ML20041G274

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPP 1.5-2 Re Notification & Communication,Epp 1.5-7 Re Radiological Dose Assessment & EPP 1.5-38 Re Containment Curie Level Estimation

ML20041G274
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	02/05/1982
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20041G047	List: B10432, Forwards Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPP 15-2 Re Notification & Communication & EPP 1.5-7 Re Radiological Dose Assessment ML20041G046 ML20041G274
References
PROC-820205-01, NUDOCS 8203190495
Download: ML20041G274 (76)

Text

{{#Wiki_filter:_ - - _ _ a o f I .) Docket No. 50-213 i t Attachment No. 1 Haddam Neck Plant Emergency Plan Procedures 1 i 1 I l I, l February, 1982 8203190495 820311 PDR ADOCK 05000213 F PDR

EMERGENCY PLAN PROCEDURES INDEX NUMBER REVISION TITLE DATE EPP 1.5-1 Rev. 4 Emergency Assessment 1/22/82 EPP 1.5-2 Rev. 8 Notification and Communication 2/5/82 EPP 1.5-3 Rev. 2 Notification of Unusual Event 9/1/81 EPP 1.5-4 Rev. 2 Alert 9/1/81 EPP 1.5-5 Rev. 2 Site Area Emergency 9/1/81 EPP 1.5-6 Rev. 2 General Emergency 9/1/81 EPP 1.5-7 Rev. 3 Radiological Dose Assessment 2/5/82 EPP 1.5-8 Rev. 3 EOF Emergency Radiological 1/28/82 Surveys EPP 1.5-9 Rev. 3 Onsite Emergency Radiological 1/28/82 Surveys EPP 1.5-10 Rev. 3 Off-Site Emergency Radiological 11/6/81 Surveys EPP 1.5-11 Rev. 1 Personnel Injuries 9/1/81 LPP 1.5-12 Rev. 1 Personnel / Vehicle Monitoring and 9/1/81 Decontamination EPP 1.5-13 Rev. 1 Personnel Accountability 9/1/81 EPP 1.5-14 Rev. 1 Evacuation and Assembly 9/1/81 EPP 1.5-15 Rev. 1

• Search and Rescue 9/1/81 EPP 1.5-16 Rev. 1 Fire 9/1/81 I

EPP 1.5-17 Rev. 1 Emergency Equipment 9/1/81 EPP 1.5-18 Rev. 1 Training and Exercise 9/1/81 l EPP 1.5-19 Rev. 1 Emergency Operations Facility 9/1/81 Activation EPP 1.5-20 Rev. 1 Re-entry and Recovery. 9/1/81 l EPP 1.5-21 Rev. 2 Director of Station Emergency 1/28/82 Operation l Page 1 of 2

r i EMERGENCY PLAN PROCEDURES INDEX 1 NUMBER REVISION TITLE DATE EPP 1.5-22 Rev. 2 Manager of Radiological-Con-1/28/82 sequence Assessment EPP 1.5-23 Rev. 2 Manager of Security 11/6/81 EPP 1.5-24 Rev. 2 Manager of Communications 1/28/82 EPP 1.5-25 Rev. 2 Manager of Public Information 1/28/82 EPP 1.5-26 Rev. 2 Manager of Control Room Operations 9/1/81 w EPP 1.5-27 Rev. 2 Manager of Onsite Resources 1/28/82 EPP 1.5-28 Rev. 2 Manager of Technical Support 1/28/82 EPP 1.5-29 Rev. 1 Emergency Dosimetry Issue 9/1/81 EPP 1.5-30 EPP 1.5-31 Original On-Shift Health Physics 9/1/81 Technician EPP 1.5-32 Rev. 1 Ping Iodine Channel Emergency 11/5/81 Procedure EPP 1.5-33 Rev. 2 Shift Supervisor's Staff 1/28/82 Assistant EPP 1.5-34 Original Emergency Telephone Testing 11/6/81 EPP 1.5-35 Original Explosion, Toxic Gas Release, 11/6/81 ,and Major Steam Release EPP 1.5-36 Original Use of Potassium Iodide Tablets 1/28/82 as a Thyroid Blocking Agent EPP 1.5-37 Original Manager of Dose Assessment 1/28/82 EPP 1.5-38 Original Containment curie Level 2/5/82 Estimation Page 2 of 2

EPP B.b5-2J-M Aomen-i ncv. s-en Original . FEB 0 51982 s PLANT OPERATIONS REVIEW COMMITTEE APPROVAL Al Connecticut Yankee ( Emergency Plan Procedure E 7 / hek EPP 1.5-38 .i * ] y& CONTAIUMENT CURIE LEVEL ESTIMATION o% AbPROVED BY $T ATioN $UPERINTENDENT ?j h $hn EFF ECTI'VE DAT E 1.0 PURPOSE 1 p p L-This procedure provides the methodology to be used to determine containment atmospheric curie levels based upon the containment high-range radiation monitor readings and/or containment grab samples. 2.0 RESPONSIBILITY The Manager of Dose Assessment is responsible for directing the Emergency Team in the implementation of this procedure. lie has the responsibility to inform the Director of Station Emergency Operations of this assessment and potential severity of the accident. 3.0 ACTIONS 3.1 The CY containment monitors are located on the charging floor approximately 90 diametrically opposite of each other. The remote monitor readouts are located on control room panel, PAM EE. Record these readings, in R/hr on line 1 of Attachment 1. 3.2 Record the time of monitor reading, relative to reactor shutdown or trip time, on line 2 (i.e. if reading is taken 30 minutes after reactor trip, t = 0.5 hrs). 3.3 Using the lowest monitor dose rate reading obtained from .line 1, proceed to the monitor response curve, Attachment 2, and obtain the containment activity concentration, in uCi/ce, which corresponds to the dose rate reading. This concen-tration must be from the closest. time-dependent curve (i.e. as a funct lon of post-shutdown relative time, line 2). Record this concentration on line 3. 3.4 Multiply the containment concentration on line 3 by the containment volume and convert to Ci to obtain an estimate of the containment airborne ' curie level. Page 1 of 7

EPP 1.5-38-C Original FEB 0 51982 3.5 Determine the amount of nobic gases in the containment by multiplying the curie icyc1 from line 3 by the fraction of noble gases as a function of time as obtained from, for the post-shutdown time indicated on line .2. Enter the appropriat.e values on line 4. 3.6 To determine an estimate of the fraction of failed fuel, divide the containment nobic gas activity, as obtained from line 4, by the core inventory noble gas activity as obtained from Attachment 4, for the time specified on line 2. Enter values on line 5. 3.7 A second method of determining the containment curie levels and estimating the severity of the accident consists of using the results of containment grab samples. Once these results are obtained, in uCi/cc, steps 3.4 through 3.6 of this procedure should be performed. 3.8 Attachment 5 presents the basis and general assumptions used in the calculation of the monitor response to containment activity. 3.9 Report the results of all calculations to the Director of Station Emergency Operation. 4.0 ATTACllMENTS Attachments Title Page 1 Containment Curie Level Estimation Worksheet 2 Containment Ili-Rad Monitor Response Curve 3 Noble Gas Fraction of Total Activity 4 Total Inventory of Noble Gases 5 Bases for Monitor Response Curve Calculation 5.0 PROCEDUPE CROSS REFERENCE ~ 5.1-EPP 1.5-7 Radiological-Dose Assessment Page 2 of 7 l 1, 'N l i

taa n f.m = n e s Original FEB 0 5 1982 Attaciunen t 1 Containment Curie Level Estimation Worksheet Date: Time: Name: 1. Containment Monitor Reading (R/hr) CD #1 CD #2 2. Time of Monitor Readings (relative to RX shutdown time) (hrs) t = 3. Containment Activity Concentration (From Attaciunent 2 or grab sample results) (uC1/cc) x 10-6 Ci/uci x 6.315 E + 10 cc = Total C1 4. Total C1 (C1) x Ci of N.C.

Fraction x 100

5. Ci of N.C. _(Ci) + = Fraction of % Failed Fuel' N.C. Inventory Failed Fuel I a 1 l l i Page 3 of 7 o 7..,--._... .m., ,9

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=. EPP 1.5-38-C Original FEB 0 51982 ~ At taclunent 3 Noble Gas Fraction of Total Activity vs. Post-Shutdown Time. Post-Shutdown Time Olrs) Noble Gas Fraction 0 .74 0.5 .75 2.0 .87 4.0 .91 12.0 .98 48.0 1.00 72.0 1.00 Page 5 of 7 x ~

EPP 1.5-38-C Original i - ' ~ FEB 0 51982 ! Total Inventory of Noble Gases vs. Post-Shutdown Time Pont-Shutdown Time (llrs) 100% Noble Gan Inventory (C1) 0 6.17 E+8 0.5 3.65 E+8 2.0 2.97 E+8 4.0 2.59 E+8 12.0 1.90 E+8 48.0 1.02 E+8 72.0 7.94 E+7 e e Page 6 of 7 9 s a

EPP 1.5-38-C Original FEg 0 51982 ~ s' i Bases for Monitor Response Curve Calculation The details behind the calculation of the monitor response curve in this procedure are on file with the NUSCo Radiological Assessment Branch. Ilowever, the basic assumptions and methodologies include: 1. The ratio of nobic gases and iodines are calculated based upon the total core inventory. 2. The reactor has been operating at steady state power for a sufficient period of time to allow all noble gas and halogen radionuclides to reach equilibrium. 3. The initial isotopic mixture assumes that 100% of available noble gases and 50% of the available iodines are released to the containment atmosphere and homogenously mixed. Any other initial mixtures less than 100% of the noble gases or 50% of the iodines will consist of the same relative proportions. 4. The exact time of the release of activity into the containment and the reactor trip time is known. 5. Platcout of radioiodines and particulate radioactivity on reactor component surfaces has negligibic effect on the monitor response. 6. The monitors are located approximately 90 from each other and are physically close together, llence, the dose rate readings should be identical. A difference in dose rate readings may be due to a localized cloud of nobic gases or some othen source term such as piping containing high coolant activity, llence, the monitor with the lowest dose rate reading should be used to determine the containment airborne activity concentration. 7. One CAR fan is assumed to be operating independently after t = 1 minute until t = 15 minutes at which time three CAR fans are assumed to be operating. As a result, the halogen source term is decreased substantially. i j Page 7 of 7

