L-03-081, Revisions to Implementing Procedures (Volume 2)
| ML031530199 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/27/2003 |
| From: | Pearce L FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-03-081 | |
| Download: ML031530199 (83) | |
Text
Beaver Valley Power Station FENOC
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168 OWN%
PO. Box 4 FlrstEnergy Nuclear Operating Conpany Shippingport, PA 15077-0004 L. WVilliamn Pearce 724-682-5234 Site Vice President Fax: 724-643-8069 May 27, 2003 L-03-081 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Beaver Valley Power Station Emergency Preparedness Plan Implementing Procedures (Volume 2)
In accordance with 10 CFR Part 50.4, this letter forwards recent revisions of the Beaver Valley Power Station Emergency Preparedness Plan Implementing Procedures (Volume 2) to the Nuclear Regulatory Commission. The changes do not decrease the effectiveness of the Plan and the Plan, as changed, continues to meet the requirements of Appendix E of 10 CFR 50. Therefore, 10 CFR Part 50.54(q) requires that these changes be submitted for information only.
There are no regulatory commitments contained in this letter. If there are any questions concerning this submittal, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Performance Improvement at 724-682-5284.
Sincerely, William Pearce - Summary of Changes -Procedure revisions c:
Mr. T. G. Colburn, NRR Senior Project Manager (w/o Enclosure 2)
Mr. D. M. Kern, NRC Sr. Resident Inspector (w/o Enclosure 2)
Mr. H. J. Miller, NRC Region I Administrator (2 copies)
VS Summary of Changes Revisions to Beaver Valley Power Station Emergency Preparedness Plan Implementing Procedures (Volume 2)
The following is a brief summary of the changes made to the Emergency Preparedness Plan Implementing Procedures.
EPP/Implementin2 Procedures:
EPP/-2 "Unusual Event" Revision 19 added additional guidance via new Steps E.1.5 through E.1.5.2, for conducting Site Assembly/Accountability during a security event.
A new "Determination of Airborne Radioactive Releases During Emergencies" was incorporated for use in Steps E.1.3, E.1.9, and E.2.2. Also, three Condition Reports were added as new references.
EPP/I-3 "Alert" Revision 18 revised Steps E.1.5.1 and E.1.5.2 regarding guidance for conducting Site Assembly/Accountability during a security event.
A new Attachment 2 "Determination of Airborne Radioactive Releases During Emergencies" was incorporated for use in Steps E.1.3, E.l.11, E.2.2, and E.2.6. Also, two Condition Reports were added as new references.
EPP/I-4 "Site Area Emergency" Revision 18 revised Steps E.1.5.1 and E.1.5.2 regarding guidance for conducting Site Assembly/Accountability during a security event.
A new Attachment 2 "Determination of Airborne Radioactive Releases During Emergencies" was incorporated for use in Steps E.1.3, E.1.12, E.2.2, and E.2.9. Also, two Condition Reports were added as new references.
EPP/I-5 "General Emergency" Revision 19 revised Steps E. 1.5.1 and E. 1.5.2 regarding guidance for conducting Site Assembly/Accountability during a security event.
A new Attachment 2 "Determination of Airborne Radioactive Releases During Emergencies" was incorporated for use in Steps E.1.3.1, E.1.12, E.2.2.1, and E.2.9.
Also, two Condition Reports were added as new references.
A5.735B yr EPP/IMPLEMENTING PROCEDURES - EFFECTIVE INDEX INSTRUCTIONS EPPlI-la Recognition and Classification of Emergency Conditions EPP/1-lb Recognition and Classification of Emergency Conditions EPP/I-2 Unusual Event EPP/I-3 Alert EPP/I-4 Site Area Emergency EPP/I-5 General Emergency Revision 4 Revision 4 Revision 19 Revision 18 Revision 18 Revision 19 IMPLEMENTING PROCEDURES 1 Series - Activation 1.1 Notification
-1.2 Communications and' Dissemination of Information 1.3 Turnover Status Checklist ED/ERM
- 1.4 Technical Support Center (TSC)
Activation, Operation and Deactivation' 1.5 Operations Support Center (OSC)
Activation, Operation and Deactivation 1.6 Emergency Operations Facility (EOF)
Activation, Operation and Deactivation 1.7 Emergency Response Organization (ERO)
Teams CONTROLLED BVPS-UNIT 3 Revision 31 Revision 18 Revision 9 Revision 18 Revision 14 Revision 16 Revision 10 REVISION 56 EPP/IP
A 5.735 B i
EPPIIMPLEMENTING PROCEDURES - EFFECTIVE INDEX 2 Series - Assessment Emergency Radiological Monitoring Revision 10 Onsite Monitoring for Airborne Release Revisio 12 Offsite Monitoring for Airborne Release Revision 13 Offsite Monitoring for Liquid Release Revision 8 Emergency Environmental Monitoring Revision 10 Environmental Assessment and Dose Revision 14 Projection Controlling Procedure 2.6.1 Dose Projection - Backup Methods
.Revision 11 2.6.2 Dose Projection - ARERAS/MIDAS Revision 12 With FSAR Defaults 2.6.3 Dose Projection - ARERAS/MIDAS Revision. 12 With Real-Time Inputs 2.6.4 Dose Projection - ARERAS/MIDAS Revision 13 With Manual Inputs 2.6.5 Alternate Meteorological Parameters Revision 10 2.6.6 Dose Projections By Hand Calculation -
Revision 6 Known Isotopic Release.
2.6.7 Dose Assessment Based on Revision 7 Field Measurements 2.6.8 Dose Assessment Based on:
Revision 6 Environmental Measurements and Samples 2.6.9 Integrated Dose Assessment Revision 6 2.6.10 Ground Contamination Assessment Revision 7 and Protective Action RE VISION 56 EPP/IP 2.1 2.2 2.3 2.4 2.5 2.6 V
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A5.735B EPP1IMPLEMENTING PROCEDURES - EFFECTIVE INDEX 2 Series - Assessment 2.6.11 Dose Projection - Miscellaneous Data 2.6.12 Dose Projection -ARERAS/MIDAS With Severe Accident Assessment 2.7 Liquid Release Estimate 2.7.1 Liquid Release Estimate -
Computer Method 3 Series - Onsite Protective Actions 3.1 Evacuation 3.2 Site Assembly and Personnel Accountability 3.3 Emergency Contamination Control 3.4 Emergency Respiratory Protection 3.5 Traffic and Access Control 4 Series - Offsite Protective Actions 4.1 Offsite Protective Actions EPP/IP 5.1 5.2 5.3 5.4 5 Series - Aid to Personnel Search and Rescue RESERVED Emergency Exposure Criteria and Control Emergency Personnel Monitoring Revision 10 Revision 9 Revision 6 Revision 9 Revision 8 Revision 13 Revision 7 Revision 8 Revision 9 Revision 16 Revision 8 Revision 8 Revision 7 REVISION 56 EPPIIP EPP/IP EPP/IP
.73 A5.735B EPPIMPLEMENTING PROCEDURES - EFFECTIVE INDEX 6 Series - Re-entry/Recoverv 6.1 Re-entry to Affected Areas -
Criteria and Guidance 6.2 Termination of the Emergency and Recovery Revision 9 Revision 10 7 Series - Maintaining Emergencv Preparedness 7.1 Emergency Equipment Inventory and Maintenance Procedure 7.2 Administration of Emergency Preparedness Plan, Drills and Exercises 8 Series - Fire Fightin2 8.1 Fires in Radiologically Controlled Areas 9 Series - Nuclear Communications 9.1 Emergency Public Information Emergency Response Organization Controlling Procedure 9.2 Reserved 9.3 Activation, Operation and Deactivation of the Emergency Public Information Organization Emergency Operations Facility (EOF) 9.4 Activation, Operation and Deactivation of the Joint Public Information Center (JPIC) 9.5 Activation, Operation and Deactivation of the Penn Power Customer Account Services Department 10 Series Corporate Response 10.1 Emergency Response Organization Corporate Support Revision 14 Revision' 9 Revision 10 Revision 11 R s 4 Revision 4 R
Revision 9 j,f Revision
.i, Revision 3 V-REVISION 56 i~~~~:
EPP/IP EPPIIP
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EPP/IMPLEMENTING PROCEDURES - EFFECTIVE INDEX EPPIIP ANNEXES Annex A -
Westinghouse Emergency Response Plan Annex B -
DELETED Annex C -
Major Injury Involving Radioactive Contamination For The Medical Center, Beaver Annex D -
Procedure for Transferring Radiation Casualties to the Radiation Emergency Response Program (UPMC Presbyterian)
Annex E -
Reserved Revision 8 Revision 9 Revision 8 REVISION 56
A5.735B Beaver Valley Power Station Unit 1/2 EPP/I-2 Unusual Event Document Owner Manager, Emergency Preparedness CONTROLLED BVPS UNIT 3 Revision Number 19 Level Of Use General Skill Reference Safety Related Procedure Yes
Beaver Valley Power Station ProcedureNum ille:
Unit:
Level Of Use:
1/2 -
General Skill Reference Unusual Event Revision:
Page Number.
1 9 i f i EFFECTIVE INDEX Issue 8 Rev.
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Issue 9 Rev.
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4 Rev.
5 Rev.
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OSC Approved OSC Approved OSC Approved OSC Approved Non-Safety Revisions Non-Safety Revisions Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision OSC Approved Non-Intent Revision 6
7 8
9.-
10 Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision 11 12 13 14 15 Non-Intent Revision Non-Intent Revision OSC Approved OSC Approved Non-Intent Revision 16 17 18 19 Non-Intent Revision Non-Intent Revision Simple Change Simple Change 3-12-87 8-13-87 6-20-88 9-22-88 2-23-89 1-12-90 10-9-90 10-1 1-91 5-15-92 12-29-92 1-27-93 1-1-94 10-14-94 5-26-95 10-31-95 12-8-95 10-23-96 1-29-97 6-17-97 10-15-97 4-1-98 4-12-00 8-8-01 12-12-01 8-15-02 4-30-03
PmeueNumber:
Beaver Valley Power Station edureN e
Title:
Unit:
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1/2 General Skill Reference Unusual Event Revision:
Page Number:
TABLE OF CONTENTS A.
Purpose B.
References C.
Responsibilities D.
Action Levels/Precautions E.
Procedure F.
Final Condition G.
Attachments H.
Records and Forms
Procedure Number.
Beaver Valley Power Station EPP/1-2 Tite:
Unit:
Level Of Use:
1/2 General Skill Reference Unusual Event*
Revision:
Page Number:
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9 1 of 14 A.
PURPOSE This procedure describes the actions to be taken once an Unusual Event has been declared at the Beaver Valley Power Station. Actions to be completed by the Control Room are outlined in Section E.1.O while TSC actions are outlined in Section E.2.0.
B.
REFERENCES 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.
2.0 Beaver Valley Power Station Operating Manuals.
3.0 Beaver Valley Power Station Health Physics Manual.
4.0 Title 10, Code of Federal Regulations Part 50, Appendix E.
5.0 NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".
6.0 Condition Report #971737.
Condition Report #993020.
Condition Report #00-2202 Condition Report #00-4309 Condition Report #01-0693 Condition Report #014468 Condition Report #02-04015 Condition Report #02-04155 Condition Report #02-05012 Condition Report #02-03442 Condition Report #02-06895 Condition Report #02-09224-15 C.
RESPONSIBILITY The Emergency Director (Shift Manager (SM) of the affected Unit, until properly relieved by a designated alternate) has the responsibility and authority for implementation of the actions prescribed in this instruction. If the Shift Manager (SM) of the affected Unit is unavailable, the Shift Manager (SM) of the unaffected Unit SHALL assume the role of the Emergency Director until relieved. Or, if the occurrence is common to both Units (e.g., Security compromise, acts of nature), the Senior Shift Manager (SM) (per 1/2-OM-48.1.A.IH.J) SHALL assume the role of Emergency Director.
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Pocdume Number Beaver Valley Power Station EPP/I-2
Title:
Unit:
Level Of Use:
1/2 General Skill Reference Unusual Event Revision:
Page Numbe il 1 9 2 of 14 l
ACTION LEVELS/PRECAUTIONS 1.0 Action Levels 1.1 An Unusual Event has been declared based on the-occurrence of off-normai events which could indicate a potential degradation of the level of safety of the plant per EPP/I-1.
2.0 Precautions 2.1 Continued surveillance and assessment of plant conditions are necessary tc ensure that the emergency classification is appropriately revised as conditions change, or as more definitive information is obtained.
2.2 Corrective actions to contend with the situation and to mitigate possiblc deterioration in plant conditions SHALL be conducted in accordance with the BVPS Operating Manual while simultaneously implementing this Instruction.
