Text

Emergency Preparedness Plan Implementing Procedures
	ML032050432
Person / Time
Site:	Beaver Valley
Issue date:	07/22/2003
From:	Pearce L; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-03-111
	Download: ML032050432 (69)
	v • d • e

FENOC Beaver Valley Power Station Route 168

_"MM% PO. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L William Pearce 724-682-5234 Site Vice President Fax: 724-643-8069 July 22, 2003 L-03-111 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 Ms. Susan L. Vicinie, Manager, Emergency Preparedness at 724-682-5767.

Sincerely, L. William Pearce Enclosure 1 - Summary of Changes Enclosure 2 -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)

Beaver Valley Power Station, Unit No. 1 and No. 2 BVPS EP-Plan Implementing Procedures (Vol. 2)

L-03-111 Page 2 bc: (w/o Enclosure 2)

A. J. Bevan H. I. Szklinski F. J. Lipchick S. L. Vicinie M. E. O'Reilly Central File - Keywords: Emergency PreparednessPlan

Reference:

NPD3MEP:0239

Enclosure 1 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/Implementin! Procedures:

EPP/IP-1.7 "Emergency Response Organization (ERO) Teams" Revision 11 standardized the format to be consistent with EP procedures and updated current titles. Steps 8.2.3.2.2, 8.2.3.2.3, 8.4.1.1, 8.4.1.1.1 and 8.4.1.1.3 were clarified. Information regarding the conduct of critiques was added to Attachment A.

EPP/IP-2.7 "Liquid Release Estimate" Revision 8 corrected a typographical error in Attachment J, Step 1.

EPP/IP-3.3 "Emergency Contamination Control" Revision 8 standardized the format to be consistent with EP procedures and made editorial title changes.

EPPIIP-5.4 "Emergency Personnel Monitoring" Revision 9 clarified Step 8.2.1.1 by changing "should" to "shall".

A5.735B EPPIMPLEMENTING PROCEDURES - EFFECTIVE INDEX INSTRUCTIONS EPPII-la Recognition and Classification Revision 4 of Emergency Conditions EPP/I-lb Recognition and Classification Revision 4 of Emergency Conditions EPPII-2 Unusual Event Revision 19 EPP/I-3 Alert Revision 18 EPPI-4 Site Area Emergency Revision 18 EPP/I-5 General Emergency Revision 19 IMPLEMENTING PROCEDURES EPPIIP 1 Series - Activation 1.1 Notification Revision 31 1.2 Communications and Revision 18 Dissemination of Information 1.3 Turnover Status Checklist ED/ERM Revision 9 1.4 Technical Support Center (TSC) Revision 18 Activation, Operation and Deactivation 1.5 Operations Support Center (OSC) Revision 14 Activation, Operation and Deactivation 1.6 Emergency Operations Facility (EOF) Revision 16 Activation, Operation and Deactivation 1.7 Emergency Response Organization (ERO) Revision 11 Teams I CONTROLLED BVPS UNIT 3 REVISION 58

1 W EPPIIMPLEMENTING PROCEDURES - EFFECTIVE INDEX A5.735B 1;

L EPPIIP 2 Series Assessment 2.1 2.2 2.3 Emergency Radiological Monitoring Onsite Monitoring for Airborne Release Offsite Monitoring for Airborne Release Revision 10 Revision 12 Revision 13 I.

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2.4 Offsite Monitoring for Liquid Release Revision 8 I!

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2.5 Emergency Environmental Monitoring Revision 11 2.6 Environmental Assessment and Dose Revision 14 Projection Controlling Procedure 2.6.1 Dose Projection - Backup Methods Revision 11 2.6.2 Dose Projection - ARERASIMIDAS Revision 12 With FSAR Defaults 2.6.3 Dose Projection - ARERAS/MIDAS With Real-Time Inputs Revision 12 (L 2.6.4 Dose Projection - ARERASIMDAS Revision 13 With Manual Inputs p.

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 REVISION 58 I,

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A5.735B EPP/IMPL EETING PROCEDURES EFFECTIVE INDEX EPP/IP 2 Series - Assessment 2.6.11 Dose Projection - Miscellaneous Data Revision 11 2.6.12 Dose Piojection -ARERAS/MIDAS Revision 9 With Severe Accident Assessment 2.7 liquid Release Estimate Revision 8 I 2.7.1 iquid Release Estimate - Revision 9 Computer Method EPPAP 3 Series - Onsite Protective Actions 3.1 Evacuation Revision 8 3.2 Site Assembly and Personnel Accountability Revision 13 3.3 Emergency Contamination Control Revision 8 I 3.4 Emergency Respiratory Protection Revision 8 3.5 Traffic and Access Control Revision 9 EPPIP 4 Series - Offsite Protective Actions 4.1 Offsite Protective Actions Revision 16 EPP/lP 5 Series - Aid to Personnel 5.1 Search and Rescue Revision 8 5.2 RESERVED 5.3 Emergency Exposure Criteria and Control Revision 8 5.4 Emergency Personnel Monitoring Revision 9 I

REVISION 58

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ISA5.735B i.

EPPIIMPLEMENTING PROCEDURES EFFECTIVE INDEX

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EPPI1P 6 Series - Re-entry/Recover 6.1 Re-entry to Affected Areas - Revision 10 I.

Criteria and Guidance 6.2 Termination of the Emergency and Recovery Revision 11 ii I

7 Series - Maintaining Emereency Prevaredness Is EPPIIP 7.1 Emergency Equipment Inventory Revision 14 and Maintenance Procedure 7.2 Administration of Emergency Preparedness Revision 9 Plan, Drills and Exercises I EPPIIP 8 Series - FIre Fightine 8.1 Fires in Radiologically Controlled Areas Revision 7 1

EPPIP 9 Series - Nuclear Communications 9.1 Emergency Public Information Revision 11 Emergency Response Organization Controlling Procedure 9.2 Reserved 9.3 Activation, Operation and Deactivation Revision 4 of the Emergency Public Information Organization Emergency Operations Facility (EOF) 9.4 Activation, Operation and Deactivation Revision 9 I.

of the Joint Public Information Center (JPIC) I.

9.5 Activation, Operation and Deactivation Revision 7 of the Penn Power Customer Account Services Department EPP/IP 10 Series - Corporate Response I,

10.1 Emergency Response Organization Corporate Support Revision 3 4

REVISION 58 I

A5.735B EPPIIMPLEMENTING PROCEDURES EFFECTIVE INDEX EPP/IP ANNEXES Annex A - Westinghouse Emergency Response Plan Revision 8 Annex B - DELETED Annex C - Major Injury Involving Radioactive Contamination For The Medical Center, Beaver Revision 9 Annex D - Procedure for Transferring Radiation Casualties to the Radiation Emergency Response Program (UPMC Presbyterian) Revision 8 Annex E - Reserved REVISION 58

A5.735B Beaver Valley Power Station Unit 1/2 EPPIIP 1.7 EMERGENCY RESPONSE ORGANIZATION (ERO) TEAM Document Owner Manager, Emergency Preparedness Revision Number 11 Level Of Use General Sldll Reference Safety Related Procedure Yes CONTROLLED BVPS UNIT 3

Beaver Valley Power Station ftouNumbEP 1.7 Thie: Unit: Levd Of Use:

1/2 General Skill Reference EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS Re'sio PageN iimber TABLE OF CONTENTS 1.0 PURPOSE ................................................. 1 2.0 SCOPE ................................................. 1

3.0 REFERENCES

AND COMMITENTS ................................................ 1 3.1 References ................................................. 1 3.2 Commitments ................................................. 1 4.0 RECORDS AND FORMS ................................................. 2 4.1 Records ................................................. 2 4.2 Forms ................................................. 2 5.0 RESPONSIBIlITIES ................................................. 2 5.1 Manager, Emergency Preparedness ................................................ 2 5.2 ERO Members ................................................. 2 5.3 BVPS Emergency Response Organization ................................................ 2 5.4 Emergency Preparedness Personnel ................................................. ;.3 6.0 PRECAUTIONS AND LMiTATIONS ................................................. 3 6.1 Precautions ................................................. 3 6.2 Limitations..............................................................................................................................3 7.0 PREREQUISTES ................................................. 3 8.0 PROCEDURE ................................................ 3 8.1 ERO Team Response Assignments/Responsibilities ................................................. 3 8.2 Beeper/Responsibility Assignments and Transfers ................................................. 4 8.3 ERO Activation ................................................. 5 8.4 ERO Response During Working and Non-working Hours ................................................. 8 ATIACHMENT A ERO EXPECTATIONS ................................................. 11

Beaver Valley Power Station EPPoAP 1.7 ide: Unit: Level Of Use:

1/2 General Skill Reference EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS Revision: Page Number 1.0 PURPOSE 1.1 This procedure provides the guidance for maintaining the Beaver Valley Power Station Emergency Response Organization (ERO) and ERO augmentation.

2.0 SCOPE 2.1 This procedure describes the Beaver Valley Power Station (BVPS) Emergency Response Organization (ERO) Teams including: designations, assignments, responsibility, transfers, overall coordination and ERO expectations.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3.1.1 Beaver Valley Power Station Emergency Preparedness Plan.

3.1.2 NUREG-0654IFEMA-REP-1 "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."

3.1.3 Title 10, Code of Federal Regulations Part 50, Appendix E.

3.1.4 NPDAP 2.14 "Fitness-For-Duty Program For FirstEnergy Employees at Beaver Valley Power Station".

3.1.5 Condition Reports 3.1.5.1 00-4309 3.1.5.2 01-6025 3.1.5.3 02-00444-6 3.1.5.4 02-10225-1 3.1.5.5 03-02032-06 3.1.5.6 03-02103-03 3.1.5.7 03-02034-03 3.1.5.8 03-02034-10 3.1.5.9 03-02103-02 3.2 Commitments 3.2.1 None

I Ir Beaver Valley Power Station Procedure Nun 1.7i Mae: ~~~~~~~~~~~~~~~~~~Ut Lave!Of Use: I 1/2 General Skill Referencel EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS j 11 P j(Number IP' 4.0 RECORDS AND FORMS e

4.1 Records I'

9:

4.1.1 None 4 A:

4.2 Forms I 4.2.1 EPP-IP-1.7.F01, On-Call ERO Response Team Transfer Form ,

RESPONSIBILITIES S

5.0 5.1 Manager. Emergency Preparedness q4 5.1.1 Is responsible for the overall coordination of the ERO Teams and the associated Call-List.

5.2 ERO Members (assigned to a dedicated response team (Red, White, Blue) or ERO Pool personnel (Green))

5.2.1 Are responsible for the actions described in this procedure. I 5.3 BVPS Emergency Response Organization 5.3.1 Will consist of three (3) dedicated response teams, each with required designated Primary and Secondary responders, supplemented by designated support (call-tree) personnel. The teams will be identified by colors (i.e., Red, White, Blue).

5.3.1.1 Primary Responders 5.3.1.1.1 Shall report to their emergency facility as soon as possible, and in all instances, within one (1) hour of notification of an Alert, or higher, emergency classification.

l

-nr -1 e to 5.3.1.2 Secoi rrJr- 'n LXUuy 1wZb1UUUr1b 5.3.1.2.1 Shall report to their emergency facility as soon as possible, and in all 1.

instances, within two (2) hours of notification of an Alert, or higher, :

emergency classification. F.

5.3.1.3 Desij;nated Support (call-tree) Personnel .1 5.3.1.3.1 Are to report to their emergency facilities as soon as possible following notification.

A, A

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I 2 l General Skill Reference EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS Revision: Page Number.

I11 . 3of 4 5.3.1.4 ERO Personnel Not Assigned to One of the Three (3) Dedicated Response Teams 5.3.1.4.1 Will be assigned to the ERO Team Pool, and shall report as soon as possible following notification. The Team Pool will also be identified by color (Green).

5.4 Emergency Preparedness Personnel 5.4.1 Initial team assignments will be determined by Emergency Preparedness personnel.

ERO response team transfers shall be approved by the Manager, EP. Temporary transfers are described in Section E.3 of this procedure.

6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions 6.1.1 None 6.2 Limitations 6.2.1 None 7.0 PREREQUISITES 7.1 This 1P remains in effect at all times to ensure a full state of readiness is maintained.

7.2 All ERO personnel shall be aware of the requirements stipulated in this procedure.

7.3 Transfers of ERO personnel responsibility shall follow the guidance provided in this procedure.

8.0 PROCEDURE 8.1 ERO Team Reponse Assignments/Responsibilities 8.1.1 Dedicated Response Teams will rotate between the following response categories: On-Call, Stand-By and Back-Up.

8.1.1.1 On-Call responders are those personnel who shall respond immediately when notified. An On-Call team shall consist of Primary Responders, Secondary Responders, and designated support personnel.

8.1.1.2 Stand-By responders have no response responsibility for the week that they are designated as Stand-By. A Stand-By team shall consist of Primary Responders, Secondary Responders, and designated support personnel.

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Beaver Valley Power Station lad~~~~~~~~~~~~~~~~~~~~~E:iI bous 1.7 1.7 il EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS Joon:1/2 General Skill Reference Pap Nu1ber.

8.1.1.3 Back-Up responders are the designated relief personnel (12-hour shifts) for the On-Call responders. A Back-Up team shall consist of Primary Responders, Secondary Responders, and designated support personnel.

8.1.2 ERO Response Teams shall rotate weekly.

8.1.2.1 Rotation assignments shall be as follows (ERO Rotation Calendar available on BVWeb, EPP Web Page):

. On-Call to Stand-By

. Stand-By to Back-Up

. Back-Up to On-Call 8.1.2.2 Rotation shall occur every Monday at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months .

8.1.3 On-Call Team Fitness For Duty (FF)) requirements.

8.1.3.1 Personnel designated "On-Call" Primary and Secondary Responders shall adhere to Fitness For Duty (FED) requirements per NPDAP 2.14.

8.1.3.2 Personnel conducting a call-out must ask the individual "If they have consumed alcohol within the last 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ."

8.1.3.2.1 Personnel responding to a call-out must meet FF) requirements.

8.1.3.3 If deemed necessary, FFD testing shall be conducted prior to beginning ERO duties.

8.1A ERO personnel shall adhere to the ERO Expectations (Attachment 1).

8.2 Beeper/Responsibility Assignments and Transfers 8.2.1 All personnel assigned to an ERO position as either a Primary or Secondary responder shall be assigned a beeper unless otherwise noted.

8.2.2 On Call personnel arranging transfer of ERO responsibility shall notify Emergency Preparedness per Form EPP-IP-1.7.FO1.

8.2.3 Transfer of assignment responsibility for On-Call Team Responders shall fal into three (3) categories.

NOTE: Individuals shall consult the ERO Call-List to determine the identity of qualified personnel for their ERO position for On Call transfer of responsibility. The ERO Call-List is distributed in paper format and is also available on the Emergency Prenaredness Web naze (most current list).

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Beaver Valley Power Station PrcedurNumber.

