ML17311A069

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Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A069
Person / Time
Site: Ginna Constellation icon.png
Issue date: 01/25/1999
From: Polfleit P
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17309A647 List:
References
NUDOCS 9902030331
Download: ML17311A069 (62)
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Text

CATEGORY 1 REGULA'~ RY INFORMATION DISTRIBUTIO SYSTEM (RIDS)

ACCESSION ~FryP902030331 DOC.DATE: 99/01/25 NOTARIZED: NO DOCKET FACIL:50%44->Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAMk AUTHOR AFF1LIAT1'ON POLFLETT,P.S.

Rochester Gas a Electric CorP. Pe.Vi/PJ g Q f RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.

C

SUBJECT:

Forwards revs to Ginna Station Emergency Plan Implementing Procedures (EPIPs).Previous rev had incorrect effective C

date.

A DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR ENCL SXZE:

TITLE: OR Submittal:

Emergency Preparedness

Plans, Implement'g Procedures, NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/HAGAN,D NRR/DRPM/PERB EXTERNAL: NOAC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME VISSING,G.

E CENTER 01 NRC PDR COPIES LTTR ENCL 1

1 2

2 1

1 1

1 D

U N

NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 9

ENCL 9

ti Eil/RiI 8$Ei$'

////////// ~ 'ill//8g

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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 FAST AVENUE, ROCHESTER, N.K 14649-0001 TELEPHONE AREA coDK 7ld 546.2700 January 25, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn:

Mr. Guy S. Vissing (Mail Stop 14D11)

Project Directorate I-1

Subject:

Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:

In accordance with 10 CFR 50.4(b)(5), enclosed are revisions to Ginna Station Emergency Plan Implementing Procedures (EPIPs).

We have determined, per the requirements of 10 CFR 50.54(q), that these procedure changes do not decrease the effectiveness ofour Nuclear Emergency Response Plan. The previous revision had an incorrect effective date.

Please destroy the previous revision and replace it with the enclosed copy.

Very trul yours, Peter S. Polfleit Corporate Nucl Emergency Planner Enclosures xc:

USNRC Region 1 (2 copies ofletter and 2 copies ofeach procedure)

Resident Inspector. Ginna Station (1 copy ofletter and 1 copy ofeach procedure)

RGkE Nuclear Safety and Licensing (1 copy ofletter)

Dr. Robert C. Mecredy (2 copies ofletter only)

PSP/jem

'P'P0203033i 9'POi25 PDR ADQCK 05000244

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PROCEDURE REVISIONNIJMBER E

P 1-5 I'PIP~

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ROCHESTER GAS 8 ELECTRIC CORPORATION GINNASTATION

~ Controlled Copy Number Procedure umber EPIP 1-5 Revisio Number 35

'OTIFICATIONS Resp si le Manager I l2 58 Effective te Catego 1.0 his procedure contains 23 pages

EPIP 1-5:1 EPIP 1-5 NOTIFICATIONS 1.0 PURPOSE The purpose of this procedure is to specify the means by which notifications are made to station personnel for all emergency action levels, to expedite the notification of selected RG&E personnel to augment the emergency response

. organization and notify offsite agencies.

2.0 RESPONSIBILITY 2.1 The Shift Supervisor, Emergency Coordinator or EOF/Recovery Manager is responsible for'making the decision to notify offsite agencies.

2.2 Ginna Station Control Room personnel are responsible for implementing this procedure.

2.3 Community Alert Network (CAN) is responsible for activating the onsite/offsite responders.

2.4 The Corporate Nuclear Emergency Planner is responsible for maintaining the station call lists up to date on a quarterly basis.

3.0 REFERENCES

3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.2 Implementing References 3.2.1 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.2 EPIP 2-1, Protective Action Recommendations (PARs) 3.2.3 0-9.3, NRC Immediate Notification 3.2.4 10 CFR 26, Fitness for Duty Programs 3.2.5 P-9, Radiation Monitoring System

EPIP 1-5 I

EPIP 1-5 NOTIFICATIONS 1.0 PURPOSE The purpose of this procedure is to specify the means by which notifications are made to station personnel for all emergency action levels, to expedite the notification of selected RGB E personnel to augment the emergency response organization and notify offsite agencies.

2.0 RESPONSIBILITY 2.1 The Shift Supervisor, Emergency Coordinator or EOF/Recovery Manager is responsible for making the decision to notify offsite agencies.

2.2 Ginna Station Control Room personnel are responsible for implementing this procedure.

2.3 Community Alert Network (CAN) is responsible for activating the onsite/offsite responders.

2.4 The Corporate Nuclear Emergency Planner is responsible for maintaining the station call lists up to date on a quarterly basis.

3.0 REFERENCES

3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.2 Implementing References 3.2.1 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.2 EPIP 2-1, Protective Action Recommendations (PARs) 3.2.3 0-9.3, NRC Immediate Notification 3.2.4 10 CFR 26, Fitness for Duty Programs 3.2.5 P-9, Radiation Monitoring System

EPIP 1-5:2 3.2.6 EPIP 2-2, Obtaining Meteorological Data and Forecasts and their use in Emergency Dose Assessment 4.0 PRECAUTIONS 4.1 New York State and Wayne and Monroe Counties must be notified of all Emergency ClassiTications within 15 minutes of a declaration.

4.2 The Licensee should notify the USNRC immediately after notification of the appropriate State and local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes.

4.3 is a specialized notification list of people and organizations who may not require immediate notification but may need to be contacted during an emergency.

5.0 PRERE UISITES An Emergency has been declared in accordance with EPIP 1-0, Ginna Station Event Evaluation and Classification or offsite assistance has been requested by RG&E personnel.

6.0 ACTIONS 6.1 6.1.1 Shift Su ervisor Emer enc Coordinator EOF/Recove Mana er 4

Ensure that notifications of all emergency declarations to New York State and Wayne and Monroe Counties are made within 15 minutes of declaring an emergency, in accordance with Attachment 3.

6.1.2 The licensee should notify the USNRC immediately after notification of the appropriate State or local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes using procedure 0-9.3 "NRC Immediate Notification".

6.1.3 Upon notification of an Unusual Event at Ginna Station, direct the control room personnel to implement section 6.2.1 of this procedure. Ifthe event is an Alert or higher, implement section 6.2.2.

6.1.4 Ifadditional assistance is required, refer to the NOG E-Plan phone list (in the RG&E telephone directory) in the Control Room and all Emergency Response Facilities, for phone numbers of station personnel.