2.3 Following the declaration of,an Unusual Event, Federal regulations require notification of offsite authorities MUST be made within fifteen minutes. (Refe to EPPIP 1.1) 2.4 Contaminated/injured personnel no longer constitute an emergency declaration However, BVPS is required to notify the NRC per OCFR50.72.
2.5 Faxing of the Initial Notification Forrn is NOT the "Official" Notification to the Offsite Agencies and does NOT meet the 15-minute notification criteria. The 15-minute notification criteria is met and "Official" notification made when representative of BVPS speaks with a representative of each Offsite Agency.
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Procedure Numiber Beaver Valley Power Station EPP-2
Title:
Unit:
Level Of Use:
1/2 General Skill Reference Unusual Event Revision:
Page Number 1 9 3§ of 1 4 E.
PROCEDURE 1.0 Control Room SM/ED actions:
1.1 Implement corrective actions.
1.2 Obtain Notification Package from the sealed EPP drawer.
1.3 Complete Form EPP-IP-l.l.F.0l*,-INITIAL NOTIFICATION FORM.
Use Attachment 2 page 1 of 2 as guidance for determining if a radioactive airborne release has occurred.
1.4 Begin notifications of Offsite Agencies per EPP-IP 1.1 - On-shift Communicator.
NOTE:
If actions are required in an emergency that are immediately needed to protect the public health and safety and departs from the license condition or Technical Specification, the action SHALL be approved, as a minimum, by a licensed Senior Reactor Operator prior to taking the action per 10 CFR 50.54(x) and (y).
NOTE:-
Routine/Batch Releases at either Unit need not be discontinued upon declaration of an Unusual Event, UNLESS the release is the cause of the Unusual Event.
CHECK L
NOTE:
Initial Notifications to the Offsite Agencies MUST be completed within 15 minutes of the Emergency Declaration.
NOTE:
Attachments and Forms designated with an
- are included in the Unusual Event Notification Package.
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Beaver Valley Power Station I
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1/2 General Skill Reference Unusual Event Revision:
Page Number-1K 1 9 4of 1 1.5 If the Emergency Response Organization (ERO) has previously been notified, PROCEED TO STEP 1.6.12, or continue:
1.5.1 For Security Events, discuss with Security personnel site accessibility AND if Site Assembly/Accountability should be conducted, (may be postponed if event is a threat to personnel safety).
1.5.2 Determine if the site is accessible for ERO response.
1.6 A SRO (from the unaffected Unit) SHALL complete the blanks below and notify the Emergency Response Organization (ERO).
"This is (Your Name) at Beaver Valley Power Station. At (time) hrs.,
Unit has declared an UNUSUAL EVENT due to:
(Choose One and Continue)
- a. DO NOT report to your emergency facility.
I repeat, DO NOT report to your emergency facility.
- b. Report to your emergency facility.
I repeat, report to your emergency facility.
OR.
- c. Report to your alternate emergency facility. I repeat, report to your alternate emergency facility."
1.6.1 If ERO activation is NOT required, proceed to step 1.6.12 to send a Lotus Notes message only.
1.6.2 From a PAX phone, dial 4370.
(Continued)
CHECK
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Procedure Number Beaver Valley Power-Station io/P-2
Title:
Unit:
Level Of Use:
1/2 General Skill Reference Unusual Event Revision:
Page Number:
9 5 f 4 CHECK 1.6.3 Interrupt the greeting by IMMEDIATELY entering L
XXXXX.
1.6.4 When prompted, enter scenario number XXXXX.
L 1.6.5 When prompted, verify scenario number (9 for YES or L
6 for NO).
1.6.6 When prompted "Do you want to record your on the fly a
message 1", Press 9 for YES or 6 for NO.
1.6.7 When prompted "Enter on the fly number 1 segment ID L
or press star to record".
1.6.7.1 PRESS * (A short delay will occur).
Li 1.6.8 When prompted "Please speak your message after the L
tone", provide the information from Step 1.6 in your on the fly message.
1.6.8.1 PRESS the #Key when done with message.
L 1.6.9 Review message, when prompted "Is that correct" L
(Press 9 for YES or 6 for NO).
1.6.10 When prompted "You will queue scenario XXXXX.
L It will now be sent.- Are you sure this is what you want to do?" (Press 9 for YES or 6 for NO) 1.6.11 Call the Central Alarm Station (CAS)
(PAX L
5114/5115) and provide the following information:
Your name and title.
EPP CODE WORD L
An UNUSUAL EVENT has been declared.
Li ERO pagers have been activated. Call back at Li PAX when pager activates.
Request Near Site Building Emergency L
Notifications be made.
(Continued) 0 -
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-. ~~~~~~Poced.ueN..bem:.:j Beaver Valley Power Station bEPl 2
Title:
Unit:
Level Of Use:
2 General Skill Reference-Unusual Event.
Revision:
Page Number:
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CHECK 1.6.12 From Lotus Notes, send a message to "beeper all call" with the information from E. 1.6 above. Include if ERO is to report or not. (Limit 220 characters) 1.7 Complete Form EPP-I-2.F.01*, UNUSUAL EVENT PAGE ANNOUNCEMENT FORM.
1.8 Announce the Unusual Event Page Party Announcement.
1.9 Complete Form EPP-IP-l.l.F.03*,
FOLLOW-UP NOTIFICATION FORM.
Use Attachment 2 page 2 of 2 for guidance on reporting the magnitude of the airbome release, if applicable.
1.9.1 On-shift Communications and Records Coordinator to perform Follow-Up Notifications.
I1 1.10 Complete NRC FORM 361*, REACTOR PLANT EVENT NOTIFICATION WORKSHEET.
1.10.1 Provide details from NRC Form 361, NRC EVENT NOTIFICATION WORKSHEET to the NRC.
NOTE:
NRC notifications MUST be completed within 1 (one) hour of Emergency Declaration. (Satisfies IOCFR50.72)
NOTE:
(Licensed) Personnel from the opposite Unit should be utilized to complete NRC notifications.
NRC Operations Center-800-532-3469 or 301-816-5100 FAX: 301-816-5151 El
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Procedure Number.
Beaver Valley Power Station EPP/-2
Title:
Unit:
Level Of Use:
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1 9 7of 14 CHECK 1.11 For Airborne release:
1.11.1 Complete EPP-I-2, Attachment 1*, OPERATIONAL L
INPUTS FOR DOSE ASSESSMENTS.
1.11.2 Provide Attachment 2 to Health Physics personnel.
L 1.11.3 Instruct Health Physics to initiate dose projections a
(EPP/IP 2.6).
1.11.4 Initiateoffsite/onsiteradiation'surveys Li (EPP/IP 2.2, 2.3).
1.11.5 Obtain Dose Projection results from Health Physics.
L 1.12 ForLiquidRelease:
1.12.1 Obtain results from Health Physics personnel.L 1.12.2 Determine if Liquid Release protective action is L
required per EPPIP 4.1 1.12.3 Notify downstream water treatment plants and relay Li PAR, if applicable, On-shift Communicator.
1.13 Escalate Emergency Classification, if necessary.
L 1.14 Terminate when termination -criteria met per EPP/IP 6.2, L *, TERMINATION GUIDELINES.
2.0 TSC Emergency Director Actions (If activated):
i 2.1 Coordinate with the Control Room to implement corrective actions.
NOTE:
Attachments and Forms designated with an
- are included in the Communications and Records Coordinator Notification Area.
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___________________________________________EPP/I-2-I
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/2 General Skill Referencel Unusual Event Revision:
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2.2 Instruct the Communications and Records Coordinator to complete Form EPP-IP-1.1.F.03*,
FOLLOW-UP
-,NOTIFICATION FORM. Use Attachment 2 page 2 of 2 for guidance on reporting the magnitude of the airbome release, if applicable.
2.2.1 Review and approve completed Form EPP-IP-1.1.F.03*, FOLLOW-UP NOTIFICATION FORM.
2.3 Instruct the Communications and Records Coordinator to fax the completed Form EPP-IP-1.1.F.03*,
FOLLOW-UP NOTIFICATION FORM to the Offsite Agencies using the instructions located in the EPP Notification Book.
2.4 Instruct the TSC Operations Coordinator to complete NRC.
FORM 361*,
REACTOR PLANT EVENT NOTIFICATION WORKSHEET.
2.4.1 Ensure that the worksheet is provided to the Operations Communicator manning the NRC ENS "RED" phone.
2.4.2 Ensure that the details from NRC FORM 361*,
REACTOR PLANT EVENT NOTIFICATION WORKSHEET are provided to the NRC.
2.5 For Airborne release:
2.5.1 Instruct EA&DP to initiate dose projections (EPP/IP 2.6).
2.5.2 Initiate offsite/onsite radiation surveys (EPP/IP 2.2, 2.3).
2.5.3 Obtain Dose Projection results from EA&DP.
CHECK
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Ill NOTE:
NRC notifications MUST be completed within 1 (one) hour o Emergency Declaration. (Satisfies 10CFR50.72) r I1
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Procedure Number:
Beaver Valley Power Station EP itle-:
Unit:
Level Of Use:
1/2 General Skill Reference Unusual Event Revision:
Page Number.
CHECK 2.6 For Liquid Release:,
2.6.1 Obtain results from EA&DP personnel.
D 2.6.2 Determine if Liquid Release protective action is required per EPPIP 4.1.
2.6.3 Instruct the Communications and Records Coordinator E
to notify downstream water treatment plants and relay the PAR, if applicable, per EPP-IP-1.1.F.02.
2.7 Escalate Emergency Classification, if necessary.
X 2.8 Terminate when termination criteria met per EPP/IP 6.2, Attachment. 1, TERMINATION GUIDELINES.
F.
FINAL CONDITIONS 1.0 On-Call ED/alternate has been contacted.
2.0 Initial and Follow-Up Notifications completed.
3.0 The Unusual Event has been terminated with normal station administration resumed or the emergency reclassified.
4.0 Event termination calls are completed per IP 1.1 G.
ATTACHMENTS 1.0, Operational Inputs For Dose Assessments 2.0, Deternination of Airborne Radioactive Releases During Emergencies H.
FORMS ASSOCIATED WITH THIS PROCEDURES 1.0 Records 1.1 Completed copies of Attachments listed below shall be routed to Manager, Emergency Preparedness prior to retention by Beaver Valley Records Center.
1.1.1 Operational Inputs For Dose Assessment 2.0 Forms 2.1 EPP-I-2.F.01 - Unusual Event Announcement
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Beaver Valley Power Station PocedureNumbeEpp, 1 :2
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-. : -1/2 General Skill Referencem Unusual Event Revision:
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OPERATIONAL INPUTS FOR DOSE ASSESSMENTS To perform a dose projection, Health Physics personnel will require the following information:
- 1)
Type of accident: (Circle One) If unknown, use (2) LOCA W/GAP Activity.
(1)
LOCA W/RCS Activity - Loss of coolant accident and no greater than Tech Spec RCS Activity.
(2)
LOCA W/GAP Activity - Loss of coolant accident and core exit thernocouples have exceeded values (e.g., core cooling, RED PATH) that may indicate damage to fuel cladding with ESF's available.
(3)
Design Basis LOCA - Double ended shear of RCS piping, rapid RCS depressurization, minimum engineered safety features function.
(4)
LOCA W/Failed ESF's (TID14844) - Double ended shear of RCS piping, rapid RCS depressurization, no engineered safety features function and loss of containment.
(5)
Small Line Break LOCA - Loss of coolant accident via piping systems outside containment (i.e., letdown) and no greater than Tech Spec RCS activity.
(6)
RCCA Ejection - Reactor control cluster ejection causes loss of coolant accident which results in 10% gap relcase.
(7)
Steam Generator Tube Rupture - SG Tube rupture with offsite power not available and affected SG used for cooldown (condenser not available).
(8)
Fuel Handling Accident - The drop of a single fuel bundle affecting another in the Fuel Handling Building.
(9)
Loss of AC Power - Loss of offsite power, natural circulation cooldown.
(10)
Gas Waste System Failure - Alarms or unplanned pressure loss from waste gas treatment/storage system.
(11)
Main Steam Line Break - Technical Specification RCS activity, with accident induced primary-to-secondary leak.
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~~~~Procedure Numbenr Beaver Valley Power Station o
Xum-EPP/I-2 Tttle:
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R P1/2 General Skill Reference.1 Unusual Event -
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i OPERATIONAL INPUTS FOR DOSE ASSESSMENT (2 of, S
- 2)
Time of plant trip or start of accident:
- 3)
Delay time between accident and start of release:
- 4)
Expected, known, or default duration of release:
(If unknown, use one (1) hour as default value.)
- 5)
Known or expected release pathway: (Circle One)
Rel. Point Unit 1
- Ventilation Vent SLCRS Process Vent Main Steam Ventilation Vent Condensate Pol.