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1/2~ General Skill Reference EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS Revision: Page Number:

I 5 of 14 NOTE: If personnel in the On-Call category will not be available for any portion of their one week rotation, they shall arrange for a qualified replacement from the GREEN or Stand-by Team prior to requesting a replacement from the Back-up Team.

8.2.3.1 On-Call Team personnel who will be unavailable to respond for a period of less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months shall do the following:

NOTE: Emergency Preparedness DOES NOT need to be informed when a transfer of responsibilities for less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months occurs. l 8.2.3.1.1 Ensure their position is covered by another qualified individual for that ERO position 8.2.3.2 On-Call Team personnel who will be unavailable to respond for a period of greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months shall do the following:

8.2.3.2.1 Ensure their position is covered by another qualified individual for that ERO position by completing form EPP-IP-1.7.FO1, "On-Call ERO Response Team Transfer Form" 8.2.3.2.2 Mail (or FAX @ PAX 5777) form EPP-IP-1.7.F01, to the Manager, Emergency Preparedness. If during off-normal working hours, contact Emergency Preparedness and provide the information on Attachment 2.

Mail (or FAX) a completed document to the Manager, Emergency Preparedness.

8.2.3.2.3 On-Call Team personnel who will be unavailable to respond due to sudden illness (NOI&) or personal emergency should attempt to locate a replacement. f a replacement can not be located, contact Emergency Preparedness.

8.2.4 All personnel assigned beepers are responsible for maintaining operability of that beeper (i.e., changing batteries when necessary). Personnel shall keep their beepers "on" at all times (and in the audible mode when appropriate) and respond accordingly to All beeper activations.

8.3 ERO Activation 8.3.1 Beaver Valley Emergency Response System (BVERS) Notification l NOTE: BVERS is a computer aided Voice Mail system that will be used to activate the ERO Beepers ad accept personnel call backs.

8.3.1.1 Beepers will be activated for ERO notifications with the following Actual Event -

On-Call ERO Team phone: 724-6434370 (or 330-3154380).

- I r AdP Beaver Valley Power Station

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in I General Skill Reference Revision:Pa m -o:

EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS 1 1 -, 6 of 14 (

8.3.1.1.1 Only On-Call ERO Team personnel shall call back into BVERS by dialing 724-643-4370/330-315-438. as required.

8.3.1.2 Beeper Holder Response 8.3.1..2.1 Upon calling into BVERS, you will be prompted to enter your Plant Photo LD. number (e.g.: 0123). Dataentry requiresa touch tone phone. BVERS will then ask you to verify the number by pressing "9"' (yes) or "6" (no).

8.3.1..2.2 A message will be provided at this time stating the Unit, time and emergency classification declared and the basis for the declaration.

NOTE: BVERS will have information on all qualified ERO personnel programmed into its data base, and will know who you are and for which ERO position you are currently qualified by your LD. entry. Personnel calling into BVERS will either access the system immediately, or receive a busy signal. Personnel calling back should be able to access the system within a few minutes.

8.3.1.2.3 BVERS will ask the following questions:

BVERS will ask if you understand the message by pressing "9"(yes) o "69 (no).

BVERS will ask if you are Fit For Duty and ask you to acknowledge by pressing "9" (yes) or "6" (no).

BVERS will ask if you are able to respond and ask you to acknowledge by pressing "9" (yes) or "6" (no).

BVERS will ask you to enter your Estimated Time of Arrival in minutes (enter your travel time from your location to your emergency facility).

BVERS will then terminate the connection.

8.3.1.2.4 BVERS will print out reports for the Control Room, Emergency Response Facility, and Joint Public Information Center identifying those personnel who have called in.

8.3.1.2.5 The ERO Team designated as Back-Up does not need to call-in but shall report 12-hours after emergency declaration, unless otherwise notified.

8.3.1.3 If BVERS determines that a specific ERO position has not been staffed, it will activate the individual Beepers for all personnel in that specific ERO position with the following display: 724-643.4370 or 330-3154380 I

Beaver Valley Power Stadon PPm 1.7 Tie: Unit Lcvl Of Use:

12 Q General Skill Reference EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS 1e Revsion: Pf 8.3.1.3.1 Any ERO Beeper Holder receiving a Beeper Code of 724-643-4370 or 330-315-4380 SHALL call Into BVERS, answer the questions requested and report to their designated emergency facility. (This assumes that the On-Call individual is unable to respond.)

8.3.1.3.1.1 If the ERO position has been filled, any other personnel calling in to respond to the position will be informed that there are no positions available.

8.3.1.3.1.2 If the On-Call individual becomes available, he/she shall call into BVERS and report to their emergency facility.

8.3.1.4 If BVERS determines that a specific ERO position has still not called in, BVERS will perform the following notifications for personnel in that specific ERO position:

Call the individual PAX phone numbers of personnel in that specific position,

Call the individual Home phone numbers of personnel in that specific position, and

Again, activate the individual Beepers for personnel in that specific ERO position.

This will continue until the ERO position is filled.

8.3.2 ERO Voice Mail System (ERO-VMS) Notification NOTE: The ERO-VMS is a typical voice mail system that is used to activate the ERO Beepers and accept personnel call backs In the event that the primary BVERS system Is unavailable. The ERO-VMS utilizes the ERF switch and has remote accessing features. There is only one beeper call back number for ERO-VMS.

8.3.2.1 Beepers will be activated for ERO notifications with the following Beeper Codes:

Actual events "9999995080

Actual events - Site Inaccessible "0000005080" 8.3.2.1.1 Only On-Call ERO Team personnel shall call back Into the ERO-VMS by dialing 724-682-5080 (PAX 5080).

8.3.2.1.2 ERO-VMS call-back number is listed on the ERO Call-List.

iI Beaver Valley Power Station r Nurnbw 1 i7 Unit Lved Of Use:

1/2 General SkIl Reference_

EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS 11ofN14 8.3.2.2 Beeper Holder Response 8.3.2.2.1 The ERO-VMS will inform you that an emergency has been declared and ask that you provide the following information. If you have not consumed alcohol in the last 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , (personnel must verbally provide this information at the sound of the tone):

Your name (please spell last name)

ERO position

Estimated time of arrival (Time of Day, i.e., 2145 Hrs., 0115 Hrs.)

8.3.2.2.2 If you have consumed alcohol in the last 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , contact an alternate for your emergency position.

NOTE: ERO-VMS has a maximum of 4 incoming lines. As a line becomes available, the next call received will be answered. If no lines are available, a busy signal will be received.

8.4 ERO Response During Working and Non-working Hours 8.4.1 Response During Working Hours 8.4.1.1 "On-Call" ERO Personnel (Primary, Secondary and designated Support (Call-Tree) personnel SHALL respond as follows:

8.4.1.1.1 Primary and Secondary responders SHALL call the Beaver Valley Emergency Response System (BVERS) prior to responding to their emergency location (This includes personnel onsite).

8.4.1.1.2 ALL "On-Call" ERO personnel SHALL respond to their emergency facility.

8.4.1.1.3 Determine manpower needs and supplement, as necessary. I, 8.4.1.2 All Other ERO Personnel 8.4.1.2.1 SHALL report to their emergency facility.

8.4.1.2.2 Take direction from the "On-Call"ERO personnel.

8.4.2 Response During Non-Working Hours 8.4.2.1 "On-Call" ERO Personnel f 8.4.2.1.1 Beeper Holders SHALL call the Beaver Valley Emergency Response System (BVERS) and respond to their emergency location.

Beaver Valley Power Station hocedwe Numb .

Title:

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1/2 General Skill Reference EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS Revision Page Nber 8A.2.1.2 Determine manpower needs and "call-out" additional personnel, if necessary.

8A.2.2 All Other ERO Personnel 8A.2.2.1 Beeper Holders SHALL remain alert for further instructions (call-out, shift rotation, etc.).

8.4.2.2.2 All other ERO personnel will be called-out, if necessary.

Beaver Valley Power Station ItN Nb. 1.7 -

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Procedur Number Beaver Valley Power Station EPP/IP 1.7 Tid: Unir Level Of Use:

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ATTACHMENT A Page of 4 ERO EXPECTATIONS I Duty Expectations/Pager Response Expectations

All ERO personnel shall understand, and adhere to, the requirements of procedure EPPIIP 1.7, Emergency Response Organization (ERO) Teams.

All ERO personnel assigned ERO Pagers are expected to wear their Pagers at all times when within the Pager Service Area (located on the EPP Webpage/ERO Info) and respond appropriately to messages. The following are some unacceptable responses for NOT responding to Pager messages:

Pager left in vibrate when not being worn

Pager left in other location too far to hear audible alarm (i.e.: bathroom, shower, etc.)

Weak/dead battery

All ERO notifications initiated by BVERS shall display one of the following messages:

1) "Actual Event-On-Call ERO Team call 724-6824730", or,

2) "This is a Drill-On-Call ERO Team call 724-682-4730" (An alternatephone number that may be displayedforBVERS is 330-31S-4380)

When the above messages are displayed ALWAYS call the number provided.

These are the ONLY two alpha messages initiated by BVERS that require ERO response (other alpha messages are for information, or non-ERO response).

Only On-Call ERO personnel are to initially call-in to BVERS.

If only the BVERS phone number (724-6824730 or 330-3154380) is displayed (BVERS searching to fill a specific ERO position), then any individual receiving this message shall call-in, respond and upon being accepted, report for your position as required.

For an actual event, or Drill/Exercise, a BVERS Pager message shall be followed by a LOTUS NOTES alpha-numeric message describing the event and emergency declaration time.

Upon notification, On-Call ERO personnel shall report to their ERO positions as soon as possible, but no later than their assigned response times from the time of the emergency declaration (this includes allowing for Facility activation time).

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Beaver Valley Power Station EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS howd=

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Revison I I 11 fpNmb 1.7 Geneal SkIll Reference 12ff4 14 X

I ATrACHMENT A Page 2 of4 ERO EXPECIATIONS l Duty Expectations/Pager Response Expectations (cont.)

On-Call ERO personnel are expected to maintain response times to their respective emergency response facilities (I or 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months from the time of event declaration., not the time of Pager activation).

For actual events, personnel are to respond appropriately when notified by Pager (via BVERS/Lotus Notes), Plant Page Party System, phone or BVERS phone call. (I.e.: take cover, "

report to emergency facilities, report to alternate facilities, etc.).

For Drills or Exercises, personnel are to respond appropriately when notified by Pager.

(BVERS/Lotus Notes), Plant Page Party System, phone or BVERS phone call (i.e.: take cover, report to emergency facilities, report to alternate facilities, call-in DrilH/OST only).

In the event alphanumeric messaging is not available, ERO Pagers will be activated with one of these message codes:

1) 9999995080 (Actual Event/Site Accessible), On-Call ERO personnel report to their assign&

emergency facilities.

2) 0000005080 (Actual Event/Site Inaccessible), On-Call ERO Managers/Coordinators report to the Alternate EOF per procedure.

The ERO call-back phone number for this response is 724-682-5080.

ERO personnel On-Call are expected to maintain fitness-for-duty per OCFR26.

For actual events occurring during normal working hours (0700-1700 hrs), all ERO personnel are expected to report to their appropriate emergency facility to support the On-Call Team (only On-Call ERO personnel call-in to BVERS).

ERO personnel are not to call the Control Room upon notification of an emergency, unless specifically requested.

On-Call ERO personnel are expected to have their FirstEnergy ID Badge and Dosimetry when reporting to their respective facilities.

If an On-Call ERO member becomes incapable of performing their ERO duties, they are to contact another qualified person for that position and transfer On-Call responsibility. (Notification to EPP(

personnel of the transfer is per EPP/IP 1.7.). K,

Beaver Valley Power Station EPP/ P 1.7

Title:

Unit: Level Of Use:

.. 12 General Skill Reference EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS Revision: Pa Number1 ATTACHMENT A Page 3 of 4 ERO EXPECTATIONS l Duty Expectations/Pager Response Expectations (cont.)

Emergency Facility Leads should define their expectations for their Team while remaining cognizant of Facility activation timing requirements (i.e.: delegate activities, maintain overview of events, involve the Team in response, etc.).

ERO personnel must provide information, not just data points, to each other and the Facility Lead, i.e.:

Explain the meaning of a data point provided to the Team (i.e.: DIG #1 tripped off vs. DIG #1 tripped off and was the only remain power supply)

ERO communications shall use three-way communications and noun descriptors.

Following Actual Events, Drills/Exercises or staffing of Emergency Facilities to provide plant support, each Emergency Facility SHALL conduct and document a critique.

The critique will be lead by the Facility Lead.

A Condition Report will be written for each Delta (Area For Improvement) as deemed necessary by the Facility Lead.

The person presenting the comment warranting the Condition Report SHALL write the Condition Report.

Each Delta presented, whether a Condition Report was warranted or not, SHALL have the presenters name written beside the comment.

Emergency Preparedness will be notified of each Condition Report written.

Facility equipment, procedure or supply challenges that occur during Actual Events, Drills or Exercises SHOULD have a resolution attempted during the Actual Event, Drill or Exercise, not simply commented upon during the critique.

Beaver Valley Power Station EPP/lP 17 rift unit LcVd Of Us i' 112 General Skill Reference EMERGENCY RESPONSE ORGANIZATION (ERO) TEAMS RcC ?jumbct ATTACHMENT A Page 4 of 4 ERO EXPECTATIONS l~ ~ ERO Training and Drill Participation Expectations. -

Attend appropriate Initial

- ERO Classroom Training for assigned position.

Attend appropriate Continuing ERO Classroom Training for assigned position.

Attend assigned ERO Team Drills/Exercises (Drill participation for key ERO positions is tracked as a NRC Performance Indicator.) . r

Managers and supervisors shall ensure that each ERO member under their supervision remains fully qualified at all times to respond to an emergency. -

Ensure ERO participation in training and Drills is documented.

Participate in Drill/Exercise critiques and identify areas for improvement and strengths so appropriate corrective actions can be taken. -

ERO personnel shall initiate Condition Reports, and notify EPP, as necessary.

ERO personnel shall respond to, or assist EPP personnel, with the response to Condition Reports.

Ensure their emergency response facility is in a state of readiness prior to leaving the facility.

.1~~

A5.735B Beaver Valley Power Station Unit 1/2 EPP-IP-2.7 LIQUID RELEASE ESTIMATE Document Owner Manager, Emergency Preparedness Revision Number 8 Level Of Use General Skill Reference Safety Related Procedure Yes CONTROLLED BVPS UNIT 3

Beaver Valley .Procedure Power Statin Number:

Bseaver valley Prower Station EPP-IP-2.7

Title:

Unit: Level Of Use:

1/2 General Skill Reference UQUID RELEASE ESTMATE Revision: Page Number:

R iO TABLE OF CONTENTS 1.0 PURPOSE ................................................... 1 2.0 SCOPE ................................................

3.0 REFERENCES

AND COMMITMENTS ..