EPIP 1-5:3 6.2 Control Room Personnel 6.2.1 Unusual Event-Go to Attachment1 6.2.2 Alert Classification or Higher - Go to Attachment 2 6.2.3 When offsite assistance has been requested - Go to Attachment 5 7.0 ATTACHMENTS Unusual Event Notification 2.

Alert or Higher Notifications 3.

Instructions for New York State Radiological Emergency Data Forms 3a.

New York State Radiological Emergency Data Form (Part 1) 3b.

New York State Radiological Emergency Data Form (Part 2) 3c.

Instructions for Event 1 and Event 2 Printouts and Plant Status Report 3d.

Event 1 Supplemental Information Form 3e.

Plant Status Report (PPCS not available) 4.

Specialized Notification Call List Notifications When Offsite Assistance has been requested Management Notification Roster (This attachment is controlled by Nuclear Emergency Preparedness.

It is not included as part of the distributed procedure)

EPIP 1-5:4 UNUSUALEVENT NOTIFICATIONS, Rev. 33 Page 1 of 3 1.

Report information to NEW YORK STATE, WAYNEand MONROE counties within 15 minutes of declaring the emergency via RECS Line using New York State Radiological Emergency Data Forms (Part 1) Attachment 3a. Fax the New York State Radiological Emergency Data Form (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center.

2.

Notify USNRC immediately after the notification of the State and Counties, using procedure 0-9.3, NRC Immediate Notification 3.

Activate the following positions by stating the following:

"We have an UNUSUALEVENT at Ginna Station based on (Initiating Condition)

Please report to your emergency duty station. The event was declared at hrs. We need to remind you of the Fitness for Duty Requirements. Are you available to report for Duty at this time? Ifnot, we are requesting that you standby so you can be notified for the next call in shift".

A

.Plant Manager: Report to the TSC to support the Control Room with offsite communications.

OR Joe Widay Business 3250

Home, 716-586-2679 Pager 716-528-3977 Cellular 716-748-4681 WillReport (YES/NO)

OR OR Dick Marchionda Business 3699 Home 315-926-0324 Pager 716-464-4403 Cellular 716-748<682 Jack St. Martin Business 3641 Home 716-586-5676 Pager 716-464-7045 Tom Alexander Business 3898 Home 315-524-8084 Pager 716-783-7045 Will Report (YES/NO)

WillReport (YES/NO)

WillReport (YES/NO)

EPIP 1-5:5, Rev. 33 Page 2 of 3 UNUSUALEVENT NOTIFICATIONS Technical Assessment Manager: Report to the TSC to support the Control Room with offsite communications.

OR OR OR OR Jeff Wayland Tom Harding Ron Ploof Brian Flynn Business 3317 Home 315-524-2899 Pager 716-464-5445 Business 3384 Home 716-671-8756 Pager 716464-5485 Business 3673 Home 716-381-9379 Pager 716-921-1722 Business 3734 Home 716-293-1 565 Pager 716-464-5134 WillReport (YES/NO)

Will Report (YES/NO)

Will Report (YES/NO)

WillReport (YES/NO)

Peter Bamford Business 3832 Home 716-924-0490 Pager 716-528-3166 WillReport (YES/NO)

Operations Assessment Manager: Report to the TSC to support the Control Room with offsite communications.

OR Terry White Pete Sidelinger Business 3667 Home 716-226-9381 Pager 716-464-7382 Cellular 716-748-4683 Business 3509 Home 716-671-3198 Pager 716-463-9830 WillReport (YES/NO)

WillReport (YES/NO)

OR Mike Ruby Business 3572 Home 716-872-6559 Pager 716-783-6435 WillReport (YES/NO)

EPIP 1-5:6 UNUSUALEVENT NOTIFICATIONS D.

USNRC Resident Inspector: Informational call only, Rev. 33 Page 3 of 3 OR Pete Drysdale Business 3265 Home 716-385-6210 518-877-6103 Pager 1-800-994-2337 (then dial personal ID¹ 53133)

Clyde Osterholtz Business 3265 Home 716-785-4872 Pager:

1-800-994-2337 (then dial personal ID¹ 51578)

OR Corporate Nuclear Emergency Planner: Informational call only Peter Polfleit Business 6772 Home 716-654-5325 Pager 716-527-2207 Cellular 716-733-2207 OR Frank Cordaro Business 3108 Home 315-524-2924 Pager 716-527-3650 Cellular 716-729<613 OR Richard Watts Business 8706 Home 716-425-2644 Pager 716-527-3749 Cellular 716-747-9760 Frank Orienter Business 2265 Home 716-288-8076 Pager 716-527-5685 Cellular 716-729-7517 Ifthe Unusual Event lasts greater than one (1) hour, report information using the New York State Radiological Emergency Data Forms (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center each hour from the time the previous notification was made.

Fax the New York State Radiological Emergency Data Form (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center after each report.

EPIP 1-5:7 ALERT OR HIGHER NOTIFICATIONS, Rev. 33 Page 1 of2 Contact Community Alert Network (CAN) at 9-1-800-552-4226. Inform the CAN operator the following information to activate the system:

a.

This is

. I am the Ginna Control Room Communicator with RG8E.

(your name)

'b.

My password is: Brookwood c.

My callback number is:

d.

This is (circle one):

an Actual Event a Drill e.

This Emergency Classification declared at:

f.

Message to deliver (circle one):

(Time from REGS form)

Drill Alert Site Area Emergency General Emergency g.

My current time is:

. Please start notifications now.

Report information to NEW YORK STATE, WAYNEand MONROE counties within 15 minutes of declaring the emergency via RECS Line using New York State Radiological Emergency Data Forms (Part 1) Attachment 3a. Fax the New York State Radiological Emergency Data Forms (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center.

NRC Resident Inspector: Informational call only Pete Drysdale Business Home 3265 716-385-6210

'18-877-6103 Pager 1-800-994-2337 (then dial personal ID¹ 53133)

OR Notify USNRC immediately after the notification of the State and Counties, using procedure 0-9.3, NRC Immediate Notification Clyde Osterholtz 'usiness 3265 Home 716-785-4872 Pager 1-800-994-2337 (then dial personal ID¹ 51578)

EPIP 1-5:8, Rev. 33 Page 2 of 2 ALERT OR HIGHER NOTIFICATIONS Ifthe Alert of higher lasts greater than 30 minutes report information using the New York State Radiological Emergency Data Forms (Part 1) Attachment 3a to New York State, Wayne County, Monroe County every 30 minutes from the time the previous notification was made.