N EPP 1.5-2-C Rev.8 Aounn-i nov. s-si FEB 0 5 :962 ~ PL NT OP RATI NS REVIEW COMMITTEE APPROVAL fi Connecticut Yankee 7-Emergency Plan Procedure / g ~j Ho. EPP 1.5-2 -- %aw m\\ 1 NOTIFICATION AND COM4UN CATION '~ YEkDY ST&ATioN () UPERI ENDENT u ~ EFFECTIVE DATE d ~)~ W7,7/ 1.0 PURPOSE This procedure provides instructions to perform the following: Notify the applicable agencies and personnel in emergency o situations. Activate the On-Site Emergency Organization via communicaticr; o with cmergency. response personnel. Establish communication interfaces with local, sente, and federal o agencies. Notify applicable agencies and personnel for reportable situations o that do not require activation of emergency plan. Maintain required records. o 2.0 RESPONSIBILITY 2.1 The Shift Supervisor and/or Duty Officer shall ensure that this procedure is impicmented. 2.2 The Shift Supervisor Staff Assistant (SSSA) is responsibic for carrying out the actions o'f this procedure. 3.0 ACTIONS 3.1 If an emergency action 1cvel has not been reached, refer to Attachment 8, Reportable Events for required notifications. NOTE: Refer to Attachment 11 and 12 to determine when a rele.:sc is reportable. Page 1 of 46 u

. _ = EPP 1.5-2-C Rev. 8 FEB 0 51982 l((~. ' ~ 3.2 Incident classification coif, rox, or Echo, Attachments 1 uul 2). LEVEL ONE Notification. l These classification icycls do not require activation of the emergency organization. 3.2.1 Notify duty officer. i NOTE: Notify Unit Superintendent if not the same individual. I j 3.2.2 Write telephone call-back message on Incident Feport form (Attachment 3) and record on code-a-phone recorders. 3.2.3 Place radio-pager message system in LEVEL ONE and initihte automatic page. 3.2.4 Within 30 minutes of initiating radio-pager message, review call-back recording to verify that ALL LEVEL ONE pagers have responded. Record on attachment 4. If the state DEP does not respond in one hour call the 24 hour number at the DEP office (566-3333). i l 3.2.5 If the radio-pager fails, telephone LEVEL ONE personnel listed in attachment 7. 3.3 Notification of Unusual Event (see attachment 2). LEVEL TWO Notification. 3.3.1 Notify duty officer. NOTE: Notify Unit Superintendent if not the same-individual. 3.3.2 Write telephone call-back message on Incident Report form (attachment 3) and record on code-a-phone recorders. 3.3.3 Place radio-pager message system in LEVEL TWO and initiate ~ automatic page. 3.3.4 Within 30 minutes of initiating radio-pager message, review call-back recording to verify ALL LEVEL TWO pagers have I responded. Record on attachment 4. NOTE: Call back verification need only be conducted on the initial radio-page, change of classification level or when specific instructions direct individuals to call back for further instructions. 3.3.5 Telephone the State Police in Colchester via commercial tele-L phone within one hour to provide a backup to the radio-pager. i Record on Backup Phone-Call Message to State Police, attachment 5. i Page 2 of 46 t

EPP 1.5-2-C Rev. 8 3.3.6 Attempt tu notify via cornercial telephone those FEB 0 5 B32 communities which have not responded to the level two radio-page. (Refer to attachment 7). Request backup assistance from the appropriate o State Police Barracks if attempt to notify non-responding communitics via commercial telephone is unsuccessful. (Refer to Attachment 10) 3.3.7 Telephone the NRC within one hour after incident classification (as required by 10CFR50.72) using attachment 6. o NRC licadquarters - llotline o NRC Regional Office - Telephone line (During normal business hours ONLY) NOTE: If the NRC llotline fails to operate, refer to A, Emergency Telephone Numbers for NRC Notification. 3.3.8 If the radio-pager system fails, telephone all LEVEL TWO personnel listed in attachment 7, excluding the local communitics. NOTE: Telephone calls to the local communities will be made by the State Police if the radio-pager is incperable. 3.4 Alert, Site-Area Emergency, and General Emergency (see attachment 2). LEVEL TWO Notification. 3.4.1 Notify duty officer. ~ NOTE: Notify Unit Superintendent if not the same individual. 3.4.2 Write telephone call-back message on the Incident Report form (attachment 3) and record on code-a-phone recorders. 3.4.3 Place radio-pager system in LEVEL TWO and initiate automatic page. 3.4.4 Activate automatic page for level-two radio-pager holders within 15 minutes after incident classification. Provide updates to LEVEL-TWO radio-pager holders every 30 to 60 minutes. 3.4.5 Within 30 minutes of the initial radio-pager message, review the call-back recording to verify that ALL LEVEL TWO pagers have responded. Record on attachment 4. NOTE: Call back verification need only be conducted on tho initial radio-page, change of classification Icvel or when specific instructions direct individuals to call back for further instructions. Page 3 of 46 . -J

.~ EPP 1.5-2-C Rev. 8-pg 0.. 'e' 3.4.6 Telephone the State Police in Colchester via the dedicated line located on the SSSAs concole, within one hour to provide 1 a backup to the radio-pager. Record on Backup Phone-Call Hessage to the State Police, attachment 5. 3.4.7 Attempt to notify via commercial telephone those communities which have not responded to the level two radio-page. (Refer to attachment 7). Request backup assistance-from the appropriate State e Police Barracks if attempt to notify non-responding communities via commercial telephone is unsuccessful. (Refer to Attachment 10). 3.4.8 Telephone the NRC within one hour after incident classification (as required by 10 CFR50.72) using attachment 6. NRC lleadquarters - llotline o NRC Regional Office - Telephone line e (During normal business hours ONLY) NOTE: If the NRC hotline fails to operate, refer to A, Emergency Telephone Numbers for NRC Notification. 3.4.9 If the radio-pager system fails, telephone all LEVEL '1VO personnel listed in attachment 7, excluding the_ local communities. NOTE: Telephone calls to the local corrmunities will be made by the state police if the, ~ C radio-pager is inoperabic. ? 3.5 Notify support agencies for assistance using attachmerit 9 for telephone numbers. i 4.0 'ATTACilMENTS/EXilIBITS Attachment Titic Page 1 State of Connecticut Nucicar Incident Classification 5 Scheme l 2 NRC/ State of Connecticut Emergency Classification 10 Interface 3 Incident Report Form 11 l 4 Call-Back Verification Checklist 14 5 Backup Phone Call Message to State Police 16 6 Checklist for Notification of Significant Events 17 6A Emergency Telephone Numbers for NRC Notification 21 7 Notification Guide 22 8 Reportable Events 26j 9 Assistance Guide 35 10 Connecticut State Police (CSP) Contact Points

40' i

. 41 ~ l 11 Reportable Releases 12 Bases for Attachment 11 43 i +,, /- 5.0 PROCEDURE CROSS REFERENCE l None y N Page 4 of 46 x u.~_

(~ EPP 1.5-2 C s ATTACIDIENT 1 i Resision 8 ~~. STATE OF CONNECTICUT NUCLEAR INCIDENT CLASSIFICATIdN SCtlEME x ' ,i, j sv st6te of Connecticut ~ Incident Class (2,3) & IncidentDe[scription Notification Actions (I) Protective Actions Plant Classification ~ ~ 6j A. GENERAL ~ 1. COLF Pbdioactivematerialtrans-

• Licensee (5) notify State,' *Linit spread of contam-portation accident outside DEP (4) fination and initiate',~~

' ', ? cican bp' a fixed facility. s, / .i 2. FOX Lost radioactive material'

• Licensee notify State

.

• Assist in source. recovery f

in excess of Title 10, DEP(4) j e r f, f "s, ~ / CFR30.71, Schedule B - ~' Quantities-r / ] l f_ a B. FIXED NUCLEAR FACILITY-SPECIFIC 4. y 1. ECHO [_6]Minorincidentofgeneral

• Licensee call appropriate None o

(Unusual interest but no public-local agency for fire / Event with-i hazard with no radioactive police / ambulance out Releases)' releases '[

• Licensee notify State DEP (4) 2.

DELTA Incident public interest-

• Licensee promptly notify None (Unusual but no public hazard with state and local officials Event with-unplanned radioactive vit'hin 10 miles out Releases) releases such that_ site x

boundary plume do'ses 're ~ '4":/,, .j a 3 less than 0.005 REM to the l I t' - ~ whole body and[or less than 0.025 REM to the ~ ,- thyroid from plume exposure pathways. 1 -/ f 1 M i m g 01 g M i

i EPP 1.5-2-C i ,3evisica S ATTACHMENT 1 (Continued)

STATE OF CONNECTICUT NUCLEAR INCIDENT CLASSIFICATION SCHDIE

~ State of' Connecticut ~ Incident Clase(2,3) & Incident Description Notification Actions (I) Protective Actions Plant Classification 3.s CHARLIE-Incident which has a

• Licensee promptly notify
• Licensee activate EOC ONE potential for or has a state and local officials
• State activate EOC if

( Ale rt) radioactive release with within 10 miles appropriate i projected site boundary

• State / local authorities
• Locals put key EOC personnel plume doses between 0.005 provide public with infor - on standby and 0.05 REM to the whole mational messages only if
• State / licensee monitor and between 0.025 and 0.25 appropriate plume and food pathways and REM to the thyroid project food pathway doses.

l Assess need to take action if FDA's Preventive PAG 1evels for food pathways exist m c n 4. CHARLIE 2' Incident which has a

• Licensee promptly notify _
• Licensec/ State / Local potential for or has a state and local officials Authorities activate EOCs

~ TWO (Site) ! radioactive release with within 10 miles

• Stafe/ licensee monitor m

projected site boundary

• If necessary State / Local plume and food pathways q

y plume doses c. 0.05 to 1.0 authorities promptly

• State consider putting milk REM to the whole body and/

activate public notification animals o.n stored feed in i or 0.25 to 5.0 REM to the system within 2 miles downwind direction ot*. to thyroid

• State / local authorities distances,where food path-provide public with way ' doses ' corresponding to

. periodic updates on food FDA's Preventive PAG's ? pathway actions occur g( n p-ao clll> -N. h, e

EPP 1.5-2-C ATTACmiENT 1 (Continued) Revision 3 STATE OF CONNECTICUT KUCLEAR INCIDENT CLASSIFICATION SCHDIE 'g State of Connecticut Incident Class (2,3) & Incident Description Notification Actions (l) Protective Actions Plant Classification 5. BRAVO Incident which has a

• Licensee promptly notify
• Licensce/ State / Local potential for or has State and Local officials Authorities activate ECCs radioactive releases with within 10 miles
• State / Local Authorities projected site boundary
• State / Local authorities implement immediately take plume doses of 1.0 to 5.0 promptly activate public shelter and access centrol REM to the whole body and/

notification system within for 2-mile radius and 5-or 5.0 t o 25.0 REM to ' the 5 miles mile downwind. Assess need thyroid

• State / Local Authorities to extend distance to 10 provide public with n'iles periodic updates on
• State / Local Authorities, protective actions if not constrained, evacuate 2-mile radius and out to downwind distances where plume exposure levels occur
• Stateilicensee monitor y

plume and food pathwayo g i

• State put milk animals on stored feed in downwind w

o direction out to 10 milet, m and assess need to extend u distance to areas where the FDA's Preventive PAG levels for food pathways exist

• State control milk / food distribution, as necessary, from affected area where the FDA's Emergency PAC's levels for food pathways exist m

N CD o C/t (O SS

Revision 8 ATTAcatEh71 (Continued) STATE OF CONNECTICUT NUCLEAR INCID"NT CLASSIFICATION SCHDIE State of Connecticut' Notification Actions (l) Protective Actions j Incident Class (2,3) & Incident Description Plant Classification 6. ALPHA Incident which has a

• Licensee promptly notify
• Licensee / State / Local potential for or has state and local officials Authorities activate EOCs radioactive releases with within 10 miles
• State / Local Authorities projected site boundary
• State / Local Authorities implement immediately take plume doses of greater than promptly activate public shelter and-access control 5.0 REM whole body and/or notification system within for 2-mile radius and 10-mile downwind 25 REM to the thyroid 10 miles
• State / Local Authorities-
• State / Local Authorities must implement evacuation provide public with' if not constrained out to periodic updates on 2-mile radius and 5 miles protective actions downwind. Assess need to extend distance to where plume exposures exceed class Bravo. levels.

