ML20073L164

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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-14A Re Release Rate Determination & EPIP-54 Re Govt Staffing at Emergency Operations Facility
ML20073L164
Person / Time
Site: Palo Verde  
Issue date: 02/08/1983
From: Bynum J, Lucia S
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML20073L169 List:
References
PROC-830208-01, NUDOCS 8304200568
Download: ML20073L164 (45)
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Text

{{#Wiki_filter:. Rsvicion 5 PALO VERDE NUCLEAR GENERATING STATION STATION MANUAL Title Division INDEX ( EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX CO?I BN

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O 4 f PALO VERDE NUCLEAR GENERATING STATION DIERGENCY PLAN Emergency Plan Implementing Procedures Index Revision 5 Page 1 of 3 Procedure Fo'rmer Date Number Number Procedure Title Rev. Effective EPIP-01 Emergency Organization 0 10/11/82 EPIP-02 Emergency Classification 0 12/10/82 EPIP-03 UNUSUAL EVENT Implementing Actions 0 10/06/82 ' PIP-04 ALERT Implementing Actions 0 10/06/82 EPIP-05 SITE EMERGENCY Implementing Actions 0 ?.0/06/82 EPIP-0 6 GENERAL EMERGENCY Implementing Actions 0 10/06/82 EPIP-07 Notification Process - UNUSUAL EVENT 0 12/ 10/8 2 EPIP-08 Notification Process - ALERT, SITE O 12/10/82 EMERGENCY or GENERAL EMERGENCY EPIP-09 EPIP-10 EPIP-il Technical Support Center / Satellite TSC 0 10/06/82 3 Activation EPIP-12 Operations Support Center Activation 0 10/06/32 EPIP-13 Emergency Operations Facility Activation 0 10/11/82 EPIP-14A Release Rate Determination 1 02/07/83 EPIP-1.4B Dose Assessment 1 12/23/82 EPIP-15 Protective Action Guidelines 0 10/06/82-EPIP-16 Onsite Survey and Sampling 0 10/06/82 EPIP-17 Offsite Survey and Sampling 0 10/06/82 EPIP-18 Emergency Exposure Guidelines 0 10/06/82 i EP IP-19 Onsite Evacuation 0 12/10/82 EPIP-20 Personnel Assembly and Accountability 0 12/10/82 .. :.. a :...... : o

t ~ PALO VERDE NUCLEAR GENERATING STATION EMERGENCY PLAN Emergency Plan Implementing Procedures Index Revision 5 Page 2 of 3 Procedure Po'rmer Date Number Number Procedure Title Rev. Effective EPIP-21 Search and Rescue 0 10/06/82 EPIP-22 Personnel Injury 0 11/12/82 EPIP-23 Pire Pighting 0 10/06/82 EPIP-24 Security 0 11/16/82 EPIP-25 Reentry for Emergency Operations 0 10/06/82 EPIP-26 Potassium Iodine (KI) Administration 0 10/06/82 EPIP-27 Sample Analysis at the Station 0 10/06/82 EPIP-28 Personnel Monitoring and Decontamination 0 10/06/82 EPIP-29 Area / Equipment Monitoring and 0 10/06/82 Decontamination EPIP-30 C EPIP-31 Recovery 0 12/10/82 EPIP-32 EPIP-33 Offsite Assistance 0 12/06/82 0 10/06/82 EPIP-34 Transportation Accidents EPIP-35 Review, Update and Revision of the PV5GS 0 11/02/82 ~ Emergency Plan EPIP-36 Emergency Preparedness Training 0 10/06/82 EPIP-37A Emergency Preparedness Drills 0 10/06/82 EPIP-37B Emergency Preparedness Exercises 0 11/02/82 EPIP-38 E. argency Equipment and Supplies Inventory 0 10/11/82 EPIP-39 Emergency Operations Director (EOD) 0 12/10/82 EPIP-40 Administrative and Logistics Coordinator 0 12/10/82 (ALC) ,4. .z. Q.

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s \\ ~ PALO VERDE NUCLEAR GENERATING STATION l EMERGENCY PLAN ~ Emergency Plan Implementing Procedures Index Revision 5 Page 3 og 3 Procedure Fo'rmer Date Number Number Procedure Title Rev. Effective EPIP-41 Radiological Assessment Coordinator (RAC) 0 12/10/82 EPIP-42 Technical An'alysis Coordinator (TAC) 0 12/10/82 EPIP-43 Radiological Assesament Communicator 0 12/10/Rt. (RACom) EPIP-44 TSC Liaiso.n Engineer (TLE) 0 12/10/82 EPIP-45 Government Liaison Engineer (GLE) 0 12/ 10/82 EPIP-46 EOF Contact 0 12/10/82. EPIP-47 Logistics Communicator 0 12/10/82 EPIP-48 Security Coordinator 0 12/10/82 EPIP-49 Dosimetry Clerk 0 12/10/82 EPIP-50 Status Board Keeper (SBK) 0 12/10/82 EPIP-51 Of fsite Technical Representative (OTR) 0 01/27/83 EPIP-5 2 ENC Technical Advisor 0 12/10/82 EPIP-53 Government Staffing at TSC 0 02/08/83 EPIP-54 Government Staffing at EOF 0 02/08/83 i i EPIP-55 TSC/ EOF Personnel Identification 0 12/10/82 9 .~..._.....u. -. -.... s :.,.. c:4.,.a.. .u'.. b

