Text

Revised Emergency Plan Implementing Procedures. Rev 4 to PMP-2081 EPP.105 Through Rev 2 of RMT-2080-TSC-001
	ML031470266
Person / Time
Site:	Cook
Issue date:	05/19/2003
From:	; Indiana Michigan Power Co
To:	; Office of Nuclear Reactor Regulation
References
	-nr, -RFPFR, AEP:NRC:3054-07
	Download: ML031470266 (176)
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{{#Wiki_filter:REVIEW AND APPROVAL TRACKING FORM Procedtire Information: Number: PMP-2081 EPP.105 Revision: 04 Change: 01

Title:

Initial Core Damage Assessment Category:. EI Change (Full Procedure) with Review of Change Only L Correction (Full Procedure) X Change (Page Substitution) with Review of Change Only D Correction (Page Substitution) L New Procedure or Change with Full Review a Cancellation L Superceded By: l Required Reviews: l Operations E] ALARA Nuc. Doc. Management L Maintenance L Training L None Required EI Design Engineering l Surveillance Section NUCLEAR RECO DS

Plant Engineering L Performance Assurance MANAGEMENT SE TION 3 Chemistry/RP 3 Business Services Procedure Group JUN 1 6 200 L Other: (Includes Technical Reviewer Determined Reviews)

CONTROLLED DOCUM CNTl Writer Task`Reviews: Revision Summary attached? 3 Yes Safety Screening complete? SS/SE Tracking No: 256Dc 13- ) I3 Yes E] Exempt L N/A Implementation Plan developed? (Ref. Step 3.4.17) 0 Yes 3 N/A Periodic Review conducted? (Da Sheet Complete) L Yes 3 No Cognizant Org Review. Date: (/ 6 /oo Technical Review: Date: 61 / Ops Mgr Concurrence: Date: 42/4 l Owner Concurrence: Date: lo /q /cD O Writer Review: Date: g j co Aprovals: 7 7 PORC Review Required: 3 Yes L No Mtg. No.: $32 5 l Approval Authority Review/Approval: T< .L K Date: , /S /6I ) Effective Date: /l4/Cr Page ( of .-.. -Office hiform -,T r-or-racking Ony;;-.Not Patot Form ' This form is derived from the information in PMP-2010.PRC.002, Procedure Correction, Change, and Review, Rev. 5, Data Sheet 1, Review and Approval Tracking Form.

REVISION

SUMMARY

-Number: PMP-2081 EPP.105 Revision: 04

Title:

Initial Core Damage Assessment Section or Step Change/Reason For Change

3.9 Change

Added step 3.9 to the Reference section of the procedure. Reason: The reference to the Design Information Transmittal (DIT) was added to this section to help track the reference to future revisions. The DIT directly references the approved calculation DC-D-3200S-227 Revision 5. This is a correction per PMP 2010 PRC.002 step 3.1.6.a.15. Appendix E.4 Change: The Containment Sump Volume vs. Containment Sump Level Indication graph and the Containment Volume vs. Containment Level Indication graph are being updated to reflect calculations performed under DC-D-3200S-227 Revision 5. Reason: During the review of containment sump issues the team assigned to the review indicated the two above referenced graphs in PMP-2081 EPP. 105 "Initial Core Damage Assessment" were not correct and needed updating based on changes to the flow paths for the Containment Sump Level Indicators and the Containment Level Indicators. Design changes to the plant (i.e., Containment flood-up wall penetrations just above the floor) have altered the flow path for water once it overflows the containment and recirculation sumps. This change rectifies the correlation between containment and containment sump level indication and containment volume. The changes to the graphs will not effect the method used to determine core damage. See Design Information Transmittal (DIT) DIT-B-01288-00 for detail information. Change: Reason: Change: Reason: OfficeInformation For Form Tracking Only -.Not Part of Form This is a free-form as called out in PMP-2010.PRC.002, Procedure Correction, Change, and Review, Rev. 5. Page or L Change: 01

r-= INDMA aMWHIGAM POWER NUCLEAR RECORDS MANAGEMENT SECTION AUG 11 1997 DONALD C. COOK NUCLEAR PLANT CONTROLLED PLANT MANAGER PROCEDURE COVER SHEET DOCUMENT PROCEDURE USAGE LEVEL OCONTINUOUS 'REFERENCE INFORMATIOr PMP 2081.EPP.1.05 I Revision No. I I,41nnLw InINr 4 TITLE INITIAL CORE DAMAGE ASSESSMENT SCOPE OF REVISION Procedure revised to completely include current analytical methodology for core damage assessment. SIGNATURES REVISION NUMBER PREPARED BY vC QUAUTY ASSURANCE SUPERINTENDENT APPROVAL PLANT NUCLEAR '§ 73$ SAFETY COMMITTEE PLANT MANAGER APPROVAL APPROVAL DATE ct3°q EFFECTIVE DATE /OI/J 3L

PMP2081 EPP.105 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER/EFFECTIVE CHANGE SHEETS Page 1 of 12 Revision 4 Page 2 of 12 Revision 4 Ci Page 3 of 12 Revision 4 Page 4 of 12 Revision 4 Page 5 of 12 Revision 4 Page 6 of 12 Revision 4 Page 7 of 12 Revision 4 Page 8 of 12 Revision 4 Page 9 of 12 Revision 4 Page 10 of 12 Revision 4 Page 11 of 12 Revision 4 Page 12 of 12 Revision 4 ATTACHMENT NO. 1 Page 1 of 2 Revision 4 Page 2 of 2 Revision 4 APPENDIX A Page 1 of 3 Revision 4 Page 2 of 3 Revision 4 Page 3 of 3 Revision 4 APPENDIX B Page 1 of 1 Revision 4 APPENDIX C Page 1 of 6 Revision 4 Page 2 of 6 Revision 4 Page 3 of 6 Revision 4 Page 4 of 6 Revision 4 Page 5 of 6 Revision 4 Page 6 of 6 Revision 4 APPENDIX D Page 1 of 8 Revision 4 Page 2 of 8 Revision 4 Page 3 of 8 Revision 4 Page 4 of 8 Revision 4 Page 5 of 8 Revision 4 Page 6 of 8 Revision 4 Page 7 of 8 Revision 4 Page 8 of 8 Revision 4 Page 1 of 2 Revision 4

PMP2081 EPP.105 PAGE NUMBER REVISION NUMBER/EFFECTIVE CHANGE SHEETS APPENDIX E Page 1 of 6 Page 2 of 6 Page 3 of 6 Page 4 of 6 Page 5 of 6 Page 6 of 6 Revision 4 Revision 4 Revision 4 Revision 4 Revision 4 Revision 4 C1 APPENDIX F Page 1 of 6 Page 2 of 6 Page 3 of 6 Page 4 of 6 Page 5 of 6 Page 6 of 6 Revision 4 Revision 4 Revision 4 Revision 4 Revision 4 Revision 4 Page 2 of 2 Revision 4

PMP 2081 EPP.105 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT

1.0 TITLE

INITIAL CORE DAMAGE ASSESSMENT 2.0 OBJECTIVE 2.1 The purpose of this procedure is to provide a method to classify and estimate the extent of core damage through measurement of fission products released to the coolant and containment atmosphere together with auxiliary measurements of core exit thermocouple temperature, water level within the pressure vessel, containment radiation monitors, and containment atmosphere hydrogen monitors. 2.2 Discussion Estimations of post accident core damage can be determined through a correlation of containment atmosphere radiation monitor readings to the appropriate NRC category of core damage. Estimations of post accident core damage can be determined through a correlation of reactor coolant core exit thermocouple temperature to NRC fuel damage categories. Additionally, estimations of post accident core damage can be determined through a correlation of PASS total measured hydrogen generated through clad oxidation to the degree of core damage. Finally, for estimations of post accident core damage utilizing fission product nuclide concentrations measured in samples obtained from the post accident sampling system, there are three factors to be considered which are related to the specific activities of the samples. These include the identification of the nuclides released from the core, the respective ratios of the specific activity of those nuclides, and the percent of the source inventory at the time of the accident which is observed to be present in the samples. The resulting estimate of core damage can be related to one or more of the ten NRC categories of core damage.

3.0 REFERENCES

3.1 Westinghouse Owner Group NUREG 0737, Item II.B.3 Post Accident Core Damage Assessment Revision 2, to WOG Methodology, November, 1984. Revision 4, page 1 of 12

PMP 2081 EPP. 105 3.2 D. C. Cook Post Accident Core Damage Assessment Methodology (developed by AEPSC), August, 1984. 3.3 The Gamma Rays of the Radionuclides, Volume 7, Erdtmann and Soyka, N.Y. 1979. 3.4 PMI-5042, Revision 3, Safety, Related Computer Software Control. 3.5 Memo from E. Neymotin to S. Brewer and T. Harshbarger of February 4, 1987; Procedure No. PMP 2081 EPP.105. 3.6 Memo from H. W. Jones to T. Andert dated October 18, 1990; Donald C. Cook Nuclear Plant PMP 2081 EPP.105, Attachment M and N Source Term Corrections for Extended Fuel Burnup and Increased Fuel Enrichment. 3.7 A Radioactive Decay Data Tables by D. C. Kocker, Oak Ridge National Laboratory, 1981, DOE/TIC-11026. 3.8 Core Damage Assessment, Rev. 1 REM Technology, 1993. 3.9 AEP Design Information Transmittal (DIT), DIT-B-01288-00. C Cl 4.0 RESPONSIBILITIES 4.1 The Plant Evaluation Team in the Technical Support Center will be responsible for initial assessment of core damage based on containment radiation monitor readings and post accident sample results. The Initial Assessment Group may assume this responsibility as a backup measure. 4.2 Records generated from this procedure are to be turned over to the emergency plan coordinator. 5.0 LIMITIATIONS/PRECAUTIONS 5.1 The results from this procedure have limited accuracy based on the assumptions made in the core damage assessment methodology. Each sample describes a static event in the system. Multiple static samples over an extended time period will give a better indication of the dynamic event. Samples that will be most indicative of actual core damage will be taken under stabilized plant conditions. 5.2 Hydrogen measurement is not a unique indicator of the amount of core clad oxidation sinte a mixture of hydrogen generated within the core by clad oxidation and also hydrogen from the radiolytic decomposition of Revision 4, page 2 of 12

PMP 2081 EPP.105 in the containment atmosphere. 5.3 Four stages of reactor core damage are categorized by the NRC. 5.3.1 No Damage Indications of core damage in these categories are halogen spiking and tramp uranium where typically less than one percent of the total core inventory is released to the coolant. A defective fuel fraction can be estimated. 5.3.2 Clad Rupture/Gas Gap Release An increase in reactor coolant noble gas concentration will be observed. In the event of a LOCA, containment radiation monitor indications will be elevated. Containment building pressure and temperature increase are an additional indication of a continuing leakage from the primary system. 5.3.3 Grain Boundary/oxidation/overheat Temperatures in the RCS as indicated by Incore Thermocouples exceed saturation temperature as the water level in the core drops and the fuel temperature increases. Containment area monitor indications increase noticeably from normal levels. This indicates probable fuel cladding damage (failure) in the hotter regions of the core releasing fission products from the fuel pellets. Containment building pressure and/or temperature will be at abnormal high levels. The coolant level in the core may continue to decrease if the water is boiling off. Fuel pellet overheating due to increasing temperatures causes additional fission products to diffuse out of the fuel pellets. Containment Spray system will be actuated to remove 99% of the elemental radiolodines and air particulates from containment. Revision 4, page 3 of 12

PMP 2081 EPP.105 5.3.4 Core melt. Further decreases in coolant level result in increasing temperatures. The temperature of the upper portion of the core increases and can reach and exceed the melting point of the zircalloy cladding (typically, zircalloy melts at > 22000F). Continued heating for a still longer period of time causes core uncovery, extensive core damage takes place and the upper, central portion of the core may begin melting. The containment radiation monitors progressively increase and may saturate. 6.0 PREREQUISITES 6.1 Any plant condition in which the operator would'suspect defect or failed fuel, and an estimate of the amount of defect or failed fuel is required. 6.2 Any plant condition in which an operator would suspect a loss of reactor core cooling or knows reactor core cooling will no longer be maintained. 6.3 If the DA computer program will be used, verify functionality by entering the data on APPENDIX F. Print the CDA report and verify results with those listed. Revision 4, page 4 of 12

PMP 2081 EPP.105 7.0 ESTIMATION OF CORE DAMAGE STATE 7.1 Initial Estimation of Core Damage Based on Containment Radiation Monitor Indications (APPENDIX A) 7.1.1 Record.the time of reactor shutdown, the time after shutdown the containment high range area radiation monitor indications were

obtained, the containment radiation monitor

number, and containment high range area radiation monitor indications on APPENDIX A.1.

7.1.2 Divide the radiation monitor readings by the power correction factor determined in APPENDIX E.2 and record on APPENDIX A.1. 7.1.3 Compare the corrected readings with APPENDIX A.2 to estimate the corresponding extent of core damage. In general, values below region C represent 3% release of noble gases and are indicative of cladding rupture, values within region B indicate between 3% and 50% noble gas release and are in the fuel pellet overtemperature region, while values in region A indicate > 50% noble gas release and are in the core melt region. 7.1.4 Based on containment radiation monitor readings, record the estimated core damage state(s) from APPENDIX A.3 on Attachment 1. 7.1.5 Report preliminary findings to the TSC PET-Chemistry or TSC Technical Director. Revision 4, page 5 of 12

PMP 2081 EPP.105 7.2 Initial Estimation of Core Damage Based on Core Exit Thermocouple Indications (APPENDIX B) N. 7.2.1 Record the maximum core exit thermocouple temperature data on APPENDIX B, Characteristics of Categories of Fuel Damage, and compare these values to determine the estimated core damage state. 7.2.2 Based on APPENDIX B, record the estimated core damage state(s) on Attachment 1. 7.2.3 Report preliminary findings to-the TSC PET-Chemistry or TSC Technical Director. Revision 4, page 6 of 12 CAUTION If a large break LOCA is suspected or indicated, undetected core heat-up and flashing of cooling water during core recovery will occur. Thermocouple readings may rise sharply, then quench when core recovery commences. In this case, this section would yield low estimates of core damage.

PMP 2081 EPP.105 .Wi ',NOTE

-he Core. Damage 'Assessment computer program: may be use t t

.-"-'sec tions, 7.3 and/or 7.4.

7.3 Comprehensive Estimation of Core Damage Based on Hydrogen Production (Appendix C) 7.3.1 Determine from the reactor vessel level instrumentation or other sources if at any time the core became uncovered. Clad rupture (gas gap release) could have occurred without any core uncovery. Momentary core uncovery may indicate only clad rupture, while extended core uncovery may very well indicate clad oxidation followed by some degree of core melt. 7.3.2 Record containment hydrogen concentration as % H2 when the Post Accident Containment Hydrogen Monitor (PACHMS) is activated on APPENDIX C.1. If ignitors have been used, the results obtained may be inaccurate. In this event, an estimate of the H2 removal should be made. CAUTION Primary systems water inventories need to be accounted for at the time of sampling. Coordinate the reported time of sampling with the primary system water inventory data available for the same point in time. 7.3.3 Obtain a liquid sample of RCS and analyze for hydrogen concentration. Record as cc/Kg H2 on APPENDIX C.1 7.3.4 Determine the total hydrogen inventory (RCS and containment atmosphere) in units of cubic feet at standard temperature and pressure. 7.3.5 Estimate the hydrogen production in containment due to the oxidation of aluminum and zinc using the worksheet in APPENDIX C.3. A plot of production rate vs. general containment temperature is provided as Appendix C.4. The maximum hydrogen yield due to the oxidation of aluminum Revision 4, page 7 of 12

PMP 2081 EPP.105 and zinc at D.C. Cook is 9.81 E3 SCF in Unit 1 and 9.64E3 SCF in Unit 2. Record this value on Appendix C.1 7.3.6 Estimate the hydrogen volume generated by the radiolysis of water. The rate of hydrogen production by radiolysis of water is dependent on power history. Determine the hydrogen production rate for the time period, At (from APPENDIX E), from the graph in Appendix C.5 or C.6 and multiply by the adjusted thermal power obtained in APPENDIX E. Record this value on Appendix C.1. 7.3.7 On Appendix C.1, determine the volume of hydrogen produced by core clad oxidation by subtracting the values for aluminum and zinc reaction and radiolysis from the total hydrogen volume to obtain the net core clad oxidation hydrogen volume. 7.3.8 Divide the net core clad oxidatiori hydrogen volume determined by the total theoretical hydrogen volume from core clad oxidation to determine extent of the zirconium-water reaction. Record the estimated core damage state(s) on. If ignitors have been activated or a burn has been indicated, quantitative use of the hydrogen concentration. is limited. It can be assumed that for ignition of hydrogen to occur a minimal concentration of 4 percent hydrogen is needed. This assumption can be used qualitatively to indicate that some percentage of zirconium has reacted, but it is difficult to determine extent of the reaction. 7.4 Comprehensive Estimation of Core Damage Based on Radionuclide Analysis (Appendix D) CAUTION Primary systems water inventories need to be accounted for at the time of sampling. Coordinate the reported time of sampling with the primary system water inventory data available for the same point in time. 7.4.1 Request samples (decay corrected to the time of sampling only) of reactor coolant, containment atmosphere, and/or containment sump as indicated in the table of suggested sampling locations. Initial core damage assessments should be relayed to any post accident sample teams at the time of sample request. Revision 4, page 8 of 12

PMP 2081 EPP.105 Analyze the selected samples for nuclide specific activity with decay correction to the time of sampling applied to sample activities. Record the measured nuclide activities in Curies/gm or Curies/cc as applicable with no decay correction from the Post Accident Sample System (PASS) analysis. Revision 4, page 9 of 12 Scenario l Primary Sampling 1 Alternate Sampling j Location J Location LOCA Small Break power < 1% RCS H/L, CTMT AT Pressurizer power > 1% RCS H/L Pressurizer LOCA Large Break ._l power < 1% CTMT Sump, CTMT AT, RCS H/L power > 1% CTMT Sump, CTMT AT Steam Line Break RCS H/L Pressurizer, CTMT AT SG Tube Rupture RCS H/L, Secondary Sys. CTMT AT CTMT Sump Increase CTMT Sump, CTMT AT CTMT RMS Alarm CTMT AT, CTMT Sump Safety Injection Actuation RCS H/L Pressurizer High RCS Activity RCS H/L Pressurizer 7.4.2 7.4.3

PMP 2081 EPP.105 7.4.4 Determine and record the Decay Correction Factor using APPENDIX D.4, Decay Correction Factorwith Parent-Daughter Effect. 7.4.5 Determine and record the corrected specific activity by multiplying the reported nuclide activity by the decay correction factor. 7.4.6 Record the total sample dilutions made on the Post Accident RCS sample. This includes dilutions by the sampling system and in the sample preparation. Containment Atmosphere PASS sample dilution factors will be. found in 12 THP 6020. PAS.007. 7.4.7 Multiply the corrected activity by the dilution factor and record the corrected specific activities of nuclides in Ci/grm or Ci/cc as applicable. 7.4.8 Record the total liquid mass from completed APPENDIX E, section 3.0 on RCS (D.1) and containment sump (D.2). If the accident did not involve a LOCA, estimate only the RCS liquid mass. If the accident did involve a LOCA, and a RCS sample and a containment sump sample were obtained, an estimate of both the RCS water mass and containment sump water mass are needed. If only one of the liquid samples (RCS or containment sump) was obtained, use the total estimated liquid mass as the water mass associated with the obtained sample. Record the appropriate liquid mass. 7.4.9 Record the total estimated Containment Volume from completed APPENDIX E, section 4.0 on APPENDIX D.3. 7.4.10 Calculate Total Post Accident (TPA) activity of each nuclide released by multiplying the decay corrected specific activity by the estimated mass for liquid samples or the estimated volume for Containment Atmosphere samples. Copy to APPENDIX D.5 (Unit 1) or D.6 (Unit 2) in the appropriate column. 7.4.11 Using the data recorded on APPENDIX D.5 or D.6, sum the activities of each nuclide of each sample to determine TPA total activity released for each nuclide. Revision 4, page 10 of 12

PMP 2081 EPP.105 ~~~~~~~~~~~~~~~~~~~~~.................. v NOTE The Total-.Core-Jnventor C) must be corrected for 'Power -Histor... 7.4.12 From APPENDIX E, section 2.0 record the power correction factor as a decimal. The number 4 or 30 in the column indicates the power history period to use for that nuclide. 7.4.13 Determine and record on APPENDIX D.5 or D.6 the adjusted core inventory for each nuclide by multiplying the equilibrium full power total core inventory (TCI,) by the power correction factor. 7.4.14 Determine and record on APPENDIX D.5 or D.6 the release fraction of each nuclide by dividing the Total Post Accident activity in column A by the Corrected Total Core Inventory in column B. 7.4.15 Transpose the release fractions to the appropriate column in APPENDIX D.7. -Si-,,ES ~~~~~~~~~~~~. i.. . i,B .,..i i ',':97:.' ~ ~ ~ ~ ~........ s' " t D

.. t.: Zs....c.°l..<

n. A<a <..t.h-<°Se t.S.

tpe. S Iftheeslticng pecen g ides o rea thn % rcacuateith the next higher<,. 7a4f t ide the uling percentage in rEatI than 100callatewit e fnl vu t i e chraceristifc Ncm listsdt e ndes whlic y be0 dentriie i the et elieals o increase in concentratin.in t 7.4.16 Divide the nuclide release fraction in APPENDIX 0.7 by the core release fraction (RF6) listed for each classification of core damage and multiply by 100 to'determine the percentage of release from the core of each nuclide. 7.4.17 Transpose the nuclide release percentages between 0.1 and 100 % in each classification of core damage to the appropriate columns in Attachment 1. Revision 4, page 11 of 12

PMP 2081 EPP.105 N O TE,..

Know g bl e udgement is used to relate. the act raio d to.the defions of10 NRC categories of core mageoun Attachn t 1 and Appendices -

through. C' o ea g .o .e-ped 'to ocrhuniformly. rThe w evaluaing parameters,f.it' ill be"posil to: idth on or mor ofthe.1.NR.................. ,cars xisting simultaneoly. 7.4.18 Evaluate the nuclide release percentages on Attachment 1 against the NRC Categories listed on page 2 of Attachment 1, Characteristics of Categories for Fuel Damage. The Characteristic Nuclide column is arranged such that the most characteristic nuclide in each classification is listed first. 7.4.19 Select the NRC Category that corresponds to between 0.1% to 100% for each nuclide. In case of overlapping categories, engineering judgement would select the higher category. 7.5 Perform the final core damage assessment by evaluating the data on Attachment

1. It is unlikely that omplete agreement between the indicators will result in exactly the same estimate of core damage. The evaluation should be the best estimate based on all parameters, their interrelationship, and engineering judgment.