\\

• State / Licensee monitor plume and food pathways
• State put milk animals within 10 miles in downwind direction on stored feed and assess need to extend R

unit to distance where the FDA's Preventive PAG es Icvels exist for food pathways

• State control milk / food distribution, as necessary, from affected area where the FDA's Emergency PAG

-levels exist for the food pathways N TTl U3

• c2 U1 O

N O S

EPP 1.5-2-C Revision S

• NOTES in the case of the licensee, notification of i

As defined in NUREG-0654, prompt notification means: State and Local officials within L5 minutes of classifying the incident and, in the case of State / 1. Local actions, notification of the public within 15 minutes of deciding public alerting and notifi-cation is necessary. State agencies promptly notified by licensee are Governor's office, state DEP, state police, state OCP. Classification of events and notification shall be done by the licensee for class, Delta, Charlie-50.72 one, Charlie-two, Bravo and Alpha events within one hour of occurrence, in accordance with 10CFR 2. and Connecticut State Regulations Section 19-13-E51. For class Golf, Fox and Echo incidents, if the event is reportable to NRC in.accordance with 10CFR50.72, then these actions shall be accomplished within one hour of occurrence. 3. 4.' State DEP or their designee. 7 n 5. Licensee can also mean facility operator. [ State Incident Class Echo is a more conservative classification of events than the NRC's Class because it covers items of general public interest and all t 6. e NUREG 0654 Unusual Event s-of the 10CFR 50.72 reporting items. i i 5 h l i i o C A

EPP-1.5-2-C Rev:ision 8 ATTACID4ENT 2 NRC/ STATE OF CONNECTICUT DIERGENCY CLASSIFICATION INTERFACE '-{ NOTIFICATION NRC STATE SITE BOUNDRY PLUME DOSES LEVELS by ACTUAL or POTENTIAL by specific EAL groupings radiation releases projected or actual doses group page N/A GOLF N/A LEVEL ONE FOX N/A LEVEL ONE N/A N/A EC110 N/A LEVEL ONE eI UNUSUAL EVENT EAL's 1-14, excluding #2 ECIIO NONE LEVEL ONE I5 less than 0.005 RDI, whole body jo UNUSUAL EVENT l "' EAL #2 ONLY DELTA less than 0.025 RDI, thyroid LEVEL TWO 's between 0.005 and 0.05 RDi, whole body ALERT CIIARLIE ONE between 0.025 and 0.25 RD!, thyroid LEVEL TWO between 0.05 and 1.0 RDI, whole body SITE AREA EMERGENCY CHARLIE TWO between 0.25 and 5.0 RDI, thyroid LEVEL TWO between 1.0 and 5.0 RDI, whole body GENERAL EMERGENCY BRAVO between 5.0 and 25.0 RDf, thyroid LEVEL TWO greater than 5.0 REM, whole body GENERAL EMERGENCY ALPilA , greater than 25.0 RBI, thyroid LEVEL TWO rn m o ~f-N

EPP 1 5-2-C Revision 8 ATTACIDfENT 3 D 61982 INSTRUCTIONS FOR FEB Incident Report Form This message is prepared by the facility operator and put on the telephone 1. call back system recorders, or if the pager telephone call back system is inoperative use alternate means as specified in procedures. Individuals receiv-2. The facility operator sends out radiopager messages. ing this message call-in to get more information from the telephone re-cording machines. They also 1 cave their names and affiliation and time at the tone at the end of the recorded message. 3. Individuals calling in to the telephone recorder should use this form to copy down the information. The preparer of the message (facility operator) should not use technical 4. jargon, abbreviations, etc. This person should use general layman lan-guage as much as possible. The preparer of the message should say "information not available" and 5. "not applicable" when appropriate. 6. The following is the relationship between the State of Connecticut State Nuclear Incident Classification Scheme and the NRC Incident Classes as given in NUREC-0654. CT. State Class NRC Class EC110 Unusual event without radioactive releases. DELTA Unusual event with radioactive releases. CllARLIE-ONE Alert CilARLIE-TWO Site Area Emergency BRAVO General emergency without major breach in containment integrity. ALPilA Gene,ral emergency with major breach in containment-integrity.

7.. The message prepared (facility operator) should use CIIARLIE-ONE as the mechanism for generating an alert if it is apparent that the potential exists for an event more serious than DELTA, but event classification is not yet final. This will enable the local community, state-agencies, and utility emergency staf f to begin assembly at their emergency operations l

centers in a timely manner while the accident assessment is being done. l 1 1 Page 11 of 46

EPP 1. 5-2-C Revision 8 10B1 ATTACllMENT 3 (Continued) 5 INCIDENT REPORT NM (Telephone Call-Hack Message Form) Report Number (Instructions on Back) (Optional) 1. This is of (name 6 title of person sending message) (organization) 2. In accordance with the. Stete Emergency Plan, this report concerns the ~ llADDA'l NECK Nuclear Power Station. 3. This IS / IS NOT a drill. 4. A State of Connecticut Incident Class (circle worst case) COLF FOX ECII0 DELTA CllARLIE-ONE C11ARLIE-TWO (ALERT) BRAVO ALPilA is being reported on at (date) (time) 5. 1F GOLF, FOX, EC110, DELTA, CIIARLIE-ONE (ALERT) skip to item 10. 6. The affected zones are as follows: (Enter only if distance specified in classification scheme is extended - Example Al, B1, Cl thru A10, BIO, C10) Class Zones Time ALPIIA thru f BRAVO thru CllARLIE-TWO thru 7. The wind is from the into at FTi!. (example NNW) (example SSE) 8. It is expected to remain in the direction for hours. 9. It IS / IS NOT expected to shif t and blow from (example NNW) 10. The event description follows: 11. Access to the site llAS / IIAS NOT been terminated. 12. The following has been requested: FIRE /, POLICE / AMBULANCE / (other) s Pase 12 of 46

EPP 1. 5-2-C Revision C ATTACllMr.NT 3 (Continued) i 13. The plant status is STABLE / UfPROVING / DECRADING. J 14. A further report W11.L / WILL NOT be y,1ven, 15. Please J eave your name, af filiation and time at sound of tone. END OF MESSAGE Page 13 of 46

EPP 165-2-C Revision S ATTACID1EhT 4 CALL-BACK VERIFICATION CllECKLIST s Level 1 Code A Phone # Time Date CY Duty Officer NU Operation Duty Officer EU Public Affairs Duty'.0fficers Department of Environmental Protection Mr. Sillin Mr. Ellis Mr. Fee Mr. Counsil Mr. Cagnetta Mr. Opeka Level 2 State Agencies Covernors Office Office of Civil Preparedness State Police at Colchester at liartford at Westbrdok ~~ at Meriden Page 14 of 46 a-',ev f.- e-v+- w-.r

EPP 1.5-2-C Revision 8 ATTACl! MENT 4 (Continued) g5 $N, Code A Phone # Time Date_ Level 2 Towns Chester Colchester Deep River Durham East flampton Eusex linddam East lladdam liebron Killingworth Lyme Madison Marlborough Middlefield Middictown Portland Salem Westb rook ETA Level 2 CY Ma6ager of l'.xternal Communication Manager of Radiological Assessment Manager of Onsite Resources 46 Page 15 of

f EPP 1.5-2-C Revision 8 FEB 0 51992 ATTACIDfENT 5 BACKUP P110NE CALL MESSAGE TO STATE POLICE (1) TilIS IS Tile IIADDAM NECK NUCLEAR PuANT (2) A STATE INCIDENT CLAS'S DELTA /CIIARLIE-ONE/CllARLIE-Th'0/BRAV0/ ALPilA MESSAGE WAS SENT OUT OVER Tile RADIOPAGER (3) TAKE FOLLOW-UP ACTION WITil STATE DEP Name of. Sender Date Time Name of Receiver (State Police) 9 5 e 4 \\ 46 Page 16 of

EPP 1.5-2-C I Revision 8' s r-Ebb ATTACIINENT 6. CllECKLIST FOR NOTIFICATION OF SIGNIFICA';T EVENTS MADE IN ACCORDANCE WITil 10 CFR 50.72 A. Identification: Date Time Name of Person Making Report Licensee Connecticut Yankee Atomic Power Company Facility Affected IInddam Neck Applicable Part of 10 CFR.50.72 B.

== Description:== Date of Event Time t Description of What IIappened C. Consequences of Event: (Complete depending on type of event) Inj uries Fatalities Contamination (personnel) (property) L j Overexposures (known/possible) Safety llazard (descr.ibe - actual / potential) i Offsite Radiation Levels Integrated Dose Location i Meterology (wind speed) From (direction) l Weather Conditions (rain, cicar, overcast, temperature) Equipment / Property, Damage D. Cause of Event: 1' i 1 1 i Page 17 of 46 i

EPP 1. 5-2-C evision 8 ATTACllMENT 6 (Continued) E. Licensee Actions: FEB 0 5 1992 Taken 1 Planned _ _ _ Emergency Flan Activated (Yes/No) Classification of Emergency 1 Resident Inspector Notified (Yes/No) State Notified (Yes/No) Press Release Planned (Yes/No) News Media Interest (Yes/No) Local / National F. Current Status: (Complete depending on type of event) 1. Reactor Systems Status Power Level Before Event After Event Pressure Temp. (thot) (tcold) RCS Flow (Yes/No) Pumps On (Yes/No) llent Sink: Condenser Steam Atm. Dump Other Sample Taken (Yes/No) Activity Level ECCS Operating (Yes/No) ECCS Operable (Yes/No) ESF Actuation (Yes/No) PZR or RX Level Possible Fuel Damage (Yes/No) S/G Levels Feedwater Source / Flow Containment Pressure Safety Relief Valve Actuation (Yes/No) Containment Water Level Indication Equipment Failurts 1 See Emergency Action Levels, Appendix 1, NUREG-0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. 46 Page 18 of

