Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPP-1 Re Emergency Conditions & Responses & EPP-2 Re Organization & Operations During Emergencies
	ML20052B050
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/17/1982
From:	Shafer P; DAIRYLAND POWER COOPERATIVE
To:	;
Shared Package
ML20052B032	List: ML20052B031; ML20052B038; ML20052B050;
References
	PROC-820317-01, NUDOCS 8204290614
	Download: ML20052B050 (113)
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/* Page 0.2 EPP-1 LACBWR EMERGENCY PLAN PROCEDURE EMERGENCY CONDITIONS AND RESPONSE Issue Notice No. 5 Dated 3/17/82 INSTRUCTIONS Remove Old Page No. Insert New Page No. Description Of and Reason for Change Remove all pages Insert all pages of Reflect changes in Emergency of EPP-1, Issue 3. EPP-1, Issue 5. Plan, Revision 1, dated March 1982. (Total revision, hence no change lines.) O PAGE SCHEDULE No. Issue No. Issue No. Issue 0.1 5 12 5 25 5 t 0.2 5 13 5 26 5 l 1 5 14 5 27 5 2 5 15 5 3 5 16 5 4 5 17 5 l 5 5 18 5 6 5 19 5 7 5 20 5 8 5 21 5 9 5 22 5 0 10 5 23 5 11 5 24 5 This issue shall not become effective unless accompanied by a new cover sheet properly signed off in the appropriate review / approval columns.

4-a Page 1 EPP-1 Issue 5 LACBWR EMERGENCY PLAN PROCEDURE EMERGENCY CONDITIONS AND RESPONSE 1.0 PURPOSE This procedure establishes conditions which may constitute an " emergency" at LACBWR, and activates the Emergency Plan. This procedure specifies Emergency Action Levels based on initiating abnormal events causing possible abnormal plant conditions.

2.0 REFERENCES

2.1 LACBWR Emergency Plan, Revision 1, March, 1982. 2.2 NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in support of Nuclear Power Plants," November, 1980. 2.3 10CFR50, Appendix E, " Emergency Planning and Preparedness (} for Production and Utilization Facilities," June 8, 1981. 2.4 Emergency Plan Procedure - EPP-2, " Organization and Operations During Emergencies." 3.0 PROCEDURE 3.1 Any plant condition or environmental condition which has the potential of increased risk to the health and safety-of the public shall be reviewed with Section 4.0 of this procedure. If abnormal indications of events require activation ~of the Emergency Plan, the onsite and offsite Emergency Response Organizations will be activated as specified in EPP-2 for the appropriate emergency classification. 3.? Pour separate classifications of emergency conditions have been established which are based upon the potential severity and required emergency response actions. These four classes are: 3.2.1 Unusual Event 3.2.2 Alert l 3.2.3 Site Area Emergency 3.2.4 General Emergency O l WP33

Page 2-EPP-1 Issue 5 () 4.0 EMERGENCY ACTION LEVELS The following tables list possible emergency conditions and their classified emergency action levels. The Shift Supervisor, with the assistance of the STA, will determine the abnormal event type, cross reference it with possible indications of possible plant conditions and determine the Emergency Action Level. He will then evoke EPP-2 for the specified level of emergency response. The Emergency Control Director must remain cognizant of conditions listed in these tables which may require escalation or de-escalation to a different emergency action level. If conditions overlap, the ECD will utilice the higher Emergency Action Level. (These possible indications for EAL's are not necessarily environmentally qualified.) 4.1 Outline of Table 4.1 Possible Conditions Emergency Action (Event Type) Level Page(s) 4.1.1 Minor and Major Primary Unusual Event 3 Coolant Leakage Alert 3 (Potential LOCA) Site Area Emergency. 4 General Emergency 4,5 ) 4.1.2 Main Steam Line Break Alert 6 Outside Containment Site Area Emergency 6 4.1.3 Radiological Effluent Unusual Event 6,7 Releases (10CFR20) Alert 6,7 Site Area Emergency 8 General Emergency 9 4.1.4 Fuel Damage Unusual Event 10 Alert 11 Site Area Emergency 11,12 General Emergency 12 4.1.5 Safety System Unusual Event 13,14,15 Alert 14,17 Site Area Emergency 13,17 General Emergency 17,18 4.1.6 Electrical Systems Unusual Event 16 Alert 16 Site Area Emergency 16 4.1.7 Natural Occurrences Unusual Event, Alert, Site Area & General Emergency 18,19,20 O 4.1.8 Other Hazards, Unusual Event, Alert, Plant Conditions Site Area & General Emergency 21-27 WP33

O O O TABLE 4.1 EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY Minor 6000 Gallon Retention Tank 1A or Reactor Primary System Coolant leak X Primary IB Level (Hi) Annunciator E12-3 rate greater than either the Coolant Reactor Building Sump Level (Hi) unidentified (1 gpm) or identified Leak Annunciator C14-1 Tech Spec limits (4 gpm), but less Containment Building Air Exhaust than 50 gpm. Gaseous Rad (Hi) Annunciator C7-1 Containment Building Air Exhaust Partic. Rad (Hi) Annunciator C7 2 Area Monitors Radiation (Hi) Annunciator C7-4 4 i l Major ECCS Pumps 1A/1B Runriing Reactor Coolant System leak rate X P rimary Annunciator D6-3 equal to or greater than Core Spray Coolant Reactor Water level (Lo) capacity of 50 gpm. Leak Annunciator Cl--2 (Potential General Atomics Containment Building LOCA) High Range Area Radiation Monitors Reach 10 R/hr Tracer Lab Area Radiation Monitor No. 7 and No 8 reach 10K mR/hr (Indications of near 100% loss of n primary coolant without fuel damage) m Reactor Water Level (Lo) 7 Annunciator D2-2 7 Reactor Level Safety Channels 1, 2, or 3. Reactor Pressure Safety y Channels 1 or 2. e Reactor Level Recorders y 5ii WP33

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY Major ECCS Pumps IA/1B Running LOCA greater than the make-up X l Primary Annunciator D6-3 capability of HPCS. Coolant Reactor Water Level (Lo) Leak Annunciator Cl-2 (Potential Reactor Water Level (Lo) LOCA) Annunciator D2-2 Containment Pressure greater than 5 psig. General Atomic's Containment High Range Area Radiation Monitor are 3 to 104 R/hr. Reading 10 Reactor Pressure Safety Channel 1 or 2. Reactor Level Safety Channels 1, 2, 3 or wide range H O level. 2 Reactor Level Recorders l

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Reactor Water Level (Lo) LOCA, No Indicated Reactor Level X I Annunciator Cl-2 Reactor Water Level (Lo) Annunciator U2-2 Containment Pressure Increasing n All Reactor Level Indicators g i Down Scale Reactor Level Recorders Down Scale 7 Alternate Core Spray System Lo Flow y Annunciator E15-3 un ECCS Pumps 1A/1B Running ce Annunciator Clears 1" t WP33

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY Major Emergency Core Spray Flow (Lo) LOCA, with failure of ECCS to X Prima ry Annunciator E14-1 perform, leading to core Coolant Alternate Core Spray System Lo Flow degradation or melt in minutes or I Leak Annunciator E15_3 hours. Loss of containment (Potential Alternate Core Spray Valve Control integrity may be imminent within LOCA) Switches Off-Auto Annunciator E15-4 20 hours. 1 General Atomics Containment High Range Radiation Monitors are reading 105 - 106 R/hr Containment Pressure greater than 48 psig and increasing. Multiple indicators. Loss of 2 or 3 fission product X barriers with a potential loss of l 3rd barrier. Visual observation Main Steam Line Break, inside X Containment Pressure Indicator containment without MSIV isolation. Main Steam Flow Indicator Reactor Pressure Indicators Containment Building Air m Activity Monitors Increasing g Iw = H g M M C O m 2 d2 O tn WP33 l l

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY Main Steam Area Monitor Radiation (Hi) Main steam line break with MSIV X Line Break Annunciator C7-4 malfunction causing leakage. Outside . Main Steam Isolation Valve Containment Not Full Open Annunciator D3-1 MSIV Position Indicators Main Steam Flow Indicators Reactor Pressure Indicators Decreasing Visual Observation Reactor Pressure Indicators Main steam line break without X Decreasing isolation. Visual Observation MSIV Position Indicator ARM Reading Hign, Annunciator C7-4. Air Activity Monitor High and Increasing Environ-Stack Gaseous Radiation (Hi) Airborne effluents greater than X mental Annunciator C5-1 Technical Specification limits. l Releases Stack Particulate Radiation (Hi) m l (Related to Annunciator C5-2 l l 10 CFR 20) Stack I_131 (Hi) SPING-4 Containment Building Air l Exhaust Gaseous Rad (Hi) Annunciator C7_1 5 l Containment Building Air Exhaust E I Particulate Rad (Hi) m Annunciator C7-2 ? MW tQm m WP33

i TABLE 4.1 (Continued)

EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY I i Environ-Stack Gaseous Radiation (Hi) Airborne effluent greater than 10 X I mental Annunciator C5-1 times Technical Specification Releases Stack Particulate Radiation (Hi) instantaneous limits (an I (Related to Annunciator C5-2 instantaneous rate which, if 10 CFR 20) Containment Building Air Exhaust - continued over 2 hours, would (Continued) Gaseous Rad (Hi) result in about 1 mr/hr at the Site Annunciator C7-1 Boundary under average Containment Building Air Exhaust meteorologcial conditions). Particulate Rad (Hi) Annunciator C7-2 j Area Monitor Radiation (Hi) Annunciator C7-4 i j Liquid Waste and Service Water Liquid Discharge Effluents greater X Radiation (hi) C6_3 than 10 CFR 20 Appendix B limits. Turbine Condenser Cooling Water Monitor Hi C8-3 Liquid Discharge Effluents greater X Saaple Analysis than 10 times the 10 CFR 20 i Appendix B limits. I i H (G i . m w i i e* i i 4 l l WP33

0 0 ( O el G TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY X Envi ron-Stack Gaseous Radiation (Hi) Stack gas effluents greater than mental Annunciator CS-1 0.02 pci/cc Hoble Gases (Whole Body) or Releases Stack Particulate Radiation (Hi) 2.00 x 10 5 pci/cc (14.0 pci/10 min) (Related to Annunciator CS-2 Iodine 131 (Infant Thyroid) for 1/2 EPA Pags) Containment Building Air Exhaust hour are detected. Gasecus Rad (Hi) Annunciator C7-1 Containment Building Air Exhaust -or Particulate Rad (Hi) C7-2 SPING-4 Hi Alarm Dose rates are projected at one mile down Channel 0101 Beta Particulate range under adverse meteorlogical condition Channel 0102 Alpha Particulate greater than 50 mrem /hr whole body for Channel 0103 Iodine-131 1/2 hour or 250 mrem /hr thyroid for Channel 0105 Low Range NG 1/2 hour with winds toward Genoa, WI. or These dose ratH are actual measured in the environment. or EPA PAGs are p Hjected to be exceeded outside the site boundary under adverse meteorology. 3 ____________________________________________________________________________________________________L________.._________ 4 Stack Gaseous Radiation (Hi) Airborne effluents greater than X Annunciator CS-1 0.2 pci/cc Noble Gases (Whole Body) or to Stack Particulate Radiation (Hi) 2.0 x 10-4 pci/cc (140 pCi/10 minutes) i I Annunciator C5-2 Iodine 131 (Infant Thyroid) for 2 minutes Containment Building Air Exhaust are detected. Gaseous Rad (Hi) Annunciator C7-1 g j Containment Building Air Exhaust or Particulate Rad (Hi) C7-2 i c ____________________________________________________________________________________________________h________..__ SPING-4 Hi Hi Alann Dose rates are projected at one mile j yi Channel 0103 I_131m down range under adverse meteorology Channel 0105 Low Range NG greater than 500 mrem /hr whole body or i SPING-4 Alert Alarm 2500 mrem /hr thyroid for 2 minutes, with j Channel 0107 Mid Range NG winds toward Genoa, WI. a3 WP33

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY Environ _ or mental These dose ratis are actual Releases measured in the environs. (Related to EPA PAGs) Stack Gaseous Radiation (Hi) EPA PAGs are projected to be exceeded (Continued) Annunciator C5-1 outside the site boundary under adverse 3 Stack Particulate Radiation (Hi) meteotorlogy. Annunciator C5-2 Containment Building Air Exhaust Stack gaseous effluent greater than X Gaseous Rad (Hi) 0.4 pci/cc Noble Gases (Whole Body) or Annunciator C7-1 4.00 x 10-4 pci/cc (280 pCi/10 minutes) Containment Building Air Exhaust Iodine 131 (Infant Thyroid). Particulate Rad (Hi) C7-2 or Dose rates greater than 1 Rem /hr whole SPING-4 Hi Hi Alarm body or 5 Rem /hr thyroid are projected Channel 0101 B Particulate (based on other plant para.neters) at 1.0 Channel 0103 I_131 mile 10wnrange under actual meteorological Channel 0105 Low Range NG cond' cions with wind toward Genoa, WI. SPING-4 Hi Alarm or Channel 0107 Mid Range NG These dose rates are measured in the environs, or predicted for the environs under actual meteoroglocial conditions. Stack Gaseous Radiation (H1) Other plant conditions exist, from whatever X Annunciator C5-1 source, that make release of large amounts of m Stack Particulate Radiation (Hi) radioactivity in a short time period possible. Annunciator C5-2 4 Containment Building Air Exhaust Gaseous Rad (Hi) Annunciator C7-1 sm Containment Building Air Exhaust Particulate Rad (Hi) C7-2 2m SPING-4 Hi Hi Alarm jn Channel 0101 B Particulate Channel 0103 I-131 y c Channel 0105 Low Range NG Channel 0107 Mid Range NG SPING-4 Hi Alarm - Channel 0109 High Range NG WP33

l o o o j TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL 4 IUNUSUALj SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS I EVENT, ALERT EMERGENCY EMERGENCY' i l Degraded Radioactive Offgas emmission rate Reactor coolant activity greater X Fuel measured at 150 cubic foot holdup than Technical Specification Integri ty tank 1100.ci/ day (.2 uci/gm of dose equivalent I-131). SPING-4 Noble Gas specific activity i l is greater than 4.0 x.10-4 pci/cc SPING-4 I-131 activity.at 4 0.28 pci/10 minutes (Approximately 4.0 x 10-7 pci/cc) 4-Reactor Coolant Chemistry sample for activity and Isopic Analyses. Air Ejector Off-Gas Monitor Annunciator C6-1 Stack Gaseous Radiation (Hi) Annunciator C5-1 l Stack Particulate Radiation (Hi) Annunciator C5-2 Ag Zeolite l I-131 Stack Sample from SPING-4 or Sample System. l t i en E, 4 i f = i g i g1 m. f

