ML20081L703
| ML20081L703 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/21/1983 |
| From: | Fry L Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18089A440 | List: |
| References | |
| PROC-831021, NUDOCS 8311160402 | |
| Download: ML20081L703 (199) | |
Text
{{#Wiki_filter:_ SALEM GENERATING STATION EMERGENCY PLAN . EMERGENCY PLAN PROCEDURES INDEX Octobe r 21, 1983 No. 101 U.S. NRC, Dir. of NRR , sECTIoN I - oN-SITE PROCEDURES Washington, D.C. 20555 prv. Nn. Mr. S. A. Va rga , Ch ie f , Ope r. EP I-0 Accident C1dasification #
.. 3 Part 1 Radiological Part 2 Operational-Part 3 Fire / Natural / Security Part 4 Miscellaneous Flow Chart ............................... 1 EP I-1 Notification of Unusual Event /Significant Event . . ........... 5 EP I-2 Alert . .... ..............................
4 EP I-3 Si t e Ar e a Eme rge ncy . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 EP I-4 General Emergency . . . . . ....................... 4 EP I-5 Personnel Emergency . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP I-6 Radioactive Spill . . . . . . . . . . .... . . . ........... 1 EP I-7 Station Fire .............................. 1 EP I-8 Personnel Accountability . ....................... 1 EP I-9 Search and Rescue operations . . .. ........ .......... 1 EP I-10 Conducting an Inventory of Emergency Equipment . . ........... 1 EP I-11 Copununications Equipment . ....................... 1 EP I-12 Site Evacuation . . . .......................... 1 i EP I-13 Post Accident Low Pressure Injection Monitoring . . ........... 1 EP I-14 Initiation of Recovery Operations . . ... . . . . ........... 1 EP I-15 Stable Iodine Thyroid Blocking . .. . ................. 1 EP I Recall of Evacuated Site Personnel ....... . ........... 1 EP I-17 Radiation Protection - Emergency Action . ................ 1 EP I-18 Operations bupport Center Activation ... ............... 1 EP I-19 Activation / Evacuation of the Technical Support Center . . . ....... 1 SECTION II - OFF-SITE PROCEDURES EP II-1 Emergency Response Manager Preparation to Assume Responsibilities . ... 2 EP II-2 Site Support Manager Preparation to Assume Responsibilities . ...... 2 EP II-3 Radiological Emergency Manager Preparation to Assume Responsibilities . . 2 EP II-4 Emergency Response Personnel Support Callout . . . ........... 3 EP II-5 Emergency Paging of Corporate Emergency Response Personnel ....... 3
.EP II-6 Off-Site Administrative Support . . . ... ............... 1 EP II-7 Test,ing of Emergency Procecure EP II-4 ................. 0 EP II-8 Emergency Operations facility Set-Up . ............... .. 0 1 of 3 Rev. 10 8311160402 8311to -
_h- hDRADOCK 05000272 PDR
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e~ SECTION III - SECURITY EMERGENCY PROCEDURES REV. NO. EP III-1. Opening of the Technical Support Centers. ................ 1 EP. III-2 Opening of the Emergency Operations Facility .............. 2 EP III-3' Personnel Accountability. . . .'. .................... 1 EP III-4 Site Evacuation . . . . . . . .. ..... ............... 1 EP III-5 Emergency Vehicle Support . . . . . . .;. . . . . ... . . . . . .,. . . . 1 SECTION IV - RADIATION PROTECTION / CHEMISTRY EMERGENCY PROCEDURE _S 4 EP IV-101 TSC Initial' Re'sponse . . . . . . ..................... 1 BP IV-102 Control Room Initial ~ Response . . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-103 Control Point Initial Response . .. ....... . . . . . . . . . . . . . 1 EP IV-104 TSC: Evacuation . . .. . . . . . ........ ............ 1 EP IV-105 Control Point and Equipment Evacuation ............. .... 1 EP IV-106 ALARA Task Review and Emergency Exposure Authorisation ......... 1 BP IV-107- Radiation Monitor Evaluation . . .................... 1
- EP IV-108 Protective Action Recommendations . . . . .' . . . . . . . . . . . . . . . - 2
'EP IV-109 Plume Tracking by Helicopter . . .................... 1 EP-IV-110A Field Monitoring coordinated by TSC .................. 2 EP IV-110B Field Monitoring coordinated by EOF .................. 0
'EP IV-111 Effluent Dose Calculations . . . ./................... 4 EP IV-112 Emergency Operations Facility - Radiological Assessment . ........ 0 EP IV-113 Computerised Dose Calculations . ..................... 3 EP IV-114 Computerised Dose Calculations on Programmable Calculator . . . . . . . . 1 1- EP IV-115 Personnel and Vehicle Survey . . .................... 1 l EP IV-116 Fire Brigade Escort . . . . . . . ..................... 1
. _ 'EP IV-117 Re-Entry Team Radiation Protection .......'............ .1 l EP IV-118 High Activity Sample Analysis . . . . . . . . . . . . . . . . . . . . . . 2 EP IV-119 Personnel Decontamination .
. . . ..... ............... 1 EP IV-120 Equipment Decontamination . . . . .................... 1 EP IV-121 Containment Atmosphere Remote Sampling ......... . . . . . . . . - .1 EP -IV-122 Emergency Staf fing Guide . . . . .................... 1 EP IV-201 Radiation Protection Senior Supervisor Response . ............ 1 1
EP IV-202 Chemistry Senior Supervisor Response ...... ............ EP IV-203 Administrative Assistant' Response . . . . . ............... 1
- p. EP IV-204 Short Term Environmental Response . . ... ' ... ..... ....... 1 EP IV-205 Material and Instruments Supervisor Response .. ............ 1
. EP IV-206 Dosimetry-Counting Room Supervisor Response . . . ............ 1 EP.IV-207.. Rad Weste Supervisor Response .'. . . . . . . .............. 1 EP IV-208. Dose Assessment - ALARA Supervisor. Response . . ............. 1 EP IV-209 In-Plant Supervisor Response . . ...... . . ............ 1
~
EP IV-210 Procedures-Training Supervisor Response . . . . . ............ 1 EP IV-211 Radiation Protection Communications Guide . ............... 1 l :EP IV-212 Radiation Protection Emergency Inventory Control ............ 1 EP IV-213 Evaluation of RMS Data From High Range Channel R45-D .......... O p EP IV-301 Interim Post Accident Primary Coolant' Sampling ............. 2 EP IV-302 Emergency Sampling Procedure for the Plant vent . ............ 2
.~ '
E 2 of 3 Rev. 10 LI
p . L 9
' SECTION V - ENGINEERING DEPARTMENT EMERGENCY PROCEDURES REV. NO.
~ EP V-1 ' Technical Support Manager Response . ... ...... . . . . . . . . -. 1 EP vw2 Corporate Engineering Support Manager Response (CHERC) . . . . . . . . . O
~
EP V-3 ' Site Engineering Support Manager Response (EOF) ..... . . . , . . . . . 0
, EP V64 Corporate Engineering Team Leader Respense (CHERC) ........... 0 EP V-S Licensing Support Team Leader Response . . ...... . . . . . . . . . 1
). EP V-4 . Fuel Support Team Leader Response . . . . . . . . . ...... . . . . . ., 1 BP V-7 Nuclear Engineering, Quality Assurance Licensing, and Nuclear Fuels . . . 1 HCTION VI - PLAN ADNINISTRATION EP VI-1 Revision and Approval of Plans and Procedures . . . .......... . 2 EP VI-2 Distribution of Plans and Procedures . . . . . . . .. . . . . . . . . . 1 EP VI-3 Review of Plans and Procedures c. . . . . .... . . . . . . . . . . . . 1 EP VI-4 Procedures Format . . . . . - . . . . . ..'...... .......... . 1 2
- OP VI-5 Conduct of Drills and Exercises . . . . . . ... . . . . . . . . . . . . .
- EP VI-4 Inventory of ROF Supply Lockers . . . . . . . . e ........ . . . - . 0 Conduct of Communications Drills . ........... . . . . . . . . O EP.VI-7 SECTION VII - PUBLIC INFORMATION EP VII-l ' Public Information Notification . . . . . . . . . . . . . . . . . . . . . 0
' EP-VII-2 ' General Manager - Information Services Response . .... . . . . . . . . -0 EP VII-3 Public Information Manager Response . ...... ... . . . . . . . . . 0 EP VII-4 Public Information Technical Liaison Response . . . ... . . . . . . . . . U
- EP VII-5 ,Public Information Technical Assistant Response . ... . . . . . . . . . 0 EP VII-4 Internal Inform 9 tion' . . . . . . . . . . . . . . . ... . . . . . . . .
O EP VII-7 Media Relations . . . . . . . . . . . . . . . . . ............. 0 EP VII-8. Emergency News Center Activation /Pulbic Information Coordinator Response . . . . . . . . . . . . ....... . .. . . . . . . . . . O ADDENDVM 4 Addendum 1 Master Phone List . . . .. . . . .... .. . .... . . . . . . . . Addendum 2 (deleted) FIGUnts
' Figure 1 . (deleted)
Figure 2 -Communications / EOF Manning Board .. .. ....... . . . . . . . . . l' Figure 3. . operationsi Status Board . . . . . .. .. ... ... . . . . . . . . . 0 Figure 4 Post, Accident RMS Assessment Data . . . . .... ... . . . . . . . . . 1 Figure 5- Aree/ Process RMS Data . . . . . . . ...... ........ . . . . . O Figure 6 Offsite Dose Summary . . . . . . . ... .. . . ... . . . . . . . . . O Figure 7 ( deleted) Figure 8 . ( dele ted) Figure 9 (deleted) 3 of 3 Rev. 10 l' - ' ' ' ' - - "
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- 4 SALEM GENERATING STATION EMERGENCY PLAN. ,
EMERGENCY PLAN PROCEDURES INDEX October 21, 1983 No. 101 U.S. NRC, Dir. of NRR SECTIoN I - ON-SITE PROCEDURES Washington, D.C. 20555 REv. No. Mr. S.A. Varga, Chief, Oper. EP I-0 Accident Classification # *
^
3 Part 1 Radiological Part 2 Operational Part 3 Fire / Natural / Security . Part 4 Miscellaneous Flow Chart .. .... . . ....................... 1 EP I-1 Notification of Unusual Event /Significant Event . ............ 5 EP I-2 Alert ... .. . ..... ....................... 4 EP I-3 Site Area Emergency . . . . . . . . . . . . . . . . . . . . . . . . .~. . 4 EP I-4 General Emergency . . . . . . . . .... ................ 4 EP I-5 Personnel Emergency . . . . ....................... 1 EP I-6 Radioactive Spill . . . . . ....................... 1 EP I-7 Station Fire .. .... . ....................... 1 EP I-8 Personnel Accountability . ....................... 1 EP I-9 Search and Rescue Operations . . ... ................. 1 EP I-10 Conducting an Inventory of Emergency Equipment . ............ 1 , EP I-11 Communications Equipment . ....................... . 1 EP I-12 Site Evacuation . .. .. . ....................... 1 EP I-13' Post Accident Low Pressure Injection Monitoring . ............ ' 1 EP I-14 Initiation of Recovery Operations . . . ................. 1 EP I-15 Stable Iodine Thyroid Blocking . . .. .................. 1 EP I-16 Recall of Evacuated Site Personnel .. ................. 1 EP I-17 Radiation Protection - Emergency Action . ................ 1 EP I-18 Operations Support Center Activation ..... . ............ 1 EP I-19 Activation / Evacuation of the Technical Support Center . . . . . . . . . . 1 SECTION II - CFF-SITE PROCEDURES EP II-I Emergency Response Manager Preparation to Assume Responsibilities . . . . 2 EP II-2 Site Support Manager Preparation to Assume Responsibilities . . . . . . . 2 EP II-3 Radiological Emergency Manager Preparation to Assume Responsibilities . . 2 EP II-4 Emergency Response Personnel Support Callout . . ............ 3 EP Il-5 Emergency Paging of Corporate Emergency Response Personnel ....... 3 EP II-6 Cff-Site Administrative Support . . .... . . . ............ 1 EP II-7 Testing of Emergency Procecure EP II-4 ................. O EP II-8 Emefgency Operations Facility Set-Up . . .............. .. 0 1 of 3 Rev. 10 1
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e*
'SECTION III - SECURITY EMERGENCY PROCEDURES REV. NO. .
1
. j EP III-1 Opening of the Technical Support Center . . . . . . . . . . . . . . . . . 1 EP III-2 -opening of the Emergency operations racility .............. 2 EP III-3 Personnel Accountability . . . . . ...... .......... ... 1 EP III-4 Sit 6 Evacuation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP III-5 Emergency Vehicle Support.. . . . . ................... 1 SECTION IV - RADIATION PROTECTION / CHEMISTRY EMERGENCY PROCEDURES EP IV-101 TSC Initial Response . ... . . . . ................... 1 EP IV-102 Control Room Initial Response . . . ................ ... 1 EP IV-103 Control Point Initial Response . . .................... 1 l EP IV-104 TSC Evacuation . . . . . . . . . . ..... . .......... ... 1 EP IV-105 Control Point and Equipment Evacuation ....... .......... 1 l EP IV-106 ALARA Task Review and Emergency Exposure Authorization ...... ... 1 EP IV-107 Radiation Monitor Evaluation ... . .................... 1 EP IV-108 Protective Action Recommendations . . . . . . . . . . . . . . . . . . . . 2 EP IV-109 Plume Tracking by tielicopter . . . ................... 1 EP IV-110A Field Monitoring coordinated by TSC .................. 2 EP IV-110B Field Monitoring' coordinated by EOF .................. O EP IV-111 Effluent Dose Calculations . . . . ......... .......... 4
.EP IV-112 Emergency 0perations Facility - Radiological Assessment . ........ 0 EP IV-115 Computerized Dose Calculations . . ................... 3 EP IV-114 Computerised Dose Calculations on Programmable Calculator . . . ..... 1 EP IV-115 Personnel and Vehicle Survey . . . ................... 1 EP IV-116 Fire Brigade Escort . . . . . . . . ................... 1 EP IV-117 Re-Entry Team Radiation Protection ................... 1 EP IV-118 High Activity Sample Analysis . . . . .................. 2 EP IV-119 Personnel Decontamination . . . . . ...... ............. 1 EP IV-120 Equipment Decontamination . . . . . ................... 1 EP IV-121 Containment Atmosphere Remote Sampling ... .............. 1 EP IV-122 Emergency Staffing Guide . . . . . ........... ........ 1 EP IV-201 Radiation Protection Senior Supervisor Response . ............ 1 l
EP IV-202 Chemistry Senior Supervisor. Response ............ ...... 1 EP IV-203 Administrative Assistant Response . . .... .. . . ....... ... 1 EP IV-204 Short Term Environmental' Reeponse . ......... .... ...... 1 EP IV-205 Material and Instruments Supervisor Response ........... ... 1 EP IV-206 Dosimetry-Counting Room Supervisor Response . .............. 1 EP IV-207 Rad Waste Supervisor Response . . . ............. ...... 1 EP IV-208 Dose Assessment - ALARA Supervisor Response . .............. 1 BP IV-209 In-Plant Supervisor Response . . . ................ ... 1 EP IV-210 Procedures-Training Supervisor Response . .. .. ............ 1 EP IV-211 Radiation Protection Communications Guide . ............... 1 EP IV-212 Radiation Protection Emergency Inventory Control ............ 1 EP IV-213 Evaluation of RMS Data From High Range Channel R45-D .......... O EP IV-301 Interim Post Accident Primary Coolant Sampling ... .......... 2 EP IV-302 Emergency Sampling Procedure for the Plant Vent .............. 2 t 2 of 3 Rev. 10 l L- . , ,,- -. -
SECTION V E ENGINEERING DEPAPTMENT EPERGENCY PROCEDURES REV. NO. EP V-1 Technical Support Manager Response . .... . .... ... .. .'... 1 EP V-2 Corporate Engineering Support Manager Response (CHERC) ... ...... 0
.EP V-3 Site Engineering Support Manager Response (EOF) ............. .
0 , EP V-4 Corporate Engineering Team Leader Response (CHERC) ..... .. .... 0 l EP-V-5 : Licensing Support. Team' Leader Response . ... .... . . ....... 1 EP V Fuel Support Team Leader Response . . . . . . . . . . . . . - . .. ... 1 EP V-7' Nuclear Engineering, Quality Assurance Licensing, and Nuclear Fuels . . . 1 SECTION VI - PLAN ADMINISTRATION EP VI-1. Revision and Approval of Plans and. Procedures . .. ... . . . ... . . . . 2 EP VI Distribution-cf Plans and Procedures . . . .. . . .. . . . ... ... < 1 EP VI-3 Review of Plans and Procedures . . . . ... . .... .. .. . ... . 1 EP VI -Procedures Format . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP VI-5 Conduct of Drills-and Exercises!. . ....'. .. . . . ...... .... 2 EP VI-6 Inventory of EOF Supply Lockers . . .,. . . . . . . ... . ....... 0
.EP VI-7 Conduct of Communications Drills '. .'. . . .<. ............. O SECTION VII - PUBLIC INFORMATION
'EP VII-l Public Information Notification . . . . . . . ........ ...... .
0 EP'VII-2 General ~ Manager - .Information Services Response . . .... ....... O EP VII-3 Public Information Manager Response ... .. . . .. ... .... .... O EP.VII-4 Pa*lic Information Technical Liaison Response . .. ..... ...... O EP VII-5 Public Information Technical Assistant Response . . - . ...... .... O EP VII-6 Internal Information . . . ....................... O EP VII-7 Media Relations . . . . . . . . . . . . . . . . ... .. . . . . . . . . - 0 EP VII-8 ' Emergency News Center Activation /Pulbic Information Coordinator Response . . . . . . . . ....................... . 0
-ADDENDUM Addendum 1 Master Phone List . . . . . ........J.' .. .. . . ... .... 4 Addendum 2 (deleted)
FIG"RES Figure 1 (deleted) Figure 2 Communications /COF Manning Board . .... . . .. ... . . .. .... 1 Figure 3 operational Status Board . ........... .. . . . . .. .... O Figure 4 Post, Accident RMS Assessment Data . .. .. . .. . . .. . ... ... . 1 Figure 5 Area / Process RMS Data . . . . . . . . .~. . .... ........... O Figure 6 Offsite Dose Summary . .. ....................... O Figure 7. (deleted) Figure 8 (deleted) Figure 9 (deleted) 3 et 3- Re v. 10 t I _ - - _ _ _ - _ _ _ _ _ _ _ _ - _ _ - - _ - _ _ _ _ _ _ _ = _ _ _ . _ . _ __ _l
l l U
. i $ EP II-l l EMERGENCY PROCEDURE !
EP II-l _ i _s . EMERGENCY-RESPONSE MANAGER RESPONSIBILITIES- ! ACTION LEVEL ! l Required for Emergency Operation Facility (EOP) activation.
~
~
Preparation to - Assume Responsibilities ,
- l. Begin log cf activities.
- 2. -Conduct a meeting with the Radiological Support Manager, Site Support Manager,. and other members of the of fsite response organization to ensure that they are prepared to assume their eR*rgency response functions. . i
- 3. Centact the Emergency Duty Of ficer '(EDO) and:
a) Determine the protective' action' recommendations-made to date with reasons for each and States' actions, if- known.
!b) Assume the duties of the emergency coordinator, which includes the nondelegatable duty to make the decision to notify-and recommend protective actions to New' Jersey and Delaware.-
Responsibilities f
- 1. -Direct Site Support . Manager tua implement EP I-l through EP I-4 for changes.in event-classification, as recommended by the EDO, SSM or.RSM.
- 2. Review and approve Initial Contact Message form, as required for event classification change or a change in Protective Action Racommendation-to the F.3tes.
- 3. Review and approve periodic press releases.
- 4. Regularly Contact the Deputy Director of the Office of Emergency l
. Management for New Jersey and the Director of the Division of C Emergency Planning and Operations for Delaware, using the phone numbers provided in Addendum 1 to insure States are satisfied
~
with data flow.from EOF. SGS 1 of 2 Rev. 2 ar
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EP II-l Responsibilities (con'd)
- 5. Review'and approve completed Station Status Checklists prior to transmission'to the states. - -
- 6. , Conduct periodic briefings with EOF Support managers to discuss l status of'the plant and protective action recommendations.
Review questions in attachment 1 of this procedure regularly during the. event, and the recoiery phase. I
- 7. Periodically contact the Senior Vice President - Energy Supply ,
and. Engineering with updates on plant status and protective l actions recommended to the States.
- 8. Regularly provide EOF staff with short announcements of status of~the event.
- 9. Ensure.that TSC and Control Room are aware of event classification and protective actions recommended.
l I SGS 2 of 2 Rev. 2
ATTACHMENT 1 Briefing Ouestions' l '. - Do 'the states understand the cause, . type and extent _ of the accident?
.(Verify by contacting State ' Emergency Coordinator) -
t-
- 2. ,What is the_ condition of the core?
(Verify by' discussing with SSM and TSM)
- 3. Is there adequate cooling?
(Verify :f rom subcooling margin data and dircussion with SSM)
-4. What is the source term?
- a. Core inventory (TSM/ Fuels)
- b. Primary coolant activity (TSM/ Fuels)
- c. Containment atmosphere - (RSM)
. d. Releases to enviornment - (RSM)
- 5. What is the offsite dose?
- a. Projected-(RSM/SSM)
- b. Measured-(RSM)
- 6. What about injestion pathway?
- a. Environmental-Samples (RSM)
Mi lk ' Vegetation J
- 7. What about habitability of Emergency Raspcase Facilities?
Control Room /OSC - (SSS/EDO) TSC - (SSS/EDO) EOF - (RSM) TB02 - (RSM)
- 8. .Has a schedule been prepared for 2 or 3 shift operation of the TSC- -
(SSM/EDO) EOF - (ASM) SGS Rev. 2 J
1 l EP'fI-l Signature Page C Prepared By: h [ Reviewed By: h)1A fhb u / d// 7/PJ Departm[ntHey1 Dste' Reviewed By: N cle ((d , rge lanning Engineer
/4/e 7, /P S Date Reviewed By: b ' 'A /8[/#/S ~5 Station Quality Assurance Review bate (if required see EP VI-2)
SORC Meeting Number: E )" N / /4!N E) Approved By: // //[_f e "a e - Sal Operations Date Approved By: , o/u[r3 Manager - Nuclear Site Protection Date SGS Rev. 2
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l l i EP II-2 i
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-EMERGENCY PROCEDURE EP II-2 5 SITE SUPPORT MANAGER RESPONSIBILITES ;
ACTION LEVEL
-Required for Emergency Operation Facility (EOF) activation. ,
Freparation to Assume Responsibilities
- 1. Begin log of. activities.
2.- Verify the capability'for communications with the Technical Support -Center, 'using the hotline phone or the numbers provided in Addendum 1. 3.. Obtain1a briefing from thel Technical Support Supervisor (TSS) or the Emergency- Duty Of ficer (EDO) on the plant status and projections for the next 8 hours.
- 4. Assign a staff member to' periodically receive plant status from the Control Room, complete the Operational Status Form and the operational portion of the Station Status Checklist (Figure 3)
-and' implement their distribution.
- 5. . Assign ~a staff member to initiate and maintain the Operations Status Log and event logaon boards at the front of the EOF.
5 6.. Assign a staff member to prepare the operational portion of the Station-Status Checklist.
- 7. Report to the Emergency Response Manager (ERM), when ready to assune responsibility for recommending protective actions based on plant conditions.
SGS 1 of 2 Rev. 2
2
- EP II-2 D.
Responsibilities 1.: Review and approve the operational portion (Part I) of the Station Status Checklist =(Attachment 1) and discuss listed parameters with
. staff.
2.'"ProvideLPart'I (operational portion) of the Station Status Checklist to RSM to'be included with Part II for distribution to
-the States.-
- 3. Provide Operational Emergency Action Level Recommendations to the Emergency Response Manager based upon discussions with the TSS and information included on the Operational Status form.
- 4. Implement EP I-l through EP I-4, when directed by the ERM, for changes in. event' classification.
- 5. Prepare an Initial Contact Message form and provide to the State communicators when-directed by the ERM for changes in Protective f
Action Rocommendations.
- 6. Prepare information on the status of the plant for the ERM's periodic briefings, using Attachment 2.
7., Discuss recommendations for event mitigating actions with the
-Technical Support Manager.
.SGS 2 of 2 Rev. 2
r- .-
-EP II-3 Attachment-1 ATTACHMENT.1 STATION STATUS CHECK LIST *.
' Salem' Generating Station Unit No.
~ Transmitted By: Namel Position:
1.1Date and Time: Event Declared: Date Time [24 hr clo'ck)
- 2. Accident Classification: .b5) Significant Event b) Unusual Event b3 Alert- b I Site ~ Area Emergency General Emergency 3..Cause of Incident:-
Primary Initiating Condition used dor declaration of incident EPI-0-Part- , Number and/or Significant Event No. ,
-Description of the incident ,
- 4. Status of Reactor: b) Tripped / Time b) At Power b ) Hot Shutdown Cold Shutdown
.5. Pressurizer Pressure psig Hottest Core Exit TC 'F
.6.:Is offsite power!available? ; YES - NO-
- 7. Are two or.more diesel generators operable? YES NO'
-8.-Did the emergency safeguards system-activate? b) YES NO
- 9. Has the containment been isolated?b ) YES- NO 10.,Other pertinent information k
a b Rev. 2
P- [ h r, . EP.II-2 , 1 Attachment 1
. Station' Status' Checklist'- Radiological Information ll.'. Gaseous . Releases YES - NO
[(A)-Release Terminated: YES ' NO f .(B)i Anticipated .or'Known Duration of Release Hours
-(C);
Type.of Release: . GROUND ELEVATED L(D) Wind-Speed:
~
MPH ' Wind Direction: (Toward) Divide by 2 to get' M/Sec. (From)
- l. Delta. Temps- (Compass Points)
!' (E) Stability _ Class: bZ)~ Unstable' bZ}. Neutral b) Stable (F) Release Rate Iodine Ci/Sec.
'(G) Release Rate Noble Gas: Ci/Sec.
- 12. Liquid Release: YES .b) NO (A) Release' Terminated: YES NO
, (B); Anticipated or Known Duration of Release Hours (C), Estimated Concentration- pico Curies / Liter (D) Release Rate .
Liters / Hour
;.13. Projected Off-site Dosc RatesL(As Soon As Data.Is Available):
Adult
-Distance-(miles): Whole Body (mrem /hr) Child _ Thyroid (mrem /hr) 14.[15. minute' updates to States: Time Initials b ) State of New Jersey
. Name
.. State of Delaware Name Others Name Agency Name Agency Rev. 2
EP II-2 ATTACHMENT 2
~ Briefing Ouestions-
. l .1 What information is,known on the'following?
Core coverage?-
~
~RCS?- '
Fuel? Fission Product Boundary? . ,
- 2. 'Can the event-be mitigated operationally?-
3.. What is the projected duration of-the event? 3 4. What probable changes in operational status would cause change in event classification? 5.- Are engineering changes required to mitigate the event? Have they been discussed with the TSM and TSS?
- 6. What operational actions could change the current radiological conditions?
Decrease onsite/of fsite doses? Increase onsite/offsite doses?-
-7. What operational data could. impact-on the RSM's_ ability to provide accurate offsite dose estimates? Has this data
-been~ collected and provided-to the RSM staff?
Steam releases? Steam' Driven Aux Feedwater Pumps? PORV's? Chemistry Samplos? e
EP II -2 Signature Page Prepared By: Reviewed By: /0/ J =2 l ff?) bepartment' Head Date' Reviewed By: //[A p u ////7/p> i i N cle E Planning Engineer Date
. Reviewed By: -
. ,m / o[f p[9 s Station Quality Assurance Review bate (if required see EP VI-2)
SORC Meeting Number: (( - / 3 / /d
/
. Approved By: *
# ol//O
, Ge eral Manager - alem O erations Date Approved By: /7/ -
A f
,!S Manager - Nuclear Site Protection Date-Rev. 2
_ .I-^' EP II-3
- - , . . EMERGENCY PROCEDURE
>~ ~EP II-3 RADIOLOGICAL SUPPORT MANAGER RESPONSE
- ACTION LEVEL.
t .
- 1) As' required at the direction of the Emergency' Response Manager. The Radiological Support Manager shall perform or_
l cause to be performed the following: JACTION STATEMENTS PREPARATION TO ASSUME RESPONSIBILITY
- 1. The'first person arriving at the EOF and qualified to act as the-RSM will report to the Emergency Response Manager (ERM) and notify the Radiation Protection Supervisor at the station, and post name on the Communications Board.
- 2. The RSM's staff will assist the Radiation Protection Department at the station until
~the RSM's staff is assembled and able to l
. -assume'its normal functions and until-the EOF is declared operational by the ERM.
- 3. Determine that the staff on had is adequate to accomplish the anticipated initial tasks and consists of at least the following personnel.
Two (2) qualified Radiological Assessment Staff Members Three -(3) qualified Communicators. Two (2) qualified Off-Site Radiological Monitoring Teams (Two [2] persons / team) SGS Page 1 of 8 Rev. 2
' ACTION' STATEMENTS _(continued) EP II-3 PREPARATION TO ASSUME RESPONSIBILITY (continued)
- 4.. Determine if a sufficient amount of equipment listed in EP VI-9 is on hand to accomplish ,
the anticipated initial tasks.- This
, equipment is located in the EOF supply and emergency _ equipment locker.
- 5. Determine that the following radios are in
" working order"
- a. Two_(2) portable radios to be used by survey teams
- b. Base station radio to be used by a Radiological Suppport Manager Communicator to the survey teams.
- 6. Determine whether a sufficient amount of pertinent site and environmental data is available to permit dose calculations to be made and to perform. assessments.
The required data would include the following: Radiation monitoring system data Meteorological data. On-site field monitoring team data and locations, if available Off-site field monitoring team data and locations, if available. Protective Action Recommendations, if any. Plant status from the SSM staff. 1 SGS Page 2 of 8 Rev. 2 1 l
- 1
EP II-3 ACTION STATEMENTS (continued)- PREPARATION TO ASSUME RESPONSIBILITY (continued)
- 7. Report to the Emergency Response' Manager that the Radiological Support Manager is .
l ready to assume the responsibilities for-off-site surveys, determining dose assessments and projections, and making Protection Action Recommendations.
'8.-When authorized by the Emergency Response Manager, notify the Radiation Protection Supervisor / designee that the Radiological Support Manager has assumed hia responsibilities.
ASSUMPTION OF' RESPONSIBILITIES
- 1. The RSM and staff shall keep a log of all l
events and actions from the first notification of an emergency to the return of the Station to normal conditions. Log books for this purpose are in the Emergency Communications Cabinets at the EOF.
- 2. Control of the off-site radiation monitoring teams will be transferred from the TSC to the EOF. Procedures EP IV-109 and E? IV-Il0B will be used. Off-site radiation monitoring personnel may consite of station Radiation Pro-tection Department personnel and/or EOF assigned.
SGS Page 3 of 8 Rev. 2 b-
ACTION'STATEMENTSi(continued) EP II-3 ASSUMPTION OF RESPONSIBILITIES ~(continued) . t
- 3. Responsibility-for'off-site dose projection will- be transferred from the TSC to the LEOF. Procedures EP IV-lli,-112, 113 and 114 will be used. These functions will be .
performed by the Radiation Assessment Staff.
- 4. Responsibility for recommending off-site protective actions will be transferred from the TSC to the EOF. Procedure EP IV-108 will be used. Protective Action Recommendations should be made'to the ERM.
.The states of New Jersey and Delaware should be informed of the basis for the
. recommendations after they have been made.
These functions will be performed by the Radiation Assessment Staff and Radiological ~ l Support Manager.
- 5. Communications with the States of New Jersey and Delaware,-the TSC, NRC, and the off-site radiation monitoring teams,will be by telephone or radio manned by Communicators.
'6. Establish and maintain phone contact.with the '
States.for the purpose of transmitting Station Station Checklist. Delaware (302/834-7431 or 302/834-4531) New Jersey (609/633-7385 or 609/882-8543) l SGS Page 4 of 8 Rev. 2 l-
I ACTION STATEMENTS'(contiuntd)' EP II-3
. ASSUMPTION OF RESPONSIBILITIES-(continued) ,
When1 authorized by the Emergency Response Manager, notify the States that future Station Status Checklists will be communciated.by a Radiological Support Manager Communicator. . Assign a-staff member to prepare Part II of the
, Station Status Checklist. Obtain ERM approval of Part I'and II prior to. transmitting.