SLCRS Decon Building Waste Gas Building Main Steam
- (Hours)
(Hours)
Unit 2 RP I RP2 RP3 RP4 Z) I F
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Procedure Number Beaver Valley Power Station EPP/1-2
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12 General Skill Reference Unusual Event Revision:
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DETERMINATION OF AIRBORNE RADIOACTIVE RELEASES DURING EMERGENCIES Has ANY of the following occurred AND is directly related to the initiating event?
O Yes 1 No O Yes O -No O Yes O No Cl Yes O No O Yes O No O Yes OINo Positive pressure in containment.
ANY reactor trip or rapid shutdown.
ANY secondary system steam release (e.g., via aux. feedwater turbine exhaust, SGADV, MSSV).
ANY other event related indication of gas/vapor release from a system containing.
radioactive material.
ANY radioactivity (other than naturally occurring, ie: Radon) detected by air sampling in site ventilation, buildings or areas, or offsite areas.
ANY VALID increase in ventilation effluent or process radiation monitors (excluding the containment airborne monitors).
YES Check on the Initial, Notification Form:
"An airborne non-routine radiological release is in progress."
VALID:
Refer to Definitions in EPP/I-la or b.
REPORT:
CONDITIONS INDICATE NO non-routine radiological release is occurring,
- AND, Check on the Initial Notification Form:
"NO non-routine radiological release in progress."
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I Beaver Valley Power'Station -:o-edureNmbcr P/I 2 JJ
Title:
Unit:
Level Of Use:
l, 1/2 General Skill Reference Unusual Event Revision:
Page Number 1 9 toft I
! (2 of 2)
DETERMINATION OF AIRBORNE RADIOACTIVE RELEASES DURING EMERGENCIES Are ANY of the following conditions met?
REPORT:
CONDITIONS INDICATE:
- A non-routine rminor release below Federally approved operating limits has occurred.
Release is being monitored.
REPORT:
CONDITIONS INDICATE:
Non-routine radiological release -
exceeding routine operational limits is occurring.
AND Perform accident dose projection and report results in accordance with EPP/IP 2.6. ]1 REPORT:
'Thyroid 0.17 mirllirem maximum for each full hour of release 2TEDE 0.06 millirem maximum for each full hour of release Actual total values will be calculated and provided after plant conditions have stabilized, and samples have been taken and analyzed.'
PAG values can not be reached at these levels.
'Based on 1500 nrem/y site boundary, instantaneous particulate & iodine release rate limit - ODCM l/2-ODC-3.03 Control 3.11.2.1b.
2Based on 500 mremly site boundary, instantaneous noble gas release rate limit - ODCM 112-ODC-3.03 Control 3.11.2.la.
I:
1 Yes Ol No Airbome radioactivity field measurements (outdoors on or off-site) >background Ol Yes O No Unmonitored pathway open between a radioactive system and the environment El Yes El No Release with effluent monitor in high-high alarm (Unit 1 except SPING) OR high alarn (Unit 2, and Unit 1 SPING)
Ol Yes l No Multiple pathway effluent monitor alarms of any level (alert, high or high-high)
El Yes No Secondary system steam release associated with accident condition (e.g., steam generator tube rupture, locked RCP rotor, rod control cluster ejection or main steam line break)
NO YES Ii
.Il I'
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A5.735B Beaver Valley Power Station Unit 1/2 EPP-I-3 ALERT Document Owner Manager, Emergency Preparedness CONTROLLED BVPS UNIT 3 Revision Number 18 Level Of Usc General Skill Reference Safety Related Procedure Yes
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.0 Beaver Valley Power Station EPP 3 Unit:
Level Of Use:
I /2 General Skill Reference LERT Revision:
Page Number:
I i f i EF FECTIVE INDEX Issue 8 Rev.
0 I
2 3
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Issue 9 Rev.
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4 Rev.
5 Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
OSC Approved OSC Approved OSC Approved OSC Approved Non-Safety Revisions Non-Safety Revisions Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision OSC Approved Non-Intent Revision 6
7 8
9 10 Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision 11 12 13 14 15 16 17 18 Non-Intent Revision Non-Intent Revision OSC Approved OSC Approved Non-Intent Revision Non-Intent Revision Simple Change Simple Change 3-12-87 8-13-87 6-20-88 9-22-88 2-23-89 1-12-90 10-9-90 10-1 1-91 5-15-92 12-29-92 1-27-93 1-1-94 10-14-94 5-26-95 10-31-95 12-8-95 10-23-96 1-29-97 6-17-97 10-15-97 4-1-98 4-12-00 8-8-01 8-15-02 4-30-03
IIBeaver Valley Power Station PPedurePNumbe 3
Title:
Unit:
Level Of Use:
.1/2 General Skill Reference ALERT Revision:
Page Number:
1 8 H of ix TABLE OF CONTENTS A.
Purpose B.
References C.
Responsibilities D.
Action Levels/Precautions E.
Procedure F.
Final Condition G.
Attachments H.
Records and Forms
Beaver Valley Power Station EPP--3
Title:
Unit:
Level Of Use:
_ 1/2 General Skill Reference ALERT Revision:
Page Number.
18 isl of 6 A.
PURPOSE This procedure describes the actions to be taken in the event that an Alert Emergency, has been declared at the Beaver Valley Power Station. Actions to be completed by the Control
.Room are outlined in Section E.1.0 while TSC actions are outlined in Section E.2.0.
B.
REFERENCES 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.
2.0 Beaver Valley Power Station Operating Manuals.
3.0 Beaver Valley Power Station Health Physics Manual.
4.0 Title 10, Code of Federal Regulations Part 50, Appendix E.
5.0 NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".
6.0 Condition Report #971737.
Condition Report #993020.
Condition Report #00-2202 Condition Report #004309 Condition Report #01-0693 Condition Report #01-4468 Condition Report #02-04015 Condition Report #02-04155 Condition Report #02-05012 Condition Report #02-03442 Condition Report #02-09224-15 C.
RESPONSIBILITY The Emergency Director (Shift Manager (SM) of the affected Unit, until properly relieved by a designated alternate) has the responsibility and authority for implementation of the actions prescribed in this instruction. If the Shift Manager (SM) of the affected Unit is unavailable, the Shift Manager (SM) of the unaffected Unit SHALL assume the role of the Emergency Director until relieved. Or, if the occurrence is common to both Units (e.g., Security compromise, acts of nature), the Senior Shift Manager (SM) (per 1/2-OM-48.1.A.M.J) SHALL assume the role of Emergency Director.
Beaver Valley Power Station PoeueNmc~
1 Ttle:.
Unit-Level Of Use:
1 i
- .1/2 General Skill Reference 1, ALERT Revision:
Page Number l'
18
? oSl2 oft16-D.
ACTION LEVELS/PRECAUTIONS 1.0 Action Levels 1.1 An Alert Emergency condition has been declared based on the occurrence of events which could indicate an actual or potential degradation of the level of safety of the plant per EPP/1-1.
1 1.2 An Unusual Event has been declared and based on subsequent inforrnation o'r upon a deterioration in plant conditions, the conditions has been reclassified as an Alert.
1:
2.0 Precautions 2.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is appropriately revised as conditions change, or as more definitive information is obtained.
1 2.2 Corrective actions to contend with the situation and to mitigate possible deterioration in plant conditions SHALL be conducted in accordance with the BVPS Operating Manual while simultaneously implementing this Instruction.
2.3 Following the declaration of an Alert, Federal regulations required notification
)
of offsite authorities MUST be made within fifteen minutes. (Refer to EPP/IP
~~~
~
~
~~~~~~~~~~~1.1)
.1,l 2.4 Faxing of the Initial Notification Form is NOT the "Official" Notification to the Offsite Agencies and does NOT meet the 15-minute notification criteria. The 15-minute notification criteria is met and "Official" notification made when a' representative of BVPS speaks with a representative of each Offsite Agency.
0 4 ~~~~~
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31.1i
Procedure Number-Beaver Valley Power Station P
e-1-3
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ALERT Revision:
Page Number:.
18 3 of 16 1.0 Control Room SM/ED actions:
1.1 Implement corrective actions.
NOTE:
Initial Notifications to the Offsite Agencies MUST be completed within 15 minutes of the Emergency Declaration.
1.2 Remove Notification Package from the sealed EPP drawer.
NOTE:
Attachments and Forms designated with an
- are included in Alert Notification Package.
1.3 Complete Form EPPLP 1.1.F.0l*, INTIAL NOTIFICATION FORM.
Use Attachment 2 page 1 of 2 as guidance for determining if a radioactive airborne release has occurred.
1.4 Onshift Communications and Records-Coordinator to begin notifications of Offsite Agencies.
1.5 If the Emergency Response Organization (ERO) has previously been notified, PROCEED TO STEP 1.6.11, or continue:
1.5.1 For Security Events, discuss' with Security personnel site accessibility AND if Site Assembly/Accountability should be conducted, (may be postponed if event is a threat to personnel safety).
1.5.2 Determine if the site is accessible for ERO response.
E.
PROCEDURE NOTE:
If actions are required in an emergency that are immediately needed to'protect the public health and safety and departs from the license condition or Technical Specification, the action SHALL be approved, as a minimum, by a licensed Senior Reactor Operator prior to taking the action per 10 CFR 50.54(x) and (y).
CHECK E
the D
11 D
El F]
Procedure Number Beaver Valley Power Station EPP-L3 itkc:
- -Unit:
ILevOfUse:
112 General Skill Reference1 ALERT 0
Revision:
Page Number:
4 18oflS 16 f
NOTE:
Activating the Emergency Response Organization beepers will begin activation of the following:
Technical Support Center (TSC), Operations Support Center (OSC), Emergency Operations Facility and the Joint Public Information Center (JPIC)..
1.6 A SRO (from the unaffected -Unit)' SHALL complete the blanks below and notify the Emergency Response Organization (ERO).
1.6.1 From a PAX phone, dial 4370.
1.6.2 Interrupt the greeting by IMMEDIATELY entering xxxx.
1.6.3 When prompted, enter scenario number XXXX.
1.6.4-When prompted, verify scenario number (9 for YES or 6 for NO).
(Continue)
CHECK El El
- En El i
i ii i
41 i
Ii i
Ii i
l
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l F.
r iI Ii' II EjI Ii' IiiI1 1 i
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"This is (Your Name) at Beaver Valley Power Station. At (time)
- hrs, Unit has declared an ALERT due to:
(Choose One and Continue)
- a. Report to your emergency facility.
I repeat, report to your emergency facility.
- b. Report to your alternate emergency facility. I repeat, report., to your alternate emergency facility."
11
Ij 11,
iIi j;
I, !
Procedure Number Beaver Valley Power Station EPP-I-3
Title:
Unit Level Of Use:
.- 12 General Skill Reference ALERT Revision:
Page Number.
19 8 of 16 CHECK 1.6.5 When prompted "Do you want to record your on the fly D]
message 1", Press 9 for YES or 6 for NO.
1.6.6 When prompted "Enter on the fly number 1 segment ID D
or press star to record".
1.6.6.1 PRESS * (A short delay will occur).
D 1.6.7 When prompted "Please speak your message after the D
tone", provide the information from Step 1.6 in your on the fly message.
1.6.7.1, PRESS the # key when done with message.
1.6.8 Review message, when prompted "Is that correct" D
(Press 9 for YES or 6 for NO).
1.6.9 When prompted "You will queue scenario XXXX. It L
will now be sent. Are you sure this is what you want to do?" (Press 9 for YES or 6 for NO) 1.6.10 Call the Central Alarm Station (CAS)
(PAX LI 5114/5115) and provide the following information:
Your name and title.
C]
EPP CODE WORD LI An ALERT has been declared.
L ERO pagers have been activated. Call back at L
PAX when pager activates.
Request Near Site Building
-Emergency L
Notifications be made.
1.6.11 From Lotus Notes, send a message to "beeper all call" LI with the information from E. 1.6 above. Include if ERO is to report or not.
1.7 Complete Form EPP-I-3.F.01*, ALERT PAGE LI ANNOUNCEMENT FORM.
K)
I Beaver Valley Power Station
Title:
ALERT V
I,
~~~~~~~~~~CHECK l
1.8 Announce the ALERT Page Party Announcement CHK 1.9 Begin completing EPP/IP 3.2, Attachment 2*, EPP SITE I:
- ACCOUNTABILITY FORM and provide to CAS as soon as possible, but in all cases, upon declaration of a Site Accountability.
1.10 Discontinue ANY Routine/Batch Releases at EITHER Unit.
Fl 1.11 Complete Form EPP-IP-1.1.F.03*, FOLLOW-UP E.
NOTIFCATION FORM. Use Attachment 2 page 2 of 2 for guidance on reporting the magnitude of the airborne release, if applicable.
1.11.1 Instruct the Onshift Communications and Records l
Coordinator to conduct Follow-Up Notifications per 1
EPP-IP-.1.
