ML20237K753

Public Version of Emergency Implementing Procedures, Including Rev 1 to HP/O/B/11009/03, Health Physics Response Following Primary to Secondary Leak & Rev 0 to HP/O/B/1009/18, Offsite Dose Projections

ML20237K753
Person / Time
Site:	Catawba
Issue date:	07/30/1987
From:	Clemson R, Wright T DUKE POWER CO.
To:
Shared Package
ML20237K724	List: ML20237K722 ML20237K753
References
PROC-870730-01, NUDOCS 8708190394
Download: ML20237K753 (114)

Text

{{#Wiki_filter:,... y Form 34731 (R9 86) (1) ID No. HP/0/B /1009/03 DUKE POWER COMPANY Change (s) O to, PROCEDURE PROCESS RECORD 1 Incorpora:ed ' 7 PREPARATION (2) STATION ca e n >h n Mel an t ' R en H o" (3) PROCEDURE TITLE m ith Physic Resnonse Fo11 ovine A Primary To Secondarv Leak I (4) PREPARED BY-he / 7-2 Y~ b DATE (5) REVIEWED BY. DATE ~ ~ l Cross Disciplinary Review By N/R C *Y (6) TEMPORARY APPROVAL (if Necessary) ey (SRO) DATE i i By DATE 7[30)M -(7) APPROVED BY d) DATE (8) MISCELLANEOUS Reviewed / Approved By DATE [ r ( Reviewed / Approved By DATE I (9) COMMENTS (For procedure reissue indicate whether additional changes, other than previoutly approved chpges, are included, Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED, CWes CNo i (10) COMPARED WITH CONTROL COPY DATE i COMPLETION (11) DATE(S) PE RFORM E D (12) PROCEDURE COMPLETlON VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R as accropriate? O Yes O N/A Listed enclosures attached? O Yes O N/A Data sheets attached, completed, dated and signed? O Yes D N/A Charts, graphs, etc. attached and properly dated, identified and marked? O Yes O N/A Acceptance criteria met? VERIFIED BY DATE

13) PROCEDURE COMPLETION APPROVED--

DATE (14) REMARKS (Attach additional pages,if necessary ) 8708190394 870807" PDR ADOCK 05000413 F PDR L__-___-___-_______-___-_______

y .u 4 i> ],e n s 1 HP/0/B/1009/03 DUKE POWER COMPANY CATAWBA KUCLE.AR STATION HEALTH PHYSICS RESPONSE FOLLOWING l A PRIMARY TO SECONDARY LEAK 1.0 PURPOSE ~ This procedure describes the manner in which Health Physics persoanel will l monitor and account for the release of. radioactivity to' the environment, q' minimize the spread of contamination, and identify radiological hazards due to a primary to secondary leak. '1

2.0 REFERENCES

2.1 HP/0/B/1000/02 - Taking, Counting, and Recording Survey,s i l 2.2 KP/0/B/1000/05 - . Delineation of RCZ's j 2.3 HP/0/B/1001/12.- Technical Specifications Gaseous Waste Sampling and Analysis-i I 4. 2.4 HP/0/B/1001/13 - Technical Specifications Liquid Waste Analysis l 2.5 HP/0/B/1001/18 - EMF Saapling i 2.6 Fr/0/B/1004/04 - Radioactive Liquid Waste Release 1 2.7 HP/0/B/1004/05 - Radioactive Gaseous Waste Release 1 2.8 HP/0/B/1009/11 - EMF Loss 2.9 CP/0/B/8800/04 - Chemistry Procedure For Corrective Action (Power Chemistry) 2.10 CP/0/B/8800/14 - Chemistry Procedure for the Determination of Steam Generator Tube' Leak Rate-2.11 Catawba Nuclear Station Technical Specifications I 2.12 Code of Federal Regulations, Title 10, Parts 20 and 50 3.0 LIMITS AND PRECAUTIONS 3.1 Ensure that all controlled releases are within the limits required in References 2.11 and 2.12. 3.2 Following identification of net activity other than naturally occurring isotopes in samples collected per Section 4.0, sampling-shall not be termi.nated until NO NET activity has been identified (~ in two consecutive samples of the appropriate system. These samples shall be counted to the lower limit'of detection (LLD) for principal gamma emitters listed in Technical Specifications Table 4.11-1 (Reference 2.11). .L.

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j.- p. -HP/0/B/1009/03' N h Page 2 of 5- _7 3.3 Prior to initiating Section 4.2 of this. procedure,' ensure that.the- .7~ ^ alarm on EE 31 is : not due to radioactivity f rom Floor. Drain ' Sumps 'C' (Unit 2) or 'D' (Unit 1) as they have the potential for'. ~ 4 becoming contaminated and : provide ' input.to the applicable Turbine' Building Sump. H 4 3.4 Turbine Building Sump sampling per T.B. Sump Sample Log (Enclosure 5.2)'may :be discontinued if samplin'g per Reference 2.6 has been initiated and approval is granted by the Station Health Physicist. 3.5 Turbine' Building Sump sampling shall be performed -in accordance - with Reference 2.8 when the applicable EMF 31 is inoperable' regardless of the-requirements of this procedure. 3.6 - All samples shall be analyzed in accordance with Reference 2.3 and/or 2.4. ,x s 3.7 Alarms ~ (Trip 2) on the Stean' Generator. Blowdown Monitors (1 and 2 l EE 34) may indicate a primary to secondary. leak and Section 4.0 of-this procedure may be implemented if' deemed necessary by Health-1 Physics Supervision. t j 4.0 PROCEDURE 4.1 Upon notification that the Condensate. Steam' Air Ejector (C.S. A.E.') i Off Gas Monitor (EMF 33) has alarmed (Trip L 2) indicating a primary' ] .3 to secondary steam generator tube leak, proceed as. follows unless ' l e ( the alarm is determined to 'be an EMF-malfunction: I s l 4.1.1 Collect and submit for analysis a 4600 ce gaseous sample' from the appropriate C.S. A.E. Monitor (EMF 33): per Reference 2.5 using new.marinelli beaker (if available). 4.1.2 Contact the Operator At The Controls (OATC) of the affected unit.and: request that Operations trend the appropriate EMF 34 on a. chart recorder and then align flow l to EMF 34 to sample each steam generator separately for L at least 5 minutes denoting on the chart recorder which steaci generator was being sampled. Utilize data from the chart recorder to determine which steam generator is leaking. Health Physics should assist Operations with above if personnel-are available. 4.1.3 If analysis results from sample obtained per Section 4.1.1-confirms'a primary to: secondary. steam generator tube leah: i 4.1.3.1 Initiate the C.S.A.E. Sample Log (Enclosure 5.1) and the T.B. Sump Sample Log (Enclosure 5.2) to record details and sample results. a e _? J l l r L___m______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _

HP/0/B/1009/ 3 l Page 3 of 5 i 1 { 4.1.3.2 Collect and submit. for analysis a 3500 ml r liquid sample from the appropriate Turbine i Building Sump (T.B. Sump) per Reference 2.5 i using a new marinelli beaker. l l 4.1.3.3 Request that Primary Chemistry implements j Reference 2.9 to identify the leaking steam j generator and that Secondary Chemistry j implements Reference 2.10 to determine the j steam generator leak rate. I 4.1.3.4 Utilize Enclosure 5.1 and 5.2 to record sample i dates, times, results, and details until sampling is terminated under the direction of the Station Health Physicist (when the requirements of Section 3.2 are ' met). 1 ( 4.1.4 If initial sample results (Per Section 4.1.1) indicate no j net activity other than naturally occurring isotopes, refer to Reference 2.8 and terminate this procedure as directed by Health Physics Supervision. ) l 4.1.5 If the C.S.A.E. Monitor sample results indicate net j activity for other than naturally occurring isotopes, l initiate Reference 2.7 to account for the released l activity. t [ 4.1.6 If the T.B. Sump sample results indicate net activity for other than naturally occurring isotopes, perform Sections j 4.2.3.4 and 4.2.3.5 of this procedure, j i 4.2 Upon notification that the T.B. Sump Monitor (EMF 31) has alarmed (Trip 2) indicating a primary to secondary steam generator tube l leak, proceed as follows unless the alarm is determined to be an EMF. malfunction: l 4.2.1 Collect and submit for analysis a 3500 m1 liquid sample from the appropriate Turbi.a Building Sump J.B. Sump) per Reference 2.5 using a new marinelli beaker. 4.2.2 If the T.B. Sump sample results indicate no net activity for other thaa naturally occurring isotopes, refer to l Reference 2.8 and terminate this procedure as directed by l Health Physics Supervision. 4.2.3 If the T.B. Sump sample results indicate net activity for l other than naturally occurring isotopes, complete the following: I l l 4.2.3.1 Initiate the T.B. Sump Sample Log (Enclosure 5.2) to record details and sample results. i i l I ^ l i l l j l__ _____________________._______2

r m-a '~ j.. ,HP/0/B/1009/03. 'E Page'4 of.5-4.2.3.2 Utilize Enclosures 5.2 to record sample dates, e times,'results, and details until: sampling is terminated under the direction of the' Station ' Health Physicist.(when the requirements'of l Section 3.2 are. met).. 1 l 4.2.3.3 Implement Section 4'.1"of this procedure (C.S.A.E. Monitor sampling) as' directed.by, i Health Physics Supervision. 4.2.3.4 Initiate Reference 2.6 to account for the activity released via the T.B. Sump as. necessary. 4.2.3.5' Notify Operations and Chemistry per T.B. Sump. ~ Sample Log (Enclosure'5.2). ~ 4.3 When it has been established that 'a primary to. secondary tube leak - has occurred, control:over the release of WC System Ponds:shallsbe as follows: 4.3.1 Request Environmental Chemistry to notify Health Physics - Shift personnel of any WC releases to be made prior to initiating the release. 4.3.2 Prior to the release of a WC Pond, collect-and submit'for analysis two 3500 m1 gamma samples and two distilled ( tritium. samples from the Pond to be released. 4.3.2.1. During the release of;a WC Pond, collest a' 3500 ml gamma sample and a distilled tritium sample daily from the Pond being released OR the WC discharge-flume. 4.3.2.2 Utilize new sample containers to collect and analyze all WC Pond samples. 4.3.3 If sample results frem Sections 4.3.2 and 4.3.2.1' indicate no net activity for other than naturally occurring isotopes, inform Environmental Chemistry that the release is allowable. 4.3.4 If any of the sample results from Sections 4.3.2 or 4.3.2.1 indicate net activity'for other than; naturally occurring isotopes, account for the activity released per Reference 2.6 methodologies -and allow the pond to -be released. 4.3.5 Terminate WC Pond sampling when authorized by the Station ~ Health Physicist. ( i

} - = - - HP/0/B/1009/03-Page 5 of 5 4 . g l

4. 4' When.it has been established that: a primary to secondary leak has

! r"' occurred, initiate actions to' minimize radiation exposure and the spread of contamination. I 1 -1 l 4.4.1 Survey-affected areas of the station for radiation levels - and/or contamination per Reference 2.1. The frequency of l surveys will be determined by Health Physics supervision based on the magnitude of the leak. 4.4.2 Consider the.following wh'en performing surveys: Jj 4.4.2.1 Leaks occurring ~at low points or areas of high' ~ 4 '" evaporation have the highest probability of being contaminated. 4.4.2.2 Pay particular attention-to system' low points,. 1 traps, demineralizers, and filters when-performing radiation surveys as contamination is concentrated in these areas. 4,.4.2.3 Systems having the highest potential-for becoming" contaminated include: AS, BB, BW, CA, CB, - CF, CL, CM, CS, CT, lHA, HB, HC, HD, HE, HF, HG, HM, HR, HS, HV, HW, 3 SA, SB, SC, SD, SH, SM, SP, SV, TE, TF, TL, - D ~ and TS. / 1 Other systems could becoce contaminated and should be evaluated for radiological impact. 4.4.3 Post all areas identified by surveys in=accordance with Reference 2.2. 4.4.4 Consider the need for job coverage on repair and maintenance activities on affected systems and components. 4.4.5 Contain contaminated leaks, if possible, t minimize the spread of contamination. I t. 5.0 ENCLOSURES 5.1 Sample of C.S.A.E. Sample Log l 5.2 Sample of T.B. Sump Sample Log s e i / e N ___-__--_------_-__-_-_.-L--- .__.-__._.-_-1

DUKE POWR COHPANY Page 1 of.2 i4 CATAWBA NUCLEAR STATION l q HP/0/B/1009/03 ENCLOSURE 5.1 ~ I !e C.S.A.E. SAMPLE LOG t' This form is to be used any time a primary to secondary leak is indicated. r 1. Upon, notification that a primary to secondary leak is indicated, record the following: l Notified by: Da te/ Time : / Health Physics personnel receiving call: 2. UNIT # Remarks / Comments: ) i l 3. If C.S.A.E. sample results indicate net activity for other than naturally occurring isotopes, notify the following Sections / Groups of sample results (i.e., confirm primary to secondary leak) and route copy to l Secondary Chemistry. 1 Secondary Chemistry: Date/ Time: / ( Radwaste Chemistry: Date/ Time: / Environmental Chemistry: Date/ Time: / Primary Chemistry: Date/ Time: / Operations: Date/ Time: / Notified by: (Health Physics) 4. The sampling frequency will normally be once per 12 hours buc may change during the primary to secondary leak as dee ed necessary by Realth Physics supervision. Record all changes below and route sample results to Secondary Chemistry. l i New Sampling I, Change 1 Health Physics l l Health Physics l Frenquency l Initiated i Shift Technicians I Supervisor 1 (Once Every) l Date/ Time

1. Recording Changel I.-

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DUKE POWR COMPANY Page 2 of 2 CATAWBA NUCLEAR STATION HP/0/B/1009/03 ENCLOSURE 5.1 C C.S.A.E. SAMPLE LOG I l DATE/ TIME l DATE/ TIME l REMARKS AND/OR RESULTS l SIGNATURE l J l OF SAMPLE I 0F NEXT l l l l l SAMPLE l l l l 1 i i l' i l-1 I l_ l I I I I l a l l I I I 1 i i l i 1 l i I I I i j i l i l I I I I I I i l I I I I i l_ l i I I I I I I I .I l 1 - 1 I I i 1 1 1 I l I I I I I I i i l l l - 1 I l-I I I I I I I I I I I I I I I I 1,- 1 I I I I N I I I I l-l 1 I I I i 1 l 1 I I I I I I I I I i I I I I I I I I I I I I I I I l l - 1 I I I I i l l l l I I I I I I I I I I I I I I I I I i l 1 I I i 1 1 1 I I i i l l I I 1. I I I l i l I i i i l l I I I I I i i I I I I I I I I I i l l I I I l__ l - 1 I I I I I I I I I I I i '~ l I i l l i l I I i S L_.___ ._________._______m

f DUKE POWR COMPANY Page 1 of.2 CATAWBA NUCLEAR STATION HP/0/B/,1009/03 ENCLOSURE 5.2 T.B. SUMP SAMPLE LOG This form is to be used any time a primary to secondary leak is indicated. 1. Upon notification that a primary to secondary leak is indicated, record the following: Notified by: Date/ Time: / Health Physics personnel receiving call: 2. UNIT # Remarks / Comments: i 3. If T.B. sump sample results indicate net activity for other than naturally occurring isotopes, notify the following Sections / Groups of sample results (i.e., confirm primary to secondary leak) and that Turbine. Building Sump releases to the WC system must be terminated. Secondary Chemistry: Date/ Time: / ( Radwaste Chemistry: Date/ Time: / Environmental Chemistry: Date/ Time: / Primary Chemistry: Date/ Time: / Operations: Date/ Time: / Notified by: (Health Physics) 4. The sampling frequency will normally be once per 12 hours but may change during the primary to secondary leak as deemed necessary by Health Physics supervision. Record all changes below. l l l New Sampling l Change l Health Physics l l l Health Physics l Frenquency l Initiated i Shift Technicians i l Supervisor ] (Once Every) l Date/ Time l Recording Changel I I 1. l I I I hours l l l 1 I I I I l I bours l l l 1 I I I I l l bours l l l 1 I I I I q l l hours l l l 1 I I I l l I hours ! I i i i l l I

DUKE POWR COMPANY Page 2 of 2 CATAVBA NUCLEAR STATION l HP/0/B/1009/03 ENCLOSURE 5.2 ~ ~ T.B. SUMP SAMPLE LOG l ) DATE/ TIME l DATE/ TIME l REMARKS AND/OR RESULTS 1 SIGNATURE l l OF SAMPLE l OF NEXT I I I i 1 SAMPII I l 1 I I I I I I I l - 1 i I I I I I I I I I I I I I I I I I I I I 1 I I I I I l I - 1 I I I I I I I I I I I I I I I I l l i i l l i 1 l i I 1 I I I I l l 1 1 I I I I I I I 1 I I l l 1 I I I I I I I I I I r I I I I . I I I I l I I I I I I I I I I i 1 1 I I _1 I I I I I I I I I I I I I I I I I I I I I I I I I I l~ l i I i I I I I l i l - 1 I i 1 I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I I I I I I l-I i i l I I I I I l_ l 1 I I I I I I I I I I i l I l l ( l I I I I I I I l I I I I I I l

m -.)) i> 1 Form,34731 (344) i5 (1)llO No HP/0/B71009/18 . DUKE POWER COMPANY Ch[rg(8). 'O to PROCEDURE PR,0 CESS RECORD ' 10 : 4 _ Incorporated PREPARATION f! . ' p,. l g., )- ,( _) STATION _ CATAWBA N'< (3) PROCEDURE TITLE OFFSITE DOSE PROJECTIONS'

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x -(4) PREPARED BY w DATE '7 - /d " 8 7 8 (5) REVIEWED BY e-DATE M @aI ' ~ ~ "ll G / / Cross Disciplinary Review By 1.c-N/R- + y (6) TEMPORARY APPROVAL (lf Necessary) C y i By

r (SRO)IDate BY Da t'e' (7) APPROVED,8Y OATE ' 7-' 6-7 7 u

(8) MISCELLANEOUS (! Reviewed / Approved 8y - Date Reviewed / Approved By-Y Date .I'., COMPLETION l l!, (9) DATE(S) PERFORMED 1 110) PROCEDURE COMPLETION VERIFICATION 3 ,s, ,). O Yes O N/A Check lists and/or 'bfanks properly initiated, signed, dated or filled in'N/A or N/R, as appropriate? O Yes O N/A Listed enclosures attached? O Yes O N/A Data sheets attached, completed, dated and signed? O Yes O N/A Charts, graphs, etc. attached and properly dated, identified and marked? O Yes O' /A Acceptance criteria met? N l l f, i-VERIFIED BY DATE \\' .] l11) PROCEDURE COMPLETION APPROVED - j DATE 'i, 112) REMARKS k, i t t .( ? j b' L d

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( 9,t. (q, q% 3-HP/0/B/ ! OOo/J FLt.N ' /, - 1, M[Q( DUKE POWER COMPANY ^ CATAWBA-NUCLEAR STATION q OFFSITE DOSE PROJECTIONS, t

1. 0.