Station Status Checklist updates will'be pro-vided to the States of New Jersey and Delaware approximately every 30 minutes by the Communicators.
;This frequency is an objective and may vary based on exiting conditions.
- 7. Establish contact with the following organizations and put them on a standby status to provide support as needed:
Radiation Management Corporation (Addendum No. 1)' Research and-Testing-Laboratory (Addendum No.~1)
-NRC - HPN
- 8. Post two TLD control badges an'd two self-reading control dosimeters in two locations in the EOF, one at the reception area and the other in the RSM's l office. Log the dosimeter numbers, time issued, and placement location.
'9. Issue a TLD badge and self-reading dosimeter to off-site radiation monitoring teams as required for initial. dispatch from the EOF, ensure that off-site radiation montioring reams that were dispatched from the TSC.and already in field have necessary dosimetry.
SGS Page 5 of 8 Rev. 2
ACTION STATEMENTS-(continund) - EP II-3 ASSUMPTION OF RESPONSIBILITIES (continued) .
- 10. If the EOF is in the Radioactive plume and the population around the EOF has been evacuated, issue TLDs to all personnel in
~
the-EOF. .
- 11. If the RSM feels that the atmosphere in the EOF should be monitored and/or filtered, the RSM-should assign one member of his staff to assure that the. portable air monitoring system (AMS) and EOF ventilation are operational The AMS should be set-up outside the west door of the EOF with a remote sample head inside the room. The EOF ventilation system is located in the mechanical room south of the EOF (key is located in Rad Support Locker). Verify that the appropriate filters are in line, then switch from normal to by-pass (switch located on west wall of mechanical room).
- 12. If the EOF becomes contaminated, access to the EOF should be controlled as necessary by activation of a frisking stc* ion at the main entrance to the EOF (student door) and instruct the guard that no one is to leave without frisking. All other entries should be secured and posted.
- 13. The RSM will initiate long term environmental monitoring and coordinate such monitoring with on-site actions and conditions. Long term assist-ance may be drawn from other nuclear power utilities and contractors.
SGS Page 6 of 8 Rev 2 I 1 I
ACTION STATEMENTS (continued) EP II-3 ASSUMPTION OF RESPONSIBILITIES (continued)
- 14. Samples from the radiological environmental monitoring stations shall be collected by the Research and Testing Laboratory and analyzed by an apropriate' radiation anaylis laboratory. The Radiological Support Manager will contact the Research and Testing Lab-oratory-when it is determined that these samples should be analyzed.
- 15. The RSM or station's Senior Radiation Pro-tection Department person will establish communication with the medical' assistance facilities and personnel of Radiation Manage-ment Corporation to put the Emergency Medical Assistance Plan into operation if necessary.
Contact will be established as defined in the Emergency Medical Assistance Plan. LONG RANGE PREPARATION AND TERMINATION OF EOF USE
- 1. After the emergency is under control and evacua-
. tion of the public is no longer likely to be necessary, the Radiological Support Manager's l staff shall asist station personnel in determining efforts which may be used to further reduce ex-posures to the station operating personnel and to the public.
- 2. Individual and population radiation exposure doses should be evaluated after the incident.
- 3. The RSM's function will be secured at the direction l of the ERM.
'SGS Page 7 of 8 Rev 2
EP II-3 NOTE Forward all completed forms to the Nuclear ~ Emergency Planning Engineer. Attach any referenced completed EP's or a'ttachment.
- ~
Prepared By: 'M f Reviewed By: [I - - ,
/o // / #J Department Head. D[te Reviewed By: [ r s ee n/n[rf i j N le e P anning Engineer Date
* * ~
Reviewed By: + e -- A /0[/JP[#S Station Ouality Assurance Review Date (if required see EP VI-2) SORC Meeting Number: 7[w/3/ /4)2.
/
d f-J
/
Approved By: y
# v v d//D neral anag - Sale Operations Date Approved By:
/# / /J
-Manager - Nuclear Site Protection Date 1
SGS Page 8 of 8 Rev. 2 l
EP IV-lll EMERGENCY PROCEDURE EP IV-111-EFFLUENT DOSE CALCULATIONS
. ACTION-LEVEL This procedure shall be implemented upon the request of the Senior Shif t Supervisor /EDO/ERM or the Radiation Protection -
a st'ff. The calculations _shall1 normally be performed by the Radiation Protection personnel in the-TSC or the~ Radiological Assessment Staff at.the EOF. At the TSC, the primary individuals ' responsible for the -initial calculations will be the Shif t Radia-tion Protection Technician (Shift RPT)'and the REP /ALARA Super-visor. LIMITS ~OF AUTHORITY
; Projected off-site dose estimates should be made available to the SeniorcShift-Supervisor /EDO/ERM, and the Radiation Protection Supervisor (RPS)_.or the Radiological Support Manager (RSM).'
Transmittal of the projected doses shall require the prior approval of the Senior Shift Supervisor, RPE, or RSM. If re-entry'into an affected area is required for effluent determination, consideration shall be given to the potential for encountering high' dose rates. Approval of the Radiation Protec-tion Supervisor and the EDO shall be obtained prior to entering the penetration-areas. Approval of SSS/EDO shall be obtained prior :to re-entry into evacuated areas. - ATTACHMENTS No. 1 - Xu/Q Value Determination No. 2'- (a) &-(b) Noble Gas / Iodine Dose Conversion Factor (K) vs. Decay Time 1 of 31 Rev. 4 _. . _ _ . _ _ - _ _ _ _ _ . ._ _ _ _ _ -- ~
l l 1 1
. EP IV-lll l
_. . ATTACHMENTS (cont.) i No. R43 Concentration Conversion Factor vs. Decay Time No. 4' . Default Values.fors Low /High Plant Vent Monitors No. 5 - Containment-Monitor R44: Response vs. Dispersion Factor' , .No. 6'-', Survey; Meter Response vs. Main Steam Activity
, No.~7 - Unit Analysis of Off-Site Dose-Calculations No. 8 - Dose-Calculation Sheet No. Liquid Release Calculations ACTION STATEMENTS'
- l. Contact the Control Room and obtain a briefing on-the incident and identify the probable pathways for release of radioactive material.
- 2. Determine which sections of this procedure are appropriate for the-particular release.
- TYPE OF RELEASE PAGE A.-Releases from PLANT VENT (Elevated Release)
- 1. Unit #1 3
- 2. Unit #2 7 B. Unmonitored releases-from:'(Ground. Release) 11
- 1. POWER OPERATED RELIEFS
- 2. AUTOMATIC RELIEFS
- 3. STEAM DRIVEN AUX FEEDWATER PUMPS C.' Releases due to CONTAINMENT LEAKAGE 14 (Ground Release)
D. Release Rate' Calculation
- Attachment 8 E. Liquid. Release Calculation Attachment 9
*See top left corner of Attachment 8 for release. rate determination calculation.
2 of 31 Rev. 4
. . ._. - . -- .=
~
EP IV-lll
- o. A.1 PLANT RELEASE'FROM UNIT NO. 1 .
A.l.1 Establish contact with the Control Room. A.l.2 Record the following plant parameters for subsequent calculations. VALUE AT PARAMETER: NUMBER SELECTED TI$E l0 3 Low Range Gaseous 1R-41C- -cpm Release Rate
- b. Medium Range Gaseous.
Release ~ Rate- 1R-45B uCi/cc
- c. High Range Gaseous 1R-45C uCi/cc Release Rate d." Backup. High Range . R-43 mR/hr
-o. Iodine Release Rate 1R-41B i.PRESENT~ MONITOR READING cpm (Cx) time (Tx)
--ii. PREVIOUS MONITOR READING cpm (Co) time (To)
J f. Plant _ Vent L(1)' Flow cfm Rate
-g.& Temp.(2)(4) at t C*
Elevation (ft) h.. Elevation ft
- i. Wind Speed (3 ) (4 ) ' (5 ) mph
- j. Wind Direction (4 ) (5)
- k.. Shutdown Time hr
- 1. Transport Distance for mi
--Calculation NOTES:
(1)- If plant. vent ficw rate is unobtainable or cannot be estimated, assume 125,000 cfm.
-(2 ) - If-the ( 3 00 '
- C )-( 33.' *C ) is unobtainable to determine the t use the
.(150'*C)-(33'*C) reading. If this is unavailable refer to Note 4 and and-note chosen-elevation.
-) If~the wind speed is unobtainable, assume 5 mph.
Use Elevation 300' data for an elevated release. Use Elevation 33' data for a ground release. J of 31 Rev. 4
z
-- EP IV-lll (4) Bcckup' meteorological data from Wilmington Airport (302-323-2280 or NAWAS JLine)1 including. wind speed, wind direction and estimated stability class.
-If'the estimated stability class is not available, assume conditions to be etable.
(5)fAverage1 data over 15 minute. period.using the strip chart recorder from the: control room. , A.l., PLANT RELEASE FROM UNIT NO. 1 (continued) NOBLE GAS CONTRIBUTION TO WHOLE BODY DOSE RATE A.l.3n Low range or default value (Attachment 4) (lR41C'or. . . Noble Gas
'DBA CPM) (Plant Vent' Flow Rate)(Xu/Q)(Dose Conversion Factor)(6.56E-5)=__ mrem hr
- (Wind Speed)
- ( rr )(b )(c )(d )(6.56E-5)= __ mrem l 7 (e ) hr A. l'.3b Medium-or High Range (lR45B or 1R45C)
Noble Gas (lR-45B or C)(Plant Vent Flow Rate)(Xu/0)(Dose Conv. Factor)(1.05E3)= mrem (Wind Speed) hr (f' )(b )(c )(d )(1.05E3)= mrem (e ) hr
'A.1.4-High Range (R43)
Noble Gas i(R-43)(Plant Vent Flow Rate)(Xu/0)(Dose Conversion Factor)(1.05E+3)= mrem (Wind Speed)(Concentration Conversion Factor) hr (f )(b )(c )(d )(1.05E+3)= mrem
-(e- )(g- ) hr NOTE
- a. 1R-41C in cpm or 1R45B(C) in uCi/ce,or equivalent cpm value from attachment 4.
b'. Plant-vent flow rate in ft /3 min.
-c. Xu/O from Attachment 1. (1/m2)
- d. Dose conversion factor from Attachment 2(b)~. mrem /hr uCi/m>
- e. Wind speed in miles per hour.
- f. R-43 reading in mR/hr.
- g. Concentration conversion factor in mrem /hr Attachment 3 uCi/cc
' Calculated By_ Date Time JReviewed By Date Time 4 of 31 Rev. 4
~
EP IV-lll.
~
A'. l ' PLANT RELEASE FROM UNIT NO. 1 (continued) IODINE CONTRIBUTION TO THYROID DOSE COMMITMENT
~A.1.5' Determine the rate of increase of iodine activity.
a):- Low Range Monitor 1R-41B . com=Cx-Co=( -)-( )=( )com=( )com
. min Tx-To-( )-( )( ) min min-
-NOTE. ,
-Refer to' Step A.l.2(e).
QR b) Using' Default-Values Use. Attachment 4.to determine the appropriate equivalent
' epm / min.-
cpm / min A.l.6 Equation for 50 year thyroid dose commitment rate during ex-posure: period. 3m Iodine imin (Plant ~ Vent Flow Rate)(Xu/Q)(Dose Conversion Factor)(3.35E-7)=__ mrem (Wind Speed) hr (m )(b -) ( c )(d )3.35E-7)= mrem (e ) hr NOTE
- a. cpm / min f rom S tep A. l . 5 (a or b).
- b. Plant vent flow rate in f t / 3min. -
- c. Xu/O from ' Attachment 1. (1/m2)
- d. Dose conversion f actor f rom Attachment 2(b) . mrem /hr uCi/m3
- e. Wind. speed in miles per hour.
Calculated'By. Date Time R3vicwed By Date Time 5 of 31 Rev. 4 C
EP IV-lll !- A.1. PLANT RELEASE FROM-UNIT NO. 1 (continued) IODINE CONTRIBUTION TO THYROID DOSE COMMITMENT (continued)
',A.l.7 To obtain dose commitment, multiply dose commitment rate by the hours exposed to that rate, (e.g., 15 mrem /hr X 5 hours exposure = 75 mrem-50 year dose commitment).
Calculated By Date Time Reviewed By Date Time 6 or al Rev. 4
l.
, EP IV-lll A.2 PLANT RELEASE FROM UNIT NO. 2 A.2.1 Contact the Control Room and obtain the following plant parameters for subsequent calculations.
PRESENT MONITOP, METER READING AFTER PREVIOUS MONITOR VALUE AT PARA"ETER NU"BER Ti"E, TX READING SELECTED TIME
- c. Low Range Gaseous 2R-41C cpm R31 ease Rate
- b. M:dium Range Gaseous 2R45B uC1/cc R31 ease Rate
. c. High Range Gaseous 2R45C uCi/cc Release Rate
- d. Stck-up High Range A-43 mr/hr
- o. Iodine Release Rate 2R-418 cpm (Cx) cpm (Co) tinte (Tx) time (To)
- f. Plant Vent (1) Flow cfm Rate g Temp (2)(4) t C*
~
' h. Elevation - ft
- i. Wind Speed (3)(4)(5) mph
- 3. Wint! Direction (4)(5) .
(from)
- k. Shutdown Time hr
- 1. Transport Distance for mi Calculation POTES:
(1) If. plant vent flew ate is unobtainable or cannot be estimated, assume 125,000 cfm. (2) If the (300'*C)-(33C) is unoctainable to determine the t use the (150**C)-(33C) reading. If this is unavailable refer to Note 4. (3) .If the wind speed is unobtainable, assume 5 mph. Use Elevation 300' data for an elevated release. Use Elevation 33' data for a ground release. (4) Backup meteorological data from wilmington Airport (302-323-2280 or NAWAS Line) including wind (peed, wind direction and an estimated stability class. If the estimated stability class is not cvailable, assume conditions to be stable. (5) Average data over 15 minute period using the strip chart recorder f rom the control room. 7 of 31 Rev. 4
~ . .. . _ . . _ _ , ,
EP IV-lli
.' A. 2 PLANT-RELEASE FROM UNIT 2 (continued)
WHOLE BODY DOSE RATE'DUE TO NOBLE GAS A.2.2a Low range og def ault values ( Attachment 4 ) -
,(2R41C or . Noble Gas DBA caes)(Plant Vent Flow Rate)(Xu/0)(Dose Conversion Factor)(6.56E-5)= Laen/hr l
. (wand Speed)
(a 1(b )(e- )(d )(6.56E-5)= aren/hr l (e ) A.2.2b Medium or High Range (2R45B or 2R45C)
' Noble Gas (2345 3 or C)(Plant Vent Flow Rate)(Xu/0)(Dose Conv. Factor)(1.05E3)= aren/hr (Wind Speed) la )(b )(c )(d- )(1.0$E3)= ares /hr te >
OR A.2.3 High Range (R-43) Noble Gas (R-43)(Plant vent Flow mate)(16u/0)(Dose Conversion raetor)(1.05E+3) = ares /hr j
.(Wind Speed)(Concentration Conversion Factor)
(f )(b )(c 1(d 1(1.05E+3) = ares /hr (e )(g ) l NOTE l a. 2R-41C in cpm-or 2R45B(C) in uCi/cc, of equivalent cpm l' value from Attachment 4. I b. Plant--vent flow rate in ft 3/ min.
- c. Xu/O value from Attachment 1. (1/m2)
' d. Dese ccnversion' factor frem Attachment 2(a). c. rem /hr uCi/m3
- e. Wind speed in miles per hour.
- f. R-43' reading in mR/hr.
- g. Concentration conversion factor in mrem /hr Attachment 3.
uCi/ cc e
' Calculated By Date Time Reviewed By Date Time t
l l 8 of 31 Rev. 4
, .__.,_s -
.,_,,,.r. _ , , . . , . _ , , _ . . . _ - - , - . . . , , _ , , . , _ _ - , , , , . . ~ . , _ . . _ . . , . ... . . . , . . . , _ _ , _ . , . , - . . . _ _ . - . . . . . .
EP IV-lli
.A.2 PLANT RELEASE FROM UNIT 2 (continued)
THYROID DOSE COMMITMENT DUE TO IODINE. 1
. A.2.4 Determine the rate of increase of lodine activity.
a) Low Range Monitor 2R-41B Sm = Cx-co = ( man Tx-To (
)-s l-(
) = (-
) (
)com = (
lain
)mutn NOTE Refer to Step A.l.2(e).
9E b).Using Default Values Use Attachment 4 to determine the appropriate equivalent cpm / min. cpm / min A.2.5 Equation for 50 year thyroid dose commitment during exposure period. Spm, Iodine sin - (Plant Vent Flow Rate)(Xu/0)(Dose conversion Factor)(3.35E-7) = mrem /hr (Wind Speed) (a )(b )(c )(d 1(3.3SE-71 = mrem /hr to ) . NOTE
- a. cpm / min from Step A.2.4 (a or b).
- b. Plant vent flow rato in ft 3/ min.
- c. Xu/Q from Attachment 1. (1/m2 )
- d. Dose conversion factor from Attachment 2(b). mrem /hr uCi/m3
- e. Wind speed in miles per hour.
' Calculated By Date Time Reviewed By Date Time 9 of 31 Rev. 4 i
EP IV-lll A.2 PLANT RELEASE FROM UNIT 2 (continued) . THYROID DOSE RATE,DUE TO IODINE 4(continued) A.2.6 To obtain dose commitment, multiply dose commitment rate by the hours exposed to that rate, (e.g., 15 mrem /hr X 5 hours exposure = 75 = rem-50 year dose commitment).
'g
's t
i i Calculated By Date Time Reviewed By Date Time f: . l 10 of 31 . Rev. 4
. t.
r - p .- evr--..memw- -m- -. .e-- ----,.g a- .w,- , e v., - - -- ---+r-w .-
+ .,+w,ew- e
EP IV-lll B. RELEASE RATE' DETERMINATION FROM UNMONITORED STEAM RELEASE POINTS 3.1 If control room personnel have determined a primary leak exists in one or more steam generators by one or more of the following indications: -
', a) Air Ejector High Radiation Alarm b) Uncontrolled increasing level in steam generator c) Increasing steam pressure in one steam gen'erator d) High Activity alarm in.the steam generator blowdown system with or without an isolation then the Senior Shift Supe'rvisor shall initiate monitoring of the affected steam lines upstream of the isolation valves to estimate the microcurie content per cc of steam in the affected steam lines. This action is required if the potential exists for a relief valve lifting, a power operated relief being opened or the operation of the steam driven Aux. Feed Pump attached to the affected Steam Generator (11 & 13)(21 & 23).
B.2 If R46 monitors are functional, uCi/cc activities can be determined for each steam line directly from the display and recorded in Step B.6. If these monitors are inoperable, measurements must be made with a portable survey meter, and the procedure. listed in B.3 through B.5 must be implemented. B.3 Before Radiation Protection personnel enter the penetration areas to measure the contact dose rate on the affected steam lines, the Senior Shift Supervisor /EDO and the Senior Representative from Radiation Protection will evaluate and determine the potential for encountering high radiatic' - 9as in the penetration areas due to a: a) Reactor malfunction resulting in fuel damage b) LOCA resulting in fission product release to containment causing radiation streaming through containment penetration. 11 of 31 Rev. 4
- EP IV-lll
~
B.4 If any of the above conditions are present, specific action points must be established in accordance with EP I-17 to determine the following requirements. . . a) Total dose accumulation for operation
', b) Maximum dose rate field to enter c) Types of dosimeters and instruments to use d) Type-of protective clothing and equipment to be used
.B.5 Enter affected penetration area or location and measure the contact dose rate on the affected steam line or Aux. Feed Pump exhaust line.
a) The contact dose rate measurement can be made with any dose rate instrument having a range of 0.1 to at least 10,000
-MR/hr.
b) If it is expected that the background in the affected penetration area will be greater than 10 mR/hr a dose r0te instrument with a. shielded probe should be used. . c) Dose rates should be taken at the indicated location marked on each steam line, d) Record below the contact dose rate on pipe. mR/hr, line, location
.B.6 Use the contact dose rate, corrected for background radiation '
to determine the uCi/cc concentration in the pipe of concern from Attachment 6, or record tne reading.directly from the R46 monitor. uCi/cc B.7 Use the following flow rates to determine steam release Istest a) Power operated relief valve 450,000 lb/hr b) Relief Valve 800,000 lb/hr each c) Aux. Feed Pump exhaust 50,000 lb/hr_ 12 of al Rev. 4
~1 i
EP IV-lli
.B.- RELEASE RATE DETERMINATION FROM UNMONITORED STEAM RELEASE POINTS (continued)
B.8 Multiply the uCi/cc from B.6 and the proper flow rate in Ib/hr from B.7 to determins the release rate in uCi/sec. - (uCi/cc)(lb/hr)(3.3) = uCi/sec (a )(b )(3.3) = uCi/sec
- 4. uCi/cc from Step B.6.
- b. lb/hr from Step B.7.
B.9 Whole body dose rate due to noble gas releases mrem /hr = (uci/sec)(Xu/0)(DCF)(2.22) (Wind Speed - El. 33') mrem /hr = (a )(b )(c )(2.22) (d ) NOTE
- a. uCi/sec from B.8.
- b. Xu/O in 1/m 2 from Attachment 1.
- c. Dose conversion factor from Attachment 2(a). mrem /hr uci/m 3
- d. Wind speed in miles per hour (EL. 33').
B.10 Document total run time for the steam driven Aux. Feed Pump. B.ll Document the total period of time the relief and power operated relief valves were open on the affected steam generator. B.12 The number of times the relief and power operated relief valves are open on the affected steam generators are limited as per Emergency Instruction I-4.7. Calculated By Date Time Reviewed By Date _ Time 13 of 31 Rev. 4
EP IV-lli C. RELEASES FROM CONTAINMENT LEAKAGE NOTE
~
This dose determination assumes a design basis ccntainment leak rate (La). Actual containment leak rates may be more or less. .This dose determination is a postulation and should be used as such. Field monitoring results are preferable. C .1- Contact the control room and obtain the reading on the high range. containment radiation monitor R-44.
, R/hr C.2 -Using Attachment No. 5, correlate the meter reading to the vertical axis and determine the base X/O from the horizontal axis.-
base X/O C.3 Determine the actual Xu/Q tising Attachment 1. actual Xu/O-C.4 Determine the 2 hcur. dose. (Actual Xu/0)(2.22) = 24 hour dose in rem
. (Wind Speed - EL. 33')(Base x/Q) i (a )(2.22) = rem
. (b )(c )
NOTE ,
- a. Acutal-Xu/O from Attachment 1.
- b. Windspeed in miles per hour (EL. 33').
- c. Base X/Q from-Attachment 5 (correlated to containment
, monitor).
Calculated By Date Time Reviewed By~ .Date Time 14 of 31 Rev. 4 r
+- r- p w. <-~3,.c y -- e+ ..7..y --w, ,-,.,,,w. ,,.,gp,,--+ww,, ,,-,-c.. ,--yr.- . u.. ye wm,, . - . , - . .c.,
., -_ , - , m ,
~
*EP IV-111 NOT_E_
Forward all completed forms to the Nuclear Emergency Planning Engineer. Attach other completed EP's or attachments used. Prepared By: Mer) ((,&f
.f .. f Reviewed By: M i
.s h /4bWh3 g /- Department Head Date Reviewed By: / b/'/r#[r _/ /v ///, NJ Nucled Emergency Plannind Engineer Date' ReviewedBy:k ^u k-= fa'/8[B5- ,
Station Quality Assurance Review Date (if required see EP VI-2) SORC Meeting No.: b[" [ / L T[7 Date l Approved By: M /8/A/!Id General Manager - Salem Operations Date Approved By: /, _.!
/ '
rManager - Nuclear Site Protection Date L i l l l l 15 of 31 Rev. 4 l-
. ., . - .- ~ . . . - , . . _ , - , - . .
7 EP IV-111 l
. ATTACHMENT 1
. . Xu/O VALUE DETERMINATION , ,
Select the Xu/O values that correspond to the stability class as determined by the temperature, tcnce from the site and the release point (ground or elevated).
- i. USE ' .19E ' TEMPERATURE VALUE FROM THE NETEOROLOGICAL TOWER TO DETERMINE STABILITY CLASS.
= Primerv Instrument NOTE 300 ft. - 33 ft.-temperature ('C) *
- UNSTABLE IS 1 -1.3*C UIISTABLE WEUTRAL STABLE NEUTRAL IS > -1.3*C 1 -0.5'C
-1.3 - 0.5 STABLE IS') -0.5'C
,Deckup Instrument NOTE' lh0 ft.'- 33 ft. tengerature ( *C)-
UNSTABLE IS 1 -0.6*C UNSTABLE NEUTRAL STABLE NEUTRAL IS > -0.4*C 1 -0.2'C STABLE IS > -0.2*C
-0.6 - 0.2 2.? DISTANC2 GROUND LEVEL RELEASE (E-6/m2)
_ ELEVATED LEVEL RELEASE (E-6/m23 METERS . MILES UNSTABLE NEUTRAL STABLE UNSTABLE NEUTRAL STABLE 1000- 0.62 14.83 58.43 244.4 16.17 39.01 *
.1270 NEA 0.79 9.91 41.54 226.29 11.23 35.34 **
i2000 1.2 4.58 21.21 166.5 5.4 23.70 . 01 3000 1.9 2.29 '11.46 111.9 2.74 14.5 . 50
~4000 2. 5 1.40 7.37 80.6 1.69 9.81 2.44
,5000 3.1 . 95 5.22 61.4 1.15 7.14 5.24 6000 3.7 . 70 -3.94 48.7 85 5.47 7. 8'4 7000 4.4 . 53 3.10 39.9 .65 4.35 9.79
'8000 4.9- . 42 2.52 33.4 .52 3.56 11.05 8045 LPI 5.0 . 42 2.5 33.2 .51 3.53 11.09 9000- 5.6 . 35. 2.10 28.6 .42 2.98 11.76 10000 6.2 . 294 1.78 24.8 .35 2.54 12.06
'11000 6.8 . 250 1.53 .21.8 .30 2.20 12.09 12000 7.5 .. 215 1.34 19.3 .26 1.92 11.93
~
13000- 8.1' . 18 1.18 17.3 .22 1.70 11.65
. 14000 8.7 . 165 1.05 15.7 .20 1.52 11.3 15000 9.3 . 14 .95 14.22 .18 1.36 10.91
.16000 EPZ 9.9 . 131_ .86 13.01 .16 1.24 10.50 4
MEA.- Minimum Exclusion Area LP2 - Low Population Zone EPt - Emergency Planning Zone 8vslue' of.Xu/O' for 1000 meters distance = 5.15E-16/m2 2 *5velue of Xu/O for 1270 :eters distance = 1.18E-12/m2 1 C ' .- ince Xu/O = E-6/m2 (ground) Xu/O = E-6/m2 (elevated) f 16 of 31' Rev. 4
- m ruii y ~ tr y?v *s $ 7ww*wwf--1e 'e y' M r tr-9t eg' M W =t Mr - --m-w
2 EP IV-lll ATT. la MEAN WIND SPEED HEIGHT ADJUSTMENT FACTOR ("GR)- , Heicht of Release Ground (10~l' Elevated (60m) INSTRUMENT STABILITY: U N S U N S HEIGHT (METERS) 10.00 1.0 1.0 1.0 1.33 1.79 2.44 (33 ft.) 45.72 .
-.781- .613 .,468 1.04 1.09 1.15 (150 ft.)
91.44 .704 .493 .331 .935 .877 .813 (300 ft. ) Example Ground Release,- t = 1.5'C, 150 ft. instrument height, windspeed = 3 mph
-Find: X/Q _ .
Use 0.781 for height adjustment for unstable ground conditions mg mph X/Q = (Xu/Q)(2.22 -m/s) = (9.91 E-6/m2) 2.22 m/s)
-(wspeed) (TR) (3 mph) (.781)
X/Q = 9.34 E-6 sec/m3 17 of 31 Rev. 4
,~ - ~. . _ _ _ _ , _ . , _ . . . _ . . - _ . _ , _ _ . . , _ , . _ . . . . _ , _ - . . - - . - _ . . - . . -
.. .~
. Ctt. 2fa). . ,
0.0 p HetLE CAS Dr ^* FOLLCWIBIG SHIFT 9004 BASED CM Ef'.4-520/1-75-008 3 3t9011Af THERM 4L AT Ettif LIGAtlM HOTEs INfm0WTH OF GASEOUS DAUGHTERS INCLUDit0 IN 9 f - 0.8 1 - . 4. vise fran shutdown to time of release in hours . = s. ,d - he i N Time for transport = foesired Distancel/(wind speedt w 1 g (
/ O.4 - ^ mil /( mphi =
N j c. Total decay time = (8tep Al.+ (Step 59 hr 3 m
/ ( ) +( l =
g i D. . he ] C 0.3 - correlate the total decay time thours following shutdown) { / 3 k to for the curves Hoble Gas, to detenmine the done conversion factore
; M t
l R r ! M O.E - - I i I t
- 0.1 -
N i I I >N 0.0 I I I I
- 1"
! O 10 I I l l 20 3e' I I 49 50 , g 60 gC TOTAI, DECAY TIME - IlOURS . H 4 i i
i ledkLE GhS BACF FOLLOWille staffp0W .- ' (DutEN/DNt 3/(UCI/MS$3 9 HOURS DRCF 1100RS ' HC DRCF HOURS NGDRCF i 4
***** ****** ***** ****** ***** ****** HOURS NCDRCF
***** *****~*
0 .528 16 .0552 31 17
.6319 46 .6284
- 1 .457 .0512 32 .6315 47 .6283 i 2 .389 18 .0479 33 .6311 48 i
3 .329 19 .0451 ' .6282 34 .6308 49 .6281 j 4 .277 20 .0428 35 .6305 50 .028 5 .234 21 .0409 36 .0302 ! 6 .19? 22 .0393 51 .0279 37 .6299 52 .0278
- 7 .168 23 .0379 38 .0297 53 8 .143 24 .0367 .0278 !
39 .0295 54 .6277 i - e 9 .123 25 .0357 40 .6293 55 .6276 l 10 .107 26 .0349 41 .6291 o 11 .0932 56 .0276
- 27 .0341 42 .0289 57 .0275 i 12 .0023 28 .0335 43 0 13 .0733 29
.0288 58 .0275
.0329* - 44 .0287 59 .0274 14 .0661 30 .0324 '
- 45 ' .6285 60
! 15 .0G01
..i', - ' -
.0274 j
l A. Tiwe fras shutdown to tline of release in hours.= . I ' hr j ,
- s. Thau for trauwport - toesired pistancel/(wind speedt i mil /I aph) =
hr , C. Totst decay tlaso = (Step A)'+ (Step B) ( ) +i ) = " hr >M D. em 1 x Corrulate tho total decay time thours following shutdoun) Ps '
$ to the curven to detendine the dose conversion factors for Iso 6te Gaa.. ui M
, %P ,
I . l l l
3 3608 - 1COINE SfteF FO 99fMS REASTOR SHUYeuuft ' Cf. SED 8H EPA-580/8-TS-000 3 i Buggr."S FROM REe OUIDE i.199 3500 fRf THEnftAt. AT Ettfit.19AEMI 8906 3 HORMALIZED TO I-13i CONC OF A 100t#99883
-T.T oner m .. +es.24..E-4.
-es... m vi.es.st m
m m ei-ve.. 3s m s.
>-<e. v.TE-..n.s.
l i - R -
#av00 E .
1-707 DNCFs NORMALI2ED TO 8 UCf/N*$3 1-138
~
j g i N. ' i g ' A.