Fax the New York State Radiological Emergency Data Form (Part 1) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center after each report.

6.

Notify Energy Operations (8944) that Ginna has an emergency and to implement procedures to increase reliability of power to Ginna.

7.

Ifrequested by the TSC or EOF, the Control Room willfax the Event 1 Supplemental Information Form, Attachment 3d to the TSC and EOF.

NOTE:

Event 1 and Event 2 printouts should not be transmitted by the Control Room, but should be faxed by the TSC Administrative/Communications Staff when it is sufficiently manned to do so.

8.

Refer to Attachment 3c for Event 1 and Event 2 instructions.

EPIP 1-5:9, Rev. 34 Page 1 of2 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICALEMERGENCY DATAFORMS The New York State Radiological Emergency Data Form, (Part 1) Attachment 3a should be filled out with the assistance of the Emergency Coordinator or EOF/Recovery Manager and Radiation Protection personnel.

For training and drills/exercise, circle "B"- An Exercise.

For actual events, circle "A"- NOT An Exercise.

The determination for item 6 is made by checking emuent monitor readings against the release rate limits given in procedure P-9.

For item 7 of the form, the Emergency Coordinator or EOF/Recovery Manager shall use EPIP 2-1, Protective Action Recommendations.

For item 8 of the form, enter the Emergency Action Level (EAL) number from EPIP 1-0, Ginna Station Event Evaluation and Classification.

NOTE'HE WIND SPEED INDICATORATTHE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLYTO 50 MILES PER HOUR.

Obtain weather information, items 11-13 of the form, using the plant process computer (PPCS)

OR Ifthe PPCS is not available, use the Control Room weather indication on the RMS rack.

OR The Radiation Protection Shift Technician or Dose Assessment Manager willdetermine the weather and stability class in accordance with procedure EPIP 2-2.

The communicator willinitial the "prepared by" line at the bottom of the form. The SS/EC (or designee) willapprove the form at the bottom prior to transmission. The communicator willensure all forms are sent to the Corporate Nuclear Emergency Planner (CNEP) at the conclusion of the event.

Report the information on the completed New York State Radiological Emergency Data Form (Part 1) Attachment 3a by reading the statement number and the statement including the designation letter (e.g. "A")to New York State, Wayne and Monroe County within 15 minutes of declaring the Emergency using the REGS Line:

A.

Press button, allow 10 seconds B.

Request roll call. Ask ifthe following are on the line:

1.

"New York State" 2.

"Monroe County" 3.

'Wayne County" C.

"This is Ginna Station" D.

Report information on New York State Radiological Emergency Data Form (Part 1) a.

EPIP 1-5:10, Rev. 34 Page 2 of 2 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICALEMERGENCY DATAFORMS 9.

IF REGS LINE IS OUT OF ORDER, perform the following:

Call Wayne County 9-1-315-946-9711 (Wayne County Warning Point)

Inform Wayne County, "This is a Ginna Emergency, please hold while we connect Monroe County and New York State". Press the conference button on the telephone.

Call Monroe County 9-528-2222 (Monroe County Warning Point)

Inform Monroe County, "This is a Ginna Emergency". Press the conference button on the telephone. Wayne and Monroe should now be connected.

Roll call Wayne County Monroe County "Please hold while we connect New York State". Press the conference button on the telephone.

Call New York State 9-1-518-457-2200 (New York State Warning Point)

Inform New York State, "This is a Ginna Emergency". Press conference button on the telephone.

Wayne County, Monroe County and New York State should all be connected.

10.

Data in items 15 through 20 of the New York State Radiological Emergency Data Form (Part 2) b should be filled out by the TSC/EOF Dose Assessment and transmitted by fax as information becomes available from the TSC/EOF.

11.

Fax all New York State Radiological Emergency Data Forms to the following using the instructions on the fax machine:

Wayne County Monroe County New York State TSC EOF Survey Center Joint Emergency News Center 9-1-315-946-9721 9-2564355 9-1-518<57-9942 3927 9-262-5788 3612 6771 12.

Blank copies of the New York State Radiological Emergency Data Form (Part 1 and Part 2) are available in the Control Room.

13.

When a County or the State request to be notified only ifconditions change or when the event is terminated, check with the State/County warning points to see ifthey agree.

Ifthey all agree, note this in section 8 of the next Part 1 Form notification. The facilitywith command and control will inform the other RG&E response facilities of the status of notifications. Perform a notification when conditions change or the event is terminated.

EPIP 1-5:11 NOTE: See Attachment 3 for instructions. a, Rev. 34 Page 1 of 1 Read everything on this page over the REGS phone.

'EW YORK STATE RADIOLOGICALEMERGENCY DATA FORM (PART I)

Roll Call Response:

New York State Warnin Point 0 Monroe Count 0 Wa ne County 0

1. Message transmitted at:

Date Time

3. Facility providing information:

C. Ginna

4. Classification:
2. This is:

Via: A. REGS B. Other A. NOT an exercise B. An exercise A. UNUSUAL EVENT B. ALERT C.

SITE AREA EMERGENCY D. GENERAL EMERGENCY E.

EMERGENCY TERMINATED F.

RECOVERY G. TRANSPORTATION INCIDENT

5. Classification Time:

This Emergency Classification declared at:

Date 6.

Release of Radioactive Materials:

(Refer to P-9l A. No Release above Technical Specifications B. Release to the Atmosphere above Technical Specifications Time C.

Release to a Body of Water above Technical Specifications

7. Protective Action RECOMMENDATIONS: (Refer to EPIP 2-1l A. No need for Protective Actions outside the site boundary B. Evacuate the following ERPAs W1 W2 W3 W4 W5 W6 W7 M1 M2 M3 M4 M5 M6 M7 MB M9 C. Shelter all remaining ERPAs
8. Brief Event

Description:

EAL //

9. Plant Status:

10.

Reactor Shutdown:

(subcriticall A. Stable C.

Degrading B. Improving D. Hot Shutdown E. Cold Shutdown A. Not Applicable B. Date Time 11.

Wind Speed:

12. Wind Direction:

A.