The evaluator should use as many indicators as possible to differentiate between the various core damage states. Because of overlapping values of release and potential simultaneous conditions of clad rupture, clad oxidation, and/or core melt, considerable judgment needs to be applied. 7.6 Deliver completed Attachment 1 to the TSC PET-Chemistry or TSC Technical Director for appropriate disposition. Revision 4, page 12 of 12

PMP 2081 EPP.105 ATTACHMENT 1 Estimation of Core Damage UNIT Estimated State(s) of Core Damage Reactor Shut Down Date/Time / Measurement ll No Damage Clad Rupture Clad Oxidation Core Melt Cat Cat Containment ll l Rad Monitor l Core Exit Thermocouple ll _ll Hydrogen Production Radionuclide Analysis Kr 85 Kr 87 = = Kr 88 Xe 131M Xe 133 = Xe 133M Xe 135 __= = 1 131 132 1 133 1 135 C s 138__ Te 129__ Te 132__ Ba 140__ La 140 La 142 l Pr 144 J_= Revision 4, page 1 of 2

PMP 2081 EPP-.,gJ5 ATTACHMENT 1 Estimation of Core Damage Revision 4, page 2 of 2 Characteristics of Categories for Fuel Damage Characteristic Nuclides % TCI Source of Hydrogen NRC Description NRC I Released Release % Core Cat No Damage 1 131 Cs 138 < 1 Gas Gap Normal No Damage 1 Xe 131m, 133 < 10 Gas Gap Normal Initial Cladding Failure 2 Xe 133m, 135 . Rupture Kr 85, 87, 88 10 to 50 Gas Gap Normal Intermediate Cladding Failure 3 Te 129, 132 I 131, 133 > 50 Gas Gap Normal Major Cladding Failure 4 Ba 140 < 10 Fuel Pellet < 10 Initial Fuel Pellet Overheating 5 La 140 Oxidation Cs 138 10 to 50 Fuel Pellet 10 - 50 Intermediate Fuel Pellet Overheating 6 Te 129 Te 132 > 50 Fuel Pellet > 50 Major Fuel Pellet Overheating 7 La 142 < 10 Fuel Pellet < 10 Initial Fuel Pellet Melt 8 l Pr 144 Core Melt l Ba 140 10 to 50 Fuel Pellet 10 - 50 Intermediate Fuel Pellet Melt 9 La 140 > 50 Fuel Pellet > 50 Major Fuel Pellet Melt 10

PMP 2081 EPP.105 APPENDIX A.1 Estimation of Core Damage Based on Containment Radiation Monitor Indications Time of reactor shut down Time of monitor measurement Time Post Accident, At hours Containment radiation monitor number Containment radiation monitor indication Power correction factor from APPENDIX E Corrected containment radiation monitor indication A R/hr B __ [A - (B/100)] _R/hr Evaluate the corrected containment radiation monitor indication against APPENDIX A.2 OR A.3. Record estimation of core damage here and on Attachment 1. Estimation of Core Darriage State:_ Revision 4, page 1 of 3

PMP 2081 EPP.105 APPENDIX A.2 Estimation of Core Damage Based on Containment Radiation Monitor Indications Typical Analysis for Post Accident Dose Rate Inside a Cylindrical Containment 1000000 100000 RJhr 10000: 10001 I I I I I II A Major Fuel Overheat B Intermediate Fuel Overheat C Initial Fuel Overheat 10 100 Tihe, Post Acddent (hs) 1000 D Major Cladding Failure E Intermediate Cladding Failure F Initial Cladding Failure Revision 4, page 2 of 3 _ -- Tt?Xi:i!l 100l1l11 X \\s 4 ] ] r B <1t l 1 X \\ _ TlTeri rt YXrlTr r T7TII i 3 V X X i \\ _ _ _ q _ __ _ _ _ _ _\\ s w oN\\---. A \\ D x \\X 7 \\\\ = \\\\ _ .. fe = _ J \\ v _

f=

H = = X 0 7 T = \\ = S = \\ X _ -F _ \\, j, E _ ' \\ s _ e _..

PMP 2081 EPF-..J5 APPENDIX A.3 Estimation of Core Damage Based on Containment Radiation Monitor Indications Record estimation on Attachment 1 Revision 4, page 3 of 3 Characteristics of Categories for Fuel Damage I Containment Radiation Percent Source ofT NRC Description 1 NRC l__________ lMonitor R/hr Damage Release [ Cat# No Damage Normal < 1 Gas Gap No Damage 1 Normal to 660 < 10 Gas Gap Initial Cladding Failure 2 Rupture 660 to 990 10 to 50 Gas Gap Intermediate Cladding Failure 3 990 to 1325 > 50 Gas Gap Major Cladding Failure 4 1325 to 8.6E4 < 10 Fuel Pellet Initial Fuel Pellet Overheating 5 Oxidation 8.6E4 t 1.7E5 10 to 50 Fuel Pellet Intermediate Fuel Pellet Overheating 6 1.7E5 to 3.4E5 > 50 Fuel Pellet Major Fuel Pellet Overheating 7 3.4E5 to 4.6E5 < 10 Fuel Pellet Initial Fuel Pellet Melt 8 Core Melt 4.6E5 to 5.8E5 10 to 50 Fuel Pellet Intermediate Fuel Pellet Melt 9 > 5.8E5 > 50 Fuel Pellet Major Fuel Pellet Melt 10

PMP 2081 EPF ,5 APPENDIX B Estimation of. Core Damage Based on Core Exit Thermocouple Indications Maximum Observed Core Exit Thermocouple indication' Date / Time Characteristics of Categories for Fuel Damage Maximum Core Exit Reference l Percent l Source of NRC Description iNRC Thermocouple Radiation Damage Release Cat Temperature F Monitor R/hr l No Damage Normal Normal c 1 Gas Gap No Damage 1 Normal to 750 Normal to 660 < 10 Gas Gap Initial Cladding Failure 2 Rupture 750 to 1300 660 to 990 10 to 50 Gas Gap Intermediate Cladding Failure 3 1300 to 1650 990 to 1325 > 50 Gas Gap Major Cadding Failure 4 > 1650 1325 to 8.6E4 < 10 Fuel Pellet Initial Fuel Pellet Overheating 5 Oxidation > 1650 8.6E4 to 1.7E5

10. to 50 Fuel Pellet Intermediate Fuel Pellet Overheating 6)

> 1650 1.7E5 to 3.4E5 > 50 Fuel Pellet Major Fuel Pellet Overheating 7 > 1650 3.4E5 to 4.6E5 < 10 Fuel Pellet Initial Fuel Pellet Melt 8 Core Melt > 1650 4.6E5 to 5.8E5 10 to 50 Fuel Pellet Intermediate Fuel Pellet Melt 9) > 1650 > 5.8E5 > 50 Fuel Pellet Major Fuel Pellet Melt 10 Record estimation on Attachment 1 Revision 4, page 1 of 1 K I \\-v Fo

PMP 2081 EPP.105 APPENDIX C.1 Estimation of Core Damage Based on Hydrogen Production 1.0 History or indication of Core Uncovery Comments: Containment Hydrogen Inventory 2.0 PACHMS Hydrogen Concentration. _% Containment H2 TH21o x 1.24E06 SCF x (.. + 14.7) x in SCF = 100 14.7 492 (Totjn + 460) = 3.0 RCS Hydrogen Concentration ______cc/Kg RCS H2 in SCF = £H2 .3531 1000 (V' from APPENDIX E or default to 3.34E5 Kg) 4.0 Total Hydrogen Concentration (2.0 + 3.0) 5.0 Estimate of hydrogeh volume generated by the oxidation of aluminum and zinc in containment using APPENDIX C.3 and C.4 (maximum: 9.81E3 SCF-Unit 1; 9.64E3 SCF-Unit 2). 6.0 Estimate of the hydrogen volume generated by the radiolysis of water in Containment A B Record At from APPENDIX E Record corrected MWt from APPENDIX E Using APPENDIX C.5 or C.6, determine the H2 production rate at At and multiply by the corrected MWt C-_ 7.0 Estimate of the hydrogen volume generated in Containment by the oxidation of core cladding (A minus B and C) D-8.0 Percent oxidation of core cladding, (D 4.10E05 SCF) X 100 9.0 Determine the Estimated Core Damage Category based on the percent oxidation of core cladding from APPENDIX C.2. Record on Attachment 1. Revision 4, page 1 of 6 no_

PMP 2081 EPrK..J5 APPENDIX C.2 Estimation of Core Damage Based on Hydrogen Production Record estimation on Attachment 1 Revision 4, page 2 of 6 Characteristics of Categories for Fuel Damage Classification Characteristic % H, Percent Oxidation Source of NRC Description NRC Measurement Released of Core Release Cat No Damage Core Exit Gas Gap No Damage 1 Thermocouple Gas Gap Initial Cladding Failure 2 Containment Rupture Radiation Gas Gap Intermediate Cladding Failure 3 Monitor l Monito < 1 <~ 1 Gas Gap Major Cladding Failure 4 Hydrogen < 10 < 10 Fuel Pellet InitialFuelPelletOverheating 5 Produced due Oxidation to Core . 10 to 50 10 to 50 Fuel Pellet Intermediate fuel Pellet Overheating 6 Oxidation > 50 > 50 Fuel Pellet Major Fuel Pellet Overheating 7 Hydrogen < 10 < 10 Fuel Pellet Initial Fuel Pellet Melt 8 Producedt to dure 10 to 50 10 to 50 Fuel Pellet Intermediate Fuiel Pellet Melr 9 Core Melt to Core 55uP tjeetl Oxidation > 50 > 50 Fuel Pellet Major' Fuel Pellet Melt 1

PMP 2081 EPP.105 APPENDIX C.3 Estimation of Core Damage Based on Hydrogen Production Hydrogen Volume Generated by the Oxidation of Aluminum and Zinc in Containment Time of Interval Interval Duration Average CTMT H2 Production H2 Produced (hrs) A Temperature (F°) Rate (SCF/hr) B (SCF) A x B Start Accident Sample Time Total Hydrogen Produced by Oxidation of Aluminum and Zinc I Revision 4, page 3 of 6

PMP 2081 EPP.105 APPENDIX C.4 Estimation of Core Damage Based on Hydrogen Production Hydrogen Production Rate from Oxidation of Aluminum and Zinc SCF/hr 1000 100 10 0.1 120 UNIT 1 and UNIT 2 140 160 180 200 220 240 260 280 300 Temperature (For this intent, Unit's 1 and 2 have similar amounts of aluminum and zinc which produce graphs that are relatively identical) Revision 4, page 4 of 6

PMP 2081 EPP.105 APPENDIX C.5 Estimation of Core Damage Based on Hydrogen Production Hydrogen Volume Generated by the Radiolysis of Water Time versus Generation from 0 to 25 hours SCF/MWt 2.5 2.5 I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ 0 1 1X 7 901111115 0

1

.8 1: + 4-4----4---4--Hou 0.5 0 1 2 3 4 5 6 7 9101112131415167188920282. 248 -Hours Revision 4, page 5 of 6

PMP 2081 EPP.105 APPENDIX C.6 Estimation of Core Damage Based on Hydrogen Production Hydrogen Volume Generated by the Radiolysis of Water Time versus Generation from 0 to 800 hours SCF/MWt 0 15 '14 13 12 11 10 9 8 7 .6 5-4 3 2 1 0 w 0 50 100 150 200 250 30 0 04 0 500550 600 650700 750 0 Hours Revision 4, page 6 of 6 15 14 13 12 11 10 9 8 7. 6 5 4 3 2 1 -rf-7, ,--.--*y-.,--.*r-v-.,--v-.r-2 2 2 2 2 I -+-I.-4 4 I I I I 2 I 2 2 I 2 I --.'- I I 2 I 1 2 I 2 2 2 I I 2 2 I 2 1 2 I f I 2 I I I I 2 j 2 2 2 2 I 2 1

PMP 2081 EPF. 5 APPENDIX D.1 Estimation of Core Damage Based on Radiochemical Analysis RCS Activity Worksheet RCS Measured Activity Decay Correction I l E r Specific Activity Dilutiojn Factor Corrected Specific Activity RCS Mass TPA RCS Activity J_**Curles/gm** APP. D.4 Ci/gm Ci/gm gm Curies Kr 85 Kr 87 Kr 88 Xe 131m Xe 133 l Xe 133m Xe 135 1132 1133 1135 Cs 138 Te 129 T e 132 l La 140 r La 142 [P r 1 4 4 Revision 4, page 1 of 8 Nuclide

PMP 2081 EPF ,5 APPENDIX D.2 Estimation of Core Damage Based on Radiochemical Analysis Containment Sump Activity Worksheet Nuclide Sump Measured Decay Specific Dilution Corrected Sump TPA Sump Activity Correction Activity Factor Specific Activity Mass Activity

- Curies/gm**

APP. D.4 Ci/gm Ci/gm gm Curies Kr 85 Kr 87 Kr 88 Xe 131m. Xe 133 l Xe 133m Xe 135 [1 1 3 1I 1 132 1133 1.135 Cs 138 Te 129 Te 132 l Ba 140 l La 140 La 142 l I Pr 144 Revision 4, page 2 of 8

PMP 2081 EPF. ,5 APPENDIX D.3 Estimation of Core Damage Based on Radiochemical Analysis Containment Atmosphere Activity Worksheet Nuclide CTMT Measured Decay Specific Dilution Corrected CTMT TPA CTMT Activity Correction Activity Factor Specific Activity Volume Activity l **Curies/cc** APP. D.4 Ci/cc Ci/cc cc Curies Kr 85 Kr 87 Kr 88 Xe 131m IX e 133 I Xe 133m Xe 135 1 132 1 133 1135 Cs 138 Te 129 Te 132 Ba 140 La 140 La 142 P r 1 4 4_ Revision 4, page 3 of 8

PMP 2081 EPF.,05 APPENDIX D.4 Estimation of Core Damage Based on Radiochemical Analysis Decay Correction Factors with Parent-Daughter Effect (USE At from APPENDIX E) Nuclide Decay Correction Factor Kr 85 e+1.6 E0 At Kr 87 e+5.4 E0I Kr 88 e+2.4 4 E01 At Xe 131 m 1/ [-195.4 e 35DE43A + 196.4 e 2.44E43At1 Xe 133 1/ r-0.189 e 33 3E42 ^' -3.42E-02 e'. 3 2E02At + 1.22 e¶ 1E0 3Atj Xe 133m 1 / -22.8 e 3E42A + 23.8 e ' 32E42 At 1 Xe 135 1/ [-2.65 e-1O5At + 1.91E-04 e + 3.65 e 1 131 1/ 2.18E-02 e'B1At - 1.27E-02 e2 3¶E4?AI -4.41 E-02 eeA + 1.017e3. 9E43A¶1 1 132 1/ [1.03 efE 3 At - 300E-02 e 30 1 1133 1/ [4.37E-04 e. 8 4 - 1.35E:02 e7 1 At + 4.31 E-03 e 3.3 4 At + 1.018 e 3.3 3 E 2 At] 1 135 e+0.106at Cs 138 1/ r1.78 e.29 At - 0.78 e 2.94At] Te 129 1/ [1.21 e 5 BAt + 0.11 e8.eE44 At - 0.32 e4 9s t1 Te 132 e+SeeE3At Ba 140 e+2.28E 3At La 140 1 r1.15 e 2.26E03 At - 015 e1.72E02Ati La 142 1/ r1.126 e430 - 0.126 e3.89 t Pr 144 P+1.08EO4At Revision 4, page 4 of 8 ..W-.,.

PMP 2081 EP J5 APPENDIX D.5 Estimation of Core Damage Based on Radiochemical Analysis Total Release Activity/Percent Released Worksheet Nuclide RCS CTMT CTMT TPA Total Total Core Power Corrected Nuclide Activity Sump Atmosphere Activity Inventory Correction TCI Release Activity Activity (A) TCI Factor (B) Fraction Curies Curies Curies Curies Curies APP. E Curies (A/B) Kr 85 4.05E7 4 Kr 87 8.84E7 4 Kr 88 1.24E8 4 Xe131 m 1.09E6 30 [Xe 133 2.32E8 30 Xe133m 4.46E6 30 Xe 135 2.27E8 4 [ 131 1.00E8 30 1 132 1.49E8 4 1 133 2.32E8 1 135 2.27E8 4 Cs 138 2.32E8 4 Te 129 2.44E7 4 Te 132 I 1.49E8 30 j Ba 140 l 2.15E8 30 La 140 2.15E8 30 La 142 l 2.02E8 4 Pr 144 1.91E8 4 Revision 4, page 5 of 8 UNIT 1

P.P.. 0 PMP 2081 EPP.105 APPENDIX D.6 Estimation of Core Damage Based on Radiochemical Analysis Total Release Activity/Percent Released Worksheet Nuclide RCS CTMT Sump CTMT TPA Total Power Corrected Nuclide Activity Activity Atmosphere Total Core Correctio TCI Release Activity Activity Inventory n Factor (B) Fraction TCI (A/B) ~( A ) -Curies Curies Curies Curies Curies APP. E Curies Kr 85 2.1E7 Kr 87 3.8E7 4 Kr 88 5.4E7 4 Xel631m 6.0E5 30 Xe 133 l X [ 2.7E7 30 Xel33m 3.5E7 30 Xe 135 1.9E8 4 [I 131 l 9.3E7 30 I 132 1.3E8 4 I 133 1.9E8 30 I 135 1.7E8 4 Cs 138 5.5E7 4 Te 129 3.1E7 Te 132 l 1.3E8 30 l Ba 140 l 1.6E8 30 La 140 1.7E8 30 La 142 1.4E8 4 Pr 144 1.1E8 Revision 4, page 6 of 8 UNIT 2

PM 281. PMP 2081 EPP.. j5 APPENDIX D.7 Estimation of Core Damage Based on Radiochemical Analysis Percent of Nuclide Released/Release Fraction (RFe) Nuclide Release Gas Gap Corrected Clad Corrected Core Corrected NRC Fractions Release Release Oxidation Release Melt Release Cat l D.5 or D.6 (RFe) 0.1 - 100 % (RF8) 0.1-100% (RFe) 0.1-100% Kr 85 0.03 0.5 1.0 Kr 87 0.03 0.5 1.0 Kr 88 0.03 0.5 1.0 Xel31m 0.03 0.5 1.0 Xe 133 l0.03 0.5 1.0 Xe133m 0.03 0.5 1.0 Xe 135' 0.03 0.5 1.0 I1131 l 0.02 0.5 1.0 1 132 0.02 0.5 1.0 1133-0.02 0.5 1.0 1135 0.02 0.5 1.0 Cs 138 0.05 0.5 1.0 Te 129 1E-4 0.1 0.3 Te 132 1 E-4 0.1 0.3 Ba 140 l l 0.01 0.2 [La 140 1E-4 =_________ _ __E La 142 I 1 E -4 _ _ __E Pr 144 = Revision 4, page 7 of 8

PMP 2081 EPP.105 APPENDIX D.8 Estimation of Core Damage Based on Radiochemical Analysis Core Release Fractions (RFe) Assumptions Core Condition lFuel Cladding Fission product Release Fraction Temperature Core Intact < 600 F Normal Coolant (Normal Leakage) Concentrations Xe, Kr 0.03 Gap Release 13000 F - 2100 F 1 0.02 (Cladding Failure) Cs 0.05 Te, Sb 1E-4 Xe, Kr 0.5 I,Cs 0.5 Grain Bouridary 3000 F Te 0.1 (Clad Oxidation) Sb 0.02 Ba 0.01 Mo 0.01 Sr 1E-3 Ru 1E-4 Xe, Kr 1.0 Cs 1.0 I ~~~~~1.0 Sb 0.02 Te 0.3 Ba 0.2 Core Melt > 4500 F Sr 0.07 MO 0.1 Ru 1 E-3 La 1 E-4 Y 1 E-4 Ce 1E-4 Np 1E-4 Revision 4, page 8 of 8

PMP 2081 EPP j5 APPENDIX E.1 Critical Data UNIT Control Room Information Reactor Shut Down Date/Time / Measurement Parameters CTMT RMS CET 0Fm PACHMS CTMT°F Date/Time of Measurement Measurement Indication System Volume Parameters RCS Sump C.A. S/G Other(a} l Other Date/Time of Measurement Level Indication (%) System Volume PASS Samples RCS Sump C.A. S/G Other Other E l ~~~~~ ~ ~~~~~~~~(a) (b) 1 Sample Date/Time Temperature l ._l_l_l Analysis Date/Time T 1 1 _11 Reactor Power History: Section 2.0 Revision'4, page 1 of 6

PMP 2081 EPP.105 APPENDIX E.2 Determination of Essential Time Periods, Power Correction Factor, Estimated Liquid Mass, and Estimated Containment Volume 1.0 DETERMINATION OF ESSENTIAL TIME PERIODS RCS Liquid Sample Record time of Reactor shut down (ti,). Record time of RCS liquid sample (t). Determine the decay time interval (At), (t..) minus (ti) Containment Uquid Sample Record time of Reactor shut down (). Record time of RCS liquid sample (t). Determine the decay time interval (At), (tm) minus (ti) Containment Atmosphere Sample Record time of Reactor shut down (t.). Record time of Containment Atmosphere sample (ti). Determine the time interval (At), () minus (t,) Date Time_ Date Time_ Interval Time(At) (Min) Date _ Time_ Date _ Time_ Interval Time(At). (Min) Date_ Time_ Date _ Time_ Interval Time(At) (Min) 2.0 Power Correct Factor Calculations 2.1 Determination of Average Reactor Power If reactor power has not changed by more than + 10 % for a period greater than thirty days, the power at the time of the shut down can be used. If the power has changed by more than + 10 % during the 4 or 30 days prior to the accident, an estimate must be made to establish the most representative power level. The thirty day average power level is not necessarily the most representative indication. Weighted average power history is determined by summing the products of power level durations multiplied by the power levels and dividing by the total duration length. Perform this estimation for the prior four day period and thirty day period. (The number 4 or 30 in the Power Correction Factor column of APPENDIX D.5 or D.6 indictes which period to use) Revision 4, page 2 of 6

PMP 2081 EPP.105 APPENDIX E.3 Determination of Essential Time Periods, Power Correction Factor, Estimated Liquid Mass, and Estimated Containment Volume z (days at power1 x %power,)+(days at power2 x %power)+... Total days considered in this history Percent Power Duration, Days Prior four days Prior 30 days Four Day Estimated Reactor Power at time of shut down (t). Thirty Day Estimated Reactor Power at time of shut down (ts) 2.2 Determination of Gross Thermal Power (Hydrogen Production) Determine the adjusted gross megawatt thermal (MWt) at t by multiplying the estimated fraction of full power determined above by 3250 MWt (U-1) or 3411 MWt (U-2). 3.0 Determination of Liquid Mass 3.1 Reactor Coolant System Date/Time RCS level % Determine. RCS volume from available level indications (%) and multiply by a default value of 88,114 gallons (3.34E08 ml) for the system volume. Record on page 1 of APPENDIX E. 3.2 Containment Liquid Mass Date/Time Containment Sump Level Containment Level 3.2.1 From the level indications, determine the volume of water in the containment sump and/or containment from the graphs below. Containment level indication includes the sump volume. Multiply the volume by 28,317 ml/ft3. Record on page 1 of APPENDIX E. Revision 4, page 3 of 6

PMP2081 EPP.105 APPENDIX E.4 Determination of Essential Time Periods, Power Correction Factor, Estimated Liquid Mass, and Estimated Containment Volume Containment Sump Volume vs Containment Sump Level Indication (599-8") 100 so -- - 70 -- - - - - - - - - - 0 =2 -0 ./- 4j 0 (589-51 0 0 5 4 4500 0 500 1000 1500 2000 2500 3000 3500 4000 4soo Volume (ft) Containment Volume vs Containment Level Indication (5 14'-O oo 90 a 0 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 7 0 6 0 -- - - - - - - - - - - - - - - - - - - - - - - - - - - (5993) o 0 20 40 60 80 100 120 Volume (Thousands ft3) Revision 4, page 4 of 6

PMP 2081 EPP.105 APPENDIX E.5 Determination of Essential Time Periods, Power Correction Factor, Estimated Liquid Mass, and Estimated Containment Volume 3.2.2 In the event the other water inventories become necessary due to the accident scenario, determine the volume in accordance with the chart below. Record on page 1 of APPENDIX E. 4.0 Determination of Containment Volume Date/Time Pressure Temperature Containment 3.50E10 cc x (,_ + 14.7) x Volume cc = 14.7 492 (T-Ul + 460) Revision 4, page 5 of 6 Source Maximum Volume l Estimated Volume (gal) Added (gal) Refueling Water Storage Tank 372,250 Accumulator A 7,263 Accumulator B 7,263 Accumulator C 7,263 Accumulator D 7,263 Boron Injection Tank 900 Spray Additive Tank 4,000 Melted Ice 2.7E6 (lb /8.341b/gal) Ib/8.34= Steam Generator See Graphs E.6 RHR 4019/train O ther i__ Total Volume Added (gal) l Sum of Volumes J (gal) Total Volume Added (gm) Total Volume x 3,785 (gm)

PMP 2081 EPP.105 APPENDIX E.6 Determination of Essential Time Periods, Power Correction Factor, Estimated Liquid Mass, and Estimated Containment Volume Steam Generator Volume versus Percent 'Ir 6 j4 3 I 0 ~7 a I5 I 0 s ThousaMde UNIT 1 7 - I - I - 7 7 7 r 0 10 20 30 40 50 so 70 80 90 100 H.ith¶ Abowe Tube Shel % Tha UNIT 2 Hu!ge# Abu" Tube St" Revision 4, page 6 of 6 rix N7 @~- p---- w *- @*----o *¢e~v- -¢--- --s-@0w- ---*t~~~~~~~~~~ H@¢-@** -- eoo-e-*w*- ............... -7'- 60 - eo 70 so 90 10 EO SO 40

PMP 2081 EPP.105 APPENDIX F.1 Core Damage Assessment Software Verification 1.0 Enter the data from the clear boxes on the following page into page 1 of the CDA computer program. Verify the results contained on page two of the program to the second page of the verification form. Ensure that the values are the same. If some error is identified, proceed with section 7.0 of the procedure. 2.0 The graphs included in this Appendix and on the CDA program menu may also be used when formally utilizing the CDA program for real accident scenarios. Revision 4, page 1 of 6

APPENDIX F.2 UNIT.- mwt E 3250 I 6/3/93 ..ROS---~- - :.Sump : 6/3/93 6/3/93 1:00AM -C.ATMOS 6/3/93 Time 8:00AM ~~~~4:00AM 2:00AM Delta T [ ... :7,00] -:x3.00[ o ROFis: 6.0E4 SUMI 3.0E4I olI [ RCS'-: I -II ~~II -1. 1I.. *. 2.27E81I sump ii -1.14E8 I PMP 2081 EPP.105 CORE DAMAGE ASSESSMENT Donald C.Cook Nuclear by REM Technology Dr. Robert 2. Mayer 5/93 I ALC..: 7' -' Nuclide, RCS sump. -- - - rn6T77 -- c,-, ----- Rcs..., SUMP Ai Atmos I - I - A., . I 17 1.-.