Purpose .l To describe a me-thod for projecting dose commitment-from a noble gas and/or iodine' release, through-the containment, the unit vent-and/or the. steam relief valves,.during an emergency. 2.0 References sI l; 2.1 HP/0/B/1000/!O, Determination of, RadiationLMonitor Setpoints 2.2. HP/0/B/1009/06, Alternative Method For Determining' Dose Rate' Within The Reactor Building. 2.3 HP/0/B/1009/*4, Health Physics ct'lons Following an Uncontrolled Release of Liquid Radioactive MJterial-t2.4 HP/0/B/1009/17 Unit 1 Post-Accident Containment Air Sampling System 2.5 HP/0/B/1009/21, Abnormal Unit Vent Sampiing [ 2.6 CNS Technical. Spec i fic a t ion 3.6' l.2 2.7 Of f s i t e Dose Cal cu l'a t i on Manua l (ODCM) 2.8 Regulatory Guide 1.4,'" Assumptions Used For Eva lua t i ng -' The l Potential Radiological Consequences of a Loss of Coolant Accident For Pressurized Water Reactors" 2.9 Regulatory GJide 1.109, " Calculations of Annual Dods to Man'From Routine Releases of Reac tor Effluents For The Purpose of.Evaluat - ing Complian:e With 10 CFR Par t 50, Appendix I" l 2.10 NuReg-0396, EPA 520/1-78-016, " Planning Basis For The Development of State and Local Government Radiological Emergency Response Plans In Support of Light Water Nuclear Power Plants" - 4 s 2.11 NuReg-0654, FEMA-REP-1,Rev.1, " Criteria For Preparation And Evaluation of Radiological Emergency Response Plans And 1 Preparedness in Suppor t of Nuc lear Power Plants" 2.12 Letter from'F.G. Hudson, 3eptember 30, 1985, re: Release Rate Information for McGui re and Ca tawba Nuc l ear S ta t i on (Fi.l e: CN-134.10) 4 2.13 Catawba Nuclear' Station Class A Computer Model Validation (Files ( NUC-0306) ( 2.14 Letter from J.E. Thomas, May 19, 1.987, Files CN-1346.05 and personal conversation with Frank Poley. l. t __L__-___---------------- - ^ ^ ^ ~ ' " ^ ' ^ ^ ~ ~ ~ ~

HP/0/B/1009/18 Page 2 r~. 3.0 Limits and Precautions 3.1 This procedure is an alternative method of dose assessment to the Catawba Class A Atmospheric Dispersion Model~ computer code. 3.2' This procedure applies to releases made from Catawba Nuclear l Station only. Many of the values contained in this procedure are site specific. 3.3. It is assumed that th'e whole body dose from an iodine release is ,s very small compared to the thyroid dosel therefore, iodine whole body dose is not considered here. I S l 3.4 This procedure considers all releases to be ground level releas-es and th~at meteorological data are 15 minute everages, 3.5 Once a zone has been added to the list of affected zones, it shall not be removed except under the direction of.the Dose Assessment Coordinator. 3.6 Once the Crisis Management Cerster -(CMC) has been activated, the doses calculated by the Technical Support Center (TSC) dose assessment group, should be compared wi th those calculated by the CMC before an evacua t ion recommenda t ion is made. e00 Procedure 4.1 Meteorology Assessment 4.1.1 Acquire the following information and record on'the Dose Assessment and Meteorology Worksheets (Enclosures 5.1 and 5.2, respectively): 4.1.1.1 Lower tower wind speed (WS) in miles per hour. 4.1.1.1.1 Use upper tower wind speed if lower tower wind speed is not available, i l 4.1.1.2 Upper tower wind direction in degrees:from North (North = 0 ). ( l 4.1.1.2.1 Use lower tower wind direction if upper tower wind direction is not i available. 4.1.1.2.2 If the wind speed or wind direction can not be obtained from plant sys-tems, obtain them from the National Weather Service (phone 704-399-6000). i / If the NWS information is unavailable, s._ then obtain data from McGuire Nuclear Station Control Room (73 or 78, then 875, then ext 4262, or 4263, or 4264). ~ )

-y J. ~ q HP/0/B/1009/182 Page:3

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l,^ p-4.!'.1.3' TemperatureLgradient-(lit).in: degrees' centigrade. l f f 4.1.1.4-Using Enclosure 5.3. record?the stabilityIclass-I ~ based on fl,T. ~ 1 i 's' 'l 4. 1 '. 1 ' 4'. 1 If the Temperature gradier.t i u n k no w n ~, the following' applies: i e 'If between 1000 ,1600 hours, f use stability class D3 wiyj I f be tween 1600 -- 1000- ho.r s, o use stability class'G. r. 4.1.1.5 If necessary, use forecasted meteorological deta' for calculating doses due +o changir.1 meteorolog-ic al condi tions.. 4.1.2 Determjne the atmospheric dispers. ion'paramters,. X/Q: i (sec/m ), for .5,'2, 5 and 10 miles (record or.'

Enclosure:

5.1): ( 4.1.2.1 Using 23,T, determine the two hour relative; concentration value(CH' ( 4.1.2.2 Convert the C - val ues to X/Q : g ^ X/Q. =- H WS 'T 4.1.3 Using Enclosure 5.4, circle on Enclosure 5.1.the; i protective action zones (PA2), based upon wind speedL and wind direction.

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I Recheck meteorology conditions approximately every 4.1.4 15 minutes to ensure that other sectors have not _ been affected. 4.2 Source Term Assessment - Steam Relief Valve ( Enc l osure ' 5. 5 ) m 4.2.'1 Determine *the Sub-Noble Gas Release Rates, SOgg(Ci/sec)'- by the following. method 4.2.1.1 'For Unit 1-EMF 26, EMF 27, EMF 28 and. EMF 29 or for Uni t 2-EMF 10, EMF 11, EMF 12,' EMF 13: SONG = R/hr X 1 X LBM X CF Ci VOPEN g Ibm R/hr where: 1 R/hr = EMF 26, EMF 27, EMF 28, EMF 29 or EMF 10, 1 EMF 11 EMF 12, EMF 13 reading VOPEN = time the valve.is open in seconds i LBM lbm released for the time ~ the = =-

~ 'HP/0/B/1009/18-Page 4 (' valve was open CF ',= 1 the correc tion f ac tor per EncJo-sure 5.6. 4.2.2 Determine the Noble Gas Release Rate, O 1/sec): NG O

• sO NG NG NG' "

' + NG SONG (EMF 29) 4.2.3 Determine the' Iodine release rate, 0)(Ci/sec): O =ONG

• I"*

g - where: Irat = ratio of 1131eqv./Xe!33eqv. from' Enclosure 5.7. 4.2.4 Record D and Og on Enc losure 5.1. NG 4.3 Source Term Assessment - Contai nment (Enc losure 5.8) 4.3.1 Determine the Noble Gas Release Pate, O 3 on one of the following methodst NG' ^ } 4.3.1.1 Based on an EMF reading, where; i 7 O NG = EMF x CF x LR wherei EMF = 39(L), if EMF 39(L) <'1E7 cpm, EMF = 39(H), if EMF 39tL) is offscale and-EMF 39(H) > 100 cpm, EMF = 53A or 53B, if EMF 39(H) is offscale, CF = the correction f actor per Enclosure 5.9 LR = Leak Rate,(ml/hr), by one of thel fo11owing methods: I based on contai nment pressure: )' LR = RLR (from Enc.losure 5.10) based on an opening L in, containment: LR = Olt (from Enclosure 5.11) based on design leak rate: LR = 2.449E6 (Reference 2.13) 4.3.1.2 Based on PACS _ sample, wheres s.. ONG = ACS x CF x LR 4 whered l L-

a HP/0/B/1009/18 n Page 5- ., ~. i PACS = uCi/ml- (Ref er ence 2.4 ) CF =~2.78E-10 Ci hr sec uCi s LR =-Leak rate, as. determined in step 4.3.1.1 above \\ i I 4.3.2 Determine the Iodine Release Rate, O{(Ci/sec) based on one' of the following methodst 4.3.2.1 Based on O I NG O =.O g NG where: l ONG Noble Gas Release Rate as determined = in step 4.3.1 above l Irat = ratio of 1131eqv./Xe133eqv. from.7.

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4.3.2.2 Based on EMF 40; O g= /\\ CPM, x 9.82E-20 Ci hr min x'LR Ll. min sec ml cps 1 where: /1, CPM = reading f rom EMF 40 fl. min = the time interval for EMF 40'ob-servation(normally 15 mgnutes) 9.82E-20 = 4.0E-5 uCi/ cpm x .25 min /ft (inverseog/ml EMF flow rate) x 3.53E-5 ft x 1Ci/1E6uci x thr/3600sec. 4.OE-5 = correlation fac tor for EMF 40 from Reference 2.1. i LR = Leak rate, as determined in step. 4.3.1.1 above i 4.3.2.3 Based on PACS sample 1 O = PACS x CF x LR g wherel PACS = (uC1/ml) (Reference 2.4) ~ CF = 2.78E-10 Ci hr sec uti c j i l

j HP/0/B/1009/10 Page 6 LR = leak rate as determined i n; step 4.3.1.1 above 4.3.3 . Record O and O on Enc l osur e 5.1. NG g 4.4 Source Term Assessment - Uni t Vent (Enclosure 5.12) l 4.4.1 Determine the Noble Gas Release Rate, QNG(Ci/sec) based on one of the follwing methods; 4.4.1.1 Based on as EMF reading, wherei I Q = EMF x CF x CFM NG wherei EMF 36(L) if EMF 36(L) < 1E7 cpa, j = EMF = 36(H) if EMF 36(L) is offscale and EMF 36(H) > 100 cpm,, j EMF = 54 if EMF 36(H) is offscale, CF = the correc-tion f ac tor per Enc losure S.13 CFM = unit vent flow rate (ft / min) 4.4.1.2 Based on unit vent sample, wherel QNG = n en ample x CF x CFM wherel l Unit Vent Sample = (uti/ml) per reference 2.5 CF = 4.72E-4 Ci min _n1 sec f t

• uCi.

CFM = unit vent flow rate (ft / min) 4.4.2 Determine'the Iodine Release Rate, Oy(C1/sec), based on one of the following.methodst 4.4.2.1 Based on D I NG O g=ONG

• II*

where) l QNG = Noble Gas Release Rate as determined in step 4.4.1 above trat = ratio of 1131eqv./Xe133eqv. from.7. t s-4.4.2.2 Based on EMF 37f ,y 9 ____.m_ ______...-___m.._.

0 m HP/0/B/1009/18 Page 7 <~; /\\ CPM X 1.11E-13 Cl min _ min x CCM = 0 Limin sec ft" cpm where: /lCPM = reading from EMF 37 41 min = the time interval for EMF 37 ob-servation(normally.15 minutes)3 1.11E-13 = 4.0E-5.uCi / cpm x 0.1667 min /ft ( i nver se of. EMF f low ra te ) x 1Ci/1E6uCi x 1 min /60sec. ib -4 20E-5 = cor r ela tion f ac tor for EMF 37 f r.om Reference 2.1. 'l CFM'=. unit vent flow rate (ft / min) i 1 4,4.2.3 Dased on unit vent sample: G = Unit vent sample x 4.72E-4 Cl min ml x y 'CFM sec ft" uCi where i Unit vent sample = (uCi/ml) (Reference 2.5) 3 CFM = unit vent. flow rate (ft / min) ( 4.4.3 Record Q n nclosur 5.1. NG "" I 4.5 Dose Assessment (Enclosure 5.1) l 4.5.1 Determine the total Noble Gas and lodine Release Rates (TO an O) from'all releases.. < NG y 4.5.2 Determine the Projected Whole Body Dose Rate, DRwb ~ (rem /hr), due to noble gases for .5, 2, 5'and 10 miles: a l 3 DRwb:= 33.6 rem m TO"O x X/G hr Ci where: 33.6 is the adult whole body dose gonversion factor from Reference 2.9 in tem m hr Ci 4.5.3 Determine the Projected Whole. Body Dose, Dwb(rem), due to noble gases for .5, 2, 5 and'10 miles: Dwb = DRwb X 2 hr. where: dose is integrated over 2 hour time period 4.5.4 Determine the Projected Thyroid Dose Rate, DRct(rem /hr), due to lodine for .5, 2, 5 and 10 miless .r ? b_______________._______________m___

F .HP/0/B/1009/19 Page 8 ~a 'DRct X/O x TO x'2.26E6 rem m = y hr Ci where: 2.26E6 is 'the child thyroid dose cogversion f ac tor. f rom Ref er ence 2.13 i n rem m hr Ci 4.5.5 Determi ne. the Pro jec ted -Thyroid Dose, 'Dc t (rem), due to iodine for .5, 2, 5 and 10 miles: Det = DRet X 2 hr where: dose is integrated over 2. hour time period 4.6 Pro tec tive Ac t ion Recommenda t ions (Enclosure 5.14 ): 4.6.1 Record-the next sequential report' number. 4.6.2 Circle the PA2s and the' actions for the current'and, pre-vious protective action recommendations. 4.6.3 If the projected dose in a PA2 is < 1 rem whole body ,~ or < 5 rem thyroid, then recommend no protective action I (action A). s 4.6.4 If-the projected dose in a PA2 is 1 - 5 rem whole. body or 5 - 25 rem thyroid, then recommend evacuate. children and pregnant women and shelter others(action B and E). 4.6.5 If the' projected dose in a PAZ is > 5 rem whole body. or > 25 rem thyrold, then recommend evacuate everyone i (action C). 4.6.6 If the dose rate at the site boundary,is >= 5.0E-4 r'em/hr whole body, then recommend an Alert. j 4.6.7 If.the dose rate at the site boundary is->= .05 rem /hr whole body or >=.25 rem /hr thyroid, then recommend a Site Area Emergency if readings last 30 minutes. 4.6.8 If the dose rate at the site boundary is >= .5 rem /hr whole body or >= 2.5 rem /hr thyroid, then recommend 1a Site Area Emergency if readings last 2 minutes. 4.6.9 If the dose rate at the site boundary is >= 1 rem /br whole i. body or >= 5 rem /hr thyroid, then recommend a General' f Emergency. \\, J-___-__-_-_._-_-.-

s HP/0/3/1009/38 Page 9 tl'- 3.0 Enc l o su r e s 5.1 Sam;1e of Source Term and Dose Assessment Worksheet 5.2 Sample of Meteorolgy Worksheet 5.3-Two-hour Relative Concentration Factors'C") i 5.4 Pro t ec tive Ac tion Zones Determination 5.5 Sample of Source Ter m Assessment Steam Relief. Valves l 5.6 EMF 2 6, EMF 27, EMF 28, EMF 29 o r EMF 10, EMF 11. EMF 12, EMF 13 Noble Gas Correction Fac tor-5.7 1131 eqv. / X e 133eq v. Ratio 5.8 Sample of Source Term Assessment - Containment 5.9 Containment Noble Gas Correction Fac tor 5.10 Cont ainment Leakage Rate versus Pressure 5.11 Cont ainment Leakage Rate versus Pressure and Si ze. Opening 5.12 Samp le of Source Term Assessment - Uni t Vent 5.13 Unit Vent Noble Gas Correction Factor 5.14 Samp l e of Recommended Pro tec tive Ac t ion Repor t 1 1 i 1 i 'i a '~. ^ - ' -

DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 (.1 i Meteorology, source Term and Dose Assessment / ~ Unit Repor t (; Reactor Trip / Projec tion based on data on / (date/ time) (date/ time) Prepared By: t Meteorology Assessment b] Current b) Hypo the t i c a ) l Wind Speed mph Wind Direction degrees from North Temp er a ture Gr adi ent (lit ) C Stability Class A C D E F G Miles .5 1 2 4 5 7 8 PAZ AO B1 El Al C1 D1 F1 B2 A2 C2 D2 E2 F F3 A3 l Total Source Term Assessment Current b) Hypo the t i c a l Steam Relief Containment Unit Vent Total (Ci/sec) l Encl. 5.5 Encl. 5.8 Encl. 5.12 Ci/sec + Ci/sec + C1/sec = TD = gg Ci/sec + Ci/sec + Ci/sec = = TO g [~ lose Assessment fH X/O = WS <---< Adult whole body 2hr Child thyroid Dose = 2 x DRwb = 33.6 x TO X/0 x 6E6 = DRet x 2 = Dose 2hr (rem) (rem /hr) (Ci/sech N (sec/m3) (C1/sec) (rem /hr) (rem) 1 Distance miles = 2 x ___

33.6 x TONG x 2.26E6

x 2= =2 x_ = 33.6 x TO O I x 2.26E6 = NG 1 x 2= =2 x = 33.6 x TO S TO x 2.26E6 = NG g x 2= =2 x

33.6 x TO 10 TO x 2.26E6

NG g x 2= =2 x _= 33.6 x TO 1 TO x 2.26E6 = NG x 2= =2 x = 33.6 x TO 4 TO x 2.26E6 = _ x 2= NG =2 x = 33.6 x TO ? TO x 2.26E6 = NG x 2=__ =2 x = 33.6 x TO O NG TO x 2.26E6 = x 2= Field Data Adul t whole body Child thyroid Location Dose Rate Ehr Dose Location Dose Rate Ehr Dose rem /hr rem rem /hr rem i. b ) Emergency Drill

p 5: _; \\ 4, a .y' 'A .j,

DUKE POWER COMPANY' CATAWBA [ NUCLEAR' STAT 10N" n"

HP/0/B/1009/18- '~ 3 Enclosure.5.2 t ' ~l ' ' Meteorology i Unit' Reactor Trip / ~ ) .-: Report l (date/. time) ~ j l Prepared By: 1 L,, l-l. Wind speed mph Wind direction 'N /_lT 'C Default data wind speed _______ mph 1000 to wind direction 'N 1600 hrs, 1 stability class ___D___ h r wind speed _______ mph 1600 to wind direction 'N. -1000 hrs. i stability class' ___G___ i Note: If the wind speed or wind direction cannot be obtained from plant-systems, obtain them from the National Weather Service (704) 399-6000. If the NWS information is unavailable, then obtain' data from the MNS Control- 'om. =%,* A_____-________---_-_--__________E__-__--_-_--_-_-_-.._-..__-__- ---__-._---_-_________--_-_--.---_.i