NOTE:
1 NRC notifications MUST be made within one (1) hour of i
Emergency Declaration. (Satisfies 10CFR50.72) l CHECK 1.12 Complete NRC Form 361*, REACTOR PLANT EVENT
[l NOTIFICATION WORKSHEET.
NOTE:
I:
(Licensed) Personnel from the opposite Unit should be utilized to complete NRC notifications.
i NRC Operations Center 800-532-3469 1
or,I 301-816-5100 Fax: 301-816-5151
.~~~~~~I 1I,
- ; ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~,
l 1
Procedure Number:
Beaver Valley Power Station EPP-I-3
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ALERT 0
Revision:
Page Number:
ALERT~
~
~
~
~~~~87 fl CHECK 1.12.1 Provide details from NRC Form 361*, REACTOR D
PLANT EVENT NOTIFICATION WORKSHEET to the NRC.
1.13 If necessary:
1.13.1 Instruct Health Physics to survey Assembly Areas, per EPP/IP 3.1.
1.13.2 Implement Site Evacuation, per EPP/IP 3.2.
D 1.13.3 Notify Beaver, Columbiana and Hancock County officials if a Site Evacuation is ordered -
Onshift Communicator.
1.14 Forairbomerelease:
1.14.1 Complete EPP-I-3, Attachment. 1*, OPERATIONAL INPUTS FOR DOSE ASSESSMENTS.
1.14.2 Provide completed Attachment to Health Physics Personnel.
1.14.3 Instruct Health Physics to initiate dose projections.
1.14:4 Initiate offsite/onsite radiation surveys D
(EPP/IP 2.2, 2.3).
1.14.5 Obtain dose projection results from Health Physics.
1.15 For Liquid Release:
1.15.1 Obtain results from Health Physics personnel.
El 1.15.2 Determine if Liquid Release protective action is required, per EPP/IP 4.1.
1.15.3 Notify downstream water treatment plants and relay PAR, if applicable - Onshift Communicator.
1.16 Escalate Emergency Classification, if necessary.
1.17 Terminate when termination criteria met per EPPIIP-6.2, I]
Attachment I *, TERMINATION GUIDELINES.
-x i I
T s z 1 n
ProcedureNumber:
f 4~~~~~~~~~
eaver Vall ey ower tationi- -
-- -I P--3--
~~~~~~~~~~~~~~~~~~~~~~~
E PP
- 1.
..I.
ritle:
ALERT I.
2.0 TSC Emergency Director Actions (Upon activation):
. 2.1 Coordinate with the Control Room to implement corrective actions.
Unit:
I Level Of Use:i 112 General Skill Referencee I Revision:
Page Number -
19
- -I of 16 CT 2.2 Complete Form EPP 1P-1.1.F.01*, INlTIAL NOTIFICATION FORM if not already completed. Use Attachment 2 page 1 of 2 as guidance for determining if a radioactive airborne release has occurred.
[ECK ID[
I I
[_F1 t;I 2.2.1 Provide completed form to Communications & Records Coordinator.
2.3 Instruct the Communications and Records Coordinator to begin notifications of Offsite Agencies per EPP-IP-1.1.
2.4 Instruct the TSC Operations Coordinator to:
2.4.1 Complete Form EPP-I-3.F.01, ALERT PAGE ANNOUNCEMENT FORM.
2.4.2 Coordinate with Control Room to sound Station Standby Alarm, per Form EPP-I-3.F.0 1, ALERT PAGE ANNOUNCEMENT FORM.
2.4.3 Using Page Party System "super page", make Alert Page Announcement immediately after Standby Alarm is sounded.
2.5 Verify ANY Routine/Batch Releases at EITHER Unit stopped.
1 1
NOTE:
Initial Notifications to the Offsite Agencies MUST be completed within 15 minutes of the Emergency Declaration.
NOTE:
Attachments and Forms designated with an
- are included in the Communications and Records Coordinator Notification Package.
I:i J:
1' I 1 r
iI I 1 V
Ir-
=
Beaver Valley Power -Station PProceurePNunbe 3
tite:
Unit:
Level Of Use:
.1/2 General Skill Reference ALERT Revision:
Page Number:
19 9 of 1S CHECK
[21 2.6 Instruct the Communications and Records Coordinator to complete Form EPP-IP-1.1.F.03*,
FOLLOW-UP NOTIFICATION FORM. Use Attachment 2 page 2 of 2 for guidance on reporting the magnitude of the airborne release, if applicable.
2.6.1 Review and approve completed Follow-Up Notification Form.
2.6.2 Instruct the Communications and Records Coordinator to conduct Follow-Up Notifications per EPP-IP-1.1=
2.7 Instruct the TSC Operations Coordinator to complete NRC Form 361*,
REACTOR PLANT EVENT NOTIFICATION WORKSHEET 2.7.1 Ensure that the worksheet is provided to the Operations Communicator manning the NRC ENS "RED" phone.
2.7.2 Ensure that the details from NRC Form 361*,
REACTOR PLANT EVENT NOTIFICATION WORKSHEET are provided to the NRC.
2.8 Verify ERDS (EPP/IP 1.4) is activated, if not already done.
2.9 If necessary:
2.9.1 Instruct Health Physics to survey Assembly Areas, per EPP/IP 3.1.
NOTE:
NRC notifications MUST be made within one (1) hour of Emergency Declaration. (Satisfies 10CFR50.72)
D~
L-I FI NOTE:
ERDS activation MUST be accomplished within one (1) hour of emergency declaration.
CHECK C]
Di'-
i II Il Beaver Valley Power Station 0
EPPI3 1
J itle:
Unit:
Level Of Use:
l 1/2 General Skill Reference v ALERT Revision:
Page Number.
18 =
10 of 16 lk-l CHECK 2.9.2 Implement Site Evacuation, per EPP/IP 3.2.'
2.9.3 Instruct the Onshift Communications and Records El Coordinator to notify Beaver, Columbiana and Hancock County officials if a Site Evacuation is ordered.
2.10 For airborne release:
2.10.1 Instruct EA&DP to initiate dose projections E
(EPP/IP 2.6).
2.10.2 Initiate offsite/onsite radiation surveys E
(EPPfIP 2.2, 2.3).
2.10.3 Obtain Dose Projection results from EA&DP.
C]
2.11 For Liquid Release:
2.11.1 Obtain results from EA&DP personnel.
-l 2.11.2 Determine if Liquid Release protective action
[I is required, per EPP/IP 4.1.
2.11.3 Instruct the Communications and Records Coordinator El to notify downstream water treatment plants and relay the PAR, if applicable, per EPP-IP-1.1.F.02.;
2.12 Escalate Emergency Classification, if necessary.
E-2.13 Terminate when termination criteria met per EPP/IP 6.2, E *, TERMINATION GUIDELINES.
i
Procedure Number:
Beaver Valley Power Station EPP-I-3
Title:
Unit:
Level Of Use:
.:.1/2 General Skill Reference ALERT Revision:
Page Number.
_1 1 o f 1 6 F.
FINAL CONDITIONS 1.0 On-Call ED/alternate and On-Call E/RM/alternate have been contacted.
2.0 Initial and Follow-Up offsite notifications are complete.
3.0 The Alert has been terminated with normal station administration resumed, a recovery organization established or the emergency classification has escalated.
4.0 Event termination calls are completed per EPP/IP 1.1.
G.
ATTACHMENTS 1.0, Operational Inputs For Dose Assessments 2.0, Determination of Airborne Radioactive Releases During Emergencies.
H.
RECORDS AND FORMS 1.0 Records 1.1 Completed copies of Attachments listed below shall be routed to Manager, Emergency Preparedness prior to retention by Beaver Valley Records Center.
1.1.1 Attachmentl,OperationalInputsForDoseAssessments 2.0 Forms 2.1 EPP-I-3.F.01 - Alert Page Announcement K-
BeaverIValley Power Station Procedure Numbcr i J i Beaver ValleyPower Station EP-1-3 4
Unit:
Level Of Use:
1/2 1 General Skill Reference.
Revision:
Page Number I18 1
12 f 16 IK I'
INTENTIONALLY BLANK
Title:
ALERT I
.1 z1 2
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Procedure Number:
Beaver Valley Power Station Ut:
EPP-I-3
Title:
,Unit:
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.itle:
1/2 General Skill Reference ALERT Revision:
Page Number:
At 13 of 16
~~~~~~~~~~~~~~~~~Attachmen 1 (1 of 2)
OPERATIONAL INPUTS FOR DOSE ASSESSMENTS To perform a dose projection, Health Physics personnel will require the following information:
I)
Type of accident: (Circle One) If unknown, use (2) LOCA W/GAP Activity.
(1)
LOCA WIRCS Activit - Loss of coolant accident and no greater than Tech Spec RCS Activity.
(2)
LOCA W/GAP Activity - Loss of coolant accident and core exit thermocouples have exceeded values that may indicate damage to fuel cladding with ESF's available.
(3)
Design Basis LOCA - Double ended shear of RCS piping, rapid RCS depressurization, minimum engineered safety features function.
(4)
LOCA W/Failed ESF's (TID14844) - Double ended shear of RCS piping, rapid RCS depressurization, no engineered safety features function and loss of containment.
(5)
Small Line Break LOCA - Loss of coolant accident via piping systems outside containment (i.e., letdown) and no greater than Tech Spec RCS activity.
(6)
RCCA Eiection - Reactor control cluster ejection causes loss of coolant accident which results in 10% gap release.
(7)
Steam Generator Tube Rupture - SG Tube rupture with offsite power not available (8)
(9)
(10)
(condenser not available).
Fuel Handling Accident - The drop of a fuel bundle in the Fuel Handling Building.
Loss of AC Power - Loss of offsite power, natural circulation cooldown.
Gas Waste System Failure - Alarms or unplanned pressure loss from waste gas treatmenustorage system.
(1 1)
Main Steam Line Break - Technical Specification RCS activity, with accident induced primary-to-secondary leak.
I I
I I V I Beaver Valley Power Station
____________________________________________EPP-I-3
Title:
Unit:
Level Of Use:
1/2 General Skill Reference ALERT Revision:
Page Number:
18
~14 of 6 i
OPERATIONAL INPUTS FOR DOSE ASSESSMENT (2 of 2)
I S.
- 2)
Time of plant trip or start of accident:
- 3)
Delay time between accident and start of release: ___-_-
- 4)
Expected, known, or default duration of release:
(If duration unknown, use one (1) hour as default value.)
- 5)
Known or expected release pathway: (Circle One)
Rel. Point Unit 1 Ventilation Vent SLCRS.:
Process Vent Main Steam Ventilation Vent Condensate Pol.
SLCRS Decon Building Waste Gas Building Main Steam (Hours)
(Hours)
Unit 2 RP I RP2 RP3 RP4 I.
[.I. I
I, I.
I1:
1 p
I'I I
[ P2 I
1
Procedure Number Beaver Valley Power Station EPP-1-3 Titke:
Unit:
Level Of Use:
12 General Skill Reference ALERT
~
Revision:
Page Number:
18
~~1-5 f 1t (1 of 2)
DETERMINATION OF AIRBORNE RADIOACTIVE RELEASES DURING EMERGENCIES Has ANY of the following occurred AND is directly related to the initiating event?
11 Yes 0 No Positive pressure in containment.
1 Yes O No D1 Yes O No O Yes [I No O Yes O No D Yes O No ANY reactor trip or rapid shutdown.
ANY secondary system steam release (e.g., via aux. feedwater turbine exhaust, SGADV, MSSV).
ANY other event related indication of gas/vapor release from a system containing radioactive material.
ANY radioactivity (other than naturally occurring, ie: Radon) detected by air sampling in site ventilation, buildings or areas, or offsite areas.
ANY VALID increase in ventilation effluent or process radiation monitors (excluding the containment airborne monitors).
YES Check on the Initial Notification Form:
"An airborne non-routine radiological release is in progress."-
Refer to Definitions in EPP/I-la or b.
k9-REPORT:
CONDITIONS INDICATE NO non-routine radiological release is
- occuning, AND, Check on the Initial Notification Form:
"NO non-routine radiological release in progress."
NO I
VALID:
Beaver Valley Power Station N
3 I
Unit:
Level Of Use:
I I 1/2 General Skill Reference Revision:
Page Number:
F' 1 8 1l6nf 16 -
P Attachment, DETERMINATION OF AIRBORNE RADIOACTIVE RELEASES DURING EMERGENCIES Are ANY of the following conditions met?
1 Yes No D Yes O No D Yes No C Yes No n Yes No Airborne radioactivity field measurements (outdoors on or off-site) >background Unmonitored pathway open between a radioactive system and the environment Release with effluent monitor in high-high alarm (Unit I except SPING) OR high alarm (Unit 2, and Unit 1 SPING)
Multiple pathway effluent monitor alarms of any level (alert, high or high-high)
Secondary system steam release associated with accident condition (e.g., steam generator tube rupture, locked RCP rotor, rod control cluster ejection or main steam line break) 4, NO 2 (2 of 2) 1I.