PVNGS EMERGENCY PLAN [ROCEDURE IMPLEMENTING PROCEDURE gp1p_133 REVISION RELEASE RATE DETERMINATION l 1 Page 1 of 25 ASSIGNED COPY 9 F-fA PVNGS = 1 APPROVED BY: IkIld3N Quf/t DATE / 3/ el v p;;.;- aa DN-1620A/0180A NtW ADA(SISD

PVNGS EMERGENCY PLAN QoCEmse IMPLEMENTING PROCEDURE EPIP-14A-REVISION RELEASE RATE DETERMINATION 1 Page 2 of 25 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 4

2.0 REFERENCES

4 3.0 LIMITATIONS AND PRECAUTIONS 4 4.0 DETAILED PROCEDURE 6 4.1 Personnel Indoctrination 6 4.2 Prerequisites 6 4.3 Ins tructions 6 Appendix A - Release Rate Determination From the Turbine 14 Building PLANT VENT Appendix B - Release Rate Determination from the condenser 15 l Air Removal System Appendix C - Release Rate Determination from the Fuel Building 16 Ventilation Exhaust Appendix D - Release Rate Determination from Main Steam System 17 Appendix E - Release Rate Determination from Containment 18 Utilizing Containment Area Monitors or Hand-Held Ins trumenes Appendix F - Ratio of Total Iodine / Noble Gas Release Rates 19 i Appendix G - Ratio of I-131/ Total Iodine Release Rates 20 Appendix H - Containment. Exposure Race 21 Appendix I - Containment Noble Gas Release Rate 22

t PVNGS EMERGENCY PLAN [ROCEDURE o IMPLEMENTING PROCEDURE. Eyrp_tur.. ~ REVISION RELEASE RATE DETERMINATION 1 Page 3 of 25

  • APPENDICES (Cont'd)

Appendix J - Plant Vent Flow Diagram 23 Appendix K - Fuel Building Vent Flow Diagram 24 Appendix L - Condenser Air Removal Flow Diagram 25 4 4 O e 'd PV216000A (8182)

PVNGS EMERGENCY PLAN [ROCEDURE o IMPLEMENTING PROCEDURE 3,7p_13, ' REVISION RELEASE RATE DETERMINATION 1 Page 4 of -25 1.0 OILTECTIVE 1.1 This procedure describes methodology for the manual determination of airborne radioactive release rates from the turbine building (plant vent and condenser air removal), the fuel building and the main steam lines utilizing effluent monitor readings. If this is not possible, release rates will be inferred indirectly from area radiation monitors or hand-held monitors. Upon determination of release rates, actual or projected plume exposure dose rates, and integrated doses may be calculated in accordance with EPIP-14B, " Dose Assessment".

2.0 REFERENCES

2.1 Implementing References 2.1.1 EPIP-08, " Notification Process - ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY N. 2.1.2 EPIP-ll, " Technical Support Center Activation" 2.1.3 EPIP-12. " Operations Support Center Activation" 2.1.4 EPIP-13, " Emergency Operations Facility Activation" 2.2 Developmental References P 2.2.1 PVNGS Emergency Plan, Rev. 2 l 2.2.2 FSAR, Chapter 11,." Process and Effluent Radiological Monitoring and Sampling Systems" 2.2.3 NUREG-0737, " Clarification of TMI Action Plan Requirements" 3.0 LIMITATIONS AND PRECAUTIONS 3.1 If an airborne radioactive material release occurs under emergency conditions, the majority of material will be released through the plant vent with the possibility of minor amounts being released through the condenser air removal system, the fuel building exhaust or the main steam lines. (Q PV21H00A $$2) l l.

PVNGS EMERGENCY PLAN pceouse IMPLEMENTING PROCEDURE g gyrp_ m REVISION ~ RELEASE RATE DETERMINATION 1 Page 5 of 25 's 3.1.1 Activity release rate calculations for the condenser air removal system, fuel building exhaust system, main steam system and the turbine building plant vent should be conducted only if the appropriate monitors indicate elevated activities, and actual releases have occurred or are expected to occur. 3.2 Depending upon release sites, one or more of the following monitors must be properly functioning; 3.2.1 Ru-143; Low Range Plant Vent Monitor ly Ru-144; High Range Plant Vent Monitor 3.2.2 Ru-145; Low Range Fuel Building Exhaust Monitor i Ru-146; High Range Fuel Building Exhaust Monitor 3.2.3 Ru-141; Low Range Turbine Building Condenser Air Removal Monitor 1 Ru-142; High Range Turbine Building Condenser Air Removal Monitor t\\ m. 3.2.4 Ru-139A,B; 140A,B; Main Steam Line Monitors 3.2.5 Ru-148 or Ru-149; Con,tainment Area Monitors 3.3 Monitor readings must be obtained from the communication console in the Control Room or the console in the radiation protection office. 3.4 Determination of containment release rates utilizing containment area monitors Ru-148 or Ru-149 or hand-held instruments should be used only if effluent monitors are nonfunctional. 3.4.1, Plant vent releases may be calculated by correlating i actual containment exposure rates to projected containment exposure rates and release rates. Projected exposure and release, rates were calculated assuming a design basis loss l of coolant accident (LOCA) based upon NUREG-0737. The entire release is assumed to be through the plant vent. l 3.5 " Effective age" refers to the time after core shutdown. Release rates will vary as a function of " effective age". 3.6 The accuracy of plant vent monitors is +25% and the accuracy of containment area monitors is +20%. Therfore, release rate y calculations can be limited to 2 significant figures. l Pv2MooA talen -3 E