3.1 References .

3.2 Commitments .2 4.0 RECORDS AND FORMS .................................................. . 2 4.1 Records ................................................... 2 4.2 Forms ................................................... 3 5.0 RESPONSIBILTIES ................................................... 3 5.1 Environmental Assessment and Dose Projection Coordinator ................................................... 3 6.0 PRECAUTIONS AND LIMITATIONS ................................................... 3 6.1 Precautions ................................................... 3 6.2 Limitations ................................................... 3 7.0 PREREQUISITES ................................................... 3 1-111 Ia ouA n nnrsfVn'%TTOD.

r. ........ . ...................................................................................

'2 J

AITACHMENT A GRAPHICAL RIVER FLOW RATE DETERMINATION .............................................. 7 ATTACHMENT B UNIT 1 NRC-EC CALCULATION (SAMPLE METHOD): UNUSUAL EVENT AND ALERT DETERMINATION ........................................................ 9 ATTACHMENT C UNIT I EPA-MPC CALCULATION (SAMPLE METHOD): PAG DETERMINATION ....................................................... 1 ATTACHMENT D UNiT I NRC-EC CALCULATION (PROCESS MONITOR METHOD):

UNUSUAL EVENT AND ALERT DETERMNATION ............................................... 13 ATTACHMENT E UNIT 1 EPA-MPC CALCULATION (PROCESS MONITOR METHOD): PAG DETERMINATION ....................................................... 15 ATTACHMENT F UNIT 1 UNMONlTORED LIQUID DISCHARGE PATHWAYS ................................. 17 ATTACHMENT G UNIT 2 NRC-EC CALCULATION (SAMPLE METHOD): UNUSUAL EVENT AND ALERT DETERMINATION ....................................................... 19 ATTACHMENT H UNIT 2 EPA-MPC CALCULATION (SAMPLE METHOD): PAG DETERMINATION ....................................................... 21 ATTACHMENT I UNIT 2 NRC-EC CALCULATION (PROCESS MONITOR METHOD):

UNUSUAL EVENT AND ALERT DETERMINATION ............................................... 23 ATTACHMENT J UNIT 2 EPA-MPC CALCULATION (PROCESS MONITOR METHOD): PAG DETERMINATION ........................................................ 25 ATTACHMENT K UNIT 2 UNMONITORED LIQUID DISCHARGE PATHWAYS ................................. 27