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O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL .UNUSU L SITE GENERAL A EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS ' EVENT ALERT EMERGENCY EMERGENCY l Degraded Radioactive Off-Gas Emmission Rate Reactor Coolant activity greater X Fuel measured at the 150 cubic foot than 15 pci/gm of dose equivalent 4 Integri ty hold-up tank greater than I-131. (Continued) 21,600 ci/ day SPING-4 Noble Gas Specific Activity l l 1s greater than 8.0 x 10-3 pci/cc or 3.0 x 102 Beq-Mev/cc Reactor Coolant Chemistry Sample (Isotopic and activity) SPING-4 I-131 at 6.0 pci/10 minutes i (Approximately 8.5 x 10 6 pci/cc) i Air Ejector Off-Gas Monitor Annunciator C6-1 i Stack Gaseous Radiation (Hi) Annunciator C5-1 Stack Particulate Radiation (Hi) Annunciator C5-2 Ag Zeolite I-131 SPING-4 or System Sample. SPING-4 Noble Gas Specific Activity Degraded core (1%) with possible loss X is 1.5 x 106 Beg-Mev/cc (40 pci/cc) of coolable geometry. General Atomics Containment High 5 Radiation Monitor reads 103 _ 104 R/hr Reactor Coolant Activity and y Isotopic Analysis H Emergency Core Spray Flow (Lo) Annunciator E14-1 Alternate Core Spray System Lo Flow lj. l Annunciator E15-3 1 Ag Zeolite l 1-131 SPING-4 or Sample System m (NG marinelle or gas bomb) j m U WP33

~ O O O ~- TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL l SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS IEVENT ALERT' EMERGENCY. EMERGENCY I Deg raded General Atomic Containment High Degraded core (10%) with possible _X 1 Fuel Radiation Monitors reads 104_ loss of coolable geometry. I Integri ty 105 R/hr (Continued) SPING-4 Noble Gas Specific Activity I 7 Beq-Mev/cc is greater than 1.5 x 10 (400 pci/cc) Reactor Coolant Chemistry Sample (Isotopic + Activity) Emergency Core Spray Flow (Lo) Annunciator E14-1 i Alternate Core Spray System to Flow Annunciator E15-3 Ag Zeolite I-131 SPING-4 or Sample System Sample (NG marinelli or gas bomb) i General Atomic Containment High Degraded Core (100%) with possible X l Range Radiation Monitors are loss of coolable geometry. reading 105 _ 106 R/Hr. i Reactor Coolant Chemistry Sample Emergency Core Spray Flow (Lo) Annunciator E14-1 Alternate Core Spray System to Flow m Annunciator E15-3 i SPING_4 Noble Gas Specific Activity 1.5 x 108 Beg-MeV/cc (Approximately 4000 pci/cc) g m Ag Zeolite I-131 SPING-4 or Sample System Sample l 8 (NG marinelli or gas bomb) ? l '8 ~ WP33

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL GENERAL UNUSUAL SITE EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY System / Reactor Pressure Indicators Lift of a Primary Relief Valve. X Equipment Primary Relief Valve Indicating (Coolant Pressure greater than Failure or Lights 1390psig). Malfunction Low Set Reactor Safety Valve Open (General) Annunciator B6-1 Reactor Pressure Indicators Stuck open relief valve. X Relief Valve Indicators Low Set Reactor Safety Valve Open B6-1 Open B6-2 hi set reactor safety valve. Fire Header Water Pressure (Lo) Unanticipated loss of fire X Annunciator B8-4 suppression water system (unable to maintain header pressure). Scram condition existing with all Complete loss of any function needed X 29 control rods not full in, for plant hot shutdown. mmmi H H Turbine Trip Turbine rotating component failure X m causing rapid plant shutdown. E O U1 = W Q G H W WP33

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL ' UNUSUAL' SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY System / Turbine Trip or loud noise. Turbine failure causing casing X Equipment penetration and the generating Failure or of missiles. Malfunction (General) (Continued) i System / MSIV Position Indicators MSIV failure to close, after steam X Equipment Steam Line Flow Indicators pressure decreases to 900 psig. Failure or Malfunction (Loss of Safety System) Emergency Core Spray Flow (Lo) Unanticipated loss of ECCS. X Annunciator E14-1 Alternate Core Spray System Lo Flow Annunciator E15-3 Emergency Diesel Generator Trouble Unanticipated loss of Emergency X M Annunciator A8-2 Diesel Generator, when required Diesel Generator 1B Trouble to be operable. Annunciator F2 4 sm i M C s O l un = m 4 O H b WP33

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY System / Diesel Building 125-VDC Bus Unanticipated loss of Diesel X Equipment Ground or lo Voltage Building DC power supply. Failure or Annunciator F2-6 Mal functi on (Loss of Safety System) (Continued) Fire Header Water Pressure (Lo) Loss of fire protection system X Annunciator B8_4. functions requiring shutdown by Technical Specifications. Surveillance Test Unanticipated loss of ESWSS, X when required to be operable. System / Airlocks fail Loss of containment integrity X Equipment Surveillance Test during operation such that the Failure or Technical Specifications require Malfunction Reactor Shutdown. m (Loss of y Contain-w ment Integri ty) g en in C O U1 = LQ \\' w U1 WP33

TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY System / Lights blink Loss of offsite power X Equipment 2400V Bus 1A or 18 Voltage Low o r'_ Failure or D7-2 or D7-3 Loss of all onsite AC power. Malfunction Emergency Diesel AC Generator (Loss of Running A8-2 Power) Diesel Generator 1B Auto Start F3-4 Breaker Position Indicators i Diesel Generator 1B Breaker Trip F4-4 Emergency Diesel Generator Trouble A8-2 and Reactor MCC 1A Voltage Low D7-1 Loss of offsite power and X Turbine MCC 1A Voltage Low D7-4 Loss of all onsite power. Total loss of AC Power, X restoration not possible within 15 minutes 2400 V Bus IA or IB Loss of all onsite DC Power, X DC Control Voltage Low A6-3 restoration from control room l 480V Swg 1A or 1B not possible. DC Control Voltage Low A6-4 480 V ESS Bus DC Control I Voltage Low A5-4 Reactor Plant Battery Charger Loss of vital DC power; X m Failure A9-1 restoration not possible Generator Plant Battery Charger within 15 minutes. ie Failure A9-2 Diesel Building 125 VDC Bus g Ground or low voltage F2-6 g c i m MW Ch WP33

O O o TABLE 4.1 ~ ' (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE CCNERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY System / CRD Position Indication Failure of Safety System to X Equipment Nuclear Instrumentation initiate and complete a l Indications reactor shutdown. I Mal function Steam Flow Indication (Safety System Failure) Multiple Indications Complete loss of any function X needed for plant cold shutdown. Shutdown occurs with loss of X ability to achiese cold shutdown, loss of containment integrity and core degradation or melt in about 10 hours. ______________________________________________________________________________________4-----_- _ _ _ _.._________...________ CRD Position Indication Transient requiring operation of X Nuclear Instrumentation shutdown systems with failure to Indications scram (continued power generation, Steam Flow Indication but no core damage immediately m Reactor Pressure evident). @i Reactor Level Indicator ,~ m Scram condition existing with Complete loss of any function X E S all 29 control rods not full in, needed for plant Hot Shutdown. tn .O___________4P_______________e N d2 O w Q WP33

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL l EVEftT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY- ) System / CRD' Position Transient (e.g., loss of offsite power) X Equipment Nuclear Instrumentation Indications plus failure of required core shutdown Malfunction Reactor Water Level systems (e.g., scram). Could lead to (Safety FC Pump Indications core melt in several hours with System Containment Building Pressure. containment failure likely. More severe j Failure) consequences if pump trip does not function. (ATWS/FCP) i i, i Natu ral Personnel Observation Any earthquake felt in-plant. X Occurrences Severe earthquake felt in-plant X with sufficient magnitude for suspected structure or equipment damage. i Severe earthquake felt in-plant with X plant not in cold shutdown, with sufficient magnitude to cause damage to vital equipment. td Personnel Observation Very severe earthquake felt in-plant X y Containment Pressure Indicator resulting in loss of ECCS and loss of Lo ECCS flow Annunciator E14-1 containment integrity. I" a Lo ECS flow Annunciator E15-3 g m M g m-U1 mm d3m N 00 WP33

j l TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL juNUSUAL SITE GENERAL j EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS ! EVENT ALERT EMERGENCY EMERGENCY Natural Visual Observation Mississippi River level greater [ X l Occurrences Lock & Dam #8 Report than fif ty year flood level. I t Mississippi River level at X 639' grade level. Mississippi River level greater than X 100 year flood level and/or loss of flood protection for safety related l? 1 l structures with plant not in cold shutdown. i Level Indication Mississippi River level at or below X HPSW Pump Suction. Mississippi River level below HPSW X pump suction with plant not in } cold shutdown. t trj l \\ w HWm C Q U1 = A 43 Q H

TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL ! UNUSUAL i SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS i EVENT ALERTiEMERGENCY EMERGENCY i I Natu ral Windspeed. meters Sustained winds greater than X Occurrences NOAA eather Report 140 mph. j j W i Sustained winds greater than i X design levels with plant not in i cold shutdown (greater than i' 140 mph). I t Visual Observation " Tornado Warning" advisory for X NAWAS the site or tornado onsite. Public Radio Security Lock & Dam 8 Personnel Dispatcher Tornado strikes plant buildings. X i } Tornado damages safety related L X structures with plant not in cold shutdown. M T I i H I 4 H M m ) C Q um 1 W d3 Q M O WP33

r\\ C\\ (h \\) \\J l xs TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL -UNUSUAL SITE GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY Other Securi ty Unusual aircraft activity over X i Hazards Visual Observation facility or crash onsite. Experienced or. Projected Aircraft crash or missile X impact on facility. Aircraft crash or missile X impact which damages safety related systems. Fire Alarms and Fire with plant not in cold X Systen Alarms shutdown which damage safety related systems. Visual Observation Train derailment onsite. X Security i M Visual Observation Near or onsite explosion or X Security projected explosion. Sheriff's Radio 1 l s m i M C O I U1 = N i C Q I hJ H 3 WP33

TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERALI EVENT TYPE POSSIBLE INDICATIONS POSSIBL'E PLANT CONDITIONS EVENT ALERT EMERGENCY EMERGENCY Other Security Explosion onsite which causes X Haza rds Personnel Observation facility damage affecting plant Experienced System Alanns operation. or PrDj ected (Continued) i Securi ty Explosion onsite which damages X Personnel Observation safety related systems or System Alarms structures with plant not in cold shutdown. Personnel Observance Near or onsite release of toxic X Portable Dectectors or flammable gases. Sheriff's Radio Uncontroled entry of toxic or X flammable gases into the facility envi rons. Uncontrolled entry of toxic or X m flammable gases into vital areas of the y plant where lack of access to the area a constitutes a safety problem. Plant I" not in cold shutdown condition. g mmcm un mW 4m N N WP33 / 2.

4 O O O ^ TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL EMERGENCY l4 EMERGENC SITE GENERAL i UNUSUAtt l EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS 'i EVENT' ALERT l X Otner NA Other plant conditions exist that () i Hazards require plant shutdown under Technical l Experienced Specification or involve other than ! 1 J normal controlled shutdown or. scram. or Projected I (Continued) i ] ___s_____.._________ NA Other plant itions thatswarrant X precautionara .tivation of RSC and placing E0F and other key emergency personnel on standby. 3 NA Other plant conditions exist that X warrant activation of energency J centers and monitoring teams or a jd precautionary notification to the q public near the site. _( ) 'i NA Any major internal or external events X m beyond design basis) which could cause i. (e.g., fires, earthquakes,substantially I 4 massive cannon damage to plant systems resulting in core melting and release of g large amounts of radioactivity in a m i short period or time. G U1 >c G } N W WP33 a

O f3 Q) b C TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE GENERAL I EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT hlERT EMERGENCY EMERGENCY. ,c j Release or Area Radiation Monitors Any uncontrolled increase in X l Loss of Air Activity Monitors radiation levels or airborne l Control of contamination levels greater Radioactive than 1000 times normal. Materials t within the jl" Plant i i Area Radiation Monitors Fuel handling accident that X g Containment Building Air Exhaust results in fuel damage with the Gaseous Rad (Hi) release of radioactivity to Annune.iator C7-1 the Containment Building. Containment Building Air Exhaust j Particulate Rad (Hi) Annunciator C7 2 Personnel Observation i ---_2 Area Radiation Monitors Major danage to spent fuel in X Containment Building Air Exhaust Containnent. Gaseous Rad (Hi) Annunciator C7-1 e m Containment Building Air Exhaust l Particulate Rad (Hi) Annunciator C7-2 L m Fuel Element Storage Well Level Uncontrolled decrease in Fuel X C (Lo) Annunciator E14-2 Element Storage Well water vi Area Rad Monitor level below fuel level. l Personnel Observation m 2 d2 O N .D. WP33

J n - TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAL SITE l GENERAL EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT ALERT EMERGENCY 8 EMERGENCY Events Visual Observation Indications or alarms on Process X Affecting System Alarms or Effluent Parameters not i Operation functional in the Control Room requiring plant shutdown. ______.1_________ Visual Observation Significant loss of assessment X System Alarms or communication capability. __...____m_________ Alarm Test Loss of most or all X Visual Observation alams/ annunciators. Alarm Test Loss of most or all alams/ X Visual Observation annunciators and plant transient inititiated or in progress. i Control Personnel Observation Evacuation of the Control Room X i Rom anticipated or required for any to Habit-reason. Shutdown outside Control ability Room initiated. i-g i m Failure of Containment Evacuation of the Control Room X j E* Building required for any reason. Shutdown Scram button outside Control Room not vi implemented within 15 minutes. o Ds tQ (D to U1 WP33

O O O d TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL lUNUSUAL SITE GENERAL i EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT' ALERT EMERGENCY EMERGENCY I Situations Communications from Transportation of contaminated X i Requiring Health Physics Personnel injured individual to the Off-Site hospital. Assistance (Personal Injury) l l Situations Security Communications Unauthorized forceable intrusion X i Requiring Operations Communications into a Vital Area. Off. Site Visual Observation Assistance i (Security Threat) Confirmed on-going sabotage X attempt in a Vital Area. Imminent loss of physical control X of the plant. Loss of physical control of the ,X plant. M ] H = H A 03 01 C G us i Du d2 O M Ch WP33

O O O TABLE 4.1 (Continued) EMERGENCY ACTION LEVEL UNUSUAU SITE GENERAL i EVENT TYPE POSSIBLE INDICATIONS POSSIBLE PLANT CONDITIONS EVENT"ALERT EMERGENCY EMERGENCY j Situations Smoke Detectors Fire within the restricted area X Requiring Fire Alarm that cannot be extinguished within i Off-Site Communications from Fire Brigade 10 minutes by the Fire Brigade. Assistance Visual Observation (Fi re) Fire nnt extinguished in 10 X minutes in an area that could affect safety related equi pment. Fire which has resulted in X degradation of the functions of one or more safety systems. f Fire in the Electrical X Penetration Room which is cut of control. l i I M t M i 7: H i m m i C O ? e O M i 4 WP33

<0 f La Crosse Boiling Water Reactor vage o.1 EPP-2 O_ LACBWR EMERGENCY PLAN PROCEDURE F ORGANIZA'110N AND OPERATIONS DURING EMERGENCIES 1 T 2 ^'"? ? ? [/i g ~'" Q g I& - Fefn@ Record and Control of Initial Issue, Revisions & Periodic Reviews Prepared By or Operations Supv. QA Supervisor Health & Safety Appy'd & Issued

Issue Periodic Rev. By Review Review Review **

Effective Date Signature Date Signature Date Signature Date Signature Date of Issue t

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- H&S Supv. or Rad. Prot. Engineer
LACBWR Plant Superintendent

4 Page 0.2 EPP-2 LACBWR EMERGENCY PLAN PROCEDURE ORGANIZATION AND OPERATIONS DURING EMERGENCIES Issue Notice No. 4 Dated 3/17/82 INSTRUCTIONS Remove Old Page No. Insert New Page No. Description Of and Reason for Change Remove and discard Insert all pages of Complete procedure revision all pages of EPP-4 EPP-2, Issue 4. (hence no change lines) to Issue 3. reflect the changes in the Emergency Plan, Revision 1, and to streamline the emergency initiation and de-escalation procedure. O PAGE SCHEDULE No. Issue No. Issue No. Issue No. Issue 0.1 4 14 4 29 4 44 4 0.2 4 15 4 30 4 45 4 1 4 16 4 31 4 46 4 2 4 17 4 32 4 47 4 3 4 18 4 33 4 48 4 4 4 19 4 34 4 49 4 5 4 20 4 35 4 50 4 6 4 21 4 36 4 51 4 7 4 22 4 37 4 52 4 8 4 23 4 38 4 53 4 9 4 24 4 39 4 54 4 10 4 25 4 40 4 55 4 m 11 4 26 4 41 4 56 4 Q 12 4 27 4 42 4 57 4 13 4 28 4 43 4 58 4 59 4 This issue shall not become effective unless accompanied by a new cover sheet properly signed off in the appropriate review / approval columns.