/ E664 - ' Thee from shutdown to thee y 1 of release in 1.oure i
U c B. Thee for transport = (Desired
={.
hri w I8400 s 01etancel/(Wind speed) M t mil /I aphi = hr
- c. Total decay th.so = (Step Al j
P., i "M300 - { w i + step al _ j BE00
! ( ) +t I-
= l[ ]
Correlate the total decay thee thoure hrl i ! rollowing shutdown) to the curves to 1 ' 8800 - l' detennine the dose conversion factors i for Todme. - 8ded - l \ l \ j E8 l avoo <
-1 s a a a e
l 0 to 20 30 40 a a a e & so so TOTAL DECAY TIME - HOURS I. b
??
t: 4
m
. l i
X-YST BRCF (hMEN/HR/UCI/Nas3)-BASED ON I-831 UERSUS TIME (HREN/HR)/4 MCI / Mas 3) HOURS DRCF HOURS sassa Esssssa mesas DRCF hours. BRCF-asssses assas Sassses
-e.1 2D36.4 21 2336.2 41 3107.3 2a79.s 22 2324.4 42 2 2831 23 21ee 2305.2 43 2002.5 3 2787.5 24 2294.6 4 2748.5 44 2e35.1 25 2276.5 45 5 2712.2 26 2478.1 2262.9 46 2071.2 6 2G78.3 27 2249.9 7 2646.6 28 47 2464.5 S
2237.3 48 2055.2 2616.7 29 2225.1 9 2598.4 49 2451.9 w 14 3e 2213.4 54 2445.9
" 25G1.6 31 2262 51 11 2536.1 32 2044.1 12 2191.1 52 2e34.4
, R 2511.9 33 2180.5 53 2028.9 i w 13 2488.7 34 2174.3
- 14 24GG.7 54 2023.6 l
35 2168.5 55 2018.5 l 15 2445.6 36 2151 1G 2425.4 56 2013.5 37 2141.7 57 2000.7 17 240G 38 2132.5 i 18 2307.5 58 2444 39 2124.2 59 1999.4 19 2369.7 48 2115.9 24 2352.6
- 64 1995
~
A. YLwn frcme shutdeua to tlwa of release in hours = . hei ; s
- c. m a for transpart = (neaired Distancel/lwind speed)
( mil /4 mph) " Nr ,' C. Total decay tiaa = (Step Al~+ (Step B) i ) +1 ) " hr D. Correlate the total decay time (hours following shutonun) to the curves to deteneine the dose conversion factors . _ f or Iodine, s ,'
ttochment 3 , 55 - R-43 cmlCENTRATION CONVERSION FACTOR FOLLOWING SHUTDONN
*' BASED OH EPA-520/8-75-0013 3200 MU THERNAL AT EQUILIBRItNf NOTE:
50 - INGROUTH FRon PARENT ISOTOPES NOT IHCLUDED ' j 45 - 40 - i M -
" 35 -
n
- R .
/ 30 - .
- U C I
! I 25 -! ' M / . C
- S C EO -
l l M 15 - l- - 10 - 3 4
~'
! 5
- I '
I 1 . .
' I ! I i 0- I I I I I I
- . O to 20 30 I I l l p r.
40 50 ll"
- SO .
! HOURS FOLLOUING SHUTDOUM *y x $ i i
.c.
r i e
i i F R-43 CALIBRATION FACTOR (MR/HR)/(UCI/CC) ' ' HOURS CAISACT HOURS CALFACT HOURS
***** ******** ***** ********- CALFACY
***** ****s*** HOURS
***** CALFACT 0 52.009 16 5.4256 31 8*******
1, 45 17 3.1342 46 2.M42 2 5.03. 32 3.0939 47 2.7832 38.289 18 4.7034 33 3.0577 48 2.773 3 32.368 19 4.4326 34 ! 4 27.287 20
'3.025 49 2.7635 5
4.207 35 2.9953 54 2.7546 23.604 21 4.0181 36 2.9683 I 6 19.439 22 51 2.7464 7 3.859 37 2.9437 52 2.7388 16.495 23 3.7242 38 2.9211 8 14.077 24 53 2.7317 9 3.6093 39 2.9305 54 2.7251 i 12.097 25 3.5107 40 2.8814 i 10 10.481 26 55 2.7189 0 3.4255 41 2.8639 56 2.7132 l 11 9.1621 27 3.3515 42 2.8477 57 l o 12 8.0868 28 3.2867 43 2.7079 l a 13 7.2094 2.8327 58 2.7029 w
~29 3.2296 44 2.8189 59 2.6983
' " 14 6.4928 30 3.1791 45 2.8661 15 5.9065 60 2.694 i c 9 ! ' e l r " l ? <
- - ra
/ i l
. . . . . . - - - -- . - . ~
5 I ATTACHMENT 4 i DEFAULT VALUES FOR LOW /HIGH PLANT VENT MONITORS Road the below accident description and determine which case is
- applicable. . From the table select the appropriate release rates (cpm).
DEFAULT I'LOCA WITH FUEL MELTING A LOCA assuming ~ severe core damage - fuel melting (Regu lIa tory. Guide 1.4 assumptions)-100% of noble gases and 25% of the iodines , l contained in the core are assumed released to the containment. The containment initially leaks at the maximum design leak rate. J DEFAULT'II LOCA WITHOUT FUEL MELTING Primary coolant leaks at a rate fast enough to increase-the temperature-of the core _to the point where there is damage to the fuel rods. For.this_ case, .it is assumed that all the gap activity ( the gases contained between the fuel- and fuel rod) is released to the containment. The containment is assumed to initially leak at the maximum-design leak rate. In this_ accident, it'is up to the Senior Shif t Supervisor or 'Emeraency Duty Of ficer (EDO) to assume that there has been no fuel meltino. If there is any question, a DEFAULT I LOCA should be assumed. DEFAULT III DECAY TANK RUPTURi
- This procedure is used only if actual radiological monitoring equipment is unavailable for release evaluation (monitors out of service, read of f scale, etc.) .
i
- DEFAULT IV FUEL HANDLING ACCIDENT
{
' Any activity occurring as a result of a fuel handling accident is l normally drawn into the Fuel Handling Building Ventilation System {
and vented to the plant-vent for release. The process monitors are j used tc~ monitor these releases; however, should these monitors be ; out of service or off scale, this technique is used to' evaluate off- l
- site dose.:
DEFAULTLV STEAM GENERATOR TUBF RUPTURE The activity released during a minor tube rupture can be determined using vent monitors and normal. procedures. This procedure addresses the steam generator tube rupture as analyzed in the FSAR. This accident is set apart from others because of ~ the inability to consult radiation monitors to determine the activity release rate. Therefore, this is the primary precedure to determine the activity release rate'resulting from a steam generator tube rupture. 24 of 31 Rev. 4
EP IV-lll Attachment 4 ATTACHMENT 4 (continued) EQUIVALENT IODINE EQUIVALENT NOBLE GAS ACTIVITY INCREASE RATE ACCIDENT CLASS RELEASE RATE CPM CPM / MIN UNIT 1 UNIT 2 UNIT 1 UNIT 2 I(l) 2.42 ES 4.34 E6 9.35 E6 9.73 E6 II(l) 7.82 E2 1.40 E4 1.45 E5 1.51 ES III(l) 1.25 ES 2.24 E6 NO RELEASE NO RELEASE IV(1)- S.9 E4 1.78 E6 1.22 E6 1.27 E6 V(2). ' 1.42 E4 2.54 E5 3.3 E6 3.50 E6 (1) Use actual or estimated plant vent flow-(cfm) as provided in the procedure. -(2) Default V is assumed not. released through the plant vent so use a flow of 125,000 cfm for this calculation. 25 of 31 Rev. 4
1 ZP Iv-111 ATT. 5 ATTACHMENT 5
, CONTAINMENT MONITOR 'R-44
. VS DISPERSIOh FACTOR
- e i
- ESESim FACH WQ - scM ,.
r5 i
.#1 -
sr3 nr2 !
'y-9 4 47099 3 4 9 8739' S 4 5 6 feet JU -
7' .- - -
..6___
gs. ., L' _! .:_ __
. _ __ l T l '- T **- E W = _
~
&" ~ , .
I, - . ._ _ _2 2. __
. . _ . . .__2. -
' E_. . V . :5:_ .i rNr6f/i-N#_ _. ~ -~~N_
,o- -
1 s1 m. ~ ..c - _ m, mm _. . m_.____ ____
.,1 o ,..'- h f. D --- -~ ~ - - - A --
; = g g - :- ;. - - -
. _ , __ y >:-;9.
O ' '
.:_-- _L _ ; RL_ L L3X=- ::^~ '_ ~ - s w a&_gpe=
~ === =w ==
, L- = ~L
==:= == _ _ _ _ _ _
'[ . .
.l-.
,- . c : -
3 i - _ - _ _ __ g ;_ 3 } +; _ -
, _ = 7_ + = -
A , . ..
- N. 9 f ._. - - .
w: =1= -ui - = X E = -= - ai ~= z=&= - - _;===_._; m z - - - - 8 -
/
[ q - [ ,
~~
2" T'- "4-
' ~ ' " . , .'
__=__== = m_ _. m y_g- -qn [ .c _
.. =w a m p spz w -
s. grr y_, n r,4.m j,. .,py%w!wN= 7 a,_ r, my?y, , - .m
- r
- wa w w~~ = ==
3 ._ w. l _" A s 1 _ =_= G . &. ;:- y
.--a
_ _ _ , _ _- g_;_= - - - -
--_== = ---
uti t , EIE L l l ^~-SITE DOSE OF 1 REM IN 24 HOURS FOLLOWING A LOCA AS DETERMINED 3Y n 44 RESPONSE AND X/Q. I r . 26 of 31 Rev. 4 l
n n-in
. wr. s f
ATTAOPENT 6 (
./ SmVEY ETER RESPONSE VS. m!N STEM LINE CONCENTRATION i 4
1 10-3 10-2 10~1 100 101' 102 i
, j i
a m Dumurt M ~.-~2.. -A h - -" 4 ,
-dr - - -
4-6e1s-ms1- - r i
-,.o.- -
,w .Mn Ji u ,;. 4 4 w - ~ - _ - w,,c, ,
.n .
we'w A % us, g .ir44r'.r rt %"h 'MJ7.m 4.. p
,y-, -
!; ** 3 de-%7 =4 t ,, ;
- - =- _ . ~ _ -. _
e3i WI. -/ e. ,; 2- -
.. - m... -.-_s- .,._.a. .
W _p-_* u -/ .9
~"-*'-_
e l.-
,_ . _ _1
- 5. ~ ] { {
, --s. --
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n .- s
,. .f )
t.. i_ .m
. _ _ - .- _- __. -- , f e Aaf*
- . _ a.- 1. >
--.m.-> , . J ,
, . "M. 4 9 aummJ wea,=J9de. T4s _ y rJw. .
, , , . . - -. 4.e ..
-. 3
* . a. v3 4 f.. e. w,yr <
= . - -- u, , g. ;_ 1,. .,a- .
i
, . . . . . - .. . . ~ _;- u - - _
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. ---= --
".J. .% L, ' % . " a . ,6 , . 6 , t -
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,p. -
.w- -- _ , = , n u .-
- e -- - - - - - 7 .. ----.a...
.- / ~ ^ ^ __ 4 4
.k'* - ./ . .T*+ , 11
.s s _f - ..
- nf a- .}
\' ~ g, 102 s, _' -_ ' ^
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,~ . .. -
~.__... _
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~ _ - .
r
- i. - . .
e
,~w m--w i 101 ,;
- c. -
_- c . - --
-=1 9- r- . s.,9, P f
- -L .- : . , ' -
, cm . - .:,7. ---1m. ,. - w ....~ ..
.s .. _
,s
,- > - 1 m , _. .- --,.. _.. _ ..-
.as _ ~* .4 r * 'E - -_m _ o ) = M r= '"1
= .-- - r .
,_ v . m .- = .- m_
I ie> *
*4 I - _w*
- r. wf -,. ..fo ,..= : -: -y s =_ . ~- __a . w-+ - um. - - - ~ -- (
W- m w u- -, ---
..c+ m - . ;-
_._=.3.=....=... 3
, , _=----.--
,1-t. == _,
7 -- -. -
- g. - -_ -- . - .--
. n_ , - . . , . .,- -
=. t ,wjs_- ,_- sr ,-= ,-T*4 -., . a . .v ,' - ."*.--.-.d . - -
3 - _
.~.-m- --
- s. ,- . - -
~ -. -- .~.- .y. n. .____n ....e -- _; .
n~..~.- . -.- _ n 1-.. -
-_..n
__- ,~ , . _... =
-_ =. .w
' ~ ~
W ,_ - CDICENTRATION IN m!N STEAM LINES ' vC /cc a 1005 PSIA * . L . ! 'TD wWVERT TO wCrAs MLTIPLY 3Y 1.2CE4 l a 27 of 31 #* 6 _ - . ~ , .. ..m...- .. -- - , ,_ ,,,,_-.,,, w ,,,.--- w ,,.- . _ , , . , , . , - , - , ,
_ ~ . . . . . - EP IV-lli Attachment 7 ATTACHMENT 7
- UNIT ANALYSIS OF OFF-SITE DOSE CALCULATIONS .
l A.l.3a. Unit 1 Low Rance Noble Gas (41C) (cpm . uCi/cc )(ft3 . 2.832E4cc . 1 min)( 1 )(mrem /hr) i 1.6E7 com (min) ft3 60 see m2 uCi/m3 = 6.56E-5 (mph . 0.45 m/sec) - mrem /hr sph A .1. 4' ' Unit 1 Hiah Rance Noble Gas-(R-43 or R-45*) (A.l.3b*) (mr/hr)(ftJ . 2.832E4cc . 1 min) ( 1 )(mrem /hr) min ft3 60-see m2 uti/m3 = 1.05E3 mrem /hr (mph 0.45 m/sec)(mr/hr)
. mph uCi/cc A.1.6 -Unit 1 Iodine (41B)
(c2m . . uCi/cc )(ft3 . 2.832E4cc . 1 min)( 1 )(mrem /hr) min 3.13E9 com/ min min ft3 60 see m2 uCi/m3 = 3.35E7 (mph . 0.45 m/sec) mrem /hr sph A.2.2a Unit 2 Low Rance Noble Gas (41C) (cpm . uCi/cc ) (ft3 . 2.832E4cc . 1 min)( 1 )(mrem /hr) 1.6E7 com min ft3 60 sec m2 uCi/m3 = 6.56E-5 mrem /hr l (mph . 0.45 m/sec) mph A.2.3 Unit 2 High-Rance Noble Gas (R-43 or R-45*) (A.2.2b*) (mr/hr)(ft3 . 2.832E4cc . 1 min)( 1 )(mrem /hr) min ft3 60 see m 4 uCi/mJ = 1.05E3 mrem /hr (mph . 0.45 m/sec)(mr/hr) mph Luci/cc A.2.5 Unit 2 Iodine (41B) (com . uCi/cc )(ft3 . 2.832E4ce.. 1 min)( 1 )(nrem/hr) min 3.13E9 com/ min min ft3 60 see m2 uCi/m3 = 3.35E-7 (mph 0.45 m/sec) mrem /hr mph B.7. Release Rate From Unmonitored B.8 Whole Body Dose Rates Steam From Release Rate ' l.20E4 cc/lb = 3.3 (uci ( 1 )(mrem /hr) 3.6E3 sec/hr gec m 2 uCi/m3 = 2.22 (mph . 0.45 m/sec) mph
- Since 1/2R-45 read directly in uCi/ce, unit analyses for R-43
'are identical except that.the mr/hr/uci/cc conversion factor need not be applied. 28 of 31 Rev. 4 4
, y ._,,-_-,,...y,y.,,.,u- - .
_.---.-w.. .,y,,,-.--,--y. ,._r.-- .--,...n ,,,,-r f., ,,w,-_,,.,. ,m,,_.,,,-ry. ,-,y. ,
g- , --t------ % r ,. -
.. - - - g m , IP IV-III I
. ga s-e .0.
. '8 j /.,. j g - sett OtttM &?loie DEtt - Attachmnt B ~~~
, anoniferlag Ameslag.
3agg . lgegt . Pem _ DILC. ante DILC. TieE , e 6 matt AmlC Diptstsitze lege sus 305E (Dw. FAcr0R 0058 70 east 47
- af LE Aft e F leffsetST CCF en
*=eC 1/ses== ==ese/m3=== 7tE LIEAtlou
==aree/he== W lefTgtt1T (See Att. 1. F IV-tfl3 (See At*. 2. tv-it in '
0 -- Semelt meseems stentsityt a eneesee o Its e g. e Fem grene er replae - thecese Omme mete => se = 0 * (1/01 * (EF) mote -- teelt Aste Elevatest e ( Cametest ) ( l (= l=
., 4 IEA aCl/sec ,ame/m3 (EF Duse mete (Ile/01(2.22) ,1/0 sosisuts rumalFuert W (el (di seren/pri sies mens een (cd ,,.gug le asia le w tmeio see Att. e e. n-isi ( ) (
- I ( l e e mA ( )i2.22) * (en e 67: eC ues. see/es uCF o.. mete
( 4 ) * (el LJ ( ) ( ) (el fel 89*t ese/o emnet at test flee e aCl/see , helt th) efe ( l ( ) t i e 4 172 ( 9(2.33
- fel 4 72 ict/see ese more 4 3( )
sec/od CC? 3rse 'ete (e) (f) 4 +3* r edBLf 445: If R$tc. assa, eng a4SC are eut of service e
*ese 483 emessel, une Att.3. p It.Ill a yZ ( l!2.723 m
( % 9 ( ) ( )e for i ters (8tmenhor to divies by I 9eral. ( H 3 (f) e_ eCI/sme lei ese/m3 - (EF Omeo mete If as3 le ef female me Att. 4, r 87188 *j (gl 8t=3 8 N ( ) ( ( 1(2.22) = (g) l ( 9 *(t) lent 8e See - emote Seer Omos tet_e == 88 e 0 (X/98 (IEF8 ( M 1
- ese e.st unet fles e aCI/ses Ae tc (jl s's Jr See Att. le. SP Iv=111 I I I I I I*
see este 4 eEA scl/sec ese/s3 IEF Ouse mete h/O tt 4/st) (6 or el (g) tare Art I trused t ( l (4.72t2) e (tl i astree gent tsee aCl/ses ( ) ( l ( I*
.**13 or C eC/
ere O LPZ uCl/sec ese/m3 G;F Dese mato 4300- *-l.3 e-0.S JD er el (el 4 tge i1 Ie( 30 ft. estet emot stat l t I (4.72E2) e (6) , . r/tr asent- east flee aCl/soe ( 3 ( l ( IEA 9.91 41.5 3 8t83 (t) efe 226 4 FZ act/sec ses/m3 OCF Dame neto 2-eellt 2.03 10.3 104 lterel (f) $9* 2
- 15044fett feet AlteepeeSteC 14 LIEF v4 Lyt $ \
( \ l ( ) ( la
' esey flee a LPZ .420 2. 501 32.2 teore 8_ eCS/sec ese/e3 (CF Dese Rete Et er el (g)
EPZ .139 .856 13.3
- 0 +3
#f*eV i
' 4t. Asessans e mA/tr shete tesy Quee Cae+e8amma+ Lemmeno i slag Att. S. F liellt 1lst asec. eCl/tg l b/Q t t-4/s2) $ IE A ( )e( )e l t 1 (3J) ( tievetes
'I (el (Sese X/Q) d/QSEA) ItSe le 7e hrt.
eCl/cc lb/hr e eCI/ses (el ecf c.t ,3 l free sense er fles 4 %0- >-0.3 4 V2 ( le ( le 30 ft, estet east stat l Sins COWT18 eENT scelTUt3 70 ESTisenTI 7F317E DOSE CSese 4/93 (2/04 VZ3 age la 24 nrs. IWie LEAfutet. 458 Att. S. y ev.Itt, (el aEA 11.2 j 35.3 e til 4 (PZ ( ), ( le 2-ellt 2.44 '33.4 8H Ihr e* Saoe I/9 to yie14 # (Bene */93 (3/gEPZ) Res en 24 nrs. f neA er S W la 2e heero * (fI l LP2 .512 3.53 11.1 ,
+
l 3: For Unit I (jl e 2.95 t-5 tenit 2 (j) e 2.33t.1 9 f. le ( le
!PI .15?'* 1.22 ; 10.)
l For Delt I th) e t.Sf!*?s Unit 2 (h) e f.3tl+F cese W (s4M_3 or la is arg. l see - (33 l9: Osas the roleone rste seen r- _:tet if e. a.
. -l.* ,.se te e a es.l. m ,=e Steen 19 two else esmed (apal and afetality Step s it ete enete hee esse rete eresses 3.5 remAr l t. non ese w - e., s= t=e ene l e.esere a.ir ,u.a ee, eCvoo ,eeen om . seele si.rt ,me es . If = ,=,r.se a.e rete --
eee.e,.i.i.tre.. = ees. t. r. ~ eier, = . . T,. as o. = i. j first toe 1eren ensue. i e ).Ing.13 stated are tetore emes. List the scrivet 3 Diesnaryms ende a the eserees meses 1 Cl/est
'~~
ttee for et t m8.lefless.
~ 0600 Cl/tr3 et asete geoes are emmes ser one. ,
eere.. Olesherges unie en the suurego emesed 7 krevel flee firs te 9:
- erstenee to secetrea tonest s
*s (29 aCl/tr) et feelee are esses der
- feine asses la soap P3 e 2tl e
I muit ts8, W 60 to get errevet time in eisuetes. O . Deus toegener )av . Sune anos acessent 3mese--
- l 'ea8 o=' ca==' 29 of 31
! me '~ a Fes 2 ins !!2 ha
- e. -- -- - + ,w-w. v. ,,-_w. e-,,-,w
l l EP IV-lll Attachment - 9 i ATTACHMENT 9 LIQUID RELEASE CALCULATION - In the event of a radioactive liquid release to the Delaware River, the following procedures should be used. A. Water Sample Activity Determination A 20 cc sample is taken and placed in a beaker. The sample is placed on top of the SAM 2 detector. The breaker's g?cmetry would be similar.to the geometry for counting a charcoal cartridge. The total gross activity is determined as follows:
- 1) Multiply the total cpm by 80 to get a reading in dpm. The efficiency of the: SAM-2 is approximately 1.25%, hence the ratio of the disintegration rate in dpm to the count rate displayed is 80.
- 2) Multiply the reading in dpm by 4.5 E-7 cc to obtain a reading in uCi.
- 3) Divide the reading in uCi by 20 cc to determine the activity in uCi/cc. Multiply this concentration by lE+9 to determine pCi/1.
- 4) The following information would be recorded:
- a. Location of sample taken:
- b. Date. Time Sample Counted:
- c. Gross Activity pCi/1:
d .- Date. Time Sample Taken: B. Dose Determination The basic equation to calculate the dose conversion factor for a given nuclide is: 30 of 31 Rev. 4
~
EP IV-lll
. Attachment 9 Dose Conversion Factor =2.13 x 10 6 (Eg + Eb/2) -
(arem/hr per pCi/1)
'Wherk: Eg = average gamma energy per disintegration (MeV)
Eb = average beta energy per disintegration (MeV) Boating: For boating activities, the above equation can be modified to the following: Dose Conversion Factor = 1.07 x 10 6 Eg (mrem /hr per pCi/1) In this equation adjustments account for the physical geometry and the beta shielding afforded by the boat hull. An additional reduction factor for gamma shielding is also appropriate but such a factor.will not be included due to the uncertainty of boat design. Using normalized dose conversion factors: Immersion = Normalized x Total isotopic x Exposure x Dilution Dose dose conver- concentration Time Factor (mrem) sion factor (pci/1 (hr) (mrem /hr per pCi/1 of the weighted isotopic (mixture) Where: The normalized dose conversion factors are: Water Immersion (Swimming): Gamma whole-body doses =
- 1. 44 x 10 6 mrem /hr per pCi/l l
Beta-gamma skin doses = 1.72 x 10 6 mrem /hr per pCi/l i p Boating: Gamma whole-body dose = 7.21 x 10 7 mrem /hr per pCi/l 31 of 31 Rev. 4
. :~
. EP IV-ll3 EMERGENCY PROCEDURE EP IV-ll3 COMPUTERIZED' DOSE CALCULATIONS
~
~
ACTION ~ LEVEL , This procedure may be used in-lieu of the manual dose calculation procedures. RESPONSIBLE INDIVIDUAL
~
An individual familiar with the Nuclear Data 6700 system (normally
.a Shif t RPT or EOF assessment team member) .
ACTION STATEMENTS
- 1. Contact the' Control Room liaison and obtain the necessary information for the respective unit. This. information can be compiled onto'the Dose' Assessment Data Sheet (See Attachment 1).
UNMONITORED GASEOUS RELBASES (additional information needed) a.) Main.steamline survey instrument reading-(contact-mr/hr.) from field measurements or from R46 (main steamline monitor) data if available. b.) Background survey instrument reading (mr/hr) from field measurements. c.) Number and duration of power operated relief valves open from CR or EDO. d.) Number and duration of automatic relief valves open from CR or EDO. e.) Number and duration of auxiliary feed pump exhaust valves open from CR or EDO. 1 of 31 Rev. 3 4
- , -. ,. . --y .- --v,-
EP ,IV-113 CONTAINMENT LEAKAGE (additional information needed) a.) High range Containment Monitor Reading (R21/R44 in R/hr.)
- 2. Ensure a valid. user is signed on the computer and that the Dec-writerLterminal settings are correct'(these settings are listed on the acoustic coupler used with the terminal). Dial 3209 (Salem) to access ND6700. If using a modem, see Attachment 2
.for proper accessing procedure.
- 3. Type in: WHO (return)
- 4. If the system indicates a user is signed on, proceed to Step 5.
If the system response is "NO USER SIGNED ON" Type in: HEL 10 (return)
- 5. If at the Control Point or EOF type in: JOB AUTO. DOSE 1 If at the TSC. type in: JOB AUTO. DOSCAL
- 6. The computer code will now ask a series of questions.
a.' Included in these questions is a query concerning whether or not this is the first meter reading in the series. A "yes" answer will eliminate all previously entered data in the
- file. A "no" answer will. add the new data to an already
[ begun file. During an emergency, (or drill) the very first set of data should have a "yes" answer. All remaining entries should be "no". After 24 hours and 45 minutes of data has been entered, it is necessary to begin a new file by
. replying "yes". ,
- b. If~an elevation for wind speed and temperature. readings of 33 feet is entered, it is necessary to call the Wilmington airport (302-323-2280) to determine the proper stability class (unstable, neutral, stable).
2 of 31 Rev. 3
ER IV-ll3 USER NOTES: < If a mistaken entry is made at any step of.the responses to the computer program's queries, enter (return) 1nstead of answering the next query. This response will return you to the beginning. At the end of each calculation, the option exists to perform additional dose calculations or to perform integated dose calculations, enter the desired distanca in. meters-(1 100). (miles x 1.61E3 = meters). To perform an integrated dose-calculation, enter the number of 15 minute projections desired (< 100). (i.e., an entry of 8 will give 2 hours of projections beginning with 15 minutes after the latest entered time.) .At least two (2) sets of data must be in file (at least one "no" answer) for the calculation to be performed.- To exit the program, enter zero (0) to stop or return (cr) to start again (see examples below).
- 7. Upon answering all of the program's . queries, the computer printer will then print out results such as those provided as examples in the following attachments.
NOTE: If all noble gas or iodine monitors (low, medium, or high range) are inoperable or offscale, after typing in the last
"-1" response, a listing of default classes will be printed.
Once a default is chosen, the computer will calculate results, based on default values for noble gas and iodine monitor count
^
rates from a file. If you wish to review these values, please refer to Attachment 3 of this procedure.
- 8. To exit and terminate the program:
a.) Enter (0) Zero to Step as per program query. b.) Hit Ctrl P to Exit job stream. c.) Type in: BYE 10 (Return) d.) Response: SIGNED OFF 3 of 31 Rev. 3
EP IV-ll3 Signature Page Reviewed By: (f.> [// {
,, j /h// 3 79
/ bepartmentHead Date.
Reviewed By: [ 'h w /#!/ ' J Nucliar Emergency Plapbing Engineer Date l Reviewed By: k- - 1- _ / c' // o[A % , Station Quality Assurance Review Date (if required see EP VI-2) SORC Meeting No.: 7 3- /} / /o/2d P3 Date Approved By: N /d/d/!Id General b ager - Salem Operations Date Approved By: , // > Manager-NuckearSiteProtection date I l t I l l l l l i i 4 of 31 Rev. 3 l 1
EXAMPLES INCLUDED IN EP IV-113
- ATTACHMENT 4 -
EXAMPLE OF ELEVATED RELEASE-PLANT VENT
?^ ATTACHMENT -5 -
EXAMPLE OF ELEVATED RELEASE -UNMONITORED l ATTACHMENT 6 - EXAMPLE OF GROUND RELEASE CONTAINMENT LEAKAGE ATTACHMENT 7 - EXAMPLE OF GROUND- RELEASE-F LAt:T VENT ATTACHMENT 8 - DEFAULT CLASS EXAMPLE
'ATTACEMENT 9 -
IODINE RELEASE RATE KNCWN ATTACHMEt'T 10 - NOBLE GAS' RELEASE RATE KNOWN ATTACHMENT 11 - INTEGRATION PERFORMED 9 6 5 of 31 Rev. 3 {
DOSE ASSESSMENT DATA SHEET Ahhme>Tt l DATE UNIT TIME OF READING Plant Vent Flow Rate (CFM) Wind Speed (MPH) or EL-300' EL-150' . Wind Direction (FROM) or g EL-300' EL-150' ' - Temp (*C) or 300'-33' 150'-33' Releace Level (circle one) Elevated / Ground R31 gra R41 A gn R41 B gn;
- gn @
last reading time R41 C cpm R43 mR/hr R44 A R/hr R44 B R/hr R45 A gn R45 B uCi/cc i R45 C uCi/cc R45 D mR/hr R46 A uCi/cc R46 B UCi/cc R46 C uCi/cc R46 D uCi/cc . R46 E** UCi/cc Stean Line Survey Instru::ent mVhr Steam Release lbs/hr (Flow Rate) obtain epm / min fror CRT display if available (note cpm / min units) R46E serves as a backup for any of the other R46 channels, the sum of the remaining 3 - R46 readings must be subtracted from R46E to determine the correct value. Whio .Stetta Soard Attendent C 6 of 31 Rev. 3 Goldenrod Commenestor M F83 43/031 df
~~ u, 5 [,.# ; T N': :s
\ '%
l '" 4
%9 - . >};
c ., EP IV-113
, ATTACHMENT-2 e SET-UP PROCEDURE FOR r AUTO DIAL MODEM AND ~
DEC LETTERWRITER TERMINAL
- 1. Modem Set-up -
s . . - a') Ensuro modem-is off (on/off Button is out). b).AL Button is out. c) Plug' modem p,ower supply transformer-into wall outlet and' modem power plug into jack on modem. d) Connect phone line into wall jack and into either phone jack in the rear of<the modem (if a: phone is needed for use it can be connected to the other phone jack in the rear of the modem). i
'2. Terminal Set-up ..
a);Ensureterminal'powerswitchisintheoffposktion. b) Insert power cord into the terminal oower connector, then.
. insert the plug into a power recepticle. ;
c) Connect the RS 232 cable to the terminal connector then connect the cable to the modem connector. ,
'3 . . Terminal Operation NOTE Operator input on. terminal will be underlined and computer or termina1 ' response will be - in quotes. ,
14 a) Turn on terminal power switch, b) . Push in modem power switch to on positioni i
.c) Push Control key and hold and simultaneously" push Set-up key. The " Set-up" light on the keyboard. hould be flashing, d) Type S return. The terminal will respond with a list of available operating speeds and indicate the current setting.- For 300 baud operation the setting should be "G" and.for 1200 baud operation the setting'should be "I". To
~
set the baud rate type: ' S=G for 300 baud, or i Y7T for 1200 baud. e
^
l 1 7 of 31 Rev. 3 i
EP IV-ll3-ATTACHMENT 2
, . SET-UP PROCEDURE FOR T -~ AUTO DIAL' MODEM AND DECELETTERWRITER TERMINAL (con?d) e) After' baud is set push Set-up key. The Set-up light will stop flashing. .
"f)' verify "Line" light on keyboard is on, if not press
- Line/Lecal key.
4 g) Type A T return.. , h) Response "OK".
- 1) To call a computer from the terminal type:
, .'T .
A T-D T', The phone number return ie. . For phone number .3209 Type A T D T z 3209 return For dialing.through-switchboard commas can be inserted
^
=af ter. access number is dialed to allow for dial tone (each comma is.a two (2) second wait).
'- Type A_ T D T t-- 4 1 1 4 2_ 9 3'2_ O_ 9_ return j) Response'" Connect" k)~Procee'd with appropriate procedure as required until computer access is.no longer desired.
