ML20028C377
| ML20028C377 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/16/1982 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20028C374 | List: |
| References | |
| PROC-821216, NUDOCS 8301070558 | |
| Download: ML20028C377 (85) | |
Text
CH NGE TO THE YANKEE EMERGENCY PLAN - IMPLEMENTING PROCEDURES 1.
Following the tab TABLE OF CONTENTS remove existing table of contents and insert attached TABLE OF CONTENTS Rev. 19 dated 12.16.82.
2.
Following the tab UNUSUAL EVENT remove existing procedure and insert attached procedure dated 12.82, Revision 5.
3.
Following the tab ALERT remove existing procedure and insert attached procedure dated 12.82, Revision 5.
4.
Following the tab EVALUATION OF RADIOLOGICAL DATA remove existing procedure and insert attached procedure dated 12.82, Revision 3.
4 0301070550 830104 PDR ADOCK 05000029 PDR p
December 16, 1982 Rev. 19 YANKEE NUCLEAR POWER STATION IMPLEMENTING PROCEDURES TO THE EMERGENCY PLAN P
TABLE OF CONTENTS TABLE OF CONTENTS Rev. 18 CONTACT LIST Rev. 2 IMPLEMENTING PROCEDURES Classification of Emergencies O P-3300 Rev. 2 4
Unusual Event O P-3301 Rev. 5 Alert O P-3302 Rev. 5 Site Area Emergency OP-3303 Rev. 5 General Emergency OP-3304 Rev. 5 l Evaluation of Radiological Data O P-3310 Rev. 3 Emergency Off-Site Radiation Monitoring O P-3311 Rev. 1 j
Activation of The Alternate Emergency Opera-tions Facility OP-3350 Rev. 0 Emergency Deescalation Procedure OP-3321 Rev. 0 Emergency Radiation Exposure, Control OP-3330 Rev. 1 i
Emergency Medical Procedure OP-3305 Rev. 1 Security Force Actions Under Emergency Conditions O P-3344 Rev. 1 Release of Public Information Under Emer-gency Conditions O P-3343 Rev. 0 Coordination and Communications During an Emergency O P-3345 Rev. 1 Vital Computer System Operation Under Emergency Conditions O P-3346 Rev. 0 SUPPLEMENTAL PROCEDURES Emergency Plan Training O P-3340 Rev. 0 Emergency Preparedness Exercises & Drills O P-3341 Rev. 0 l
Emergency Equipment Readiness Check OP-3325 Rev. 2 L
~
Proc. No.
OP-3301 Rev. No.
5 (Major)
Date 12/82 UNUSUAL EVENT l
SCOPE To outline the actions required of plant personnel, visitors, and contractors i
when an Unusual Event is declared.
ENCLOSURES Withhold Attachment OP-3301 - Pg. 1 - Rev. 5 From Public Disclosure OP-3301 - Pg. 2 - Rev. 1 ORM.AT10,
l Appendix I - Pgs. 1 Rev. 5 r. CFR 23901 j
Appendix II - Pg. 1 - Rev. 5 10 Appendix III - Pg. 1 - Rev. 4 Appendix III - Pg. 2 - Rev. 5 Appendix IV - Pg. 1 - Rev. 5 DISCUSSION An Unusual Event is defined as any plant-related event which indicates a potential degradation of plant safety margins which is not likely to affect personnel on-site or the public off-site or result in radio-active releases requiring off-site monitoring.
Unusual Event conditions have not caused serious damage to the plant and may not require a change in operational status.
The basic shift complement is able to deal with Unusual Event conditions.
The On-Call TSC Coordinator and the On-Call Emergency Coordinator will be notified by the radio paging system and will report to the plant. Addi-I tional plant personnel will be notified and will respond at the discre-tion of the Shift Supervisor / Plant Emergency Director.
The Manager of Operations will be notified.
The decision to make an immediate initial declaration rests with the Shift Supervisor (Emergency Director) or in his absence the Supervisory Control Room Operator, who, in turn, instructs Control Room personnel to activiate the notification system. On-duty personnel are assigned to functions as required. Notification is made to off-site authorities as delineated. Additional members of the plant organization, including top management, are notified and augment on-duty personnel as necessary.
l PROCEDURE 1.
Select the appropriate appendix checklist from the following:
i Appendix I - Shift Supervisor / Plant Emergency Director Appendix II - Security Appendix III - Technical Support Center Coordinator i
Appendix IV - Emergency Coordinator
~
1 r_
_ OP-3301 Rev. 1 NOTE:
Actions required in each appendix may be assigned by the responsible individual to other personnel as appropriate. The designated individual, however, has the overall responsibility for the execution of this checksheet.
2.
Proceed with the implementation of the appropriate appendix and record time and initials as required.
FINAL CONDITIONS As specified in the appropriate appendices.
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APPENDIX I OP-3301 Appendix I Page 1 Rev. 5 UNUSUAL EVENT - PLANT EMERGENCY DIRECTOR IMMEDIATE ACTIONS:
1.
Instruct control room personnel to use the page system and make the following announcement:
" Unusual Event, Unusual Event, Unusual Event (dest. ribe conditions and affected area) All personnel without emergency duties report to your department area. All visitors and contractors report to the Gatehouse".
REPEAT THE ABOVE ANNOUNCEMENT SUBSEQUENT ACTIONS Time / Initials 1.
IF AFTER NORMAL WORKING HOURS a.
Initiate a page on 01 and 10 on the plant radio 1
paging system.
/
b.
Instruct the SAS operator on the class of emergency and have him initiate Appendix II.
/
2.
If the emergency condition has de-escalated to an Unusual Event classification, then instruct control room personnel to use the page system to make the following announcement:
/
"We are de-escalating to an Unusual Event, emergency status. (describe the reason for the change in emer-gency status). All plant personnel report to your appropriate Emergency Center Coordinator for re-assign-ment."
REPEAT THE ABOVE ANNOUNCEMENT l
NOTE:
If the emergency condition has de-escalated to an Unusual Event classification, DO NOT instruct the i
l SAS operator to re-initiate Appendix II.
3.
Notify the Massachusetts and Vermont State Police within 15 minutes by depressing 222 on the Nuclear Alert System (NAS) or utilizing the commercial telephone (see OP-Memo 20-4 for numbers). After communi-cations have been established, make one of the following announce-f/lIthhcid Attachment i
Ihm Public Disclosum 10 pr n a 'w^^ "in"rw-ATION
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--m OP-3301 Appendix I Rev. 5' either:
If the event has terminated, OR:
If the event is still stabilized and below the in progress:
initiating EAL:
I a.
"This is Yankee Nuclear Power l
a.
"This is Yankee Nuclear Station, in Rowe, MA:
l Power Station in Rowe, MA" b.
"We have had an emergency con-b.
"We have declared an Unusual dition which was terminated Event because (indicate the prior to classifying".
initiating condition per OP-l 3300".
c.
"I repeat, this is Yankee Nuclear c.
"The plant is (pick one)
Power Station.
Please acknow-ledge with your name".
1.
Continuing normal oper
-ation 2.
Reducing present power levels d.
VT:
3.
Shutdown Name of Dispatcher d.
"A release (pick one) 1.
Is anticipated MA:
2.
Is in progress, or Name of Dispatcher 3.
Is not expected" e.
"Present meteorological conditions indicate (provide wind speed and direction from (degrees)".
f.
"At the present time we recommend no protective action".
l g.
"I repeat, this is Yankee Nuclear Power Station.
Please acknowledge with your name".
l VT.
l Name of Dispatcher I
l MA:
l l
Name of Dispatcher
,s
, s Re f which message is used, complete this ggDR r required procedures.
igdC g mergency condition has de-escalated'to an U
usual Event classification, then request the TTg Emergency Coordinator to notify the appropriate off-site authorities of the change:
_ OP-3301 Appendix I
~
Rev. 5 Time / Initials 4.
WITHIN ONE HOUR OF THE DECLARATION OF THE EMERGENCY, designate an individual to notify the NRC on the Emergency Notification System (RED PHONE). Maintain an open communi-cations channel on this line.
Tnis channel will be closed only when allowed to do so by the NRC.
/
NOTE:
If the Emergency Notification System (red phone) is disabled, then use the following commercial telephone lines to notify NRC Operation Center:
a.
Dial 202-951-0550 0_R b.
Dial 301/427-4056 5.
As soon as contacted via the state notification fan-out process, the Departments of Public Health of Vermont and Massachusetts will call the plant.
Be prepared to provide the following infor-mation if known and appropriate upon request:
/
a.
Name of caller; b.
Time and class of emergency; j
c.
Type and quantity of release, height of release, and estimated duration / impact times; d.
Prevailing weather conditions (wind velocity, direction, temperature, atmospheric stability, form of precipitation, if any);
e.
Projected dose rates at 0.5 miles from the site; f.
Emergency response actions underway; and g.
Recommended protective actions based on the combination of all in plant indications, release parameters, and off-site radiological assessment results.
NOTE:
Once the Emergency Coordinator has reported to the plant, transfer the responsibility for implementation of Step 5 under Subsequent Actions to him.
6.
Inform the TSC Coordinator of current plant status and discuss required actions to terminate the event. Direct the activities of the emergency response organization unless otherwise directed by the TSC Coordinator.
/
7.
Inform the Manager of Operations of the incident.
/
NOTE:
Any further updates to the Manager of Operations after the initial notification will be provided by the TSC Coordinator.
8.
Request assistance of outside agencies (fire, law enforcement or medical rescue personnel and related equipment) as needed Withholdo Anachmentent. See EmergencyLPlan Implementing Pro-ceduregManualforphonenumbers.
From Public miscicante
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A0..CF-R-E.790 iNFORMATiGN OP-3301 Appendix I Rev. 5 Time / Initials a.
Fire
/
b.
Medical
/
c.
Law Enforcement (coordinate with the Security Shift Supervisor)
/
9.
Re-evaluate the emergency classification and if conditions warrant, escalate to a higher classification.
/
NOTE:
If conditions warrant escalation to a more severe class, immediately instruct the SAS operator as to the appropriate notification prccess.
10.
If the event produces abnormal in plant radiological conditions, direct the shift Radiation Protection technician and the Auxili-ary Operator to evaluate the situation. (Normally the R.P. tech-nician will initiate the collection and analysis of Primary Vent Stack and/or Vapor Container samples (OP-9450) and the Auxiliary Operator will initiate a Control Room habitability study), App.
VI of OP-3302, 3303 or 3304).
/
11.
In the event that it becomes necessary, the Super'visory Control Room Operator or the Shift Technical Advisor will perform off-site dose assessment determinations.
FINAL CONDITIONS 1.
When the Unusual Event is terminated, announce it on the plant page system.
/
2.
Summarize all actions and resultant conditions in the Shift Supervisor's Log.
/
Completed by:
Date/ Time:
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APPENDIX II OP-3301 Appendix II UNUSUAL EVENT - SECURITY Rev. 5 Time / Initials NOTE:
Applicability of this Appendix is restricted to backshifts, weekends, or holidays only.
During normal shifts, response actions would be initiated as directed When notified by the Shift Supervisor, or, in his absence, the Supervisory Control Room Operator of Unusual Event Conditions, the guard at the SAS shall:
1.
Inform the on-duty Security Lieutenant of the Unusual Event condition and of the immediate need for initiation of OP-3344,
" Security Force Actions Under Emergency Conditions"
/
2.
Stand by to receive incoming calls from the Emergency Response Personnel, a.
Pick up the incoming call at the SAS by dialing 90 and answering:
" Yankee Atomic, (your name)"
/
NOTE:
DO NOT linger on the phone as more calls will be coming in.
Take the name of the responder, record the time, on OP-Memo 2E-4, Attachment "A", Page 2, that he called and relay to him the information adjacent to his name.
b.
If the re vonder wishes to speak to the Centrol Room, transfer him to 236, 237 or 238.
Inform the Control Room who is on the line and hang up.
/
c.
Answer the next call.
/
3.
When specifically requested to recall additional Operations Support Center Personnel initiate call-in in accordance with the OP-Memo 2E-4 and give the following message:
"This is Officer (your name) at Yankee Rowe. We have an unusual Event condition.
Please report to the Operations Support Center.
/
FINAL CONDITIONS 1.
Return this sheet to the TSC Coordinator.
/
Date/ Time:
Withh0gplgted by-- !!Ochment Froni PulAiu Dim!cstire Ob 2730j,N'f g g N
APPENDlX III OP-3301 Appendix III Rev. 4' Page 1 UNUSUAL EVENT - TECHNICAL SUPPORT CENTER C0ORDINATOR IMMEDIATE AND SUBSEQUENT ACTIONS Time / Initials l'.
Assess the situation based on the information supplied by the Plant Emergency Director and assure all necessary plant re-sources are applied to the event.
/
NOTE:
For_backshifts, weekends or holidays, the TSC Coordinator will be paged through activation of the plant radio page system.
In response to this page, the TSC Coordinator should complete the following steps in addition to Step 1 above:
a.
Immediately contact the' plant and identify the emergency status, b.
Discuss plant status with the Shift Supervisor / Plant Emergency Director.
c.
Identify a list of which Technical Support Center Emergency Re-sponse Personnel (those on pagers) who should be requested to report versus remain on " standby" as they call in.
d.