Miles/hour at elevation feet From:

dee eee at etoeattoo feet

~

13. Stability Class:

Unstable, Neutral, Stable Do NOT REPORT Stability Class Work Sheet Temperature at 250 feet

'F Temperature at 33 feet

'F Temperature Difference

'F

-1.74

-0.65 Unstable Neutral I Stable

-3

-2

-1 0

1 Temperature Difference 14.

Reported By:

Name Area Code Number Monroe County 0 Time Approved:

Approved By:

Roll Call Response:

New York State Warning Point 0 FOR RG8rE USE ONLY:

Time Prepared:

Prepared By:

Wayne County 0 Completed form sent to CNEP - 49/2

EPIP 1-5:12 b, Rev. 34 Page 1 of1 NEW YORK STATE RADIOLOGICALEMERGENCY DATA FORM (PART II)

Telefax this data form to: 0 New York State 15.

Message transmitted at:

0 Monroe County G Wayne County Date Time Location/Facility Transmitted From:

16.

General Release Information A. Release

> Tech Specs started:

Date B. Release

> Tech Specs expected to end:

Date C.

Release

> Tech Specs ended:

Date D. Reactor Shutdown:

N/A OR Date E. Wind Speed:

miles/hour at elevation F. Wind Direction from:

degrees at elevation G. Stability Class:

PASQUILL A B

C D

E F

G OR Time Time Time Time feet Other feet OR 0 Unknown 17.

Atmospheric Release Information A. Release from: 0 Ground 0 Elevated D. Noble Gas Release Rate B. Iodine/Noble Gas Ratio E. Iodine Release Rate C. Total Release Rate Ci/sec F. Particulate Release Rate Ci/sec Ci/sec Ci/sec 18.

Waterborne Release Information A. Volume of Release B. Total Concentration gal or liters C. Radionuclides in Release yci/ml D. Total ActivityReleased 19.

Dose Calculations Ibased on a release duration of hours)

Calculation is based on (circle one)

A. Inplant Measurements B. Field Measurements C. Assumed Source Term Table below applies to (circle one)

Distance Site Boundary 2 Miles 5 Miles 10 Miles Miles A. Atmosphere Release B. Waterborne Release Xu/Q TEDE (rem)

Dose CDE - Child Thyroid Irem) 20.Field Measurements of Dose Rates or Surface Contamination/Disposition Miles/Sector OR Miles/Degrees Location OR Sampling Point Time of Reading Dose Rate OR Contamination Ilnclude Units)

FOR RG8E USE ONLY:

Time Prepared:

By:

Completed form sent to CNEP - 49/2 Time Approved:

By:

EPIP 1-5:13 c, Rev. 34 Page 1 of1 INSTRUCTIONS FOR EVENT 1 AND EVENT 2 PRINTOUTS AND PLANTSTATUS REPORT Assure the Plant Process Computer System (PPCS) is operational. IfPPCS is not operational, go to step 5.

NOTE: Obtain Event 1 and Event 2 printouts from the computer analyst ifthat position is staffed, otherwise perform the following step.

Obtain Event 1 and Event 2 printouts by entering:

GASR <return>

Computer response - Enter Group Name EVENT1 <return>

Computer response - Select Printer Location Press F1 for Control Room, F2 for EOF, F3 for TSC GASR <return>

Computer response - Enter Group Name EVENT2 <return>

Computer Response - Select Printer Location Press F1 for Control Room, F2 for EOF, F3 for TSC Place printout in the Event 1 & 2 group trend log book NOTE: Event 1 and Event 2 group trend (GTLOG) should be printed every 15 minutes.

Initiate Event 1 & 2 group trend log (GT LOG) by entering:

GTLOG <return>

Computer response - Enter Name of Group to Log EVENT1 <return>

Computer response - Enter Update Rate (30-1800 seconds) 60 <return>

Computer response - Enter Print Interval (1-30 minutes) 15 <return>

Computer Response - Select Printer Location (F1-F4)

Press F1 for F3 for TSC Initiate Event 1 and Event 2 Group Trend Log in EOF by repeating step 3 and enter F2 when selecting printer location.

Place printouts in Emergency Coordinator or EOF/Recovery Manager notebook Verifywith the TSC computer analyst that the PPCX (plant computer data) is being transmitted to New York State, Wayne County and Monroe County via computer modem.

Ifthe PPCX (plant computer data) to offsite agencies is unavailable, perform step 2 and fax the printout to New York

~

State, Wayne County and Monroe County.

Ifthe PPCS is unavailable, the Plant Status Report (Attachment 3e) must be completed by the Control Room and faxed to the TSC for distribution to New York State, Wayne County, Monroe County and EOF.

When completing Attachment 3e, ifthe parameter is measurable (e.g. pressurizer level) use the numerical value. When the parameter is not measurable, the condition of any deviation from normal should be noted (e.g. core circulation - forced or natural).

EPIP 1-5:14 EVENT 1 SUPPLEMENTAL INFORMATIONFORM d, Rev. 34 Page1 of1 61 Aux Feedwater System 62 Safety Injection System 63 Diesel Generators 64 Containment Fan Cooler System 65 Service Water System 66 Post Accident Charcoal Filters Inservice Inservice Inservice Inservice Insewice Inservice Standby QOS Standby OOS Standby OOS Standby OOS Standby OOS Standby OOS 67 Containment Spray Pumps Inservice Standby OOS 68 Component Cooling System 69 DC System 70 NaOH Tank Level Inservice Standby OOS B

v Time Completed:

Completed By:

EPIP 1-5:15 Plant Parameters PLANTSTATUS REPORT PPCS NOT AVAILABLE)

Plant Parameters Radiation Monitoring e, Rev. 34 Page1 of1 Reactor Shutdown YES/NO TIME AuxiliaryFeedwater System Inservice Standby OOS R-1 Control Room Mrem/hr RCS Pressure PRZR Level Core Circulation Subcooled Forced/Natural PSIG Safety Injection Diesel Generators Service Water System

'F Cnmt Fan Coolers System Inservice Standby OOS Inservice Standby OOS Inservice.