1)-When-completed with computer, turn off the modem and turn off the terminal. NOTE Each tire the terminal is turned off the terminal operation steps should be u*ad when restarting the terminal to ensure
- the operating l speed is_ set'as desired. If the terminal speed is not the samenas the speed of the modem connected to the 1 . computer the computer will automatically disconnect the call l within a few
- seconds. The modem will then cause the response
!. on'the terminal."NO CARRIER". e
~
i
- 8 of 31 Rev. 3 L.-
1 EP'IV -113 ATTACHMENT 3
" ~
ATTACHMENT-3 -
. -DEFAULT VALUES FOR PLANT VENT MONITORS.
~
Read the-below accident description and determine which case is applicable. .? rom the table select the appropriate release rates
- (cpm).- ~
DEFAULT I LOCA WITH FUEL MELTING A LOCA assuming severe core damage --fuel melting (Regulatory Guide
. l.4 assumptions ) 100% of noble gases and 25% of the iodines-
- contained-in the core are assumed released to the containment. The containment-initially leaks at the maximum design leak rate. -
DEFAULT II-LOCA WITHOUT FUEL ~ MELTING Primary coolant leaks at a rate fast-enough to increase the temperature of the core to the point where there is damage to the fuel rods.- For this case,.it is assumed thet all.the gap activity (the gases contained between the fuel and fuel rod) is released to the containment. The containment is assumed to initially leak at the maximum design leak rate. In this accident, it is up to the Senior Shift' Supervisor or Emergency Duty Officer (EDO) to assume that there has been no fuel melting. If there is any question, a DEFAULT I LOCA should be assumed. DEFAULT III DECAY TANK RUPTURE
- This procedure is used only if actual radiological monitoring equipment is unavailable for release evaluation (monitors out of
. service, . read off scale, etc.)'..
DEFAULT IV FUEL HANDLING ACCIDENT Any activity occurring as a result of a fuel handling accident is normally drawn into the Fuel Handling Building Ventilation System
- and-vented-to the plant. vent for release.= The process monitors are used to monitor these releases; however, should these monitors be-
- out of' service or off scale, this technique is used to evaluate off-site dose.
-DEFAULT'V STEAM GENERATOR TUBE RUPTURE The activity released during a minor tube rupture can be determined using. vent. monitors and normal procedures. This procedure addresses the steam generator tube rupture as analyzed in the FASR. This
, accident is set apart from others because of the inability to consult radiation monitors no determine the activity release rate.
.Therefore, this is,the primary procedure to determine the activity release rate resulting from a steam generator tube rupture.
9 of 31 Rev. 3 _ _. , . _. __ _ _ . - _ . . ~ _ _ _ _ ._.. . ~ . . - _ _ _ _ . _ _
EP IV-ll3 Attachment 3 ATTACHMENT 3 (continued) EQUIVALENT IODINE EQUIVALENT NOBLE GAS ACTIVITY INCREASE RATE
' ACCIDENT CLASS RELEASE RATE CPM CPM / MIN UNIT l- ,__ UNIT 2 UNIT 1 bNIT 2-
_I(l) 2.42 E5 4.34 E6 9.35 E6 9.73 E6 II(l)~ 17.82 E2 1,40 g4
~
1.45 E5 1.51 E5 , III(I)' l.25 ES 2.24 E6 'NO RELEASE NO RELEASE IV(1) 9.9 E4 1.78 E6 1.22 E6 1.27 E6 V(2). 1.42 E4 2.54 ES 34 3 E6 3.50 E6
'(1) Use actual or estimated plant vent flow (cfm) as provided in the procedure.
~
(2) Default V is. assumed not. released through the plant vent so use a flow of 125,000 cfm for this-calculation. f
m
.- 1
. l
> ,EP IV-ll3 Attachment 4 NOTE: Responses are underlined for this procedure only _(program entries are not underlined).
EXAMPE Is EEVATED REEASE - PIAfC VENT (perform as per request of RPE or RSM) DERGENCY PROCEDURE - EFFEENT DOSE CALCUIATIONS: EP IV-ll3 1 JAN 1982 0:19:11 OPERATOR'S INITIALS - ENIER <CR) AIONE TO STOP. . . . . . . . . ..# PIE INDICATE TYPE OF RELEASE EOR '1EIS CAIfUIATION
- 1. EEVATED REEASE - PIRE VENT
- 2. GROUND REEASE - UNMONITORED
- 3. GROUND REGASE - CCNIAINMENT LEAKAGE
- 4. GROUND REMASE - PIJNT' VENT
.......................................# 1 ENTER TIME FOR METER READINGS (MILITARY TIME - HRMN) ..
- YOU MUST ENTER 4 DIGITS (E.G. 0945).............# 1800 EOR 'IEE SAKE OF INTEGRATED DOSE CAIfUIATIONS IS THIS
'IEE FIRST METER READING IN THIS SERIES (Y/N) ....#Y UNIT NUMBER ( 1, OR 2 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . # l_
IF AVAILABLE ENTER NOBE GAS RELEASE RATE (UCI/SEC) 01EERWISE ENTER -1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . #d IF AVAIIABLE ENTER IODINE REEASE RATE (UCI/SEC) OlEERWISE ENIER -1..............................t d ICW RANGS GASEQUS RELEASE RATE - MEIER 1R-41C (cpm) IF OFFSCALE OR INOPERABLE ENIER -1. . . . . . . . . . . . . . # 4E5 INITIAL IODINE RELEASE PATE - METER 1R-41B (cpm) IF OFFSCALE OR INOPEPABLE ENTER -1. . . . . . . . . . . . . . : 30 FINAL IODINE RELEASE RATE - METER 1R-41B (cpa) IF OFFSCALE CR INCPERABLE END T -1. . . . . . . . . . . . . . # 1200 EIAPSED TIME BETIWEEN IODINE READINGS (MIN ) . . . . . . . . . . . e 5 PIRE VENT FIfW RATE (cfm) IF VALUE UNATIAINABLE ENIFR 125000..............g 68000 ELEVATION FOR WIND SPEED' & TEMPERATURE READINGS (FEET)
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ( 3 3 OR 150 OR 3 00 ) # 300 TEMP (300 ' ) - TEMP (33 ' ) - DELTA T (EEG C) . . . . . . . . . . . # .5 WIND SPEED 9300 FEEI (MPH) - ENTER 5 IF UN%NOWN......# 1 WIND DIRECTICN (DEGREES FROM) . . . . . . . . . . . . . . . . . . . . . . . . # 216, TIME FROM SHUIDOWN TO RELEASE (HRS ) . . . . . . . . . . . . . . . . . . #1_
11 of 31 Rev. 3
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,EP IV-ll3 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX XXXXX XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX StMLARY RENRT NOBIE GAS RELEASE RATE. . . . . . . . . . . . . . . . . . . . . . . . . . . . = 8.02 4E 05 (UCI/SEC)
IODINE RELEASE RATE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . = 2. 643E 00 (UCI/SEC) RATE OF ' INCREASE OF . IODINE ACTIVITY. . . . . . . . . . . . . . . = 2. 540E 02 (CIN/ MIN) DISTANCE FROM VENT XU/O WB DOSE THY DOSE TIME FOR PLLNE
- (METERS) (MILES)' (1/N2) (MREN,41R) (MREM /ifR) TO TRAVEL DIST (MIN)
======= = =
MEA- 1270. 0.79 4.260E-05 3.041E-01 7.106E-01 47.4 CIA = 18:47 3218. 2.00 1.525E-05 8.935E-00 2.499E-01 120.0 ETA = 19:59
, 5500.- 3.42 7.ll5E-06 3.2865-00 1.142E-01 205.l~ ETA = 21:25 LPZ- 8045. 5.00 4.031E-06 1.427E-01 6.340E-02 300.0 ETA = 22:59 10000. 6.22 2.897E-06 8.384E-01 4.4902-02 372.9 EIA = 0:12 13000. 8.08 1.938E-06 4.182E-01 2.942E-02 484.8 ETA = 2: 4 EPZ- 16000. 9.94 -1.408E-06 2.333E-01 2.096E-02 596.6 ETA = 3:56 ENTER DISTANCE FOR ADDITIONAL CAIfUIATIONS (METERS)
OR ENTER # OF 15 MIN DOSE PROJECTIONS DESIRED (<100) ENTER 0 TO STOP - ENTER <CR) AIONE TO BEGIN AGAIN. ... # 0 12 of 31 Rev. 3
.EP-IV-113
Attachment:
5
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XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXxXX XXXXXxXXXXXXXXXXxXXXXxXXXXXxXXXXXXXXXXXXXXXxXXXXXxxXXxxx-EXAK 2'II - GROUND REIEASE - UMONITORED (E.G. dn.AM GENERA 7DR TUBE RUPIURE EVENIS) EMERGENCY PROCEDURE - EFFIDENT DOSE CAIEUIATION:'EP IV-113
-1 JAN 1982 '0:22:05 OPERATOR'S IN' ITIALS - ENTER <CR> AIfNE TO SIOP . . . . . . . . . . 2 PIE INDICATE TYPE OF RELEASE FOR 'IMIS CAILULATION
- l. ELEV4TED REIEASE - PIANT VENT
'2. GROUND RELEASE - UNMONITORED 3.' GROUND RELEASE - CONTAIMENT IEAKAGE
- 4. GROUND RELEASE - PIANT VENT
.................................. # 2 ENIER TIME FOR METER READINGS (MILITARY TIME - HRM)-
YOU MJST ENIER 4 DIGITS (E.G. 0945)........ # 1800 FOR THE SAKE OF INTEGRATED DOSE CAI4UIATIONS IS THIS THE FIRST METER READING . IN 'INIS SERIES ( Y/N) . . . . . . . . . . . . . . . . .Y_ ENTER APPROPRIATE VALUES
- 1. # OF POWER OPERATED RELIEF VALVES OPEN.... # 1 L 2. # OF ALTICMATIC RELIEF VALVES OPEN. . . . . . . . . # 2_
l 3.- # OF STEAM DRIVEN AUX FEEDWATER PUMPS ON.. # 3 EIrv% TION FOR WIND SPEED & TEMPERATURE READINGS (FEET)
..........................(33 Ca 150 CR 300) # 150 TEMP (150') - TEMP (33' ) -
DELTA T (DEG C)..........# .1 WIND SPEED @ 33 FEET (MPH) - ENTER S IF UNKNOWN. .. ..# 3_3 3 WIND DIRECTION (DEGREES FROM).......................# 1 TIME FROM SHUIDOWN-TO RELEASE (HRS).................A 6 CCNTACT DOSE RATE ON AFFECTED STEN 4 LINE OR i: AUXILIARY FEED PUMP LINE (MR/HR)............# 300 , [ DAGGROUND DCSE RATE (MR / HR) . . . . . . . . . . . . . . . . . . . . . . . . # 160 L ACTIVITY CCNCENTRATICN IN PIPE. . . . . . . . . . . . . . . . . . . . . .= 5.320E-01 ( UCI/CC ) REIEASE RATE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .= 3. 86 2E-06 (UCI/SEC ) !~ l 13 of 31 Rev. 3
. ~ _ _ -
- EP' IV-113 TUTAL RUN TIME FOR SIDM DRIVEN AUXILIARY FEED PWP ( HRS ) . . . . . . . . . . . . . . . . . . . # 3.5 TUTAL PERIOD OF TIME RELIEF -
AND POERDPERATED RELIEF VALVES WERE OPEN ON THE AFFECTED STEAM GENERATOR ( HR) . . . . . . # 4_ RESULTS DISTANCE FRCM 'v72.T XU/O KB DOSE NCB GAS ECF TI*AE FCR PLEME (METERS)' (MILES) (1/M2) (MREM /HR) MR/HR/UCI/CC TO TFAVEL DIST (MIN)
===================================== -===========---==- ======-============
MEA- 1270. 0.79 2.263E 1.163E+01 1.979E-01 1.4 ETA = 18: 1 3218. 2.00 1.036E-04 5.295E-00 -1.967E-01 3.6 ETA = 18: 3 5500.- 3.42 5.447E-05 2.764E-00 1.953E-01 6.2 ETA = 18: 6 LPZ - 8045. 5.00 3.319E-05 1.671E-00 -1.937E-01 9.1 ETA = 18: 9 10000. -6.22 2.478E-05 1.240E 1.925E-01 11.3 ETA = 18:11 13000. 8.08 1.733E-05 8.585E-01 1.907E-01 14.7 ETA = 18:14 EPZ- 16000. '9.94 1.301E-05 6.385E-01 1.889E-01 18.1 ETA = 18:18-ENTER DISTANCE FOR ADDITIONAL CAILUIATICNG (METERS) ENIER 0 TO STOP - ENTER <CR> AIONE TO BEGIN AGAIN. .. . # 8045 DISTANCE FROM VENI XU/O 2 DOSE NOB GAS DCF TIME FOR PLUME _ (METERS) ~(MILES) (1/M2) (MREM /HR) MR/HR/UCI/CC TO TRAVEL DIST (MIN)
. -_.._..._..._ ---.....--. ..--._._. -,--------.a.+ . - _ , =
8045. 5.00 3.319E-05 1.671E-00 -1.937E-01 9.1 ETA = 18: 9 ENTER ~ DISTANCE FOR ADDITIONAL CAILUIATIGS (METERS) OR ENIER # OF 15 MIN DOSE PROJECTIONS DESIRED (<100) ENTER 0 TO STOP - ENTER <CR> AIONE 10 BEGIN AGAIN. . . . # 0_ XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX 14 of 31 Rev. 3
w--- o
. EF IV-ll3 Attachment 6-EXAMPLE III - GROUND RELEASE - CONTAINMENT LEAKAGE (PEREORMED AS PER REQUEST OF RPE OR RSM) -
EMERGENCY PROCEDUPE - EFFLUENT IXEE CAICUIATION: EP IV-III
-1 JAN 1982 .0:23:01 OPERAIOR's INITIAIS - ENTER <CR> AIINE TO SIOP. . . . . . . . . . . . # PIE INDICATE TYPE OF RELEASE FOR THIS CAICUIATION
- 1. ELEVAIED RELEASE - PIANT VENT
-2.. GROUND REIEASE - UNMONITORED
- 3. GROUND RELEASE - CONTAIPNENT LEAKAGE ~
'4. GROUND RELEASE - PIAVE VENT
.................................. # 3 ENIER TIME FOR METER READINGS (MILITARY TIME - HRMN)
YOU MUST ENIER 4 DIGITS (E.G. 094 5) . . . . . . . . # 2000 EUR THE SAKE OF ' INTEGRATED DOSE CALCULATIONS IN THIS
' THE FIRST METER READING IN THIS SERIES (Y/N)..*Y
/' ' -
UNIT NtNBER - ( 1, OR 2 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . # 1 ELEVATICN EOR WIND SPEED & TEMPF'ATURE READINGS (FEET)
.......................(33 OR 150 OR 300) # 300 TEMP (300' ) TEMP (33') - DELTA T . ( DEG C) . . . . . . 4 '-1. 2 WIND SPEED @ 33 FEER (MPH) - ENTER 5 IF Uh7NCKN.. # E WIND DIRECTIL1 ( DEGREES FROM ) . . . . . . . . . . . . . . . . . . . . # 3 i
TIME FROM SHUII.OW TO RELEASE (HTS) . . . . . . . . . . . . . . . . # d HIGH IGNGE CONTAINMENT RADIATICN MONITOR R21/R44 READING ( R/HR ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . # 3 3 3 -
' DISPERSION FACIOR (X/0).......................... 4 3.lS3E-01 (SEC/M3) 15 of 31 Rev. 3 i
. ~-
EP IV-ll3 RESULTS DISTANCE FROM VENT XUM WB DOSE TIME FOR PLUME (MEIERS) (MILES) (1/M2) (MREM /HR) TO TRAVEL DIST'(MIN) MEA--- 1270. 0.79 4.154E-05 1.329E-05 2.2 ETA = 20: 2
'3218. 2.00 1.029E-05 3.293E-06 5.5 ETA = 20: 5 -
5500. -3.42 -4.503E 1.441E-06 9.3 ETA = 20: 9 LPZ- 8045. 5.00 -2.496E-06~ 7.989E-07 13.6 ETA = 20:13 10000. , 6.22 1.*iB0E-06 5.697E-07 17.0 ETA = 20:16 13000. 8.08 1.183E-06 3.787E-07 22.0 ETA = 20:22-9.94 8.564E-07 2.741E-07 ~27.1 ETA = 20:27
.EPZ .16000.
ENTER DISTANCE FOR ADDITIONAL CAICUIATICNS (METERS)
. ENTER 0 TO STOP - ENTER <CR> AIDNE TO BEGIN AGAIN.... # 3218
' DISTANCE FROM VENE XU/O WB DOSE TIME FOR PLUME (METERS) (MILES) '(1/M2) :(MREWHR) TO TRAVEL DIST (MIN) 3218. 2.00 1.029E-05 3.293E-06 5.5 ETA = 20: 5 ENTER DISTANCE FOR ADDITICNAL CAIEUIATIONS (METERS)
OR ENTER # OF 15 MIN DOSE PIO7ECTIONS DESIRED (<100) ENTER 0 TO STOP - ENTER <CR) AIONE TO BEGIN AGAIN.... # 0_ xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx - xxxxxx
- _-- _-x-x-x---xwucivvvvvv_v_vxwuuwy-x-x-x-xxxxxxxxxxxxxxx 16 of 31 Rev. 3
[. EP IV-ll3 Attachment 7 EXAMP 2 IV: GBOUND RELEASE - PLANT VENT (FOR MOST PLN E VENT RELEASES) EMERGENCY PROCEDURE - EFFLUENT DOSE CAIfUIATION: EP IV-113
- 1 JAN 1982 0:23:50'~ -
OPERATOR' S INITIALS - ENIER <CR> AIONE TO STOP. . . . . . . . . . . # PLF INDICATE TYPE OF REMASE FOR 'IMIS CAICUIATION
- 1. EEVATED REEASE - PLANT VENT ,
- 2. GROUND REMASE - UNMONITORED
- 3. GPU)ND RELEASE - CONTALPENT LFAKAGE
- 4. GROUND RELEASE y PLANT VENT
#4 ENIER TIME FOR METER READINGS (MILITARY TIME - HRW)
YOU MUST ENIER 4 DIGITS (E.G. 0945)........ # 1800 EOR THE SAKE OF INTEGRATED DOSE CAICULATIONS IS THIS THE FIRST METER READING IN THIS SERIES (Y/N)..#Y UNIT ( 1, OR 2 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . # 1 IF AVAILABLE ENTER NOBG GAS REMASE RATE (UCI/SEC) OIHERWISE ENIER -1. . . . . . . . . . . . . . . . . . . . . . . . . . # _l, l IF AVAIIABE ENIER IODINE RELEASE RAIE (UCI/SEC)' oniERWISE ENIER -1. . . . . . . . . . . . . . . . . . . . . . . . . . #d ICW RANGE GASEOUS RELEASE RATE - (MEIER 1R-41C (CH4) IF OFFSCALE OR INOPERABLE ENTER -1. . . . . . . . . # 4E5
. INITIAL IODINE REMASE RATE - METER 1R-41B (CPM)
IF OFFSCALE OR INOPERABLE ENTER -1. . . . . . . . . # 30, FINAL IODINE RELEASE PATE - MEIER 1R-41B (CPM) IF OFFSCALE OR INOPERABLE ENIER -l. . . . . . . . . # 1300 EIAPSED TIME BEIWEEN ICDINE READINGS (MIN) . . . . . . . 4 5 PIANI VENT FIDW RATE (CFM) IF VALUE UNATIAINABG ENIER 125000......... e 68000 l-EEVATION FOR WIND SPEED & TEMPERATURE READINGS (FEET)
. . . . . . . . . . . . . . . . . . . . . . . . . . ( 30 OR 150 or 300 ) # 150 TEMP (150' ) TEMP (33') = DELTA T (DEG C) . . . . . . . . # .5 WIND SPEED 0 33 FEER (MPH) - ENIER 5 IF UNKNCWN... # 1 WIND DIRECIION (DEX3REES FROM) . . . . . . . . . . . . . . . . . . . . . # 25 6 d TIME FROM SHUIDOWN TO PEIIASE (HRS ) . . . . . . . . . . . . . . . # 1 1
17 of 31 Rev. 3 i i o
._ - - . -- - , , , w- - - , - - , ,
1 EP IV-113 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX E(XXXXXXXXXXXXX XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX SIM RRY REPORT NOBLE GAS REIEASE RATE. . . . . . . . . . . . . . . . . . . . . . . . . . . . = 8. 024E-05 (UCI/SEC) '
' IODINE RELEASE RATE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . = 2. 64 3E-00 (UCI/SEC)
RATE OF INCREASE OF IODINE ACTIVITY. . . . . . . . . . . . . . . = 2.540E-02 (CRi/ MIN) DISTANCE FPOM VENT- XU/O NB DOSE < THY DOSE TIME FOR PLUME (METERS) ^ (MILES) (1/M2)- (MREM /HR) (MREMAR) 'IO 'IPAVEL DIST (MIN) MEA- 1270. 0.79 4.154E-05 1.428E-01 6.930E-01 47.4 ETA = 18:47 3218. 2.00 1.029E-05 2.901E-00 1.686E-01 120.0 ETA = 19:59 5500. 3.42 4.503E-06 1.001E 7.230E-02 205.1 -- ETA = 21:25 LPZ- 8045. 5.00~ 2.496E-06 4.252E-01 3.926E-02 300.0- ETA = 22:59 10000. -6.22 1.780E-06 2.480E-01 2.759E-02 372.9 ETA = 0:12 13000. 8.08 1.187E-06 1.229E-01 1.796E-02 484.8 ETA = 2: 4 EPZ- 16000. 9.94 8.564E-07 6.833E-02 1.275E-02 596.6 ETA = 3:56 ENIER DISTANCE FOR ADDITIONAL CAICUIATIONS (METERS) OR ENTER # OF 15 MIN DOSE PRO.7 ECTIONS DESIRED (<100) ENTER 0 'IO S'IOP - ENTER <CR> AIDNE 'IO BEGIN AGAIN. . . . # O_ 18 of 31 Rev. 3
e
~
Default Class Example Attachment 8 EMERGENCY; PROCEDURE'- EFFLUENT DOSE CALCULATION:,EP IV-113
~
- 22 SEP:1983.9:26:13
- ~,
OPERATOR'S INITIALS - ENTER <CR> ALONE TO STOP .............# KG INDICATE TYPE OF RELEASE FOR THIS CALCULATION 1.- ELEVATED RELEASE - PLANT VENT
- 2. GROUND RELEASE - UNMONITORED
'3. . GROUND' RELEASE - CONTAIMENT LEAKAGE ,
- 4. : GROUND RELEASE --PLANT VENT
.................................i L
- ENTER TIME FOR METER READINGS-(MILITARY TIME - HRMN)
YOU MUST ENTER 4 DIGITS (E.G. 0945)...,..# 1800 FOR THE SAKE OF INTEGRATED DOSE -CALCULATION IS THIS ^
.THE FIRST METER READING IN THIS SERIES (Y/N).....# Y UNIT NUMBER (1, OR 2) ...........................# 1
! IF AVAILABLE ENTER NOBLE GAS. RELEASE RATE-(UCI/SEC) OTHERWISE ENTER -1.......................# -1 IF AVAILABLE' ENTER IODINE RELEASE . RATE (UCI/SEC) OTHERWISE-ENTER -1 ..................... 9 -1 LOW RANGE GASEOUS RELEASE RATE - METER 1R-41C (CPM) IF OFFSCALE OR INOPERABLE ENTER -1.......# -1 MEDIUM OR HIGH-RANGE GASEOUS-RELEASE MONITOR R45B OR R45C (UCI/CC)
.IF OFFSCALE OR. INOPERABLE ENTER -1 ......# -1
-HIGH RANGE GASEOUS RELEASE RATE - METER R-43'(MR/HR)
[ _IF OFFSCALE OR. INOPERABLE ENTER -1 ......#.-l CASE'l LOCA
......u.... .
A LOCA ASSUMING SEVERE CORE ',AnnGE WITH FUEL MELTING. ASSUME 100% OF THE NOBLE GAJES AND 25% OF THE IODINES ARE RELEASED TO THE CONTAINMENT.- THE CONTAINMENT
- i. INITIALLY LEAKS AT THE MAXIMUM DESIGN LEAK RATE.
i CASE 2'LOCA-c ........... LESS SEVERE LOCA THEN CASE 1. PRIMARY COOLANT HAS LEAKED FAST ENOUGH~TO INCREASE THE TEMPERATURE OF THE CORE TO TH,E POINT'WHERE THERE IS DAMAGE TO THE FUEL RODS. IT IS UP l TO THE SENIOR SHIFT SUPERVISOR /EDO TO ASSUME THAT THERE ! HAS BEEN NO FUEL MELTING. IF THERE IS ANY QUISTION. CASE 1 LOCA SHOULD BE ASSUMED. l !~
.19 of 31 Rev. 3
..-.-....a-_ . . . - - - . . . . - , . . - . _ . - . - . .
x CASEi3 GAS' DECAY: TANK' RUPTURE *
=============================
~THESE DEFAULT' VALUES SHOULD~BE USED ONLY IF THE ACTUAL.
RADIOLOGICAL MONITORING EQUIPMENT-IS UNAVAILABLE-FOR
' RELEASE - EVALUATION. .
- CASE 4 FUEL HANDLING ACCIDENT' ,
=============================
NORMALLY ANY. RELEASE ~SHOULD BE DRAWN INTO THE PLANT-VENT FOR MONITORING. 'IF THE EFFLUENT MONITORS ARE INOPERABLE. THEN THESE VALUES SHOUT D BE USED.-
~ CASE'S STEAM GENERATOR TUBE RUPTURE
...=================================
' THESE VALUES ARE FROM THE TUHE RUPTURE AS ANALYZED IN
-THE FSAR. MONIORS MAY:NOT BE AVAILABLE.TO MONITOR THE RELEASE POINT. fTHEREFORE, THIS IS THE PRIMARY WAY TO ESTIMATE OFF-SITE: DOSES..
SELECT'THE. APPROPRIATE' ACCIDENT.DISCRIPTION (1-5)
- 1. CASE I .LOCA.
.2. ' CASE II -.LOCA
'3.- CASE III-- DECAY TANK RUPTURE 4.- CASE IV - FUEL HANDLING' ACCIDENT
- 5. CASE V - STEAM GENERATOR TUBE RUPTURE 1,
INITIAL IODINE RELEASE RATE - METER 1R-41B - (CPM ) IF OFFSCALE OR INOPERABLE ENTER -1 ..........# -l' FINAL-IODINE RELEASE RATE - METER'lR-41B (CPM) IF'OFFSCALE OR INOPERABLE ENTER -1 ......... 4 -1 2 PLANT VENT. FLOW RATE (CFM)
~.IF.VALUE UNATTAINABLE ENTER 125000 ..........# 68000
' ELEVATION'FOR WIND SPEED & TEMPERATURE READINGS (FEET)
..........................(33 OR 150 OR 300)'e 150
-TEMP (150') - TEMPT (33') - DELTA T (DEG C) ........ 4 .5 it WIND SPEED @ 33 FEET (MPH) - ENTER 5 IF UNKNOWN .... # 1, WIND DIRECTION (DEGREES FROM) ...................... 8 256 TIMELFROM SHUTDOWN TO RELEASE (HRS) ................ d 1 l
l l 20 of 31 Rev. 3
1 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX -
SUMMARY
REPORT . NO2LE GAS RELEASE RATE.................... = 4.855E 05 (UCI/SEC) IODINE RELEASE RATE ......................-= 9.728E 04 (UCI/ SECT RATE OF-INCREASE OF IODINE ACTIVITY ...... = 9.350E 06 (CPM / MIN) DISTANCE FROM VENT XU/Q WB DOSE THY DOSE TIME FOR PLUME TO (METERS) (MILES) (1/M2) (MREM /HR) (MREM /HR) TRAVEL DIST (MIN.)