Report to the TSC.
2.
Assume responsibility for completing the subsequent actions of the Plant Emergency Director's duties if not already completed.
/
3.
If plant conditions require escalation to a more severe emergency class, ensure that the following actions are completed:
a.
Massachusetts and Vermont State Police Agencies have been notified of the change in emergancy status via Nuclear Alert.
/
b.
The NRC has been notified of the change in emergency status.
_/
c.
Sufficient emergency response personnel have been notified to augment plant manpower needs.
/
NOTE:
If plant conditions have de-escalated to an Unusual Event emergency status, direct TSC staff in recovery actions as necessary.
4.
Review and,appreve any public information statements to be made on the event by the Manager of Public.Information.
/
NOTE:
If the event has de-escalated to an Unusual Event from a higher classification, the responsibility of,
Withhokl att gggate Management.
Step 4 may be assume f-sure From ruolic Di n
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o APPENDEX III OP-3301 Appendix III
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Rev. 5 Page 2 FINAL CONDITIONS 1.
Determine if a written report is required by the NRC.
NOTE:
If a written report is required by the NRC, advise the States that a written report will l
follow the verbal close-out in Step 2 below:
2.
Provide verbal dose out of event with off-site authorities as follows:
a.
NRC
/
l b.
State of Vermont
/_
c.
State of Massachusetts
/
l 3.
Provide four (4) copies of written report, if required, to the following off-site authorities:
a.
Commissioner of Public Safety - State of Vermont b.
Director of Civil Defense - State of Massachusetts OR i
De-escalate the emergency classification based on changing plant conditions. (0P-3321, " Emergency De-escalation Procedure").
Completed by:
Date/ Time:
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Withhold Atiochment From Public Disclosure 10'CFR 2.79O WORWN
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APPENDIX IV OP-3301 Appendix IV UNUSUAL EVENT - EMERGENCY C0ORDINATOR Page l' Rev. 5 IMMEDIATE AND SUBSEQUENT ACTIONS:
Time / Initials 1.
Assess the situation based on the information supplied by the Emergency Director and coordinate communications with off-site i
authorities.
/
NOTE:
For backshifts, weekends or holidays, the Emergency j
Coordinator will be paged through activiation of the plant radio page systems.
In response to this page, the Emergency Coordinator should complete the follow-ing steps in addition to Step 1 above.
a.
Immediately contact the plant and identify the emergency status.
I b.
Discuss plant status with the Shift Supervisor / Plant Emergency Director (or his designate).
c.
Identify a list of which Emergency Operations Facility staff (those on pagers} should be required to report versus remain on " standby" as they call in, d.
Report to the TSC.
i 2.
Augment plant manpower as requested by the TSC Coordinator and the Shift Supervisor / Plant Emergency Director.
/
NOTE:
If plant conditions have de-escalated to an Unusual Event emergency status, coordinate manpower resources in conjunction with re-covery operations.
3.
Notify ANI at 1-203-677-7305.
Supply as much information as possible.
4.
If plant conditions warrant re-classification to a more severe classification, report to the EOF; implement appropriate pro-cedures.
/
5.
Standby and continue to assist the TSC Coordinator and Shift Supervisor / Plant Emergency Director until the event is terminated.
/
NOTE:
If plant personnel have been requested to standby until further notice and conditions warrant termi-nation of the emergency status, ensure that these personnel have been notified.
FINAL CONDITIONS 1.
Direct the appropriate personnel to restore all emergency
,7_
equipment to its normal readiness state.
/
Complygthhold Attachment Date/ Time-From Public Disclosure 10 CFR 2.790 INFORMATION
Proc. No. OP-3302 Rev. No.
5 Date 12/82 ALERT SCOPE To outline the actions required of plant personnel, visitors, contractors, and other affected personnel when an Alert is declared.
ENCLOSURES OP-3302 - Pg. 1 - Rev. 5 Withhold Attachment p
xI Pgs. 1 Re. 3
$"N II -$: !~2 ~e""5 From Public Disclosure
~
Appendix II - Pg. 2 - Rev. 4 Appendix III - Pgs. 1 Rev. 5 10 CFR 2.790 INFORMATION Appendix IV - Pgs. 1 Rev. 5 Appendix V - Pgs. 1 Rev. 5 Appendix V Pgs. 1 & 3 - Rev. 1 Appendix V Pg. 2 - Rev. 5 Appendix V Pg. 1 - Rev. 5 Appendix V Pg. 1 - Rev. 1 Appendix V Pg. 1 - Rev. 5 Appendix V Pg. 2 - Rev. 1 Appendix VI - Pg. 1 - Rev. 5 OPF-3302.1 &.3 - Original OPF-3302.2;.4
.6
- Rev. 5 DISCUSSION An Alert is defined as an indication of a substantial degradation of plant safety margins which could affect on-site personnel safety, could require off-site impact assessment, but is not likely to require off-site public protective action.
An Alert requires action beyond the normal capability of the basic shift complement.
Plant response and off-site notification associated with this event classfication will assure that sufficient emergency response personnel are readily available to activate the Technical Support Center (TSC) and the Operations Support Center (OSC). The Emergency Operations Facility (EOF) will be activated with the Emergency Coordinator and sufficient emergency assistance personnel to assess off-site radiological impact.
All personnel with plant emergency assignments who are off-site at the declaration of an emergency shall report to the Emergency Coordinator located in the EOF and obtain authorization to enter the plant protected area.
The decision to make the initial declaration rests with the Shift Supervisor / Plant Emergency. Director or in his absence the Supervisory Control Room Operator.
Prompt notification is made to off-site authorities.
Public information concerning the event will be provided via appropriate an"Withh'ld. Attachment d
From Public Disclosure 10 CEB 2.Z90 JNFORMAT10N
- OP-3302 Rev. 1, PROCEDURE 1.
Select the appropriate appendix checklist from the following:
Appendix I Shift Supervisor / Plant Emergency Director Appendix II Security Appendix III Technical Support Center Coordinator Appendix IV Operations Support Center Coordinator Appendix V Emergency Coordinator Appendix V-1 Radiological Evaluation Assistant Appendix V-2 Communications Assistant Appendix V-3 Manpower Assistant Appendix V-4 Coordinators Assistant Appendix VI Radiological Habitability Assessment NOTE:
Actions required in each appendix may be assigned by the responsible individual to other personnel, as appropriate. The designated individual, however, has the overall responsibility for the execution of his checksheet.
2.
Proceed with the implementation of the appropriate appendix and record time and initials as required.
FINAL CONDITIONS As specified in the appropriate appendices.
Withhold Attachment blic Disclosur.s 10 FR 2.790 INFORMATLO
OP-3302 Appendix I Rev. 5 APPENDIX I SHIFT SUPERVISOR / PLANT EMERGENCY DIRECTOR IMMEDIATE ACTIONS IF NORMAL WORKING HOURS Instruct control room personnel to make either announcement 1 or 2:
1.
If the AARM is less than 50 mr/hr (0.5 x 102) announce:
a.
" ALERT, ALERT, ALERT" b.
"(describe condition and affected area)"
c.
All personnel without emergency duties report to your departmental areas. All contractors and visitors report to the Gatehouse.
d.
Repeat the above announcement.
2.
If the AARM is greater than or equal to 50 mR/hr (0.5 x 102) announce.
a.
" ALERT, ALERT, ALERT" b.
"(describe condition and affected area)"
c.
All personnel without emergency duties evacuate the site.
Repeat The Announcement Then: SOUND THE EVACUATION ALARM NOTE:
If plant conditions have de-escalated from a higher emergency classification, DO NOT repeat the above; instead, instruct control room personnel to use the page system to make the-following announcment:
"We are de-escalating to an Alert Emergency. (describe the reason for the change).
REPEAT THE AB0VE ANNOUNCEMENT SUBSEQUENT ACTION 1.
IF AFTER NORMAL WORKING HOURS Time / Initials a.
Initiate a page on 01 and 10 on the plant radio system.
/
N1Ig trgt{@ChAllMtor on the class of emergency
/
havehiminiti_ ate,.gpendixII.
% r..From Public D,m.a 10VER 2.790 INFORMAT!ON
- OP-3302 Appendix I Rev. 3 2.
Notify the Massachusetts and Vermont State Police within 15 minutes by depressing 222 on the Nuclear Alert System (NAS) or utilizing the commercial telephone (see OP-Memo 2U-4 for numbers). After communications have been established, make one of the following announcements:
either:
If the event has OR:
If the event is still in terminated, stabilized progress.
and below the initiating EAL:
a.
"This is Yankee Nuclear Power a.
"This is Yankee Nuclear Power Station in Rowe, MA" Station in Rowe, MA" b.
"We have had an emergency b.
"We have declared an " Alert" condition which was termi-because (indicate the initia-ated prior to classifying".
ting condition per OP-3300.
c.
"I repeat, this is Yankee c.
"The plant is (pick one)
Nuclear Power Station. Please acknowledge with your name".
1.
Continuing normal operation 2.
Reducing present power levels 3.
Shutdown d.
VT:
d.
"A release (pick one)
Name of Dispatcher MA:
2.
Is in progress, or Name of Dispatcher 3.
Is not expected".
e.
"Present meteorological conditions indicate (provide wind speed and direction from (degrees)".
f.
"At the present time we recommend no protective action".
g.
"I repeat, this is Yankee Nuclear Power Station.
Please acknowledge with your name".
VT:
Name of Dispatcher MA:
Name of Dispatcher NOTE:
Regardless of which message is used, complete this and all other required procedures.
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- OP-3302 Appendix I Rev. 5 1
Time / Initials 3.
Determine if a release is in progress or projected.
/
NOTE:
Elevated AARM readings are an example of a projected release; that is, the release may not be in progress but the potential is real.
If releases are in progress or projected:
a.
Instruct the Supervisory Control Room operator or the Shift Technical Advisor to perform Appendix A of OP-3310,
" Evaluation of Radiological Data" to determine the estimated 1/2 mile whole body dose rate.
This will be needed when the Departments of Health of Massachusetts and Vermont respond to the initial notification.
b.
Instruct the Radiation Protection technician to initiate a Primary Vent Stack or Vapor Container sampler and analysis, j
(OP-9450), " Post Accident Sampling and Analysis".
c.
Instruct the Auxiliary Operator to initiate a Control Room habitability study. (Appendix VI of this procedure).
4.
Account for operations shift personnel, implement search and rescue as necessary.
If medical problems exist initiate Emergency Medical Procedure (0P-3305).
/
NOTE:
The following subsequent actions may be performed by the TSC, once personnel are available.
5.
WITHIN ONE HOUR OF THE DECLARATION OF THE EMERGENCY, Designate an individual to notify the NRC on the Emergency Notification System (RED phone). Maintain an open communications channel f
on this line.
This channel will be closed by the NRC.
/
NOTE:
If Emergency Notification System (red phone) is disabled, then use the following commercial telephone lines to notify NRC Operations Center:
a.
Dial 202-951-0550 OR b.
Dial 301/427-4056 6.
As soon as contacted via the State notification fan-out process, the Departments of Public Health of Vermont and Massachusetts will call the plant.
Be prepared to provide the following information if known and appropriate, upon request:
/
a.
Name of caller; b.
Time and class of emergency; Withho}d AMiafMuanit[ty of release, height of release, and c.
Type an m times:
Pr conditions (wind velocity, direction, tempera-From Publieu Dajlinkweadt edstabt11ty, form of precipitation, if any);
ise s
Nuo'ugsat0.5milesfromthesite; dose ra e.
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, OP-3302 Appendi,x I Rev. 4 4
Time / Initials f.
Emergency response actions underway; and g.
Recommended protective actions based on the combination of all in plant indications, release parameters and off-site radiological assessment results.
7.
When the TSC establishes contact with the Control Room, outline current plant status and request any needed assis-tance.
Inform the TSC at this time of operations shift accountability.
/
Request assistance of outside agencies (fire, law enforce-ment, or medical response personnel) as needed to deal with the event.
See Emergency Plan Implementing Procedures Manual for phone numbers:
a.
Fire b.
Medical c.
Law enforcement (coordinate with Security i
Shift Supervisor)
/
9.
If the event produces abnormal in plant radiological conditions, direct the shift Health Physics representa-l tive to evaluate the condition.
/
- 10. Together with personnel at the TSC, re-evaluate the emer-gency classification and if conditions warrant, escalate or de-escalate the classification.
/
11.
Repair and corrective action missions shall be performed in accordance with the Emergency Radiation Exposure Con-trol procedure (OP-3330).
/
FINAL CONDITIONS 1.
When the Alert no longer exists, announce on the plant page system that the Alert is ended.
/
2.
Summarize all actions and resultant conditions in the Shift Supervisor's Log.
/
Completed by:
Date/ Time:
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APPENDIX II OP-3302 Rev. 5 ALERT - SECURITY Page 1 SAS Operator:
1.
Inform the CAS operator of the emergency classification and of the immediate need for initiation of OP-3344, " Security Force Actions Under Emergency Conditions".
/
2.
Notify the NSD Security of the incident by:
a.
Dial: 86-856-2184 OR 97-1-617-872-8100 (Ext. 2184)
/
OR 97-1-617-879-2755 b.