3 7 7 6 6 5 5 5 E E E E E E 8 8 0 3 8 6 l 1 1 6 1 3 8 7 6 6 5 5 4 E E E E E E 7 9 4 3 6 3 2 1 1 7 1 4 1 7 6 6 5 5 4 E E E E E E 6 0 9 2 0 3 l 2 1 9 2 5 1 ) 7 6 5 5 5 4 g C E E E E E E ( ) 5 5 7 2 5 3 7 s s r e 2 2 1 2 6 1 o l t i D G c M 7 6 5 5 5 4 s s a ( s s F E E E E E E a a e 4 2 9 5 2 0 7 n c l l Y o n 3 3 1 3 8 2 C C N i a A 3. t t y y P a s 7 6 5 5 4 4 i i t t M 5 r i l l O t D E E E E E E i i m. C en 3 l re 3 5 2 7 7 b b R uc a a 4 6 2 5 1 2 t t E sn W oo S S O lC 7 5 5 5-4 4 e e P c ne E E- -E E E-s s E Ev 2 E U U 9 3 9 6 0 3 K i U t 5 1 4 9 2 4 D a le s s R r r 6 5 4 4 4 3 u u r o o E E E E E E h h u 1 o 2 5 4 5 l 1 h 0 0 1 4 1 2 5 1 0 0 -o 6 0 w 1 1 T 0 0 5 4 4 4 3-3 0 0 5 E E E-0 6 E E E 4 5 8 9 1 8 1 1 1 1 3 6 1 1

e y

s t u 1 e 1 e m M A C D E F G b l e a t l S iavan 6 5 2 4 2 u ) 0 0 0 O 1 is e C G G .s r ( u T T T T T T . AT t t A a n G f f G A A A< r e 6 5 2 4 2 f e i p d 0 0 0 0 1 -I m e + + a r T C E ) ) ) ) ) ) T 1 2 3 4 5 6 ON

DUXE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 j ls.4 j l Protective Ac t ion Zones Determina tion Determire the af fec ted zones (based on wind direction) from the table below Gnd record on Enclosure 5.1 1 l NOTE: If wind speed is less than or equal to 5 mph, the affected zones i for O - 5 miles shall be AO, A1,Bl iC1,D1,E t,F1

l l,

i al Wind Direction PA2's I (degrees from North) 0 - 5 miles 5 - 10 mi l es 0.1 - 22 AO.C1,D1, C2,02 j e t I l 22.1 - 73 AO,C1,D1,El C2, D2, E2, F 2 j i 73.1 - 108 AOiC1,DI,E1,F1 D2,E2i F2,F3 l 108.1 120 AO,01,E1,F1 D2, E 2, F2, F 3 120.1 - 159 AO,E1,F1 D2, E2,F2, F3, A2 ? 7 159.1 - 207 AO,E1,F1,Al l l-E2,FE iF3, A2,82 j 207.1 - 247 AO,F1,A1,81 F2,F3,A2,B2 l l 247.1 - 265 AO A1,B1 F3, A2, B2. A3, C2 l 265.1 - 298 AO,A1,81,C1 A2,B2,A3,C2 3 298.1 - 338 AO,B1,C1 B2,A3 C2,D2 338.1 360 AO,B1,C1,D1 B2,C2,02 l l l 1 ~ (

7. l DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 l-.5 Source Term Assessment Steam Relief Valves Reactor Trip / Projection based ~on data on / (date/ time) (date/ time) Calculations based on Melted Core LOCA j f NOBLE GAS I l based on EMF 26.or EMF 10 .SCgg R/hr X 1 X lbm X Ci = C_!, see Ibm R/hr sec (Enc l. 5.6) + based on EMF 27 or EMF 11 R/hr X 1 X lbm X Ci C, _i, = sec lbm R/hr .sec (Enc l. 5. 6 ) + based on EMF 28 or EMF 12 R/hr X 1 X lbm X ~Ci = C.J., sec lbm R/hr sec j (Encl. 5.6) j ,'-( .s s e d on EMF 29 or EMF 13 + R/hr X 1 X lbm X _ Ci

p_l,

= sec lbm R/hr sec (Enc 1, 5.6) Total from all Steam Relief Valves, O = NG. i/sec i TODINE From all Steam Relief valves O i y Q X 1131eqv./Xe133eqv. ratio = NG Ci/sec (Encl. 5.7) U Emergency Drill Prepared by: (.

-i-l I I I DUKE POWER-COMPANY CATAWBA NUCLEAR STATION l HP/0/B/1009/18 f.6 EMF 26, EMF 27 EMF 28, EMF 29 or EMF 10iEMF11, EMF 12, EMF 13 Noble Gas Correction Fac tor Time Since Trip (hrs) Correction Factor based on Mel ted Core or LOCA 1^ .3.622

• - 12 3.971 14 4.041 18 4.029-124 3.332 148 2.647 1100 2.438

.l 1250 2.438 1 1500 2.438 1720 2.438

• units in Cl

( lbm R/hr t ~.6 is the correlation factor per Reference 2.13 X g 2.83E4 ml3* I ft Ibm 1E6 ml .41 = specific gravity of steam per Reference 2.13 l l l i I l l l k,

I l' DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 ,.7 1131eqv./Xe133eqv. Ratio Time Since Trip (hrs) Ratio based on Ratio based on LOCA Melted Core (Column 1) (Column 2) 10 2.74E-3 2.24E-3 12 3.42E-3 9. 66 E - 3 l 14 3.82E-3 1.59E-2 le 4.34E-3 2.85E-2 lac 4.79E-3 7.52E-2 l 148 4.84E-3 1.11E-1 l 1100 5.06E-3 1'33E-1 1 >250 6.55E-3 1.80E-1 l l 1500 1.02E-2 2.90E-1 1720 1.44E-2 4.33E-1

• Enclosure 5.7 is from Reference 2.13

( ate: For unit vent releases in which Irat is utilized to determine 1-131 l' equiv. co nc en t r a t i on, apply the appropriate correction from the table below: l

1. L OCA, use column 1 (based on LOCA).

2. LOCA throuch charcoal filters, divide column 1 value by 100.

3. Core damace, use column 2 (based on Core Melt).

4. Core damace throuch charcoal filters, divide column 2 value by 100.

5. Tube ruoture, divide column i value by 1,000.

6. New fuel accident, divide column' 2 value by 600.

7. Old fuel accidente divide column 2 value by 600.

l

8. Gas decay tank, assume no radiciodine released, only noble gases are considered to be released from gas tank.

ll l '%.

lC DUKE POWER COMPANY l CATAWBA NUCLEAR STATION HP/0/B/1009/18 ..8 !,.g Source Term Assessment - Containment 1 Report # I Reactor Trip / Projection based on data on / (date/ time) (date/ time) Calculations based on _ Melted Core LOCA Containment pressure osig LR = ml/hr LR based on Realistic Leak Rate (Check one) i 1" 2" 4" 6" 8" 12" 18" 34" diameter opening j (circle one) Personnel Hatch opening Equipment Hatch opening l Design Leak Rate (2.449E6) NOBLE GAS based on (check one) EMF 39(L) EMF 39(H) EMF 53 b) if < 1E7 cpm b) if > 100 cpm if 39(H) is off scale' EMF CF LR ONG or X X ml/hr R/hr (Encl. 5.9) C1 = l [.. (See Note on Encl. 5.9) sec s based on PACS sangle 1 uCi/ml X 2.78E-10 Ci hr X ml/hr = Ci sec uCi sec IODINE based on NG O g _ Ci ? 1131eqv./Xe133eqv. = Ci sec based on ratio (Encl. 5.7) sec EMF 40 LR /\\ cpm X 9.82E-20 Ci he min X ml/hr = Ci /\\ min sec ml cpm sec based on PACS sample uCi/ml X 2.78E-10 Ci he X m./hr = Ci \\( sec uCi sec '(. b) Emergency b) Drill Prepared by: 1 I

0 d c / Fe i P Ms .T Ce H E a 00 00 00 00 00 s b 1 1 1 1 1 1 1 1 1 1 n i EE EE EE EE EE 1 4 06 55 55 55 s A 81 84 33 33 33 t C 7 1 7 4 33 33 33 i O n L 33 22 22 22 22 u la E r 1 o 1 t c 33 33 44 44 44 c r a e 1 1 1 1 1 1 1 1 1 1 e h F r s r / o EE EE EE EE EE n C 93 25 90 98 00 0 h R o 20 39 36 98 66 R 0 0 / i d 40 21 30 65 55 m 5 6 t e p Y 0 1 c t 1 1 1 1 76 55 55 c 5 e ) l r H n e 3 1 d r l 1 ( o M e d p Y a N o 9 h d a i C 3d 2 d r A 9 c e i a t P s Fs Ce e 0 MO 5 a Ma s c , 5 r C G Eb 44 44 44 44 44 n e t n 0 1 o e 1 1 1 1 1 1 1 1 1 1 i r s s c re Aul e p i i a A EE EE EE EE EE s f i e N' sb C 66 66 66 66 66 t e r g g r oo O 55 55 55 55 55 i R t n n l N L i c 55 55 55 55 55 u r r d d c n i i e E nt K E n e o a a n U e p t e e i 2 D c r r s n r a i o e 'B 8 s a t r 3 3 y t c 5 5 a n a e d o f c r r C n o o 2 n i L a o s A A 0 b i 3 3 w e a y o t s 5 5 m a r 77 77 77 77 88 l a f f r t o 1 1 1 1 1 1 1 1 1 1 e d I I F a C r C EE EE EE EE EE r 2 d 28 83 26 06 04 o e 74 51 15 94 39 m c r t 64 01 10 34 73 p e ) l c e t L n e 64 32 11 11 96 h f ( o M l t A 9 r a 3d h e s c i Fs i e Ma C 4 s 1 Eb A ' 6 88 88 88 88 9 1 1 11 1 1 1 1 n 5 2 i C ri EE EE EE EE e e O 4 4 44 44 44 44 s r c L 9 0 99 99 99 99 t u n ~ 30 33 33 33 33 i s e n o r 66 66 66 66 66 u l e c f n e E R -1 e) cs nr E i h T (, S( 00 00 O 48 05 02 N 02 4 [8 ir > [4 >1 2 1 2 5 [7 ep > [] mi ] TT

m-DUKE ' POWER l COf1PANY. CATAWBA' NUCLEAR STATION HP/0/B/1009/18 , ^*s.10 r. Containment Leakage Rate Versus. Pressure-PSIG ml/hr 10 2.330E4 12 3.175E4 14 5.821E4 18 9.779E4 .i 110 1.114E5 -111 1.164E5 112 1.199ES 113 1.235E5 114 1.260E5 115 1.285ES

• Enc losur e 5.10 fs the' realistic.' leakage rate (m /sec) per Reference 2.12 X 1E6 ml/m X 3600 sec/hr.. X 0.07 (0.07 per Reference 2.6).

I I 4 g 1 l t l ,m' l I

i DUKE POWER COMPANY CATAW8A NUCLEAR STATION HP/0/8/1009/18 fw.11 Containment Leakage Rate Versus Pressure and Si ze Openi ng l For 1" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr I >1.25 2.209E8 >5.0 3.908E8 >12.5 5.862E8 ) >2.50 2.889E8 >7.5 4.588E8 >15.0 6.287E8 l >3.75 3.483E8 >10.0 5.268E8 For 2" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr l l >1.25 8.496E8 >5.0 1.512E9 >12.5 2.243E9 0 >2.50 1.121E9 >7.5 1.784E9 >15.0 2.464E9 >3.75 1.342E9 >10.0 2.022E9 For 4" opening PSIG .ml/hr PSIG ml/hr PSIG ml/hr >1.25 3.144E9 >5.0 5.692E9 >12.5 8.496E9 >2.50 4.248E9 >7.5 6.797E9 >15.0 9.176E9 >3.75 5.098E9 >10.0 7.?31E9 For 6" opening q PSIG ml/hr PSIG ml/hr PSIG ml/hr j { >1.25 7.137E9 >5.0 1.291E10 >12.5 1.937E10 j >2.50 9.516E9 >7.5 1.529E10 >15.0 2.124E10 ) >3.75 1.138E10 >10.0 1.716E10 For 8" opening i PSIG ml/hr PSIG ml/hr PSIG ml/hr r >1.25 1.257E10 >5.0 2.243E10 >12.5 3.381E10 i I( >2.50 1.648E10 >?.5 2.634E10 >15.0 3.568E10 >3.75 1.971E10 >10.0 3.042E10 For 12" opening [ PSIG ml/hr PSIG ml/hr PSIG ml/hr >1.25 2.719E10 >5.0 5.012E10 >12.5 7.476E10 >2.50 3.738E10 >7.5 5.947E10 >15.0 8.156E10 >3,75 4.452E10 >10.0 6.712E10 For 18" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr >1.25 5.522E10 >5.0 1.003E11 >12.5 1.529E11 >2.50 7.476E10 >7.5 1.189E11 >15.0 1.665E11 >3.75 0.836E10 >10.0 1.351E11 For 34" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr >1.25 1.869E11 >5.0 3.398E11 >12.5 5.132E11 >2.50 2.583E11 >7.5 4.078E11 >15.0 5.607E11 >3.75 3.093E11 >10.0 4.588E11 For Personnel Hatch opening PSIG ml/hr PSIG ml/hr PSIG ml/hr >1.25 2.379E12 >5.0 4.690E12 >12.5 6.967E12 >2.50 3.390E12 >7.5 5.573E12 >15.0 7.646E12 >3.75 4.111E12 >10.0 6.372E12 For Equipment Hatch opening PSIG ml/hr PSIG ml/hr PSIG ml/hr ( (N- >1.25 1.121E13 >5.0 2.022E13 >12.5 3.059E13 >2.50 1.478E13 >7.5 2.379E13 >15.0 3.398E13 >3.75 1.767E13 >10.0 2.719E13 Y

• Enclosure 5.11 is the containment leakage for an gpening size let standard cubic feet per min (scfm) X 2.83E4 ml/ft X 60 min /hr.

DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1000/18.12 Source Term Assessment - Unit Vent Report # Reactor Trip / Projection based on data on / (date/ time) (date/ time) Calculations based _on Melted Core LOCA CFM e ft / min tiOBL E GAS based on (ceck one) EMF 36(L) EMF 36(H) EMF 54 b) if < IE7 com b) if > 100 com if 36(H)' is offscald EMF CF CFM Q_ Nu cpm or X X ft = R/hr (Encl. 5.13) C1 min sec I based on Unit Vent Sample _uCi/ml X 4.72E-4 Ci min ml X ft 3 i = sec ft" uCi C1 min (_ sec _ IODINE based on NG 1 Ci X Il31eqv./Xe133eqv. = Ci cec ratio (Encl. 5.6) based on sec EMF 37 CFM Licpm X 1.llE-13 Ci min min X ft = Ci /imin sec f t" cpm min sec based on Unit Vent Sample uCi/ml X 4.72E-4 Ci min,ml X ft 3 = Ci sec ft" uCi min sec b) Emergency b) Drill Prepared by: l i

/ 4 o nt 0 5 if / d P F e m e H M s i e E a Cs b 44 44 44 44 44 n i A EE EE EE EE EE l C 88 A8 88 88 88 s m D 55 55 55 55 55 t I 33 33 33 33 33 i m 6 n E 22 22 22 22 22 u I c n es i m 0 .6 ro t l c e m a r 77 77 77 88 88 4 F o E C EE EE EE EE EE 3 n 64 1 0 69 67 00 m 8 o d 20 93 4 2 78 44 p i e 47 00 20 64 44 c 2 t t c l 21 22 1 1 99 99 X e ) e Y r H n M nt i I 3 r ( o N o 6 m 1 A3 P1 C 3d c L e 2 e M.s F s C s O5 C a M a L n ce eG Eb 88 88 88 88 88 i n Rr e e E u A EE EE EE EE EE s r l f W s C 44 44 44 44 44 t e b O o h 44 44 44 44 44 i f o Pl I N n e c 99 99 99 99 99 u R E nt KE n r UD e e V p t r i o n t U ca a f b w n a e o t r 01 11 11 11 1l t i a o 11 11 11 11 1I a C C EE EE EE EE EE e l d 32 27 84 04 26 e r e 35 98 89 65 58 p r t 15 1 5 87 34 60 c o l c ) e 17 53 11 22 11 Ln M ( o nt e 6 if h 3d m t e c Fs ie s Cs i Ma 11 11 11 11 11 Eb 1 1 11 1 1 11 1 1 n 3 A i C EE EE EE EE EE 1 O 66 66 66 66 66 s 5 L 88 88 88 88 88 t 00 00 00 00 00 i e n r 11 11 11 11 11 u uso l 3 c e) n -r s nr cs E i h 00 00 S( 48 05 02 0 48 24 1 2 > [2 >1 >1 >1 5 [7 ep mi ir TT

DUXE POWER COMPANY CATAWBA NUCLEAR STATION 'N HP/0/B/1009/18 !.14 Recommended Protective Action Report j To: Emergency Coordinator t Report H ) The recommended protec t ive ac t ions for the public are: Current Miles PAZ Previous Actions Actions 05 AO A B C E A B C E i j 1 B1 El A B C E A B C E 2 Al C1 D1 F1 A B C E A B C E 4 82 A B C E A B C E i 5 A2 C2 D2 E2 F2 A B C E A B C E 7 F3 A B C E A B C E 8 A3 A B C E ,A B C E A - No protective action is recommended at this time. B - Remain indoors with windows closed, turn of f air condi tioners and other ventilation, monitor EBS stations. Control access. (Action E j I also). C - Evacuate all affected zones, seek designated shelter. l E - Pregnant women and children evacuate and

• - based on field data.

go to designated shelter. Emergency Classification based on Radioloolcal Data Recommend Alert Recommend Site Area Emergency if readings last 30 minutes b] Recommend Site Area Emergencyif readings last 2 minutes Recommend General Emergency Comments: / Dose Assessment Coordinator Date/ Time b) Emergency I l Drill i m.