EPP 1.5-2-C pgg 0 51333 ATTACIDIENT 6 (Continued) Revision 8 Normal Offsite Power Available (Yes/No) Major Busses / Loads Lost Safeguards Busses Power Source D/G Running (Yes/No) Loaded (Yes/No) 2. Radioactivity 1:elease Liquid / Gas Location / Source Release Rate Duration Stopped (Yes/No) Release Monitored (Yes/No) Amount of Release Tech Spec. Limits Radiation Levels in Plant Areas Evacuated 3. Security / Safeguards 2 nomb Threat: Search Conducted (Yes/No) Search Results Site Evacuated (Yes/No) Intrusion: Insider Outsider Point of Intrusion Extent of Intrusion Apparent Purpose Strike / Demonstrations: Size of Group Purpose Sabotage: Radiological (Yes/No) Arson (Yes/No) Equipment / Property Extortion: Source (phone, letter, etc.) Location of Letter Demands 2 See 10 CFR 73.71(c), effective April 6, 1981. \\ 46 Page 19 of

EPP 1. 5-2-C ' c.0 0 5193E Revision 8 ATTACllMENT 6 (Continued) General: Firearms involved (Yes/No) Violence (Yes/No) Control of Facility Compromised or Threatened (Yes/No) Stolen / Missing Material Agencies Notified (FBI, State Police, Local Police, etc.) Media Interest (present, anticipated) O e e .A* \\ Page 20 of 46

EPP 1.5 Rev. B FEB 0e 19 8'l ATTACllMENT 6A \\ EMERGENCY TELEP110NE NUMBERS FOR NRC NOTIFICATI JN TELEPIIONE NUMBER TELEP110NE SYSTEM 1. Emergency Notification System (Lift Receiver from Cradle) to NRC Operations Center 2. Commercial Telephone System to 301/492-8111 NRC Operations Center (via Bethesda Central Office) 3. Commercial Telephone System to 301/427-4056 NRC Operations Center (via Silver Spring Central Of fice) 4. Ilealth Physics Network to

• 22 (Touch-Tone) 22 (Rotary Dial)

NRC Operations Center 5. Commercial Telephone System to NRC Operator (via liethesda Central Of fice) 301/492-7000 Page 21 of 4'6

EPP 1.5-2-C Revision 8 ATTACHMENT 7 EB 0 5 1982 I. NOTIFICATION CUIDE NOTIFICATION TELEPHONE NUMBERS NOTIFICATION DOCUMENTATION ORGANIZATION LEVEL TITLE NAME BUSINES3 HOME DATE TIME PERSON CONTACTED Connecticut 1&2 Station Yankee Superintendent R. H. Graves X Notify all Unit listed Superintendent J. H. Ferguson X. Services Superintendent R. Z. Test X. Security Supervisor G. R. Hallberg X Security ,3 Shift Supv. X. M \\ N o Northeast 1&2 e-Utilities Duty Officer T. Dente t Nuclear } Engineering and Duty Officer

3. Dietz Operations Notify One Duty Officer H. Wong of listed starting with Duty Duty Officer J. Quinn Officer.

l Duty Officer W. Bartron NUSCO Duty Officer Night-Line Duty Officer 1-666-3944 h

... _ _ _.. _. _ _ _EPP-1.5-2-C_. _ _. _, _ t Revision 8 ATTACINENT 7 (Continued) EB 6 o E2., NOTIFICATION CUIDE NOTIFICATION TELEPHONE NUMBERS NOTIFICATION DOCUMENTATION ORGANIZATION LEVEL TITLE NAME BUSINESS HOME DATE TIME PERSON C0YTACTED* Supt. Nuclear Operation J. F. Opeka Sr. Vice Pres. Nuclear Eng/ Ops W. G. Counsil' Exec.Vice Pres. Nuclear Eng/ Ops W. F. Fee ] i 3 p ~ Northeast 1&2 Utilities j2 System Duty Officer A. E. Nericcio X iS Cormunica-lj tion N. o,, Duty Officer E. C. Hill 4 Notify one e of listed starting with Duty Duty Officer-R. A. Winkler' Officer R. S. Bromberg, Duty Officer i Duty Officer Manager System G. R..DoughtyJ Nuclear Info. i N. 1 1 1 <s-

E@P f.M-N-s l Revision S ATTACHMENT 7 (Continued) FEB 0 51982 'v 1 NOTIFICATION GUIDE f. NOTIFICATION TELEPil0NE NUMBERS bbTIFICATION DOCU)ENTATION ORGANIZATION LEVEL TITLE NAME BUSINESS HOME DATE TIME PERSON CONTACTED State Dept. -Radio of Environ-1&2 Commissioner S. Pac Pager mental No response to GOLF, FOX, ECHO. Protection radiopage within 1 hr. of initiation Nuclear Use Hot Regulatory 2 Region I Line to Comaission I&E --- - ~ ~ - Bethesda Resident In spector Tom Smith State Police 2 Colchester Dispatcher Northeast As Manager Utilities Needed Ins. & Claims R. M. Seger go O Insurance analyst R. R. Iffland - Local 2 Chester First Selectman Communities Chester First Selectman Deep River First Selectman Durham First Selectman East Haddam First Selectman-Chief Administrative East Hampton Officer Essex First Selectman IInddam First Selectmi o liebron First Selectman Killingworth First Selectman' Lyme First Sel ectman Madison First Selectman! Marlborough First Selectman Middlefield First Selectman yddletown Mayor

1ggf mog t Revision F. ATTACHENT 7 (Continued) 0051932. NOTIFICATIOS CUIDE NOTIFICATION TELEPHONE NUMBERS NOTIFICATION D0'CUMENTATION ORGANIZATION LEVEL TITLE NAME mt91 NESS.HOME DATE TIME PERSON CONTACTED Local 2 Portland First Selectman Communities Salem First Selectman 'Westbrook First Selectman 2 0 = \\ O e 9 e G em emo ummu w- - ***

c EPP 1.5 C Revision 8 ATTACHMENT 8 i Eg 0 51932 REPORTABLE EVENTS STATE STATE NRC NOTIFICATION EVENTS DIERGENCY REPORTING REPORTING LEVEL CLASSIFICATION REQUTREMENT REQUIREMEh7 1 General Emergency A or.B within 15 Within 1

min, hour Hot Line 2

2 Site Area Emergency C2 Within 15 Within 1 min. hour Hot Line 2 3 . Alert Emergency Cl Within 15 Within 1 ~ min. hour Hot Line 2 4 Notification of Unusual Event D Within 15 Within 1 [ min. hour Hot Line-2 o 5 Any event requiring initiation of the s .licens,ec's emergency plan or any sec-tion of that plan. 6 The exceeding of any Technical Speci-E Within few With I fication Safet.y Limit. hours hour Hot Line 1 Note 1 7 Any event that results in the nuclear E Within few Within 1 hours hour Hot Line 1 power plant, not being in a controlled or expected condition while operating Note 1 or shut down. NOTE 1 10CFR50.72 item. Report on NRC Hot Line using attached form. During normal hours telephone regional office also (see noti-fication guide attached). O e

EPP 1.5-2-C ATTACHMENT 8 (Continued) R,evision 8 REPORTABLE EVENTS FEB 0 51932 STATE STATE NRC NOTIFICATION EVENTS EMERGENCY REPORTING REPORTING LEVEL CLASSIFICATION REQliiREMENT REQUIREMENT 8 Any act that threatens the safety of E Within few Within 1 1 the nuclear power plant or site per-hours. hour Hot Line sonnel, or the security of special Note 1 " ' k <_ ', nuclear material, including instan-7 ~,, ces of sahatoge or attempted sabot-age. 7u#s %3 n 9 Any event requiring initiation of E Within few Within 1 4' .di shutdown of the nuclear power plant hours hour Hot Line in accordance with Technical Speci-Note i fication Limiting Conditions for Operation. IJ 10 Personnel error,or procedural in-E Within few Within 1 1 adequacy which, during normal hours hour Hot Line m g operations, anticipated operation-Note 1 al occurrences, or accident condi-tions, prevents or could prevent, by itself, the fulfillment af the safety function of those struct-ures, systems, and components im-portant to safety that are needed to (i) shut down the reactor safely and maintain it in a safe shutdown condition, or (ii) re-move residual heat following reactor shutdown, or (iii) limit the release of radioactive mat-erial to acceptable levels or re-duce the potential for such re-lease. Note 1 10CFl:50.72 item. Report on NRC Hot Line using attached form. During normal hours telephone regional office also (see noti-fication guide attached).

EPP 1.5-2-C \\ ATTAC1DIENT 8 (Continued) ~ FEB 0 31992 REPORTABLE EVENTS STATE STATE NRC NOTIFICATION EVENTS EMERGENCY REPORTING REPORTING LEVEL CLASSIFICATION REQU1RCMEhT REQUIREMENT 11 Any event resulting in manual or E Within few Within 1 1 automatic actuation of Engineered hours hour Hot Line Note 1 Safety Features, including the Reactor Protection System. 12 Any accidental, unplanned, or un-D Within 15 Within 1 2 controlled radioactive release,

min, hour Hot Line Note 1 (Normal or expected releases from maintenance or other operational activities are not included.)

13 Any fatalit y or serious injury occur-E Within few Within 1 1 -s ring on the site and requiring trans-hours hour Hot Line Note 1 5 port to an offsite medical facility 4 for treattmnt. e ~. 14 Any serious persontel radioactive E. Within few Within 1 1 contamination requiring extensive hours hour Hot Line onsite decontamination or outside Note 1 assistance. 15 Any event meeting the criteria of E Within few Within 1 1 10 CFR 20.403 for notification. hours hour Hot Line Note 1 Note 1 10Cif>0.72 item. Report on NRC Hot Line using attached form. Durin;; normal hours telephone regional office also (see noti-fication guide attached). 1 I e. 9

~~ ATTACEMENT 8 (Continued) EPP 1.5-2-C FEp 0 5 1S87 REPORTABLE EVENTS Revision 8 STATE STATE NRC NOTIFICATION EVENTS DIERGENCY REPORTING REPORTING LEVEL CLASSIFICATION REQUIRD1F,NT REQUIRDIENT 16 Strikes of operating employees or E Within few Within 1 1 security guards. or honoring of hours hour Hot Line Note 1 picket lines by these employees. 17 Event of significant public interest E Within few I but of no public hazard. No radio-hours active release. Includes but is not limited to: 2

a. Any unscheduled shutdown esti-E mated to last more than 48 hours.

(State) we 3,

b. Any scheduled shutdown for testing, maintenance, or refueling expected I

a-* to last more than 72 hours. (State)

c. Derating caused by Regulatory Action.

(State)

d. Derating greater than 50% caused by l

equipment malfunction lasting more than 72 hours. (State) Note 1 10CFR50.72 item. Report on NRC Hot Line using attached form. During normal hours telephone regional office also (see noti-fication guide attached).

EPP 1.5-2-c ' Revision 8 ATTACHMENT 8 (Continued) REPORTABLE EVENTS FEB 0 51932 STATE STATE NRC NOTIFICATION EVENTS EMERGENCY REPORTING REPORTING LEVEL CLASSIFICATION REQUIRDIENT REQUIREMENT ,r

e. Loss or damage to major system components.