Provide the following message:
"This is Yankee Rowe, we have an Alert Condition.
Standby for Yankee staff call" REPEAT MESSAGE AND HANG UP
/
c.
Activate the NSD Response List by:
1.
Dial:
2.
Give the following PAGER NUMBER:
/
NOTE:
Implementation of the remainder of this procedure is restricted to backshifts, weekends, or holidays only.
During normal shifts response actions would be initiated as directed.
3.
When notified by the Shift Supervisor or, in his absence, the Supervisory Control Room Operator of Alert Conditions, the guard at the SAS shall:
a.
Standby to receive incoming calls from Emergency Response Personnel.
1.
Pick up the incoming call at the SAS by dialing 90 and l
answering " Yankee Atomic, (your name).
l l
NOTE:
DO NOT linger on the phane as more calls will be coming in.
Take the name of the responder, record the time, on OP-Memo 2E-4, Attachment "A, Page 2, that he called and relay to him the information adjacent to his name.
If other than a responder, explain that we have a major evolution in progress i
and ask them not to call back.
2.
If the responder must speak to the Control Room, transfer him to 236, 237 or 238. Inform the Control Room who is on the line and hang up.
Withhold Attachment From Public Disclosure 10 CFR g.7_90 INFORMATION
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APPENDIX II OP-3302 Rey. 5 Page 2 Time / Initials 3.
Answer the next call.
/
4.
After about 15 minutes, reinitiate Step 2
/
FINAL CONDITIONS 1.
Return this sheet to the TSC Coordinator.
/
Completed by:
Date/ Time:
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APPENDIX III OP-3302 Rev. 5 Page 1 ALERT - TECHNICAL SUPPORT CENTER C0ORDINATOR IMMEDIATE ACTIONS 1.
Establish voice communications with the control room, using Channel 1 of the plant paging system.
2.
Ensure that OP-Memo 2E-4, "Backshift Augmentation" has been activated and that the following staff are represented at the TSC:
a.
Plant Superintendent / Assistant Plant Superintendent b.
Reactor Engineering Supervision / Shift Technical Advisor c.
Instrumentation and Control Supervision d.
Operations Supervision e.
Maintenance Supervision NOTE:
Communications operators will be directed to report here.
3.
Take over the remaining subsequent actions of the Emergency Director.
4.
Take charge of Radiological Evaluations.
SUBSEQUENT ACTIONS NOTE:
If the emergency classification has changed (escalated or de-escalated) DO NOT duplicate actions in emergency implementing procedures as a result of the transition.
Time / Initials 1.
Check that incoming personnel have been assigned and that they have signed in on the organization status board.
/
2.
Direct the OSC staff to determine the habitability of the TSC, OSC and Control Room in accordance with Appendix VI.
/
3.
Assign one staff member to complete OPF-3302.5, "TSC/ Control 1
Room Accountability".
Forward this information and informa-tion from OPF-3302.6, "0SC Accountability" to the Chief of Security at the EOF.
l If any missing persons are indicated, call for missing per-l sonnel over the plant page system.
Prepare for search and rescue as necessary.
/
4.
Utilize the information acquired through the SPDS system to analyze problems in the area of system operations and/or instrumentation and control.
/
Withhold Attachment From Public Disclosure 10 CFR 2.Z90 JNFORMAT:0.N
' OP-3302 Appendix III Rev. 5 Time / Initials 5.
Inform the Emergency Coordinator as to on-site manpower / equip-ment needs.
/
6.
Assign individuals to maintain a communiations link to the EOF, OSC and the Engineering Support Center (YNSD Emergency Center).
Those personnel assigned to this function must maintain a log of center activities.
/
j 7.
Assume the responsibility for maintaining open communica-tions with the NRC (RED phone).
/
8.
Periodically update the TSC status board.
/
9.
Coordinate information with Yankee NSD personnel.
/
10.
Periodically review emergency classification and escalate or de-escalate the emergency response in accordance with the appropriate emergency class.
/
- 11. Develop TSC, Control Room and OSC shift schedules and coordinate this effort with the Manpower Assisant.
/
12.
Respond to all NRC inquiries regarding plant emergency actions.
/
- 13. Direct the emergency organization until such time that the emergency condition has been terminated.
/
NOTE:
Notify plant staff, corporate office and other emergency resources if the emergency condition requires a transition to a recovery phase.
FINAL CONDITIONS f
1.
Log all TSC emergency response actions and provide this to the Emergency Coordinator when the event has ended.
/
2.
The TSC Coordinator closes out the event with off-site authorities (OPF-3302.4)
/
3.
Direct the appropriate personnel to restore all emergency equipment to its normal readiness state when the Alert con-dition is terminated.
/
M B 5 c-Completed by:
Date/ Time:
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OP-3302 Rev. 1 APPENDIX IV Page 1 ALERT - OPERATIONS SUPPORT CENTER COORDINATOR IMMEDIATE ACTION 1.
The first OSC member to arrive will establish communications with the TSC and initiate the necessary actions required to support the response effort.
l 2.
Direct all incoming personne'l to sign in on the OSC Tag Board.
NOTE:
The TSC Coordinator will assign the OSC Coor-dinator; otherwise, the first member of the OSC staff to arrive at OSC will assume this T
responsibility until relieved.
3.
Determine the habitability of the OSC in accordance with Appendix VI of this procedure.
T NOTE:
If radiological conditions warrant the evacuation of the primary OSC location, then the staff should move to the alternate location.
4.
Assign one member of the staff to complete OPF-3302.6 "0SC Accounta-T bility" and forward it to the TSC Coordinator.
T NOTE:
This must be completed as soon as possible so that a missing 1 person /s search can be initiated expeditiously.
1 SUBSEQUENT ACTIONS Time / Initials 1.
Assure that the following staff are represented at the OSC:
a.
Maintenance Electrician b.
Maintenance Mechanic l
c.
Instrument & Control d.
Health Physics j
e.
Chemistry
/
2.
Provide assistance in the investigation or repair of plant systems in the collection of post-accident monitoring samples and in the decontamination of affected plant areas if conditions warrant such action, as directed.
See OP-3330 " Emergency Exposure Control" and OP-9450 " Post Accident Sampling and i
Analysis"
/
3.
Work in conjunction with the TSC in preparing for operating shift turnover and relief.
/
withhold Attachment From Public Disclosure 10 CFR2.790 INFORMATi, -
APPENDIX IV OP-3302 j
Rev. 1 Pa'ge 2 FINAL CONDITIONS 1.
Remain active and manned until terminated by the TSC i
Coordinator
/
i 2.
When terminated, direct the appropriate personn2l to restore all emergency equipment to its normal readiness state.
/'
Completed by:
Date/ Time:
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APPENDIX V OP-3302 Rev. 5 ALERT - EMERGENCY COORDINATOR IMMEDIATE AND SUBSEQUENT ACTIONS Time / Initials 1.
Activate the E0F and contact the TSC Coordinator / Plant Emergency Director to obtain a plant status report.
/
2.
Assure that the following staff positions have been filled.
/
a.
Coordinator's Assistant b.
Radiological Evaluation Assistant c.
Manpower Assistant d.
Communications Assistant e.
Off-site Monitoring Team (8) f.
Communications Team (3) g.
Sample Analysis Team (4) h.
Emergency Medical Team (2) 1.
Road Barrier Team (8) j.
Records Management V
Ensure that the most qualified personnel have been assigned 1
a.
to the E0F management organization.
/
4.
Assemble the E0F management staff to initially brief them of emergency conditions and establish any immediate priority tasks.
/
NOTE:
Periodically call EOF management staff meetings to ensure that all EOF functions being coordinated in an efficient / effective manner.
5.
Periodically confer with tne TSC Coordinator concerning in-plant conditions, evaluate the impact of these conditions on current EOF activities and direct the EOF staff as to appropriate response measures.
/
6.
Coordinate accident information with appropriate off-site authorities.
Inform them of projected dose rates, actual plant conditions, field sample results and recommendations concerning emergency actions, if conditions warrant such action via the Nuclear Alert System
/
NOTE:
Coordinate protective action recommendation with the responding State officials.
Recommendations should be provided based on the prognosis of in-plant indications and/or on dose projection action levels specified by EPA Protective Action Guides.
7.
Notify ANI at 1-203-677-7305. Give as much information as possible.
Y ylithhold ggchM public Disclosure CER 2.790 WW#
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' OP-3302 Appendix V Re'v. 5 Time / Initials 8.
Evaluate the need for re-entry / recovery missions in con-junction with the TSC Coordinator and direct the Radio-logical Evaluation Assistant to review and recommend appropriate protective measures required to implement any re-entry / recovery missions.
/
9.
Periodically confer with the Engineering Support Center staff concerning the evaluation / interpretation of the on going emer-t gency condition (s) including Public Information needs.
/
NOTE:
The Engineering Support Center staff will make the initial contact.
- 10. Based on updated emergency conditions, review and re-evaluate the emergency classification in conjunction with the TSC Coor-dinator.
/
11.
Ensure that the EOF remains active and adequately manned and supplied for the duration of the emergency condition.
./
l4 NOTE:
If it is determined that the center may become uninhabitable, direct EOF Staff 1
as to appropriate evacuation measures.
(
12.
If the emergency classification changes, ensure that the EOF management is informed and direct them to modify emergency i
response actions accordingly and prevent duplication of response actions as a result of the transition in the use of emergency implementing procedures.
/
1 13.
Ensure that the States of Vermont and Massachusetts are advised of any transition in emergency status if the emergency classi-fication changes.
/
14.
If the EOF must be evacuated, refer to OP-3350 " Actuation of the Alternate EOF".
FINAL CONDITIONS 1.
Ensure that all completed survey and sample analysis forms are submitted to the Health Physics Department for review and filing.
/
2.
Direct that an Emergency Equipment Readiness Check, be conducted. (OP-3325) gghbold OSUI6 w*"%ew y
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- OP-3302 Appendix V Rev. 5 3.
Complete OPF-3302.3 " Emergency Plan Incident Report" and distribute 1
copies to:
/
(1) Plant Superintendent (2) Assistant Plant Superintendent (3) Technical Director (4) All Department Heads (5) Control Room - Shift Supervisor i
(6) Plant Health Physicist (7) Manager of public Information (8) Plant Technical File l
(9) Manager of Operations i
1 i
Completed by:
Date/ Time:
i chment withhold ^ Disclosure 10 CFR 2N0 pf0RMAN
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OP-3302 Appendix V-1 Re'v. 1 APPENDIX V-1 ALERT - RADIOLOGICAL EVALUATION ASSISTANT Time / Initials Immediate and Subsequent Actions:
1.
Appoint a Sample Coordinator who will insure that the following activities are coordinated and that the pertinent results are transferred to the Radiological Evaluation Assistant for evalu-ation.
/
a.
Direct qualified emergency personnel in the establish-ment of off-site monitoring teams (i.e., assignment and initial preparation).
b.
Dispatch off-site monitoring teams to appropriate sampling locations as directed by the Radiological Evaluation Assis-tant.
c.
Direct radio operations, d.
Review and evaluate incoming reports from off-site monitoring
- teams, e.
Prioritize the retrieval of the sampler (s) based upon the initial evaluation.
f.
Review the need for resampling and/or relocation of the off-site monitoring team with the Radiological Evaluation Assistant.
g.
Direct Sample Analysis Team members in the establishment of a priority preparation and sample counting system for retrieved field samples.
h.
Evaluate the results from the SAM-II analysis for the estimate of thyroid doses.
i.
Transfer pertinent SAM-II results to the Radiological Evaluation Assistant for review and evaluation.
2.
Appoint a Radiation Protection Assistant who will ensure that the following activities are coordinated and that pertinent results are transferred to the Radiological Evaluation Assistant for evaluation.
/
a.
Direct qualified emergency personnel in the determination of center habitability and the periodic reassessment of center conditions, b.
Direct the establishment of radiological access and control measures at the EOF.
c.
Assign and direct personnel for decontamination purposes when applicable.
d.
Direct personnel in the review and maintenance of emergency exposure records.
e.
Coordinate exposure / job authorization.
gfDh0N sC s*#,,s e g cFa2
- OP-3302 Appendix V-1 Rev. 5 Time / Initials f.
Establish HP re-entry support as directed by the Radiological Evaluation Assistant.
g.
Coordinate the transfer of personnel dosimetry for evaluation to the Environmental Lab and/or the Mobile TLD Van when appli-cable.
3.
Appoint an Environmental Sampling Assistant who will insure that the following activities are coordinated and that pertinent results are transferred to the Radiological Evaluation Assistant for evalua-tion.
/
a.
Direct the retrieval of environmental samples.
b.
Establish a priority system for the evaluation of environmental station (air) sample analysis in con-junction with the Sample Coordinator, c.
Evaluate environmental TLD and record the results, when applicable.
d.
Coordinate the transfer of environmental samples for evaluation to the Environmental Lab and/or the Mobile Environmental Lab Van, when applicable.
4.
Evaluate in plant radiological conditions (App. VI of this procedure) 1 in conjunction with current meterological data, especially, wind speed, wind direction and Delta-T (UPWSAV, UPWDAV and UPDTAV, respectively on the terminal print-out).