PVNGS EMERGENCY PLAN '[ROCEDURE IMPLEMENTING PROCEDURE. I . tyrp_ tax - REVISION RELEASE RATE DETERMINATION 1 Page 6 of ~25 ~ 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination 4.1.1 As delineated in EPIP-01, the Radiation Protection Technician (affected unit) will be responsible for initial offsite' dose calculations and/or projections. 4.1.2 At an ALERT or more severe level, the TSC will be activated and 'the Radiological Protection Coordinator (at i the TSC) will be responsible for dose calculations and/or projections. 4.2 Prerequisites 4.2.1 An Alert or higher level e'mergency ha; been classified per the provisions of EPIP-02. 4.2.2 An actual or projected release of airborne radioactive material has occurred or will occur. t : \\~j 4.2.2.1 Add'itionally, release rates shall be determined upon significant changes (+20%) in monitor readings and at lA a minimum of every hour for effective. ages 0-10 hours and every 10 hours for effective ages 10-100 hours. 4.3 Ins tructions 4.3.1 Determine release point (s) from effluent monitor reading (s). Proceed to the appropriate section. Plant Vent Section Utilizing Ef fluent Monitor, 4.3.2. o Condenser Air Removal System, 4.3.3. o Fuel Building dentilation Exhaust, 4.3.4. o o Main Steam Lines, 4.3.5.. o Plant Vent or Containment Utilizing Containment Area Monitors or Hand-Held Ins truments, 4.3.6. .~ = s Pv24000A (8/82) --g

i PVNGS EMERGENCY PLAN [ROCEDURE IMPLEMENTING PROCEDURE sp rp_.43 REVISION RELEASE RATE DETERMINATION 1 Page 7 of 25 4.3.2 Determination of Activity Release Rate From the Plant Vent (Appendix A). 4.3.2.1 Obtain the noble gas air concentration in units of uCi/cc from the gross beta channel (Channel B) of monitor Ru-143 (low range), or Ru-144 (high range). l* Record this value on Appendix A, Column 2, Section A. 4.3.2.2 Obtain the I-131 air concentration, in units of uCi/cc from the I-131 channel of monitor Ru-143 or Ru-144. li - Record this value on Appendix A, Column 2, Section B. 4.3.2.3 Using Appendix J, " Plant Vent Flow Diagram", determine from indications in the control room which plant vent fan is "on". 4.3.2.4 Add together flow rates from plant vent fans shown in Appendix J that indi: ate "on" to get total plant vent flow. i ( 4.3.2.5 Multiply the monitor reading (uci/cc) by the vent flow rate (6.64 E+07 cc/sec, default value) to obtain the noble gas and/or I-131 release rate in uCi/sec. C9 avert to Ci/see utilizing the conversion o 1.'0E-06Ci/vci. 4.3.2.6 If the I-131 channel-is nonfunctional multiply the noble gas release rate by the appropriate conversion factors (Appendices F and G) to obtain the release rates of total radioiodines and I-131 (Section C). Calculation l RRNG =ANG x Flow Rate ec/see x 1.0E-06 Ci/uci RRTI = RRNG x C1 RR -131 = RRTI x C2 I Where: RR = noble gas release rate (Ci/sec) NG RRTI = total radioiodine release rate (Ci/sec) e PY24000A 181821 +

~ PALO VERDE NUCLEAR GENERATING [ROCEDURE o ^ STATION MANUAL N, EPIP-14A s t l REVISION RELEASE RATE DETERMINATION 1 Page 8 of 25 - RR _131 = iodine.131 release rate (Ci/sec) I ANG

noble gas air concentration (uci/cc) from' monitor Ru-143 or Ru-144 Flow Rate = flow rate ec/sec; plan,t vent flow rate

6.64E+07 cc/sec (default value) or (operating vents x flow rates) 1.0E-06 Ci/uCi = conversion from uCi to Ci C1 = ratio of total iodine / noble gas release rates (Appendix F) C2 =' ratio of I-131/ total iodine release rates (Appendix G) 4.3.3 Determination of Activity Release Rate From the Condenser Air Removal System (Appendix B). % _./ 4.3.3.1 Obtain the noble gas air concentration ANG, in units of uCi/cc from the gross Beta channel (Channel B) of monitor Ru-141 (low range) or Ru-142 (high range). Record this value on Appendix B, Column 2. 4.3.3.2 Using Appendix L " Condenser Air Removal Flow Diagram" determine from indications in the control room which condenser pumps are "on". 4.3.3.3 Add together flow rates from condenser pumps shown on Appendix L that indicate "on", also add 1300 for the steam packing exhausters to obtain the total air removal flow rate. 4.3.3.4 Convert air flow to ec/see by multiplying the CFM by 472. If the pump "on" indications are not known, use the 6.99ES cc/sec air flow default value. Record the vent flow rate in column 3. 4.3.3.5 Convert to Ci/see utilizing the conversion factor 1.0E-06 Ci/uci and recording the result in colum 5. d Pv2400o AEV 8/82