Standby OOS Inservice Standby OOS R-2 Containment R-9 Letdown R-10 "A"Containment Iodine R-11 Containment Particulate Mrem/hr Mrem/hr CPM CPM A"S/G Level "8" S/G Level "A"S/G Pressure PSIG Post Acc. Charcoal Filter Cnmt. Spray Cnmt. Spray Pumps Comp. Cooling System Damper Open

/

Inseivice Standby Inservice Standby OOS Inservice Standby OOS Damper Closed R-12 Containment Gas R-10 "B" Plant Vent Iodine R-13 Plant Vent Particulate CPM CPM CPM "8" S/G Pressure PSIG D.C. System Volts R-14 Plant Vent Gas CPM Safeguard Offsite Power Train B (16/17)

EDG/Turbine/Offsite Available/Unavailable NaOH Tank Level RWST Level R-29 Containment High Range R-30 Containment High Range Cnmt Pressure Sump "A Level Sump "8" Level RCS Temp RVLIS CET R/hr =

Roentgen/Hour pCi/cc =Microcuries/Cubic Centimeter Mrem/hr =

Millirem/Hour PSIG B.A. Tank Level FT Wind Speed IN Wind Direction (From)

'F Temperature 33 FT Temperature 250 FT

'SPING Unit readigs may be deleted if radiation monitors R-12 and R-14 onTime scale.

MPH Degrees 0F 0F R-15 AirEjector Gas

'R-12A SPING Containment Gas

'R14A SPING Plant Vent Gas

'R-15A SPING AirEjector Gas R-31 Steam Line "A" R-32 Steam Line "B" Date Completed Completed By CPM IiCi/cc pCi/cc Mrem/hr Mrem/hr

EPIP 1-5:16 SPECIALIZED NOTIFICATIONLIST, Rev. 34 Page1 of5 Medical 1.

Ontario Volunteer Emergency Squad 2.

Wayne County Emergency Dispatcher 3.

Rochester General Hospital, Emergency Department Triage Nurse 4.

Rochester General Hospital Main Switchboard 769-911 (Ginna Control Room Only)

(To request ambulance)

.9-1-315-524-5757 (Business number) 9-1-315-946-5304 9-338-2300 9-338-4000 5.

RG8E Medical Services Dr. Robert W. George Dr. T. K. Oates Dr. Alexander Kurchin Office Alternate Office Answering Service 8600 4616 9-226-3800 6.

Newark-Wayne Community Hospital Police 9-1-315-332-2267 1.

New York State Police Warning Point 2.

Canandaigua State Police 3.

Williamson State Police 4.

Wayne County Sheriff 5.

Monroe County Sheriff Fire 9-1-518<57-2200 9-1-315-457-6811 9-398-3200 9-1-800-962-0810 9-1-315-946-9711 9-428-5511 1.

Ontario Volunteer Fire Department 769-911 (Ginna Control Room Only)

(To report fire) 9-1-315-524-2661 (Business number)

EPIP 1-5:17 SPECIALIZED NOTIFICATIONLIST, Rev. 34 Page 2 of 5 Westin house Emer enc Res onse Or anization Notify one Westinghouse contact using list in order shown. Provide available facts to individual and provide updates.

2.

Dan Lipman ESBU Service Response Manager 3.

Rose Cotton ESBU Emergency News Communications ENC Manager 4.

Mike Young ESBU Emergency Response Support Manager Technical 5.

Tom Hart ESBU Emergency Response Logistic Manager Other 1.

Hank Sepp Director ESBU Emergency Response Home Hotline Home Home Home Home Hotline Pager 9-1-412-374-5282 9-1-412-856-4036 9-1-412-856-6121 9-1-412-374-6920 9-1-412-744-3244 9-1-412-374-6805 9-1-412-963-6129 9-1-412-374-5081 9-1-412-243-7996 9-1-412-374-6980 9-1-412-837-9486 9-1-412-837-1737 9-1-412-765-8886 1.

Ontario Town Supervisor, Roy Herrmann 2.

Ontario Water Department 3.

Plant Protection Department Kodak Park Office Home 9-1-315-524-7105 9-1-315-524-8087 9-1-315-524-2941 9-722-2122 4.

Wayne County Emergency Operations Center 5.

Director Wayne County Office of Disaster Preparedness-Thelma Wideman Home 9-1-315-946-5663 9-1-315-597-6291 6.

Monroe County Office of Emergency Preparedness (Nights, Weekends, Holidays)

Daytime Offhours 9-473-0710 9-528-2222

EPIP 1-5:18 SPECIALIZED NOTIFICATIONLIST (Cont'd.), Rev. 34 Page 3of5 7.

Administrator, Monroe County Office of Emergency Preparedness-Mary Louise Meisenzahl 8.

University of Rochester Advance RAP Team - David Maillie Home Pager Home 9-624-3194 9-428-5141 9-275-3788 9-334-2428 9.

National Weather Service (Buffalo) 10.

Radiation Management Consultants Office Emergency Fax 9-1-800<62-7751 9-1-215-824-1300 9-1-215-243-2990 9-1-215-824-1371 11.

Helgeson Nuclear Services Inc 12.

James C. Hutton (NSARB) 13.

Institute of Nuclear Power Operations 14.

American Nuclear Insurers 15.

Emergency Preparedness Canada Phone Fax 9-1-415-846-3453 9-1-716-381-8473 9-1-800-321-0614 9-1-203-677-7305 9-1-613-991-7000 9-1-613-996-0995 16.

NYPA Environmental Laboratory Fulton, New York Daytime Lab Manager pager Mgr Home¹ RES on call pager 9-1-315-593-5740 9-1-315-593-5735 9-1-800-436-2732 enter pager ¹ 713-6710 then your number 9-1-315-342-0015 9-1-800-436-2732 enter pager ¹ 713-6726 then your number

EPIP 1-5:19 Com an Personnel SPECIALIZED NOTIFICATIONLIST (Cont'd.), Rev. 34 Page 4 of 5 Thomson, Bill Manager, Radiation Protection and Chemistry Richards, Thomas Chief Executive Officer Lappan, George Manager of Corporate Communications Business Home Pager Business Home Business Home 3219 315-342-5082 716-528-8561 8299 (716) 288-9186 8812 716-377-2490 Mecredy, Robert Vice President Nuclear Operations Wilkens, Paul Sr. Vice President Generation Watts, Richard Manager, Nuclear Training Business Home Pager Business Home Pager:

Business Home Pager Cellular 3494 716-381-6430 716-783-4900 8076 716-248-2385 716-529-6426 8706 716-425-2644 716-527-3749 716-747-9760 Nuclear Re ulato Commission Nuclear Regulatory Commission Region 1 - King of Prussia, PA Radiation Assistance Program Dept of Energy Brookhaven National Lab 610-337-5000 516-282-2200 3.

Commercial telephone system to NRC Operations Center (via Bethesda Central Office)

Commercial telephone system to NRC Communications Center (via Silver Spring Central Office)

Commercial telephone system to NRC Operator (via Bethesda Central Office) 301-951-0550 301-427-4056 301-492-8893

EPIP 1-5:20, Rev. 34 Page 5 of 5 SPECIALIZED NOTIFICATIONLIST (Cont'd.)