/
5.
Determine the affected downwind direction, evaluate plume transit time, and inform the Sample Coordinator as to the appropriate sampling locations.
/
6.
Utilizing in plant radiological monitor responses in conjunction with meterological data (OP-3310 App. A), estimate the projected 1
downwind dose rates.
Report findings to the Emergency Coordinator.
/
7.
Re-evaluate initial dose rate projections based on in-coming field sample results, interpret these results, update the Emergency Coordinator on these findings and recommend appro-priate protective measures, if necessary.
/
8.
Based on in plant monitor / survey results, evaluate any re-entry /-
recovery plans in terms of the projected radiological hazard which could be encountered.
/
9.
Recommend appropriate protective measures required for re-entry and direct the Radiation Protection Assistant in the establishment of HP support and/or exposure / job authorization s i q' ',
requirements. {QP-3330 " Emergency Radiation Exposure Control")
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Time / Initials 10.
Periodically evaluate the emergency exposure records in con-i junction with manpower requirements.
/
I
- 11. Maintain response efforts to determine radiological status j
and be prepared to adjust radiological assessment efforts as conditions change.
/
FINAL CONDITIONS 1.
Summarize emergency actions and provide this documentation to the Emergency Coordinator.
/
2.
Update exposure records of plant personnel.
/
3.
Transfer all sample media appropriately for further analysis, documentation and disposal.
/
Completed by:
Date/ Time:
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OP-3302 Rev. 5 APPENDIX V-2 ALERT - COMMUNICATIONS ASSISTANT Time / Initials Immediate and Subsequent Actions 1.
Assign and direct emergency personnel in the establishment of continuous communication channels between the TSC, off-site monitoring teams, security and the EOF as follows:
/
a.
One (1) Radio Operator (have him report to Sample Coordinator or Radiological Evaluation Assistant) b.
One (1) Radio Operator's Assistant c.
One (1) Met. Terminal Operator d.
Two (2) Telephone Operators 1
2.
Direct all communication personnel to record the parties involved, date and time of each incoming or outgoing message by telephone, plant page or radio on a Message Form.
/
3.
Establish priority system for transfer of recorded messages and ensure that communication personnel promptly reply.
/
4.
Write all information received in the Emergency Monitoring
-Log.
/
l S.
Direct personnel in maintaining updated status boards in the EOF.
/
6.
Dispatch communication personnel to all centers to facilitate emergency response, upon request.
/
1 l
NOTE:
If additional personnel are required to fulfill this responsibility, contact the i
Manpower Assistant and request additional support.
7.
If plant communications systems are inadequate to handle the flow of incoming calls, notify the Emergency Coordinator and recommend ad hoc measures.
/
FINAL CONDITIONS 1.
Collect all message forms, tabulate them in sequential order and provide this documentation to the Emergency Coordinator.
/
l 6N Date/ Time:
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OP-3302 Rev. 1 APPENDIX V-3 ALERT - MANPOWER ASSISTANT Time / Initials Immediate and Subsequent Actions 1.
Assure that sufficient personnel to fulfill all emergency functions have been mobilized to maintain continuous emer-gency preparedness.
/
2.
Review center equipment / supplies and augment resources accordingly.
/
NOTE:
Review Manpower Planning Package.
If plant manpower can not provide the necessary per-sonnel, notify the Yankee Engineering Support Center of the need to get personnel available through the Yankee Mutual Assistance Plan.
Pro-vide Yankee ESC with list of required personnel.
3.
Coordinate the activities of the Road Barrier Teams, as required.
/
4.
Coordinate the activities of the Emergency Medical Team, as required.
/
5.
Coordinate the activities of the Re-Entry Team, as required.
/
6.
Coordinate security access and control measure with the Security Coordinator.
/
NOTE:
The Security Coordinator will be responsible for organizational control of evacuating personnel and personnel accountability.
7.
Establish communications with each emergency center to determine the organizational structure.
/
8.
Maintain an updated roster of emergency personnel using the Emergency Assignment Chart.
/
9.
Ensure that one plant member is assigned to activate the Alternate EOF.
/
- 10. Coordinate the distribution of equipment at the EOF.
/
11.
Establish shift relief schedules.
/
g((GCDN FINAL CONDITIONS y
Fr g h g Qi8 1.
Coordinate the return of emerge u
h a
state of readiness.
N/
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10 GrR A 4
OP-3302 Rev. 5 APPENDIX V-4 ALERT - C00RDINATOR'S ASSISTANT IMMEDIATE AND SUBSEQUENT ACTIONS Time / Initials 1.
Cunction as aide / alternate to the Emergency Coordinator.
/
2.
6 sist the Emergency Coordinator in assigning personnel to emergency duties using the EOF Tag Board (if not done pre-viously).
/
3.
Coordinate personnel accountability with plant security, con-tact the TSC with the results.
If the TSC identifies missing personnel, coordinate search and rescue with the TSC and OSC.
/
4.
If there are any injured personnel, assign Emergency Medical Response Personnel to administer first aid and prepare the patient for transfer to the North Adams Regional Hospital, if hospitalization is required. (See " Medical Emergency Procedure" OP-3305).
/
1 5.
If hospitalization is required:
a.
Call the ambulance (see Contact List). Advise the ambul-ance service of the location of the desired pickup.
/
b.
Provide the North Adams Regional Hospital Nursing Sup-ervisor (see Contact List) with the following information before the patient arrives at the hospital:
/
(1) Number of accident victims (name if possible)
(2) Nature of medical problem (s)
(3) Anticipated time of arrival at the hospital.
(4) Radiological considerations including, as applicable, the site of contamination, isotope and activity present.
If no contamination j
problems exist so indicate.
(5) Name of person (s) escorting victims.
c.
Transfer the patient (s) to the ambulance.
If the patient is contaminated, assign a Health Physics representative to accompany or,.gneet him at the hospital to maintain radio-l o'
/
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' OP-3302 Appendi.x V-4 Rev. 1 Time / Initials 6.
Provide briefings to incoming emergency personnel as to the accident status and direct them to appropriate assembly areas.
/
7.
Coordinate entry of TSC/OSC support personnel to the plant when necessary.
/
8.
Assist the Emergency Coordinator in coordinating the interface with State and Federal agency emergency response personnel at the EOF.
/
FINAL CONDITIONS 1.
Coordinate the return of emergency equipment and supplies to a state of readiness.
/
Completed by:
Date/ Time:
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OP-3302 Rev. 1 APPENDIX VI RADIOLOGICAL HABITABILITY ASSESSMENT Time / Initials Immediate and Subsequent Actions 1.
Perform the Radiological Monitoring Assessment section of the " Emergency Radiation Exposure Control" (OP-3330 App. I).
/
1 2.
Obtain a RM-14, survey instrument and air sampler.
Perform the necessary function checks on the instrumentation.
/
3.
Monitor conditions in the area (s) assigned:
Technical Support Center Operations Support Center Emergency Operations Facility Other areas.
4.
Place a high range pocket dosimeters in a representative location or locations at each center.
/
5.
Complete OPF-3302.2 " Emergency Conditions Radiological Assessment Y
I Form" and report findings to the TSC Coordinator or EOF Coordinator, or their assistant.
/
NOTE:
Additional information, such as area surveys, should be recorded on the reverse side unless otherwise provided.
FINAL CONDITIONS 1.
Collect all forms and forward to the Plant Radiation Protection Department.
/
Completed by:
Date/ Time:
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Description of incident.
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EVENT CLOSE CUT CHECK LIST 1.
Determine if a written report is required by the NRC.
NOTE:
If a written report is required by the NRC, advise the states that a written report will follow the verbal close-out in step 2 below.
2.
Provide verbal close-out of event with off site authorities as follows:
a.
NRC b.
State of Vermont c.
Commonwealth of Massachusetts 3.
Provide four (4) copies of written report, if required, to the following off-site authorities:
l a.
Commissioner of Public Safety - State of Vermont b.
Director of Civil Defense Commonwealth of Massachusetts OR De-escalate the emergency classification based on changing plant conditions.
(OP-3321 " Emergency De-Escalation Procedures").
Completed by:
Date/ Time:
OPF-3302.4 Rev. 5 C) e s
TSC/ CONTROL ROOM ACCOUNTABILlTY LOG SHEET Record the name of all personnel present in the TSC/ Control Room.
Forward these names and the names on OPF-3302.6 "0SC Accountability" to the Chief of Security at the EOF.
OPF-3302.5 Rev. 5 Withhold Attachment From Public Disclosure 10 CFR 2.790 INFORMAT'0?!
OSC ACCOUNTABILITY LOG SHEET.
(Record the names of all personnel present as assigned to OSC and forward this sheet to the TSC Coordinator).
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Proc. No. OP-3310 Rev. No.
3 Date 12/82 EVALUATION OF RADIOLOGICAL DATA SCOPE To assess the off-site radiological hazards due to an abnormal release of radioactive material by evaluating information received from within the plant at effluent points, the off-site radiation monitoring teams, and the environmental monitoring stations, so that appropriate pro-tective actions may be recommended.
ENCLOSURES OP-3310 - Pgs. 1 Rev. 3 Appendix A - Pgs. 1 Rev. 3 OPF-3310.1 - Pgs. 1 Rev. 3 OPF-3310.2 - Pgs. 1 Rev. 3 Appendix B - Pgs. 1 Rev. 2 OPF-3310.3 - Pgs. 1 Rev. 1 OPF-3310.3 - Pg. 3 - Rev. 2 OPF-3310.4 - Rev. 1 Appendix C - Pgs. 1 Rev. 2 OPF-3310.5
.8 - Rev. 1 OPF-3310.9 - Pgs. 1 Rev. 3 Appendix D - Pg. 1 - Rev. 2 OPF-3310.10 - Rev. 1 Appendix E - Pgs. 1 Rev. 2 OPF-3310.11 - Pg. 1 - Rev. 3 OPF-3310.12 - Pg. 1 - Rev. 2 Appendix F - Pgs. 1 Rev. 3
REFERENCES:
Yankee Rowe Nuclear Power Station Emergency Plan.
DISCUSSION Radiological assessment is made to the extent of projecting doses / dose rates to the public from each source of information. The dose rate projections produced by this procedure represent the best estimate possible for each method.
They will be made using an HP-41CV calculator.
The calculator is capable of determihing dose rates at distances from 1/2 to 10 miles. As a backup, nomograms are available which can be used for dose projections at 1/2 mile.
If projecticns from in plant paramenters are significantly different than those measured in the environment, it may be due to meteorological modeling and/or due to inaccuracies in release rate estimates. The results obtained from this procedure should be carefully analyzed since these may form the basis for protective action recommenda-tions to the public.
There are two areas from which information will be available for the analysis of radiological hazards; in plant (stack effluent monitor, containment source term, or steam line effluent) and off-site field monitoring surveys of off-site whole body and thyroid dose rates.
In
I
' OP-3310 Rev. 3, order to categorize the different techniques used to evaluate the radio-logical hazards, the procedure has been divided into several appendices listed as follows:
APPENDIX TITLE IMPLEMENTATION RESPONSIBILITIES A
Whole body dose rate projections-Plant Emergency Director or from the use of inplant parameters.
Technical Support Center Coordinator B
Evaluation of Off-Site Particulate TSC Coordinator and Iodine Concentrations C
Radiological Conditions Projection Radiological Evaluation To Other Distances Of Interest Assistant D
Evaluations of Environmental Station Radiological Evaluation samples, and other environmental Assistant sample media.
E Protective Action Recommendations Radiological Evaluation for the Public.
Assistant These appendices should be used in the order that they appear since they are arranged in the order of priority. A brief description of the appendices and the interpretation of the results 's giva, below. Each appendix uses the current meteorology conditions onu therefore these parameters should be periodically monitored for significant changes.
This procedure may be implemented at any time by and under the direction of the Plant Emergency Director, the Technical Support Center Coordina-tor or the Emergency Coordinator.
Responsibility for performing each appendix is addressed below.
Interpretation of Appendix A results is initally the direct respon-sibility of the Emergency Director. The Supervisory Control Room Operator or the Shift Technical Advisov will be assigned to assist the Emergency Director in the evaluation of Appendix A. Appendix A is used to obtain an estimate of the offsite whole body dose rate due to a high level stack release, containment release or steam line effluent release during a loss of coolant accident (LOCA). To initiate Appendix A it must first be determined if a release is occurring.
This is accomplished in the Control Room through observations of various plant parameters and process monitoring systems.
This appendix uses the Emergency Offsite Dose Nomogram or an HP-41C programmable calculator which require the following inputs: time after shutdown, Accident Area Radiation Monitor (AARM) dose rate, (wind speed, delta temperature) (for atmospheric stability class), the high range real time radiation monitor response, and the high range noble gas monitor response. The information obtained is Total Noble Gas Release Rate and Offsite Whole Body Dose Rate (projec-tion is for 1/2 mile if nomograms are used).
It must be acknowledged that information obtained from the Containment Leakage Nomogram is very
- OP-3310 Rev. 3 conservative since it assumes a containment leakage of 0.1% per day which is the maximum allowed design basis leakage at peak containment pressure.
Correction for actual containment pressure is included in this appendix.