(NUSCO) 7

f. Fish kill, unusual fish entrap-ments, or unusual environmental

~ situation. (NUSCO)

g. Oil spill or other contamin-ants into river water. (State)

Note 3 4 4

h. Incident that required police aspistance.

(State) l o E

1. Incident that requires fire department assistance for fire us i

[ lasting LESS than 10 minutes. (State) m a i Note 1 10CFR50.72' item. Report on NRC Hot Line using attached form. 4 During normal hours telephone regional office also (see noti-fication guide attached). Requires a telephone call by the Duty OfficerL o the NUSCO Nuclear Operations Duty Officer perferably t . Note 2 i i. the day of occurrence but no later than the morning of the next work day. Requires a telephone call to the' Coast Guard, National Resource Center and Spill Response Center of .; i Note 3 Connecticut within a few hours of occurring. (Refer'to Assistance Guide for telephone numbers.) 9 i l' i ^

.~ EPP 1.5-2-C FEB 0 51982 ATTAC10iENT 8 (Coatinued) Revisica 8 REPORTABLE EVENTS STATE STATE NRC NOTIFICATION EVENTS DIERGENCY REPORTING REPORTING LEVEL CLASSIFICATION REQUIREMENT REQUIRDiENT 18 Reports of theft or loss of radio-F Within few Within hours 1 active material in accordance with hours 10 CFR 20.402 (Ref. 10 CFR 30.71) 19 Radioactive material transport G Withi'n few 1 hours accident i E Within few 30 Day 1 l 20 Reports of overexposure and hours excessive levels and concen-trations in accordance with 10 CFR 20.405. p i d 21 All Section 6.9.2-a E Within few 24 Hours 1 hours Safety Technical Specification o Reports 1 as 30 Day l i 22 All Section te.9.2-b Note 2 Safety Technical Specification Reports 23 All Section 5.6.2-a(1)- E Within few 24 Hours 1 { hours Environmental Technical Speci-fication Reports 30 Day 24 All Section 5.6-2-a(2) Note 2 Environmental Technical Speci-fication Reports Wate 1 10CFR50.72 item. Report on NRC Hot.Line using attached form. During normal hours telephone regional office also.(see noti-fication guide attached). l Requires a telephone call by the. Duty Officer to the NUSCO Nuclear Operations Duty Officer perferably Note 2 the day of occurrence but no later than the morning of the next working day.

EPP 1.5-2-C p_n n 3 982 g' ~ ATTACHMENT 8 (Continued) Revision 8 REPORTABLE EVENTS STATE STATE NRC NOTIFICATION EVENTS EMERGENCY REPORTING REPORTING LEVEL CLASSIFICATION REQUIREMENT REQUIREMENT 25 All Section 5.6.2-b(1) 10 Day Note 2 Environmental Technical Speci-fication Reports 26 All Section 5.6.2-b(2) 30 Day Note 2 Environmental Technical Speci-fication Reports 27 All Section 5.6.2-c 30 Day Note 2 Environmental Technical Speci-i 2 fication Reports 5 28 Any unexpected or unanticipated ser-E Within few 24 Hours 1 9 e vice water system leaks within con-hours j tainment IEB 80-11-21-80 g 2, es 29 Major loss of physical security-E Within few Within 1 1 effectiveness which allow hours hour hotline unauthorized and undetected access Note 1 to vital area. a. Loss of all communications to summon State Police. Eote 1 10CFR50.72 item. Report on NRC Hot Line using attached form. During normal hours telephone regional office also (see noti-fication guide' attached). Note 2 Requires a telephone call by_the Duty Officer to the NUSCO Nuclear Operations Duty Officer preferably I the day of the occurrence but.no later than the-morning of the next working day. / s s. e, ~ s. +, s

1. 7

-w

s' / ,?. LMV M Rev. S-FEB ' $ M ' " <) s: ' f ['jl[, ATTACHMF,'S 8 (Continued) ,7 REPC-" FABLE EVENTS ' ~ STATK' STATE NRC NOTIIICATION j r' s EVENTS EMERGENCY REPORTING REPORTINGm 1EVEL: y CLASSIFICATION REQUIREMENT REQUIREMENT I / f lj b. CompTete lors dC;both CAS and-?AS of'which+ compensatory / measures are not in place s within 10 rain. of event providing a level,of security 4 equivalent to thattexisting prior to the event. ~ p-t 4 Attempted and confirmed C ~ 5- ,7 c. intrusion into the protected . and vital areas.

j' e

7 v ca 30. Moderate Loss of;Secuyity E Within few 24 hours 1 ,Ca sitours 7 ,',- o Effectiveness y. w( 7-w ';J Theft,~pf,secur16; weapon-h[ _-j

• e

'O f',,L n a. .J ,s ^ 7 f, ' t.,, at:stte. ~ j i i i b." Confi.rmed tampering with ,r a. n --.,.. s security eq3fpuen & ~ J _ / ;-~ - Al c ^ UnexplaitM)' fire or c. j..# explosion within protected L y. or vital area that'could j '.. [, ~ security. affect plant ,/ 1-s. i s >?, Note 1 10CFR5032 item. Report on NRC Hot Line using attached form. During normal hours telephone regional of fice also (see noti- .f ~ ,l [( fication guide attached). ~ i.. I ~~ i

1. l. g w

• ' ^
• ,. s

e.,

,fr + ,s. e, ,p: f /;- / e.. '.; / g .n

9 k EPP 1.5-2-C REPORTABLE EVENTS f Revision 8 .EE 5M ATTACiDiENT 8 (Continued) STATE STATE NRC NOTIFICATION ~ EVENTS DIERGENCY REPORTING REPORTING LEVEL CLASSIFICATION REOUIRI~ MENT REOUIREMENT d. Security related injury to l a security member caused by l malfunctioning of security equipment. 1 Complete loss of either CAS e. or SAS. f Note 4 31. Serious danage to plant equipment or facilities. s 32. Load decrease greater than 257. Note 4 or anticipated removal of unit from service within next 24 y hours. g I + y o Uote 1 10GFR50.72 item. Report on NRC Hot Line using attached form. During normal hours telephorie regional office also (see noti-fication guide attached). i Requires a telephone call by the Duty Officer to the NUSCO Nuclear Operations _ Duty Officer greferably Note 2 ( the day of occurrence but no later than the morning"of the next working day. l Note 3 Requires a telephone call to the Coast Guard', National Resource Center and Spill Response Center of Connect.icut within a few hours of occurring. (Refer to Assistance Guide for telephone numbers.) j Requires a telephone call by the Duty Office to the NUSCO Nuclear Operations Duty Officer within Note 4 one hour of determination. t I t i P e [

ATTACHMENT 9 EPP 1.5-2-C ASSISTAECE GUIDE Rsv. 8 FEB 0.51952 TELEPHONE NUMBERS EOTIFICATION DOCUMENTATION "'] AGENCY TITLE NAME BUSINESS !!OME - DATE TIME PERSON CONTACTED State Police Colchester Dispatcher Fire Department Haddam Neck Dispatcher Ambulance East Hampton Dispatcher Hospital Middlesex (if confaminatedr Memorial (not contaminated) 2 Lawrence U Memorial i' Doctor Medical Consultant Dr. H. Levine, r Radiation Management Corp ~ President Dr. R. Linnemann Coast Guard Captain of Lieutenant .the Port M. A. Conway State Office of Civil Preparedness i National Resource Duty _ Center Officer -w nWB-6$

tartetr.7Futb ASSISTANCE GUIDE Rev. S FEB 0 51982 TELEPl!ONE NUMBERS-NOTIFICATION DOCUMENTATION AGENCY TITLE NAME BUSINESS HOME DATE TIME PERSON CONTACTED Spill Response Center of Connecticut State Department of Environmental Protection I Brookhaven National Chief Engineer Laboratory Operations D. Schnelley + i Combustion Engineering R. Hoover i Director Rad Control (normal weekday) l Rad Control Foreman Electric -(off hours, weekends) l Boat ' Guard Force s United Nuclear Manager Nuc- .j Corporation Icar/ Indust-rial Safety W. F. Kirk ( Millstone Unit 1 Shift Supervisor i Unit 2 Shift Supervisor DIPO i Emergency Page 36 of 46 \\ Telecopier

EPP 1.5-2-C Revision 9 J. ATTACHMENT 9 (Continued) FEB 0 5 1981 '4 7 ASSISTANCE GUIDE TELEPHONE NDiBERS NOTIFICATION DOCDIENTATION AGENCY TITLE NAME EUSINESS HOME DATE TIME PERSON CONTACTED Westinghouse Field Service Frank Noon l Manager k 1st Alternate Ray Sabol i a 2nd Alternate Dallas Lokay t m S o d ? o \\ Service Re-Joe Lablang sponse Manager 1st Alternate Frank Noon 2nd Alternate John Mill'er + i \\~ e G ~

ATTACIDfENT 9 (Continued) Rev. 8 ASSISTANCE CUIDE FEB 0 51932 TELEPilCNE NUMBERS NOTIFICATION DOCUMENTATION i .ACENCY TITLE NAME BUSINESS HOME DATE TIME PERSON CONTACTED Westinghouse Emergency Re-Hank Ruppel .{ (Continued) sponse Director i Emergency Re-Ron Lehr sponse Deputy Director i Emergency News Mike Mangan j Communications i i \\ Shipman Fire General E. Wallace Equipment Manager AMTRACK Ceneral Superin-R. Duggan tendent l l 1 I D:tteo, Inc. President L. A. DeVivo .l I ( Page 38 of 46 I ~ l L ~

N ATTACHMENT 9 (Continued) 8 FEB 0 51982 ASSISTANCE CUIDE TELEPHONE NUMBERS NOTIFICATION DOCUMENTATION 't ACE';CY TITLE NAME BUSMESS IlOME. DATE TIME PERSON CONTACTED Beebe Transportation General M. O' Leary Manager Nichols Bus President C. Nichols Interex D. Newton Corporation R. Fix Teledyne A. Hayter J. D. Martin Isotopes H. Jeter Travelers k'ea the r Service t Page 39 of 46 y

~ ~ ~ ~ EPP 1.5-i-C i Rev.8 i ?EB 0 5121 j. ATTAClotENT 10 CONNECTICUT STATE POLICE (CSP) CONTACT POINTS 11ADDAM NECK i + Colchester CSP Barracks (Troop K)- Westbrook CSP Barracks (Troop F) Via 11ot Line Via Telephone: ~~ ~~ Colchester Chester East 11addam Deep River East flampton Durham i liebron Essex j Marlborough lladdam Portland Killingworth i g Salem Lyme Madison Middlefield Middletown Westbrook NOTE: This list is to be used AFTER station attempt to contact ~ local communitics by telephone. 2 h I 4 i 6 i 1 4 46 Page 40 of . w v. ,-yr-. rv.. e, em -_r-. -, --__ -, ,m. -...,,-.re,