5 Page 1 EPP-2 Issue 4 <~s LACBWR EMERGENCY PLAN PROCEDURE ORGANIZATIO*1 AND OPERATIONS DURING EMERGENCIES 1.0 PURPOSE This procedure delineates authority, responsibility and limits on actions of Dairyland Power Cooperative management during emergencies at the La Crosse (BUR). This procedure defines the actions to be taken under the La Crosse (BWR) Emergency Plan to direct emergency response and guides the Emergency Control Director and his emergency staff in controlling the emergency. It further delineates the interactions between plant and cooperative personnel, and between cooperative and off-site emergency organizations. The procedure provides means of documenting all key emergency operations parameters and radiological assessment communications between the Control Room, the Technical Support Center, the Emergency Operations Pacility and Offsite Emergency Agencies.

2.0 REFERENCES

I~} 2,1 NUREG-0654, " Criteria for Preparation and Evaluation of k/ Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," November, 1980. 2.2 RUREG-0696, " Functional Criteria for Emergency Response Pacilities," February, 1981. 2.3 LACBWR Emergency Plan, Revision 1, March, 1982. 2.4 Emergency Plan Procedure 1, " Emergency Conditions and Response." 3.0 DEFINITIONS / RESPONSIBILITIES 3.1 The Emergency Control Director (ECD) is the Cooperative management person responsible for overall direction of the response to the emergency condition. Initially, this role will be performed by the Duty Shift Supervisor. If the accident escalates to a Site Area Emergency, or the Emergency Operations Facility is activated, a key Cooperative Manager as listed in Appendix C will become the Emergency Control Director. The ECD will assign responsibilities to other staff personnel as required. HE WILL NOT, HOWEVER, ASSIGN THE ULTIMATE DECISION OF RECOMMENDED SHELTERING OR EVACUATION TO STATE AUTHORITIES, NOR INITIATION OF REENTRY / RECOVERY (^} OPERATIONS. THE ECD is the focal point of all emergency (_) activities. The operation and safe shutdown of the facility WP33 remains the responsibility of the Duty Shift Supervisor.

a b Page 2 EPP-2 Issue 4 (a) The ECD has the authority to request outside assistance from r State, Federal, local governmental agencies, DPC staff personnel, consultants or any other response organizations. He has the responsibility to augment plant staf f as requested by the Duty Shift Supervisor, Technical Support Center (TSC) staff as requested by the Onsite Emergency Response Director or the Emergency Operations Facility (EOF) Staff. The ECD is responsible for the dissemination of emergency information to all off-site emergency support agencies, and to the public via the joint public information center (JPIC). The ECD is the single spokesperson for Dairyland Power Cooperative if an emergency condition exists at LACBWR and all information to be released to non-DPC emergency personnel must be cleared through the ECD. The ECD's Secretary / Recorder maintains documentation of messages received or transmitted to and from the EOF, other than from LACBWR, on the Emergency Communication Form included as Table 3. 3.2 The Onsite Emergency Response Director (ERD) is responsible for the coordination of the total site response ef fort and has full authority for all activities at LACBWR. He is responsible for implementation of onsite aspects of the Emergency Plan. Initially this role will be performed by the Duty Shift Supervisor. If the accident escalates to an <3(j Alert, or the Technical Support Center is activated, a key LACBWR flanager as listed in Appendix B will become the Onsite Emergency Response Director. He directs technical assistance given the operations and radiation protection staffs by the TSC staff for implementation of in-plant recovery effort in a manner which minimizes effect to the J / public health and safety. The ERD also provides technical advice to the ECD concerning the overall emergency direction upon request from the ECD. The ERD reports to the ECD upon activation of the Emergency Operations Facility. 3.3 The Onsite Operations Parameters Director (OPD) is responsible for obtaining current reactor operations parameters by direct communications from the control room for use by the TSC staff through a plant parameters communicator. The OPD advises the Duty Shift Supervisor in control of specific plant parameters necessary to prevent accident escalation. Upon request from the ECD in the COF, the OPD may provide technical advice to the EOF. It is preferable that the OPD have a Senior Reactor Operators License. The OPD answers directly to the Onsite. Emergency Response Director. He maintains documentation of reactor operations parameters by using Reactor Operations Parameters Communications Forms in Table 4. l l WP33 L

a f Page 3 EPP-2 Issue 4 3.4 The Onsite Radiological: Assessment Director (RAD) is responsible for obtaining current plant radiological conditions by direct cornmunications with the Control Room, HP Technicians surveying inside the plant and HP Technicians surveying within the site boundary. The RAD directs inplant and onsite HP Technician survey teams and assists the OPD in evaluation of plant parameters which might result in unnecessary release of radioactive materials to the environment. The RAD is responsible for initial calculations of off-site doses or projections of those doses based on effluent releases of radioactive material and current site meteorology. Upon request from the ECD in the EOF, the RAD may provide technical advice to the EOF staff. The RAD answers directly to the Onsite Emergency Response Director. He maintains documentation of plant radiological parameters by using In-Plant Radiological Parameters Communications Forms listed in Table 5. 3.5 The Cooperative Operations Parameters Director (OPD) is responsible for obtaining all current operations parameters from the Control Room. The OPD reports directly to the ECD upon activation of the EOF. The OPD is responsible for technically advising the ECD on current reactor conditions and safety system functions. The OPD () establishes direct communications with the Control Room, and may concurrently establish direct communications with the TSC, through a Technical Communicator who documents all messages on Table 4. Operations advice from the ECD to the plant are communicated through the OPD. 3.6 The Cooperative Radiological Assessment Director (RAD) is responsible for obtaining all current radiological parameters available to the TSC. He reports directly to the ECD upon activation of the EOF. The RAD is responsible for technically advising the ECD on current plant radiological conditions and advises the ECD on off-site radiological conditions. The RAD works closely with the ECD and recommends public protective actions to the ECD. ( He is responsible for final calculation of off-site dose estimates based on radioactive releases and l meteorological conditions. He is responsible for the overall direction of off-site radiological assessment l including the In-Field RAP teams. The RAD establishes direct communication with a HP Technian in the Control Room, and/or the plant RAD through a Technical Communicator who documents messages on Table 4. Radiological advice from the EOF to the onsite RAD are communicated by the Cooperative RAD. I O V UP33 I m

m Page 4 EPP-2 issue 4 (m) 3.7 The Cooperative In-Field Radiological Assessment Director (IRAD) is responsible for all actual off-site radiological assessments. In conjunction with the plant RAD, the IRAD coordinates the activities of all in-field radiological assessment parameters (RAP) teams. The IRAD reports to the cooperative RAD. The.IRAD is responsible for comparing calculated off-site dose estimates with actual RAP team assessment. The IRAD secretary / recorder documents all messages on Table 5. He works closely with the Cooperative RAD at the EOF to assess necessary Public Protective Actions. 3.8 The Off-site Dose Calculations and Trajectory Specialist is responsible for actual calculations of off-site dose estimates based on available meteorolgocial data and radiological release data supplied by the HP Technician in the Control Room or the onsite RAD or &ctual field data supplied by the RAP team. He also determines projected trajectory of the radioactive material released from the plant and plots this on maps in the EOF. _His computed data is supplied to the RAD and IRAD for their assessment of proper in-field RAP Team placement and analysis of recommended public protective actions. 3.9 The Cooperative Emergency Support Director (ESD) is (') responsible for obtaining additional cooperative or \\~J outside manpower or equipment as necessary for LACBWR re-entry / recovery operations. He reports directly to the Emergency Control Director. He reports to the La Crosse Office upon notification by the ECD. (Refer to Appendix D). 3.10 The Public Information Director (PID) is responsible for the activation and operation of the Joint Public Information Center (JPIC). He reports to the Emergency Control Director and obtains all information to be disseminated to the public from the ECD. He is the official company spokesman for the emergency. He will assure that this concept of " single spokesman" is in fact carried out to avoid even minimal contradictions of detail or analysis. He is responsible for arranging interviews, for statements quoted in press releases or other announcements, and for presiding at formal press conferences. He coordinates information at the news center with his counterparts f rom local, state, and I tederal agencies and with other companies involved with the emergency, and provides a means of. meeting the media's needs. 3.11 The Cooperative Emergency Communications Director will l (^T be used as necessary by the ECD to augment or repair (_) communications equipment. (Refer to Appendix D). WP33

Page 5 EPP-2 Issue 4 4.0 PROCEDURE INDOCTRINATION This procedure is organized into 6 sections corresponding to the 4 activity levels outlined in EPP-1 " UNUSUAL EVENT," 1 " ALERT," " SITE AREA EMERGENCY," and " GENERAL EMERGENCY," and generic, initiating, or de-escalating requirements. Each response section is prepared as though the activity event occurs on backshift. The Emergency Control Director is initially the Duty Shift Supervisor. Each section has a checklist. The Control Room and TSC checklists are the official checklists except when the EOF is activated. The checklist maintained at the EOF is the official checklist during EOF activation. All checklists used should be retained. Any communication system out of service or non-working phone numbers should be referred to EPP-3, " Communications," for such alternatives as exist. i 4 t'.c f WP33 > k,,.t. l ik h hP - t =L.

Page 6 EPP-2 Issue 4 fh Q 4.1 ALL EMERGENCY ACTION LEVELS 4.1.1 The Duty Shif t Supervisor is the Emergency Control Director and the Onsite Emergency Response Director, as well as the Supervisor of reactor operations and manipulation of controls. He will assess the abnormal event, and using EPP-1, determine the appropriate emergency action level. He will initiate all actions as necessary to bring the plant to a safe shutdown. 4.1.2 Notify the Shift Technical Advisor. 4.1.3 After determining the appropriate Emergency Action Level, turn to the appropriate section of this procedure. Unusual Event------------Section 4.2 Alert--------------------Section 4.3 Sire Area Emergency------Section 4.4 General Emergency--------Section 4.5 C) WP33 i . ~,

.=. I Page 7 EPP-2 Issue 4 ( 4.2 UNUSUAL EVENT 4.2.1 Notify the Plant Superintendent or Alternate. Notify Radiation Protection Management if event involves unmonitored release of radioactivity, degradation of plant ef fluent monitors or significant personnel contamination. (See Appendix A). 4.2.2 Notify the USNRC via the ENS network (red phone). 4.2.3 Call up any offsite resources required to assist in bringing the Emergency Plan activities to a closeout. t 4.2.4 Escalate Emergency Response by turning to the appropriate EAL section of this procedure, or deactivate the Emergency Plan by turning to Section {} 4.6.10, " Deactivation of Emergency Plan." a G WP33 i .m-.. ,._m.-,c

Page 8 EPP-2 Issue 4 m) (_ 4.3 ALERT 4.3.1 Activate the Technical Support Center by calling personnel listed on the Technical Support Center roster. (Appendix B) (Onsite Emergency Response Director) (Onsite Operations Parameter Directof) (Onsite Radiological Assessment Director) (Duty Shif t SupervisoE fnftials) 4.3.2 The ERD will notify the ECD who will Place the Emergency Operations Facility on standby by requiring the first individual contacted on the Emergency Operations Facility list (eg. the ECD) in Appendix D to standby a telephone with a known number that will be indicated below. Upon activation of the EOF, the ECD is required to supplement EOF manpower by calling additional () individuals listed in Appendix C. (ECD) (Phone No.) (ERD Initials) 4.3.3 Notify Vernon County Sheriff via (637-2123) or (637-2910) or (637-2992) or NAWAS and Wisconsin Warning Center 1.(Wisconsin Division of Emergency Government) via NAWAS or (266-3232) that an alert is being declared and the offsite agencies should be placed on a standby basis. The message should state: "This is (Caller's Identification) calling from the La Crosse Boiling Water Reactor. An alert has occurred at LACBWR. This call is being made to comply with NRC notification requirements only and no assistance or other action by your agency is required at this time." (Duty Shift Supervisor) 4.3.4 Notify the USNRC via the ENS network (red phone). Ob (Duty Shif t Supervisor) WP33 I

Page 9 EPP-2 Issue 4 4.3.5 Once the Technical Support Center is activated, establish liaison with the Technical Support Center. The ERD will call a plant parameters communicator to the TSC. (Appendix B) ERD Initials ~ 4.3.6 Augment the staff as needed in accordance with Appendix A. ERD Initials 4.3.7 If a radiological condition activated the alert level, obtain air and ground surveys (as outlined in EPP-7), observing appropriate precaution as outlined in EPP-6. RAD Initials 4.3.8 If the activating event could result in exposure to the public in excess of those resulting from normal maximum allowable operating levels (as defined by LACBWR Technical Specifications), notify the Vernon County Sheriff at 637-2123, 637-2910, or 637-2992 or NAWAS of wind speed and direction. RAD Initials / ERD Initials ~~ 4.3.9 Determine potential offsite doses (Reference EPP-5) and notify the Vernon County Sheriff of resulting estimates (Phone 637-2123). If those estimates indicate exceeding Environmental Protection Agency Guidelines,* escalate to General Emergency Class Step. RAD Intitials 4.3.10 If samples of 4.2.8 indicate potential on-site doses in any area not normally a high radiation area or any calculation doses above MPC, evacuate the subject area to either Operations Support Center (Genoa 1 or the lunch room by the Control Room), or other area designated by the Emergency Control Director. Time Evacuation Ordered (If Appropriate) (Duty Shift Supervisor)/(ERD) (s -)

of 1 Rem whole body or 5 Rem to the thyroid from iodine exposure.