PALO VERDE NUCLEAR GENERATING - @'esouRe 7, . STATION MANUAL EPIP-14A REVISION RELEASE RATE DETERMINATION 1 Page 1/ of 25. 4.3.3.6 To calculate total Iodine release rate, multiply.the noble gas release rate by the " Total I/NG" ratio obtained from Appedix'F. The " Total I/NG" ratio is related to the effective age at time ot release. 4.3.3.7 To calculate the I-131 release rate, multiply the total Iodine release rate by the I-131 total iodine ratio obtained from Appendix G. The I-131 iodine ratio is related to the effective age at the time of release. Calculation RRNG =ANG x Flow Rate ec/sec x 1.0E-06 Ci/uci = RRNG x C1-RRTI RR -131 =RTI x C2 I (Refer to Section 4.3.2.5 for parameter descriptions). ] 4.3.4 Determination of Activity Release Rate From the Fuel Building Ventilation Exhaust (Appendix C). 4.3.4.1 Obtain the noble gas air concentration, (Channel B), in units of uCi/cc from the gross B channel of l monitor Ru-145 or Ru-146. Record this value on Appendix C, column 2. a 4.3.4.2 Determine the Fuel Building Ventilation flow rate-using Appendix K, " Fuel Building Vent Flow Diagram". indicator lights' showing which fans are on are located on panel B02 in the control room. o Record the flow rate in column 3 of Appendix C. o Multiply the monitor reading (uCi/cc) by the ventilation exhaust rate to obtain the noble gas release rate uCi/sec. 4.3.4.3 To calculate total Iodine release rate, multiply the i noble gas release rate by the " Total I/NG" ratio l obtained from Appedix F. The " Total I/NG" ratio is l related to the effective age at time of release. l Q l i l Pvris-um Mv.t.ier

PALO VERDE NUCLEAR GENERATING Qcaouse ' STATION MANUAL EPIP-14A m REVISION RELEASE ' RATE DETERMINATI0N ~ 1 Page-10 Sf 25. 4.3.4.4 To calculate the I-131 release rate, multiply the total Iodine release rate by the I-131 total Iodine ratio obtained from Appendix G. The 1-131 Iodine ratio is related to the effective age at the time of release. Calculation = A( G) x Flow Rate ec/sec x 1.0E-06 Ci/uci l RRNG RRTI = RRNG x C1 I = RRTI x C2 RR -131 (Refer to section 4.3.2.5 for parameter descriptions ~) 4.3.5 Determination of Activity Release Rate From the Main Steam ~ Lines (Appendix D). 4.3.5.1 Obtain the exposure rate (mr/hr) from the main steam line monitor (s) Ru-139A,B or Ru-140A,B. Record these values in column 2 of Appendix D. 4.3.5.2 Select the appropriate correction factor (based on effective age) from the following table and record in column 3 of Appendix D. i 4.3.5.3 Multiply the monitor reading (s) (mr/hr) by the correction factor and record the resulting " corrected l monitor reading" in colt.mn 4 of Appendix D. Effectiva Age (hr) Correction Factor 0 - 7.9 6.6 8.0 - 95.9 8.4 i 96.0 - 191.0 22.0 192.0 - 719.9 21.0 1 720.0 - 14.0 4.3.5.4 Record the steam flow (s) (103 lbs/hr), from meters on the steam generator portion of the main cont.rol room console, in column 6. l i ( 1 e' t l

PALO VERDE NUCLEAR GENERATING 2CEWRE STATION MANUAL EPIP-14A REVISION i RELEASE RATE DETERMINATION 1 Page 11 of 25 - 4.3.5.5 Carry out the calculations in Appendix D to get the " Noble Gas Release Race" (uCi/sec in column 8. o The conversion factor in column 5 is used to convert the corrected exposure rate in mr/hr to a concentration in Ci/103 lbs steam (this coversion factor will be supplied when the instrument is calibrated). o The coversion factor of 3600 sec/hr is used to convert the noble gas release rate in Ci/hr to Ci/sec. 4.3.5.6 Record the ratio of total idoine to noble gas (from Appendix F) in column 9 of Appendix D. 4.3.5.7 Multiply the noble gas release rate (Ci/sec by the ratio of total iodine to noble gas and by the factor of 4 indicated on Appendix D to get the total iodine release rate which is entered in column 10. -m o The factor of 4 is used to conmect for the assumptions used when Appendix F was generated (i.e., only 1/2 of iodine in core inventory is released to containment during a LOCA and 1/2 of the released iodine plates out). 4.3.5.8 Record the ratio of I-131 to total iodine (from Appendix G) in column 11 of Appendix D. 4.3.5.9 Multiply the total Iodine release rate (Ci/sec) by the ratio of I-131 to total iodine to get.the I-131 release ratio (Ci/ sect which is recorded in column 12 of Appendix D. 4.3.5 Det9rmination of Activity Release Rate From the Plant Vent Utilizing Containment Area Monitors Ru-148 Or Ru-149 or Hand-held Instruments (Appendix E). 4.3.6.1 This method should be utilized only if effluent j monitors are nonfunctional. I f ev24@O REV.8/82

