Latest revision as of 20:50, 30 December 2020

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Public Version of Rev 13 to Emergency Plan Implementing Procedure EPIP 1.5-2, Notification & Communication
	ML20204F355
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1983
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20204F314	List: B10755, Forwards Public Version of Rev 13 to Emergency Plan Implementing Procedures EPIP 1.5-2, Notification & Communication & EPIP 1.5-41 Re Core Damage Estimate.W/O Procedure 1.5-41; ML20204F307; ML20204F355;
References
	EPIP-1.5-2-01, EPIP-1.5-2-1, NUDOCS 8304290256
	Download: ML20204F355 (41)
	v • d • e

{{#Wiki_filter:- EPIP 1.5-2-D t*' ,* Pcv. 13

                     ,              ,                                                                                                    (EPIP3)

MAR 311983 P OPERATIONS REVIEW COMMITTEE APPROVAL t ,

V 1 '.I du ; 1..- ' Connecticut Yankee '

                                                                                                                                               '^l                   i Emergency Plan Implementing Procedure                                                                 h ItA d u n 0

[' EPIP 1.5-2 NOTIFICATION AND COMMUNICATION ANDW AhitovEb BYAT Ti UpRIN ENoENT W"- EFFECTIVE DAT$, e - 1.0 PURPOSE b~ bi"[ -] To provide guidance and instructions for Notification and Communication for the following situations: o Notify the applicable agencies and personnel during a plant emergency. o Activate the Station Emergency Response Organfzation via the Radiopager System. - o Establish communication interfaces with Federal and State agencies and local communities, o Notify applicable agencies and personnel for reportable conditions that do not require activation of emergency plan. o Initiate and maintain required records. 2.0 RESPONSIBILITIES 2.1 The Shift Supervisor and/or Duty Officer shall ensure that this procedure is implemented. 2.2 The Shift Supervisor's Staff Assistant (SSSA) is responsible for implementing this procedure. l 3.0 ACTIONS 3.1 If an Emergency Action Level (FAL) has not been reached or exceeded. -{ refer to Attachment 6, Reportable Events for required notifications. i NOTE: Refer to attachments 9 and 10 to determine when a release is reportable. O 8304290256 830422 Page 1 of 41 7 PDR ADOCK 05000 , F

EPIP 1.5-2-D i - . = .' Rav. 13 l . (EPIP3) MAR 3'11c83 l , 3.2 Ceneral Intetest Notification (Connecticut State Incident Posture Code Golf, Fox, or Echo). LEVEL ONE Notification. NOTE: These incident classification levels do not require l activation of the Station Emergency Plan or Response Organization. . l l ' l 3.2.1 Notify Duty Officer. NOTE: Notify Unit Superintendent if not the same individual. 3.2.2 Write telephone call-back message on the Incident Report Form (attachment 1) and record on code-a-phone recorders. NOTE: Guidelines on completing the Incident Report Form and the operation of the radiopage system are included in EPIP. 1.5-33, Shif t Supervisor's Staff Assistant. 3.2.3 Place the level selector toggle switch in the LEVEL ONE t position, select the appropriate tape which corresponds to the incident in progress and initiate the automatic page by pressing the red ALERT button. 3.2.4 Within 30 minutes of initiating the radiopager message, review call-back recorders excluding the top three code-a-phones to verify that LEVEL ONE personnel have responded. Record on' attachment 2.

                  ~                                                 ~

NOTE: Contact the NUSCO Duty Officer if any NUSCO Level 1 and 2 personnel have not responded within the specified time. Request confirmation when nonresponders are notified. NOTE: If the State Department of Environmental Protection (DEP) does not respond in one hour, call the 24-hour number at the DEP office l 3.2.5 If the radiopager system is inoperable or fails', telephone i LEVEL ONE personnel listed in attachment 5. l 3.2.6 Leave telephone call-back recorder information on the li code-a-phone recorders for at least one hour after radiopager has been initiated. ! 'i ll L .a l l i I i ! I 9 Page 2 of 41 4 w +

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              ,                                                                                              .                hp{p          MAR 311983 3.3 Notification of Unusual Event (Connecticut State Incident Posture Code Delta-One and Delta-Two). LEVEL TWO Notification.

NOTE: These incident classification levels do not require activation of the Station Emergency Plan or Response Organization. 3.3.1 Notify Duty Officer. NOTE: Notify Unit Superintendent if not the same individual. 3.3.2 Write telephone call-back message on the Incident Reptre Form (attachment 1) and record on code-a-phone recorders. NOTE: 'Cuidelines on completing the Incident Report Form and the operation of the radiopage system are included in EPIP 1.5-33, Shift Supervisor's Staff 4 Assistant. 3.3.3 Place the level select toggle switch in the LEVEL TWO position, select the appropriate tape which corresponds to the incident in progress and initiate the automatic page by pressing the red ALERT button. 3.3.4 Within 30 minutes of initiating the radiopager message, 4

                                                       . review call-back recorders excluding the top three

. code-a-phones to verify LEVEL TWO personnel have responded.

Record on attachment 2. NOTE: Call-back verification will be conducted on the initial radiopage, change of classification, and when specific instructions direct individuals to call back for further instructions. 3.3.5 Telephone the State Police Barracks in Colchester via the dedicated telephone located on the SSSA consoles within one hour to provide a backup to the radiopager. Record on attachment 3. . ! 3.3.6 Make one (1) attempt to notify, via commercial telephone,

                                                        .those local communities which have not responded to the LEVEL TWO radiopage.                           (Attachment 5) l o     If the attempt to notify nonresponding local                                                     ,

communities via commercial telephone is unsuccessful, I request backup assistance from the appropriate State i Police Barracks. (Attachment 8) q NOTE: A follow-up call to the State Police is required to confirm notification of local l communities. i l 4 _ Page 3 of 41 - 1 _ _ . - _ _ . - - - - , - - - . , ~ ~ ~ --- - -

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                     '   '                                                                                                                                                      EPIP 1.5-2-D R:v. 13            MAR 311963 (EPIP3) 3.3.7                   Notify the NRC within one hoor after incident is classified (as required by 10CFR50.72).

o NRC Headquarters (Bethesda) - Emergency Notification System (ENS) Hotline o NRC Region One Office - Health Physics Network (HPN) Hotline (during normal business hours ONLY) NOTE: If the NRC Hotline is inoperable or fails, refer to attachment 4, Energency Talaphone Numbers for NRC Notification. 3.3.8 If the radiopager system is inoperable or fails, telephone all LEVEL TWO personnel listed in attachment 5, excluding the local communities. [ NOTE: Request assistance from the appropriate State l Police Barracks to make telephone calls to the local communities. (Attachment 8) 3.4 Alert, Site Area Emergency, and General Emergency (Connecticut State Incident Posture Code Charlie-One, Charlie-Two, Bravo, and Alpha). LEVEL TWO Notification. NOTE: These incident classification levels require activation of the Station Emergency Plan and Response Organization. 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 1) and record on code-a-phone recorders. NOTE: Guidelines on completing the Incident Report Form and the operation of the radiopage system are included in EPIP 1.5-33, Shif t Supervisor's Staff I Assistant. I 3.4.3 Place the level select toggle switch in the LEVEL TWO position, select the appropriate tape which corresponds to the incident in progress and initiate the automatic page by pressing the red ALERT 'outton. NOTE: Be prepared to provide updates to LEVEL TWO radiopager personnel every 30 to 60 minutes. I Page 4 of 41 - s