1.

.Kr85rnm Xe133 ~~5.OE-05 1 0E0 5.0E-05 E.OO0 5.0E+02 1.EO -Xel33rn If'. 1131: 5.0E+03 1.02E00 5.0E+03 1'01 EOCY 5.OE-02 1.00-387 4132: '1135 ~Cii38_ Te129 Te132 5.02+03 1.06200~ ~ 5.02+03 -:1.03E00: 8a140 ~~5.02+02 1.02E00 5.02+02 10100 La4Z 5.2-0 1.88E01 5.OE-02 3 E80 _ _ _ _ _ _ _~~I. ~~-. II 1 ,C s

Ratio+'

Cs1+ 34.-:. 2 1::34/1'37'-1 _ _ _ _ _ I_ _ _ _ _ _ I_ -_ _ _ _ _ _ _ _ _ I _ __ff_ 2 I -HYORG 'AlJ/7n Hrs@.Tenip k-.Giip# CFH 1 ~~1.28 Ii150 ] .20 .Grp i [Z I ~ i650 -.Atmos% 2.1 _______ ___ ii .24E 8 ~~~160J ~.A Press L F~ E ~ ~3 CET ~POWER AJI cells Li~IIIjRx vi45 IROS Vol ' 5 6 7 8 9 10 Y V Revision 4, page 2 ot b 4.5E4 DATA:. S hutdown:-. .lamp ng: +' i:+-Oate,:-...' I .4 VOLUMES: Letdo-wn+, I I I '.Pr144":-,' "... t'C ..+..+. -m

PMP 2081 EPP.105 A.PPENDIX F.3 I TOTAL C.A. H2 I. .'.2.'42E4 I I UNIT INet Hydrogen 2.33E4I I%FF from H2 5.75. 1 S/D Date 6/3/93 S/D Time 1:00AM Report#

% FAILED FUEL from Specific Release Fractions (Rfe)

NUCLIDE CORE Inventory TPA NO CLAD I CLAD I CORE Nuclides DAMAGE RUPTURE OXIDATION MELT 'Kr88 .Xe 131 m Xe133 ~~~~~~~~~~~2.32E08.17E3222 15.14 7.57

Xe l3S 1131 1.00E08; :."

1.73E12' 1.04 6.234173 1133'-- " 612 Te132

1 49E08~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

71 12021.45..12.02 4.01 8a140 215E....1.7.E11-1102 0.4E Lal 404 2.02E08 232EO9 1.15 P r 1 4 4 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __~~~~ Revision 4, page 3 of 6

APPENDIX F.4 Estimation of Core Damage Based on Hydrogen Production PMP 2081 EPP.105 Hvrrogen Production Rate from Oxidation of Aluminum and Zinc S.. (Zr'/hr I IIT I nrl IINIT 1000 100 10 1 awI I I L.A u I Is

c 01 I I

I I I I .I I l 120 140 160 180 200 220 240 260 280 300 Temperature (For this intent, Unit's 1 and 2 have similar amounts of aluminum and zinc which produce graphs that are relatively identical Revision 4, page 4 of 6 I'l,,

PMP 2081 EPP.105 APPENDIX F.5 Core Damage Assessment Software "-..'.ydrogen Volume Generated by the Radiolysis of Water Time versus Generation from 0 to 25 hours SCF/MWt Hours 25 25 2.5 2.5~~~~~~~~~~~~~~~~~~~~~~~~~~ .1 5 1 5 2. '.. Z !.~~~2 I, : 1.5 1.5~~~~~~~~~~~~~~~~f 0.55 2 [ I i. ~~~~~~~~~~~~~~~~~~~~~1 .i 5 i j i I l I.2 2 5 ~ ~ ~ ~~~ 2 Ij 05~~~~~~~~~ i 'i i 5 11 i Ii 411i 0 7 i T i~~~~~~~~I .i I i 2 i 7 0 2 3 !5 7 8 911112314 1 ,78 1234 0 0 1 2 3 4 5 6 7 8 9 10111213141516171819202122232425 Revision 4, page 5 of 6

PMP 2081 EPP.105 APPENDIX F.6 Core Damage Assessment Software ','ydrogen Volume Generated by the Radiolysis of Water Time versus Generation from 0 to 800 hours SCF/MWt -j - 10 14 13 12 11 10 9 8

6 5

4 3 2 1 0 ) 50 100 150 200 250 300 350 400 450 500 550 600 650 700 750 8C 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 010 Hours Revision 4, page 6 of 6

i-1t--q S

S I I I 4-.--- S 4.----- I 5 S I I U I I I I I I I 'I I I I I I ___ I I I I ____ I

R1BVWEW AND APPROVAL TRACKING FOR Prcedurinfrnton; c.. Number: RMT-2080-EOF-001 Rev. 03 Change: 00

Title:

Activation and Operation of the EOF Category (Select One Only):.~.2r ..- ;- a - -; i --y;-i i ;;: g tmi-441 M -. -f El Correction (Full Procedure) E Change (Full Procedure) with Review of Change Only El Correction (Page Substitution) [ Change (Page Substitution) with Review of Change Only f Cancellation Z New Procedure or Change with Full Review 2 Superseded (list superseding procedures): Associated.Conflguration Impact:Assessmet' V......r Change Driver/CDI Tracking No(s).: __ N/A Required Reviews: Cross-Discipline Reviews: Progrannatic Reviews: M Chemistry E Training El ALARA ^ []Reactivity Mgmt Team M Maintenance E] Work Control El Component Engineering E SPS (Safety & Health) El NDM E Emergency E Design Engineering El Surveillance Section E] Operations ^ Directors [] Emerg Oper Proc Grp [ ]System Engineering E PA/PV E ] Environmental LISOMS Administrator Fl Reg Affairs ] f ISIIST Coordinator L 3 RP E None Required ,f Perform apce Assurance 3 None Required E Cognizant Org Review: kl!z I) 4/ Z/ /j4-{wf Date: / / 3 3 Technical Review: 4 stm! Date: 3 o O3 ConcurrenceQ' -i . : i.. El Ops Director Concurrence: N/A Date: /_I P,,atc age,Check: ~ 3/4'.A Z. -i - a Updated Revision Summary attached? E Yes 10 CFR 50.59 Requirements complete? Tracking No.: 2003-0063-00 z Yes El N/A Implementation Plan developed? (Ref Step 3.4.17) F1 Yes N/A Package Complete: ,1Date: C1O I PORC Review Required: 3 Yes 2 No Mtg. No.: Administrative Hold Status: El Released e A CR No.: .:2 Approval Authority Review/Approva Date: +/-4/12 Expiration Date/Ending Activity / Effective Date: 5L'12L'0 Periodic Review conducted? (Data Sheet 5 Complete) 2 ^t< ies No L L A A Commitment Database update requested in accordance with PMP-7100-CMP-001? F-Yes N/A NDM notified of new records or changes to records that could affect record retention? E Yes E N/A ~~...... I Office Information For Form Tracking Only - Not P.ar of Form- .;~~~~~~~C): -f 5 Tflp~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~~~~~~~~ ^~~~~~~~~~~~~~~~~~~~~~~~A c. .AR 2. ! l0 This form is derived from the information in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10a, Data Sheet 1, Z Vorl ROLLLIV Review and Approval Tracking Form. Page I of i

REVISION

SUMMARY

RMT-2080-EOF-OO1 Revision: 03 Change: 00 Activation-and Operation of the EOF Section or Step Change/Reason For Change Step 2.5 Change: Revised step to remove "in Appendix C" and insert the title of the applicable reference section of the Emergency Plan. Reason: Use of the title (v. Appendix) clarifies which reference to the Emergency Plan is to be used for additional industry/agency support. Step 2.6 Change: New step to address OSC/TSC responders directed to the Buchanan Office Building via Dialogic pager code '007'. Reason: Establishes communication and transportation contingencies in the event of a '007'-code response. Step 2.7 Change: Corrected typo in the referenced procedure for termination and recovery. Reason: Typo correction. Step 3.1.3 Change: Revised reference to the correct procedure number. Reason: Typo correction., Change: Removed "continuous air monitor" from the bulletized list of Step 1.1 equipment. Reason: Continuous air monitor is not required equipment outside the 10-mile EPZ per any regulatory requirement or guidance in NUREG-0737, NUREG-0654, or NUREG-0696. This equipment was intended for those EOFs within the 10-mile EPZ per NUREG-0696 and Supplement 1 to NUJREG-0737., Change: Deleted the "Start the continuous air monitor" step. Step 1 Reason: Continuous air monitor is not required equipment outside the 10-mile EPZ., Step Change: Deleted the units "R/hr" in first bullet.

6.2 Reason

Units could be in units other than R/hr., e.g., tR/hr., Step Change: Removed the bulleted statement, "The ED approves the EMD-12 32b form." Reason: Unnecessary step since a change in classification or PAR would result in negating the need for the EMD-32b form., Change: Revised "request to speak to the Nuclear Emergency Director" Step 1.1.2 to "request to speak to meteorological forecaster" Reason: Murray & Trettle do not have a "Nuclear Emergency Director". Page ;-of I/ Number:

Title:

l*ig~< <4>-^ffelformationForFormT'c"i 0 Not.Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev.1 Oa.

RE VISION

SUMMARY

Number: RMT-2Q80-EOF-001

Title:

Activation and Oner: Revision: 03 Change: 00 ation of the EOF Section or Step Change/Reason For Change, Change: Added, "use the NOAA" website. Step 1.1.4 Reason: Provides another optional resource for obtaining the weather forecast., Step Change: Corrected typo "PARS" to "PARs".

2.5.1 Reason

Typo correction., Change: Corrected two typos in the first bullet (removed "." at the Step 2.5.2 beginning of the step, and added "a" to "EMD-32". Reason: Typo correction., Step Change: Added commas to the sentence. 2, Second Bullet Reason: To correct sentence structure., Change: Added "or change in PAR" to this step. Step 4 Reason: Provides clarification in the event a PAR has already been issued and an additional PAR becomes necessary., Change: Added clarification on frequency of faxing EMD-32 forms to Step 7 the State of Michigan; deleted the News Center as a destination and revised JPIC to read ENC/JPIC. Reason: Provides clarification as to the frequency these forms are faxed; reference to News Center was for its previous location at the Cook Energy Information Center-no longer applicable. 0, Change: Added NOTE to prompt Dose Assessment personnel that help Step 1 from other utilities is available with off-site activities per pre-arranged agreements. Reason: Reminds EOF personnel that additional help with off-site activities is available from other utilities. 0, Change: Added NOTE prior to Step to regarding administration of Kl for Step 2 field team members. Reason: Allows for permission to be obtained from SEC and EAD for KI administration for field team members. 0, Change: Added these steps to specify facilities that can be used for Step 4 and Step 5 analysis and to implement analysis of samples. Reason: For clarity as this was not previously specified. 0, Change: Corrected typo "boundries" to "boundaries". Step 3.2.3.a.4 Reason: Typo correction. I '%- ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ ',~~~~~~P.......... ' ' >zA..... ....ar..t =;^.; tfiekorniatioh Fbor 'rm'.' rackingOnlv -o Par ofFom < ; This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, 3 t. Change, and Review, Rev. I Oa. Page of

REVISION SUAIARY RMT-2080-EOF-001 Activation and Oneration of the EOF Revision: 03 Change: 00 Section or Step Change/Reason For Change 1, Change: Added step regarding analysis of sampling media. Step 7 Reason: For clarity as this was not previously specified. 2, Change: Corrected referenced procedure typo ("12" prior to procedure #). Step 4 Reason: Typo correction. 2, Change: Deleted Emergency Planning from the list of persons to be Step 6 contacted. Reason: Position eliminated from the EOF; this position is not required by the Emergency Plan or any regulatory guidance. 3, Change: Renamed the "Security Directors' lock box" to "Dialogic Pager Step 1.3 Code lock box". Reason: New name for pager lock box. 4, Change: Added an apostrophe to "Directors". Step 3 Reason: Typo correction. 5, Change: Added text to ensure that control room is informed of transfer of Steps 1.1.2 and communications duty with the county.

1.2.2 Reason

Clarifies when/how the control room is informed of this function. 8, Change: Revised area code from "616" to "269" in Michigan State Police Step 3 phone number. Reason: Change in area code. Figure 2 Change: Deleted position description for Emergency Planning; added a bullet to the EAD and Industry Support Communicator positions regarding solicitation of assistance from other utilities, per pre-arranged agreements. Reason: Position eliminated from the EOF; remind individuals that offsite RP and laboratory support is available per the agreements. 7 r:- ' `-A0ffl.ce nfornation-For FormTrackfng On,ly 'NotPart of-Form: f,c-> This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. I Oa. Page / of L/ Number:

Title:

AMERICAN o ELECTRIC RAIT-2080-EOF-001 Rev. 3 Page 1 of 50 Activation and Operation of the EOF Reference tEffective

L 1 C. J. Graffenius S. M. Partin Emergency Planning Writer Owner Cognizant Organization TABLE OF CONTENTS 1

PUTRPOSE AND SCOPE................. 3 2 -DETAILS................ 3 3 REFERENCES. 4 : : : : : : : : : 0: 1: 2: 3: 4: Activation.............................. 6 Briefings.............................. 8 Habitability................................ 9 Dose Assessment.............................. 10 Meteorological Data ................................ 13 Pasquill Category................................ 15 Classifications.............................. 16 Protective Action Recommendations (PAR)................................ 18 Document Transmission/Distribution................................ 21 Field Team Communications.............................. 23 Environmental Sampling................................ 27 Shift Designation................................ 29 Dialogic Paging System................................ 31 Logistical Support.............................. 33

AMERICAN'o l ELECTRIC l RMT-2080-EOF-001 Rev. 3 Page 2 of 50 Activation and Operation of the EOF Reference Effective Date: ai 105 C. J. Graffenius S. M. Partin Emergency Planning Writer Owner Cognizant Organization 5: County Communications........................................... 34 6: ENS Communications........................................... 36 7: HPN Communications............. .............................. 37 8: Michigan State Police Communications......................................... 38 9: External Support........................................... 39 0: Information Requests........................................... 41 Data Sheet 1: Meteorological Forecast........................................... 42 Data Sheet 2: Offsite Survey Log........................................... 43 Data Sheet 3: Environmental Sample Collection........................................... 44 Figure 1: Definitions and Abbreviations............................ ............... 45 Figure 2: Position Descriptions.47

Reference X RIT-2080-EOF-001 Rev. 3 Page-3 of 50 Activation and Operation of the EOF 1 PURPOSE AND SCOPE 1.1 This procedure provides guidance to Emergency Operations Facility (EOF) personnel during emergencies. 1.2 Use of this procedure is restricted to emergency conditions or drills/exercises only. NOTE: 10 CFR 50.54(x) and (y) describe the actions required if deviation from Technical Specifications or License Condition becomes necessary. 2 DETAILS 2.1 The Emergency Director (ED) implements this procedure. 2.2 Use Attachment 1, Activation, when an emergency response is initiated. 2.3 Use Figure 1, Definitions and Abbreviations for a listing of abbreviations, acronyms, and their meanings. 2.4 Figure 2, Position Descriptions contains supplemental directions for ERO personnel. 2.5 IF additional assistance from other utilities or agencies is required THEN refer to "Agreements With Off-Site Support Agencies" in the Emergency Plan. Phone numbers. are available in the Emergency Response Organization Phone Directory. 2.6 IF emergency responders have been directed to the Buchanan Office Building per Dialogic pager code '007', THEN make the following provisions: NOTE: The Shift Manager/SEC may direct that alternate communication links be used after initial contact is established with the control room. 2.6.1 Establish a line of communication with the affected unit Control Room or Unit 1 Control Room if a dual unit event is in progress.

a.

Any available personnel (such as the Control Room Communicator, Operations 'Advisor, or PET Operations) may establish communications between the EOF and the Control Room. 2.6.2 When conditions warrant (i.e., safe conditions at the plant) arrange for transportation of necessary OSC/TSC responders to the plant site. I

Reference RM'T-2080-EOF-001 Rev. 3 Page 4 of S0 Activation and Operation of the EOF NOTE: 0 = Optional M = Mandatory 2.7 Perform activities based on the following table. 3 REFERENCES 3.1 Use

References:

3.1.1 PMP-2080-EPP-101, Emergency Classification. 3.1.2 PMP-2081-EPP.105, Initial Core Damage Assessment. 3.1.3 RMT-2080-EOF-002, Emergency Termination and Recovery. 3.1.4 Donald C. Cook Nuclear Plant Emergency Plan. Activity Attachment/ Responsible Position UE Alert SA GE Procedure Activation 1 ED 0 M M M Briefings 2 ED M M M M Habitability 3 EAD M M Dose Assessment (EMD-32) 4 EAD 0 M M PAR 8 ED M Core Damage Assessment PMP-2081-Reactor Physics Analyst 0 0 0 EPP. 105 Classification 7 ED M M M M Document Transmission /9 Commnunications Director 0 M M M Distribution Field Team Communications 10 FMT Coordinator 0 M M Enviromnental Sampling 11 Field Teams Logistical Support 14 Scheduling/Planning 0 0 Manager Shift Designation 12 Security Director 0 0 0 0 Information Requests 20 Communications Director Extemal Support 19 Industry Support 0 0 0 Communicator ENS Conmunications 16 ENS Conmunicator M M M HPN Communications 17 HPN Communicator M M M County Communications 15 Berrien County M M Communicator State Communications 18 MSP Comrmunicator M M Termination/Recovery RMT-2080-ED M M M EOF-002

Reference RMT-20S0-EOF-001 Rev. 3 Page 5 of 50 Activation and Operation of the EOF' 3.2 Writ-ing

References:

3.2.1 Source References.

a.

Donald C. Cook Nuclear Plant Emergency Plan.

b.

EPA 400-R-92-001 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

c.

Dose Assessment Program - Computer Program, Rev. 7.

d.

Meteorology and Atomic Energy 1968. U. S. Atomic Energy Commission.

e.

Evacuation Time Estimates for the D. C. Cook Nuclear Plant Plume Exposure Emergency Planning Zone HMM Associates July 1992 (Rev. 1). 3.2.2 General References

a.

Michigan Emergency Preparedness Plan.

b.

Berrien County Emergency Preparedness Plan. I

Reference RMT-2080-EOF-001 Rev. 3 Page 6 of 50 Activation and Operation of the EOF Activation Pages: 6 - 7 NOTE: The EOF should be activated within 60 minutes of the time of a declaration of an Alert, SAE, or GE. I Ensure the facility has the foilowing or an acceptable alternate prior to activation. 1.1 Equipment Facility Power Plant Process Computer (RDR) Dose Assessment Programs and Printers Area Radiation Monitor Clocks set with the Plant Process computer 1.2 Conmunications 1.2.1 Telephones, Fax machines, or Radios to: State of Michigan Emergency Operations Center Berrien County Emergency Operations Center 1.2.2 Field Monitoring Team Radios 1.2.3 Communications with the Control Room 1.2.4 Managers Telephone Bridge 1.3 Personnel NOTE: With the exception of the Emergency Director, the use of non-qualified personnel is permissible provided they are briefed and understand the position specific requirements. O Emergency Director O Communications Director O Environmental Assessment Director O Boardwriter O Communicator - Berrien County Sheriff Department O Communicator - Michican State Police 0 Communicator -ENS I

2 Perform the-following: Assume responsibilities for communications with offsite agencies. Assume responsibilities for Classification, Notification and PARs from the SEC. Determine the time the control room will issue their last EMD-32. Determine the time the EOF will issue the first EMD-32, Nuclear Plant Event form; The EMD-32a must be issued within 15 minutes of a classification or PAR change. The EMD-32b must be issued within 30 minutes of.the last EMD-32a or EMD-32b. 3 Perform a facility brief. 4 Activate the facility. 5 Inform the other ERO facilities that the EOF has been activated. Reference I RMT-2080-EOF-001 I Rev. 3 T Page 7 of 50 Activationl and Operation of the EOF Attachment Activation Pages:

1 Announce the briefing time 2 to 3 minutes prior to it beginning. 2 Ensure everyone is paying attention, there are no phone conversations or side discussions taking place, and personnel remain stationary during the brief. 3 Perform the briefing. (Time limits are for reference only.) 3.1 Current Plant Status (1-Minute Maximum) Major on-going events Major Equipment out of service Prognosis Facility priorities 3.2 Current Classification (30-Seconds Maximum) PAR in effect Anticipated changes in classification or PAR 3.3 Status of the EOF (for initial briefings up to and including activation) -Activation Status (When command and control will be taken over from the Control Room), Problems delaying activation, Time the first EMD-32 is required for transmission to the State (at activation only). 3.4 Ask the EOF team for updates on important information Don't solve the problems here. Delegate; then update at the next briefing if necessary. 3.5 Ask the EOF team if anyone is having any problems Don't solve the problems here. Delegate; then update at the next briefing if necessary. Reference RMT-2080-EOF-001 I Rev. 3 Page 8 of 50 Activation and Operation of the EOF Briefings Page: 8

Reference RMT-2080-EOF-001 Rev. 3 Page 9 of 50 Activation and Operation of the EOF Habitability Page: 9 NOTE: The EOF has no specific habitability requirements because it is outside the 10-mile Emergency Planning Zone. Actions taken are at the discretion of the EAD. 1 IF a radioactive plume is expected to pass over the EOF, THEN: Issue dosimetry to all EOF occupants. Shelter or evacuate non-essential personnel in the Buchanan Office Building. Turn off or close dampers on ventilation systems that draw air from outside the facility. Have personnel remain in the EOF and office building. Perform routine surveys to assess dose rates, airborne activity, and post plume contamination. 2 Maintain the dose to the occupants of the EOF below the following for the duration of the emergency. TEDE < 5 Rem CDE Thyroid < 25 Rem I

1 UNLESS the State of Michigan EOC has been notified in advance of a delay or change in frequency, THEN transmit Nuclear Plant Event Technical Data forms (EMD-32b) to the State of Michigan at least every 30 minutes. 2 Obtain and record an 8-hour and 24-hour weather forecast on Data Sheet 1, Meteorological Forecast. 2.1 Forecasts are normally obtained through Murray and Trettle. The phone number is available in the Emergency Response Organization Phone Directory. 2.2 Provide Data Sheet 1, Meteorological Forecast, to the runners for distribution. 2.3 Obtain subsequent forecasts approximately every 8 hours. 3 IF a projected dose is NOT available from the Dose Assessment Program, THEN use projected doses based on measured dose rates from the field and expected duration of the exposure time. 4 IF projected doses are NOT available and a PAR is necessary, THEN use the default PAR. See Attachment 8, PAR. 5 Obtain Meteorological Data. See Attachments 5, Meteorological Data, and 6, Pasquill Category, for additional information and help. 6 Obtain radiological data as applicable. 6.1 Radiation Monitoring System (RMS) data listed in order of preference: PPC/RDR RMS Display Terminals Technical Support Center Direct readings from the Local Area Data Acquisition Modules 6.2 Field Team data Radiation reading Iodine concentration in jiCi/cc Sample location Reference RMT-2080-EOF-001 Rev. 3 I Page 10 of 50 Activation and Operation of the EOF Dose Assessment Pages:

7 Determine the Coolant Type from: EOF Reactor Physics Analyst Technical Support Center Plant Evaluation Team GO TO Initial Core Damage Assessment procedure, PMP-2081-EPP-105.