e O PROCEDURE PVNGS EMERGENCY PLAN NO. IMPLEMENTING PROCEDURE EPIP-14A ~ REVISION RELEASE RATE DETERMINATION 1 Page 12 of'25 '- 4.3.6.2 Obtain the actual exposure rate, E(act) from the high range area monitor Ru-148 and/or Ru-149 in R/hr or the sum of both divided by two for an average over the containment. Record this value on Appendix E, Column 2. If these monitors are nonfunctional and radiological conditions allow, as determined by dose rate measurement at outer containment door, obtain a contact dose rate measurement (R/hr) with a hand-held beta / gamma (shield closed) instrument at the inner containment door pyrex viewing window. Multiply by the appropriate correction factor below. Record on Appendix E, Column 2. Effective Age' (hr) . Correction Factor 0 - 96 1.5 1 96.0 - 192.0 3.4 19 2 - 720 1.6 4.3.6.3 Determine the projected containment exposure rate (LOCA), E(pro) as a function of " effective age" using the " Total" line from Appendix H. Record this value on Appendix E Column 3. 4.3.6.4 Determine the projected noble gas release rate (LOCA), NGpro using the noble gas line from Appendix I. R Record this value on Appendix E, Column 4. 4.3.6.5 Calculate, release rates as follows: RRNG ACT = E(act) - E(pro) x RNGpro ~ RRrr = RRNG ACT x Ct RR _t31 = RRTI x C2 I Where: RRNG ACT = noble gas release rate (Ci/sec) = total radioiodine release rate RRTI (Ci/sec) l l RRg_131 = I-131 release rate (Ci/sec) = actual high range monitor EACT l reading from Ru-148 and/or Ru-149 in R/hr or corrected a hand-held instrument reading evm.ceoA $sa i

PROCEDURE PVNGS EMERGENCY PLAN NO. IMPLEMENTING PROCEDURE epip_144 REVISION RELEASE RATE DETERMINATION 1 Page 13 of 25 - E(pro) projected containment exposure = rate (LOCA) at " effective age" from Appendix H RNG pro Projected Noble Gas release rate (LOCA) at " effective age" j from Appendix I C1 ratio of total iodines / noble gas = release ratea (Appendix F) C2 ratio of I-131/ total iodine = release rates (Appendix G) e 9 e G Y M N (W E O

t ( t. 4 -7 rO REi. EASE RATE DETERNINATION FR001 THE TURSINE RUlt. DING, FI.AKF VENT Nonttore Ru-143 or Ru-144 g c=: [Tl Effective Noble Gas Flant' Vent Converston Noble Gas q Age Air cone Flow Rate Factor Release Rate h

== (hr) (uC1/cc) - (cc/sec)* (uct to C1) (Ct/sec) N OC I NOTE: If I-131 monitor is inoperable, 2 O Section A x x 1.0E-6 = ts F complete Section C only, otherwise g x x 1.0E-6 = complete only Sections A and R. E x x 1.0E-6 = w 3 =g 3 x x* 1.0E-6 = H 8 1 bO x x 1.0E-6 = H >m x x 1.0E-6 = 5 FZ 25 m Effective I-131 Flant Vent Converstoa 1-131 3 Age Air Conc Flow Rate Factor Release Rate (hr) (uct/cc) (cc/sec)* (uCi to C1) (C1/sec) p q Section R x x 1.0E-6 2 = x x 1.0E-6' = Q x x 1.0E-6 = x x 1.0E-6 =

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x 1.0E-6 g Oy x x 1.0E-6 = u> m o ~ m m Effective Noble Cao Flant Vent Conversion Noble Ces Tot Iodine I-131 2 y h Age Air Conc Flow Rate Factor Release Rate Tot 1/MG Relesse Rate 1-131/ Tot 1 Release Rate 8 2) 7 A (h r) (uCt /cc) (cc/sec)4 (oC1 to C1) (Ct/sec) App F (Ct/sec) App C (Ci/sec) g Scaction C = = x x x 1.0E-6 = x ~ = x = x x 1.0E-6 = x = x = x x 1.0E-6 = x 2

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  • Honitor Ru-145 ventilation exhaust = 2.17E + 7 (cc/sec)

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i 1 l PR CEDURE [ PVNGS EMERGENCY PLAN O* APPENDIX I IMPLEMENTING PROCEDURE gprp_154 p,, 1,, 1 REVISION RELEASE RATE DETERMINATION 1 Page 22 of 25 * ' CONTAINMENTNOSt.t:UAs.TOTALlODINES. ANOI-Gl RELEASE AATES (Ci/sec) AS A FUNCTION OF EFFECTIVE AGE (hr), PVNGS 8 101