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EPIP 1.5-2-D R;v. 13 MAR 311983 (EPIP3) 3.4.4 Within 30 minutes of initiating the radiopager message, review the call-back recorders to verify that LEVEL TWO personnel have respcnded. Record on attachment 2. NOTE:

                                                 " " ~ ~             Call-back verification will be conducted on the 4

initial radiopage, change of incident j classification, and when specific instructions direct individuals to call back for further instructions. 3.4.5 Telephone the State Police Barracks in Colchester, via the dedicated telephone located on the SSSAs console, within one hour to provide a backup to the radiopager. Record on attachment 3. , 3.4.6 Make one (1) attempt to notify, via commercial telephone, those local communities which have not responded to the LEVEL TWO radiopage. (Attachment 5). o If the attempt to notify nonresponding local communities.via commercial telephone is unsuccessfu3, request backup assistance from the appropriate State Police Barracks. (Attachment 8) 3.4.7 Notify the NRC within one hour after incident is classified (as required by 10CFR50.72).

                                               .o          NRC Headquarters (Bethesda) - ENS Hotline o         NRC Region One Office - HPN Hotline

, (During normal business hours ONLY) NOTE: If the NRC Hotline is inoperable or fails, refer-to attachment 4, Emergency Telephone Numbers for NRC Notification. 3.4.8 If the radiopager system is inoperable or fails, telephone all LEVEL TWO personnel listed,in attachment 5 excluding the local communities.

 ;i                                              NOTE:               Request assistance from the appropriate State Police Batracks to make telephone calls to the local communities. (Attachment 8) 1 3.5 Notify support agencies for assistance as necessary.                                                    (Attachment 7) 1 1

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l^ ! , EPIP 1.5-2-D Rev. 13 MAR 31883 (EPIP3) 4.0 ATTACHMENTS / EXHIBITS Attachment Title Page l 1 Incident Report Form 9 2 Call-Back Verification Checklist- 11 3 Backup Phone Call Message to State Police 15 4 NRC Notification Emergency Telephone Numbers 16 5 Notification Guide 17 6 Reportable Events 21 7 Assistance Guide 29 8 Connecticut State Police (CSP) Contact Points 34 9 Reportable Releases 35 , 10 Bases for Reportable Releases 37 5.0 PROCEDURE CROSS REFERENCE 5.1 EPIP 1.5-33. Shift Supervisor's Staff Assistant k i i l . I j Page 6 of 41 i.

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EPIP 1.5-2-D Rev. 13

                 ,                                                                                     j         (EPIP3)             MAR 311983 i-ATTACHMENT 1 l                                              INSTRUCTIONS FOR COMPLETION OF THE INCIDENT REPORT FORM

1. The Incident Report Form is prepared by the licensee and put on the l 2

code-a-phone system recorders, or, if this radiopager code-a-phone '

,                        call-back system is inoperative, use alternate meens as specified in EPIP 1.5-33, Shif t Supervisor's Staff Assistant.

2. The facility operator sends out radiopager messages. Individuals

, receiving the radiopager ressage call-in to get more information from the code-a-phone recorder system. They also leave their name, affiliation, j and time at the sound of the tone. . a 3.- Individuals calling in to the code-a-phone recorder system should use this q form to copy down the information. i 4. The preparer of the message (licensee) should NOT use technical jargon, j abbreviations, etc. This person should use general layman language as

.                        auch as possible, j                  5. The preparer of the message (licensee) should say " inform,ation not l

available" and "not applicable" when appropriate. i 6. The following is the relationship between the Nuclear Incident l Classification Scheme and the State / Local Posture Codes. _ Incident Classification Posture Code 4 GENERAL INTEREST EVENT ECHO T 4 UNUSUAL EVENT without radioactive releases DELTA-ONE 4 UNUSUAL EVENT with radioactive releases DELTA-TWO j ALERT CHARLIE-ONE l SITE AREA EMERGENCY CHARLIE-TWO { GENERAL EMERGENCY without major breach in BRAVO j , containment integrity J GENERAL EMERGENCY with major breach in ALPHA containment integrity a i Page 7 of 41 -

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                ' -                                                                                                             . Rsv. 13 (EPIP3)

MAR 311983 ATTACHMENT 1 (Cent'd) INSTRUCTIONS FOR COMPLETION OF THE INCIDENT REPORT FORM

i. 7. The preparer of the message (licensee) should use the ALERT incident classification / Posture Code CHARLIE-ONE it it is apparent that the POTENTIAL exists for an event more serious than an UNUSUAL EVENT incident classification / Posture Code DELTA-TWO, but event classification is not yet final. This will enable the utility Emergency Response Organization personnel to begin assembly at the Emergency Operations Facilities in a timely manner while the incident / accident assessment is being done. It 1

will also enable State Agencies and local communities to begin actuation of their Emergency Response Organizations.

8. In filling out Item #9 of the Incident Report Form, the affected radius around the site may be increased from that specified in the Incident Classification Scheme. Also, if the need exists for Pro:ective Actions in the downwind sectors beyond the distances prescribed in the Incident i Classification Scheme, additional zones will be designated. Zones in three (3) affected sectors will be given, i.e., the downwind section and each adjacent sector. This item will be filled in only for Site Area Emergency and General Emergency Incident Classifications.

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l! . EPIP 1.5-2-D R v. 13

              ,                                                                                                 (EPIP3)        MAR 311963 INCIDENT REPORT 5-(Please Circle Appropriate Item)                            Report No.

i! I 1. This is of Ii (name & title of person sending message) (organization) j' 2. This report concerns an incident at: ji Millstone Site Millstone Unit 2 Haddam Neck Plant { Millstone Unit 1 Millstone Unit 3 ' j, 3. This IS / IS NOT a drill. i

!!               4.             This is an:        INCIDENT CLASS (Circle One)                                         POSTURE CODE (Circle One) it

e RADI0 ACTIVE MATERIALS INCIDENT -

GOLF j FOX CENERAL INTEREST EVENT - ECHO UNUSUAL EVENT - DELTA-ONE j DELTA-TWO 1-i ALERT - CHARLIE-ONE ! SITE AR'EA EMERGENCY - CHARLIE-TWO 3 GENERAL EMERGENCY - BRAVO 4 ALPHA

The event occurred on at __ hours (use military time) i Date Time l' '

and is being reported on hours (use military time)

                                                                                                                  ~
                                                                                         ,, at Date                             Time

] 1I The event involves:

5. (circle one) i'