WP33

.=. Page 10 EPP-2 Issue 4 r~ i ( 4.3.11 flaintain a routine of site monitoring to ensure that conditions do not degrade and require are escalation.to a higher cla:1lification or require site evacuation to an offsite OSC as outlined in the Emergency Plan. 4.3.12 Notify INPO of the alert status at (404)953-0904, as time permits. 4 (ERDT~~ ~ 4.3.13 Notify American Nuclear Insurers of the alert status at (203) 677-7305. ~ [ ERD) 4.3.14 Escalate Emergency Response by turning to.the appropriate EAL section or de-escalate to Unusual Event by turning to Section 4.6.9 or. deactivate Emergency Plan by turning to Section 4.6.10. (ERD) ~ ~ r- \\J i 1 l l t i l l WP33 4 ,.,., -. ~ _,,. - -. _..,, -,, _.. - _, _...,. _-,.,..,_,,..,_.m..,_,..

Page 11 EPP-2 Issue 4 () 4.4 SITE AREA EMERGENCY 4.4.1 Evacuate all onsite personnel except Operational crew, oncrew Health Physics Technician, Shif t Technical Advisor, CAS Operator, and TSC personnel to either the Evacuation Point at Genoa 1, the lunchroom or lockerroom, or St. Charles School at the discretion of the Duty Shift Supervisor. (Use the St. Charles School

if radiological conditions are such that the Genoa 1 power plant is not habitable or will not be habitable, and offsite evacuation of nonessential personnel is required.) The Security Supervisor /Sargeant on duty will account for all onsite personnel and notify the Control Room.

The normal exit pathway through the Administrative Building will remain open for egress. The CAS operator will run a LIC, I, OTI listing. The Security Supervisor /Sargeant will ensure the printout is brought to the evacuation point.

(Contact school by calling Rev. Schute at 689-2646.)

(1) Announce "A site area emergency exists - all personnel evacuate to Genoa 1 (or " lunchroom" or "offsite to St. Charles School") immediately." Then push the Reactor Building Evacuation Siren and Outside and Turbine Building Siren start and allow siren to sound for 30 seconds. Repeat announcement } and siren two more times. NOTE: FOR DRILLS ONLY - Shortly before initiating the drill, contact the G-3 Shif t Supervisor or Plant Superintendent at 689-2335 and the Sheriff's Office at 637-2123, and the Genoa Lock and Dam No. 8 at 689-2625 to notify them of the.forth-coming drill, and the fact that the siren will sound, and what if any action is required on their part. The first announcement should be preceded by the words, "This is a Drill," then the emergency announcement should be followed by, "This is a Drill." (Duty Shift Supervisor) 4.4.2 Notify any additional personnel the Duty Shift Supervisor wants to retain to go to the lunchroom OSC adjacent to the Control Room. 4.4.3 If Genoa-1 or the St. Charles School OSC is to be used for the evacuation point, the Security Supervisor / Sargeant on duty at the P.A. Access Control Point will bring the Visitor's Log, any available dosimeters, the Sheriff's Band two-way radio, the LACBWR truck, and the S Evacuation Point Emergency Feyring (G-1 only) to the ("j activated assembly point; and shall select Channel 88 or s 76 and activate the FM radio in the LACBWR truck for backup communications with the Control Room. WP33

Page 12 EPP-2 Issue 4 /~)'s (, 4.4.4 The Genoa 3 Duty Shift Supervisor will evacuate personnel not needed to safely reduce facility operation. If expected personnel exposure exceeds 5 rems whole body exposure or 25 rems thyroid exposure, the ECD shall require total evacuation of Genoa 3. 4.4.5 The warehouse personnel will also evacuate upon command. 4.4.6 If during normal office workday, switchboard operator should switch phone PABX to Control Room' and bring visitor's record to Evacuation Point. 4.4.7 The Security Supervisor /Sargeant shr.ll account for all personnel onsite by the following outline: (1) The Control Room will notify him of all vital crew members' accountability. (2) The computer listing will be checked against personr.el present at the Evacuation Point to ensure all LACBWR personnel are accounted for. (3) A member of the administrative technical staff present in the Administration Building will report O.. on all personnel in the building being present at the Evacuation Point. The Security Supervisor /Sargeant will designate this person. (4) The visitor log will be used to account for all personnel in LACBWR not listed in (2). (5) A member of the Genoa 3 staf f assigned by the Security Supervisor /Sargeant will account for these people. (6) The Resident Inspector will account for all individuals onsite under NRC jurisdiction not accounted for in (2),.(3), or (4). (7) A member of the DPC staff housed in the Annex will account for Annex personnel. (8) A member of the Warehouse Staff assigned by the Security Supervisor /Sargeant will account for these people. 4.4.8 Report to the ECD. (^3 (Security Supervisor /Sargeant) '(_/ HP33

Page 13 EPP-2 Issue 4 () Any re-entry to evacuated areas shall be by direction of the ECD in accordance with re-entry procedure, Section 4.7 4.4.9 Notify the Vernon County Sheriff via (637-2123) or (637-2910) or (637-2992) or NAWAS, Wisconsin Warning Center 1 via NAWAS or (266-3232), and Wisconsin Warning Center 3 via NAWAS or (372-3251) that a site area emergency is being declared and the offsite agencies should be placed in a standby basis. The message should s ta te: "This is (Caller's Identification) calling from La Crosse Boiling Water Reactor. A site emergency has been declared at LACBWR. We recommend that you initiate yoar Einergency Reponse Plan as soon as possible. The Site Emergency is (brief narrative description of the event)....." (STA or Duty Shift Supervisor) 4.4.10 Activate the Technical Support Center by calling personnel listed on the Technical Support Center roster (Appendix B). (ERD) (RAD) ( OPD) 4.4.11 The ERD activates the Emergency Operations Facility by calling the ECD listed on the EOF roster (Appendix C). Persons Contacted (ECD) (ERD Initials) The ECD will notify the staff to report to the EOF by calling the RAD and OPD listed on the EOF roster (Appendix C). Persons Contacted (RAD) ( OPD) (ECD Initials) WP33

Page 14 EPP-2 Issue 4 m 4.4.12 Notify the USNRC via the ENS network (red phone). (ERD or Duty Shift Supervisor) 4.4.13 Activate the Joint News Center by contacting the Public Information Director listed in Appendix E. (ERD) 4.4.14 Once the Technical Support Center has been activated, establish liaison between the Control Room and TSC. The ERD will call a Plant Parameters communicator to the TSC. (Appendix B) (ERD) 4.4.15 Augment the staf f as needed in accordance with Appendix A. 4.4.16 Once the EOF has been activated and the Cooperative Manager in overall charge of the emergency has arrived in the EOF, the Cooperative Manager will call the Shift Supervisor at the plant and assume the Emergency Control () Director role. (Duty Shif t Supervisor) (ECD) Step in the Procedure ECD Transferred To Complete at Transfer Time /Date (Duty Shift Supv.) Once the EOF has been transferred from the Duty Shif t Supervisor to the Cooperative Manager, the TSC Staff and/or the Control Room will communicate with the EOF staff and provide the incident details, known radiological releases, if applicable, sample results if taken, time of event, and current status. The telephone numbers for the EOF are listed in Appendix F. Keep the EOF notified of changes of plant condition. The ECD will now contact the Joint News Center and establish communications. The EOF Staff reporting to the EOF will call in additional individuals listed in Appendix C as l {} needed. WP33 i

Page 15 EPP-2 Issue 4 () 4.4.17 The ECD shall in conjunction with Cooperative RAD determine areas in and around the facility to be surveyed to determine the extent of radiological release and contamination (EPP-6, 7, and 8). Any indication that dose rates or contamination rates at the site boundary downwind may exceed 1 Rem whole body or 5 Rem to the thyroid shall cause the ECD to escalate the emergency status to that of General Emergency and evaluate offsite doses (EPP-8). Actual dose predictions to offsite areas shall be calculated using EPP-5 under direction of Health and Safety personnel. These calculations should be double-checked. Control Room personnel will furnish meteorological data as required until such time as this f"nction is remoted. The Vernon County Sheriff shall be furnished with meteorological conditions and dose projections where appropriate by the ECD. (RAD and ECD) 4.3.18 Notify INPO of the site area emergency status at (404)953-0904, as time permits. O ~ (ECD) 4.3.19 Notify American Nuclear Insurers of the Site Area Emergency status at (203) 677-7305. (ECD) 4.3.20 Escalate Emergency Response by turning to General Emergency EAL Section 4.5, or de-escalate to Alcrt by turning to Section 4.6.4, or deactivate emergency plan by turning to Section 4.6.10. Q V UP33 i

Page 16 EPP-2 Issue 4 g(,) 4.5 GENERAL EMERGENCY 4.5.1 Evacuate all onsite personnel except Operational crew, oncrew Health Physics Technician, Shif t Technical Advisor, CAS Operator, and TSC personnel to either the Evacuation Point at Genoa 1, the lunchroom or lockerroom, or St. Charles School at the discretion of the Duty Shift Supervisor. (Use the St. Charles School

if radiological conditions are such that the Genoa 1 power plant is not habitable or will not be habitable, and offsite evacuation of nonessential per.sonnel is require.) The Security Supervisor /Sargeant on duty will account for all onsite personnel and notify the Control Room.

The normal exit pathway through the Administrative Building will remain open for egress. The CAS operator will run a LIC, I, OTI listing. The Security Supervisor /Sargeant will ensure the printout is brought to the evacuation point.

(Contact school by calling Rev. Schute at 689-2646.)

(1) Announce "A site area emergency exists - all personnel evacuate to Genoa 1 (or " lunchroom" or "of f site to S t. Charles School") immediately." Then push the Reactor Building Evacuation Siren and Outside and Turbine Building Siren start and allow siren to sound for 30 seconds. Repeat announcement I~h and siren two more times. \\_/ NOTE: _FOR DRILLS ONLY - Shortly before initiating the drill, contact the G-3 Shift Supervisor or Plant Superintendent at 689-2335 and the Sheriff's Office at 637-2123, and the Genoa Lock and Dam No. 8 at 689-2625 to notify them of the forth-coming drill, and the fact that the siren will sound, and what if any action is required on their part. The first announcement should be preceded by the words, "This is a Drill," then the emergency announcement should be followed by, "This is a Drill." (Duty Shift Supervisor) 4.5.2 Notify any additional personnel the Duty Shift Supervisor wants t o retain to go to the lunchroom OSC adjacent to the Control Room. 4.5.3 If Genoa-1 or the S t. Charles School OSC is to be used for the evacuation point, the Security Supervisor / Sargeant on duty at the P.A. Access Control Point will bring the Visitor's Log, any available dosimeters, the Sheriff's Band two-way radio, the LACBWR truck, and the Evacuation Point Emergency Keyring (G-1 only) to the (~)T (_ activated assembly point; and shall select Channel 88 or 76 and activate the FM radio in the LACBWR truck for backup communications with the Control Room. HP33

Page 17 EPP-2 Issue 4 (_) 4.5.4 The Genoa 3 Duty Shif t Supervisor will evacuate personnel not needed to safely reduce facility operation. If expected personnel exposure exceeds 5 Rems whole body exposure or 25 Rems thyroid exposure, the ECD shall require total evacuation of Genoa 3. 4.5.5 The warehouse personnel will also evacuate upon command. 4.5.6 If during normal office workday, switchboard operator should switch phone PABX to Control Room and bring visitors' record to Evacuation Point. 4.5.7 The Security Supervisor /Sargeant shall account for all personnel onsite by the following outline: (1) The Control Room will notify him of all vital crew members accountability. (2) The computer listing will be checked against personnel present at the Evacuation Point to ensure all LACBWR personnel are accounted for. (3) A member of the administrative technical staff present in the Administration Building will report () on all personnel in that building being present at the Evacuation Point. The Security Supervisor /Sargeant will designate this person. (4) The visitors' log will be used to account for all personnel in LACBWR not listed in (2). (5) A member of the G-3 staff assigned by the Security Supervisor /Sargeant will account for these people. (6) A member of the warehouse staff assigned by Security Supervisor /Sargeant will account for their people. (7) The Resident Inspector will account for all 1 individuals onsite by NRC jurisdiction not j accounted for in (2), (3), or (4). (8) A member of the DPC staff housed in the Annex will account for Annex people. A member of the warehouse staff will account for warehouse people. l l m a WP33 .Y--

Page 18-EPP-2 Issue 4 () 4.5.8 Report to the ECD. (Security Supervisor /Sargeant) Any re-entry to evacuated areas shall be by direction of the ECD in accordance with Section 4.7, re-entry procedure. 4.5.9 Notify the Vernon County Sheriff via (637-2123) or (637-2910) or (637-2992) or NAWAS and Wisconsin Warning Center 1 via NAWAS or (266-3232) and Wisconsin Warning Center 3 via NAWAS or (372-3251) that a general emergency is being declared and that the offsite agencies should be activated. The message should state: "This is (Caller's Identification) calling from the La Crosse Boiling Water Reactor. A General Emergency has been declared at LACBWR. Immediate notification of the public is warranted. Assistance from your agency is requested immediately and we recommend that you implement your Emergency Response Plan immediately. The General Emergency is (brief narrative description of the event) () (STA or Duty shif t Supervisor) 4.5.10 Have the Health Physics Technician begin calculating offsite dose estimates as per EPP-5. (Duty Shift Supervisor) 4.5.11 Activate the Technical Support Center by calling personnel listed on the Technical Support Center roster (Appendix B). (ERD) (OPD) (RAD) 4.5.12 The ERD activate the Emergency Operations Facility by calling personne'l listed in the EOF roster (Appendix C). Transfer Operational Control of the emergency to the Emergency Control Director upon his reaching the EOF. The number at the EOF is 8-284 or 8-343. (See Section 4.4.16.) Persons Contacted: {~ (ECD) (OPD) (RAD) WP33

Page 19 EPP-2 Issue 4 4.5.13 Notify the USNRC via the ENS network (red phone). O (ECD) 4.5.14 Activate the Joint News Center by contacting a person listed in Appendix E. (ECD) 4.5.15 The llealth Physics Technician shall perform offsite exposure estimates using the methology of EPP-5. If the calculations result in estimated offsite dose for the duration of the release which exceed the following guidelines, the RAD or the Cooperative RAD shall verify the calculations. The Cooperative RAD will report the off-site dose caluclation to the ECD. The CCD shall contact the Verr.on County Sheriff and make the recommendation for Protective Action outlined for the zone in Figure 1 towards which the wind is blowing. If on a border, include the adjacent zone. PROJECTED DOSE (REM) TO THE Tile POPULATION RECOMMENDED ACTIONS ( a ) COMMENTS () Whole Body < 1 No planned protective Previcusly recom-actions (b). State may mended protective issue an advisory to seek actions may be shelter and await further reconsidered or instructions. Monitor terminated. environmental radiation levels Whole Body 1 to Seek shelter as a minimum. If contraints exist, < 5 Consider evacuation, special considera-Evacuate unless constraints tion should be given make it impractical. for evacuation of Thyroid 5 to Monitor environmental children and < 25 radiation levels. Control pregnant women. access. Whole Body 5 Conduct mandatory evacua-Seeking shelter and Above tion. Monitor environ-would be an alterna-mental radiation levels and tive if evacuation adjust area for mandatory were not immediately evacuation based on these

possible, levels.