Beaver Valley Power Station

~~~~~~~~~~~~~~~EPP ProceduNumber. IP2.7 1ile: uni: Level Of Use:

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R I f 8 1.0 PURPOSE 1.1 This procedure provides various methods of determining the fractions of NRC -EC's and EPA-MPC's following an unplanned or uncontrolled release of radioactive materials via a monitored or unmonitored pathway to the Ohio River. The Environmental Assessment and Dose Projection Coordinator is responsible to ensure that actions outlined in this procedure are implemented when necessary.

2.0 SCOPE 2.1 This procedure provides several different calculation methods for determining the concentration in the discharge or the drinking water after an unplanned release. The method used will be determined by the availability of sampling or radiation monitoring data along with release rate and dilution rate information. Brief descriptions of the different procedures (methods) are described in Section 8.0.

2.2 IF a liquid discharge is occurring at Unit 1 and Unit 2, THEN perform the appropriate attachment calculations for NRC-EC and EPA-MPC determination for both sites and all discharge pathways. Interpret the results as follows:

2.2.1 Use the maximum calculated NRC-EC fraction from both sites and all discharge pathways for comparisons against Unusual Event and Alert EAL criteria as follows:

2.2.1.1 IF the maximum fraction is >2, and the release is 260 minutes, THEN an Unusual Event is declared.

2.2.1.2 IF the maximum fraction is >200 and the release is >15 minutes, THEN an Alert is declared.

2.2.2 Use the sum total of the EPA-MPC fraction that is calculated from both sites and all discharge pathways for comparisons against PAG criteria as follows:

2.2.2.1 IF the sum total fraction is >12, THEN a protective action recommendation is made per EPP/IP 4.1.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 3.1.1 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.

3.1.2 Appendix B, Table 2, Col. 2 to 10 CFR Part 20.1001-20.2401.

3.1.3 Appendix I to 10 CFR Part 50.

3.1.4 Plan for Nuclear Power Generating Station Incidents Commonwealth of Pennsylvania Dept. of Environmental Resources/Bureau of Radiation Protection.

- - -- - - - - -- - - - - -I -*F Procedue Nwmbcr Beaver Valley Power Station EPP-IP-2.7 Tit Unit: Levd Of Use:

/2 General Skill Refere I LIQUID RELEASE ESTIMATE RcVISIOo PAL 9 of29 3.1.5 NUREG-0654/FEMA-REP-1 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Powet Plants.

3.1.6 Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and in Water for Occupational Exposure, U.S. Department of Commerce, National Bureau of Standards, Handbook 69.

3.1.7 DLC Calculation Package No. ERS-ATL-93-030, EPPIEP 2.7 Procedure.

3.1.8 Offsite Dose Calculation Manual, including procedure 112-ODC-2.01, Iiqud Effluents, 1/2-ODC-3.03, Controls for RETS and REMP programs.

i A 3.2 Commitments II 3.2.1 None 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 The following QA Records are generated by this procedure:

4.1.1.1 Attachment B, Unit 1 NRC-EC Calculation (Sample Method): Unusual Event and Alert Determination 4.1.1.2 Attachment C, Unit 1 EPA-MPC Calculation (Sample Method): PAa Determination 4.1.1.3 Attachment D, Unit 1 NRC-EC Calculation (Process Monitor Method): Unusual Event and Alert Determination 4.1.1.4 Attachment E, Unit I EPA-MPC Calculation (Process Monitor Method): PAG Determination 4.1.1.5 Attachment F, Unit 1 Unmonitored liquid Discharge Pathways 4.1.1.6 Attachment G. Unit 2 NRC-EC Calculation (Sample Method): Unusual Event and Alert Determination 4.1.1.7 Attachment H, Unit 2 EPA-MPC Calculation (Sample Method): PAG, Determination 4.1.1.8 Attachment I, Unit 2 NRC-EC Calculation (Process Monitor Method): Unusual Event and Alert Determination 4.1.1.9 Attachment J, Unit 2 EPA-MPC Calculation (Process Monitor Method): PAG Determination

Procedure Number.

Beaver Valley Power Station EPP-IP-2.7 ritle: unit Levd Of Use:

12 General Skill Reference LIQUI) RELEASE ESTIMATE Revision: PageNumber R 13 tuf 8 4.1.1.10 Attachment K, Unit 2 Unmonitored Liquid Discharge Pathways 4.2 Forms 4.2.1 None 5.0 RESPONSIBILITIES 5.1 Environmental Assessment and Dose Projection Coordinator 5.1.1 Responsible to ensure that actions outlined in this procedure are implemented when necessary.

6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions 6.1.1 The NRC-Effluent Loncentrations (NRC-EC's) referred to in this procedure, and throughout the Offsite Dose Calculation Manual (ODCM), were adjusted to accommodate operational flexibility needed for effluent releases. Therefore, the limits associated with liquid release concentrations (i.e., the OEC ODCM Effluent Concentration) are based on 10 times the NRC-EC's stated in Appendix B, Table 2, Col.

2 of 10 CFR 20.1001-20.2401. The multiplier of 10 is justified because the annual dose of 500 mrem (old 10 CFR 20 MPC bases, and BVPS Technical Specification bases) is a factor 10 times higher than the annual dose of 50 mrem (new 10 CFER EC bases).

6.2 Limitations 6.2.1 The estimation methods in this procedure are based on a uniform distribution of the released activity within the river water. The actual concentrations at the Midland Water Treatment Plant may vary as a function of mixing. Mixing is projected to be complete at the East Liverpool Water Treatment Plant intake.

7.0 PREREQUISITES 7.1 An unplanned or uncontrolled release of radioactive materials to the Ohio River has occurred, is imminent, or is suspected.

8.0 PROCEDURE NOTE: This method is one of the backup methods for determining the river flow rate.

The primary method is to call the National Weather Service and request the Ohio River flowrate at the Montgomery Dam in cuft/sec.

8.1 ATIACHMENT A, Graphic River Flow Rate Determination 8.1.1 The graph represents a means to determine the Ohio River Flow Rate necessary for obtaining various dilution factors used in the calculations of EPP/IP 2.7.

Beaver Valley Power Station -E PNP'-IP-2.7 iLtD LEUnitE ETvc I Of sc Neral SM Macy:

LIQUID RELEASE ESTIMATE 8 _ _ __ bmJ N. '5 Iu 4 of 2 8.2 ATTACHMENT B (Unit 1) and G (Unit 2), NRC-EC Calculation (Sample Method):

Unusual Event and Alert Determination 8.2.1 This method determines the concentration in the release prior to dilution by the Ohio River, and compares the result to the appropriate Technical SpecificationlODCM limits.

The resulting factor is used as the basis of the Unusual Event and Alert Emergency Action Levels. This method requires an isotopic or gross beta-gamma sample from the discharge or directly from the source (i.e., from a tank). IF a source sample is taken, THEN an appropriate dilution factor between the discharge flow and the cooling tower blowdown/emergency outfall structure flow must be applied, unless the release is directly to the river via the Catch Basin System.

8.3 ATTACHMENT C (Unit 1) and H (Unit 2), EPA-MPC Calculation (Sample Method): PAG Determination 8.3.1 This method determines the concentration in the Ohio River (at the Midland Water Treatment Plant Intake) following dilution by the river, and compares the results to the appropriate EPA Drnking Water Standard. This concentration is assumed to be in the drinking water at Midland and East Liverpool; and is the basis to provide a protective action to downstream water treatment plants. This method requires isotopic or gross beta gamma sample from the discharge source (i.e., the appropriate tank) and a dilution factor between the discharge flow and the flow of the Ohio River. This attachment may (4

also be used for a sample from the Midland Water Treatment Plant without a dilution factor.

8.4 ATTACHMENT D (Unit 1) and I (Unit 2), NRC-EC Calculation (Process Monitor Method):

Unusual Event and Alert Determination it 8.4.1 This method duplicates the methods of Attachment B and 0 except that a process monitor reading is used in lieu-of an actual sample. The criteria for use of these Attachments requires an upper alarm indication on one or more of the following radiation monitors:

Unit I Unit 2 RM-lLW-104 2SGC-RQ100 ;

RM-lLW-116 2SWS-RQOOAB,C,D RM-lRW-100 2SWS-RQ101 RM-IRW-101 2SWS-RQ102 RM-1RW-100A,B,C,D RM-1DA-100 8.5 ATACHMENT E (Unit 1) and J (Unit 2), EPA - MPC Calculation (Process Monitor Method): PAG Determination C

i

Pwvccdur Number.

Beaver Valley Power Station EPP2.7

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Unit: Level Of Use:

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R~~~ Sof

- 2R 8.5.1 This method duplicates the methods of Attachment C and H except that a process monitor reading is used in lieu of an actual sample. The criteria for use of these Attachments requires an upper alarm indication on one or more of the following radiation monitors:

Unit Unit 2 RM-lLW-104 2SGC-R100 RM-ILW-116 2SWS-RQ100AB,C,D RM-lRW-100 2SWS-RQ101 RM-lRW-101 2SWS-RQ102 RM-lRW-100A,B,C,D RM-1DA-100 8.6 ATTACHMENT F (Unit 1) and K (Unit 2), Unmonitored Liquid Discharge Pathways 8.6.1 This method determines the release rate and dilution rate of an unplanned and unmonitored release of radioactive material via leakage of a storage tank, etc. Use of this attachment requires knowledge of the amount of liquid released and the estimated duration of the release. After completion of this attachment, enter the release rate and dilution rate into Attachments B and C or G and H (as appropriate) and continue the calculation as before.

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v

,;! :- I Procdur Numbcr.

Beaver Valley Power Station EPP-P-2.7 Rf Tife unit LveZ Of Us=c 1/2 General Skill Ref i LIQUID RELEASE ESTIMATE RevisiOD-g I~Pago N 6~2 INTENTIONALLY BLANK :1 K,

I

Beaver Valley Power Station

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1/2 General Skill Reference UQUID RELEASE ESTIMATE Revisio Page Number R 7 of 2 ATTACHMENT A Page 1 of 2 GRAPHICAL RIVER FLOW RATE DETERMINATION IF the Stage Height method is used to determine the River Flow Rate in ft/sec, THEN call the Montgomery Dam at 724-643-8400 to obtain the Lower Gauge Height (ft) (stage height) (ft) of the Ohio River at the dam site. Find this value on the vertical axis and move horizontally on the graph (Attachment A) to the solid line marked flow rate. At this point, move vertically down the graph to the associated River Flow Rate on the horizontal axis. The value is in the necessary unit of ft /sec. This number is used in determining various dilution factors of liquid waste discharge.

A Beaver Valley Power Station EPP--2.7 fltle LIQUID RELEASE ESTATE Unit 1/2 RcvBa Level Of Use Gencral Skilll Pago Numbcr I

_ __9 ____ ____ ______ 4 RofR -

ATTAClEhVMT A Page 2 of 2 GRAPHICAL RIVER FLOW RATE DETERMINATION River Va Icty ,- FT/SEC 4:

60. t4s

,9 Sv S. _ _ n i

J~tT I ;TT ~~WFI~flV A. FlTfI? ci I

... i:-,,.S . . ... . ., .. :1 0

-0

.0

..+ -- J -0 48 I

.U) 0 U

), -3 :-i US p..

b lb Cm

'Ri've Flw Rt, cu ft/sec X 1000 vsod- on Corps of 69i1neers dals for tantgosery Due Q

Beaver Beaver Valley Valley Power Power Statlon Station Pocedure Number EPP-IP-2.7

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_ _ ~~~ __ 9 Of7 A[TACHMIENT B IUI Page of 2 UNIT 1 NRC-EC CALCULATION (SAMPLE METHOD): UNUSUAL EVENT AND ALERT DETERMINATION lWd Release Estimate Unit 1: NRC - EC Calculation (Sanple Melhod) CALCULATIONS (RTILA5.715TFG) 2.7-2F 11/1994 Unusual Event Determination .... (Cdtea: >2 x lSODCM Liit, and release > ora 60 )nums)

AlTk. t.,n,,I r - . 2NV MitrWif I, 1 t ,A . ... 5. - - - 14n-1nt

-~u -- . ........ - .~og¢s--.- s~a so.-E sP *z- --

Sample Location: Sanle Date: __s a Release Start ars, 0 Release Stop: 0 brs, Release Ton: - minutes

-v Col A Col B Sample WODCM Lhlt Cel C IFsample was taken fromthe outfn Nudide Ccton 10 x NRC-EC (Cl I Cel B)

Iwnfin )ili~ Awtfin afTiffit strre a cooling tower blowdown, THEN Be-7 _ 6E43

enter ID In Block (4) and determine Cr-51 / 5E-03 -

_ Mn-54 _ / .04 Block ()

A Fe-59 _ IE04 -

R Co57 I 6E-04 . Otherwise, do dhe fhlowing T Co-5S _ 2244 -

1 CO-60 _ 3E-05 . Enter Liquid Waste Release Rat in C NI-59 3E-03 a U Ni-63 1E-03 _ Block (2)

L Zn-5 I 5E-05 .

A ZD?4b-95 / 22-04 = (2)RcleaseRate p T Nb-97 I 3-03 a Enter die Cooling Tower Blowdown In E Mo-99 1 2E04 a Block (3), as obtained ur S Tc-99m _ 1E02 a o FT-1CW-101-1 Ag-llOm I 6E-05 a o)er

_ Sb-124 I 7E-05 a Sb-125 I 3E-04 a (3) Dhtio Ratei* gpm I 1-131 1 IE-05 _

O 1-133 7E45 a Divie Block (2) by Block (3), den D 1-135 3E04 a enter result in Block (4) rt I Q-134 I 9-06

N Cs-137 I IE-05 (4) DF -

E Bala-140 I SE45 _ _ Multiply Block (I) by Block (4), ben S Ce-141 I 3-04 . enter the result In Block ()

Ce-144 I 3E05 .

W-17 I 3-04 a (5) Fr of NRC Limit a_ __

H-3 _ IE42 -

Fe-55 143 IE a Note 1: F Block (5) s>2 and th release Sr-89 EO0 a_ Is > or

60 ninutes, TEEN Sr-90 I 5E.06 a declare an Unusual Event.

GrBetaGamma I 1207 a Note 2: 11 Block (5)is > 200, and th release is > or - S inutes. THEN Sum Tald(Udluted Fraction of lit) a () declar au Alket Note 3: IFn danm erelease

Use de latest approprate coeposite sample analysis.

ngoing, THEN calculate a Blbck

~ Use only If Isotopic sample analysis i not available.

(5) fa release. Use be max Blck (5) to lassify On event Calculations Br. Date: 0 - r.

()No Eergency Reviewed By: Date: 0 - ns ()Unusual Event Energency

()Aler Eergency

I a II I I I Beaver Valley Power Station N' EP 27 rft Unit Level Of Use:

1URS General Skill ReferenceJ LIQUID RELEASE ESTIMATE Revision: Pa 7br s : ~10 oif R h ATpAClBIENT B I : I I Page 2 of 2 UNIT 1 NRC-EC CALCULATION (SAMPLE METHOD): UNUSUAL EVENT AND ALERT DETERMENATION Liquid Release Unit 1: NRC - BC Calculation (Sample Method) INS2RUCONS (RTL A5.15FG) 2.7-2R 11/1994

. Obtain an isotopic sample from the source (e.g.: the Liquid Waste Discharge Line) or from dhe Cooling Tower Blowdown.

1.1 . tfe radiactivity is a result of a lking heatexchange, TH obtainhe sample from the Combined Cooling Tower Blowdowa.

2. Enter the nuclide concentratio= (uCiftD, or grosu beta-gamma concentration (uCilml) in the Cohlmn A.

3. Divide the nuclide concentration (uC~i'm) in Column A by the TS/ODCM Limit (uCifto in Columnti D. Enter the resul in Column C (Praction of Limit).

3.1 Note that the TSODCM Limit Value are based an 10 times the NRC-EC concentrations fisted in 10 CFR 20 Appendix B to 20.1001

- 20.2401, Table 2 CoL 2.

4. Sum the Fraction of TS/ODCM Limit values. Enter the Undiluted Fraction of TS/ODCM Limit total in Block (1).

5. F the sample was taken from the outfall structures, the cooling tower blowdown, or the Catch Basin System THEN enter i in Block (4) and proceed to Step 9.

6. IF the sample was taken from the Liquid Waste System. THEN obtain the Release Rate (gpm), for the appropriate pathway, Enter the value in Block (2).

7. Obtain the combined Cooling Tower Blowdowo Flowrate frm Fr-iCW-101-1 (gpm) or obtain any other applicabli Dilution Flowrate (gpm). Enter the appropriate value in Block ().

K S. Determine the Dilution Factor by dividing the Release Rate (gpm) in Block (2) by the Diluton Rate (gpm) in Block (3). Enter the result in Block (4).

9. Determine the Diluted Fraction of TS/ODCM Limit by Multiplying the Undiluted Fraction of TSIODCM Limit in Block (I) by the Dilution Factor in Block (4). Enterthe result in Block (5).

9.1 IF the Diluted Fraction of TSIDCM Umit from Block (5) is > 2, and the release is > or = 60 minutes, THEN declare an Unusual EveuL 9.2 iF the Diluted Faction of TSIODCM Limit from Block (5) is > 200. and the release Is > oro 15 minutes, THEN declare an AlerL 9.3 IF mc than one release is ongoing. T1EN calculate a Diluted Fraction of TS/ODCM Limit as shown in Block (5). for each release.

Use the highest Block (5) value for event classification.

, t i

I i0 I I

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Beaver Valley Power Station EPP-11'-2.7 Titk: Unit Level Of Use:

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---~ ~~ 11 f 2R ATTACBfMENT C I UNIT Page of 2 D

-j UNIT 1 EPA-UPC CALCULATION (SAMPLE METHOD): PAG DETEMINATION Lguid Release Estmate Unit 1: EPA -MPC Calculation (Sample Meod) CALCULATIONS (RTLAS.715M1 2.7-3F I3111994 FAG Dete nan .... (Criteria > 12 x EPA - NMC Unit)

Sampl Locanon Samk Date: a JI Release Star 0 hrs, Release Stop: 0 hs Release Tme: - inutes Col A Cal B Sazqle EPA-MPCUit CoIC IF aple was taken fhm the Midland Nudlide Concentration EPA-570 (Cot A/Col B) ffiOi/fl (unrninI4- Fraction of tnit Water eatment Plant intake THEN coter I I 4 -_ . 4

_o Be-7 I 6-06 a 10 in Block (4) sd determine cr-51 I 6-06

Mn-4 / 3E-07 . Block (5)

A Fe-59 2-07 a

/ IE-06 a otherwise, do the following:

R Co-57 T Co-5 I 3E07 _

I Co-60 I IE-07 - Entr Liquid Waste Release Rate In C Ni-59 _ 3-07 -

U Ni-63 _ / SE4S a Block (2)

L Zn-45 I 3-07 a A ZdNb-95 _I -

_1-7 (2)Release Rate a ______

T Nb-97 / 3-06 Enter Ohio River Flowrale in Block (3)

E Mo-99 _ 6E-07 _ (See INSTRUCFIONS)

S Tc 99mn 2E-05 a ()table value for nh of At-110m _ 9E-08 . ober~

& Sb-124 _ 62-OS a Sb-125 I 32-07 _ (3) Obio River Flow cf/sec 1 1-131 3-09 O 1-133 _ IE208 . Divide Block (2) by Block (3). dm atiply by D 1-135 I _ f 3-4O 223E-3. Enter the result in Block (4)

I Cs-134 _ tEMS a N Ca-137 I - 2207 2_ = (4' D)F -

E BaA-140 _ I fE-08 - Multiply Block (I) by Block (4) the S Ce-141 _ 3E07 . enter he result in Block (5)

Cc-144 I 0E400 =

W-17 _ 2E207 a (5) R ofEPA Unit -

H-3 _ 2E.05 .

Fe-55 I 2E426 a Note 1: IF Bock (5) kI> 12,THEN

Sr49 22-O imlent the PAG per EPPIIP 4.1.

Sr-90 _I -9 _

Note 2 EF mre than onerelee is ongoing,

- Gr Beta-Gazmm I_ 93-11 THEN alculate a Block () for each release. Sum di Block (5)shr Stun Total (Umifted Fraction of liit) . (I) eachelese. IF The aumeeeds 12.

THEN Inplement die FAG per EPPIP 41.

Use te lest appropriate copnosite sanle analysis.

Use oIly if otopic ample analysis kn ot available () Sum EPA-MPC 2. No PAG Calculatios BF Date: _ sO

() SumEPA-MPC>12, No PAG R-r.CV1CWCQ Joy; , Date ea -hs

Beaver Valley Power Station N EPP-PN-2.7 itl. Unit Leve Of Use:

1/2 IGeneral Sillfeer LIQUD RELEASE MATE Revision: PagpNumb.

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ATACH]MENT C I UNIT EPA-MWC CALCULATION (SAMPLE METi~HOD): PAG DETERMINATION Page 2 of 2 I Lid Release Estide Unk 1: EPA - MPC Cakulao (San Mediod) CALCUlAIONS (ItlLA5715F1 2.7-3R 11199 94 ,

4

1. Obtain an isotopic sample from the source or from th Midland Water Treatment Plant intake.

2. Enter the nuclde concentrations (uCihml) or gross bagamma concentrations (uCihmi) in the Column A.

3. Divide the nuclide concentration (uCiml) in Column A by te EPA-MPC limit (uC/mI) in Column B. Enter the results in Column C (Praction of limit). (:

3.1, Note that the EPA-MPC Limit Values are fm the Interim Drinking Water Regulations (EPA-S70/9-76-003), and from DLC Calculation Package No. ERS-DKY-82-022.

4. Sum the Fraction of EPA-MPC Limit values. Enter the Undiluted Fraction of EPA-M Limit total in Block (1).

S. IF the sample was taken from the Midland Water Treatment Plant intake, THEN ee 1.0 in Block (4) and proceed t6 Step 9.

6. Determine the Release Rate (gpm), by one of the following methods, and enter the value in Block (2).

( For a sampletafom a tank or piping; Ree Rat gpm= Discharge Rate from tank or piping.

) or a sample taken from the Cl Blowdown; Release Rate

gpm

Cl Blowdown Flowrate. -i

() For a sample taken from the Catch Basin; Release Rate gpm a Catch Basin Flowrate.

7. Determine the Ohio River Flowrate (cuftsec) by one of the following methods, and enter the value in Block (3).

PRD9{ARY MIO

() Call the National Weather Service - 412-262-1882 or 412-262-1984 and request the following-iI

() ___cut/sec

Ohio River Flowrate at the Montgomery Dam.

BACKUPMFIHOD .tt

() Call the National Weather Service- 412-262-1882 or 412.262-1984 and request one of the following:

() __ cusec = Ohio River Flowrate at the Wheeling Dam'

() ftObioRiverStageHcightattheWheelingDaoctthe MontgomeryDamo.

Convert this value to_ _ _ cuflt/sec using the graph on Attachment A.

() Use one of the folowing approximations based on the average reported monthly Ohio River Flowates:

(53,000 cuft/sec

January (44,000 cuftsec = May 11.000 cufltsec - September 055,000 cuftsec

February 023.000 culsee - June 016,000 cuf/sec - October 077,000 cut/sec - March 01),000 cu/sec = July 02,000 cult/sec - November

)64,000 cuftsec - April 012000 cufl/see

August 043,000 cult/sec - December 0 Determin the Ohio River Flowrate By detemining the Stage Hight fotm one of the following onsite methods

) ft Ohio River Stage Hght a read from the Intake Sctu Convert this value to cuftsec using the graph on Attachment A.

0) _ ft = Ohio River Stage Height as read fom ILR-CW-101 (located in lntake Structure).

Convert this value to cultsec using the graph on Attachment A.

S. Determine the Dilution Factor by dividing the Release Rate (gpm) In Block (2) by the Ohio River Flowrate (gpm) in Block (3) and multiply by a conversion factor of 2.2E-3. Enter the result in Block (4). i

9. Determine the Diluted Fraction of EPA-MPC Limit By Multiplying the Undiluted Faction of EPA-MPC Limit in Block (1) by the Dilution Factor in Block (4). Enter the result in Block (5). (.

9.1 IPthe Diluted Fraction of EPA-MPC Limitfiom Block(S) is> 12,THN implement the PAG per EP/IP 4.1.

9.2 IF more than one release is ongoing, THEN calculate a Diluted Fraction of EPA-MPC limit as show in Bloc (), for each release. Sun the Block(S) freachrelease. Ithesumexceeds 12,THEN implement PAG pe EPP/I74.1.

. _ _ . t ~~~~~~~~~~~PedureNumber.

Beaver Valley Power rsStation

e Numb 2.

Title:

Unit Level Of Use:

1/2 General Skill Reference LIQUID RELEASE ESTIMATE Revision: 3e Number-ATTACHMENT D l UNIT 1 Page 1 of 2 UNIT 1 NRC-EC CALCULATION (PROCESS MONITOR METHOD): UNUSUAL EVENT AND ALERT DETERMINATION Uquid Release Esadnate Unit 1: NRC -EC Calculation (Process Monitor Metd) (RILAS.71S)

V7-4F 1111994 Uusual Event Determination .... (Otteria: 2 x SODCM Unit and release is > or -60 ninutes)

Ale Deterninaon ............... Ci a: > 200 x TSIODCM U~lnit, and rekase is > or a 15 minutes)

Release Start 0 hrs. Release Stop: 0 i, ReleaseT: minu Ak DETERMINATiON OF DULLTED FRACMN OFTSODCM LIMIT FOR VARIOUS PLANT SYSTEMS

1. Liquid Waste System Release (Criteria: Monitor Reading Exceeds Tbe HI H Alarm Setpoint) 1.1 Obtain the Release Rate for the appropriate pathway using one of the following methods:

() RM-ILW-116: Reease Rate = gpm; As read from FR-lLW-103. or

() RM-ILW-104:ReleaseRate- gpmAs readfrmFR-ILW-104 1.2 Obtain the Cooling Tower Blowdown Flowrate as follows:

UI/2 CIBD Flowrate gpm; As read from Fr-ICW-101-1 1.3 Determine the Dilution Factor as follows:

DF * (Release Rate - pn) (U12 ClED Flwrate - pm) _

IA Determine the Diluted Fraction of TS/ODCM Limit using one of the following methods:

() RM-ILW-116: frTSIODCM Limit-(DF_)x(MonRe ading- cpm) x(1.36E-3) * .,or

() RM-lLW-104: frTSIODCM Limit = (DF - ) x(Mon Reading ucpm) x (136E-3) =-

2. Reactor Plant River Water System Release (Criteria Monitor Reading Exceeds The HI HI Alarm Setpoint) 2.1 Determine the Release Rate for the appropriate pathway using one of the following inethods:

() RM-ILW-100: Release Rate = (9000 gpm per RPRWP) x ( RPRWP's) = gpn, or

() RM-ILW-101: ReleaseRate (9000 gpm per RPRWP) x ( RPRWP's) - - p or

() RM-lLW-100 ABCD: Release Rate = (2250 gpm per RPRWP) x ( RPRWP's) gpm S

Do not use if in a CIB Do not use unless IRM-RW-100 is INOPERABLE 2.2 Obtain the Cooling Tower Blowdown Flowrates as follows U1 CIBD Flowrate - gpm; As read fiom FT-ICW-101. and Ul2 CIBD Flowrate __ gpm; As read from Fl-ICW-10-1 2.3 Determine the Cooling Tower Recirculation Flowrates as follows:

CT Recirc Rate (127,000 gpm per Cll) x ( CIFs) - gpm

2. Determine the Dilution Factor as follows:

(Release Rate gpm) x (Ul CIBD 'lowrate _ gpm)

DF - -

CT Recirc Rate gpm) s (Ul/2 CIBD Flowrate - gpm) 2.5 Determine the Diluted Fraction of TSODCM Limit using one of the following methods:

() RM-IRW-100 frTSlODCMLinit(DF - )x(Mon Reading_ cpm)x(3.44E-04) = .or

() RM-IRW-l01: fr TISDCM imit =(DF _ ) x (Mon Reading ncpm) x (36E-3) _ , or

() RM-lRW-100 ABCD: fr TS/ODCM Umit . (DF .) x(Sum Mon Rds - ncpm) x(3.44E-4)- _

I I I iII r:i Beaver Valley Power Station LIQUID RELEASE ESTAATE r

u niL 1/2 EP-NP-2.7 vel Of Use General Skill Refer;n g u14 of 2R I

A ATACEN. D 0

Page 2 of 2 i

5 UNIT 1 NRC-EC CALCULATION (PROCESS MONITOR METHOD): UNUSUAL EVENT AND I ALERT DETERMINATION 3

II Lqud Release Estimate Unit 1: NRC - BC Caluatn (Procesa Monitr Metho(

i 2.7-4R I 11994 I

I

'-i

j A. DETERMINATION OP DllTED FRACrION OFTSIODCM LIMiT FOR VARIOUS PLANT SYSTEMS (Continued) z

3. Auxiliary Peed Pump Bay Drai System Release (Criteric Monitor Reading Exceeds The H Alarm Setpint) i A

i 3.1 Determine the Diluted fctiono a oET DCM Limit as follows:

RM-IDA-100: fr TSIODCM Limit (0.333 DP) x (Monitor Reading .npm) s (2.46E,4)

I i

i I

4 :i o

i B. DETERMINATION OF EVENT CLASSFICATMON

1. IF the Dilute Pratic of TSODCM Limit is > 2, and the release is > at 60 minutes, THEN declare an Unusual Evei i 2. IFthe Diuted raciof ThODCM Limit is> 200. and the release is> r*lS minutes, THEN declar a A-lest c

3. IF mor than one reease is ongoing, THEN calculate a Diluted raction ofTSODCM limit for each release.

Use the highest Fraction of TSODCM Limit value for event classification.

() No Emergency

() Unusual Event Emergency

( Alert Emergency Calculatiom By. Da a -bra; Reviewed By - _ Date: 0 - lrs.

(,

Procedure Number.

Beaver Valley Power Station EPPI2.7 rItle unit: Lvel Of Use:

l1/2 General Skill Reference LIQUID RELEASE ESTMATE Revision: Page Number:

._ __ _ _ ~ ~ 1~R 5 f 2R ATTACHMENTEE NT Page of 2 UNIT 1 EPA-MPC CALCULATION (PROCESS MONITOR METIOD): PAG DETERMNATION lIquid Relese Estimate Unit 1: EPA M Calulation MPoces Monitor Mcdod (RTLA5.715 2.7-5F11n994 PAG Determination .... (Criteria: > 12 a EPA - MPC Limit)

Relea Stort: _ a k, Release Stop: 0 hs, Rkea Tim: - minutes A. DETERMINATION OF OHIO RIVER FLOW RATE Determine the Ohio River Flowrate by one of the following methods:

PRIMARY METHO

() Call the National Weather Service -412-262-1882or 412-262-1984 and request the following.

() - cuf/sec a Ohio River Flowrate at the Montgomery Dam.

BACKUP METHOD

() Call the National Weather Service - 412-262-1882 or 412-262-1984 and request one of the following-() _ cutsec a Ohio River Flowrate at the Wheeling Dam.

( - ft - Ohio River Stage Height at the Wheeling Dam ( ) or the Montgomery Dam (.

Convert this value to cull/sec using the graph on Attachment A.

() Use one of the following approximations based on the average reported monthly Ohio River Flowrates:

053,000 cufttsec = January (44,000 cul/sec - May 1 1,000 cuftfsec = September 055,OO cuft/sec - February 023,000 cul/sec - June 016,000 cuftlsec = October 077,000 cufVsec

March 015,000 cuflsec = July () 28,000 cufsec = November 064,000 cull/sec - April (12,000 cllsec - August 043,000 cufi/sec = December

() Dtmine te Ohio River Fowat By detemining tbe Stage Heit fom one of the foowing osite methods.

() ft - Ohio River Stage Height as read from the Intake Strucum Convert this value to cul/sec using the graph on AItachment A.

ft Ohio Rivcr Stage Height as read fm IIR-CW-101 (loated In itake Structure).

Convert this value o cult/sec using the graph on Atachment A.

B. DETERMINATION OF DIllJED FRACTION OF EPA-MPC LIMIT FOR VARIOUS PLANT SYSTEMS

1. Liquid Waste System Release (Criteria: Monitor Reading Exceeds The HI HI Alam Setpoint) 1.1 Obtain the Release Rate for the appropriate pathway using one of the following methods:

() RM-ILW-116: Release Rate- gpm; As read from FR-ILW-103,or 0 RM-ILW-104: Release Rate = gpm; As read from R-ILW-104 1.2 Determine the Dilution Factor as follows:

(Release Rate__ pm) x (2.23E-3)

DF- *

(Ohio River Flowrate cuft/sec) 1.3 Determine the Diluted Fraction of EPA-MPC Limit using one of the following methods:

0 RM-ILW-116: frEPA-MPCLimit-(DF _ )x(MonReading ncpm)x(1.95E+0)_ _ ,or 0 RM-ILW-104: fr EPA-MPC Limit (DF _ ) x (Mon Reading ncpm) x (1.95E+0) -

1 Number Beaver Valley Power Station jP Ttle: unit: Level Of Use:

1/2 Genral SII Referenci w LIQUID RELEASE ESTIMATE Revision: l Page Number j d

R I IAf9R I -

ATTACHMIENT E Page 2 of 2 l UNIT I UNIT 1 EPA-MPC CALCULATION (PROCESS MONITOR METIOD): PAG DETERMINATION IUquid Release Estimte)

Unit 1: EPA- MPC Caculaiom (Proces Monitr Metbod 2.7-5RI11/1994 B. DETERMINATION OPDILVTED FRACTION OF EPA-MPC LIMrr FOR VARIOUS PLANT SYSTEMS (Continued)

2. Reactor Plant River Water System Release (Criteia: Monitor Reading Exceeds The HI HI Alarm Setpoint) 2.1 Determine the Release Rate for the appropriate pathway using one of the following method:

() RM-IRW-OO: Release Rate a (9000 gpm per RPRWP) x ( RPRWP's) - gpn cr

() RM-IRW-101: Release Rate - (9000gpm per RPRWP) x ( RPRWPs) = gpm, or

" () RM-IRW-100 ABCDi Release Rate -(2250 gpm per RPRWP) s ( RPRWs) - - gpm

Do not use if in a CIB

Do not use unless IRM-RW.100 is INOPERABLE 2.2 Obtain the Cooling Tower Blowdown Flowratet as follows:

U1 CTBD Flowte gpm: As read fron Fl'-ICW-101. and 23 Determine the Cooling Tower Recirculation Flowrates as follows:

CT Recirc Rate - (27,000 gpm ICM x( CTPs')

gpm 2.4 Determine the Dilutin Factor as follows:

(Release Rate gpm) x (Ul CTBD Flowrate gpm) x (223E-3)

DF= -

CT Recit Rate gpm) x (Ohio River Flowrate cuft/sec) (1, 2S Determine the Diluted Fraction of TS/ODCMllimt using on of the foowing methods

() RM-IRW-100 ftTIODCMLimit*(DP _ )x(MonReading ncpm)T(7.929-1) . .or

() RM-IRW-101: firTSIODCM Undit- DP _ ) x (Mon Reading - ncpm) x (1.9SE+0) or

{) RM-IRW-IOOABCD-frTSIODC4E~mt-(DP _ )x(SumMonRdngs ncpm)x(7.92E-)-

3. Auxiliary Feed Pump Bay Drain System Rcl (Criterla Monitor Reading Exceeds Th HI HI Alarm Setpoint) 3.1 Determine the Diluted Factor as follows DP= (120 gpm Release Ratel x (2.23-31 -

(Ohio River Flowrate cufl/sec) 3.2 Determine the Diluted Faction ofTSODCM Umit as follows:

RM-IDA-100 fr TS/ODCM Limit (DP - . )x(Monitor Reading ncpm) x (1.02E+0)

C. DETERMINATION OF EVENT CLASSIFICATION I. IF the Diluted Fraction of EPA-MPC limit is > 12, THEN implement the Protective Action Guide (PAG) per EPP/IP 4.1.

2. IF more than one release is ongoing. THEN calculate a Diluted Fraction of EPA-MPC Unit for each release.

Sum the valuea for each release. IF the sum is > 12, THEN implement the PAG per EPPP4.1

() Sum EPA-MPC < 12, No PAG Required

() Sum EPA-MPC> 12, PAO Required (Implement PAG per P/IP4.1)

Calculations By: Date: *D h-Reviewed By. - Date: __ _ his.