     ;                          g RELEASE OF RADI0 ACTIVITY                           TERMINATED RADIOACTIVE RELEASE i;

i POTENTIAL RADICACTIVE RELEASE ONGOING RADIOACTIVE RELEASE

'l

,l 6. Details: ai l

i NOTE: IF CLASSIFICATION IS RADIOACTIVE MATERIALS INCIDENT, GENERAL 4

INTEREST EVENT, UNUSUAL EVENT, OR ALERT, SKIP TO ITEM 10. l i 1 'l, Page 9 of 41 i -

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EPIP 1.5-2-D R:v. 13 l MAR 311983 l , (EPIP3)

7. The wind at the Site is from the into the (Example NNW) (Example SSE) l at MPH.

l' l> 8. It is expected to remain in this direction for hours. t After this time it is expected to shift and blow from (Example NNW) into' . at MPH. (Example SSE)

9. The affected zones for the incident classification being reported are:

Radius Around Site (Miles) Affected Zones . thru l3 thru' l thru l

10. The station status is STABLE / DEGRADING / IMPROVING.

11. Access to the site HAS / HAS NOT been terminated.

12. The following has been requested: POLICE / FIRE / AMBULANCE / NONE /

OTHER ,

13. A further report WILL / WILL NOT be given.

14. Please leave your AFFILIATION (i.e., town / State Agency /NU Dept.),

NAME and TIME at sound of tone. i

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a+, id -- ,e 4_L 2- & - -- -. - - EPIP 1.5-2-D R v. 13 MAR 311983 (EPIP3) ATTACHMENT 2 CALL-BACK VERIFICATION CHECKLIST LEVEL CNE CY/NUSCO TIME CODE-A-PHONE CY Duty Officer NU Nuclear Operation Duty Officer NU Public Affairs Duty Officers State Department of Environmental Protection Mr. Sillin Mr. Ellis

    ;                                Mr. Fee Mr. Counsil                            ,

Mr. Sears Mr. Opeka Manager. - Radiological Assessment Branch NOTE: Contact the NUSCO Duty Officer if any NUSCO LEVEL ONE or TWO personnel

'(                                                              have not responded within 30 minutes. Document confirmation call on this form.           Include the time of confirmation by the NUSCO Duty Officer.

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EPIP 1.5-2-D R v. 13 (EPIP3) MAR 31. ?S83 , ATTACHMENT 2 (Cont'd)

                                                                               ,CALL-BACK VERIFICATION CHECKLISJ LEVEL TWO STATE AGENCIES                                                             NAME                       TIME              CODE-A-PHONE Covernor's Office Office of Civil Preparedness State Police (Troop K)

Colchester i

l' State Police at Hartford State Police (Troop F)

Westbrook 1 t C e I , f i

Page 12 of 41

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CALL _BACK VERIFICATION CHECKLIST LEVEL TWO LOCAL COMMUNITIES NAME TIME CODE-A-PHONE Chester Colchester Deep River d Durham East Haddam East Hampton , Essex Haddam Hebron Killingworth Lyme Madison Marlborough Middlefield Middletown Portland

 ,                               Sales l                               Westbrook I

NOTE: Contact the appropriate person, emergent-y organisation or State

Police Barracks if local communities cannot be contacted. Request j that the First Selectman / Mayor be contacted. A follow-up call to

  !                                                  the organization contacted is required to confirm notification of local conatunities. Document notification on this form.                                                 Include the time of notification.                                                                                                                             j T

l Page 13 of 41 - 3

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{ ATTACHMENT 2 (Cont'd) CALL-BACK VERIFICATION CHECKLIST LEVEL TWO ) CONNECTICUT YANKEE

,                             EMERCENCY RESPONSE ORCANIZATION             Name                                       ETA

, Manager of Communication Managar of Radiological Consecuence Assessment hanager of Onsite Resources Manager of Radiological Dose Assessment Manager of Public Information Electrical Maintenance Mechanical Maintenance I&C Specialist HP Technician ~

!                             Radiological Monitoring Team Radiological Monitoring Team Radiological Monitoring Team Radiological                                                                     -

Monitoring Team Radiological i Monitoring Team

   -                          F.adiological
   !                           Monitoring Team 4

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R;v. 13 MAR 311983 . (EPIP3) ATTACHMENT 3

,                                                            BACKUP TELEPHONE CALL MESSAGE TO STATE POLICE i-(1) THIS IS THE HADDAM NECK NUCLEAR PLANT (2) A STATE INCIDENT POSTURE CODE DELTA-ONE/ DELTA-TWO/ CHARLIE-ONE/ CHARLIE-TWO/

BRAV0/ ALPHA MESSAGE WAS SENT OUT OVER THE RADIOPAGER SYSTEM (3) TAKE POLLOW-UP ACTION WITH STATE DEP 4 . I Name of Sender Date Time I.

f Name of Receiver (State Police)

Local Communities which have not responded: 5 4 I .i !t i i j 't 4 i 1

I Page 15 of 41

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EPIP 1.5-2-D Rev. 13

<>                     ,_                                                                                                                (EPIP3)          MAR 31 E63 l!                                                                                                      ATTACHMENT 4
     !                                                                     NRC NOTIFICATION EMERCENCY TELEPHONE NUMBERS TELEPHONE SYSTEM                                                              TELEPHONE NUMBER

1. Emergency Notification System (Lift Receiver from Cradle) to NRC Operations Center f 2. Commercial Telephone System to 202/951-0050
NRC Operations Center (via Bethesda Central Office) j 3. Commercial Telephone System to 301/427-4056 NRC Operations Center

] (via Silver Spring Central Office)

4. Health Physics Network to *22 (Touch-Tone)

NRC Region One Office 22 (Rotary Dial)

5. NRC Region One Office 215/337-5000

6. Commercial Telephone System

__ to NRC Operator (via-Bethesda Central Office) 301/492-7000 . 1 4 i i i T i I ii

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EPIP 1.5-2-D . . Rev. 13 . MAR 311983 - > - i ATTACHMENT 5 NOTIFICATION CUIDE i' NOTIFICATION TELEPHONE NUMBERS NOTIFICATION DOCUMENTATION ORCANIZATION I.EVEL TITLE NAME BUSINESS I!OME DATE TIME PERSON CONTACTED

Connecticut 1&2 Station Yankee Superintendent R. H. Graves Notify all Unit listed Superintendent J. H. Ferguson Services . Superintendent R.'Z.. Test Securdty Shift Supervisor

t Northeast 1&2 Utilities Duty Officer T. Dente Nuclear '

Engineering.- and Duty Officer W. Dietz Operations , Notify one Dut.y Officer D. Moore of listed

              . Duty Duty Officer     W. Bartron Vice President Night Line Nuclear N __        _7 ~

Page 17 of 41

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EPIP 1.5-2-D .. Rsv. 13 . ATTACHMENT 5 (Cont'd) NOTIFICATION CUIDE [ NOTIFICATION . TELEPHONE NUMBERS NOTIFICATION DOCUMENTATION 1. ORCANIZATION LEVEL TITLE NAME BUSINESS HOME DATE TIME PERSON CONTACTED

Northeast 1&2 'Vice President

                      - UtilicAce                                           Nuclear                                                                                                              ,

Nuclear Operation J. F. Opeka Engineering and Operations Sr. Vice Pres. Nuclear Eng/ Ops W. G. Counsil Exec.Vice Pres. . Eng/Opa W. F. Fee 4

      .               . Northeast                    1&2 Utilities System                                              Duty Officer     A. E. Nericcio                                                                                      t Communica-

. tion Duty Officer E. C. Hill - Notify one of listed' Duty - Duty Officer R. A. Winkler Officers Manager System Nuclear Info R.S. Bromberg .