-I 4
REPORT:
CONDITIONS INDICATE:
A non-routine rinor release below Federally
- approved operating limits has occurred.
Release is being
. I monitored.
YES lr AND l
Perform accident dose projection and report results in accordance with EPP/IP 2.6.
l I
REPORT:
'Thyroid 0.17 millirem maximum for each full hour of release 2TEDE 0.06 millirem maximum for each full hour of release Actual total values will be calculated and provided after plant conditions have stabilized, and samples have been taken and analyzed.
PAG values can not be reached at these level e 1K I
= ![1J
- I.
'Based on 1500 mremt/y site boundary, instantaneous particulate & iodine release rate limit - ODCM 1/2-ODC-3.03 Control 3.1 1.2.1b.
2Based on 500 mremly site boundary, instantaneous noble gas release rate limit - ODCM 1/2-ODC-3.03 Control 3.11.2.1a.
Title:
ALERT REPORT:
CONDITIONS INDICATE:
Non-routine radiological release exceedinz routine operational limits is occurring.
1.
I I;V
i l
I iII I
I51
I
-A5.735B Beaver Valley Power Station Unit 1/2 EPP-I-4 SITE AREA EMERGENCY Document Owner Manager, Emergency Preparedness CONTROLLED BVPS UNIT 3 Revision Number 18 Level Of Use General Skill Reference Safety Related Procedure Yes
Procedure Number:
Beaver Valley Power Station E
.EPP-1-4
Title:
Unit:
Level Of Use:
1/2 General Skill Reference SITE AREA EMERGENCY Revision:
Pge Nume I 9~~~~~~~~~~~~~~~~~~~~~~~1 i of i EFFECTIVE INDEX Issue 8 Rev.
0 OSC Approved I
OSC Approved 2
OSC Approved 3
OSC Approved 4
Non-Safety Revisions 5
Non-Safety Revisions Issue 9 Rev.
0 Non-Intent Revision 1
Non-Intent Revision 2
Non-Intent Revision 3
Non-Intent Revision 4
OSC Approved Rev.
5 Non-Intent Revision Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
6 7
8 9
10 I11 12 13 14 15 16 17 18 Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision OSC Approved OSC Approved Non-Intent Revision Non-Intent Revision Simple Change Simple Change 3-12-87 8-13-87 6-20-88 9-22-88 2-23-89 1-12-90 10-9-90 10-11-91 5-15-92 12-29-92 1-27-93 1-1-94 10-14-94 5-26-95 10-31-95 12-8-95 10-23-96 1-29-97 6-17-97 10-15-97 4-1-98 4-12-00 8-8-01 8-15-02 4-30-03
- s4 B
r,tle i
SITE AREA E1\\
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5 eaver Valley Power Station edureNum Unit:
Level Of Use:
1/2 General Skill Reference vIERGENCY Revision:
Page Number:
I lIg ii of ii TABLE OF CONTENTS A.
Purpose B.
References C.
Responsibilities D.
Action Levels/Precautions E.
Procedure F.
Final Condition G.
Attachments H.
Records and Forms
~-
I
Procedure Number Beaver Valley Power Station EPPPe14
Title:
Unit:
Level Of Use:
1/2 General Skill Reference SITE AREA EMERGENCY Revision:
Page Number:
18 1~ o.f 16i A.
PURPOSE This instruction describes the actions to be taken in the event that a Site Area Emergency has been declared at the Beaver Valley Power Station. Actions to be completed by the Control Room are outlined in Section E.1.0 while TSC actions are outlined in Section E.2.0.
B.
REFERENCES 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.
2.0 Beaver Valley Power Station Operating Manuals.
3.0 Beaver Valley Power Station Health Physics Manual.
4.0 Title 10, Code of Federal Regulations Part 50, Appendix E.
5.0 NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".
6.0 Condition Report #971737 Condition Report #993020 Condition Report #00-2202 Condition Report #00-4309 Condition Report #01-0693 Condition Report #01-4468 Condition Report #02-04015 Condition Report #02-04155 Condition Report #02-05012 Condition Report #02-03442 Condition Report #02-09224-15 C.
RESPONSIBILITY The Emergency Director (Shift Manager (SM) of the affected Unit, until properly relieved by a designated alternate) has the responsibility and authority for implementation of the actions prescribed in this instruction. If the Shift Manager (SM) of the affected Unit is unavailable, the Shift Manager (SM) Shift Manager (SM) of the unaffected Unit SHALL assume the role of the Emergency Director until relieved.
Or, if the occurrence is common to both Units (e.g.,
Security compromise, acts of nature), the Senior Shift Manager (SM) (per 1/2-OM-48.1.A.M.J)
SHALL assume the role of Emergency Director.
Beaver Valley Power Station uNum I
L
.EPP-I i
Title:
Unit:
Level Of Use:
1/2 General Skill Re nce S1TE AREA EMERGENCY Revision:
Page Number.
k 18
- 2of 6--t D.
ACTION LEVELSIPRECAUTIONS 1.0 Action Levels 1.1 A Site Area Emergency has been declared based on the occurrence of events which involve actual or likely failures of plant functions needed for th'e protection of the public.
Events classified as Site Area Emergencies are described in EPP/I-1.
I 1.2 An Unusual Event or an Alert emergency condition had been declared and emergency measures are being performed; and on the basis of subsequent information or upon deterioration in plant conditions, the condition has been reclassified as a Site Area Emergency.
2.0 Precautions 2.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is appropriately revised as conditions change, or as more definitive information is obtained.
2.2 Corrective actions to contend with the situation and to mitigate possible, deterioration in plant conditions SHALL be conducted in accordance with the BVPS Operating Manual while simultaneously implementing this Instruction.,
j 2.3 Following the declaration of an Site Area Emergency, Federal regulations required notification of offsite authorities MUST be made within fifteen:
minutes. (Refer to EPP/IP 1.1) 1 2.4 Faxing of the Initial Notification Form is NOT the "Official" Notification to the" Offsite Agencies and does NOT meet the 15-minute notification criteria. The 15-minute notification criteria is met and "Official" notification made when a, representative of BVPS speaks with a representative of each Offsite Agency.
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Procedure Number.
Beaver Valley Power Station
- PPurNu
Title:
Unit:
Level Of Use:
1/2 C
General Skill Reference SIHE AREA EMERGENCY Revision:
Page Number:
r~~~~~~~~~
4 of 16t E.
PROCEDURE 1.0 Control Room SM/ED actions: (IF TSC NOT ACTIVATED) 1.1 Implement corrective actions.
ital Notifcatinst NOTE:
Initial Notifications to the Offsite Agencies MUST be completed within 15 minutes of the Emergency Declaration.
1.2 Remove Notification Package from the sealed EPP drawer.
1.3 Complete Form EPP-IP-1.I.F.01
- INITIAL NOTIFCATION FORM.
Use Attachment 2 page 1 of 2 as guidance for determining if a radioactive airborne release has occurred.
1.4 Onshift Communications and Records Coordinator to begin notifications of Offsite Agencies.
1.5 If the Emergency Response Organization (ERO) has previously been notified, PROCEED TO STEP 1.6.11, or continue..
1.5.1 For Security Events, discuss with Security personnel site accessibility AND if Site Assembly/Accountability should be conducted, (may be postponed if event is a threat to personnel safety)..
CHECK LI D
D C]
-1.5.2 Determine if the site is accessible for ERO response.
NOTE:
If actions are required in an emergency that are immediately needed to protect the public health and safety and departs from the license condition or Technical Specification, the action SHALL be approved, as a minimum, by a licensed Senior Reactor Operator prior to taking the action per 10 CFR 50.54(x) and (y).
NOTE:
Attachments and Fonns designated with an
- are included in the Site Area Notification Package.
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Beaver Valley Power Stion ProcedureNumber:
._________v_a__
.iey_row er___________
EPP-I-4 V
Title:
Unit:
Level Of Use:
, 1 ;
112 General Skill Reference,. l SITE AREA EMERGENCY Revision:
Page Number:
IK I_of16 NOTE:
Activating the Emergency Response Organization beepers will begin activation of the following.,
Technical Support Center (TSC), Operations Support Center (OSC), Emergency Operations Facility, and the Joint Public Information Center (JPIC).
I 1.6 A SRO (from the unaffected; Unit) SHALL complete the blanks below and notify the Emergency Response Organization (ERO).
CHECK E
"This is at Beaver Valley Power Station. At.
hrs., -
Unit due to:
(Your Name)
(time) has declared a SITE AREA EMERGENCY (Choose One and Continue)
- a. Report to your emergency facility.
report to your emergency facility.
OR I repeat,
- b. Report to your alternate emergency facility.
I repeat, report to-your alternate emergency facility."
1.6.1 From a PAX phone, dial 4370.
, 1.6.2 Interrupt the greeting by IMMEDIATELY entering xxxx.
1.6.3 When prompted, enter scenario number XXXX.
1.6.4. When prompted, verify scenario number (9 for YES or 6 for NO).
(Continue)
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Procedure Number:
Beaver Valley Power Station EPP-I4
Title:
Unit:
Level Of Use:
1/2 General Skill Reference SUE AREA EMERGENCY Revision:
Page Number 1 8
~5 of 1 6 CHECK
[]
1.6.5 When prompted "Do you want to record your on the fly message 1", Press 9 for YES or 6 for NO.
1.6.6 When prompted "Enter on the fly number 1 segment ID or press star to record".
1.6.6.1 PRESS * (A short delay will occur).
1.6.7 When prompted "Please speak your message after the tone", provide the information from Step 1.6 in your on the fly message.
1.6.7.1 PRESS the # key when done with message..
1.6.8 Review message, when prompted "Is that correct" (Press 9 for YES or 6 for NO).
1.6.9 When prompted "You will queue scenario XXXX. It will now be sent. Are you sure this is what you want to do?" (Press 9 for YES or 6 for NO) 1.6.10 Call the Central Alarm Station (CAS)
(PAX 5114/5115) and provide the following information:
Your name and title.
EPP CODE WORD A SITE AREA EMERGENCY has been declared.
ERO pagers have been activated. Call back at PAX when pager activates.
D El FEl E1 El El El Request
-Near Site Building Notifications be made.
Emergency 1.6.11 From Lotus-Notes, send a message to "beeper all call"
-vwith the information from E.1.6 above. Include if ERO
-is to report or not.
1.7 Notify Security to implement-Site Accountability, if not already done.
Assembly and C]
El
i BeaverValleyPowerStation`
Po-edureNumbe I
Title:
-Unit Level Of Use:
Title:
1/2 General Skill Reference.
S1TE AREA EMERGENCY Revision:
Page Number:
-- ~~~~
of nf6 r
1.8 Complete Form EPP-I-4.F.01
- SITE AREA EMERGENCY PAGE ANNOUNCEMENT.
1.9 Announce the Site Area Emergency Page Party Announcement.
i 1.10 Complete Attachment 2,
EPP/IP 3.2*,
EPP SITE ACCOUNTABILITY FORM and provide to CAS, if not already done.
1.11 Discontinue ANY Routine/Batch Releases at EITHER Unit.
1.12 Complete Forrn EPP-IP-1..F.03*.FOLLOW-UP NOTIFICATION FORM. Use Attachment 2 page 2 of 2 for guidance on reporting the magnitude of the airborne release, if applicable.
1.12.1 Instruct the Onshift Communications and Records Coordinator to conduct Follow-Up Notifications per EPP-IP 1.1.
1.13 Complete NRC Form 361*, REACTOR PLANT. EVENT NOTIFICATION WORKSHEET.
NOTE:
For a Site Area Emergency or General Emergency, the EPP SITE ACCOUNTABILITY FORM MUST be delivered to CAS within 20 minutes of the Emergency Declaration.
CHECK I
D I :
'HECK
- E D
IiF D-NOTE:
NRC notifications MUST be made within one (1) hour of emergency declaration. (Satisfies 10CFR50.72)
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Beaver Valley Power Station, Pd Number:~~~~~~~~~~~~~~~~~~~EPP
Title:
Unit:
Level Of Use:
1/2 General Skill Reference SUTE AREA EMERGENCY Revision:
Page Number:
~
~~~
18 7 f 16S 1.13.1 Provide the details from NRC Form 361 REACTOR PLANT EVENT NOTIFICATION WORKSHEET to the NRC.