~~~~~Procedure Nwniber:

Beaver Valley Power Station

PPd 2.7 Tile: Unit: Level Of Use:

1/2 General Skill Reference LIQUID RELEASE ESTIMATE Revision: Page Numbe ATTACHMENTF UNIT 1 Page 1 of 1 I I UNIT UNMONITORED LIQUID DISCHARGE PATHWAYS Uquid Relase Esdnue Unit 1: Utod lquid Discharge Parhways (RL AS.715L) 2174 1111994

1. Unmonitored Release Origin

1. This type of unmonitored discharge can occur in the outside yard area by means of abnormal leakage from a storage tank. The pathway for this type of discharge is over the yard area curbs, to the Catch Basin system, and then directly to the Ohio River.

Choose one of the following options:

(I)QS-TK-1: Refueling Water Storage Tank (RWST) Capacity = 452,000 gallons This tank is filled with borated water supplied by the Boric Acid Blender. The tank provides suction head for the Quench Spray Pumps during a CIM, and provides a return path for these pumps during normal operation. Since this water is used in the reactor cavity during refueling, it is highly contaminated.

() BR-TK-6A: Primary Grade Water Storage Tank Capacity = 75,000 gallons

()1BR-TK-6B: Primary Grade Water Storage Tank Capacity = 75,000 gallons These tanks receive processed water from the Boron Recovery System or the Water Treatment System. These tanks can contain low level particulate contaminants, but generally high levels of tritium

()ILW-TK-7A: Steam Generator Drain Tank Capacity = 34,500 gallons (I)LW-TK-7B: Steam Generator Drain Tank Capacity = 34,500 gallons These tanks generally receive processed water from the Liquid Waste System. The water in these tanks can contain low-to-high level particulate contaminants, and generally high levels of tritium.

() Other.

2. Unmonitored Release Calculations 2.1 Determine the amount of liquid released.

Liquid Released = gallons 2.2 Determine or estimate the duration of the release.

Release rime = minutes 23 Calculate the Release Rate as follows:

() Release Rate = (liquid Release - gal) I (Release Tune _ in) = gpm Enter this Release Rate in Block (2) of Attachment B, and Block (2) of Attachment C.

2.4 Determine or estimate the Dilution Rate for the release.

() Dilution Rate = - gpm Enter this Dilution Rate in Block (3) of Attachment B. IF the Dilution Flowrate is zero, or IF the Dilution Flowrate cannot be determined, THEN consider the Dilution Factor to be 1.0 and enter 1.0 in Block (4) of Attachment B.

Calculations By: Date: _ QD his.

Reviewed B: Date: __ e__ brs.

I Beaver Valley Power Station

_______________________ _______________________EPP-llP-2.7II PN umb1e Te Unit Lvel Of Use: -

1/2 RELEAaS Per'b Sldl Rvin I LIQUID RELEASE ESTIMATE Revision: nPagrN, g l~f? I t I I

I INTENTIONALLY BLANK

(:

Beaver Valley Power Station ureNur.

Title:

Unit: Level Of Use:

1/2 General Sill Reference LIQUID RELEASE ESTHAATE Revision: Page Number:

I F 19 Of ?

AITACHMENT G I UNIT 2 1 Page of 2 UNIT 2 NRC-EC CALCULATION (SAMPLE METHOD): UNUSUAL EVENT AND ALERT DELERMINATION Uquid Release Estimate Unit 2: NRC - EC Calculation (Sample Method) CALCULATIONS (RTL AS.71SFG) 2.7-7F 11l1994 Unusual Event Determination .... (Criteria: >2 x TS/ODCM Limit, and release is > or - 60 minutes)

Alert Determination ............... (Criteria: > 200 x TS/ODCM Umit, and release is > or = 15 minutes)

Sample Location: Sample Date: 0 brs Release Start 0 hrs, Release Stop: 0 brs, Release Tume: _ _ - minutes Cot A Col B Sample TSIODCM Limit Col C IF sample was taken from the outfall Nuclide Concentration 10 x NRC-EC (Col A I Col B)

I (uCin!)

t-I-(uCirOm

- I-..

Fraction of Lmit structure or cooling tower blowdown, Be-7 / 6E-03 - THEN enter 1.0 in Block (4) and cr-SI / SE43 determine Mn-54 I 3E-04 Block (S)

Fe-59 IE-04 -

Co-57 6E-04

_ Otherwise, do the following Co-58 _ 2E-04 Co-60 / 3E-05 . Enter liquid Waste Release Rate in I Ni-59 3E-03 =

Ni-63 I IE-03 = Block (2)

Zn-65 _ 5E-S -

ZdNb-95 I 2E-04 . (2) Release Rate = gpm Nb-97 _ 3E-03 _ Enter the Cooling Tower Blowdown in Mo-99 I 2E-04 . Block (3). as obtained fiom:

Tc-99m IE-02 - ()Fr-ICW-101-1 Ag-I lOn 6E-O . _ ( ) othen _

Sb-124 7E-05 _

Sb-125 / 3E-04 = (3) Dilution Rate = gpin 1-131 / IE05 -

1-133 I 7E-5 . Divide Block (2) by Block (3). then 1-135 I 3E-04 = enter the result in Block (4)

Cs-134 9E-06 -

Cs-137 / IE-05 - (4) DF -

Baa-140 8ES 05

Multiply Block (1) by Block (4), ihen Ce-141 I 3E-04 - ater the resuk in Block (S)

Ce-I" I 3H-OS =

W-197 3E-04 = (5) Fr of NRC Limit .___

H-3 1E-02 _ Note 1: IF Block (S) is > 2. and the Fe-55 I 1E-03 - release is > or -60 minutes, Sr-89 I SE-s - THEN declare an Unusual Sr-90 I 5E06 . Event Note 2: IF Block (5) is > 200, and the

- ur Beta-Gamma I IE-07 W release is > or -15 minutes, THEN declare an Alert.