========================================================u..========
MEA- 1270. 0.79 2.263E-04 9.775E 01 1.390E 05 47.4 ETA = 18:47 3218. 2.00 1.036E-04 3.672E 01 6.248E 04 120.0 ETA = 19:59 5500. 3.42 5.447E-05 1.522E 01 3.220E 04 205.1 ETA = 21:25 LP2- 8045. 5.00 3.319E-05 7.107E 00 1.922E 04 300.0 ETA-= 22:59 10000. 6.22 2.478E-05 4.340E 00 1.414E 04 372.9 ETA = 0:12 13000. 8.08 1.733E-05 2.262E 00 9.681E 03 484.8 ETA = 2:04 EPZ- 16000. .9.94 1.301E-05 1.305E 00 7.132E 03 596.6 ETA = 3:56 ENTER DISTANCE FOR ADDITIONAL CALCULATIONS (METERS) OR' ENTER # OF 15 MIN DOSE PROJECTIONS DESIRED (<100) ENTER 0 TO STOP - ENTER <CR) ALONE TO BEGIN AGAIN....# 0 21 of 31 Rev. 3
iJ . l IODINE RELEASE RATE KNOWN ATTACHMENT.9 EMERGENCY PROCEDURE - EFFLUENT DOSE CALCULATION: EP IV-113 22 SEP 1983 9:30:47 OPERATOR'S INITIALS -. ENTER <CR) ALONE TO STOP .........'...' # KG INDICATE TYPE OF RELEASE FOR'THIS CALCULATION
- 1. ELEVATED RELEASE - PLANT VENT
-2. GROUND RELEASE UNMONITORED -
- 3. GROUND RELEASE - CONTAINMENT LEAKAGE
~4. GROUND RELEASE - PLANT VENT
.................................. # 4
' ENTER TIME FOR METER READINGS (MILITARY TIME - HRMN)
YOU MUST ENTER 4 DIGITS (E.G. 0945) ........ # 1800 FOR THE SAKE OF INTEGRATED DOSE CALCULATIONS IN THIS THE FIRST METER READING IN'THIS SERIES (Y/N) ........... #Y UNIT NUMBER (1 OR 2) ............................... # 1,
.IF AVAILABLE ENTER NOBLE GAS RELEASE RATE (UCI/SEC)
OTHERWISE ENTER -1 ......................... # -1 IF AVAILABLE ENTER IODINE RELEASE RAT.S (UCI/SEC) OTHERWISE. ENTER -1 ......................... # 6E2 LOW ~ RANGE GASEOUS RELEASE RATE - METER 1R-41C (CPM) IF OFFSCALE OR INOPERABLE ENTER -1 ......... # 4E5 PLANT VENT FLOW RATE (CFM) IF VALUE UNATTAINABLE ENTER 125000 ......... # 68000 ELEVATION FOR WIND SPEED & TEMPERATURE READINGS (FEET)
..........................(33 OR 150 OR 300)
- 150
-TEMP (IS0') - TEMP (33') - DELTA T (DEG C) .......... 4 .5 WIND SPEED @ 33 FEET (MPH) - ENTER S IF UNKNOWN .... # 1 l WIND DIRECTION (DECREES FROM) ...................... # 256 TIME FROM SHUTDOWN TO RELEASE (HRS) ................ 4 1 22 of 31 Rev. 3
~XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
SUMMARY
REPORT NOBLE GAS RELEASE RATE ................... = 8.024E 05 (UCI/SEC) IODINE RELEASE RATE ...................... = 6.000E 02 (UCI/SECL RATE OF INCREASE OF IODINE ACTIVITY ...... = 9.350E 06 (CPM / MIN) DISTANCE FROM VENT XU/Q WB DOSE THY DOSE TIME FOR PLUME TO (MiETERS ) (MILES) (1/M2) (MREM /HR) (MREM /HR) TRAVEL DIST (MIN)
===================================================================
MEA- 1270. 0.79 4.154E-05 2.966E 01 1.573E 02 47.4 ETA = 13: 47 3218. 2.00 .1.029E-05 6.027E 00 3.827E 01 120.0 ETA = 19:59 5500. 3.42 4.503E-06 2.000E 00 1.642E 01 205.1 ETA = 21:25 LPZ- 8045. 5.00 2.496E-06 8.834E 01 8.915E 00 300.0 ETA = 22:59 10000, 6.22 1.780E 5.151E 01 6.264E 00 372.9 ETA = 0:12 13000. 8.08 1.183E-06 2.553E 01 4.078E 00 484.8 ETA = 2:04 EPZ- 16000. 9.94 8.564E-07 1.420E 01 2.896E 00 596.6 ETA = 3:56 ENTER DISTANCE FOR ADDITIONAL CALCULATIONS (METERS) OR ENTER 9 OF 15 MIN DOSE PROJECTIONS DESIRED (<100) ENTER 0 TO STOP - ENTER <CR> ALONE TO BEGIN AGAIN....# 0, 23 of 31 Rev. 3
.i
NOBLE GAS RELEASE RATE KNOWN ATTACHMENT 10 EMERGENCY PROCEDURE - EFFLUENT DOSE CALCULATION: EP IV-ll3 22 SEP 1983 9:33:56 OPERATOR'S INITIALS - SNTER <CR) ALONE TO STOP ........... # KG
. INDICATE TYPE OF RELEASE FOR THIS. CALCULATION
- 1. ELEVATED RELEASE - PLANT VENT
- 2. ' GROUND RELEASE - UNMONITORED
- 3. ' GROUND RELEASE - CONTAINMENT LEAKAGE
- 4. GROUND RELEASE - PLANT VENT
.......................... # 4, ENTER TIME FOR METER READING (MILITARY-TIME - HRMN)
YOU MUST ENTER 4 DIGITS (E.G. 0945)........ # 1800 FOR THE. SAKE OF INTEGRATED DOSE CALCULATIONS IS THIS THE
'FIRST METER READING IN THIS SERIES (Y/N) .......... # Y UNIT NUMBER (1 OR 2) .............................. # 1,
.IF AVAILABLE ENTER NOBLE GAS RELEASE RATE (UCI/SEC)
OTHERWISE ENTER -1 ........................ #.8E5 IF'AVAILABLE ENTER IODINE RELEASE RATE (UCI/SEC) OTHERWISE ENTER -1 ....................... 4 -1, INITIAL IODINE RELEASE RATE - METER 1R-41B (CPM) IF OFFSCALE OR INOPERABLE ENTER -1 ........ # 30, FINAL IODINE RELEASE RATE - METER 1R-41B (CPM) IF OFFSCALE OR INOPERABLE ENTER -1 ........ # 1300 ELAPSED TIME BETWEEN IODINE READINGS (MIN) ........ # 5 PLANT VENT FLOW RATE (CFM) IF VALUE UNATTAINABLE ENTER 125000 ........ # 68000 ELEVATION FOR WIND SPEED & TEMPERATURE READING (FEET)
............... .......(33 OR 150 OR 300) # 150 TEMP (.150') - TEMP (33') - DELTA T (DEG C) ......... # .5 WIND SPEED @- 33 FEET (MPH) - ENTER 5 IF UNKNOWN ... # 1, WIND DIRECTION (DEGREES FROM) ..................... # 256 TIME FROM SHUTDOWN TO RELEASE (HRS)................ # 1, 24 of 31 Rev. 3
XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
SUMMARY
REPORT , NOBLE GAS RELEASE RATE ................... = 8.000E 05 (UCI/SEC) IODINE RELEASE RATE ...................... = 2.643E 00 (UCI/SEC) RATE OF INCREASE OF IODINE ACTIVITY ...... = 2.540E 02 (CPM / MIN) DISTANCE FROM VENT XU/O WB DOSE THY DOSE TIME FOR PLUME TO (METERS ) (MILES) (1/M2) (MREM /HR) (MREM /HR) TRAVEL DIST (MIN)
===================================================================
MEA- 1270. 0.79 4.154E-05 2.957E 01 6.930E 01 47.4 ETA = 18:47 3218. 2.00 1.029E-05 6.000E 00 1.686E 01 120.0 ETA = 19:59 5500. 3.42 '4.503E-06 2.074E 00 7.230E 02 205.1 ETA = 21:25 LPZ- 8045. 5.00 2.496E-06 8.808E 01 3.926E 02 300.0 ETA = 22:59 10000, 6.22 1.780E-06 5.136E 01 2.759E 02 372.9 ETA = 0:12 13000. 8.08 1.183E-06 2.546E 01 1.796E 02 484.8 ETA = 2:04
-EPZ- 16000. 9.94 8.564E-07 1.415E 01 1.275E 02 596.6 ETA = 3:56 ENTER DISTANCE FOR ADDITIONAL CALCULATIONS (METERS)
OR ENTER i OF 15 MIN DOSE PROJECTIONS DESIRED.(<100) ENTER 0 TO STOP - ENTER <CR) ALONE TO BEGIN AGAIN....# 0, HIT CTRL P TO EXIT JOB STREAM
> BYE 10
.GNED OFF '
25 of 31 Rev. 3
INTEGRATION PERFORMED ATTACHMENT 11 EMEPGENCY PROCEDURE - EFFLUENT DOSE CALCULATION: EP IV-113 22 SEP 1983 8:33:16 OPERATOR'S INITIALS - ENTER <CR> ALONE TO STOP ........... # JC INDICATE TYPE OF RELEASE FOR THIS CALCULATION
- 1. -ELEVATED RELEASE - PLANT VENT
- 2. GROUND RELEASE.- UNMONITORED
- 3. GROUND RELEASE.- CONTAINM'ENT-LEAKAGE
- 4. GROUND RELEASE - PLANT VENT
.............................. # 4
~ ENTER TIME FOR-METER READING (MILITARY TIME - HRMN)
YOU MUST ENTER 4 DIGITS (E.G. 0945) .......... # 0800 FOR THE SAKE OF ~ INTEGRATED DOSE CALCULATIONS IS THIS
'THE.FIRST METER-READING-IN THIS SERIES (Y/N) ......... # j[
UNIT NUMBER (1 OR 2).................................. # 1, IF AVAILABLE ENTER NOBLE GAS RELEASE RATE (UCI/SEC) OTHERWISE ENTER -1 ........................... # 7E6 IF AVAILABLE ENTER IODINE RELEASE RATE (UCI/SEC) OTHERWISE ENTER -1 ........................... # 8E2 PLANT VENT FLOW RATE ~(CFM) IF VALUE-UNATTAINABLE ENTER' 125000 ........... # 70000 ELEVATION' FOR WIND SPEED & TEMPERATURE READINGS (FEET)
..........................(33 OR 150 OR 300) # 150
~
TEMP (150') - TEMP (33')~- DELTA T (DEG C) ............. # -l WIND SPEED @ 33 FEET (MPH) - ENTER 5 IF UNKNOWN ...... # 1 WIND DIRECTION (DEGREES FROM) ... 4 ................... # 0, TIME FROM SHUTDOWN TO RELEASE (HRS) .................. # 0 i l 26 of 31 Rev. 3
- "c XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
.XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX i j
1 l
SUMMARY
REPORT ' NOBLE GAS RELEASE RATE ................... = 7.000E 06 (UCI/SEC) IODINE RELEASE RATE ...................... = 8.000E 02 (UCI/SECJ RATE OF INCREASE OF IODINE ACTIVITY ...... =.0.000E-01 (CPM / MIN) DISTANCE FROM VENT XU/O WB DOSE THY DOSE TIME FOR PLUME TO ( METE RS ) - (MILES) (1/M2) (MREM /HR) (MREM /HR) TRAVEL DIST (MIN)
===================================================================
MEA ~ 1270. 0.79 9.911E-06 7.234E 01 5.086E 01 47.4-ETA = 3:47 3218. 2.00 2.028E-06 1.221E 01 1.021E 01 120.0 ETA = 9:59 !- 5500. 3.42 8.082E-07 3.852E 00 3.984E 00 205.1 ETA = 11: 25 LP2- 8045. 5.00 4.204E-07 1.536E 00 2.028E 00 300.0 ETA = 12:59 10000. 6.22 2.893E-07 8.615E 01 1.374 E 00 372.9 ETA = 14: 32 13000. 8.08 1.842E-07 4.048E 01 8.559E 01 484.8 ETA = 16:04 EP2- 16000. 9.94 1.289E-07 2.138E 01 5.870E 01 5'6.6 9 ETA = 17:56 ENTER DISTANCE FOR ADDITIONAL CALCULATIONS (METE RS ) OR ENTER # OF 15 MIN DOSE PROJECTIONS DESIRED (<100) ENTER 0 TO STOP - ENTER <CR) ALONE TO.BEGIN AGAIN....# W p l l 27 of 31 Rev. 3 l _ _ . _ _ _ _ _ _ _ _ _ _ _ _
4 INTEGRATION PERFORMED ATTACHMENT 11 (CONT'D) EMERGENCY PROCEDURE - EFFLUENT DOSE CALCULATION: EP IV-113 22 SEP 1983:8:42:16 OPERATOR'S. INITIALS . ENTER <CR> ALONE TO STOP ........... # JC, INDICATE TYPE'OFERELEASE FOR THIS CALCULATION . lJ. ELEVATED-RELEASE - PLANT VENT
-2; GROUND RELEASE.- UNMONITORED
.3. GROUND RELEASE - CONTAINMENT LEAKAGE 4.- GROUND RELEASE - PLANT VENT-
.'............................. # 4,
- ENTER TIME FOR METER READING (MILITARY TIME - HRMN)
YOU'MUST ENTER 4 DIGITS (E.G. 0945) .......... # 0815 FOR THE SAKE OF INTEGRATED DOSE CALCULATIONS IS THIS
.THE FIRST METER READING IN THIS SERIES (Y/N) ......... 4 N UNIT NUMBER (1 OR 2)';............................. ... # 1 IF AVAILABLE ENTER NOBLE GAS RELEASE RATE (UCI/SEC)
OTH ERWI S E ENTE R - 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . # 9E6 IF AVAILABLE ENTER IODINE RELEASE RATE.(UCI/SEC) OTHERWISE ENTER -1 ........................... # 2E3 PLANT VENT FLOW RATE'(CFM) IF VALUE UNATTAINABLE ENTER 125000 ........... # 70000
' ELEVATION FOR WIND' SPEED & TEMPERATURE READINGS (FEET)
..........................(33 OR 150-OR 300) # 150 I
TEMP (150') - TEMP (33').- DELTA T (DEG C) ............. # -l WIND SPEED 9 33 FEET (MPH) - ENTER 5 IF UNKNOWN ...... d 1 WIND. DIRECTION (DEGREES FROM) ........................ # 0 TIME FROM SHUTDOWN TO RELEASE (HRS) .................. # 0 28 of 31 Rev. 3
XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX,XXXXXXXXXX
SUMMARY
REPORT , NOBLE GAS RELEASE RATE ................... = 9.000E 06 (UCI/SEC) IODINE RELEASE RATE ...................... = 2.000E 03 (UCI/SEC-) RATE OF INCREASE OF IODINE ACTIVITY ...... = 0.000E-01 (CPM / MIN) DISTANCE FROM VENT XU/Q WB DOSE THY DOSE TIME FOR PLUME TO (METERS) (MILES) (1/M2) (MREM /HR) (MREM /HR) TRAVEL DIST (MIN)
..==================================================================
MEA- 1270. 0.79 9.911E-06 9.301E 01 1.272E 02 47.4 ETA = 9:02 3218, 2.00 2.028E-06 1.570E 01 2.552E 01 120.0 ETA = 10:14 5500. 3.42 8.082E-07 4.953E 00 9.959E 00 205.1 ETA = 11:40 LPZ~ 8045. 5.00 4.204E-07 1.975E 00 3.069E 00 300.0 ETA = 13:14 10000. 6.22 2.893E-07 1.108E 00 3.434E 00 37 2. 9 ETA = 14 : 27 13000. 8.08 1.842E-07 5.204E 01 2.140E 00 484.8 ETA = 16:19 EPZ- 16000. 9.94 1.289E-07 2.749E 01 1.468E 00 596.6 ETA = 18:11 ENTER DISTANCE FOR ADDITIONAL CALCULATIONS (METERS ) OR ENTER # OF 15 MIN DOSE PROJECTIONS DESIRED (<100 ) ENTER 0 TO STOP - ENTER <CR> ALONE TO BEGIN AGAIN....# 12 l l l l ! 29 of 31 Rev. 3 i
~ _ . - - ..
INTEGRATION OF DOSES AND RELEASE RATES -MEA-
* ~
TIME.'
' TOT WBLDOSE TOT. THY DOSE- NOBLE GASES IODINE PROJ/ CALC
.. (MR)' .(MR) (UCI) (UCI)
.815. 1.808E 01 1.272E Olt 1.750E 06 2.000E 02 CALC
.830.- 4.134E 01 .4.452E-01' 4.000E 016 7.000E 02 ~ PROJ 845. 6.459E 01 7.630E 01 6.250E 06 -1.200E 03 PROJ 1900. 8.7$4E 01. 1.081E.02. 8.500E 06 1.700E 03 -
PROJ
-915.- 1.lllE 02 1.399E 02. -1.075E 07- 2.200E 03 PROJ 1930. 1.343E 02 1.717E 02 1.300E 07 '2.700E 03 PROJ 945s -1.576E.02 2;035E 02 '
1.525E'07 3.200E 03 PROJ: 1000.- 1.808E 02 2.352E 02 1.750E 07 -3.700E 03 PROJ
-1015.< 2.041E 02 2.670E 02 -1.975E 07 4.200E 03' PROJ
- 1030
;2.273E-02 2.988E.02 '2.200E 07- 4.'/00E 03 PROJ 1045. 2.506E 02 3.306E 02 2.425E 07 5.200E'03 PROJ 1100 2.739E 02 3.624E 02 2.650E 07- 5.700E 03 -PROJ 11115. 2.971E 02 3.942E 02. 2.875E 07 6.200E 03 PROJ INTEGRATION OF DOSES AND RELEASE RATES -LPZ -
- TIME' TOT.WB DOSE TOT THY DOSE NOBLE GASES IODINE PROJ/ CALC
. (MR ) - (MR) -(UCI) (UCI) 815. 3.840E 01 5.069E Oil 1.750E 06 2.000E 02 CALC 830. 8.776E 01- 1.774E 00- 4.~000E 06 7.000E 02 PROJ P*5.. 'l'.371E 00 3'.042E 00 6.250E 06- 1.200E 03 PROJ
. 1.865E 00 4.309E 00 8.500E 06 1.700E 03 PROJ
, ' 915. : 2.359E 00 - 5.576E 00 1.075E 07 2.200E 03 PROJ 930. 2.852E 00 6.844E 00 1.300E 07 2.700E 03 PROJ 945. 3.346E 00 8.lllE 00 1.525E 07 3.200E 03 PROJ 1000. 3.840E 00 9.378E 00 1.750E-(T7 3.700E 03- PROJ 11015. 4.333E 00 1.065E 01 1.975E-07 4.200E 03 PROJ 1030.: -4.827E 00 ~1.191E 01 2.200E.07 4.700E 03 PROJ 1045. 5.321E 00 1.318E 01 2.425E 07 5.200E 03 PROJ
;1100 5.814E 00 1.445E 01 2.650E 07 5.700E 03 PROJ 1115. 6.308E 00 1.572E 01 2.875E 07 6.'200E 03 PROJ
, 30 of 31 Rev. 3
1 INTEGRATION OF DOSES AND RELEASE RATES -EPZ-TIME TOT WB DOSE TOT THY DOSE NOBLE GASES IODINE PROJ/ CALC
.(MR) (MR) (UCI) (UCI) 815. 5.345E 02- 'l.468E 01
-l.750E 06 2.000E 02 CALC 830. 1.222E 01 5.137E 01 4.000E 06 7.000E 02 PROJ 845. 1.909E 01 8.086E 01 6.250E 06- 1.200E 03 , .PROJ 900. 2.596E 01 1.247E 00 .8.500E 06 1.700E 03 PROJ 915. 3.283E 01 1.614E 00 -1.075E 07 2.200E 03- PROJ 930 3.971E 01 1.981E 00 1.300E 07 2.700E 03 PROJ 945. 4.658E 01 2.348E 00 1.525E 07 3.200E 03 PROJ 1000 5.345E 01 2.715E 00 1.750E 07 3.700E 03 PROJ 1015. 6.032E 01 3.082E 00 1.975E 07 4.200E 03 PROJ
-1030. -6.720E 01 3.449E 00 2.200E 07 4.700E 03 PROJ 1045, 7.407E 01 3.8168 00- 2.425E 07 5.200E 03 PROJ 1100. 8.094E 01 4.183E 00 2.650E 07 5.700E 03 PROJ 1115, 8.781E 01 4.550E 00 2.875E 07 6.200E 03 PROJ ENTER DISTANCE FOR ADDITIONAL CALCULATIONS (METERS )
OR ENTER # OF 15 MIN DOSE PROJECTIONS DESIRED-(<100) ENTER 0 TO STOP - ENTER <CR) ALONE TO BEGIN AGAIN ...... # 0, i t-l l l l 31 of 31 Rev. 3
/ ..,
EP IV-ll4
'b EMERGENCY PROCEDURE EP IV-114 COMPUTERIZED DOSE CALCULATIONS ON PROGRAMMABLE CALCULATOR (TI-59)
ACTION LEVEL This procedure may be used in lieu of the manual dose calculation
" procedures.
- RESPONSIBLE INDIVIDUAL An individual' familiar with the Texas Instruments TI-59
~
programmable calculator (normally a Shift RPT or EUF assessment team member) . ACTION STATEMENTS PART A DOSE CALCULATIONS FOR PRE-SELECTED LOCATIONS (MEA, LP2, EP2, OR 5.5 10, AND 13 Km LOCATIONS)
- 1. Contact the Control Room (or TSC) and obtain the necessary information for'the respective unit. This information can be compiled onto the Dose Assessment Data sheet ( Attachment 3, EP IV-ll2).
WIND SPEED (mph) WIND DIRECTION (degrees, _from) DELTA TEMPERATURE ( AT , 'C) TIME FROM START OF INCIDENT (hrs) NOBLE GAS MONITOR (cpm) - Unit 1 (lR-41C); I Unit 2 (2R-41C) HIGH RANGE MONITOR (mR/hr) - R-45/R-43 l INITIAL READING FROM IODINE MONITOR (cpm) - Unit 1 (IR-41B); Unit 2 (2R-41B) ! FINAL (OR MOST RECENT) READING FROM IODINE MONITOR (cpm) - Unit 1 (lR-41B); Unit 2 (2R-41B) l TIME BETWEEN READINGS ON IODINE MONITOR (minutes) _ Unit 1 (IR-41B); Unit 2 (2R-41B) l 1 of 27 Rev. 1
. 1 EP IV-Il4
.(, PART A (continued) ;
- 2. Prepare. programmable calculator TI-59.for use: ,
. a)-Lock TI-59 calculator securely into printer cradle (PC-100).
.b) Turn printer power on, then turn calculator power on.
c) Select the Salem 1 or 2 (appropriate) MET-RMS-DOSE ,- calculation cards (two cards - three sides) for the distances of' interest (i.e., MEA, LP2, EPZ or 5.5, 10.13 Km). d) Prior to card reading, press 3,Og-(2nd tier) 11. (The number 719.29 should appear on display.) Then press CLR. Press CLR before reading any card side. e) Read all appropriate program card sides (cards are to be inserted into slot on right hand side of TI-59). This program is contained on three (3 ) sides of two (2) cards. If the calculator display blinks follow.ng the attempt to read the cards, the' card has not bee'n raad. Press CLR and reinsert this card side until number des ignated of card side is shown on display without flashing. f) Af ter reading all appropriate program cards,
. initialize calculator by pressing 2nd A.
I
- 3. RUN DATA ON PROGRAM (see example - Attachment 1) .
a) Enter wind direction from which the wind blows (degrees i_ l AZIMUTH), then press A. l NOTE l The direction the wind blows towards will also automatically printout. l 2 of 27 Rev. 1
y
~~
l '1 EP.IV-114 PART A (continued) i b) Enter the wind speed (mph) then press R/G. . c)' Enter station delta temperature L&T), then ' press R/S. ,
- d) Select type of release,. Press O for ground level release 1 or 1 for elevated release (plant vent), then press R/S.
NOTE The calculator will now pause for 5.to : 10 seconds anc then print three numbers with exponents representing the X/Q values V-for the three program distances (i.e., MEA,
,y- LPZ, and EPZ).
e) Following this calculator printout, enter the plant vent flow rate in cubic feet per minute (cfm), then-press B.
' (Default value for flow rate is- 125,000 cfm).
f)' Select type of data to be introduced: for low range vent monitors or FSAR Design _ Basis Accident (DBA), enter 0; for , hich-range monitors, press 1, then press R/S. 9) 1.- If ~0 (zero) is' selected above enter the appropriate Noble Gas Monitor reading (cpm), or DBA cpm equivalent then press R/S. DBA (design basis accident) classes and epm equivalents are given in Attach =cnt 5.
- 2. If one (1) is selected above, enter reading from R-45 as actually read on the instrument (uci/cc), then press R/S. Next, enter one (1) then press R/S. If R-45 is out of order, enter mr/hr reading from R-43 as read 'frem the monitor and press R/S. Next, enter the R43 concentration conversion factor from attachment 4 and press R/S.
- t!
3 of 27 Rev. 1 g e-+ - -
-w g- nr- r r +- +t 3----w- y 4 yg - ---e' we he - * * + + - %*-- ~~'+w"w* * * * * ' + - * * + - * - * " * ' ' * * * = ' " * * * " * ' - * " " ~ " - ' - ' - ^ - - " -
*t u
. 7 ; ,. _.-
*EP-IV-114 Is '
PART A (continued)- h) Enter the initial iodine monitor reading (cpm),.or 0 for DBA cpm equivalent, then press R/S. ,' ' i) Enter the latest iodine monitor' reading (cpm), then press R/S. If.off-scale, use DBA default values - these defaults
- can be used with R-45 readings (see Attachment 5 for DBA default values).
j) Enter the amount of time lapse .(delta time) between the iodine monitor reading time ( to) and latest reading time (ti)_in minutes, then press R/S. NOTE For DBA default or zero readings use one (1) minute.. k) After. calculator finishes printing (eight lines of numbers in exponential form taking 10 to 20 seconds), enter the appropr'iate. Noble Gas Doso Rate Conversion Factor (DRCF) for MEA. See Attachment 2 for decay time versus factor graphic. After entering this factor, press C. NOTE The eight lines of output represent Noble Gas and iodine source terms and calculated concentrations (see Attachment 1).
- 1) Enter the appropriate Iodine Dose Rate Conversion Factor for MEA (see Attachment 3), then press R/S.
m) Enter the appropriate Noble Gas DRCF for LPZ (Attachment 2), then press R/S. n) Enter the appropriate Iodine DRCF for LPZ ~(Attachment 3), then press R/S. 4 of 27 Rev. 1 1 - . - . - -
. -~
EP IV-ll4 PART A (continued) o) Enter-the appropriate Noble Gas DRCF for EPZ (Attachment 2),
~
then press R/S. ., p) Enter the appropriate Iodine DRCF for EPZ (Attachment 3),
- then press R/S. ,
q) This completes the dose calculation program, (e.g., the dose rates for whole body and thyroid are printed out for the MEA, LPZ, and EPZ). To reinitialize calculator, press CLR, then press 2nd A. To sign off, press CLR and then turn off calculator first and then the printer. NOTE L
- 1. Be sure to partition (3 OP 17) before reading cards.
i
- 2. Be sure that all card sides are read properly.
- 3. Be sure to initialize calculator (2nd A) before data entry.
- 4. ALL KEYBOARD ENTRIES REQUIRE CLOSING STATEMENT: THIS STATEMENT IS R/S for all entries except wind direction (press A), plant vent flow rate (follow with B), and the Noble Gas Dose Rate Conversion Factor for MEA (thenpressl C).
l l l l 5 of 27 Rev. 1 l
J e
. i, EP IV-ll4 Attachment l' ATTACHMENT 1
- EXAMPLE PROBLEM FOR TT-94 CALCULATIONS
- EXAMPLE .
GIVEN: a) Meteorological data is as'follows: wind direction (from) = 230' at 300' Elevation wind spee,d = 1 aph Adr = 0. 5 'C b) Unit 1 Containment monitor IP41B reads 1500 cpm now. Five ninutes ago, this monitt- 's reading 50 cpm. c) Plant vent flow rate = 68,000 cfm d) Monitor 1R-41C reads 500,000 cpm e) Reactor has been shut down for two hours b SOLVE: a) What are the whole body and thyroid dose rates for L the' MEA, LPZ, and EPZ distances. ANSWERS: (mrem /hr) DISTANCE WHOLE BODY THYROID l M*4 A 32.5 0.792 - LPZ l.54 0.071 EPZ .253 0.023 l L 6 of 27 Rev. 1 i
PRINTOUT POR EXAMPLE PRUALEM (TI-59)
., g TI-59 PRINTOUT OUTPUT UNITS olanation RI,ggg, Units f,
- 32. cind direction 230 (e)
(fron) a
- 50. Wind direction (towards) ,
(*)
- 33. cind speed M 1. . (mph) -
- 33. A temperature M -0.5 (*C) l 3d. C1;vated release M 1.
(sec/m ). 7.8963851-05 MEA R/O 7.0963851-06 LP2 X/Q (sec/m i 2.729062F 06 EP2 X/Q (sec/m ) 3e. ctction vent flow 1 68000. (cfm) 32096000. Vent flow (in ec/sec) 3f. Iow range monitor Choice M 0. 5.05 (epm) 3g. nob! gas monitor M 3h. initial iodine
- 50. (cpm) monitor reading M
- 31. current iodine (cpm) monitor reading M 1500.
- 33. delta time between 5.
i 11ne readings M (uinutes) 1.003 06 Noble Gas Source (uCi/s c) 2.969201 00 Iodine *ource Ter:n (uci/s c) 7.9*70743 U1 NG-MEA conc. (uCi/m ) 7.9200743 00 NG=LP2 conc. (uC1/m ) 2.7372495 00 NG-EP2 conc. (uC1/m ) 2.3445954-04 I-MEA conc. (uct/m ) 2.3445954-05 1-LP2 conc. (uCi/m ) 8.1031343-06 3-EP2 conc. (uCi/m ) 3k. MEA dose rate conv. C .34 (-) fastor-Noble Gss (NG)
- 31. MEA dose rate cony. M 2780. (-)
f 0stor-iodine 3m. LP2 dose rate conv. M .17 l-) factor-Noble Gas c) 3a. LP2 dose rate conv. M 2650 fcctor-iodine
- 32. EP2 dose rate cony. M 08 (-)
fMtor-Noble Gas 3p. EP2 dose rate conv. R/S 2520 (-) f0stor-iodine 26.92825251 WB Dose Rate MEA (arem/hr)
.6517975252 Thyrcia Dose Rate MEA inrem/hri 1.346412625 WB Dost Rate LPZ (arem/hr!
.0621317788 Thyroid Dose Rate LP2 (arem/hr)
.2189799571 WB Dose Rate EP2 (arem/hr)
.020419"A85 Thyroid Dose Rate EP2 (arem/hr) 7 of 27 Rev. 1
O.8 m M llLE C^.5 L.
- F D L L O W I N G S H tt f O c W I :
,,,NASED OH EPA-520/1-75-003 3 3200 NW THERM 4L AT E4Wf LISAttM ;g Hb7Ee IHOROUTH OF GASEOUS DAUGHTERS INCLUDED IN Do8E ftATES '
0.5 -
- ; . A. Tine fran shutdown to time of release in hours =
hr. j B. Time for transport = (Desired Distance)/(wind speed) l N l g ( mi)/1 aph) =
/ 9.4 hr C. Total decay time = (Step A).+ (Step Bl N
) N I I+I I "
/- hr g D. Correlate the total decay time (hours following shutdown)
C to the curves to determine the dose corwarston factors 3 0.3 - for Noble Gas. i k / M i* 5 3 .- l 0.2 - l - i l 0.1 - l' i
>n d *'*
. U" j
O.0 o I' 10 I*' I I --.I- I I. - l 1 I I 20 30 40 50-u ! I 60 [ TOTAL DECAY TIME - HOURS - i . l l
O .* i Heatt ens sACF FOLLOWING s1alteousi 1 anneneun vauerenssa> i . HOURS BRCF fl0URS HCDRCF HOURS HG'DRCF - HOURS HCDRCF il ***** ***x** ***** ****** ***** ****** ***** ****** ~ 0 .528 16 .0552 31 .0319 46 .0284 ! 1 .457 17 .0512 32 0315 47 .6283 ! 2 .389 18 .0479 33 .6311 48 .6282 i 3 .329 19 .0451 34 .6308 49 .6281 1 ! 4 .2?? 20 .0428 35 .0305 50 .628 5 .234 21 .0409 36 .0302 51 .6279 i
- 6 .197 22 .0393 37 .0299- 52 .6278 7 .168 23 .0379 -
38 .0297 53 .0278 ' i A 8 .143 24 .0367 39 .0295 54 .6277 i 9 .123 25 .0357 40 .0293 55 .6276 l 5 le .107 26 .0349 41 -
.0291 56 .0276 i 11 .6932 27 .0341 42 .6289 57 .0275 i 12 .0823 . 28 .0335 43 .0288 58. .0275 l 13 .0733 29 .0329' - - 44 .0287 59 .0274
! 14 .0GG1 30 .0324 ' ' 45 - .0285 60 .0274 j 15 .0G01 . r, - ' - . i A. Time froa shutdown to tiene of release in hours . = { , hr ym ao l m. v1.se for transport = foesired Distancel/(wind speedl a m ( ell /t ophi = hr N - l C. Total decay tlue = (Step Al.+ (Step B) . I ) +t i = hr ! D. correlate the total decw.y tisse thours following shutdo6ml . j . . to the curves to detonaine the dose cowersion factore - { t for Hoble Gas. An- - _ _ _ _ _ _ _ _ _ _ _ _ . _ - _ _ _ _ _
. Att, *. _
Attr~~ w t 3 r , 10eINE DRCF FCs Atlet REACTOR SHUThouN "9ASES ON EPA-580/8-75-0083 380 0 000 THERft4L AT EOUILIBRItSt 1, , 8900 BNCF'S FR0il REG OUIDE 1.1093 NORMALI2ED TS I-131 CONC .0F 1 WCI/ftt$3 I-TOT BRCF=8988.8-(50.08987)+(t.ST8387388)-40.04003587883)
, _ +(5.34SSE-48T*84l-(8.3757E-05T*85) l -
N 8700 - N E . V-TOT BRCFs HORMALIZED TO 1 UCI/M883 1-131 - ' l $8800 - 1 g i g A. Time fram shutdown to thee ~ i /E600 - of release in houre = h: U U B. C Time for transport = (Desired ! % I8400 - Distance)/(Wind speed)
'j
/ ( mi)/I sph) = 1 hr i N I
- c. Total decay time = (step A)
*8300 -
+ step a) i )+( ) "
ha
- 8800 - .
Correlate the total decay thee (hoasts i following shutdown) to the curves to determine the dose conversion .factora 8100 - 2000 -
> tv 1900 O
'"--*I"'I I I I I I I I- I I I N
{ 90 20 30 40 E 50 SO .*E TOTAL DECAY TIME - IlOURS O ' j . . l 4 . I 1
5 0 l - 1 I-YeY BRCF (NMH44R/tlCI/ftss33 BASED 308 I-831 UERSUS 7I81E . t (hdEll/6Wl/(48CI/ns833
- HOUR $ bRCf HOURS DRev MOURS 9RCF 1 asssa Bassssa sassa asssses assus asasses i e. ED3G.4 21 2336.2 41 Rie7.3 1 2H79.6 22 2320.4 42 210e 4
2 2831 23 2305.2 i 3 2787.8 24 43 2092.5 2290.6 44 2445.1 4 2748.5 25 2276.5 S 2712.2 26 45 2078.1 2262.9 45 2071.2 G 2679.3 27 a249.9 47 j 7 2E4G.6 2064.6 25 2237.3 43 2058.2 i S 2816.7 29 2225.1 l 9 2599.4 49 2051.9 g 16 34 2213.4 50 2445.9 1 ESG1.6 31 2202 51 ! o 11 253G.1 2044.1 12 32 2191.1 52 2034.4 2511.9 33 2180.G 53 2023.9 u 13 2488.7 34 2170,J 54 14 246G.7 2023.6 35 2860.5 55 201s.5 4 15 2445.S 36 2151: 56 2013.5 ! 16 2435.4 37 2141.7 57 I 17 2406 200s.7 38 2132.3 Sa 2444 ! le 2387.5 39 2124.2 59 1999.4 j 19 23G9.7
- 40 2115.9 EG 1995 i ad 2352.8 .