                                                                                 .                                                                                                               t Page 18 of 41 w

_ . . - - . . -- -- ---- - tysy ;,,_;.y 4 Rzv. 13 . ATTACHHENT 5 (Cent'd) MAR 311983 N9TIFICATION CUIDE . NOTIFICATION TELEPl!ONE NUMBERS NOTIFICATION DOCUMENTATION . *? ORGANIZATION LEVEL TITLE NAME BUSINESS !!OME DATE TIME PERSON CONTACTED State Dept. 1&2 Commissioner S. Pac . of Environ-mental

No, response to COLF, FOX, ECHO, t Protection radiopage within 1 hour of initiation Nuclear 2 Region I NA l Regulatory I&E Cocimission ' Resident Inspector T.-Rebelouski State Police 2 Colchestar Dispatcher Northeast Manager

Utilities Ins. & Claims R. M. Seger Insurance See Note 1 Analyst T. J. Connell American Nuclear N/A Insurers (ANI)

Emergency Local Chester Dispatcher - Communities Colchester First Selectman Deep River First Selectman

                      .                             Durham           First Selectman
              ,                                     East lladdam     First Selectman Police East flampton    Department                                       -

Emergency Essex Dispatcher Fire lladdam Dispatcher Emergency lichron Dispatcher Emergency Killingworth Dispatcher: Lyme First Selectman

            . N0'fE 1         Ir. the event of an incident involving a f atality or'seriou. a. 3-cy, svaramanation or significant damage such as that caused by, fire, explosion, lightning or loss of electrical power, make a telephone report of the circumstances to one of the persons listed within one (1) hour.                  If unable to contact
                          -    cither individual, contact the insurer listed directly.

PaEe 19 of 41

Rev, 13 . i. MAR 311983 T- i! ATTACHMENT 5 (Cont'd) NOTIFICATION CUIDE -{

  !                                     NOTIFICATION                                                 TELEPl!ONE NUMBERS          NOTIFICATION DOCUMENTATION
               ' ORGANIZATION                LEVEL                TITLE               NAME              BUSINESS    HOME     DATE      TIME           PERSON CONTACTED Police                                                                                                  ,
                                                         . Madison               Department "                        .(24 hour number)

Marlborough First Selectman. Middlefield First Selectman ;I '- Fire I Middictown Dispatcher - (24 hour number) Fire U Local 2 Portland Dispatcher - (24 hour number) Communities Emergency - p.

Salem Dispatcher - (24 hour number)

Emergency Westbrook Dispatcher - (24 hour number)

SALEM Emergency Dispatcher must be called on the Control Room telephone numbers ,

m . _ . , _ _ . . - 4 9 Page 20 of 41

Rzv. 13 - - MAR 311983 ." ATTACHMENT 6 '

               ,                                                                                                        REPORTABLE EVENTS                                                   -

STATE STATE NRC NOTIFICATION OTHER REPORTING - EVENTS INCIDENT REPORTING REPORTING LEVEL REQUIREMENTS ' POSTURE CODE REQUIREMENT REQUIREMENT ; General Emergency A or B Within 15 Within 1 2 minutes hour Hotline 1 - Site Area Emergency C2 Within 15 Within 1 2 minutes hour Hotline l ,

          . .}

Alert Cl Within 15 Within 1 2 minutes hour Hotline

              ..I
         .I                                                 Unusual Event                                          D2                Within 15   Within 1            2                               i

{ D1 minutes hour Hotline I; Any event requiring initiation of the licensee's emergency plan or any section of that plan, f, t The exceeding of any Technical D1 Within a Within 1 f f, Specification Safety Limit. few hours hour Hotline 2 NOTE 5 i

                                                                                                                                               NOTE 1                                              i'
           -i
        .i                                                                                                                                                                                            :

e Any event that results in the nuclear D1 Within a Within I f {l power plant not being in a controlled - few hours hour Hotline 2 , or expected condition while operating NOTE 1 ! j or shutdown. - NOTE I 10CFR50.72 item. Report on NRC Hotline. Also during normal working hours, j telephone regional office (see attachment 4). NOTE'S Notify Vice President. Ncclear Operations and NRB Chairman within 24 hours, (Technical Specification 6.7.1.b item). . t

},

Page 21 of 41

   ;                                                                                                   EPIP 1.5-2-D                 .

Rsv. 13 - ATTACHMENT 6(Cont'd) MAR 3123 . REPORTABLE EVENTS - STATE STATE NRC NOTIFICATION OTHER REPORTING -

   ;                     EVENTS                  .           INCIDENT          REPORTING    REPORTING       LEVEL        REQUIREMENTS            j.

POSTURE CODE REQUIREMENT REQUIREMENT i , , I- t Any act that threatens the safety of D1 Within a Within 1 2 ! the nuclear power plant or site per- few hours ' hour Hotline sonnel, or the security of special NOTE 1 nuclear material, including instances of sabotage or attempted sabotage. Any event requiring initiation of E Within a Within 1 1 shutdown of the nuclear power plant few hours hour Hotline in accordance with Technicial Speci- NOTE 1 fication Limiting Conditions for Operation.

Personnel error or procedural ~in- E Within a Within 1 1 i e adequacy which, during normal few hours hour Hotline ! i operations, anticipated operational EOTE 1 1j occurrences, or accidental conditions,

   -;              prevents or could prevent, by itself, "i-the fulfillment of the safety function                                                                                        ,

of those structures, systems, and

                 . components important to safety thar                                                                                           <

are needed to (1) shutdown the ; i reactor safely and maintain it in a [ j safe shutdown condition, or [ (ii) remove residual heat following l reactor shutdown, or (iii) limit ; l the release of radioactive material [ to acceptable levels or reduce the t

.j                  potential for such release.                            .