CHECK E
1.14 If Necessary:
1.14.1 Instruct Health Physics to survey Assembly Areas, per EPP/IP 3.1.
1.14.2 Implement Site Evacuation, per EPP/1P 3.2.
1.14.3 Notify Beaver, Columbiana and Hancock County officials if a Site Evacuation is ordered. -
Onshift Communicator 1.15 For Airbome release:
1.15.1 Complete EPP-I4, Attachment. 1*, OPERATIONAL INPUTS FOR DOSE ASSESSMENTS.
1.15.2 Provide completed attachment to-Health Physics personnel.
1.15.3 Instruct Health Physics to initiate dose projections (EPP/IP 2.6).
1.15.4 Initiate offsite/onsite radiation surveys (EPP/IP 2.2, 2.3).
El El El1 El El 1.15.5 Obtain Dose Projection results from Health Physics.
NOTE:
(Licensed) Personnel from the opposite Unit should be utilized to complete NRC notifications.
NRC Operations Center 800-532-3469 or 301-816-5100 Fax: 301-816-5151 o
I [I."
Beaver Valley Power Station edureNumber.
Title:
Unit:
Level Of Use:
1/2 General Skill Reference.
SITE AREA EMERGENCY Revision:
Page Number:
1 %
L 8 Of 1 l
CHECK 1.16 For Liquid Release:
1.16.1 Obtain results from Health Physics personnel.
1.16.2 DeterTnine if Liquid Release protective action is required, per EPP/IP 4.1.
1.16.3 Notify downstream water treatment plants and relay the PAR, if applicable. - Onshift Communicator 1.17 Escalate Emergency Classification, if necessary.
1.18 Terminate when termination criteria met per EPP/IP-6.2, Attachment. 1*, TERMINATION GUIDELINES.
2.0 TSC Emergency Director Actions (Upon activation):
2.1 Coordinate with the Control Room to implement corrective actions.
2.2 Complete Form EPP-IP-1.1.F.01*, INITIAL NOTIFICATION FORM. Use Attachment 2 page 1 of 2 as guidance for determining if a radioactive airborne release has occurred.
2.2.1 Provide completed form to Communications and Records Coordinator.
2.3 Instruct the Communications and Records Coordinator to begin notifications of Offsite Agencies per EPP-IP-1.1.
E'lC
. 1 i
i sj 1.
b NOTE:
Initial Notifications to the Offsite Agencies MUST be completed within 15 minutes of the Emergency Declaration.
NOTE:
Attachments and Forms designated with an
- are included in the Communications and Records Coordinator Notification Package.
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Procedure Number:
-Beaver Valley Power Station a
EPP--4
Title:
Unit:
Level Of Use:
1/2 General Skill Reference SITE AREA EMERGENCY Revision:
Page Number.
\\
-18 9 cB~~~~~~~~~~~~~
i CHECK 2.4 Instruct the TSC Operations Coordinator to:
E 2.4.1 Complete Form EPP-I4.F.01*,
SITE AREA EMERGENCY ANNOUNCEMENT FORM.
2.4.2 Coordinate with Control Room to sound the Station Standby Alarm, per Form EPP-I-4.F.O*, SITE AREA
-EMERGENCY ANNOUNCEMENT FORM.
2.4.3 Using Page Party System "super page", make Site Area Emergency Page Announcement immediately after Standby Alarm is sounded.
2.4.4 Instruct the Control Room to complete and deliver EPP l
SITE ACCOUNTABILITY FORM, if not already done.
2.5 Instruct Security to implement Site Assembly and Accountability, if not already done.
2.6 Notify the TSC Coordinators and ERM of emergency Li escalation and accountability, if not already done.
2.7 Provide update to ERF personnel via building page.
E 2.8 Discontinue ANY Routine/Batch Releases at EITHER Unit.
El 2.9 Instruct the Communications and Records Coordinator to El complete Form EPP-IP-1.1.F.03*,
FOLLOW-UP NOTIFCATION FORM. Use Attachment 2 page 2 of 2 for guidance on reporting the magnitude of the airbome release, if applicable.
2.9.1 Review and approve completed Follow-Up Notification E
Form.
Beaver Valley Power Station PceueN bEPP-1-4
Title:
Unit:
Level Of Use:
5 1/2 General Skill Reference,i SITE AXEA EMERGENC XRevision: Page Number.
S_F ARAIMRECY8lf1 2.9.2 Instruct the Communications and Records Coordinator to conduct Follow-Up Notifications per EPP-IP-1.1 2.10 Instruct the TSC Operations Coordinator to complete NRC Form 361, REACTOR PLANT EVENT NOTIFICATION WORKSHEET.
2.10.1 Ensure that worksheet is provided 'to Operations Communicator manning NRC ENS "RED" phone.
2.10.2 Ensure that the details: from NRC Forn
- 361, REACTOR PLANT EVENT NOTIFICATION ORKSHEET are provided to the NRC.
2.11 Verify ERDS (EPP/IP 1.4) is activated, if not already done.
2.12 If Necessary:
2.12.1 Instruct Health Physics to survey Assembly Areas, per EPP/IP 3.1.
2.12.2 Implement Site Evacuation, per EPP/JP 3.2.
2.12.3 Instruct the Onshift Communications and Records Coordinator to notify Beaver, Columbiana and Hancock County officials if a Site Evacuation is ordered.
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-C El ElF-CHECK
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I NOTE:
NRC notifications MUST be made within one (1) hour of Emergency Declaration. (Satisfies 10CFR50.72)
NOTE:
ERDS activation MUST be=accomplished within one (1) hour of emergency declaration.
[1I i I:
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Procedure Number Beaver Valley Power Station EPP-I-4 ritle:
Unit:
Level Of Use:
- - 1/2 General Skill Reference SITE AREA EMERGENCY R
CHECK 2.13 For airborne release:
2.13.1 Instruct EA&DP to initiate dose projections (EPP/IP 2.6).
2.13.2 Initiate offsite/onsite radiation surveys (EPP/IP 2.2, 2.3).
[]
2.13.3 Obtain Dose Projection results from EA&DP.
LI 2.14 ForLiquid Release:
2.14.1 Obtain results from EA&DP personnel.
LI 2.14.2 Determine if Liquid Release protective action is C
required, per EPPIP 4.1.
2.14.3 Instruct the Communications and Records Coordinator LI to notify downstream water treatment plants and relay the PAR, if applicable, per EPP-IP-1.1.F.02.
2.15 Escalate Emergency Classification, if necessary.
LI 2.16 Terminate when termination criteria met per EPPIP 6.2,
[] *, TERMINATION GUIDELINES.
F.
FINAL CONDITIONS 1.0 On-Call ED/alternate and E/RM/alternate contacted.
2.0 Offsite notification initiated and updated.
3.0 The Site Area Emergency has been terminated with normal station administration resumed, a recovery organization established or the emergency reclassified.
4.0 Event termination calls are completed per EPP/IP 1.1.
K>
Beav-er Valley-Power Station
- EPP-.IureNumb-epp 4 e
7]
Title:
Unit:
Level Of Use:
. :1/2 General Skill Reference SITE AREA EMERGENCY Revision:
Page Number
[
1~~I8 12 of 16':
w G.
ATTACHMENTS 1.0, Operational Inputs For Dose Assessments 2.0, Determination of Airborne Radioactive Releases During Emergencies H.
RECORDS AND FORMS 1.0 Record 1.1 2.0 Forms 2.1 s
Completed copies of Attachments listed below shall be routed to Manage Emergency Preparedness prior to retention by Beaver Valley Records Center.
1.1.1, Operational Inputs For Dose Assessments EPP-I4.F.01 Site Area Emergency Page Announcement r
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- 1. 1
Beaver Valley Power Station edre Number:
Title:
Unit:
Level Of Use:
1/2 General Skill Reference SITE AREA EMERGENCY Revision:
Page Number.
.18 lX~1 of 16S (1 of 2)
OPERATIONAL INPUTS FOR DOSE ASSESSMENTS To perform a dose projection, Health Physics personnel will require the following information:
- 1)
Type of accident: (Circle One) If unknown, use (2) LOCA W/GAP Activity.
(1)
LOCA W/RCS Activity - Loss of coolant accident and no greater than Tech Spec RCS Activity.
(2)
LOCA W/GAP Activity - Loss of coolant accident and core exit thermocouples have exceeded values that may indicate damage to fuel cladding with ESF's available.
(3)
Design Basis LOCA - Double ended shear of RCS piping, rapid RCS depressurization, minimum engineered safety features function.
(4)
LOCA V/Failed ESF's (TID14844) - Double ended shear of RCS piping, rapid RCS depressurization, no engineered safety features function and loss of containment.
(5)
Small Line Break LOCA - Loss of coolant accident via piping systems outside containment (i.e., letdown) and no greater than Tech Spec RCS activity.
(6)
RCCA Ejection - Reactor control cluster ejection causes loss of coolant accident which results in 10% gap release.
(7)
Steam Generator Tube Rupture - SG Tube rupture with offsite power not available (condenser not available).
(8)
Fuel Handling Accident - The drop of a fuel bundle in the Fuel Handling Building.
(9)
Loss of AC Power - Loss of offsite power, natural circulation cooldown.
(10)
Gas Waste System Failure - Alarms or unplanned pressure loss from waste gas treatment/storage system.
(11)
Main Steam Line Break - Technical Specification RCS activity, with accident induced primary-to-secondary leak.
Beaver Valley Power Station P
e
_______E PP-I-4I itle:
=.:
Unit:
Level Of Use:
E-
{
- te:
Uni:1/2 General Skill Reference SITE AREA EMERGENCY Revision:
Page Number I8 14 off ik6 (2 OPERATIONAL INPUTS FOR DOSE ASSESSMENTS
- 2)
Time of plant trip or start of accident:
- 3)
Delay time between accident and start of release:
- 4)
Expected, known, or default duration of release:
(If duration unknown, use one (1) hour as default value.)
- 5)
Known or expected release pathway: (Circle One)
Rel. Point Unit 1 Ventilation Vent SLCRS Process Vent Main Steam Ventilation Vent -
Condensate Pol.
SLCRS Decon Building Waste Gas Building Main Steam 4.
of 2)
~I F
1' Iii 1*
i.
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!1 (Hours)
(Hnrs)
i i 1
'i' 1i 1V -ik 1
I
Procedure Number Beaver Valley Power StationEP-4
Title:
Unit:
Level Of Use:
_1/2 General Skill Reference SITE AREA EMERGENCY Revision:
Page Number 189 15 of 16 ( of 2)
DETERMINATION OF AIRBORNE RADIOACTIVE RELEASES DURING EMERGENCIES Has ANY of the following occurrend AND is directly relted to the initiating event?
n Yes No E3 Yes O No DYes D Yes 0 Yes n Yes Positive pressure in containment.
ANY reactor trip or rapid shutdown.
O No ANY secondary system steam release (e.g., via aux. feedwater turbine exhaust, SGADV, MSSV).
ni No ANY other event related indication of gas/vapor release from a system containing radioactive material.
O No ANY radioactivity (other than naturally occurring, ie: Radon) detected by air sampling in site ventilation, buildings or areas, or offsite areas.
o No ANY VALID increase in ventilation effluent or process radiation monitors (excluding the containment airborne monitors).
YES Check on the Initial Notification Form:
"An airborne non-routine radiological release is in progress."
VALID:
Refer to Definitions in EPP/I-la orb.
REPORT:
CONDITIONS INDICATE NO non-routine radiological release is occurring,
- AND, Check on the Initial Notification Form:
"NO non-routine radiological release in progress."
NO I
i Beaver Valley Power Station-Numbe s~, -
EPP-I-4,-
Unit:
Level Of Use:
I 1/2 I General Skill Reference, Revision:
Page Number:
R I
I 16 of 16 (2 of 2)
DETERMINATION OF AIRBORNE RADIOACTIVE RELEASES DURING EMERGENCIES Are ANY of the following conditions met?
l AND Perforn accident dose projection and report results in accordance with EPP/IP 2.6.
NO REPORT:
CONDITIONS INDICATE:
A non-routine ninor release below Federally approved operating limits has occurred.
Release is being monitored.
I: t l:I
.11 REPORT:
'Thyroid 0.17 millirem maximum for each full hour of release 2TEDE 0.06 millirem maximum for each full hour of release Actual total values will be calculated and provided after plant conditions have stabilized, and samples have been taken and analyzed.l PAG values can not be reached at these levels.
i
'Based on 1500 mrenVy site boundary, instantaneous particulate & iodine release rate limit - ODCM 12-ODC-3.03 Control 3.11.2. lb.
2Based on 500 rnrem/y site boundary, instantaneous noble gas release rate limit - ODCM 12-ODC-3.03 Control 3.11.2.1a
Title:
SITE AREA EMERGENCY o Yes 0 No Airborne radioactivity field measurements (outdoors on or off-site) >background O Yes 0 No Unmonitored pathway open between a radioactive system and the environment O Yes 0 No Release with effluent monitor in high-high, alarm (Unit 1 except SPING) OR high alarm (Unit 2, and Unit 1 SPING)
O Yes 0 No Multiple pathway effluent monitor alarms of any level (alert, high or high-high) o Yes 0 No Secondary system steam release associated with accident condition (e.g., steam generator tube rupture, locked RCP rotor, rod control cluster ejection or main steam line break) 1.