Control access. (a) These actions are recommended for planning purposes. Protec-tive action decisions at the time of the indicent must be taken (~N into consideration. s_) (b) At the time of the incident, officials may implement Jow-impact P581SElbh e9@b 8P8s 9s 9ggigg yfggggg81prdB618dSb?$. maintaining i k WP33

Page 20 EPP-2 Issue 4 (q 4.5.16 Augment the staf f as needed in accordance with f Appendix A. 4.5.17 Contact the NRC on the HP hotline (SS-4 Network). Call Region III at Ext. 23; if no answer (off-hours), call Bethesda, Maryland at Ext. 22. No dial tone or ringing will be heard. Keep an open line until NRC terminates if operational conditions permit. 4.5.18 Once the EOF has been activated, contact the EOF staff' and provide the incident details, known radiological releases, if applicable, sample results if taken, time of event, and current status. Keep the EOF Staff notified of changes of plant condition. The ECD will now contact the Joint News Center and establish communications. The EOF Staff reporting to the EOF will call in additional individuals listed in Appendix C. Step in the Procedure ECD Transferred To Complete at Transfer Time /Date 7 (Duty Shif t Supervisor) (Emergency Control Director) 4.5.19 The ECD shall in conjunction with the Cooperative RAD determine areas in and around the facility to be surveyed to determine the extent of radiological release and contamination (EPP-6, 7, and 8). Control Room personnel will furnish meteorological data as required until such time as this function is remoted. The county emergency operations center shall be furnished, via the Vernon County Sherif f, with meteorological conditions and continuing dose projections by the EOF Staff. O WP33

Page 21 EPP-2 Issue 4 /% 4.5.20 The Joint News Center shall function (EPP-16) to act as liaison with news media. The county emergency operations center (Vernon County Sherif f) shall be the liaison with offsite governmental agencies. The ECD shall keep both centers appraised of all developments and changes in plant status, particularly those which may potentially effect offsite doses. Additional communication capabilities are outlined in EPP-3. All information released to the public shall have been cleared through the ECD by the PID. 4.5.21 The ECD shall contact any personnel required for augmentation of available staff as he determines to be' necessary. Resources by area of expertise are listed in Section 4.6. The ECD has DPC management approval to augment resources as needed to bring the reactor to a stable condition and minimize offsite impact. The ECD may augment staff and material through the EMMPD. 4.5.22 Notify INPO of the general emergency status at (404)953-0904, as time permits. 4.5.23 Notify American Nuclear Insurers of the general emergency status at (203) 677-7305. O 4.5.24 Once the condition which caused activating the Emergency Plan has been stabilized, initial recovery and re-entry of evacuated site area may be made for assessment or mitigation per Section 4.7. 4.5.25 If appropriate, de-escalate to Site Area Emergency by turning to Section 4.6.1, or to Alert by turning to Section 4.6.4, or to Unusual Event by turning to Section 4.6.9. l (ECD) I O WP33 ll

Page 22 i EPP-2 Issue 4 () 4.6 DE-ESCALATION OF EMERGENCY ACTION LEVELS'-At3D DEACTIVATION Nhen the activating condition has been resolved, the 4.6.1 t general emergency status shall be either de-escalated or terminated. Notify Wisconsin War.ning Centers 1 and 3 and Vernon County SheriffTof'the action. ~ ~ (ECD) 4.6.2 Notify the USNRC via the EN,S neEwork (red phone). (ECD) 1 4.6.3 Notify INPO and ANI as time permi,ts that emergency status has been reduced. (ECD) 4.6.4 When the pctivating condition has been resolved, the _si site area \\ emergency status shall be either de-escalated or terminaied. Notify the Vernon County Sheriff's Office andVWisconsin Warning Centers 1 and 3 of the action. (ECD) 4.6.5 Notify the USNRC via the ENS network (red phone). l l l (ECD) 4.6.6 The EOF will deactivate the Joint News Center. s (ECD) 4.6.7 Notify INPO and ANI. (ECD) O WP33 e w-. y c-, --,. ~., ,,s.

Page 23 EPP-2 Issue 4 4.6.8 Deactivate the Emergency Operations Facility after providing a verbal closecut to any public officials present, and upon direction of the ECD. (ECD) 4.6.9 Once the condition which required alert status has been resolved, close out Emergency Plan activation or de-escalate to Unusual Event Status. If closeout is indicated: (1) Notify the Vernon County Sheriff's Department and Wisconsin Warning Center. (ERD) (2) Notify the USNRC. I l (ERD) (3) Notify the Shif t Technical Advisor. i (ERD) l (4) Remove the Standby Status of the Emergency l Operations Facility if applicable. l l (ERD) (5) Notify INPO and ANI. (ERD) (6) Deactivate the OSC if applicable. (ERD) (7) Deactivate the Technical Support Center. (ERD) O WP33

Page 24 EPP-2 Issue 4 () 4.6.10 Deactivate the Emergency Plan and notify the NRC and Superintendent _ (if appropriate). Duty Shift Supervisor Date 4.6.11 Provide written summary of emergency events to appropriate organizations as outlined in the Emergency Plan. (1) Alert - Written summary to ERD and offsite agencies i within eight (8) hours of closeout.or class reduction. (2) Site Area Emergency - Written summary to ECD and of fsite agencies within eight (8) hours of closeout or class reduction. (3) General Emergency - Written summary to ECD and of f site agencies within eight (8) hours of closeout or class reduction. 4 J f l 1 l' l O WP33 l 1 w ,,-.-w.e.-,.., -,-,,,---.,-----,.,.,,--,w.,,, -,_,.-,.w ,..-r..,r,,_--, ---v-

Page 25 EPP-2 Issue 4 [ 4.7 RECOVERY AND RE-ENTRY 4.7.1 After the initial preplanned emergency actions have alleviated the emergency situation, additional actions may be necessary to effect the most complete recovery possible. All recovery actions will be preplanned and all actions will be documented. Affected areas will be roped of f and posted with warning signs indicating radiation levels or other hazards. Every reasonable effort should be made to limit radiation exposure. However, the exposure levels justifiable will depend on the specific circumstances, taking into account risk versus benefit factors in the particular situation. 4.7.2 Section 4.8 indicates resources which can be utilized during the recovery and re-entry phases of an emergency at LACBWR. The Emergency Control Director will have the authority and responsibility to manage the overall re-entry and recovery operation. He has the authority to request offsite support and assistance from other utilities, consultants, INPO, etc. 4.7.3 The initial return to the plant af ter a site area evacuation will be made by a re-entry team composed of at leant two members. The team will consist of at least ) one member of the LACBWR Health and Safety Department s/ and one member of the LACBWR Operations Department. More than two persons may be used in the party if it can result in the saving of human life or reduction of inj ury. The decision to re-enter shall be made by the Emergency Control Director and the following prerequisites should be considered: (1) protective clothing, (2) respiratory protective equipment, (3) personnel monitoring TLD badges and dosimeters, (4) radiation monitoring instrumentation, (5) communication with the Emergency Control Team or with the Control Room, preferably both, and (6) if available, the conditions inside the plant should be determined from the in-plant radiation monitoring instrumentation. O WP33

Page 26 EPP-2 Issue 4 () 4.7.4 Planned exposure (1) to the whole body and/or specific organs should not exceed the following recommendations of the National Council on Radiation Protection and Measurements (NCRP-39), and U. S. EPA, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," (EPA-520ll-75-001, Revision 1). Protective Or Lifesaving Organ Corrective Actions Actions Whole Body 25 Rems 75 Rems Hands and Forearms 100 Rems 300 Rems (including whole body component) Thyroid 125 Rems No Limit (2) - All reasonable measures must be taken to control contamination and internal exposures, utilizing the best available respiratory protection and protective clothing. /~h - Persons performing emergency activities should be (_/ familiar with exposure consequences. - Women capable of reproduction should not take part in actions requiring emergency exposures. - Retrospective doses shall be evaluated on an individual case basis. - Other things being equal, volunteers above the age of 45 should be selected. (1) Authorization for volunteers to receive these recommended exposures is a nondelegatable responsibility of the Emergency Control Director. (2) Thyroid exposure should be minimized to the extent feasible by the use of respirators and/or thyroid prophylaxis (administration of stable iodine salts). However, no upper limit is specified for life saving action since the complete loss of the thyroid may be considered an acceptable risk for saving life. l WP33

Page 27 EPP-2 Issue 4 _ ps 4.7.5 Re-entry after an area evacuation will be by decision of ~ the LACBWR Health and Safety. representative on duty at N the time.. No one should re-enter an area until approval is given by a qualified person. Special monitoring equipment, in addition to that in the emergency boxes, is kept in the Waste Treatment Building and in the Change Room to assist in evaluation of re-entries. The in-plant monitoring equipment should also be used when possible. 4.7.6 Once the potential of escalating an event has passed, steps should be started to recover from the incident. Guidelines and responsibilities for recovery are outlined below: (1) There must be assurance that the problem which-caused the emergency is solved and that this same incident cannot immediately reoccur. (2) The general occupancy areas must be free of significant contamination and radiation and high radiation areas properly defined and posted. I (3) Airborne radioactivity must be eliminated or controlled within 10CFR20 limits. () (4) Access to the area must be controlled and exposures of personnel documented.- Exposure for recovery should be limited to 10CFR20 limits. (5) The LACBWR Operations Review Committee under the Emergency Control Director is responsible for evaluating recovery advisability. (6) Plant records and other essential information necessary for evaluating the emergency must be i available. (7) All major recovery steps will be performed in accordance with written procedures. These procedures will be prepared under the supervision of the Onsite Emergency Response Director, by qualified LACBWR staff members, or outside consultants. They will be reviewed by the Operations Review Committee and approved by the Emergency Control Director. O WP33

Page 28 EPP-2 Issue 4 (~)N 4.7.7 When the recovery operation has been completed and the ( -plaat has been returned to an operable condition, the Emergency Control Director is responsible for authorizing the return to normal operation. If the emergency shutdown resulted from a safety limit being exceeded, reactor operation will not be resumed until authorized by the NRC. A complete analysis of the situation will be made, together with recommendations for preventing a reoccurrence. This report shall be submitted to the DPC General Manager, the Safety Review Comiai ttee, a nd the NRC. The plant will be restarted only when: (1) the conditions causing the ' emergency are returned to normal, (2) the cause of the emergency is understood, (3) restoration, repair, and testing are complete as

required, (4) no unreviewed safety questions exist, (5) all conditions of the License and Technical Specifications are satisfied, and

-s (6) all required approvals have been received. 4.8 RESOURCES 4.8.1 Resources are available to supplement staff in emergency situations. Backup capabilities from DPC staff and outside entities are outlined in this section. EPP-3 lists numbers and messages for several of these contacts. 4.8.2 Upon initiation of any emergency response, specific plant groups, departments, or individuals have general responsiblity to take &ctions. These assignments are described in Table 4.2. Listed first is the group available for first response onsite at all times. Listed next are others available for assistance based on their availability for response. O WP33

Page 29 EPP-2 Issue 1 (~ TABLE 4.1 V) Task Position Offsite Augmentation Plant Operations.

Shift Supervisor /

Operations Department Three (3) Operators Personnel. Emergency Control Shif t Supervisor / Cooperative Management, Director Shift Technical Individual. Advisor Notification / Operator / Shift Additional Plant or Communications Technical Advisor / Cooperative Staff Security Supervisor / Indiviual Assigned When Sargeant Reaches Site or EOF. Offsite Dose Health Phsyics Director Environmental Assessment Technician / Shift Affairs / Radiation Supervisor Protection Engineer / Environmental Engineer Offsite & Onsite Health Physics Health Physics Tech., Outside of Plant Technician Environmental Affairs Surveys Department Personnel. (~) Implement Surveys Health Physics Radiation Protection Technician Engineer / Health and Safety Supervisor Chemistry Health Physics Radiation Protection Technician Engineer / Health and Safety Supervisor Technical Support Shift Technical Plant Engineering Staff, Advisor System Engineering Department Staff Personnel. Repair Operators Maintenance Mechanics, I&E Technicians. Radiation Health Physics Radiation Protection Protection Technician Engineer / Health and Safety Supervisor / Radiation Protection Engineering Specialist

As prescribed in LACBWR Technical Specification 6.2.2.

O WP33

Page 30 EPP-2 Issue 4 (() Task Position Offsite Augmentation Firefighting Fire Brigade Local Fire Department. Resuscitation Operators, Local Ambulance & Security Personnel . Hospital Staf f. Access Control Security Personnel Personnel Acct. Logistics Support DPC Administrative for Onsite Group - Particularly Emergency Personnel Purchasing. Staf f Engi neers, DPC Technical Support for Re-Entry / Power Projects Group, Recovery Operation Consultants, Environ-mental Affairs Depart-ment, Staff Personnel. Management Level Assistant General Government Manager - Power Authorities Production. DPC Information & Confirmation [) Release to News Marketing Department. Media Headquarters Personnel Area of Capabilities Director of Environmental Environmental Monitoring and Dose Affairs and Staff Assessment. Assistant General Manager - Technical Support for Planning and Power Group Recovery Operations, Special Equipment and Supplies Procurement, Notification of Government Agencies. Director of Information and Notification of Government Marketing Agencies Public Affairs, and News Media. Transportation Supervisor and/ Special Vehicle Use, or Construction Superintendent Manager of Insurance and Insurance Needs. Contracts O WP33 ~.