D Fe,rm 34731.R9 86) (t) IO No.JP /0/A / 50H/02 { DUKE POWER COMPANY PROCEDURE PROCESS RECORD Change (s) o ,o 10 i PREPARATION loc 9erated Recype 4 ) '(2) STATION PATAURA MTfET V_AD 9TATTny L l (3) PROCEDURE TITLE NOTTTTCATTON OF INUSUAT. 7WNT } (4) PREPARED BY / W 42 MW _DATE / 'l / (5) REVIEWED BY-DATE. I~' N Cross. Disciplinary Review By 'N h?* N/R / / (6) TEMPORARY APPROVAL (if Necessary) By (SRO) OATE By DATE 1f30h (7) APPROVED BY - .__ D ATE (3) MISCELLANEOUS a 1 Reviewed / Approved By _DATE-1(. Reviewed / Approved By I DATE ) '" (9) COMMENTS (For procedure reissue indicate whether additional changes, other than pre i Attach additional pages,1f necessary.) ADDITIONAL CHANGES INCLUDEO. C Yes E!Jo (10) COMPAREO WITH CONTROL COPY .. D ATE \\ COMPLETION (11) DATE(S) PERFORMED l1 PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate? O Yes O N/A Listed enclosuret attached? O Yes O N/A Data sheets attached, completed, dated and signed? O Yes O N/A Charts, graphs, etc. attacned and properly dated, identified and marked? O Yes O N/A Acceptance criteria met? VERIFlED BY-DATE (13) PROCEDURE COM.*LETION APPROVED-DATE \\ (14) REMARKS (Attach additional pages,if necessary.)

j [ i RP/0/A/5000/02 /. DUKE POWER COMPANY CATAWBA NUCLEAR STATION NOTIFICATION OF UNUSUAL EVENT 1.0 SYMPTOMS j 1.1 This condition exists when events are in process or have occurred which indicate a potential degradation of the 'evel of safety of the plant. 2.0 IMMEDIATE ACTIONS I 2.1 Make initial notifications to individuals and organizations, i j 2.1.1 Complete Part I of Warning Message Form. (See example

.3.)

Record receivers name and time (initial contact). NOTE: Emergency Coordinator shall initial forms when message is approved for transmission. l i NOTE.: Warning Message Forms are kept in the Control Room l and TSC, ensure that all used forms are returned l to the back of the notebook. }, P' 2.1. 2 - Notifications shall be as the order of Enclosure 4.1 i s indicates. See RP/0/B/5000/13 for NRC Notification. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 2.2 Notify the Nuclear Production Duty Engineer using Enclosure 4.2. l 3.0. SUBSEQUENT ACTIONS 3.1 Assess the emergency condition, then remain in a Notification of Unusual Event, escalate to a more severe class or terminate the emergency. NOTE: When Terminating the Emergency use Parts 1 t, 3 of Warning Message Form. 3.2 Followup Notifications 3.2.1 See RP/0/A/5000/06, Follow-up Notifications l i. w___._.._.___.-_.--

E o. 4 t RP/0/A/5000/02 '

Page.2 of 2 N

3.3. - Augment shift resources to assess and respond to'the'. emergency , "w situation as neededc 3.4 The Compliance Engineer or delegate'shall follow up-with a written. summary to county and state authorities, notified in 4.1.3 of.1, within 24 hours. l 4.0 ENCLOSURES l 4.1 Telephone Notification List 4.2 . Emergency Message. Format 4.3' Example Warning Message: Nuclear. Facility to ' State / Local Government l- <Y s e f 4 u

7_ RP/0/A/5000/02 1 !.1 l Page' 1 of 2 TELEPHONE NOTIFICATION LIST y. l Initial 4.1.1 Station Man r - J. W. Hampton

• Conference Call Offic Home i

l i 1st Alternate - H. B. Barron oe 2nd' Altern - R. F. Wardell Offic Home' 3rd Alternat - G. - T. Smith Office Home l 4th Alternate - B. F. Caldwell l e 5th Alternat - T. E. Crawford Office r Home 4.1.2 Compilance En ineer - C. L. Hartzell

• Conference Call Offic Home o 1st Attorn

- D. P. Simpson Offic Hom 1 2nd Alternate - F. P. Schiffley Offic Home ~

• Conference Call Instructions 1.

Press and release the receiver button to put the first call on " hold". You will hear three beeps, then dial tone. ~~ 2. Dial the third person's number. You can talk before including the original-caller. 3. To begin the Conference call, press and release the receiver button. All three parties will be on the line. (if the line is busy or there's no answer, you can return to the original call by pressing and releasing the receiver button.) 4. All parties are disconnected when you hang up.

t RP/0/A/5000/02

• .1

Page 2 of 2 TELEPHONE -d G

s NOTIFICATION IST ' I 4.1.3 State t, County Warning Points **Use Warning Message Form ** GROUP CALL i 1. Mecklenburg, County l 9, " * ' ., h

,. r{

w u Back-up: Emergency Radio, Code: 's .j. 2. York County ) P: Selective Signal - 1 A: M-Back-up: Emergency Radio, Code:. 3. Gaston County P: Selective Signal A M: Back-up: Emerge'ncy Radio, Code l 4. N.C. State, Ralelyh A td "1 o 5. S.C. State, Columbi ( snal - 4.1.4 Operations Dut Engineer - Plant Page A: See current Operations Work List for Home Phone Number. 4.1.5 Nuclear Production 0 E Mobile Ph

• • USE EN LOSURE 4.2 **

l NRC Operations Center, Bethesda, Mf. (Rh0/B/5000/13) 4.1.6 i t i

I RP/0/A/5000/02 ' { Enclosura 4.2 Paga 1 of 1 i DUKE POWER COMPANY m CATAWBA NUCLEAR STATION i TO NUCLEAR PRODUCTION DUTY ENGINEER l EMERGENCY MESSAGE FORMAT l ) 1. This is at Catawba Nuclear Station. j (Name and Title) ? 2. This is is not a drill. An X Unusual Event ~ Alert i Site Area Emergency i General Emergency { was declared by the Emergency Coordinator at_ _ on Unit # l (Time) 3. Initiating. Condithn: (Give as close to the emergency plan description as possible together with station pa-ameters used to determine emergency status.) I l 4. Corrective measures being taken: (' i l i 5. There _ have have not not been any injuries to plant personnel. 3 j 6. Release of radioactivity: Is taking place is not taking place 7. NRC Yes No; State Yes No; Counties Yes No; have been notified. .q 8. The Crisis Management Team should X should not be activated. Corporate Communications and Company Management should be notified. i Ensure that Corporate Communications sends a copy of any News Release, to I Control Room. ) 1 l 9. I can be reached at _ for follow-up information. l (Telephone Number) 10. Additional Comments: i i i l, Name of Person Contacted Date Time i

[ 1 I. RP/0/A/5000/02 l PART 1 INITIAL WARNING MESSAGE Enlosura 4.3 l Pagd 1 of 4 1. Date: Time: hours 2. This is: Catawba _ Nuclear Station concerning Unit # t My name is: _ Telephone: { this message (Number ): j (a) Reports a real emergency, t (b) Reports the change in the class of a real emergency. (c) Reports the termination of a real emergency. I (d) is an exercise message, f 3. Messago Authentication Message Sender: I authenticate as (a) IF A TERMINATION MESSAGE. GO TO PART 3. 4. The class of emergency is: i X (a) Unusual Event (c) Site Area Emergency I (b) Alert (d) General Emergency f 5. This class of emergency was declared at: on (time) (date) 6. The initiating event causing the emergency classification is: { } l ,e !( 7. The emergency condition: I i (a) Does not involve the release of radioactive material from the plant. i 'l (b) Involves the potential for a release, but no release is l l occuring. (c) involves the release of radioactive materials. i 8. The following protective actions are recommended \\ X (a) No protective action is recommended at this time. 1 (e) Other recommendations: t 9. I repeat, this message: (a) Reports a real emergency. (b) Reports a change in the classification of a real emergency. (c) is an exercise message. l 10. Do you have any questions? (Copy on separate sheet.) j 11. RELAY THIS INFORMATION TO THE PERSONS LISTED IN YOUR ALERT PROCEDURES WHO MUST BE NOTIFIED OF INCIDENTS AT A NUCLEAR l FACILITY. l,

• For Message sender:

record names of Message Receivers on Page 4 ] l v END OF PART 1 I l I i i

RP/0/A/5000/02 PART 2 FOLLOW-UP MESSAGE (S) Encleaure 4.3 Page 2 of 4 j 1. Plant status: O. Reactor (a) is not tripped / was tripped ai: (Time): Plant is at: (a) % power (c) hot shutdown (b) cold shutdown (d) cooling down Prognosis is: (a) stable (c) degrading (b) Improving (d) unknown I l 2. Emergency actions underway at the facility include: 3. Onsite support needed from offsite organizations: j ( 4. Dose Projection Data Windspeed: mph Wind direction: From i Precipation: Release Type: (a) Ground /(b) Elevated Stability Class: ( A, B, C, D, E, F,or G) { Weighted dose Conversion Factor: (a) (R/hr)/(Ci/m')(whole body) { (b) (R/hr)/(Ci/m )(Child Thyr,oid) j 8 Radiological Release: Noble Gas Equivalent Xe-133 & 1-131 l curies /sec. i ( lodine Equivalent j curies /sec. 5. The type of actual or pro,' >cted release is: i (a) Airborne (b) Waterborne I (c) Surface Spill (d) Other (e) No release is in progress or expected at this time j (Skip Items 6, 7 & 8) am 6. Release (a) will begin at

hours, i

(b) began at hou rs. I i 7. The estimated duration of the release is hours. 8. The source and description of the release is: j l 1 1 i!L l 1 i i

[ R P/0/ A/5000/02 D' PART 2 FOLLOW-UP MESSAGE (S) Continued Enclosure 4.3 Pago 3 of 4 9.' Dose Projections: ' ' '~. Dose Commitment Projected Integrated Dose in Rem Based on hou rs of release Whole Body Child Thyroid Distance (rem / hour)(Rem / Hour of inhalation) Whole Body Child Thyroid Site Boundary i 2 miles 5 miles l 10 miles 10. Field measurement of dose erste (mr/hr) or contamination (X) (if available): Time Zone - Distance f rom Direction from Whole Body Child Thyroid, plant Plant 1 i b 1 1 k 11. I repeat, this message: l (a) Reports a real emergency. (b) Reports a change in the class of a real emergency. l (c) is an exercise message. ~ 12. Do you have any questions? (Copy on Separate Sheet)

• • • • • EN D O F FO L LOW-U P M E S S A G E ( S ) *****
• For Message Sender:

Record names of Message Receivers ' n Page 4. o PART 3 TERMINATION MESSAGE 1. The event was terminated at on (time) (date) 2. The event at the plant.was terminated for the following reason (s): l - a ^END OF TERMINATION ' MESSAGE **"* l/(,

• For Message Sender:

record names of Message Receivers on Page 4_. l i

[ .j RP/0/A/5000/02. .< 1-WARNING POINTS ALERTED Enclosura 4.3 . Page 4 of 4 h (name)

l. (title)

^ s <1 (date) (time),, (warning point) 2. ~ (name) >I (title) t 4 (date) . (time) (warning point) 3. (name) (title) 1 v. ~ (date) (time) (warning point) 4.

t 4

.(name) (title) (date) (time) (warning point) 5. (name) ~ (title) '/ \\ (date) (time) -3 (warning point)_ l 6. l (name) 1 l (title) (date) (time) -(warning point) 7. -( nan 1e) ~ ~~ (title) (date) (time) (warning point)

• • • • • FOR UTILITY USE ONLY*****

Release of this message approved by: at: (Name) (Time) (Date) + l I w/ I 5 m--

m ' Form 34731 (R9 86) (1) 10 No. RP/0/AQOgf DUXE POWER COMPANY 9 Change (s) .:o j PROCEDURE PROCESS RECORD 10 incorporated PR EPAR ATION Retype 4 { (2) STATION FATAW A M FAR 9T ATTM (3) PROCEDURE TITLE M.ERT 1 l (4) PREPARED BY Wb DATE 7'A 87 i (5) REVIEWED 8Y DATE 7*70' Cross Disciplinary Review By __N/R / j (6) TEMPORARY APPROVAL (if Necessary) By (SRO) DATE By DATE '7f30]8') (7) APPROVED BY DATE (8) MISCELLANEOUS Reviewed / Approved By DATE Reviewed / Approved By DATE g. (' (9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously approved changes, are inc Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. O Yes RNo (10) COMPARED WITH CONTROL COPY DATE COMPLETION j (11) D ATE (S) PE R FORMED (12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate? O Yes O N/A Listed enclosures attached? O Yes O N/A Data sheets attached, completed, dated and signed? O Yes O N/A Charts, graphs, etc. ateached and properly dated, identified and marked? O Yes O N/A Acceptance criteria met? VERIFIED BY _DATE (13) PROCEDURE COMPLETION APPROVED DATE ! 'I (14) REMARKS (Attach additional pages,if necessary.) .tr I !L______._.________._____..__...

n j RP/0/A/5000/03 i i l DUKE POWER COMPANY CATAWBA NUCLEAR STATION ALERT 1.0 SYMPTOMS 1.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. 2.0 IMMEDIATE ACTIONS 2.1 Make initial notifications to individuals and organizations. 2.1.1 Complete Part I of Warning Message Form (see example l.3), Record receiver's name and time l (initial contact). NOTE: Emergency Coordinator shall initial forms when message is approved for transmission. I NOTE: Warning Message forms are kept in a Notebook in the Control Room and TSC, ensure that all used forms - are returned to the back of the notebook. 2.1.2 Notifications shall be as the order of Enclosure 4.1 indicates. See RP/0/B/5000/13 for NRC Notification. ( NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 2.1.3 Advise station personnel to activate TSC and OSC. 2.1.4 Complete Enclosure 4.2 and advise the Nuclear Production Duty Engineer to bring the CMC to standby. 3.0 SUBSEQUENT ACTIONS 3.1 Accident Assessment: 3.1.1 Dispatch on site monitoring teams with associated communications equipment, see HP/0/B/1009/09. 3.2 Follow up Notifications. 3.2.1 See RP/0/A/5000/06, Follow-up Notifications. 3.3 Recommend Protective Action Offsite NOTE Protective Action Recommendations are obtained from: OAC Program " Nuclear-23" or RP/0/A/5000/11, if the OAC is not operational, for Operations Personnel, if you have determined the l 's need for the offsite protective actions, then reasses the emergency classification. You are no longer in an Alert situation. l

.- q [ n. 7, RP/0/AI5000/03 3 x Pags 2 of 2,. i 3.4 If the emergency situation is rapidly degrading then conduct a Site 1 n Assembly, see RP/0/A/5000/10. -{ 3.5 Augment shift resources:to assess and respond to the emergency-situation as needed. ~ 3.6 Armounce over the plant PA system the current emergency classification-level and summary of plant status. 3.7 Assess the emergency condition,; then remain in an Alert, escalate to a more severe class, reduce the Emergency Class or terminate:the emergency. Make an announcement over the plant PA system anytime emergency classification level changes. Include summary. I of plant status. 3.8 The Compliance Engineer or ' delegate shill close out the em'ergency with verbal. summary to' county and state authorities, notified in 4.1.3 of Enclosure 4.1, followed by written summary within 8 hours. 4.0 ENCLOSURES 4.1 Telephone Notification Ust-i 4.2 Emergency Message Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government ( b b ? l e I Li

o RP/0/A/5000/03 ,.1' Page.1 of 2 TELEPHONE NOTIFICATION LIST ~' Initial 4.1.1 Station' Man er - J. W. Hampton

• Conference Call Office Home -

1st Alterna . Barron. - Offic Home l 2nd Alterna ' - . F. Wardell Offic Home 3rd Alternate - G'. 'T. Smith l e e 4th ' Alternate - B. F. Caldwell e Sth Alternate - T. E. Crawford i o e 4.1.2 Compilance ' eer - C. L. Hartzell

• Conference Call Offic Home 1st Alternat

. Simpson Office Home 2nd Alterna - F P. Schiffley Office Home

• Conference Call Instructions only) 1.

Press and release the receiver button to put the first call on " hold". You will hear three beeps, then dial tone. 2. Dial the third person's number. caller. You can' talk before including the original 3. To begin the Conference call, press and release the receiver button. three parties will be on the line. All (if the line is busy or there's no answer, you can return to the original call by pressing and releasing the receiver button. ) 4. All parties are disconnected when you hang up. (.