New York State 1.

James Baranski, State Emergency Management Office (SEMO) 2.

SEMO Lake District 3.

NYS Department of Health Rochester Office 518-457-8909 315-331-4880 716-262-2010 4.

New York State Emergency Operations Center (EOC) Albany 5.

EOC Albany - Dose Assessment 518<54-3337 518-454-3321 518-454-2176 Federal Emergency Management Agency (FEMA) 1.

Emergency Information Coordination Center 202-634-7800 202-646-2400

EP IP 1-5:21, Rev. 34 Page 1 of 3 NOTIFICATIONSWHEN OFFSITE ASSISTANCE HAS BEEN REQUESTED When offsite assistance has been requested activate:

Security Nuclear Management Emergency Planning Examples of initiating events that could require offsite assistance are:

Fire Medical Emergency Security Event HAZMATIncident Natural Events (such as flooding, earthquakes or severe weather)

Security Contact Security at 3210, so that they can make preparations for the arrival of the emergency vehicles and personnel.

Nuclear Management Notifythe following individuals:

"This is the Ginna Control Room. We have requested offsite assistance from

. Can you be the Nuclear Management contact for this event?

Your duties are (a) act as the RG8 E lead for this event and (b) act as the liaison between the Control Room and the corporation."

Nuclear Mana ement (One person required to respond)

OR Joe Widay Business Home Pager Cellular 3250 716-586-2679 716-528-3977 716-748-4681 Available (YES/NO)

OR Dick Marchionda Business Home Pager Cellular 3699 315-926-0324 716-464-4403 716-748-4682 Available (YES/NO)

Available (YES/NO) 8069 716-381-6430 716-783-4900 Bob Mecredy Business Home Pager The nuclear management representative may call other nuclear managers or members of the Ginna leadership team.

EPIP 1-5:22, Rev. 34 Page 2 of 3 NOTIFICATIONSWHEN OFFSITE ASSISTANCE HAS BEEN REQUESTED Emergency Planning Notify the following individuals:

"This is the Ginna Control Room. We have requested offsite assistance from

. Can you be the Emergency Planning contact for this event' Your duties are (a) activate Public Relations and (b) act as the liaison between the Control Room and government agencies.

is acting as the Nuclear Management lead for this event. He can be reached at

~ I Emer enc Plannin (One person required to respond)

Peter Polfleit Business 6772 Home 716-654-5325 Pager 716-527-2207 Cellular 716-733-2207 OR Frank Cordaro Business Home Pager Cellular 3108 315-524-2924 716-527-3650 716-729-4613 OR Richard Watts Business Home Pager Cellular 8706 716-425-2644 716-527-3749 716-747-9760 Frank Orienter Business Home Pager Cellular 2265 716-288-8076 716-527-5685 716-729-7517 The Emergency Planning representative will call the duty public information officer (PIO) via the ECC at 771-2233, and inform them of the event. The duty PIO willdetermine ifa media announcement is warranted. The Emergency Planning representative willalso contact Wayne County, Monroe County and New York State officials to brief them on offsite resources being used

EPIP 1-5:23, Rev. 34 Page 3of3 NOTIFICATIONSWHEN OFFSITE ASSISTANCE HAS BEEN REQUESTED 5.

Contact the NRC resident inspector OR Pete Drysdale Business Home Pager 3265 716-385-6210 518-877-6103 1-800-994-2337 (then dial personal ID¹ 53133)

Clyde Osterholtz Business Home Pager 3265 716-785-4872 1-800-994-2337 (then dial personal ID¹ 515 I 8)

ROCHESTER GAS 8 ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER ~~

PROCEDURE NO.

EPIP 2-16 REV. NO.

9 CORE DAMAGE ESTIMATION RESPONSIBLE MANAGER EFFECTIVE DATE CATEGORY 1.0 THIS PROCEDURE CONTAINS 28 PAGES

EPIP 2-16:1 EPIP 2-16 CORE DAMAGE ESTIMATION 1.0 PURPOSE

To provide an estimate of the degree of core damage based on fission product concentrations and other indications under accident conditions.

2.0 RESPONSIBILITY 2.1 The Radiation Protection 8 Chemistry Manager is responsible for obtaining post-accident sampling and analysis information.

2.2 The Engineering Support Manager is responsible for implementing this procedure to obtain estimates of core damage.

3.0 REFERENCES

3.1 Developmental References 3.1.1 NUREG-0737, II.B.3 3.1.2 Westinghouse Mitigating Core Damage Training Manual.

3.1.3 Rogovin Report, Part 2, Volume II, pp 524 - 527.

3.1.4 WASH-1400 Appendix Vll.

3.1.5 Westinghouse Owner's Group Post Accident Core Damage Assessment Methodology, Rev. 2, November, 1984.

3.1.6 NUREG 1210, NRC Severe Reactor Accident Incident Response Training Manual 3.1.7 Technology for Energy Report No. R-81-012 3.1.8 Westinghouse Owner's Group (WOG) Severe Accident Management Guidelines, June 1994 3.2 Implementing References 3.2.1 CH-EPIP-LIQUID, Alternate Emergency Sampling of Primary Coolant 3.2.2 CH-EPIP-CV-AIR, Containment Atmosphere Sampling and Analysis During Containment Isolation

EPIP 2-16:2 3.2.3 CH-PASS-ACCIDENT, Post Accident Sampling at the PASS - Accident Conditions 3.2.4 CH-PASS-SAMP-ANAL, Analysis of Samples Taken at the PASS for Isotopic Analysis 3.2.5 P-9, Radiation Monitoring System 3.2.6 S-14.3, Operation of Containment High Range Area Monitors R-29, R-30.

3.2.7 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.8 CH-EPIP-CVHZ, Containment Atmosphere Hydrogen Monitoring 4.0 PRECAUTIONS 4.1 Care should be taken to avoid defining too precisely the extent of core damage based upon initial sampling results. Other plant indicators will also be available (such as incore temperature indication, containment hydrogen monitors, etc.) which should also be considered in arriving at a more refined estimate.

4.2 The time of sampling relative to the suspected transient or core degradation sequence must be considered.

The effects of isotope decay, sampling equilibrium and progressing core degradation may tend to,complicate sample interpretation.