8 Determine the Projected Duration of the Release.

IF the projected duration of the release is unknown, THEN use 1-hour. -IF releases are occurring from multiple points, THEN use the longest projected duration. 9 Determine if an Actual Release versus a Potential Release is occurring. 9.1 An actual release is occurring when any of the following are true: Valid indication on release point radiation monitoring system channels are present that are associated with a classified event, or Measured offsite radiation readings indicate a release is in progress, or Indications exist that an unmonitored release may be occurring. 9.2 A potential release exists if calculated data is postulated based on present plant conditions (i.e., Containment Loss Of Coolant Accident, CLOCA). 10 Complete the EMD-32b form. The EMD-32b, Release/Offsite Dose Data section, is only required to be completed if a release is or is suspected to be occurring. The EMD-32b, Measured Offsite Radiation Levels section, needs only be reported when available. 11 Review the EMD-32b form to determine if a change in classification or PAR is required. 12 IF a change is necessary, THEN: Follow the instructions on the Classification or PAR attachment. Reference I IT-2080-EOF-001 Rev. 3 Page 11 of 50 Activation and Operation of the EOF Paanes: Dose Assessment 10I1

13 IF a change is not necessary, THEN: The ED approves the EMD-32b.form. Provide the EMD-32b form to the Fax operators for transmittal. Reference RMT-2080-EOF-001 Rev. 3 l Page 12 of 50 Activation and Operation of the EOF Dose Assessment Pages:

Reference RMT-2080-EOF-001 Rev. 3 l Page 13 of 50 Activation and Operation of the EOF Meteorological Data Pages: 13 - 14 NOTE: Wind speeds are expressed as Miles per Hour. To convert Knots to Miles per Hour multiply by 1.15. Consider lake breezes in the dose assessment process if all the following are true: The current date is between April 15 and October 31, The current time is between 1-hour after sunrise and 1-hour after sunset, Ambient temperature measured at the main tower must be greater then the Lake Michigan temperature, Wind speed on the shoreline tower is < 13.4 Miles per Hour, Pasquill category must be A, B, C, or D, Shoreline tower wind direction is FROM 205° to 23° (i.e., Wind is from ~the lake). Obtain meteorological data from one of the following sources. Sources are listed in order of preference. 1.1.1 Plant Process Computer 10 Meter Main 10 Meter Backup 60 Meter Main 1.1.2 Murray and Trettle

a.

Obtain the phone number from the Emergency Response Organization Phone Directory.

b.

Request to speak to a meteorological forecaster.

c.

Obtain Wind Speed in Miles per Hour Wind Direction from, in degrees Pasquill Category as a letter NOT a number Eight and 24-hour meteorological forecast

1.1.3 Manual Acquisition of Meteorological Tower Data Contact the Technical Support Center and request a team be dispatched to collect this data. 1.1.4 National Oceanic and Atmospheric Administration (NOAA) Obtain the plants NOAA phone extension from the Emergency Response Organization Phone Directory. Use any NOAA weather radio. Use the NOAA website Reference RMT-2080-EOF-001 Rev. 3 1 Page 14 of 50 Activation and Operation of the EOF Meteorological Data 13e14 I

1 Obtain Pasquill Category data from one of the following sources. Sources are listed in order of preference. 1.1 Plant Process Computer 1.2 Temperature Differential AT°F.= T@60m-T@ 10m Pasquill Category AT°C = T @ 60m - T lOm (Z = 50 Meters) .(Z = 50 Meters) AT F -1.8 A AT C - 1.0 -1. < AT F - 1.6 B -1.0 < AT C - 0.9 -1.6 < AT F - 1.4 C -0.9 < AT C - 0.8 -1.4 < AT°F -0.5 D -0.8 <AT°C -0.3 -0.5 < AT F +13 E ..3 < AT C ' +0.7. + 1.3 < AT F +3.6 F +0.7 < AT C +2.0 +3.6 < AT F G +2.0 < AT C Standard Deviation of the Horizontal Wind Direction (STD) STD Pasquill Category STD22.5 A 22.5 STD > 17.5 B 17.5>Ž STD >12.5 C.' 12.5 STD > 7.5 D .7.5 2 STD> 3.8 E 3.82STD > 2.1 F '2.1 2ŽSTD _ _ _ __4_:-G =.. Murray and Trettle See Attachment 5, Meteorological Data. Observation Incoming Solar Radiation (Day Only) -(1 hour after surlrise to 1 hour before sunset) Sun Angle Cloud Cover Degrees from Horizon None 1/8 - 5/8 5/8 - 7/8 8/8 .________.Middle Clouds Low Clouds 150 350 -Slight Slight Slight

-Slight:

Slight 350 - 600 Moderate Slight Slight Slight Slight > 600 Strong Strong Moderate Slight Slight Day Night Wind Speed @ 10 meters Incoming Solar Radiation Thinly Overcast or S 3/8 Miles per Hour (Mph) Strong Moderate Slight 2 4/8 Low Clouds Clouds Mph 5 A A-B B 5 < MphS7 A-B B C E F 7 < Mph 11 B B-C C D E 11 < Mph5 S13 C C-D D D D Mph > 13 C D D D D Reference l RiMT-2080-EOF-001 I Rev. 3 l Page 15 of 50 Activation and Operation of the EOF Pasquill Category Page: ~~~~~~~~~~~~~~15 1.3 1.4 1.5

1 Perform classifications using PMP-2080-EPP-101. 2 If a classification upgrade is made: 2.1 Note the time of the classification and determine the 15-minute notification time. 2.2 Notify the control room to initiate plant public address announcements and sound the Nuclear Emergency Alarm as specified in the control room procedures. 2.3 Complete an EMD-32a, Nuclear Plant Event Notification, form. 2.3.1 Reason for Classification: IF (H-1) SEC Judgement is used, THEN select the reason most applicable to the situation. 2.3.2 Radiological Release in Progress Due to Event is yes when: Valid indications on release point radiation monitoring system channels are present that are associated with a classified event, or Measured offsite radiation readings indicate a release is in progress, or Indications exist that an unrnonitored release may be occurring. 2.3.3 IF the classification is a General Emergency, THEN develop a PAR. 2.4 The ED approves the classification upgrade. 2.5 The ED notifies the State/County authorities. 2.5.1 If the State EOC has NOT been activated: Transmit the EMD-32a to the Berrien County Sheriff's Department The ED discusses the EMD-32a data and applicable PARs, with the Berrien County Sheriff's Department. 2.5.2 If the State EOC has been activated: Transmit the EMD-32a to the State of Michigan EOC. The ED discusses the EMD-32a data, and applicable PARs, with the State EOC. Referenlce RMT-2080-EOF-001 I Rev. 3 1 Page 16 of 5 Activation and Operation of the EOF Classifications It)e

2.6 Notify the other facilities as applicable. 2.7 Perform a facility brief. 2.8 Update the facility status boards/maps with classification data, PARs, and Protective Action Orders received from the State of Michigan. Reference RMT-2080-EOF-001 l Rev. 3 l Page 17 of 50 Activation and Operation of the EOF Classifications PGes: 16 - 17

Reference RAMT-2080-EOF-001 Rev. 3 Page 18 of 50 Activation and Operation of the EOF Protective Action Recommendations (PAR) Paes: 18 - 20 NOTE: PARs must accompany the declaration of a General Emergency. 1 Note the time of the PAR and determine the 15-minute notification time. 2 Use the Default PAR if: A General Emergency has been declared for non-radiological release conditions, or It is not possible to determine the Site Boundary TEDE or CDE dose and a release is, or is suspected to be, in progress. 3 Prior to developing a PAR, consider any forecasts of changing weather conditions. 4 IF a PAR or change in PAR is based on Dose Calculations, THEN an EMD-32b, Nuclear Plant Event Technical Data sheet must accompany the EMD-32a, Nuclear Plant Event Notification form. 5 Compare field team data to the projected -area of the PAR. 6 IF the field team data indicates the plume is outside the projected area, THEN change the PAR to include the actual data. 7 Update the EMD-32a with the PAR information. 8 The ED approves the PAR change. 9 The ED notifies the State/County authorities. 9.1 If the State EOC has NOT been activated: 'Transmit the EMD-32a (and EMD-32b as applicable) to the Berrien County Sheriff's Department. The ED discusses the EMD-32 data, and applicable PARs with the Berrien County Sheriff's Department. 9.2 If the State EOC has been activated:

Transmit the EMD-32a (and EMD-32b as applicable) to the State of Michigan EOC. The ED discusses the EMD-32 data, and applicable PARs with the State EOC. 10 Notify the other facilities as applicable. 11 Perform a facility brief. 12 Update the facility status boards/maps with classification data, PARs, and Protective Action Orders received from the State of Michigan. Reference I RAMT-2080-EOF-001-T Rev 3 l Page 19 of 50 Activation and Operation of the EOF Attachrnent 8 Protective Action Recommendations (PAR) P8ages:

R,A&Bto5miles [ Iand2 Reference RMT-2080-EOF-001 Rev. 3 l Page 20 of 50 Activation and Operation of te EOF Attaclment 8 Protective Action Recommendations (PAR) Pag 2 Q, R & A to 5 miles I

Referenice RMT-2080-EOF-001 1 Rev. 3 Page 21 of 50 Activation and Operation of the EOF § ~ ~ ~ ~ ~ 0 ~~~~~~Page: Document Transmission/Distribution 21 - 22 NOTE: Some of the facility Fax machines are designated within the phone directory as TRANSMIT and others as RECEIVE. These machines should remain in their designated mode to better facilitate communications between facilities. 1 Ensure the Fax machine dates and times are set correctly. 2 Obtain the Fax machine phone numbers for the facilities and off site agencies from the Emergency Response Orga'nization Phone Directory. 3 Forward all documents for duplication and distribution to the facility runners. 4 Forward all original documents to the Communication Director. 5 Log all incoming and outgoing Fax's in the facility Fax Log. 6 IF a Fax is NOT specifically addressed to an individual or position, THEN distribute incoming Fax's to all positions as described on the facility distribution map located in the copy area.

7 The following table gives additional direction on the transmission and distribution of material: Document Destiniation Frequency Additional Instructions Nuclear Plant Event State EOC EMD-32a The EMD-32a and b forms Notification Form Within 15 minutes of a transmitted to the State of (EMD-32a) classification or PAR Michigan should have change priority over all other Nuclear Plant Event Fax's. - Technical Data EMD-32b (EMD-32b) 30-Minutes after EMD-32a or EMD-32b is sent; Accompanying EMD-32a at General Emergency, OR PAR upgrade due to dose. TSC As Available ENC/JPIC As Available Distribution to the ENC/JPIC members. EOF As Available Distribute to EOF Personnel members. Meteorological State EOC As Available None Forecast Data Sheet 1 Berrien As Available None County EOC NRC As Available None EOF As Available Distribute to EOF Personnel members. Boardwriter Notes EOF As Available Distribute to EOF Personnel members. Reference RMT-20S0-EOF-001 Rev. 3 1 Page 22 of 50 Activation and Operation of the EOF Document TransmissionlDistribution Pae: I ~~~~~~~~~~~~~~~~~~~21 - 22

Reference RMT-2080-EOF-001 Rev. 3 Page 23 of 50 Activation and Operation of the EOF 0 Field Team Communications Pages: 23 - 26 NOTE: Assistance with off-site radiation protection activities may be arranged with the Industry Support Communicator and EAD per Step 2.5, Details, of this procedure. 1 IWHEN dose assessment is considering lake breezes, THEN dispatch the field teams along the standard routes to locations either North and/or South of the plant to determine if the plume is moving in a parallel path to the Lake Michigan shore line. NOTE: Verbal permission from the EAD and SEC may be used to authorize KI administration for field team members. RMT-2080-OSC-001, Data Sheet 3, KI Consent Form, should be completed as soon as practical thereafter. 2 IF the projected offsite dose rates for the team positions exceed 1 rem/hr TEDE or - 5 rem/hr CDE Thyroid, THEN consider: 0 Repositioning the team(s) to reduce the overall expected exposure. Distribution of Potassium Iodine (KI) to team members. 3 Have the field teams perform surveys based on the appropriate release status: 3.1 Pre-release - no release has occurred. 3.1.1 Determine the postulated direction and dispersion width of the plume based, on the wind direction, wind speed, Pasquill Category stability class, and its associated isopleth. 3.1.2 Position the survey vehicles downwind on Red Route 1. 3.1.3 Have the survey vehicle traverse the downwind portion of the route while surveying for radiation readings above background. 3.1.4 IF above background readings are reported, THEN notify the EAD immediately. An unmonitored release may be occurring. 3.2 Plume Phase

3.2.1 Determine the postulated direction and dispersion width of the plume based on the wind direction, wind speed, Pasquill Category stability class, and isopleth. 3.2.2 Use the projected dose rates as guidance to determine the best distance from the plant to collect airborne sample data without risking overexposure to field team members. Iodine and particulate materials tend to-plate out quickly on surrounding surfaces. Airborne samples should be collected at the location of the highest dose rate reading within the plume. 3.2.3 Direct the survey teams to perform either a full traverse or plume definition survey.

a.

Full Traverse

1.

Direct the survey teams to traverse the plume reporting back, as a minimum, boundary (0.1 mR/hr) and centerline (highest reading) data.

2.

IF an air sample is necessary, THEN have it taken at the plume centerline.

3.

Record the Field Team data on Data Sheet 2, Offsite Survey Log.

4.

Plot the data on a map to define the plume boundaries and centerline.

b.

Plume Definition

1.

Direct the survey teams to: Enter the plume until > 0.1 nR/hr is detected. Immediately exit the plume. Report back the plume boundary location and radiation reading.

2.

Record the Field Team data on Data Sheet 2,Offsite Survey Log.

3.

Plot the data on a map to define the plume boundary. Reference RMIT-2080-EOF-001 I Rev. 3 1 Page 24 of 50 Activation and Operation of te EOF ,Attachment 10 Field Team Cornmunications Pages:

Reference RaIT-2080e 001 cai o m Pae25 of 50 Activation and Operation of the OF Atitachment lO Field Team CommunicationsPae 3.2.4 IF field teams report a reading R/hr, THEN imiediately notify the EAD. A change in the emergency classification may be necessary. 3.2.5 Compare the field team data to the most recent PARs. 3.2.6 IF the field team data does NOT match the projected location of the plume, THEN immediately notify the EAD. A change to the PAR may be necessary. 3.3 Post Plume Phase 3.3.1 The post plume phase should be performed in 2 stages: (initial and long term)

a.

Initial (Ground Deposition Foot Print)

1. Direct the field monitoring teams to traverse the areas the plume covered starting close-in to the plant and working outward.

2.

Plot the results on a map to determine the extent of the ground deposition.

3.

NhEN the deposition footprint has been determined, THEN initiate the long-term post plume phase sampling.

b.

Long Term NOTE: Though the emergency may have been terminated prior to entering the long-term post plume phase, these directions are intended to give the field team guidance for the collection of samples.

1. Direct the field teams to collect soil, water, snow, and vegetation samples as applicable within the ground deposition area. Take samples in locations to define deposition on the ground.

2.

Direct the field teams to collect soil, water, snow, and vegetation samples as applicable outside the ground deposition area. Negative results are necessary to confirm no hazards are present.

3.

Plot the sample positions on a map to allow for further deposition analysis.

4 Direct field team(s) to one of the following locations (as appropriate) for analysis of sampling media as necessary during/after the emergency: Plant counting facility (OSC counting facility, Chemistry Lab., or RP counting facility). Palisades Nuclear Plant (coordinated with the Industry Support Communicator). 5 Analyze (or direct the analysis of) sampling media per RP and/or Chemistry counting room procedures. Rleference i RtMT-2080-EOF-001 I Re. Page 26 of 50 Activatioii and Operation of the OF .Attachnment 10 Field Team Communications Pages-I

1 Collect samples that are representative of the topography of the area unless otherwise specifically requested. 2 Change the volume or surface area of samples collected as conditions warrant. Note the changes in the comment section on the appropriate form. 3 Log all samples on Data Sheet 3, Enviromnental Sample Collection, giving a specific location listed in order of preference. -Physical location Onamap Using landmarks; ensure sufficient references are documented to relocate the specific area. 4 Perform Plume Surveys, as directed: 4.1 Plume Traverse 4.1.1 Traverse the route as instructed by the EOF, keeping the closed window probe outside the vehicle. 4.1.2 Record the location and reading on Data Sheet 2, Offsite Survey Log, where the instrument indicates: The leading edge of the plume (0.1 mRJhr) The centerline (highest reading) of the plume The trailing edge of the plume (0.1 mR/hr) 4.1.3 Transmit the data to the EOF. 4.1.4 IF an air sample was requested, THEN re-enter the plume to the instructed location and obtain the sample. This is normally performed at the plume centerline. 4.2 Plume Definition 4.2.1 Start the route as instructed by the EOF, keeping the closed window probe outside the vehicle. 4.2.2 Record the location and reading on Data Sheet 2,0ffsite Survey Log, where the instrument indicates the leading boundary ( 0.1 mR/hr) of the plume. Reference RMT-2080-EOF-001 Rev. 3 Page 27 of 50 Activation and Operation of the EOF 1 Environmental Sampling Pages-

Reference RMT-2080-EOF-001 Rev. 3 Page28 of 50 Activation and Operation of the EOF 1 Environmental Sampling Pages: 27 - 28 4.2.3 Exit the plume. 4.2.4 Transmit the data to the EOF. 5 Obtain an air sample as follows: Draw a minimum of 4 cubic feet of air. Document all air sample data on the air sample envelope. 6 Obtain soil, snow, water, and vegetation samples as follows: Use Data Sheet 3 for instructions for collection and documentation of environmental samples. 7 Return collected samples to the location specified by the EOF for analysis.

Reference RMT-2080-EOF-001 Rev. 3 Page 29 of 50 Activation and Operation of the EOF 2 Shift Designation Pages 29 -30 NOTE: Obtain individual phone numbers from the Emergency Response Organization Phone Directory. 1 Managers coordinate shift turnovers to ensure plant conditions allow individuals to report to their respective facilities without undue risk or exposure. 2 Security Director coordinates and communicates any plant access restrictions with the security force. 3 Finalize routing instructions prior to notifying any individuals. 4 Obtain position lists specific to the OSC and TSC from RMT-2080-OSC-001 and RMT-2080-TSC-001. 5 IF roadblocks have been established by local or state law enforcement, THEN the State EOC should be notified with the list of oncoming personnel to allow passage through roadblocks. 6 IF desired, THEN the Dialogic Paging system can be used to contact off-duty team members. Attachment 13, Dialogic Paging System gives detailed instructions for reprogramming and activation. Shift Start Time: Routing Instructions: Position Title Name Berrien County Liaison Boardwriter Communicator - Berrien County Sheriff Department Communications Director Communicator - Michigan State Police Communicator -ENS

Communicator -HPN Computer Analyst Emergency Director Engineering Design & Site Services Manager Environmental Assessment Coordinator (1) Environmental Assessment Coordinator (2) Environmental Assessment Director Fax Operator Field Monitoring Team Coordinator Industry Support Communicator Michigan State Police Liaison Operations Advisor Reactor Physics Analyst Regulatory Affairs Coordinator Runner (1) Runner (2) Scheduling & Planning Manager Security Director Reference RMT-2080-EOF-001 Rev. 3 l Pae30 of 50 Activation and Operation of the EOF 2 Shift Designation Pages 29 -30 I2

Reference RMT-2080-EOF-001 Rev. 3 Page 31 of 50 Activation ad Operation of the EOF 3 Dialogic Paging System Pages: 0 '~~~~~31 -32 NOTE: The Dialogic Paging system can be reprogrammed to contact off-duty members of the Emergency Response Organization. These actions should only be performed from one facility, preferably the EOF, and should be done to provide subsequent staffing for ALL facilities. 1 Prior to contacting Dialogic: 1.1 Notify the facility managers to instruct all ERO members who are currently in a facility, NOT to respond to the page. 1.2 Prescript the instructions (Dialogic refers to this as a greeting) that will be recorded prior to the activation of the pagers. Consider: 1.2.1 All ERO pagers will be activated. You cannot select a specific team for response. 1.2.2 Having ERO members contact the EOF at particular phone number(s) to receive further instructions after accepting a position. 1.2.3 Where and how the individuals should report. If a release has occurred, it may be advantageous to have member's report to the EOF for transport to the plant. 1.2.4 What time the ERO members are to report. 1.3 Obtain the password code, located in the Dialogic Pager Code lock box in the EOF. 2 - To change the recorded instructions for responding ERO members and activate the scenario: 2.1 Call Dialogic. The Dialogic Pager Activation phone number can be obtained from the Emergency Response Organization Phone Directory. 2.2 The system will ask you for your company ID number, followed by the # sign. Enter 1344 # 2.3 The system will ask for your scenario activation password, followed by the # sign. Enter the password code followed by the # sign.

Reference RMT-2080-EOF-001 Rev. 3 Page 32 of 50 Activation and Operation of the EOF .Attachment 13 l Dialogic Paging System 3l-3 2.4 To start a scenario, enter the scenario ID followed by the # sign or press # alone for more options. Enter 911 # 2.5 The system will state: 2.5.1 To listen-to the current scenario message, Press 1 2.5.2 To re-record the scenario message, Press 2 The system will direct you to record the new message followed by the

sign.

2.5.3 To start the scenario, Press 3 The system will respond with "The scenario is building". Press # and hang up. 2.5.4 To return to the main menu, Press # The system will give more options to consider or press # to end this call. 2.6 Reports will be faxed to the EOF containing the names of the individuals who have responded and accepted a position. 2.7 Forward results to the appropriate facility managers.

Reference RMIT-2080-EOF-001 Rev. 3 Page 33 of 50 Activation and Operation of the EOF 4 Logistical Support Page: 33 NOTE: The Scheduling and Planning Manager can provide the following services to the ERO. This position has the authority to purchase or lease materials and e4uipment necessary to support the ERO and the Plant and to generate contracts necessary for the augmentation of staffing. Arranging lodging for ERO personnel who cannot return to their homes because of an evacuation. Arranging lodging for personnel responding from outside agencies.

Providing for the purchase of food to ERO facility members and support personnel.
Purchasing or renting equipment necessary to mitigate or respond to emergencies.
Providing for additional assistance from contractors or other agreement facilities.
Arranging for delivery of equipment and materials.
Providing assistance for contractual issues.

Other services as deemed necessary by the Emergency Director. 1 Obtain permission from the Emergency Director to initiate the requested actions. 2 Generate the appropriate documents necessary to perform the requested action. 3 UPON completion of the documents, THEN obtain the Emergency Director's approval. 4 IF the materials need to be brought into the 10-mile Emergency Planning Zone, THEN: Obtain concurrence from the Environmental Assessment Director for delivery restrictions. Discuss the delivery route with the TSC Security Director. Ensure the State of Michigan EOC has been notified of the intended delivery and route. 5 Implement the approved request, including any restrictions.