F EPP 1.5-2-C Rev. 8 ,7n g g spg? (" ! ' fu~ t , 1 Reportab1'c Releases The following releases are reportable: 1. Any release, liquid or gaseous, exceeding technical specifications. 2. Any release from a release path which does not have an established monitor or sampling program and a grab sample indicates that release concentrations exceeded: 1 x 10-7 'uCi/10. for liquids or, 1 x 10-10 uCi/cc for airborne particulates or iodine or, 2 x 10-8 uCi/cc for airborne noble gases. 3. Any increane in noble gas release rates which is greater than 1500 uCi/sec above the normal (existing) release rate and this increase is not due to a. planned or expected event. Note 1: It is recognized that what constitutes a " planned' or expceted event" is still ambiguous at this time. 11ow-ever, the following philosoply should be used: 1) If the increased release rate is less than 1500 uCi/sec above nornal it is not reportable even if the cause of the increase is unknown or unplanned. ii).If the increase is greater than 1500 uCi/sec,' bi is due to a planned activity which is known to be the cause (e.g. - Increasing power level, releasing a waste gas tank, purging the containment, etc.) then the release is not reportable provided it remains below the technical specification limits. iii) If the increase is greater than 1500 uCi/sec, and the cause was unplanned (e.g. - Lifting of a relief valve, error in valve line-up, etc.) or the cause is still unknown, then the release should be. reported. Note 2: The stack monitor reading in CPM (CPS for MP1) which corresponds to the normal reading plus 1500 uC1/sec depends on the normal reading at that time, the latest mo-t a. ,libration factor, and the number of ventilation fans operating. Si e these parameters are subject ot change, so is the corresponding monitor reading. Thus, it should be required that a member of the Chemistry Department determine the appropriate reading and post it for the operator's use. This should be done at least weekly and after any sinulficant change in power level or a new monitor calibration curve developed). \\ Page 41 of 46 n

EPP 1.5-2-C I' Rev.8 pgn 9 5**** l . 1 - Page 2 Example - !!P2 stack monitor Normal reading has been running at 25 CPM Present" monitor calibration factor = 6.2 uCi/sec per CPM (assuming 2 fan operation) Thus,.1500 uCi/sec = 240 CPM Thus, monitor reading corresponding to reportable level = 240 CPM + 25 CPM = 265 CPM This value and the monitor calibration factor should be posted for the operator's use. Also, the clarm set point should be set at or below 265 CPM. i i Page 42 of 46 .a

lf +1 EPP 1.5-2-C

7..

Rev. 8 0 515B2 . 2 Bases for Attachment 11 Exceeding tech spec limits Criteria 1 This criteria is cicar. Any release, whether due to a planned or unplanned event or activity, must be reported if the tech spec limits were exceeded. f Criteria 2 - Unmonitored Reicases i) Established Monitor - t Any release from a path which has a fixed monitor (e.g. - stack, MP1 isolation condenser vent, SCBD line, etc.) would not be reportable due to the un-monitored release criteria. If the monitor was { inoperabic, but grab nampics were being taken in accordance with the action statements in the tech-nical specifications, then likewise any rele.ases I would not be reportable.

11) Established Sampling Program -

There are certain paths which do not have a fixed monitor but have an established sampling program where grab sampics are obtained on a fixed schedule. l The main reason these pathways are not monitored is because the potential release rates are less than the lower limit of detection for gross moni-tors. Since grab samples are more sensitive, they are used to detect and hence account for any low level releases from these pathways. Thus, for exnaple, any releases detected coming from the MP1 Condensate Storage Tank vent would not be reportable since there exists an established sampling program to measure the level of gases in the tank and account for the activity released. ~ iii) Release Concentrations - 1 x 10-7 uCi/ml, etc. There are numerous release paths of trivial amounts of plant related radioactivity at our sites which are not monitored or sampled. Some examples of these are PWR turbine building exhaust, opening a door from the outside to get into the PAB, opening a contaminated laundry drum outside, etc. If sampics were tal.en from some of these pathways and l ' Page 43 of 46 s

EPP 1.5-2-C 2 - Page 2 Rev. 8 / ' ce g J f, '.A counted at a low background laboratory, plant re-lated activity could be detected. This is a recognized fact. It is also recognized that the total contribution from thesc pathways is trivial and insignificant compared to the releases from the monitored release paths. llence, these releases do not have monitoring or sampling requirements. There is a potential for releases of non-trivial 3cycis of radioactivity from unmonitored paths. This would most likely be due'to an accident, equip-ment failure or human error (e.g. - a leak develops in a tank trunk being used to trasnfer liquid wastes onsite). Criteria cre, therefore, required to determine which unmonitored releases are trivial and do not require reporting and which are non-trivial and i should be reported. i j The concentrations listed in Attachment I represent the dividing line. The concentrations given are the most limiting value from either 10CFR20 - Ap-pendix B - Table II (maximum Permissible Concentrations in Air and Water Outside the Site Boundary) or 10CFR30.70 Schedule A (Exempt Concentrations in Cas and Liquids.) Criteria 3 - Unplanned Releases The routine operation of a nuclear power plant results in numerous increases and decreases in gaseous release rates. Valve packing and pump seals may leak at varioug rates, startup or shutdown of a system may result in brief puff releases due to pressure transients, opening up a system for maintenance will release trapped gases, etc. Most of these changes are so small that they cannot be detected on the stack monitor. Some of them may cause slight in-creases in the monitor response. Any release of signifi-cant levels will cause a significant increase in the mon-itor response. It is not feasible for an operator to explain every minor increase in the stack monitor reading due to the wide range of trivial events which could result in this increase. In addition, it does not make sense to -t all such. increases as it would lead to a large voiun. of. reports which serve no purpose but to prove that t.ie routine oper-ation of a nucicar plant results in numerous increases and decreases in gaseous release rates. l Page 44 of 46

EPP 1.5-2-C 1 FEB 0 5 BEi n "cv 3 - 2 - Page 3 ( It is therefore necessary to define the difference be-tween these minor increases and a significant increase. If the release is significant, then it should either be due to a pla,nned or expected event or it should be re-ported. In order to avoid differences in interpretations, the dividing line between minor increases and significant increases should be as specific as possible. The only practical way to do this is to define it as a specific release rate. This release rate was determined to be 1500 uCi/sec. The value 1500 uCi/sec was c.u en based on the following facts: 1. The limiting nobic gas concentration from 10CFR20 - Appendix B - Table 11 for offsite noble gas con-centrationi is 2 x 10-8 uCi/sec for kr-88. The maximum annual average X/Q from either the CY stack, MP1 stack or MP2 stack at the critical site 3 boundary is 1.3 x 10-5 sec/M. Assuming the required release rate to get 2 x 10~8 uCi/cc is: 3 2 x 10-8 uCi/cc/(1.3 x 10-5 sec/m3. 10-6 m fcc). 1540 uCi/sec I Thus, for the most limiring nuclide, the most limiting release point, and the most limiting site boundary, a release rate of 1500 uCi/ rec will result in concentrations less than allowed by 10CFR20. 2. For the sane limiting site boundary and CY stack release point, the expected I hour dose from a re-Icase rate of 1500 uCi/sec should be in the range of 0.001 - 0.003 mrem which is less than the expected hourly background dose of 0.005 to 0.01 MRFlf. 3. The nohic gas concentration in CY primary coolant is approximately 2 uCi/ml. Thus, a leakage rate of 750 ml/see would result in a release of 1500 uC1/sec into building air and eventually to the stack. 750 ml/sec is equal to 11 gallons per minute which is not untypical of potential Icakage rates from Icaking valves or pumps. 4. The present background reading on the CY stack monitor is 500 cpm. The present calibration. factor is about 3 uC1/sec per cpm. Therefore, 1500 uC1/sec = 500 cpm which is a practical level to detect above the present reading. 1 Page 45 of 46

EPP 1.5-2-C Rev. 8 w Attachr.ent 12 - Pane 4 5 5. The present background reading on the MP1 stack monitor is 6 cps. The present calibration factor is about 57 uci/sec per cps. Therefore, 1500 uC1/sec = 26 cps which is a practical. level to detect-above the present reading. 6. The present background reading on the MP2 stack monitor is 26 cpm. The present calibration factor is about 6.2 uC1/sec per cpm. Therefore, 1500 uC1/sec = 240 cpm which is a practical Icvel to detect above the present reading. t l l Page 46 of 46 s

. EPP 1.5-7-C ao osn-i nov. 6.oi Retrision 3 -.m, FEB 0 5 882 PLA T OP A I NS REVIEW COMMITTEE APPROVAL W Connecticut Y'c. Ace Emergency Plan uccedure EPP 1.5-7 O [j g, f RADIO 1DGICAL-DOSE ASSESS!!ENT M O L A Lec L % a g g y 7 _- o EFFECTIVE DATE f 3 ~

1. -6 Y /

1.0 PURPOSE This procedure provides the instructions for calculating projected doses during an alert, a site-area emergency, or a general emergency: to the whole body from released noble gases o to the child thyroid from radioiodines o 2.0 RESPONSIBILITY 2.1 The !!anager of Radiological Consequence Assessment is responsibic for-directing the Dose-Assessment Team to implement this procedure. The Manager has the responsibility to inform the Director of Station Emergency Operations (SEO) of the assessment; however, o'nly the Director has the authority to recommend protective actions to off-site authorities. 2.2 The Shift Supervisor, until relieved by the Director of SEO, will make protective-action recommendations to off-site authorities. 3.0 ACTIONS 3.1 Dose-Calculation Data Sheet (attachment 1). 3.1.1 Using monitor readings and meteorological. data, complete the Dose-Calculation Data Sheet. 3.2 Whole-Body Dose Assessment at Site Boundary. 3.2.1 Complete part 1 of attachment 2, Noble-Gas Release Rate, as follows: 3.2.1.1 If grab sample results are available from the monitored release paths, enter the release rate in Ci/s in item 5, and enter 0 in the Ci/s space for the cor esponding monitor so that the release estimates are not doubled for that release path. Page 1 of 22 m