4.3 Reactor power history is to be considered in determining whether certain key radionuclides have reached equilibrium.

44 Measured concentration of radioactivity may need to be adjusted to account for system dilution (e.g. accumulators, safety injection water) prior to estimating fuel damage.

4.5 When providing guidance on plant operations, use the setpoints and instructions found in the Emergency Operating Procedures (EOP's) or Severe Accident Management Guidelines (SAMGs) as appropriate.

5.0 5.1

~PRERE UIEITEE Isotopic analysis of primary liquids.

5.2 5.3 Data from plant radiation monitors.

Plant operational status including pertinent core data.

Isotopic analysis of containment atmosphere

EPIP 2-16:3 5.5 58 6.0 Hydrogen analysis of containment atmosphere.

Data from core exit thermocouples.

ACTIONS 6.1 Initial Assessment of Core Damage 6.1.1 Core damage will be initiallyclassified into one of the following categories:

No damage Gap activity released Fuel activity released 6.1.2 Check the following plant indications to assess initial core damage:

Indicator R-9 (if not isolated)

R-29/30 Core Exit Thermocouples No Damage

<2000 mR/hr.

<100 R/hr (approx: 10 R/hr for a LOCA)

<750 F Gap Activity 2000 = 1%

5000 = 5%

>100 R/hl'50 F - 1650 F Fuel Activity N/A

>1000 R/hr

>1650 F Containment Hydrogen None detectable None detectable

>1%

6.1.3 Other indications that core damage may be taking place:

a.

Nuclear instrumentation does not follow normal decay curve following reactor trip.

Ifthere is voiding in the core, excore nuclear instrumentation can read high. This is due to a loss of the water shielding and increased amount of gamma and neutron radiation reaching the detectors.

b.

Reactor Vessel Level Indicating System (RVLIS)

RVLIS indication can determine ifthe core has remained covered.

The top of the core, using RVLIS indication, is 78%.

Ifthe core has remained covered, core damage should be limited to gap released from cladding defects.

However, ifthe core was uncovered, it becomes more probable that extensive cladding oxidation could have occurred lading to cladding and fuel pellet fragmentation.

Refer to drawing 03021-687 for help in determining ifthe core has been uncovered.

EPIP 2-16:4 c.

Core Exit Thermocouples (CETs)

Attachment 1 shows possible core damage states as core temperature increases.

d.

Containment Radiation Monitors provides a series of curves showing a monitor dose rate versus time after shutdown.

The curves have been calculated for various amounts of core damage.

These curves are representative of core damage ifthere has been a loss of coolant accident (LOCA). The curves will not be representative of core damage from increased radiation or normal leakage into containment.

Containment AirActivity Attachments 3, 4, 5 and 6 have containment air activity for various states of core damage.

These activities can be used to estimate the activity in samples drawn from the containment atmosphere or to estimate the amount of curies/second that will released from containment using the design leak rate of 2% a day.

The calculated activities are for the following states of core damage:

100% release of coolant into containment 100% release of the gap activity into containment (using Reg.

Guide 1.25 methodology) 100% release of the gap activity into containment (using Westinghouse WCAP 7828 methodology) 1% release of fuel into containment.

6.2 Detailed Assessment of Core Damage 6.2.1 A detailed assessment of core damage will be performed when isotopic data is available from Radiation Protection and Chemistry.

6.2.2 Use isotopic information and the following table to assess core damage:

Category of Damage No Damage Isotopes Released Normal levels of l-131, l-133, Cs-137, Kr-88, and Xe-133 Gap Activity Released Increased levels of Kr-88, Xe-133 I-131 and I-133 Fuel Overheating Te-129, Te-132, Sr-90, Ba-140, La-140, La-142 and Pr-144

EPIP 2-16:5 Fuel. Melting Ru-103, Ru-106, Rh-105, Mo-99, U, Pu 6.2.3 Use isotopic information and the following ratios to assess core damage:

~

tiice It d ~

tii~

G Atilt ~ t ~

F IP I~I tRii Kr-87/Xe-1 33 I-132/I-131 I-133/I-131 I-135/I-131 0.022 0.17 0.71 0.39 0.22 1.5 2.1 1.9 6.3 Calculation of Released Activity

                        • k******************************************************************

CAUTION REVIEW DATA NEEDED TO PERFORM CORE DAMAGE (CR)

(ATTACHMENT7) PRIOR TO CALCULATION.

                      • A***********k*******************************************************

6.3.1 Record the following plant indications.

The values should be recorded as close as possible to the time at which the samples are taken.

Reactor Coolant System:

Pressure Temperature Reactor Vessel level Pressurizer level PSIG F

Containment Building:

Atmosphere Pressure Atmosphere Temperature A. Sump level B. Sump level PSIG oF Feet Inches 6.3.2 Obtain and analyze selected samples using approved procedures.

Use reactor shutdown as time zero for all decay calculations.

EPIP 2-16:6 6.3.3 Correct samples for decay.

Correct containment atmosphere samples for temperature and pressure using the following:

Act. (atm) = Act. (Sample) x ~P~xT,~+460 P,

(T2 + 460) where:

Act.

=

Decay-corrected sample activity (uCi/cc)

TP,

=

measured sample temp. ('F) and pressure (psia)

TP,

=

CV atmos. temp. ('F) and pressure (psia) 6.3.4 Record decay corrected liquid sample data on the Liquid Sample Worksheet (Attachment 7).

Record decay corrected, pressure corrected, temperature corrected containment atmosphere samples on the Containment Atmosphere Worksheet (Attachment 8).

6.3.5 Calculate the sum of the total quantity of each fission product available for release from sampled sources.

                  • kk******kk*****k****************k*kk*k*******k***k***kk*********k***kk*kk**

CAUTION IT IS ASSUMED FOR THIS DISCUSSION THAT THE RCS IS AT NORMAL MASS AND A LOCA HAS NOT OCCURRED.

IF A,LOCA HAS OCCURRED, THE DETERMINATIONOF THE MASS IN THE RCS MUST BE ESTIMATED BY INDICATIONSAVAILABLETO OPERATIONS. THE MAJOR ACTIVITYWOULD PROBABLY BE IN THE CONTAINMENT SUMP "A".

      • k**************k***k************k*****k************************************k*

a.

Calculate the quantity of activity in the reactor coolant using:

RCS Mass = (6236 ft') x (2.83E4) x (Ratio correction factor)

Curies activity = Act,(uCi/gm) x RCS Mass x 1E-6 where:

RCS Mass calculated from data in step 6.3.1 and Ratio Correction Factor from Figure 1 of Attachment 13.

