8 hrs > 22 R/hr>8 hrs > 13 R/hr 4. Emereencv Coordinator/EOF Director 4. SC Secondary Side Release With Primary-to-Secondary Leakagle* Not applicable | * Containment radiation monitor 53 A or 53 B Reading at time since Shutdown.0-0.5 hrs > 99 R/hr 0.5-2 hrs > 43 R/hr 2-4 hrs > 31 R/hr 4-8 hrs > 22 R/hr>8 hrs > 13 R/hr 4. Emereencv Coordinator/EOF Director 4. SC Secondary Side Release With Primary-to-Secondary Leakagle* Not applicable | ||
| Line 1,198: | Line 1,064: | ||
4.2.1I.5-2 Loss of all offsite communications capabi Iity (Duke Emergency Mianagemenit Network {DI-rv.NI | 4.2.1I.5-2 Loss of all offsite communications capabi Iity (Duke Emergency Mianagemenit Network {DI-rv.NI | ||
'li.NR(" ETS lines. of'fsite radio system, commercial phone system) affecting! | 'li.NR(" ETS lines. of'fsite radio system, commercial phone system) affecting! | ||
the ability to communicate wvith ol'lsite authl ori ties.ENI) 0 Enclosure | the ability to communicate wvith ol'lsite authl ori ties.ENI) 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 o1'5 GENERtAI. | ||
Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 o1'5 GENERtAI. | |||
EMER(GENCTY IJNIJSI IAl, E:VENTI ALERT'SlITE AREA EM EIRGENC\: 4.3.ti.1 Any lUnplanned Release of(Gaseous or -t.3.A.1 Liquid Radioactivity to the Environment that Exceeds Two Times the SLC Limits fo~r 60 Minutes or Longer.Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environnment that Exceeds 200 Times the SLC limits for 15 Mlinutes or Longer.OPERA ITIN(; MODE: ALL OPERATING MODE.ALL 4t.3.UAt-t A vatid '[rip 2 alarm on radiation monitor EMIF-49L or EMF-57 for > 60 minutes or oil! likely continue obr > 601 minutes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H- P/0/B3/1009/0 14.4.3.1U.1-2 A valid indication on radiation monitor EMF- 36L of_> 3.00E+04 cpm lbr > 60 minutes or will likely' continue tbr _> 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD)-EI'-ALL-0202.4.3.A.l-1 A valid indication on radiation monitor EMF- 49L or EMF-57 of_ 1.2E+05 cpm lbr > 15 mfinutes or will likely continue for >15 mtnutes, which indicates that the releatse may have exceeded the initiating condition and indicates the need to assess the release with procedure ItP/0/B/ 1009/014.(Continued) 4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100l mirem TED)E or 500 anrem CDE Adult Thyroid for the Aetual or Projected Duration of the Release.OPERATING NMODE: ALL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of">_ 2.7E+06 cpm sustained for > 15 minutes.4.3.S.1-2 Dose assessment temn~calculations indicate dose consequences greater than 100 mrem T1EDE or 500 turen CDE Adult Thyroid at the site boundary.{(Continued) 4.3.G.1 Boundary l)ose Resulting from an Actual or Inmminent Release of Radioactivity that Exceeds 1000 wrenm ITEDE or 5000 mrema CDE Adult Thyroid fo~r the Actual or Projected Duration of the Release.OPERATING MIODE: ALL 4.3.G.t-1 A valid indication on radiation monitor EMF-36H]of">_ 8.3 E+03 cpm sustained tbr > I5 tminutes.4.3.G.1-2 Dose assessment team calculations indicate dose consequences greater than 1000 mrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.I Continued) t( 'ontinued) | EMER(GENCTY IJNIJSI IAl, E:VENTI ALERT'SlITE AREA EM EIRGENC\: 4.3.ti.1 Any lUnplanned Release of(Gaseous or -t.3.A.1 Liquid Radioactivity to the Environment that Exceeds Two Times the SLC Limits fo~r 60 Minutes or Longer.Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environnment that Exceeds 200 Times the SLC limits for 15 Mlinutes or Longer.OPERA ITIN(; MODE: ALL OPERATING MODE.ALL 4t.3.UAt-t A vatid '[rip 2 alarm on radiation monitor EMIF-49L or EMF-57 for > 60 minutes or oil! likely continue obr > 601 minutes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H- P/0/B3/1009/0 14.4.3.1U.1-2 A valid indication on radiation monitor EMF- 36L of_> 3.00E+04 cpm lbr > 60 minutes or will likely' continue tbr _> 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD)-EI'-ALL-0202.4.3.A.l-1 A valid indication on radiation monitor EMF- 49L or EMF-57 of_ 1.2E+05 cpm lbr > 15 mfinutes or will likely continue for >15 mtnutes, which indicates that the releatse may have exceeded the initiating condition and indicates the need to assess the release with procedure ItP/0/B/ 1009/014.(Continued) 4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100l mirem TED)E or 500 anrem CDE Adult Thyroid for the Aetual or Projected Duration of the Release.OPERATING NMODE: ALL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of">_ 2.7E+06 cpm sustained for > 15 minutes.4.3.S.1-2 Dose assessment temn~calculations indicate dose consequences greater than 100 mrem T1EDE or 500 turen CDE Adult Thyroid at the site boundary.{(Continued) 4.3.G.1 Boundary l)ose Resulting from an Actual or Inmminent Release of Radioactivity that Exceeds 1000 wrenm ITEDE or 5000 mrema CDE Adult Thyroid fo~r the Actual or Projected Duration of the Release.OPERATING MIODE: ALL 4.3.G.t-1 A valid indication on radiation monitor EMF-36H]of">_ 8.3 E+03 cpm sustained tbr > I5 tminutes.4.3.G.1-2 Dose assessment team calculations indicate dose consequences greater than 1000 mrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.I Continued) t( 'ontinued) | ||
Enclosure | Enclosure 4.3 Abnormal Rad Levels/Radiologicai Effluent RP/O/A/5000/001 Page 2 ot'5 GENERAL EMERGENCY UNulSUAL EVENT ALERT SITE AREA EMERGENCY 4.3.U.1-3 Gaseous effluent being released exceeds two times SLC 16.11-6 lbr >60 minutes as determined by RP procedure. | ||
Rad Levels/Radiologicai Effluent RP/O/A/5000/001 Page 2 ot'5 GENERAL EMERGENCY UNulSUAL EVENT ALERT SITE AREA EMERGENCY 4.3.U.1-3 Gaseous effluent being released exceeds two times SLC 16.11-6 lbr >60 minutes as determined by RP procedure. | |||
4.3.U.I-4 Liquid effluent being released exceeds two times SLC 16.11-I for>60 minutes as determined by RP procedure. | 4.3.U.I-4 Liquid effluent being released exceeds two times SLC 16.11-I for>60 minutes as determined by RP procedure. | ||
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continuemd) 4.3.A.i-2 A valid indication on radiation monitor EMF- 36L of>_5.4E+05 cpm for > 15 minutes or will likely continue for >15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202. | Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continuemd) 4.3.A.i-2 A valid indication on radiation monitor EMF- 36L of>_5.4E+05 cpm for > 15 minutes or will likely continue for >15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202. | ||
| Line 1,217: | Line 1,077: | ||
ENDI 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 1000 inrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.Note I : These EMF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available. | ENDI 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 1000 inrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.Note I : These EMF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available. | ||
Note 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid monitor reading should be used for emergency classification. | Note 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid monitor reading should be used for emergency classification. | ||
E NI 0 Enclosure | E NI 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 3 of 5.GENERAL EMERGENCY UNUSIJAL EVENT ALERT SITE AREA EM'ERGENCV: | ||
Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 3 of 5.GENERAL EMERGENCY UNUSIJAL EVENT ALERT SITE AREA EM'ERGENCV: | |||
4.3.U.2 Unexpected increase iin Plant Radiation or Airborne Concentration. | 4.3.U.2 Unexpected increase iin Plant Radiation or Airborne Concentration. | ||
OPERATING MODE: ALL 4.3.UJ.2-1I Indication of uncontrolled water level decrease of greater than 6_inches in the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.11.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pooi and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.11.2-3 Unplanned valid area EMF reading increases by a factor of 1 ,000 over normal levels as shown in Enclosure 4.10.EN I)4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that tlas or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor V'essel.SDoes not apply to spent fuel in dry cask storage. Refer to EPLAN Section D basis document OPERATING MIODE: ALL 4.3.A.2-1 An unplanned valid trip II alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge 1IEMF- 15 2EMF-4 Spent Fuel Pool Ventilation 1EM F-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Mode Only)l EMF-17 2EMF-2 Containment Noble Gas Monitor (Applies to Mode 6 andMode Only)I EM F-39 21N'lF-39 C(oniliiniud) | OPERATING MODE: ALL 4.3.UJ.2-1I Indication of uncontrolled water level decrease of greater than 6_inches in the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.11.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pooi and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.11.2-3 Unplanned valid area EMF reading increases by a factor of 1 ,000 over normal levels as shown in Enclosure 4.10.EN I)4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that tlas or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor V'essel.SDoes not apply to spent fuel in dry cask storage. Refer to EPLAN Section D basis document OPERATING MIODE: ALL 4.3.A.2-1 An unplanned valid trip II alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge 1IEMF- 15 2EMF-4 Spent Fuel Pool Ventilation 1EM F-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Mode Only)l EMF-17 2EMF-2 Containment Noble Gas Monitor (Applies to Mode 6 andMode Only)I EM F-39 21N'lF-39 C(oniliiniud) | ||
Enclosure | Enclosure 4.3 RPIOIAI5 000/001 Abnormal Rad Levels/Radiological Eftluent Page 4 of 5 UNUSUAL EVENTI ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any irradiated fiuel will become uncovered. | ||
000/001 Abnormal Rad Levels/Radiological Eftluent Page 4 of 5 UNUSUAL EVENTI ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any irradiated fiuel will become uncovered. | |||
4.3.A.2-3 NC system wide range level <95% after initiation ofhNC system make-up.AN.__D_Anly irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.4.3.A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.ANDI Any irradiated fuel assembly not capable of being fully lowered inb the spent fuel pool racks or transfer canal fuel transfer system basket.(Colnlinlued) | 4.3.A.2-3 NC system wide range level <95% after initiation ofhNC system make-up.AN.__D_Anly irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.4.3.A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.ANDI Any irradiated fuel assembly not capable of being fully lowered inb the spent fuel pool racks or transfer canal fuel transfer system basket.(Colnlinlued) | ||
Enclosure 4.3 RP/0/A/5000/00 Abnormial Rad Levels/Radiological Effluent Page 5 of 5 IUNtJSUAI EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases inl Radiation Levels Within the Facility That Inmpedes Operation of Systems Required to Mlaintain Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.3.A.3-1 V'alid reading on IEMF-12 greater than 1 5 mremihr in the Control Room.4.3.A.3-2 Valid indication of radiation levels greater than 15 nmremihr in the Central Alarm Station (_CAS) or Secondary Alarm Station (SAS).4.3.A.3-3 | Enclosure 4.3 RP/0/A/5000/00 Abnormial Rad Levels/Radiological Effluent Page 5 of 5 IUNtJSUAI EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases inl Radiation Levels Within the Facility That Inmpedes Operation of Systems Required to Mlaintain Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.3.A.3-1 V'alid reading on IEMF-12 greater than 1 5 mremihr in the Control Room.4.3.A.3-2 Valid indication of radiation levels greater than 15 nmremihr in the Central Alarm Station (_CAS) or Secondary Alarm Station (SAS).4.3.A.3-3 | ||
| Line 1,254: | Line 1,108: | ||
* Spent Fuel Pool level anld/or tempeC~llratr sho~v degraded pcrlbrmance | * Spent Fuel Pool level anld/or tempeC~llratr sho~v degraded pcrlbrmance | ||
!('on tin ued) | !('on tin ued) | ||
Enclosure 4.6 RP/0/A/5000/001 Fire/Explosion and Security Events Page 3 of 3 UJNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling~.4.6.A.3 IIOSTILE ACTION Within the OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift. Supervision 4.6.A.3-2 A validated notification from*NRC of airliner attack threat wiihin 30 minutes of the site.END Enclosure | Enclosure 4.6 RP/0/A/5000/001 Fire/Explosion and Security Events Page 3 of 3 UJNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling~.4.6.A.3 IIOSTILE ACTION Within the OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift. Supervision 4.6.A.3-2 A validated notification from*NRC of airliner attack threat wiihin 30 minutes of the site.END Enclosure 4.7 Natural Disasters, Iltazards, And Other Conditions Affecting Piant Safety UNUSUAL EVENT ALERT SITE AREA EMIERGENCY 4.7.U.1 Natural and Destructive Phenomena Affectinig tihe Protected Area. | ||
Disasters, Iltazards, And Other Conditions Affecting Piant Safety UNUSUAL EVENT ALERT SITE AREA EMIERGENCY 4.7.U.1 Natural and Destructive Phenomena Affectinig tihe Protected Area. | |||
MIODE: ALL 4.7.U.l-1 Tremor felt and valid alarm on the Syscom Seismic Monitoring System (OAC C 1D225 2).4.7.U.I-2 Report by plant personnel of tor'nado striking within protected area boundary/ISFSl. | MIODE: ALL 4.7.U.l-1 Tremor felt and valid alarm on the Syscom Seismic Monitoring System (OAC C 1D225 2).4.7.U.I-2 Report by plant personnel of tor'nado striking within protected area boundary/ISFSl. | ||
4.7.U.I-3 Vehicle crash into phlan structures or systems within protected area boundary/ISFSI. | 4.7.U.I-3 Vehicle crash into phlan structures or systems within protected area boundary/ISFSI. | ||
| Line 1,265: | Line 1,116: | ||
OPERATING MODE: ALL 4.7.S.2-1 Other conditions exist which in the J udgemient of the Emergency Coordinator/EOF-Director indicate actual or likely ma~jor lhuilures ofplant functions needed lbr protection of the public.I"N I)RP/0/A/5000/001I P~age I of 4 GENERAL EMIERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency. | OPERATING MODE: ALL 4.7.S.2-1 Other conditions exist which in the J udgemient of the Emergency Coordinator/EOF-Director indicate actual or likely ma~jor lhuilures ofplant functions needed lbr protection of the public.I"N I)RP/0/A/5000/001I P~age I of 4 GENERAL EMIERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency. | ||
OPERATING MODE: ALL 4.7.G.1-1 Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (I) actual or imminent substantial core degradation with potential for loss of containment OR (2) potential for uncontrolled radionuclide releases. | OPERATING MODE: ALL 4.7.G.1-1 Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (I) actual or imminent substantial core degradation with potential for loss of containment OR (2) potential for uncontrolled radionuclide releases. | ||
These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.L-NI)OR sustained winds >_ 74 mph lbr-" I5 minutes.t(oinllliuiedl 0 Enclosure | These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.L-NI)OR sustained winds >_ 74 mph lbr-" I5 minutes.t(oinllliuiedl 0 Enclosure 4.7 Natural Disasters, Hazards, Andi Other Conditions Affe~cting Plant Safety RP/0/A/5 000/001 Page 2 of 4 GENERAL EMERGENCY UNUSUAL EVENT ALERT SITE AREA EMERGENCY 4.7.11.2 Release of toxic or Fininniable Gases Deemed Detrimental to Safe Operation of the FPlant.O IPERATING MODE: ALL 4.7.U1.2-I Report or detection of toxic or flammable gases that could enter within the site boundary in amounts that can affect safe operation of the phlan.4.7.U1.2-2 Report by Local, County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgemtent of the Emergency Coordinator/EOF Dir-ector Warrant Declaraition of art Unusual Event.OIPERATING MODE: ALL 4.7.11.3-1 Other conditions exist which in thle juidg~eicnt of, the Emergency Coord ilnatoriLOF-lirector indicate a potei ti al dcegradation of the level of satet o~t' " theU p3tlant.4.7.A.1-3 Visible structural damage caused by cither:* Vehicle crashes OR* Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures: | ||
Disasters, Hazards, Andi Other Conditions Affe~cting Plant Safety RP/0/A/5 000/001 Page 2 of 4 GENERAL EMERGENCY UNUSUAL EVENT ALERT SITE AREA EMERGENCY 4.7.11.2 Release of toxic or Fininniable Gases Deemed Detrimental to Safe Operation of the FPlant.O IPERATING MODE: ALL 4.7.U1.2-I Report or detection of toxic or flammable gases that could enter within the site boundary in amounts that can affect safe operation of the phlan.4.7.U1.2-2 Report by Local, County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgemtent of the Emergency Coordinator/EOF Dir-ector Warrant Declaraition of art Unusual Event.OIPERATING MODE: ALL 4.7.11.3-1 Other conditions exist which in thle juidg~eicnt of, the Emergency Coord ilnatoriLOF-lirector indicate a potei ti al dcegradation of the level of satet o~t' " theU p3tlant.4.7.A.1-3 Visible structural damage caused by cither:* Vehicle crashes OR* Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures: | |||
* Reactor Building* Auxiliary Building* FW'ST* Diesel Generator Rooms* Control Room* RN Pump I-ouse* SSF* Doghouses* CAS* SAS V NI | * Reactor Building* Auxiliary Building* FW'ST* Diesel Generator Rooms* Control Room* RN Pump I-ouse* SSF* Doghouses* CAS* SAS V NI | ||
* | * | ||
Revision as of 02:25, 7 May 2019
| ML16070A245 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/08/2016 |
| From: | Henderson K Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNS-16-016 RP/0/A/5000/001, Rev. 035, RP/0/A/5000/001, Rev. 036 | |
| Download: ML16070A245 (97) | |
Text
Kelvin Henderson DUKE Vice President ENERGY°Catawba Nuclear Station Duke Energy CNS-1 6-016 CNO1VP 1 4800 Concord Road York, SC 29745 o: 803.701.4251 March 8, 2016 f- 803.701.3221 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414 Emergency Plan Implementing Procedures Please find enclosed for NRC Staff use the following Emergency Plan Implementing Procedures:
RP/O/A/5000/001 Classification of Emergency Revision 035 RP/0/A/5000/001I Classification of Emergency Revision 036 Due to a printing error in Revision 035 on page 1 of 5, Enclosure 4.1, Revision 036 has also been included.
These revisions are being submitted in accordance with 10OCFR 50.54(q) and do not cause a reduction in the effectiveness of the Emergency Plan Implementing Procedures or the Emergency Plan.There are no new regulatory commitments in these documents.
By copy of this letter, two copies of these documents are being provided to the NRC, Region II.If there are any questions, please call Tom Arlow at 803-701-4027.
Kelvin Henderson Vice President, Catawba Nuclear Station Attachments U.S. Nuclear Regulatory Commission March 8, 2016 Page 2 xc (w/attachments):
Catherine Haney, Regional Administrator U. S. Nuclear Regulatory Commission
-Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1 257 (w/o attachments):
Jeffrey Whited NRC Project Manager (CNS)U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-B1A 11555 Rockville Pike Rockville, MD 20852-2738 Page 1 of S PROCEDURE SRP/0/A/5000/001 RP/0/A/5000/002 RP/0/A/5000/003 RP/0/A/5 000/004 RP/0/A!5000/005 RP/0/A/5000/06 RP/0/A/5000/006 A RP/0/A/5000/006 B.RP/0/A/5000/006 C RP/0/A/5 00 0/0 07 RP/0/A/5000/08 RP/0/B/5000/008 RP/0/A/5000/009 RP/0/A/5000/0 10 RP/0/A/5000/1l1 RP/0/B/5000/12 RP/0/B/5000/0 13 RP/0/B/5000/14 RP/0/A!5000/0 15.RP/0/B/5000/016 RP/0/B/5000/17 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I TITLE Classification of Emergency (Rev. 035)Notification of Unusual Event (Rev. 045)Alert (Rev. 050)Site Area Emergency (Rev. 053)General Emergency (Rev. 054)Deleted Notifications to States and Counties from the Control Room (Rev. 033)Notifications to States and Counties from the Technical Support Center (Rev. 0/37)Deleted Natural Disaster and Earthquake (Rev. 043)Deleted Hazardous Materials Spill Response (Rev. 043)Collision/Explosion (Rev. 012)Conducting a Site Assembly or Preparing the Site for an Evacuation (Rev. 027)Deleted Deleted NRC Notification Requirements (Rev. 038)Deleted Core Damage Assessment (Rev. 007)Deleted Deleted February 17, 2016 Page 2 of 5 PROCEDURE RP/0/A/5000/01 8 RP/0/B/5000/019 RP/O/A/5000/020 RP/0/A/5000/021 RP/0/B/5000/022 RP/0/B/5000/023 RP/0/A/5000/024 RP/0/B/5000/025 RP/0/A/5000/026 RP/0/B/5 000/028 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I TITLE Emergency Worker Dose Extension (Rev. 002)Deleted Technical Support Center (TSC) Activation Procedure (Rev. 038)Deleted Deleted Deleted OSC Activation Procedure (Rev. 034)Recovery and Reentry Procedure (Rev. 003)Site Response to Security Events (Rev. 017)Nuclear Communications Emergency Response Plan (Rev. 006)February 17, 2016 Page 3 of 5 PROCEDURE HP/O/B/1000/006 HP/0/B/1009/001 HP/0/B/1009/003 HP/0/B/1009/004 HP/0/B/1009/005 HP/0/B/1009/006 HP/0/B/1 009/007 HP/0/B/1009/008 HP/0/B/1009/009 HP/0/B/1009/014 HP/0/B/1009/016 HP/0/B/1009/017 HP/1/B/1009/017 HP/2/B/1009/017 HP/0/B/1009/0 18 HIP/0/B/1009/019 HP/0/B/1009/024 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II TITLE Emergency Equipment Functional Check and Inventory (Rev. 060)Deleted Radiation Protection Primary to Secondary Leakage Program (Rev. 012)Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 031)Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 018)Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 009)In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 020)Contamination Control of Injured Individuals (Rev. 016)Deleted Radiation Protection Actions Following an Uncontrolled Release of Liquid Radioactive Material (Rev. 009)Deleted Deleted Deleted Deleted Deleted Emergency Radio System Operation, Maintenance and Communication (Rev. 010)Implementing Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 002)February 17, 2016 Page 4 of 5 PROCEDURE HP/0/B/1009/025 HP/0/B/1 009/026 SH/0/B/2005/00 1 SH/0/B/2005/002 SH/0/B/2005/003 OP/0/A!6200/02 1 SR/0/B/2000/001I SR/0/A/2000/001 SR/0/B/2000/002 SR/0/A!2000/003 SR/0/B/2000/003 SR/0/A!2000/004 SR/0/B/2000/004 AP/0/A/5500/046 AD-EP-ALL-0202 AD-EP-ALL-0203 AD-EP-ALL-0204 AD-EP-ALL-0301 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II TITLE Deleted Superseded Superseded Deleted Deleted Deleted Deleted Standard Procedure for Corporate Communications Response to the Emergency Operations Facility (Applies to Catawba/McGuire/Oconee) (Rev. 002)Deleted Activation of the Emergency Operations Facility (Rev. 008)Deleted Notifications to States and Counties from the Emergency Operations Facility for Catawba, McGuire and Oconee (Rev. 006)Deleted Hostile Aircraft Activity (Rev. 008)Emergency Response Offsite Dose Assessment (Rev. 001)Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev 000 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev 000)Activation of the Emergency Response Organization Notification System (ERONS) (Rev. 000)February 17, 2016 Page 5 of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE AD-EP-ALL-0406 TITLE Duke Energy Management Network (DEMNET) (Rev 001)February 17, 2016 Form 703-1. Procedure Process Record (PPR)S I II- 41 Duke Energy PROCEDURE PROCESS RECORD (I) ID No. RP/0/A/5000/001 RC 0 o. 035 PREPARATION (2) Strat ion _____(3) Procedure Title Ca.awa.Nucear.Satio (5) Requires NSD 22, Applicability Determination?
[] Yes (New procedure or revision with major chang'es)
-Attach NSD 228 documentation E] No (Revision with minor changes)Date ~ V I (6) Reviewed By* ________________________________(OR) (KI) D)ate _______Cross-D~isciplinary Review By* '________________________(OR) (KI) NA ______ ate_______
Reactivity M gmt. Review By*~ ((OR) NA_______Date_______
Mgmt. Involvement Review By* (Ops. Mgr.) NA_______
ate ______(7) Additional Reviews (8) Approved By* ,t Date .-7-./ O///PERFORMANCE (Compare witih control copy every 14 calendar days while work is being performed.)
(9) Compared with Control Copy* Date_________
Cornpared with Control Copy* l)are_________
Compared with Control Copy* ____________________________________D
[)te _____(1I0) Date(s) Performed Work Order Number (WO#)COMPLETION (I I) lProcedure Completion Verification:
E] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
E] Yes E] NA\ Required enclosures attached'?
E] Yes [] NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked'?E] Yes E] NA Calibrated Test Equipment, if used, checked out/in antd referenced to this procedure?
E] Yes E] NA Procedure requirements met?Verified By*(12) Procedure Completion Approved*
______(13) Remarks 'Attachr additional poges, if necessary) l)ate ________P tinted Nooe and Simnatoore Form 703-1. Procedure Process Record (PPR)511.14)Duke Energy PROCEDURE PROCESS RECORD (I) ID,'o. RP/0/A15000/00I Re ~oiNo. 035 PREPARATION (2) Station ___(3) Procedure Title Catawba Nuclear Station Classification of Emergency (4) Prepared By*C~\c~r .1'Date -~ Y' ((5) Requires NSD 228 Applicability Determination?
[] Yes (New procedure or revision with niajor changes) -Attach NSD 22S documentation E] No (Revision wVith minor changes)(6) Reviewed By* (OR) (KIb l)ute_______
Cross-Disciplinary Review By" ________________________(Q R)(K[) NA ______ ate_______
Reactivity Mgmt. R~eviewv By* (OR) NA____ D__late_____
Mgmt. Involvement Review By* (Ops. Mgr.) NA________Date_______
(7) A\dditional Reviewvs ,1 .((8) Approved B3y Date PERFORMANCE (Compare wiith control copy every 14 calendar dlays while work is being per~hrmed.)
(9) Compared with Control Copy* _______________________________________________ )ate________
Compared with Control Copy* ___________________________________________
Date _______Compared with Control Copy* _______________________________________
ate_______
(1U) Date(s) Performed Work Order Number (WO#) ________________________________________________
COMPLETION (11) P'rocedure Completion Verification:
E] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA. as appropriate!
E] Yes E] Ni\ Required enclosures attached?E] Yes E] NA graphs, data sheets, etc. attached, dated, identified, anid marked?[] Yes [] NA Calibrated Test Equipment, if used, checked out/in and referenced to this procedure'?
E] Yes [] NA Procedure requirements met?Verified By* ______________
(12) Procedure Completion A~pproved*
(13) Remarks (Attach Ltdd~iioal poges, if necessaor)'rinted Naome and Signaottre IDate_______
[)ate _______
ENEGY.Facility Code : CN Applicable Facilities:
Document Number: RP/0/A/5000/001 Document Revision Number : 035 Document EC Number : Change Reason : Document Title : Classification of Emergency Arlow, Tom A EP Manager review 2/16/2 016 Notes :
10 CFR 50.54(q) Screening Evaluation Form Screening and Evaiuation Number Applicable Sites BNP []EREG #:01 997084 CNS l[]PPR AR# 01935311 CR3 []HNP []MNS []5AD #:01995501 ONS []RNP C]GO C]Document and Revision Classification of Emergency RP/0/A./5000/001 Revision 035 Part 1. Description of Activity Being Reviewed (event or action, or series of actions that may result in a change to the emergency pian or affect the implementation of the emergency plan): Activity description RP/0/A/5000IO01 (Classification of Emergency ) Rev.035 1) Procedure Body Section 2 Immediate Actions- Step 2.4 -Changed to read "I' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix)O__R refer to EAL wallboards".
- 2) Procedure Body Section 2 Immediate Actions- Step 2.5 -IF' a General Emergency is NOT declared in Step 2.40..OR the condition does NOT affect fission product barriers, review the listing of enclosures ORR refer to EAL wallboards to determine if the event is applicable to one the categories shown.3) Procedure Body Section 3 Subsequent Actions- Step 3.1 -Changed to read "To escalate, dc-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures
- 4) Procedure Body Section 3 Subsequent Actions- Step 3,2 -Changed to read -'Refer to Enclosure 4.8 (Definitions/Acronyms)
O__R 4.9 (Emergency Declaration Guidelines), as needed.'Re ferences: PRR0193531 1
Part I1. Activity Previously Reviewed?E Is this activity Fully bounded by an NR, C approved 10 CFR 50.90 submittal or Alert and Notification System Design lBeport?If yes, identify bounding source document number or approval reference and ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification:
Yes El[ No IX 10 CFR 50.54(q)Effectiveness Evaluation is not required.
Enter justification below and complete Attachment 4, Part V.Continue to Attachment 4 ,10CFR 50.54(q)Screening Evaluation Form, Part Ill Bounding document attached (optionall)
Part Ill. Editorial Change ',Yes El[ No X Is this activity an editorial or typographical change only, such as formatting, 10 CFR 50.54(q) Continue to paragraph numbering, spelling, or punctuation that does not change intent? Effectiveness Attachment 4, Evaluation is not Part IV and Justification:
required.
Enter address non ,,justification and editorial complete changes Attachment 4,___________________________________________Part V & VI.Part IV. Emergency Planning Element and Function Screen (Reference Attachment 1, Considerations for Addressing Screening Criteria)
'Does this activity involve any of the following, including program elements from NUREG-0654/FEMA REP-i Section I17 If answer is yes, then check box.1 10 CFR 50.47(b)(1)
Assignment of Responsibility (Organization Control)___
1la Responsibility for emergency response is assigned.
El 1lb The response organization has the staff to respond and to augment staff on a continuing basis El (24-7 staffing) in accordance with ithe emergency plan.___2 10 CFR 50.47(b)(2)
Onsite Emergency Organization
__2a Process ensures that on-shift emergency response responsibilities are staffed and assigned [2b The process for timely augmentation of on-shift staff is established and maintained.
Emergency Riesponse Support and Resources
__3a Arrangements for requesting and using off site assistance have been made. El 3b State and local staff can be accommodated at the EOF in accordance with the emergency plan. El (NA for CR3) __4 10 CFR 50.47(b) (4) Emergency Classification System 4a A standard scheme of emergency classification and action levels is in use. El__(Requires final approval of Screen[ and Evaluation by EP CFAM.)5 10 CFR 50.47(b) (5) Notification Methods and Procedures 5a Procedures for notification of State and local governmental agencies are capable of initiating notification C]of the declared emergency within 15 minutes (30 minutes for CR3) after declaration of an emergency and providing follow-up notificati~on.
5b Administrative and physical means have been established for alerting and providing prompt instructions
[]to the public within the plume exposure pathway. (NA for CR3)Sc The public ANS meets the design requirements of FEMA-REP-1 0, Guide for Evaluation of Alert and C]Notification Systems for Nuclear'Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. (NA for CR3)___Part IV. Emergency Planning Element and Function Screen (cont.)6 10 CFR 50.47(b)(6)
Emergency)
Communications
__6a Systems are established for prompt communication among principal emergency response C]organizations.
6b Systems are established for prompt communication to emergency response personnel.
Public Education and Information 7a Emergency preparedness informnation is made available to the public on a periodic basis within the []plume exposure pathway emergency planning zone (EPZ). (NA for CR3)___7b Coordinated dissemination of p~ublic information during emergencies is established.
[8a Ad qu t C F acilities8 a mr gema nt ya cined to esuppor e q imer ency r s onet 8a 10qut CfR 04)8 mrecacilities andmitiedt upr eqimerentyrsos.[
8b Adequate equipment is maintained to support emergency response.
___9 10 CFR 50.47(b)(9)
Accident A~ssessment 9a Methods, systems, and equipm'ent for assessment of radioactive releases are in use. J C 10 10 CFR 50.47(b)(10)
Protective Response 10Oa A range of public PARs is available for implementation during emergencies. (NA for CR3) C]10Ob Evacuation time estimates for the population located in the plume exposure pathway EPZ are available C]to support the formulation of PARs and have been provided to State and local governmental authorities. (NA for CR3)10Oc A range of protective actions is available for plant emergency workers during emergencies, including C]those for hostile action events.10Od KI is available for implementation as a protective action recommendation in those jurisdictions that []chose to provide KI to th~e public.11 10 CFR 50.47(b)(1
- 1) Radiologic.al Exposure Control 11 a The resources for controlling radiological exposures for emergency workers are established.
C [12 10 CFR 50.47(b)(12)
Medical and Public Health Support 1 2a Arrangements are made for medi~ical services for contaminated, injured individuals.
C [13 10 CFR 50.47(b)(13)
Recovery 'Planning and Post-accident Operations 1 3a Plans for recovery and reentry are developed.
C [14 10 CFR 50.47(b)(14)
Drills and Exercises 14a A drill and exercise program (including radiological, medical, health physics and other program areas) C]is established.
1 4b Drills, exercises, and training ev.olutions that provide performance opportunities to develop, maintain, C]and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses.
14c Identified weaknesses are corrected.
C]
15 [10 CFR 50.47(b)(1
- 5) Emergency Response Training 15a ~Training is provided to emergency responders.
Part IV. Emergency Planning Element and Function Screen (cont.)16 [10 CFR 50.47(b)(16)
Emergency Plan Maintenance___
1 6a Responsibility for emergency plan development and review is established.
jC 1 6b Planners responsible for emergency plan development and maintenance are properly trained. JC PART IV. Conclusion If no Part IV criteria are checked, a 10 CFR 50.54(q) Effectiveness Evaluation is not required, then complete X Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part V. Go to Attachment 4, 10 CFR 50.54(q)Screening Evaluation Form, Part VI for instructions describing the NRC required 30 day submittal.