Reference RMT-2080-EOF-001 Rev. 3 Page 34 of 50 Activation and Operation of the EOF 5 County Communications Pages: 34 - 35 NOTE: The Berrien County Emergency Operations Center may not be operational immediately after the declaration of a Site Area or General Emergency. Continue to conmunicate with the Berrien County Sheriff's Department until the Berrien County EOC is operational. 1 Contact the appropriate Berrien County facility based on the emergency classification. 1.1 Alert 1.1.1 Contact the Berrien County Sheriff's Department. 1.1.2 Once communications are established and upon activation of the EOF ensure that the unaffected Control Room is informed that the EOF has taken over communications with Berrien County. This may be done via the Boardwriters' or Managers' Bridge. 1.1.3 UPON receipt of an EMD-32a or EMD-32b, THEN provide the following information:

a.

Provide your name, Title (BCSD Communicator), and your telephone number.

b.

Provide the remainder of the information as entered on the EMD-32. 1.1.4 UPON receipt of any inquiries from the Sheriff's Department, THEN follow the instructions on the Information Request attachment. 1.1.5 UPON completion of each communication with the Sheriff's Department, THEN hang up the phone and re-establish communications when necessary. 1.2 SAEORGE 1.2.1 Contact the Berrien County Liaison at the Berrien County EOC. This individual is provided to the county EOC by AEP and is an AEP employee. 1.2.2 Once communications are established and upon activation of the EOF ensure that the unaffected Control Room is informed that the EOF has taker over communications with Berrien County. This may be done via the Boardwriters' or Managers' Bridge.

Reference RiI'T-2080-EOF-001 Rev. 3 Page 35 of 50 Activation and Operation of the EOF 5 County Communications Pages: 34 - 35 1.2.3 UPON receipt of an EMD-32, THEN provide the following information:

a.

Provide your name, Title (BCSD Connunicator), and-your telephone number.

b.

Provide all information except the Protective Action Recommendations on the EMD-32a. 1.2.4 UPON receipt of any inquiries from the Berrien County EOC, THEN follow the instructions on the Information Requests attachment. 1.2.5 Maintain constant communications with the Berrien County EOC. Do not hang up the phone.

I Contact the NRC using the Emergency Notification System phone. 1.1 Dial the MAIN number listed on the phone. IF there is no answer, THEN dial the BACKUP number. 1.2 Once communications is established state the following: "This is the D. C. Cook Emergency Operations Facility. This is an initial contact notification to ensure communications have been established. The EOF is not activated at this time. Communications relative to plant status should continue from-the control rooms. 2 Provide the NRC Duty Officer witlh the following information relative to plant conditions: Current emergency classification. Emergency Condition Category (ECC) under which the emergency was declared. Include'the ECC number, title, and a brief description of the actual event. Current plant conditions. 3 Continue to notify the NRC of changes such as: Changes to the emergency classification Status of injured personnel Equipment unavailability Damage control team status Calculated leak rates Core damage assessment Fission product barrier status 4 UPON receipt of any inquiries from the NRC that cannot be answered using data already available from other sources, THEN follow the instructions on the Information Requests attachment. Reference RMT-2080-EOF-001 R 'ev. 3 Page 36 of 50 Reference I,e. Activation and Operation of the EOF -Attachment 16 ENS Communications Page: 36

Contact the NRC using the Health Physics Notification System phone. 1.1 Dial the MAIN number listed on the phone. IF there is no answer, THEN dial the BACKUP number. -1.2 Once communications is established state the following: "This is the D. C. Cook Emergency Operations Facility. This is an initial contact notification to ensure communications have been established. Communications relative to Health should continue from the control rooms. 2 Provide the NRC Duty Officer with the following information relative to plant conditions: Current emergency classification. Emergency Condition Category (ECC) under which the emergency was declared. Include the ECC number, title, and a brief description of the actual event. Current plant conditions. 3 Continue to notify the NRC of changes from the EMD-32 such as: Changes to the emergency classification Meteorological data Radiological releases Calculated offsite dose and dose rates Field Team monitoring data PAR 4 UPON receipt of any inquiries from the NRC that cannot be answered using data already available from other sources, THEN follow the instructions on the Information Requests attachment. Reference I RMT-2080-EOF-001 Rev. 3 t Page 37 of 50 Activation and Operation of the EOF Aitachment 17 HPN Communications Page: 37

Reference RMT-2080-EOF-001 Rev. 3 Page 38 of 50 Activation and Operation of the EOF ~~~~~~~~~~~~~~~~~~~a-age: .Attachment 18 Michigan State Police CommnunicationsPae38 NOTE: Phone extension 1088 exists in the control rooms and the EOF MSP Communicators position. Communications should already be established between the Control Room and the MSP. 1 Contact the Control Room and the MSP Operations Center by: 1.1 Using EOF phone extension 1088, pick up the handset and listen for a dial tone. 1.2 IF a dial tone is present, THEN using another phone, contact the Control Room MSP Communicator by dialing extension 1088. 1.3 IF a dial tone is NOT present, THEN identify yourself and wait for a reply from the Control Room and/or the State. 2 WHEN communications is established, THEN provide the current activation status of the EOF. 3 IF, after activation, the EOF is NOT capable of faxing EMD-32 forms to the State, THEN transmit the information verbally. Provide your name, Title (MSP Communicator), and your telephone

number (1-269-465-5901, Ext. 1088).

Provide the remainder of the information as entered on the EMD-32a or EMD-32b. 4 UPON receipt of any inquiries from the MSP, that cannot be answered using data already available from other sources, THEN follow the instructions on the Inforrnation Request attachment.

I UPON declaration of an Alert, SAE, or GE, and activation of the EOF, THEN contact the following agencies. Obtain phone numbers and contact names from the Emergency Response Organization Phone Directory. American Nuclear Insurers (ANI) Institute of Nuclear Power Operators (INPO) Westinghouse 2 Provide each with the following information: 2.1 ANI Plant status Current emergency classification Offsite PAR Offsite Protective Action Orders 2.2 INPO Plant status Unavailable equipment Current emergency classification Offsite PARs Offsite Protective Action Orders 2.3 Westinghouse Plant status Unavailable equipment Current emergency classification 3 UPON receipt of any inquiries that cannot be answered using data already available from other sources, THEN follow the instructions on the Information Requests attachment. 4 IF requested, arrange for assistance from the following power plants per Step 2.5, Details, of this procedure. Palisades Nuclear Power Plant for analysis of sampling media (Reciprocal Laboratory Use Agreement). Reference l RMT-2080-EOF-00l1 Rev. 3 Page 39 of 50 Activation and Operation of the EOF Page: 9 External Support 39 4

Reference I RMT-2080-EOF-001 I Rev. 3 l Page 40 of 50 Activation and Operation of the FOF 9 External Support - Page: 39 - 40 a Palisades Nuclear Plant or Fermi II for assistance with off-site radiation protection activities.

Reference l RMT-2080-EOF-001 Rev. 3 l Page 41 of 50 Activation and Operation of the EOF 0 Information Requests Page: J NOTE: Information requests are designed -to document questions and answers for information nQt normally available. 1 Generating a request. 1.1 Print information request on all-purpose forms in complete and legible format. 1.2 Supply the following minimal information: Position requesting the information. Position the request is being sent to. Detailed question. 1.3 Retain the bottom copy. 1.4 Forward the request to the Communications Director. 1.5 The Communications Director: 1.5.1 .Reads the request and ask for clarification if necessary. 1.5.2 Forwards the request to the appropriate position. 2 Responding to a Request. 2.1 Print responses in complete and legible format. 2.2 Forward the response to the Communications Director. 2.3 The Communications Director: 2.3.1 Forwards a copy of the response to the originator. 2.3.2 Retains the original message form.

Facility: Cook Nuclear Plant Time/Date Forecast Obtained: _______________________________I________________________ Forecast Source: Murray & Trettle NOAA Other A. Eieht Hour Forecast Wind Direction: Wind Speed: Differential Temperature: Stability Class: Degrees From Miles Per Hour °F or °C Remarks: B. Twenty-four Hour Forecast -Wind Direction: Wind Speed: Differential Temperature: Stability Class: Degrees From Miles Per Hour °F or °C Remarks: Reference I RMT-2080-EOF-001 I Rev. 3 1 Page 42 of 50 Activation and Operation of the EOF Data Sheet 1 Meteorological Forecast Page: 42 1. 2. 3. 4. 5. 1. 2. 3. 4. 5.

Reference l RMT-2080-EOF-001 l Rcv. 3 l Pagc43 ofS0l Activation and Operation of te EOF Data Sheet 2 Offsite Survey Log Page: Date Time Leading Edge Centerline Trailing Edge Initials Location Reading Location Reading Location Reading

Environmental Sample Collection Data Sheet Date: Time: Sampled By:_ Type: Soil Snow Water Vegetation Location: Location Commnents: Soil

1) Do NOT obtain samples from disturbed areas or under trees containing foliage.

2) Remove sufficient soil from the surface of the area to fill a 4-liter sample container.

3) Mark all containers with the date, time, and samplers initials.

Surface area of material removed cm2 Snow

1) Do NOT obtain samples from drifts, disturbed areas, or under trees containing foliage.

2) IF additional snow has fallen since the release occurred, THEN remove fresh snow to obtain a representative sample.

3) IF it was snowing during the plume phase, THEN take the-sample to the depth of the accumulated snow exposed to the plume.

4) Collect a minimum of 12-liters of snow.

5) Mark all containers with the date, time, and samplers initials.

Surface area of material removed cm2 Depth cm Water

1) Do NOT collect samples from stagnant pools under trees containing foliage.

2) Avoid disturbing and collecting the surrounding sediment.

3) Collect a minimum of 4 liters of water.

4) Mark all containers with the date, time, and samplers initials.

Sample obtained from a: Stagnant Pool Running Tributary Vegetation

1) Do NOT obtain samples from disturbed areas or under trees containing foliage.

2) Cut as close to the root as possible, when sampling ground vegetation.

3) Remove material from the outer, exposed areas only, when sampling trees or bushes.

4) Collect only the normally edible portion, when sampling foodstuffs.

5) Collect a minimum of 12 liters of vegetation.

6) Mark all containers with the date, time, and samplers initials Surface area of material removed cm2 Reference RMT-20S0-EOF-01 Rev. 3 I

Page 44 of 50 Activation and Operation of the EOF Data Sheet 3 Environmental Sample Collection Page 44

Reference RMT-2080-EOF-001 Rev. 3 Page 45 of S0 Activation and Operation of the EOF Figure 1 Definitions and Abbreviations Pages: 45 - 46 Term Meaning AEP American Electric Power ANI American Nuclear Insurers BCSD Berrien County Sheriff's Department CDE Committed Dose Equivalent CLOCA Containment Loss of Coolant Accident DAP Dose Assessment Program EAD Environmental Assessment Director ECC Emergency Condition Category ED Emergency Director EMD-32a Nuclear Plant Event Notification form EMD-32b Nuclear Plant Event Technical Data form EOC Emergency Operations Center EOF Emergency Operations Facility ENS Emergency Notification System ERO Emergency Response Organization FMT Field Monitoring Team GE General Emergency HPN Health Physics Network INPO Institute of Nuclear Power Operations JPIC Joint Public Information Center KI Potassium Iodine thyroid blocking agent

Reference RMT-2080-EOF-001 Rev. 3 Page 46 of 50 Activation and Operation of the EOF Figure 1 Definitions and Abbreviations Pages 45 - 46 Term Meaning MSP Michigan State Police NOAA National Oceanic and Atmospheric Administration NRC Nuclear Regulatory Commission OSC Operations Support Center PAO Protective Action Order PAR Protective Action Recommendation PC Personal Computer PET Plant Evaluation Team PPC Plant Process Computer PORV Power Operated Relief Valve RDR Real-Time Data Repository RMS Radiation Monitoring System SAE Site Area Emergency STD Standard Deviation TEDE Total Effective Dose Equivalent TSC Technical Support Center X/Q Mathematical term for Dispersion Coefficient AT Net Temperature Difference AZ Net Vertical Distance

The position descriptions provided are intended as guidance. Deviations and additions to these descriptions are allowed as long as the accomplished objectives can be achieved. Berrien County Liaison Reports to the Berrien County EOC at an SAE or GE. He should be dispatched at an Alert if escalation is expected. Assists county personnel with interpretation of data supplied by plant and state facilities as necessary. Boardwriter Reports to the Communications Director. Obtains data from the other facilities and the EOF that is considered common to all facilities and the affected control room in a chronological order. Provides other facilities with information and decisions generated in the EOF. Maintains the Emergency classification Board with the proper emergency classification, classification time, and reasons for the classification. Documents incoming messages or inquiries to other EOF personnel on all-purpose message forms and forwards them to the Communication Director. Provides the EOF runners with copies of board data at, at least, 15-minute intervals. Berrien County Sheriff Department Communicator Reports to the Communications Director. Prior to activation of the Berrien County EOC, provides plant status to the county. Upon activation of the Berrien County EOC, provides plant status and radioactive release data to the Berrien County Liaison. Communications Director Reports to the Emergency Director. Directs and coordinates communication activities within the facility. Computer Analyst Reports to the Comnmunications Director. Provides for all repair/replacement of computer related equipment in the EOF. Operates the PPC/RDR used to display data throughout the EOF. Emergency Director Is responsible for the overall command and control of the emergency. Assumes responsibility for Classification, Notification and PAR's. Communicates with senior state and county officials on plant conditions and PARs. Reviews press releases. Directs and coordinates EOF activities. ~~~~~~~~~-T T-Pag 4of0 Reference 7 RiMT-2080-EOF-001 Rev. 3 Page 47 of 50 Activation and Operation of the EOF Figure 2 Position Descriptions Pages:

Activates the EOF. Maintains regular communication with the other facility managers on the Managers Bridge. Updates EOF members through facility briefs on the status of the emergency approximately every 30 minutes. Informs the Environmental Assessment Director of changes in plant parameters that may effect off-site releases or PARs. Engineering Design & Site Services Manager Reports to the Emergency Director. Coordinates engineering and technical support from sources outside the ERO. Provides engineering support and analysis to the EOF. ENS Communicator Reports to the Communications Director. Provides information to the NRC relative to plant equipment conditions and plant status. Environmental Assessment Coordinator Reports to the Environmental Assessment Director. Evaluates plant effluent readings for indications of radiological releases. Evaluates off-site field team data. Performs dose assessment. Generates EMD-32 Nuclear Plant Accident Notification forms. Make recommendations to the Environmental Assessment Director relative to radioactive releases and plant status. Environmental Assessment Director Reports to the Emergency Director. Directs and coordinates offsite radiological assessment. Provides basic direction to the Environmental Assessment Coordinators for performing dose assessment. Generates PARs Directs the Field Team Coordinator for placement of survey vehicles. Provides overall radiological habitability assessments of the EOF. Requests off-site assistance per pre-arranged agreements with other utilities, if necessary. Fax Operator Reports to the Communications Director. Provides Fax services to personnel within the EOF. Reference RMT-2080-EOF-001 Rev. 3 Page 48 of 50 Activation and Operation of the EOF Figure 2 Position Descriptions Pages 47 - 50

Forwards all copies of incoming Fax's to the facility Runners for distribution and maintenance. Forwards all original outgoing Fax's and data sheets to the Communications Director. Field Monitoring Team Coordinator Reports to the Environmental Assessment Director. Directs off-site monitoring teams for tracking of radioactive releases (Plumes). Directs off-site monitoring teams for collection of post plume samples. Provides data plots to the Environmental Assessment Team showing plume locations and footprints. HPN communicator Reports to the Communications Director. Provides information to the NRC relative to radiological conditions on-site and off-site releases. Provides PARs and Protective Action Orders information. Industry Support Coordinator Reports to the Communications Director. Provides communications links to ANI, Westinghouse, and INPO relative to plant status and radioactive releases. Arranges for assistance per pre-arranged agreements with other utilities, if necessary. Michigan State Police Communicator Reports to the Communications Director Provides plant status and PAR data to the State of Michigan EOC. Michigan State Police Liaison Reports directly to the State of Michigan Emergency Operations Center in Lansing, Michigan. Reports to the State of Michigan EOC at a'SAE or GE. He should be dispatched at an Alert if escalation is expected. Obtains answers to inquiries form the State of Michigan and ensuring these responses-are relayed to the State. Assists state personnel with interpretation of data supplied by plant facilities as necessary. Reference RMT-2080-EOF-001 Rev. 3 Page 49 of 50 Activation and Operation of the EOF 'Figure 2 Position Descriptions Pages: I 1 ~~~~~~~~~~~~~~~~~~~47 - 50

Operations Advisor Reports to the Emergency Director. Assists the ED with classification determinations. Provides EOF personnel and off-site agencies with plant status clarifications. Reactor Physics Analyst Reports to the Engineering Design & Site Services Manager. Provides EOF personnel with the current core status. Deternines the current reactor coolant status used in dose assessment. Coordinates core damage assessment with TSC-PET personnel. Regulator Affairs Coordinator Reports to the Emergency Director. Provides guidance to the Emergency Director for license-based decisions and actions. Primary EOF contact for the NRC site response team. Runner - Reports to the Communications Director. Picks up and delivers copies of forms generated by EOF personnel needing either faxing to other facilities or duplication and distribution to EOF personnel. Scheduling & Planning Manager Reports to the ED and Engineering Design and Site Services Manager. Provides support for items such as meals, transportation, temporary lodging, and other logistical issues for personnel within the ERO and other organizations responding to the facility. Purchases, leases, or contracts with suppliers for equipment, materials, or personnel necessary to support the emergency. Security Director Reports to the Emergency Director. Maintains control of personnel entering and exiting the facility. Maintains control of unauthorized personnel within the owner-controlled area at the Buchanan Office Building Provides transportation to and from the plant as necessary. Arranges shift designations. Telecommunications Personnel Reports to the Communications Director. Provide any communications equipment or repair/replacement necessary to support the emergency facilities. Reference RMT-2080-EOF-001 Rev. 3 l Page 50 of O0 Activatioin and Operation of the EOF Figure 2 Position Descriptions Pages: 47 - 50

REVIEW AND APPROVAL TRACKING FORM Procedure Jformation: Number RMT-2080-EOF-002 Rev. I Change: 0

Title:

Emergency Termination and Recovery Category (Select One Only): 5 Correction (Full Procedure) 3 Change (Full Procedure) with Review of Change Only EJ Correction (Page Substitution) O Change (Page Substitution) with Review of Change Only 5 Cancellation 5 New Procedure or Change with Full Review 7 Supcrseded (list superseding procedures): Associated Configuration Impact Assessments: Change Driver/CDI Tracking No(s).: N/A Required Reviews: Cross-Discipline Reviews: Programmatic Reviews: 5 Chemistry a Training 5 ALARA r Reactivity Mgmt Team 5l Maintenance 5 Work Control 5 Component Engineering [- SPS (Safety & Health) a NDM C Emernencx a Design Engineering 5 Surveillance Section l Operations Directors a Emerg Oper Proc Grp a System Engineering Ej PA/PV 5 [5Environmental a 5] Reg Affairs [O [ ISIIIST Coordinator a 5 RP O E Perforrmance Assurance Z None Required 5 None Required Z Cognizant Org Review: __Date:_1 Technical Review: Date: I/J Concurrence: 5 Ops Director Concurrence: N/A Date: / Package Check: I Updated Revision Summary attached? s Yes 10 CFR 50.59 Requirements complete? TrackingNo.: L0j-1 E Yes SN/A Implementation Plan developed? E. Step 3.4.17) DYes SN/A Package Complete: Date: a I3j Approvals: PORC Review Required: Z Yes [] No Mtg. Noi, Administrative Hold Status: 5 Released Rei NIA CR No.:_ Approval Authority alAutho r Date: / /11 /' Expiration DateEndingN/ Effective Date: I /rlj/0 Periodic Review: Periodic Review conducted? (Data Sheet 5 Complete) 5 Yes 3 No Follow-up Actions: Commitment Database update requested in accordance with PMP-7 100-CMP-001? 5l Yes 3 N/A NDM notified of new records or changes to records that could affect record retention? a Yes E N/A >1 7E 0 9

D

5 z

Page o Office Information For Form Tracking Only - Not Part of Form This forn is derived from the infornation in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10, Data Sheet I, Review and Approval Tracking Forn. I 4 I

REVISION

SUMMARY

RMT-2080-EOF-002 Emermencv Termination and Recoverv Revision: I Change: 0 Number:

Title:

Scction or Step Change/Reason For Change Step 2.3 Change: Added the following text to the step: "for a Site Area Emergency or General Emergency only. PORC concurrence is not required for an Unusual Event or Alert." Reason: Lesson learned from Alert event of 6/12/02; Plant Manager input. Consensus of managers revealed that PORC concurrence not necessary for an Unusual Event or Alert termination. Step 2.4 Change: Removed the reference to obtain agreement from "local organizations, and FEMA" to terminate an emergency classification. Reason: The State of Michigan (or Berrien County if State EOC is not activated) and the NRC are the concurrence organization contacts necessary to terminate an event; concurrence of FEMA and "local organizations" are not required to terminate. Step 2.5 Change: Added text for EOF to send a final EMD-32a form upon termination and for notifying the ERO of the termination. Reason: Incorporation of "termination" check box on State of Michigan EMD-32a form; enhancement to inform the remainder of the ERO of event termination. Of fice Information For Form Tracking Only - Not Part of Form This is a free-form as callei out in PMP-201 0-PRC-002, Procedurc Correction, Change, and Review, Rev. 10. Page 7 of a

ZLN RMIT-2080-EOF-002 Rev. I Page 1 of 5 Emergency Termination and Recovery Information T I Effective Date:i/17/05 C. J. Graffenius S. M. Partin Emergency Planning Writer Owner Cognizant Organization TABLE OF CONTENTS 1 PURPOSE AND SCOPE................... 2 2 DETAILS................... 2 3 REFERENCES.................. 5

Information R RMT-2080-EOF-002 i Rev. 1 Page 2 of 5 Emergency Termination and Recovery I PURPOSE AND SCOPE 1.1 This procedure provides guidance to the Emergency Response Organization (ERO) for termination of the emergency and initiating recovery actions from an Alert, Site Area Emergency, General Emergency, or when directed by the Site Emergency Coordinator (SEC). 1.2 The termination of an emergency and subsequent recovery efforts will depend on the nature of the emergency and the status of plant systems following the emergency. The general provisions within this procedure are expected to be applicable to all emergencies, however, it is permissible to supplement or deviate from this guidance with provisions specific to the emergency at hand. 1.3 Use of this procedure is restricted to emergency conditions or drills/exercises only. 2 DETAILS 2.1 IF the Emergency Directors' (ED) position has been staffed THEN, the ED assumes the responsibilities for implementation of this procedure OTHERWISE, the SEC maintains these responsibilities. 2.2 Prior to termination of the emergency or reduction in the emergency staff and its facilities the ED: Evaluates existing conditions with respect to the criteria established for each emergency classification. a Determines that plant conditions are stable and will continue to improve. Determines the plant has control of and terminated any non-routine releases of radioactive material to the environment and dose assessmentlprotective action recommendations can be terminated. Determines the control or cessation of any fires, floods, earthquakes, windstorms, or similar natural occurring phenomenon. Determines equipment availability is adequate and can be accessed for repair or redundant systems are available. Determines the plant status relative to technical specifications, including any compensatory actions. Determines that long term corc cooling is available. Determines the core shutdown margin is adequate.

Information RMT-2080-EOF-002 Rev. 1 Page 3 of 5 Emergency Termination and Recovery Determines the core shutdown margin is adequate. Determines offsite power is available for long term operation of emergency equipment. Determines offsite conditions will not limit access of personnel or support resources. Determines access to radiological areas of the plant necessary for operation of plant equipment is adequate. a Ensures all required notifications have been completed. 2.3 Obtain Plant Operations Review Committee (PORC) concurrence with the above evaluation for a Site Area Emergency or General Emergency only. PORC concurrence is not required for an Unusual Event or Alert. 2.4 IF it is determined the emergency can be terminated THEN prior to termination the ED obtains agreement to terminate the emergency with the NRC and the State of Michigan, (or Berrien County if the State EOC is not operational). 2.5 IF an agreement is reached, THEN the ED terminates the emergency by: Faxing a final EMD-32a form to offsite agencies indicating that the event is terminated,

Informing the ERO that the event is terminated.