!.1 a Page 2 of 2. 4.1.3 State L County Warning P_oints **Use. Warning % ~ M / _, GROUP CALL 1. Mecklenburg Count l P: ' e Signal ) l A Bac -up: Emergency Radio, Code: j 2. York County P Signal - l A Back-mergency Radio, Code: 3 3. Gaston Countyr P: Selective Signal gency Radio, Cod N.'C. Sth' e, Raleigh 4. ~ t 5. S.C. State, Columbia l l 4.1.4 Oper Page {( A: See Current Operations Work List for Home Phone. Number. { 4.1.5' Nuclear Production Dut E nee Mobile Phon i )

• • USE ENCLOSURE 4.2 l

4.1.6 NRC Operations Center, = Bethesda, Md. (RP/0/B/5000/13) m* 4

RP/0/A/5000/03 Enclosuro 4.2 Page 1 of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION TO NUCLEAR ~ PRODUCTION DUTY ENGINEER i EMERGENCY MESSAGE FORMAT 1. This is at Catawba Nuclear Station. -) (Name and Title) 2. This is is not a drill. An Unusual Event X Alert l Site Area Emergency i General Emergency was declared by the Emergency Coordinator at o n U n i t # _,,_,. (Time) 3. Initiating Condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status.) 4. Ccrrective measures being taken: 1 s, ( 5. There have have not not been any injuries to plant personnel. l B. Release of radioactivity: Is taking place ( 1 is not taking piace 7. NRC Yes No; State Yes No; Counties Yes No; have been notified. 8. The Crisis Management Team _ X should be told to standby. t Corporate Communications and Company Management should be notified. Ensure that Corporate Communications sends a copy of any News Release, to Control Room. 9. I can be reached at for follow-up information, (Telephone Number) 10. Additional Comments: Name of Person Contacted Date Time C e (

PART 1 INITIAL WARNING MESSAGE Enlosure 4.3 l Paga 1 of 4 1. Dato: Time: _, hou rs 2. This is: Catawba Nuclear Station concerning Unit # My name is: . Telephon e: l this message (Number ): (a) Reports a real emergency. (b) Reports the changs in the class of a real emergency. (c) Reports the termination of a real emergency. l (d) is an exercise message. 3. Message Authentication Message Sender: I authenticate as (a) IF A TERMINATION MESSAGE. GO TO PART 3. 4. The class of emergency is: (a) Unusual Event (c) Site Area Emergency X (b) Alert (d) General Emergency 5. This class of emergency was declared at: on (time) (date) 6. The initiating event causing the emergency classification is: [ 7. The emergency condition: l' (a) Does not involve the release of radioactive material from the plant. _ (b) Involves the potential for a release, but no release is occu rin g. _ (c) Involves the release of radioactive materials. 8. The following protective actions are recommended-(a) No protective action is recommended at this time. (e) Other recommendations: 9. I repeat, this message: (a) Reports a real emergency. (b) Reports a change in the classification of a real emergency. l (c) is an exercise message. 10. Do you have any questions? (Copy on separate sheet.) 11. RELAY THIS INFORMATION TO THE PERSONS LISTED IN YOUR ALERT PROCEDURES WHO MUST BE NOTIFIED OF INCIDENTS AT A NUCLEAR q 4 FACILITY. QFor Message sender: record names of Message Receivers on Page 4. '( END OF pART 1 l t l t_____________-_--__-------------

RP/0/A/5000/03 l PART 2 FOLLOW-UP MESSAGE (S).3 f 1. Plant status: -Pags 2 of 4 i a Reactor (a) is not tripped / was tripped at (Time): i Plant is at: (a) % power (c) hot shutdown (b) cold shutdown (d) cooling down Prognosis is: (a) stable (c) degrading (b) Improving (d) unknown 2. Emergency actions underway at the facility include: 3. Onsite support needed from offsite organizations: 4. Dose Projection Data i Windspeed: . mph Wind direction: From __ Precipation: a Release Type: (a) G round/(b) Elevated ~ Stability Class: ( A, B, C, D, E, F,or G) Weighted dose Conversion Factor: (a) (R/hr)/(Cl/m*)(whole body) (b) (R/hr)/(Ci/m*)(Child Thyroid), - 1 Radiological Release: Noble Gas Equivalent Xe-133 & l-131 curies /sec. lodine Equivalent (~ curies /sec. (. 5. The type of actual or projected release is: l (a) Airborne (b) Waterborne (c) Surface Spill (d) Other (e) No release is in progress or expected at this _ time (Skip Items 6, 7 & 8) 6. Release (a) will begin at hours. (b) began at hours. 7. The estimated duration of the release is hou rs. 8. The source and description of the release is: ( er

RP/0/A/5000/03 PART 2 FOLLOW-UP MESSAGE (S) Continusd Enclosure 4 3 9, Dose Projtetions: Page 3 of 4 Dose Commitment Projected integrated i Dose in Rem Based on hours { l of release Whole Body Child Thyroid, i Distance (rem / hour)(Rem / Hour of inhalation) Whole Body Child Thyroid I Site Boundary t i 2 miles I 5 miles i 10 miles 10. Field measurement of dose rate (mr/hr) or contamination (X) '(if available): Time. Zone Distance from Direction from Whole Body Child Thyroid Plant - Plant 11. I repeat, this message: (a) Reports a real emergency. (b) Reports a change in the class of a real emergency. (c) is an exercise message. 12. Do you have any questions? (Copy on separate Sheet)-

• • • • • E N D O F FO L LOW-U P M E S S A G E ( S ) *****
• For Message Sender:

Record names of Message Receivers on Page 4. l i PART 3 TERMINAT-lON MESSAGE 1. The event was terminated at on (time) (date) 2. The event at the plant was terminated for the following reason (s): t

• • • • • END OF TERMINATION MESSAGE *****

eb

• Fo'r Message Sender:

record names of Message Receivers on Page 4. L

p RP/0/A/5000/03 ' WARNING POINTS ALERTED.3 1 Paga 4. of 4 l 1. l (name) (title) (date) (time) (warning point) 2. (name) (title) i (date) (time) (warning point) 3.' (name) (title) (date) (time) (warning point) 4. (name) i (title) l l (date) (time) (warning point) I 5. \\ 1 (name) (title) t ( (date) (time) I ( (warning point) 6. (name) . (title) l (date) (time) (warning point) 7. (name) (title) (date) (time) (warning - point)

• • • • • FO R U TI LI TY U S E O N LY*****

Release of this message approved by: s at: (Name) (Time) (Date) l l s I ( $ ee

L Form 34731 (R9 AS) -(1) 10 No. RP/0/A/5000_/& DUKE POWER COMPANY Changels) 9 PROCEDURE PROCESS RECORD ~to 't blncorporated P_R EPAR ATION Recypt 4 (. ,( (3) STATION cATAun A wmAn <TATTrw (3) PROCEDURE TITLE SITE AREA EMRGENCY Il l (4) PREPARED BY-W WW DATE M ~2 M (5) REVIEWED BY-o OATE l Cross. Disciplinary Review By-I )-I' O e N/R / / l (6) TEMPORARY APPROVAL (if Necessary) l OY (SRO) DATE By DATE (7) APPROVED BY h _. D ATE (8) MISCELLANEOUS Reviewed / Approved By DATE Reviewed / Approved By F DATE (9) COMMENTS (For procedure reissue indicate whether Additional changes,other than previously appro Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. Oyes GNo (10) COMPARED WITH CONTROL COPY DATE-COMPLETION (11) DATE(S) PERFORMND (92) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as approp J O Yes O N/A Usted enclosures attached? O Yes O N/A Data sheets attached, completed, dated and signed? Oyes O N/A Charts, graphs, etc. attached and properly datec', identified and marked? O Yes O N/A Acceptance criteria met? I s VERIFIED BY _DATE (13) PROCEDURE COMPLETION APPROVED-DATE i 116) REMARKS (Attach additional pages,if necessary.) k L_____________._ .i_ -<

Q RP/0/A/5000/04 DUKE POWER COMPANY CATAWBA NUCLEAR STATION SITE AREA EMERGENCY 1.0 SYMPTOMS t 1.1 Events are in process or have occurred which involve an actual or tikely major failures of plant functions needed for protection of the public. 2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to individuals and organizations. 2.1.1 Complete Part I of Warning Message Form (see Example.3). Record receiver's name and time (initial contact). NOTE: Emergency Coordinator shall initial forms wh'en message is approved for transmission. NOTE: Warning Message forms are kept in a notebook in the Control Room and TSC, ensure that all used forms I are returned to the 'back of the notebook. 2.1.2 Notifications shall be as the order of Enclosure 4.1 indicates. See RP/0/B/5000/13 for NRC Notification. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 2.1.3 Advise station personnel to activate TSC and OSC. 2.1.4 Complete Enclosure 4.2 and advise the Nuclear Production Duty Engineer to activate the CMC. 2.2 Protective Action Offsite 2.2.1 Recommend to Offsite Agencies that the Alerting Sirens be sounded and that the EBS be activated to inform the public of a potential for later protective actions. 2.3 Protective Action Onsite 2.3.1 Conduct a Site Assembly, see RP/0/A/5000/10. /

p R P/0/A/5000/04 3 Paga 2 of 4 I l l 3.0 SUBSEQUENT ACTIONS I 4 3.1 Accident Assessment: I 3.1.1 Dispatch field monitoring teams with associated communications equipment, see HP/0/8/1009/04. 3.2 Follow up Notifications. 3.2.1 See RP/0/A/5000/06, Follow-up Notifications. l t j 3.3 Follow-up Recommend Protective Action Offsite NOTE l Protective Action Recommendations are obtained from: OAC l Program " Nuclear-23" or RP/0/A/5000/11, if the OAC is not available, for Operations personnel. i 3.3.1 The Emergency Coordinator shall make Protective Action Recommendations to the affected county warning points and to both SC and NC state warning points (Emergency Operations Center if established) or the designated state department as per the state's Radiological Emergency Response Plan. See Enclosure 4.4 for aid in protective action decision making. NOTE This authority shall not be delegated to other elements of the emergency organization. 3.3.2 If actual release of radioactive material will result in a projected dose to the population of: EPA Protective Action Guides Whole Body Thyroid Recommendation <1 Rem <5 Rem No Protective Action is Required. 1 to <5 Rem 5 to <25 Rem Recommend seeking shelter and wait for further instruction. Consider evacuation particularly for children & pregnant women. Control access to affected areas. > 5 Rem > 25 Rem Recommend mandatory evacuation of population in the affected areas. Control access to affected areas. b r

RP/0/A/5000/04 l Pass 3 of 4 ) NOTE i Monitor environmental radiation levels to verify and adjust recommendations as necessary. 3.4 Follow-up Protective Actions On-site. 3.4.1 Consider evacuation of nonessential station pe sonnel, see RP/0/A/5000/10. 3.4.2 Emergency Worker Exposure Limits Skin of W.B. orl Activity Extrerrities (Rem) Whole Body (Rem) Thyroid (RemTl 1 \\ Normal Dose Limit 75 5 30 Emergencies (a) 75 25 125 Lifesaving Activities (a)(b) 375 75 150(c) (a) Appropriate controls of emergency workers, include: time limitations, respirators and Potassium lodide (KI) - See . H P/0/ B/1009/16. The Emergency Coordinator may authorize doses to these limits. (b) Volunteers only. ,e*' i i. (c) Although respirators and Potassium lodide should be used j where effective for emergency team work, Thyroid dose may not be a limiting factor for lifesaving missions. 3.5 Augment shift resources to assess and respond to the emergency situation as needed. 3.6 Announce over the plant PA system the current emergency classification level and summary of plant status. 3.7 Assess the emergency condition, then remain in a Site Area Emergency, escalate to a more severe class, reduce the emergency class, or terminate the emergency. Make an announcement over the plant PA system anytime emergency classification level changes. Include summary of plant status. 3.8 The Recovery Manager at the Crisis Management Center shall close out or recommend reduction of the emergency class, by briefing l of offsite authorities at the Crisis Management Center or by j phone if necessary, followed by written summary within 8 hours. 4.0 ENCLOSURES 4.1 Telephone Notification List 4.2 Emergency Message Format g lV l l r w_____________________--

RP/0/A/5000/04 Pago 4 of 4 4.3 Example Warning Message: Nuclear Facilit9 to State / Local l Government \\ 4,4 Protective Action Recommendation Flow Chart i i s 4.5 10 Mile Emergency Planning Zone (EPZ) Map and Wind Direction Determination Worksheet. a l l i e 2 I (' i s 1 I ) i I I l l 1 i j 1 i i h I 1 l l e i

-~ i RP/0/A/5000/04 -.1 l Page 1 of 2 TELEPHONE NOTIFICATION LIST .s 3 Initial 4.1.1 Station M - J. W. Hampton

• Conference Call Offic Home i

1st Alternate - H. B. Barron. I e / 2nd Altern . F. Wardell Offic i, Home 3rd Alter - G. T. Smith Offic Home 4th Alternate - B. F. Caldwell e 5th Alternate T. E. Crawford e I' 4.1.2 Compliance r - C. L. Hartzell

• Conference ' Call I

Office Home i l 1st Alternat - D. P. Simpson i Office Home l j i 2nd Alterna F. P. Schiffley l Offic Hom j

• Conference Call Instructions nly) l 1.

Press and release the receiver button to put the first call on hold". i You will hear three beeps, then dial tone.

i i

i 2. Dlal the third person's number. You can talk before including the original 'l caller. i 3. To begin the Conference call, press and release the receiver button. All three parties will be on the line. (If the line is busy or there's no answer, you can return to the original call by pressing and releasing the receiver button.) 4. All parties are disconnected when you hang up. l i 1 l l 4

RP/0/A/5000/04 l

• .1 Page 2 of 2 i

4.1.3 State & County Warning Points **Use Warning sage Form ** l GROUP CALL 1. Mecklenburg Courty q gnal - Back-up: Emergency Radio, Code 2. York County P: Selective Signal A h: I Back-up: Emergency Radio, Cod 3. Gaston County gnal Back-up: Emeisency Radio, Co 4. N.C. ~ State, Raleigh 5. S.C. State, Columbia 1 4.1.4 ( Operations Duty Engineer - Plant Page Mh A: See Current Operat.ons Work List for Home Phone Number. 4.1.5 Nuclear Production Dut En E Mobile Phone

• • USE ENCL 4.1.6 NRC Oper.ations Center, Bethesda, Md._ (RP/0/B/5000/13) i e

a W/ 6 8

ENCLOSURE 4.2 PAGEl'OF'1 DUKE POWER COMPANY i CATAWBA NUCLEAR STATION. 1 'N TO NUCLEAR PRODUCTION DUTY. ENGINEER l EMERGENCY MESSAGE FORMAT 1. This is at Catawba Nuclear Station. (Name and Title) l 2. This is is not a drill. An Unusual Event l Alert l X Site Area Emergency General Emergency ] was declared by the Emergency Coordinator at on Unit # (Time) 3. Initiating Condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emerge,ncy status.) 1 j l l l 4. Corrective measures being taken: I 5. There have have not been any injuries to plant personnel. 6. Release of radioactivity: is taking place is not taking place 7. NRC Yes No; State Yes No Counties Yes No; have been notified. 8. The Crists Management Team X should should not be activated. Corporate Communications r, Company Management should be notified. Ensure. l that Corporate Communications sends a copy of any News Release.to Control Room. 9. I can be reached at for follow-up information. (Telephone Number) 10. Additional Comments: ~ Name of Person Contacted Date Time ( m e

[ RP/0/A/5000/04 PART 1 INITIAL WARNING MESSAGE Enlosura 4.3 Page 1 of 4 1. Data: Time: hours 2. This is: Catawba Nuclear Station concerning Unit # o My name is: Telephone: this message (Number ): (a) Reports a real emergency. (b) Reports the change in the class of a real emergency. (c) Reports the termination of a real emergency. (d) is an exercise mescage. 3. Message Authentication j Message Sender: I authenticate as I (a) IF A TERMINATION MESSAGE. GO TO PART 3. 4. The class of emergency is: l (a) Unusual Event X (c) Site Area Emergency (b) Alert (d) General Emergency f 5. This class.of emergency was declared at: on _ (time) (date) 6. The initiating event causing the emergency classification is: ] l 7. The emergency condition: (a) Does not involve the release of radioactive material l from the plant. 1 i( (b) Involves the potential for a release, but no release is l occu ri n g. (c) Involves the release of radioactive materials. 8. The following protective actions are recommended: I (a) No protective action is recommended at this time. l 1 (b) People living in zones remain indoors with the doors and windows closed, turn off air conditioners and other ventilation, monitor EBS stations. (c) People living in zones evacuato thier homes and businesses and go to the designated shelter. (d) Pregnant women and children in zones remain indoors with the doors and windows closed, turn off air conditioners and other ventilation, and monitor. EBS stations. X (e) Other recommendations: Activate the alerting siren system and inform the public via the Emergency Broadcast System. 9. I repeat, this message: (a) Reports a real emergency. ~ (b) Reports a change in the classification of a real emergency. (c) is.an exercise message. 10. Do you have any questions? (Copy on separate sheet.) 1 11. RELAY THIS INFORMATION TO THE PERSONS LISTED IN YOUR ALERT PROCEDURES WHO MUST BE NOTIFIED OF INCIDENTS AT A NUCLEAR FACILITY.

• For Message sender:

record riames of Message Receivers on Page 4. END OF PART 1 I

RP/0/A/5000/04 PART 2 FOLLOW-UP MESSAGE (S).3 Page 2 of 4 1. Plent status: Reactor (a) 'is not tripped / was tripped at (Time): Plant is at: (a) % power (c) hot shutdown (b) cold shutdown (d) cooling down Prognosis is: (a) stable (c) degrading (b) Improving (d) unknown l 2. Emergency actions underway at the facility include: ) 3. Onsite support needed from offsite organizations: ) l 4. Dose Projectio'n Data Windspeed: mph Wind direction: From Precipation: Release Type: (a) 'G round/(b) Elevated J Stability Class: ( A, B, C,0, E, F,or G) -i Weighted dose Conversion Factor: (a) (R/hr)/(Ci/m*)(whole body) (b) (R/hr)/(Ci/m*)(Child Thygoid) I Radiological Release: Noble Gas Equivalent curies /sec. 7 lodine Equivalent H curies /sec. 1 [' 5. The type of actual or projected release is: (a) Airborne (b) Waterborne ] (c) Surface Spill (d) Other I (e) No release is.in progress or expected at' this time (Skip items 6, 7 2 f, 8) 6. Release will begin at

hours, began at hours.

l 7. The estimated duration of the release is hours. 8. The source and description of the release is: l L __-____..--__n__.

r RP/0/A/5000/04 PART 2 FOLLOW-UP MESSAGE (S) Continusd Enclosure 4.3 Page 3 of 4 i 9. Doso Projections: , Dose Commitment Projected Integrated i[ Dose in Rem Based on hours of release Whole Body Child Thyroid Distance (rem / hour)(Rem / Hour of inhalation) Whole Body Child Thyroid Site Boundary i 2 miles I 5 miles 10 miles 10. Field measurement of dose rate (mr/hr) or contamination (X) ] (if available): / Time Zone Distance from Direction from Whole Body Child Thyroid l Plant Plant p e 1 j N. j ? 11. I repeat, this mesr e: i (a) Ror.

s a real emergency.

l (b) Repo. s a change in the class of a real emergency. .l (c) is an exercise message, i 1 12. Do you have any questions? (Copy on separate Sheet) j ( \\ l

• • • • • EN D O F FO L LOW-U P M E S S A G E ( S ) *****

I

• For Message Sender:

Record names of Message Receivers on Page 4 PART 3 TERMINATION MESSAGE I 1. The event was terminated at on 1 (time) (date) 2. The event at the plant was terminated for the following reason (s):

• • • • • E N D O F T E R M I N A T I O N ME S S A G E*****

i L(

• For Message Sender:

record names of Message Receivers on Page 4. s l i ) i

- - m RP/0/A '5000/04 WARNING POINTS ALERTED.3 - Page 4 of 4 1. ( nam,e) (title) (date) (time) (warning point) -2. f l (name) -(title) l l (date) (time) (warning point) 3. (name) (title) '\\ (date) (time) (warning point) ~l , 4. (name) (title) (date)- (time) -(warning point) 5. (name) (titte) Id g (date) (time) (warning point)- (..,_ 6. 1 1 (name) (title) i 1 l (date) (time) (warning point) 7. (name) (title) (date) (time) (warning point)-

• • • • • FO R U TI LI TY US E ON LY*****

Release of this message approved by: at: (Name) (Time) (Date)

RP/0/A/5000/04. i -SITE AREA EMERGENCY ENCLOSURE 4,4 PROTECTIVE ACTION RECOMMENDATION. FLOW CHART ( i CLASSIFICATION is a l l SITE AREA EMERGENCY. i I. l ONSITE OFFSITE P 4 P i Conduct a. Site. Assembly Recommend Sirens-l & Consider an Evac. of be Sounded & Notify N6rt-Essential Personnel the Public,via EBS, of the Situation. 1 i ( (', 1P Continue Assessment O e i. t /g

c RP/0/A/5000/04 - . Enclosure 4.5 CATAWBA NUCLEAR STATION 10-MILE EMERGENCY PLANNING ZONE (EPZ) ' MAP enume Zone or EFZ Soutwiery h1 Zone Hwnber . F3 ../. ^ _g _= 4 g i F3 M h ( \\ lt v. = * = =. F1 / C A-3 . - J. / i >A

• i.