If any Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV criteria are checked, then complete Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part V and perform a 10 CFR 50.54(q)Effectiveness Evaluation.
Shaded block requires final approval of Screen and Evaluation by EP CFAM.[]The changes included in this revision include enhancements for allowing the use of wallboards.
These changes do not impact any planning standard functions, and therefore do not require 50.54Q;evaluation.
Part V. Signatures:r
/ / ., Preparer Name (Print): Mandy B. Hare Preparer Sign tue Date:2/4/16 S('o-ReiwrNm Pit:TmAlwReviewer Signature:cd Date: Approver (EP Manager Name (Print): Cecil Fletcher Apr SintDate:
, Approver (CFAM, as required)
Name (Print) " Approver Signature:
Dat: Part VI. NRC Emergency Plan and Implementing Procedure Submittal Actions Create two EREG General Assignments.
- One for EP to provide the 10 CFR 50.54(q) summary of the analysis, or the completed 10 CFR 50.54(q).to Licensing.
- One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.___
QA RECORD Duke Energy Company Procedure No.CATAWBA NUCLEAR STATION RPIOIA/5O001001 Classification of Emergency Revisioli No.035 Reference Use PERFORMANCE I This Procedure was printed on 2/16/20 16 10:54 AM from the electronic library as: (ISSUED) -PDF Format Compare with Control Copy every 14 calendar days while work is being performed.
Compared with Control Copy
- Date _______Compared with Control Copy
- Date _______Compared with Control Copy
- Dt El Yes El NA Required attachments included?El Yes El NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked?El Yes El NA Calibrated Test Equipment, ifused, checked out/in and referenced to this procedure?
El Yes El NA Procedure requirements met?Verified By Date* Printed ANcme anzd Si~gnature Procedure Completion Approved Date* Printed Na/oe and Signature Remarks (attach addfitional pages, ifnecessa~y)
IMPORTANT:
Do NOT mark on barcodes.
lPrinted Date: '2/16/16*t ,acmet "T2D I IiII ~IlI I I l III l 11 IIl IIll I IIllIl Procedure No.:
RP/OIAI5000100 i Page 2 of 4 Classification of Emergency 1. Symptoms 1.1. Notification of Unusual Event 1. 1.1I Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs 1.2 Alert 1.2.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of'saf'ety of the plant or a security event that involves probable life threatening risk to site personnel or dlamagze to site equipment because of HOSTILE ACTION.1 .2.2 Any releases are expected to be limited to small fractions of" the EPA Protective Action Guideline exposure levels.1.3 Site Area Emergency 1.3.1 Events are in process or have occurred which involve actual or likely major failures of" plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I1) toward site personnel or equipment that could lead to the likely failure of" or: (2) that prevent effective access to equipment needed for protection of the public.1 .3.2 Any releases are not expected to result in exposure levels which exceed [PA Protective Action Guideline exposure levels beyond the site boundary.1.4 General Enmergency 1.4. 1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of" physical control of the facility.1 .4.2 Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site ajrea 2. Immediate Actions 2. 1 IF performing this procedure due to security-related event(s) considered to be a CREDIBLE THREAT or HOSTILE ACTION, perform the following.
RP/O/AI5000/00 Page 3 of 4 I..F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/026, Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence of" the event.2.2 Assessment, classification and declaration of any applicable emergency condition should be completed within 15 minutes after the availability of indications or information to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 [F' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1l (Fission Product Barrier M'atrix) OR. refer to [AL wvallboards.
2.5 IF a General Emergency is NOT declared in Ste p 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to [AL wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated.
2.7 Document the declaration time.___________
2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERG Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportunity that will not interf'ere with the performance of the crew or the fhow of the Emergency Procedure.
- 2. 10 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel.
RPIOIAI/001001 Page 4 o f 4 2.11 Implemnent the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure.
Notification of Unusual Event RP/O/A/5000/O02 Alert RP/0/A/5000/003 Site Area Emergency RP/O/A/5000/004 General Emergency RP/0/A/5000/005
- 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures 4.1 through 4.7 OR. EAL wallboards.
3.2 Refer to Enclosure 4.8 (Definitions/Acronyms)
OR 4.9 (Emergency Declaration Guidelines), as needed.3.3 Refer to Section D of the Catawba Emergency Plan for basis information about thle Emergency Classification System as needed.3.4 Refer to RP/0/A/5000/020, "TSC Activation Procedure' concerning the use of 10CFR50.54(x).
If the TSC is activated, contact the TSC Emergency Coordinator
([C)for concurrence when using I10CFR50.54(x).
- 4. Enclosures
- 4. 1 Fission Product Barrier M'atrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radiological Effluent 4.4l Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.1I0 Radiation Monitor Reading for Enclosure 4.3 EALs S Enclosure 4.1 Fission Product Barrier Matrix RPIOIAI500010011 Page 1 of 5 ission Product Barrier status (,Intact, Potential Loss, or Loss). Add points for all barriers.
Classify J)W.Ie events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is hours). In this IMMINENT LOSS situation, use judgment and classify as if the thresholds are exceeded.ission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions
- or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.ion (C SF) indications are not meant to include transient alarm conditions which may appear during the start-up of ment. A CSF condition is satisfied when the alarmed state is valid and sustained.
The STA should be consulted to alidated prior to the CSF being used as a basis to classify an emergency.
of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-___{ IC jAlert IC f Site Area Emergency
{ IC General Emergency 4. l.A.l Loss OR Potential Loss of Nuclear Coolant System 4.1.S.1 Loss OR Potential Loss of Both Nuclear Coolant System AN I Fuel Clad 4. I.G.I Loss of All Three Barriers 4.l.A.2 4.L.A.3 Loss OR_ Potential Loss of Fuel Clad Loss AND l'otential Loss Combinations of B~oth Nuclear Coolant System ANt)Fuel Clad 4.l.G.2 Loss of Any Two B~arriers AN I Potential Loss of the Third Cot a' t ll mlncolt A N )l~oss of Containmnent A N)ILoss OR Potenthil Loss 0 Enclosure 4.1 Fission Product Barrier Matrix RP/O/A/5000/001I Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based on a "potential loss" or" a "loss." "Not Applicable" is inclu~ded in the table as a place holder only, and has no point v'alue assigned.Barrier IPoints (1-5) Potential Loss (X) Loss (X) Total IPoints Classification Containment 1 3 1 -3 Unusual Event-NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Elmergency Total Points 1 -13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of 5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description.
- 3. For each barrier, write the highest single point value applicable for the barrier in the "'Points" column and mark the appropriate
"'loss"~COltllnnl.
- 4. Add the points in the lPoints'" column and record the sum as "'Total Points".5. Determine the classilqcation level based on the number of "Total Points".6. In the table on" page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. 1 for Loss of Nuclear Coolant System) that best fits the loss of harrier descriptions.
- 7. Usingt the number (e.g. 4.1 .A. I). select the preprinted notification form OR a blank notification form and complete the required nflornmt ion Ibr Emergency Coordinator approval and transmittal.
0 Enclosure 4.1 RPIOIA15000100 1 Page 3 of 5 Fission Product Barrier Matrix 4.1.C CONTAINMIENT BARRI,1ER 4.1.N NCS BARRIER 4.I.F FUEL CLAD BARRIER POTENTIAL LOSS -/(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points).....h .. .. ... .. ..I -I -* I 1. Critical Safety Function Status* Containment-RED
- Not applicable
- Core cooling-RED Path is indicated for > 15 minutes 2. Containnment Conditions
- i. Critical Safety Funlctiun Status* NCS Integrity-Red
.N 1. Critical Safety Function Status ,lot applicable
- Core Cooling-Orange* Core Cooling-Red
- Containment Pressure > 15 PSIG* H2 concentration
>9%* Containmcni pressu~re greater than 3 psig with less than oree full train of NS and a VX-CARF operating after actuation.
- Rapid unexplained decre~ase in containment pressure following initial increase Containment pressure or sump level response not consistent with LOCA conditions, NOTE: Refer to Emergency Plan, Sect. D, 4.1 .C.2, last paragraph for inability to maintalin normaal tannuluis pressure.* Heat Sink-Red 2. NCS Leak Rate* Unisolable leak exceeding the capacity of one charging pump in thle normal charging mode with letdown isolated.* Heat Sink-Red 2. Primary Coolant Activity Level* GREATER TIHAN available makeup capacity as indicated by a loss of NCS subcooling.
- Not applicable
- Coolant Activity GREATER THAN 300 ltCi/cc Dose Equivalent Iodine (DEl) 1-131 (-'ON'I'INIIEI)
CONTINIIFI)
CONT'INUIED NTNJ)CONTINIJEI)
Enclosure 4.1 RIp/O/A/5000/001 Fission Product Barrier Matrix Page 4 of 5 4.1.C CONTAINMENTI BARRIER POTENTIAL LOSS -(I Point)LOSS -(3 Points)4. I.N NCS BARRIER POTENTIAL LOSS -(4 Points)LOSS -(5 Points)4.1I.F FUEL CLAD BARRIER POTENTIAL LOSS -(4 Points)LOSS -(5 Points)..... ..T .. .. .... .." -F -1.. ... ....... ......m- "II.. ........3. ContainmentIsolation Valves Status After 3. SC. Tube Rupture 3. C~ontaiunment Radiation M'onitoring Con~tainnment Isolation Actuation Not applicable Containment isolation is incomplete and a direct release path from containment exists to the environment Primary-to-Secondary leak rate exceeds the capacity of one charging pump in the normal charging mode*with letdown isolated.* Indication that a SG is Ruptured and has a Non-lsolable secondary line fault* Indication that a SG is ruptured and a prolonged release of contaminated secondary coolant is occurring from the affected SC to the environment Not applicable
- Containment radiation monitor 53 A or 53 B Reading at time since Shutdown.0-0.5 hrs > 99 R/hr 0.5-2 hrs > 43 R/hr 2-4 hrs > 31 R/hr 4-8 hrs > 22 R/hr>8 hrs > 13 R/hr 4. Emnergenmcy Coordiinator/EOF IDirector 4. SC Secondary Side Release WNithi Primary-to-
- 4. Cointainiaent Radiaition NMoiitoringf Secondary Leakagze* Not applicable
- Release of secondary side to the environment w~ith primary to sccondatr, leakage GREATER THAN Tech Spec allowvable
- Not applicable
- Not applicable Jiudgenment
- Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coordinator/EOF Director indicates LOSS or POTENTIAL LOSS of the fuel clad barrier.END (N)O N'I N I) OlNLiD CONTIN UI-D Enclosure 4.1 RP/O/A/5000/O01I Fission P~roduct Barrier Matrix Page 5 of 5 4.1.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4.1I.F FUEL CLAD BARRIER POTENTIAL LOSS -(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)..................................I I I I ... .l F .. ..5. Significant Radioactive Invenutory In Conitainmnezut
- Containment Rad.Monitor EMF53A or 53B Reading at time since°shutdown:
U -0.5 hr > 390 R/lhr (.5 -2 hr >170 RIhr 2-4 hr > 125 R/hr 4-8 hr > 90R/hr>8 hr > 531Uhr* Not applicable
- 5.
Coordiiuator/EOF Director.Judgenement Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coordinator/IEOF Director indicates LOSS or POTENTIAL LOSS of the NCS barrier.EN...pD 6. Emieri, ency Coordinator
/EOF Director J udgmnent Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coord inator/EOF Director indicates LOSS or PO1'ENTIAL LOSS of the containmeni batTier.EN I Enclosure 4.2 RP/O/A/5000/001I Page 1 of 2 System Malfunctions UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.2.U1.1 Inability to Reach Required 4.2.A.1 Unplanned Loss of Most or All 4.2.S.1 Shutdown Within Technical Safety System Annunciation or Specilication Limits. Indication in Conitrol Room With Either (I) a Significant OP~ERATING MODE: 1, 2, 3, 4 Transient in Progress, or (2)Compensatory Non-Alarming OPER 4.2.U.1-1 Plant is not brought to required Indicators Unavailable.
operating mode within Technical 4.2.S. 1 Specifications LCO Action Statement OPERATING MODE: 1, 2, 3, 4 Time.Inability to Monitor a Significant Transient in Progress.END 4.2.U.2 Unplanned Loss of M'ost or All Safety System Annunciation or Indication in the Control Room for Greater Than 15 Minutes.OPERATING MODE: 1 ,2, 3, 4 4.2.U.2-1 The following conditions exist: Unplanned loss of most (>50%)annunciators associated with safety systems for greater than 15 minutes.AND Ina the opinion of the Operation~s Shift Manager/Emergency CoordinatoriEOF Director, the loss of the annunciators or indicators requires additionafl personnel (beyond normal shift compliment) to saflyv operate thle unit.4.2.A.1I-I The following conditions exist: Unplanned loss of most (>50%)annunciators associated with safety systems for greater than 1 5 minutes.AND In thle opinion of the Operations Shift Manager/Emergency Coordinator/EOF Director, the loss of the annunciators or indicators requires additional personnel (beyond normal shift compliment) to safely operate thle unit.AND1 EITIIER of the following:
- A SIGNIFICANT PLANT TRANSIENT is in progress* Loss of the OAC.ENI)ATING MODE: 1,2,3,4-1 The following conditions exist: Loss of most (>50%)Annunciators associated with safety systems.AND A SIGNIFICANT PLANT TRANSIENT is in progress.AND Loss of the OAC.AND Inability to provide manual monitoring of any of the following Critical Safety Functions:
- suberiticality
- core cooling* heat sink* eontaln~ntelt.
('ONTINIIEI)
ENDI Enclosure 4.2 RP/O/A/5000/O01I System Malfunctions Page 2 of 2 UNUSUJAL EVENT ALERT SITE AREA EMERGENCY EMERGENCY 4.2.U..3 Fuel Clad Degradation.
OPERATING MODE: I, 2, 3, 4I, 5 4.2.U.3-1 Dose Equivalent 1-131 greater than thle Technical Specifications allowable limit.4.2.U.4 Reactor Coolant System (NCS)Leakage.OPERATING MODE: 1,2,3,4 4.2.U.4-l Unidentified leakage > 10 gpm.4.2.UJ.4-2 Pressure boundary leakage > 10 gprn.4.2.U.4-3 Identified leakage > 25 gpm 4.2.U.5 Unplannied Loss of All Onisite or Offsite Coinnunicationls.
OIPERATING MODE: ALL 4.2.11.5-1 Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perfonn routine operations.
- 4.2.UJ.5-2 Loss of all offsite communications capability (Duke Emergenacy M-anagemtent Network [DE MN El].NR(" ETIS linies, ol'lhite radio system, commcreial phonec system) a llicting the abilitly to commun~icate wvith of'tsite antltori ties.END)
Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 of"5 G;ENERAl.
EMERG ENC\Y[;NUSI!AI, I-\.'ENT ALERT SITE Ai REA E:M ERG EN(CV 4.3.L .1 Any Unplanned Release (of Gaseous or 4.3.A.1 Liquid Radioactivity to the Environment thtat Exceeds Two Tiumes the SL(: Limits for 60 Minutes or Longer.Any I nlplaunnd Release of Gaseous or Liquid Radioactivity to the Eiuvironmcnt thatt Exceeds 200 Times the SLC limits for 15 Minutes or Longer.4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100 mrem TED)E or 500 mrem CDE Adult TIhyroid for the Actual or Projected Duration of the Release.OPERV [TINC MODE: AII OPElRATING MODE: ALL 4.3.Ui.1-1 A valid Tlrip 2 alarm on radiation monitor E~vlF-49L or ENvlF'-57 or > 60 minuteS or will likely continue for >_ 60 minultes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure
[-IP/0/B/1009/0 14.4I.3.tJ..i-2 A valid indication on radiation monitor EMF- 36L of>_ 3.(0E+t04 cpm for->_ 60)minutes or will likely continue for >- 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AID-HP-ALIL-0202.4..3.A.1-1 A\ valid indication on radiation monitor EMF- 49L or EMvF-57 of> 1.2E+05 cpm lbr> 15 minutes or will likely continue for --15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H-P/0/B3/1009/014.(Continued)
OIPERATING NIOIOE: ALiL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of> 2.7E+06 cpm sustained for> IS1 minmutes.4.3.S.1-2 Dose assessment teamn calculations in~dicate dose consequences greater than 100 mrem "IEDE or 500 mrem CDE Adult Thlyroid at the site houndary.4.3.G.1 Boundary l)ose Resultitng f'rom an Actual or hmnmitent Release of Radioactivity that Exceeds 1000 mrenm TEDE or 5000)onrei CDE Adult Thyroid for the Atuald or Projected Duration of the Release.
MODE: ALL 4.3.G.1-1 A valid indication on radiation monitor EMF-36t-of> _8.3E+03 cpm sustained lbr > 15 minutes.4.3.G.1-2 Dose assessment team calculations indicate dose conseqtuences greater than 1000 ,mrem TEDE or 5000 mrcm CDL Adtmh Thyroid at the site boundary.lConmtin ned)(( "ontini, ed) 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent R.P/O/A/5000/OO01 Page 2 of 5 GENERA I EM'ERGENCY UNU.SUAL, EVENT ALERT SITE AREA EM1ERGENCY 4.3.12...-3 Gaseous effluent being released exceeds two times SLC 16.1 1-6 for >60 minutes as determined by RP~procedure.
4,3.U.1-4 Liquid effluent being released exceeds two times SLC 16.11 I- for>60 minutes as determined by RP procedure.
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continued) 4.3.A.1-2 A valid indication on radiation nmonitor EMF- 36L of_>5.4E+05 cpm for> 15 minutes or will likely continue for >-15 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202.
4.3.A.1-3 Gaseous effluent being released exceeds 200 times the level of SLC 16.11-6 for> 15 minutes as determined by RP procedure.
4.3.A.1-4 Liquid efiluent being released exceeds 200 times the level of SLC 16.11-1 for> 15 minutes as determined by RP procedure.
Note: If the monitor reading is sustained lbr the time period indicated in the EAL AND the required assessments (procedure calcula.tions) cannot be completed within this time period, declaration mast be made baise on the valid rad iat ion monitor reading.( Conltinu Led)4.3.S.1-3 Analysis of field survey results or theld survey samples indicates dose consequences greater than 100 mrem TEDE or 500 mrem CDE Adult Thyroid at the site bounmdary.
Note 1I: These EMF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EM~F readings should not be used if dose assessment team calculations are available.
Note 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid mtonitor reading should be used for emergency class iIi cation.ENDI 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 1000 ,mrem TEDE or 5000 mrem CDE Adult Thyroid at the site ho unda ry.Note I: These EMF readings are calculated based on average anntual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF iread ings should not be uised if dose assessment team calculations are available.
Note 2: If dose assessment team calculations cannot be completed in I 5 minutes.then valid monitor reading should be used for emergency classification.
END)
Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/O/A/5000/001I Page 3 of"5 GENERAL EM'ERGENCY UNLUSI.1AL EVENT ALERT SITE AREA EMERGENCY 41.3. I.2 Uneixpected Increase in Plant Radiation or Airborne Concentration.
OPERATING MODE: ALL 4.3.U.2-1 Indication of uncontrolled water level decrease of greater than _6 inches inl the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.U.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pool and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.U.2-3 Unplanned valid area EM~F reading increases by a factorof 1,000 over normal levels as shown in Enclosure 4.10.END 4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel.Does not apply to spent fuel in diy cask storage. Refer to EPLAN Section D basis document OPERATING MODE: ALL 4.3.A.2-1 An unplanned valid trip I1 alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge IEMF-15 2EMF-4 Spent Fuel Pool Ventilation I EMIF-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Nlode Only)IEMF-17 2EM lF-2 Containment Noble Gas Monitor (Applies to Mode 6 and No Mode (Jnly)1 EMF-39 2EiNlF-3')
l( " liii ijed I 0 VP Enclosure 4.3 RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 4 of"5 UiNtSUAkL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity. spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any iIradiated fuel will become uncovered.
4.3.A.2-3 NC system wide range level <95% after initiation of NC system make-up.AND Any irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.4.3,A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.AN___D_Any irradiated fuel assembly not capable of being fully lowered into the spent fuel pool racks or transfer canal fuel transfer system basket.(C'ontinued) 0 0 Enclosure
- 4. RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 5 of 5 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases in Radiation Levels WVithin the Facility That Impedes Operation of Systems Required to Mlainitaini Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.3.A.3-1 Valid reading on IEMF-12 greater than 15 mremlhr in the Control Room.4.3.A.3-2 Valid indication of radiation levels greater than 1 5 mrem/hr in the Central Alarm Station (CAS) or Secondary Alarm Station (SAS).4.3.A.3-3 Valid radiation monitor reading exceeds the levels shown in Enclosure 4.10.ENI) 0 Enclosure 4.4 RP/0/A/5000/001I Page 1 of 3 Loss of Shutdown Functions UJNU~SUAL EVENT'ALERT SITE AREA EMERGENCY GENERAL EMIERGENCY END 4.4.A. I Failure of Reactor Protection System Instrumentation to Complete or initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Been Exceeded and Manual Trip Was Successful.
OPERATING MODE: 1, 2, 3 4.4.S.1 Failure of Reactor Protection System iostrnmnentation to Complete or Initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Beeni Exceeded and Manual Trip Was NOT Successful.
OPERATING MODE: I 4.4.A.1-1 The following conditions exist: 4.4.S.1-1 The following conditions exist: 4.4.G.1 Failure of the Reactor Protection System to Coniplcte an Automatic Trip and Mianual Trip Was NOT Successful and There is Indication of an Extreme Challenge to the Ability to Cool the Core.OPERATING MODE: 1 4.4.G.1-1 The following conditions exist: Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND M~anual reactor trip from the control rooml was uot successfufl in reducing reactor power to less than 5% and decreasing.
ANDI Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND Manual reactor trip from the control room is successful and reactor power is less than 5%and decreasing.(Cnntinuedl)
Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND M'anual reactor trip from the control room was not successful in reducing reactor power to less than 5% and decreasing.
((omntiniuedl)
ErIT'HER of' the following conditions exist:* Core ('ooling (SF-RED* 1-eat Sink (SF-RED.EN I Enclosure 4.4 Loss of Shutdown Functions RP/0/A/5000/001I Page 2 I'3 GENERAL EM~ERG ENCY UNUSUAL EVENT A LERT 4.4.A.2, Inability to M~aintain Plant in Cold Shutdown.-
OPERATING MODE: 5, 6 4.4.A.2-1 Total loss of ND and/or RN and/or KC.AND One of the following:
- Inability to maintain reactor coolant temperature below 200 0 F* Uncontrolled reactor coolant temperature rise to> 180 0 F.END SITE AREA EMERGENCY 4.4.S.2 Complete Loss of Functioni Needed to Achieve or Maintain ltot Shutdown.OPERATING MODE: 1, 2,3, 4 4.4.S.2-1 Suberiticality CSF-RED.4.4.S.2-2 1-eat Sink CSF-RED.4.4.S.3 Loss of Water Level in the Reactor Vessel That Has or Will._[ Uncover Fuel in the Reactor Vessel.OPERATING MODE: 5,6 4.4.S.3-1 Failure of heat sink causes loss of cold shutdown conditions.
AND Lower range Reactor Vessel Level Indication System (RVLIS) decreasing after initiation of NC system makeup.4.4.S.3-2 Failure of heat sink causes loss o f cold shutdown conditions.
A~NI Reactor Coolant (NC) system mid or wide range level less than 11% and decreasing after initiation ot NC system makeup.(C(iollltin lied)
Enclosure 4.4 RP IO IAI5S 001001 Page 3 of 3 Loss of Shutdown Functions IUNIUSIAL EVENT'ALERT SITE AREA E M ERGENCY GENERAL EMERGENCY 4.4.S.3-3 Failure of heat sink causes loss of cold shutdown conditions.
AND Either train ultrasonic level indication less than 7.25% and decreasing afier initiation of NC system makeup.END 0 Enclosure 4.5 Loss of Power[UNUSUAIL EVENT ALERT'SITE AREA EMERGENCY 4.5.U.1 Loss of All Offsite Power to Essential Busses for Greater Than 15 Minutes.OPERATING MODE: 1, 2, 3, 4I 4.5.U.I-1 The tbllowing conditions exist: Loss of offsite power to essential buises ETA and ETB for" greater than 15 minutes.AN_.D_Both emergency diesel generators are supplying power to their respective essential busses.(Continued) 4.5.A.1 Loss of All Offsite Power and Loss of All Onsite AC Power to Essential Busses During Cold Shutdown Or Refueling Mode.OPERATING MIODE: 5, 6, No Mode 4.5.A.i-I Loss of all offsite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB.AND Failure to restore power to at least one essential bus within 15 minutes.4.5.S.1! Loss of All Of1site Power and Loss of All Onsite AC P~ower to Essential Busses.OPERATING MIODE: 1, 2,3, 4 4.5.S.1-1 Loss of all oti~ite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB.AND Failure to restore power to at least one essential bus within 15 minutes.(Continiuedj RP/O/A/5000/OO01 Page 1 o f2 GENERAL EMERGENCY 4.5.G.1 Prolonged Loss of All (Offsite and Onsite) AC Power.OPERATING MODE: 1, 2, 3, 4 4.5.G.1-1 Prolonged loss of all offsite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB for greater than 15 minutes.AN....D Standby Shutdown Facility (SSF) fails to supply NC pump seal injection OR CA supply to Steam Generators.
AND (Continued)(Conitinued) 0 0 Enclosure 4.5 Loss of Power RPIO/AtS001001 Page>2 or)2 GENERAL. EMERGENCY 1JNIJSI.JAIL EVENT" ALERTI OPERATING MODE: 5, 6, No Mode 4.5.LL.I-2 The following conditions exist: Loss of offsite power to essential buses ETA and ETB for greater than] 15 minutes.AND One emergency diesel generator is suipplying power to its respective essential bus.4.5.U.2 Unplaiiued Loss of Required DC Power During Cold Shutdown or Refueling Miode for Greater thani 15 Minutes.OPERATING MODE: 5, 6 4.5.11.2-1 The following conditions exist: 4.5.A.2 AC power to essential busses ireduced to a single power source for greater than 15 minutes such that an additional single failure could result in station blackout.OPERATING MODE: 1, 2, 3, 4 4.5.A.2-1 The following condition exists: AC power capability has been degraded to one essential bus powered from a single power source for > 15 riin. due to the loss of all but one of: SITE AREA EMERGENCY 4.5.S.2 Loss of All Vital DC Power.OPERATING MODE: 1, 2,3, 4 4.5.S.2-1 The following conditions exist: Unplanned loss ot both unit related busses: EBA and EBD both <112 VDC, and EBB and EBC both <109 VDC.AN__.DD Failure to restore power to at least one required DC bus within 1 5 minutes from the time of loss.At least one of the Iollowing conditions exist:* Restoration of at least one essential bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is NOT likely* Indication of continuing degradation of core cooling based on Fzission Prodtuct Barrier monitoring.
ENI)END SATA ATC DiG A SATB ATD DIG B I ilplaliied loss of1 both unit irelated busses: EBA and 1.BD1 both <112 \'DC. and EBB and EBC both <109 V DC.:ANID Fa i ure_ to restore po~~'er Ito alleast one treulireul D(" bus wvithiin 15 Ininntes fromn lhe lime ofl loss.I.N I)[NI)
Enclosure 4.6 IP/O/A/5000/O01I Fire/Explosion and Security Events Page 1 of 3 UNUISUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.6.U.1 Fire Within Protected Area Boundary NOT Extinguished Within 15 Min utes o f Detection OR._Explosion Within the Protected Area Boundary.OPERATING MODE: ALL 4.6.U.I-1 Fire inl any of the following areas NOT extinguished within 15 minutes of control room notification or verification of a control room fire alarm.* Reactor Building* Auxiliary Building* Diesel Generator Rooms* Control Room* RN Pumphouse* SSF* CAS* SAS* Doghouses* FWST* Turbine Building* Service Building* Monitor'Tank Building* ISFSI* [.Jit I.;1 -Iranslbrnmer Yard Areas (Contiinued) 4.6.A.1 fire or Explosion Affecting the Operability of Plant Safety Systems Required to Establish or Manintain Safe Sbhutdown.
OPERATING MIODE: 1, 2, 3, 4, 5, 6 4.6.A. 1-1 The following conditions exist: (Non-security events)Fire or explosion in any of the following areas:* Reactor Building* Auxiliary Building* Diesel Generator Rooms* Control Room* RN Pumphouse* SSF* CAS* SAS* FWST* Doghou~ses (Applies in Mode 1, 2, 3, 4 only).4.6.S.1 HOSTILE ACTION within the PROTECTED AREA OPERATING MODE: ALL 4.6.S.1-I A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the CNS Security Shift Supervision EN.._D 4.6.G.1 HOSTILE ACTION Resulting in Loss of Physical Control of the Facility.OPERATIN(G M~ODE: ALL 4.6.G.l-1 A H-OSTILE ACTION has occurred such that plant personnel are unable to operate equipment required to maintain safety functions.
4.6.G.I-2 A IHOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT fuel damage is likely Ibr a FRESHLY OFF-LOADED REACTOR CORE in pool.ENI)AND One of the following:
- Aff~ected safety system parameter indications show-degraded performance ttConlinued)
Enclosure 4.6 RP/0/A/5000/00 I Fire/Explosion and Security' Events Page 2 of 3 UNUSUAL EVENT ALERT SIT'E AREA EMERGENCY GENERAL EMERGENCY 4.6.U.1-2 Report by plant personnel of an unanticipated explosion within protected area boundary resulting in visible damage to permanent structure or equipment or a loaded cask in the ISFSI.4.6.U_.2 Confirnmed SECUJRITY CONDITION or T'hreat Which Inidicates a Potential Degradation in the Level of Safety of the Plant.OPERATING MODE: All 4.6.U..2-1 A SECURITY CONDITION that does NOT involve a HOSTILE ACTION as reported by the CNS Security Shift Supervision.
4.6.LJ.2-2 A credible site-specilie security threat notiflication.
4.6.11.2-3 A validated notilication from NRC providing ijiformatioji ol'an airerati threat.ENI)*Plant personnel report visible damtage to permanent structures or equipment within the specified area required to establish or maintain safe shutdown within the specifications.
Note: Only one train of a system neceds to be affected or damaged in order to satisfy this condition.
4.6.A.2 Fire or Explosion Affecting the Operability of Plant Sa.fety Systems Required to Establish or Maintain Safe Shutdown.OPERATING MODE: No M~ode 4.6.A.2-I The following conditions exist: (Non-security events)Fire or exp~losion in any of the following areas:* Spent Fuel Pool* Auxiliary Buildingz.
- RN Pump house AND One of the following:
- Spent Fuel Pool level alnd/or" temlperalture showv degraded performlance t(-'ontinulicd)
Enclosure 4.6 RP/0/A/5 000/001 Fire/Explosion andi Security Events Page 3 of' 3 I)NLISLAL EVENT AILERT SITE AREA EMERGENC'Y GENERAL ENIER(GENCY' Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling.4.6.A.3 HOSTILE ACTION Within tihe OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift Supervision 4.6.A.3-2 A validated notification from NRC of airliner attack threat within 30 minutes of the site.E NI)
Enclosure 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant SafetyEVENT'ALERT SITE AREA EMERGENCY 4.7.1U.1 Natural and Destructive Phenomena Affecting tihe Protected Area.OPERATING MODE: ALL 4.7.U1.1-1 Tremor felt and valid alarm on tihe Syscom Seismic Monitoring Systemn (OAC C 1 D22 52).4.7.U1.1-2 Report by plant personnel of toi-nado striking within protected area botmdary/ISFSI.
4.7.U1.1-3 Vehicle crash into plant structures or systems within protected area boundary!/ISFSlI.
4.7.U1.1-4 Report of turbine Fa~ilure resulting in casing penetration or damage to turbine or generator seals.4.7.1_1.1-5 Independent Spent Fuel Cask tipped over or dr'opped greater than 24 inches.4.7.11..1-6 Uncontrolled Ilooding in the ISFSI area.4.7.11. .1-7 Tornado generatecd missiles(s) impacting the ISFSi.{(C oiitn liicud)4.7.A.!I Natural and Destructive Phenomena Affecting the Plant Vital Area.OPERATING MODE: ALL 4.7.A.1-1 Valid "OBE Exceeded" Alarm on I AD-4.B/8 4.7.AAl-2
'Tornado or high winds: Tornado striking plant structures within the vital a rea: e 0i 0 a 0 a Reactor Building Auxiliary Building FWST Diesel Generator Rooms Control Room RN Pumphouse SSF Doghouses CAS SAS 4.7.S.1 Control Room Evacuation Ha4s Been Initiated and Plant Conitrol Cannot Be Established.
OPERATING MODE: ALL 4.7.S.1-1 The following conditions exist: Control Room evacuation has been initiated per AP/II(2)/A15500/017 AN.__D Control of the plant cannot be established fi'om the ASP or the SSF within 15 minutes.4.7.S.2 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of Site Area Emergency.
OPERATING MIODE: ALL 4.7.S.2-l Other conditions exist which in the Judgement of the Emergency Coordinator!EGF Director indicate actual or likely major f~itilures ol plant functions needed lor protection of the~ public.END RP/O/A/5 000/001 Page 1 of 4 GENERAL EM'ERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency.
OPERATING MODE: ALL 4.7.G.1-I Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (1) actual or imminent substantial core degradation with potential for loss of containmaent OR (2) potential for uncontrolled radionuclide releases.