Sum Total (Undiluted Fraction of limit) _ (1)

Note 3: IF more than one release is

Use the latest appropriate composite sample analysis. ongoing, ThIEN calculate a

- Use only if isotopic sample analysis is not available. Block (S) for each release.

Use the max Block (S) to Calculations By-. Date: I@ hrs. classify the event.

Reviewed By Date: O0 brs. () No Emergency

() Unusual Event Emergency OAertEmergency

'- i

. eI Beaver Valley Power Station EPI27 i

Tie. Unit: Level Of Use:

1/7 General Skill Reference.

LIQUID RELEASE ESTIMATE RIs Page Numba I

ATTACHMENT G l0- 2 Page 2 of 2 UNIT 2 NRC-EC CALCULATION (SAMPLE METHOD): UNUSUAL EVENT AND ALERT DEIERMNATION Liquid Rdease Estmate Unit 2: NRC - EC Calculation (Sample Method INSTRUCIONS (RTL A5.715FG) 2.7-7R 11/1994 i I. Obtain an isotopic sample from the soue (e.: the Liquid Waste Discharge Line) or from the Cooling Tower Blowdowit or fim the Emergency Outfall Structure.

1.1 IF the radioactivity is a result of a aking heat exchange, THEN obtain the sample from the Combined Cooling Tower Blowdowa or the Emergency Outfal Structure, as appropriate, However, IF the sample is obtained fiom the Service Water Systm, THEN consult EADP pesonnel for an appropriate Dilution Factor.

2. Enter the nuclide concentrations (uCiml), or gross beta-gamma concentrations (uCifml) in the appropriate column.

3. Divide the nuclide concentrations (uCifm) in Column A by the TS/ODCM limit (uCilml) in Column B. Enter the resuti in Column C (Fraction of limit).

3.1 Note that the TS/ODCM limit Valu are based on 10 times the NRC-BC concentradons isted in 10 CFR 20 Appendix B to 20.1001- 20.2401,Table 2 CoL 2.

4. Sum the Fraction of SODCM limit values. Enter the Undiluted Fraction of TSIODCM limit toal in Block (1).

S. IF the sample was taken from the outfall structures, the cooling tower blowdown or the Catch Basin System, THE enter 1.0 in Block (4) and proceed to Step 9.

6 IP the sample was taken from the Liquid Waste System, THEN obtain the Release Rate (gpm) for the appropriate pathwa. Enter the value in Block (2).

7. Obtain the combined Cooling Tower Blowdown Flowrate fron FT-ICW-lO1-1 (gpm), or obtain any other applicable Dilutio Flowrate (gpm). Enter the appropriate value in Block (3).

L. Determine the Dilution Factor by dividing the Release Rate (gpm) in Block (2) by the Dilution Rate (gpm) in Block (3). Enter the result in Block (4).

9. Determine the Diluted Fraction ofTS/ODCM Limit By Multiplying the Undiluted Fraction of TS/ODCM Limit in Block (I) by the Dilution Factor in Block (4). Enter the result in Block (S).

9.1 IF the Diluted Fraction of TS/ODCM lit from Block (S) is >2, and the release is > or 60 minute THEN declare an Unusual EvenL 9.2 IF the Diluted Fraction of TSODCM Limit from Block (5) is >200, and the release is > or - IS minutes, THEN declare an Alert 9.3 IF more than one release is ongoing THEN calculate a Diluted F tion of 1 DCM Limit, as shown in Block (5), for each release. Use the highest Block (S) valuc for event classification.

Procedure Number:

Beaver Valley Power Station EPP-IP-2.7 Title Unit Level Of Use:

__1/2 General Skill Reference LIQUD RELEASE ESTIMATE Revision: Page Number ATTACHMENT H Page 1 of 2 UNIT 2 EPA-MPC CALCULATION (SANTPLE METHOD): PAG DETERINATION liquid Release Esdmate Unit 2: EPA PC Calculation (Sample Method) CALCULATIONS (RTL A5.71SFH)

PAG Determination ........... (Criteria: > 12 x EPA - MPC Limit) 2.7-SF 11/1994 Sample Location: Sample Date: 0 brs Release Start: hr, Release Stop: @. br, Releaserime: -minutes Col A Col B Sample EPA-MPC Limit Col C IF sample was taken from the Midland Nuclide Concentration EPA-570 (Col A/ Col B) Water Treatment Plant Intake, THEN (ui/ml) (uCitW) fraction of Limit enter 1.0 in Block (4) and determine Block (S)

Be-7 / 6E-06 Cr-Sl 6E-06 = Otherwise, do the following-Mn-54 / 3E-07 Fe-59 2E-07 =

Co-S7 IE-06 =

Co-5S8 3E-07 =

CO-60 IE-07 Enter Liquid Waste Release Rate in Ni-S9 / 3E-07 =

Ni-63 / SE-08 a Block (2)

Zn-65 / 3E-07 -

ZdNb-95 / 2E-07 _ (2) Release Rate = gpm Nb-97 3E-06 = Enter Ohio River Flowrate in Block (3)

Mo-99 / 6E-07 = (See INSTRUCIIONS)

Tc-99m / 2E-05 _ () table value for month of A- 10m / 9E-08 = Ooth:

Sb-124 I 6E-08 _

Sb-125 I 3E-07 . (3) Ohio River Fow =i caft/sec 1-131 / 3E-09 =

1-133 /IE-0S . Divide Block (2) by Block (3). then 1-135 / 3E-OS = Multiply by 2.23E-3. Enter the result Cs-134 / SE-08 = in Block (4)

Cs-137 2E-07 = (4) DF -

BatlA-140 / 6E-08 - Multiply Block (I) by Block (4), then Ce-141 / 3E-07 - enter the result in Block (S)

Cc-144 / OE-00 W-187 2E-07 (5) Fr of EPA lmit H-3 _ T 2E-05 =

Fc-55 _ 2E-06 _ Note 1: IF Block (5) is> 12, THEN Sr-89 / 2E-0S implement the PAO per EPP/IP Sr-90 I SE-09 _ 4.1.

Or Beta-Gamma / 9E-l1 Note 2 IF more than one release is ongoing, THEN calculate a Sum Total (Undiluted Fraction of Limit) m (1) Block (S) for each release. Sum the Block (5)'s for each release.

IF the sumexceeds 12, THEN

Use the latest appropriate composite sample analysis.

- Use only if isotopic sample analysis is not available. implement the PAG per EPPAP 4.1.

Calculations By. Date:

()Sum EPA - MPC <12,

@* hrs. No PAG Required Reviewed By- Date:

brs. ()Sum EPA - MPC >12, PAG Required per EPPAP4.1.

I I.,

Beaver Valley Power Station EPP-IP-2.7 -

I Tift: Unit: Leve Of Use:r 1/2 Gcneral Sll Re LIQUID RELEASE ESTIMATE pag. ., _

ATTACHMIENT H Page 2 of 2 UNIT 2 EPA-WPC CALCULATION (SAMPLE METHOD): PAG DETERMINATION Liquid Release Estimate Unit 2: EPA - PC Calcuhtion (Sample Method) INSTRUCIIONS., (R1T AS.715FH) 2.7-8R 11/1994

1. Obtain an isotopic sample mm the source or form the Midland Water Treatment Plant Intaker

2. Enter the nuclide concentrations (uCiml), or g beta-gamn concentrations (uCimi) in the Column A.

3. Divide the nuclide concentrations (uCilml) in Column A by the EPA-MPC Limit (uCihnl) in Column B. Enter the results in Column C (Fraction of Limit).

3.1 Note that the EPA-MPC Limit Values are from the Interim Drinking Water Regulations (EPA-570/9-76-W003), and from DLC Calculation Package No. ERS-DKY-824022.

4. Sum the Fracdon of EPA-MPC Limit valuae. Enter the Undiluted Fracdon ofEPA-MPC I mit total in Block (1).

5. IF e sample was taken fimn die Midland Water Treatment Plant intake THEN enter 1.0 in Block (4) and proceed to Step 9.

6. Determine the Release Rate (gpm) by one of the following methods, and enter the result in Block (2).

0Fcr a sample taken from a tank cr piping; Release Rate - gpm

Discharge Rate fom tank or piping.

()Pr a sample taken from the Cr Blowdown; Release Rate

gpm - CT Blowdown Flowate.

0 Par a sample take lrom the Catch Basin; Relase Rate-- gpm

Catch Basi Flowrate.

7 Detcrmine the Ohio River Flowrate (cuf/sec) by one of the following methods, and enter the result in Block (3).

0 Call the National Weather Service - 412-262-1882 or 412-262-1984 and request one of the following.

() cuftsec - Ohio River Plowrate at the Wheeling Dam ( ) ar the Montgomery Dam 0.

ft Ohio River Stage Height at theWheeling Dam ()or the Montgomery Damt)

Convert this value to cufltsec using the graph on Attachment A.

( Use one of the following approximations based os the average reported monthly Ohio River Flowiates 053000 culsec - January 044000 cutsec *May 11.000 cultfsec

September (55000 cult/sec - Februazy 0 23000 cuft/sec

June 016,000 cuf/sec

October 077,000 cuft/sec

March () 15,000 cult/sec

July 028,000 cuitsec = November (64000 cuft/sec April ()1Z000cuft/secuAugust .43000 cuft/sec . December 0 Determine the Ohio River Flowrate by determining the Stage Height fim one of the following onsite methods.

0() ___ft Ohio River Stage Height as read from the Intake Structur Convert this value to culsec using th graph on Attachment A.

() __ft

Ohio River Stage Height as read from ILR-CW-101 (located in Intake Structure).

Convert this value to cultfsec using te graph on Attachment A.

8. Determine the Dilution Factor by dividing the Release Rate (gpm) in Block (2) by the Ohio River Flowrate (gpm) in Block (3) and multiply by a conversion factor of 2.23B-3. Enter the result in Block (4).

9. Determine the Diluted Fraction of EPA-MPC Limit By Multiplying the Undiluted Fraction of EPA-MPC Limit in Block (1) by the Dilution Factor in Block (4). Enter the result in Block(S).

9.1 IFthe Diluted Fracti of EPA-MPC Limit from Block(5) is >12 THEN implement the PAG per EPP/AP4.1.

9.2 lFmore than one rclease is ongoing. THEN calculate a Diluted Fraction of EPA-MPC Limit as show. i Block(S), fa each release. Sum the Block (5)s for each release. IF the sum exceeds 12.THEN implement PAO per EPP/IP 4.1 1

Beaver Valley Power Station urNumP 27

Title:

Unit Level Of Use:

1/2 General Skill Reference LIQUID RELEASE ESTIMATE Reioof: Page Number:

ATTACHM1ENT I UI Page 1 of 2 UNIT 2 NRC-EC CALCUILATION (PROCESS MONrrOR METHOD): UNUSUAL EVENT AND ALERT DEIERMINATION Liquid Release Estimate Unit 2: NRC - EC Calculation (Process Monitor Method) (RTL AS.715F3) 2.7-9P 11/1994 Unusual Event Determinatin.... (Criteria: >2 x TSIODCM Limit, mnd release Is > or = 60 minutes)

Alert Determination ............... (Criteria: > 200 x TS/ODCM Limit, and release is > or - 15 minutes)

Release Start_ _brs, Release Stop: @ brs, Release Time: nminutes A. DETERMINA1ON OF DILUTED FRACllON OF TS/ODCM LIMIT FOR VARIOUS PLANT SYSTEMS

1. Liquid Waste System Release (Criteria Monitor Reading Exceeds the HI HIl Alarm Setpoint) 1.1 Obtain the Release Rate using the following method.

2SOC-RQI00: Release Re - gm; As read from 2SOC-HIC100 1.2 Obtain the Cooling Tower Blowdown Flowrate as follows:

Ul/2 CTBD Flowrate =- gpnn; As read from Fl-ICW-101-1 1.3 Determine the Dilution Factor as followm:

DF= (Release Rate - gpm) l (U112 ClBD Flowrate pi) =-

1.4 Determine the Diluted Fraction of TSIODCM Limit as follows::

2SGC-RQIOO fr TSODCM Limit a (DF .) x (Mon Reading net uCilcc) x (2.90E+5) -

2. Recirculation Spray System Release (Criteria: In a C3. and Monitor Reading Exceeds The High Alarm Setpoint) 2.1 Determine the Dilution Factor (VIA Emergency Outfall Structure) using one of the following methods:

(DF - O.4 (For one SWSP in operation)

(DF - 0.22 (For two SWSPs in operation) 2.2 Determine the Diluted Fraction of TSODCM Limit as follows:

2SWS-RQ1OO ABCD: fr TSIODCM - (DF _) x (Sum Mon Rdngs - net Ci/cc) x (3.04E+4) * -

Beaver Valley Power Station

____ __ __ _____ _ __ ___ __ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ P-2 .7_ PP-

_he Unit Level Of Use: de 1QU2 GeRrEal SdlRe LIQUID RELEASE ESTIMATE - Revision: _ u 74be .

ATIACHMENT I Page 2 of 2 2 UNIT 2 NRC-EC CALCULATION (PROCESS MONITOR METHOD): UNUSUAII EVENT AND ALERT DETERMINATION liquid Release Estimate Unit 2: NRC - BC Calculation (process Monitor Method) (IlL AS.7 :F7) 2.7-9R 11/1994 A. DETERMINATION OF DIUTED FRACTION OF TS/ODCM LIMT FOR VARIOUS PLANT SYSTEMS (Continued)

3. Component Cooling I Service Water System Release (Criteria: Monitor Reading Exceeds The Eigh AlaUm Setpoint) 3.1 Determine the Release Rate using one of the following metodws:

(2SWS-RQ101: Release Rate = (1900 gpm per SWSP) x ( SWSts)

gpm. or

()2SWS-RQ102: ReleaseRatea(1900 gpmper SWSP) x SWSs. gpm 3.2 Obtain the Cooling Tower Slowdown Flowrate as folows:

U2 CBD Flowrate - gpm As read from 2CWS-.F1101, and Ul2 CIBD Flowrat - gpm; As read from FI1CW-101-1 33 Determine the Cooling Tower Recirculation Flowrate as follows:

CT Recie Rate - (127,000 gpm per CIT) x t ClPs)

gpm 3.4 Determine the Dilution Factor (VIA Ufl Ouf Structe) as follows:

(Release Rate gpm) x (U2 CIBD Flowrate gpm) y DF _ ____

(CF Recirc Rate gpm) x (U2 C18D Flowrate gpm) 3.5 Determin the Diluted 1Fctdoe of TSIODCM limit (VIA UI/2 Outfal Structure) using on of the following:

(2SWS-RQ101: OS fr TSIODCM - (DF ) x(Mon Reading net uCi/cc) x (2.72E+4) * . or o 2SWS-RQ102: OS ft TSJODCM - (DP ) x (Mon Reading .net u~fcc) x (2.72B+4) -

3.6 Determine the Diluted Faction ofSCI0DCM Limit (VIA Emergency Outfal Structure) using one of the following:

()2SWS-RQ101: EOS frTSIODCM * (0.86 D) x (Mon Reading net uCicc) x (2.72E+4) = or

()2SWS-RQ102 BOS fr TSODCM - (0.86 DP) (Mon Reading --- net uCi/cc) x (2.72E+4) =

3.7 Record the maximum diluted Fracti of TS1ODCM limit (Fom Step A.33 or A.3.6)

B. DTERMNTION OP EVENT LASSIFICATION

1. IF the Diluted Fraction of WS/0DCM Limit is > 2, and the release Is > or

60 minutes, THEN declare an Unusual Event 2 IF the Diluted Fractdon of TSIODCM Limit is > 200, and the release is > or - 1 minutes, THEN declare an Alert.