/ / 51 _. ' ho q p1 3 I W 2 j $1 [ me ', l D2 ( p C1 I .'3, g..$-[ , -b. . s. ...'s.1 c g / 4P 7, 2 h' W ~. j,.;a t s (. s 9 4

Page 2 of '2 M -DUKE POWER COMPANY ' CATAWBA NUCLEAR STATION RP/0/A/5000/04 ENCLOSURE 4.5 WIND DIRECTION DETERMINATION WORK SHEET I Based on wind direction (WD), determine the affected zones from the tables below. Circle the. wind direction and affected zones. NOTE: . Upper tower wind direction is preferred. if not available, use lower WD, then use WD from National Weather Service. 1 A. IF WIND SPEED IS < 5 MPH, THE AFFECTED ZONES ARE A-0, A-1, B-1, C-1, D-1, ' E-1 and F-1. B. IF WIND SPEED IS >'5 MPH, SELECT THE AFFECTED ZONES FROM THE TABLES BELOW AS APPLICABt E. Table 2.1 Table 2.2 0-5 Mlle Radius Affected 5-10 Mile Radius Affected . Wind Direction Zones Win'd Direction Zones 0.1* .360 A-O PLUS a 0.1* - 22' C-1, D-1 0.1 - 27* - C-2, D-2 22' - 73* C-1, D-1, E-1 27 - 69* C-2, D-2, E-2 73* - 108* C-1, D-1, E-1, F-1 69* - 95* D-2, E-2, F-2 (n, 108' - 120* D-1, E-1, F-1 95* - 132* D-2,.E-2, F-2, F-3 120' --159* E-1, F-1 132* - 144' E-2, F-2, F-3 159* - 207* E-1, F-1, A-1 144 - 160* E-2, F-2,<F-3, A-2 207' - 247' F-1, A-1, B-1 160* - 201* F-2,. F-3, A-2 247' - 265* A-1, B-1 201* - 229* F-2, F-3, A-2, B-265* - 298* A-1, B-1, C-1 229* - 249* ' F-2, A-2, B-2 298* - 338' B-1, C-1 249* -'259' A-2, A-3, B-2 338' - 360* B-1, C-1, D-1 259* - 290* A-2, B-2, C-2, A-3 290* - 304* A-3, B-2, C-2 304* - 333* B-2, C-2 333* - 360* B-2, C-2, D-2 l' (

k.-

s i f 9 4

-__-_-___-__-------------------7--- ' Form 34731 (R9 60) (1) ID No. RP/0/A/5000_/04 ? DUXE POWER COMPANY Change (s) 9 to PROCEDURE PROCESS RECORD to _lncorporatea i PR EPAR ATION { Retype 4 (2) STATION CATAWA WN TAM RT A"TM (3) PROCEDURE TITLE General Emergency 5 (4) PREPARED BY-d- N DATE (5) REVIEWED BY M DATE A >3**b Cross Disciplinary Review By - N/R / / (6) TEMPORARY APPROVAL (if Necessary) i By-(SRO) DATE Oy DATE (7) APPROVED BY DATE 30 1 (8) MISCELLANEOUS Reviewed / Approved By ~ OATE Reviewed / Approved By _DATE-(9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously approved chang Attach additional pages,if necessary.) ADDITIONA L CHANG ES INC LU DE D. O Yes gNo (10) COMPARED WITH CONTROL COPY DATE COMPLETION (11) DATE(S) PERFORMED (12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate? O Yes O N/A Listed enclosures atteched? O Yes O N/A Data sheets attached, t:ornpleted, dated and signed? O Yes O N/A Charts, graphs, etc. attached and properly dated, identified and rnarked? O Yes O N/A Acceptance criteria met? VERIFIED BY DATE (13) PROCEDURE COMPLETION APPROVED DATE \\ N u4) REMARKS (Attach additional pages,if necessary.) l ~ ~

RP/0/A/5000/05 DUKE POWER COMPANY T CATAWBA NUCLEAR STATION- ~ GENERAL EMERGENCY 1.0 SYMPTOMS 1.1 Events are in process or have occurred which involve an actual or imminent substantial core degradation or melting with potential for loss of containment integrity. 2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to individuals and organizations. 2.1.1 Complete Part i of Warning Message Form (see example.3). Record receiver's name and time (initial contact). NOTE: Emergency Coordinator shall initial forms when message is approved for transmission. NOTE: Warning Message forms are kept in a notebook in the Control Room and TSC, ensure that all used forr6s are returned to the back of the notebook. 2.1.2 Notifications shall 'ue as the order of Enclosure 4.1 indicates. See RP/0/8/5000/13 for NRC Notification. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 2.1.3 Advise station personnel to activate TSC and OSC. l 2.1.4 Complete Enclosure 4.2 and advise the Nuclear Production Duty Engineer to activate the CMC. 2.2 Protective Actions Offsite 2.2.1 Recommend to Offsite Agencies that all residents of the 2 mile radius zone (A-0) and any zone 5 miles downwind of the plant seek immediate shelter and await futher instructions. 2.3 Protective Action Onsite 2.3.1 Conduct a Sito Assembly, see RP/0/A/5000/10. 2.3.2 Evacuate non-essential personnel to the Evacuation Relocation Centers, see RP/0/A/5000/10. 'i I

[H . ?' . R P/0/A/5000/05! # 9-Page 2 of 3 a 3.0 SUBSEQUENT ACT!ONS T s, 3.1 Accident Assessment: .j q i a 3.1.1 Dispatch field monitoring teams with associated communications equipment, see -HP/0/B/1009/04. 3 3.2 Follow up N6tifications. 3.2.1 See RP/0/A/5000/06,. Follow-up Notifications, n 3.3 Follow-up Recommend Protective Action Offsite NOTE Protective Action Recommendation are obtained from: OAC Program " Nuclear-23" or RP/0/A/5000/11, operational, for Operations personnel. ' if the OAC is not d o-3.3.1 The Emergency Coordinator shall make Protective Action j s Recommendations.to the affected ~ county. warning points and to both SC and NC state warning points ~(Emergency i Operations Center if established) or the designated - C state department as per the state's Radiological j 1 Emergency Response Plan. See Enclosurb 4.4 for aid in protective action ' decision making. g ( NOTE a . This authority shall not be' delegated to other elements- 'of the emergency organization. n 3.3.2 If a.:tual release of radioactive material will result in a projected dose to the population of: EPA Protective Action Guides Whole Body Thyroid Recommendnion <1 Rem <5 Rem No Protective Action is Required. 1 to <5 Rem 5 to <25 Rem Recommend seeking shelter and wait for further instruction. -Consider evacuation particularly for children L. pregnant women.- Control access to affected areas, f l >5 Rem >25 Rem Recommend mandatory evacuation of population in the affected areas. Control access to affected areas. Q. l i

RP/0/A/5000/05 Page 3 of 3 NOTE Monitor environmental radiation levels to verify and adjust recommendations as necessary. 4 ) 3.4 Emergency Worker Exposure Limits S kin of W. B Activity Extremities (Rem) Whole Body (Rem) Thyroid (RemT Normal Dose Limit 75 5 30 Emergencies (a) 75 25 125 Lifesaving Activities (a)(b) 375 75 150(c) l t (a) Appropriate controls of emergency workers, include: time i limitations, respirators and Potassium lodide (Kl) - See l H P/0/B/1009/16. j f The Emergency Coordinator may authorize doses to these limits. l (b) Volunteers only. f (c) Although respirators and Potassium lodide should be used where effective for emergency team work, Thyroid dose may not be a limiting factor for lifesaving missions. l l 3.5 ( Augment on shift resources to assess and respond to th'e emergency situation as needed. 3.6 Announce over the plant PA system the current emergency classification l level and a summary of plant status. j i 3.7 Assess the emergency condition, then remain in an General Emergency, j reduce the emergency class or terminate out the emergency. Make an t announcement over the plant PA system anytime emergency classification level changes. Include summary of plant status. l l 3.8 The Recovery Manager at the Crisis Management Center shall close out i the emergency or recommend reduction of the emergency class by briefing the offsite authorities at the Crisis Management Center or by phone if necessary, followed by written summary within 8 hours, 4.0 ENCLOSURES 4.1 Telephone Notification List 4.2 Emergency Message Format l 4.3 Example Warning Message: Nuclear Facility to State / Local Government I 1 4.4 Protective Action Recommendation Flow Chart 4.5 10 Mile Emergency Planning Zone (EPZ) Map and Wind Direction Determination Worksheet l i I l

3 RP/0/A/5000/05 s Enclosura 4.1 1 Page 1 of 2 TELEPHONE NOTIFICATION LIST .y. Initial ' 4.1.1 Station Mana r - J. W. Hampton

• Conference Call Offic Home -

1 1st Alternate - H. B. Barron. Offic Hom _o.C 2nd Alterna . F. Wardell Offic Home s 3rd Alterna - G. - T. Smith Office Home 4th Alternate - B. F. Caldwell t ) 5th Alterna E. Crawford Office Home ( l 4.1.2 Compliance 'neer - C. L. Hartzell

• Conference Call-1 Office Home 1st Alterna

. P. Simpson Offic Home .s 2nd Alternate - F. P. Schiffley Offic Home ~

• Conference Call Instructions only) 1.

Press and release the receiver button to put the first call on " hold". You will hear three beeps, then dial tone. 2. Dial the third person's number. You can talk before including the original-caller. 3. To begin the Conference call, press and release the receiver button. All three parties will be on the line. (If the line is busy or there's no answer, you can return to the original call by pressing and releasing the receiver button.) . 4. All parties are disconnected when you hang up. ~ 4

x R P/0/A/5000/05 -

• .1 TELEPHONE 4.1.3

' State r, County Warning Points **Use Warnin~ ' Message Form ** g GROUP CALLh 1. Mecklenburg County Signal - Back-up: Emergency' Radio, Code: 2. York County A Back-up: Emergency Radio, Code: .l 3. Gaston County ignal Back-up: Emergency Radio, Code 1 4. N.C. State, Raleigh 5. S.C. State, Columbia ( 4.1.4 Ope Page A: See Current operations Work List for Home Phone Number. 4.1.5 plu,. clear Production Dut En inee u

• • US NCLOSURE 4.2 4.1.6 NRC Operations Center, Bethesda,- Md. (RP/0/B/5000/13) i 4

e t

.c RP/0/A/5000/05 Enclosura '4.2 ~Pago l'of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ~ TO NUCLEAR PRODUCTION DUTY ENGINEER EMERGENCY MESSAGE FORMAT 1. This is-at Catawba Nuclear Station. (Name and Title) 2. This is is not a drill. An Unusual Event Alert Sito Area Emergency-X General Emergency was declared by the Emergency Coordinator at on Unit # (Time) 3. Initiating Condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status.) 1 4. Corrective measures being taken: ( 5. There have have not not been any injuries 'to plant personnel. 6. Release of radioactivity: is taking place is not taking.placs 7. NRC Yes No; State Yes No; Counties Yes No; have been notified. 8. The Crisis Management Team X should should not be activated. Corporate Communications and Company Management should be notified. Ensure that Corporate Communications sends a Copy of any News Release, to Control Room. 9. I can be reached at for follow-up infor mation. (Telephone Number) 10. Additional Comments: Name of Person Contacted Date Time-t %c

3 RP/0/A/5000/05' ; PART 1 INITIAL WARNING MESSAGE Enlosura 4.3 .i l Pago.1 of 4 1. Date: Time: hou rs 2. This is: Catawba Nuclear Station concerning Unit # l .? My name is: Telephone: this message (Number ): (a) Reports a real emergency. l ~~ (b) Reports the change in the class of a real emergency. i l (c) Reports the termination of a real emergency- ] l (d) is an exercise message. 3. Message Authentication i Message Sender: I authenticate as (a) IF A TERMINATION MESSAGE. GO TO PART 3. 4. The class of emergency is: 1 (a) Unusual Event X (c) Site Area Emergency ) i (b) Alert (d) General Emergency i I 5. This class of emergency was declared at: on (time) (date) 6. The initiating event causing the-emergency classification is: 1 a 7. The emergency condition: 1 (a) Does not involve the release of radioactive material 1 from the plant. 1 ( (b) involves the potential for a release, but no release is occu ring. (c) Involves the release of radioactive materials. 8. The following protective actions are recommended: ) (a) No protective action is recommended at this time. (b) People living in zones remain indoors with j the doors and windows closed, turn off air conditioners and other ventilation, monitor EBS stations. (c) People living in zones evacuate thier homes i and businesses and go to the designated shelter. I (d) Pregnant women and children in zones remain ~ indoors with the doors and windows closed, turn off air conditioners and other ventilation, and monitor EBS stations. j X (e) Other recommendations: Activate the alerting siren system ) and inform the public via the Emergency Broadcast System. i 9. I repeat, this message: (a) Reports a real emergency. j (b) Reports a change in the classification of a real emergency. j (c) is an exercise message. 10. Do you have any questions? (Copy on separate sheet.) j 11. RELAY THis INFORMATION TO THE PERSONS LISTED IN YOUR ALERT I PROCEDURES WHO MUST BE NOTIFIED OF INCIDENTS AT A NUCLEAR i* FACILITY.

• For Message sender:

record names of Message Receivers on Page 4_. j END OF PART 1 .j i l

6 PART 2 FOLLOW-UP MESSAGE (S) Enclosuro 4.3 Pagg 2 of 4 1. Plant status: Reactor.(a) is not tripped / was tripped at (Time): /-~, b Plant is at: (a) % power (c) hot shutdown (b) cold shutdown (d) cooling down Prognosis is: (a) stable (c) degrading. (b) Improving (d) unknown 2. Emergency actions underway at the facility include: 3. Onsite support needed from offsite organizations: 4. Dose Projection Data Windspeed: mph Wind direction: From Precipation: 1 Release Type: (a) G round/(b) Elevated Stability Class: ( A, B, C, D, E, F,or G) Weighted dose Conversion Factor: (a) (R/hr)/(Ci/m )(whole body) 8 (b) (R/hr)/(Ci/m*)(Child Thyroid) Radiological Release: Noble Gas Equivalent curies /sec. lodine Equivalent ( curies /sec. 5. The type of actual or projected release is: (a) Airborne (b) Waterborne (c) Surface Spill (d) Other (e) No release is in progress or expected at this time (Skip Items 6, 7 r, 8) 6. Release l will begin at hours. began at hours. ~ 7. The estimated duration of the release is hours. 8. The source and description of the release is: I (, -. i

RP/0/A/5000/05 - PART 2 FOLLOW-UP MESSAGE (S) Continusd Enclosuro 4.3 Pago 3 of 4 1 9. Dose Projections: 1 Dose Commitment Projected Integrated Dose in Rem Based on-hou rs of release-Whole Body , Child Thyrold' j Distance (rem / hour)(Rem / Hour of inhalation) Whole Body Child Thyroid l Site I Boundary {i j 2 miles i l 5 miles - i 10 miles i 10. Field measurement of dose rate (mr/hr) or contamination (X) l (if available). l i Time Zone Distance from Direction from Whole Body Child Thyroid Plant Plant l 1 i 11. I repeat, this message: (a) Reports a real emergency. (b) Reports a change in the class of a real emergency. (c) is an exercise message. 12. Do you have any questions? (Copy on Separate Sheet) 1

• • • • • E N D O F FO L LOW-U P M E S S A G E ( S ) *****
• For Message Sender:

Record names of Message Receivers on Page 4. PART 3 TERMINATION MESSAGE 1. The event was terminated at on (time) (date) 2. The event at the plant was terminated for the following reason (s): 5

• • • • • END OF TERMINATION MESSAGE *****

( - *For Message Sender: record names of Message Receivers on Page 4. .______._m______-_.m_ - - - - - - - - - ^ - - - - - -

4 RP/0/A/5000/05 WARNING POINTS ALERTED Enclosurs 4.3 Page 4 of 4 '1. (name) (title) (date) (time) (warning point) 2. (name) (title) (date) (time) (warnin5 point) 3. (name) (title) (date) (time) twarning point) 4. (name) (title) 1 (date) (time) (warning point) 5. l (narne) (title) (date) (time) (warning point) (name) (title) (date) (time) (warning point) 7. (name) (title) (date) (time) (warning point)

• • • • • FO R UT I L I TY U S E O N L Y*****

Release of this message approved by: at: (Name) (Time) (Date) L_- _-_ _ _ _ __

RP/0/A/5000/05 GENERAL EMERGENCY ENCLOSURE 4.4 PROTECTIVE ACTION RECOMMENDATION FLOW CHART

, r.

CLASSIFICATION is a l GENERAL EMERGENCY Conduct a, q Site Evacuation' Has Physical Yes Consider a 2MLR. Control of Plant

Precaut.. Evac?

I Been Lost?

1. 3 No Irnmediately Redommend-2Mi.R.