2.6 UPON termination of the emergency, THEN the ED: 2.6.1 Assembles a Recovery Team with the following recommended disciplines: Managerial Operations Engineering Maintenance Radiation Protection Chemistry Safety Scheduling

Information RMT-2080-EOF-002 I Rev. I I Page 4 of 5 Emergency Termination and Recovery Emergency Planning a Plant Protection Licensing a Training 2.6.2 The ED briefs the Recovery Team on current plant and emergency status. NOTE: Steps 2.6.3 and 2.6.4 should be performed concurrently. 2.6.3 The Recovery Team: 1, Develops an initial recovery plan and recovery organization

2.

Obtains PORC approval of the plan

3.

Implements the plan 2.6.4 The Recovery Team: Apprises all offsite agencies of the recovery process. Coordinates recovery activities with offsite agencies, as applicable. Assembles all documentation generated during the emergency. Terminates all emergency radiation exposure limit controls. Obtains PORC review and approval of any procedures to be used relative to nuclear safety and plant recovery. Documents any procedural changes or corrections instituted during the emergency either through termination or the procedure change process. Restores the emergency response facilities and organization to its full readiness. 2.7 WVHEN the plant has been restored to its pre-emergency status or to a modified pre-emergency status capable of power operations, THEN the ED terminates recovery efforts.

Information I RMT-2080-EOF-002 I Rev. I Pagc 5 of 5 Emergency Termination and Recovery 3 REFERENCES 3.1 Use

References:

3.1.1 None 3.2 Writing

References:

3.2.1 Source References

a.

D. C. Cook Nuclear Plant Emergency Plan

b.

NUREG-0654 Criteria For Preparation And Evaluation Of Radiological Emergency Response Plans And Preparedness In Support Of Nuclear Power Plants. 3.2.2 General References

a.

10 CFR 50, Appendix E

REVIEW AND APPROVAL TRACKING FORM Number: RMT-2080-OSC01 Rev. 2 Change: 0

Title:

Activation and Operation of the OSC El Correction (Full Procedure) Change (Full Procedure) with Review of Change Only E Correction (Page Substitution) El Change (Page Substitution) with Review of Change Only ElCancellation El New Procedure or Change with Full Review O Superseded (list superseding procedures): Change Driver/CD1 Tracking No(s).: N/A Cross-Discipline Reviews: Programmatic Reviews: O Chemistry . U Training 0 ALARA Performance Assurance O Maintenance 1] Work Control l Bus. Services Proc Grp El Reactivity Mgmt Team O NDM _SEC/ED El Component Engineering l SPS (Safety & Health) E Operations 0 El Design Engineering. 0 Surveillance Section El PA/PV El Bmerg Oper Proc Grp O System Engineering O Reg Affairs O _ Environmental El A RP E None Required O ISIIIST Coordinator v 0 None Required Cogiiizant Org Review: =*Date: 1.27160 iTechnical Review: t7Date: C / _O/ 2 El Ops Mgr Concurrence: N/A ¢ - Date: / 1 0 -Owner Concurrence' Date: j.LZ7 lo. Updated Revision Summary attached? 1 zy6s 10 CFR 50.59 Requirements complete? Tracking No.: 2002B4-00 0 Yes El N/A Implementation Plan developed? ef. Step 3.4.18) El Yes Eg N/A Package Complete: -_Date: _/ PORC Review Required: 0 Yes l No Mtg. No.: 3 57 E Administrative Hold Status: E Re ed Q leissued 0 N/A CR No.: Approval Authority Review/Approval: Date: IL, /QO Expiration Date/Ending Activity Effective. Date: 0 0 Periodic Review conducted? (Data Sheet 5 Complete) El Yes 0 No _2_S __l_ X M~~~~~~~~~~~~~~~ Commitment Database Updated? El Yes O 0 N/A NDM notified of new records or changes to records that could affect record retention? O Yes E N/A This form is derived from theififormation in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 9a. Data Sheet 1, Review and Approval Tracking Form.' Pages I of 2

REVISION

SUMMARY

Number: RNU4-2080-OSC-001 Revision:: '2

Title:

Acti-vation and Operation of the OSC-Change:0 Ng marginal markings.used. Section or Step Change/Reason For Change Note. prior to Step. Change: Changed note to state:that the facility'should be activated 1 of Attachment within an hour, rather than having a one hour requirement. Reason: To bring 'procedure in line With the Emergency Plan-which states that ne hour. aciation is a goal.' This is a free-for-m as called out in PMP-2010.-PRC-002, Procedure Correction, Change, and Review, Rev. 9a... Page. Of..

POW= -lRMT-208 0-00-1 Rev. 2 Page 1 of 26 Activation and Operation of the OSC Reference Effective Date: / q C. J. Graffenius. S.M. Partin 'Emergency Planning Writer Owner Cognizant Organization TABLE OF CONTENTS PU1RPQSE AND SCOPE................. 3 DETAILS.................... 3 REFERENCES................. 4 .3 ~~~~~~~~~~~~~~~~~~~~~~~~~~~.4~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ : : : : : : : : : 0: Data Sheet 1: Data Sheet 2: Data Sheet 3: Activation 5 Facility Briefings............. .6 Hlabitability 7 Meteorological Data 8 Plant PABX........ Team Briefings.... Team Status......- Personnel Rescue. .Qh;ff fl df' Document TransmissionlDistribution.. Team Briefing Form.... Team De-Briefing Form.'................. lI Consent Form..;.................................. I0 II ................ 14 ................ 16 18 19 2 ........................................................ 21 Definitions and Abbreviations.............. 2 3 I............................................ JL 1 KlllLU............................................................................. .........i............................................... 22 . z -, - t. .;!.U .Figure 1:

Z~~~w jKK4N RT-2080-OSCOO1 Rev 2 Page 2 of 26 . ~ ~~~~ ~~~~ 2 Activation and Operation of the OSC Reference Effective Date: I I C. J. Graffenius. S.M. Partin Emergency Planning Writer Owner Cognizant Organization Figure 2: .Position

a. --

AI Jb Av- . 24

,. t..

Reference RMT-2080-SC-OO Rev. 2 Page 3 of 26 Activation and Operation-of the OSC, 1 PURPOSE AND SCOPE 1.1. This procedure provides guidance to Operation Support Center (OSC) personnel during epnergencies. 1.2 Use of this procedure is restricted to emergency, conditions or drills/exercises' only. NOTE: If a deviation from Technical Specifications or License Condition is necessary, then refer to 10 CFR 50.54(x) and (y) for requirements. 2 'DETAILS 2.1 The OSC Manager implements this procedure. 2.2 Limit dose to all'workers during an emergency to 5 rem whole body unless a dose extension is authorized by the SEC. 2.3 This procedure provides guidance through the use of attachments. 2.4 Use Attachment 1, Activation, when an emergency is declared. 2.5 Use Figure 1, Definitions and Abbreviations, for listing of abbreviations, acronyms, and their meanings. 2.6 Figure 2, Position Descriptions contains supplemental directions for ERO personnel. J.-.

eference vRMT-2080SC-OO1 Rev..2 Page 4 of 26 --Ativation and Operation of the'OSC, I~. 2.7 Perform activities based' on the-following table: I~~ .ffV A u = upuonat lvi = IvIanaavory. 3 REFERENCES 3.1 Use

References:

3.1.1 THP-6010-RPP-705, Manual Access.Control. 3.2 Writing

References:

3.2.1 Source References

a.

Donald C. Cook Nuclear Plant Emergency Plan

b. NUREG-0654/FIEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness-in Support of Nuclear Power Plants 3.2.2

c.

NUREG-0696, Functional Criteria for Emergency Response Facilities General

References:

a.

None INU1M: Activity Attachment Responsible Position UE Alert Site General Area. Activation 1 OSC Manager M... M Facility Briefings. 2 OSC Manager -M M M M Habitability 3 RPD 0 M. M Meteorological Data 4 Maintenance M M M Supervisor Plant PABX 5 OSC Security 0 O M M Team Briefing 6 Skills Supervisors M ,. M M Team Status 7 Resource Coordinator M M M Personnel Rescue, 8-OSC Manager M M M OSC Shift Designation 9 OSC Manager M M M Document Transmission 10 Asst. OSC Manager M M M Exposure Tracking THP-6010-RPD M M M M _RPP-705.' I. : . I

Reference T-2080-OSC001: Rev. 2: Page 5 of 26 Activation and'Operation of the OSC j Activation Pages:

v.

Attachment Activation l Pae:,.- 5 NOTE: The OSC should'be activated'within 60 minutes of the time'of the declaration of an Alert, SAE or GE.

'. 1 Ensure the facility has the'following or an acceptable alternat'e (as determined by the OSC, Manager) prior to activation.

1.1 Equipment ' Facility power Survey instruments Clocks set with the PPC (RDR) 1.2 Communications Telephone or radios Communications with the TSC Manager's'telephone bridge NOTE: The use of non-qualified personnel is permissible provided they are briefed and understand the position specific requirements.

1.3 Personnel 0

OSC Manager.or assistant o RP Director o OSC Boardwriter oj Maintenance Supervisor... o RP Technicians (4)(includes personnel reporting to the Control Room) Cl Maintenance Personnel (4) o Chemistry Technician (2)(includes personnel reporting to, the Control Room) 2 Prior to activation of the OSC, perform a facility briefing. 3 'Notify the other facilities that the OSC is activated.

Reference RMT-2080-OSC-001 :. Rev. 2 .Page 6 of 26 Activation and Operation of the OSC 'Attachment 2 'Facility Briefings. Page NOTE: Facility briefings should be.conducted at least once every 30 minutes unless l changing plant conditions. warrant. more frequent briefings.

1 Announce the briefing time 2 to 3 minutes prior to it beginning.

2 Ensure everyone is paying attention, there are no phone conversations or side discussions taking place, and personnel'should restrict movement during the brief. 3 Perform the briefing. (Time limits are for reference only.) 3.1 Current Plant Status (1-Minute Maximum) ' Major on-going events Major Equipment out of service Prognosis Significant radiological problem areas Direction of airborne release, if known 3.2 Current Classification (30-Seconds Maximum) 3.3 Status of the OSC (for initial briefings up to and including activation) QSC equipment or co£nmunications problems Activation Status Poblems delaying activation 4 Identify any High Priority information that the TSC is waiting for from the OSC (30 seconds maximura). 5 Identify the OSC's first-priority (15 seconds maximum). 6 Request updates from the OSC team on important information or problems Don't solve the problems here. Delegate; then update at the next briefing if necessary.

7.. -

i z

b,* 'Reference Periodicalll OSC prso: Whole Bo~ Rate ~~~Total Effe Dose Equl 1-131 Airl Concentra i assess OSC'for protective actions (evacuation, Kl adiinistration) for nnel based upon the following: dy Dose 100 mRlhr. dose. rate Evacuate OSC within' 1 hr. ctive

3. rem individual(s) cumulative Evaluate need for affected ivalent dose

'individual(s) borne 2E-6 p.Cilcc

Evacuate OSC immediately AND tion

._recommend KI administration *

KI should be distributed when activity reaches approximately 2E-6.Ci/cc of I-131.

KI is available in the OSC RPD office. Use Data Sheet 3, XI Consent Form. 2 Post OSC according to RP procedures. Post signs and control points where necessary... 3 Perform routine habitability surveys where and when necessary. 3.1 Check plant areas for habitability where plant personnel are assembled: Both Control Rooms Operations Shift Manager's.Office Central Alarm Station (CAS) Secondary Alarm Station (SAS). TSC Assembly Areas ,North Access Control. South Access Control 4 Perform routine plant surveys where necessary. 4.1 Check plant areas for habitability as directed by RPD. Turbine Building Auxiliary Building. Inside the Protected Area 5 Request assistance from the BOF. Survey plant areas,outside the Protected Area RMT-2080-OSC-01 Rev. 2 P e 7 of 26 Activation and Operation of the OSC. ..ag. Habitability Page: 7

. ~ ~ ~ ~ ~ ~ ~ ~ Rv Pag 8 f2 Reference RMT-2080-OSC-OO

01 Re.2..

Pa e8of26 Activation and (peration 'of the: OSC Meteorological Data ges: NOTE: This attachment is.ONLY required if Met Data cannot be obtained from the PPC (RDR). 1 To obtain localMet Tower data: 1.1 Obtain the keys to the Met Tower from the OSC key box in the RP supply room. 1.2 Contact the affected Control Room prior to obtaining the Met Data. 1.3 Proceed to the Met Tower, located east of the plant across Red Arrow Highway. 1.4 Take directions from the EOF. 2 Open the box (on the North wall) housing the data logger.. 3 Remove the blue ribbon cord plug from the receptacle near the center of the data recorder. 4 Plug' the other blue ribbon cord from the keypad into the receptacle on the data recorder wheie the previous plug was removed. NOTE: Pressing "A" will'advance to the next parameter, pressing B" will backup one parameter. 5 Establish communications using the data. recorder key pad by pressing: a.*

b. '*...

~~.

c.

6

d. A

Obtain the requested parameters, using:the following table Parameter Code Wind Speed at 10 meters () 01. Wind Speed at 60 m 02 'Wind Direction at 10 m 03 Wind Direction at 60 m 04 Temperature at 10 m (°C) 05 Delta Temperature (60 - 10 m) 06 Dew Point at-10 07 Precipitation 08 Communicate requested Data to the EOF. UPON completion of obtaining Met Data, THEN:. Remove the keypad ribbon from the receptacle. Plug the data recorder nbbon into the receptacle. Close the data logger box. Exit and Jock building. Return to the OSC or as directed by the EOF or OSC. Return the keys to the key box. Reference RMT-2080-OSC-~001 t Rev 2 l Page 9 of 26 'aivation and Operation of the OSC l 'Meteorological Data P.ge: 6' le o codes.. '7 .8 8.1 8.2 8.3 8.4 8.5 8.6 4

Reference RMT-2080SC-OO1 Rev. 2 Activation and Operation of the OSC. .. Attachment 5. Plant PABX Page 10 of 26 Perform the following to bar the plant PABX:. Proceed-to the PABX room, located 2n floor, Lakeside Office Building. - Turn Switch# 1 from"Normal" to Emergency". Turn Switch #2 from "Normal" to Emergency". Report position of the PABX switch to the OSC Manager. 2 WHEN it is desired to unbar the PABX System,.lTEN perform the following: Turn Switch # 1 from "Emergency" to "Normal". Turn Switch #2 from "Emergency" to "Noimal". Report position of the PABX switch to the OSC:Manager. -~~~~~~~~~~~~~~~~ . Page: .. 10. v.

. Reference RMT-2080-OSC-OO1 1 Rev. 2 Page 11. of 26 Activation. and Operation of.the OSC. Team.Briefings Pages. ~~~~~~~~~~~1 1 NOTE: The following teams are automatically dispatched as soon as the appropriate personnel are available: Two Offsite survey teams (Designated as Teams #1 and #2)) 1 Onsite Teams 1.1 Obtain the Team Request Form. 1.2 Determine Initial Plant Conditions. 1.3 Determine the type of team needed: Damage Control Rescue Survey 1.4 Assemble appropriate team members; 1.5 Complete Team. Briefing Form. 1.6 Conduct Data Sheet 1, Team Briefing and consider the following: Determine tools and equipment needed to complete mission Determine drawings/prints needed for mission Determine protective clothing needed for mission Determine respiratory equipment needed for mission Determine the need for potassium iodide tablets Determine in-plant route to follow 1.7 Notify Resource Coordinator prior to leaving OSC 1.8 UJpdate Team Status Board. Reference I

.1.9 Ongoing Mission Status Reports:.- Brief the appropriate skills supervisor approximately every 15 minutes ' The 'skills supervisor will brief the assistant 'OSC Manager on the field team status for Team Status Board Updates. 1.10 Mission Completion:'.

Check in with he Resource Coordinator De-Brief with appropriate sldlls supervisors, RPD, and Assistant OSC Manager and complete Data Sheet 2, Team De-Briefng Form.

. Update Team Status Board '. Brief the TSC zOffsite Teams Offsite Briefing: Determine if a radiological release is in progress. IF the EOF is. activated, THEN, contact the FMT Coordinator in the EOP, for survey instructions -OR-IF the EOF is not activated, and a release is in progress, THEN' information needs to be provided to the offsite team(s) by the-Control Room: or TSC (such as): Release point Wind direction ' Wind speed' Reference RMT-2080-OSC-001, l" . Rev. 2 Page 12 of 26: Activation and Operation of the OSC -. Team Briefings P'ges: 2 2.1

1 Appropriate Skills.Supervisors 1.1 Obtain the. following information from the Field Team.(s), approximately every 15 minutes. .Job progress Problems encountered Dose levels' Dose rate levels Estimated job duration 1.2 Brief Team Status to the Assistant OSC.Manager. 2 Assistant OSC Manager 2.1 Update Team Status Board in the OSC Manager's. Office. 2.2 Brief the TSC. Reference RMT-2080-OSC-OO1 ev.. 2 'Page 13 of 26 Activation and Operaton of the OSC. I Team Staitus

[. . Reference RMT-2080-OSC-OO Re. 2 Page 14 of 26 Activation and Operation of 'the OSC' [

' Attachment8.

Personnel Rescue Pages: 14 -15 Personnel Rescue Medical'emergencies have priority. .Consideration should b given to the radiological exposure already obtained ..by the injured-person and rescue personnel. Consider plant conditions prior to leaving the OSC (plant lighting, radiation levels, steam line breaksi etc.). Consider Dose Extension paperwork. This can be done during the team' briefing. . Dose extensions should be automatic for'life saving and rescue missions. Dose extensions CAN NOT be approved for personnel if they have already exceeded their limits. 2 Assign two individuals to the team at a minimum. e Assign a RP Technician and a plant EMT to the team if possible or have one readily available. Assign an OSC person to receive continuous radio transmissions from the rescue. team. Provide a short briefmg'to the team. (A briefing form does not need to be completed prior to the team being dispatched out of the OSC.) 3 Consider the following safety. concerns (Activities in hazardous areas). Be aware of hazardous material exposure areas. Be aware.of entries into confined areas. Caution should be taken in areas where fires are present or could start. Consider. moving the person out of 'the area -if high radiation levels are present. . Deviation from normal RP controls and policies is only permitted when it has been identified to be a life-threatening situation.

4 Rescue Actions 4.1 Report findings.to the Operations Shift Manager (or Designee) and . Number of injured personnel. (if known.) ' Nature. and severity of injuries . Contamination levels (if known) Location of injured'personnel Cause of injury (if known). Special medical needs. Ambulance/hospitalization required Is additional assistance required from the OSC )SC: Egress Actions Contact the Operations Shift Manager and request the location on the ambulance. Notify the Operation's Shift Manager to notify the hospital(s) to prepare. to receive contaminated or non-contaminated patient(s) from the plant. Inform the hospital of the patient(s) status. Transport the patient(s) to the ambulance. Report patient(s) conditions to the ambulance personnel: Injuries... First Aid measures taken Patient's current condition Radiological status Contamination status

Debrief with OSC'

' Complete De-Briefing form. Reference RMT-2080OSC-OO.1.: Rev. 2 I Page 15 of 26 Activation and Operation of. the OSC' l Personnel Rescue

Pages,

~~~14 -15' ~5 5.1' 5.2 .5.3 5.4 5.5 6 . ~ ~ ~ ~ ~ a -

NOTE: Obtain individual phone numbersfrom the Emergency Response Organization Phone Directory.' 1 Facility Managers; coordinate shift turnovers to ensure plant conditions allow individuals to report to their respective facilities without undue risk or exposure. 2 Facility Managers should determine manpower resources required for next shift designation and report this to the EOF Security Director. 3 Next Shift Notification 3.1 Provide a list of the current OSC responders to the EOF Security Director. Reference . I .. RMT-2080-OSC-001 I Rev. 2 . Page 16 of 26 , Activation and Operation of the SC - ' Shift Designation , Pages: 16 -17'

Position Title Name OSC Manager Asst. OSC Manager O SC B oardw riter Maintenance Supervisor.._._._- BP. Director Chemistry Supervisor Resource Coordinator Mechanic (3)$ Eltrician (4)* I&C Technician.(4)* Welder (2)* Che miistry Technician (3)* RP Technician (7)* Driver (2) F ire B rigade Security C h m s r The e 0 rs o d r do) no a r R a e s a d m u t b o t c e y p o e Reference. RMT-2080SC-Rev. 2 Page 17 of 26 Activation and:Opeation ot the OSC -Shift Designation. Pages: I ~~~~~~~~~~~~~~~~~~~~~~~ -'I7 I. .~~~~~~ These OSC responders do not carry BRO pagers and must be contacted by phone.

Reference RMT-2080-OSC-001 -Rev. 2 Page 18 of.26 Activation and Operation of the OSC .~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~~Pg: 0 Document Transmission/Distribution Page: NOTE: 'Some of the facility Fax machines are designated within the phone directory as TR;ANSMIT and others as RECEVE. These Fax machines should remain -in their designated mode to better facilitate communications between facilities. 1 Ensure the Fax machine's date and time' is set correctly. 2 Obtain the Fax machine phone numbers for the facilities from the Emergency Response Organization.Phone Directory. 3 IF an incoming Fax is NOT specifically addressed to an individual or position, THEN distribute the incoming Fax. within the facility as directed by the document. 4. Copy and distribute incoming documents within the facility as directed by. the,. document. S Log all incoming and outgoing Fax's in the facility Fax Log.. 6 ' Utilize the following table for directions on the distribution of material: Document Destin'ation Frequency Additional Instructions -Team Request Form Assistant OSC. As Available Incoming team request from the ._ Manager TSC. Boardwriter Notes OSC As Available The boardwriter notes shall be Personnel distributed to the OSC Manager, 'RPD, and posted for OSC. skilled personnel. Dialogic OSC Manager As Available ERO personnel responding to Persons Responding .from Dialogic-emergency. or next shift. Report

Team Mission:

Team Number:

Team Members: TL-- Team Priority: ACAD Niimber Team Mission Details: Turn Back Dose Rate: Dosimetry Required Turn Back Dose: Protective Clothing Required Respiratory Required Potassium Iodide Required: YES I NO Dose Extension Approved: YES - / NO Linits:

Rem TEDE Rem Thyroid CDE Special Instructions:

Reference RMT-2080-OSC001 Rev 2 -Page 19 of 26 Activation and Operation of the OSC j Data Sheet. 1. Team Briefing Form Pa19' I.. .w ..9 4

Team Mission: Team Number: Work Performed: Tea'm Leader: o. Problems Encountered: Radiological Conditions: Notes: Was Mission Completed: YES I NO Were KI Tablets Ingested: Reference.MT-2080SC-0O1 Rev. 2 Page 20 of 26 Activation and Operation of the:OSC Data Sheet 2 Team De-Breing Forn Page 20 ,YES / NO

'Reference RMT-2080-OSC-01. Rev..2 Page 21 of 26 Activation and Operation.of the OSC Data Sheet 3 KI Consent Foim age WHO SHOULD NOT TAKE POTASSIUM IODIDE TABLETS The only people who should not take potassium iodide are people who know they are allergic to iodide. You may take potassium iodide even if you are taking medicines for a thyroid problem (for exainple, a thyroid hormone or, antitbyroid drug). Pregnant and nursiag women, babies, and children rnay also take this drug. SIDE EFFECTS: Usually side effects of potassium iodide happen when people take higher doses for a long time. You should be careful not to take more than the recbnimended dose or take it longer than you are told. Side effects are unlikely because of the low dose and the short time you will be taking the drug. Possible side effects include skin rashes, swelling of the salivary glands, and iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, 'and sometimes stomach upset and diarrhea). A few people have bad an allergic reaction with more serious symptoms. These could be fever:and joint pains; swelling of parts of the face and body and at times severe shortness of breath requiring immediate medical attention. Taking iodide may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter).- WHAT TO DO IF SIDE EF;FECTS OCCUR: If side effects are severe or a possible allergic reaction occurs, notify plant RP or your immediate supervisor. DOSAGE: Take one tablet a day for a total'period of ten (10) days. Report to RP each day to receive your KI dose or take it on your own if RP gave the whole bottle to you. INDIVIDUAL RIGHTS: The use of KI as a thyroid blocking agent is voluntary. If you have a known allergy to iodide or iodine, do not participate in this activity. If you choose to participate, you must complete this KI CONSENT FORM. I, , volunteer to receive 130 miligrams per day of the thyroid blocking agent potassium iodide (KI), for a period of the next ten (10) days consecutive days. I have been informed of the'intent and possible consequences of the use of potassiurn iodide. Signatuire : Date:._ KI administration has been authorized by theSC: I Time J Date Dosage/DateTaken:I/ ,2/ '3/ ,4/ 5/ 6/ ,71 ,81 9 ,10I RP Supervisor/Engineer Review:__ 'Upon completion of Ki Administration

Term Meaning ALARA As Low As Reasonable Achievable CDE Committed Dose Equivalent ED Emergency Director EMT Emergency Medical Technician EOF Emergency Operations Facility ERO Emergency Response Oiganization. FMT Field Monitoring Team GE General Emergency KI Potassium Iodide OSC Operations Support Center PABX Private Automated Branch Exchange (Plant,Telephone System) PPC Plant Process Computer RAC Radiological Assessment Coordinator RDR Real-Time Data Repository RP Radiation Protection RPD Radiation Protection Director SAE Site Area Emergency SEC Site Emergency.Coordinator SPO Security Post Order. TEDE Total Effective Dose Equivalent TL Team Leader Reference RMT-2080-OSC-001., Rev. 2 -Page 22 of 26. Activation and Operation of the.OSC Figure 1 Definitions and Ablreviations P ages: 22,-23, "',:' I..

Reference' RMT-2080-OSC-OO1 Rev. 2 -Page 23 of 26 Activation. and Operation of the OSC J Figure 1 Definitions and-Abbreviations TLD Thermoluminescent Dosimeters TSC 1 Technical Support Center UE Unusual Event w

The position descriptions provided are intended as guidance. Deviations and additions to'these ' descriptions are allowed as long as the 'accomplished objectives, can be achieved. OSC Manager. Directs and coordinates OSC activities Activates the OSC ' Maintains constant communications with the other facility managers on the Managers Bridge.

Updates OSC members through facility briefs -on the status of the emergency*

approximately every 30 minmtes Assistant OSC Manager Reports to the OSC Manager Assumes the duties of the OSC Manager in his absence

Assist in the'briefs of the OSC Teans
Distributes all-purpose message forms as needed*

.Maintains the OSC Team Board in the OSC Manager's office Directs the de-briefs of the teams upon returning to the OSC RP Director Reports to the:OSC Manager Briefs the OSC, Teams on radiological concerns Obtains plant conditions from the Radiological Assessment Coordinator in the TSC ., Directs and coordinates.the activities of the RP Technicians, .*. Assists in the de-briefs of the teams upon retuIrning to the OSC OSC Boardwriter Reports to the Asst. OSC Manager Obtains data from the other facilities and the OSC that is considered'common to all facilities and the.affected Control Room in a chronological order Provides' other facilities with information and decisions generated in the OSC Maintains the Emergency. Classification Board with the proper emergency classification, classification.time, and reasons for the classification Documents incoming messages or inquiries to other OSC personnel on all-purpose message forms and forwards them to,the Asst. OSC Manager Provides the *OSC' Manager/Asst. OSC Manager, RP Director, and skilled personnel witli copies of board data Maintain the Fax Logbook Reference 7 RMT-2080-OSC-001 Rev. 2 l Page 24 of 26 Acti'vation and' Operation of the OSC'.. .Figure 2 Position Descriptions Page: '.24.26

'.Reference. l RMT-20850SC-001 Rev. 2 l Page 25 of 26. Activation and Operation of the OSC '.Figure 2 Position Descriptions Pages: 1 ~~~~~~~~~~~~~~~~~~24,-26 Maintenance Supervisor

Reports to the OSC Manager Directs and coordinates the activities of the Maintenance personnel Briefs the Maintenance Teams prior to being dispatched Assists in the de-briefs of the teams.upon returning to the OSC.

Communicates information from.the.teams in the field and advises team status back to the Asst. OSC manager Chemistry Supervisor Reports to the OSC Manager Directs and coordinates the activities of the Chemistry Technicians Assist-in the de-briefs of the Chemistry teams upon returning to the OSC .D RP Technicians Reports to the RP Director Provides radiological support and coverage to ERO Teams and Facilities-.. Performs plant habitability surveys' Maintenance Personnel Reports to the Maintenance Supervisor. Performs maintenance activities as directed Chemistry Technicians Reports to the Chemistry Supervisor Performs chemistry activities.as directed Off-Site Survey Drivers Upon initial arrival to the OSC,.reports to the RP Director After leaving site, reports to the FMT Coordinator: in the EOF Drives the RP Survey Team as directed. by the FMT Coordinator Resource Coordinator Reports to the Asst. OSC Manager Maintains the OSC Team Status Board. Coordinates Teams in and out of the OSC

Reference RMT-2080-SC001 - l Rev. 2 l Page 26 of 26 Activation and Operation of the OSC-Figire 2 l Position Descrnptions Pages.