EPP 1.'5-7-C l Revision 3 EB 0 5 B82 NOTE: The Chemistry Dept., Radiation Assessment Branch (RAB), or designated group will cal-culate release rates in C1/s based upon grab samples, if taken. NOTE: If no grab-sample results are availabic, enter 0 in Ci/s in item 5. 3.2.1.2 If the main-stack monitor is on scale, record the gross counts per minutes (cpm). Calculate and enter the release rate in curies per second (Ci/s). NOTE: If the monitor is off scale, enter 0 in Ci/s in. item 1. 3.2.1.3 If the main-stack monitor is off scale, record the interim high-range vent-duct monitor reading in mR/hr. Calculate and enter the release rate in Ci/s. NOTE: If the main-stack monitor is on scale, enter 0 in Ci/s in item 2. 3.2.1.4 If the containment pressure is greater than 2 pounds per square inch (psig) (available from control room), enter the containment-hatch monitor reading in R/hr. Calculate and enter the release rate in Ci/s. NOTE: If the containment pressure is less than 2 psig, enter 0 in Ci/s in item 3. 3.2.1.5 If a steam-generator tube rupture is be'lieved to have occurred and if releases are in progress from the atmospheric steam dump or Terry Turbine, then determine the release rate as follows. An Emergency Team will be designated and obtain the dedicated teletector located at the Health Physics control point and perform the following survey: ~ Take a general-area background reading at the base o of stairs Icading up to the atmospheric steam-dump line. Climb up to the platform located under the atmos-o pheric steam-dump line. o Take a dose-rate reading 3 feet radially out from the bottom surface of the muffler on the atmospheric steam-dump line. Report this reading, minus background reading, to the Manager of Radiological Consequence Assessment. Page 2 of 22 s - ~~ o P"K

EPP 1.5-7-C FEB 0 5 G82 l[ Revision 3 o Enter net reading in mR/hr in item 4. Calculate and enter the release rate in Ci/s in item 4. o If a positive reading above background is obtained, repeat above four items every 15 minutes until releases terminate and record results. NOTE: If there are no releases from this pathway, enter 0 in Ci/s in item 4. 3.2.1.6 If all monitors for the known release points are inoper-abic and no grab-sample results are available, determine the type of accident which has occurred and enter one of the default release-rate values in C1/s in item 6. NOTE: If monitoring or grab-sample results are available from the appropriate release points, enter 0.in Ci/s in item 6. 3.2.1.7 The total nobic-gas release rate will be the sum of items 1 through 6. Enter on Line 7. 3.2.2 Complete part 2 of attachment 2, Whole-body Dose at Site Doundary, as follows: 3.2.2.1 Enter the total noble-gas release rate from part 1. 3.2.2.2 Record _the wind speed in miles per hour. Determine and enter the corresponding wind-speed correction factor. 3.2.2.3 Determine and enter-the appropriate release-height correction factor based on release point. 3.2.2.4 Calculate and enter the whole-body dose rate at the site boundary from the equation: Dose Rate Total Noble-Wind-Speed Release-Height (mrem /hr) Gas Release x Correction x Correction x 0.7 =- Rate , Factor, Factor 3.2.2.5 Determine and enter the actual or predicted durntion of ;he release. If the release has terminated, enter the actual duration in hours. Do not use 1 hour for short releases. For example: for a 6-minute release, enter 0.1 hour and not I hour. If the release has not terminated, project the expected duration. If projected duration is unknown, enter 10 hours. ~ Page 3 of 22

EPP 1.5-7-C Revision 3 j" ' ', FEL, a 51982 3.2.2.6 Calculate and enter the projected whola-body dose at the site boundary from the equation: ~ Dose Whole-Body Duration Dose Rate x of '(mrem) = ~ ~ Release ~ .3.3 Thyroid-Dose Assessment at Site Boundary. 3.3.1 Complete part 1 of attachment 3, Calcu1'ation of X/O Value, as follows: 3.3.1.1 Enter the wind speed, u. 3.3.1.2 Record the temperature differential (AT) at 196' in F from the computer readout in the EOF or control room. 3.3.1.3 Determine and enter the Xu/0 value corresponding to the AT. 3.3.1.4 Calculate and enter X from the equation: Q 2[ (s/m3) = Xu/Q x 2.2 Q u 3.3.2 Complete part 2 of attachment 3, Iodine Release Rate, as follows: 3.3.2.1 If release rates based on iodine grab-sample results are availabic from the Chemistry Departmpnt, RAB, or other source, enter'the data in item 4 and go on to step 3.3.3 of this procedure. 3.3.2.2 If iodine grab-sample results are not available, enter the total noble-gas release rate from item 7, part-1, attachment 2 in item 1, part 2, of attachment 3. _I dine ratio. 3.3.2.3 Determine and enter the f Noble Gas 3.3.2.4 Calculate and enter the iodine release rate from the equation. Total Noble-Iodine Ratio Release Rate (Ci/s) = Gas Release x Noble Gas Rate 3.3.3 Complete part 3 of attachment 3, Thyroid Dose at Site Boundary, as follows: 3.3.3.1 Enter the 25 value from item 4, part 1, of attachment 3. Q 3.3.3.2 Enter the iodine release rate trom item 3 or 4, part 2, of attachment 3. Page 4 of 22

W c \\ Revisi " 3 g 0 5 GB2-1 3.3.3.3 Calculate and enter the iodine concentration at the site boundary _ from the equation: Iodine I-131 (uCi/cc) = X x Reicase Q Rate 3.3.3.4 Determine and enter the predicted or actual duration of the release. If the release has terminated, enter the actual duration Do not use 1 h'ur for short relcanes. For in hours. o example: for a 6-minute release enter 0.1 hour and not I hour. If the release has not terminated, project the expected duration. If the projected duration is unknown, enter 10 hours. 3.3.3.5 Calculate and enter the projected thyroid dose at the site boundary from the equation: 1-131 Duration 8 Concentration x of x 5 x 10 Dose (mrem) = Reicase 3.4 Whole-Body and Thyroid-Dose Assessments at Locations beyond the Site Boundary 3.4.1 If the site-boundary whole-body dose is greater than 5 mrem but Icas than 50 mrem, or the thyroid dose is greater than 25 mrem but 1 css than 250 mrem, complete item,3 of attachment 4 as follows: 3.4.1.1 Divide 5 by the site-boundary whole-body dose. 3.4.1.2 Divide 25 by the site-boundary thyroio dose. 3.4.1.3 Using Attachment 6, page 20, determine the distance in kilometers to which the dose exceeds 5 mrem to the whole body or 25 mrem to the thyroid. 3.4.1.4 Calculate the distance in miles by dividing the kilo-meters by 1.6. l 3.4.2 If the site-boundary whole-body dose is greater than 50 mrem but 1 css than 1000 mrem, or the thyroid dose is greater than 250 mrem but less than 5000 mrem, complete item 4 of attach-ment 4 as follows: i 3.4.2.1 Divide 50 by the site-boundary whole-body dose. 3.4.2.2 Dividd 250 by the site-boundary thyroid dose. Page 5 of 22 s ~ q

Revision 3 l~ ' ~ FEB 0 5 1982 .t. 3.4.2.3 Using Attachment 6, page 20, determine the distance in kilometers to which the dose exceeds 50 mrem to the whole body or 250 mrem to the thyroid. 3.4.2.4 Calculate the distance in miles by dividing the kilometers by 1.6. 3.4.3 If the site-boundary whole-body dose is greater than 1000 mrem. but less than 5000 mrem, or the thyroid dose is greater than 5000 mrem but less than 25000 mrem, complete item 5 of attach-ment 4 as follows: 3.4.3.1 Divide 1000 by th'e site-boundary whole-body dose. 3.4.3.2 Divide 5000 by the site-boundary thyroid dose. 3.4.3.3 Using Attachment 6, page 20, determine the distance in' kilometers to which the dose exceeds 1000 mrem to the whole body or 5000 mrem to the thyroid. 3.4.3.4 Calculate the distance in miles by dividing the kilometers by 1.6. 3.4.4 If the site-boundary whole-body dose is greater than 5000 mrem or the thyroid dose is greater than 25000 mrem, complete item 6 ,of attachment 4 as follows: 4 3.4.4.1 Divide 5000 by the site-boundary whole-body dose. 3.4.4.2 Divide 25000 by the site-boundary thyroid dose. 3.4.4.3 Using Attachment 6, page 20, determine the distance in kilometers to which the dose exceeds 5000 mrem to the whole body or 25000 mrem to the thyroid. 3.4.4.4 Calculate the distance in miles by dividing the kilo-meters by 1.6. 3.5 Downwind Sectors Affected by the Release. Using Attachment 7, page 21, and the wind-direction value from item 8 of attachment 1, determine and enter the down-wind sector affected by the release in attachment 5, item 1. 3.6 Recalculations. 3.6.1 Doses should be recalculated when directed to by the Manager l of Radiological Consequence Assessment, which would typically result if: Wind direction changes by more than 45 or wind speed by o more than 5 mph. I Page 6 of 22 s

EPP 1.5-7-C Revision 3 0 5 1902 FEB 4 1 ) Actual or estimates of release-rate change by tore than a o factor of 3. l The maximum icvels measured by field monitoring teams indi-o i cate dose rates or lodine concentrations 3 times greater than or less than the calculated valucs for comparable locationn and t,imes. In this case, the calculations should be rechecked for errors, and the field monitoring teams should expand their i surveys and verify original measurements. 3.7 Report the results of all calculations to the Manager of Radiological 1-Consequence Assessment. 4.0 ATTACmfENTS i l Attachments ' Title h1110 I Dose-Calculation Data Sheet 8 9 2 Whole-Body Dose Assessment i 13 3 Thyroid-Dose Assessment-4 Whole-hody and Thyroid-Dose Assessments at Locations beyond the Site Boundary 16 5 Downwind Sectors Affected by Release 19 6 Dose-Reduction Factor with Distance. 20 7 Wind Directions and Sectors 21 8 Bases for Radiological-Dose Assessment 22 5.0 PROCEDURE CROSS REFERENCE 5.1 Safety Technical Specification-Section 6.16. l ~ I Page 7 of 22 I

EPP 1.5-7-C [- Revision 3 FEB 0 51982: 'f" ', Dose-Calculation Data Sheet 1. Main-Stack Monitor / Reading: cpm 2. Interim liigh-Range Vent-Duct Monitor / Reading: (if Main-Stack Monitor of f scale or R/hr nonfunctional) ContainmentHatchbonitorReading: 3. R/hr (only if containment pressure is greater than 2 psig) 4. Survey Data from Terry Turbine or mR/hr Atmospheric Steam Damp: '5. Type of Accident: 6. ECCS Operating as Designated: Yes or No 7. Wind Speed:* mph 0 33' icvel mph @ 196' icyc1 8. Wind Direction: 0 33' icyc1 0 196' level Use

• 196-foot data if only main-stack releases are present.