These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.En __)OR sustained winds >_ 74 mph for> 15 minutes.(Continued) 0 Enclosure 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety RPIO/AI/500I/O01 Page 2 o1"4 GFNERAL EMERGENCY IJNUSUJAL EVENT ALERT SITE AREA 4.7.1_1.2 Release of Toxic or Flanmnable Gases D~eemed Detrimental to Safe Operation or the Plant.OPERALTING MODE: ALL 4.7.U.2-l Report or detection of'toxic or flammable gases that could enter within the site boundary in amounts that can aff'ect safe operation of the plant.4.7.U.2-2 Report by Local. County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgeinent of the Emergency Coordiziator/EOF Director Warrant Declaration of an Unusual Event.OPERATING MODE: AILL 4.7. U.3-1I Other conditions exist which in the j udgcmlcnt o f thte Emcrgency Coordinazor/ELOF D)irector indic'ate a potential degradatlion ofth lt evel of Siitct\' of'thlw plaint.4.7.A. 1-3 Visible structural damage caused by either:* Vehicle crashes OR*Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures:
- Reactor Building* Auxiliary Building* FWST* Diesel Generator Rooms SControl Room* RN Pump 1-ouse* SSF* Doghouses* CAS* SAS (Continued)
[NI)
Enclosure 4.7 RI?/01A/5000/00 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 3 of"4 UNUSUIAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.2 Release of Toxic or Flammable Gases Within a Facility Structure Which Jeopardizes Operation of Systems Required to Maintain Safe Operationis or to Establish or Majatain Cold Shutdown.OPERATING MODE: ALL 4.7.A.2-1 Report or detection of toxic gases within a Facility Structure in concentrations that will be life threatening to plant personnel.
4.7.A.2-2 Report or detection of flammable gases within a Facility Structure in concentrations that will affect the safe operation of the plant.Structures lor the above EALs:* Reactor Building* Auxiliary Building* Diesel Generator Ro~oms* Control IRtooi* RN Ptinmphouse
- SSF* CAS* S:\S (C~onin iiiid)
Enclosure 4.7 IP/0/A/5 000/001 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 4 of 4 UINUISUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.3 Control Room Evacuation llas Beeni Initiated.
OPERATING MODE: ALL 4.7.A.3-I Control Room evacuation has been initiated per AP/1 (2)/A/5500/0 17.4.7.A.4 Other Conditions Existing Which ini the Judgemnent of the Emergency Coordinator/EOF Director Warrantr Declaration of an Alert.OPERATING MODE: ALL 4.7.A.4-10dtler conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate that plant safety systems may be degraded and that increased monitoring of plant functions is warranted.
END Enclosure 4.8 RP/O/A/5000/O00 Definitions/Acronyms Pagze I of 4 ALERT- Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of hostile action. Any releases are expected to be limited to small fractions of the EPA protective action guideline exposure levels.ALL (As relates to Operating Mode Applicability)
-Mlodes 1, 2, 3,4,5,6 and No M~ode (Defueled)
BOMB -Refers to an explosive device suspected of having sufficient force to damage plant systems or" struictuires.
CARF -Containment Air Return Fan.CIVIL DISTURBANCE
-A group often (10) or more people violently protesting station operations or activities at the site. A civil disturbance is considered to be violent wvhen force has been used in an attempt to injure site p~ersonnel or damage plant property.COGNIZANT FACILITY STAFF -Any member of facility staff, who by virtue of training and experience.
is qualified to assess the indications or reports for validity and to compare the same to the EALs in the licensee's emergency classification scheme (Does not include staff" whose positions require they rcport, rather than assess, abnormal conditions to the facility.).
CREDIBLE THREAT -A threat should be considered credible when:* Physical evidence supporting the threat exists.* Information independent (law enforcement) from the actual threat message exists that supports the threat.* A specific group or organization claims responsibility for the threat.EPA PAG -Environmental Protection Agency Protective Action Guidelines for exposure to a release of radioactive material.EMERGENCY RELEASE -Any unplanned, quantifiable radiological release to the environment during~ an emergency event. The release does not have to be related to a declared emergency.
EXPLOSION
-A rapid. violent unconfined combustion, or a catastrophic failure of pressurized equ~ipment (e.g., a steam line or f'eedwater line break) that imparts energy sufficient to potentially damage or creates shrapnel to actually damage permanent structures, systems or components.
An electrical breaker flash that creates shrapnel and results in damage to other components beyond scorching should also be considered.
EXTORTION
-An attempt to cause an action at the site by threat of force.FIRE -Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required if" large quantities of smoke and heat are observed.
An electrical breaker f'lash that creates high temperatures for a short duration and merely localized scorching to that breaker and its coinpartinent shouild not be considered a fire.FRESHLY OFF-LOADED REACTOR CORE -The complete removal and relocation of all fuel assemblies from the reactor core and placed in the spent fuel pool. (Typical of a 'No Mode' operation during a refuel outage that allows safety system maintenance to occur and results in maximum decay heat load in the spent fuel pool system.)
Enclosure 4.8 RPIOIA/5000/O()I Definitions/Acronyms Page 2 o f 4 FUNCTIONAL
-A component is fully capable of meeting its design function.
It would be declared INOPERABLE if unable to meet Technical Specifications.
GENERAL EM'ERGENCY-Events are in process or have occurred which involve actual or imminent substantial core degradation or melting wvith potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility.
Releases can be reasonably expected to exceed EPA protective action guideline exposure levels offsite for more than the immediate site area.HOSTAGE -A person(s) held as leverage against the station to ensure demands will he met by the station.HOSTILE ACTION -An act toward an NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidates the licensee to achieve an end. This includes attack by air.land, or water using guns, explosives, PROJECTILES, vehicles or other devices used to deliver destructive force. Other acts that satisfy, the overall intent may be inacluded.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concer'ted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (e.g.. violent acts between individuals in the OWNER CONTROLLED AREA).HOSTILE FORCE -One or more individuals who are engaged in a determined assault, overtly or by' stealth and deception.
equipped with suitable weapons capable of killing, maiming or causing destruction.
IMMINENT -Mitigation actions have been ineffective, additional actions are not expected to be successful.
and trended information indicates that the event or condition will occur. Where IMMINENT time fr'ames are specified, they shall apply.INOPERABLE
-A component does not meet Technical Specifications.
The component may be f'unctional, capable of meeting its design.INABILITY TO DIRECTLY MONITOR -Operational Aid Computer data points are unavailable or gauges/panel indications are not readily available to the operator.INTRUSION
-A person(s) present in a specified area without authorization.
Discovery of a BOMB in a specified area is indication of INTRUSION into that area by a HOSTILE FORCE.ISFSI -Independent Spent Fuel Storage Installation
-Includes the components approved for loading anod storage of spent fuel assemblies.
LOSS -A component is INOPERABLE and not FUNCTIONAL.
NO MODE -Defueled.OWNER CONTROLLED AREA -Area outside the protected area fence that immiiediatelv surrounds the plant. Access to this area is generally restricted to those entering on official business.PROJECTILE
-An object directed toward a NPP that could cause concern for its continued operability.
reliability or personnel saf-ety.PROLONGED
-A duration beyond normal limits, defined as 'greater than 15 minutes" or as determined b'c the judgment of the Emergency Coordinator.
Enclosure 4.8 RP/O/A/5000O/O0 I Definitions/Acronyms Page 3 o f4 PROTECTED AREA -Typically, the site specific area which normally encompasses all control led areas within the security PROTECTED AREA fence.REACTOR COOLANT SYSTEM (RCS/NCS)
LEAKAGE -RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13.RUPTURED (As relates to Steam Generator)
-Existence of primary to secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.
SABOTAGE -Deliberate damage, misalignment, or misoperation of plant equipment with the intent to render the equipment unavailable.
Equipment found tampered with or damaged due to malicious m ischie f nay not meet the definition of SABOTAGE until this determination is made by security superv ision.SECURITY CONDITION
-Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.SIGNIFICANT PLANT TRANSIENT-An unplanned event involving one or more of the f'ollowing:
J )Automatic turbine runback >25% thermal reactor power, (2) Electrical load rejection
>25% full electrical load; (3) Reactor Trip, (4) Safety Injection, (5) Thermal power oscillations
> 10%.SITE AREA EMERGENCY
-Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I) toward site personnel or equipment that couild lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public.Any releases are not expected tO exceed EPA Protective Action Guidelines to exposure levels beyond the site boundary.SITE BOUNDARY -That area, including the protected area, in which Duke Energy has the authority to control all activities, including exclusion or removal of personnel and property.SLC -Selected Licensee Commitments.
SUSTAINED
-A duration of time long enough to confirm that the CSF is valid (not momentary,).
TERMINATION
-Exiting the emergency condition.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) -The sum of external dose exposure to radioactive plume, to radionuclides deposited on the ground by the plume, and the internal exposure inhaled radionuclides deposited in the body.TOXIC GAS -A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g. chlorine l.UNCONTROLLED
-Event is not the result of planned actions by the plant staff.UNPLANNED
-An event or action is UNPLANNED if it is not the expected result of normal operations.
testing, or maintenance.
Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.
Enclosure 4.8 R Pi0/Ai5000i00O( 1 Definitions/Acronyms Page 4 oft 4 UNUSUAL EVENT- Events are in process or have occurred which indicate a potential degradation1 ofthe level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.VALID -An indication or report or condition is considered to be VALID when it is conclusively verified by: (1 ) an instrument channel check, or (2) indications on related or redundant instrumentation, or (3) by direct observation by plant personnel such that doubt related to the instrument's operability, the condition's existence or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.
VIOLENT -Force has been used in an attempt to injure site personnel or damage plant property.VISIBLE DAMAGE -Damage to equipment or structure that is readily observable without measurements.
testing, or analyses.
Damage is sufficient to cause concern regarding the continued operability or reliability of aff'ected structure, system, or component.
Example damage: deformation due to heat or impact, denting.penetration, rupture, cracking, paint blistering.
VITAL AREA -Areas within the PROTECTED AREA that house equipment important for nuclear safety.Access to a VITAL AREA is allowed only if an individual has been authorized to he in that area pe:r the security plan. Therefore, VITAL AREA is a security term.
Enclosure 4.9 RPlOli/150001001 Emergency Declaration Guidelines Page 1 of 2 THE FOLLOWING GUIDANCE IS TO BE USED BY THE EMERGENCY COORDINATOR IN ASSESS ING EMERGENCY CONDITIONS.
- Assessment, classification and declaration of any applicable emergency condition shouild be completed with 15 minutes after indication or information is available to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded.* The Emergency Coordinator shall review all applicable initiating events to ensure proper classification.
- The BASIS Document (located in Section D of the Catawba Nuclear Site Emergency Plan) is available for review if any questions arise over proper c lassification.
- Emergencies are declared for the site. If an event results in multiple emergency action levels onl a unit or different emergency action levels on each unit, then the emergency' declaration shall be based on the higher classification.
Information relating to the unit with the lesser classification wvill be noted as additional information on the Emergency Notification Form (EN F).* If an event occurs, and a lower or higher plant operating mode is reached before the classification can be made, the classification shall be based on the mode that existed ait thle time the event occurred.*The fission product barrier matrix is applicable only to those events that occur at (Mode 1-4) hot shutdown or higher. An event that is recognized at cold shutdown or lower (Mode 5 or 6) shall not be classified using the fission product barrier matrix. Reference would be made to the other enclosures that provide emergency action levels for specific events (e.g. severe weather, fire.security).
- If a transient event should occur, the following guidance is provided.I. Some emergency action levels specify that a condition exist for a specific duration prior to declaration.
- a. For these EALs, the classification is made when the Emergency Coordinator assessment concludes that the specified duration is exceeded or will be exceeded (i.e. condition cannot be reasonably corrected before the duration elapses)..
whichever is sooner.b. If a plant condition exceeding EAL criteria is corrected before thle specified duration time is exceeded, the event is NOT classified by that EAL. Lower Severity EALs, if any, shall be reviewed for possible applicability' in these cases.
Enclosure 4.9 R P!O/A/5000/O0 I Emergency Declaration Guidelines Page 2 of 2 2. If" a plant condition exceeding EAL criteria is not recognized at the time of" occurrence.
but is identified well after the condition has occurred (e.g. as a result of routine log or record review) and the condition no longer exists, an emergency shall NOT be declared.Reporting under IOCFR5O.72 may be required.
Such a condition could occur, f'or example, ifra f'ollow-up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.3. If an emergency classification is warranted, but the plant condition is corrected prior to declaration and notification, the Emergency Coordinator must consider thle potential that the initiating condition (e.g. Failure of Reactor Protection System or earthquake) may have caused plant damage that warrants augmenting the on-shif't personnel via activation of the Emergency Response Organization.
The following action shall be taken: a. For UNUSUAL EVENTS, the condition shall be declared and notifications made. The event may be terminated in the same notification or in a follow-up notificati on.b. For ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY.
the event shall be declared and the emergency response organization activated.
DETERMINATION OF "EVENT TIME" (TIME THE 15 MINUTE CLOCK STARTS)I.Event time is the time at which indications become available that an EAL has been exceeded.2. Event time is the time the 15 minutes clock starts for classification.
- 3. The event classification time shall be entered on the emergency notification form.MOMVENTARY ENTRY INTO A HIGHER CLASSIFICATION If', while in an emergency classification, the specified EALs of a higher classification are met momentarily, and in the judgment of the Emergency Coordinator are not likely to recur, the entry into the higher classification must be acknowledged.
Acknowledgment is perf'ormled as follows: If" this condition occurs prior to the initial notification to the emergency response organization and off site agencies, the initial message should note that the site is currently in the lower classification, but had momentarily met the criteria f'or thne higher classification.
It should also be noted that plant conditions have improved and stabilized to the point that the criteria f-or the higher classification are not expected to be repeated.
0 Enclosure 4.10 RPIOIAiSO001001I Page 1 of Radiation M'onitor Readings fo~r Enclosure 4.3 Note: These values are not inatended to apply to anticipated temporary increases due to planned events (e.g. incore detector movement, radwaste container movemenat, depleted resin transfers, etc.).Detector Elevation Column Identifier Unusual Event Alert SnR/hr mR/hr 1EMF-lI 522' FF, 57 Auxiliary Building Corridor 500 5000 I1ENMF-3 543' GG, 55 Unit I Charging Pump Area 100 5000 IEMF-4 543' GG. 59 Unit 2 Charging Pump Area 100 5000 I ENIF-7 560' NN, 55 Unit I Auxiliary Building Corridor 1500 5000 1 EMF-8 560' >NN, 59 Unit 2 Auxiliary Building Corridor 500 5000 I EMF-9 577' LL. 55 Unit 1 Aux. Building Filter Hatch 100 5000 I EME- 10 577' LL. 58 Unit 2 Aux. Building Filter H~atch 100 5000 I EMvF-22 594' KK, 53 Containment Purge Filter Area 100 5000 2EMF-9 594' KK, 61 Containment Purge Filter Area 100 5000 Page I of 5 PROCEDURE SRP/0/A/5000/001 RP/0/A/5000/002 RP/0/A/5000/003 RP/0/A/5000/004 RP/0/A/5 000/005 RP/0/A/5000/06 RP/O/A!5000/006 RP/0/A!5000/006
.RP/0/A/5000/006 RP/0/A/5 000/007 RP/0/A!5000/08 RP/0/B/5000/008 RP/0/A/5000/009 RP/0/A15000/010 RP/0/A/5000/1 1 RP/0/B/5000/12 RP/0/B/5000/0 13 RP/0/B/5000/14 RP/0/A/5000/015
.RP/0/B/5000i016 RP/0/B/5000/17 A B C DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I TITLE Classification of Emergency (Rev. 036)Notification of Unusual Event (Rev. 045)Alert (Rev. 050)Site Area Emergency (Rev. 053)General Emergency (Rev. 054)Deleted Notifications to States and Counties from the Control Room (Rev. 033)Notifications to States and Counties from the Technical Support Center (Rev. 037)Deleted Natural Disaster and Earthquake (Rev. 043)Deleted Hazardous Materials Spill Response (Rev. 043)Collision/Explosion (Rev. 012) , Conducting a Site Assembly or Preparing the Site for an Evacuation (Rev. 027)Deleted Deleted NRC Notification Requirements (Rev. 038)Deleted Core Damage Assessment (Rev. 007)Deleted Deleted February 18, 2016 Page 2 of 5 PROCEDURE RP/0/A/5000/01 8 RP/0/B/5000/019 RP/0/A/5000/020 RP/0/A/5000/021 RP/0/B/5000/022 RP/0/B/5000/023 RP/0/A/5000/024 RP/O/B/5000/025 RP/0/A/5000/026 RP/0/B/5000/028 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I TITLE Emergency Worker Dose Extension (Rev. 002)Deleted Technical Support Center (TSC) Activation Procedure (Rev. 038)Deleted Deleted Deleted OSC Activation Procedure (Rev. 034)Recovery and Reentry Procedure (Rev. 003)Site Response to Security Events (Rev. 017)Nuclear Communications Emergency Response Plan (Rev. 006)February 18, 2016 Page 3 of 5 PROCEDURE HP/0/B/1 000/006 HP/0/B/1009/001 HP/0/B/1009/003 HP/0/B/1009/004 HP/0/B/1 009/005 HP/0/B/1009/006 HP/0/B/1009/007 HP/0/B/1009/008 HP/0/B/1 009/009 HP/0/B/1009/014 H-P/0/B/1009/016 HP/0/B/1009/017 FIP/1/B/1009/017 FIP/2/B/1009/017 l-P/0/B/1009/018 JHP/0/B/1009/019 IIP/0/B/1 009/024 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II TITLE Emergency Equipment Functional Check and Inventory (Rev. 060)Deleted Radiation Protection Primary to Secondary Leakage Program (Rev. 012)Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 031)Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 01 8)Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 009)In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 020)Contamination Control of Injured Individuals (Rev. 016)Deleted Radiation Protection Actions Following an Uncontrolled Release of Liquid Radioactive Material (Rev. 009)Deleted Deleted Deleted Deleted Deleted Emergency Radio System Operation, Maintenance and Communication (Rev. 010)Implementing Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 002)February 18, 2016 Page 4 of5 PROCEDURE HP/0/B/1009/025 HP/0/B/1009/026 SH/0/B/2005/00 1 SI-/0/B/2005/002 SH/0/B/2005/003 OP/0/A/6200/021 SR/0/B/2000/001 S R/0/A/2000/00 1 SR/0/B/2000/002 SR/0/A/2000/003 SR/0/B/2000/003 SR/0/A/2000/004 SR/0/B/2000/004 AP/O/A/5500/046 AD-EP-ALL-0202 AD-EP-ALL-0203 AD-EP-ALL-0204 AD-EP-ALL-03 01 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II TITLE Deleted Superseded Superseded Deleted Deleted Deleted Deleted Standard Procedure for Corporate Communications Response to the Emergency Operations Facility (Applies to Catawba/McGuire/Oconee) (Rev. 002)Deleted Activation of the Emergency Operations Facility (Rev. 008)Deleted Notifications to States and Counties from the Emergency Operations Facility for Catawba, McGuire and Oconee (Rev. 006)Deleted Hostile Aircraft Activity (Rev. 008)Emergency Response Offsite Dose Assessment (Rev. 001)Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev 000 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev 000)Activation of the Emergency Response Organization Notification System (ERONS) (Rev. 000)February 18, 2016 Page 5 or" 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE AD-EP-ALL-0406 Duke Energy Management Network (DEMNET) (Rev 001)February 18, 2016 Form 703-1. Procedure Process Record (PPR)(RIO0-14)Duke Energy PROCEDURE PROCESS RECORD (I) ID No. RPI0/AI5000I001 Revision No. 036 PREPARATION (2) Station Catawba Nuclear Station (3) Procedure Title Classification of Emergency Classiicatio ofEerec (4) Prepared By* (j. 4,/i4/la, Date (5) Requires NSD 228 Applicability Determination?
[] Yes (New procedure or revision with major changes) -Attach NSD 228 documentation E] No (Revision with minor changes)(6) Reviewed By* I * -( (Kl)Cross-Disciplinary Review (QR) (KI) NA Reactivity Mgmt. Review By* .(QR) NA Ii Mgmt. Involvement Review By* .fOps. Mgr.) NA .I (7) Additional Reviews Reviewed By*g Reviewed By* 11)ate kate PERFORMANCE (Compare with control copy every 14 calendar days while work is being performed.)
(9) Compared wVith Control Copy* _______________________________________late_______
Compared with Control Copy* lDate______
Compared with Control Copy* ___________________________a__________DIte______
(10) Date(s) Performed Work Order Number (WO#) _____________________________________________
COMPLETION (It ) Procedure Completion Verification:
0] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
0] Yes 0] NA Required enclosures attached?[] Yes 0] NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked?0] Yes 0] NA Calibrated Test Equipment, if used, checked out/in and referenced to this procedure?
0] Yes 0] NA Procedure requirements met?Verified By* _____________
(12) Procedure Completion Approved'*
(13) Remarks (Attach additional pages, if necessary,)
- Printed Namte aitd Signature l)ate _______lDate I
~ENERGY!, Facility Code : CN Applicable Facilities
- Document Number: RP/0/A/5000/001 Document Revision Number : 036 Document EC Number : Change Reason : Document Title : Classification of Emergency Hare, Mandy B.EP manager designee review 2/1 7/20 16 Notes :
10 CFR 50.54(q) Screening Evaluation Form Screening and Evaluation Number
- Applicable Sites BNP El EREG #:2001696 CNS [PPR AR# 2001696 CR3 El HNP El MNS El 5AD #:02001728 ONS El RNP El GO El Document and Revision Classification of Emergency RP/0/A/5000/001 Revision 036 [Part I. Description of Activity Being Reviewed (event or action, or series of actions that may restult in a change to the emergency plan or affect the imnplementation of the emergency plan): Activity
Description:
RP/O/A15000/O F (Classification of Emergency)
Rev.036 1) Enclosure 4.1 -page 1 of 5 -Corrected Fusion PDF error during rendition.
No content wats chatnged.There was an error during the rendition to a PDF that caused a portion of the page to be cut off.
References:
PRR02001.696 Part II. Activity Previously Reviewed?Is this activity Fully bounded by an NRC approved 10 CFR 50.90 submittal or Alert and Notification System Design Report?If yes, identify bounding source document number or approval reference and ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification:
Yes El No El]10 CFR 50.54(q)Effectiveness Evaluation is not required.
Enter justification below and complete Attachment 4, Part V.Continue to Attachment 4 ,10 CFR 50.54(q)Screening Evaluation Form, Part Ill Bounding document attached (optional)
Part Ill. Editorial Change Yes IIX No El Is this activity an editorial or typographical change only, such as formatting, 10 CFR 50.54(q) Continue to paragraph numbering, spelling, or punctuation that does not change intent? Effectiveness Attachment 4, Evaluation is not Part IV and Justification:
required.
Enter address non justification and editorial Corrected Fusion PDF error during rendition.
No content was changed. There was an complete changes error during the rendition to a PDF that caused a portion of the page to be cut off. The Attachment 4, procedure is required to be revised to correct these issues. Part V & VI.Part IV. Emergency Planning Element and Function Screen (Reference Attachment 1, Considerations for Addressing Screening Criteria)Does this activity involve any of the following, including program elements from NUREG-0654/FEMA REP-i Section I1? If answer is yes, then check box.1 10 CFR 50.47(b)(1)
Assignment of Responsibility (Organization Control)la Responsibility for emergency response is assigned.
El 1 b The response organization has the staff to respond and to augment staff on a continuing basis [(24-7 staffing) in accordance with the emergency plan.V 2 10 CFR 50.47(b) (2) Onsite Emergency Organization___
2a Process ensures that on-shift emergency response responsibilities are staffed and assigned El 2b The process for timely augmentation of on-shift staff is established and maintained.
J[]3 10 CFR 50.47(b) (3) Emergency Response Support and Resources
__3a Arrangements for requesting and using off site assistance have been made. El 3b State and local staff can be accommodated at the EOF in accordance with the emergency plan. El__(NA for CR3)4 10 CFR 50.47(b) (4) Emergency Classification System 4a A standard scheme of emergency classification and action levels is in use. El (Requires final approval of Screen and Evaluation by EP CFAM.)5 10 CFR 50.47(b) (5) Notification Methods and Procedures 5a Procedures for notification of State and local governmental agencies are capable of initiating notification El of the declared emergency within 15 minutes (30 minutes for CR3) after declaration of an emergency and providing follow-up notification.
Sb Administrative and physical means have been established for alerting and providing prompt instructions El to the public within the plume exposure pathway. (NA for CR3)___Sc The public ANS meets the design requirements of FEMA-REP-1 0, Guide for Evaluation of Alert and El Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. (NA for CR3)___Part IV. Emergency Planning Element and Function Screen (cont.)6 10 CFR 50.47(b)(6)
Emergency Communications 6a Systems are established for prompt communication among principal emergency response El organizations.
6b Systems are established for prompt communication to emergency response personnel.
El 7 10 CFR 50.47(b)(7)
Public Education and Information 7a Emergency preparedness information is made available to the public on a periodic basis within the []plume exposure pathway emergency planning zone (EPZ). (NA for CR3)7b Coordinated dissemination of public information during emergencies is established.
Emergency Facilities and Equipment___
8a Adequate facilities are maintained to support emergency response.
[8b Adequate equipment is maintained to support emergency response.
____9 10 CFR 50.47(b)(9)
Accident Assessment 9a Methods, systems, and equipment for assessment of radioactive releases are in use. J ]10 10 CFR 50.47(b)(10)
Protective Response 10a A range of public PARs is available for implementation during emergencies. (NA for CR3) []10Ob Evacuation time estimates for the population located in the plume exposure pathway EPZ are available EJ to support the formulation of PARs and have been provided to State and local governmental authorities. (NA for CR3)10Oc A range of protective actions is available for plant emergency workers during emergencies, including EJ those for hostile action events.10Od KI is available for implementation as a protective action recommendation in those jurisdictions that 0]chose to provide KI to the public.11 10 CFR 50.47(b)(1
- 1) Radiological Exposure Control 11 la The resources for controlling radiological exposures for emergency workers are established.
0 [12 10 CFR 50.47(b)(12)
Medical and Public Health Support 12a Arrangements are made for medical services for contaminated, injured individuals.
[]13 10 CFR 50.47(b)(13)
Recovery Planning and Post-accident Operations 1 3a Plans for recovery and reentry are developed:
[]14 10 CFR 50.47(b)(14)
Drills and Exercises 14a A drill and exercise program (including radiological, medical, health physics and other program areas) 0]is established.
14b Drills, exercises, and training evolutions that provide performance opportunities to develop, maintain, []and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses.
14c Identified weaknesses are corrected.
[]15 10 CFR 50.47(b)(15)
Emergency Response Training iaTraining is provided to emergency responders.
0 Part IV. Emergency Planning Element and Function Screen (cont.)16 10 CFR 50.47(b)(16)
Emergency Plan Maintenance 1 6a Responsibility for emergency plan development and review is established.
0]16b Planners responsible for emergency plan development and maintenance are properly trained. 0]
PART IV. Conclusion If no Part IV criteria are checked, a 10 CFR 50.54(q) Effectiveness Evaluation is not required, then complete Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part V. Go to Attachment 4, 10 CFR 50.54(q)Screening Evaluation Form, Part VI for instructions describing the NRC required 30 day submittal.
The changes included in this revision include editorial changes only. This revision corrected Fusion PDF error during rendition.
No content was changed. There was an error during the rendition to a PDF that caused a portion of the page be cut off. No planning standards were impacted because there were no content changes to the procedure.
If any Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV criteria are checked, then complete Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part V and perform a 10 CFR 50.54(q)Effectiveness Evaluation.
Shaded block requires final approval of Screen and Evaluation by EP OFAM.
Part V. Signatures; Preparer Name (Print): Tina Kuhr Preparer Signature:
Date:2/1 6/16 Reviewer Name (Print): Mandy Hare Re jwer Signatur Date:2/17/16 Approver (EP Manager Name (Print): Tom Ariow App.prove&., Approver (CFAuM, as required)
Name (Print) Approver Signature:
z -7.) ae Part VI. NRC Emergency Plan and Implementing Procedure Submittal Actions Create two EREG General Assignments.
- One for EP to provide the 10 CFR 50.54(q) summary of the analysis, or the completed 10 CFR 50.54(q), to Licensing.
- One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.___
QA RECORD UF Duke Energy Company Procedure No.CATAWBA NUCLEAR STATION RP/O/.-1sooo/oo1 Classification of Emergency Revision No.036 Rcference Use PERFORaMANCE This Procedure was printed on 2/17/2016 3:25 PM from the electronic library as: (ISSUED) -PDF Format Compare with Control Copy every 14 calendar days while work is being performed.
Compared with Control Copy
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- Irinted NVane and Signature Date(s) Pertbrmed Work Order/Task Number (WOn)COMPLETION O [ Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA-. as approprkite'?
E] Yes [] NA Required attachments included?[] Yes 0] NA Charts, graphs, data sheets. etc. attached, dated, identified, and marked?[] Yes [] NA Calibrated Test Equipment, if used, checked outhin and referenced to this procedure'?
[] Yes [] NA Procedure requirements met?Verified Dy Date* Printed N~ame and SVignamtre Procedure Completion Approved Date* Printed Name and Signature Remarks (attach additional pages, i/necessary)
IMPORTANT:
Do NOT mark on barcodes.
I'rmted Date. '2/"17.1o" Pirocedure No. 'RF'/OU./5i/S IIIO/l I' RP/0/A/5000/00 I Page 2 o f 4 Classification of Emergency 1. Symptoms 1.1. Notification of Unusual Event I.1 .1 Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs 1.2 Alert 1 .2.1I Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION.1.2.2 Any releases are expected to be limited to small fractions of the EPA Protective Act ion Guideline exposure levels.1.3 Site Area Emergency 1.3.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for protection of the public.1.3.2 Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.1.4 General Emergency I1.4. 1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.1.4.2 Releases can be reasonably expectedto exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
RP/0/A/5000/001 Page 3 of'4 2. Immediate Actions 2.1 IF performing this procedure due to security-related event(s) considered to be a CREDIBLE THREAT or HOSTILE ACTION, perform the Ibllowing.
- F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/t026.
Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence or" the event.2.2 Assessment, classification and declaration of any applicable emergency condition shouild be completed within 15 minutes after the availability of indications or inf'ormation to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 IF the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix) OR refer to EAL wvallboards.
__2.5 IF a General Emergency is NOT declared in Step 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to EA\L wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated.
2.7 Document the declaration time. __________
2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERO Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportuinity that will not intert'ere with the performance of the crew or the flow of the Emergency Procedure.
- 2. 1 0 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel.
RP/O/A/5000/00 I Page 4 o t"4 2.1!1 Implement the applicable Emergency Response Procedure (RP) f~or that classification and continue with subsequent steps of this procedure.
Notification of Unusual Event RP/0/A/5000/002 Alert RP/0/A/5000/003 Site Area Emergency RP/0/A/5000/004 General Emergency RP/0/A/5000/005
- 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the initiating Conditions of Enclosures 4.1I through 4.7 OR EAL wallboards.
___3.2 Refer to Enclosure 4.8 (Definitions/Acronyms)
OR 4.9 (Emergency Declaration Guidelines), as needed.3.3 Ref'er to Section D of the Catawba Emergency Plan for basis inf'ormation about the Emergency Classification System as needed.3.4 Ref'er to RP/0/A/5000/020, "TSC Activation Procedure" 1 concern ingz the use of" l0CFR50.54(x).
If the TSC is activated, contact the TSC Emergency Coordinator (EC)for concurrence when using IOCFR5O.54(x).
- 4. Enclosures
- 4. 1 Fission Product Barrier Matrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radio logical Effluent 4.4 Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.10 Radiation Monitor Reading for Enclosure 4.3 EALs 0 0 Enclosure 4.1 RPIOIA!5000/001I Page 1 of'5 Fission lProduct Barrier Matrix 1.Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all barriers.
Classify according to the table below.Note 1 : An event (or multiple events) could occur which results in the conclusion that exceeding thle Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT LOSS situation, use judgment and classify' as if the thresholds are exceeded.Note 2: When determining Fission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions for the Fuel Clad Barrier loss or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.Note 3: Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the stait-up of engineered safeguards equipment.
A CSF condition is satisfied when the alamred state is valid and sustained.
The STA should be consulted to affirm that a CSF has been validated prior to the CSF being used as a basis to classify an emergency.
Example: If ECA-0.0, Loss of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF should be used as the basis to classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-O.O.IC Unusual Event IC Alert IC Site Area Emergency IC General Emergency LossOR Ptenial ossLoss OR Potential Loss Potential Loss of of 41 1of Both Loss of 4.1nU.aI4.1ent.
Nuclear Coolant System Nuclear Coolant System AND 4. G otimn ___All Three Barriers Fuel Clad Loss AND Loss OR P~otential Loss Potential Loss CombinationsLosf
- 4. U2 Loss ofl .A2o .S2o oh41.. Any Two Barriers AN D 4IU Containment 4... f4lS2o oh4102 Potential Loss of the Fuel Clad Nuclear Coolant System ANDThr Fuel CladThr Potentia Losssofof Containment ANI)4. Conaimet.3t 4.1.S.3 Loss Ok Potential Loss of I .A.~ Loss OR Potential LossAnOtrBrie Aof OteyBare Any Other Barrier 0l Enclosure 4.1 Fission Product Barrier Matrix RPlO I AI50 00/001 Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based onl a "potential loss" or a "loss." "Not Applicable" is included in thle table as a place holder only, and has no point value assigned.Barrier Points (1-5) Potential Loss (X) Loss (X) Total Points Classification Containmenat 1 3 1 -3 Unusual Event NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Emergency Total Points
-13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of"5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description.
- 3. For each barrier, write the highest single point value applicable for the barrier in the "Points" column and mark the appropriate "loss" column.4. Add the points in the "'Points" column and record the sum as "Total Points".5. Determine the classification level based on thle number of "Total Points".6. In thle table on page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. I for Loss of Nuclear Coolant S,,ystem) that best fits thle loss of barrier descriptions.
- 7. Using the nillmlbcr (e.g. 4.1 IA. I), select the prelprinted notification forml- O1_.R a blank notification forml and complete the required in formaat ion lfr Emer'gency Coordinator approval and transmittal.