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\\ l PVNGS EMERGENCY PLAN PROCEDURE j NO. APPENDIX J ~' IMPLEMENTING PROCEDURE ' EPIP-14A Page 1 of I s REVISION l RELEASE RATE DETERMINATION 1 Page 23 of 25 . PLANT VENT FLOW DIAGRAM RU 143 k 44 RADIATION 5 MONITOR A HAN-JOIA 28,380 CFM k AUX BUILDING NORMAL 56,750 CFM ~ EXHAUST AIR HAN-JOI-B ^ FILTRATION Q UNITS 28,380CFM HRN-JOI-A 25,500 CFM RAOWASTE BUILDING AORMAL n EXHAUST AIR -- *- + S1,000 CFM FILTRATION HRN-JOlB UNITS g 25,500CFM l CPN-JOI-A,g,ggg (py ~' CONTAINMENT W REFUELING u 33,000 CFM PURGE NORMAY CPN-JO + EXHAUST FANS N 1 SOOCFM ' M CONTAINMENT F0WER ACCESS CPN-JO2-PURGE NORMAL EXHAUST AIR S = FILTRATION UNITS - 22OO CFM CONVERSION FACTOR FOR CONVERTING FROM CFM TO CClSEC IS 472 (CC SEC) CFM g Pv2164004 (est2) g

~ PVNGS EMERGENCY PLAN Q~cEouaE APPENDIX K IMPLEMENTING PROCEDURE EPIP-14A Paste 1 of 1 REVISION RELEASE RATE DETERMINATION 1 Page 24 of 25 ' FUEL BUILDING VENT FLOW DIAGRAM TO ATMOSPHERE N HFN-J01-A RU 21,750 CFM I4S ( = 14 6 '00 FUEL BUILDING NORMAL EXHAUST FANS HFN-JOI-B Y ,750 CFN 1 6000_CFM h HFA-JOI j 6000 CFM FUEL BUILDING & AUY BUILDING 6000 CFM EXHAUST + ESSENTIAL AIR

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~ PROCEDURE PVNGS EMERGENCY PLAN N O. QENDI IMPLEM.ENTING PROCEDURE gprp_1u , 1 REVISION RELEASE RATE DETERMINATION 1 Page 25 of 25 ' CONDENSER A!R REMOVAL FLOW DIAGRAM TO ATMOSPHERE RU 141 14 2 9 g. I STEAM VACUUM PUMP A PACKING EXHAUST-CONDENSER 60CFM ER DRAIN TAN!.' n[ -+- 1300 CFM A 5 STEAM %J l PACKING EXHAUST ' K ~ERS VACUUM PUMP B n60 CFM CONDENSER y TO ATMOSPHERE B g -+- J SVACUUM PUMP C 60 CFM ' ~ ~ ~ CONDENSER E D' VVACUUM PUMP O + n 60 CFM E D CONVERSION FACTOR - CFM X 472 ( CC /SEC)= C CFM 'W" PV214000A (4/42) ..~^ . -..-e.

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1 PVNGS EMERGENCY PLAN PROCEDURE N O. r IMPLEMENTING PROCEDURE EPIP-54 REVISICN COVERNMENT STAFFING AT EOF 0 Page 2 of,.9 ~ TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 OBJECTIVE 3 2.0 REFERENbES 3 3.0 LIMITATIONS AND PREC\\UTIONS 3 4.0 DETAILED PROCEDURE 3 41 Personnel Indoctrination 3 4.2 Prerequisites 4 4.3 Instructions 4 f-APPENDICES Appendix A - Route from Phoenix to PVNGS 6 Appendix B - Site Access Route 7 Appendix C - EOF Floor Plan 8 Appendix D - EOF Emergency Control Center Equipment Iayout 9 e 0 /- Pv2HOOA im =, c.s.

PALO VERDE NUCLEAR GENERATING gcEmns /* STATION MANUAL EPIP-54 REVISION GOVERNMENT STAFFING AT EOF 0 Page 3 of 9 1.0 OBJECTIVE The objective of this procedure is to provide guidance to representatives of government agencies who report to the PVNGS Emergency Operations Facility and to the APS emergency personnel who are responsible for assisting government staff. This guidance is provided as an aid, not as a requirement to be enforced by EOF personnel.

2.0 REFERENCES

2.1 Implementing References 2.1.1 EPIP-13 " Emergency Operations Facility Activation" 2.2 Developmental References 2.2.1 NUREG-0654, Rev. I " Criteria for Preparation and Evaluation /' of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.2.2 PVNGS Emergency Plan, Rev 2 3.0 LIMITATIONS AND PRECAUTIONS ( 3.1 Provision shall be made for a limited number of government employees in the EOF. This shall include representatives from the Nuclear Regulatory Commission (NRC), Federal Emergency Management Agency (FEMA) and State of Arizona. 3.2 Government employees entering the EOF shall be properly badged by Security prior to entry. . - -q 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination 4.1.1 NRC, FEMA and State of Arizona emergency response plans include provisions for sending representative to the Emergency Operations Facility. 4.1.2 APS is responsible for allowing access, providing physical facilities for use by government staff, and for ongoing l / ( coordination and briefing of government staff. l l 4 4 em A 6+ N s e + O

PALO VERDE NUCLEAR GENERATING pceouse STATION MANUAL EPIV-54 REVISION GOVERNMENT STAFFING AT EOF 0 Page 4 of 9 4.2 Prerequisites 4.2.1 An ALERT or more severe emergency has been declared and procedure EPIP-13 is being implemented. 4.3 Ins t. ructions 4.3.1 State of Arizona representatives shall travel to PVNGS from

  • Phoenix, by automobile, using the route shown on the map in Appendix A.