Page 31 EPP-2 Issue 4 f) 4.8.3 The offsite non-DPC support agencies having specific expertise in various areas are listed in this section. 4.8.3.1 Sheriff's Office - Vernon County The Vernon County Sheriff's Department Headquarters is located in Viroqua, Wisconsin, twenty (20) miles from the plant site. The department will cooperate in any emergency situation brought to its attention. The County Sheriff is responsible for providing local public support in the area of public notification, evaucation, emergency assistance, and crowd and traffic control. The Sheriff's Office has 24-hour response capability. He is responsible for notifying the following agencies: Surrounding County LLEA's. o Vernon County Civil Defense Director. o Wisconsin Division of Emergency Government. o / Minnesota Officials, including Houston o tN County, Minnesota Sheriff's Department, Caledonia, Minnesota. Allamakee County, Iowa Sheriff's Department, o if required. The County Sheriff is also responsible for followup notification of the population-at-risk within the 5-mile radius of the 45' sector of the potential plume pathway. 4.8.3.2 Tri-State Ambulance An agreement has been mada with Tri-State Ambulance located in both Viroqua and La Crosse, Wisconsin, to provide DPC with ambulance service and in-route life support treatment for persons with radiological and non-radiological injuries resulting from an emergency at LACBWR. v WP33

Page 32 EPP-2 Issue 4 () 4.8.3.3 U. S. Army Corps of Engineers An agreement has been made with the U. S. Army Corps of Engineers, through the St. Paul District for Lockmasters, to provide assistance in controlling area' river traffic at Lock & Dam Nos. 7, 8, and 9 during an emergency at LACBWR. Lock and Dam No. 8 will provide small craft, emergency shelter, medical first aid, and telephone communications. 4.8.3.4 United States Coast Guard (USCG) By agreement, the U. S. Coast Guard will be responsible for controlling river traffic using their craft and communications. Craft can be provided from Davenport, Iowa, and Has tings, Minnesota. Response time depends on craft location and river conditions. 4.8.3.5 Genoa Fire Department The Genoa Fire Department, by agreement is responsible for providing rescue and firefighting support to LACBWR during emergencies. Upon request by the Genoa Fire O_ Chief, all fire departments of Vernon County can be coordinated and directed by the Fire Services Director for the Vernon' County Civil Defense Organization to support the Genoa Fire Department during an emergency at LACBWR. 4.8.3.6 La Crosse Lutheran Hospital - Gundersen Clinic Vernon Memorial Hospital.- Viroqua, Wisconsin Arrangements have been made with the La Crosse Lutheran Hospital to provide DPC with medical treatment for radiological and non-radiological injuries incurred during an emergency at LACBWR. The Vernon Memorial Hospital in Viroqua is nomally considered the backup hospital for medical treatment for radiological and non-radiological injuries incurred during an emergency at LACBWR. WP33

Page 33 EPP-2 Issue 4 4.8.3.7 U. S. Nuclear Regulatory Commission The role of the NRC during a radiological emergency is to verify that emergency plans and procedures have been implemented, assure that the public health and safety are protected, and conduct investigative activities associated with the incident. The NRC will assist in coordinating federal response resources and will provide DPC, state and local agencies with advisory assistance associated with assessing and initigating hazards to the public. 4.8.3.8 U. S. Department of Energy The Department of Energy has prepared a Federal Radiological Monitoring and Assessment Plan and an Interagency Radiological Assistance Plan. Under the provisions of these plans, the Department of Energy, upon request from the State of Wisconsin Division of Emergency Government, will dispatch radiological teams to assist local and state agencies with monitoring and provide technical guidance. These teams are intended to be advisory, and will not () assume control from local authorities who are present. 4.8.3.9 Burlington Northern Railroad An agreement with Burlington Northern Railroad stipulates that they will control rail traffic passing the site during an emergency when the Chief Dispatcher in Cicero, Illinois, is notified by telephone. The La Crosse Assistant Road Superintendent or Train Telegraph operator can be used as alternate contacts. 4.8.3.10 Modern Crane Service Modern Crane Service, by Letter of Agreement, will provide a crane with a boom of 150 feet, as well as other necessary equipment and services during an emergency. (N ! L.] i WP33

Page 34 EPP-2 Issue 4 I) 4.8.3.11 Grant County and Sauk County, WI., Sheriff's Helicopter Service The Vernon County Sheriff, upon request by DPC, can notify the. Sheriffs of Grant and Sauk Counties to dispatch their helicopters which are equipped with sirens and loud speakers to notify sportspersons and tourists on the Mississippi River and on the Federal Wildlife Refuge Islands and backwaters within the plume exposure pathway EPZ. 4.8.3.12 State of Minnesota The Minnesota Division of Emergency Services, administers the State of Minnesota Radiation Emegency Plan. The State Civil Defense Director located in St. Paul is responsible for activating the Minnesota Plan and for providing the assistance it details. The State Division of Emergency Services maintains a 24-hour duty officer for continuous response capability. 4.8.3.13 State of Iowa The Office of Disaster Services administers the O's_- State of Iowa Radiation Incident Response Plan and has continuous respone capability. The State Civil Defense Director located in Des Moines is responsible for activating the Iowa Plan and providing the assistance it details. 4.8.3.14 State of Wisconsin r The Wisconsin Department of Local Affairs and Development, Division of Emergency Government administers the State of Wisconsin Radiological Emergency Response Plan. The Division of Emergency Government has continuous response capability. The Regional Director at Madison is responsible for activating the Wisconsin Plan and providing the assistance detailed within it. This support includes the following: Alerting appropriate state agencies, o Providing a radiological response team. o operating the state emergency communications o control center. (- WP33

Pcge 35' EPP-2 Issue 4 (~N Informing appropriate government agencies o (_[ and adjacent counties and states. Assisting local authorities through the o State Highway Patrol. Coordinating state mutual aid. o 4.8.4 Additional specific physical resources both DPC and non-DPC owned are listed in this section. 4.8.4.1 Radiological Monitors and Dose Measuring Devices Environmental Direct Radiation Monitoring - o TLD's Thirty-eight environmental TLD's, with capability of detecting both beta and gamma radiation dose equivalents, are located at specific locations at distances from LACBWR ranging from 1 to 23 miles. TLD's beyond 5 miles are considered to be background environmental radiation dose equivalent s monitors. \\ A Five Air Monitoring Stations o At least five air monitoring stations are in operation as part of the Environmental Survey Program. Each contains a particulate filter and charcoal cartridge which could be analyzed with portable survey points around LACBWR and are capable of measuring radiciodine concentrations of 10-7 pCi/cc and lower. An EPP gives the relationships between radionuclides and the resulting dose levels for comparison to projections. All stations have Ag Zeolite cartridges in desicant bags which would be inserted in the air sampler to replace charcoal cartridges during an emergency. LACBWR has the capability of placing a portable air sampler at a spot within the plume which can then have its media removed to the laboratory for isotopic analysis. In addition, a variety of offsite samples are analyzed by an outside contractor in La Crosse at the University. Those I') facilities would normally be available for use during emergency assessment situations. p 4 e g u,.

Page 36 EPP-2 Issue 4 () 4.8.4.2-Meteorological Monitors Various meteorological parameters can be monitored from the Control Room. These parameters include: (1) barometric pressure, (2) ambient temperature ground level, (3) differential temperature between the top of the stack and the ten meter tower, (4) wind speed and direction at top of the stack, and (5) relative humidity. The site meteorological data also includes data on wind speed and wind direction at the 10-meter height. This data is currently available in the office annex. This data is available to the Emergency Operations Facility. Meteorological data is available from the Alma Wisconsin Energy Center of Dairyland Power Cooperative. Meteorological data is also available at the Rochester, Minnesota, U. S. Weather Bureau. (} 4.8.4.3 offsite Laboratory Facilities The Univeristy of Wisconsin-La Crosse Nuclear Radiation Center, located in Cowley Hall will serve as an offsite laboratory. Also, avail-able will be the Dairyland Powr;r Cooperative laboratory located in the Service Center Building on East Avenue in La Crosse. The University of Wiaconsin-La Crosse labora-tory has the capability to analyze environmental samples for gross alpha, gross beta, gross gamma, as well as isotopic identification. The capability also exists for the analysis of iodine in milk. Analysis can be provided on a 24-hour immediate notification basis. The University of Wisconsin-La Crosse Radiation Center has two multi-channel analyzers with Sodium Iodide and Germanium detectors, liquid scintillation counters, thin window proportional counters, alpha spectro-meter, Geiger-Mueller counters, and single channel analyzers to determine the radioactivity content of multiple environmental 4 samples. s, WP33 ~. . ~

Page 37 EPP-2 Issue 4 () A letter of agreement to have access and use of their facility has been provided to Dairyland l Power Cooperative by the University of Wisconsin-La Crosse. The Dairyland Power Cooperative Environmental Laboratory will have the capability of analyzing environmental samples for gross beta and gross alpha content. This laboratory will be available on a 24-hour basis. 4.8.4.4 Protective Facilities and Equipment The OSC at G-1 is able to accommodate all personnel present onsite at any given time. There are approximately 70 workers at LACBWR and 80 at Genoa 3 present during the day shift. The OSC is equipped with a telephone. It also has a first aid kit. The S t. Charles School in Genoa, Wisconsin, by agreement with DPC, will be used as the offsite evacuation point-in the event that radiological conditions make onsite evacuation points not habitable. The school has the capability of 0-accommodating 150 people. It is equipped with a telephone. Also, located at the OSC is an emergency equipment kit, which contains protective equipment, radiological monitoring equipment, and emergency supplies. 4.8.4.5 Damage Control Equipment . Numerous DPC vehicles and a variety of heavy equipment are available onsite for use. This equipment is maintained by the adjoining coal plant (Genoa 3 unit) and the Alma Dock Corporation. Equipment includes bulldozers, mobile cranes, tugboats, forklifts, winches, welding equipment, chain falls, etc. All DPC heavy equipment normally present at the Cooperative's Office is available at the site within two hours. WP33 i ~__

Page 38 EPP-2 Issue 4 4.8.5 This section lists various technical consultants with which DPC has worked previously, along with INPO. 4.8.5.1 Institute of Nuclear Power Operations (INPO) is an industry group which maintains a list of available staff and equipment from other nuclear power plants. DPC has a mutual assistance agreement with INPO to' coordinate outside assistance from other utilities. I 4.8.5.2 Nuclear Energy Services (NES) has acted as the principal consultant to DPC or LACBWR. They have numerous personnel familiar with plant layout and design and have reference drawings, etc. 5.0 RECORDS The checklists maintained in the Control Room and the EOF shall be maintained in accordance with ACP-18.1. f j e O 4 4 WP33 , _..... _ _ _.. _ _ _. _ - _ - _.. _ - - _ _. _... ~.,, _. _ _ _,.. _....., _. _ _... _ _..... - _..,. _ _ _ _ _.,.., _. _ _. _ _ ~.

Page 39 EPP-2 Issue 4 () APPENDIX A EMERGENCY MANPOWER NOTIFICATION EMERGENCY CLASSIFICATION APPLICABILITY Unusual Event Only PLANT SUPERINTENDENT Richard E. Shimshak-------------788-4166 John D. Parkyn------------------788-7004 George S. Boyd------------------457-2746 Larry W. Kelley-----------------874-4260 Duty Shif t S upervisor----------- NA RADIOLOGICAL PROTECTION

Paul W.

Shafer------------------637-2946 Bruce R. Zibung-----------------788-0904 Larry L. Nelson-----------------783-4164 73 (_)

If unusual event involves significant unmonitored release of radioactivity, degradation of plant gaseous effluent monitors, or significant personnel contamination as defined in ACP 17.1.

4

O WP33

Page 40 EPP-2 Issue 4 h' APPENDIX A (Cont'd) s_- LACBWR PERSONNEL AVAILABLE FOR STAFF AUGMENTATION (Refer to LACBWR Phone List) the It may be necessary under emergency conditions to augment Activation and augmentation of the Emergency LACBWR staff onsite. Operations Facility and the Technical Support Center are coveredT separately in EPP-2. listed below are cross-referenced to Table A-1 of the March 198 revision of the LACBWR Emergency Response Plan. (Including Firefighting Rescue and First Aid) SUPPORT FOR OPERATIONS Senior Reactor Licensed Personnel Dale Croonquist Gary Whynaucht Larry Kelley Marc Polsean George Boyd Roger Christians Lynne Goodman f-w) (_ John Parkyn _L__icensed Personnel Mike Johnsen Steve Buck Gerald Dunnum Tony Startz Paul Crandall Gregory Holmstadt Randy Thorson Mike Wilchinski Gerald Gadow RADIOLOGICAL SUPPORT (Inplant Surveys, Offsite Surveys, and Dose Assessment Assistance) Fred Schroeder Al Hansen Mark Holmes John Papierniak Bill Montalvo Jeanette Gaynor Larry Nelson O Bruce Zibung Paul Shafer WP33 ~.. -

Page 41 EPP-2 Issue 4 i SYSTEM REPAIRS Electrical: Gardner i Weise Yeoman D. Olson W. Nowicki Instrumentation: L. Mitchell P. Hess D. Flottmeyer G. Gentry Mechanical: John Tischer Edmund Wolf Reay Ross Al Twinde Jim Lintelman Dave Carroll Rodney Bolstad l Duane Froh Michael Bina John Russ Paul Gray SITE SECURITY ( Also Commur.ications) Contact the Security Sargeant and use any or all of the Shif t Guard i Force as required. The Security Sargeant can call in additional aff-duty personnel as needed. Gerald Joseph John Parkyn !C) WP33 _ ~. _ _ _ _ _, _. -.. _

Page 42 EPP-2 Issue 4 O APPENDIX B EMERGENCY MANPOWER TECHNICAL SUPPORT CENTER EMERGENCY CLASSIFICATION APPLICABILITY: Alert, Site Area Emergency, General Emergency ONSITE EMERGENCY RESPONSE DIRECTOR (1 Person Required) Richard E. Shimshak----------------788-4166 John D. Parkyn---------------------788-7004 Dr. Seymour J. Raffety-------------788-3406 George S. Boyd---------------------457-2746 Larry W. Kelley--------------------874-4260 ONSITE OPERATIONS PARAMETERS ~ DIRECTOR (1 Person Required) George S. Boyd---------------------457-2746 73 Larry W. Kelley--------------------874-4260 (') Marc A. Polsean--------------------689-2369 Off-Duty Shift Supervisor----------NA ONSITE RADIOLOGICAL ASSESSMENT DIRECTOR (1 Person Required) Bruce R. Zibung--------------------788-0904 Paul W. Shafer---------------------637-2946 Larry L. Nelson--------------------783-4164 Off-Duty Senior HP Technician------NA Off-Duty HP Technician *------------NA

Does not include (OJT) HP Technicians.