NOTE 1 10CFR50.72 item. Report on NRC Hotline. Also during vormal working hours telephone regional office (see-attachment 4). . E ,3 ( Page 22 of 41

_ . . . _ _ _ _ __ _ _ . _ _ m. - . . _ .. _ _ _ _ - _ _ . . _ _ _ _ _ . . . _ _

                                                                                                                               ~. . _ _ _ _ . _ _ _ _ . _ - _ _ _ . _ .                                  . _     _ _ _ _           _

EPIP 1.5-2-D . Rev. 13 . ' .., i + ATTACHMENT 6(Cont'd) buut31I9B3 REPORTABLE EVENTS - 1 - STATE STATE NRC NOTIFICATION OTHER REPORTING - , 1 I EVENTS INCIDENT POSTURE CODE REPORTING REPORTING LEVEL REQUIREHENTS 3

REQUIREMENT REQUIREMENT

     -                           Any event resulting in manual or                            D1                     Within a             Within 1                             2 automatic actuation of Engineered                                                  few hours            hour' Hotline                                                                                                       i
                               - Safety Features, including the                                                                          NOTE 1 Reactor Protectiod System.

Any accidental, unplanned, or D2 Within 15 Within 1 2 uncontrolled radioactive release, minutes hour Hotline j ' (Normal or expected releases from maintenance or other operational NOTE 1 activities are not included.)

   't i

Any fatality or serious injury occur- E Within a Within 1 1 NOTE 6 ring on the site and requiring trans- few hours hour Hotline port to an offsite medical facility NOTE 1 for treatment, i Any serious personnel radioactiv'e. D1 Within a Within 1 2 NOTE 6

           ,                     contamination requiring extensive                                                  few hours             hour Hotline onsite decontamination or outside                                                                        NOTE I assistance.

Any event meeting the criteria of D2 Within a Within 1 2 ' NOTE 6 j 10CFR20.403 for notification. few hours hour Hotline 1 NOTE 1 rq. NOTE 1 IDCFR50.72. item. Report on NRC Hotline. Also during normal

      <                                     vorking hours telephone regional office (see attachment 4).

s . NOTE 6 In the event of an incident involving a fatality 'or serious injury, contamination or significant '

damage such as that caused by fire, explosion, lightning or loss of electrical power, make a j1

      ;                                     telephone report of the circumstances-to one of the individuals listed in attachment 5 in the                                                                                                                  !

NU Clains'and Insurance section within one (1) hour. e i Page 23 of 41 1

EPIP 1.5-2-D .

    -                                                                                                     R2v. 13                       - *   .

MAR 31 M3 . ATTACHMENT 6(Cent'd) ,' REPORTABLE EVENTS - 1 STATE STATE NRC NOTIFICATION OTHER REPORTING-EVENTS INCIDENT REPORTING REPORTING LEVEL REQUIREMENTS i POSTURE CODE REQUIREMENT REQUIREMENT { Strikes of operating employees or E Within a Within 1 I security guards, or honoring of few hours hour Hotline picket lines by these employees. NOTE I Event of significant public interest E Within a 1 ,

       ,               Lat of no public hazard. No radio-                           few hours active release.      Includes but is not limited to

{ n. Anr. unscheduled shutdown esti-mated to last more than 48 hours. i (State)

b. Any scheduled shutdown for testing, i maintenance, or refueling expected to last.nore than 72 hours. (State)

c. Derating caused by Regulatory Action.

(State)

d. Derating greater than 50% caused by equipment malfunction lasting more than 72 hours. (State)

NOTE 1 10CFR50.72 item. Report on NRC Hotline. Also during normal working hours telephone regional office (see attachment 4). q . 1 Page 24 of 41

          - . - - . _ . . . . - - . . . . . . .   - . . - - ~ -

EPIP 1.5-2-D .

   )                                                                                                              ' Rev. 13                             -

AGU1311983 i ATTACRMENT 6(Cont'd)

j. - ~. .

 .i                                                                              REPORTABLE EVENTL                                                              .

l, STATE STATE NRC NOTIFICATION OTHER REPORTING EVENTS INCIDENT REPORTING REPORTING LEVEL REQUIREMENTS i POSTURE CODE REQUIREMENT- REQUIREMENT

e. Loss or damage to major system E (Cont'd) Within a N/A 1 NOTE 6 components. (NUSCO) few hours

f. Fish kill, unusual fish entrap-ments, or unusual environmental situation. (NUSCO)

                      .g.        Oil'apill or other contaminants                           NOTE 3                                        NOTE 6 into river water.              (State)

h. Incident that required police assistance. (State)

   ,                    i.       Incident that requires fire                                                                             NOTE 6
   !                             department assistance for fire lasting LESS than 10 minutes.

(State) I

  '[                   NOTE 3             Requires a telephone call to the Coast Guard, National Response Center and Spill Response Center of                       '

d Connecticut State DEP, within one hour of occurrence. (Refer to Assistance Guide for telephone number.) NOTE 6 In the event of an incident involving a fatality or serious injury, contamination or significant damage such as that caused by fire, explosion, lightning or loss of electrical power, make a telephone report of the circumstances to one of the individuals listed in attachment 5 in the NU Cleins and Insurance section within one (1) hour. Page 25 of 41

EP1P 1.5-2-D . Rav. 13 . . ATTACHMENT 6(Cont'd) MAR 317983 I. REPORTABLE EVENTS . i . .I . STATE STATE NRC NOTIFICATION OTHER REPORTINC - ,

!                                                             EVENTS                                 INCIDENT          REPORTING   REPORTING      LEVEL          REQUIREMENTS             l

~A POSTURE CODE REOUIREMENT REQUIREMENT

 \
 +                                                                                                                                                                                        t 4

Report of thef t or loss of radio- F Within a Within hours 1

  ,                     active material in accordance with                                                             few hours
]

10CFR20.402 (Ref. 10CFR30.71)

 }                      Radioactive material transport                                                     G           Within a    N/A                  1        NOTE 6 accident taking place in Connecticut                                                           few hours
'l Reports'of overexposure and                                                        E           Within a    30 Days              1        NOTE 6 excassive levels and concen-                                                                   few hours trations in accordance with
  ;                     10CFR20.403 and 10CFR20.405.

All Section 6.9.2-a E Within a 24 Hours 1 Safety Technical Specification few hours Reports All,Section 6.9.2-b N/A ' N/A 30 Day N/A Safety Technical Specification NOTE 2 Reports

All Section 5.6.2-a(1) E Within a 24 Hours 1 f Environmental Technical Speci- few hours

  ,                     fication Reports NOTE 1                                        Requires a telephone call by the Duty Officer to the NUSCO Nuclear Operations Duty Officer preferably the day of occurrence but no later than the morning of the next working day, NOTE 6                                        In the event of an incident involving a fatality or serious injury, contamination or significant
                                                                      ' damage such as that caused by fire, explosion, lightning, or loss of electrical power, make a l                                                                   telephone report of the circumstances to one of the individuals listed in attachment 5 in the i                                                                    NU Claims and Insurance section within one'(1) hour.                                                                   ,

Page 26 of 41

~, EPIP 1.5-2-D . i Rev. 13 t, I ATTACHMENT 6(Cont'd) NUdt 311983 .. ( REPORTABLE EVENTS , t STATE STATE NRC NOTIFICATION OTHER REPORTING - EVENTS INCIDENT REPORTING REPORTING LEVEL REQUIREMENTS ; POSTURE CODE REQUIREMENT REQUIREMENT All Section 5.6.2-a(2) N/A N/A 30 Day N/A Environmental Technical Speci- NOTE 2 fication Reports i All Section 5.6.2-b(1) N/A N/A 10 Day N/A i NO E 2 m a All Section 5.6.2-b(2) N/A N/A 30 Day N/A Environmental Technical Speci- NOTE 2

    ,                       fication Reporte All Section 5.6.2-c                                                                      N/A        N/A           30 Day                  N/A l

Environmental Technical Speci- NOTE 2 fication Reports Any unexpected or unanticipated E Within a 24 Hours 1

      ,                     service water system leaks within                                                                   few hours containment IEB 80-11-21-80 Serious Security Loss. Refer to                                                          E          Within a      Within 1                1 SEC 1.3-32 for reporting requirements.                                                              few hours     hour Hotline NOTE 1 NOTE 1                                              10CFR50.72 item. Report on NRC Hotline. Also during normal working hours telephone regional office (see attachment 4).