Enclosure 4.1 RP/0/A/5000/001I Fission Product Barrier Matrix Page 3 of 5 4.1.C CONTAINMENTl BARRIER POTENTIAL LOSS -(I1 Point)LOSS -(3 Points)4.I.N NCS BAR POTENTIAL LOSS -(4 Points).RIER LOSS -(5 Points)4.I.1 FUEL CLA[POTENTIAL LOSS -(4 Points)SBARRIER LOSS -(5 Points)II1$ -M -Ill !ill .... ...... ...Em im 1. Critical Safcty Function Status* Containment-RED
- Not applicable
- Core cooling-RED Path is indicated for > 15 minutes 2. Containment Conditions
- 1. Critical Safety Function Status 1. Critical Safety Function Status* NCS Integrity-Red
- Heat Sink-Red 2. NCS Leak Rate* UnisoLable leak exceeding the capacity of one charging pump innormal charging mode with letdown isolated.* Not applicable
- Core Cooling-Orange* Core Cooling-Red
- Heat Sink-Red 2. Primary' Coolant Activity Level[ I* Containment Pressure > 15 PSIG*H2 concentration
>9%* Containment pressure greater than 3 psig with less than trne full train of N S and a VX-CARF operating atecr ac!uation.
- Rapid unexplained decrease in containment pressure following initial increase* Containment pressure or sump level response not consistent with LOCA conditions.
NOT'E: Refer to Emergency Plan.Sect. D. 4, .C1 last paragraph for inability to ma~intain nollnmal anUlulltS pfressture.
- GREATER THAN available makeup capacity as indicated by a loss of NCS subcooling.
- Not applicable
- Coolant Activity* GREATER THAN 300 p~i/cc Dose Equivalent Iodine (DEl) 1-131 CONTINtJEI)
()TNJI N NtEI (-'ONTIN I)ED ('ONTINIIED Enclosure 4.1 RPIOIAIS001001 Page 4 of 5 Fission Product Barrier Matrix 4.!.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4. I.F FUEL CLAI) BARRIER POTENTIAL LOSS -( I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)lil r... ... .. .I I I I 3. Containment lsolation Valves Status After Containment Isolationi Actuation 3. SC Tube Rupt ire ItI BIB tlhtl tIi tiIUl J RTU lllfl B lURB .Not applicable
.Containment isolation is incomplete and a direct release path lioin containment exists to the environment Pri mary-to-Secondary leak rate exceeds the capacity of one charging pump in the normal charging mode with letdown isolated.* Indication that a SG is Ruptured and has a Non-Isolable secondary line fault* Indication that a SG is ruptured and a prolonged release of contaminated secondary coolant is occurring from the affected SG to the environmnent Not applicable
- Containment radiation monitor 53 A or 53 B Reading at time since Shutdown.0-0.5 hrs > 99 R/hr 0.5-2 hrs > 43 R/hr 2-4 hrs > 31 R/hr 4-8 hrs > 22 R/hr>8 hrs > 13 R/hr 4. Emereencv Coordinator/EOF Director 4. SC Secondary Side Release With Primary-to-Secondary Leakagle* Not applicable
.Release of secondary side to thle environmlent with primary to secondary leakage GREATE-R TH-AN Tech Spec:illowabh" 4. Containment Radiationi Nlonjiorinl!
- Not applicable Not applicable Judg~enent
- Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coord inator/EOF Director indicates LOSS or POTENTIAL LOSS of the fuel clad harrier.EN I ('()NTINI:EI)
CONININU .D Enclosure 4.1 RP/O/A/5000/001I Fission Product Barrier Matrix Page 5 of 5 4.1.C CONTAINMENT BARRIER 4.I.N NCS BARRIER POTENTIAL LOSS -(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)4.I.F FUEL CLA[POTENTIAL LOSS -(4 Points))BARRIER LOSS -(5 Points)..... .... .....I ' -'III I 5. Significant Radioactive Inventory, In Containment
- 5. Emergency Coordinator/EOF Director Judgement Containment Rad.Monitor EMF53A or 53B Reading at time since shutdown: o -0.5 hr > 390 R/hr 0.5 -2 hr > 170 R/hr 2-4 hr > 125 k/hr 4 -8 hr > 90Rk/hr>8 hr > 53kUhr* Not applicable
- Any condition, including inability to monitor the batTier that in the opinion of the Emergency Coordinator
/EOF Director indicates LOSS or POTENTIAL LOSS of the NCS barrier.END 6. Emergency Coordinator
/EOF Director Judgment Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coordinator/EDF Director indicates LOSS or POTENTIAL LOSS of the containment barrier.END Enclosure 4.2 RPIOIAI5000/001I Page 1 of 2 System Malfunctions ALERT UNU3SUAL EVENT SITE AREA EMERGENCY GENERAL. EMERGENCY 4.2.U.1 Inability to Reach Required Shutdown Within Technical Specification Limits.OPERATING MODE: 1, 2,3, 4 4.2.U.!-l Plant is not brought to required operating mode within Technical Specifications LCO Action Statement Time.4.2.U.2 Unplanned Loss of Most or All Safety System Annunciation or Indication in.the Control Room for Greater Thain 15 Minutes.OPERATING MODE: 1, 2, 3, 4 4.2.Ui.2-I The following conditions exist: Unplanned loss of most (>50%/)annunciators associated with safety systems for greater than 1 5 minutes.AND In the opinion of the Operations Shif~t Manager/Emergency Coordinator/EOF Director, the loss of the annunciators or indicators requires additional persoimcl (beyond normal shif~t COlnpl~iment) to sale~ly operate the unit, 4.2.A.1 Unplanned Loss of Most or All Safety System Annunciation or Indication in Control Room With Either (1) a Significant Transient in Progress, or (2)Compensatory Non-Alarming Indicators Unavailable.
OPERATING MODE: 1, 2, 3, 4 4.2.A. 1-1 The following conditions exist: Unplanned loss of most (>50%)annunciators associated with safety systems for greater than 1 5 minutes.4.2.S.1 Inability to Monitor a Significant Transient in Progress.END OPERATING MODE: 1, 2, 3, 4 4.2.S.1-I The following conditions exist: Loss of most (>50%)Annunciators associated with safety systems.AND AND In the opinion of the Operations Shift Manager/Emergency Coordinator/EOF Director, the loss of the annunciators or indicators requires additional personnel (beyond normal shift compliment) to safely operate the unit.AN I EITHiER of the following:
- A SIGNIFICANT PLANT TRANSIENT is in progress* Loss of the GAG.ENDI A SIGNIFICANT PLANT TRANSIENT is in progress.AND Loss of the GAG.AND Inability to provide manual monitoring of any of' the following Critical Safety* subcriticality
- core cooling* heat sink* containment.
('ON'IINI)
ENEI)I- N !)
Enclosure 4.2 RP/0/A/5000/001 System Malfunictions Page 2 of 2 U.NUSUAL EVENT ALERT SITE AREA EMERGENCY GENEiRAL EMERGENCY 4.2.11.3 Fuel Clad Degradatdion.
OPERATING MODE: 1, 2, 3, 4, 5 4.2.1_1.3-I Dose Equivalent 1-131 greater than the Technical Specifications allowable limit.4.2.U1.4 Reactor C~oolant System (N CS)Leakage.OPERATING MODE: 1,2,3,4 4.2.U1.4-1 Unidentified leakage > 10 gpm.4.2.U1.4-2 Pressure boundary leakage > 10 gpmn.4.2.U.4-3 Identified leakage>Z 25 gpm 4.2.UJ.5 Unplannecd Loss of All Onsite or Offsite Commiuniicationts.
OPERATING MIODE: ALL 4.2.1_1.5-I Loss of all onsite communications capability (internal phone system. PA system. onsite radio system) affecting the ability to perlbrm routine operations.
4.2.1I.5-2 Loss of all offsite communications capabi Iity (Duke Emergency Mianagemenit Network {DI-rv.NI
'li.NR(" ETS lines. of'fsite radio system, commercial phone system) affecting!
the ability to communicate wvith ol'lsite authl ori ties.ENI) 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 o1'5 GENERtAI.
EMER(GENCTY IJNIJSI IAl, E:VENTI ALERT'SlITE AREA EM EIRGENC\: 4.3.ti.1 Any lUnplanned Release of(Gaseous or -t.3.A.1 Liquid Radioactivity to the Environment that Exceeds Two Times the SLC Limits fo~r 60 Minutes or Longer.Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environnment that Exceeds 200 Times the SLC limits for 15 Mlinutes or Longer.OPERA ITIN(; MODE: ALL OPERATING MODE.ALL 4t.3.UAt-t A vatid '[rip 2 alarm on radiation monitor EMIF-49L or EMF-57 for > 60 minutes or oil! likely continue obr > 601 minutes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H- P/0/B3/1009/0 14.4.3.1U.1-2 A valid indication on radiation monitor EMF- 36L of_> 3.00E+04 cpm lbr > 60 minutes or will likely' continue tbr _> 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD)-EI'-ALL-0202.4.3.A.l-1 A valid indication on radiation monitor EMF- 49L or EMF-57 of_ 1.2E+05 cpm lbr > 15 mfinutes or will likely continue for >15 mtnutes, which indicates that the releatse may have exceeded the initiating condition and indicates the need to assess the release with procedure ItP/0/B/ 1009/014.(Continued) 4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100l mirem TED)E or 500 anrem CDE Adult Thyroid for the Aetual or Projected Duration of the Release.OPERATING NMODE: ALL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of">_ 2.7E+06 cpm sustained for > 15 minutes.4.3.S.1-2 Dose assessment temn~calculations indicate dose consequences greater than 100 mrem T1EDE or 500 turen CDE Adult Thyroid at the site boundary.{(Continued) 4.3.G.1 Boundary l)ose Resulting from an Actual or Inmminent Release of Radioactivity that Exceeds 1000 wrenm ITEDE or 5000 mrema CDE Adult Thyroid fo~r the Actual or Projected Duration of the Release.OPERATING MIODE: ALL 4.3.G.t-1 A valid indication on radiation monitor EMF-36H]of">_ 8.3 E+03 cpm sustained tbr > I5 tminutes.4.3.G.1-2 Dose assessment team calculations indicate dose consequences greater than 1000 mrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.I Continued) t( 'ontinued)
Enclosure 4.3 Abnormal Rad Levels/Radiologicai Effluent RP/O/A/5000/001 Page 2 ot'5 GENERAL EMERGENCY UNulSUAL EVENT ALERT SITE AREA EMERGENCY 4.3.U.1-3 Gaseous effluent being released exceeds two times SLC 16.11-6 lbr >60 minutes as determined by RP procedure.
4.3.U.I-4 Liquid effluent being released exceeds two times SLC 16.11-I for>60 minutes as determined by RP procedure.
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continuemd) 4.3.A.i-2 A valid indication on radiation monitor EMF- 36L of>_5.4E+05 cpm for > 15 minutes or will likely continue for >15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202.
4.3.A.1-3 Gaseous effluent being released exceeds 200 times the level of SLC 16.11-6 for> 15 minutes as detennined by RP procedure.
4.3.A.1-4 Liquid effluent being released exceeds 200 times the level of SLC 16.11-1 for> I5 minutes as determined by RP~procedure.
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be comnpleted within this time period, declaration mstls be made based on the valid rad iat ion monitor reading.
4.3.S.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 100 mrem TEDE or 500 mrem CDE Adult Thyroid at the site bounmdarmy.
Note 1: These EMAF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available.
Note 2: If dose assessment team calculations cannot be completed in I5 minu~tes.then walid monitor reading~should be used lbr emergency classification.
ENDI 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 1000 inrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.Note I : These EMF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available.
Note 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid monitor reading should be used for emergency classification.
E NI 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 3 of 5.GENERAL EMERGENCY UNUSIJAL EVENT ALERT SITE AREA EM'ERGENCV:
4.3.U.2 Unexpected increase iin Plant Radiation or Airborne Concentration.
OPERATING MODE: ALL 4.3.UJ.2-1I Indication of uncontrolled water level decrease of greater than 6_inches in the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.11.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pooi and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.11.2-3 Unplanned valid area EMF reading increases by a factor of 1 ,000 over normal levels as shown in Enclosure 4.10.EN I)4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that tlas or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor V'essel.SDoes not apply to spent fuel in dry cask storage. Refer to EPLAN Section D basis document OPERATING MIODE: ALL 4.3.A.2-1 An unplanned valid trip II alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge 1IEMF- 15 2EMF-4 Spent Fuel Pool Ventilation 1EM F-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Mode Only)l EMF-17 2EMF-2 Containment Noble Gas Monitor (Applies to Mode 6 andMode Only)I EM F-39 21N'lF-39 C(oniliiniud)
Enclosure 4.3 RPIOIAI5 000/001 Abnormal Rad Levels/Radiological Eftluent Page 4 of 5 UNUSUAL EVENTI ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any irradiated fiuel will become uncovered.
4.3.A.2-3 NC system wide range level <95% after initiation ofhNC system make-up.AN.__D_Anly irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.4.3.A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.ANDI Any irradiated fuel assembly not capable of being fully lowered inb the spent fuel pool racks or transfer canal fuel transfer system basket.(Colnlinlued)
Enclosure 4.3 RP/0/A/5000/00 Abnormial Rad Levels/Radiological Effluent Page 5 of 5 IUNtJSUAI EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases inl Radiation Levels Within the Facility That Inmpedes Operation of Systems Required to Mlaintain Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.3.A.3-1 V'alid reading on IEMF-12 greater than 1 5 mremihr in the Control Room.4.3.A.3-2 Valid indication of radiation levels greater than 15 nmremihr in the Central Alarm Station (_CAS) or Secondary Alarm Station (SAS).4.3.A.3-3
\"alid radiation monitor reading exceeds the levels shown in Enclosure 4.1l0.ENDI Enclosure 4.4 Loss of Shutdown Functions UNUSUAL EVENT ALERT ENDp~4.4.A. 1 Failure of Reactor Protection System liastrunientation to Comiplete or Iuitiate anl Automatic Reactor Trip Once a Reactor Protection System Setpoint ilas Been Exceeded and Manual Trip Was Successful.
OPERATING MODE: 1, 2,3 SITE AREA EMERGENCY 4.4.S.1 Failure of Reactor P~rotection System Instrunientation to Complete or Initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoiut 1-as Beeni Exceeded and Manual Trip Was NOT Successful.
OPERATING MODE: I RP/0/A/5000/001I Page 1 of 3 GENERAl. EMERGENCY 4.4.G.1 Failure of the Reactor Protection System to Complete an Autonmatic Trip and Manual Trip Was NOT Successful and There is Indication of an Extreme Challenge to the Ability to Cool the Core.OPERATING MODE: I 4.4.G.l-l The following conditions exist: Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND Manual reactor trip from the control room was not successful in reducing reactor* power to less than 5% and decreasing.
AND)4.4.A.1-1 The following conditions exist: 4.4.S.1-1 The following conditions exist: Valid reactor trip signal received or required and automatic reactor trip wa~s not successful.
AND Manual reactor trip from the control room is successful and reactor power is less than 5%and decreasing.(Continued)
Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND Manual reactor trip from the control room was miot successful in reducing reactor power to less than 5% and decreasing.(Continued)
E ITIE I lof the followingt conditions exist:* Core Cooling CSF-RED* Heat Sink CSF-RED.ENDI Enclosu re 4.4 RP/0/A/5000/001I Loss of Shutdown Functions P~age 2 of 3[UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.4.A.2 Inability to Miaintain Plant in Cold Shutdown.OPERATING MODE: 5, 6 4.4.A.2-I Total loss of ND and/or RN and/or KC.AND One of the following:
- Inability to maintain reactor coolant temnperature below 200 0 F* Uncontrolled reactor coolant temperature rise to> 180 0 F.END 4.4.S.2 Complete Loss of Function Needed to Achieve or Mlaintain Hot Shutdown.OPERATING MODE: 1,2, 3, 4 4.4.S.2-I Subcriticality CSF-RED.4.4.S.2-2 Heat Sink CSF-RED.4.4.S.3 Loss of Water Level inl the Reactor Vessel That I-las or Will__ Uncover Fuel inl the Reactor Vessel.OPERATING MODE: 5, 6 4.4.S.3-I Failure of heat sink causes loss of cold shutdown conditions.
ANI)Lower range Reactor Vessel Level Indication System (RVLIS) decreasing after initiation of NC system mnakeup.4.4.S.3-2 Failu~e of heat sink causes loss of cold shutdown conditions:
AND Reactor Coolant (NC) system mid or wide range level less than 1 1% and decr-easing after initiation of NC system makeup.{Conitinued) 0 0 Enclosure 4.4 RP/0/A/5000/001I Page 3 of 3 Loss of Shutdown Functions IJNISIAIi.
EVENT'ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.4.S,3-3 Failure of heat sink causes loss of cold shutdown conditions.
AND Either train ultrasonic level indication less than 7.25% and decreasing after initiation of NC system makeup.END 0 Enclosure 4.5 Loss of Powver JNI.JSUIAL EVENT ALERT 4.5.UL.1 Loss of All Offsite Power to Essential Busses for Greater Than 15 Minutes.OP~ERATING MODE: I, 2, 3, 4 4.5.U.1-1 The following conditions exist: Loss of offsite power to essential buses ETA and ETB for greater than 15 minutes.ANDI Both emergency diesel generators are supplying power to their respective essential busses.(Continued) 4.5.A.1 Loss of All Offsite Power and Loss of All Onsite AC Power to Essential Busses During Cold Shutdown Or Refueling Mode.OPERATING MODE: 5, 6, No Mode 4.5.A.I-1 Loss of'all ot/hite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB.AND Failure to restore power to at least one essential bus within 15 minutes.SITE AREA EMIERGENCY 4.5.S.1 Loss of All Offsite Power and Loss of All Onsite AC Power to Essential Busses.OPERATING MODE: 1, 2, 3, 4 4.5.S.1-1 Loss of all off'site and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB.AND Failure to restore power to at least one essential bus within 1 5 minutes.(Continued)
RP/O/A/5000/001I Page 1 of 2 GENERAL EMERGENCY 4.5.G.1 Prolonged Loss of All (Offsite and Onsite) AC P~ower.OPERATING NMODE: 1,2,3,4 4.5.G.1-1 Prolonged loss of all offsite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB for greater than 15 minutes.AND Standby Shutdown Facility (SSF) fails to supply NC pump seal injection OR CA supply to Steam Generators.
AND (Continued)(Continnued) 0 Enclosure 4.5 Loss of Power RP/0/A/5000/001I Page 2 o1"2 UNUSUAL EVENT ALERT OPERATING MOI)E: 5, 6, No Mode'4.5.U.I1-2 The 1Ibllowinlg conditions exist: Loss of off'site power to essential buses ETA and ETB for greater than I5 minutes.AN_._D_One emergency diesel generator is supplying power to its respective essential bus.4.5.U.2 Unplanned Loss or Required DC Power IDuring Cold Shutdown or Refueling Mode for Greater than 15 Minutes.OPERATING; MODE: 5, 6 4S.5.LJ.2-1I The following conditions exist: 4.5.A.2 AC power to essential busses reduced to a sinlgle power source for greater than 15 nuinutes such that an additional single failure could result in station blackout.OPERATING MODE: 1, 2,3, 4 4.5.A.2-I The following condition exists: AC power capability has been degraded to one essential bus powered from a single power source for > 15 maii. due to the loss of all but one of: SITE AREA EMERGENCY 4.5.S.2 Loss of'All Vital I)C Power.OPERATING MODE: 1, 2, 3, 4 4.5.S.2-1 The following conditions exist: Uniplanned loss of both unait related busses: EBA and EBD both <112 VDC, and EBB and EBC both <109 VDC.AND Failure to restore power to at least one required DC bus within 15 minutes from the time of loss.GENERAL EMERGENCY At least one of the following conditions exist:* Restoration of at least one essential bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is NOT likely* Indication of'continuing degradation of core cooling based on Fission Product Barrier monitoring.
END END SATA ATC DiG A SATB ATD D/G B l nlflauned loss of bo0th unit related busses: IBA and LBD both <112 \"L)C. and I'BB 13 ad F B&( both -109 V DC'.ANxi___IF iue to testor ie power to at Ileast one requi jred I )(' bus within 15 inivmutcs from ihc tinme of loss.E NI)END 0 0 Enclosure 4.6 Fire/Explosion and Security Events RPIOIAI50001001I Page 1 of 3 G EN ERAL EM ERG ENCYEVENT ALERT SITE AREA EMERGENCY 4.6.LJ.1 Fire Within Protected Area Boundai'y NOT Extinguished Within 15 Minutes of Detection OR Explosion Within the JProtected Area Boundary.OPERATING MODE: ALL 4.6.UJ.l-1 Fire in any of the following areas NOT extinguishned within 15 minutes of control room notification or verification of a control room fire alarm.* Reactor Building* Auxiliary Building* Diesel Generator Rooms* Control Room* RN Pumphouse* SSF* CAS* SAS* Doghouses* FW\ST" Turbine Bu~ilding* Service lBuilding* Monitor Tank Buildine* ISI:SI* tin it 1'2 ransfIbriner Yard ((01 'olin ed 4.6.A.1 Fire or Explosion Affecting thne Operability of Plant Safety Systems Required to Establish or Maintain Safe Shutdown.OiPERATING MODE: 1, 2, 3, 4, 5, 6 4.6.A.1-1 The following conditions exist: (Non-security events)Fire or explosion in any of the following areas:* Reactor Building* Auxiliary Building* Diesel Generator Rooms*Control Room* RN Pumphouse* SSF* CAS* SAS* FWST" Doghouses (Applies in Mode I, 2, 3, 4 only).4.6.S.1 110OSTILE ACTION within the PROTECTED AREA OPERAUTING MODE: ALL 4.6.5.1-I A IIOSTILE ACTION is occu~rring or has occurred withfin the IPROTECTED AREA as reported by thne CNS Security Shif't Supervision END 4.6.G.! ltOSTILE ACTION Resulting in Loss of Physical Control of the Facility.OPERATING MODE: ALL 4.6.G.I-1 A hlOSTILE ACTION has occurred such that plant personnel arc unable to operate equipment required to maintain safety functions.
4.6.G.1-2 A HOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT fuel damage is likely for a FRESHtLY OFF-LOADED REACTOR CORE in pool.END)ANDI Onle of the liollow~ing:
- Affected safety system Iparaumcter indications show degraded perlirmnance l(-'oniiinucd) 0 Enclosure 4.6 Fire/Explosion and Security Events RP!OIAI5 000/001I Page 2 of 3 GENERAL EMERGENCY UINUISUAL EVENT ALERT SITE AREA EMERGENCY 4.6. U.i1-2 Report by plant personnel of an unanticipated explosion within protected area boundary resulting in visible damage to permanent structure or equipment or a loaded cask inl the ISFSI.4.6.[I.2 Confirmed SECURITY CONDITION or Threat Which Indicates a Potential Degradationi in the Level of Safety of the Plant.OIPERATING MODE: All 4.6.U1.2-I A SECURITY CONDITION that does NOT involve a ItOSTILE ACTION as reported by the CNS Security Shift Supervision.
4.6.U.2-2 A credible site-specific security threat notification.
4.6.U1.2-3 A validated notificaltion frol'NRC providing inlormation ol an aircrafft threat.ENDI*Plant personnel report visible damage to permlanenlt structures or equipment within the specified area required to establish or maintain safe shutdown within the specifications.
Note: Only one train of a system needs to be affected or damaged in order to satisfy this condition.
4.6.A.2 Fire or Explosion Affecting tihe Operability of P~lant Safety Systems Required to Establish or Maintain Safe Shutdown.OPERATING MODE: No Mode 4.6.A.2-1I The following conditions exist: (Non-security events)Fire or explosion in any of the following areas:* Spent Fuel Pool* Auxiliary Building.* RN Pump houise AND One of the following:
- Spent Fuel Pool level anld/or tempeC~llratr sho~v degraded pcrlbrmance
!('on tin ued)
Enclosure 4.6 RP/0/A/5000/001 Fire/Explosion and Security Events Page 3 of 3 UJNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling~.4.6.A.3 IIOSTILE ACTION Within the OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift. Supervision 4.6.A.3-2 A validated notification from*NRC of airliner attack threat wiihin 30 minutes of the site.END Enclosure 4.7 Natural Disasters, Iltazards, And Other Conditions Affecting Piant Safety UNUSUAL EVENT ALERT SITE AREA EMIERGENCY 4.7.U.1 Natural and Destructive Phenomena Affectinig tihe Protected Area.
MIODE: ALL 4.7.U.l-1 Tremor felt and valid alarm on the Syscom Seismic Monitoring System (OAC C 1D225 2).4.7.U.I-2 Report by plant personnel of tor'nado striking within protected area boundary/ISFSl.
4.7.U.I-3 Vehicle crash into phlan structures or systems within protected area boundary/ISFSI.
4,7.U.1-4 Report of turbine failure resutlting inl casing penetration or damage to turbine or generator seals.4.7.1_1.1-:5 Independenlt Spent Fuel Cask tipped over or dropp~ed greater than 24 inches.4.7.11.I-6 LUncontrolled flooding in the ISFSI area.4.7.1 .1-7 "l'rnado generated missiles(s) impactin-~
the ISFS I.S('ioninuitd) 4.7.A. 1 Natural and Destructive Phenomena Affecting the Plant Vital Area.OPERATING MODE: ALL 4.7.A.1-1 Valid "~OBE Exceeded" Alarm on I AD-4.B/8 4.7.A.i-2 Tornado or high winds: Tornado striking plant structures within the vital a rea:* Reactor Building* Auxiliary Building* FWST* Diesel Generator Rooms* Control Roorn* RN Pumphouse* SSF* Doghouses* CAS* SAS 4.7.S.1 Conitrol Room Evacuatiou Iltas Been hnitiated and Plant Control Cannot Be Established.
OPERATING MODE: ALL 4.7.S.1-1 The followving conditions exist: Control Room evacuation has been initiated per API/1 (2)/A/5500/0 17 AND Control of the plant cannot be established from the ASP or the SSF within 15 minutes.4.7.S.2 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of Site Area Emergenicy.
OPERATING MODE: ALL 4.7.S.2-1 Other conditions exist which in the J udgemient of the Emergency Coordinator/EOF-Director indicate actual or likely ma~jor lhuilures ofplant functions needed lbr protection of the public.I"N I)RP/0/A/5000/001I P~age I of 4 GENERAL EMIERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency.
OPERATING MODE: ALL 4.7.G.1-1 Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (I) actual or imminent substantial core degradation with potential for loss of containment OR (2) potential for uncontrolled radionuclide releases.
These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.L-NI)OR sustained winds >_ 74 mph lbr-" I5 minutes.t(oinllliuiedl 0 Enclosure 4.7 Natural Disasters, Hazards, Andi Other Conditions Affe~cting Plant Safety RP/0/A/5 000/001 Page 2 of 4 GENERAL EMERGENCY UNUSUAL EVENT ALERT SITE AREA EMERGENCY 4.7.11.2 Release of toxic or Fininniable Gases Deemed Detrimental to Safe Operation of the FPlant.O IPERATING MODE: ALL 4.7.U1.2-I Report or detection of toxic or flammable gases that could enter within the site boundary in amounts that can affect safe operation of the phlan.4.7.U1.2-2 Report by Local, County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgemtent of the Emergency Coordinator/EOF Dir-ector Warrant Declaraition of art Unusual Event.OIPERATING MODE: ALL 4.7.11.3-1 Other conditions exist which in thle juidg~eicnt of, the Emergency Coord ilnatoriLOF-lirector indicate a potei ti al dcegradation of the level of satet o~t' " theU p3tlant.4.7.A.1-3 Visible structural damage caused by cither:* Vehicle crashes OR* Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures:
- Reactor Building* Auxiliary Building* FW'ST* Diesel Generator Rooms* Control Room* RN Pump I-ouse* SSF* Doghouses* CAS* SAS V NI
- 0 Enclosure 4.7 RP/0/A/5000/00 Natural Disasters, Hazards, And Other Conditions Affe~cting Plant Safety Page 3 o1"4 UNUSUAL EVENT ALERT SITE AREA EM1ERGENCY' GENERAL EMERGENCY 4.7.A.2 Release of Toxic or" Flanmnable Gases Within a Facility Structure Which Jeopardizes Operation of Systems Required to Maintain Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.7.A.2-1 Report or detection of toxic gases within a Facility Structure in concentrations that will be life threatenine to plant personnel.
4.7.A.2-2 Report or detection of flammable gases within a Facility Structure in concentrations that will affect the safe operation of the plant.Structures lbr the above EALs:*, Reactor Building* Auxiliary Building* Diesel Generator R~oomas* Control Room* RN lPumphouse
- SSF* CAS* SAS
- 0 Enclosure 4.7 RP/O/A/5000/O0 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 4 of 4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.3 Control Room Ev'acuatjion llas Beeni Initiated.
OPERATING MODE: ALL 4.7.A.3-1 Control Room evacuation has been initiated per API/1 (2)/A15500/0 17.4.7.A.4 Other Conditions Existing Which in the Judgemnent of the Emnergency Coordinator/EOF Director Warrant Declaration of an Alert.OPERATING MODE: ALL 4.7.A.4-1 Other conditions exist which in the Judgement of the Emergency Coordinabor/EOF Director indicate that plant safety systems may be degraded and that increased monitoring of plant functions is warranted.
ENDI Enclosure 4.8 R P/O/A/5000iOO0I Definitions/Acronyms Page I of"4 ALERT- Events are in process or have occurred which involve an actual or potential substantial degradation of the level of saf'ety of the plant or a security event that involves probable life threatening risk to sire personnel or damage to site equipment because of hostile action. Any releases are expected to he limited to small fractions of the EPA protective action guideline exposure levels.ALL (As relates to Operating Mode Applicability)
-Modes 1, 2, 3,4,5,6 and No Mode (De fueled)BOMB -Refers to an explosive device suspected of having sufficient force to damage plant systems or structures.
CARF -Conatainment Air Return Fan.CIVIL DISTURBANCE
-A group often (10) or more people violently protesting station operations or activities at the site. A civil disturbance is considered to be violent when force has been used in anl attempt to injure site personnel or damage plant property.COGNIZANT FACILITY STAFF -Any member of facility staff, who by virtue of train inJg and experience.
is qualified to assess the indications or reports fobr validity and to compare the same to the EALs in the licensee's emergency classification scheme (Does not include staff whose positions r'equire they report, rather than assess, abnormal conditions to the facility.).
CREDIBLE THREAT -A threat should be considered credible when:* Physical evidence supporting the threat exists.* Information independent (law enforcement) from the actual threat message exists that supports the threat.o A specific group or organization claims responsibility for the threat.EPA PAG -Environmental Protection Agency Protective Action Guidelines for exposure to a release of radioactive material.EMERGENCY RELEASE -Any unplanned, quantifiable radiological release to the environment during an emergency event. The release does not have to be related to a declared emergency.
EXPLOSION
-A rapid, violent unconfined combustion, or a catastrophic failure of pressurized equipmenlt (e.g., a steamline or feedwater line break) that imparts energy sufficient to potentially damage or creates shrapnel to actually damage permanent structures, systems or components.
An electrical breaker flash that creates shrapnel and results in damage to other components beyond scorching should also be considered.
EXTORTION
-An attempt to cause an action at the site by threat of force.FIRE -Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observed.
An electrical breaker flash that creates high temperatures for a short duration and merely localized scorching to that breaker and its compartment should not be considered a fire.FRESHLY OFF-LOADED REACTOR CORE -The complete removal and relocation of" all fuel assemblies fr'om the reactor core and placed in the spent ftiel pool. (Typical of a "No Mode" operation during a refuel outage that allows safety system maintenance to occur and results in maximum decay heat load in the spent fuel pool system.)
Enclosure 4.8 RP/0/AIS000/001 Definitions/Acronyms Page 2 of" 4 FUNCTIONAL
-A component is fully capable of meeting its design function.
It would be declared INOPERABLE if unable to meet Technical Specifications.
GENERAL EMERGENCY-Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility.
Releases can be reasonably expected to exceed EPA protective action guideline exposure levels offsite for more than the immediate site area.HOSTAGE -A person(s) held as leverage against the station to ensure demands will be met by the station.HOSTILE ACTION -An act toward an NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidates the licensee to achieve an end. This includes attack by air.land, or water using guns, explosives, PROJECTILES, vehicles or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on thle NPP. Non-terrorism-based EALs should be used to address such activities (e.g.. violent acts between individuals in the OWNER CONTROLLED AREA).HOSTILE FORCE -One or more individuals who are engaged in a determined assault, overtly or by stealhh and deception, equipped with suitable weapons capable of killing, maiming or causing destruction.
IMMINENT -M itigation actions have been ineffective, additional actions are not expected to be sutccessfl, and trended information indicates that the event or condition will occur. Where IMMVINENT time frames are specified, they shall apply.INOPERABLE
-A component does not meet Technical Specifications.
Thle component may be f'unctional.
capable of meeting its design.INABILITY TO DIRECTLY MONITOR -Operational Aid Computer data points are unavailable or gnu ges/panel indications are not readily available to the operator.INTRUSION
-A person(s) present in a specified area without authorization.
Discovery of a BOMB in a specified area is indication of INTRUSION into that area by a HOSTILE FORCE.ISFSI -Independent Spent Fuel Storage Installation
-Includes the components approved for loading and storage of spent fluelI assemblies.
LOSS -A component is INOPERABLE and not FUNCTIONAL.
NO MODE -Defue led.OWNER CONTROLLED AREA -Area outside the protected area fence that immediately surrcounds the plant. Access to this area is generally restricted to those entering on official business.PROJECTILE
-An object directed toward a NPP that could cause concern for its continued operability.
reliability or personnel safety.PROLONGED
-A duration beyond normal limits, defined as "greater than 15 m~inutes' or as determine~d by the judgment of the Emergency Coordinator.