PLANT PARAMETERS COMMUNICATOR (1 Person Required) Larry Mitchell----------------(319)S44-4845 Paul Hess--------------------------788-1768 D. Plottmeyer----------------------788-2322 (' (_% G. Gentry--------------------------788-1650 ) WP33

Page 43 EPP-2 Issue 4 p) (_ APPENDIX C EMERGENCY MANPOWER / EMERGENCY OPERATIONS FACILITY EMERGENCY CLASSIFICATION APPLICABILITY Site Area Emergency, General Emergency EMERGENCY CONTROL DIRECTOR (1 Person Required) James W. Taylor--------------------783-3125 Thomas A. Steele-------------------788-5520 James Sherwood---------------------782-8788 Paul Finner------------------------788-3188 COOPERATIVE OPERATIONS PARAMETERS DIRECTOR (1 Person Required) Lynne S. Goodman-------------------788-5008 Robert M. Brimer-------------------783-7497 Hugh A. Towsley---------------( 507)643-6237 Off-Duty Shift Supervisor----------NA COOPERATIVE RADIOLOGICAL ASSESSMENT DIRECTOR (1 Person Required) Thomas A. Steele-------------------788-5520 Paul W. Shafer---------------------637-2946 Bruce R. Zibung--------------------788-0904 IN-FIELD RADIOLOGICAL ASSESSMENT DIRECTOR (1 Person Required) Paul W. Shafer---------------------637-2946 George Johnston--------------------788-1417 TECHNICAL COMMUNICATORS (2 Persons Required) Robert Wery------------------------788-1939 Glenn Tullius----------------------782-8214 Paul Sampson-----------------------783-6015 Don Egge---------------------------734-3619 i OFFSITE DOSE CALCULATIONS & TRAJECTORY SPECIALIST (1 Person Reg.'d) Eric Hennen------------------------783-5360 Dan Weiss--------------------------788-9424 l l COOPERATIVE EMERGENCY SUPPORT DIRECTOR (1 Person Required) Paul Finner------------------------788-3188 /~} Dan Crady--------------------------788-3114 \\_/ r WP33 l l

Page 44 EPP-2 Issue 4 APPENDIX D SUPPLEMENTAL EMERGENCY MANPOWER EMERGENCY OPERATIONS FACILITY SUPPORT STAFF EMERGENCY CLASSIFICATION APPLICABILITY General. Emergency if necessary COOPERATIVE EMERGENCY COMMUNICATIONS DIRECTOR i Charles Sans Crainte---------------782-6564 Kenneth Adams----------------------788-7153 i O t ' O j WP33 i

Page 45 EPP-2 Issue 4 APPENDIX E EMERGENCY MANPOWER JOINT PUBLIC INFORMATION CENTER EMERGENCY CLASSIFICATION APPLICABILITY Site Area Emergency, General Emergency EMERGENCY PUBLIC INFORMATION DIRECTOR Ronald Marose----------------------786-1966 Keith Kuehn------------------------788-6352 Peter Delwiche----------------( 507)894-4299 EMERGENCY TECHNICAL INFORMATION SPECIALIST Dr. Seymour J. Ra f f e ty-------------78 8-3 4 0 6 () Contact the EOF for alternate. l l 1 l i WP33 i _,.. _ _., _.,. -.. - -, _. _ _ _ _. _. -... -... _... _, _ _ _ _ _ _. _. - ~. ~.,.,..., --

Page 46 EPP-2 Issue 4 APPENDIX F KEY COMMUNICATIONS LIST DAIRYLAND POWER COCf-ERATIVE 1. LACBWR TSC---------------------------l-689-2331, Ext. 236, 434 Microwave: 72-236 2. LACBWR C ONTROL ROOM------------------l-6 8 9 - 2 3 31, E x t. 222 223 233 Microwave: 72-222 223 233 DPC System Radio 3. EOF (LA CROSSE)----------------------l-788-4000, Ext. 284 (Speaker Phone) Ext. 343 Microwave: 8-284 (Speaker Phone) Microwave: 8-343 () 1-788-4248* (Unlisted No.) DPC System Radio Both In/Out on Both: 788-4000 and 788-4248 4. GENOA 1 OPERATIONS SUPPORT AREA------PABX Ext. 275 689-2341 DPC System Radio 5. GENOA 3 SUPERINTENDENT---------------689-2335, Ext. 300 Microwave: 8-73-300 DPC System Radio 6. JPIC (STODDARD ELEMENTARY SCHOOL)----457-2631 457-2632 l O WP33 J w-w-g -g- ,w ._.n, w,-,e--.n.-ee

,-----,,e--

,.y. --w,ww r,-o, -+---,.--,-~-o-. e-, --e-s- ,-g

Page 47 EPP-2 Issue 4 KEY COMMUNICATIONS LIST - (Cont'd) VERNON COUNTY EMERGENCY GOVERNMENT (EOC) - (Viroqua, Wisconsin) 1. 637-2123 2. 637-2992 3. NAWAS 4. Sheriff's Radio From Control Room STATE OF WISCONSIN D.tVISION OF EMERGENCY GOVERNMENT 1. WI. DEG (Madison)--------------------l-266-3232 NAWAS 2. WI. DEG (Tomah)----------------------l-372-5937 (Radef) 1-372-3251 1-372-3252 NAWAS Relay From Sheriff's Radio (' STATE OF MINNESOTA DIVISION OF EMERGENCY SERVICES 1. MN. DES (St. Paul)-------------------l-612-296-0484 1-612-296-0487 (Radef) (Patch In Through WI DEG & NAWAS) 2. MN. DES & HOUSTON COUNTY EMERGENCY GOVERNMENT EOC (Caledonia, Mn)-------l-507-724-2623 1-507-724-3632 Relay On Sheriff's Radio Point To Point From Viroqua to Caledonia l U. S.' NUCLEAR REGULATORY COMMISSION 1. NRC RED PHONE---ENS 2. NRC HP HOTLINE O WP33

Page 48 EPP-2 Issue 4 KEY COMMUNICATIONS LIST - (Cont'd) INPO-1. 1-404-953-0904 LOCK AND DAM NO. 8 1. 689-2625 LA CROSSE LUTHERAN HOSPITAL EMERGENCY 1. 1-785-0530 2 VERNON MEMORIAL HOSPITAL EMERGENCY 1. 637-2101 2.- 637-2123 TRI-STATE AMBULANCE SERVICE 1. 1-784-4997 6 2. 637-7589 (Relay From Viroqua) 3. 648-3359 (Relay From De Soto) ET. CHARLES CATHOLIC SCHOOL 9" . 1. 689-2646 2. 689-2642 1 l i i O WP33 4 ~..., _ _., __.._._,.,.._,...-_..,,.,_..__.,,...__,.,._m.... ...._..,..,_..,.,,.,..__._,..,,...,,.____,__.._..,.. _-..,..,.... -,.,_ _~.,,_,

f) O DPC EMERE hCY RESP 0h;E CAGARIZATian 7:Gunt A-1 C00PtaAYlvt PuuiAGE 4 mT y__________1 1 Fe m a At. STATE, LOCAL 8 Ptatic InsonnATIO" IIHillatini EntnGenCv Confa0L Pasv Aft kamCats l DIRECT 08 DIRECTDA i,,,,,,,,,,,l ItaC/Fa ma i g g W s Rime I ______l __________l SECatTAnv/ ReconDre I I I RAD ICAL mATI s C00PtRAYlvt E m eGamCv AssassM m1 W Dh AaAntTEas $uPPORY DittCTOR DIRECT 011 DistCTOR " ADMINISTRATIvt SuPPopf SiCatTAAT/ al3Hs1 LACa.ne OrtaAYlons = itCunlCAL & Em6 stantas RECORDER EMestmCy ORGAmf1AT)0m PAAarE Ytes $gpponi (OPTtoM AL.T (FR6upt A-2) (seemICATOR = CormuutCAftons E alHillfilfisillllHillllltffilllllllllllllllinit;I 1 m IRANSPORTAflom =_ = 8 g C00PfnAfivt opp. SITE Dost isC 4 - PowustmuY I STAft a FlotaAL In-FIELD CALCuLAfl0ms a i I 8 PLAmi N w itas g RADIAT19e RESPonst Illvillillai RADIOLOGICAL TnA.acCY0mv l PAAAN Ytes 1 8 ftAns s

Sta ssMui SPECIALIST E0""'"8C# "

Comm:CAfon 1 - CouTnACTon & InsunAmCE e DietCTom g __________s 3 I ,____,_____l P-3 H trj 'O MIC De I 8 s s tn C l o M ow b >* b Organization Control e: IeIIeeIIeei Interface /Communicatior.3

O O LACBWR EMERGENCY ORGANIZATION FIGURE A-2 EMERGEhtY CopTROL DIRECTOR (Eor) d i Onsite Emergency flesponse Director 8 tc& PLANT SECRETARY / Cd RECORDER (_oPTlCN ALT M Onsite operations Onsite Radiological Parameter Director Assessment Director df l PLAmi PARAMETERS 1 ComuuIgAToR lilliglillll ComuniCAToR (Tsc g ggo,3 1 5 - - - - E- - - - I Jililitalitsilistisilistil-5 5 5 HMT = = C2 m CJ I I g, _ _ _ _ = _ _ _ _ _I,____2_____ g7; l g RADIOLOGICAL 1 ON-SITE OM E CoeITROL $HIFT SuPERVIson TECHNICAL & Roon PARAMETER $ g RADIOLOGICAL U1 a OPERATIONS OPERATI AL i' pggS ComusstCATOR I COMMuselCATOR MONITORING A O ~ SHIFT 8 STA SUPPORT OUPS i (CR) I (CR) (TSC 4 OSC) g g (EOF ) I IEAMS t OPT'o u a'i .__________l -_________i i Organization Control 4 Interface / Communications ii iii iie

'E T^8ts 3 rase si DAIRYLAND POWER COOPERATIVE EPP-2 C COMMUNICATIONS DISPATCH Issua 4 D DATE: TIME: INITIALS: MESSAGE #* T0/FROM: (Circle One) FROM/TO: (Circle One) US NRC (Region III) EOF (Emergency Control Director US NRC R.A.P. US NRC (Bethesda) E0F (Radiological Assessment Director) Vernon Co. EOC (Viroqua) State of WI EOC (Tomah) State of WI EOC (Madison) State of WI R.A.P. Houston County E0C (Caledonia) State of MN E0C (Rochester) State of MN EOC (St. Paul) State of MN R.A.P. ~ ~ ~ ~ ~ JPIC FEMA Other MESSAGE: O Originators Name ~ ECD Reviewed & Approved (If Reg'd)

l. Use Rad # if originated by Rad Communicator.

2. Use Opd # if originated by Opd Communicator.

3. Use Secretary's initial #

if originated by secretary.

4. Use TSC # if originated by TSC Plant Parameters Communicator.

5. Use CR # if originated by Control Room.

l l

h Pago 52 TABLE 4 EPP-2 f DAIRYLAND POWER COOPERATIVE 188 " 4 D EMERGENCY OPERATIONS FACILITY / TECHNICAL SUPPORT CENTER REACTOR _0PERATIONS PARAMETERS " COMMUNICATIONS A DATE: MESSAGE # (,) TIME: INITIALS: T0/FROM: TSC FROM/TO: EOF (Ci rcle CONTROL ROOM (Circle TSC One) OSC - 2 (Genoa 1) One) CONTROL ROOM EOF OSC - 2 (Genoa 1) MESSAGE: 1. Reactor Water Level in. (Safety Channels 1, 2, 3) (Wide Range) 2. Reactor Pressure psig. 3. Reactor Temperature

F.

4. Containment Building Isolated: YES N0 5. Emergency Systems in Operation: a. Shutdown Condenser YES N0 b. ECCS YES N0 c. ACS YES N0 d. lA Diesel / Generator YES N0 e. 18 Diesel / Generator YES N0 f. HPSW YES N0 g. ESWSS YES N0 6. Containment Building Pressure psig Temp.

F.

Level Inches 7. High Range C. B. Rad. Monitors (A) R/hr (B) R/hr. Fuel Clad Degradation Indication: HRCB Rad Monitor Fuel Degradation 101 - 102 R/hr 0% 103 - 104 R/hr s 1% 104 - 105 R/hr s 10% 105 - 106 R/hr s_100% 8. Other significant Reactor Operations Parameters. 9. Current Emergency Classification Status: Unusual Event Site Area Emergency Alert General Emergency Originators Name Received By

TABLE 5 Paga 53 R DAIRYLAND POWER COOPERATIVE EPP-2 A EMERGENCY OPERATIONS FACILITY / TECHNICAL SUPPORT CENTER Issue 4 INPLANT RADIOLOGICAL PARAMETERS D c0ssuNica110NS DATE: MESSAGE # TIME: INITI ALS: T0/FROM: TSC FROM/T0: E0F ~ ~ ~ ~ (Circle CONTROL ROOM (Circle TSC One) OSC 2 (Genoa 1) One) CONTROL ROOM E0F OSC - 2 (Genoa 1) 0THER 0THER MESSAGE: 1. Low Range ARM's (0 104 mR/hr) mR/hr ave. mR/hr max # 2. ARM 7 (0-105 mR/hr) mR/hr 3. ARM 8 (0 105 mR/hr) mR/ir 4. H.R.C.B.A.R.M.(0-108 R/hr) A R/hr B R/hr 5. Perimeter ARM OSC 2 (Genoa 1) mR/hr G-3 mR/hr .........c 6. STACK AIR MONITOR Stack Blower Flow Rate: O cc/sec 1.65 x 107 cc/sec 3.3 x 107 cc/sec A. SPING-4 o$N

1. g Part pCi

3. 1-131 pCi

5. LR Noble Gas pCi/cc

gp

2. a Part pCi

7. MR Noble Gas pC1/cc

9. HR Noble Gas pCi/cc g,=

B." @ 6 pCi/C1) p. (To obtain source term in Ci/sec mutiply the pCi/cc x cc/sec + 10 5 B. TRACER LAB ~$$

1. Immed. Part cpm

2. Delay Part cpm

3. Noble Gas epm 833 g3g 7.

Meteorological Information: Type of Release None Ground Elevated gge WS mph 0 m AT (100-10m) 7 a: v-WD 0 m 8. Containment Building Air Monitor A. SPING-3

1. g Part pCi

3. I-131 pCi

5. LR Noble Gas pCi/cc

2. a Part pCi

7. MR Noble Gas pCi/cc B.

TRACER LAB

1. Immed. Part cpm

2. Delay Part cpm

3. Noble Gas cpm 9.

Tunnel Mon. cpm

10. Forced Circulation Pump Cub. Monitor cpm.

11. Liquid Waste Monitor cpm.

12. Additional Portable Radiological Surveys; O

13. Current Emergency Classification:

Unusual Event Site Area Emergency Alert General Emergency Originator Received By

TABLE 6 Page 54 l DAIRYLAND POWER COOPERATIVE EPP-2 R EMERGENCY OPERATIONS FACILITY Issue 4 A INFInD RADIOL 0arCat AsSeSseeNT REAMS Q ASSESSMENT PARAMETERS RADIO COMMUNICATIONS /] DATE: MESSAGE # 0 TIME: INI TI ALS: T0/FROM: Field RAP Team 1 FROM/T0: E0F (Circle Field RAP Team 2 (Circle Field Rap Team 1 One) Field RAP Team 3 One) Field Rap Team 2 EOF Field Rap Team 3 Other Other .____...__..__._-_____..___..__.________..___.._-__._____________.___._____._...____._________...__) ca MESSAGE: oz Ov 1. Location Sector hun e o ee Distance from LACBWR mi. > cue k; 3 '* C mu 2. Direct Irmersion Dose Equivalent Rates mR/hr mrad /hr a2E oteO m e O o. e e 3. Ground direct radiation readings: L& E4m g,c 3 m g cpm s cpm oc ________..__._____.....___...___..___._________.....____________.__________...__.____..._________..e 4. Permanent Environmental Air Sampler Charcoal Cartridge changed to Ag-Zeolite YES NO Filter Paper Changed YES N0 a. mR/hr s mR/hr 6 b. Flow rate cfm. c. Total Flow cf. d. Filter gross beta counts cpm. e. Cartridge gross beta counts cpm. f __7.______.______.___...______.___________________________________... ._______.__.____.______..___.c Ks Ogg g y f. NaI(Tl) or Germanium MCA analysis results guggogo Total spa pCi/cc, Isotopes: N Euu to hh O r r e-o > c-0 U tu m M e m% 0%- m ECON % I O-uzo w 5. Portable Radeco - DC Air Sample Taken YES NO CHr.'IC0AL AgZeolite a. Flow rate Ipm b. Total sample time min. c. Total sample flow 1pm x min. x 103 =, cc d. Filter gross beta counts cpm e. Cartridge gross beta counts cpm l ...e____,..____________________________________.___________.________.______________________________< l SE% f. NaI(T1) or Germanium MCA analysis results: I"15e83 Total spa pCi/cc, Isotopes: N Euu tO hb O c-