33-foot data for all cases. "F 9. AT at 196 fect: hr 10. Estimated or Actual Duration Release:

11. All calculations must be carried out to 3 decimal places.

Recorded by Date Time Page 8 of 22

EPP 1.5-7-C Revision 3 FEB 0 5198,< Wl:0LE-BODY DOSE ASSESSMENT J PART 1 - Noble-Cas Reicase Rate -6 ci/s 1. Main-Stack Monitor: cpm x 5 x 10 = e l 2. Interim liigh-Range Ci/s Vent-Duct Monitor: R/hr x 50 = 3. Containment-11atch Monitor: (If containment pressure'is 2 psig) R/hr x 1.2 x 10-4 Ci/s 4. Atmospheric Steam-Dump Monitor or -3 Ci/s Terry Turbine: mR/hr x 2.5 x 10 = l i 5. Crab-Sample Results: from main stack Ci/s from containment hatch Ci/s 6. Defnuit Values: (if no information availabic) Ci/s LOCA - ECCS working 3.3 Ci/s 4 LOCA - ECCS not working 33 C1/s SG-tube rupture 4.0 Ci/s Fuel-handling accident 170.0 Ci/s Page 9 of 22 e ....-.--- x

1 EPP 1.5-7-C j" ' ' )(evision 3 .EB 0 51982 t- . (Continued) Wi!01,E-P,0DY DOSE ASSESSMERT 7. Total Noble-Gas Release Rate (one of the following): o Sum of items I through 5 Ci/s Value from item 6 only if all monitors from o known release points inoperabic and no grab-Ci/s sample results availabic 8. Enter total noble-gas release rate from item 7 in item 1 of part 2. Page 10 of 22 s en n

EPP 1.5-7-C FEB 0 5 1982 "*I" ' (Continued) i PART 2 - Whole-Body Dose at Site Boundary 1. Total Noble-Cas Release Rate: Cf/s i ) 2. Wind Speed: mph (196' data if only main stack releases are l present. Use 33' data in all other cases) 3. Wind-Speed Qorrection Factor: Wind Speed Correction Factor Wind Speed Correction (mph) Factor Less than 2 2.5 i 2-7 2.0 8-11 1.5 Greater i than 11 1.0 I 4. Release-lleight Correction Factor: Release liefght Correction Factor Release Correction Point Factor Main Stack only 3.5 l Any other 6.0 _If _ releases are from both points, enter 6.0 1 l l S. Whole-Body Dose Rate at Site Boundary: [ Total Nob 1c-Wind-Speed Release-tieight Gas Release Correction Correction Factor Rate _ Factor _ X 0.7 = mrem /hr. t X ,X I Page 11 of 22 l

EPP 1.5-7-C N"VI8I 3 05N Attaclunent 2 (Continued) W110LE-00DY DOSE ASSESSMENT PART 2 - Whole-Body Dose at Site Boundary (Continued) 6. Actual or Predicted Duration of Release: hr If the release is continuing and the duration is unknown, enter a value of 10. 7. Projected Whole-Body Dose at Site Boundary: Iuration Whole-Body D Dose Rate of l ~ _ Release] x = mrem 8. If the PROJECTED W110LE-BODY DOSE exceeds 5 mrem, enter the value in item 1 of attachment 4. Page 12 of 22 s m

EPP 1.5-7-C (' ' '. Revision 3 I FEB u 51982 Tl!YROID-DOSE ASSESSMENT PART 1 - Calculation of X/Q Value 1. Wind Speed: mph 0 33' (enter 1 if < 1.0 mph) mph 0 196' NOTE: Use 196-foot data if only main-stack releases are present. Use 33-foot data in all other Cases. 2. Tenperature Differential AT at 196 feet: F 3. Xu: 4 Xu Q AT Xu/Q > +0.5 F 2x10-3 -1.6 <AT < +0.'5 F 5x10-4 < -1.6 F 1x10-4 4. X. Q 2! =.MindlXu/Q x 2.2 Q .Speeg X= [ ] x 2.2 = s/m3 Q C 3 Page 13 of 22

r EPP 1.5-7-C } Revision 3 FEB 0 5 22 ' (Continued) TilYROID-DOSE ASSESSME';T PART 2 - Iodine Release Rate C1/s 1. Total Noble-Gas Release Rate: (f rom item 7, part L, attachment 2) 2. (Iodine / Noble Gas) Ratio Type of Accideilt (Iodine / Noble Gas) Ratio Ratio LOCA 0.06 SG-Tube 0.0005 Rupture Fuel-liandling, Accident 0.004 Any Other 0.003 3. Iodine Release Rate: Total Noble-' Rate -Iodine /NobleGasRatio]~ Gas Release Ci/s = I-131 Release Rate = x Ci/s 4. 1-131 Release Rate from Iodine Grab-Sampic Data =

s

.j Page 14 of 22

EPP 1.5-7-C e' Revision 3 4, / 'dttachment3(Continued) e i y w t 1. j k. ' 1. TilYROID-DOSE ASSESSMENT <\\ *. \\ w t i4 ^ Ig PART_3 - Thyroid Dose at Site Boundary b ', 4 g .a-3 N s/m 1. X. q-(from it.em 4, part 1, of attachment 3) s g, I' 3u4 t Ci/s ( 2. Iodine Balcase Rate: (from item 3 or 4, part 2, of attachment 3)- N-4 \\m

i. g

_~ 3. 'Iodfac' Ccmcentration at Site Boundary: ' ' ~ L1 ' \\ ,,._7 X Iodine 1' Q Release f, t e, Rate L . D; s'. uCi/cc*

1. 4'I-131 a x

= $bn \\ t. g*, I l

• Note:

1 Ci/m3 = 1 uCi/cc. g' ' ' th Y, s i s., l>' A,. <t 4. Predicted or Actual Duration of Release: l'f. i 'g ~,, hr, p.Q N 'I + - (If the release is continuing and the I-duration is unknown, enter a value of 10.) 1: .\\ _ y 7; * ~ ci, ~ ', 5. Projected Thyroid Dose at the Site Boundary: m m s. 'I-131 Duration d. of. Concentration L. Release, E ] x E. '] x 5x108, ,,g, ,a x. 6)'\\ f the projected thyroid dose exceeds 25 mrem, enter the value s '< s in item 2 of attachment 4. g 1 i ~ ( g a 4 f 6 j Page 15 of 22 -j s ( s s s s -m

F EPP 1.5-7-c FER 0 51982 . Revision 3 Wi! OLE-BODY AND TilYROID-DOSE ASSESSMENTS AT LOCATIONS BEYOND Tile SITE BOUNDARY 1. Projected Whole-Body Tose Site Boundary: (from item 7, part 2, of attachment 2) mrem 2. Projected Thyroid Dose at Site Boundary: (from item 5, part 3, of attachment 3) mrem 3. Distance to Which State Emergency-Classification Charlie-1 Exists: Whole-Body Dose greater than 5 mrem but less than 50 mrem Thyroid Dose greater than 25 mrem but less than 250 mrem (a) 5 5 = = "Whole-Body Dose 25 _ (b) 25 = ' Thyroid"' q Dose,, Use smaller of (a) or (b) and figure 1, page 21, to determInc corresponding distance in kilometers: Distance = km ' Distance in Miles: ~ Kilometer Listance. =- = miles 1.6 1.6 4. -Distance to Which State Emergency-Classification Charlie-2 Exists: ~ Whole-Body Dose greater than 50 mrem but less than 1000 mrem Thyroid Dose greater than 250 mrem but less than 5000 mrem (a) 50 50 = = ^ ~ Whole-Body ~g Dose J Page 16 of 22 \\ .....m

EPP 1.5-7-C FEB 0 51982 Revision 3 (c, - (Continued) Wil0LE-BODY A M TlIYROID-DOSE ASSESSMENTS AT LOCATIONS BEYOND Tile SITE BOUNDARY (b) 250 250 = = ~1hyroicT~ ~ ~ . Dose _ Use smaller of (a) or (b) and figure 1 to determine corresponding distance in-kilometers: Distance = km Distance in Miles: Kilometer mi = Distance. = 1.6 1.6 5. Distance to Which State Emergency-Classification Br.avo Exists: Whole-Body Dose greater than 1000 mrem but less than 5000 mrem Thyrold Dose greater than 5000 mrem but less than 25000, mrem (a) 1000 1000 = = khole-Body Dose (b) 5000 5000 = = ~ Thyroid " Dose Use smaller of (a) or (b) and figure 1, page 21, to determine corresponding distance in kilometers: Distance = km Distance in Miles: Kilometer i mi = . Distance = 1.6 1.6 Page 17 of 22

EPP 1.5-7-C Revision 3 FEB 0 5 1902 , (Continued) Wil0LE-BODY AND TilYROID-DOSE ASSESSMENTS AT LOCATIONS BEYOND Tile SITE BOUNDARY 6. Distanca to Which State Emergency-Classification Alpha Exists: I Whole-Body Dose 5000 mrem Thyroid Dose 25000 mrem ' ('a) 5000 5000 = h ole-Body Dose (b) 25000 25000 = = ~ ~ ' Thyroid - Dose I Use smaller of (a) or (b) and figure 1, page 21, to determine corresponding distance in kilometers: Distance = km f Distance in Miles: Kilometer mi = Distance,= I 1.6 1.6 l Page 18 of 22 y

-- yyy '1.5-7--C. _ _. _ Revision 3-EB 0 519E

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,s DOWNWIND SECTORS AFFECTED BY RELEASE 1. Wind Direction'(from item 8 of Attachment 1) o 196' icvel o 33'-level 2. Downwind Direction 0 i *1800 = Wind Direction

• Add or subtract such that result in between 0 and 360 3.

Downwind Sector (from Attachment 7, page 21) Page 19 of 22 9

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~7 WfW~VTM;FRU Revision 3 FEB 0 61R92 WIND DIRECTIONS + SECTORS DIRECTION WIND IS FROM DOWNWIND DIRECTION DOWNWIND SECTOR ~ 1690 - 1910 3490 - 110 A (N) 192 - 2130 12 - 330 B (NNE) 214 - 235 - 34 - 560 C (NE) 2370 - 258 570 - 780 D (ENE) 2590 - 2810 790 - 1010 E (E) 282 - 3030 1020 - 123 F (ESE) 3040 - 326 1240-- 1460 G (SE) 327o - 3480 147 - 1680 H (SSE) 3490 - 11 1690 - 191 J (S) 120 - 330 1920 - 2130 K (SSW) 340 - 560 2140 2360 L (SW) 57 - 78 237 - 258 M (WSW) 281 N (W) 790 - 1010 259 1020 - 123 282 - 303 P (WNW) 1240 - 1460 3040 - 326 Q (NW) 1470 - 168 3270 - 3480 R (NNW) Page 21' of 22

EPP 1.5-7-C Revision 3 rge 0 51932 BASES FOR RADIOLOGICAL-DOSE ASSESSMENT The details behind each of the values and conversion factors in this procedure are on file with the NUSCO Radiological Assessment Branch. lloweve r, the basic assumptions and methodologies include: 1. Monitor response as function of noble-gas activity assumes an average gamma energy of 0.8 McV. 2. Iodine to noble-gas ratios and default-value release rates are based on the results of design-basis accident calculations and assume the appropri-ate decay and filtration. 3. Effluent-flow rates assume normal operating-flow rates. (sarebasedonWorkbookforAtmosphericDispersionEstimatesby 4. D. B. Turner, 1967, for the particular release height, stability class, and wind speed in question. Calculations are done at a distance of 500 meters from the release point. 5. Iod.ine-dose conversion factors are based on the EPA's Manual of Protective Action Guides and are for the child's thyroid. 6. Dose rate-reduction factors with distance are based on the results of the AIRD1 code and on Turner's Workbook. l 1 i i Page 22 of 22 b}}