I 1 A. Tkao from shutdow to tlana of release in hours . = . he h5 B. Tbum for transport = (Desired DistancelflWind Speed) ; 1 l 6 mo/I = phi " he "E C. Total dacey time u (Step Al'+ IStep 89 4 ( ) +l I " hr D. correlate the total decay thee thours following shutdowsd to the curves to dete witne the done coswersion factorm for r dene. o 1
EP IV-114 ATT. 4 1.w .
.,, 2: o 1 4 g 4
, ,l '
.E se , -
ed O l m en -
"ga E
*p-wM -
~
S k g vs
, f= _
. oI-D,8rr
.E. = -
E "Ea gW IE - o .g. . t 8 .. a. I a3 b
- eg -
2 *8*E 5 2
- e~4 8
e$ "03= b$5 \
-t-7w_
- a w k* 2
.E W '
W 4 f I f
' ' I I I I l --
I
-~..,..$
C e o
,8 6
o 12 of 27 Rev.0
R-43 CALIBRATION FACTOR (MR/HR)/(UCI/CC) HOURS cat. FACT HOURS CALFACT HOURS CALFACT
- ***** ******** ***** ******** ***** ******** HOURS CALFACT t
6 52.009 16 5.4256 1, 45 17 31 3.1342 4G 2.M42 . 5.03 32 3.9939 47 2 38.289 18 4.7834 33 2.7832 3 32.368 3.8577 48 2.773 19 4.4326 34 3.925 49 2.7635 4 27.287 28 4.207 35 2.9953 59 5 23.004 21 4.0181 36 2.7546 6 19.439 2.9683 51 2.7464 22 3.859 37 2.9437 52 i 7 1G.495 23 3.7242 38 2.7388 i 8 14.077 2.9211 53 2.7317 ' 24 3.6093 39 2.9005 54 9 12.097 25 3.5107 48 2.7251 10 10.481 2.8814 55 2.7189 26 3.4255 41 2.8639 56 2.7132
" 11 9.1621 27 3.3515 42 2.8477 57 2.7979 12 14.0868 28 3.2867 43 2.8327
- R 13 7.2094 58 2.7029
' ~29 3.2296 44 2.8189 59 2.6983 u 14 G.4928 30 3.1791 45 15 5.9065 2.8961 68 2.694 l j -
#4
\ ?~ l
#1 5
{ . i l
g EP IV-ll4 i Attachment 5 ATTACHMENT 5 DEFAULT VALUES FOR LOW /HIGH PLANT VENT MONITORS Read the be3cw accident description and determine which case is .' applicable. From the table select the appropriate release rates (cpm). CASE I LOCA A LOCA assuming severe core damage - fuel melting (Regulatory Guide 1.4 assumptions) 100% of Noble Gases and 25% of the iodines contained in the core are assumed released to the containment. The containment initially leaks at the maximum design leak rate. CASE II LOCA Primary coolant leaks at a rate fast enough to increase the temperature of the core to the point where there is damage to the fuel rods. For this case, it is assumed that all the gap activity (the gases contained between the fuel and fuel rod) is released to the containment. The containent is assumed to initially leak at the maximum dcsign leak rate. In this accident, it is up to the Senior Shif t Supervisor or Emergency Duty Of ficer (EDO) to assume that there has been no fuel melting. If there is any question, a Case I LOCA should be assumed. CASE III DECAY TANK RUPTURE This procedure is used only if actual radiological monitoring equip-ment is unavailable for release evaluation (monitors out of service, read off scale, etc.). CASE IV FUEL HANDLING ACCIDENT Any activity occurring as a result of a fuel handling accident is normally drawn into the Fuel Handling Building Ventilation System and vented to the plant vent for release. The process monitors are used to monitor these releases; however, should these monitors De out of service or off scale, this technique is used to evaluate off-site doso. CASE V STEAM GENERATOR TUBE RUPTURE The activity released during a minor tube rupture can be determined using vent monitors and normal procedures. This procedure addresses the steam generator tube rupture as analyzed in the FSAR. This accident is set apart from others because of the inability to consult radiation monitors to determine the activity release rate. Therefore,
.g this is the primary procedure to determine the activity release rate resulting from a system generator tube rupture.
14 of 27 Rev. 1 I i-
lf EP IV-114 Attachment 5 EQUIVALENT NOBLE GAS EQUIVALENT' IODINE
- ACCIDENT CLASS RELEASE RATE CPM' ACTIVITY INCREASE RATE (CPM / MIN)
~
- Unit'l Unit 2 Unit 1 Unit 2 ,
I(l) 2.42 ES- 4.34 E6 9.35 E6 9.73 E6 II(l) 7.82 E2 1.40 E4 1.45 E5 1.51 ES. I III(l) 1.25 E5 2.24 E6 NO RELEASE NO RELEASE , IV(1) . 9.9 E4 . l.78 E6 1.22 E6 1.27 E6 V(2) 1.42 E4 2.54 E5 3.3 E6 3.50 E6 i .
~
(1) Use actual or estimated plant vent flow (cfm) as provided in the procedure. (2) Case V is assumed not-to be released through the plant vent so use a flow of 125,000 cfm for this calculation. t 15 of 27 Rev. 1 4 ,=vo.gr. --- y y em -.-,,=,,.e - 4 %,, %.w-,,--,,,---..e ,,e+m mmwww-.%se.,,,%9.,,---,.e ey v.c-- ,,>-%.,. ,,,-i
~~
l e' EP IV-ll4 s PART B DOSE CALCULATIONS BASED ON RELEASE RATE OR FIELD MEASUREMENT
- (OPTIONAL) FOR ANY LOCATION .'
1.. Contact the Control Room or TSC or EOF field team coordinator, Obtain the necessary information from the respective unit.
- a. Noble Gas Release Rate in. Curies per second (can be calculated from RMS data using Part A of this procedure).
- b. Wind speed in miles per hour (mph),
direction, and stability class.
- 2. Based on the time since shutdown and the plant conditions affecting the release, determine the Noble Gas and iodine dose rate conversion factors (DRCF) from Attachments 6 and 7, and estimate the duration of exposure.
- 3. Prepare programmable calculator TI-59 for use
- a. Lock TI-59 Calculator into printer cradle (PC-100).
- b. Turn printer on, then calculator power on.
- c. Select.the Release Rate Dose Calculation Cards (two s ..ss-three sides).
- d. Prior to card reading, partition the TI-59 by pressing 3 02 (2nd tier) 17. (The number 719.29 should appear on i display.) Then press CLR. Press CLR before reading any card side.
- e. Read all three sides from the two program cards. If the calculator display blinks following the attempt to read the I card side, the card side has not been read. Press CLR and reinsert this card side until number designation of card side is shown on display without flashing.
l l l 16 of 27 Rev. 1
. . ~ , - . . . _ _ . ._.-
7- , EP IV-ll4 ( PART B (continued)
- f. After reading all three (3) card sides, initia'lize calculator by pressing 2nd A.
- 4. Data Entry .
a.. Enter distance in miles for which dose rates and dose commitments are desired and press A (e.g., if dose calculations for a location 10 miles from the station are desired, press 10 A).
- b. Enter appropriate Xu/O (Attachment 11), then press B (program code inserts exponent of 10-6; if Xu/O = 6.1 x 10-6, then simply enter 6.1).
- c. Enter Noble Gas release rate (Qn) in Curies /second (Ci/sec),
then press C.
- d. Enter Iodine release rate (Qi) in Ci/see then press D.
- e. Enter wind speed in miles per hour (mph), then press E.
- f. If available, enter field measured iodine concentration (XI) in Ci/m3 (same as (uCi/cc), then press A' (press 2nd A).
- g. If available, enter field measured whole body dose rate in R/hr, then press B' (press 2nd B). If not available enter I
zero, then press 2nd A.
- h. Enter estimated duration of release in hours and minu 1 l
with decimal point, then press C' (press 2nd C).
- i. Divide value of DRCF for Iodine from Attachment 7 by 1000 tt correct to appropriate units (rem-m3/Ci-hr, and enter this value, then press D' (press 2nd D).
_j. Multiply value of DRCF for Noble Gas frcm Attachment 6 by 10 to correct to appropriate units (rem-m 3 /Ci-hr), and enter this value, then press E' (2nd E). l 17 of 27 Rev. 1
l _:* - 1 l l
- k. EP IV-ll4 PART B (continued) .,
~
- 5. Running Program -
- a. Press R/S and program will run. ,-
'b. Example printout:is.shown on Attachment 8. Initial data entries should first be logged on data log sheet (Attachment 9). Results should be logged onto calculation sheet (Attachment 10).
18 of 27 Rev. 1
~
. Attachment 4 Att. 4 ,
l 9 M J'O F"- C BLE C05 DAct OLLCWING $HNTpop4
- u ,
BASED ON EPA-520/1-75'-00lg 3200 W THERML AT E4dlLf 4AttM L 3 T HOTE: -8 I INGROUTH W GASEGUS DAUGHTERS INCLUDED IN 00$E RATES 4 P . . ! L 0.5 -
~
Y g, yg.ua fran shutdown to time of release in hours - g fI N B. Tisae for transport = (Desired Distance)/(Wind Speed) j sR O.4 ~ ( mit ) / ( mph) = i / C. NN Total decay time = (Step Al .+ (Step B) { ug ( ) +( P: f ) = ! B g hr g D. j E g Correlate the total decay time thours following stutdownl j , R g 0.3 - to forthe Noblecurves Gas.to detenmine the dose conversion factors I B Y 13
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TOTAL DECAY TIME - HOURS 4 ) i 1
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. EP IV-ll4, Att. 6a
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_. Att.*r. - - l J D 3000 ICOINE DNCF F6LL JINO AEACTOR SHlff90UH . 1 SW8EB ON EPA-580/A-75-003 3 3800 till THEftftAL AT EQUILIBRIGIN 2 4 u [ 8900 BftCF*ts FROM REO QUIDE 1.1093 NORMALIZE 8 70 1-131 coNO OF i 490 5 /098 8 3
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- a. Time for transport = (Desired _
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u I , mil /l uph) " hr
- y 1 H
- c. Total decay tima = (step A) j g ,8300 -
+ step a)
{ 0 3 I I+I ) = hr F 8800 - . Correlate the total decay time (hours o following shutdown) to the curves to l R determine the dose conversion factors l 8100 - P A h 8000 - I I8I I I i 1900 L--- I I I I I I I I I' I
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$ TOTAL DECAY TIME - HOURS
' 4 , 0
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i l I-707 DNCF (MWEN/lut/UCI/ MSS 3) BASED ett I-838 'UEASUS TIME . 8 3-(MAEN#8M S/448CI/N883) i HOURS IMCF HOURS DItCF HOURS BACF sasas $sssssa sasas assasse assas assssas j e, 293a.4 21 233s.2 41 a167.3 - '
- 1 2a70.s 22 2320.4 42 2109 l 2 2831 23 2305.2 43 2092.5 l 3 2?u?.s 24 2294.6
- 4 274u.5 25 44 2e55.1 2276.5 45 2078.1 E 2712.2 26 2262.9 i s 2G78.3 27 4G 2071.3
! 2249.9 47 20G4.8 ' 7 2G46.6 as 2237.3 du 2e55.2 . 5 2616.7 29 2225.1 ! 9 49 2451.9 !
" 25su.4 34 2213.4 Se
- to asG1.s 2445.9 3 22e2 5
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11 2536.1 32 2191.4 52 2034.4 i- 12 2511.9 33 2188.5 53 2025.9 l w 13 24Bb.7 34 2170.3 54 2023.6
- 14 2466.7 35 2164.5 15 55 2018.5 l 2445.S 3G 2151 66 2013.5 i 1G 2425.4 37 2141.7 57 2005.7 l 17 243G 35 2132.3
! 18 58 2004 2387.5 39 2124.2 59 1999.4
- 19 2369.7 44 2115.9 l 20 2362.6
- Ge 1995 i
i A. Time frces shutdown to time of release in hours = . hr
.s B. Time for tranuport = (Desired Distancel/twind speed) y
( mil /( mph) = hr 1 C. Total docay tiane = (Step A)'+ (Step BI
- . l.( i =
,, r D. Corrolate the total decay time (hours following shutdown) -
! to the curves to detenweine the dose coswarston factore l f or Iodine . . 1
,. - .~ _ . - - .
. 4:*
- I EP IV-ll4 Attachment 8 ATTACHMENT 8 EXAMPLE PRINTOUT OF DOSE CALCULATIONS BASED ON REL. EASE. RATE
- TIME Distence from Site (miles) 3.00 00 'Al Distance (meters) 4.83 03 A2 Xu/O(1/MgromSite X 10-0) 3.20 00 B-Wind speed (u) in meters /second 2.25 00 C Plume Travel Time (ETA) 2 hrs. min. 360.00-03 D Dispersion X/O (1/m ) 1.42-06 E Iodine Release Rate (Ci/sec) 1.20 00 F1 Noble Gas Release Rate (Ci/sec) 100.00 00 F2 Dispersion Model Projected Iodine Concentration at distance A 1.71-06 G1 Dispersion Model Projected Noble Gas Concentration at distance A 142.22-06 G2 Measured Iodine concentrations (if any) (uCi/cc) 0.00 00 G'l Measured Noble Gas Exposure Rate (R/hr) (gfany) 0.00 00 G'2 hr) 5.60 00 H1 Dose Rate Conversion Dose Rate ConversionFactor-Noble Factor-Iodine -(rem-m Gas (rem-m/Cj/Ci-hr) 3.30 00 H2 Calculated Thyroid Dose Rate-Model 9.56 00 Il Calculated Whole Body Dose Rate-Model 46.93-03 12 Thyroid Dose Rate-Field Data (if any) 0.00 00 I'l Whcle Body Dose Rate-Field Data (if any) 0.00 00 I'2 Estimatec Duration of release (hrs. min.)
(3.30 = 3 hours, 30 minutes) 3.30 00 J' Calculated Thyroid Dose Commitment-Model 33.45 00 K1 Calculated WB Dose Commitment-Model 164.27-03 K2
. Thyroid Dose Commitment-Field Data 0.00 00 K'l 0.00 00 K Whole Body Dose Commitment-Field Data. .____
_______--____________________---__----------------------_'2 -__ INPUT CHECK Distance in miles 3.00 00 A Xu/O X 10-6 3.20 00 B Noble Gau Release Rate (Ci/sec) 100.00 00 C Iodine Release Rate (Ci/sec) 1.20 00 D Wind Speed in mph 5.00 00 E Measured Iodine Field Conc. ( if any) 0.00 00 A' Measured Field Exposure Rate (if any) 0.00 00 S' 3.30 00 C' EstimatedDuratignofRelease(hrs em-m 3
/ min) 5.60 00 D' Iodine DRCF X 10 hr)
Noble Gas DRCF X 10(*5 (rem-m/Cg/Ci-hr) 3.30 00 E' 23 of 27 Rev. 1
. ~
i -
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~
ATTACHMENT 9 PROGRAM DATA FORM RELEASE RATE DOSE CALCULATION TIME (A) (B) (C) (D) (E) -(A') (B') (C') (D') (E') OF DISTANCE Xu/O* NOBLE IODINE WIND -MEASURED ** MEASURED ** ESTIMATED IODINE *** NOBLE *** DATA FROM x GAS- RELEASE SPEED FIELD FIELD DURATION- DRCP GAS DRCF I 24 HOUR SITE 10-6 RELEASE RATE (mph) IODINE EXPOSURE OF x x CLOCK (MILES) RATE (Ci/sec) CONCENTRATION RATE RELEASE 106 102 (Ci/sec) (uCi/cc) (R/hr) (hrs / min) (rem-m3/ (rem-m3_ Ci hr) Ci hr) R. , U 4 l
- y_ ~
i y . A " INITIALS NOTES: *Taken from Attachament.11 i
**If available
***Taken from Attachments 6 and 7 i
n. l
.e i . l ATTACHMENT 10 CALCULATION SMEET FOR ABSORBED DOSE RATES AND DOSE COMMITMENTS (AIR 80RNE RELEASES) . DATE TIME (44 HM CLOCK)
PREPARED BY { A D G C' I I' K K' DISTANCE PLUME CALCULATED MEASURED CALCULATED DOSE CALCULATED FROM TRAVEL ATMOSPHERIC ATMOSPHERIC DOSE RATE RATE DOSE DOSE SITE TIME CONCENTRATION CONCENTRATION FROM BASED ON COMMITMENT . COMMITMENT T X (C1/m3) DISPERSION FIELD FROM BASED ON Al M (hr. min) (Ci/m3) NOBLE GAS MODEL MEASUREMENT DISPERSION FIELD A2 METERS ETA EXPOSURE RATE (res/hr) (ren/hr) MODEL MEASUREMENT (R/hr) ** ** (ren)** (rem)** Al G1 G'1 11 I'1 kl K'1 A2 G2 G'2 R/hr 12 I'2 K2 K'2 - Al G1 G'1 Il I'1 l K1 K'1 A2 G2 - G'2 R/hr 12 I'2 42 K'2 A1 G1 G'1 11 I'1 K1 K'1 A2 G2 G'2 R/hr 12 I'2 K2 K'2 Al G1 G'1 11 I'1 K1 K'1 A2 G2 G'2 R/hr 12 I'2 K2 K'2 A1 G1 G'1 Il I'1 K1 K'1 A2 G2 G'2 R/hr 12 I'2 K2 K'2 Al G1 G'1 11 I'1 K1 K'1 G2 G'2 R/hr I2 I'2 K2 K'2 G1 G'1 Il I'1 K1 K'1 [A1 A2 G2 G'2 R/hr 12 I'2 .K2 K'2 l NOTE: THE TOTAL DECAY TIME IS THE SUM OF THE TIME FROM R* ACTOR SHUTDOWN UNTIL THE TIME OF PLUME , ARRIVAL. NO CREDIT WILL BE TAKEN FOR I DEPLETION FROM THE PLUME OR DECAY IN TRANSIENT. LETTERS CORRESPOND TO LETTERS IN OUTPUT OF PROGRAM l
*:: UMBER FOLLOWING LETTER IS INTERPRETED AS FCLLOWSs 1 (CNE) IODI:;Er I (TW3) = NCBLE CAS
** NUMBER FOLLOWING LETTER IS INTERPRETED AS FOLLOWSs 1 (ONg) e THYROID 2 (TWO) = WHOLE BODY 25 of 27 Rev. 1 l
* .e .
EP IV-114
' ATTACHMENT 11 Xu/Q VALUE DETERMINATION S t the Za/O values that correspond to the stability class as determined by the temperature, dau gnce from the site and the release point (ground or elevated).
- 1. USE THE TEMPERATURE VALUE FROM TME METEOROLOGICAL TotfER TO DETERMINE STABILITY CLASS.
Primary Instrument NOTE .
"300 f t. - 33 f t. temperature ('C) UNSTABLE IS 1 -1.3'c UNSTABLE NEUTRAL STABLE NEUTRAL IS > -1.3'c i -0.5'c
-1.3 -0.5 STABLE IS > -0.5'c ,
Backuo Instrument NOTE 150 ft. - 33 ft. temperature ('C) UNSTABLE IS i -0.6*C UNSTABLE NEUTRAL STABLE NEUTRAL IS > -0.6*C 1 -0.2'c STtJLE IS > -0.2*C
-0.6 -0.2
- 2. DISTANCE GROUND LEVEL RELEASE (E-6/m2) ELEVATED LEVEL RELEASE (E-6/m2)
M M UNSTABLE NEUTRAL STABLE UNSTABLE NEUTRAL STABLE 1000 0.62 14.83 58.43 244.4 16.17 39.01
- 11.23 35.34 **
1270 MEA 0.79 9.91 41.54 226.29 2000 1.2 4.58 21.21 166.5 5.4 23.70 .01 3000 1.9 2.29 11.46 111.9 , 2.74 14.5 .50 4000 2.5 1.40 7.37 80.6 1.69 9.81 2.44 5000 3.1 .95 5.22 61.4 1.15 7.14 5.24 6000 3.7 .70 3.94 48.7 .85 5.47 7.u4 7000 4.4 .53 3.10 39.9 .65 4.35 9.79 8000 4.9 .42 2.52 33.4 .52 3.56 11.05 8045 LP2 5.0 .42 2.5 33.2 .51 3.53 11.09 9000 5.6 .35 2.10 28.6 .42 2.98 11.76 10000 6.2 .294 1.78 24.8 .35 2.54 12.06 11000 6.8 .250 1.53 21.8 .30 2.20 12.09 12000 7.5 .215 1.34 19.3 .26 1.92 11.93 13000 8.1 .18 1.18 17.3 .22 1.70 11.65 14000 3.7 .165 1.05 15.7 .20 1.52 11.3 15000 9.3 .14 .95 14.22 .18 1.36 10.91 16000 EP2 9.9 .131 .56 13.01 .16 1.24 10.50 CEA - Minimum Exclusion Area f.P1 - Low Population Zone EPZ ~ Emergency Planning Ione CV:1ue of Xu/O for 1000 meters distance = 5.15E-16/m2
**V1ue of Xu/Q for 1270 meters distance = 1.18E-12/m2 Dict 0 Ice Xu/O = E-6/m2 (ground) Xu/Q = E-6/m2 (elevated) 24 of 27 Rev. 4 m _ _ __ _ _ __ . . . _ . _ _ . - - . _ - _ _ _ _
1 EP IV-ll4 i Signature Page Prepared By: 7/A#f// Reviewed By: -
' /5 $!f3
##/ Department Head Date
- Reviewed By
- /2[u [/[ e- /d//'[El- l Nuclea[EmergencyPlanningEngineer Da t.e l Reviewed'By: - _-
/ o!/.8/9 %
i ! \ Station Quality Assurance Review Date ! (if required see EP VI-2) SORC Meeting No.: P3- /3/ /W! 2 a/pj
' /
Date Approved By: // J// N General Manager - Salem Operations Date Approved By: /s J Manager - Nuclear Site Protection Date i l i l l 1 i 27 of 27 Rev. 0
4
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- EP IV-213 EMERGENCY PROCEDURE .
l EP IV-213
, EVALUATION OF RMS DATA PROM HIGH RANGE CHANNEL R45-D ACTION LEVEL l
After high rangt monitor R45 is triggered into service by high alarm on the R41C noble gas plant vent monitor channel. The data from R45D can be used to calculate iodine release rates when other means are unavailable (e.g. R41B iodine plant vent monitor). RESPONSIBLE INDIVIDUAL The Radiation Protection Engineer, a Technical Supervisor cf Radiation Protection, the Radiological Support Management, or a Radiological Assessment Staff member shall be responsible for implementing this procedure. ACTION STATEMENTS Obtain the R45D count rate (in cpm) from the control room liaison (or from Dose Assessment Data Sheet, Attachment 1 of EP IV-113).
-Obtain sample buildup time for R45D monitor. Sample buildup time for this RMS channel is the difference in time between when the R45 channel is triggered into service and the time of the current monitor reading. For example, if R41C went into alarm at 1015 hours triggering R45 into service and the monitor reading time is .
1215 hours, then two (2) hours of sample buildup have occurred. Once sample buildup time has been established, use Attachment 1 to determine concentration of iodine (in uCi/cc) in the plant vent effluent based on the channel count rate (cpm). 1 of 4 Rev. 0
r EP IV-213 ACTION STATEMENTS (cont'd) , Convert the plant vent-flow rate in cubic feet per minute (cfm) to cubic centimeters per sec (cc/sec). To. perform this conversion' multiply _ cfm by 472 to obtain ec/sec. To obtain. iodine release rate'in uCi/sec, multiply iodine plant vent concentration (uci/cc) by the plant vent flow rate in (cc/sec). Example Given 1) 2R45D is reading 100 cpm at 1200 hours
- 2) 2R41C triggered 2R45 into service at 1100 hours
- 3) Plant vent flow rate is 80,000 cfm
. Solve 1) Sample buildup time = 1200 - 1100 hours = 1 hour
- 2) Plant vent flow rate = 80,000 ft / min 3 (cfm) X 472 cc. min /ft .sec = 37,760,000 cc/sec = 3.78E7 cc/sec 3
- 3) 100 cpm after 1 hour sample buildup tarresponds to 7.0E-4 uCi/cc iodine concentration in the plant vent (see Attachment 1).
- 4) Iodine release rate is the product of 3.78E7 cc/sec and 7E-4 uCi/cc which is 2.65 E + 4 uCi/sec.
These release rate data can be used in Emergency Procedures EP IV-lli, EP IV-ll3, and EP IV-ll4 to perform dose calculations. 2 of 4 Rev. 0
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- 2P IV-213
- Signature Page Prepared By:
- Y f Reviewed By: k.D & /O-/7 M3 O Department Hec.d Date Reviewed By: In [ mu //-/ 7 M Nuclear b ergency Planning Engineer Date Reviewed By: *-- n - M /d[/ P!P3 Station Quality Assurance Review Date
- h. (if required see EP VI-2)
SORC Meeting No.: ? 3- /3 / /d!z e 5 3 Date Approved By: /#M/!bd GeneralMknager-SalemOperations Date Approved By: r
/> < <
!/J __
Manager - Nuclear Site Protection Date 4 4 of 4
1 o EP V-1 EMERGENCY PROCEDURE EP V-1
- TECHNICAL' SUPPORT MANAGER (TSM)' RESPONSE ACTION LEVEL This procedure shall be implemented upon receipt of notification that the EOF is to be activated.
ACTION STATEMENTS TIME INITIAL -
- 1. Implement Procedure EP II-4 (Initiation
-and Activation of Emergency Response Support Callout) and, if necessary, EP II-5 (Paging Emergency Response Personnel).
- 2. Proceed to the Emergency Operations Facility (EOF) and enter through the student entrance.
NOTE Be certain you have'your PSEGG ID card with you.
- 3. Upon arrival at the EOF, initiate a log of your activities.
- 4. Report to the Emergency Response Manager (ERM) to inform him of your arrival.
S. Verify operation of telephone lines. o l SGS Page 1 of 4 Rev. 1
m_ l EP V-1 ACTIONS: STATEMENTS (continued)
' TIME INITIALS
- 6. Verify that the following Technical Suppor.t positions are staffed.
Technical Support-Team Leader - EOF Technical. Support Team - EOF Technical Support Team Leader - TSC Ouality Assurance Team Leader - EOF Quality Assurance Team - EOF Licensing Support Team Leader - EOF _ Licensing Support' Team - EOF' Fuel Support Team Leader - EOF Fuel Support Team - EOF
- 7. Report to the-ERM and inform him that the t
- L
-Nuclear Support function is fully opera-tional.
- 8. Meet with-Technical Support Team Leader -
. EOF.to assess support required by Technical
-Support Team Leader - TSC.
- 9. Meet with the Site Support Manager (SSM) to assess:
4
- a. present level of technical support 4 needed by SSM
- b. future level of technical support anticipated.
- 10. Meet with staff team leaders and assign support tasks.
U _ SGS Page 2 of 4 Rev. 1
. . _ .. --~.. _ _ . . . _ _ . _ . , , _ . _ _ . _ , _ . ~ . . _ , _ . ~ . . . _ - . . . . . - _ . - . . _ . - . . _ . _ . - - - . . _
EP V-1 JACTION STATEMENTS (continued) TIME INITIALS
- 11. Direct staf f teata leaders -to prepare a watch bill for continuous 24-hour operation of their functional-areas.
- 12. Assist the ERM by:
- a. technical assessment of' plant conditions; and
- b. providing information on technical support operations both planned and in progress.
NOTE t. Forward all completed forms to the Nuclear-Emergency Planning Engineer. Attach any referenced completed EPs or attachments. l i l l l 1 SGS Page 3 of 4 Rev. 1 L.
f. 1 i .EP.V-1 Prepared By: D. Jagt Reviewed By: 2% [3-De h ment Head Date Reviewed By: Nu [M Me Planning #Ang'ineer E E
/d /f f3 Date Reviewed By: L
+ _ , _ _
/ o /.([g 3 Station Quality Assurance Review Date (if required see EP VI-2)
SORC Meeting Number: [3~/N 1 /d / IS
'J Approved By:
//////G alI ager [alemOperations Da e
. Approved By: 7Ge . /7 f.f Manager - Nuclear Site Protection Date l
~.
SGS Page 4 of 4 Rev. 1
s EP V-5 EMERGENCY PROCEDURE EP V-5 LICENSING SUPPORT TEAM LEADER RESPONSE ACTION LEVEL This procedure shall be implemented upon notification of activation of the EOF. ACTION STATEMENTS
- TIME- ' INITIALS
- 1. Implement Procedure EP II-4 (Initiation and Activation of Emergency Response Support Callout) and, if necessary, EP II-5 (Paging Emergency Response Personnel).
- 2. Proceed to the Emergency Operations Facility (EOF) and enter through the student entrance.
NOTE Be sure to have Public Service Identifica-tion Card with you to f acilitate passage -
-through police road blocks and for access to the EOF.
- 3. Upon arrival initiate a log of your activities.
- 4. Advise the Technical Support Manager of your arrival and state of readiness to provide support.
- 5. Provide support as necessary in all aspects of licensing and safety.
SGS Page 1 of 2 Rev. 1
i l l
. *EP'V-5 Prepared By: D. Jagt Reviewed By: I d! De artment Head Date Reviewed By: v-+- A. /#/f cP3' Nuc1 ar Eme y Planning Enginee'r Date' Reviewed By: im he. - b / o[f/83 Station Quality Assurance Review Date (if required see EP VI-2)
SORC Meeting Number: I8"/N dd[ /d / d Date Approved By: ////V d G .ral d ager - Sakem Operations Da Approved By: / 4 /J kanager - Nuclear Site Protection Date l 1 l l SGS Page 2 of 2 Rev. 1
- b. - ~
. ~
e'N . EP V-6 EMERGENCY PROCEDURE-EP V-6 FUEL SUPPORT' TEAM: LEADER (FSTL)' RESPONSE ACTION._ LEVEL This procedure-shall be implemented _upon notificetion of activation of'the EOF.- . ACTION STATEMENTS TIME -INITIALS 1.' Implement Procedure EP II-4 (Initiation and Activation of Emergency Response Support Callout) and, if necessary, EP II-5 (Paging' Emergency Response Personnel).
- 2. Proceed to the EOF.
NOTE Be sure to have Public Service Identifica- , tion Card with you to facilitate passage through police road blocks and permit access to the EOF.
- 3. Establish your work area. The Nuclear Fuel Support Team Leader shall be responsible for all fuel matters and directing personnel to. perform the following functions:
- a. Obtain information regarding core condi-tion, including plant operating history, coolant activity, etc.
. b. Assess the condition of tne core. SGS' Page 1 of 4 Rev. 1 m q , -y - --,4.,-,_,,--,+-e.- 3,.+ -v.. ,. ,-~...r--...-.m. -
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.EP V-6
' ACTION STATEMENTS (continued)
TIME INITIALS -
- c. Evaluate coolant activity and core-condition and perform a' fuel damage, transient and T/H analyses.
- 4. Verify that you have adequate staff available to perform core damage / fuel-safety evaluation.
- 5. Verify that computer terminals required are
. operable. Locate and check operation of terrinals.
- 6. Report to the Engineering Support Manager to inform him.of your arrival.
- 7. Notify ths Engineering Support Manager when adequately staffed for the event in progress.
- 8. Establish contact with the Operations Assessment Engineer in the TSC and determine present condition of the core.
The following codes will be run to verify core and fuel conditions. T:ansients SGS Page 2 of 4 Rev. 1 _ _ - ._ ._- - . _ - , -~ _ ._ __ .- _ . . - - _ , . _ . , _ - _ , _ _ _ , - _ . _
r
.~.
EP V-6 4 ACTION STATEMENTS _(continued) , Use -DYNOLE or RETRAN to- calculate system, pressure, temperature, flow, etc. o T/M Use COBRA or VIPRE to calculate DNBR,
' fuel and coolant temperatures in hot channel (s).
Fuel Performance Use MICROPOSHO (on TI-59) or other available codes to calculate fuel failure fraction. Use FRAP to calculate hot channel fuel temperature.
- 9. Evaluate the information available to the Technical Support Team - TSC as required to perform core safety / damage analysis.
- 10. Contact fuel vendor (Westinghouse) and/or consultants (JAI or SI) for additional support as reguried.
- 11. Report results of evaluations to the ESM.