NOTE 2 Requires a telephone call by the Duty Officer to the NUSCO Nuclear Operations Duty Officer preferably the day of occurrence but no inter than the morning of the next working day.

Page 27 of 41

                                          .-.   .. _-    . . .                ..          . . .  -     =.
           . . . w..    -.    .    . . . . . ,.    - - . .

EPIP 1.5-2-D . Rzv. 13 q ATTACHMENT 6(Cont'd) AUUl 311963 , REPORTABLE EVENTS STATE STATE NRC NOTIFICATION OTiiER REPORTING > '; EVENTS INCIDENT REPORTING REPORTING LEVEL REQUIREMENTS' f POSTURE CODE REQUIREMENT REQUIREMENT ) 1- ,

  ;                  Serious damage to plant                           N/A              N/A       NOTE 4               N/A j.

equipment or facilities. y i Ii I, i { Load decrease greater than 25% N/A N/A NOTE 4 N/A

   !                 or anticipated removal of unit I                  from se~rvice within next 24 hours.

r 3 c. i NOTE 4 Requires a telephone call by the Duty Officer to the NUSCO Nuclear Operations Duty Officer within one hour of determination.

Page 28 of 41

EPIP 1.5-2-D .

   -                                                                                                                   Rev. 13-                                  .
                                                                        -ATTACHMENT 7 (Cont'd)                        FAR 311983 ASSISTANCE CUIDE                  .
                                                                                     . TELEPI!ONE NUMBERS               NOTIFICATION DOCUMENTATION AGENCY                                         TITLE          NAME                BUSINESS     HOME       DATE      TIME       PERSON CONTACTED State Police                  Colchester               Dispatcher Fire Department               Haddam Neck              Dispatcher 1

Ambulance East flampton Dispatcher 4 Hospital Middlesex Memorial L Lawrence Memorial b)6 Doctor Medical Dr. H. Levine . Consultant - Radiation President 'Dr. R. tfanagement Corp 1 Linnemann Coast Guard Captain of " Lieutenant

                                      .the Port                 Commander ~                s     ~ ~         - --

M. A. Conway

                                                                             .Page 29 of 41

    .           _.       . . .      . ._ _.._.                __.._.__m                   _      __... .- _.                 ._. _,..___ ___ . .. _ . . .           _  . _ .         _      _

EPIP 1.5-2-D . s

                                                                                       ',                                       Rev. 13                                         -
                                                                               ' ATTAChMDCE 7                                       MAR 311983                                          .

ASSISTANCE CUIDE - 1 TELEPHONE NUMBERS NOTIFICATION DOCW.ENTATION - AGENCY TITLE NAME BUSINESS HOME DATE TIME PERSON CONTACTED t-V '

        -State Office of                        Duty Officer Civil. Preparedness
        . National Resource                     Duty Center                                 Officer Spill Response Center                  Duty Officer of Connecticut State Department                       Duty Officer of Environmental                                                           "

Protection ,

        .Brookhaven National                    Chief Engineer D. Schnelley Laboratory                             Operations Combustion Engineering                                      R. Hoover General                                Director Rad Control                                                                                                                           !

Dynamics (normal weekday) (Electric. . Rad Control Foreman Boat). (off hours, weekends) Security Officer 1

                                                                   ,                                                                                                                        't United Nuclear                         Manager              W. F. Kirk"                                         ,

CorporationL Nuclear Safety .

I A

Page 30 of.41 1

  ._ - _ _ = _ _

p 'EPIP !.5-2-D . , i. . Rev. 13 - 1' ATTACHMENT 7 MAR 311983 - - ASSISTANCE CUIDE f

TELEPl!ONE NUMBERS NOTIFICATION DOCUMENTATION -

           ,-                        AGENCY                                  TITLE        NAME                                                        BUSINESS HOME    DATE   TIME                                          PERSON CONTACTED                  {

Millstone Station Unit 1 Shift ! Supervisor Unit 2 Shift Supervisor INPO Duty Officer Emergency

            ;                                                                         Telecopier 9:

Westinghouse . Field Service George Dillor.

Manager let Alternate Steve Swigart - 2nd Alternate Ron Von 0sinski t Service

Bob Stokes

Response

Manager

1 let Alternate John. Miller [ , A~~_.___ __

                                                                                                                 ,$Page31of41

EPIP 1.5-2-D . Rev. 13 - - ATTACHMENT 7 MAR 311983 , ?. ASSISTANCE CUIDE . TELEPl!ONE NUMBERS NOTIFICATION DOCUMENTATION AGENCY TITLE Nt.ME BUSINESS Il0ME DATE TIME PERSON CONTACTED . 2nd Alternate Dave Campbell Emergency Tom Anderson

Response

Director Emergency Ron Lehr Response l Director Emergency. News Mike Mangan Communications

Shipman Fire General E. Wallace

Equipment Manager l

l. AMTRACK ~ Ceneral ,R. Duggan j, Superintendent

                                                                        *~ %                  . . . .     -
                                                                        'Page 32 of 4'l

j -

                                                                                          .                       EPIP 1.5-2-D              .
!                                                                                                                 R v. 13                            -
                                                                                                                                                       ~
      .                                                                          ATTACHMENT 7                      MAR 311983

ASSISTANCE CUIDE *i TELEPIIONE NUMBERS NOTIFICATION DOCUMENTATION ,

AGENCY TITLE NAME BUSINESS I!OME DATE TIME PERSON CONTACTED Datteo, Inc. President L. A. DeVivo 4

                                                       .                                                                                                      t i                                                                                                                                                            j.