NOTE:
There may be more than one release pathway in progress.
If so a summation of release rates and off-site dose projection must be done. This
" sum" is to be used in final evaluation as in-dicated on Data Reduction Sheet A.
Appendix B is separated into two sections. The first describes the method by which the air samples at the stack should be analyzed and evaluated to obtain concentrations at 1/2 mile.
This section is the responsibility of the TSC Coordinator.
The TSC Coordinator may call upon Chemistry and/or RP personnel located in the OSC to assist in this section.
From.this result, the " Field Sample Thyroid Dose Nomogram" may be used to obtain adult and newborn thyroid dose estimates per unit inhalation time and air sample concen-trations.
The second section describes the methods to be used to evaluate the results reported by the offsite survey teams from the air sample field counting and to analyze the sample cartridge at the EOF for.more accurate radiological estimates. This section is the responsibility of the Radio-logical Evaluation Assistant.
These results are also used in conjunction with the field sample thyroid dose Nomogram to obtain adult and newborn thyroid doses per unit inhalation time.
Appendix C will be the responsibility of the Radiolog4 cal Evaluation Assistant. Appendix C describes the method to be used to project the in-plant estimates of whole body and thyroid dose rate to distances greater than 1/2 mile. The results of these projections should be compared to the field sample measurement performed by the Offsite Survey Teams.
In the event that these measurements are significantly different, it may indicate i
one of the following:
a)
Errors in release rate estimates, b)
Meteorological conditions have changed rapidly, or c)
Actual plume dispersion disagrees with model.
Appendix D calls attention to the use of the environmental station's samples, soi.1 and other environmental sample media to be used for dose assessment to the public during the later stages of the accident. The analysis of these samples will be made by the Yankee Environmental Lab.
This section describes sample collection and labelling techniques that should be employed.
Appendix E covers the determination of public protective actions. This section is performed by the Radiological Evaluation Assistant (REA). The Emergency Coordinator approves and makes the final recommendations to the States.
~. -
- OP-3310 Rev. 3 PRECAUTIONS 1.
Meteorological conditions are subject to change and must be closely monitored during the potential radiological hazard.
2.
Results of the different dose projection methods must be carefully compared for a complete evaluation of the radio-logical offsite conditions.
3.
If the high range effluent monitors (PVS and/or main steam line) become inoperable, data collected by off-site monitoring teams must be used for gathering dose assignment data (OP-3311, "Emer-gency Off-Site Radiation Monitoring")
PROCEDURE:
NOTE:
At each stage of the precedure, pass the appropriate information to the Emergency Coordinator or Director whichever is the cognizant individual so that appropriate protective actions may be recommended.
1.
Upon notification of an Emergency condition, complete the steps in Appendix A to determine the offsite whole body dose rate at 1/2 mile. This 1/2 mile projection is mandatory as it is com-pared against the Emergency Action levels in OP-3300 and also reported to the States as an indicator of the release severity.
2.
Once the PVS air samples have been analyzed or offsite air samples have been collected, determine the 1/2 mile offsite projected thyroid dose per unit inhalation time and evaluate the particulate concentra-tion as described in Appendix B.
If this sample has not been taken proceed to Step 3.
3.
If using the nomograms after the 1/2 mile projected dose rates have been determined, go to Appendix C and calculate projected dose rates at other locations of interest.
4.
Under the direction of the Emergency Coordinator, or a designa-ted representative make provisions to collect the air samples at the environmental sample stations and other environmental samples (soil, water, vegetation, milk, etc.) as outlined in Appendix D.
5.
Once the EOF is staffed the REA determines protective action re-commendations per Appendix E.
The Emergency Coordinator approves-and transmits the recommendation to the States.
6.
As updated information becomes available, repeat the steps in each Appendix as appropriate.
1
,7-.
~
r
- OP-3310 Rev. 3 FINAL CONDITIONS 1.
The Radiological hazard associated with the plume exposure pathway has been defined by the best means available.
2.
All calculated and measured parameters have been logged on the appropriate data reduction forms.
3.
All information and data forms have been given to the Emergency Coordinator,.TSC Coordinator or Emergency Director as appro-priate for Protective Action Recommendations.
4.
Environmental Samples have been collected and analyzed for more refined dose assessment determinations.
7 OP-3310 App. "A" Rev. 3-Page 1 APPENDIX A Whole Body Dose Rate Projections from In-Plant Parameters A.1.0 Proceed to the emergency equipment locker and get'the nomogram board and special marking pens, the extra copies of OPF-3310.2
" Data Reduction Sheet A"., and.the HP-41C calculator. Using the nomogram board,-log the calculation number (i.e., #1, 2, 3, etc) and the date/ time at-the top of the data sheet.
A.1.1 Log the time in hours after reactor shutdown.
A.1.2 VAPOR CONTAINER A.1.2.1 Log the containment pressure (psig)
A.1.2.2 Log the In-Containment AARM reading in (R/hr) from the Victoreen panel.
NOTE If the AARM reading is less than 500 R/hr the containment dose projection need not be done.
A.1.3 PRIMARY VENT STACK A.1.3.1 Log the number of stack fans running.
A.1.3.2 Log the Primary Vent Stack High Range Noble Gas Channel reading in (mr/hr) from the Victoreen panel.
NOTE: a.
If this reading.is less than 1000 MR/hr.the PVS dose projection need not be done.
b.
If the Victoreen channel is inoperable initiate OP-3740 to take the readings.
A.1.4 STEAM LINES From operational information and/or the steam line high range radiation monitors (on the Victoreen panel) determine if a release is occurring to atmosphere.
NOTE: a.
The radiation monitors are located up-stream of the safety. valves to indicate steam line true readings.
b.
If the Victoreen channels are inoperable initiate OP-8741 to determine the steam line readings.
A.1.4.1 Log the affected main steam line number on the data sheet.
A.1.4.2 Log the affected main steam line radiation level in (MR/hr).
i
- OP-3310 App. "A" Rev. 3 A.1.4.3 Log the main steam line release pathway: Atmospheric Steam Dump (ASD); Normal or Emergency, OR Safety Valve (SRV), HI, Med. or
}
Low.
f A.1.5 LOCA DESIGNATION Using the In-Containment AARM reading (Step A.1.2.2) and the i
figure on OPF-3310.2, Page 3, determine the LOCA Designation I or III. The figure is also located on the nomogram board.
l NOTE:
A LOCA I indicates main coolant leakage with trivial fuel failure. A LOCA III indicates major coolant leakage with fuel failure.
i l
A.1.5 WIND SPEED Proceed to the Met Tower panel and log the latest wind speed (p) in miles per hour (from printer or chart).
l NOTE:
There is a table on the nomogram board indicating which sensor to use.
For a PVS release the 60 meter sensor is used, for a VC or steam line release the 10 meter sensor is used.
A.1.6 DELTA TEMPERATURE j
Log the latest Delta temperature in ( F) from the printer l
or the chart (make sure to note the + or - sign and which l
tower; Prinary or Secondary) f A.1.7 STABILITY CLASS Frc:n the appropriate table and the value of of Delta T, determine the atmospheric Stablility Class and log it on Data Reduction Sheet A.
PRIMARY TOWER 2
DELTA TEMPERATURE PASQUILL ATMOSPHERIC Delta T ( F)
STABILITY CLASS Delta T Less than or equal to - 1.71 A
Delta T between -1.71 and - 1.53 B
Delta T between -1.53 and - 1.35 C
1 i
Delta T between -1.35 and - 0.45 D
Delta T between -0.45 and + 1.35 E
Delta T between +1.35 and + 3.60 F
l Delta T greater than +3.60 G
L
~
....-..,..,.r-
.-,,r..-.,.
,.,,.,,,, _,,,.... _ -....,.,,,..,, ~ _. - - _.,, - -, -., -,, -,... -,,, - -
r
' OP-3310 App. "A" Rev. 3' SECONDARY TOWER DELTA TEMPERATURE PASQUILL ATMOSPHERIC Delta T ( F)
STABILITY CLASS Delta T Less than or equal to - 1.04 A
Delta T between -1.04 and - 0.93 B
Delta T between -0.93 and - 0.82 C
Delta T between -0.82 and - 0.27 D
Delta T between -0.27 and + 0.82 E
Delta T between +0.82 and + 2.20 F
Delta T greater than +2.20 G
NOTE: a.
Be aware of the '+' or " " sign for Delta T b.
These tables are also found on the nomogram board.
A.1.8 WIND DIRECTION Determine the sensor to be used (10 meter or 60 meter) using the source of the release and the atmospheric stability class chosen in steps previously. Use the guidance in OPF-3310.2, Page 2, to choose the sensor.
Proceed to log the wind direction from that sensor in DEGREES (if cross valley trajectories) or by indicating " UPSTREAM" or " DOWNSTREAM" when the plume is con-strained by the valley.
If data from the Primary Tower is unavailable, use the Secondary Tower sensor (30.5 meters).
NOTE:
The guidance in OPF-3310.2, Page 2, is found on the nomogram board.
A.4 RELEASE PA.TH From the data collected and the guidance provided in the notes of Steps A.1.2 and A.1.3, determine the release pathways in order of significance.
Proceed to determine the release rates and projected 1/2 mile whole body dose rates.
In the case where there is more than one significant release pathway, the release rates and 1/2 mile dose rates will be determined for each pathway and then added to estimate the total release rate and the total 1/2 mile whole body dose rate.
A.4.1 HP-41C CALCULATOR If the HP-41C CALCULATOR is available determine the release rates and 1/2 mile whole body dose rate as follows:
A.4.1.1 Turn calculator ON.
A.4.1.2 Place in " USER" mode.
A.4.1.3 Hit the I+ key.
' OP-3310 App. "A" Rev. 3 A.4.1.4 As the calculator prompts the operator, enter the data and hit the R/S key.
A 4.1.5 Log the release rate displayed on the nomogram board data sheet.
A.4.1.6 Hit the R/S key.
i A.4.1.7 Entee the distance of 0.5 miles and hit the R/S key to obtain the plume average dose rate.
A.4.1.8 Hit the R/S key again to get plume centerline (CL) dose rate.
Re-cord this value on OPF-3310.2.
A.4.1.9 If no other significant pathways exist the operator may hit the LN key.
In this mode the calculator will provide dose projections at one mile intervals from 1 to 10 miles, in sequence.
Simply press R/S after each projection is displayed.
A.4.1.10 If other significant release pathways exist the operator should hit the I+ key and repeat this procedure from Step A.4.1.4. When complete, add the release rates from all pathways and log; then add the 1/2 mile dose rates from all pathways and log.
A.4.1.11 Report'these values to the Emergency Director together with the time of the estimate and the plume trajectory.
A.4.2 USE OF NOMOGRAMS l
If the HP41-C Calculator is not available the release rates and the projected whole body dose rate at 1/2 mile is determined using the three nomograms.
For a specific release pathway, pro-ceed to the step as indicated below:
a.
Containment Pathway - Step A.4.3 i
b.
Primary Vent Stack Pathway - Step A.5 c.
Steam Line Pathway - Step A.6 A.4.3 USE OF CONTAINMENT NOM 0 GRAM A.4.3.1 Locate the " TIME AFTER SHUTDOWN" axis, at the appropriate value of
't' (hours) and draw a verticle line through the curves of parameters "J(t)/f(t)" and "J(t)".
l A.4.3.2 DETERMINATION OF RELEASE RATE l
A.4.3.2.1 At the intersection of the verticle line just drawn and the "J(t)"
curve, draw a horizontal line towards the right through the dia-gonal " Containment AARM" curves.
A.4.3.2.2 Draw a verticle line downwards from the horizontal line at the actual AARM reading listed on the Data Sheet A Step A.1.2.
The i
example on the nomogram is for an AARM reading of 10,000 R/hr.
t i
i
OP-3310 App. "A" Rev. 3 A.4.3.2.3 Record the Noble Gas Release Rate (Q) in (pCi/sec) indicated on the scale.
(Log on Data Sheet A).
NOTE:
If containment pressure is less_than 34 psig, correct the value of Q as follows:
)
Corrected Q = (Nomogram Q) x (VC Pressure PSIG) + 34 psig.
Log the corrected Q on Data Sheet A.
A.4.3.3 DETERMINATION OF 1/2 MILE DOSE RATE A.4.3.3.1 From the intersection of the initial verticle line and the "J(t)/f(t)" curve, draw a horizontal line to the right through the diagonal " CONTAINMENT AARM" curves.
A.4.3.3.2 Locating the intersection of this horizontal line and the AARM read-ing, proceed vertically upward to the appropriate stability class.
I A.4.3.3.3 From this point proceed horizontally to the right to the appropriate wind speed.
A.4.3.3.a From this point proceed vertically upward and log the off-site whole body dose rate at 1/2 mile on Data Sheet A.
NOTE:
If containment pressure is less than 34 psig, correct the value of dose rate as follows:
1 Corrected Dose Rate = (Nomogram Dose Rate) x (VC Pressure Psig) + 34 psig.
Log the corrected dose rate on Data Sheet A.