NOTE Forward all completed forms to the Nuclear Emergency Planning Engineer. Attach any referenced completed EPs or attachments. SGS Page 3 of 4 Rev. 1
ims EP V-6 Prepared By: D. Hsu Reviewed By: . a /d/6/d3 DepartmedHead D' ate Revfewed By: h$ ln /b///f?3 Nuc r lannip[ Engineer Dat Reviewed By:- m /o !/ g /B"5 Station Quality Assurance Review Dat (if required see EP VI-2) SORC Meeting Number: [3-/3! /d D
. Approved By: / /&/E.I ert ager - Salem Operations Da e Approved By: g A/u 1 hanager--NuclearSiteProtection Date i-SGS Page 4 of 4 Rev. 1 i
'-- - - . - - - , ,,.,.-...,_,y , , , , _ . , , , , _ _ _ , , _ , , , _ . , _ , , , , , , . , , , . _ . , , _ _ , _ _ _ _ _ _
(~ EP.V a. EMERGENCY PROCEDURE . EP V-7 NUCLEAR ENGINEERING,^ QUALITY ASSURANCE, LICENSING, AND NUCLEAR FUELS DIVISION REPRESENTATIVES - ACTION' LEVEL
.This' procedure shall be implemented upcn notification of activation of the TSC and/or EOF.
ACTION STATEMENTS TIME INITIALS 12 Upon notification, proceed as soon as
.possible to your assigned emergency duty station (TSC or EOF).
NOTE Be sure to carry-Public Service Identification card which will facilitate passage through police road blocks and for entry to the site or EOF. Your arrival at your emergency duty
-station is expected within two hours of initial contact.
- 2. Sign in upon arrival at your emergency duty station.
- 3. If the emergency notification is during
-normal work hours, all Division personnel without emergency duty assignments will remain at their work normal area and follow instructions received from their Group Leaders and/or Division Head.
SGS Page 1 of 3 Rev. 1 D
l i
<i. l
.l,
. EP V ,?"b; .
-n NOTE Forward-all_ completed forms to the Ndclear -
l. Emergency Planning.. Engineer. - Attach any- ' referenced completed EPs or attachments. i r
.- /
6 i 1 i SGS Page 2 of 3 Rev. 1
. _ _ . . _ . _ . _ . _ , _ - - - _ . _ - . . _ . . , _ , . ~ _ . - _ . . , _ . _ _ _ , , _ . . _ - - ~ - . .
~
- EP V-7
- Prepared By: D. Jagt Reviewed By: /) k 2.7-( 3 DepahndntHead Date Reviewed By,: Me_a _I _ _ /, _
/>
/d///P)
Nuc r erg Plening Engineer Date Reviewed By: -^ - Y / o/d 93
' Station Quality Assurance Review Date (if required see EP VI-2)
SORC Meeting Number: [d '/Ef 4 /0 / v Approved By: ,
// /V[
Ge eral anager - Salem Operations Da Approved By: Ap /J 47 7 Manager - Nuclear Site Protection ' Date } SGS Page 3 of 3 Rev. 1
M EP.VI-l ADMINISTRATIVE PROCEDURE
'EP'VI-l
; REVISION AND APPPOVAL OF PLANS AND PROCEDURES ACTION ~ LEVER
^ This' procedure details the methods - for reviewing the Salem Generating Station' Emergency Plan, Emergency Plan Procedures Manual and Emirgency Plan Training Manual.
' Revisions;to any of these three-(3) manuals will be made whenever changes.are necessary to ensure-.that the Emergency Plan can be
' properly implemented.
, NOTE
'On-the-spot changes'to any portion of an Emergency Proce-dure mustibe. approved by the Emergency Coordinator (SSS, EDO or ERM).. On-the-spot changes will only:be requested during Jan actualzincident otherwise routine revision procedures
.will-be utilized.
'Any holder of a manual may prepare revision (s) to any section or procedure included in one of the mutuals. Implementing procedure
~ changes will be coordinated by the department head responsible for the given procedure (see Table 6-1.1).
A Revision Request Form (Figure 6-1.1) is filled out by the person 7 preparing the revision. A description of the revision requested and reason for revision shall be included.
'A' list of effective revisions shall be maintained in front of each manual. indicating the latest revision number and effective date.
When an on-the-spot change is made, it is the responsibility of the individual authorizing the change to ensure that a revision request is submitted within 10 days. 1 of 7 Rev. 2 7
EP VI-l
- ACTION STATEMENTS ~ - SECTION I lOn The Spot Changes ~to Procedures- _
- 1. When making an on-the-spot change, the initiator must not change the intent of the procedure. Before making the change the initiator should ask, as a minimum, the following questions:
a) Would the on-the-spot change involve a' violation of 10CFR50, Appendix E? b) Would the on-the-spot change supersede existing Technical Specification requirements? c) Would the on-the-spot change alter the technical content or aporoach of the procedure? If the ansser to any of'these questions is yes, then the on-the-spot change-should not be made.
- 2. =The initiator should-hand write the change at the appropriate
-point.of the-procedure and request approval of the emergency coordinator (SSS, EDC, ERM).
- 3. The' emergency coordinator must review and approve any on-the-spot change, by initialing the hand written change.
t
- 4. It-is the responsibility of the individual authorizing the change to ensure that a Revision Torn (Figure 6-1.1) is submitted at the conclusion of the event. Proceed to Section II for detailed instruction.
- 2 of 7 Rev. 2
" ~~e
EP VI-l ACTION STATEMENTS - SECTION TI Plan and Procedure Revisions
- l. Preparer- completes Revision Request Form (Figure 6-1.1).
a) Contact Nuclear Emergency Planning Engineer for revision' l number. b) Fill in appropriate names _and titles on Figure 6-1.1 based on information in Table 6-1.1.
-c) Attach edited copies and supporting documents as appropriate.
d). Transmit Revision Request Form to appropriate department head (see Table 6-1.1).
- 2. Department' head performs initial review of proposed revision.
a) Department. head will return revision to preparer if revision request-is disapproved er further information is needed. b) If the department head approves, submit the revision to the Nuclear Emergency Planning. Engineer as indicated on Table l
'6-1.1.
c) As' indicated on Table 6-1.1, submit the revision to the Station Quality Assurance for review prior to SORC approval, d) Contact the Chairman of SORC and arrange for a review meeting.- Transmit a copy of the change to the SORC Chairman and to the Nuclear Emergency Planning. Engineer for file. l'
- 3. SORC reviews proposed revision.
i
.a) Department head presents revision.
b) SORC recommendation is made to General Manager - Salem Operations. c). Proposed revision is transmitted with SORC Meeting number and date for approval by the General Manager - Salem Operations. 3 of 7 Rev. 2 _, - . _ . . _ . -- - - _ _ _ _ - _ _.-.- _~ . . _ _ _ . . . -
I i e
- EP VI-l ACTION STATEMENTS'(continued) ,
- 4. = Manager - Nuclear Site- Protection gives the proposed revision a final review and approval. Revision is forwarded to Nuclear Emergency Planning Engineer for distribution.
- 5. Nuclear _ Emergency Planning Engineer' revises plan.
a)-Revisions will be made to each-section or procedure of the manual.- The initial revision number will be Revision 0 and' each subsequent revision will be the succeeding number. Revised pages will be issued with the entire section or procedure and not as individual pages. b ') ~ Revisions will be indicated by a vertical line in the right margin. c) Revisions will be correlated with the other two emergency plan documents for consistency. d) All changes will be documented and pages will be distributed in accordance with EP VI-2 and EP VI-3. l l-d 4 of 7 Rev. 2
. -~ - - . , . . - - - - - - . _ . . .- .. , . - .
--' EP VI-l Prepared By: y Reviewed By: /7 M/r/E3 Department Head Date Reviewed By: Abgj 4 /,'r[/t:5 NuclearEmergencyPlan[ingEngineer Date Reviewed By: 1 .- 7 !J of G'"5 Station Quality Assurance Review Date (if-required ee P VI-2) f SORC. Meeting No.: h8' /?k $ /d /Nd Date Approved By: /d IV J' General [anager - Sab m Operations Date Approved By: // J I Manager - Nuclear Site Protection Date 5 of 7 Rev. 2
'~
'~
EP VI-l
, FIGURE 6-1.1 .
EMERGENCY PLAN-REVISION REQUEST FORM FIGURE'6-1.1 SALEM GENERATING STATION '
- PLAN- SECTION PROCEDURE MANUAL- ' PROCEDURE NO.
TRAINING MANUAL SECTION REVISION NO. OBTAIN REVISIONLNUMBER FROM NUCLEAR EMERGENCY PLANNING ENGINEER BRIEF DESCRIPTION OF REVISION PROPOSED: REASON FOR REVISION: RESPONSIBLE DATE .DATE
~ INDIVIDUAL NAME RECEIVED TRANSMITTED SIGNATURE PREPARER ~, NA DEPART!!ENT HEAD (SEE. TABLE 6-1.1) i NUCLEAR EMERGENCY PLANNING ENGINEER STATION QA I (SEE TABLE 16-1.1)
SORC MEETING'NO. MANAGER - NUCLEAR SITE PROTECTION 5.LEAREMERGENCY ' PLANNING ENGINEER o 6 of 7 rev. 2
i TABLE 6-1.1 i: ISION REVIEW RESPONSIMILITY P14W REVISION' Dt.PT. HEAD "P OA SOE REVISION AND ' MANt1Al. SECTION RY REVIEW P#dtFW REVIEW REVIEW APPROVAL DISTRItuT1008
' Emergency Plan (All) ' Preparer Nuclear Emer- Nuclear Emer- .* SORC General. Name
- r - . leuclear Emergeacy gency Planning gency Planning Manager Nuclear Site Plant.ing Engineer Engineer Engineer Approval Protection Training Manual (All) Preparer Nuclear Emer- Nuclear Emer- * .SORC Ceneral' Manager touclear Emergency gency Planning .gacy Planning Manager Nuclear flite Planning Engineer Engineer Engineer Approval Protection Procedures I - On Site Preparer Operatione' Nuclear Emer- ~ Station OA SORC Ceneral -Manager . touclear Emergency.
Nuclear Site Planning Engineer Manager gency Planning. Manager Engineer Apps oval Protection Procedusse II - Off Site Preparer Nuclear Emer- Nuclear Emer- Station OA SORC Ceneral hanager Nuclear Emergency gency Planning gency Planning Managwr Nuclear Site Planning Engineer Engineer Engineer Apphovel Protection Proceduree Ilt - Security Preparer Security Nuclear ftsper- Station OA SORC Ceneral Manager h elear Eneroency Supervisor gency Planning Manager Nuclear Site. Planning Engineer [ Engineer Apptoval Protection { Proceducee IV - Preparer Radiation Nuclear Emer- Station OA SORC ^ Co r.e r a l Manager Nuclear Emergency Radiation Protection Protection gency Planning Manager Nuclear Site Planning Engineer Engineer Engineer Approval Protection Procedures IV - Preparer Technical Nuclear Emer- Station OA SORC G9neral Manager Nuclear Emergency Cheelstry Manager gency Planning Manager Nuclear $ite Planning Engineer y Engineer Approval Protection O Preparer General Nuclear Emer- Station OA ScaC Ceneral Manager Nuclear Emergency m Procedurae V - Nuclear Support Manager gency Planning Manager Nuclear Site- Planning Engineer q lupartment Nuclear Support Engineer Approval Protection
- Not Required 9
9 l .l
EP VI- 2 ADMINISTRATIVE PROCEDURE EP VI-2 DISTRIBUTION OF PLANS AND PROCEDURES ACTION LEVEL This procedure details the methods-for-distribution of the Salem
~ -Generating ' Station Emergency Plan, . Emergency Plan Procedures Manual and Emergency-Plan Training Manual.
All revisions shall be distributed by the-Nuclear Emergency Planning Engineer. When the manual is to be located in a particular location, vehicle, locker, etc., a person ~shall be designated who is responsible for the maintenance of that manual. The holder shall insert the revision, sign and'date the form appropriately and indicate the date revisions were entered and when the information was reviewed with subordinates if applicable. The form shall be returned to the Nuclear Emergency Planning Engineer. ACTION STATEMENT When an approved Emergency Plan Revision is forwarded to the LNuclear Emergency Planning Engineer for distribution, the f) Nuclear Emergency Planning Engineer shall perform the following:
- 1. Distribute revision.
a) Follow distribution instructions provided on Figure 6-2.1. b) Distribute a revision in accordance with Figure 6-2.2. Rev. 1 1 of 3
, EP VI- 2 c)l Include a revised index indicating the.date of the revision
-and-the plan section(s) or procedure (s) which have been revisep in each distribution. -
I:2. Verify distribution.
-a) When'the distribution sheets are returned by the manual holders the revision status of each manual will be recorded on Figure ~6-2.3. The distribution sheets shall be.retaine3 on file by the, Manager - Nuclear Site Protection.
b)-If more than a-one month lapse occurs between issuance'of a revision to distribution and return of a revision sheet a check will be made with the manual holder to insure prompt entry of the revision. Y Rev. 1 2 of 3
. _ _ . . _ __ . _ . _ . _ _ . - _ _ _ _ . ~ . . . _ . . . _ . . . _ _ _ _ _ _ _ __ _
. l EP VI- 2 1 Prepared By: h 9
Reviewed By: o e M A/E#E 4/f/f3
# Department Head # Date ',
I Reviewed By: OM#Ma., M 6 /9/P_3 _ Nuclear Emergency Plannikg Engineer Date Reviewed By: # -m~ 7 !Aof b6 Station Quality Assura ce Revie Date SORC Meeting No.: ~/ < D'atl l Approved By: y , ,
/d!2 3 General Manager - Salem Operations Date Approved By: # fl Manager - Nuclear Site Protection Date
( Rev. 1 3 of 3 I
m EP 'VI- 2 Figure 6-2.1 EMERGENCY PLAN REVISION-REOUEST FORM FIGURE 6-2.1 . SALEM GENERATING STATION MANUAL NO. REVISION NO. TO:~b) PLAN b3 PROCEDURES MANUAL b TRAINING MANUAL REVISE 'YOUR COPY OF ~ THE PLAN BY INSERTING THE ATTACHED SECTION(S ) IN THE APPROPRIATE PLACE, AS SPLECIFIED BELOW, AND DESTROYING THE.0LD SECTION(S). -REVISIONS ARE IDENTIFIED BY A VERTICAL'LINE IN THE RIGHT MARGIN. NOTE: COMPLETE THE FOLLOWING INFORMATION AND RETURN THIS SHEET TO THE NUCLEAR EMERGENCY PLANNING ENGINEER, P.O. BOX 236, HANCOCKS BRIDGE, NEW JERSEY '08038. - MANUAL NO. DATE THIS CHANGE ENTERED DATS THIS INFORMATION REVIEWED WITH SUBORDINATES: SIGNATURE: n ,w~ w.,.w,--
EP VI- 2 FIGURE 6-2.2 DISTRIBUTION LIST Manual No. 1 Manual-No. 10 Operations Manager Technical Engineer . Senior Shift Supervisors Office J. Jackson Salem Generating Station Salem Generating Station Manual No. 2: Manual No. 11 Operations Manager Tecnical Manager Unit Al Control Room L.K. Miller Salem Generating Station Salem Generating Station Manual No. 3 Manual No. 12
' Operations Manager O. A. - Salem Unit #2 Control Room B. Leap Salem Generating Station Salem Generating Station Manual No.1 4 Manual No. 14 General Mgr.-Salem Operations Radiation Protection Engineer J. M. Zupko, Jr. .
J. O'Connor l Salem Generating Station Salem Generating Station l
' i.
Manual No. 5 Manual No. 15 Public Af f airs Manager-Nuclear Security Supervisor R. A. Silverio T. DiGuiseppi [ Artificial Island Salem Generating Station Manual No. 6 Panual No. 17 Asst. General Mgr.-Salem - Oper. Nuclear Emergency Planning J. Driscoll Engineer. Salem Generating Station Artificial Island Manual No. 7 Manual No. 18 Operations. Manager Safety Review Group L. Fry B. Hall Salem Generating Station Artificial Island Manual No.8 Manual No. 19 Maintenance Manager Senior Public Infc. Rep. J. Gallagher W. Denman Salem Generating Station Second Sun - Salem
-Salem Generating Station Manual No. 9 Manual No. 20 Office Administrator Security Supervisor R.-Potter Guard House - Main Gate Salem Generating Station Salem Generating Station
~'
EP VI-2 Figure 6-2.2 Manual'No. 21 Manual No. 30 through:32 Security Supervisor .
. Manager-Nuclear Site Pro-Guard House - Contractor tection - TSC Salem Generating Station Artif.cial Island Manual No. 22 Manual No. 33 tnrough 36 Maintenance Manager Manag.er - Nuclear Site Pro-Se nior . Supe rvisor tection - EOF Locker Salem Generating Station Artificial Island Manual No. 23 Manual Nos. 37 & 38
-I & C Engineer Library Salem Generating Station Nuclear Training Center-Salem
. Manual.No. 24 Manual No. 39 Chemical Engineer Training Staff ER . Dc.lan Pat Landers Salem Generating Station Nuclear Training Center-Salem Manual Fn. 25' Manual No. 40 Radia ion Protection Engineer Training Staff Senior Supervisor-RP James Beattle Salem Generating Station Nuclear Training Center-Salem Manual No. 26 Manual No. 41 Radiation Protection Engineer Radiation Protection Engineer Control Point (Main) Emergency Van Salem Generating Station Salem Generating Station Manual No. 27 Manual No. 43
~ Radiation ^ Protection Engineer Control Point (Main)
Salem Generating Station Manual No. 28 Manual No. 44 Radiation Protection Engineer Senior Public Info. Re p . - Sa lem
. Control Point (A Building) Emergency News Center Salem Generating Station Second Sun Manual No. 29
-Radiation Protection Engineer Control Room Emergency Locker Salem Generating
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_ EP VI- 2 Figure 6-2.2 Manual No. 45 Manual No. 54 General Manager . Hope Creek Manager-Nuclear Procurement & R. Salvesen Material Control-R. DeSanctis
~ ~
Hope Creek Generating Station Artificial Island Manual No. 46 Manual No. 55 Techuical Document Room Senior Engineer M. Ochs C. A. Sakenas Salem Generating Station Artificial Island Manual No. 47 Manual No. 56 Public Affair: Manager Principal Staff Engineer R.A. Silverio (Home Copy) N. C. Allman
. Salem Generating Station 80 Park Plaza 16C Manual No. 48 Manval No. 57 Operations Engineer General Manager-Nuclear Sys.
L. Catalfomo H. J. Midura Salem Generating Station Artificial Island Manual No. 49 Manual-No. 58 Senior Staff Engineer Mgr.-Nuclear Site Maintenance J. Clancy F. Meyer
' Artificial Island Artificial Island Manual No. 50 Manual No. 59 Manager-Nuclear Fuel OA Office E. S. Rosenfeld Salem Generating Station Artificial Island Manual No. 51 Manual No. 60 Emergency Duty Officer Manager-Systems Engineering l
L. Catalfomo (Home Copy) L. A. Reiter Salem Generating Station Artificial Island Manual No. 52 Manual No. 61 Emergency Duty Officer Assistant to V.P. L. Fry (Home Copy) C. P. Johnson Salem Generating Station 80 Park Plaza 15A Manual No. 53 Manual No. 63 Manager-Nuclear Engineering Emergency Duty Of ficer & Controls - T.N. Taylor , Salem Generating Station Artificial Island
E P VI- 2 Figure 6-2.2 Manual No. 64 Manual No. 73 Manager-Radiation Protection Manager-Methods & Admin.
-Services - W. L. Britz R. A. Burricelli. ~
Artificial Island Artificial Island Manual No. 65 Mgr.-Nuclear Plant Engineering Manual No. 74 R. Gura M..Gavioli Artificial Island Nuclear Training Center Sa lem Manual No. 66
-Manager - Nuclear Site Manual No. 75
- Protection General Manager P. A. Moeller Nuclear Support Artificial Island 'J . T. Boettger Ar tificial Island Manual No. 67 Manager - Nuclear Engineering Manual No. 76 Design Supervisor OA Audits-Salem A.- Thomson H. Lowe Artificial Island QA Trailer Manual No. 68 Manual No. 77-Chief System Operator - Elec. Manager-Licensing & Analysis Elec. Load Dispatch Center R. P. Douglas 80 Park Plaza, Newark- 80 Park Plaza 16D Manual No. 69 Lead Engineer Manual No. 79 C. A. Burg Manager-Nuclear Licensing &
Artificial Island Regulation - E. Liden Artificial Island Manual No.'70 Principal Staf f Engineer Manual No. 81 R. F. Yewdall General Manager - Info. Svs. 80 Park Plaza, Newark A. F. Lenehan 80 Park Plaza, Newark Manual No. 71 Senior Vice President -- Energy Supply & Engineering Manual No. 82 R. M. Eckert Gen. Mgr. Mech. Eng. 80 Park Plaza, Newark T. Pietrofitta-Atlantic Elect. P.O. Box 1500 Pleasantville, NJ 08232 Manual No. 72 General Manager- Manual No. 83 Corporate OA Vice President-Public Relat. R. L. Mitti R. H. Franklin 80 Park Plaza 16E 80 Park Plaza 4B
I i i l E P VI- 2 Figure 6-2.2 Manual No. 87 Manual No. 98 Manager - Nuclear Const. Support Cumberland County OEM E. W. Barradale Coordinator ~ Artificial Island Mr. E. J. Hoffman R. D. #8,. Box 46 Manual No. 88 Bridgeton Avenue Manager - QA Nucler Operations Bridgeton, New Jersey' 08302 A. Nassman Artificial Island. Manual No. 99 e 102 New Castle County, Department of Public Safety
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Manual No. 89 Coordinator for Emergency Vice President - Preparedness Nuclear Mr. R. Kendall R. A. Uderitz 3601 North Dupont High/ay Artificial Island New Castle, Delaware 19720 Manual No. 91 Manual 100 Asst. General Mgr.- Nuclear New Jersey BPU Engineering - D. J. Jagt Mr. R. Hartung Artificial Island Department of Energy 1100 Raymond Boulevard Manual No. 92 and 93 Newark, New Jersey 07102
'New Jersey Bureau of Radiation Protection Manual No. 101 Mr. Frank Cosolito, Chief- U.S. Nuclear Regulatory Comm.
380 Scotch Road Director of Nuclear Reactor Trenton, New Jersey 08628 Regulation Washington, D.C. 20555 Manual No. 94 & 95 Delaware Emergency Planning Attention: Mr. S.A. Varga
& Operations Chief Mr. C. Jester, Director Operating Reactors Delaware City, Delaware 19706 BRAl Div. of Licensing Manual No. 96 New Jersey State Police (OEM) Manual Nos. 111 and 112 Major H. Spedding U.S. Nuclear Reguatory Comm.
Deputy Director Office of Inspection and P.O. Box 7068 Enforcement - Region I West Trenton, New Jersey 08625 Administrator 631 Park Avenue Manual No. 97 King of Prussa, PA 19406
' Salem County OEM Coordinator Mr. D. C. May Manual No. 113 Salem County Admin. Bldg. U.S. Nuclear Regualtory Comm.
94 Market Street Resident Inspector - Salem, New Jersey 08098 Salem Generating Station
1 EP VI-2 Figure 6-2.2
-Manual No. 114 Lower Alloways Creek Towship The Honorable Harry Coleman .
Mayor . The Municipal Building Hancocks Bridge, New Jersey 08038 M nual No. 115 Radiation Management Corporation Mr. T. Linnemann 3508' Market Street Philadelphia, PA 19104 Manual No. 116 Institute for Nuclear Power Oper. Emergency Preparedness Department 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 Manual No. 117 Kent County, Department of Emergency Planning and Operations
-Mr. E. C. Golder, Director 38 The Green Dover, Delaware 19901-M:nual No. 118 Westinghouse Electric Company T. G. Satryan, Manager.
Operating Plant Projects - NSID P. O. Box 2728 Pittsburg, PA 15230 Manual No. 119 Porter' Consultants 125 Argyle Road Ardmore,-PA 19003 Mcnual No. 120 Commanding Officer U.S. Coast Guard Base Gloucester City, New Jersey 08030
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Po VI- 2 1 gure 6-2.2 Manual No. 121 -
. Manager Environmental Division- -
PSE&G Research Corporation - ' Research and Testing Lab Maplewood 220 Manual No. 122 Conner & Wetterhahn Room 1050 1747 Pennsyulvania Avenue, N.W. Washingten, D.C. 20006 Attention: Mr. Mark Wetterhahn Manual No. 123
-T. Deckard Lead Construction Engineer Hope Creek Generating Station Manual No. 124 P. Kudless Project Construction Manager Hope Creek Generating Station
EP VI- 2 Figure 6-2.3 FIGURE 6-2.3 EMERGENCY. PLAN DISTRIBUTION VERIFICATION SHEET' -
' MANUAL.NO.- REV. REV. REV. -REV. REV. REV.- . REV. .REV. - REV.
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l . EP VI-3 1 l ADMINISTRATIVE PROCEDUPE l EP VI-3 REVIEW OF PLANS AND PROCEDURES ACTION LEVEL This procedure details the methods for performing the annual planning reviews and quarterly telephone list verification. ACTION STATEMENTS.
- 1. The Manager - Nuclear Site Protection shall insure that the Emergency Plan Manuals are reviewed, that all revisions have been made, that the plan and pru edures are accurate and adequate and that agreement between PSE&G and other emergency response groups are adequate.
a) Prior to the annual exercise, manuals located in emergency
-response centers will be reviewed to insure that all revisions have been made.
Other manuals used for implementing the plan will be reviewed as described in EP VI-2 to insure that all revisiorc have been made. b) Following receipt of the critique review comments on the annual exercise, the emergency manuals shall be reviewed and revised as necessary to incorporate substantive drill and exercise critique comments. This review will be documented on Figure 6-3.1. c) Following-the annual exercise, all letters of sgreements between PSE&G and other emergency response groups shall be reviewed. This review will take into account the critique t 1 of 4 Rev. I
EP VI-3 ACTION STATEMENTS (continued) comments from the annual exercise. Biennially all' letters . of agreement will be renewed. This renewal may consist of
- either a letter from the parties to the formal agreement stating that the agreement is satisfactory or a new-formal agreement.
- 2. - The Manager - Nuclear Site Protection shall insure that the-l emergency telephone lists are reviewed quarterly and updated.
This review will be-documented on in accordance with the Inspection Order System. I l-l 2 of 4 Rev. 1 w
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. ' E P VI- 3 Prepared By: ha r-Reviewed By: OIA/[1 n .e d #'E/S E 4 /f //J
# Department Head# Date Reviewed By: [MMcI- -- k 4/f/PJ Nuclear'EmergencyPlanninh-Engineer Date Reviewed By: Aas- >
1 f}ofB % Station. dality Assu ance Review Date SORC Meeting No.: I 8 U' 6ee' Approved By:
/#!7 General _Mapager - Salem " Operations Date Approved By: /# fl Manager - Nuclear Site Protection bate 3 of 4 Rev. 1
Ti EP VI-3 Figure 6-3.~1 FIGURE 6-3.1 .
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DOCUMENTATION.OF REV12WS 19__ SALEM GENERATING SATION Review Performed By- ' Date Signature Annual Manual
. Revision verification
- Annual' EP VI Manual-
~ Review.
Annual Agreement Review Reviewed By: Nuclear Emergency Planning Engineer 4 of 4 Rev. 1 p wv-------owrT -wt- V M-' T e* w-- Vew ,- -- - e v-*- -
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E P VI- 4 ADMINISTRATIVE PROCCDURE
. EP VI-4 PROCEDURES FORMAT
' ACTION LEVEL-This procedure provides format guidance 'for preparers of emergency plan implementing procedures.
-RESPONSIBLE INDIVIDUAL Emergency Plan Procedure preparer.
ACTICN STATEMENT
- 1. GENERAL GUIDANCE Implementing procedures for emergency plan actions shall ,
contain, as appropriate, the following elements: Individual assignment of authorities and responsibilities for performance of specific tasks or staf f position. Protective action levels and protective measures outlined for the identified emergency. Specific actions to be taken by coordinating support groups. Procedures for medical treatment and handling of contaminated individuals. Special equipment requirements for items such as medical treatment, emergency personnel rescue, specific radiation - detection, personnel dosimetry, procedures for making emergency equipment available, plus operating instructions for this equipment, and provisions for its periodic inspection and maintenance. 1 of 8 Fev. 1
' j . E P VI- 4' ACTION STATEMENTS (continued) Identification bf the-emergency communications network,
' including communications required for' personnel notificatiqn and effective coordination of all support groups.
Description of alarm signals in each facility. (Signals for initiating protective measures should be clear and distinct from process or operatiornal alarm system to avoid confusion.) Procedures required to-restore the plant to normal condi-
.tions following an emergency.
Requirements for periodically testing of procedures, communications network and alarm systems to assure that they function properly.
- 2. ' PROCEDURE FORMAT GUIDANCE Procedures should be typed on 8-1/2 x 11 inch paper for ease of use, duplication and preparation.
The words CAUTION, DANGER, WARNING and all actual switch or indicator positions should be capitalized for emphasis. Equipment when specifically identified should oe capitalized (Example: No. 11 Steam Generator). When an uncommon abbreviation is used in a procedure it shall be accompanied by its unabbreviated form the first time it appears. The abbreviation may then be used unaccompanied. Procedure sections should be capitalized and underlined. The following sections should be used in the order provided when applicable): 2 of 8 Fev. 1
EP VI '
' ACTION STATEMENTS (continued)
ACTIONILEVEL - Gives guidance on_ when the procedure should
; be used,- including _ alarms or communi cations. ..
RESPONSIBLE' INDIVIDUAL - Lists -individual (s) by title who
-is responsible for; initiation or implementation of the pro-
~ cedure. This may be included as-a-portion of the action
-statement section. ..
ACTION STATEMENTS - Individual steps necessary to carry out the response required, these steps should be sequentially numbered (1., 2., etc.) and should be written to provide the-following: general guidance, procedural action (s) to be taken-or verification and record of completion of an action or series of actions. LIMITS ON AUTHORITY - Where specific limits on the authority of the responsible individual exist these limits should be clearly described and the chain of authority or reporting clearly indicated. 4 EQUIPMENT REOUIREMENT - This may either be a list of equipment required to perform the procedures or reference to an-attachment, figure or table which provides any equip. ment requirements. COMMUNICATION NETWORK - Describes the communications flow for implementating the procedure and when required the personnel identification methods to be used to insure positive identification of the person (s) making communica-tions. ATTACHMENTS - Lists the attachments which are to be used with the procedure. 3 of 8 Fev. 1
EP VI- 4'
' ACTION STATEMENTS (continued)
- 3. PAGE FORMAT GUIDANCE' Each page of the procedure should be identified by Generic.
Code, Section Number, and Procedure Number (Example: EP IV-3) near the upper right hand corner of the page. Sufficient space should ne allowed above and to the right of the procedure identit er to permit reproduction without loss of the identifier. Each pag.e of the procedure should be sequentially numbered and identify total number of pages in the documents. The total page count should include tables and figures included in the procedure. Attachments should be separately numbered in this same manner. The page numbers should be located at the bottom center of the page. Sufficient space should be allowed below the page numbers to permit reproduction without loss of the page number. Each page of the procedure should indicate the revision. The revision number should be located near the lower right hand corner of the page. Sufficient space should be allowed below and to the right of the revision number to permit reproduction without loss of the revision number. The first page of each procedure should provide generic title (Emergency Procedure or Administrative Procedure), procedure number and procedure title. This should be located near the
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upper center of the first page.
- 4. SIGNATURE BLOCK GUIDANCE A signature block shall be provided at the end of the procedure. This signature block shall be as shown:
4 of 8 Rev. 1
e
., EP' VI- 4 2 .. ,
- ACTION STATEMENTS (continued) l
~
Prepared.By: Name of Preparer . Reviewed By: 1 Department Head Date Reviewed By: Nuclear Ersergency Planning Engineer Date q Reviewed By:- Station-Quality Assurance-R7 view Date (if required see EP VI-2)- SORC. Meeting No.':
- Date Approved: By:
General Manager - Salem Operations Date
- Approved By:
Manager - Nuclear Site Protection Date i l 5 of 8 Rev. 1 f
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- 5. EP VI- 4 ACTION STATEMENTS (continued).