Beebe Transportat1~on General M. O' Leary [ Manager

                                                                                                                                                              !i i                 Nichols Bus                       President      C. Nichols
  .                 Interex                                          D. Newton Corporation                                      R. Fix                         ,

4 i' Teledyne A. Ilayter > Isotopes J. D. Martin

11. Jeter Travelers Weather

                   -Service e
                                                                                       -Page 3'l of 41

                  ..                                                                                                                EPIP 1.5-2-D                 '

Rsv. 13 i MAR 311983 ATTACHMENT 8 { CONNECTICUT STATE POLICE (CSP) CONTACT POINTS I HADDAM NECK Colchester CSP Barracks (Troop K) Westbrook CSP (Troop F) Via Hot Line Via Telephone: 399-6221 Colchester Chester East Haddam Deep River East Hampton Durham Hebron Essex Marlborough Haddam

Portland Killingworth l Salem Lyme Madison t Middlefield Middletown

   !                                                                                             Westbrook NOTE:         This list is to be used AFTER station attempt to contact local communities by telephone.

9 OGu @e. m *M eW-e @ I 1 4 4 I 5 . 1, i I

t

l 1 .

Page 34 of 41~ . X .*

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                                                  .~v.-,  .~v,-,-..m..~.--:--n--          > -       ,~. - v : , . . ,--n : i- v~ -   --   -~   -s ,e v - :
                                                                           .     ,                              _ ,                        ~ -          , ,   #-i

                                  "~                                                                                     -             "                     "
                                                                                                  . .. . n
                                                                    ~

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l, -

                      ..                                                                                                               EPIP 1.5-2-D Rav. 13

f. . .

                            ,                                                                                                          M 311S83 i

j - ATTACHMENT 9 REPORTABLE RELEASES . i

The following releases are reportable

j 1. Any release, liquid or gaseous, exceeding technical specifications. 4

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:

                                                                  -7 1 x 10 uCilal for liquids or, 1 x 10-0            uCi/cc for airborne particulates or iodine or,
                                                                  ~

j 2 x 10 uCi/cc for airborne noble gases. l

j. .

3. Unplanned Liquid Release Reporting Criteria'

1) Any release (planned, unplanned, monitored or unmonitored) exceeding 1 the technical specification instantaneous release rate limit. That li is: The sum of the MPC fractions (per 10CFR20. App. B. Table II, j Column II) after dilution exceeds one.

1 . Dilution should be taken credit'for. Therefore, if the release is

into the CY discharge canal, the dilution by the plant circulating.

i water should be used in determining diluted concentrations and

therefore MPC fractions.

I j 11) Any unplanned or unmonitored release for which the total activity released (excluding Tritium and dissolved gases) exceeds 1 n 10"

curies (or 1000 microcuries).

[ iii) Any release less than the above limits need not be reported due to - i the release itself, unless of course the initiating event is of such i importance that it is determined to be reportable on its own. i i ; 4. Unplanned Gaseous Release Reporting Criteria 1 Any increase 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 j planned or expected event.

h 1 i i i i i 1 I

     'l I

lI Page 35 of 41 - 1 ~

                                                                                                                \   .
          .;.,_-__.y.                      ,a-.-..  . , . . ~ . -
                                                                       ~m e - .Q.-- - -~ ~          .
                                                                                                                      ~ .-

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EPIP 1.5-2-D

                          ..                                                                                                         R:v. 13
                 * =

4'

           ,-       =
                                                                                                    ,                             MAR 311983 e

ATTACHMENT 9 (Cont'd) REPORTABLE RELEASES Note 1: It is recognized that what constitutes a " planned or expected event" is still ambiguous at this time. However, the following philosophy should be used: i) If the increased release rate is less than 1500 uci/see above normal 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, but is due to a planned activity which is known to be the cause (e.g., increasing power level, releasing a vaste 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 grcater 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. I Note 2: The stack monitor reading in CPM which corresponds to the normal reading plus 1500 uCi/sec depends on the normal reading at that time, the latest monitor calibration factor, and the number of ventilation. fans operating. Since these parameters are subject to 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 following a calibration, or change in the activity verses count-rate calibration graph.. Example - MP2 stack monitor Normal reading has been running at 25 CPM Present monitor calibration factor,= 6.2 uCi/sec per CFM (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 alarm set point should be set at or below 265 CPM. t i .

Page 36 of 41

    . + - . - +                    -

w ., ewe, y per winery ,~me , ++9s-ocee-tw - ,m
mpy epw w e+ y -e*w+- -e- e ~w=- =~my-e.-

                                                  . _ - , . _                                                    ..         .-.-m--.-

EPIP 1.5-2-D p ,\,.' . Rav. 13

c' ., MAR 31583 l ATTACHMENT 10 BASES FOR REPORTABLE RELEASES Criteria 1 -

Exceeding technical specification limits i This criteria is clear. Any release, whether due to a planned or unplanned event or activity, must be reported if the technical specification limits were exceeded. Criteria 2 - Unmonitored Releases

1) Established Monitor -

, i

    ;                                                                       Any release from a path which has a fixed monitor (e.g.,

l

stack, MP1 isolation condenser vent, steam generator

                                                                          blowdown line, etc.) would not be reportable due to the unmonitored release criteria.                       If the monitor was inoperable, but grab samples were being taken in accordance 2

with the action statements in the technical specifications, i

then likewise any releases would not be reportable.. 4 .

11) Established Sampling Program -

l - There are certain paths which do not have a fixed monitor

                                                                           -but have an established sampling program where grab samples ar,e obtained on a fixed schedule. The main. reason these .                                                                     _

f pathways are not monitored is because the potential release rates are less than the lower limit of detection for gross

monitors. Since grab samples are more sensitive, they are i used to'dt.act and hence account for any low level releases from these pathways. For example, 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.

j ,, iii) Release Concentrations - 1 x 10 uCi/ml, etc. }} ' There are numerous release paths of trivial amounts of plant related radioactivity at our sites which are not

'Ij                                                                         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                                                                            )
;{i                                                                         outside, etc.         If samples were taken from some of these                                                                      l J

l ; il i 1 i . Page 37 of 41 J

          ,,              , , ,                ,               -                        --a r M - wm e%=    - os ar wm-r. -   e     ~-     *-*-=**mP'es*
                                                                                                                                             . _ '         *w"*-    -
                                                                                                                                                                            * " - * ' * * = ' *
  . - - - _ _ - _ _ . . . - _ _ . _ _ _ _                                          _                          .-                                                 ,,     .                     - ~ ,

                           . _. . ;_; _ r -                                 - n        . _ _ .
                                                                                                                .c : . .- -       --   . ~ . . 2 EPIP 1.5-2-D R:v.-13 w

M 31 SS3 i ATTACHMENT 10 (Cent'd) i BASES FOR REPORTABLE RELEASES 4 pathways and counted at low background laboratory, plant

,                                                  related activity could be detected. This is a recognized i                                                   fact. It is also recognized that the total contribution l,                                                  frcm these pathways is trivial and insignificant compared to the releases from the monitored release paths. Hence,

] these releases do not have monitoring or sampling j , requirements. ) There is a potential for releases of non-trivial levels of j radioactivity from unmonitored paths. This would most likely be due to an accident, equipment failure or human j error (e.g., a leak develops in a tank truck being used to transfer liquid wastes onsite. 1 i Criteria are, therefore, required to determine which l unmonitored releases are trivial and do not require j . reporting and which are non-trivial and should be reported. The concentrations listed in attachment 9 represent the dividing line. The concentrations given are the most limiting value from either 10CFR20.- Appendix B - Table II

                                                  -(Maximum Permissible Concentrations in Air and Water l            _                         _

Outside'the Site Boundary) or 10CFR30.70, Schedule A. ~ j . (Exempt Concentrations in Gas and Liquid). j ' Criteria 3 - Unplanned Releases (Liquids) i) Exceeding Instantaneous Tech. Spec. Concentration Limit j This criterion is clear. Any release, whether planned or

unplanned, must be reported if the Technical Specification limits were exceeded.