3. IF mor thaD one release is ongoing. TH calculate a Diluted Fraction of TSODCM Limit for each release. Use the highest acdon of TSIODCM Limit value for event classification.

()No Emergency

()Unusual Event Emaergency

()Alert Emergency Calculations By Date a _ b Reviewed By Datc brs.

Beaver Valley Power Station EPP-IP-2 7

'ride: Unit Level Of Use:

1/2 General Skill Reference LIQIJD RELEASELIQUIDRELEAS ESTIMATE ESTIMTE I Revision:

8 Page Number 215 Of 2 AITACHMENT J l NT 2 Page 1 of 2 UNIT 2 EPA-MPC CALCULATION (PROCESS MONITOR METHOD): PAG DETERMINATION liquid Release Estimate Unit 2. EPA - MPC Calculation (Process Monitor Method) (RTL AS.71S51K) 2.7-lOPI11/1994 PAO Determination ........... (Criteria: > 12 x EPA - MPC Limit)

Release Start: @ hrs, Release Stop: @ hrs, Release Time: _ minutes A. DETERMINATON OF OHIO RIVER FLOW RATE

1. Determine the Ohio River Flowratc by one of the following methods:

PRIMARY MElhQr

() Call the National Weather Service-412-262-1882 or 412-262-1984 and request the following.

() ___cufttsec - Ohio River Flowrate at the Montgomery Dam.

BACKUIPMIO

() Call the National Weather Service - 412-262-1882 or 412-262-1984 and request one of the following.

( cufttsec a Ohio River Flowrate at the Wheeling Dam.

() _ ft Ohio River Stage Heit at the Wheeling Dam ( ) or the Montgomery Dam (.

Convert this value to cufttsec using the graph on Attachment A.

) Use one of the following approximations based on the aveage reported monthly Ohio River Flowrates.

(53,000 cuft/sec - January (44,000 cufttsec = May 1 1,000 cufttsec - September 0 5,000 culsec Febtruary 0 23,000 cuft/sec - June (16,000 cuft/sec

October 077,000 cuftsec March 0 15,000 cufttsec July (28,000 cuftsec November 064,000 cuftisec April 012,000 cuft/sec = August 043,000 caft/sec

December 0 Determine the Ohio River Flowrate by determining the Stage Height from one of the following onsite methods.

0) __ft Obio River Stage Height as read from the Intake Structure.

Convert this value to cuft/sec using the graph on Attachment A.

0 - ft = Ohio River Stage Height as read from ILR-CW-101 (located in Intake Structure).

Convert this value to - cufttsec using the graph on Attachment A.

B. DRMINATION OF DIUTIED FRACTION OF EPA-MPC LIMIT FOR VARIOUS PLANT SYSTEMS

. Liquid Waste System Release (Criteria: Monitor Reading Exceeds he High Alarm Setpoint) 1.1 Obtain the Release Rate using the following method 2SGC-RQ100: Release Rate - gpm; As read from 2SGC-HIC100 1.2 Determine the Dilution Factor as follows:

DF - ((Release Rate - gpm) x (2.23E-3)) 1 Ohio River Flowrate cufitsec) -

1.3 Determine the Diluted Fraction of EPA-MPC Limit using the following method:

2SGC-RQ100: fr EPA-MPC Limit - (DF -) x (Mon Reading net uCi/cc) x (2.76E+B) =

2. Recirculation Spray System Release (Criteria: In a CIB, and Monitor Reading Exceeds The High Alarm Setpoint) 2.1 Determine the Dilution Factor (VIA Emergency Outfall Structure) as follows::

DF* (6000 gpm Release Rate) x (2.23E-3) I (Ohio River Flowrate cuittsec) -

2.2 Determine the Diluted Fraction of EPA-MPC Limit as follows::

2SWS-RQI00 ABCD: fr EPA-MPC - (DF ) x (Sum Mon Rdngs net uCi/cc) x (.01 E+7) = _

Procedure Nunber.

Beaver Valley Power Station EPP IP2.7

Title:

Unit Lavel Of Use:

112 General Skill Reference LIQUID RELEASE ESTIMATE Revistom pageub.

AlTACHMENT J NIT 2 Page 2 of 2 2 UNIT 2 EPA-UPC CALCULATION (PROCESS MONITOR METHOD): PAG DETERMINATION liquid Release Estimat Unit 2: EPA-MPC Calculatiom (Process Monitor Meaod) (tTL A5.715FK) 2.7-lOR 11/1994 B. DETERMINATION OF DLUTED FRACTION OF EPA-MFC LIMIr IR VARIOUS PLANT SYSIEMS (Contnued)

3. Component Cooling / Service Water System Release (Criteria: Monitor Reading Exceeds The Higb Alarm Setpoint) 3.1 Detrmine the U112 Outfall Structure (Ul/2 OS), and the EOS Release Rates using the following methods:

(2SWS-RQ101: Ul/2 OS Reease Rate * (1900 gpm per SWSP x (SWSPrs) gpm, or

()2SWS-RQ102 Ul/20S ReleaseRate-(l900gpmperSWSP)x t SWSPs)- gpm AND,

()2SWS-RQ101: Ul2 EOS Release Rate - (36S0 gpm per SWSP) x

SWSP's)

gpm or

()2SWS-RQ102 UI/2 BOS Release Rate a (3650 gpm per SWSP)x t SWSP's) * - gpm 3.2 Obtain the Cooling Tower Blowdown Flowrat as follows:

U2 CTBD Flowrate - gpm; As read from 2CWS-FFl01 3.3 Determine the Cooling Tower Recirculation flowate as follows:

CT Recirc Rate - (127,000 gpml CTP) x L CTPs) - gpm 3.4 Determine the Dilution Factors(A U2 Out Structure and VIA BOS) as follows:

(U/2 OS Release Rate gpm) x (U2 CTBD Plowrate gpm) x (2.23S-3)

UlZOSDF* -

(CT Recrc Rate

gpm) x (Ohio River Flowrate - cuff/sec)

(EOS Release Rate gpm) x (2.23B-3)

EOS DP-_

(Ohio River Flowrate

cufVscc) 3.5 Determine the Diluted rac of EPA-MPC (VIA U112 OS and VIA OS) as folows:

()2SWS-RQ101: UI/2 OS EPA-MPC - (Ul/2 OS DP _) x (Mon Rd8 _..et uCilcc) x (9.17EF7) - or

()2SWS-RQ102 Umt2 OS EPA-MPC * (U112 OS DF ) x (Man Rdg .net uCicc) x (9.17B+7) -

AND,.

()2SWSRQ101: EOS ft EPA-MPC - (BOSDP )(Mon Rdg -- net uCilcc) x (9.17E+7) - or (2SWS-RQ102: BOS fi EPA-MPC - (EOS DF ) x (Mon Rdg net uCi/cc) x (9.17E47) -

3.6 Record the Total Diluted Fraction of EPA-MPC Lmit (Sum the valuesfrom Step B.3.5)

C. DETERMINATION OF EVENT CLASSIFICATION

1. DPthe Diluted Fraction of EPA-MPC limit is > 12, THEN implemet the Protective Action Guide (PAG) per EPP/IP 4.1.

I

2. IF more than one reease is ongoing. T cakulate a Diluted Fracdon of EPA-MPC Ljmit for eacb releasc Sum the valua fr achlse. IFthsumis>12.THENimplementthePAGpEPP/IP4.1.

()Sum EPA-MPC < 12, No PAG Required

()Sam EPA-MPC > 12, PAG Required (Implement PAO per EPPIIP 4.1)

Calculations By. Date _ __ hr.

Reviewed By: Date: _ _ _ _ has.

Beaver Valley Power Station roeuePP P-2.7 Tile: Unit: Level Of Use:

1/2 General Skill Reference LIQUID RELEASE ESTIMATE Revision: Page Number.

A1TACHMENT K Page 1 of 1 L~iZJ UNIT 2 UNMONITORED LIQJID DISCHARGE PATHWAYS lUquid Release Estimate Unit 2: Unmonitored liquid Discharge Pathways (RTL A.715FL) 2.7-11 1111994 1 Unmottitored Release Origin

1. is type of unmonitored discharge can occur n the outside yard area by means of abnormal leakage from a storage tank. e pathway for this type of discharge is over the yard ea curbs, to the Catch Basin system, and then directly to the Ohio River. Choose one of the following options:

()2QSS-TK21: Refueling Water Storage Tank (RWS7) Capacity = 850,000 gallons This tank is filled with borated water supplied by the Boric Acid Blender. The tank provides suction head for the Quench Spray Pumps during a CM, and provides a return path for these pumps during normal operation. Since this water is used in the reactor cavity during refueling, it is highly contaninated.

()Other

2. Unmonitored Release Calculations 2.1 Determine the amount of liquid released.

liquid Released* gallons 2.2 Determine or estimate the duration of the release.

Release Time

_ __ minutes 23 Calculate the Release Rate as follows:

() Release Rate * (iquid Release gal) /(Release l1me min) - gpm Enter this Release Rate in Block (2) of Attachment 0. and Block (2) of Attachment H.

2.4 Determine or estimate the Dilution Rate for the release.

() Dilution Rate

gpm Enter this Dilution Rate in Block (3) of Attachment U. IF the Dilution Flowrate is zero, or IF the Dilution Fowrate cannot be determined, THEN consider the Dilution Factortobe . and enter 1.0 in Block (4) of Attament G.

Calculations By Date: 0 hrs.

Reviewed By Date: 0 hrs.

I t Procedur Numnbw Beaver Valley Power Station _____________ wt' ntle:~~~~~~~~~~~~~~~~~~Unit: LcveOf UseM 1 /2 Geneal Skill Refreio, 0 6.0 PRECAUTONS AND LMITATIONS ....... 2 6.1 Precautions .................................. 2 6.2 Iimitations .................................. 2 7.0 PREREQUISES .................................. 2 8.0 PROCEDUIRE ................................................................................................................................... 2 8.1 Contamination Control .................................. 2 8.2 Decontamination.....................................................................................................................4 8.3 Final Conditions......................................................................................................................5