I & SML D.W. Sheiter indoors. Continue l ' Assessment t 3 yn: Yes Core Damage No EPA PAG's

• Projected to be Fission + Products

)_20% Actual Exceeded or m f pein Containment r Projected? Measured in Environs? i l ) GAP Activity? Yes-y No Yes Recommend Action l Release in in Accordance with % ogress or EPA PAG's Projected > Design No See Section 3.3.2 Leak Rate? No Yes l Rec 5mmend Recohnend Recommend. Shelter for Evacuation. Evacuation s Areas that 2MLR. & ' 5MLR. & Cannot be 5ML D.W. 10ML D.W. Evac. Before +1 +2 +1+2 Proceed with Pkane Arrival W I Recommendation " #4 Is Evac.IFeasible? No +3 +4 Yes Abbreviations: D.W.- Downwind (90' Sector) Notes #1,#2,#3,#4 are on page 2_. CATAWBA Evacuation Time Estimates are on page 2_. c______________________ E

] Page 2 of 2 RP/0/A/5000/05 ~ l GENERAL EMERGENCY l ENCLOSURE 4.4 j PROTECTIVE ACTION RECOMMENDATION FLOW CHART m 3 1' l Notes: 1. For an evacuation recommendation, sheltering of the downw'ind subzones of the plume exposure EPZ should be recommended. l 2. Concentrate on evacuation of areas nearest the plant. j 3. The feasibility of an evacuation must be determined by responsible offsite authorities at the time of the emergency. Consideration should include: l a. Can State /Ccunty agencies support the evacuation? b. Will weather condition inhibit evacuation? c. Do bridge and road conditions present an impediment to evacuation? l d. Is the release continuous (>2 hours) or a puff? EPA - i 520/1-75-001 Table.1.3. l (' 4. Promptly relocate the population affected by ground 1 ) s. _.. contamination following plume passage. l 3 5. Evacuation Time Estimates for Catawba Plume Exposure EPZ: i Normal Adverse conditions conditions All Zones (except as noted) 3:25 hrs 3:25 hrs Zone C-2 4:00 hrs 6:15 hrs l Zone B-2 3:25 hrs 4:00 hrs Special Facilities (except as noted) 2:45 hrs 4:15 hrs i Special i Facilities B-1,C-1,F-1,F-3 1:40 hrs 2:30 hrs j I I' t %.c a

u g{ f dGDICY PLAHgigG1 ZONE. - - - ~ gm6eWOWG O* a \\ PageJ.,ofE. (y,pz) MAP. g Zone Nwnber ,,e $ta\\ \\ P3 I . L. /, "a R x _= ,,e -- = - g s f 72 F1 'W ] ~ .k1 '\\ g.S ,1 ) f ,f k. ',1 - r ) q ) j gj k 5 a~ 1 ( )f 41 '[' i .--iN ./.7 .\\ ,e .~ on / '. t, ,," '9 g,' ..J ?== M k en e-e 9 4 f __.m_____.__

A-1 .Pago 2 of 2 g g ' '/ DUKE POWER COMPANY CATAWBA NUCLEAR STATION RP/0/A/5000/05 ENCLOSURE 4.5 Y y WIND DIRECTION DETERMINATION WORK SHEET Based on wind direction (WD), determine the affected. zones from the tables below. Circle the wind direction and affected zones. NOTE: Upper tower wind direction is preferred, if not available, use lower WD, then use WD from National Weather Service. 4 i A. IF WIND SPEED IS < 5 MPH, THE AFFECTED ZONES ARE A-0, A-1, B 1, C-1, D-1, E-1 AND F-1. B. IF WIND SPEED IS > 5 MPH, SELECT THE AFFECTED ZONES.FROM THE TABLES BELOW AS APPLICABLE. i i Table 2.1 Table 2.2 0-5 Mile Radius Affected 5-10 Mile Radius

Affected, Wind Direction Zones l

Wind Direction Zones I 0.1 - 360 > A-0 PLUS I j 0.1* - 22* C-1, D-1 0.1 - 27 >-C-2, D-2 1 ~ 22* - 73* C-1, D-1, E-1 27 69 > C-2, D-2, E-2 l 73* - 108* > C-1, 0-1, E-1,. F-1 69* - 95 > D-2, E-2, F-2 108* - 120* D-1, E-1, F-1 95* - 132 --->-D-2, E-2, F-2, F-3 120* - 159* E-1, F-1 132 - 144 y E-2, F-2, F-3 1 159* - 207* > E-1, F-1, A-1 144* - 160 M E-2, F-2, F-3, A-2 l 207* - 247* > F-1, A-1, B-1 160* - 201 y F-2, F-3, A-2 247* - 265*- ' A-1, B-1 201* - 229* > F-2, F-3, A-2, B.-2 265 - 298* Y [-1, B-1, C-1 229' - 249* y F-3, A-2, B-2 298* - 338* y B-1, C-1 249 - 259* F A-2, A-3, B-2 338' - 360 y B-1, C-1, D-1 259' - 290* y A-2, B-2, C-2, A-3 290* - 304* - ) A-3, B-2, C-2 304* - 333* > B-2, C-2 333 - 360* y B-2, C-2, D-2 i l 1 4.*. q l l

[.; e Form 34731 (R9 86)T (1) 10 No. RP/0/d/5000/0 ~ DUXE POWER COMPANY Change (s) 1 to ~ PROCEDURE PROCESS RECORD 2-Incorporated 1 PREPARATION Retype 'l l (2) STATION CATAMA WFT F AR RTATTON ( (3) PROCEDURE TITLE. Entf. T R TnM/NPT.n R TON (4) PREPARED BY DATE (5) REVIEWED BY DATE ~' Cross Disciplinary Re 8 NA N/A / / (6) TEMPORARY APPROVAL (if Necessary) i By (_ SRO) DATE sy DATE Soh (7) APPROVED BY DATE (8) MISCELLANEOUS a Reviewed / Approved By DATE Reviewed / Approved By DATG (9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously approved changes, are includ Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. O Yes $ No (10) COMPARED WITH CONTROL COPY DATE COMPLETION (11) DATE(S) PERFORMED (12) PROCEDdRE COMPLETION VERIFICATION l O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate? l O Yes O N/A Listed enclosures attached? O Yes O N/A Data sheets attached, completed, dated and s'igned? O Yes O N/A Charts, graphs, etc attached and properly dated, identified and marked? O Yes O N/A Acceptance criteria met? VERIFlED BY DATE (13) PROCEDURE COMPLETION APPROVED DATE RE$tARKS (Attach additional pages,if necessary.)

i14) r I

L__--__-_________--__-_.__--__-_-___-__

N RP/0/A/5000/09 ~ DUKE POWER COMPANY CATAWBA NUCLEAR STATION COLLISION / EXPLOSION 1.0 SYMPTOMS 1.1 Observance of the following incident onsite or near site: 1.1.1 Aircraft crash or threatening aircraft activity { 1.1.2 Train derailment 1.1.3 Waterborne collision 1.1.4 Missile impact 1.1.5 Explosion 1.1.6 Incident jeopardizing vital structures or safe shutdown equipment ( 2.0 IMMEDI ATE ACTIONS Initial /N/A ( 2.1 Classify the emergency by RP/0/A/5000/01, Classification of

E Emergency, and commence notification and/or other protective measures as directed by appropriate Emergency Response Procedure.

3.0 SUBSEQUENT ACTIONS

• 3.1 Take appropriate actions to ensure the safety of the reactor (s).

3.2 Perform emergency first aid as necessary. 3.3 Extinguish any fire (s) if applicable. 3.4 Notify Chemistry if there are any chemical implications. 3.5 Notify Health Physics if there are any radiological implications. l l 3.6 Notify Security for any event. 3.7 Notify applicable outside agencies as necessary. (Enclosure 4.1) 4.0 ENCLOSURES 4.1 Emergency Telephone Numbers I

• These actions may be performed concurrently as appropriate

\\Y, O L ---------

m J RP/0/A/5000/09 . Enclosure 4.1 ' DUKE POWER COMPANY i CATAWBA NUCLEAR STATION EMERGENCY TELEPHONE NUMBERS I Ambulance & Medical

• Piedmont Medical Center.

Rescue Squad

• Clover Rescue Squad.......

l

• Security will normal! e initiate the call for outside medical assistanc l

l Fire Department Bethel Volunteer Fire Department l Federal Aviation Administration - 24 Hr. Number Duke Power Company Railroad Contact - Wayne Hallman Home 9 / l l e

Porm 34731 (R9 86) (1) 10 No. PP/0/3/5000]1{ OUKE POWER COMPANY Change (s) G to PROCEDURE PROCESS RECORD 0 Incorporated PREPARATION Retype-5 (2) STATION ONA (3) PROCEDURE TITLE NPC Num1GMON PNN . (4) PREPARED BY DATE i DATE S O (5)' REVIEWED BY Cross Disciplinary Review By._. b 2'3 N/R ) J (6) TEMPORARY APPROVAL (if Necessary) I By (SRO) DATE By DATE { 7/3c/0 (7). APPROVED BY Al DATE l (8) MISCELLANEOUS Reviewed / Approved By DATE l W Reviewed / Approved By DATE k i (9) COMMENT 3 lFor procedure reissue indicate whether additional changes, other than previously approved changes, are includI Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. C Yes CNo l (10) COMPARED WITH CONTROL COPY DATE i COMPLETION (11) DATE(S) PERFORMED (12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate? O Yes O N/A Listed enclosures attached? O Yes O N/A Data thests attached, completed, dated and signed? Oyes O N/A Charts, graphs, etc. attached and properly dated, identified and marked? Oyes O N/A Acceptance criteria met? .I VERIFIED BY-. DATE (13) PROCEDURE COMPLETION APPROVED DATE i-. (14) REMARKS (Attach additional pages,if necessary.) (

7.. ?- t m i [p-DUKE ' POWER COMPANY RP/0/B/5000/13 - 9 i CATAWBA. NUCLEAR STATION NRC NOTIFICATION REQUIREMENTS 1.0 SYMPTOMS l 1 1.1 Plant conditions requiring NRC notification in accordance with: l 10 CFR50.72,10 CFR20.205,10 CFR20.403, and 10 CFR73.71. i l 1.1.1 Immediate,1 Hour and 4 Hour Notifications, i 1.1.2 ' 24 Hour Notifications for Operating License Condition Deviations. 1.2 See Enclosure 4.1 for determination of appropriate ' notification requirement. 2.0 IMMEDIATE ACTIONS i 2.1 Complete one of the following enclosures: 2.1.1.2 " Checklist for Significant Event Notification" NOTE: Emergency Coordinator shall initial forms when message is approved for transmission.; j E I 2.1.2.3 " Report of Serious Physical Security Eventn" 1 l When reporting from Section 4.1.2.7 or Section 4.1.4.2 ) of Enclosure 4.1 1 2.2 Notify the NRC Operations Center by th'e following means: 2.2.1 Prl. - Emergency Notification System Phone I i ? i E I I 2.2.2 Alt. 3 2.3 Notify the NRC Region !! Office at/ of any event' listed in Section 4.1.1.5 of Enclosure 4.1. NOTE: No Enclosure for reporting to Region 11 from Section 4.1.1.5 of Enclosure 4.1 3.0 SUBSEQUENT ACTIONS 1 3.1 Provide follow-up notification as described below: e i l

RP/0/ B/5000/13 I '* ~ Page 2 of 3 3.lil Emergency Classes 3.1.1.1 Any further degradation in level of safety of the plant including those that require j declaration of any Emergeccy Class, if such a i declaration has not been pre.viously made.- 3.1.1.2 Any change in the Emergency Class 3.1.1.3 Termination of the Emergency I 3.1.2 Results of ensuing evaluations or assessments of plantL { conditions { 3.1.3 Effectiveness of response or protective measures taken } 3.1.4 Information related to plant behavior that is not j understood 3.2 Maintain an "Open", continuous, communications channel with the NRC Operations Center, upon request by the NRC. j 3.3 Notify the following individuals: 1 t i 3.3.1 Compliance Engineer ( P rima ry Alternate Duty Compliance C. L. Hartzell Engineer Office: (See cQrrent Station Home: Duty. List) 3.3.2 If neither the Compilance Engineer nor the Duty Compliance Engineer can be reached then call directly to the: NRC Resident inspector Primary - Unit 1 Primary - Unit 2 P. K. Van Doorn P. K. Doorn Office: Office: Home: Home: Alternate'- For Either Unit e 3.3.3 Nuclear Production Duty Engineer

RP/0/ B/5000/13 y Page 3 of 3@ 3.3.4 Duty Station Manager -l ,n (See ' Current Station Duty. List) I 3.4 Upon completion of this procedure, fill out the Completion Section of the Procedure Process Record Form and forward to the Compilance Engineer for review prior to submission to Master File. 4.0 ENCLOSURES l 4.1 Events Requiring' NRC Notification. J i 4.2, Checklist for Serious Event Notification 4.3 Report of Serious Physical Security Events 4.4 List of Engineered Safeguard Features (ESF) Actuations W l l j i l O .? I E_________i--___-------__--_-_-------- - - - - - - ~ -

F . 5 R P/0/ 8/5000/13 Events Requiring NRC Notification.1 Pago 1 of 6 ./ ~ 4.1.1 Events Requiring "lMMEDI ATE NOTIFICATIONS": Immediately after notification to states and counties and not later than one hour after the time the Emergency Class was declared. 4.1.1.1 The declaration of any of the Emergency Classes specified in the Catawba Emergency Plan 4.1.1.2 Any change from one Emergency Class to another ~ 4.1.1.3 Termination of the Emergency 4.1.1.4 For any incident involving byproduct, source or special nuclear material which may have caused or threatens to cause the following: 4.1.1.4.1 Individual Exposure l 125 Rem Whole Body l or l 3150 Rem Skin of Whole Body J _or i > 375 Rem Extremities 4.1.1.4.2 Release of radioactive material in concentration which if averaged over a 24 hour period would exceed 5.000 times the applicable concentration of the limits specified in 10CFR20, Appendix B, Table 11. 4.1.1.4.3 Loss of one working week or more of the operation of any unit. 4.1.1.4.4 Damage to property in excess of $200,000. 4.1.1.5 Notification to NRC Regional Office, Region 11, i Atlanta, GA. (see Step 2.3). Receipt of a package of radioactive materials with: 2 4.1.1.5.1 10.01 uCi/100cm loose radioactive material on the external surface or l%

RP/0/B/5000/13 : Events Requiring NRC Notification Enclosura '4.1 '4 Page 2 of 6 4.1.1.5.2 >200~ MR/hr. on ' external surface r or ~4.1.1. 5.3 - >10 MR/hr. at three (3) feet from the -) external surface l } 4.1. 2 ' Events Requiring "ONE HOUR REPORTS": As soon 'as practical and within one hour of the occurrence. l The 'nitiation' of any nuclear plant shutdown I 4.1.2.1 i required by Technical Specifications (i.e. j . Safety Limit Violation).. See notes: l l NOTE: 1.The initiation of a shutdown is defined I as, "A reduction in Power required by I an action statement of Tech. Specs., to Mode 3." 2. A Shutdown is defined (for reporting i requirements) as, " Mode 3 and below". i 4.1.2.2 Any deviation from a plant License Condition or l Technical Specification authorized in i 10C F R50. 54(x). [- (Licensee may take reasonable action'that departs from a license condition or a technical specification in an emergency when this action' is immediately needed to protect the health and safety of the public 'and no action' consistent-with license conditions and technical specifications that can provide adequate or equivalent protection 'is immediately apparent.) 4.1.2.3 Any event or condition during operation that results in the condition of the plant, including. the principle safety barr ers, being seriousiy i degraded, or results in the plant being: 4.1.2.3.1 in an unanalyzed condition that significantly compr,omises plant safety. 4.1.2.3.2 in a condition that is outside the design basis of the plant. 4.1.2.3.3 in a condition not covered by the plant's operating and emergency p roced u res. 4.1.2.4 Any event that results or should have resulted ( in Emergency Core Cooling System (ECCS) discharge into the reactor coolant system as a result of a valid signal.

R P/0/B/5000/13 f Events Recuiring NRC Notification.1 Page 3 of 6 4 4.1.2.5 Any event that results in a major loss 'of ^ emergency assessment capability, offsite 'i response capability, or communications i capability (e.g., significant portion of control j room-indication, Emergency Notification System i or Offsite Notification System). Note: A loss of 25% of th'e' Prompt Alerting Siren System for Catawba Nuclear Station is reportable when 19 or more i sirens are reported inoperable for > 4 hou rs. 4.1.2.6 Any natural phenomenon or other external condition or any event that poses an actual threat to. the safety 'of the' plant or significantly hampers. site personnel in the performance of ' l duties necessary for the safe operation of the i plant, including fires, toxic gas releases or j . radioactive releases. 4.1.'2.7 Safeguard events as determined by Security personnel and Station Management. 4.1.2.7.1 A trace investigation of a lost or { i unaccounted for shipment pursuant to 10C F R73.27. (- l 4.1.2.7.2 An attempt (actual or suspected) to-I l commit a theft or unlawful diversion of Special Nuclear Material. 4.1.2.7.3 Any event which significantly threatens 'or lessens the effectiveness of the physical security system: NOTE: Reports of Safeguards Events should be made by Catawba Security Procedure # 106, " Reporting of Safeguards Events". Security Supervision will provide all information to-the Operation's-Shift Supervisor for NRC notification. i- + Nw L___-_-__-

p RP/0/8/5000/13 - Events Requiring NRC Notification'.1: As 33 Page 4 of 6 f g; mc q 4.1.3 Events Requiring '"FOUR HOUR.RERORTS"

j

,v E" a 8 As soon as practical-und within four hours of the 'f occurrence, g ( (1 4.1.3.1 Any event found whi!e the peactor(s). is/are l shutdown,. that had it been' found. while' the. 1 reactor (s) was/were in operation would have 1 resulted in the plant,- inclu' ding its principle i safety barriers, being seriously' degraded or 1 being in an unanalyzed condition thht,.q' A L ~ I significantly compromises ' plant safety. ~ j s ~ q 4.1.3.2 Any event or condition that results in d :{ manual or automatic activation-of any. a Engineered Safety Feature (ESF), ~ see Enclosure. l ' 4.4, including the Reactor Protection System ,[ g (RPS). (However,: activation of an ESF including - the RPS, that results frons and is part of 1 the preplanned sei uence <during testing or i t reactor operation need not!be reported). 4.1.3.3 Any event or condition that alone could have pre' anted the fulfill nentjf the safety - v i function %i structures or systems that ach, i needed to: N' it ' (- 4.1,3.3.1; Shutdown the reactor and-g. a i f N maintain it'in a safe shutdown l u condition. i 4.1.3.3.2 Remove residuaitheat. 4 - Ll l 4.1.3.3.3 Control the relhnse of. radioactive! ~ \\' material. 9 e, 4.1.3.3.4 Mitigate the ~ consequences of an-s accident.- q 4 i 4.1.3.4-Any airborne radioactiveirelease that' Exceeds 2 times the applicsble 66ncentrations of the limits specified in' 10CFR20, Appendix B, Table 11 in t t, / unrestricted areas when averaged over a time period of one hour. 3- \\ k l'T,, ; y. i \\, [Q 9 ;. l r R e q '( i,- i, ' N 1 - -

[]' ' ' ' Yf II RP/0/B/5d00/13 i Events Requiring fNRU Notification Enclosura 4.1 N Pass 5 ' of ' 6 - ] a; 4.1.3.5 Any liquid effluent' release.that exceeds 2 ^ times the limiting combined MPC (See t] 10CFR20, Appendix B, Note 1.) 'at the ] point.of' entry into the' receiving water. 1 (unrestricted area) for all radionuclides l except tri;ium and dissolved noble gases; d when averaged over a time period of one hour. (Immediat.e Notifications. made under this-requirement < also satisfy the requirements ~ of 10CFR20.403, Paragraph (a)(2) and (b)(2)). -(See 4;t.1.4.2). 4.1.3.6 Any event requiring the transport of a radioactively contaminated person to an I offs'ite medical facility for treatment. l 4.1.3.7 Any event or situation, related to the - health and safety of the public or. onsite. 3 ~ personnel, or prdtection of the environment, for which a News Release is planned or Notification to Other Government Agencies has been or will be made. Such.an event may include an onsite fatality or inadvertent release of radioactively l contaminated mate' rials. 4.1.3.8 Steam Generator Tube Plugging in accordance with Tech Spec 3.4.5, Table 4.4-2. 4.1.4 Events Requiring "24 Hour Reports" 4.1.4.1 Operating License Conditions Deviations Requiring "24 Hr. Notifications": 4.1.4.1.1 Refer to Operating License 4.1.4.2 Security Events: NOTE: Reports of Safeguards Events should be I l made by. Catawba Security Procedure

1. 106, " Reporting of Safeguards Events".