YES REPORT:
CONDITIONS INDICATE:
Non-routine radiological release exceeding routine operational limits is occurring.
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A5.735B Beaver Valley Power Station Unit 1/2 EPP-I-5 GENERAL EMERGENCY Document Owner Manager, Emergency Preparedness CONTROLLED BVPS UNIT 3 Revision Numbcr 19 Level Of Use General Skill Reference Safety Related Procedure Yes
Title.
GED; 1,
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l -
4s Procedure Number Beaver Valley Power Station EPP-I-5 Unit:
Level Of Use:
1/2 General Skill Reference NERAL EMERGENCY Revision:
Page Number:
EFFECTIVE INDEX Issue 8 Rev.
Issue 9 Rev.
0 1
2 3
4 Rev.
5 Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
Rev.
0 OSC Approved 1
OSC Approved 2
OSC Approved 3
OSC Approved 4
Non-Safety Revisions 5
Non-Safety Revisions OSC Approved Non-Intent Revision Non-Intent Revision Non-Intent Revision OSC Approved Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision Non-Intent Revision OSC Approved OSC Approved Non-Intent Revision Non-Intent Revision Non-Intent Revision Simple Change Simple Change 6
7 8
9 10 11 12 13 14 15 16 17 18 19 3-12-87 8-13-87 6-20-88 9-22-88 2-23-89 1-12-90 9-27-90 10-11-91 5-15-92 12-29-92 1-27-93 1-1-94 10-14-94 5-26-95 10-31-95 12-8-95 10-23-96 1-29-97 6-17-97 10-15-97 4-1-98 12-30-98 4-12-00 8-8-01 8-15-02 4-30-03
w s
~~~~~~~~~~~~~Procedure Number:
Beaver Valley Power Station EPP-I-5
Title:
Unit:
Level Of Use:
1/2 General Skill Reference GENERAL EMERGENCY 0
Revision:
Page Number:
1 9 ii of ii TABLE OF CONTENTS A.
Purpose B.
References C.
Responsibilities D.
Action Levels/Precautions E.
Procedure F.
Final Condition G.
Attachments H.
Records and Forms
)
x r o
ce
~~~~~~~~~Procedure Numher:
Beaver Valley Power Station P
NumbE~~~~~~~~~~~~~~~~~~EPP-
Title:
Unit:
Level Of Use:
1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number:
I.
L - I L I I
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I 1 of 1 P A.
PURPOSE This instruction describes the actions to be taken in the event that a General Emergency has been declared at the Beaver Valley Power Station. Actions to be completed by the Control Room are outlined in Section E.1.0 while TSC actions are outlined in Section E.2.0.
B.
REFERENCES 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.
2.0
-Beaver Valley Power Station Operating Manuals.
3.0 Beaver Valley Power Station Health Physics Manual.
4.0 Title 10, Code of Federal Regulations Part 50, Appendix E.
5.0 NUREG-0654/FEMA-REP-l, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".
6.0 Condition Report #971737.
Condition Report #993020.
Condition Report #00-2202 Condition Report #00-4309 Condition Report #01-0693 Condition Report #02-04015 Condition Report #02-04155 Condition Report #02-05012 Condition Report #02-03442 Condition Report #02-09224-15 C.
RESPONSIBILITY The Emergency Director (Shift Manager (SM) of the affected Unit, until properly relieved by a designated alternate) has the responsibility and authority for implementation of the actions prescribed in this instruction. If the Shift Manager (SM) of the affected Unit is unavailable, the Shift Manager (SM) of the unaffected Unit SHALL assume the role of the Emergency Director until relieved. Or, if the occurrence is common to both Units (e.g., Security compromise, acts of nature), the Senior Shift Manager (SM) (per 1/2-OM-48.1.A.f.J) SHALL assume the role of Emergency Director.
.1 n Procedurc Number F
Beaver Valley Power Station EPP-I-5 j
Talie:
Unit:
Level Of Use:
1/2 General Skill Reference -
Revision
-Page Number 1
GENERAL EMERGENCY[
1 2f1 19'~~~~~~~~~~~~~
2 of I
D.
ACTION LEVELS/PRECAUTIONS 1.0 Action Levels.,
1.1 A General Emergency has been declared based on the occurrence of eventis which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity, including. Severe Accident Management Guidelines (SAMG). Events classified as General Emergencies are described in EPP/I-1.
1.2 A less severe emergency has been declared and emergency measures are being performed; and on the basis of subsequent information or upon deterioration in plant conditions, the condition has been reclassified as a General Emergency.
2.0 Precautions 2.1 Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is appropriately revised as conditions change, or as more definitive information is obtained.
2.2 The General Emergency classification includes actual or imminent events for which offsite protective actions will be needed.
Notifications! to offsite authorities MUST be made within 15 minutes after the declaration of the General Emergency.
2.3 Corrective actions to contend with the situation and to mitigate possible deterioration in plant conditions in accordance with the BVPS Operating Manual SHALL be conducted simultaneously with this instruction.
2.4 Faxing of the Initial Notification Form is NOT the "Official" Notification to theE I
Offsite Agencies and does NOT meet the 15-minute notification criteria. Thel.
15-minute notification criteria is met and "Official" notification made when a3 representative of BVPS speaks with a representative of each Offsite Agency.
Y3
Procedure Number:
.:Beaver Valley Power Station EPP-I-5
Title:
Unit:
Level Of Use:
1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number:
1 9 3of 8 E.
PROCEDURE 1.0 Control Room SM/ED actions: (IF TSC NOT ACTIVATED)
C:
ion oted 1.1 Implement corrective actions, including Severe Accident Management Guidelines (SAMG's),; as directed by the EOP's NOTE:
Initial Notifications, including a
Protective Acti Recommendation, to the Offsite Agencies MUST be comple within 15 minutes of the Emergency Declaration.
1.2 Obtain Notification Package from the sealed EPP drawer.
1.3 Complete the following:
1.3.1 Form EPP-IP-I.1.F.01*,
INITIAL NOTIFICATION FORM including a
PROTECTIVE ACTION RECOMMENDATION (Reference EPP/IP 4.1, )
Use Attachment 2 page 1 of 2 as guidance for determining if a radioactive airborne release has occurred.
NOTE:
If actions are required in an emergency that are immediately needed to protect the public health and safety and departs from the license condition or Technical Specification, the action SHALL be approved, as 'a minimum, by a licensed Senior Reactor Operator prior to taking the action per 10 CFR 50.54(x) and (y).
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LI NOTE:
Attachments and Forms designated with an
- are included in the General Emergency Notification Package.
Beaver Valley Power Station Procedurc Numbe 5
[I
Title:
GENERAL EMERGENCY Unit:
1/2 Revision:.
Page Number - -
19 4of lR CHECK 1.4 Onshift Communications and Records Coordinator to begin Ei notifications of Offsite Agencies.
1.4.1 Provide Initial Notification Protective Recommendation (PAR).
I
- I Action El 1.5 If the Emergency Response Organization (ERO) has previously been notified, PROCEED TO STEP 1.6.11, or continue.
l.5.1 For Security Events, discuss with Security personnel site accessibility AND if Site Assembly/Accountability should be conducted, (may be postponed if event is a threat to personnel safety).
1.5.2 Deternine if the site is accessible for ERO response.
Level Of Use:
I General Skill Reference NOTE:
For a fast breaking emergency, the SM/ED SHALL deliver the Protective Action Recommendation (PAR) at this time via the Initial Notification Conference (INC).
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~~~~~~~~~~~~~~Procedure Number.
Beaver Valley Power Station P
Numbe.
_E P P -I-5
Title:
Unit:
Level Of Use:
1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number:
19 5 of 18 NOTE:
Activating the Emergency Response Organization beepers will begin activation of the following:
Technical Support Center (TSC), Operations Support Center (OSC), Emergency Operations Facility and the Joint Public Information Center (JPIC).
1.6 A SRO (from the unaffected Unit) SHALL complete the blanks below and notify the Emergency Response Organization (ERO).
1.. 1 -From a PAX phone, diai 4370.
1.6.2 Interrupt the greeting by IMMEDIATELY entering xxxx.
1.6.3 When prompted, enter scenario number XXXX.
1.6.4 When prompted, verify scenario number (9 for YES or 6 for NO).
CHECK El El El El El (Continue)
(Your Name) at "This is (time) hrs..
Beaver Valley Power Station. At Unit has declared a GENERAL EMERGENCY due to:
(Choose One and Continue)
- a. Report to your emergency facility.
I repeat, report to your emergency facility.
- b. Report to your alternate emergency facility. I
- repeat, report to your alternate emergency facility."
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Beaver Valley Power Station PredureNun EPP-I-5
Title:
Unit.
Level Of Use:
- .: 1/2 General Skill Reference GENERAL EMERGENCY Revision:-
Page Number:
19 6 of 1 L_
CHECK 1.6.5 When prompted "Do you want to record your on the fly El message 1", Press 9 for YES or 6 for NO.
1.6.6 When prompted "Enter on the fly number 1 segment ID l
or press star to record".
1.6.6.1 PRESS * (A short delay will occur).
F 1 1.6.7 When prompted "Please speak your message after the Ea tone", provide the information from Step 1.6 in your on the fly message.
1.6.7.1 PRESS the # key when done with message..
El 1.6.8 Review message, when prompted "Is that correct" l
(Press 9 for YES or 6 for NO).
1.6.9 When prompted "You will queue scenario XXXX. It C]
will now be sent. Are you sure this is what you want to do?" (Press 9 for YES or 6 for NO) 1.6.10 Call the Central Alarm Station (CAS)
(PAX Liii 5114/5115) and provide the following inf6rmnation:
-* Your name and title:
I EPP CODE WORD O
A GENERAL EMERGENCY has been EO declared.
ERO pagers have been activated. Call back at l
PAX when pager activates.
Request Near Site Building-Emergency El Notifications be made.
1.6.11 From Lotus Notes, send a message to "beeper all call" El with the information from E.1.6 above. Include if ERO is to report or not.
1.7 Complete Form EPP-I-5.F.01*, GENERAL EMERGENCYNYl PAGE ANNOUNCEMENT.
Procedure Number.
Beaver Valley Power Station EPP-I-5
Title:
Unit:
Level Of Use:
1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number:
CHECK 1.8 Announce the General Emergency Page Party Announcement.
El 1.9 Complete EPP/IP 3.2, Attachment 2*,
EPP SITE ACCOUNTABILITY FORM and provide to CAS, if not already done.
1.10 Notify Security to implement Site Assembly and Accountability, if not already done.
1.11 Discontinue ANY Routine/Batch Releases at EITHER Unit.
1.12 Complete Form EPP-IP-1.1.F.03*,
FOLLOW-UP NOTIFICATION FORM. Use Attachment 2 page 2 of 2 for guidance on reporting the magnitude of an airborne release, if applicable.
1.12.1 Instruct the Onshift Communications and Records Coordinator to conduct Follow-Up Notifications per EPP-IP-1.1.
NOTE:
For a Site Area Emergency or General Emergency, EPPIIP 3.2, *, EPP SITE ACCOUNTABILITY FORM MUST be delivered to CAS within 20 minutes of the Emergency Declaration.
[1 l -
- I NOTE:
NRC notifications MUST be made within one (1) hour of emergency declaration. (Satisfies 10CFR50.72)
Procedure Number Beaver Valley Power Station
Title:
Unit:
Level Of Use 1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number:
19 8 of 18 Cf 1.13 Complete NRC Form 361*, REACTOR PLANT EVENT
- NOTIFICATION WORKSHEET.
- 1.13.1 Provide details. from NRC Form 361, REACTOR PLANT EVENT NOTIFICATION WORKSHEET to the NRC.
IECK El ElI 1.14 If Necessary:
1.14.1 Instruct Health Physics to survey Assembly Areas, per EPP/IP 3.1.
1.14.2 Implement Site Evacuation, per EPPIP 3.2.
1.14.3 Notify Beaver, Columbiana and Hancock County officials if a Site Evacuation is ordered. -
Onshift Communicator 1.15 For Airbome release:
1.15.1 Complete EPP-I-5, Attachment 1*, OPERATIONAL INPUTS FOR DOSE ASSESSMENTS.
1.15.2 Provide completed attachment to Health Physics personnel.
NOTE:
(Licensed) Personnel from the opposite Unit should be utilized to complete NRC notifications.
NRC Operations Center 800-532-3469 or 301-816-5100 Fax: 301-816-5151
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Procedure Number.
Beaver Valley Power Station EPP-I-5
Title:
Unit:
Level Of Use:
1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number 19 -
-9 of 8 CHECK 1.15.3 Instruct Health Physics to initiate dose projections L
(EPP/IP 2.6).