I j
A.5 USE OF PRIMARY VENT STACK NOM 0 GRAM il A.5.1 DETERMINATION OF RELEASE RATE (See example)
J A.5.1.1 Locate the " Time After Shutdown" axis. At the appropriate value of
't' (hours) draw a line vertically upward to the appropriate LOCA class on the J(t) curve.
f A.5.1.2 Proceed horizontally to the right to the monitor reading (from-the diagonal curves).
A.5.1.3 Proceed vertically downward to the proper scale for 1 fan or 2 fans.
j.
Log the Noble Gas Release Rate on Data Sheet A.
4 A.S.4 DETERMINATION OF 1/2 MILE DOSE RATE A.S.4.1 Locate the " Time After Shutdown" axis of the "J(t)/f(t)" curve.
At the appropriate value of
't' (hours) draw a line vertically upwards to the appropriate LOCA class.
1 I
' OP-3310 4
App. "A" Rev. 3 A.S.4.2 Proceed horizontally to the right to the monitor reading (from the diagonal curves).
1 A.5.4.3 Proceed vertically upward to the appropriate stability class.
A.S.4.4 Proceed horizontally to the right to the appropriate wind speed.
A.5.4.5 Proceed vertically upward to the proper scale for 1 fan or 2 fans.
Log the off site whole body dose rate at 1/2 mile on Data Sheet A.
A.6 USE OF THE MAIN STEAM LINE NOM 0 GRAM i
A.6.1 DETERMINATION OF RELEASE RATE i
~
A.6.1.1 Locate the " Time After Shutdown" axis on the "J(t)" curve. At the appropriate value of
't' (hours) draw a verticle line upwards to the appropriate LOCA class.
A.6.1.2 Proceed horizonatally to the right to the affected steam line monitor reading (from the diagonal curves).
il A.6.1.3 Proceed vertically downward to the proper scale depending on the-release point.
Log the Noble Gas Release Rate on Data Sheet A.
A.6.4 DETERMINATION OF 1/2 MILE DOSE RATE A.6.4.1 Locate the " Time After Shutdown" axis of the "J(t)/f(t)" curve.
y At the appropriate value of
't' (hours) draw a line vertically upward to the appropriate LOCA class.
A.6.4.2 Proceed horizonatally to the right to the affected steam line monitor reading (from the diagonal curves).
A.6.4.3 Proceed vertically upward to the appropriate stability class.
A.6.4.4 Proceed horizontally to the right to the appropriate wind speed.
A.6.4.5 Proceed vertically upward to the proper scale depending on the release point.
Log the Off-Site Whole Body Dose Rate'at 1/2 mile on Data Sheet A.
NOTE:
If the release point is the Emergency Atmospheric Steam Dump, the Off-Site Whole Body Dose Rate at 1/2 mile may be determined by one of the following ways:
1.
Calculate the W.B.D.R. for the Primary Atmospheric Steam Dump and multiply that value by 2.8.
2.
Calculate the W.B.D.R. for the Low Set Safety Valve and
[
multiply that value by 0.36.
T
~ OP-3310 App. "A" Rev. 3 A.7 If there was more than one significant release path add the release rates and 1/2 mile dose rates and log in the " Totals" section of Data Sheet A.
A.8 Report these values to the Emergency Director together with the time of the estimate and the plume trajectory.
DATA REDUCTION SHEET A DATE:
PREPARED BY:
CALCULATION NUMBER:
TIME AFTER SHUTDOWN:
HRS.
PRESENT TIME:
l RELEASE PATH:
1 2
3 l VAPOR CONTAINER (VC): If PRIMARY VENT STACK (PVS): If l STEAM LINE (SL) No.
l l less than 500 R/hr go to less than 1000 mr/hr go to l
{
l PVS.
Steam Lines STEAM LINE RADIATION CONTAINMENT NO. OF FANS = 1 or 2 LEVEL =
mR/hr PRESSURE =
psig i
i VAPOR CONTAINER RADIATION VENT STACK RADIATION ASD OR SRV 1.
LEVEL =
R/hr LEVEL =
mR/hr NORMAL - EMER. HI MED LOW l
l LOCA 1 or LOCA 3 WIND SPEED =
MPH WIND DIRECTION =
Degrees (from)
RELEASE RATE =
pCi/sec STABILITY CLASS: A,B,C,D,E,F,G l
I l
OFFSITE WHOLE BODY DOSE RATE (mR/hr) l l
l l
DISTANCE FROM SITE (MILES) l SECTOR AVERAGE l
CENTERLINE l
I
.s 1.0
)
l 2.0 i
l l
3.0-l l
4.0 5.0 6.0 7.0 8.0 9.0 10.0 (Other):
Total W.B. dose rate at miles. (sum of all release paths) mr/hr.
OPF-3310.2 Rev. 3 Page 1
r PROCEDURE FOR PROJECTING PLUME TRAJECTORTES BEYOND THE YANKEE PLANT'S EXCLUS10N AREA B0UNDARY A.
Atmospheric Stability:
A, B, C, D (Delta T less:.than or equal to -
0.45*F primary tower or -0.27 F back-up tower).
1.
Wind Sensors a.
Primary Vent Release:
use 60 m wind speed and direction b.
All other release points: use 10 m wind speed and direction 2.
Plume Trajectory a.
Wind from 350 clockwise through 79 (N through ENE):
Assume downstream trajectory b.
Wind from 80 clockwise through 169 (E through SSE):
Assume cross valley trajectory towards the W-NNW c.
Wind from 170 clockwise through 259 (S through WSW):
Assume upstream trajectory d.
Wind from 260 clockwise through 349 (W through NNW):
Assume cross valley trajectory towards the E-SSE 4
B.
Atmospheric Stability:
E, F, G (Delta T greater than -0.45 F primary tower or greater than -0.27 F back-up tower).
1.
Wind sensors a.
Primary Vent Release:
use 60 m wind speed and direction b.
All other release points:
use 10 m wind speed and 60 m_
l wind direction (a) 2.
Plume Trajectory a.
Wind from 301 clockwise through 120 :
Assume downstream trajectory (toward SSW) 1 b.
Wind from 121 clockwise through 300 :
Assume upstream trajectory (toward NNE)
(a) The 10 m wind direction sensors are often affected by localized drainage winds flowing down the East slope of the river valley during stable, nighttime hours; however, the plume should remain within the valley under these conditions. As such, the 60 m wind direction sensor should be used to determine if an upvalley or downvalley flow prevails.
OPF-3310.2 Rev. 3 Page 2 1
LOCA DESIGNATION BASED ON IN-CONTAINMENT AARM d
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l OPF-3310.2 Rev. 3 Page 3 t
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1 APPENDIX B OP-3310 Rev. 2 l
AppendiiB
{
EVALUATION OF 0FF-SITE PARTICULATE AND IODINE CONDITIONS B.1 Inplant Analysis of PVS Air Samples.
NOTE:
Proceed to "Section 2 of Appendix B" if PVS sample has not been taken.
B.1.1 Obtain sample according to procedures, OP-8740 and OP-9450.
B.1.2 Once the PVS air samples has been analyzed, on the plant GeLi,-(if available) or the SAM II (if plant Geli is not available) proceed as follows:
8.1.2.1 If counted on the plant GeLi, the primary desired output information is the activity of I-131 (C1)'and other particulates. Log this result on Data Reduction Sheet B.
B.1.2.2 If the charcoal cartridge is counted on the SAM II, calculate the ' activity on the cartridge using OP-8701 and log on Data Sheet B or proceed as follows:
Obtain the net count rate from the sample and the i
instrument efficiency. Log these results on Data Sheet B.
Determine the sample activity using the lower left quandrant of the " Field Sample Thyroid Dose Nomogram" by locating the I-131 Count Rate (cpm)" axis, proceed toward the right to the appro-priate counting efficiency (%), then proceed down and read the " SAMPLE ACTIVITY", mci (I-131).
Re-cord this result on Data Reduction Sheet B.
B.1.2.3 If the particulate filter is counted on the RM-14/HP 210 probe, repeat the Steps in B.2 using a counting efficiency of 10% for mixed particulates.
Record this result on Data Sheet B.
8.1.3.
Determine the concentrations of iodines and particulates at 1/2 mile as follows:
1 B.1.3.1 Determine the' stack release factors, 'X' and
'Y', and log on Data Sheet B.
X=b (sec 2) and t.Ff Y = 2.22.[px/Q]. [1/p(mph)] [sec m 3]
NOTE:
If the available meterological data for wind speed is in units of meters /sec, then eliminate the 2.22 conversion factor from the above equation defining j
parameter Y f
r n--
g -. - -. - - - - - - - _.,... -
-.-----.,y
,..,,.,.y y
,r-,,,.
.-..,,_.-<c.-e
_ _ _ _ _. OP-3310 Appendix B Rev. 2 Where:
Fs = PVS flow rate (CFM)
For 1 Fan, Fs = 23,000 CFM For 2 Fans, Fs = 35,000 CFM t = Time since beginning of release that cartridge was in sample stream, sec.
Ff = Flow rate through PVS air samples, CFM i
= 15 min. average wind speed (mph) i X/Q = 1/2 mile elevated release concentration diffusion factor from OPF-3310.7 B.1.3.2 Calculate the release rates and the 1/2 mile concentrations of iodine and particulates as indicated below, then log the results on Data Sheet B.
. Release Rate, Q (Ci Sec. ~1)
Q (Ci Sec. ~2) = Af (Ci) ' X Where A = Activity of the PVS air sample (C1) f
. Concentration, C(pCi/cm ), at 1/2 mile; 2
C (pCi/cm ) = Q(C1 Sec-1)
- Y 2
B.I.4.
Determine the Projected Adult and Newborn Thyroid Dose as follows:
Using the " Field Sample Thyroid Dose Nomogram" determine the appropriate Projected Dose Rates as follows:
B.1.4.1 Locate the "I-131 air concentration, micro Ci/cc" axis.
B.1.4.2 From the appropriate concentration value, proceed vertically upward to the one hour inhalation time value.
B.1.4.3 From this intersection proceed horizontally to the right and read the value of the Adult and Newborn Thyroid Dose. The dose rate estimate is the thyroid dose for every hour of inhalation.
Log these results on Data Sheet B.
B.1.5 Report projected thyroid dose rates and the particulate concentra-tions to the Emergency Coordinator.
l
r
" OP-3310 Appendi.x B Rev. 2 B.2 Analysis of Offsite Air Sample Results B.2.1 Obtain the following survey team sample results, sample location code, sample flow rate (CFM), sample collection time and sample count results.
Log them on Data Sheet B.
NOTE:
If significant positive net counts are reported from offsite monitoring teams, have the iodine sample analyzed on the SAM II per OP-8701 or on the in plant GeLi system.
B.2.2 Using the " Field Sample Thyroid Dose Nomogram" and the above information, determine the Adult-and Newborn Thyroid Dose Rate as follows:
B.2.2.1 Locate the "I-131 Count Rate (cpm)" axis (lower left quadrant).
B.2.2.2 From the appropriate cpm value, proceed to tho right to the I-131 counting efficiency line.
NOTE:
. RM-14 efficiency is 0.24%
. SAM-2 efficiency must be obtained from the top of the instrument.
. For Geli analysis, obtain sample activity (micro Ci) and-enter Nomogram at the " Sample Activity, micro C1 (I-131)"
axis.
B.2.2.3 From this point, proceed vertically upwards to the appropriate " Sampling Flow Rate" line.
B.2.2.4 Proceed horizontally to the right to.the value of.
the sample collection time.
B.2.2.5 From the point proceed vertically downward to the estimate of the " Inhalation Time (hours)" line.
B.2.2.6 From this line, proceed horizontally to the right and read the value of the Adult and Newborn Thyroid Dose Estimate.
Log these results on Data Sheet B.
B.2.2.7 Report projected dose rate results to the Emergency Coordinator.
B.2.2.8 Update Status Board.
B.2.3 By using the " Field Sample Thyroid Dose Nomogram" and the survey team particulate filter sample results, determine the particule airborne concentration as follows:
B.2.3.1 Locate the " Particulate Sample" count rate (CPM) using the "I-131 Count Rate" axis.
B.2.3.2 From the appropriate CPM value, proceed to the right until you intersect the 10% counting effi-ciency line.
1 OP-3310 Appendix B Rev. 2 B.2.3.3 From this point, proceed vertically upwards until you intersect the appropriate " Sampling Flow Rate" line.
B.2.3.4 From this point, proceed horizontally to the right to the appropriate value of the sample collection time.
B.2.3.5 From this point, proceed vertically downard until you intersect the "I-131 Air Concentration" line.
This value read at the intersection point will correspond to the gross (Beta, Gamma) particulate air concentration for the sample.
Report this result to the Emergency Coordinator.
r DATA REDUCTION SHEET B EVALUATION OF 0FF-SITE PARTICULATE AND I0 DINE CONDITIONS I
'I.
PVS AIR SAMPLES - ANALYSIS I
A.
Collect the following information:
Date/ Time Date/ Time Stack Flow l Sample l Sampling l (p x/Q)c l
PVS Sample Sample Sample Rate l
Flow l
Time l
1/2 mile l
Number Off Count CFM l
Rate (CFM) l t (sec) l l
l l
1 l
I I
I I
I i
B.
Calculate Release Rates l
PVS l PVS Sample Activities,A M l Release Factors lReleaseRate,Q(CiSec)T f
Sample Part.