4.3.2. NRC and FEMA representatives shall travel to PVNGS from Phoenix Airport, by automobile, using the route shown on the map in Appendix A. ' 4.3.3 Government representatives shall report to the PVNGS Security Building as shown on the map in Appendix B upon arrival at the site. / 4.3.4 Security Building staff shall register the government representatives and issue Visitor Passes in accordance with standard security procedures. 4.3.5 Security Building staff shall notify the Security Coordinator at the EOF and arrange to escort the government representatives to the EOF (Administration Annex Building basement). 4.3.6 At the EOF, the Security Coordinator shall issue an Emergency Personnel Identirication Badge labeled with the appropriate agency name. (Note that all key APS employees at the EOF shall also wear badges labeled with their emergency position titles to assist government staff and others in locating appropriate personnel,.) .i 4.3.7 The Dosimetry clerk shall issue radiation Dosimetry to' the government staff. 4.3.8 The Emergency Operations Director shall arrange for a briefing for government staff upon their arrival. 4.3.9 The Administrative and Logistics Coordinator shall direct the government staff to appropriate working locations in accordance with Appendix C and Appendix D. The f Administrative and Logistics Coordinator shall also identify communications equipment and other resources available to the government staff. %esw

PVNGS EMERGENCY PLAN Tcsune IMPLEMENTING PROCEDURE EPIP-54 's REVISION GOVERNMENT STAFFING AT EOF O Page 5 of,9 4.3.9.1 State of Arizona Access shall be provided to the following as necessary: 1 Dedicated voice line to ARRA 2. Dedicated voice line to ADES 3. State REAT radio system 4. Facsimile transmission to ARRA and ADES 5. Commercial telephone 4.3.9.2 Nuclear Regulatory System Access shall be provided to the following as necessary: f, 1. ENS line to NRC headquarters i 2. HPN line to NRC regional office and headquarters 3. Facsimile transmission system 4. Commercial telephone 4.3.9 3 Federal Emergency Management Agency Access shall be provided to the following as necessary: 1. Dedicated voice line to ADES 2. Commercial telephone -7 4.3.10 The Technical Analysis Coordinator shall be responsible for coordination with government staff and for providing periodic briefings on the condition of plant systems and the status of corrective actions. 4.311 The Radiological Assessment Coordinator shall be responsible for providing periodic briefings concerning radiological assessment and protective actions and for coordinating with State of Arizona representatives for radiological assessments. PY1't@OA i&821 .i.,._._

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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX B IMPLEMENTING PROCEDURE EPIP-54 Page 1 of 1 REV!SION GOVERNMENT STAFFING AT EOF O Page 7 of 9 SITE ACCESS ROUTE from Interstate 10 Westbound ["= f 1I f_ .i E a e (EOF) 5 E e 2 Administration e e Annex 3 'D Technical Support g O Center (Underground) a y Security Building i Parking "\\ = y 1 \\ l Southern (Last) l Gate to PVNGS Site 4 N PV2 H OCA iten -,,w .e.*.- i o

i i PVNGS EMERGENCY PLAN pnocEcuRE N O. APPENDIX C e IMPLEMENTING PROCEDURE EPIP-54 Page 1 of 1 ] REVISION COVERNMENT STAFFING AT EOF O Page 8 of,,9 EOF FLOOR PLAN I r 1 ll 1

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F PVNGS EMERGENCY PLAN PROCEDURE NO. IMPLEMENTING PROCEDURE APPENDIX D \\ EPIP-54 Page 1 of 1 REVIS4CN GOVERNMENT STAFFING AT EOF 0 Page 9 of 9 EOF EMERGENCY CONTROL CENTER EQt/IPMENT LAYOUT s y (2 lines) q, a 7.. .Q d M A5 M ze a[pa M .ti g,.- 1 g% F o ~~ g 4 l t a ~ .N Q ,(. ley. b* = 7 O W*R Communications 7 4 1 NAN M_ p y 2 EC/EOo 4 3 RIM Terminal Q 4 ENC Facsimile / 5 McLhe h.94 6 Voice circuit (411, ARRA, AD: ~ t. 7 Facsimile & Backup Table Personnel Locations (411, ARRA, ADES) A. Emergency' Operations Director 8 Technical Line B. Administrative and Logistics Coordinator 9. TSC Line C. Logistics Communicator 10 Environmental Line D. Government Liason Engineer 11. C.R. A.C.S. Terminal E. EOF Contact 12 Base Station Radio F. Security Coordinator 13 CR Line G. Technical Analysis Coordinator 14 S.P.D.S. Terminal H. Status Board Keeper 15 STSC Line I. Radiological Assessment Coordinator

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1 ~ ~ PVNGS EMERGENCY PLAN QocEcune j IMPLEMENTING PROCEDURE EPIP-53 REVISION GOVERNMENT STAFFING AT TSC o p,g, y of,,7 ASSIGNED COPY PVNGS 2-9 A / 's, A i 1 e l APPROVED BY: - t,y)LLCH{. @Ud DATE ,,,DATE EFFECTIVE ./, 7/, [ J , 9,,9 F 3 [ DN-3858A/0295A