Enclosure 4.8 RPi0/A/5000i00 I Definitions/Acronyms Page 3 of 4 PROTECTED AREA -Typically, the site specific area which normally encompasses all controlled areas wvithin the security PROTECTED AREA fence.REACTOR COOLANT SYSTEM (RCS/NCS)
LEAKAGE -RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13.RUPTURED (As relates to Steam Generator)
-Existence of primary to secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.
SABOTAGE -Deliberate damage, misalignment, or misoperation of plant equipment wvith the intent to render the equipment unavailable.
Equipment found tampered with or damaged due to malicious mischief may not meet the definition of SABOTAGE until this determination is made by security supervision.
SECURITY CONDITION
-Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.SIGNIFICANT PLANT TRANSIENT-An unplanned event involving one or more of the following: (I)Automatic turbine runback >25% thermal reactor power, (2) Electrical load rejection
>25% full electrical load; (3) Reactor Trip, (4) Safety Injection.
(5) Thermal power oscillations
>1 0%.SITE AREA EMERGENCY
-Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public.Any releases are not expected to exceed EPA Protective Action Guidelines to exposure levels beyond the site boundary.SITE BOUNDARY -That area, including the protected area, in which Duke Energy has the autthority to control all activities, including exclusion or removal of personnel and property.SLC -Selected Licensee Commitments.
SUSTAINED
-A duration of time long enough to confirm that the CSF is valid (not nmomentary).
TERMINATION
-Exiting the emergency condition.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) -The sum of external dose exposure to radioactive plume, to radionuclides deposited on the groutnd by the plume, and the internal exposure inhaled radionuclides deposited in the body.TOXIC GAS -A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g. chlorine).
UNCONTROLLED
-Event is not the result of planned actions by the plant staff.UNPLANNED
-An event or action is UNPLANNED if it is not the expected result of normal operations, testing, or maintenance.
Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.
Enclosure 4.8 R PIOIAI50001001 Definitions/Acronyms Page 4 of 4 UNUSUAL EVENT- Events are in process or have occurred which indicate a potential degradation of" the level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless fuirther degradation or" safety systems occurs.VALID -An indication or report or condition is considered to be VALID when it is conclusively verified by: (I) an instrument channel check, or (2) indications on related or redundant instrumentation, or (3) hy direct observation by plant personnel such that doubt related to the instrument's operability, the condition's existence or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.
VIOLENT -Force has been used in an attempt to injure site personnel or damage plant property.VISIBLE DAMAGE -Damage to equipment or structure that is readily observable without measurements, testing, or analyses.
Damage is sutfficient to cause concern regarding the continued operability or reliability of affected strutcture, system, or component.
Example damage: deformation due to heat or impact. denting, penetration, rupture, cracking, paint blistering.
VITAL AREA -Areas within the PROTECTED AREA that house equipment important for nuclear safety.Access to a VITAL AREA is allowed only if an individual has been authorized to be in that area per the secuirity plan. Therefore, VITAL AREA is a security term.
Enclosure 4.9 RPiO/A/5000/OO01 Emergency Declaration Guidelines Page I ot'2 TI-E FOLLOWING GUIDANCE IS TO BE USED BY THE EMERGENCY COORDINATOR IN ASSESSING EMERGENCY CONDITIONS.
- Assessment, classification and declaration of any applicable emergency condition should be completed with 15 minutes after indication or information is available to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded.o The Emergency Coordinator shall review all applicable initiating events to ensure proper classification.
- Thle BASIS Document (located in Section D of the Catawba Nuclear Site Emergency Plan) is available for review if any questions arise over proper classification.
- Emergencies are declared for the site. If an event results in multiple emergency action levels on a unit or different emergency action levels on each unit, then the emergency declaration shall be based on the higher classification.
Information relating to the unit with the lesser classifica'tion will be noted as additional information on the Emergency Notification Form (EN F).* If an event occurs, and a lower or higher plant operating mode is reached before the classification can be made, the classification shall be based on the mode that existed at the time the event occurred.*The fission product barrier matrix is applicable only to those events that occur at (Mode 1-4) hot shutdown or higher. An event that is recognized at cold shutdown or lower (Mode 5 or 6) shall not be classified using the fission product barrier matrix. Reference would he made to the other enclosures that provide emergency action levels for specific events (e.g. severe weather, fire.security).
- If a transient event should occur, the following guidance is provided.1.Some emergency action levels specify that a condition exist for a specific dluration prior to declaration.
- a. For these EALs, the classification is made when the Emergency Coordinator assessment concludes that the specified duration is exceeded or will be exceeded (i.e. condition cannot be reasonably corrected before the duration elapses), whichever is sooner.b. If a plant condition exceeding EAL criteria is corrected before the speci fied duration time is exceeded, the event is NOT classified by that EAL,. Lower Severity EALs, if any, shall be reviewed for possible applicability in these cases.
Enclosure 4.9 RR/O/A/5000/O01 Emergency Declaration Guidelines Pace 2 o f 2 2. If a plant condition exceeding EAL criteria is not recognized at the time of occurrence, but is identified well after the condition has occurred (e.g. as a result of routine log or record review) and the condition no longer exists, an emergency shall NOT be declared.Reporting under 10OCFR50.72 may be required.
Such a condition could occur, f'or example, ifra follow-up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.3. If an emergency classit'ication is warranted, but the plant condition is corrected prior to declaration and notification, the Emergency Coordinator must consider the potential that the initiating condition (e.g. Failure of Reactor Protection System or earthquake) may have caused plant damage that warrants augmenting the on-shift personnel via activation of the Emergency Response Organization.
Thle following action shall be taken: a. For UNUSUAL EVENTS, the condition shall be declared and notifications made. The event may be terminated in the same notification or in a f'ollow-up notification.
- b. For ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY, rhe event shall be declared and the emergency response organization activated.
DETERMINATION OF 'EVENT TIME" (TIME THE I5 MINUTE CLOCK STARTS)I. Event time is the time at which indications become available that an EAL has been exceeded.2. Event time is the time the 15 minutes clock starts for classification.
- 3. The event classification time shall be entered on thle emergency notification fbrm.MOMENTARY ENTRY INTO A HIGHER CLASSIFICATION If. while in an emergency classification, the specified EALs of a higher classification are met momentarily, and in the judgment of the Emergency Coordinator are not likely to recur, the entry into the higher classification must be acknowledged.
Acknowledgment is performed as follows: If this condition occurs prior to the initial notification to the emergen cy response organization and off site agencies, the initial message should note that the site is currently in the lower classification, but had momentarily met the criteria for the higher classification.
It should also be noted that plant conditions have improved and stabilized to the point that the criteria for the higher classification are not expected to be repeated.
./Enclosure 4.10 Radiation Monitor Readings for Enclosure 4.3 RP/O/A/5000/001I Page 1IoflI Note: These values are not intended to apply to anticipated temporary increases due to planned events (e.g. incore detector movement, radwaste container movement, depleted resin transfers, etc.).Detector Elevation Column Identifier Unusual Event Alert____________mrRlhr mnR/hr IEMF-l 522' FF, 57 Auxiliary Building Corridor 500 5000 I EMF-3 543' GG, 55 Unit 1 Charging Pump Area 100 5000 1EMF-4 543' GG, 59 Unit 2 Charging Pump Area 100 5000 IEMF-7 560' NN, 55 Unit 1 Auxiliary Building Corridor 1500 5000 1 EMF-8 560' NN, 59 Unit 2 Auxiliary' Building Corridor 500 5000 1EM~'F-9 577' LL. 55 Unit 1 Aux. Building Filter [latch 100 5000 I1EMF- 1 0 577' LL, 58 Unit 2 Aux. Building Filter Hatch 100 5000 1EMNF-22 594' KK, 53 Containment Purge Filter Area 100 5000 2EMF-9 594' KK, 61 Containment Purge Filter Area 100 5000 Kelvin Henderson DUKE Vice President ENERGY°Catawba Nuclear Station Duke Energy CNS-1 6-016 CNO1VP 1 4800 Concord Road York, SC 29745 o: 803.701.4251 March 8, 2016 f- 803.701.3221 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414 Emergency Plan Implementing Procedures Please find enclosed for NRC Staff use the following Emergency Plan Implementing Procedures:
RP/O/A/5000/001 Classification of Emergency Revision 035 RP/0/A/5000/001I Classification of Emergency Revision 036 Due to a printing error in Revision 035 on page 1 of 5, Enclosure 4.1, Revision 036 has also been included.
These revisions are being submitted in accordance with 10OCFR 50.54(q) and do not cause a reduction in the effectiveness of the Emergency Plan Implementing Procedures or the Emergency Plan.There are no new regulatory commitments in these documents.
By copy of this letter, two copies of these documents are being provided to the NRC, Region II.If there are any questions, please call Tom Arlow at 803-701-4027.
Kelvin Henderson Vice President, Catawba Nuclear Station Attachments U.S. Nuclear Regulatory Commission March 8, 2016 Page 2 xc (w/attachments):
Catherine Haney, Regional Administrator U. S. Nuclear Regulatory Commission
-Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1 257 (w/o attachments):
Jeffrey Whited NRC Project Manager (CNS)U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-B1A 11555 Rockville Pike Rockville, MD 20852-2738 Page 1 of S PROCEDURE SRP/0/A/5000/001 RP/0/A/5000/002 RP/0/A/5000/003 RP/0/A/5 000/004 RP/0/A!5000/005 RP/0/A/5000/06 RP/0/A/5000/006 A RP/0/A/5000/006 B.RP/0/A/5000/006 C RP/0/A/5 00 0/0 07 RP/0/A/5000/08 RP/0/B/5000/008 RP/0/A/5000/009 RP/0/A/5000/0 10 RP/0/A/5000/1l1 RP/0/B/5000/12 RP/0/B/5000/0 13 RP/0/B/5000/14 RP/0/A!5000/0 15.RP/0/B/5000/016 RP/0/B/5000/17 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I TITLE Classification of Emergency (Rev. 035)Notification of Unusual Event (Rev. 045)Alert (Rev. 050)Site Area Emergency (Rev. 053)General Emergency (Rev. 054)Deleted Notifications to States and Counties from the Control Room (Rev. 033)Notifications to States and Counties from the Technical Support Center (Rev. 0/37)Deleted Natural Disaster and Earthquake (Rev. 043)Deleted Hazardous Materials Spill Response (Rev. 043)Collision/Explosion (Rev. 012)Conducting a Site Assembly or Preparing the Site for an Evacuation (Rev. 027)Deleted Deleted NRC Notification Requirements (Rev. 038)Deleted Core Damage Assessment (Rev. 007)Deleted Deleted February 17, 2016 Page 2 of 5 PROCEDURE RP/0/A/5000/01 8 RP/0/B/5000/019 RP/O/A/5000/020 RP/0/A/5000/021 RP/0/B/5000/022 RP/0/B/5000/023 RP/0/A/5000/024 RP/0/B/5000/025 RP/0/A/5000/026 RP/0/B/5 000/028 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I TITLE Emergency Worker Dose Extension (Rev. 002)Deleted Technical Support Center (TSC) Activation Procedure (Rev. 038)Deleted Deleted Deleted OSC Activation Procedure (Rev. 034)Recovery and Reentry Procedure (Rev. 003)Site Response to Security Events (Rev. 017)Nuclear Communications Emergency Response Plan (Rev. 006)February 17, 2016 Page 3 of 5 PROCEDURE HP/O/B/1000/006 HP/0/B/1009/001 HP/0/B/1009/003 HP/0/B/1009/004 HP/0/B/1009/005 HP/0/B/1009/006 HP/0/B/1 009/007 HP/0/B/1009/008 HP/0/B/1009/009 HP/0/B/1009/014 HP/0/B/1009/016 HP/0/B/1009/017 HP/1/B/1009/017 HP/2/B/1009/017 HP/0/B/1009/0 18 HIP/0/B/1009/019 HP/0/B/1009/024 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II TITLE Emergency Equipment Functional Check and Inventory (Rev. 060)Deleted Radiation Protection Primary to Secondary Leakage Program (Rev. 012)Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 031)Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 018)Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 009)In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 020)Contamination Control of Injured Individuals (Rev. 016)Deleted Radiation Protection Actions Following an Uncontrolled Release of Liquid Radioactive Material (Rev. 009)Deleted Deleted Deleted Deleted Deleted Emergency Radio System Operation, Maintenance and Communication (Rev. 010)Implementing Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 002)February 17, 2016 Page 4 of 5 PROCEDURE HP/0/B/1009/025 HP/0/B/1 009/026 SH/0/B/2005/00 1 SH/0/B/2005/002 SH/0/B/2005/003 OP/0/A!6200/02 1 SR/0/B/2000/001I SR/0/A/2000/001 SR/0/B/2000/002 SR/0/A!2000/003 SR/0/B/2000/003 SR/0/A!2000/004 SR/0/B/2000/004 AP/0/A/5500/046 AD-EP-ALL-0202 AD-EP-ALL-0203 AD-EP-ALL-0204 AD-EP-ALL-0301 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II TITLE Deleted Superseded Superseded Deleted Deleted Deleted Deleted Standard Procedure for Corporate Communications Response to the Emergency Operations Facility (Applies to Catawba/McGuire/Oconee) (Rev. 002)Deleted Activation of the Emergency Operations Facility (Rev. 008)Deleted Notifications to States and Counties from the Emergency Operations Facility for Catawba, McGuire and Oconee (Rev. 006)Deleted Hostile Aircraft Activity (Rev. 008)Emergency Response Offsite Dose Assessment (Rev. 001)Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev 000 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev 000)Activation of the Emergency Response Organization Notification System (ERONS) (Rev. 000)February 17, 2016 Page 5 of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE AD-EP-ALL-0406 TITLE Duke Energy Management Network (DEMNET) (Rev 001)February 17, 2016 Form 703-1. Procedure Process Record (PPR)S I II- 41 Duke Energy PROCEDURE PROCESS RECORD (I) ID No. RP/0/A/5000/001 RC 0 o. 035 PREPARATION (2) Strat ion _____(3) Procedure Title Ca.awa.Nucear.Satio (5) Requires NSD 22, Applicability Determination?
[] Yes (New procedure or revision with major chang'es)
-Attach NSD 228 documentation E] No (Revision with minor changes)Date ~ V I (6) Reviewed By* ________________________________(OR) (KI) D)ate _______Cross-D~isciplinary Review By* '________________________(OR) (KI) NA ______ ate_______
Reactivity M gmt. Review By*~ ((OR) NA_______Date_______
Mgmt. Involvement Review By* (Ops. Mgr.) NA_______
ate ______(7) Additional Reviews (8) Approved By* ,t Date .-7-./ O///PERFORMANCE (Compare witih control copy every 14 calendar days while work is being performed.)
(9) Compared with Control Copy* Date_________
Cornpared with Control Copy* l)are_________
Compared with Control Copy* ____________________________________D
[)te _____(1I0) Date(s) Performed Work Order Number (WO#)COMPLETION (I I) lProcedure Completion Verification:
E] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
E] Yes E] NA\ Required enclosures attached'?
E] Yes [] NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked'?E] Yes E] NA Calibrated Test Equipment, if used, checked out/in antd referenced to this procedure?
E] Yes E] NA Procedure requirements met?Verified By*(12) Procedure Completion Approved*
______(13) Remarks 'Attachr additional poges, if necessary) l)ate ________P tinted Nooe and Simnatoore Form 703-1. Procedure Process Record (PPR)511.14)Duke Energy PROCEDURE PROCESS RECORD (I) ID,'o. RP/0/A15000/00I Re ~oiNo. 035 PREPARATION (2) Station ___(3) Procedure Title Catawba Nuclear Station Classification of Emergency (4) Prepared By*C~\c~r .1'Date -~ Y' ((5) Requires NSD 228 Applicability Determination?
[] Yes (New procedure or revision with niajor changes) -Attach NSD 22S documentation E] No (Revision wVith minor changes)(6) Reviewed By* (OR) (KIb l)ute_______
Cross-Disciplinary Review By" ________________________(Q R)(K[) NA ______ ate_______
Reactivity Mgmt. R~eviewv By* (OR) NA____ D__late_____
Mgmt. Involvement Review By* (Ops. Mgr.) NA________Date_______
(7) A\dditional Reviewvs ,1 .((8) Approved B3y Date PERFORMANCE (Compare wiith control copy every 14 calendar dlays while work is being per~hrmed.)
(9) Compared with Control Copy* _______________________________________________ )ate________
Compared with Control Copy* ___________________________________________
Date _______Compared with Control Copy* _______________________________________
ate_______
(1U) Date(s) Performed Work Order Number (WO#) ________________________________________________
COMPLETION (11) P'rocedure Completion Verification:
E] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA. as appropriate!
E] Yes E] Ni\ Required enclosures attached?E] Yes E] NA graphs, data sheets, etc. attached, dated, identified, anid marked?[] Yes [] NA Calibrated Test Equipment, if used, checked out/in and referenced to this procedure'?
E] Yes [] NA Procedure requirements met?Verified By* ______________
(12) Procedure Completion A~pproved*
(13) Remarks (Attach Ltdd~iioal poges, if necessaor)'rinted Naome and Signaottre IDate_______
[)ate _______
ENEGY.Facility Code : CN Applicable Facilities:
Document Number: RP/0/A/5000/001 Document Revision Number : 035 Document EC Number : Change Reason : Document Title : Classification of Emergency Arlow, Tom A EP Manager review 2/16/2 016 Notes :
10 CFR 50.54(q) Screening Evaluation Form Screening and Evaiuation Number Applicable Sites BNP []EREG #:01 997084 CNS l[]PPR AR# 01935311 CR3 []HNP []MNS []5AD #:01995501 ONS []RNP C]GO C]Document and Revision Classification of Emergency RP/0/A./5000/001 Revision 035 Part 1. Description of Activity Being Reviewed (event or action, or series of actions that may result in a change to the emergency pian or affect the implementation of the emergency plan): Activity description RP/0/A/5000IO01 (Classification of Emergency ) Rev.035 1) Procedure Body Section 2 Immediate Actions- Step 2.4 -Changed to read "I' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix)O__R refer to EAL wallboards".
- 2) Procedure Body Section 2 Immediate Actions- Step 2.5 -IF' a General Emergency is NOT declared in Step 2.40..OR the condition does NOT affect fission product barriers, review the listing of enclosures ORR refer to EAL wallboards to determine if the event is applicable to one the categories shown.3) Procedure Body Section 3 Subsequent Actions- Step 3.1 -Changed to read "To escalate, dc-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures
- 4) Procedure Body Section 3 Subsequent Actions- Step 3,2 -Changed to read -'Refer to Enclosure 4.8 (Definitions/Acronyms)
O__R 4.9 (Emergency Declaration Guidelines), as needed.'Re ferences: PRR0193531 1
Part I1. Activity Previously Reviewed?E Is this activity Fully bounded by an NR, C approved 10 CFR 50.90 submittal or Alert and Notification System Design lBeport?If yes, identify bounding source document number or approval reference and ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification:
Yes El[ No IX 10 CFR 50.54(q)Effectiveness Evaluation is not required.
Enter justification below and complete Attachment 4, Part V.Continue to Attachment 4 ,10CFR 50.54(q)Screening Evaluation Form, Part Ill Bounding document attached (optionall)
Part Ill. Editorial Change ',Yes El[ No X Is this activity an editorial or typographical change only, such as formatting, 10 CFR 50.54(q) Continue to paragraph numbering, spelling, or punctuation that does not change intent? Effectiveness Attachment 4, Evaluation is not Part IV and Justification:
required.
Enter address non ,,justification and editorial complete changes Attachment 4,___________________________________________Part V & VI.Part IV. Emergency Planning Element and Function Screen (Reference Attachment 1, Considerations for Addressing Screening Criteria)
'Does this activity involve any of the following, including program elements from NUREG-0654/FEMA REP-i Section I17 If answer is yes, then check box.1 10 CFR 50.47(b)(1)
Assignment of Responsibility (Organization Control)___
1la Responsibility for emergency response is assigned.
El 1lb The response organization has the staff to respond and to augment staff on a continuing basis El (24-7 staffing) in accordance with ithe emergency plan.___2 10 CFR 50.47(b)(2)
Onsite Emergency Organization
__2a Process ensures that on-shift emergency response responsibilities are staffed and assigned [2b The process for timely augmentation of on-shift staff is established and maintained.
Emergency Riesponse Support and Resources
__3a Arrangements for requesting and using off site assistance have been made. El 3b State and local staff can be accommodated at the EOF in accordance with the emergency plan. El (NA for CR3) __4 10 CFR 50.47(b) (4) Emergency Classification System 4a A standard scheme of emergency classification and action levels is in use. El__(Requires final approval of Screen[ and Evaluation by EP CFAM.)5 10 CFR 50.47(b) (5) Notification Methods and Procedures 5a Procedures for notification of State and local governmental agencies are capable of initiating notification C]of the declared emergency within 15 minutes (30 minutes for CR3) after declaration of an emergency and providing follow-up notificati~on.
5b Administrative and physical means have been established for alerting and providing prompt instructions
[]to the public within the plume exposure pathway. (NA for CR3)Sc The public ANS meets the design requirements of FEMA-REP-1 0, Guide for Evaluation of Alert and C]Notification Systems for Nuclear'Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. (NA for CR3)___Part IV. Emergency Planning Element and Function Screen (cont.)6 10 CFR 50.47(b)(6)
Emergency)
Communications
__6a Systems are established for prompt communication among principal emergency response C]organizations.
6b Systems are established for prompt communication to emergency response personnel.
Public Education and Information 7a Emergency preparedness informnation is made available to the public on a periodic basis within the []plume exposure pathway emergency planning zone (EPZ). (NA for CR3)___7b Coordinated dissemination of p~ublic information during emergencies is established.
[8a Ad qu t C F acilities8 a mr gema nt ya cined to esuppor e q imer ency r s onet 8a 10qut CfR 04)8 mrecacilities andmitiedt upr eqimerentyrsos.[
8b Adequate equipment is maintained to support emergency response.
___9 10 CFR 50.47(b)(9)
Accident A~ssessment 9a Methods, systems, and equipm'ent for assessment of radioactive releases are in use. J C 10 10 CFR 50.47(b)(10)
Protective Response 10Oa A range of public PARs is available for implementation during emergencies. (NA for CR3) C]10Ob Evacuation time estimates for the population located in the plume exposure pathway EPZ are available C]to support the formulation of PARs and have been provided to State and local governmental authorities. (NA for CR3)10Oc A range of protective actions is available for plant emergency workers during emergencies, including C]those for hostile action events.10Od KI is available for implementation as a protective action recommendation in those jurisdictions that []chose to provide KI to th~e public.11 10 CFR 50.47(b)(1
- 1) Radiologic.al Exposure Control 11 a The resources for controlling radiological exposures for emergency workers are established.
C [12 10 CFR 50.47(b)(12)
Medical and Public Health Support 1 2a Arrangements are made for medi~ical services for contaminated, injured individuals.
C [13 10 CFR 50.47(b)(13)
Recovery 'Planning and Post-accident Operations 1 3a Plans for recovery and reentry are developed.
C [14 10 CFR 50.47(b)(14)
Drills and Exercises 14a A drill and exercise program (including radiological, medical, health physics and other program areas) C]is established.
1 4b Drills, exercises, and training ev.olutions that provide performance opportunities to develop, maintain, C]and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses.
14c Identified weaknesses are corrected.
C]
15 [10 CFR 50.47(b)(1
- 5) Emergency Response Training 15a ~Training is provided to emergency responders.
Part IV. Emergency Planning Element and Function Screen (cont.)16 [10 CFR 50.47(b)(16)
Emergency Plan Maintenance___
1 6a Responsibility for emergency plan development and review is established.
jC 1 6b Planners responsible for emergency plan development and maintenance are properly trained. JC PART IV. Conclusion If no Part IV criteria are checked, a 10 CFR 50.54(q) Effectiveness Evaluation is not required, then complete X Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part V. Go to Attachment 4, 10 CFR 50.54(q)Screening Evaluation Form, Part VI for instructions describing the NRC required 30 day submittal.
If any Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV criteria are checked, then complete Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part V and perform a 10 CFR 50.54(q)Effectiveness Evaluation.
Shaded block requires final approval of Screen and Evaluation by EP CFAM.[]The changes included in this revision include enhancements for allowing the use of wallboards.
These changes do not impact any planning standard functions, and therefore do not require 50.54Q;evaluation.
Part V. Signatures:r
/ / ., Preparer Name (Print): Mandy B. Hare Preparer Sign tue Date:2/4/16 S('o-ReiwrNm Pit:TmAlwReviewer Signature:cd Date: Approver (EP Manager Name (Print): Cecil Fletcher Apr SintDate:
, Approver (CFAM, as required)
Name (Print) " Approver Signature:
Dat: Part VI. NRC Emergency Plan and Implementing Procedure Submittal Actions Create two EREG General Assignments.
- One for EP to provide the 10 CFR 50.54(q) summary of the analysis, or the completed 10 CFR 50.54(q).to Licensing.
- One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.___
QA RECORD Duke Energy Company Procedure No.CATAWBA NUCLEAR STATION RPIOIA/5O001001 Classification of Emergency Revisioli No.035 Reference Use PERFORMANCE I This Procedure was printed on 2/16/20 16 10:54 AM from the electronic library as: (ISSUED) -PDF Format Compare with Control Copy every 14 calendar days while work is being performed.
Compared with Control Copy
- Date _______Compared with Control Copy
- Date _______Compared with Control Copy
- Dt El Yes El NA Required attachments included?El Yes El NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked?El Yes El NA Calibrated Test Equipment, ifused, checked out/in and referenced to this procedure?
El Yes El NA Procedure requirements met?Verified By Date* Printed ANcme anzd Si~gnature Procedure Completion Approved Date* Printed Na/oe and Signature Remarks (attach addfitional pages, ifnecessa~y)
IMPORTANT:
Do NOT mark on barcodes.
lPrinted Date: '2/16/16*t ,acmet "T2D I IiII ~IlI I I l III l 11 IIl IIll I IIllIl Procedure No.:
RP/OIAI5000100 i Page 2 of 4 Classification of Emergency 1. Symptoms 1.1. Notification of Unusual Event 1. 1.1I Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs 1.2 Alert 1.2.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of'saf'ety of the plant or a security event that involves probable life threatening risk to site personnel or dlamagze to site equipment because of HOSTILE ACTION.1 .2.2 Any releases are expected to be limited to small fractions of" the EPA Protective Action Guideline exposure levels.1.3 Site Area Emergency 1.3.1 Events are in process or have occurred which involve actual or likely major failures of" plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I1) toward site personnel or equipment that could lead to the likely failure of" or: (2) that prevent effective access to equipment needed for protection of the public.1 .3.2 Any releases are not expected to result in exposure levels which exceed [PA Protective Action Guideline exposure levels beyond the site boundary.1.4 General Enmergency 1.4. 1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of" physical control of the facility.1 .4.2 Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site ajrea 2. Immediate Actions 2. 1 IF performing this procedure due to security-related event(s) considered to be a CREDIBLE THREAT or HOSTILE ACTION, perform the following.
RP/O/AI5000/00 Page 3 of 4 I..F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/026, Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence of" the event.2.2 Assessment, classification and declaration of any applicable emergency condition should be completed within 15 minutes after the availability of indications or information to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 [F' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1l (Fission Product Barrier M'atrix) OR. refer to [AL wvallboards.
2.5 IF a General Emergency is NOT declared in Ste p 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to [AL wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated.
2.7 Document the declaration time.___________
2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERG Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportunity that will not interf'ere with the performance of the crew or the fhow of the Emergency Procedure.
- 2. 10 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel.
RPIOIAI/001001 Page 4 o f 4 2.11 Implemnent the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure.
Notification of Unusual Event RP/O/A/5000/O02 Alert RP/0/A/5000/003 Site Area Emergency RP/O/A/5000/004 General Emergency RP/0/A/5000/005
- 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures 4.1 through 4.7 OR. EAL wallboards.
3.2 Refer to Enclosure 4.8 (Definitions/Acronyms)
OR 4.9 (Emergency Declaration Guidelines), as needed.3.3 Refer to Section D of the Catawba Emergency Plan for basis information about thle Emergency Classification System as needed.3.4 Refer to RP/0/A/5000/020, "TSC Activation Procedure' concerning the use of 10CFR50.54(x).
If the TSC is activated, contact the TSC Emergency Coordinator
([C)for concurrence when using I10CFR50.54(x).
- 4. Enclosures
- 4. 1 Fission Product Barrier M'atrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radiological Effluent 4.4l Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.1I0 Radiation Monitor Reading for Enclosure 4.3 EALs S Enclosure 4.1 Fission Product Barrier Matrix RPIOIAI500010011 Page 1 of 5 ission Product Barrier status (,Intact, Potential Loss, or Loss). Add points for all barriers.
Classify J)W.Ie events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is hours). In this IMMINENT LOSS situation, use judgment and classify as if the thresholds are exceeded.ission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions
- or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.ion (C SF) indications are not meant to include transient alarm conditions which may appear during the start-up of ment. A CSF condition is satisfied when the alarmed state is valid and sustained.
The STA should be consulted to alidated prior to the CSF being used as a basis to classify an emergency.
of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-___{ IC jAlert IC f Site Area Emergency
{ IC General Emergency 4. l.A.l Loss OR Potential Loss of Nuclear Coolant System 4.1.S.1 Loss OR Potential Loss of Both Nuclear Coolant System AN I Fuel Clad 4. I.G.I Loss of All Three Barriers 4.l.A.2 4.L.A.3 Loss OR_ Potential Loss of Fuel Clad Loss AND l'otential Loss Combinations of B~oth Nuclear Coolant System ANt)Fuel Clad 4.l.G.2 Loss of Any Two B~arriers AN I Potential Loss of the Third Cot a' t ll mlncolt A N )l~oss of Containmnent A N)ILoss OR Potenthil Loss 0 Enclosure 4.1 Fission Product Barrier Matrix RP/O/A/5000/001I Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based on a "potential loss" or" a "loss." "Not Applicable" is inclu~ded in the table as a place holder only, and has no point v'alue assigned.Barrier IPoints (1-5) Potential Loss (X) Loss (X) Total IPoints Classification Containment 1 3 1 -3 Unusual Event-NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Elmergency Total Points 1 -13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of 5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description.
- 3. For each barrier, write the highest single point value applicable for the barrier in the "'Points" column and mark the appropriate
"'loss"~COltllnnl.
- 4. Add the points in the lPoints'" column and record the sum as "'Total Points".5. Determine the classilqcation level based on the number of "Total Points".6. In the table on" page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. 1 for Loss of Nuclear Coolant System) that best fits the loss of harrier descriptions.
- 7. Usingt the number (e.g. 4.1 .A. I). select the preprinted notification form OR a blank notification form and complete the required nflornmt ion Ibr Emergency Coordinator approval and transmittal.
0 Enclosure 4.1 RPIOIA15000100 1 Page 3 of 5 Fission Product Barrier Matrix 4.1.C CONTAINMIENT BARRI,1ER 4.1.N NCS BARRIER 4.I.F FUEL CLAD BARRIER POTENTIAL LOSS -/(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points).....h .. .. ... .. ..I -I -* I 1. Critical Safety Function Status* Containment-RED
- Not applicable
- Core cooling-RED Path is indicated for > 15 minutes 2. Containnment Conditions
- i. Critical Safety Funlctiun Status* NCS Integrity-Red
.N 1. Critical Safety Function Status ,lot applicable
- Core Cooling-Orange* Core Cooling-Red
- Containment Pressure > 15 PSIG* H2 concentration
>9%* Containmcni pressu~re greater than 3 psig with less than oree full train of NS and a VX-CARF operating after actuation.
- Rapid unexplained decre~ase in containment pressure following initial increase Containment pressure or sump level response not consistent with LOCA conditions, NOTE: Refer to Emergency Plan, Sect. D, 4.1 .C.2, last paragraph for inability to maintalin normaal tannuluis pressure.* Heat Sink-Red 2. NCS Leak Rate* Unisolable leak exceeding the capacity of one charging pump in thle normal charging mode with letdown isolated.* Heat Sink-Red 2. Primary Coolant Activity Level* GREATER TIHAN available makeup capacity as indicated by a loss of NCS subcooling.
- Not applicable
- Coolant Activity GREATER THAN 300 ltCi/cc Dose Equivalent Iodine (DEl) 1-131 (-'ON'I'INIIEI)
CONTINIIFI)
CONT'INUIED NTNJ)CONTINIJEI)
Enclosure 4.1 RIp/O/A/5000/001 Fission Product Barrier Matrix Page 4 of 5 4.1.C CONTAINMENTI BARRIER POTENTIAL LOSS -(I Point)LOSS -(3 Points)4. I.N NCS BARRIER POTENTIAL LOSS -(4 Points)LOSS -(5 Points)4.1I.F FUEL CLAD BARRIER POTENTIAL LOSS -(4 Points)LOSS -(5 Points)..... ..T .. .. .... .." -F -1.. ... ....... ......m- "II.. ........3. ContainmentIsolation Valves Status After 3. SC. Tube Rupture 3. C~ontaiunment Radiation M'onitoring Con~tainnment Isolation Actuation Not applicable Containment isolation is incomplete and a direct release path from containment exists to the environment Primary-to-Secondary leak rate exceeds the capacity of one charging pump in the normal charging mode*with letdown isolated.* Indication that a SG is Ruptured and has a Non-lsolable secondary line fault* Indication that a SG is ruptured and a prolonged release of contaminated secondary coolant is occurring from the affected SC to the environment Not applicable
- Containment radiation monitor 53 A or 53 B Reading at time since Shutdown.0-0.5 hrs > 99 R/hr 0.5-2 hrs > 43 R/hr 2-4 hrs > 31 R/hr 4-8 hrs > 22 R/hr>8 hrs > 13 R/hr 4. Emnergenmcy Coordiinator/EOF IDirector 4. SC Secondary Side Release WNithi Primary-to-
- 4. Cointainiaent Radiaition NMoiitoringf Secondary Leakagze* Not applicable
- Release of secondary side to the environment w~ith primary to sccondatr, leakage GREATER THAN Tech Spec allowvable
- Not applicable
- Not applicable Jiudgenment
- Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coordinator/EOF Director indicates LOSS or POTENTIAL LOSS of the fuel clad barrier.END (N)O N'I N I) OlNLiD CONTIN UI-D Enclosure 4.1 RP/O/A/5000/O01I Fission P~roduct Barrier Matrix Page 5 of 5 4.1.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4.1I.F FUEL CLAD BARRIER POTENTIAL LOSS -(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)..................................I I I I ... .l F .. ..5. Significant Radioactive Invenutory In Conitainmnezut
- Containment Rad.Monitor EMF53A or 53B Reading at time since°shutdown:
U -0.5 hr > 390 R/lhr (.5 -2 hr >170 RIhr 2-4 hr > 125 R/hr 4-8 hr > 90R/hr>8 hr > 531Uhr* Not applicable
- 5.