Iodine - 131 l
x Y
Part.
l (sec-1)
(Sec m-3) l 1
I i
l i
C. Calculate Concentrations and Thyroid Dose Rate 1
PVS 1/2 Mile Conc., y C1/cc Thyroid Dose Rate, Rem /hr, I-131 Sample #
Part.
1-131 Adult Newborn I
l l
I
.i i
I I
i l
I OPF-3310.3 4
Appendix B Rev. 1 Page 1 1
I
-l
~ _
D
DATA REDUCTION SMEET B EVAL'UATION OF 0FF-SITE PARTICULATE AND IODINE CONDITIONS-II.
ANALYSIS OF 0FF-SITE AIR SAMPLES A.
Field Analysis Sample Sample l Time l Sampling l Particulate Filter Iodine Cartridge Location ' Flow Rate Sample l Duration l RM-14 l Part.
RM-14 T_hyroid Dose (rem /hr)
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l l
l l
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l l
l l
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B.
EOF Analysis of Iodine Cartridge (SAM II) l Sample l Sample Time Sampling Particulate Filter Iodine Cartridge Location l Flow Rate Sample Duration RM-14 Part.
Code l
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l 1
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OPF-3310.3 Appendix B
-Rev. 1 Page 2 N
r --
DATA REDUCTION SHEET B
~
Thyroid Dose Assess:ent From Inplant and Offsite Measurements I.
Inplant Measurements (PVS Release)
B PVS Sample.
l l
1/2 Mile I-131 l
Sample Activity PVS I-131 1/2 Mile p
x/Q Concentration
-l 1 C1 (I-131)
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(m/sec)
(sec m 3)
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l I
1 l
l 1
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I 4
l l
l I
5 l
C. PROJECTED THYROID DOSES (from " Field Sample
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Sample I-131 Conc. @ 1/2 Mile Projected Thyroid Dose Rate (From Above)
Adult Newborn l
l 1
l l
l 2
l 3
4 5
l l
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II 0FFSITE SAMPLE ANALYSIS l
SAM II ANALYSIS l
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I l
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APPENDIX C OP-3310 Appendix C
.Rev. 2 Page 1 RADIOLOGICAL CONDITION PROJECTIONS TO OTHER DISTANCE OF INTEREST NOTE:
Record all data on the Data Reduction Sheet C as this Appendix is performed.
C.1 Whole body dose / dose rate projections NOTE:
Whole body doses / dose rates may be projected from any distance, X, to any other distance, X3 whether g
the value at X, is measured by off-site teams or calculated from Appendix A.
C.1.1 Obtain the value of whole body dose / dose rate at any distance from the site, Xo (radial distance).
C.I.2 Determine the present stability class (see OPF-3310.9, Page 1)
C.1.3 From the above stability class, determine the value of the EFFECTIVE GAMMA DOSE DIFFUSION FACTORS, (px/Q)T, for the distance Xo and desired distance, X, for the appropriate release height on OPF-3310.5 or OPF-3310.6.
Log these values on Data Reduction Sheet C.
NOTE:
ONLY A STACK RELEASE IS CONSIDERED AS ELEVATED C.1.4 Determine the whole body dose / dose rate at distance X, as follows and log on Data Sheet C.
D * (p x/Q) X /(p x/Q)#y.
D
=
x x
I 1
o o
1 i
I t
4
r 1 OP-3310 Appendix C Rev. 2 C.2 Thyroid Dose or Air Concentration Projections NOTE:
Thyroid dose or air concentrations may be projected from any distance, Xo to any other distance, X i, whether the value at Xo is measured by off-site teams or calculated from Appendix A.
C.2.1 Obtain the value of thyroid dose or air concentration at any distance from the site, Xo (radial distance).
C.2.2 Determine present stability class (see OPF-3310.9, Page 2)
C.2.3 From the above stability class, determine the value of the CONCENTRATION DIFFUSION FACTORS (px/Q)c, for the distance, Xo, and the desired distance, X 2 for the appropriate release height on OPF-3310.7 or OPF-3310.8.
(px/Q)cX D
"0 x
x (px/Q)c Eo NOTE:
ONLY A STACK RELEASE IS CONSIDERED AS ELEVATED C.2.4 Determine the thryoid dose or air concentrations at distance X, as follows and log on Data Sheet C.
C.3 Particulate Concentration Projections C.3.1 Perform the same procedure as for Iodine (C.2) using OPF-3310.9, Page 3 and dealing only with concentrations.
YANKEE ROUE EFFECTIVE GAMMA DOSE DIFFUSION FACTORS yx T.M2 ELEVATED LEVEL RELEASE Q
(All values should be multiplied by 10~ ')
Downwind Stability Category Distance Pasquill A Pasquill B Pasquill C Pasquill D Pasquill E Pasquill F Pasquill G 0.5 miles 7.9 16.0 19.0 19.0 18.0.
17.0 17.0 1.0 miles 1.2 4.1 8.0 9.9 9.7 8.9 8.6 2.0 miles 0.62 0.67 2.9 4.6 4.9 4.8 4.4 3.0 miles 0.42 0.42 1.5 2.8 3.2 3.3 3.0 4.0 miles 0.31 0.31 0.93 1.9 2.3 2.5 2.3 5.0 miles 0.25 0.25 0.64 1.4 1.8 2.0 1.9 6.0 miles 0.21 0.21 J.47 1.1 1.4 1.6 1.6 7.0 miles 0.18 0.18 0.36 0.91 1.2 1.4 1.4 8.0 miles 0.16 0.16 0.29 0.77 1.0 1.2 1.2 9.0 miles 0.14 0.14 0.24 0.66 0.89 1.1 1.1 10.0 miles 0.12 0.12 0.20 0.57 0.78 0.97 0.97 OPF-3310.5 Rev. 1
T YANKEE R0WE EFFECTIVE GAMMA DOSE DIFFUSION FACTORS yx i. M 2' ELEVATED LEVEL RELEASE Q
(All values should be multiplied by 10 ')
Downwind Stability Category Distance Pasquill A Pasquill B Pasquill C Pasquill D Pasquill E Pasquill F Pasquill G 0.5 miles 8.3 19.0 26.0 34.0 37.0 41.0 47.0 1.0 miles 1.3 4.3 9.5 14.0 16.0 18.0 20.0 2.0 miles 0.63 0.68 3.1 5.7 6.9 8.3 9.4 3.0 miles 0.42 0.42 1.6 3.3 4.2 5.2 6.0 4.0 miles 0.31 0.31 0.93 1.9 2.3 2.5 2.3 5.0 miles 0.25 0.25 0.66 1.6 2.2 2.9 3.4 6.0 miles 0.21 0.21 0.49 1.3 1.7 2.3 2.8 7.0 miles 0.18 0.18 0.37 1.0 1.4 2.0 2.4 8.0 miles 0.16 0.16 0.30 0.85 1.2 1.7 2.0 9.0 miles 0.14 0.14 0.24 0.72 1.0 1.5 1.8 10.0 miles 0.13 0.13 0.20 0.62 0.92 1.3 1.6 OPF-3310.6 Rev. 1
YANKEE R0WE c -
EFFECT1VE GAMMA DOSE DIFFUS10N FACTORS yx g2 ELEVATED LEVEL RELEASE Q
(All values should be multiplied by 10 ')
Downwind Stability Category Distance Pasquill A Pasquill B Pasquill C PasquiiI D Pasquill E Pasquill F Pasquill G 0.5 miles 6.3 23.0 40.0 29.0 9.5 0.03 0.00 1.0 miles 1.4 4.9 17.0 32.0 31.0 5.8 0.04 2.0 miles 0.77 1.1 5.7 17.0 24.0 20.0 2.2 3.0 miles 0.55 0.73 2.9 10.0 17.0 20.0 5.9 4.0 miles 0.43 0.56 1.8 6.9 12.0 18.0 8.5 5.0 miles 0.36 0.46 1.2 5.1 9.8 15.0 9.2 6.0 miles 0.31 0.40 0.92 4.0 8.0 13.0 9.5 7.0 miles 0.26 0.35 0.72 3.3 6.8 12.0 9.5 8.0 miles 0.23 0.32 0.58 2.8 5.9 11.0 9.4 9.0 miles 0.21 0.29 0.49 2.4 5.1 9.6 9.1 10.0 miles 0.19 0.26 0.42 2.1 4.5 8.8 8.7 OPF-3310.7 Rev. 1 a
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YANKEE R0WE EFFECTIVE GAMMA DOSE DIFFUSION FACTORS yx.Ma ELEVATED LEVEL RELEASE Q
(All values should be multiplied by 10 ')
Downwind Stability Category Distance Pasquill A Pasquill B Pasquill C Pasquill D Pasquill E Pasquill F Pasquill G 0.5 miles 6.4 26.0 60.0 160.0 260.0 450.0 920.0 1.0 miles 1.4 4.9 19.0 60.0 110.0 210.0 350.0 2.0 miles 0.77 1.1 5.9 21.0 41.0 85.0 170.0 3.0 miles 0.55 0.73 3.0 12.0 24.0 52.0 110.0 4.0 miles 0.43 0.56 1.8 7.6 16.0 38.0 79.0 5.0 miles 0.36 0.46 1.2 5.5 12.0 29.0 61.0 6.0 miles 0.31 0.40 0.92 4.3 9.6 23.0 50.0 7.0 miles 0.26 0.35 0.72 3.5 7.9 20.0 42.0 8.0 miles 0.23 0.32 0.58 3.0 6.7 17.0 36.0 9.0 miles 0.21 0.29 0.49 2.5 5.8 15.0 32.0 10.0 miles 0.19 0.26 0.42 2.2 5.1 13.0 29.0 OPF-3310.8 Rev. 1
7 v
DATA REDUCTION SHEET C I. WHOLE BODY DOSE / DOSE RATE PROJECTIONS A. Determine Stability Class from the following table:
PRIMARY TOWER SECONDARY TOWER AT ( F)
STABILITY CLASS ~
AT ( F)
'ATs - 1.71 A
'ATs - 1.04
-1.71 'ATs - 1.53 8
-1.04 'ATs - 0.93
-1.53 'ATs - 1.35 C
-0.93 'ATs - 0.82
-1.35 'ATs - 0.45 0
-0.82 'ATs - 0.27
-0.45 'ATs + 1.35 E
-0.27 'ATs + 0.82 o1.35 'ATs + 3.60 F
+0.82 'ATs + 2.20
+3.60 'ATs G
+2.20 'ATs B.
Project Oose/ Dose Rates A
B C
D E
F G
H I
l Distance l Distance l Stab l rI i
l(E)+(D) l WB Dose /
l(G) X (F),W.B. Date/ Time l at Xo I at X2 l Classl(px/Q) l(px/Q) l Dose l Dose / Rate I Dose / Dose of Pro-l (mi)
I (mi) l l
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l Rate l at Xo l Rate at X jection i
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- Indicate all units in tables OPF-3310.9 Appendix C Rev. 3 Page 1
DATA REDUCTION SHEET C I. WHOLE BODY D'SE/ DOSE RATE PROJECTIONS 0
j A. Determine Stability Class from the following table:
PRIMARY TOWER SECONDARY TOWER AT ( F)
STABILITY CLASS AT ( F)
'ATs - 1.71 A
'ATs - 1.04
-1.71 'ATs - 1.53 B
-1.04 'ATs - 0.93
-1.53 'ATs - 1.35 C
-0.93 'ATs - 0.82
-1.35 'ATs - 0.45 0
-0.82 'ATs - 0.27
-0.45 'ATs + 1.35-E
-0.27 'ATs + 0.82
+1.35 'ATs + 3.60 F
+0.82 'ATs + 2.20
+3.60 'ATs G
+2.20 'ATs B.o Project Dose / Dose Rates A
B C
D E
F G
H I
l Distance l Distance l Stab l r
T l(E)+(D) l WB Dose /
l(G) X (F),W.B.lDate/ Time at Xo l at X1
' Classl(px/0)
(px/Q)
Dose lDose/ Rate l Dose / Dose l of Pro-(mi)
I (mi)
I Xl X
Rate l at Xo l Rate at X l jection 2
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Page 1
m DATA REDUCTION SHEET C
'II.
THYROID DOSE / DOSE RATE PROJECTIONS A. Determine Stability Class from the following table:
PRIMARY TOWER SECONDARY TOWER AT ( F)
STABILITY CLASS AT ( F)
'ATs - 1.71 A
'ATs - 1.04
-1.71 'ATs - 1.53 8
-1.04ATs - 0.93
-1.53 'ATs - 1.35 C
-0.93 'ATs - 0.82
-1.35 (ATs - 0.45 D
-0.82 'ATs - 0.27
-0.45ATs + 1.35 E
-0.27 'ATS + 0.82
+1.35 'ATs + 3.60 I F
+0.82 'ATS + 2.20
+3.60 i Ts G
+2.20 'ATs A
B.o Project Dose / Dose Rates A
B C
D E
F G
H I
Distance i Distance I Stab l r
T
'(E)+(D)
WB Dose /
- (G) X (F),W.B. Date/ Time
- at Xo l at XY Class (px/Q)
'(px/Q)
Dose Dose / Rate Dose / Dose of Pro-(mi)
.(mi)
X X
Rate at Xo Rate at X jection 1
1 o
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F DITA REDUCTION SHEET C III.