                                                                                     -3 Curies

[ j ii)~ Total Activity Limit 1 x 10 j As discussed in the referenced 1981 letter for gaseous j releases,'there must be a clear dividing line between what 4 constitutes a trivial release that does not warrant j reporting and what constitutes a non-trivial reportable i release per the intent of 10CFR50.72. In-this regard, i nontrivial refers to the potential NRC, state or public interest in the event. The potential public health corisecuences are still triviai at these levels. i It was determined that the criteria should be based on total curies released rather than concentrations or release

}   .

rates. The total curies are directly related to the dose which is the item of interest. A release of 10,000 gallons of 1 x 10 uCi/cc water h'as a greater dose co.nsequence

  ;                                                than a release of 1 gallon of 1 x 10" uCi/cc water.

i Page 38 of 41 j .

          . __,._ ,__.                          .     .___m.                                   _ ~_              _ . _ . - _ _                   _

2-. .: u : '- - - ~ - - - - - ^ ' - EPIP 1.5-2-D

                  , ,. ., .                                                                                                                          R:v. 13
                                 ,                                                                                                                 MAR 311983 Releases of any significance from a concentration viewpoint would be reportable per criterion i above.

The value of 1 x 10

                                                                                            -3 Curie was chosen based on the following i                                                                     criteria:

1 i) NRC NURECn'0016 and 0017 provide the methodology to be used to make realistic estimates of the annual gaseous and liquid Curie releases from BWRs and PWRs respectively. The i NUREGs are used to ensure that the design basis of the plant meets the requirements of 10CFR50 Appendix I. They

were used for our Appendix I design submittals in 1976.

Attached is page 1-7 from NUREG-0017 (NUREG-0016 is i . similar). As indicated in Section 1.5.1.16.1 the design basis for our plants assume liquid releases of 0.15 Ci/ year per reactor from anticipated occurrences such as operator 3 error resulting in unplanned releases. The value of 1 x 10 Curies was chosen as being less than 1% of 0.15 Curies. It is considered insignificant and, therefore, not within the intent of 10CPR50.72 if the Curies released during any one event are less than 1% of what-the NRC already anticipates from unplanned events. We would not anticipate more than 2 to 5 such events during a year and,~ j hence, the total Curies from unreported events should still be well below 10% of the anticipated amount. *

l

ii) 1 x 10 Curies is less than 1% of the' average ~ annual-1 release of liquid activity per reactor. iii) The resulting dose tc the maximum individual from a release

of 1 x 10 Curies would conservatively be in the range of: at CY ,

                                                                                         ~3 2 x 10 area whole body dose from a typical mixture 1 x 10 -3 mrem thyroid dose if all I-131                                           .

These doses are truly insignificant. They are less than 1% of the average daily background dose and are less than 0.1%

   .j                                                                      of the Appendix I annual design limits for liquid                                        .

effluents. . Criteria 4 Unplanned Releases (Gaseous) 1 The routine operation of.a nuclear power plant results in .-l numerous increases and decreases in gaseous release rates.

      ;.                                                             Valve packing and pump seals may leak at various rates, startup 7

or shutdown of a system may result in brief puff releases 'due to j pressure transients, opening up a system for maintenance will i release-trapped gases, etc. Most of these changes are so.small

    -]                                                               that they cannot be' detected on the stack monitor. Some of them-i                                                              may cause slight increases in the monitor response. Any release.
                                                                    .of significant levels will cause'a significant increase in the

j. .'

, e monitor response. i F Page 39 of 41 . .

                                                                   ,--,,.--,,.:..n.3-,-                                  - . - - - .               ,-~e--~~~.
                     .~              ,   . . , . . .         -- -                - ,            ,,e   , . - . . - -                  . --,       .                    . . .           - , , - ,

EPIP 1.5-2-D 4*.

A, . Ray. 13

              .      e-
                                                                                                            .                                     VAR 311983 -

ATTACHMENT 10 (Cont'd) BASES FOR REPORTABLE RELEASES ! l. 1 It is not feasible for an operator to explain every minor f 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 report all such increases as

                                     ,             it would lead to a large volume of reports which serve no purpose but to prove that the routine operation of a nuclear plant results in numerous increases and decreases in gaseous                                                                        >

release rates. It is therefore necessary to define the difference between these + minor increases and a significant increase. If the release is significant, then it should be either due to a planned or , expected event or it should be reported. 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/see. 1 The value 1500 uCi/sec was chosen based on the following facts:

1. The-limiting noble gas concentration from 10CFR20 -

Appendix B - Table II for offsite noble gas concentrations ,

                                                                                -8 4

is 2 x 10 uCi/see for kr-88. The maximum annual average [ i X/Q from either the CY stack, MP1 stack or MP2 stack at the critical site boundary is 1.3 x 10-5 ,,,jy3 . Assuming this I/Q, the required release rate to get 2 x 10-8 ; uCi/cc is:

      ,                                                      2 x 10 -8          uci/cc/(1.3 x 10-5 ,,,j,3                  . 10-6 ,3je, ,                                             ,

1540 uCi/sec l l l Thus, for the most limiting nuclide, the most limiting [

, i                                                          release point, and the most limiting site boundary, a
       ;                                                     release rate of 1500 uC1/see will result in concentrations l                                                    less than allowed by 10CFR20.                                                                                            :

I i-6 4

i , Page 40 of 41' .! j .

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                                                                    ~ -           - . - ~ - -              - -          - - -
          .                                                                                                      EPIP 1.5-2-D j[ *,

4 .
R:v. 13 ,

l MAR 311983 i ATTACHMENT 10 (Cont'd) BASES FOR REPORTABLE RELEASES

2. For the same limiting site boundary and CY stack release point, the expected I hour dose from a release rate of 1500 uCi/see 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 MREM.

3. The noble gas concentration in CY primary coolant is approximately 2 uCi/nl. Thus, a leakage rate of 750 ml/see vould result in a release of 1500 uCi/sec into building air and eventually to the stack. 750 ml/see is equal to 11 gallons per minute which is not untypical of potential leakage rates from leaking valves or pumps.

4. The present background reading on the CY stack monito_r is 500 cym. The present calibration factor is about 3 uCi/ s sec per cpm. Therefore, 1500 uCi/sec = 500 cpm which is a practical level to detect above the present reading.

i 1

Page 41 of 41 .

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ML20204F355: Difference between revisions

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