Coordiiuator/EOF Director.Judgenement Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coordinator/IEOF Director indicates LOSS or POTENTIAL LOSS of the NCS barrier.EN...pD 6. Emieri, ency Coordinator
/EOF Director J udgmnent Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coord inator/EOF Director indicates LOSS or PO1'ENTIAL LOSS of the containmeni batTier.EN I Enclosure 4.2 RP/O/A/5000/001I Page 1 of 2 System Malfunctions UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.2.U1.1 Inability to Reach Required 4.2.A.1 Unplanned Loss of Most or All 4.2.S.1 Shutdown Within Technical Safety System Annunciation or Specilication Limits. Indication in Conitrol Room With Either (I) a Significant OP~ERATING MODE: 1, 2, 3, 4 Transient in Progress, or (2)Compensatory Non-Alarming OPER 4.2.U.1-1 Plant is not brought to required Indicators Unavailable.
operating mode within Technical 4.2.S. 1 Specifications LCO Action Statement OPERATING MODE: 1, 2, 3, 4 Time.Inability to Monitor a Significant Transient in Progress.END 4.2.U.2 Unplanned Loss of M'ost or All Safety System Annunciation or Indication in the Control Room for Greater Than 15 Minutes.OPERATING MODE: 1 ,2, 3, 4 4.2.U.2-1 The following conditions exist: Unplanned loss of most (>50%)annunciators associated with safety systems for greater than 15 minutes.AND Ina the opinion of the Operation~s Shift Manager/Emergency CoordinatoriEOF Director, the loss of the annunciators or indicators requires additionafl personnel (beyond normal shift compliment) to saflyv operate thle unit.4.2.A.1I-I The following conditions exist: Unplanned loss of most (>50%)annunciators associated with safety systems for greater than 1 5 minutes.AND In thle opinion of the Operations Shift Manager/Emergency Coordinator/EOF Director, the loss of the annunciators or indicators requires additional personnel (beyond normal shift compliment) to safely operate thle unit.AND1 EITIIER of the following:
- A SIGNIFICANT PLANT TRANSIENT is in progress* Loss of the OAC.ENI)ATING MODE: 1,2,3,4-1 The following conditions exist: Loss of most (>50%)Annunciators associated with safety systems.AND A SIGNIFICANT PLANT TRANSIENT is in progress.AND Loss of the OAC.AND Inability to provide manual monitoring of any of the following Critical Safety Functions:
- suberiticality
- core cooling* heat sink* eontaln~ntelt.
('ONTINIIEI)
ENDI Enclosure 4.2 RP/O/A/5000/O01I System Malfunctions Page 2 of 2 UNUSUJAL EVENT ALERT SITE AREA EMERGENCY EMERGENCY 4.2.U..3 Fuel Clad Degradation.
OPERATING MODE: I, 2, 3, 4I, 5 4.2.U.3-1 Dose Equivalent 1-131 greater than thle Technical Specifications allowable limit.4.2.U.4 Reactor Coolant System (NCS)Leakage.OPERATING MODE: 1,2,3,4 4.2.U.4-l Unidentified leakage > 10 gpm.4.2.UJ.4-2 Pressure boundary leakage > 10 gprn.4.2.U.4-3 Identified leakage > 25 gpm 4.2.U.5 Unplannied Loss of All Onisite or Offsite Coinnunicationls.
OIPERATING MODE: ALL 4.2.11.5-1 Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perfonn routine operations.
- 4.2.UJ.5-2 Loss of all offsite communications capability (Duke Emergenacy M-anagemtent Network [DE MN El].NR(" ETIS linies, ol'lhite radio system, commcreial phonec system) a llicting the abilitly to commun~icate wvith of'tsite antltori ties.END)
Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 of"5 G;ENERAl.
EMERG ENC\Y[;NUSI!AI, I-\.'ENT ALERT SITE Ai REA E:M ERG EN(CV 4.3.L .1 Any Unplanned Release (of Gaseous or 4.3.A.1 Liquid Radioactivity to the Environment thtat Exceeds Two Tiumes the SL(: Limits for 60 Minutes or Longer.Any I nlplaunnd Release of Gaseous or Liquid Radioactivity to the Eiuvironmcnt thatt Exceeds 200 Times the SLC limits for 15 Minutes or Longer.4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100 mrem TED)E or 500 mrem CDE Adult TIhyroid for the Actual or Projected Duration of the Release.OPERV [TINC MODE: AII OPElRATING MODE: ALL 4.3.Ui.1-1 A valid Tlrip 2 alarm on radiation monitor E~vlF-49L or ENvlF'-57 or > 60 minuteS or will likely continue for >_ 60 minultes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure
[-IP/0/B/1009/0 14.4I.3.tJ..i-2 A valid indication on radiation monitor EMF- 36L of>_ 3.(0E+t04 cpm for->_ 60)minutes or will likely continue for >- 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AID-HP-ALIL-0202.4..3.A.1-1 A\ valid indication on radiation monitor EMF- 49L or EMvF-57 of> 1.2E+05 cpm lbr> 15 minutes or will likely continue for --15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H-P/0/B3/1009/014.(Continued)
OIPERATING NIOIOE: ALiL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of> 2.7E+06 cpm sustained for> IS1 minmutes.4.3.S.1-2 Dose assessment teamn calculations in~dicate dose consequences greater than 100 mrem "IEDE or 500 mrem CDE Adult Thlyroid at the site houndary.4.3.G.1 Boundary l)ose Resultitng f'rom an Actual or hmnmitent Release of Radioactivity that Exceeds 1000 mrenm TEDE or 5000)onrei CDE Adult Thyroid for the Atuald or Projected Duration of the Release.
MODE: ALL 4.3.G.1-1 A valid indication on radiation monitor EMF-36t-of> _8.3E+03 cpm sustained lbr > 15 minutes.4.3.G.1-2 Dose assessment team calculations indicate dose conseqtuences greater than 1000 ,mrem TEDE or 5000 mrcm CDL Adtmh Thyroid at the site boundary.lConmtin ned)(( "ontini, ed) 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent R.P/O/A/5000/OO01 Page 2 of 5 GENERA I EM'ERGENCY UNU.SUAL, EVENT ALERT SITE AREA EM1ERGENCY 4.3.12...-3 Gaseous effluent being released exceeds two times SLC 16.1 1-6 for >60 minutes as determined by RP~procedure.
4,3.U.1-4 Liquid effluent being released exceeds two times SLC 16.11 I- for>60 minutes as determined by RP procedure.
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continued) 4.3.A.1-2 A valid indication on radiation nmonitor EMF- 36L of_>5.4E+05 cpm for> 15 minutes or will likely continue for >-15 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202.
4.3.A.1-3 Gaseous effluent being released exceeds 200 times the level of SLC 16.11-6 for> 15 minutes as determined by RP procedure.
4.3.A.1-4 Liquid efiluent being released exceeds 200 times the level of SLC 16.11-1 for> 15 minutes as determined by RP procedure.
Note: If the monitor reading is sustained lbr the time period indicated in the EAL AND the required assessments (procedure calcula.tions) cannot be completed within this time period, declaration mast be made baise on the valid rad iat ion monitor reading.( Conltinu Led)4.3.S.1-3 Analysis of field survey results or theld survey samples indicates dose consequences greater than 100 mrem TEDE or 500 mrem CDE Adult Thyroid at the site bounmdary.
Note 1I: These EMF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EM~F readings should not be used if dose assessment team calculations are available.
Note 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid mtonitor reading should be used for emergency class iIi cation.ENDI 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 1000 ,mrem TEDE or 5000 mrem CDE Adult Thyroid at the site ho unda ry.Note I: These EMF readings are calculated based on average anntual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF iread ings should not be uised if dose assessment team calculations are available.
Note 2: If dose assessment team calculations cannot be completed in I 5 minutes.then valid monitor reading should be used for emergency classification.
END)
Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/O/A/5000/001I Page 3 of"5 GENERAL EM'ERGENCY UNLUSI.1AL EVENT ALERT SITE AREA EMERGENCY 41.3. I.2 Uneixpected Increase in Plant Radiation or Airborne Concentration.
OPERATING MODE: ALL 4.3.U.2-1 Indication of uncontrolled water level decrease of greater than _6 inches inl the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.U.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pool and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.U.2-3 Unplanned valid area EM~F reading increases by a factorof 1,000 over normal levels as shown in Enclosure 4.10.END 4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel.Does not apply to spent fuel in diy cask storage. Refer to EPLAN Section D basis document OPERATING MODE: ALL 4.3.A.2-1 An unplanned valid trip I1 alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge IEMF-15 2EMF-4 Spent Fuel Pool Ventilation I EMIF-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Nlode Only)IEMF-17 2EM lF-2 Containment Noble Gas Monitor (Applies to Mode 6 and No Mode (Jnly)1 EMF-39 2EiNlF-3')
l( " liii ijed I 0 VP Enclosure 4.3 RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 4 of"5 UiNtSUAkL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity. spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any iIradiated fuel will become uncovered.
4.3.A.2-3 NC system wide range level <95% after initiation of NC system make-up.AND Any irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.4.3,A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.AN___D_Any irradiated fuel assembly not capable of being fully lowered into the spent fuel pool racks or transfer canal fuel transfer system basket.(C'ontinued) 0 0 Enclosure
- 4. RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 5 of 5 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases in Radiation Levels WVithin the Facility That Impedes Operation of Systems Required to Mlainitaini Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.3.A.3-1 Valid reading on IEMF-12 greater than 15 mremlhr in the Control Room.4.3.A.3-2 Valid indication of radiation levels greater than 1 5 mrem/hr in the Central Alarm Station (CAS) or Secondary Alarm Station (SAS).4.3.A.3-3 Valid radiation monitor reading exceeds the levels shown in Enclosure 4.10.ENI) 0 Enclosure 4.4 RP/0/A/5000/001I Page 1 of 3 Loss of Shutdown Functions UJNU~SUAL EVENT'ALERT SITE AREA EMERGENCY GENERAL EMIERGENCY END 4.4.A. I Failure of Reactor Protection System Instrumentation to Complete or initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Been Exceeded and Manual Trip Was Successful.
OPERATING MODE: 1, 2, 3 4.4.S.1 Failure of Reactor Protection System iostrnmnentation to Complete or Initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Beeni Exceeded and Manual Trip Was NOT Successful.
OPERATING MODE: I 4.4.A.1-1 The following conditions exist: 4.4.S.1-1 The following conditions exist: 4.4.G.1 Failure of the Reactor Protection System to Coniplcte an Automatic Trip and Mianual Trip Was NOT Successful and There is Indication of an Extreme Challenge to the Ability to Cool the Core.OPERATING MODE: 1 4.4.G.1-1 The following conditions exist: Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND M~anual reactor trip from the control rooml was uot successfufl in reducing reactor power to less than 5% and decreasing.
ANDI Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND Manual reactor trip from the control room is successful and reactor power is less than 5%and decreasing.(Cnntinuedl)
Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND M'anual reactor trip from the control room was not successful in reducing reactor power to less than 5% and decreasing.
((omntiniuedl)
ErIT'HER of' the following conditions exist:* Core ('ooling (SF-RED* 1-eat Sink (SF-RED.EN I Enclosure 4.4 Loss of Shutdown Functions RP/0/A/5000/001I Page 2 I'3 GENERAL EM~ERG ENCY UNUSUAL EVENT A LERT 4.4.A.2, Inability to M~aintain Plant in Cold Shutdown.-
OPERATING MODE: 5, 6 4.4.A.2-1 Total loss of ND and/or RN and/or KC.AND One of the following:
- Inability to maintain reactor coolant temperature below 200 0 F* Uncontrolled reactor coolant temperature rise to> 180 0 F.END SITE AREA EMERGENCY 4.4.S.2 Complete Loss of Functioni Needed to Achieve or Maintain ltot Shutdown.OPERATING MODE: 1, 2,3, 4 4.4.S.2-1 Suberiticality CSF-RED.4.4.S.2-2 1-eat Sink CSF-RED.4.4.S.3 Loss of Water Level in the Reactor Vessel That Has or Will._[ Uncover Fuel in the Reactor Vessel.OPERATING MODE: 5,6 4.4.S.3-1 Failure of heat sink causes loss of cold shutdown conditions.
AND Lower range Reactor Vessel Level Indication System (RVLIS) decreasing after initiation of NC system makeup.4.4.S.3-2 Failure of heat sink causes loss o f cold shutdown conditions.
A~NI Reactor Coolant (NC) system mid or wide range level less than 11% and decreasing after initiation ot NC system makeup.(C(iollltin lied)
Enclosure 4.4 RP IO IAI5S 001001 Page 3 of 3 Loss of Shutdown Functions IUNIUSIAL EVENT'ALERT SITE AREA E M ERGENCY GENERAL EMERGENCY 4.4.S.3-3 Failure of heat sink causes loss of cold shutdown conditions.
AND Either train ultrasonic level indication less than 7.25% and decreasing afier initiation of NC system makeup.END 0 Enclosure 4.5 Loss of Power[UNUSUAIL EVENT ALERT'SITE AREA EMERGENCY 4.5.U.1 Loss of All Offsite Power to Essential Busses for Greater Than 15 Minutes.OPERATING MODE: 1, 2, 3, 4I 4.5.U.I-1 The tbllowing conditions exist: Loss of offsite power to essential buises ETA and ETB for" greater than 15 minutes.AN_.D_Both emergency diesel generators are supplying power to their respective essential busses.(Continued) 4.5.A.1 Loss of All Offsite Power and Loss of All Onsite AC Power to Essential Busses During Cold Shutdown Or Refueling Mode.OPERATING MIODE: 5, 6, No Mode 4.5.A.i-I Loss of all offsite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB.AND Failure to restore power to at least one essential bus within 15 minutes.4.5.S.1! Loss of All Of1site Power and Loss of All Onsite AC P~ower to Essential Busses.OPERATING MIODE: 1, 2,3, 4 4.5.S.1-1 Loss of all oti~ite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB.AND Failure to restore power to at least one essential bus within 15 minutes.(Continiuedj RP/O/A/5000/OO01 Page 1 o f2 GENERAL EMERGENCY 4.5.G.1 Prolonged Loss of All (Offsite and Onsite) AC Power.OPERATING MODE: 1, 2, 3, 4 4.5.G.1-1 Prolonged loss of all offsite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB for greater than 15 minutes.AN....D Standby Shutdown Facility (SSF) fails to supply NC pump seal injection OR CA supply to Steam Generators.
AND (Continued)(Conitinued) 0 0 Enclosure 4.5 Loss of Power RPIO/AtS001001 Page>2 or)2 GENERAL. EMERGENCY 1JNIJSI.JAIL EVENT" ALERTI OPERATING MODE: 5, 6, No Mode 4.5.LL.I-2 The following conditions exist: Loss of offsite power to essential buses ETA and ETB for greater than] 15 minutes.AND One emergency diesel generator is suipplying power to its respective essential bus.4.5.U.2 Unplaiiued Loss of Required DC Power During Cold Shutdown or Refueling Miode for Greater thani 15 Minutes.OPERATING MODE: 5, 6 4.5.11.2-1 The following conditions exist: 4.5.A.2 AC power to essential busses ireduced to a single power source for greater than 15 minutes such that an additional single failure could result in station blackout.OPERATING MODE: 1, 2, 3, 4 4.5.A.2-1 The following condition exists: AC power capability has been degraded to one essential bus powered from a single power source for > 15 riin. due to the loss of all but one of: SITE AREA EMERGENCY 4.5.S.2 Loss of All Vital DC Power.OPERATING MODE: 1, 2,3, 4 4.5.S.2-1 The following conditions exist: Unplanned loss ot both unit related busses: EBA and EBD both <112 VDC, and EBB and EBC both <109 VDC.AN__.DD Failure to restore power to at least one required DC bus within 1 5 minutes from the time of loss.At least one of the Iollowing conditions exist:* Restoration of at least one essential bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is NOT likely* Indication of continuing degradation of core cooling based on Fzission Prodtuct Barrier monitoring.
ENI)END SATA ATC DiG A SATB ATD DIG B I ilplaliied loss of1 both unit irelated busses: EBA and 1.BD1 both <112 \'DC. and EBB and EBC both <109 V DC.:ANID Fa i ure_ to restore po~~'er Ito alleast one treulireul D(" bus wvithiin 15 Ininntes fromn lhe lime ofl loss.I.N I)[NI)
Enclosure 4.6 IP/O/A/5000/O01I Fire/Explosion and Security Events Page 1 of 3 UNUISUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.6.U.1 Fire Within Protected Area Boundary NOT Extinguished Within 15 Min utes o f Detection OR._Explosion Within the Protected Area Boundary.OPERATING MODE: ALL 4.6.U.I-1 Fire inl any of the following areas NOT extinguished within 15 minutes of control room notification or verification of a control room fire alarm.* Reactor Building* Auxiliary Building* Diesel Generator Rooms* Control Room* RN Pumphouse* SSF* CAS* SAS* Doghouses* FWST* Turbine Building* Service Building* Monitor'Tank Building* ISFSI* [.Jit I.;1 -Iranslbrnmer Yard Areas (Contiinued) 4.6.A.1 fire or Explosion Affecting the Operability of Plant Safety Systems Required to Establish or Manintain Safe Sbhutdown.
OPERATING MIODE: 1, 2, 3, 4, 5, 6 4.6.A. 1-1 The following conditions exist: (Non-security events)Fire or explosion in any of the following areas:* Reactor Building* Auxiliary Building* Diesel Generator Rooms* Control Room* RN Pumphouse* SSF* CAS* SAS* FWST* Doghou~ses (Applies in Mode 1, 2, 3, 4 only).4.6.S.1 HOSTILE ACTION within the PROTECTED AREA OPERATING MODE: ALL 4.6.S.1-I A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the CNS Security Shift Supervision EN.._D 4.6.G.1 HOSTILE ACTION Resulting in Loss of Physical Control of the Facility.OPERATIN(G M~ODE: ALL 4.6.G.l-1 A H-OSTILE ACTION has occurred such that plant personnel are unable to operate equipment required to maintain safety functions.
4.6.G.I-2 A IHOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT fuel damage is likely Ibr a FRESHLY OFF-LOADED REACTOR CORE in pool.ENI)AND One of the following:
- Aff~ected safety system parameter indications show-degraded performance ttConlinued)
Enclosure 4.6 RP/0/A/5000/00 I Fire/Explosion and Security' Events Page 2 of 3 UNUSUAL EVENT ALERT SIT'E AREA EMERGENCY GENERAL EMERGENCY 4.6.U.1-2 Report by plant personnel of an unanticipated explosion within protected area boundary resulting in visible damage to permanent structure or equipment or a loaded cask in the ISFSI.4.6.U_.2 Confirnmed SECUJRITY CONDITION or T'hreat Which Inidicates a Potential Degradation in the Level of Safety of the Plant.OPERATING MODE: All 4.6.U..2-1 A SECURITY CONDITION that does NOT involve a HOSTILE ACTION as reported by the CNS Security Shift Supervision.
4.6.LJ.2-2 A credible site-specilie security threat notiflication.
4.6.11.2-3 A validated notilication from NRC providing ijiformatioji ol'an airerati threat.ENI)*Plant personnel report visible damtage to permanent structures or equipment within the specified area required to establish or maintain safe shutdown within the specifications.
Note: Only one train of a system neceds to be affected or damaged in order to satisfy this condition.
4.6.A.2 Fire or Explosion Affecting the Operability of Plant Sa.fety Systems Required to Establish or Maintain Safe Shutdown.OPERATING MODE: No M~ode 4.6.A.2-I The following conditions exist: (Non-security events)Fire or exp~losion in any of the following areas:* Spent Fuel Pool* Auxiliary Buildingz.
- RN Pump house AND One of the following:
- Spent Fuel Pool level alnd/or" temlperalture showv degraded performlance t(-'ontinulicd)
Enclosure 4.6 RP/0/A/5 000/001 Fire/Explosion andi Security Events Page 3 of' 3 I)NLISLAL EVENT AILERT SITE AREA EMERGENC'Y GENERAL ENIER(GENCY' Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling.4.6.A.3 HOSTILE ACTION Within tihe OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift Supervision 4.6.A.3-2 A validated notification from NRC of airliner attack threat within 30 minutes of the site.E NI)
Enclosure 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant SafetyEVENT'ALERT SITE AREA EMERGENCY 4.7.1U.1 Natural and Destructive Phenomena Affecting tihe Protected Area.OPERATING MODE: ALL 4.7.U1.1-1 Tremor felt and valid alarm on tihe Syscom Seismic Monitoring Systemn (OAC C 1 D22 52).4.7.U1.1-2 Report by plant personnel of toi-nado striking within protected area botmdary/ISFSI.
4.7.U1.1-3 Vehicle crash into plant structures or systems within protected area boundary!/ISFSlI.
4.7.U1.1-4 Report of turbine Fa~ilure resulting in casing penetration or damage to turbine or generator seals.4.7.1_1.1-5 Independent Spent Fuel Cask tipped over or dr'opped greater than 24 inches.4.7.11..1-6 Uncontrolled Ilooding in the ISFSI area.4.7.11. .1-7 Tornado generatecd missiles(s) impacting the ISFSi.{(C oiitn liicud)4.7.A.!I Natural and Destructive Phenomena Affecting the Plant Vital Area.OPERATING MODE: ALL 4.7.A.1-1 Valid "OBE Exceeded" Alarm on I AD-4.B/8 4.7.AAl-2
'Tornado or high winds: Tornado striking plant structures within the vital a rea: e 0i 0 a 0 a Reactor Building Auxiliary Building FWST Diesel Generator Rooms Control Room RN Pumphouse SSF Doghouses CAS SAS 4.7.S.1 Control Room Evacuation Ha4s Been Initiated and Plant Conitrol Cannot Be Established.
OPERATING MODE: ALL 4.7.S.1-1 The following conditions exist: Control Room evacuation has been initiated per AP/II(2)/A15500/017 AN.__D Control of the plant cannot be established fi'om the ASP or the SSF within 15 minutes.4.7.S.2 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of Site Area Emergency.
OPERATING MIODE: ALL 4.7.S.2-l Other conditions exist which in the Judgement of the Emergency Coordinator!EGF Director indicate actual or likely major f~itilures ol plant functions needed lor protection of the~ public.END RP/O/A/5 000/001 Page 1 of 4 GENERAL EM'ERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency.
OPERATING MODE: ALL 4.7.G.1-I Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (1) actual or imminent substantial core degradation with potential for loss of containmaent OR (2) potential for uncontrolled radionuclide releases.
These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.En __)OR sustained winds >_ 74 mph for> 15 minutes.(Continued) 0 Enclosure 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety RPIO/AI/500I/O01 Page 2 o1"4 GFNERAL EMERGENCY IJNUSUJAL EVENT ALERT SITE AREA 4.7.1_1.2 Release of Toxic or Flanmnable Gases D~eemed Detrimental to Safe Operation or the Plant.OPERALTING MODE: ALL 4.7.U.2-l Report or detection of'toxic or flammable gases that could enter within the site boundary in amounts that can aff'ect safe operation of the plant.4.7.U.2-2 Report by Local. County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgeinent of the Emergency Coordiziator/EOF Director Warrant Declaration of an Unusual Event.OPERATING MODE: AILL 4.7. U.3-1I Other conditions exist which in the j udgcmlcnt o f thte Emcrgency Coordinazor/ELOF D)irector indic'ate a potential degradatlion ofth lt evel of Siitct\' of'thlw plaint.4.7.A. 1-3 Visible structural damage caused by either:* Vehicle crashes OR*Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures:
- Reactor Building* Auxiliary Building* FWST* Diesel Generator Rooms SControl Room* RN Pump 1-ouse* SSF* Doghouses* CAS* SAS (Continued)
[NI)
Enclosure 4.7 RI?/01A/5000/00 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 3 of"4 UNUSUIAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.2 Release of Toxic or Flammable Gases Within a Facility Structure Which Jeopardizes Operation of Systems Required to Maintain Safe Operationis or to Establish or Majatain Cold Shutdown.OPERATING MODE: ALL 4.7.A.2-1 Report or detection of toxic gases within a Facility Structure in concentrations that will be life threatening to plant personnel.
4.7.A.2-2 Report or detection of flammable gases within a Facility Structure in concentrations that will affect the safe operation of the plant.Structures lor the above EALs:* Reactor Building* Auxiliary Building* Diesel Generator Ro~oms* Control IRtooi* RN Ptinmphouse
- SSF* CAS* S:\S (C~onin iiiid)
Enclosure 4.7 IP/0/A/5 000/001 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 4 of 4 UINUISUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.3 Control Room Evacuation llas Beeni Initiated.
OPERATING MODE: ALL 4.7.A.3-I Control Room evacuation has been initiated per AP/1 (2)/A/5500/0 17.4.7.A.4 Other Conditions Existing Which ini the Judgemnent of the Emergency Coordinator/EOF Director Warrantr Declaration of an Alert.OPERATING MODE: ALL 4.7.A.4-10dtler conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate that plant safety systems may be degraded and that increased monitoring of plant functions is warranted.
END Enclosure 4.8 RP/O/A/5000/O00 Definitions/Acronyms Pagze I of 4 ALERT- Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of hostile action. Any releases are expected to be limited to small fractions of the EPA protective action guideline exposure levels.ALL (As relates to Operating Mode Applicability)
-Mlodes 1, 2, 3,4,5,6 and No M~ode (Defueled)
BOMB -Refers to an explosive device suspected of having sufficient force to damage plant systems or" struictuires.
CARF -Containment Air Return Fan.CIVIL DISTURBANCE
-A group often (10) or more people violently protesting station operations or activities at the site. A civil disturbance is considered to be violent wvhen force has been used in an attempt to injure site p~ersonnel or damage plant property.COGNIZANT FACILITY STAFF -Any member of facility staff, who by virtue of training and experience.
is qualified to assess the indications or reports for validity and to compare the same to the EALs in the licensee's emergency classification scheme (Does not include staff" whose positions require they rcport, rather than assess, abnormal conditions to the facility.).
CREDIBLE THREAT -A threat should be considered credible when:* Physical evidence supporting the threat exists.* Information independent (law enforcement) from the actual threat message exists that supports the threat.* A specific group or organization claims responsibility for the threat.EPA PAG -Environmental Protection Agency Protective Action Guidelines for exposure to a release of radioactive material.EMERGENCY RELEASE -Any unplanned, quantifiable radiological release to the environment during~ an emergency event. The release does not have to be related to a declared emergency.
EXPLOSION
-A rapid. violent unconfined combustion, or a catastrophic failure of pressurized equ~ipment (e.g., a steam line or f'eedwater line break) that imparts energy sufficient to potentially damage or creates shrapnel to actually damage permanent structures, systems or components.
An electrical breaker flash that creates shrapnel and results in damage to other components beyond scorching should also be considered.
EXTORTION
-An attempt to cause an action at the site by threat of force.FIRE -Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required if" large quantities of smoke and heat are observed.
An electrical breaker f'lash that creates high temperatures for a short duration and merely localized scorching to that breaker and its coinpartinent shouild not be considered a fire.FRESHLY OFF-LOADED REACTOR CORE -The complete removal and relocation of all fuel assemblies from the reactor core and placed in the spent fuel pool. (Typical of a 'No Mode' operation during a refuel outage that allows safety system maintenance to occur and results in maximum decay heat load in the spent fuel pool system.)
Enclosure 4.8 RPIOIA/5000/O()I Definitions/Acronyms Page 2 o f 4 FUNCTIONAL
-A component is fully capable of meeting its design function.
It would be declared INOPERABLE if unable to meet Technical Specifications.
GENERAL EM'ERGENCY-Events are in process or have occurred which involve actual or imminent substantial core degradation or melting wvith potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility.
Releases can be reasonably expected to exceed EPA protective action guideline exposure levels offsite for more than the immediate site area.HOSTAGE -A person(s) held as leverage against the station to ensure demands will he met by the station.HOSTILE ACTION -An act toward an NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidates the licensee to achieve an end. This includes attack by air.land, or water using guns, explosives, PROJECTILES, vehicles or other devices used to deliver destructive force. Other acts that satisfy, the overall intent may be inacluded.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concer'ted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (e.g.. violent acts between individuals in the OWNER CONTROLLED AREA).HOSTILE FORCE -One or more individuals who are engaged in a determined assault, overtly or by' stealth and deception.
equipped with suitable weapons capable of killing, maiming or causing destruction.
IMMINENT -Mitigation actions have been ineffective, additional actions are not expected to be successful.
and trended information indicates that the event or condition will occur. Where IMMINENT time fr'ames are specified, they shall apply.INOPERABLE
-A component does not meet Technical Specifications.
The component may be f'unctional, capable of meeting its design.INABILITY TO DIRECTLY MONITOR -Operational Aid Computer data points are unavailable or gauges/panel indications are not readily available to the operator.INTRUSION
-A person(s) present in a specified area without authorization.
Discovery of a BOMB in a specified area is indication of INTRUSION into that area by a HOSTILE FORCE.ISFSI -Independent Spent Fuel Storage Installation
-Includes the components approved for loading anod storage of spent fuel assemblies.
LOSS -A component is INOPERABLE and not FUNCTIONAL.
NO MODE -Defueled.OWNER CONTROLLED AREA -Area outside the protected area fence that immiiediatelv surrounds the plant. Access to this area is generally restricted to those entering on official business.PROJECTILE
-An object directed toward a NPP that could cause concern for its continued operability.
reliability or personnel saf-ety.PROLONGED
-A duration beyond normal limits, defined as 'greater than 15 minutes" or as determined b'c the judgment of the Emergency Coordinator.
Enclosure 4.8 RP/O/A/5000O/O0 I Definitions/Acronyms Page 3 o f4 PROTECTED AREA -Typically, the site specific area which normally encompasses all control led areas within the security PROTECTED AREA fence.REACTOR COOLANT SYSTEM (RCS/NCS)
LEAKAGE -RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13.RUPTURED (As relates to Steam Generator)
-Existence of primary to secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.
SABOTAGE -Deliberate damage, misalignment, or misoperation of plant equipment with the intent to render the equipment unavailable.
Equipment found tampered with or damaged due to malicious m ischie f nay not meet the definition of SABOTAGE until this determination is made by security superv ision.SECURITY CONDITION
-Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.SIGNIFICANT PLANT TRANSIENT-An unplanned event involving one or more of the f'ollowing:
J )Automatic turbine runback >25% thermal reactor power, (2) Electrical load rejection
>25% full electrical load; (3) Reactor Trip, (4) Safety Injection, (5) Thermal power oscillations
> 10%.SITE AREA EMERGENCY
-Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I) toward site personnel or equipment that couild lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public.Any releases are not expected tO exceed EPA Protective Action Guidelines to exposure levels beyond the site boundary.SITE BOUNDARY -That area, including the protected area, in which Duke Energy has the authority to control all activities, including exclusion or removal of personnel and property.SLC -Selected Licensee Commitments.
SUSTAINED
-A duration of time long enough to confirm that the CSF is valid (not momentary,).
TERMINATION
-Exiting the emergency condition.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) -The sum of external dose exposure to radioactive plume, to radionuclides deposited on the ground by the plume, and the internal exposure inhaled radionuclides deposited in the body.TOXIC GAS -A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g. chlorine l.UNCONTROLLED
-Event is not the result of planned actions by the plant staff.UNPLANNED
-An event or action is UNPLANNED if it is not the expected result of normal operations.
testing, or maintenance.
Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.
Enclosure 4.8 R Pi0/Ai5000i00O( 1 Definitions/Acronyms Page 4 oft 4 UNUSUAL EVENT- Events are in process or have occurred which indicate a potential degradation1 ofthe level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.VALID -An indication or report or condition is considered to be VALID when it is conclusively verified by: (1 ) an instrument channel check, or (2) indications on related or redundant instrumentation, or (3) by direct observation by plant personnel such that doubt related to the instrument's operability, the condition's existence or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.
VIOLENT -Force has been used in an attempt to injure site personnel or damage plant property.VISIBLE DAMAGE -Damage to equipment or structure that is readily observable without measurements.
testing, or analyses.
Damage is sufficient to cause concern regarding the continued operability or reliability of aff'ected structure, system, or component.
Example damage: deformation due to heat or impact, denting.penetration, rupture, cracking, paint blistering.
VITAL AREA -Areas within the PROTECTED AREA that house equipment important for nuclear safety.Access to a VITAL AREA is allowed only if an individual has been authorized to he in that area pe:r the security plan. Therefore, VITAL AREA is a security term.