1.15.4 Initiate offsite/onsite radiation surveys (EPP/IP 2.2, 2.3).
0 1.15.5 Obtain Dose Projection results from Health Physics.
L 1.15.6 Update PAR, if necessary.
Li 1.16 For Liquid Release:
1.16.1 Obtain results from Health Physics personnel.
LI 1.16.2 Determine if Liquid Release protective action is LI required, per EPPIP 4.1.
1.16.3 Notify downstream water treatment plants and relay the 1
PAR, if applicable. - Onshift Communicator 1.17 Terminate when termination criteria met per EPPIP-6.2, LI *, TERMINATION GUIDELINES.
2.0 TSC Emergency Director and EOF Emergency/Recovery Manager L
Actions (Upon activation):
2.1 Coordinate with the Control Room to implement corrective LI actions.
This may include oversight of Severe Accident Management Guidelines (SAMG's) activities.
NOTE:
Initial Notifications, including a
Protective Action Recommendation, to the Offsite Agencies MUST be completed within 15 minutes of the Emergency Declaration.
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Beaver Valley Power Station Pr-edureNumepp I 5
Title:
Unit:
Level Of Use:
1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number:
19 1()of 18 I
-4 a:
C*
CHECK 2.2-Complete the following:
2.2.1 EPP-IP-l.I.F.01*, INITIAL NOTIFICATION FORM including a
PROTECTIVE ACTION RECOMMENDATION, (Reference EPP/IP 4.1, ).
Use Attachment 2 page 1 of 2 as guidance for determining if a radioactive airborne release has occurred.
2.2.2 Provide completed form to the Communications and Records Coordinator.
2.3 Instruct the Communications and Records Coordinator to begin notifications of Offsite Agencies per EP-JIP-1.1.
2.4 Per discussion with the ERM, instruct the Assistant to the E1RM to initiate the Gold Executive Conference (GEC), per EPP/IP 4.1, if not already done.
2.4.1 E/RM SHALL provide the PAR to Offsite Agencies via the GEC.
2.5 Notify Security to implement Site Assembly and Accountability, if not already done.
2.6 Notify the TSC and EOF of emergency escalation and PAR via the building page.
2.6.1 Relay escalation information over headset circuits.
2.7 Instruct the TSC Operations Coordinator to:
2.7.1 Complete Form EPP-I-5.F.0l*, GENERAL EMERGENCY PAGE ANNOUNCEMENT FORM.
NOTE:
Attachments and Forms designated with an
- are included in the Communications and Records Coordinator Notification Package.
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Beaver Valley Power Station edureNum
_E P P -- 5
Title:
Unit:
Level Of Use:
1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number.
1 9 1 1 of 8 CHECK 2.7.2 Coordinate with the Control Room to sound the Station Standby Alarm, per Form EPP-I-5.F.01*,- GENERAL EMERGENCY PAGE ANNOUNCEMENT FORM.
2.7.3 Using Page Party System "super page", make General Emergency Page Announcement immediately after Standby Alarm is sounded.
2.7.4 Instruct the Control Room to complete and deliver EPP SITE ACCOUNTABILITY FORM, if not already done.
2.8 Discontinue ANY Routine/Batch Releases at ElITHER Unit.
2.9 Instruct the Communications and Records Coordinator to complete Form EPP-IP-1.1.F.03*,
-FOLLOW-UP NOTIFICATION FORM. Use Attachment 2 page 2 of 2 for guidance on reporting the magnitude of an airborne release, if applicable.
2.9.1 Review and approve completed Follow-Up Notification Form.
2.9.2 Instruct the Communications and Records Coordinator to conduct Follow-Up Notifications per EPP-IP-1. 1.
2.10 Instruct the TSC Operations Coordinator to complete NRC Form 361*, REACTOR PLANT EVENT NOTIFICATION WORKSHEET.
2.10.1 Ensure that the worksheet is provided to the Operations Communicator manning the NRC ENS "RED" phone.
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11 D
I -NOTE:
NRC notifications MUST be made within one (1) hour of Emergency Declaration. (Satisfies 10CFR50.72)
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'1
'O-Beaver Valley Power Statio;n
-Pcedure Numbe 1 5 1I ritle:
Unit:
Level Of Use:
5 1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number 19 12 onf 8 t
CI 2.10.2 Ensure that the details from NRC Form 361*,
-. I REACTOR PLANT EVENT -
NOTIFICATION WORKSHEET are provided to the NRC.
2.11 Verify ERDS (EPP/IP 1.4) is activated, if not already done.
2.12 If Necessary:
2.12.1 Instruct Health Physics to survey Assembly Areas, per EPP/IP 3.1.
2.12.2 Implement Site Evacuation, per EPP/IP 3.2.
2.12.3 Instruct, the Onshift Communications and Records Coordinator to notify Beaver, Columbiana and Hancock County officials if a Site Evacuation is ordered.
2.13 For airborne release:
2.13.1 Instruct EA&DP to initiate dose projections (EPP/IP 2.6).
2.13.2 Initiate offsite/onsite radiation surveys (EPPIP 2.2, 2.3).
2.13.3 Obtain Dose Projection results from EA&DP.
2.13.4 Update PAR, if necessary.
NOTE:
ERDS activation MUST be accomplished within one (1) hour of an Alert or higher emergency declaration.
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Beaver Valley Power Station Procedure Numb-I 5
Title:
Unit:
Level Of Use:
. D.,1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number:
19 13 of S CHECK 2.14 For Liquid Release:
2.14.1 Obtain results from EA&DP personnel.
2.14.2 Determine if Liquid Release protective action is required, per EPP/IP 4.1.
2.14.3 Instruct the Communications and Records Coordinator to notify downstream water treatment plants and relay the PAR, if applicable, per EPP-IP-1.1.F.02.
2.15 Terminate when termination criteria met per EPP/IP 6.2, *, TERMINATION GUIDELINES.
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FINAL CONDITIONS 1.0 On-Call ED/alternate and E/RM/alternate contacted.
2.0 Offsite notification initiated and updated.
3.0 The General Emergency has been terminated with normal station administration resumed, a recovery organization established or the emergency reclassified.
4.0 Event termination calls are completed perEPP-IP-1.1.
G.
ATTACHMENTS 1.0 Attachment l, Operational Inputs For Dose Assessments 2.0, Determination of Airborne Radioactive Releases During Emergencies H.
RECORDS AND FORMS 1.0 Records 1.1 Completed copies of Attachments listed below shall be routed to Manager, Emergency Preparedness prior to retention by Beaver Valley Records Center.
1.1.1, Operational Inputs For Dose Assessments 2.0 Forms 2.1 EPP-I-5.F.01 General Emergency Page Announcement
Procedume Number Beaver Valley Power Station EPP-15 ij
Title:
Unit:
Level Of Use:
1, 1/2 General Skill Reference [
GENERAL EMERGENCY Revision:
Page Number
-~~~~
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~~~~~~~~~~~~~~~~
9
-14 ofl I 8 INTENTIONALLY BLANK i'
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1'
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Beaver Valley Power Station Poeue ubr~~~~~~~~~~~~~~~~~~~EPP
Title:
Unit:
I-eve] Of Use:
1/I2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number: (1 of 2)
OPERATIONAL INPUTS FOR DOSE ASSESSMENTS To perform a dose projection, Health Physics personnel will require the following informnation:
I)
Type of accident: (Circle One) If unknown, use (2) LOCA W/GAP Activity.
(1)
LOCA W/RCS Activity - Loss of coolant accident and no greater than Tech Spec RCS Activity.
(2)
LOCA W/GAP Activity - Loss of coolant accident and core exit thermocouples have.
exceeded values that may indicate damage to fuel cladding with ESF's available.
(3)
Design Basis LOCA - Double ended shear of RCS piping, rapid RCS depressurization, minimum engineered safety features function.
(4)
LOCA W/Failed ESF's (TID14844) - Double ended shear of RCS piping, rapid RCS depressurization, no engineered safety features function and loss of containment.
(5)
Small Line Break LOCA - Loss of coolant accident via piping systems outside containment (i.e., letdown) and no greater than Tech Spec RCS activity.
(6)
RCCA Ejection - Reactor control cluster ejection causes loss of coolant accident which results in 10% gap release.
(7)
Steam Generator Tube Rupture - SG Tube rupture with offsite power not available (condenser not available).
(8)
Fuel Handling Accident - The drop of a fuel bundle in the Fuel Handling Building.
(9)
Loss of AC Power - Loss of offsite power, natural circulation cooldown.
(10)
Gas Waste System Failure -Alarmns or unplanned pressure loss from waste gas treatment/storage system.
(I11)
Main Steam Line Break - Technical Specification RCS activity, with accident induced, primary-to-secondary leak.
11
~~~~~~~~~~~~~~Procedure Number:
Beaver Valley Power Station P
NumbE
. J
Title:
-r -
Unit:
Level Of Use:
- f2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number
.~~~~~~~~~~~~~~~~
9 16of-kg. (2 of 2)
OPERATIONAL INPUTS FOR DOSE ASSESSMENTS
- 2)
Time of plant trip or start of accident:
- 3)
Delay time between accident and start of release:
- 4)
Expected, known, or default duration of release:
(If duration unknown, use one (1) hour as default value.)
- 5)
Known or expected release pathway: (Circle One)
Rel. Point Unit Ventilation Vent SLCRS Process Vent Main Steam Ventilation Vent Condensate Pol.
SLCRS Decon Building Waste Gas Building Main Steam (Hours)
(Hours)
I
Procedure Number:
Beaver Valley Power Station.
EPP4-5
Title:
Unit:
Level Of Use:
-1/2 General Skill Reference GENERAL EMERGENCY Revision:
Page Number:
1 9 17 of 18 (I of 2)
DETERMINATION OF AIRBORNE RADIOACTIVE RELEASES DURING EMERGENCIES Has ANY of the following occurred AND is directly related to the initiating event?
O Yes 1 No Positive pressure in containment.
O Yes 0 No ANY reactor trip or rapid shutdown.
O Yes El No ANY secondary system steam release (e.g., via aux. feedwater turbine exhaust, SGADV, MSSV).
O Yes 0 No ANY other event related indication of gas/vapor release from a system containing radioactive material.
o Yes O No ANY radioactivity (other than 0 Yes No naturally occurring, ie: Radon) detected by air sampling in site ventilation, buildings or areas, or offsite areas.
ANY VALID increase in ventilation effluent or process radiation monitors (excluding the containment airborne monitors).
NO YES Check on the Initial Notification Form:
"An airborne non-routine radiological release is in, progress."
VALID:
Refer to Definitions in EPPII-la or b.
REPORT:
CONDITIONS INDICATE NO non-routine radiological release is occurring,
- AND, Check on the Initial Notification Form:
"NO non-routine radiological release in progress."
p j
ProcedurNumbew:1 Beaver Valley Power Station EPP-1-5 1
Title:
Unit:
Level Of Use:
1/2 Gcneral Skill Reference GENERAL EMERGENCY Revision:
Page Number:
GENERAL EMERGENCY~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~a
-9 ofl f
Attachment' DETERMINATION OF AIRBORNE RADIOACTIVE RELEASES DURING EMERGENCIES Are ANY of the following conditions met?
2 (2 of 2) t' I
II,
-1, OYes O No D Yes No D Yes No DYes No D Yes No Airborne radioactivity field measurements (outdoors on or off-site) >background Unmonitored pathway open between a radioactive system and the environment Release with effluent monitor in high-high alarm (Unit 1 except SPING) OR high alarm (Unit 2, and Unit I SPING)
Multiple pathway effluent monitor alarms of any level (alert, high or high-high)
Secondary system steam release associated with accident condition (e.g., steam generator tube rupture, locked RCP rotor, rod control cluster ejection or main steam line break)
NO REPORT:
CONDITIONS INDICATE:
A non-routine minor release below Federally approved operating limits' has occurred.
Release is being monitored.
YES lAND Perform accident dose projection and report results in accordance with EPP/IP 2.6 and EPP/IP 4.1:
RELEASE LESS THAN PAG HAS OCCURRED OR RELEASE REOUIRING PAG HAS Il
~
lOCCURRED I
REPORT:
'Thyroid - 0.17 millirem maximurm for each full hour of release 2TEDE 0.06 nillirem maximum for each full hour of release Actual total values will be calculated and E
provided after plant conditions have stabilized, J and samples have been taken and analyzed.
PAG values can not be reached at these levels. '
'Based on 1500 mrem/y site boundary, instantaneous particulate & iodine release rate limit - ODCM 12-ODC-3.03 Control 3.11.2.1b.
2Based on 500 mrem/y site boundary, instantaneous noble gas release rate limit - ODCM 1/2-ODC-3.03 Control 3.11.2.1 a.
REPORT:
CONDITIONS INDICATE:
Non-routine radiological release exceeding routine operational limits is occuring.
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