- 15. TABLES AND FIGURES GUIDANCE
~
Tables'will usually consist of information in columns and rows. Each table should be numbered according to procedure section, procedure number, table sequence number -(Example: Table 6-4.1)-and titled appropriately. The number and title should be'placed at the top of the first page of the table. The table identifier (Example: Table 6-4.1) will be placed below the procedure identifier in the upper right hand corner of the page. Example:' EP VI-4 Table 6-4.1-A figure usually will consist of information which'is either graphic or nor. tabular in form. Each figure should be numbered according to procedure section, procedure _ number, figure sequence number -(Example: Figure 6-4.1), and titled appropriately. The figure identifier and title should be placed below-the figure. . Additionally the figure identifier should be placed below the procedure identifier in the upper right hand corner of the page. Example: EP VI-4 Figure 6-4.1
- 6. ATTACHMENT AND ADDENDA GUIDANCE An attachment should be considered to be a removaole part of a procedure and should be used to separate information from the
. body of the procedure which may be either a special case (Example: Telephone Lists) or not necessary for implementing the procedure. Attachments should be sequentially numbered (Example: Attachment 1, Attachment 2, etc.) and identified on each page below the procedure identifier. An attachment should be revised with the procedure to which it is attached.
6 of 8 Rev. 1
EP VI- 4
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ACTION' STATEMENTS (continued) l An. addenda should be. considered to be an attachment which has an independent status (Example: EP Telephone Directofy) and . thus may be referenced by one or more procedures. Addenda
'should be sequentially numbered (Example: Addendum 1, Addendum 2,'etc.) Land identified on each page in the upper right hand corner of the^page. Addenda will be prepared, reviewed and approved'in the same manner as a procedure.
c 7 of 8 Rev. 1
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- EP VI-4 Prepared By: C. A. Burge Reviewed By:
IA - * '- c/A M4~/#I 4///# 3 Department Head # Date Reviewed By: 4 ne t //F//.3 Nuclear [mergency Plannin k Engineer Date Reviewed By: e_# _ 7 )M!& 3 ' Station Quality surance Da'te SORC Meeting No.: f/ d N l Wate' Approved By: / 7/b General kanager - Salem Operations Date Approved By:
/ A , ,
Manager - Nuclear Site Protection Date 8 of 8 Fev. 1
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-E 'EP VI-5 ADMINISTRATIVE PROCEDURE EP VI-5 CONDUCT OF DRILLS AND EXERCISES .
- ACTION LEVEL
- 1. Drill or exercise required to be conducted by an Inspection i 1
Order.
- 2. Drill or exercise required to be conducted as ordered by the
' Manager - Nuclear Site Protection. l ACTION STATEMENTS NOTE Tnis procedure is to be comp,leted by the Nuclear Emergency Planning Engineer.
- 1. If an Inspection Order has been received, record the date and Inspection Order number.
Date Inspection Order No.
- 2. Assign a Coordinator to prepare a scenario, using Attachment 1 of this procedure.
Coordinator
- 3. After review by the Nuclcar Emergency Planning Engineer, submit to the Manager - Nuclear Site Protection for approval and schedule the date the drill is to be conducted, with the concurrence of the General Manager - Salem Operations.
1 of 5 Rev. 2
1 r. r l
~-
EP VI-5 ACTION STATEMENTS (continued)
-4. The coordinator shall assign observers and perform the following: '
a) Brief observers on the approved scenario, including details and information they are to provide to participate during the actual performance of the drill or exercise. b) Assign them to locations. c) Provide each observer-with an Observation Sheet (Attachment 2 of this procedure). NOTE Observers shall normally include Licensed Operators, Emergency Duty Officers, Radiation Protection personnel, and Ouality Assurance personnel, however, other Company employees or consultants may be assigned as observers at the discretion of the Nuclear Emergency Planning Engineer. Off-site organizations may supply their own observers. 5.- As determined for each drill or exercise, notify off-site organizations and/or Company employees of the. drill in advance to confirm their level of participation.
- 6. Conduct the drill or exercise under the following guidelines:
2 of 5 Rev. 2
^ ^
'~ ^
_ -, . . 1 * ^ ' '
"~
-m EP VI-5 l
; ACTION STATEMENTS (continued) 1 a) Announcements should be preceeded and followed by the words:-
~"THISLIS A DRILL, THIS IS A DRILL."
t
, b) During a ~ drill or' exercise, any action to i alter actual plant operating conditions shall; be simulated unless otherwise directed by the General Manager L- Salem Operations.
- 7. -All drill worksheets and/or observation sheets should be collected and reviewed by the Nuclear Energency Planning Engineer.
- 8. The Coordinator shall critique the drill or exercise with observers, and participants.
Complete the Evaluation Report (Attachment 3), , and forward to the Nuclear Emergency Planning Engineer.
- 9. Following a drill or exercise, the Coordinator shall prepare an Exercise Dificiency Sheet and forward - to the Nuclear Emergency Planning Engineer. The Nuclear Emergency Planning j Engineer will submit the Evaluation Report (Attachment 3) and any Exercise Deficiency Sheets (Attachment 4) to SORC within 90 days of the drill or exercise.
- 10. SORC shall review the completed exercise package, including deficiencies, with
- recommendations for resolution.
3 of 5 Rev. 2 i'
r
^ '
EP VI-5
~
ACTION STATEMENTS (continued)
- 11. ' Forward Deficiency Sheets (Attachment 4) to the appropriate personnel for resolution.
- 12. The Nuclear Emergency Planning Engines. shall review and file all completed drill and exercise results and ensure that all deficiencies are adequately reviewed and corrected.
Return-completed copy of this procedure with all attached documents to the Manager - Nuclear Site Protection. Coordinator. Date
-NOTE i Drills and exercises are scheduled in acordance with Table I with referenced procedures and Inspection Order. Numbers.
I i I l l l 4 of 5 Re v. 2 j l
)
- EP VI-5 Signature Page Prepared By: C. A. Sakenas -
Reviewed By: [ OgI-- _
~ 4//f/#3
- s. < <
Department Head Date Reviewed By: [M/e --- d d // s-/p3 Nuclea$EmergencyPdnningEngineer Date. Reviewed By: 7!O O!SS Station Quality Assu nce Review Date (if required s EP I-2) SORC Meeting No.: 8-/77 W /d / Id Date Approved By: /////!O General .Marbger - Salem Operations Date f Approved By: /f S M[ nager-NuclearSiteProtection Date i l 5 of 5 Rev. 2 I-i l . . . . . . . _ . . _ . _ . _ . - . _ _ _ . , . _ . _ _ _ _ - . , . - . - _ . - - . . _ _ . _ . . _ . . - -
* +
-TABLE I <
EMERGENCY PLAN EXERCISES'AND DRILLS EXERCISE TITLE FREOUENCY. REFERENCE
- 1. State of New Jersey /PSE&G Annually I.O. 300073
- 2. State of Delaware /PSE&G Annually I.O. 300072 NOTE Items 1 and 2 may be conducted separately or as a coordinated single exercise.
Items 1 and 2 shall include one night exercise (beginning between 6:00 p.m. and 6i:00 a.m.) within six (6) years. DRILL TITLE FREOUENCY REFERENCE
- 1. Fire Brigade Ouarterly Fire Protection Plan I.O. 800010
- 2. First Aid Team Quarterly Fire Protection- '
Plan I.O. 800012 r
- 3. Medical Emergency (Contaminated Personnel) Annually Radiation Management Corporation I.O. 300067
- 4. Radiological Monitoring Annually I.O. 300068
- 5. Health Physics (Simulated Elevated Samples Only) Semi-Annually I.O. 300069
- 6. Personnel Accountability Annually I.O. 300070 l .
i
' EP VI-5 Attachment 1 DRILL OR EXERCISE SCENARIO SHEET ATTACHMENT 1 ,
l
Title:
Drill or Exercise Date l I.O. Num'oer ! INTENT NOTE: List 1here those outstanding procedures, instructions, equipment and communications, including specific actions of personnel or emergency teams that the drill or exercise is to check. 1 i i _s-l 1 of 2 Rev. 2
.= .
;x '
EP VI-5 Attachment 1 DRILL SCENARIO: WOTEq: (1) Scenario shall be sufficiently detailed such that~ simulated emergency conditions, locations and-reports (inc_luding values) are described' fully enough to enable responsible: actions (may be simulated) to be taken. Include simulated casualties,. local support services support required, personnel emergencies, use of protective clothing, deployment of survey teams.and PIO activities. (2) All~ scenarios shall include the following notes: NOTE 1: Advise the Senior Shif t Supervisor to terminate the drill or: exercise if plant operating conditions warrant such an action. NOTE 2: For all notification to local, . state and federal agencies predetermined statements shall be available to prevent confusion. i
\ -
Review: __ Approval: Nuclear Emergency Manager - Nuclear Site Planning Engineer Protection
~_ l Return completed copy to the Nuclear Emergency Planning Engineer l l
l 2 of 2 Rev. 2 l l
....-...-_.-.,.---.--..--....--I
EP VI-5 Attachment 2
, ~ . .
^ DRILL OR EXERCISE
^
OBSERVATION SHEET ATTACHMENT 2 Drill or Exercise Date: -
-observers 1Name:
~ Observers Location:
Title:
Information to Provide: 4. Time Commenced: Time Terminated: OBSERVATIONS, COMMENTS AND RECOMMENDATIONS NOTE: Observations should include the proper and effective use of procedures, equipment and personnel. i NOTE: Use additiona3 pages as necessary. Signature:
Title:
Return completed copy to the Nuclear Emergency Planning Engineer l Page _ of _ i 1 of 1 Rev. 2 i
EP VI- 5 Attachment 3 DRILL OR EXERCISE EVALUATION REPORT ATTACHMENT 3 Drill or Exercise . Titles- I.O. No.: Exercise or Drill Date: COMMENTS (Using evaluations of observers'and critiques) ) l l DEFICIENCIES Prepared By: Approved By: Dates Nuclear Emergency Planning Engineer Return completed copy to the Nuclear Emrgency Planning Engineer. 1 of 1 Page of Rev. 2
P EP VJ-5 Attachment 4 I EXERCISE DEFICIENCY SHCET ATTACHMENT 4
~
-Title: I.O. No.:
Exercise or Date: Deficiency No. : i Date Noted:- RECOMMENDATION o 4 > SORC Reviewed within 90 days of Exercise CORRECTIVE ACTION Assigned To: Department Date;for Completion: Action Taken: Completed By: Date Completed: NOTE: Return completed Drill Deficiency Sheets to the Nuclear
- j. Emergency Planning Engineer.
Corrective Action Satisfactory Unsatisfactory Manager - Nuclear Site Protection *
. 1 of 1 Rev. 2
EP VI-6 EMERGENCY PROCEDURE EP VI-6 INVENTORY OF EOF SUPPLY LOCKERS
~
ACTION LEVEL ,- Inventory of Emergency Supply Lockers at the EOF will be performed on a quarterly schedule, as required by an Inspection Order, and following use. This will be the responsibility of the Nuclear Energency Planning Engineer. ACTION STATEMENTS
- 1. If an inspection order has been received, record the date and Inspection Order number'at the top of Attachment 1.
- 2. Using Tables 1 - 8 of Attachment 1, perform an inventory of emergency supplies located in the appropriately labeled lockers.-
- 3. Note any discrepencies on Attachment 1. The Nuclear Emergency Planning Engineer is responsible for correcting the noted discrepencies.
- 4. Complete and return one copy of the Inspection Order to the Tachnical Department in accordance with Administrative Procedure No. 10.
Page 1 of 2 Re v. 0
1 EP VI-6 _, Signature Page Prepared By: A {,, Reviewed By: f dA Ab - a _ b paso f hf/5.3 h partment Head [ Dat'e Reviewed By: [IM//- ee % a/f/ps Nuclear' Emergency Plan dng Engineer Date 7!M{#4 Reviewed By: ei -- Station Quality Assura e Revieh Date SORC Meeting No.: , [ D[teI Approved By: // General M bager - Salem Operations Date ( Approved By: /o J Manager - Nuclear Site Protection Date 2 of 2 Rev. 0
TABLE 1 + - EMERGENCY EQUIPMENT INVENTORY STATE LOCKER NOMINAL QUANTITY SPECIAL SHELF ITEM QUANTITY FOUND INSTRUCTION 1 NJ State Emergency' Plan and . Procedures' 1 1 Telephone 935-5003' 1 1- Telephone PL 389 186 1 . 1_ Telephone PL 388 420 J 2 Telephone 93S-7606 1
- - 2 Telephone 935-7607 1
) 2~ Telephone.935-5002 1 2 Delaware State Emergency Plan and Procedures 1 3 EMRAD Radio 1 ( 4 NJ State Radio .1 I 1 l I l
. - - _ = - . _ . . . = .- _ - . . . -
~. _ ..
3
- TABLE 2 * *
,4 EMERGENCY EQUIPMENT INVENTORY
). ' RADIATION' SUPPORT MANAGER NOMINAL. QUANTITY SPECIAL' , SHELF- ITEM OUANTITY FOUND. INSTRUCTION ! 1 Salem Emergency Plan and Procedures 1 2 Clerical supplies - ' 3 Calculational forms
- Station Status Checklist 20
- Dose Assessment (RMS) 20
- Field Monitoring 20
- Dose Calculation Sheet 20
' i.
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- TABLE 3 - -
,\ EMEkGENCY EQUIPMENT INVENTORY RADIATION SUPPORT LOCKER NOMINAL QUANTITY SPECIAL SHELF ITEM QUANTITY FOUND INSTRUCTION
- i. 1 Reference books' -
ll 1 Logbcoks 10 . 2 Clerical supplies - 2, Tape recorder 1 2 Rulers 12 - 3 TI-59 Calculator 1 3 EPZ map 1 1 4 Headsets-(phone) 6 b b l V_ . a c.+,. . .. m-
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' TABLE 4 *
- _ EMF,RGENCY EQUIPMENT INVENTORY-SITE SUPPORT / ENGINEERING SUPPORT-NOMINAL QUANTITY SPECIAL SHELF ITEM QUANTITY FOUND INSTRUCTION 1 Salem Emergency Plan and Procedures 1 1,2 Logbooks 2 1,2- Clerical supplies -
3- Calculational forms operations data 20
- initial contact 20 3 Headsets 6 4 Station diagrams 1
- mylar 1 set i
4 Waste baskets 4 s w-
~ 'd
s TABLE 5 -
' EMERGENCY EQUIPMENT INVENTORY SUPPLY LOCKER NOMINAL OUANTITY SPECIAL SHELF ITEM OUANTITY FOUND INSTRUCTION 1 First aid kits 4 1 Headsets 6 2 Computer paper -
2 Printer 1 2 Hazeltine terminal 1 4 Logbooks 20 4 Letter pads 20 4 Pens 20 5 File Folders 20 5 Plant drawings 1 set ( I I u_. l l l
TABLE 6 . -
, EMERGENCY EQUIPMENT INVENTORY
' ADMINISTRATIVE SUPPORT MANAGER NOMINAL QUANTITY SPECIAL SHELF ITEM- OUANTITY FOUND INSTRUCTION 1 Registration log 1 1 Name tags 50 2 Petty cash forms 2 pads 2 Clerical supplies -
2 Logbook 1 3 Baskets- 2 3 File folders 12 4 Letter pads 12 4 Bookends 1 box 5 Markers 12 4
a
- TABLE 7 * '
EMERGENCY EQUIPMENT INVENTORY EMERGENCY RESPONSE MANAGER NOMINAL QUANTITY. SPECIAL SHELP ITEM OUANTITY FOUND INSTRUCTION 1 Salem Emergency Plan and Procedures 1
-1 Delaware Emergency Plan and Procedures 1 1 NJ Emergency Paan and Procedures 1 2 Clerical supplies -
3 PA system 1 4 Wastebasket 1
TABLE 8 * ~ s, EMERGENCY EQUIPMENT INVENTORY PUBLIC INFORMATION MANAGER NOMINAL OUANTITY SPECIAL SHELF ITEM OUANTITY FOUND ENSTRUCTIO,,N 1 Salem Emergency Plan and
' Procedures 1 1 Delaware Emergency Plan '
and Procedures 1 1 NJ Emergency Plan and Procedures 1 2 Clerical supplies - 3 EBS radio 1
-4 New Jersey Emergency Plan and Procedures 1 5 Delaware Emergency Plan and Procedures 1 i
t
s EP VI-7
- ADMINISTRATIVE PROCEDURE I EP VI-7 i CONDUCT OF COMMUNICATIONS DRILLS ACTION-LEVEL - '
- l. Communications drill required to be conducted by an Inspection order.
- 2. Communications. drill required to be conducted as ordered by the Manager - Nuclear Site Protection.
' ACTION STATEMENTS-NOTE This procedure is to be completed by the Nuclear Emergency Planning Engineer.-
- 1. If an Inspection Order has been received, record the date and Inspection Order number.
Date Inspection Order No.
- 2. Refer the appropriate attachment to the designated individual using Table 1 as a guide.
- 3. Upon completion of the drill the attachment should be forwarded to the Nuclear Emergency l Planning Engineer for review.
i
- 4. The Nuclear Emergency Planning Engineer will complete and return the I.O. card to the Adminstrative Office - Salem Operations.
- 5. The Nuclear Emergency Planning Engineer is s responsible for ensuring all problems or deficiencies are corrected and documented as soon as possible.
1 of 2 Rev. O
EP VI-7 Signature Page Prepared By: C. A. Sakenas Reviewed By: ( A#A In- 6//rd_3 Department Head Date Reviewed By: M4 ed 4//r/#3 Nuclear Emergency Planning Engineer Dabe Reviewed By: 1j .2.m f g* Station Quality Assurance Date (if required dee EP VI-2 SORC Meeting No.: )j jf _" _ V l. ba[e Approved By: /#/7/[3 Genera [ Manager - Salem Operations Date Approved By: /4 J Manager - Nuclear Site Protection Date l 2 of 2 Rev. O i l _ __.._ _._,___...._ _ ._.__ __.., _ .__ .._ _ ._ _ _ _ __ ._. .J
TABLE I COMMUNICATIONS DRILLS DRILL TITLE _ _ FREQUENCY Attachment _ REFERENCE
- 1. New Jersey and oelaware Monthly 1 I.O.300063 (State, County, & local governments)
- 2. Federal Agencies Quarterly 2 I.O.300064
- 3. Full Fan Out - New Jersey and Annually .3 I.O.3Ca065 s
Delaware
.4. PSEEG' Facilities and Survey Teams Annually 4 I.O.300066 I
l 1
1 EP VI-7 , Attachment'l EMERGENCY PLAN COMMUNICATIONS DRILL WORKSHEET NEW JERSEY AND DELAWARE (STATE, COUNTIES AND LOCAL GOVERNMENTS)
- 1. NEW JERSEY STATE POLICE
- a. Direct Line The Senior Shift Supervisor, or designee, shall initiate a test call for each of the following locations. Repeat the following test message:
THIS'IS A COMMUNICATION TEST DRILL, THIS IS A COMMUNICATION TEST DRILL THIS IS FROM SALEM GENERATING STATION. DO
~~~TnEme [ ~
YOU READ ME LOUD AND CLEAR? THIS IS A COMMUNICATION TEST DRILL. SAT UNSAT CALLER DATE/ TIME Senior Shift Supervisor's -- -- -- --- TSC' . _, , ___, EOF _ -_______ ,,
- b. Secondary Line The Senior Shift Supervisor, or designee, shall initiate a test call to the New Jersey State Police Dispatcher on 882-2000. Repeat the test message in 1.a above.
Caller . Person Contacted ___ , Time /Date __ Unsat* Sat
*If unsat describe ' problem at bottom of page, s_
1 of 8 Rev. 0
EP VI-7 Attaqhment 1 1
- 2. DELAWARE STATE POLICE
- a. Direct Line
.The: Senior Shift FJpervisor or designee shall initiate a' test call from.each of the following locations. Repeat the test message in 1.a.
SAT UNSAT, CALLER DATE/ TIME Senior Shift Supervisor's - - ---- _ - - - - - . . - TSC ___-__ .-- - EOF _ _________
- b. Secondary Line The Senior Shif t Supervisor or designee shall initiate a test call to the Delaware State Police on 302-736-5851. Repeat the test message in 1.a.
Caller . ,_______ _ Person Contacted ,_ Time /Date Unsat* _,_ Sat , 1 s.s
*If unsat describe problem at bottom of page.
2 of 8 Rev. 0
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EP VI-7 Attachment 1
- 3. SALEM COUNTY EOC
- a. Direct Line The Senior Shift Supervisor or designee shall initiate a test call from each of the following locations., Repeat the test message in 1.a.
SAT UNSAT' _ CALLER _ DATE/ TIME Senior Shift Supervisor's ----- --------- -. ----- TSC _______ _____ EOF
- b. Secondary Line The Senior shift Supervisor or. designee shall' initiate a test call to the Salem County Fire Dispatcher on 935-4505. Repeat the test message in 1.a.
Caller _ , , _ _ _ ____,,,_ Person' Contacted ,,__ ____,,,_ Time /Date ,,,_ _, Unsat* ,___ Sat , (, *If unsat describe problem at bottom of page. L 3 of 8 Rev. O
EP VI-7 Attachment 1 , 3 . 4.~CUMBERLAND COUNTY EOC
~
- a. Primary (Direct Line)
The Senior Shitt Supervisor or designee shall initiate a test call from each of the following locations. Repeat the test message in 1.a. SAT UNSAT_, _ CALLER DATE/ TIME Senior shift Supervisor's ___,, _ Office TSC .___ _ _ , _ EOF ,,, _
- b. Secondary Line The Senior Shift Supervisor or designee shall initiate a test call to the Cumberland County on 455-8500. Repeat the test message in 1.a.
Caller __ , __ Person Contacted __ ______ 4 {. s-
. Time /Date . _ _ _ _ ,
Unsat* __ Sat
*If unsat describe problem at bottom of page.
4 of 8 Rev. 0
-. ~ . . . _ . . ~ . -. - - . . . . . . . -. . - . . - . . . - - . . . . - . . . . ..---.. -. ..- ._..-
u- d*
- EP VI-7 Attachment 1
- 5. NEW CASTLE COUNTY EOC a.. Primary-(Direct Line)
The Senior Shift Supervisor or designee _shall initiate a test - a call from each of the following locations.. Repeat the test . message in 1.a. SAT UNSAT CALLER - DATE/ TIME Senior Shift Supervisor's 1 Office TSC EOF
- b. Secondary Line the Senior Shif t Supervisor or designee shall initiate a test call to New Castle County on 302-571-7949. Repeat the test message in 1.a.
Caller f Person Contacted. Time /Date Unsat* Sat l l l I I i
*If unsat describe problem at bottom of page.
5 of 8 Rev. O r I l l- - . 4 -4,~. _ _ .- . , - _,._. ._-m...._....,,,,,,_.,.m, . r._.,-. _... . , _ . . , , , . _ -.m._m - . . , _ , _ . _ , . . . _ _ . . . .
v e wt-' EP VI-7 Attachment.1
- 6. KENT COUNTY EOC
^
- a. Primary (Direct Line)
'The Senior' Shift Supervisor or des'ignee shall initiate a test call from each of.the following locations. Repeat the test message in 1.a.
SAT UNSAT_ CALLER _ DATE/ TIME Senior Shif t . Supervisor's ~ ~ ~ ~ ~ ~~~ ~ ~ Office TSC _ _ _ _ _ _ EOF __
- b. . Secondary Line The Senior Shift Supervisor or designee shall initiate a test
. call to Kent County on 302-678-9111. Repeat the test message in.1.a.
Caller _ _ _ _ _ _ _ _
'( Person Contacted _ _ _ _
Time /Date ,__ _ _ _ _ _ _ Unsat* Sat i s..
*If unsat describe problem at bottom of page.
i 6 of 8 Rev. 0
_ _ . . _ . - m EP VI-7 Attac,hment 1
- 7. LOWER ALLOWAYS CREEK TOWNSHIP
- a. Primary (Direct Line)
The Senior Shift Supervisor or. designee shall initiate a test call from each of the following locations. Repeat the testi message in 1.a. SAT- UNSAT_ _ CALLER DATE/ TIME Senior Shift Supervisor's _ _ _ _ _ _ _ Office TSC EOF , _ ____ b.. Secondary Line The Senior Shift Supervisor or designee shall initiate a test call to-the LAC Dispatcher on 935-7300. Repeat the test message in 1.a. Caller _ ____,,_ __ _ _ _ , , Person Contacted
-Time /Date _ __ _ _ _ _ _ _ _ _ _ _
Unsat* , Sat ,,, J
*If unsat describe problem at bottom of page.
7 of 8 Rev. 0 1
. . , . , , , _ . , . . . . . - - . . - , , , , - - - - - ---- - - - - -- - -~ - -~ - - - - ~ ~ - - - - - ~ ~ ' ~ ' ~ ' '
EP VI-7 Attachment 1 R. NOAA WEATHER STATION (WILMINGTON AIRPORT) The' Senior Shif t Supervisor or designee shall initiate a test call to the NOAA 9eather Station on 302-323-2280. Repeat the tost message in 1.a. . Caller _ _ _ , , _______, Person Contacted ,,,_ __,,,__ Time /Date __,,,,_ , , , , , _ Unsat* Sat (
*If unsat describe problem at bottom of page.
Forward completed forms to the Nuclear Emergency Planning Engineer. Reviewed By: _ _ , Date: __ _ ___, 8 of 8 Rev. 0
EP VI-7 Attachment 2 EMERGENCY PLAN COMMUNICATIONS DRILL WORKSHEET FEDERAL AGENCIES
- l. NRC~(ENS) DIRECT LINE .
The Senior Shift Supervisor or designee shall initiate a test call from each of the following locations. Repeat the test message in 1.a. THIS.IS A COMMUNICATION TEST DRILL, THIS IS A COMMUNICATION TEST DRILL. THIS IS - - - -- - FROM THE SALEM GENERATING STATION. DO YOU READ ME LOUD AND CLEAR?
- THIS IS A COMMUNIATION TEST DRILL.
SAT UNSAT CALLER DATE/ TIME Senior shift Supervisor's _ _ _ _ _ _ _ _ , _ _ 4 Office No. 1 Control Room - - - ----- - - b No. 2 Control Room _ __ , _ _,_, , TSC ___ _ , , _ _ _ _ ___ _ _ _ , , EOF ,__ __ _ ___,,__ ., _ , , _ _ 4
*If unsat describe problem.
1 of 5 Rev. 0
)
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EP VI-7 Attachment ~2
- 2. NRC (HPN) DIRECT LINE The Senior shift Supervisor or designee shall. initiate a test call ~from each of the following locations. Repeat the test message in 1.a. ,
SAT UNSAT CALLER DATE/ TIME
- TSC _ _ _ _ _ _
. Control Point _ _ _ _ _
EOF ___ __ _ _ _ _ __
*If unsat describe problem.
r 2 of 5 Rev. O _ .. m. . _ _ _ , , _ _ . - . _ - - - - . . _ . _ . _ _ - - . - - - - . _ _ . _ _ . . _ , , _ , . - _ _ _ - - . - , . _ . . , , _ _ . . , _ , .
EP VI-7 , Attachment 2
- 3. U.S.' DEPARTMENT OF ENERGY (FRMAP) BROOKHAVEN AREA The Senior Shif t' Supervisor or designee shall initiate a test call to the U. S. Department.of Energy (Brookhaven) at (516) 282-2200. Repeat the message in 1.a. ,
Telephone Number Called Shift Clerk Person Contacted Time /Da te Unsat* Sat
*If unsat describe problem.
3 of 5 Rev. 0
a EP VI-7 Attaohment 2
- 4. U.S. COAST GUARD The Senior shif t Supervisor or designee shall initiate a test call to the U.S. Coast Guard-Station (Gloucester) at (609) 455-1370. Repeat-the test message in 1.a. ,
Telephone Number Called Shift Clerk Person Contacted Time /Date Unsat* Sat i. ]
*If unsat describe problem.
s_. 4 of 5 Rev. 0
EP VI-7
, Attachment 2 i
- 5. INGESTION STATES (PENNSYLVANIA AND MARYLAND CIVIL DEFENSE)
The Senior Shift Supervisor or designee shall initiate a test call to the Maryland Civil Defense at (301)4 86-4422 and Pennsylvania Emergency Management Agency at (717) 7.83-8150.. Repeat the test message in 1.a. - PENNSYLVANIA MARYLAND Telephone Number Called Shift Clerk Person Contacted Time /Date Unsat* Sat , .Unsat* Sat
*If unsat describe problem'.
I Reviewed By: Date: . 5 of 5 Rev. O
EP VI-7 Attachment 3 ) EMERGENCY PLAN COMMUNICATIONS DRILL WORKSHEET-FULL FAN OUT - NEW JERSEY AND DELAWARE I ~
\
A. . Nuclear Emergency Planning Engineer contacts both states at least l one week prior to drill the full fan out to inform them of the-upcoming drill'.
- l. State of New Jersey Pers6n Contacted ~~~ Contac Ed By Time /Date
- 2. State of Delaware
~~~
Persdd CodEEdted~ Contacted By T Ed[Date t B.- Contact the states and repeat the following-message: THIC IS A TEST DRILL,.THIS IS A TEST DRILL. THIS IS TtIEm'e) AT SALEM NUCLEAR GENERATING STATION. PLEASE (TitfE) INITIATE A FULL FAN OUT COMMUNICATIONS TEST OF YOUR AGENCIES. THIS IS A TEST DRILL. CONTACT CALLER TIME /DATE
- 1. -New Jersey State __ ,_ _ _ _ __,_ __ __
Police Primary: Direct Line Secondary: 882-2000 2.- Delaware State ------ - - - - . - Primary: -(Direct Line) Secondary: 302-736-5851 , Return this completed form to the Nuclear Emergency Planning Engineer. Reviewed By: _ . Date 1 of 1 Rev. O _ . _ . _ _ . . _ _ - . - _ . . - . ~ . - _ _ , __-___.__ _._- _ . . _ . . . , . _ . _ . . . _ . . , . . . _ . . . _ _ . _ _ _ _ _ _
.- .-. .~ . , _ .
<EP VIL7 -
- Attachment 4 EMERGENCY PLAN COMMUNICATIONS DRILL WORKSHEE1 PSE&G FACILITIES AND SURVEY TEAMS
~
~
- 1. FACILITIES
~
The Shift Supervisor or designee shall initiate phone calls to-each of the.below listed facilities using the conference lines. Repeat'the-following message: THIS IS A COMMUNICATIONS TEST, THIS IS A COMMUNICATIONS TEST.
, DO YOU READ ME LOUD.AND CLEAR?
THIS IS ___fn_ame) THIS IS A COMMUNICATION TEST. LINE** SAT UNSAT CALLER CONTACTED TIME /DATE TSC/ Senior Shift ~~~~~~ Supervisor
'TSC/ Senior Shift ~~~ ~~~~ "~ ~~~~~~~~~~~
Supervisor / Newark
~
TSC/No. 1 Control ~~~ Room
~~
TSC/No. 2 Control _____ _ _ _ _ __ , _ ___ Room TSC/ Senior Shift ~~~~ ~ Supervisor / EOF. ~ ~~~~ 4 t
*If unsatisfactory state reason.
** Arrangement should be made for third party assistance, where necessary.
1 of 2 Rev. 0
- - . _ . _ . . . . -. _ _-....~ -.-. _ _ _ . _ . _ _ - . . . _ _ _ _ .. -
{ 4 EP VIr7 - Attachment 4
, '2. SURVEY TEAMS Have Radiation Protection dispatch four one man survey " teams" to various areas of the building. Attempt to contact each team using normal plant communications. Each team must be contactdd at least twice (at two different locations) for a minimum of eight
-contacts. The areas must include each Reactor Building, the Auxiliary Building and each Fuel Handling'-Building.
All abortive attempts must be logged and indicated as unsatis-factory. AREA PHONE EXT. PERSON DATE/ BUILDING ELEV. OR PA ' SAT UNSAT CALLER CONTACTED TIME l-2 3 4
- 5. -
(-
. g--
~7 8 ..
- 9 O
i
*If unsat state reason.
, = T' # sed all completed forms to the Nuclear Emergency Planning Engineer. Rov k wed By: _ _ _ _ _ ______ Date: _ _ _ , 2 of 2 Rev. 0
- . - - - . _ . = . - _ . - - - - . - . - - . ~ . - . - - . - - . . - - . . - . - - . . -}}