Enclosure 4.9 RPlOli/150001001 Emergency Declaration Guidelines Page 1 of 2 THE FOLLOWING GUIDANCE IS TO BE USED BY THE EMERGENCY COORDINATOR IN ASSESS ING EMERGENCY CONDITIONS.
- Assessment, classification and declaration of any applicable emergency condition shouild be completed with 15 minutes after indication or information is available to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded.* The Emergency Coordinator shall review all applicable initiating events to ensure proper classification.
- The BASIS Document (located in Section D of the Catawba Nuclear Site Emergency Plan) is available for review if any questions arise over proper c lassification.
- Emergencies are declared for the site. If an event results in multiple emergency action levels onl a unit or different emergency action levels on each unit, then the emergency' declaration shall be based on the higher classification.
Information relating to the unit with the lesser classification wvill be noted as additional information on the Emergency Notification Form (EN F).* If an event occurs, and a lower or higher plant operating mode is reached before the classification can be made, the classification shall be based on the mode that existed ait thle time the event occurred.*The fission product barrier matrix is applicable only to those events that occur at (Mode 1-4) hot shutdown or higher. An event that is recognized at cold shutdown or lower (Mode 5 or 6) shall not be classified using the fission product barrier matrix. Reference would be made to the other enclosures that provide emergency action levels for specific events (e.g. severe weather, fire.security).
- If a transient event should occur, the following guidance is provided.I. Some emergency action levels specify that a condition exist for a specific duration prior to declaration.
- a. For these EALs, the classification is made when the Emergency Coordinator assessment concludes that the specified duration is exceeded or will be exceeded (i.e. condition cannot be reasonably corrected before the duration elapses)..
whichever is sooner.b. If a plant condition exceeding EAL criteria is corrected before thle specified duration time is exceeded, the event is NOT classified by that EAL. Lower Severity EALs, if any, shall be reviewed for possible applicability' in these cases.
Enclosure 4.9 R P!O/A/5000/O0 I Emergency Declaration Guidelines Page 2 of 2 2. If" a plant condition exceeding EAL criteria is not recognized at the time of" occurrence.
but is identified well after the condition has occurred (e.g. as a result of routine log or record review) and the condition no longer exists, an emergency shall NOT be declared.Reporting under IOCFR5O.72 may be required.
Such a condition could occur, f'or example, ifra f'ollow-up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.3. If an emergency classification is warranted, but the plant condition is corrected prior to declaration and notification, the Emergency Coordinator must consider thle potential that the initiating condition (e.g. Failure of Reactor Protection System or earthquake) may have caused plant damage that warrants augmenting the on-shif't personnel via activation of the Emergency Response Organization.
The following action shall be taken: a. For UNUSUAL EVENTS, the condition shall be declared and notifications made. The event may be terminated in the same notification or in a follow-up notificati on.b. For ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY.
the event shall be declared and the emergency response organization activated.
DETERMINATION OF "EVENT TIME" (TIME THE 15 MINUTE CLOCK STARTS)I.Event time is the time at which indications become available that an EAL has been exceeded.2. Event time is the time the 15 minutes clock starts for classification.
- 3. The event classification time shall be entered on the emergency notification form.MOMVENTARY ENTRY INTO A HIGHER CLASSIFICATION If', while in an emergency classification, the specified EALs of a higher classification are met momentarily, and in the judgment of the Emergency Coordinator are not likely to recur, the entry into the higher classification must be acknowledged.
Acknowledgment is perf'ormled as follows: If" this condition occurs prior to the initial notification to the emergency response organization and off site agencies, the initial message should note that the site is currently in the lower classification, but had momentarily met the criteria f'or thne higher classification.
It should also be noted that plant conditions have improved and stabilized to the point that the criteria f-or the higher classification are not expected to be repeated.
0 Enclosure 4.10 RPIOIAiSO001001I Page 1 of Radiation M'onitor Readings fo~r Enclosure 4.3 Note: These values are not inatended to apply to anticipated temporary increases due to planned events (e.g. incore detector movement, radwaste container movemenat, depleted resin transfers, etc.).Detector Elevation Column Identifier Unusual Event Alert SnR/hr mR/hr 1EMF-lI 522' FF, 57 Auxiliary Building Corridor 500 5000 I1ENMF-3 543' GG, 55 Unit I Charging Pump Area 100 5000 IEMF-4 543' GG. 59 Unit 2 Charging Pump Area 100 5000 I ENIF-7 560' NN, 55 Unit I Auxiliary Building Corridor 1500 5000 1 EMF-8 560' >NN, 59 Unit 2 Auxiliary Building Corridor 500 5000 I EMF-9 577' LL. 55 Unit 1 Aux. Building Filter Hatch 100 5000 I EME- 10 577' LL. 58 Unit 2 Aux. Building Filter H~atch 100 5000 I EMvF-22 594' KK, 53 Containment Purge Filter Area 100 5000 2EMF-9 594' KK, 61 Containment Purge Filter Area 100 5000 Page I of 5 PROCEDURE SRP/0/A/5000/001 RP/0/A/5000/002 RP/0/A/5000/003 RP/0/A/5000/004 RP/0/A/5 000/005 RP/0/A/5000/06 RP/O/A!5000/006 RP/0/A!5000/006
.RP/0/A/5000/006 RP/0/A/5 000/007 RP/0/A!5000/08 RP/0/B/5000/008 RP/0/A/5000/009 RP/0/A15000/010 RP/0/A/5000/1 1 RP/0/B/5000/12 RP/0/B/5000/0 13 RP/0/B/5000/14 RP/0/A/5000/015
.RP/0/B/5000i016 RP/0/B/5000/17 A B C DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I TITLE Classification of Emergency (Rev. 036)Notification of Unusual Event (Rev. 045)Alert (Rev. 050)Site Area Emergency (Rev. 053)General Emergency (Rev. 054)Deleted Notifications to States and Counties from the Control Room (Rev. 033)Notifications to States and Counties from the Technical Support Center (Rev. 037)Deleted Natural Disaster and Earthquake (Rev. 043)Deleted Hazardous Materials Spill Response (Rev. 043)Collision/Explosion (Rev. 012) , Conducting a Site Assembly or Preparing the Site for an Evacuation (Rev. 027)Deleted Deleted NRC Notification Requirements (Rev. 038)Deleted Core Damage Assessment (Rev. 007)Deleted Deleted February 18, 2016 Page 2 of 5 PROCEDURE RP/0/A/5000/01 8 RP/0/B/5000/019 RP/0/A/5000/020 RP/0/A/5000/021 RP/0/B/5000/022 RP/0/B/5000/023 RP/0/A/5000/024 RP/O/B/5000/025 RP/0/A/5000/026 RP/0/B/5000/028 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I TITLE Emergency Worker Dose Extension (Rev. 002)Deleted Technical Support Center (TSC) Activation Procedure (Rev. 038)Deleted Deleted Deleted OSC Activation Procedure (Rev. 034)Recovery and Reentry Procedure (Rev. 003)Site Response to Security Events (Rev. 017)Nuclear Communications Emergency Response Plan (Rev. 006)February 18, 2016 Page 3 of 5 PROCEDURE HP/0/B/1 000/006 HP/0/B/1009/001 HP/0/B/1009/003 HP/0/B/1009/004 HP/0/B/1 009/005 HP/0/B/1009/006 HP/0/B/1009/007 HP/0/B/1009/008 HP/0/B/1 009/009 HP/0/B/1009/014 H-P/0/B/1009/016 HP/0/B/1009/017 FIP/1/B/1009/017 FIP/2/B/1009/017 l-P/0/B/1009/018 JHP/0/B/1009/019 IIP/0/B/1 009/024 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II TITLE Emergency Equipment Functional Check and Inventory (Rev. 060)Deleted Radiation Protection Primary to Secondary Leakage Program (Rev. 012)Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 031)Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 01 8)Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 009)In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 020)Contamination Control of Injured Individuals (Rev. 016)Deleted Radiation Protection Actions Following an Uncontrolled Release of Liquid Radioactive Material (Rev. 009)Deleted Deleted Deleted Deleted Deleted Emergency Radio System Operation, Maintenance and Communication (Rev. 010)Implementing Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 002)February 18, 2016 Page 4 of5 PROCEDURE HP/0/B/1009/025 HP/0/B/1009/026 SH/0/B/2005/00 1 SI-/0/B/2005/002 SH/0/B/2005/003 OP/0/A/6200/021 SR/0/B/2000/001 S R/0/A/2000/00 1 SR/0/B/2000/002 SR/0/A/2000/003 SR/0/B/2000/003 SR/0/A/2000/004 SR/0/B/2000/004 AP/O/A/5500/046 AD-EP-ALL-0202 AD-EP-ALL-0203 AD-EP-ALL-0204 AD-EP-ALL-03 01 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II TITLE Deleted Superseded Superseded Deleted Deleted Deleted Deleted Standard Procedure for Corporate Communications Response to the Emergency Operations Facility (Applies to Catawba/McGuire/Oconee) (Rev. 002)Deleted Activation of the Emergency Operations Facility (Rev. 008)Deleted Notifications to States and Counties from the Emergency Operations Facility for Catawba, McGuire and Oconee (Rev. 006)Deleted Hostile Aircraft Activity (Rev. 008)Emergency Response Offsite Dose Assessment (Rev. 001)Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev 000 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev 000)Activation of the Emergency Response Organization Notification System (ERONS) (Rev. 000)February 18, 2016 Page 5 or" 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE AD-EP-ALL-0406 Duke Energy Management Network (DEMNET) (Rev 001)February 18, 2016 Form 703-1. Procedure Process Record (PPR)(RIO0-14)Duke Energy PROCEDURE PROCESS RECORD (I) ID No. RPI0/AI5000I001 Revision No. 036 PREPARATION (2) Station Catawba Nuclear Station (3) Procedure Title Classification of Emergency Classiicatio ofEerec (4) Prepared By* (j. 4,/i4/la, Date (5) Requires NSD 228 Applicability Determination?
[] Yes (New procedure or revision with major changes) -Attach NSD 228 documentation E] No (Revision with minor changes)(6) Reviewed By* I * -( (Kl)Cross-Disciplinary Review (QR) (KI) NA Reactivity Mgmt. Review By* .(QR) NA Ii Mgmt. Involvement Review By* .fOps. Mgr.) NA .I (7) Additional Reviews Reviewed By*g Reviewed By* 11)ate kate PERFORMANCE (Compare with control copy every 14 calendar days while work is being performed.)
(9) Compared wVith Control Copy* _______________________________________late_______
Compared with Control Copy* lDate______
Compared with Control Copy* ___________________________a__________DIte______
(10) Date(s) Performed Work Order Number (WO#) _____________________________________________
COMPLETION (It ) Procedure Completion Verification:
0] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
0] Yes 0] NA Required enclosures attached?[] Yes 0] NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked?0] Yes 0] NA Calibrated Test Equipment, if used, checked out/in and referenced to this procedure?
0] Yes 0] NA Procedure requirements met?Verified By* _____________
(12) Procedure Completion Approved'*
(13) Remarks (Attach additional pages, if necessary,)
- Printed Namte aitd Signature l)ate _______lDate I
~ENERGY!, Facility Code : CN Applicable Facilities
- Document Number: RP/0/A/5000/001 Document Revision Number : 036 Document EC Number : Change Reason : Document Title : Classification of Emergency Hare, Mandy B.EP manager designee review 2/1 7/20 16 Notes :
10 CFR 50.54(q) Screening Evaluation Form Screening and Evaluation Number
- Applicable Sites BNP El EREG #:2001696 CNS [PPR AR# 2001696 CR3 El HNP El MNS El 5AD #:02001728 ONS El RNP El GO El Document and Revision Classification of Emergency RP/0/A/5000/001 Revision 036 [Part I. Description of Activity Being Reviewed (event or action, or series of actions that may restult in a change to the emergency plan or affect the imnplementation of the emergency plan): Activity
Description:
RP/O/A15000/O F (Classification of Emergency)
Rev.036 1) Enclosure 4.1 -page 1 of 5 -Corrected Fusion PDF error during rendition.
No content wats chatnged.There was an error during the rendition to a PDF that caused a portion of the page to be cut off.
References:
PRR02001.696 Part II. Activity Previously Reviewed?Is this activity Fully bounded by an NRC approved 10 CFR 50.90 submittal or Alert and Notification System Design Report?If yes, identify bounding source document number or approval reference and ensure the basis for concluding the source document fully bounds the proposed change is documented below: Justification:
Yes El No El]10 CFR 50.54(q)Effectiveness Evaluation is not required.
Enter justification below and complete Attachment 4, Part V.Continue to Attachment 4 ,10 CFR 50.54(q)Screening Evaluation Form, Part Ill Bounding document attached (optional)
Part Ill. Editorial Change Yes IIX No El Is this activity an editorial or typographical change only, such as formatting, 10 CFR 50.54(q) Continue to paragraph numbering, spelling, or punctuation that does not change intent? Effectiveness Attachment 4, Evaluation is not Part IV and Justification:
required.
Enter address non justification and editorial Corrected Fusion PDF error during rendition.
No content was changed. There was an complete changes error during the rendition to a PDF that caused a portion of the page to be cut off. The Attachment 4, procedure is required to be revised to correct these issues. Part V & VI.Part IV. Emergency Planning Element and Function Screen (Reference Attachment 1, Considerations for Addressing Screening Criteria)Does this activity involve any of the following, including program elements from NUREG-0654/FEMA REP-i Section I1? If answer is yes, then check box.1 10 CFR 50.47(b)(1)
Assignment of Responsibility (Organization Control)la Responsibility for emergency response is assigned.
El 1 b The response organization has the staff to respond and to augment staff on a continuing basis [(24-7 staffing) in accordance with the emergency plan.V 2 10 CFR 50.47(b) (2) Onsite Emergency Organization___
2a Process ensures that on-shift emergency response responsibilities are staffed and assigned El 2b The process for timely augmentation of on-shift staff is established and maintained.
J[]3 10 CFR 50.47(b) (3) Emergency Response Support and Resources
__3a Arrangements for requesting and using off site assistance have been made. El 3b State and local staff can be accommodated at the EOF in accordance with the emergency plan. El__(NA for CR3)4 10 CFR 50.47(b) (4) Emergency Classification System 4a A standard scheme of emergency classification and action levels is in use. El (Requires final approval of Screen and Evaluation by EP CFAM.)5 10 CFR 50.47(b) (5) Notification Methods and Procedures 5a Procedures for notification of State and local governmental agencies are capable of initiating notification El of the declared emergency within 15 minutes (30 minutes for CR3) after declaration of an emergency and providing follow-up notification.
Sb Administrative and physical means have been established for alerting and providing prompt instructions El to the public within the plume exposure pathway. (NA for CR3)___Sc The public ANS meets the design requirements of FEMA-REP-1 0, Guide for Evaluation of Alert and El Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. (NA for CR3)___Part IV. Emergency Planning Element and Function Screen (cont.)6 10 CFR 50.47(b)(6)
Emergency Communications 6a Systems are established for prompt communication among principal emergency response El organizations.
6b Systems are established for prompt communication to emergency response personnel.
El 7 10 CFR 50.47(b)(7)
Public Education and Information 7a Emergency preparedness information is made available to the public on a periodic basis within the []plume exposure pathway emergency planning zone (EPZ). (NA for CR3)7b Coordinated dissemination of public information during emergencies is established.
Emergency Facilities and Equipment___
8a Adequate facilities are maintained to support emergency response.
[8b Adequate equipment is maintained to support emergency response.
____9 10 CFR 50.47(b)(9)
Accident Assessment 9a Methods, systems, and equipment for assessment of radioactive releases are in use. J ]10 10 CFR 50.47(b)(10)
Protective Response 10a A range of public PARs is available for implementation during emergencies. (NA for CR3) []10Ob Evacuation time estimates for the population located in the plume exposure pathway EPZ are available EJ to support the formulation of PARs and have been provided to State and local governmental authorities. (NA for CR3)10Oc A range of protective actions is available for plant emergency workers during emergencies, including EJ those for hostile action events.10Od KI is available for implementation as a protective action recommendation in those jurisdictions that 0]chose to provide KI to the public.11 10 CFR 50.47(b)(1
- 1) Radiological Exposure Control 11 la The resources for controlling radiological exposures for emergency workers are established.
0 [12 10 CFR 50.47(b)(12)
Medical and Public Health Support 12a Arrangements are made for medical services for contaminated, injured individuals.
[]13 10 CFR 50.47(b)(13)
Recovery Planning and Post-accident Operations 1 3a Plans for recovery and reentry are developed:
[]14 10 CFR 50.47(b)(14)
Drills and Exercises 14a A drill and exercise program (including radiological, medical, health physics and other program areas) 0]is established.
14b Drills, exercises, and training evolutions that provide performance opportunities to develop, maintain, []and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses.
14c Identified weaknesses are corrected.
[]15 10 CFR 50.47(b)(15)
Emergency Response Training iaTraining is provided to emergency responders.
0 Part IV. Emergency Planning Element and Function Screen (cont.)16 10 CFR 50.47(b)(16)
Emergency Plan Maintenance 1 6a Responsibility for emergency plan development and review is established.
0]16b Planners responsible for emergency plan development and maintenance are properly trained. 0]
PART IV. Conclusion If no Part IV criteria are checked, a 10 CFR 50.54(q) Effectiveness Evaluation is not required, then complete Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part V. Go to Attachment 4, 10 CFR 50.54(q)Screening Evaluation Form, Part VI for instructions describing the NRC required 30 day submittal.
The changes included in this revision include editorial changes only. This revision corrected Fusion PDF error during rendition.
No content was changed. There was an error during the rendition to a PDF that caused a portion of the page be cut off. No planning standards were impacted because there were no content changes to the procedure.
If any Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV criteria are checked, then complete Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part V and perform a 10 CFR 50.54(q)Effectiveness Evaluation.
Shaded block requires final approval of Screen and Evaluation by EP OFAM.
Part V. Signatures; Preparer Name (Print): Tina Kuhr Preparer Signature:
Date:2/1 6/16 Reviewer Name (Print): Mandy Hare Re jwer Signatur Date:2/17/16 Approver (EP Manager Name (Print): Tom Ariow App.prove&., Approver (CFAuM, as required)
Name (Print) Approver Signature:
z -7.) ae Part VI. NRC Emergency Plan and Implementing Procedure Submittal Actions Create two EREG General Assignments.
- One for EP to provide the 10 CFR 50.54(q) summary of the analysis, or the completed 10 CFR 50.54(q), to Licensing.
- One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.___
QA RECORD UF Duke Energy Company Procedure No.CATAWBA NUCLEAR STATION RP/O/.-1sooo/oo1 Classification of Emergency Revision No.036 Rcference Use PERFORaMANCE This Procedure was printed on 2/17/2016 3:25 PM from the electronic library as: (ISSUED) -PDF Format Compare with Control Copy every 14 calendar days while work is being performed.
Compared with Control Copy
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- Irinted NVane and Signature Date(s) Pertbrmed Work Order/Task Number (WOn)COMPLETION O [ Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA-. as approprkite'?
E] Yes [] NA Required attachments included?[] Yes 0] NA Charts, graphs, data sheets. etc. attached, dated, identified, and marked?[] Yes [] NA Calibrated Test Equipment, if used, checked outhin and referenced to this procedure'?
[] Yes [] NA Procedure requirements met?Verified Dy Date* Printed N~ame and SVignamtre Procedure Completion Approved Date* Printed Name and Signature Remarks (attach additional pages, i/necessary)
IMPORTANT:
Do NOT mark on barcodes.
I'rmted Date. '2/"17.1o" Pirocedure No. 'RF'/OU./5i/S IIIO/l I' RP/0/A/5000/00 I Page 2 o f 4 Classification of Emergency 1. Symptoms 1.1. Notification of Unusual Event I.1 .1 Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs 1.2 Alert 1 .2.1I Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION.1.2.2 Any releases are expected to be limited to small fractions of the EPA Protective Act ion Guideline exposure levels.1.3 Site Area Emergency 1.3.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for protection of the public.1.3.2 Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.1.4 General Emergency I1.4. 1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.1.4.2 Releases can be reasonably expectedto exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
RP/0/A/5000/001 Page 3 of'4 2. Immediate Actions 2.1 IF performing this procedure due to security-related event(s) considered to be a CREDIBLE THREAT or HOSTILE ACTION, perform the Ibllowing.
- F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/t026.
Site Response to Security Events, as soon as possible for scripted message.* Perform accelerated notification to the NRC within 1 5 minutes of the occurrence or" the event.2.2 Assessment, classification and declaration of any applicable emergency condition shouild be completed within 15 minutes after the availability of indications or inf'ormation to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed)2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.2.4 IF the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix) OR refer to EAL wvallboards.
__2.5 IF a General Emergency is NOT declared in Step 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to EA\L wallboards to determine if the event is applicable to one the categories shown.2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated.
2.7 Document the declaration time. __________
2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERO Notification Job Aid.2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportuinity that will not intert'ere with the performance of the crew or the flow of the Emergency Procedure.
- 2. 1 0 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel.
RP/O/A/5000/00 I Page 4 o t"4 2.1!1 Implement the applicable Emergency Response Procedure (RP) f~or that classification and continue with subsequent steps of this procedure.
Notification of Unusual Event RP/0/A/5000/002 Alert RP/0/A/5000/003 Site Area Emergency RP/0/A/5000/004 General Emergency RP/0/A/5000/005
- 3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the initiating Conditions of Enclosures 4.1I through 4.7 OR EAL wallboards.
___3.2 Refer to Enclosure 4.8 (Definitions/Acronyms)
OR 4.9 (Emergency Declaration Guidelines), as needed.3.3 Ref'er to Section D of the Catawba Emergency Plan for basis inf'ormation about the Emergency Classification System as needed.3.4 Ref'er to RP/0/A/5000/020, "TSC Activation Procedure" 1 concern ingz the use of" l0CFR50.54(x).
If the TSC is activated, contact the TSC Emergency Coordinator (EC)for concurrence when using IOCFR5O.54(x).
- 4. Enclosures
- 4. 1 Fission Product Barrier Matrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radio logical Effluent 4.4 Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.10 Radiation Monitor Reading for Enclosure 4.3 EALs 0 0 Enclosure 4.1 RPIOIA!5000/001I Page 1 of'5 Fission lProduct Barrier Matrix 1.Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all barriers.
Classify according to the table below.Note 1 : An event (or multiple events) could occur which results in the conclusion that exceeding thle Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT LOSS situation, use judgment and classify' as if the thresholds are exceeded.Note 2: When determining Fission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions for the Fuel Clad Barrier loss or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.Note 3: Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the stait-up of engineered safeguards equipment.
A CSF condition is satisfied when the alamred state is valid and sustained.
The STA should be consulted to affirm that a CSF has been validated prior to the CSF being used as a basis to classify an emergency.
Example: If ECA-0.0, Loss of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF should be used as the basis to classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-O.O.IC Unusual Event IC Alert IC Site Area Emergency IC General Emergency LossOR Ptenial ossLoss OR Potential Loss Potential Loss of of 41 1of Both Loss of 4.1nU.aI4.1ent.
Nuclear Coolant System Nuclear Coolant System AND 4. G otimn ___All Three Barriers Fuel Clad Loss AND Loss OR P~otential Loss Potential Loss CombinationsLosf
- 4. U2 Loss ofl .A2o .S2o oh41.. Any Two Barriers AN D 4IU Containment 4... f4lS2o oh4102 Potential Loss of the Fuel Clad Nuclear Coolant System ANDThr Fuel CladThr Potentia Losssofof Containment ANI)4. Conaimet.3t 4.1.S.3 Loss Ok Potential Loss of I .A.~ Loss OR Potential LossAnOtrBrie Aof OteyBare Any Other Barrier 0l Enclosure 4.1 Fission Product Barrier Matrix RPlO I AI50 00/001 Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based onl a "potential loss" or a "loss." "Not Applicable" is included in thle table as a place holder only, and has no point value assigned.Barrier Points (1-5) Potential Loss (X) Loss (X) Total Points Classification Containmenat 1 3 1 -3 Unusual Event NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Emergency Total Points
-13 General Emergency 1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of"5.2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description.
- 3. For each barrier, write the highest single point value applicable for the barrier in the "Points" column and mark the appropriate "loss" column.4. Add the points in the "'Points" column and record the sum as "Total Points".5. Determine the classification level based on thle number of "Total Points".6. In thle table on page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1 I.A. I for Loss of Nuclear Coolant S,,ystem) that best fits thle loss of barrier descriptions.
- 7. Using the nillmlbcr (e.g. 4.1 IA. I), select the prelprinted notification forml- O1_.R a blank notification forml and complete the required in formaat ion lfr Emer'gency Coordinator approval and transmittal.
Enclosure 4.1 RP/0/A/5000/001I Fission Product Barrier Matrix Page 3 of 5 4.1.C CONTAINMENTl BARRIER POTENTIAL LOSS -(I1 Point)LOSS -(3 Points)4.I.N NCS BAR POTENTIAL LOSS -(4 Points).RIER LOSS -(5 Points)4.I.1 FUEL CLA[POTENTIAL LOSS -(4 Points)SBARRIER LOSS -(5 Points)II1$ -M -Ill !ill .... ...... ...Em im 1. Critical Safcty Function Status* Containment-RED
- Not applicable
- Core cooling-RED Path is indicated for > 15 minutes 2. Containment Conditions
- 1. Critical Safety Function Status 1. Critical Safety Function Status* NCS Integrity-Red
- Heat Sink-Red 2. NCS Leak Rate* UnisoLable leak exceeding the capacity of one charging pump innormal charging mode with letdown isolated.* Not applicable
- Core Cooling-Orange* Core Cooling-Red
- Heat Sink-Red 2. Primary' Coolant Activity Level[ I* Containment Pressure > 15 PSIG*H2 concentration
>9%* Containment pressure greater than 3 psig with less than trne full train of N S and a VX-CARF operating atecr ac!uation.
- Rapid unexplained decrease in containment pressure following initial increase* Containment pressure or sump level response not consistent with LOCA conditions.
NOT'E: Refer to Emergency Plan.Sect. D. 4, .C1 last paragraph for inability to ma~intain nollnmal anUlulltS pfressture.
- GREATER THAN available makeup capacity as indicated by a loss of NCS subcooling.
- Not applicable
- Coolant Activity* GREATER THAN 300 p~i/cc Dose Equivalent Iodine (DEl) 1-131 CONTINtJEI)
()TNJI N NtEI (-'ONTIN I)ED ('ONTINIIED Enclosure 4.1 RPIOIAIS001001 Page 4 of 5 Fission Product Barrier Matrix 4.!.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4. I.F FUEL CLAI) BARRIER POTENTIAL LOSS -( I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)lil r... ... .. .I I I I 3. Containment lsolation Valves Status After Containment Isolationi Actuation 3. SC Tube Rupt ire ItI BIB tlhtl tIi tiIUl J RTU lllfl B lURB .Not applicable
.Containment isolation is incomplete and a direct release path lioin containment exists to the environment Pri mary-to-Secondary leak rate exceeds the capacity of one charging pump in the normal charging mode with letdown isolated.* Indication that a SG is Ruptured and has a Non-Isolable secondary line fault* Indication that a SG is ruptured and a prolonged release of contaminated secondary coolant is occurring from the affected SG to the environmnent Not applicable
- Containment radiation monitor 53 A or 53 B Reading at time since Shutdown.0-0.5 hrs > 99 R/hr 0.5-2 hrs > 43 R/hr 2-4 hrs > 31 R/hr 4-8 hrs > 22 R/hr>8 hrs > 13 R/hr 4. Emereencv Coordinator/EOF Director 4. SC Secondary Side Release With Primary-to-Secondary Leakagle* Not applicable
.Release of secondary side to thle environmlent with primary to secondary leakage GREATE-R TH-AN Tech Spec:illowabh" 4. Containment Radiationi Nlonjiorinl!
- Not applicable Not applicable Judg~enent
- Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coord inator/EOF Director indicates LOSS or POTENTIAL LOSS of the fuel clad harrier.EN I ('()NTINI:EI)
CONININU .D Enclosure 4.1 RP/O/A/5000/001I Fission Product Barrier Matrix Page 5 of 5 4.1.C CONTAINMENT BARRIER 4.I.N NCS BARRIER POTENTIAL LOSS -(I Point)LOSS -(3 Points)POTENTIAL LOSS -(4 Points)LOSS -(5 Points)4.I.F FUEL CLA[POTENTIAL LOSS -(4 Points))BARRIER LOSS -(5 Points)..... .... .....I ' -'III I 5. Significant Radioactive Inventory, In Containment
- 5. Emergency Coordinator/EOF Director Judgement Containment Rad.Monitor EMF53A or 53B Reading at time since shutdown: o -0.5 hr > 390 R/hr 0.5 -2 hr > 170 R/hr 2-4 hr > 125 k/hr 4 -8 hr > 90Rk/hr>8 hr > 53kUhr* Not applicable
- Any condition, including inability to monitor the batTier that in the opinion of the Emergency Coordinator
/EOF Director indicates LOSS or POTENTIAL LOSS of the NCS barrier.END 6. Emergency Coordinator
/EOF Director Judgment Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coordinator/EDF Director indicates LOSS or POTENTIAL LOSS of the containment barrier.END Enclosure 4.2 RPIOIAI5000/001I Page 1 of 2 System Malfunctions ALERT UNU3SUAL EVENT SITE AREA EMERGENCY GENERAL. EMERGENCY 4.2.U.1 Inability to Reach Required Shutdown Within Technical Specification Limits.OPERATING MODE: 1, 2,3, 4 4.2.U.!-l Plant is not brought to required operating mode within Technical Specifications LCO Action Statement Time.4.2.U.2 Unplanned Loss of Most or All Safety System Annunciation or Indication in.the Control Room for Greater Thain 15 Minutes.OPERATING MODE: 1, 2, 3, 4 4.2.Ui.2-I The following conditions exist: Unplanned loss of most (>50%/)annunciators associated with safety systems for greater than 1 5 minutes.AND In the opinion of the Operations Shif~t Manager/Emergency Coordinator/EOF Director, the loss of the annunciators or indicators requires additional persoimcl (beyond normal shif~t COlnpl~iment) to sale~ly operate the unit, 4.2.A.1 Unplanned Loss of Most or All Safety System Annunciation or Indication in Control Room With Either (1) a Significant Transient in Progress, or (2)Compensatory Non-Alarming Indicators Unavailable.
OPERATING MODE: 1, 2, 3, 4 4.2.A. 1-1 The following conditions exist: Unplanned loss of most (>50%)annunciators associated with safety systems for greater than 1 5 minutes.4.2.S.1 Inability to Monitor a Significant Transient in Progress.END OPERATING MODE: 1, 2, 3, 4 4.2.S.1-I The following conditions exist: Loss of most (>50%)Annunciators associated with safety systems.AND AND In the opinion of the Operations Shift Manager/Emergency Coordinator/EOF Director, the loss of the annunciators or indicators requires additional personnel (beyond normal shift compliment) to safely operate the unit.AN I EITHiER of the following:
- A SIGNIFICANT PLANT TRANSIENT is in progress* Loss of the GAG.ENDI A SIGNIFICANT PLANT TRANSIENT is in progress.AND Loss of the GAG.AND Inability to provide manual monitoring of any of' the following Critical Safety* subcriticality
- core cooling* heat sink* containment.
('ON'IINI)
ENEI)I- N !)
Enclosure 4.2 RP/0/A/5000/001 System Malfunictions Page 2 of 2 U.NUSUAL EVENT ALERT SITE AREA EMERGENCY GENEiRAL EMERGENCY 4.2.11.3 Fuel Clad Degradatdion.
OPERATING MODE: 1, 2, 3, 4, 5 4.2.1_1.3-I Dose Equivalent 1-131 greater than the Technical Specifications allowable limit.4.2.U1.4 Reactor C~oolant System (N CS)Leakage.OPERATING MODE: 1,2,3,4 4.2.U1.4-1 Unidentified leakage > 10 gpm.4.2.U1.4-2 Pressure boundary leakage > 10 gpmn.4.2.U.4-3 Identified leakage>Z 25 gpm 4.2.UJ.5 Unplannecd Loss of All Onsite or Offsite Commiuniicationts.
OPERATING MIODE: ALL 4.2.1_1.5-I Loss of all onsite communications capability (internal phone system. PA system. onsite radio system) affecting the ability to perlbrm routine operations.
4.2.1I.5-2 Loss of all offsite communications capabi Iity (Duke Emergency Mianagemenit Network {DI-rv.NI
'li.NR(" ETS lines. of'fsite radio system, commercial phone system) affecting!
the ability to communicate wvith ol'lsite authl ori ties.ENI) 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 1 o1'5 GENERtAI.