Beaver Valley Power Station I Nu.ber.

~~~~~~~~~~~~~~~~~~EPP-IP rtile: Unit velOf Use:

1/2 General Skill Reference EMERGENCY CONTAMINATION CONTROL Revision: dag Nuber 1.0 PURPOSE 1.1 This procedure provides general instructions to the TSC staff to supplement the guidance contained in the Health Physics Manual (HPM) and/or the Radiation Protection Procedures.

2.0 SCOPE 2.1 None

3.0 REFERENCES
AND COMMITMENTS 3.1 References 3.1.1 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.
3.1.2 Beaver Valley Power Station Radiation Protection Procedures.
3.1.3 Title 10 Code of Federal Regulations Part 20 and Part 50.
3.1.4 NCRP Report No. 65, "Management of Persons Accidentally Contaminated with Radionuclides".
3.1.5 ICRP Publication 28, "The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers".
3.1.6 NUREG-0654IFEMA-REP-1 "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."
3.1.7 BVPS Operations Manual, Chapter 56A 3.2 Commitments 3.2.1 None 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 None 4.2 Forms 4.2.1 None
1I Beaver Valley Power Station E Pru Num 33 I; Unflc it Lcvd Of Use:
12 General SIldi Reference EMERGENCY CONTAMINATION CONTROL . Revision: A e 5.0 RESPONSIBILITIES 5.1 Radiological Controls Coordinator:
5.1.1 Is responsible to implement this procedure when necessary.
6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions 6.1.1 The Beaver Valley Power Station Radiation Protection procedures contain provisions governing the control of contamination. The requirements and guidelines of these documents shall apply to contamination control during emergency conditions except as specifically provided in this EPP/IP, the BVPS Emergency Preparedness Plan, and/or by direction of the Radiological Controls Coordinator/Emergency Director.
6.1.2 Most cases of skin contamination with radioactive materials can be decontaminated using methods established in Radiation Protection procedures. Since the annual SDE-WB limit for the skin is 50 rem, skin decontamination efforts should never take precedence over necessary first aid. While not life threatening, discrete radioactive particles can rapidly (
cause skin doses in excess of limits. Personnel should remain alert for such particles when doing skin contamination surveys.
6.2 limitations 6.2.1 None 7.0 PREREOUISrTES 7.1 An emergency condition has been declared at the Beaver Valley Power Station as provided in the BVPS Emergency Preparedness Plan.
7.2 As a result of the emergency condition, measurable abnormal contamination levels are noted.
8.0 PROCEDURE l: l I
8.1 Contamination Control 8.1.1 It may become necessary to extend the boundaries of the Radiologically Restricted Area (RRA). Appropriate access control and associated contamination control measures shall be established for any area in which contamination exists at levels higher than specified for a non-contaminated area in the Radiation Protection procedures.
( 1, i I
Beaver Valley Power Station PF-d3NumP3 Tidle: unit: Lvel Of Use:
1/2 General SIll Reference EMERGENCY CONTAMINATION CONTROL Revision: Page Number:
1 14 f -
8.1.2 Personnel and equipment monitoring and release procedures and criteria shall remain in force to the extent possible. There may be exceptions applicable to emergency conditions, as follows:
8.1.2.1 If background dose rates at normal monitoring locations preclude detection of levels of contamination equivalent to the non-contaminated limit, monitoring shall be moved back to a location where this can be done. However, if significant levels of contamination exist, it may be appropriate to perform a gross screening at the exit of grossly contaminated area, to be followed by a more complete monitoring at a more suitable location.
8.1.2.2 If dose rates within the contaminated area (or Controlled Area) warrant an immediate evacuation, personnel monitoring shall not be required prior to evacuation. If possible, personnel exiting such areas should remove any clothing thought to be contaminated and/or don clean coveralls to minimize the spread of potential contamination, pending subsequent monitoring. In this case, appropriate monitoring should be performed at the designated assembly area.
8.1.2.3 Contamination limits for release of personnel, equipment, and areas specified in the Radiation Protection procedures shall remain in effect to the maximum extent possible. The Radiological Controls Coordinator will determine when a change in contamination limits is applicable and will establish appropriate revised limits.
However, under site evacuation conditions, decontamination is normally mandatory if the removable contamination exceeds 5000 dpm/lOOcm2.
8.1.3 The conditions under which a Site Evacuation would be initiated might involve significant releases with resultant contamination of environmental surfaces offsite.
Under these conditions, delaying Site Evacuation to monitor and/or decontaminate personnel or vehicles would be inconsistent with maintaining exposures as low as reasonably achievable, and may be superfluous in light of the potential for re-contamination offsite. The following procedures should be used:
8.1.3.1 Personnel should be directed to the upwind remote assembly area for monitoring (Western Power Delivery Division or Hookstown Grange). Rad Protection shall monitor personnel on the basis of a screening process to identify contaminants in excess of 5000 dpm/l0 cm2. Personnel monitoring should basically consist of checking hands, feet, and the face with an E140IHP210 or equivalent survey instrument.
8.1.3.1.1 Personnel identified as contaminated should be segregated to an area for eventual decontamination.
8.1.3.1.2 Documentation of the extent and magnitude of the individual's contamination will be performed after the initial segregation phase of the group monitoring.
Beaver Valley Power Station
________________________________________ JProcedu I Numba.
EPP-IP-3.3 fltle Unit Lzvel Of Use:
. General Sll Reference EMERGENCY CONTAMINATION CONTROL Revision: =3 U :
8.1.3.2 If the Remote Assembly Area is within sectors from which the population is being evacuated, the Emergency Director, in cooperation with FENOC management and State and county agencies shall designate an assembly area at which personnel monitoring will be performed. In this event, personnel and vehicles will be monitored the same as members of the general public as provided in the emergency plans of the affected jurisdictions.
8.1.4 In situations where there is potential for the imminent death of the victim and the magnitude of radiological conditions are generally known, rescue efforts take first priority.
8.1.4.1 An Emergency Squad member(s) should proceed to the scene without protective clothing to assess the situation and render first aid if personal safety permits.
8.1.4.2 Other Emergency Squad members should don appropriate clothing and proceed to the area to assist.
8.1.4.3 The initial Emergency Squad member providing assistance should leave the area and be monitored and/or decontaminated as soon as practical. -
8.1.5 For fire-fighting efforts, normal fire-fighting gear (helmets, coats, boots, gloves, etc.)
may take the place of protective clothing. This apparel will provide protection from contaminated water spray.
8.2 Decontamination 8.2.1 Personnel decontamination shall be performed as provided in the Radiation Protection procedures.
8.2.2 Contaminated/injured personnel should be decontaminated pior to transfer to the hospital, if possible, and if compatible with the extent of the injuries. Even a superficial initial decontamination to remove the loose contamination or the removal of outer clothes will help minimize the contamination of ambulances and hospital facilities and personnel. Refer to Operations Manual 56A and Radiation Protection procedures.
8.2.3 Most cases of skin contamination with radioactive materials can be decontaminated by Radiation Protection personnel using methods established in the Radiation Protection Procedures. Refer to 1/2-HPP-3.02.003, Decontamination Control. If the contamination has entered wounds or body openings, medical assistance should be sought. The urgency of such treatment will depend on the dose rate attributable to the contamination.
8.2.3.1 Since the annual SDE-WB limit for the skin is 50 rem, skin decontamination
, i1 efforts should never take precedence over necessary first aid. However an evaluation should be conducted under direction of the Radiation Protection staff to assess the consequence of the skin dose.
Beaver Valley Power Station Procedure Nume 33 MRitl: uit evel Of Use:
112 - - General Skill Reference EMERGENCY CONTAMINATION CONTROL Revision: Page Number-8.2.3.2 If skin contamination is the primary health hazard or if persistent contamination remains after decontamination efforts, Presbyterian - University Hospital should be contacted. The individual should be transferred to that facility for evaluation under their Radiation Emergency Response Program.
8.24 Decontamination of persons with significant internal contamination shall be referred to medical personnel at the Presbyterian-University Hospital and their Radiological Emergency Response Plan (RERP) program for evaluation and treatment. In the event of a significant uptake of radioiodine, potassium iodide may be administered in accordance with EPP/IP-3.4, "Emergency Respiratory Protection".
8.3 Final Conditions 8.3.1 The use of this procedure shall be terminated when monitoring results indicate contamination control is not necessary and all applicable documentation has been completed.
A5.735B Beaver Valley Power Station Unit 1/2 EPP-IP-5A EMERGENCY PERSONNEL MONITORING Document Owner Manager, Emergency Preparedness Revision Number 9 Level Of Use General Skill Reference Safety Related Procedure Yes CONTROLLED BVPS UNIT 3
- . Beaver Valley Power Station EPP-IP-5.4 rilde: Unit: Level Of Use:
1/2 General Skill Reference EMERGENCY PERSONNEL MONITORING Revision: Page Number:
- I 9 ~~~~~~~~~~~~~~~~~~
f i TABLE OF CONTENTS 1.0 PURPOSE ................................. 1 2.0 SCOPE ................................. 1
3.0 REFERENCES
AND COMMITMENTS.........................................................................................1 3.1 References ................................ 1 3.2 Commitments ................................. 1 4.0 RECORDS AND FORMS ................................. 1 4.1 Records ................................. 1 4.2 Forms ................................. 1 5.0 RESPONSIBILITIES ................................ 2 6.0 PRECAUTIONS AND LIMITATIONS ................................ .2 6.1 Precautions ... 2...............
6.2 Limitations ................................. 2 7.0 PREREQUISITES ... 2...............
8.0 PROCEDURE ................................. 3 8.1 Expanded Use of Personal Monitoring Devices .3 8.2 Accelerated Dosimeter Collection and Processing .4 8.3 Increased Bioassay Analyses .4 8.4 Post Accident Exposure Evaluation .5 8.5 Final Conditions .5
Beaver Valley Power Station I Procedure Number
. % Beaver Valley Power Statlon EPP-IP-5.4
Title:
Unit: Level Of Use:
1/2 General Skill Reference EMERGENCY PERSONNEL MONITORING Revision: Page Number:
9 1 of 6 1.0 PURPOSE 1.1 This procedure provides general guidance to the TSC staff, and in particular, the Radiological Controls Coordinator, for establishing personnel monitoring suitable for the radiological conditions observed or expected at the time of the accident. Three modifications/exemptions are addressed in this EPPAIP. The first is expanded use of personal monitoring devices. The second is accelerated collection and processing of personal monitoring devices. The third is increased bioassay analyses.
2.0 SCOPE 2.1 This procedure is used durng a declared emergency to establish appropriate actions for internal and external personnel radiation monitoring.
3.0 REFERENCES
AND COMMITMENTS 3.1 References 3.1.1 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.
3.1.2 Title 10, Code of Federal Regulations Part 20.
3.1.3 Regulatory Guide 8.9 Revision 1 "Interpretation of Bioassay Data".
3.1.4 Beaver Valley Power Station Health Physics Procedures.
3.1.5 NUREG-0654IFEMA-REP-1 "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."
3.1.6 Regulatory Guide 8.34 "Monitoring Criteria and Methods to Calculate Occupational Radiation Dose".
3.2 Commitments 3.2.1 None 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 None 4.2 Forms 4.2.1 None
Beaver Valley Power Station Poedure Numr 5 4 I
Title:
Unit: Level Of Use:
112 General Skill Referen EMERGENCY PERSONNEL MONITORING Revision; P Num 9 2 of, 6 5.0 RESPONSIBILITIES 5.1 Radiological Controls Coordinator 5.1.1 Is responsible for establishing personnel monitoring suitable for the radiological conditions observed or expected at the time of the accident.
6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions 6.1.1 The Beaver Valley Power Station Radiation Protection procedures contain standards for personnel monitoring, including bioassay requirements and dosimetry requirements for issuing, using, collecting and processing of dosimetry devices. The provisions of these documents shall apply to emergency conditions except as specifically provided in this EPP/IP or in the BVPS Emergency Preparedness Plan, or as provided by the Radiological Controls Coordinator.
6.1.2 During emergencies when there is a great demand for dosimetry, compounded by delays in processing and recording the exposures in the exposure record system (due to the large number of devices in use, and/or inaccessibility to dosimetry processing data systems, etc.), caution shall be exercised to ensure that the exposure recorded on the dosimetry is credited against the proper individual, and that all exposures are recorded.
6.1.3 To facilitate later evaluation of exposures, all dosimeter issue and processing documents should be marked with the date and time the document was completed or processed.
6.1.4 Personnel radiation doses, which exceed regulatory limits, shall be reported to the NRC in accordance with 10CFR20.2202 and 20.2203, as applicable.
6.2 Limitations 6.2.1 None 7.0 PREREOUISITES 7.1 An emergency condition has been declared at the Beaver Valley Power Station as provided in the BVPS Emergency Preparedness Plan.
7.2 As a result of the emergency condition, radiation and/or airborne radioactivity levels significantly higher than normal are observed or are likely to be encountered.
. ~~I
Beaver Valley Power Statin .Procedure Number
. Beaver Valy owerStation EPP-IP-5.4
Title:
Unit: Level Of Use:
1/2 General Skill Reference EMERGENCY PERSONNEL MONITORING Revision: Page Number:
9 '3of 6 8.0 PROCEDURE 8.1 Expanded Use of Personal Monitoring Devices 8.1.1 As a general rule, personnel remaining within the Controlled Area following a site evacuation should wear dosimetry at all times. Monitoring teams (onsite or offsite) shall wear their normal and high range dosimetry as required by Radiation Protection (RP)
Supervision.
8.1.2 Under non-emergency conditions, regulations require occupational exposure monitoring if it is likely that an external monitoring threshold will be exceeded. This practice should be maintained under emergency conditions. Monitoring thresholds are:
. 500 milliremlyear Deep Dose Equivalent (DDE)
. 1500 milliremlyear Eye Dose Equivalent (LDE)
. 5000 millirem/year Shallow Dose Equivalent - Whole Body (SDE-WB)
. 5000 milliremlyear Shallow Dose Equivalent - Extremity (SDE-ME) 8.1.3 Under emergency conditions, exposed individuals who are not normally issued dosimeters, shall be assigned appropriate dosimeters if it is likely that an external monitoring threshold will be exceeded, or if the radiological status of the area that they occupy is not known.
8.1.4 Any individual authorized to receive emergency exposure shall be assigned appropriate dosimeters.
8.1.5 Electronic alarming radiation dosimeters (EAD) should be issued if available. Indicating range of an assigned direct-reading dosimeter-pocket ion chamber (DRD) should be such that a 75% of full scale reading will not be exceeded given the expected stay time and known or expected exposure rate.
8.1.6 Extremity dosimeters and neutron dosimeters should be issued and worn as indicated in RP procedures.
8.1.7 Beta radiation may become a significant dose contributor in radiological emergencies.
For this reason, if any skin surface or the eyes are unshielded, the TLD front should be unshielded. If shielding is provided (e.g., respirator and full Anti-C clothing), the TLD should be worn within the shielding so that accurate eye and shallow dose equivalents can be assessed.
Beaver Valley Power Station ENuppIP 5.4
Title:
Unit: Level Of Use
. ~~~~~~~~~~~~~~~~1/2 General Skill Refeec EMERGENCY PERSONNEL MONITORING i Page Number 8.2 Accelerated Dosimeter Collection and Processing 8.2.1 1/2-ADM-1601 provides for TLD processing under non-emergency conditions. In addition:
8.2.1.1 Daily exposure tracking shall be performed during the emergency and, initially, during recovery operations until such time as exposure trends have been identified and normal access and exposure control methods have been reestablished. This shall be done for any Site Area or General Emergency that has resulted in the release of radioactivity to the Site, or to the environment.
8.2.1.2 In the event of an accidental exposure, or a planned emergency exposure, the TLD's of the individuals involved shall be processed as soon as practicable following exposure. Further exposure of these individuals should not be allowed until the results of their TLD badge reading are available and have been evaluated.
8.2.1.3 All assigned personal monitoring devices should be processed as soon as practical after a radiological emergency situation is recognized. This provides for updated dose history information and a basis for future dose limitation/authorization.
8.3 Increased Bioassay Analyses 8.3.1 1/2-ADM-1601 and 1/2-HPP-3.04.002 of the BVPS Radiation Protection procedures contains provisions for the bioassay program. In addition:
8.3.1.1 If whole body count results indicate significant fission products, such that Sr-89 or Sr-90 uptake is suspected, in-vitro bioassay measurements will be performed in addition to whole body counting. A preliminary screen level for above which urinalysis is indicated is 7OnCi of 1-131, if the Unit has been at power within 40 days prior to the accident. Arrangements have been made with offsite vendors for appropriate analyses if this screening level is exceeded. The Radiological Controls Coordinator will establish screening levels based on the actual airborne radioactivity mix following the accident, if the Unit has been shutdown longer than 40 days, or refine the preliminary screening level.
8.3.1.2 If a long-term recovery effort is necessary, periodic comparison of whole body counting and urinalyses/fecal analyses should be performed on a random sampling of radiation workers to establish the adequacy of the monitoring program. DAC-hour calculations could also be used in this evaluation. Urine and/or fecal analyses should include gamma scans, Sr-89, Sr-90 and Pu-241 determinations, titium determinations, and alpha determinations.
8.3.1.3 Special whole body counts (and urinalyses/fecal analyses, if indicated) should be performed in accordance with 1/2-ADM-1601. However, under emergency conditions, priority should be given to those individuals who have known or suspected intake, which exceeds 0.1 AU.
Procedure Number:
- Beaver Valley Power Station EPP-IP-5.4
Title:
Unit: Level Of Use:
1/2 General Skill Reference EMERGENCY PERSONNEL MONITORING Page Number 8.3.1.4 If the result of the bioassay analysis indicates that a given individual has an intake of radionuclide, or combinations of radionuclides, that exceeds 0.1 ALl, an investigation shall be performed and documented. Recounts or additional samples/analyses shall be performed to determine the validity of the result. If the result is valid, the following minimum additional actions should be taken:
. Restrict the access of the individual to prevent additional exposure until the nature of the intake can be determined.
. Arrange a schedule of additional analyses as necessary to support dose assessment.
. Evaluate, using suitable models and calculational methods, the Committed Effective Dose Equivalent (and Committed Dose Equivalent for the maximally exposed organ, if appropriate) from the intake. Document all assumptions and calculations.
8.4 Post Accident Exposure Evaluation 8.4.1 In those situations in which an individual has been contaminated and some persistent contamination has remained following decontamination; and/or the individual has received significant external or internal exposure in excess of 10 CFR 20 limits as indicated by bioassay, personal dosimeters or survey data, perform an evaluation of the individual's Total Effective Dose Equivalent and other appropriate dose quantities.
8.4.2 Rad Protection personnel, in conjunction with outside consultation (such as Presbyterian-University Hospital), shall perform this evaluation using accepted health physics dosimetry practices as outlined in guidance documents such as ICRP-30, ICRP-54, Federal Guidance Report No. 11 and the MIRD pamphlets. This evaluation will be documented, reviewed by the Plant Operations Review Committee (PORC), and filed in the individual's exposure record.
8.5 Final Conditions 8.5.1 This procedure shall be terminated when conditions at the Site have returned to normal or upon direction of the Radiation Controls Coordinator and/or Emergency Director.
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L-03-111, Emergency Preparedness Plan Implementing Procedures

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