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e PVNGS EMERGENCY PLAN PROCEDURE N O. IMPLEMENTING PROCEDURE EPIP-53 s REVISICN GOVERNMENT STAFFING AT TSC O Page 2 of,7 TABLE OF CONTENTS SECTION PACE NUMBER .1. 0 OBJECTIVE 3 '2. 0 REFERENCES 3 3.0 LIMITATIONS AND PRECAUTIONS 3 4.0 DETAILED PROCEDURE 3 4.1 Personnel Indoctrination 3 4.2 Prerequisites 3 4.3 Instructions 4 7, 1 APPENDICES Appendix A - Route from Phoenix to PVNGS 5 { Appendix B - Site Access Route 6 Appendix C - TSC Floor Plan 7 / l l Pv21ee0A 488 s. s-, s..

6 PALO VERDE NUCLEAR GENERATING PROCEDURE NO. STATION MANUAL EPIP-53 REVISION GOVERNMENT STAFFING AT TSC 0 Page 3 of 7.- 1.0 OBJECTIVE The objective of this 7tocedure is to provide guidance to representatives of government agencies who report to the PVNGS Technical Support Center (TSC) and to the APS emergency personnel who are responsible for assisting government staff. This guidance i's provided as an aid, not as a requirement to be enforced by TSC personnel.

2.0 REFERENCES

2.1 Implementing References 2.1.1 EPIP-11 " Technical Support Center / Satellite TSC Activation" 2.2 Developmental References 2.2.1 NUREG-0654, Rev. 1 " Criteria for Preparation and Evaluation s' of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.2.2 PVNGS Emergency Plan, Rev 2 3.0 LIMITATIONS AND PRECAUTIONS 3.1 Provision shall be made for a limited number of NRC employees in the TSC. All other government staff shall report to the EOF. 3.2 Government employees entering the TSC shall be properly badged by Security prior to entry. 4.0 DETAILED PROCEDURE 4.1 Personnel Indoctrination 4.1.1 NRC plans to place an Emergency Response Team in the TSC. Previsions have been made to locate a limited number of NRC ~ staff in the TSC. 4.1.2 The Emergency Coordinator is responsible for interfacing with the NRC Team Leader at the TSC. He may delegate this f responsibility to another member of the TSC staff. -y::

i PVNGS EMERGENCY PLAN pcame IMPLEMENTING PROCEDURE EPIP-53 REVISION GOVERNMENT STAFFING AT TSC O Page 4 of,7 4.2 Prerequisites 4.2 1 An ALERT or more severe emergency has been declared and procedure EPIP-ll is being implemented. 4.3 Instructions 4.3.1 The NRC Response Team shall travel to PVNGS from Phoenix Airport, by automobile, using the route shown on the map in Appendix A. 4.3.2 NRC representatives shall report to the PVNGS Security Building as ~ shown on the map in Appendix B upon arrival at the site. 4.3.3 Security Building staff shall register the NRC representatives and issue Visitor Passes in accordance with standard security procedures. 4.3.4 Security Building staff shall notify the Security Director at the TSC and arrange to escort the government representatives to the TSC. m 4.3.5 At the TSC, the Security Director shall issue an Emergency Personnel Identification Badge labeled with the appropriate agency name. (Note that all key APS employees at the TSC shall also wear badges labeled with their emergency position titles to assist government staff and others in locating appropriate personnel.) 4.3.6 The Emergency Coordinator shall arrange for a briefing for NRC representatives upon their arrival. The Emergency Coordinator or designee shall direct the NRC staff to the appropriate location (see Appendix C) and identify the ENS telephone for use by NRC staff. 4.3.7 The Technical Engineering Coordinator shall provide periodic briefings on plant status and corrective actions. 4.3.8 The Radiological Protection Coordinator shall provide periodic briefings on radiological assessment and protective actions. PV2140004 48#823 e ,p

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PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX A IMPLEMENTING PROCEDURE EPIP-53 Page 1 of 1 REVISION GOVERNMENT STAFFING AT TSC O Page 5 of' 7 ROUTE FROM PHOENIX ,TO PVNGS ~ ci" laterchange E No. SS ~ 3d laterchange A A fD 1-' 90 g g' AoGOODYEAR owl;ATEnssuno A sUCKEYE RD. A A@ 8 6 5 SKY PVNGS A q HARBOR g g INT L AIRPORT A - -A distance in miles F m m <*en ...,.e.

~ PVNGS EMERGENCY PLAN PROCEDURE NO. APPENDIX B IMPLEMENTING PROCEDURE EPIP-53 Page 1 of 1 REVISION GOVERNMENT STAFFING AT TSC 0 Page 6 of.7 SITE ACCESS ROUTE ) from interstate 10 Westbound ' f+ = 4 A If q E o (EOF) E Administration 3 e-Annex D 3 - Technical Support Y O Center (Underground) n Security Building N Parking \\ = .2 H \\ Southern (Last) Gate to PVNGS Site. 4 f. N m-am

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