~~~~~~~~~~~~~~~~~~~~~~2

- 26. Fire Brigade Reports to the OSC Manager e Provides Fire Protection Services to the OSC Manager Coordinates OSC and plant activities pertaining to fighting, HAZMAT and rescue concerns OSC Security Officer Rsnrc t t-nCrl WM<n-b SV ` U L V - I TY1S Maintains the emergency key Bars the PABX as directed' cards and plant keys

REVIEW AND APPROVAL TRACKING FORM Number. RMT-280-TSC-OOt Rev. 2 'Change: 0

Title:

Activation and Operation of the TSC El Corction (Full Procedure) 0 Change (Full Procedure) with Review of Change Only 5 Correction (Page Substitution) E] Change (Page Substitution) with Review of Change Only El Cancellation E5 New Procedure or Change with: Full Rnview 5 Superseded (list superseding procedures): Change DriveCDI Tracing No(s). N/A Cross-Discipline Reviews: Programmatic-Reviews: e 5 Chemistry. Training []ALARA Peformanc Assumnce 5 Maintenance W Work Control 5 Bus. Services Proc Gsp [ Reactivity Mgmt Team 5 NDM 0 SECstEDs 5 Component Engineering f SPS (Safety & Health) Opcrations D 5 Design Engineerng 5 Survefillance Section 5 PA/PV 5 Emerg Oper Proc Grp 5 System Engineering f Reg Afirs a None Required 5 Environmental 5 El P E ISIIIST Coordinator 0 None Required Cogniizant Org Review: -^,Date: /00 1g Olas 3Technical Review: Date: < h E] Ops Mgr Concurrence: Date: /I Ug Owner Concurrence: Date: /r7'/)z. Updated Revision Summary attached? 0 Yes 10 CFR 50.59 Requirements complete? TrackingNo.: 20021429-00 0Yes 5NA Implementation Plan developed? (R f tep 3.4.18) 5 Yes 0 N/A Package Complete: Date:/. / tL-PORC Review Required: 0 Yes E5 No Administrative Hold Status: Released Reissued N_A CRNO.: Approval Authority Review/Approv: Date: IO/ /- Expiration Date/Ending Activity Effective Date: V °l I °L Periodic Review conducted? (Data Sheet 5 Complete) 5 Yes 0 No V0-IV-IS i Commitment Database Updated? Yes E N/A NDM notified of new records or changes to records that could affect record retention? Yes 0 N/A This form is derived fiom the information in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 9a, Data Sheet 1, Review and Approval Tracking Fonn. Page_( of

REVISION

SUMMARY

Number. RMT-2080-TSC001 Revision: 2

Title:

Activation and Operation of the TSC Change: 0 Section or Step Change/Reason For Change Note prior to Step Change: Revised note to state that the TSC should be activated within 60 I of Attachment 1 minutes of emergency declaration, raiher than requiring facility acivation within 60 minutes of emergency declaration. Reason: Revised staternent to match the Emergency Plan, that the 60-minute activation tine isa goal, not a requirement. UN .~ Chne an eiw

e.

9a ae .fZ

-P¢ltRIC RMT-2080-TSC-001-Rev. 2 Page 1 of 36 Activation-and Operation of the TSC Reference Effective Date: /6/ / C; J. Graffenius S.M. Partin Emergency Planing Writer Owner Cognizant Organization TABLE OF CONTENTS 1 PUJRPOSE AND SCOPE. ...................3 3... 2 'DETAILS 3..........5 3 IEFEIDENCES....................................................... 5 : : : : : : : : : 0: 1: 2: 3: 4: Activation 6 Briefings 8 Habitability............. .,.9 Shift Designation........... ,,.11 Document Transmission/Distribution 12 E D ..1 F.gRDIS.... 14 Radiological Assessment/Release in Progress.,,,.. 15.- Team Requests and Prioritization....................... 17 Accountability................ 18 Site Evacuation 19 Loss of RDR.......... .,.,.,,,,,,.,. 21 Dose Extension and Authorization 22 KI Administration..... ... 25 Classification............. 26

1.

RMT-2080-TSC-001 Rev. 2 Page 2 of 36 Activation and Operation of the TSC: Reference YEffecve Date: / / C. J. Graffenius S.M. Partin Erergency Planning Writer Owner Cognizant Organization Data Sheet 1: - Data Sheet 2: Data Sheet 3: Figure 1: Figure 2: Response Team Request.......... Radiation Monitoring System.. Dose Extension Form........... Definitions and Abbreviations.. Position Descriptions................. 27 IQ 33. Ou - -31 I....................

Reference RD MT-2080-TSC-001-Rev. 2 Page 3 of 36 Activation and Operation of the TSC I PURPOSE AND SCOPE 1.1 This procedure provides guidance to Technical Support Center (TSC) personnel during emergencies. 1.2 Use of this procedure is restricted to emergency conditions or drills/exercises only. 2 DETAILS NOTE:

2.1 2.2 2.3 10 CFR 50.54(x) and (y) descnbe the actions required if deviation from Technical Specifications or License Condition becomes necessary.

The SEC/Assistant SEC implements this procedure. Use Attacbment 1, Activation, when an emergency response is initiated. Refer to Figure 1, Defmiitions and Abbreviations, for a listing of abbreviations, acronyms, and their meanings. 2.4 Refer to Figure 2, personnel. Position Descriptions, for supplemental directions for ERO .1 % i q

Rev. 2 . I. Page 4 of 36 I Reference I RMT-2W(J-1SC-(iO1 F Activation arnd Operation of the TSC: I I f NOTE: 0 = Optional M = Mandatory 2.5 Perform activities based on the following table. Activity Attachment Responsible Position UE Alert Site. General A rea Activation 1 SEC/Assistant SEC 0 M M M Briefings 2 SEC/Assistant SEC M M M M Habitability 3 RAC 0 M M Shift Designation 4 SEC/Assistant SEC 0 . M M M Document 5 Administrative. 0 M M M Transmission/Distribution Coordinator Emergency Response Data. 6 Computer Analyst O M M M System (ERDS) Radiological 7 RAC 0 M M M Assessment/Release in Progress Team Requests/Team 8 PET/SEC 0 0 0 Priority Team Status 8 Team Coordinator. .O 0 0 Accountability 9 Security Director 0 M M Site Evacuation 10 Security Director 0 M M Loss of RDR 11 -PET OPS/RAC (ARAC) 0 0 0 0 Dose Extension 12 SEC M M M Authorization Potassium Iodide (Ki) 13 SEC M M M Administration Authorization Classification 14 SEC M M M M Core Damage Assessment. PMP-2081-. PET Reactor Physics M M M EPP-105 Analyst*. Barring of the Plant PABX RMT-2080-Security Director 0 M M OSC-001, A ttachm ent 5 Fission Product Barrier 12-PMP-2080-PET Operations 0 0 0 0 Status.(relative to EPP-101 Emergency Classifications) Page 4 of 36 I. RMT-2080-TSC-001- '--J RJe'v. 2 - I -. Reference

I Reference RMT-2080-TSC-001 Rev. 2 Activation and Operation of the TSC 3 REFERENCES 3.1 Use

References:

3.1.1 EPA400-R-92001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 3.1.2 10 CFR 20, Standards for Protection Against Radiation 3.1.3 Donald C. Cook Nuclear Plant Emergency Plan 3.2 Writing

References:

3.2.1 Source References

a.

EPA-400-R-92001

b.

10 CFR 20

c.

Donald C. Cook Nuclear Plant Emergency Plan

d.

NRC Commitment #3863

3.2.2 General References

a.

10 CFR 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities Page 5 of 36

Reference RMT-2080-TSC-001 Rev. 2 Page 6 of 36 Activation and Operation of the' TSC ' Activation Page: NOTE: The TSC should be activated within 60 minutes of the time of a declaration of an Alert, SAE, or GE. I Ensure the facility has the following or an acceptable alternate (as determined by the Assistant SEC or SEC) prior to activation. 1.1 Equipment Facility Power Contimous Air and Area Radiation Monitor

PPC (RDR)

Clocks synchronized with the PPC 1.2 Communications Telephones, Fax machines, or Radios Communications with the Control Room Managers Telephone Bridge Communicators Bridge 1.3 Personnel NOTE: The use of non-qualified personnel is permissible if they are briefed and understand the position specific requirements. O Administrative Coordinator a Boardwriter Control Room Communicator (located in the Control Room, but vital to TSC operation) 0 0 SEC. a PET Operations or PET Trainng o PET Maintenance Engineering O PET Reactor. Physics Analyst

U Radiological Assessment Coordinator *
Position may not be necessary in all situations (e.g., non-radiological emergencies).

i ... Y

2 Prior to activation of the TSC,:perform a facility briefing. 3. .Inform TSC personnel and the other ERO facilities that the TSC has been activated. .Reference RMT-2080-TSC-001

l Rev. 2 Page 7 of 36 Activation and Operation of the TSC.

. Attachment I Activation Page: Attachment 6ctv-7on

Reference 7T RMT-2080-TSC-001 Rev. 2 Page 8 of 36 Activation and Operation of th'e TSC J BriefingsPa: 1 Announce the briefing time 2 to 3 minutes prior to it beginning. 2 Ensuire personnel. are paying attention, there are no phone coniversations or side discussions taking place, and personnel remain stationary during the brief. 3 Perform the briefing. (Timne limnits are for reference only.) 3.1 Current Plant Status ('Minute Maximnum) Major on-going events Major equipment out of service Prognosis 3.2 Current Classification (30 Seconds Maximnum). PAR in effect Anticipated chafiges in classification or PAR 3.3 Identify'any high priority information that the Control Room is waiting for from the TSC (30 seconds maximum) 3.4 Identify the TSC's first priority (15 seconds maximum) 4 Status of the TSC (not required after activation)' Activation Status (When command and control wil be taken over. from the Control Room) Problems delaying activation S Ask the TSC team forupdates on important information Don't-solve the problems here. Delegate; hen update at the next briefing if necessary. ~6 Ask the TSC team i anyone is-having any problems Don't solve the problems here. Delegate; then update at the niext briefing if necessary.

Reference RMT-2080-TSC-O1 Rev. :2 l Page 9 of 36 Activation and Operation'of the TSC l Habitability Pages: 9 10 I TSC Ventilation System 1.1 Request permission from the Control Room to place the TSC ventilation system in the recirculation mode if any of the following apply: The emergency involves a loss of coolant accident The Control Room Pressurization System has been activated Other air quality issues (e.g., smoke, fumes)' affect the TSC. 1.2 IF permission is obtained from the affected unit control room, THEN place the TSC ventilation switch in the recirculation mode. This switch is located on the north wall of the communications room. 1.3 Inform the SEC that the TSC ventilation has been placed in the recirculation mode. 2 Radiological Monitoring 2.1 Periodically assess the TSC for protective actions (evacuation, KI administration) for TSC personnel based upon the followiiig: Parameter Action Level Recommended Action Whole Body Dose Rate 2 R/hr. dose rate Evacuate TSC immediately Total Effective Dose 3 rem individual(s) Evacuate affected Equivalent cumulative dose individual(s) immediately I-13 1 Airborne 2E-5 1tCi(cc

Evacuate TSC imnediately Concentration,

AND recommend KY administration $

KI should be distributed'when activity reaches approximately 2E-5.LCi/cc of 1-131.

KI is available in the TSC NRC room. Obtain authorization from the SEC and consent from affected individuals using Data Sheet 3 of 12-RMT-2080-OSC-001.

Reference RMT-2080-TSC-001 Rev. 2 Page 10 of 36 Activation and Operation of the TSC P

Habitability.

.abitabiity 9-10 3 Evacuation of TSC 3.1 Per the recommendation of the RAC, or based upon the SEC's discretion, the TSC may be'evacuated for radiological'or other habitability considerations. This should be accomplished via the following guidaice: Only the minimum number of staff members (as determined by the SEC) should be relocated to the unaffected unit's Control Room. All others should be evacuated to the OSC for radiological assessment and possible site evacuation. Staff members evacuating to the OSC will do so by following the route designated by the RAC. Notify the SEC, Control Room, OSC and EOF of the evacuation of the TSC.

Reference RMT-2080-TSC-001' l Rev. 2 Page 11 of 36 Activation and 'Operation' of the TSC:, Shift.Designation Page: 1 : ' Facility Managers coordinate shift turnovers to ensure plant conditions allow individuals to report to their respective facilities without undue risk or exposure. 2 Managers should determine manpower resources required for next shift designation and report this to the EOF Security, Director. 3 To aid in the callout process, provide a list of,the TSC responders currently in attendance to the EOF Security Director, using the following 'table: Position Title. TSC Responders Currently in Attendance Assistant Radiological Assessment Coordinator Radiological Assessment Coordinator Site Emergency Coordinator TSC Administrative Coordinator TSC Boardwriter TSC Control Room Communicator TSC Administrative Support TSC PET-Computer Analyst. TSC PET-Maintenance TSC PET-Operations TSC PET-Training TSC Team Coordinator TSC PET-Reactor Physics Analyst TSC Public Affairs Liaison TSC Security Director Assistant SEC t

Reference RMT-2080-TSC-001 ,Rev. 2 Page 12 of 36 Activation'and'Operation of the TSC Document Transmission/Distribution l Pages j NOTE: Some of the facility Fax machines are' designated within the phone directory as TRANSMIT and others as RECEIVE. These machines:should remain in their designated mode to better facilitate communications between facilities. Documentation to be Distributed or Transmitted (Faxed or hand carried) Ensure the Fax machine Dates and Times are set correctly. Fax machine phone numbers for the facilities and offsite agencies are available in the Emergency Response Organization'Phone Directory. Duplicate all documents for distribution per Steps 1.6 and 1.7. Forward all originals to the Administrative Coordinator. Log incoming and outgoing faxes in the facility Fax Logbook. Distribute incoming faxes to the positions as described on the facility distribution map located. in the copy area. 1.1 1.2 , 1.3 1.4 1.5 1.6

-1 -Reference RMT-2080-TSC-01 Rev. 2 .Page 13 of 36 Activation and Operation of the TSC Document Transmission/Distribution Pages: 12-3 1.7 The following table gives additional direction.on the transmission/distribution of material: Document Destination . Frequency. Additional Instructions EMD-32a (class. Upgrade) Received from EOF Upgrade or Distributed to TSC andlor EMD-32b (technical .30 minutes personnel. update) Technical Iformation Sheet . Obtained from the 15 minutes. Onlysent/distributed (PMP-2080-EPP-100, Data Control Room, it is' ONLY when the PPC is Sheet 1) Faxed to the EOF when the unavailable; copies to (Completedldistributed ONLY and ENC or JPIC, PPC is TSC personnel. when the PPC is unavailable)' also distributed in unavailable TSC Radiation-Monitoring System, Obtained by the. 15 minutes RAC completes this form Data. Sheet (Data Sheet 2 of RAC or designee, it ONLY with data of interest. this procedure) is Faxed to the ENC when the Only sent when the PPC (Completed/distributed ONLY or JPIC; also PPC is is unavailable. when the PPC is unavailable) distributed in TSC unavailable TSC Plant Chronological Distribute in TSC As TSC Boardwriter prints a Status Board Notes available , copy of the status board before cleaning to make room for new data. Response Team Request (Data Approved by the As TSC faxes. this form to Sheet 1 of this procedure) SEC, this form is necessary the OSC; this information Faxed to the OSC. can be disseminated concurrent with verbal communications through the TSC OSC Communicator. Persons Responding Report Received from 15 min. Distributed to (Dialogic) Dialogic (for 1 hr.. SEC/Assistant SEC (ERO after pager personnel responding to .activation) emergency or next shift)

Reference T RMT-2080-TSC-001 - I-Rev. 2 l Page 14 of 36 Activation and Operation of the TSC ER Page: NOTE: 10 CFR 50, Appendix E requires ERDS to be activated within hour following an Alert or higher event classification., 1 Activate ERDS from the PPC by: 1.1 1.2 1.3 Clicking on 'Cook E-Plan Tasks'. Clicking on the appropriate Unit designator (1, 2, or Sinulator). Either: Type in ERDS" and'press'enter or Click on ER", then ERDS" 1.4 Activate the ERDS transmission to the NRC by: Pressing the Fl key or Click on the screen location labeled 'ACTIVATE" 2 IF ERDS transmission is lost, THEN: Press the F3 key or Click on the'screen location labeled "RECONNECT" 3 3.1 Terminate ERDS transmission by: Contacting the NRC to request permission to terminiate the ERDS transmission. (The ERDS Operation Center phone number is located in the Emergency Response Organization Phone Directory.) 3.2 IF permission is granted, TIEN: a Press the F2 key or Click on the screen location labeled TERMINATE"

1 Review the Radiation Monitoring System channel and meteorological data concentrating on:

1.1 Effluent release points; 1.1.1 IF an ummonitored release is suspected to be in progress and the associated.

RMS monitor is unavailable, THEN dispatch off-site monitoring team(s), immediately to perform a site boundary survey, and inform the SEC and EAD. 1.2 Containment high range area monitors. Trigger points for classification changes are: 10 R/hr - Alert 200 Ihr -. SAE 1000 R/hr - GE 1.3 Channel operability status; 1.4 Trends; NOTE: PPC displays what direction the wind is coming from (e.g., a PPC display' of wind direction at 270o indicates thai the wind is coming from due west)., 1.5 Wind speed and wind direction.. 2 Review current locations of personnel within the facility to:. 2.1 Determine occupied downwind facilities; 2.2 Evaluate the need for pre-release facility evacuation. 3 Evaluate radiological conditions for the OSC by: 3.1 Review Radiation Monitoring System monitors to determine site,radiological conditions; Determine best entry and egress team routes. Reference RMT-2080-TSC-001 -Rev. 2 Page 15 of.36 .. I' Activation and Operation of the'.TSC I. Radiological Assessment/Release in Progress Pages .15 - 16 '3.2

Reference RMT-2080-TSC-0O1., Rev. 2 Page 16of3 Activation and Operation of the TSC. Pag 16 Radiological Assessment/Release in Progress'.. 4 IF any significant changes occur which could affect teams or other plant personnel, THEN notify: Radiation Protection Director (in the OSC) .. Site Emergency Coordinator 5 IF a radiological release. is imminent or occurring, THEN: 5.1 Immediately notify the Assistant SEC or SEC. 5.2. Evacuate downwind facilities. 5.3 Inform the Radiation Protection Director in the OSC. Determine consequences and implement corrective actions for dispatched teams and other occupied-facilities. i;,- Consider: Sheltering in an unaffected area of the plant Evacuation back to the OSC Effect on or need for on-site accountability and evacuation Facilities occupied outside the Control Rooms, TSC and the OSC 5.4 Pinpoint the release origin point with the assistance of the PET. 5.5 Initiate Control Room, TSC, OSC, and assembly'area habitability assessments.. 5.6 Evaluate the need to administer KI to individuls exposed to, or potentially exposed to the plume. 5.7 Evaluate the need for any uptake assessments or medical follow-up observations for individuals exposed to the plume.

~.