EMER(GENCTY IJNIJSI IAl, E:VENTI ALERT'SlITE AREA EM EIRGENC\: 4.3.ti.1 Any lUnplanned Release of(Gaseous or -t.3.A.1 Liquid Radioactivity to the Environment that Exceeds Two Times the SLC Limits fo~r 60 Minutes or Longer.Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environnment that Exceeds 200 Times the SLC limits for 15 Mlinutes or Longer.OPERA ITIN(; MODE: ALL OPERATING MODE.ALL 4t.3.UAt-t A vatid '[rip 2 alarm on radiation monitor EMIF-49L or EMF-57 for > 60 minutes or oil! likely continue obr > 601 minutes which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure H- P/0/B3/1009/0 14.4.3.1U.1-2 A valid indication on radiation monitor EMF- 36L of_> 3.00E+04 cpm lbr > 60 minutes or will likely' continue tbr _> 60 minutes. which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD)-EI'-ALL-0202.4.3.A.l-1 A valid indication on radiation monitor EMF- 49L or EMF-57 of_ 1.2E+05 cpm lbr > 15 mfinutes or will likely continue for >15 mtnutes, which indicates that the releatse may have exceeded the initiating condition and indicates the need to assess the release with procedure ItP/0/B/ 1009/014.(Continued) 4.3.S.1 Boundary Dose Resulting fronm an Actual or Imminent Release of Radioactivity Exceeds 100l mirem TED)E or 500 anrem CDE Adult Thyroid for the Aetual or Projected Duration of the Release.OPERATING NMODE: ALL 4.3.S.1-1 A valid indication on radiation monitor EMF-36L of">_ 2.7E+06 cpm sustained for > 15 minutes.4.3.S.1-2 Dose assessment temn~calculations indicate dose consequences greater than 100 mrem T1EDE or 500 turen CDE Adult Thyroid at the site boundary.{(Continued) 4.3.G.1 Boundary l)ose Resulting from an Actual or Inmminent Release of Radioactivity that Exceeds 1000 wrenm ITEDE or 5000 mrema CDE Adult Thyroid fo~r the Actual or Projected Duration of the Release.OPERATING MIODE: ALL 4.3.G.t-1 A valid indication on radiation monitor EMF-36H]of">_ 8.3 E+03 cpm sustained tbr > I5 tminutes.4.3.G.1-2 Dose assessment team calculations indicate dose consequences greater than 1000 mrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.I Continued) t( 'ontinued)
Enclosure 4.3 Abnormal Rad Levels/Radiologicai Effluent RP/O/A/5000/001 Page 2 ot'5 GENERAL EMERGENCY UNulSUAL EVENT ALERT SITE AREA EMERGENCY 4.3.U.1-3 Gaseous effluent being released exceeds two times SLC 16.11-6 lbr >60 minutes as determined by RP procedure.
4.3.U.I-4 Liquid effluent being released exceeds two times SLC 16.11-I for>60 minutes as determined by RP procedure.
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this time period, declaration must be made based on the valid radiation monitor reading.(Continuemd) 4.3.A.i-2 A valid indication on radiation monitor EMF- 36L of>_5.4E+05 cpm for > 15 minutes or will likely continue for >15 minutes, which indicates that the release may have exceeded the initiating condition and indicates the need to assess the release with procedure AD-EP-ALL-0202.
4.3.A.1-3 Gaseous effluent being released exceeds 200 times the level of SLC 16.11-6 for> 15 minutes as detennined by RP procedure.
4.3.A.1-4 Liquid effluent being released exceeds 200 times the level of SLC 16.11-1 for> I5 minutes as determined by RP~procedure.
Note: If the monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be comnpleted within this time period, declaration mstls be made based on the valid rad iat ion monitor reading.
4.3.S.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 100 mrem TEDE or 500 mrem CDE Adult Thyroid at the site bounmdarmy.
Note 1: These EMAF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available.
Note 2: If dose assessment team calculations cannot be completed in I5 minu~tes.then walid monitor reading~should be used lbr emergency classification.
ENDI 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 1000 inrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.Note I : These EMF readings are calculated based on average annual meteorology, site boundary dose rate, and design unit vent flow rate.Calculations by the dose assessment team use actual meteorology, release duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available.
Note 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid monitor reading should be used for emergency classification.
E NI 0 Enclosure 4.3 Abnormal Rad Levels/Radiological Effluent RP/0/A/5000/001I Page 3 of 5.GENERAL EMERGENCY UNUSIJAL EVENT ALERT SITE AREA EM'ERGENCV:
4.3.U.2 Unexpected increase iin Plant Radiation or Airborne Concentration.
OPERATING MODE: ALL 4.3.UJ.2-1I Indication of uncontrolled water level decrease of greater than 6_inches in the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.4.3.11.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pooi and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.4.3.11.2-3 Unplanned valid area EMF reading increases by a factor of 1 ,000 over normal levels as shown in Enclosure 4.10.EN I)4.3.A.2 Miajor Damage to Irradiated Fuel or Loss of Water Level that tlas or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor V'essel.SDoes not apply to spent fuel in dry cask storage. Refer to EPLAN Section D basis document OPERATING MIODE: ALL 4.3.A.2-1 An unplanned valid trip II alarm on any of the following radiation monitors: Spent Fuel Building Refueling Bridge 1IEMF- 15 2EMF-4 Spent Fuel Pool Ventilation 1EM F-42 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Mode Only)l EMF-17 2EMF-2 Containment Noble Gas Monitor (Applies to Mode 6 andMode Only)I EM F-39 21N'lF-39 C(oniliiniud)
Enclosure 4.3 RPIOIAI5 000/001 Abnormal Rad Levels/Radiological Eftluent Page 4 of 5 UNUSUAL EVENTI ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any irradiated fiuel will become uncovered.
4.3.A.2-3 NC system wide range level <95% after initiation ofhNC system make-up.AN.__D_Anly irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.4.3.A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.ANDI Any irradiated fuel assembly not capable of being fully lowered inb the spent fuel pool racks or transfer canal fuel transfer system basket.(Colnlinlued)
Enclosure 4.3 RP/0/A/5000/00 Abnormial Rad Levels/Radiological Effluent Page 5 of 5 IUNtJSUAI EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases inl Radiation Levels Within the Facility That Inmpedes Operation of Systems Required to Mlaintain Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.3.A.3-1 V'alid reading on IEMF-12 greater than 1 5 mremihr in the Control Room.4.3.A.3-2 Valid indication of radiation levels greater than 15 nmremihr in the Central Alarm Station (_CAS) or Secondary Alarm Station (SAS).4.3.A.3-3
\"alid radiation monitor reading exceeds the levels shown in Enclosure 4.1l0.ENDI Enclosure 4.4 Loss of Shutdown Functions UNUSUAL EVENT ALERT ENDp~4.4.A. 1 Failure of Reactor Protection System liastrunientation to Comiplete or Iuitiate anl Automatic Reactor Trip Once a Reactor Protection System Setpoint ilas Been Exceeded and Manual Trip Was Successful.
OPERATING MODE: 1, 2,3 SITE AREA EMERGENCY 4.4.S.1 Failure of Reactor P~rotection System Instrunientation to Complete or Initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoiut 1-as Beeni Exceeded and Manual Trip Was NOT Successful.
OPERATING MODE: I RP/0/A/5000/001I Page 1 of 3 GENERAl. EMERGENCY 4.4.G.1 Failure of the Reactor Protection System to Complete an Autonmatic Trip and Manual Trip Was NOT Successful and There is Indication of an Extreme Challenge to the Ability to Cool the Core.OPERATING MODE: I 4.4.G.l-l The following conditions exist: Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND Manual reactor trip from the control room was not successful in reducing reactor* power to less than 5% and decreasing.
AND)4.4.A.1-1 The following conditions exist: 4.4.S.1-1 The following conditions exist: Valid reactor trip signal received or required and automatic reactor trip wa~s not successful.
AND Manual reactor trip from the control room is successful and reactor power is less than 5%and decreasing.(Continued)
Valid reactor trip signal received or required and automatic reactor trip was not successful.
AND Manual reactor trip from the control room was miot successful in reducing reactor power to less than 5% and decreasing.(Continued)
E ITIE I lof the followingt conditions exist:* Core Cooling CSF-RED* Heat Sink CSF-RED.ENDI Enclosu re 4.4 RP/0/A/5000/001I Loss of Shutdown Functions P~age 2 of 3[UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.4.A.2 Inability to Miaintain Plant in Cold Shutdown.OPERATING MODE: 5, 6 4.4.A.2-I Total loss of ND and/or RN and/or KC.AND One of the following:
- Inability to maintain reactor coolant temnperature below 200 0 F* Uncontrolled reactor coolant temperature rise to> 180 0 F.END 4.4.S.2 Complete Loss of Function Needed to Achieve or Mlaintain Hot Shutdown.OPERATING MODE: 1,2, 3, 4 4.4.S.2-I Subcriticality CSF-RED.4.4.S.2-2 Heat Sink CSF-RED.4.4.S.3 Loss of Water Level inl the Reactor Vessel That I-las or Will__ Uncover Fuel inl the Reactor Vessel.OPERATING MODE: 5, 6 4.4.S.3-I Failure of heat sink causes loss of cold shutdown conditions.
ANI)Lower range Reactor Vessel Level Indication System (RVLIS) decreasing after initiation of NC system mnakeup.4.4.S.3-2 Failu~e of heat sink causes loss of cold shutdown conditions:
AND Reactor Coolant (NC) system mid or wide range level less than 1 1% and decr-easing after initiation of NC system makeup.{Conitinued) 0 0 Enclosure 4.4 RP/0/A/5000/001I Page 3 of 3 Loss of Shutdown Functions IJNISIAIi.
EVENT'ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.4.S,3-3 Failure of heat sink causes loss of cold shutdown conditions.
AND Either train ultrasonic level indication less than 7.25% and decreasing after initiation of NC system makeup.END 0 Enclosure 4.5 Loss of Powver JNI.JSUIAL EVENT ALERT 4.5.UL.1 Loss of All Offsite Power to Essential Busses for Greater Than 15 Minutes.OP~ERATING MODE: I, 2, 3, 4 4.5.U.1-1 The following conditions exist: Loss of offsite power to essential buses ETA and ETB for greater than 15 minutes.ANDI Both emergency diesel generators are supplying power to their respective essential busses.(Continued) 4.5.A.1 Loss of All Offsite Power and Loss of All Onsite AC Power to Essential Busses During Cold Shutdown Or Refueling Mode.OPERATING MODE: 5, 6, No Mode 4.5.A.I-1 Loss of'all ot/hite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB.AND Failure to restore power to at least one essential bus within 15 minutes.SITE AREA EMIERGENCY 4.5.S.1 Loss of All Offsite Power and Loss of All Onsite AC Power to Essential Busses.OPERATING MODE: 1, 2, 3, 4 4.5.S.1-1 Loss of all off'site and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB.AND Failure to restore power to at least one essential bus within 1 5 minutes.(Continued)
RP/O/A/5000/001I Page 1 of 2 GENERAL EMERGENCY 4.5.G.1 Prolonged Loss of All (Offsite and Onsite) AC P~ower.OPERATING NMODE: 1,2,3,4 4.5.G.1-1 Prolonged loss of all offsite and onsite AC power as indicated by: Loss of power on essential buses ETA and ETB for greater than 15 minutes.AND Standby Shutdown Facility (SSF) fails to supply NC pump seal injection OR CA supply to Steam Generators.
AND (Continued)(Continnued) 0 Enclosure 4.5 Loss of Power RP/0/A/5000/001I Page 2 o1"2 UNUSUAL EVENT ALERT OPERATING MOI)E: 5, 6, No Mode'4.5.U.I1-2 The 1Ibllowinlg conditions exist: Loss of off'site power to essential buses ETA and ETB for greater than I5 minutes.AN_._D_One emergency diesel generator is supplying power to its respective essential bus.4.5.U.2 Unplanned Loss or Required DC Power IDuring Cold Shutdown or Refueling Mode for Greater than 15 Minutes.OPERATING; MODE: 5, 6 4S.5.LJ.2-1I The following conditions exist: 4.5.A.2 AC power to essential busses reduced to a sinlgle power source for greater than 15 nuinutes such that an additional single failure could result in station blackout.OPERATING MODE: 1, 2,3, 4 4.5.A.2-I The following condition exists: AC power capability has been degraded to one essential bus powered from a single power source for > 15 maii. due to the loss of all but one of: SITE AREA EMERGENCY 4.5.S.2 Loss of'All Vital I)C Power.OPERATING MODE: 1, 2, 3, 4 4.5.S.2-1 The following conditions exist: Uniplanned loss of both unait related busses: EBA and EBD both <112 VDC, and EBB and EBC both <109 VDC.AND Failure to restore power to at least one required DC bus within 15 minutes from the time of loss.GENERAL EMERGENCY At least one of the following conditions exist:* Restoration of at least one essential bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is NOT likely* Indication of'continuing degradation of core cooling based on Fission Product Barrier monitoring.
END END SATA ATC DiG A SATB ATD D/G B l nlflauned loss of bo0th unit related busses: IBA and LBD both <112 \"L)C. and I'BB 13 ad F B&( both -109 V DC'.ANxi___IF iue to testor ie power to at Ileast one requi jred I )(' bus within 15 inivmutcs from ihc tinme of loss.E NI)END 0 0 Enclosure 4.6 Fire/Explosion and Security Events RPIOIAI50001001I Page 1 of 3 G EN ERAL EM ERG ENCYEVENT ALERT SITE AREA EMERGENCY 4.6.LJ.1 Fire Within Protected Area Boundai'y NOT Extinguished Within 15 Minutes of Detection OR Explosion Within the JProtected Area Boundary.OPERATING MODE: ALL 4.6.UJ.l-1 Fire in any of the following areas NOT extinguishned within 15 minutes of control room notification or verification of a control room fire alarm.* Reactor Building* Auxiliary Building* Diesel Generator Rooms* Control Room* RN Pumphouse* SSF* CAS* SAS* Doghouses* FW\ST" Turbine Bu~ilding* Service lBuilding* Monitor Tank Buildine* ISI:SI* tin it 1'2 ransfIbriner Yard ((01 'olin ed 4.6.A.1 Fire or Explosion Affecting thne Operability of Plant Safety Systems Required to Establish or Maintain Safe Shutdown.OiPERATING MODE: 1, 2, 3, 4, 5, 6 4.6.A.1-1 The following conditions exist: (Non-security events)Fire or explosion in any of the following areas:* Reactor Building* Auxiliary Building* Diesel Generator Rooms*Control Room* RN Pumphouse* SSF* CAS* SAS* FWST" Doghouses (Applies in Mode I, 2, 3, 4 only).4.6.S.1 110OSTILE ACTION within the PROTECTED AREA OPERAUTING MODE: ALL 4.6.5.1-I A IIOSTILE ACTION is occu~rring or has occurred withfin the IPROTECTED AREA as reported by thne CNS Security Shif't Supervision END 4.6.G.! ltOSTILE ACTION Resulting in Loss of Physical Control of the Facility.OPERATING MODE: ALL 4.6.G.I-1 A hlOSTILE ACTION has occurred such that plant personnel arc unable to operate equipment required to maintain safety functions.
4.6.G.1-2 A HOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT fuel damage is likely for a FRESHtLY OFF-LOADED REACTOR CORE in pool.END)ANDI Onle of the liollow~ing:
- Affected safety system Iparaumcter indications show degraded perlirmnance l(-'oniiinucd) 0 Enclosure 4.6 Fire/Explosion and Security Events RP!OIAI5 000/001I Page 2 of 3 GENERAL EMERGENCY UINUISUAL EVENT ALERT SITE AREA EMERGENCY 4.6. U.i1-2 Report by plant personnel of an unanticipated explosion within protected area boundary resulting in visible damage to permanent structure or equipment or a loaded cask inl the ISFSI.4.6.[I.2 Confirmed SECURITY CONDITION or Threat Which Indicates a Potential Degradationi in the Level of Safety of the Plant.OIPERATING MODE: All 4.6.U1.2-I A SECURITY CONDITION that does NOT involve a ItOSTILE ACTION as reported by the CNS Security Shift Supervision.
4.6.U.2-2 A credible site-specific security threat notification.
4.6.U1.2-3 A validated notificaltion frol'NRC providing inlormation ol an aircrafft threat.ENDI*Plant personnel report visible damage to permlanenlt structures or equipment within the specified area required to establish or maintain safe shutdown within the specifications.
Note: Only one train of a system needs to be affected or damaged in order to satisfy this condition.
4.6.A.2 Fire or Explosion Affecting tihe Operability of P~lant Safety Systems Required to Establish or Maintain Safe Shutdown.OPERATING MODE: No Mode 4.6.A.2-1I The following conditions exist: (Non-security events)Fire or explosion in any of the following areas:* Spent Fuel Pool* Auxiliary Building.* RN Pump houise AND One of the following:
- Spent Fuel Pool level anld/or tempeC~llratr sho~v degraded pcrlbrmance
!('on tin ued)
Enclosure 4.6 RP/0/A/5000/001 Fire/Explosion and Security Events Page 3 of 3 UJNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling~.4.6.A.3 IIOSTILE ACTION Within the OWNER CONTROLLED AREA or Airborne Attack Threat.OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift. Supervision 4.6.A.3-2 A validated notification from*NRC of airliner attack threat wiihin 30 minutes of the site.END Enclosure 4.7 Natural Disasters, Iltazards, And Other Conditions Affecting Piant Safety UNUSUAL EVENT ALERT SITE AREA EMIERGENCY 4.7.U.1 Natural and Destructive Phenomena Affectinig tihe Protected Area.
MIODE: ALL 4.7.U.l-1 Tremor felt and valid alarm on the Syscom Seismic Monitoring System (OAC C 1D225 2).4.7.U.I-2 Report by plant personnel of tor'nado striking within protected area boundary/ISFSl.
4.7.U.I-3 Vehicle crash into phlan structures or systems within protected area boundary/ISFSI.
4,7.U.1-4 Report of turbine failure resutlting inl casing penetration or damage to turbine or generator seals.4.7.1_1.1-:5 Independenlt Spent Fuel Cask tipped over or dropp~ed greater than 24 inches.4.7.11.I-6 LUncontrolled flooding in the ISFSI area.4.7.1 .1-7 "l'rnado generated missiles(s) impactin-~
the ISFS I.S('ioninuitd) 4.7.A. 1 Natural and Destructive Phenomena Affecting the Plant Vital Area.OPERATING MODE: ALL 4.7.A.1-1 Valid "~OBE Exceeded" Alarm on I AD-4.B/8 4.7.A.i-2 Tornado or high winds: Tornado striking plant structures within the vital a rea:* Reactor Building* Auxiliary Building* FWST* Diesel Generator Rooms* Control Roorn* RN Pumphouse* SSF* Doghouses* CAS* SAS 4.7.S.1 Conitrol Room Evacuatiou Iltas Been hnitiated and Plant Control Cannot Be Established.
OPERATING MODE: ALL 4.7.S.1-1 The followving conditions exist: Control Room evacuation has been initiated per API/1 (2)/A/5500/0 17 AND Control of the plant cannot be established from the ASP or the SSF within 15 minutes.4.7.S.2 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of Site Area Emergenicy.
OPERATING MODE: ALL 4.7.S.2-1 Other conditions exist which in the J udgemient of the Emergency Coordinator/EOF-Director indicate actual or likely ma~jor lhuilures ofplant functions needed lbr protection of the public.I"N I)RP/0/A/5000/001I P~age I of 4 GENERAL EMIERGENCY 4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator/EOF Director Warrant Declaration of General Emergency.
OPERATING MODE: ALL 4.7.G.1-1 Other conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate: (I) actual or imminent substantial core degradation with potential for loss of containment OR (2) potential for uncontrolled radionuclide releases.
These releases can reasonably be expected to exceed Environmental Protection Agency Protective Action Guideline levels outside the site boundary.L-NI)OR sustained winds >_ 74 mph lbr-" I5 minutes.t(oinllliuiedl 0 Enclosure 4.7 Natural Disasters, Hazards, Andi Other Conditions Affe~cting Plant Safety RP/0/A/5 000/001 Page 2 of 4 GENERAL EMERGENCY UNUSUAL EVENT ALERT SITE AREA EMERGENCY 4.7.11.2 Release of toxic or Fininniable Gases Deemed Detrimental to Safe Operation of the FPlant.O IPERATING MODE: ALL 4.7.U1.2-I Report or detection of toxic or flammable gases that could enter within the site boundary in amounts that can affect safe operation of the phlan.4.7.U1.2-2 Report by Local, County or State Officials for potential evacuation of site personnel based on offsite event.4.7.U.3 Other Conditions Existing Which in the Judgemtent of the Emergency Coordinator/EOF Dir-ector Warrant Declaraition of art Unusual Event.OIPERATING MODE: ALL 4.7.11.3-1 Other conditions exist which in thle juidg~eicnt of, the Emergency Coord ilnatoriLOF-lirector indicate a potei ti al dcegradation of the level of satet o~t' " theU p3tlant.4.7.A.1-3 Visible structural damage caused by cither:* Vehicle crashes OR* Turbine failure generated missiles, OR* Other catastrophic events on any of the following plant structures:
- Reactor Building* Auxiliary Building* FW'ST* Diesel Generator Rooms* Control Room* RN Pump I-ouse* SSF* Doghouses* CAS* SAS V NI
- 0 Enclosure 4.7 RP/0/A/5000/00 Natural Disasters, Hazards, And Other Conditions Affe~cting Plant Safety Page 3 o1"4 UNUSUAL EVENT ALERT SITE AREA EM1ERGENCY' GENERAL EMERGENCY 4.7.A.2 Release of Toxic or" Flanmnable Gases Within a Facility Structure Which Jeopardizes Operation of Systems Required to Maintain Safe Operations or to Establish or Maintain Cold Shutdown.OPERATING MODE: ALL 4.7.A.2-1 Report or detection of toxic gases within a Facility Structure in concentrations that will be life threatenine to plant personnel.
4.7.A.2-2 Report or detection of flammable gases within a Facility Structure in concentrations that will affect the safe operation of the plant.Structures lbr the above EALs:*, Reactor Building* Auxiliary Building* Diesel Generator R~oomas* Control Room* RN lPumphouse
- SSF* CAS* SAS
- 0 Enclosure 4.7 RP/O/A/5000/O0 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 4 of 4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.3 Control Room Ev'acuatjion llas Beeni Initiated.
OPERATING MODE: ALL 4.7.A.3-1 Control Room evacuation has been initiated per API/1 (2)/A15500/0 17.4.7.A.4 Other Conditions Existing Which in the Judgemnent of the Emnergency Coordinator/EOF Director Warrant Declaration of an Alert.OPERATING MODE: ALL 4.7.A.4-1 Other conditions exist which in the Judgement of the Emergency Coordinabor/EOF Director indicate that plant safety systems may be degraded and that increased monitoring of plant functions is warranted.
ENDI Enclosure 4.8 R P/O/A/5000iOO0I Definitions/Acronyms Page I of"4 ALERT- Events are in process or have occurred which involve an actual or potential substantial degradation of the level of saf'ety of the plant or a security event that involves probable life threatening risk to sire personnel or damage to site equipment because of hostile action. Any releases are expected to he limited to small fractions of the EPA protective action guideline exposure levels.ALL (As relates to Operating Mode Applicability)
-Modes 1, 2, 3,4,5,6 and No Mode (De fueled)BOMB -Refers to an explosive device suspected of having sufficient force to damage plant systems or structures.
CARF -Conatainment Air Return Fan.CIVIL DISTURBANCE
-A group often (10) or more people violently protesting station operations or activities at the site. A civil disturbance is considered to be violent when force has been used in anl attempt to injure site personnel or damage plant property.COGNIZANT FACILITY STAFF -Any member of facility staff, who by virtue of train inJg and experience.
is qualified to assess the indications or reports fobr validity and to compare the same to the EALs in the licensee's emergency classification scheme (Does not include staff whose positions r'equire they report, rather than assess, abnormal conditions to the facility.).
CREDIBLE THREAT -A threat should be considered credible when:* Physical evidence supporting the threat exists.* Information independent (law enforcement) from the actual threat message exists that supports the threat.o A specific group or organization claims responsibility for the threat.EPA PAG -Environmental Protection Agency Protective Action Guidelines for exposure to a release of radioactive material.EMERGENCY RELEASE -Any unplanned, quantifiable radiological release to the environment during an emergency event. The release does not have to be related to a declared emergency.
EXPLOSION
-A rapid, violent unconfined combustion, or a catastrophic failure of pressurized equipmenlt (e.g., a steamline or feedwater line break) that imparts energy sufficient to potentially damage or creates shrapnel to actually damage permanent structures, systems or components.
An electrical breaker flash that creates shrapnel and results in damage to other components beyond scorching should also be considered.
EXTORTION
-An attempt to cause an action at the site by threat of force.FIRE -Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observed.
An electrical breaker flash that creates high temperatures for a short duration and merely localized scorching to that breaker and its compartment should not be considered a fire.FRESHLY OFF-LOADED REACTOR CORE -The complete removal and relocation of" all fuel assemblies fr'om the reactor core and placed in the spent ftiel pool. (Typical of a "No Mode" operation during a refuel outage that allows safety system maintenance to occur and results in maximum decay heat load in the spent fuel pool system.)
Enclosure 4.8 RP/0/AIS000/001 Definitions/Acronyms Page 2 of" 4 FUNCTIONAL
-A component is fully capable of meeting its design function.
It would be declared INOPERABLE if unable to meet Technical Specifications.
GENERAL EMERGENCY-Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility.
Releases can be reasonably expected to exceed EPA protective action guideline exposure levels offsite for more than the immediate site area.HOSTAGE -A person(s) held as leverage against the station to ensure demands will be met by the station.HOSTILE ACTION -An act toward an NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidates the licensee to achieve an end. This includes attack by air.land, or water using guns, explosives, PROJECTILES, vehicles or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on thle NPP. Non-terrorism-based EALs should be used to address such activities (e.g.. violent acts between individuals in the OWNER CONTROLLED AREA).HOSTILE FORCE -One or more individuals who are engaged in a determined assault, overtly or by stealhh and deception, equipped with suitable weapons capable of killing, maiming or causing destruction.
IMMINENT -M itigation actions have been ineffective, additional actions are not expected to be sutccessfl, and trended information indicates that the event or condition will occur. Where IMMVINENT time frames are specified, they shall apply.INOPERABLE
-A component does not meet Technical Specifications.
Thle component may be f'unctional.
capable of meeting its design.INABILITY TO DIRECTLY MONITOR -Operational Aid Computer data points are unavailable or gnu ges/panel indications are not readily available to the operator.INTRUSION
-A person(s) present in a specified area without authorization.
Discovery of a BOMB in a specified area is indication of INTRUSION into that area by a HOSTILE FORCE.ISFSI -Independent Spent Fuel Storage Installation
-Includes the components approved for loading and storage of spent fluelI assemblies.
LOSS -A component is INOPERABLE and not FUNCTIONAL.
NO MODE -Defue led.OWNER CONTROLLED AREA -Area outside the protected area fence that immediately surrcounds the plant. Access to this area is generally restricted to those entering on official business.PROJECTILE
-An object directed toward a NPP that could cause concern for its continued operability.
reliability or personnel safety.PROLONGED
-A duration beyond normal limits, defined as "greater than 15 m~inutes' or as determine~d by the judgment of the Emergency Coordinator.
Enclosure 4.8 RPi0/A/5000i00 I Definitions/Acronyms Page 3 of 4 PROTECTED AREA -Typically, the site specific area which normally encompasses all controlled areas wvithin the security PROTECTED AREA fence.REACTOR COOLANT SYSTEM (RCS/NCS)
LEAKAGE -RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13.RUPTURED (As relates to Steam Generator)
-Existence of primary to secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.
SABOTAGE -Deliberate damage, misalignment, or misoperation of plant equipment wvith the intent to render the equipment unavailable.
Equipment found tampered with or damaged due to malicious mischief may not meet the definition of SABOTAGE until this determination is made by security supervision.
SECURITY CONDITION
-Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.SIGNIFICANT PLANT TRANSIENT-An unplanned event involving one or more of the following: (I)Automatic turbine runback >25% thermal reactor power, (2) Electrical load rejection
>25% full electrical load; (3) Reactor Trip, (4) Safety Injection.
(5) Thermal power oscillations
>1 0%.SITE AREA EMERGENCY
-Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public.Any releases are not expected to exceed EPA Protective Action Guidelines to exposure levels beyond the site boundary.SITE BOUNDARY -That area, including the protected area, in which Duke Energy has the autthority to control all activities, including exclusion or removal of personnel and property.SLC -Selected Licensee Commitments.
SUSTAINED
-A duration of time long enough to confirm that the CSF is valid (not nmomentary).
TERMINATION
-Exiting the emergency condition.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) -The sum of external dose exposure to radioactive plume, to radionuclides deposited on the groutnd by the plume, and the internal exposure inhaled radionuclides deposited in the body.TOXIC GAS -A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g. chlorine).
UNCONTROLLED
-Event is not the result of planned actions by the plant staff.UNPLANNED
-An event or action is UNPLANNED if it is not the expected result of normal operations, testing, or maintenance.
Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.
Enclosure 4.8 R PIOIAI50001001 Definitions/Acronyms Page 4 of 4 UNUSUAL EVENT- Events are in process or have occurred which indicate a potential degradation of" the level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless fuirther degradation or" safety systems occurs.VALID -An indication or report or condition is considered to be VALID when it is conclusively verified by: (I) an instrument channel check, or (2) indications on related or redundant instrumentation, or (3) hy direct observation by plant personnel such that doubt related to the instrument's operability, the condition's existence or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.
VIOLENT -Force has been used in an attempt to injure site personnel or damage plant property.VISIBLE DAMAGE -Damage to equipment or structure that is readily observable without measurements, testing, or analyses.
Damage is sutfficient to cause concern regarding the continued operability or reliability of affected strutcture, system, or component.
Example damage: deformation due to heat or impact. denting, penetration, rupture, cracking, paint blistering.
VITAL AREA -Areas within the PROTECTED AREA that house equipment important for nuclear safety.Access to a VITAL AREA is allowed only if an individual has been authorized to be in that area per the secuirity plan. Therefore, VITAL AREA is a security term.
Enclosure 4.9 RPiO/A/5000/OO01 Emergency Declaration Guidelines Page I ot'2 TI-E FOLLOWING GUIDANCE IS TO BE USED BY THE EMERGENCY COORDINATOR IN ASSESSING EMERGENCY CONDITIONS.
- Assessment, classification and declaration of any applicable emergency condition should be completed with 15 minutes after indication or information is available to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded.o The Emergency Coordinator shall review all applicable initiating events to ensure proper classification.
- Thle BASIS Document (located in Section D of the Catawba Nuclear Site Emergency Plan) is available for review if any questions arise over proper classification.
- Emergencies are declared for the site. If an event results in multiple emergency action levels on a unit or different emergency action levels on each unit, then the emergency declaration shall be based on the higher classification.
Information relating to the unit with the lesser classifica'tion will be noted as additional information on the Emergency Notification Form (EN F).* If an event occurs, and a lower or higher plant operating mode is reached before the classification can be made, the classification shall be based on the mode that existed at the time the event occurred.*The fission product barrier matrix is applicable only to those events that occur at (Mode 1-4) hot shutdown or higher. An event that is recognized at cold shutdown or lower (Mode 5 or 6) shall not be classified using the fission product barrier matrix. Reference would he made to the other enclosures that provide emergency action levels for specific events (e.g. severe weather, fire.security).
- If a transient event should occur, the following guidance is provided.1.Some emergency action levels specify that a condition exist for a specific dluration prior to declaration.
- a. For these EALs, the classification is made when the Emergency Coordinator assessment concludes that the specified duration is exceeded or will be exceeded (i.e. condition cannot be reasonably corrected before the duration elapses), whichever is sooner.b. If a plant condition exceeding EAL criteria is corrected before the speci fied duration time is exceeded, the event is NOT classified by that EAL,. Lower Severity EALs, if any, shall be reviewed for possible applicability in these cases.
Enclosure 4.9 RR/O/A/5000/O01 Emergency Declaration Guidelines Pace 2 o f 2 2. If a plant condition exceeding EAL criteria is not recognized at the time of occurrence, but is identified well after the condition has occurred (e.g. as a result of routine log or record review) and the condition no longer exists, an emergency shall NOT be declared.Reporting under 10OCFR50.72 may be required.
Such a condition could occur, f'or example, ifra follow-up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.3. If an emergency classit'ication is warranted, but the plant condition is corrected prior to declaration and notification, the Emergency Coordinator must consider the potential that the initiating condition (e.g. Failure of Reactor Protection System or earthquake) may have caused plant damage that warrants augmenting the on-shift personnel via activation of the Emergency Response Organization.
Thle following action shall be taken: a. For UNUSUAL EVENTS, the condition shall be declared and notifications made. The event may be terminated in the same notification or in a f'ollow-up notification.
- b. For ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY, rhe event shall be declared and the emergency response organization activated.
DETERMINATION OF 'EVENT TIME" (TIME THE I5 MINUTE CLOCK STARTS)I. Event time is the time at which indications become available that an EAL has been exceeded.2. Event time is the time the 15 minutes clock starts for classification.
- 3. The event classification time shall be entered on thle emergency notification fbrm.MOMENTARY ENTRY INTO A HIGHER CLASSIFICATION If. while in an emergency classification, the specified EALs of a higher classification are met momentarily, and in the judgment of the Emergency Coordinator are not likely to recur, the entry into the higher classification must be acknowledged.
Acknowledgment is performed as follows: If this condition occurs prior to the initial notification to the emergen cy response organization and off site agencies, the initial message should note that the site is currently in the lower classification, but had momentarily met the criteria for the higher classification.
It should also be noted that plant conditions have improved and stabilized to the point that the criteria for the higher classification are not expected to be repeated.
./Enclosure 4.10 Radiation Monitor Readings for Enclosure 4.3 RP/O/A/5000/001I Page 1IoflI Note: These values are not intended to apply to anticipated temporary increases due to planned events (e.g. incore detector movement, radwaste container movement, depleted resin transfers, etc.).Detector Elevation Column Identifier Unusual Event Alert____________mrRlhr mnR/hr IEMF-l 522' FF, 57 Auxiliary Building Corridor 500 5000 I EMF-3 543' GG, 55 Unit 1 Charging Pump Area 100 5000 1EMF-4 543' GG, 59 Unit 2 Charging Pump Area 100 5000 IEMF-7 560' NN, 55 Unit 1 Auxiliary Building Corridor 1500 5000 1 EMF-8 560' NN, 59 Unit 2 Auxiliary' Building Corridor 500 5000 1EM~'F-9 577' LL. 55 Unit 1 Aux. Building Filter [latch 100 5000 I1EMF- 1 0 577' LL, 58 Unit 2 Aux. Building Filter Hatch 100 5000 1EMNF-22 594' KK, 53 Containment Purge Filter Area 100 5000 2EMF-9 594' KK, 61 Containment Purge Filter Area 100 5000