-4 >

l r-O O to m M r-te % U % e4 3 ecOsw C- <-uao-w 6. Vegetation Sample Taken YES NO l 7. Surface Soil Sample Taken YES NO 8. Surface Water Sample Taken YES N0 9. Milk Sample Taken YES NO

10. Weather Conditions l

11. Other significant items:

l (oi l l l l l Orininators Namp Doroived Rv l

Page 55 EPP-2 Issue 4 ENERGENCY OPERATINS FACILITY ENERGENCY ONIPOL DIRECIOR'S ACTIW. TION GECKLIST !%) INITIALS All telephones and headsets hooked up properly and tested to be operational. Omm2nicaticns forms available and distributed to appropriate EOF personnel. Synchrcnize the wall clock and watches. Procedure Book and Worksheet notebook in frcnt of ECD and OPD and turned to Site Area Ehergency of EPP-2. All personnel are present in EDP and ready to go. Offsite dose ocznputer (TI-99) is working and ready to canpute. Maos and charts are in place. Secretary is instructed that gold copy of ccmtunication forms are to be placed on bulletin board outside EOF. l ( EDF " Authorized Personnel Only" sign is cn the door. EDF "Name Tags" in place on table. Proper "Ehergency Status" sign afixed to board behind EXI). l Determine what phone ntribers to use at TSC and C%mtrol Boczn to establish three-wy OPD and two-way RAD ccumunicaticus. Enter on 02munications Network Forms and place in front of ccm:Unicators and cm board behind ECD. EED contacts Shift Suoervisor and receives status report and where in procedure EPP-2 to begin. ECD assumes overall managemnt control of Drergency Situation at IACEMR. l Ocxmunicaticns networks with plant established. Ebliow EPP-2 frun here. 1

Page 56 EPP-2 Issue 4 O E D.Rc. SYSTEM radio b NRC-RED PHOME Q HP PHONE E D.R C. SYSTEM Q COMMERCI AL TELCPHONE RAOlo REPEATER & MICROWAVE PHOME I M I microwave R4, & NAWAS OlD DISPATC.H C.ARRIER LIME. (( DEDICATED HEAD 5ET/MICROP90 J FM RAbtO fg9 ( HANDLE. /TALKLF FM RAQlo {M - - -- RAOlo LINK IM PLAhlT g) 2 g R Abt0 LINK cut PLAMT 3 N gf_ \\ g M' WAVE. y O I 2%0$ N% TRUNKS i V wwcw I 2 COMMERCIAL / 2 3 / TRuMKS W IM l >2 N O' ' 3 5 - [ if 's 's 'W g2IE aC D J '-- $y_ s N g Md,Y N 1% Md5 "--% - - ' - g am m. l 1J 2 LO M N E k.. %o N ni _m._ NNNS

l s

i-- -i i- -i 3 1 kl 9 n 2 b d< 2 N j zu b i 1 3 / m STAtR. NK WAY I g g g g ze zu zu O i I

Page 57 EPP-2 Issue 4 O e PUSH BUTTON PKoME EXT. 284 (788-9 804) o HEADSET FOR R PHOWE GRAMD DAD'S o .B_ HEADSET FOR LACROSSE PHOME RAP TE'M OFFI CE To ESE. INSERTED IF [ coF ACTIVATE.D O , OF PHONES F' AILS / u sq ~@ wac. l ~ h\\ ( m a h ka ha / sgu say soso343 m o343 g l ( -IRAD + ( l) l l M can n l I23+ 1 234 i COM ME RCI AL. TRUNKS COMME.RCI A L COMMERCIAL O (7as-+ooo ) Tau"xs <788-+oo0) T== < <788-Se 8+)

E 2 Issue 4 O EMERGEMCY CONTROL COM MUNICATIONS G E. G O f J L I I l / / 1 r / 0 L / NSC RED PHONE kiRC at 284 / HP hot LIME / CHICAGO / / BETHESCA JPIC p / / / / /, ' // U rs m O

Page 59 EPP-2 Issue 4 OPERATIONS COMMUNIC AT IONS g ' Eof 343 Coureoc. 7 sc i Rocyn O-R ADIOLOC,1 C AL COMMUNICATION s =O = /g6 ~~ / s / Nx o I I / 1 O --o 5y a

La Crosse Boiling Water Reactor ,,, o.1 0 LACBWR ""~ EMERGENCY PLAN PROCEDURE COMMUNICATIONS SYSTEMS g[m). TDARYLA/VD l ?MZUP lg Mr$W ~ Record and Control of Initial Issue, Revisions & Periodic Reviews Prepared By or Operations Supv. QA Supervisor Health & Safety Appy'd & Issued

Issue Periodic Rev. By Review Review Review **

Effective Date Signature Date Signature Date Sigcature Date Signature Date of Issue Y~f/3M Ns'N/ l An f) z) A Y A 0 J f3 hlit / l3-1-et bu+c6( 3/ I '{ isi 1 J '"/ ~AV8 1-rn$:'A Y .,/. M A~ i i s (/ (/ (/ l i ! /~T l ,g 1 l HSP EPP

- ii&S Supv. or Rad. Prot. Engineer
LACBWR Plant Superintendent

Page 0.2 EPP-3 LACBWR EMERGENCY PLAN PROCEDURE Issue Notice No. 1 Dated 3/17/82 INSTRUCTIONS Remove Old Page No. Insert New Page No. Desc:,iption Of and Reason for Change Remove and discard Insert all pages of Reflect changes in Emergency all pages of EPP-3, EPP-3, Issue 1. Plan, Revision 1, dated March Issue 0. 1982. O PAGE SCHEDULE No. Issue No. Issue No. Issue 0.1 1 0.2 1 1 1 2 1 3 1 4 1 5 1 O This issue shall not become effective unless accompanied by a new cover sheet properly signed off.in the appropriate review / approval columns.

Page 1 EPP-3 Issue 1 0/ LACBUR EMERGENCY PLAN PROCEDURE COMMUNICATIONS SYSTEMS 1.0 PURPOSE This procedure provides information on communication systems for contacting onsite personnel, offsite personnel, and support agencies for assistance during an emergency. It also provides for periodic testing of communications systems. 2.0 RESPONSIBILITIES The Emergency Control Director or designated alternate is responsible for contacting offsite support agencies and for calling in extra personnel, required contacts are listed in EPP-2; additional support agency contacts are listed here. Any knowledgeable person may announce an evacuation or actuate the Reactor Building siren locally if conditions require it. /G () The Health and Safety Supervisor is responsible for ensuring periodic testing is performed.

3.0 REFERENCES

3.1 LACBWR Operating Manual, Volume V, Section 3. 4.0 REQUIREMEGTS 4.1 Assistance shall be requested only if an emergency exists and support is necessary. 4.2 The following individuals or locations shall be contacted prior to any General Emergency Exercise to notify them of the exercise, the fact that siren will sound, and what if any action is required on their part: (1) Vernon County Sheri f f (2) Genoa Lock and Dam No. 8 (3) Genoa Site Plant Superintendents 4.3 Use PABX phone system, plant page, handie-talkies, and/or sound powered headphone tranceivers for communications onsite during an emergency. () 4.4 Use microwave, regular telephone system, dispatch phone, 4 FM radio, red phone, HP hotline, or NAWAS for offsite communications as applicable. WP33

f Page 2 j EPP-3 Issue 1 5.0 ACTIONS. 5.1 Prior to any notification of-offsite support agencies, the-Shift Supervicor, STA, and Plant Superintendent or his designated alternate shall be notified. 5.2 Any personnel needed shall be notified by plant page or PABX telephone if onsite, microwave.or telephone if~at the ? La Crosse. Office, or by telephone if at home.. 1 5.3 Backup Communications Methods (1) Notify the NRC by red phone. If the red phone is out of service, call NRC Operations Center at 301-492-8111, use Health Physics Hotline, or call 301-427-4056 or 301-492-7000 and ask for NRC Operations Center. j (2) Notify Vern'on County Sheriff at 608-637-2123. 608-637-2992. -l Two-Way FM Radio or i NAWAS. I 5.4 Contact the following agencies if the need exists for. !(} their assistance as per EPP-2. (1) Genoa Fire Department Genoa 608-689-2561. 1 l Inform them of situation, if additional aid is needed at this time, and where to respond. ( 2) Tri-State Ambulance La Crosse 608-784-4997 Service Viroqua 608-637-7589 i (Relay from De Soto) 608-648-3359 Refer to EPP-13. (3) La Crosse Lutheran Hospital 608-785-0530 Vernon Memorial Hospital 608-637-2101 l Inform Emergency Ward Doctor in charge cr Emergency Ward Head Nurse to-initiate the " Nuclear Emergency Medical Plan." Refer to EPP-10 and EPP-ll. (4) Modern Crane Service La Crosse 608-782-1113 Request a crane with a 15'0-foo.t boom if Reactor Building insulation removal is necessary and when needed. O WP33 l

Page 3 EPP-3 Issue 1 k-) ( 5) DOE Radiological

Argonne, Assistance Team Illinois 312-972-4800 (Duty Hours)

(Security Office) 312-972-5731 (Off Hours) (6) American Nuclear Insurers Farmington, (ANI formerly NEL-PIA) Connecticut 203-677-7305 (7) UW-L Radiochemistry Dept. La Crosse 608-785-8268 Dr. William Nieckarz Home 608-788-2620 (8) U.S. Coast Guard - River Traffic Control Normal Office Hours Only, Twin Cities District Office 612-725-7452 24-Hour Operations Davenport, Iowa 319-322-6297 St. Louis, Missouri 314-425-4614 (9) Alma Dock Genoa 608-689-2625 Tug "Blackhawk", La Crosse Marine Operator 608-784-3456 or via Lock and Dam No. 8. O) 6.0 TESTING 6.1 The Health & Safety Department is responsible for testing the LACBWR phone systems at the frequency listed below: Communication System Testing Frequency LACBWR PABX State, Lccal Monthly l Federal Annual Microwave Network Local Monthly High Frequency Radio Local-Vernon Mont*ly County Sheriff ENS NRC Red Phone Federal Monthly l (All Extensions) SS-4 NRC Health Physics Federal Annual NAWAS State Annual Site Sirens Full Test Incl. Annual Various Areas in ) Plant 6.2 The annual tests may be performed in conjunction with the annual exercise. WP33 l

= 1. j-Page EPP-3 Issue 1 e 6.3 The tests shall be. documented on the attached -Emergency j Phone Checklist. 1 i 7.0 . RECORDS I Checklists shall be maintained by the Health and Safety -Supervisor for five (5) years. t l j I r l l i. 4 1 l 's r L f k i!O WP33 f a l l \\

Page 5 EPP-3 Issue 1 EMERGENCY PHONE TESTING CHECKLIST MONTHLY TESTS INITIALS LACBUR PABX Wisconsin Division of Emergency Government (1-266-3232) LACBWR PABX Vernon County Sheriff (1-637-2123) Microwave Network Vernon County Sheriff Iligh Frequency Radio Vernon County Sheriff ENS NRC Red Phone a. Control Room Extension b. Shif t Supervisor c. TSC Extension d. EOF Extension O ANNUAL TESTS LACBWR PABX NRC Region III (1-312-932-2500) SS-4 NRC Health Physics 11otline NAWAS Wisconsin Warning Center One i Site Sirens Full Test Including Various Areas in Plant i PERFORMED BY DATE I REVIEWED BY DATE (ll&S Supervisor) \\ ~ APPROVED BY DATE ( Emergency Planning Coordinator) i j WP33

l DPC [DPC \\ (MANNEEMENT>l DISmTCHER \\ IA ALMA [ Docx \\ U.S. t oDs CORR \\ oog MISC. SERVICES Y A,K FEDERAL iM-L MK j6 l k us. OLEM \\ \\ COAST \\ l l %{ we E!^ y/ \\ l I s s y an. ~ ~' ~ )s \\ \\ l /,/ / 'N 4, g l l "on" NA W EMERGEHCY / 1 l l / ) OPERATloNS / N g L B,C.F_gAf _ _ _ _ _ puM"'NL NO C Q~'- CO L 00M $sypggL MANNED CONTINUOUSLY) -- 84,Ef ( CENTER p '3g V,. sg.=,ge w ,A - CAL I s Nk (/ l 'ke ..s Te o%5dIrionAt E t/ lA 's ontws summTCENTER / lF g 5 z unicua m m , won s j g ^ s / l / I INS *$ / / l WM **'t Q W,^ I mE COUNTY / +A I En"vic7 s I i swE wh \\ l , y,' SHAPE KEY COMMUNICATION SYSTEMS f pesAsTer A A.PUBLIC TELEPHONE SERVICE SERvicar5 gu,p m, 21 INTI%/lNTER PLANT TEl.EntoNE SERVICE (PABX) ,/ f \\ {0 0P 7 ASSISTANCE C. PLANT PAGE D. DPC CARRIER-CURRENT volCE COMMUNICATIONS LufH AmeUUueCE MISC. $,cge,N,Cv) E. orc NiC,H rRE.UENCy RAoiO aaseiTA' s - Ce CEs F. DPC FICROWAVE INTERFACE TOTELER40NE SYSTEM G. NRC RED PHONE SYSTEM AAEDICAL H. NRC NEALTH PHYSLCS PHONE SYSTEM 4.N Es V I. NATiotlAL WARNING SYSTEM (NAWAS) FORMS OF COMMUNICATi&N AVAILABLE TOLACBWR l J. FM HANDl-TALKIES K. SHIP TOSHORE RADIO FIctPtt D-4 AGENCIES L. FACE TO FACE CONVERSATION p_ M. SITE SIRENS D-19}}

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