PARTICULhTE (AIRBORNE) CONCENTRATION PROJECTIONS A. Determine Stability Class from the following table:
PRIMARY TOWER SECONDARY TOWER AT ( F)
STABILITY CLASS AT ( F)
'ATs - 1.71 A
'ATs - 1.04
-1.71 'ATs - 1.53 B
-1.04 'ATs - 0.93
-1.53 'ATs - 1.35 C
-0.93 'ATs - 0.82
-1.35 'ATs - 0.45 D
-0.82 'ATs - 0.27
-0.45 'ATs + 1.35 E
-0.27 'ATs + 0.82
+1.35 'ATs + 3.60 F
+0.82 'ATs + 2.20
+3.60 'ATs G
+2.20 'ATs B.o Project Dose / Dose Rates A
B C
D E
F G
H I
TDistancel Distance l5 tab l ri r
l(E)*(D) l WB Dose /
l(G) X (F),W.B.lDate/ Time l at Xo l at X2 l Class (px/Q) l(px/Q) l Dose IDose/ Rate Dose / Dose I of Pro-l (mi) l (mi) l Xl X
l Rate I at Xo Rate at X l jection l
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l F
OP-3310 A::pendix D Rev. 2 APPENDIX D Collection of Environmental Samples D.1 Equipment and supplies at Emergency Operations Facility (EOF)
D.1.1 Thermoluminercent Dosimeters (TLD) reader.
D.1.2 TLD annealing oven.
D.1.3 Spare TLD's and TLD holders.
D.1.4 A supply of charcoal cartridges (a minimum of 50) impregnated with triethylindiamine (T.E.D.A.)
D.1.5 A supply of_2h x 4 inches manila envelopes.
D.1.6 A supply of one (1) gallon containers (approximately 50) 0.1.7 A supply of one (1) liter, wide mouth poly bottles (approx.50) 0.1.8 A supply of 12" x 12" zip-lock bags (approximately 200) 0.1.9 Keys to the Air Sample Stations.
D.1.10 Copies of OP-4802, " Radiological Environmental Sample Collec-tion" and DP-4817, " Operation of The Teledyne Isotopes Thermo-luminescent Dosimetry System" D.2 Actions D.2.1 Immediately upon arrival at EOF, turn on the TLD annealing oven (set main dial on LOW and small dial at 52) 0.2.2 At the direction of the Emergency Coordinator collect samples according to OP-4802. Refer to the map on OPF-3310.15 for sampler locations.
D.2.3 Insure that all samples are properly labeled with location, date and time and collector.
D.2.4 Transport all samples except TLD's to the Yankee mobil van or to the Westboro Environmental lab as directed by the Emergency Coordinator.
D.2.5 Return TLD's to the E0F for analysis per DP-4817.
D.2.6 For each air sample collected, complete Data Sheet D.
F DATA SHEET D OP-3310 Rev. 1 PLUME DATA SHEET Air Sample Station ID:
Distance and Azimuth mi 2
Date Sample Removed:
Time Sample Removed:
Total Sample Time hours 2 Estimated Plume Immersion time:
hours.
Plume Radioactivity Concentration Factor Total Sample Time (hours)
Estimated Plume Immersion Time (hours)
Multiply the activity concentration on the air particulate filter and charcoal cartridge by the above factor to obtain plume con-centration.
2 From Table I 2 From OPF-4802.1 l
l l
OPF-3310.10 l
Rev. 1 L
7 APPENDIX'E OP-3310
~
Rev. 2 Appendix E Page 1 PROTECTIVE ACTION RECOMMENDATIONS FOR THE PUBLIC DISCUSSION:
This section is the responsibility of the Radiological Evaluation Assistant (REA) who reports to the Emergency Coordinator.
The Emergency Coordinator has the final responsibility and authority to act on the recommendation of the Radiological Evaluation Assistant and communicate the recommendation to the State authorities.
The REA gathers the appropriate information concerning projected and measured dose rates. The population at risk is determined based on the meteorological data. An exposure time is determined based on the best available information.
The projected dose is calculated by multiplying the dose rate and the exposure time..The protective action is determined from the EPA guidance.
If the EPA levels are reached, the Emergency Coordinator communicates the recommendation, the projected dose, the plume direction, the plume arrival time, and the plume duration.
It should be emphasized to the State that no compensation in the recom-mendation was made for the plume travel time, duration, or the time to implement and complete protective actions.
For an accident involving loss of all core cooling capability, explicit protective action recommendations are contained in OPF-3310.11.
PROCEDURE E.1 Using OPF-3310.12 or a similar form, document the information recorded as the procedure is performed.
For LOSS OF ALL CORE COOLING CAPABILITY go directly to OPF-3310.11.
E.2 Obtain the current wind direction.
E.3 Determine the location of concern (population at risk) see OPF-3310.11.
E.4 Obtain the latest dose rates at the location of concern from any of the following:
1 a.
In plant 1/2 mile projections (0P-3310, Appendix A) b.
Off-site monitoring results (OP-3310, Appendix B) c.
Projections to other distances (OP-3310, Appendix C) i E.5 Determine the plume duration.
If better information is not avail-able, a value of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shall be used.
E.6 Calculate the projected doses.
F
. OP-3310 APP. E Rev. 2 E.7 If the projected doses DO NOT exceed the EPA levels on OPF-3310.11, forward this information to the Emergency Coordinator with no re-commendation for protective action.
The Emergency Coordinator or the Radiological Evaluation Assistant shall communicate this infor-mation to the States.
E.8 If the projected dose reaches the EPA levels in OPF-3310.11, deter-mine the appropriate protective action recommendation and forward this to the Emergency Coordinator.
E.9 The Emergency Coordinator should evaluate the recommendation and transmit it to the States.
l l
l
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l
PROTECTIVE ACTION RECOMMENDAT10N GUIDELINES A.
EPA PROTECTIVE ACTION GUIDES Whole Body Thyroid Protective Action l
51 rem 45 rem No Actio'n 1 to 85 rem 5 to (25 rem Seek shelter, await further instructions l
l l
l B.
POPULATION AT RISK 1.
For wind direction from NORTH the populertion at risk is to South only.
2.
For wind direction from SOUTH any recommendation made shall include the Town of Monroe Bridge.
C.
LOSS OF ALL CORE COOLING CAPABILITY the protective action recommen-dations are as follows:-
1.
For wind direction from North or cross flow:
Monroe - Evacuation Readsboro - Take shelter, await instructions 2.
For wind direction from South:
Monroe - Evacuation Readsboro - Evacuation i
OPF-3310.11 Rev. 3
F PUBLIC PROTECTIVE ACTION RECOMMENDATION WORK SHEET DATE:
Wind Direction:
From NORTH From SOUTH Location:
Dose Rate:
REM /hr (whole body):
REM /hr (thyroid)
Plume Duration:
hours Projected Dose:
REM (Whole Body)
REM (thyroid)
YES NO 1.
Protective Action Recommendation: (If EPA PAG is exceeded)
SHELTER EVACUATE 2.
Projected Dose:
REM (Whole Body)
REM (thyroid) 3.
Wind Direction:
From NORTH From SOUTH 4.
Location:
5.
Plume Arrival Time:
hours (Time of Day) 6.
Plume Duration:
hours 7.
Name of person making recommendation:
a.
R.E.A.
b.
E.C.
8.
Name of person receiving recommendation:
NAME:
STATE:
TIME:
NAME:
STATE:
TIME:
OPF-3310.12 Rev. 2
)
APPENDIX F OP-3310 App. F Rev. 3 TABLE I AIR SAMPLE LOCATIONS LOCATION DISTANCE FROM VC (miles)
. AZIMUTH A-1 Furlon House
.5 232 A-2 Harriman Station 2.0 359*
A-3 Rowe School 2.6 128*
A-4 Observation Stand
.3 313*
A-5 Williamstown 13.8 265 A-6 Heartwellville 7.8 333 A-7 Monroe Bridge
.7 236 Sample Frequency:
Continuous.AP = Filter CF = Charcoal TABLE II WATER SAMPLE LOCATIONS LOCATION DISTANCE FROM VC (miles)
AZIMUTH WR-1 Harriman Reservoir 6.3 Upriver UR-2 Sherman Pond
.06 349 WR-3 Bear Swamp Lower Reservoir 3.9 Downriver WF-1 Plant Potable On-Site Well WF-2 Sherman Spring
.12 304*
UW-1 East Storm Drain
.06 6
60-2 West Storm Drain
.06 280 Sample Frequency: WR-1 thru WR-3 Monthly (Quarterly Composite)
WF-1 and WF-2 Quarterly WW-1 and WW-2 Monthly (In-House)
TABLE III SOIL SAMPLE LOCATIONS LOCATION DISTANCE FROM VC (miles)
AZIMUTH TS-1 Rowe School 2.6 128 TS-2 Monroe Bridge
.7 236 TS-3 Observation Stand
.3 313 TS-4 Harriman Station 2.0 359 TS-5 Dunbar Brook 2.0 211*
TS-6 West Cemetary 2.0 150 TS-7 Crossroad 2.3 83 TS-8 Whitingham Line 2.2 32 TS-9 Adams Hi-Line 1.3 289 TS-10 Heartwellville 7.8 333 TS-11 Williamstown 13.8 265 Sample Frequency: Once per three years TABLE IV VEGETATION SAMPLE LOCATIONS I
LOCATION DISTANCE FROM VC (miles)
AZIMUTH TG-1 Monroe Bridge
.7 236 TG-2 Harriman Station 2.0 359
}
TG-3 Rowe School 2.6 128 TG-4 Observation Stand
.3 313 TG-5 Williamstown 13.8 265 TG-6 Heartwellville 7.6 333 Sample Frequency: Once per 92 days April thru December
~ OP-3310 App. F i
Rev. 3 TABLE V RIVER SEDIMENT SAMPLE LOCATIONS LOCATION DISTANCE FROM VC (miles)
AZIMUTH SE-1 Harriman Reservoir 6.3 Upriver SE-2 Sherman Pond
.06 332 SE-3 #5 Station Pond
.6 Downriver SE-4 #4 Station Pond 22.5 Downriver SE-5 Griswoldville Pond 3.1*
Upriver
- From confluence of Deerfield and North River Sample Frequency:
Semi-Annually TABLE VI MILK SAMPLE LOCATION LOCATION DISTANCE FROM VC (miles)
AZIMUTH TM-1 Lively Farm (Heath, MA) 3.6 100 TM-2 King Farm (Readsboro, VT) 3.8 354 TM-3 Mt. Williams Dairy (Williamstown, MA) 13.0 258 Sample Frequency: Monthly TABLE VII FISH AND AQUATIC PLANT SAMPLE LOCATIONS LOCATION DISTANCE FROM VC (miles)
AZIMUTH FH-1 Harriman Reservoir 6.3 Upriver FH-2 Sherman Pond
.9 FH-3 #4 Station Pond 22.5 Downriver Sample Frequency:
Semi-Annual TABLE VIII FOOD SAMPLE LOCATIONS 1.*
Monroe Bridge, Readsboro or Rowe; specify location, distance from plant and Azimuth.
2.*
Williamstown; specify location, distance from plant and Azimuth.
Sample Frequency: Annual (harvest time)
Use Code TV if sample is green leafy vegetable, otherwise use Code TF
r OP-3310
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~
App. F Rev. 3 i
TABLE IX GAMMA MONITORING LOCATIONS LOCATION APPROXIMAIE DISTANCE FROM VC (miles)
SECTOR GM-1 Furlon House
.5 SW GM-2 Observation Stand
.3 NW GM-3 Rowe School 2.6 SE GM-4 Harriman Station 2.0 N
GM-5 Monroe Bridge
.7 WSW GM-6 Readsboro Road Barrier
.8 N
GM-7 Whitingham Line 2.3 NE GM-8 Monroe Hill Barrier 1.1 S
GM-9 Dunbar Brook 2.0 SW GM-10 Cross Road 2.3 E
GM-11 Adams Hi-Line 1.3 WNW GM-12 Readsboro, VT.
3.4 NNW GM-13 Restricted Area Fence
.05 SW GM-14 Restricted Area Gence
.07 WNW GM-15 Restricted Area Fence
.05 NNW GM-16 Restricted Area Fence
.08 NE GM-17 Restricted Area Fence
.087 ENE GM-18 Restricted Area Fence
.087 ESE GM-19 Restricted Area Fence
.1 SE GM-20 Restricted Area Fence
.1 SSE GM-21 Restricted Area Fence
.07 WSW GM-22 Heartwellville 7.8 NNW GM-23 Williamstown 13.8 W
GM-24
~4.6 N
GM-25
~4.8 NNE GM-26 4.7 NE GM-27 4.8 ENE GM-28 3.7 E
GM-29 5.2 ESE GM-30 5.8 SE GM-31 4.7 SSE GM-32 4.9 S
GM-33 4.3 SSW GM-34 4.0 SW GM-35 5.3 WSW GM-36 4.2 W
GM-37 4.2 WNW GM-38 4.2 NW GM-39 4.3 NNW GM-40 0.3 W
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