Security. Supervision -will ' provide all information to the Operation's Shift Supervisor for NRC notification. u

,P-- U V ,,.1 RP/0/B/5000/13 Events Requiring' NRC' Notification Enciosure 4.1 Page 6 of 6' 4.1.5 Follow-up Notifications 4.1.5.1 During the course of the event, ' report: 4.1.5.1.1 Any further degradation in the level of safety of the plant or.other worsening plant ' conditions, including. those that require'the declaration ~ of any of the Emergency Classes, if such a declaration has not been previously; made L 'or l Any. change in the Emergency: Class l or. Termination of the Emergency. 1 4.1.5.1.2 The results of ensuing evaluations or assessments of plant conditions 1 a l 4.1.5.1.3 The effectiveness of response or protective measures taken. 4.1.4.1.4 Information related to plant > cl( behavior that is not understood. l I i I . s. j. Y L_____________1._._

'] R P/0/ B/5000/13' ENCLOSURE 4.2 PAGE 1 OF 4_ CHECKLIST FOR SIGNIFICANT EVENT NOTIFICATION -) Complete the applicable portions of this enclosure and transmit to the NRC ) Operations Center as required by Enclosure 4.1. Approved by the Shift Supervisor or Emergency Coordinator l. State the following to the NRC Operations Center: l { "THIS NOTIFICATION IS MADE IN ACCORDANCE j WITH 10CFR50.72. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION l'a NRC REGION 11 MAKING THE NOTIFICATION" 1 1. a. My Name is: My title is: l My Location is: Catawba Nuclear Station, Concerning Unit. 1 (1/2/Both) I can be called-back at b. "Your Name Please" Event Report Sequence No[ "Do we have your permission to tape record this conversation?" c. If No, turn off the recorder. Yes/No 2. Time of Notification .Date of Notification 3. Event Classification: Check appropriate box (s). a -Emergency Plan Declaration -Other immediate Notification G-Notification of Unusual Event O-Alert O-Site Area Emergency. O - General Emergency

b. O -A "ONE-HOUR" Notification

c. O-A "FOUR-HOUR" Notification 4

d. O-A "24-HOUR" Notification 4.

Event

Description:

Category initiation Signal Reactor Trip e ESF Actuation ( ECCS Actuation Safety injection Flow Other r LCO Action Statement i

RP/0/8/5000/13 ENCLOSU RE !4.2 PAGE 2 OF 4 System Component Cause: Mechanical Electrical Personnel Error Event Time EDT/ Event Date Mo./ Day Event

Description:

5. Plant Status: a. Power Prior to event: b. Power at time of report: Did all systems function as required (If no, c. (Yes/No) explain below. ) a d. Anything " unusual" or not understood? (If yes, (Yes/No) explain below. ) l '( e. Corrective Actions: f. Mode of Operation till correction 9 Estimate of time to restart 6. Agencies or personnel notified: State: N.C. & S.C. County: York, Gaston & Mecklenburg NRC Resident (Yes) (No) (will be) Duty Station Manager l Compliance Duty Engineer l NPD Duty Engineer

-- - -;m RP/0/ B/5000/13 ENCLOSURE 4.2 [. Page'3 OF 4 l c. 7. Radiological Release: (If yes, complete this paragraph) { Yes/No a. Release: Liquid __ Gaseous Planned Unplanned i b. Location /Sou rce: I c. Release Rate:' d. Duration of Release: . Estimated Total Activity: e. f. Estimated Total lodine: g. Grab ' Sample: h. Monitor Reading: i. Tech Spec Limit: J. Personnel Exposed or Contaminated: k k. Areas Evacuated: c l. Plant HP Backup Requested: m. Additional Information: l 8. Additional information on NC System Leaks or S/G Tube Leak's: Sudden or Long Term Development: a. b. Start Date & Time: l c. Leak Rate: d. Leak Volume: f e. Tech Spec Limit: f. Primary Coolant Activity: g. Secondary Coolant Activity:

r-g-- --- a i R P/0/ B/5000/13 ~ ENCLOSURE 4.2 i Page 4 OF 4, i h. Radiation Monitor Readings. l 1. Condenser l 2. Main Steam Line i 3. S/G Blowdown i I. Safety Related Equipment Not Operational: 1 l t J. Special Actions Taken (if any): I i i l 'I j 1 l l l

y ..n RP/0/ B/5000/13 / ENCLOSURE 4.3 .PAGE 1 OF 1 1 REPORT OF SERIOUS PHYSICAL SECURITY EVENTS i '{. DATE/ TIME OF NOTIFICATION NRC PERSON NOTIFIED State the following to ^he NRC Operations Center: "THIS NOTIFICATION IS MADE IN ACCORDANCE WITH 10C F R73.71. THIS IS DUKE POWER COMPANY'S. CATAWBA NUCLEAR STATION IN NRC REGION 11 MAKING THE NOTIFICATION". My Name is: My title is: I can be reached at "Your Name Please" l 1.

• DATE OF OCCURRENCE:

3.* POWER LEVEL OF UNITS: 1 2.

• TIME OF OCCURRENCE:

Unit 1 Unit 2 ~

• lf date and time of occurrence are not known, indicate the date 'and time of' 7

discovery. 4. DESCRIPTION OF EVENT: l. l S. SECURITY RESPONSE / COMPENSATORY MEASURES ESTABLISHED: 1 6. LLEA (Local Law Enforcement Agency) NOTIFIED? YES NO (If Yes, name organization and telephone' number) 7. CONSEQUENCES AT PLANT: Description of Equipment Systems Affected E.

] L. RP/0/ B/5000/13 ) ENCLOSURE 4.4 i Paga 1 OF 3 j ~ LIST OF ESF ACTUATIONS REQUIRING NRC l NOTIFICATION WITHIN FOUR HOURS I 1 i NOTE: This is a guideline only, it may not contain all possible ESF i actuations. i { 1. . Safety injection (FSAR 6.3.1, 6.3.2) l a. NV charging path b. Ni charging path l c. ND charging path 2 l d. UHI injection e. CLA injection f. D/G sequencer activation 1 i 9 RX trip signal h. FWST - Containment sump ND suction swap i ) 2. Containment Spray (FSAR 6.2.2) NS pump start / valve alignment a. ,s' b. Actual spray down of containment 3. Containment isolation (FSAR 6.2.4) i I a. Phase A (St) b. Phase B (Sp) i { Containment Purge and Exhaust (Applicable to VP during core l c. alteration and movement of irradiated fuel within j containment. VQ isolation due to EMF 38, 39 and 40 l activation is not reportable.) l 1. EMFs 38, 39, 40 activated i 2. VQ isolations constitute ESF actuations only if initiated by high containment pressure signal, d. NW system injection 4. Steam Line Isolation (FS AR 10.3.2) a. Individual steam line valve closure

• i b.

System isolation I i

• Individual component activation due to component failure not reportable per this requirement, i

J

e RP/0/B/5000/13 ENCLOSURE 4.4 Pago 2 OF 3 l[' 5. Feedwater isolation (FSAR 10.4.7.2) a. Main feedwater control valve closure

• b.

Main feedwater control bypass valve closure * ' c. Main feedwater containment isolation valve closure

• I d.

Main feedwater containment bypass valve closure

• e.

Aux feedwater tempering valve closure

• l 6.

Turbine Trip (FSAR 10.2.1) caused by: Manual actuation (required because of b --e and no auto a. trip) s b. Safety injection signal c. S/G Hi Hi water level (P-14) d. RX trip (P-4) Trip of both Main feed pumps e. 7. Containment Pressure Control System (FSAR' 7.6.5) w a. Start or termination permissive actuation 8. Auxiliary Fecdwater System i t a. Aux feed pump start (Auto) b. Pump suction swap to RN 9. Loss of Power (FSAR 8.3.1.1.2) " Actuation of undervoltage relays on loss of a. l voltage to essential busses b. Actuation of undervoltage relays on grid degraded voltage c. D/G sequencer activation 10. Control Room Area Ventilation Operation (FSAR 9.4.1) Simultaneous operation of A and B trains a. b. EMF 43A/B, chlorine or smoke detectors closing VC intakes *

• Individual component activation due to component failure not reportable per this requirement.

~

RP/0/B/5000/13.. ENCLOSURE 4~ 4 - t Page 3 OF 3 T 11. Containment Air Return and Hydrogen Skimmer. Operation K (FSAR 9.4.10) a. Any. unanticipated system operation i 12. Annulus Ventilation Operation (FSAR 9.4.9, 6.2.3) a. Any. unanticipated system operation 13. Nuclear Service Water System (FSAR 9.2.1.2, 9.2.1.3) a. Auto pump starts 1 b. RN train separation * - c. RN pump suction transfer. to SNSWP 14. Auxiliary Building Filtered Ventilation Exhaust' Operation (FSAR 9.4.3.1) Filtered mode of operation in conjunction witP isolation of all i Auxiliary Building Areas,-except ECCS Pump Rooms. 15. Spent Fuel Pool Ventilation Operatior. (FSAR 9.4.2) l( System placed in the filter mode by EMF ~42 - a. ls 16. Engineered Safety Features Actuation System interlocks a. Any unanticipated activation

• lndividual component activation due to component failure not ~

l reportable per this requirement. i 4 l-I, (N. .=

orm 34701 (R9 86) (1) 10 No.FP/0/B/5000/14 DUKE POWER COMPANY Change (s) O to PROCEDURE PROCESS RECORD 1 Incorporated PR EPAR ATION gg " 2 l\\ (2) STATION CATAWBA NUCLEAR STATION (3) PROCEDURE TITLE I M 4UP NOTIFICATIONS FROM THE TSC (4) PREPARED BY-DATE (5) REVIEWED BY / DATE Cross Disciplinary Review By 1 D' N/R / (6) TEMPORARY APPROVAL (if Necessary) By (SRO) DATE By DATE (7) APPROVED BY '7[34f8] DATE (8) MISCELLANEOUS Reviewed / Approved By DATE Reviewed / Approved By, DATE ~ i l (9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously approved changes Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. Oyes No (10) COMPARED WITH CONTROL COPY DATE C3MPLETION (11) DATE(S) PERFORMEO (12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate? O Yes O N/A Listed enclosures attached? Oyes O.N/A Data sheets attached, compieted, dated and signed? Oyes O N/A Charts, graphs, etc. attached and properly dated, identified and marked? O Yes O N/A Acceptance criteria met? VERIFIED BY DATE (13) PROCEDURE COMPLETION APPROVED-DATE '(14) REMARKS (Attach additional pages,if necessary.)

l l RP/0/B/5000/14 j h., DUKE POWER COMPANY CATAWBA NUCLEAR STATION FOLLOW-UP NOTIFICATIONS FROM TSC 1.0 SYMPTOMS 1.1 An alert or greater emergency has been declared. 1.2 The Technical Support Center (TSC) is in the process of or has been activated. 2.0 IMMEDIATE ACTIONS 2.1 Prior to TSC Activation. 2.1.1 The Offsite Communicator (s) shall proceed directly to the Control Room, to obtain a turnover from the Operations Group, o Ensure all message forms that have been transmitted are available to take back to the TSC. ,o Note the time of the last message transmission and ensure that the next required message is sent on. time. I 2.2 Notification Schedule 2.2.1 Give Follow-up Messages to offsite agencies listed on.1, use the f:,iiowing schedule: o Every hour for Alert, every half hour fer Site Area & General Emergency, until the emergency is terminated, i 91 if there is any significant change to the ' situation o of escalating to a higher emergency classification. [ NOTE: The State and County notification must be i made within 15 minutes of escalation of the l emergency. Use part I only for this circumstance. E As agreed upon with the individual agencies. o NOTE: Documentation shall be maintained for any agreed upon schedule change and the interval shall not be greater.than every 6 hours for s. Alert, 2 hours for Site Area & General l Emergency, to any agency. l -__~

R P/0/B/5000/14 L Page 2 of 3 2.2.2 Use parts 1 L 11 of Warning Message Form for l ' p ', follow-up notifications. : Mark all spaces "N/A" when information is "Not Applicable" and mark "Later" when information is not currently available. 3.0 SUBSEQUENT ACTION 3.1 Telephone numbers for offsite agencies are listed on Enclosure 4.1. Messages are authenticated using Enclosure 4.4. i 3.2 Log the transmission of all messages in the Emergency Communications Log, Enclosure 4.2. 3.3 Copy all pertinent questions (from offsite agencies) received on a Message Reply Form (MRF) and relay the message to the Emergency Coordinator 'or a response. Retain a' copy of the MRF with the Emergency Ccmm. Log. 3.4 Information for transn ission offsite shall be obtained as indicated by Enclosure 4.3, Information Flowchart. Approval by. > the Emergency Coordinator must be~ obtained prior to transmission. 3.5 Problems with the Communications Systems shou!d be directed to the Compliance Engineer. g. 3.G Important! Anytime that the emergency classification is escalated (. ensure the following is included on the message form: Alert to Site Area Emergency - Activate the alerting Siren l o l System and inform the public via the Emergency Broadcast l System. j I Site Area Emergency to General Emergency - People living in o zones A'-O '+ 5 mi OW remain indoors. i i 3.7 Document the turnover of communications responsibilities, from you to the CMC's Offsite Notification Coordinator. Inform the Emergency Coordinator of the turnover, i 3.7.1 After the turnover to the CMC, one offsite Communicator shall remain at the TSC to maintain contact with the Offsite Notification Coordinator. l l 3.7.2 In the event of a loss of communications capability at the CMC or a loss of communications to the CMC, the ' station Offsite Communicators will have to' re-assume the information transmission duties. 3.8 Ensure that the Emergency Message Forms, Message Reply Forms L Emergency Comm. Log is received by the Compliance Engineer i following termination of the emergency. I ( l l u__.__.________

R P/0/ B/5000/14 f Paga 3 of 3 t 4.0 ENCLOSURES 4.1 Offsite Agency Telephone List 4.2 Emergency Communication Log 4.3 Information /iowchart 4.4 Message Authentication Mechanism - (to be omitted, except with the Control Copy of this procedure) t l r e t 0

o IO (0E SI 5R I D /U1 RA BS CR /O 0L e /Cg PNa REP ro E NOH P E L ET T S I NL r r O o o IE YTN NAO G ATH N PSP I M E L ORL A CAE N ET G t I uY S bC OHN E P E V b AG I EBA T y KW C l l UAE E o t p r n DTT L l u t i AI E a-e n o CS S i wh o j a F t ot C i F il d n nl t e o e O t l i oa a s t t n f t s s t i r n e l a o o ,e e c l G l P t t yc m c i r t n nl i n a H n g i i nf o a t i n o oof r e k h n o i P P O i b c 't C p i P n s v o e o r g gey n y R D C r P g a n n gt E a n W Oe i i aud m e Et g i n nsD e d l c n n n y r rs d n s S ye i r t a aeei a t R a Cl tC l i n a n W Wmh v n E H Oo n r W u t o h i T C EP ut a o a an r t o N Oy on W y C n noop l p E Et yy Ce t i iit a C i tt m y n g l l t e g yC nn ge t u r o oao H n S t uu rc n o u r rl t e i N nl oo ur u C b a aa n f n O ul CC b o o n C Cceo o r I oi nf C n e s gh a T CH nn en o l h h eap w A oo l E S k t k t t se t R kk tt k T s r s c r udsl p e E s rc ss cw N e o a e o onee e s P e oo aa ea I i Y G M s N S amt D e O i YR GG ML O t e P n h t t u T Y n a G o C u t N o N C 1 2 3 S 1 2 E C 1 2 3 I I N G R R A E W A M 8 E A I I I

E I R D U2 A S R O L e C g Na EP ~. E NO H P t E a L ) E T sno i t T a S c I i NL n O u IE m TN m AO G o TH N C SP I E L m RL A e AE N t ET G s L I y CY S S UC ( NN E E V r AG I e BA T n W C n AE E a TT L l ) AI E P CS S e F c F n y a 0 e r t n o t e m t o r n l A r i r a a d o r M h r t e C a c g l u e a l G r n a y i a c r l r D M o a o m S C. n t t t m r R o a n n e C A E S i c e e t N T t i m m s a d N a a R n s s y n r E n a N E u s s s i h a C i i T m e e l g u l b r N m s s o i d S o m e E o s s S h e r e T N r C u C v C C A A E t a Cl R r O a 0l Oo T C O a Ei I C E o El T y e O h a l ER SA T SC FC N t s a N t h A h E n o c i d t R t M u D G we r i E u E o g N g o P o G C e o I sa s N a b O S a b A / t l L mp e t N e i o A e Y A t s i N l m a C M a f d G b e t N t f a I oh S 1 E 2 S S O R S rt G I p R S E e E I V rv M R I oa B E C, A B C T Fh C E I L I I E I I S 1 l I

R P/0/ 6/5000/14 ENCLOSURE 4.2 Page of Date: DUKE POWER COMPANY CATAWBA NUCLEAR STATION i' EMERGENCY COMMUNICATIONS LOG TIME INITIALS ITEM NO. IN OUT INCIDENT OR MESSAGE ACTION i l N Y

m / ~' RP/0/B/5000/14 i '.3 l Page 1 of 1 i DUKE POWER COMPANY. CATAWBA NUCLEAR STATION INFORMATION FLOWCHART lx I i I OFFSITE COMMUNICATOR v l HEALTH PHYSICS -) RADIOLOGICAL DATA ANALYSIS COORD. DATA Part 2 Items #4, 5, 6,.7, 8, 9, & 10 l i i ? Part.1 V Item #4, 5, 6, &7 l OPERATIONS --) PLANT Part 2 lj ASST. OPERATING ENGR. STATUS

Items #1, 2&3 Part 3 Items #1 & 2 SUPERINTENDENT PROTECTIVE Part 1 TECHNICAL SERVICES ACTION Item d'8 RECOMMENDATION Y

APPROVAL FOR TRANSMISSION BY EMERGENCY COORDINATOR W

DUKE POWER COMPANY RP/0/ B/5000/14 CATAWBA NUCLEAR STATION.4 MESSAGE AUTHENTICATION MECHANISM Paga 1 of 1 This page is left intentional y blank. a e _ _ _ _. _ -. _. _ _ - - _ _ _ _ _ - -}}