00

....Page............ Reference RMT-2080-TSC-OO1 Rev. 2 Page Activation and Operation of the TSC Teani Requests and Prioritization-NOTE: The SEC approves requests for OSC teams; Request a response team by: Completing Data Sheet 1, Response Team Request. 9~~~~~~~~~~~~~~~~~ Obtaining RAC opinion/concurrence'on the feasibility of the team being able to perform the task (from a radiological standpoint). The'SEC determines overall need and team priority by: Determining'the ininediate need of the request.:-' Comparing the need to teams already being assembled or' dispatched. Consider: The effect on the OSC of re-prioritization of previously requested teams Possibility of existiig teams performing the work The SEC then approves the request as appropriate and determines team priority. The TSC Team Coordinator: Updates the team status board. Infonns the OSC verbally of the request. Updates the OSC of team priorities as they are established or changed. WHEN the SEC has approved. the request, THEN transmit Data Sheet 1, Response Team Request, to the OSC. 7. I 1.1 1.2 2 2.1 .2.2 2.3 .3 3.1 3.2 3.3 4

Reference RMT-2080-TSC-001- - l . Rev. 2 Page 18 of 36 -. 9Activation and Operation of the TSC Accountability 18 1 Notify the SAS or CAS to initiate accountability per Security procedures. 2 WHEN accountability has been completed, THEN notify the-SEC of any unaccounted for individuals [Comnmitnient #3863]. This must be accomplished within 30 minutes of the accountability order..

.NO :IF individuals are unaccounted for, THEN the Security Director shall:

3.1 Provide a.list of unaccounted personnel to each of the facilities. 3.2 Instruct the managers of each facility to verify the missing personnel-are not in the facilities. 3.3 Initiatesearches for themissingpersoinel. Searches can bedone via: Plant public address system Plant personnel paging system witn 3Assembin g search teams via the TSC 3.4 Provide the SEC and facilities with periodic updates on status until all missing personnel are accounted for.

Reference RMT-208-ISO-o01 Rev. 2 Page 19 of 36 Activation and Operation of the TSC' 0 l Site Evacuation Pages: .19 -20 I 1 IFin analert, THEN:.' 1.1 Recommend to the SEC the immediate evacuation of containIment buildings and the Auxiliary Building of all personnel not responding to the emergency. 1.1.1 IF the recommendation is approved and has not already been performed by the Control Room, THEN:

a.

Notify the Control Room that an announcement will be made.

b. Notify the other emergency facility managers the announcement will be made.

c.

Make the following announcement 2 times on the plant public address system: ,-t "Attention all plant personnel. Attention all plant'personnel. Because of plant conditions, all personnel within the Auxiliary and Containment buildings imImediately evacuate the area." 1.2 Recommend to the SEC that all non-essential personnel be required to leave site. -2.1 IF the recommendation is approved and has not already been performed by' the Control Room, THEN:

a.

Notify the control room that an announcement will be made..

b.

Notify the other emergency facility managers the announcement will be made.

c.

Make the following announcement 2 times'on the plant public address system: "Attention all plant personnel. Attention all plant personnel. Because of plant conditions, all non-essential personnel are to leave the, plant site at this time using their vehicles and normal plant access routes."

d. Make the same announcement 2 times in the training building by:

Dialing 1646

e.

Initiate Security actions (via the TSC Security Director) to evacuate all' personnel from all plant facilities outside the protected area.

Reference RMT-2080-TSC-001 Rev. 2 l Page 20 of 36 Activation and Operation of the TSC 0 Site Evacuation Pages: 19 - 20 NOTE: It is possible to enter a Site Area Emergency or General Emergency without having passed through an Alert. Because accountability is required at a Site Area Emergency or a General, Emergency, all personnael within the plant-protected area should be either at or in the process of reporting to an emergency assembly area. 2 IF in a Site Area Emergency or General Emergency, THEN: ,2.1 Obtain directions from the RAC foi the evacuation process and route to be used. Consider: If a release of radioactive material has occurred. The potential. for a release of radioactive material to occur during the evacuation process. Wind direction, wind speed,.and the potential for a wind shift Current weather conditions or plant conditions that might affect evacuees safety. If sheltering is preferred over evacuation until a release of radioactive material is terminated or other conditions warrant. If evacuees should use personal vehicles or mass transit. If evacuees should assemble at an off-site location outside the 10-mile EPZ for further instructions or subsequent staffing. 2.2 Notify the SEC of the intended route and evacuation process to be used. 2.3 IF the evacuees cannot use their personal vehicles, THEN: Arrange for mass transportation to be available at a predetermined pickup point'through the Befrien County EOC. Release personnel only after transportation has been confirmed in route or in place. 2.4 IF the Security procedure for the evacuation of personnel outside the protected area has not already been initiated, THEN initiate the procedure. 2.5 Request a team from the OSC to brief evacuees and direct them offsite using the recommended evacuation route. 2.6 Periodically report the evacuation progress to the SEC until completed.

lL Reference RMT-2080TSC-001 Rev. 2 P 21 of 36

. Activation and Operation of the'TSC

' Attachment 1.1 Loss of RDR , Page ~~~~~~~~~~~~~~~~2.. NOTE: Loss of the RDR or PPC. in any facility will require personnel from the TSC to respond and supply data.as. needed. The methods used for collection of data are listed in order of preference to minimize 'interference with control room operations and employ. ALARA principals. 1-- 1-IF-the RDR is not available-in a facility,'THEN determine which data is needed. It is recommend'this data be supplied at 15-minute intervals with significant changes being transmitted immediately; 1.1 RMS (RAC or ARAC) x 1.1.1 Obtain data from: MRMS Interface Terminals PPC mUnaffected control. room Control Terminal Affected c'ontrol room Control Terminal Local DAM readings (request a team from the OSC) 1.1.2 Record RMS data for requested channels'on Data Sheet 2, Radiation Monitoring System. 1.1.3 'Supply data sheets to TSC Administrative personnel for transmittal and dissemination (as per Attachment 5, Document Transmission/Distrbution, of this procedure). 1.2 Plant Status (PET Operations or PET Training) 1.2.1 Obtain data from: PPC Affected control room Available local devices (request a team from the OSC) 1.2.2 Record plant status data on Technical Information Sheet: (PMP-2080-EPP-100, Data Sheet 1). 1.2.3 SuppIy data sheets to TSC Administrative personiel for transmittal and dissemination. ' 1.2.4 WEN the RDR returns to service, THEN recall any field teams, if appropriate.

Reference RMT-2080-TSC-001 Rev. 2 Page 22 of 36 -. - Activation and Operation of the TSC .Attachment 12 l Dose Extension and Authorization Pages: I ~~~~~~~~~~~~~~~~~~~~22 -24 .NOTE: The SEC authorizes dose extensions (doses in excess of 10 CFR 20 and per the guidance in EPA-400-R-92-001) for.individuals/teams during emergencies. Section 1 is provided as guidance when considering dose extensions. Exposures. exceeding 25 REM whole body should only be considered and used as a last resort. The use of ALARA. principles and multiple personnel shall be considered first. 1 Precautions and.Limitations 1.1 Dose to all workers during an emergency should be limited to 5 rem whole body when practical. 1.2 Dose to workers performing emergency services under emergency conditions are treated as a once in a lifetime exposure. 1.3 Individuals who have received > 10.rem in a previous incident have received their. "once in a lifetime' exposure and are not allowed to exceed 10 rem in this incident. 1.4 Dose extensions should not be authorized for exposures which would be accrued in an emergency that are not related to the incident. Administrative dose limits should apply in these cases. 1.5 Minors and Declared Pregnant Females are not to be considered for receiving emergency doses. 1.6 Workers should not be allowed dose limits greater than 5 rem whole body unless both of the following conditions have been satisfied. Lower doses through the rotation of workers or other commonly used dose reduction methods are not.possible, and, .Instrumentation is available to measure their exposure' 1.7 Workers performing services during emergencies should, for the duration of the

incident, be lirnited to:

Dose to the lens of the eye to three (3) times. the listed whole body values Dose to any other organ, including skin and body extremities, to ten (10) times the listed whole body values

.1.8 Exposures should be limited as fo,lows: 1.8.1 Protection of Valuable Property 10 rem whole body per incident'for ti 1.8.2 Protection of Large Population he protection of valuable property -a.. <25 rem whole.body per.lifetime if the exposure of workers.that is incurred for the protection of large population may be considered justified for situations in. which the collective dose avoided by the emergency operation is significantly larger than that incurred by the workers involved.

b.

>25 rem whole body per lifetime if the exposure of workers that is incurred for the protection of larger populations may be considered. justified for situations in which the collective dose avoided by the emergency.operation is significantly larger than that incurred by the workers involved provided: The dose. received is on a voluntary basis The individual has full awareness of the risks involved M The individual has'signed next to his/her name on the dose extension form 1.8.3 Life Threatening Situations

a.

<25 rem whole body per lifetime for life saving activities

b.

>25 rem. whole body per lifetime for an unavoidable life threatening-situation provided-The Dose received is on a voluntary basis The individual.has full awareness of the risks involved (see Section 2 of this attachment) The individual has signed next to his/her name on the dose extension form 1.9 Dose extensions are given for the task, not for the duration of the emergency. Reference RMT-2080-TSC-001' r Rev. 2. Page 23 of 36 Activation and Operition of the'TSC Attacliment 12 Dose Extension and Authorization

Reference RMT-2080-,TSC-D01 Rev. 2 Page 24 of 36 I

-Activation and Operation of the TSC

Attachment 12.

Dose Extension andAuthorization Pages .- ~ ~ ~ ~ ~ ~~~~2

2 Provide the information contained in this section to the individuals receiving emergency dose extensions:

a Risks will be lower for protracted exposure periods. b Supportive medical treatment may. increase 'the dose. at which these frequencies occur by approximately 50 percent. Forewarning symptoms of more serious health effects associated with large doses of radiation. Approximate Cancer Risk to Average Individuals from 25 rem Effective Dose Equivalent Delivered Promptly. To estimate average cancer mortality for moderately higher doses the results may be increased linearly. 3 Complete Data Sheet 3, Dose Extension Form (using TSC Administrative personnel between the OSC and TSC as necessary). 3.1 Once SEC permission has been obtained, individuals may be dispatched from the OsC. Age at exposure (years) Appropriate risk of premature Average years of life lost if death (deaths per 1,000 premature death.occurs persons exposed) l (years). 20 to 30 9.1 24 30 to 40 7.2 .19 40 to 50 5.3. 15 50to60 3.5 11 r@Xo

Reference RMT-2080-TSC-Oo1 -Rev. 2.. Page 25 of 36 Activation and Operation of the TSC J 3 KI Administration Page: NOTE: The SEC authorizes the use of KI during emergencies, under the recommendations of the RAG or RPD.. Section 1. provides guidance for when KI should be administered. 1 The RAC or RPD should consider KI administration to affected.individuals in the following instances: 1 1 Prior to teams being dispatched when a radioactive release, is known or suspected following fuel or clad damage. 1.2 Prior to teams being dispatched when airborne concentrations to iodine are likely, suspected, or unknown following fuel or clad damage. .1.3 Within 2 hours of a known or suspected uptake of iodine. 1.4 When 1-131 airborne concentrations approach 2E-51LCi/cc. 2 IF the RAC or RPD determines that KI administration is advisable, THEN request authorization of the SEC for KI administration. 3 IF authorization for KI administration has been obtained from the SEC, OBTAIN consent from individual(s) via 12-RMT-2080-OSC-001, Data Sheet 3, KI Consent Form. 4 IF consent has been given TEN administer KI per the instruction of the RAC or RPD. NOTE:. KI is normally taken once per day for 10 days. 5 UPON completion. of KI administration, RETURN the completed KI Consent Form to RP.

Reference RMT-2080-TSC-001. .Rev. 2 Page 26 of 36 Activation.and Operation of the TSC'. 4 Classification Page: -26 i 1 Perform classifications using PMP-2080-EPP-10. 2 IF a classification upgrade is warranted and the EOF has not been activated: Note the time of the classification. X Notify the control room of the following: S> classification upgrade > the time of the classification > to initiate plant.public address announcemenis > sound the Nuclear Emergency Alarm as specified in the control room procSdires > to make off-site notifications as specified in the control room procedures. Notify the other facilities as applicable. Perform a facility brief. 3 IF the EOF has been activated, THEN the Emergency Director must approve all classification upgrades.

TIME/DATE l. MISSION :DETAILS: ,,,.,7. { ADDITIONAL INFORMATION:- APPROVED: SEC TIME DATE

TRANSMITTED TO OSC:

i TIME DATE Reference RMT-2080-TSC-o1 Rev. 2 Page 27 of 36 Activation and Operation of the TSC Data Sheet. 1 Response Team Request Page: I ~~~~~~~~~~~~~~~27 ll.

Unit No. Date - Data Collected by ..Reviewed by ALARMS iTRENDS MONITOR CURRENT READING UNITS LOCAr1ON / I .. VRS-1101 1201 /1 VRS-210i / 2201 I. VRA-1310 / 2310

1

,-VRA-141012410 / ERS-1301/2301 I ERS-1303 I 2303

. I ERS 1305 /2305

/ ERS-1307 I 2307 / ERS-1309 /2309 /1. ' ERS-1401 I 2401 1 '.ERS-1403 / 2403 I ERS-1405 / 2405 ERS-1407 / 2407 / ERS-1409 2409 / VRS-1501 / 2501 / I VRS-1503 I 2503 / VRS-1505 1 2505 I VRS-1507 I 2507 /

VRS-1509 1 2509

/ MRA-1601 /2601 / I MRA-1602 / 2602' / MRA-1701 / 2701 / MRA-1702 I 2702 l ,SRA-1805/2805 / SRA-1807 / 2807 / SRA-1809 / 2809 I SRA-1905 /2905 l SRA-1907 I 2907 l SRA-1909 /2909 / DRS-3101 l4101 / DRS-3201 I 4201 /I SFR'1810 / 2810 / SFR-1910 12910 / VFR-151012510 / I Wind Speed t Wind Direction I Air Temp. AT R/h RJh Ai+/-C JACI/. il&ci/cc piCi/cc.

ici j+/-Ci

~~~pCi/cc.

gCi1cc PM/c=
I j~~~~~Li I

pC~~~~i I p~~~1Ci/cc pCi/cc I ~~~pCi/cc pCi/cc pACi/cc..

pCi/cc
pCi/cc
Ci/c Pci/cc pCi/cc ICi/cc
pCi/cc piCi/cc CFM 1

~CFM M PH o (rom) Upper CIMT Area Upper CTMT Area Upper CTMT High Range Area Lower CTMT High Range Area Lower CTMT Airborne Particulate Lower CTMT Airborne lodine Lower CTMT Airborne LRNG Lower CvIIT Airborne MRNG Lower CTM[T Airbome HRNG Lower CTMT Airborne Particulate Lower CTMT Airbome Iodine Lower CTMT Airbome LRNG 'Lower CTMT Airbome MRNG Lower CTMT Airborne HRNG Unit Vent Effluent Particutate .Unit Vent Effluent Iodine Unit Vent Effluent LRNG .Unit Vent Effluent,MRNG Unit Vent Effluent.HRNG S/G PORV Loop 1 SIG PORV Loop 4 SIG PORV Loop 2 SIG PORV Loop 3 Gland Steam akoff LRNG Gland Steam Leakoff MRNG Gland Steam LeakoffHRNG Steam Jet Air Ejector LRNG Steam Jet Air Ejector MRNG Steam Jet Air Ejector HRNG.. SIG Blowdown SIG Blowdown Treatment Gland Steam Leakoff Flow Steam Jet Air Ejector Flow Unit Vent Effluent Flow Reference RMT-2080-TSC-001 Rev. 2 Page 28 of 36 - Activation and Operation of the TSC Data Sheet 2 l Radiation Monitoring System Pages: 1 ~~~~~~~~~~~~~~~~~~~28 -29 . Time -. 1 .2 3 4. 5 6 7 8 9 10 11 12 13 14 15 16 17 18

19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34

,35 36 37 .= Z.

I Reference RMT-2080-TSC001. Rev. 2 Page 29 of 36 Activation and Operation of the TSC Data Sheet 2 Radiation Monitoring System.ages: ALARMS: ( High, (A) Alert, (F) Fail, -etc. TREND: 1' 4-e (ncrease,Decrease, Steady, etc.) Comments: DOSE RATES IN AREAS OF THE PLANT:. 650' SFP Aea 633' Hallway 609'Hallway 587' Hallway 573' Hallway 609' Access Control Emergency Sampling U1 591' BDFT Area U2 591' BDFT Area OTHER:

d,I

Request Date: . Estimated Dose Rate: Estimated Stay Time: Estimated-.Dose: Reason for Dose Extension Request: Radiological Assessment Coordinator: Approval Authority (Non-Delegable Signatire) Site Emergency Coordinator: Approval Authority (Non-Delegable Signature) Date/Time: Date/Time: Reference RiMT-208 TSC-001.l Rev.: 2. Page 30 of 36 Activation and Operation of the TSC Data Sheet 3 Dose Extension Form.. Page 30 Time: Name SSN Current Incident Dose Dose Extension Limit t~~~~~~~~~~~ .. ~~~

z.

7

Reference RMT-2080-TSC-OO1.... Rev. 2. Page 31 of 36 Activation and. Operation of the TSC Figure 1 Definitions and Abbreviations

Pae Term Meaning ARAC Assistant Radiological Assessment

. Coordinator CAS Central Alarn Station DAM.. Data Acquisition Module EAD Environmental Assessment Director (EOF) EOC Emergency.Operations Center (Lansing) EOF Emergency Operations Facility ENC Emergency News Center ERDS Emergency Response Data System ERO Emergency Response Organization GE. General Emergency JPIC Joint Public Information Center KI Potassium odide (thyroid blocking-agent) OSC Operations Support Center PAR Protective Action Recommendation PET Plant Evaluation Team. . PPC Plant Process Computer RAC Radiological Assessment Coordinator RDR .Real-time. Data Repository RMS Radiation Monitoring System SAE Site Area Emergency.

Reference RMT-2080-TSC001 i Rev. 2 -7 Page 32 of 36 Activation and Operation of the TSC J Figure 1 Definitons and Abbreviations Page Term Meaning SAS Secondary Alarn Station SEC Site Emergency Coordinator TSC Technical Support Center. UE Unusual Event s

Reference. RMT-20$0-TSC-001 Re.2Page 33 of 36' Activation and Operation of the TSC ,Figure 2 Position Descriptions 33ages6 -The position descriptions provided are intended as guidance Deviations and additions to these descriptions are allowed as long as the accomplished objectives can be achieved. Assistant SEC Ensures all TSC staff carry:out their assigned functions;.:. Ensures timely. exchange of information within the TSC staff and among inte'rfacing facilities; Manages the activities of the Plant Evaluation Team (PET); Works with the Operations Support. Center Manager to implement repair and corrective action activities; Interfaces with the SEC on matters such as emergency classification and on-site actions in progress.

Confers and/or advises the Public Affairs Liaison in determining responses to requests. for information when requested.
Fulfills SEC duties in the absence of the SEC.

Radiological Assessment Coordinator and Assistant RAC

Provides expertise in 'the area of radiation protection to the PET.and Assistant SEC; Provides assistance to the Radiation Protection Director in determination of protective actions for on-site personnel, including emergency response teams. These protective action determinations include:

> Assembly/evacuation of non-essential personnel, > Evacuation of on-site emergency response facilities due to adverse radiological conditions, Administration of KI.

Determines, staffing needs in the area of radiation protection a'nd informs the SEC/Assistant SEC of deficiencies in this area.

Obtains the approval of the Site Emergency Coordinator (SEC) for individuals to exceed the dose limits specified in 10 CFR 20;

Periodically assesses -TSC radiological habitability and makes recommendations to the SEC/Assistant SEC for facility evacuation if necessary.
Obtains RMS data from the Control Terminal or directly from radiation monitors when the PPC is unavailable. Applicable data is transcribed on the Radiation'Monitoring System Data Sheet for transmission to the EOF and applicable public information center. (ENC or JPIC).

Reference RMT-2080-TSC-001 Rev. 2 Page 34 of 36

Activation-and Operation of the TSC.

Pages: Figure 2 .Positon Descriptions 3 36 -~ ~ ~ ~ ~~~~~~~~~3 - 3 Plant Evaluation Team Requests. OSC response team(s) (through the SEC) to perform, diagnostic or mitigating actions as necessary; .. Provides an independent technical analysis of plant conditions; Develops corrective action recommendations; Provides technical assistance to Operations' personnel when requested; Monitors fission product barrier status (PET Operations); Recommends emergency classification. changes as necessary; -Responds to questions from off-site agencies; as' directed by the SEC/Assistant SEC; Provides-a person to act as Scribe in updating the Plant Status Board in the event that the PPC becomes unavailable (PET-Training. representative is suggested), as requested by the Administrative Coordinator.. Public Affairs Liaison Communicates with public affairs personnel at the ENC or JPIC to provide information. relative to the emergency when requested. Confers with the SEC/Assistant SEC to determine responses to public affairs personnel information requests when necessary. TSC Boardwriter Maintains the chronological. event status board based upon information obtained;from the Control Room Communicator and as deemed necessary by the Assistani SEC;' . Communicates information from thX TSC to the EOF and Control Room, including status/activities of the OSC; Relays incoming messages/requests to the. applicable TSC member when requested by the Control Room or EOF. TSC Administrative Support .. Transmission of hard copy documents from the TSC'to the EOF and/or OSC; Transmission of hard copy documents from the TSC to the ENC or JPIC as appropriate (see Attachment 5 "Document Transmission/Distribution" for documents that are "routinely" transmitted). H Hand carries documents between the TSC and Control'Room (conditions permitting); Duplicates and distributes dociuments within the TSC;

Reference RMT-2080-TSC-1 Rev. 2 1 Page 35 of 36 Activation and Operation of the TSC Figure 2 Position Descriptions Pages: I ~~~~~~~~~~~~~~33-36 Performs general administrative tasks as directed by,the.Administrative Coordinator (see. "Document TransmissionlD istribution" for documents that are "routinely"'.' distributed)." TSC Team Coordinator Communicates directions regarding team dispositioring from the Assistant SEC 'or SEC to the OSC; Receives status reports on emergency response teams from the OSC and provides this information to the TSC. Relays messages from the OSC to the applicable TSC personnel. TSC Administrative'Coordinator Directs and coordinates communications activities in the TSC, including providing-direction to the FAX Administrative Support, Boardwriter, and TSC Team Coordinator;

Duplicates and distributes,hard copy documents within the TSC;
Transmits hard copy documents to the EOF, ENC, or JPIC;
Acquires technical documents (prints, procedures, technical manuals, etc.) at the request of the Plant Evaluation Team.

& Compiles information to be reported off-site from the PET and RAC; Obtains approval of the SEC/Assistant SEC prior to releasing any information off-site.

Announces'information over the plant Public Address system as directed by the.

SEC/Assistant SEC.

Assigns a TSC menber.to'act as a Scribe-in updating the Plant Status Board in the event that the PPC is not functioning. (It is suggested that the PET-Training representative perform this function.)

Security Director Initiates and oversees Security actions for site personnel.assembly and accountability when requested by te SEC.

Initiates and' oversees Security actions for evacuation of site personnel when requested by the SEC.

Implements Security actions to bar the PABX (plant telephone system) upon the declaration of a Site Area Emergency or higher classification.

Reference RMT-2080-TSC-001 Rev. 2 Page 36 of 36 Activation and Operation of the TSC. Figure 2 Position Descriptions Pages: 33 -36 -Site Emergency Coordinator Reviews the emergency.situation with the Shift Supervisor. Assumes the Site Emergency.Coordinator responsibilities from the. Shift Supervisor for . overall management of plant and emergency response functions, and assures that proper actions are being taken to.mitigate the event. Ensures that the:proper State/County authorities, NRC and AEP officials are notified. Makes recommendations to State/County. authorities responsible for offsite emergency. measures during the initial phase of the nuclear incident prior to activation of the EOF. Orders the assembly; accountability, and evacuation of all non-essential plant personnel upon the declaration of a Site Area Emergency (or higher) classification, or at a lower classification if deemed prudent by SEC judgement. (Accountability may be performed via the plant exit turnstiles, rather than:assembly areas,. if so designated by.the SEC.) . Grants approval of PET requests for OSC team actions.

A Prioritizes OSC team nissions by importance.

Orders the evacuation of the TSC for habitability -concerns, if necessary, and relocation or evacuation of TSC personnel. Relinquishes all TSC and Control Room responsibilities and functions relative to Classification, Notification,. and PAR's upon activation of the EOF.}}

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