Record total curies in the appropriate column of Summation Record of Release Quantity (Attachment 9).

b.

Calculate total quantity of activity in the sump using:

Curies activity = Act, (uCi/cc) x Sump Volume x 1E-6

EPIP 2-16:7 where:

Sump volume is determined from Figure 2 of 3. As an approximate temperature for the liquid in the sump, use the air temperature of containment.

Activity in sump is calculated on Attachment 7.

Record total curies in the appropriate column of Summation Record Release Quantity (Attachment 9).

c.

Calculate the total quantity of fission products in the containment building atmosphere by completing Attachment 8 using:

Curies activity = Act.(uCi/cc) x 2.75E10 x 1E-6 where:

Act. is the pressure and temperature corrected activity from Attachment 8. Containment Volume at STP is 9.7E5 cubic feet or 2.75E10cc.

Record total curies in the appropriate column of Summation Record of Release Quantity (Attachment 9).

6.4 d.

Sum total activity (D) obtained in items A, B and C on Attachment 9.

Power Correction Factor (PCF)

                                            • A******%****************************A*4***k**********k****

CAUTION STEADY STATE POWER IS ASSUMED PRIOR TO SHUTDOWN.

STEADY STATE POWER CONDITION IS ASSUMED WHERE THE POWER DOES NOT VARY BY MORE THAN + 10 % OF RATED POWER LEVEL FROM TIME AVERAGED VALUE.

            • AAA******A*******%%**A************Ark%*A*****&*************A************%Wc**

6.4.1 For half-life of nuclides approximately <1 day:

PCF =Avera e Power Level Mwt for rior4da s Rated Power Level (Mwt) 6.4.2 For half-life of nuclide approximately >1 day:

PCF = Avera e Power Level Mwt for rior 30 da s Rated Power Level (Mwt)

EPIP 2-16:8 6.4.3 For half-life Nuclides <1 year:

PCF =Avera e Power Level Mwt for rior ear Rated Power Level (Mwt) 6.4.4 For half-life of nuclides>

1 year:

PCF =

Actual o eratin EFPD of e uilibrium c cle Total expected EFPD of equilibrium cycle operation

                    • 0'*********%**************k***k***************k************************

CAUTION FOR THE MAJORITY OF THE SELECTED NUCLIDES, THE 30-DAY POWER HISTORY PRIOR TO SHUTDOWN IS SUFFICIENT TO CALCULATEA POWER CORRECTION FACTOR.

                                    • %***A********************************************************

6.4.5 Determine the Fission Product Core Inventory by correcting the Equilibrium Source Inventory using the power correction factor equation:

                            • 4k*******4**k******4k*t*********A**4k***********A*******************%

CAUTION THE POWER CORRECTION FACTOR EQUATION BELOW APPLIES TO THE CATEGORY OF NUCLIDES WITH HALF-LIVESGREATER THAN ONE DAY.

%*********************************************************************%%%A******

Power Correction Factor

=

Z-P. 1-e" t'. e~

t'P where:

Pj = average power level (Mwt) during operating period t, at power j RP = rated power level of the core (Mwt) operating period in days at power j where power does not vary more than + 10 percent power of rated power level from time averaged value (Pj) decay constant of nuclide i in inverse days

EPIP 2-16:9 j =

time between end of period of operating at power j and time of reactor shutdown in days 6.4.6 Record power, correction factor and calculate corrected source inventory on the Corrected Source Inventory (Attachment 10).

6.4.7 Determine the fraction of release by completing the Record of Fractional Release (Attachment 11 for the source of the release (either gap or fuel pellet).

6.5 Containment Hydrogen Concentration

    • A************A**War**%*A%****%4'kk****kAkAki%A****A*******************************

CAUTION THE USE OF THIS SECTION ASSUMES A LOCA RELEASING H~ INTO CONTAINMENTFORMED BY A ZIRCONIUM-WATERREACTION IN THE CORE.

IF VESSEL FAILURE HAS OCCURRED FOLLOWING CORE DAMAGE,ADDITIONALH MAYBE GENERATED DUE TO CORE CONCRETE INTERACTION. THIS ADDITIONALH~ IS NOT ACCOUNTED FOR IN THE CALCULATIONSWITHINTHIS SECTION.

                              • kkk******%%A%*****************A%****A%*****************************

t***********************************I***i**************i**+********************

CAUTION THE MAXIMUMVALUETHAT % H~ APPROACHES DUE TO ZIRCONIUM WATER REACTION IS 13.8% @ STP.

              • A*********A***************************A%**%***4k*********%A********k*4'**%**A 6.5.1 Obtain a measurement of containment atmosphere hydrogen concentration.

EPIP 2-16:10 Assuming that all hydrogen formed by a zirconium-water reaction is released to the containment atmosphere, either use Figure 3 of Attachment 13 or calculate the fraction of zirconium-water reaction with the equation:

where:

FZWR = ~%H correction factor for STP (ZM) (H) (100- %H2)

FZWR =

Fraction of Zirconium-Water Reaction V

=

Containment volume, SCF, approx. 9.7E5 ft'M H

Total zirconium mass, approx. 23,900 lbs.

I Conversion factor, 7.92 SCF of H, per pound of zirconium reacted the above equation becomes:

FZWR =

~%H 5.12 Carr Factor for STP (100-%H2) 7.0 ATTACHMENTS 1.

Possible Core Damage States as Core Temperature Increases 2.

R-29 and R-30 Dose Rate Versus Time After Shutdown 3.

Containment Activity (uCi/cc) for a 100% Release of the Coolant Activity 4.

Containment Activity (uCi/cc) for a 100% Release of the Gap Activity (RG 1.25) 5.

Containment Activity (uCi/cc) for a 100% Release of the Gap Activity (WCAP 7828) 6.

Containment Activity (uCi/cc) for a 1% Release of the Fuel Inventory 7.

Liquid Sample Worksheet 8.

Containment Atmosphere Worksheet 9.

Summation Record of Release Quantity 10.

Corrected Source Inventory

EPIP 2-16:11 70 ATTACHMENTS (Cont'd.)

11.

Record of Fractional Release 12.

Guideline to Obtain Data Needed for Core Damage Assessment Estimation 13.

Figures Ratio of H,O Density to STP Density as a function of Temperature.

¹2 Gallons in Sump vs Sump Level Indication.

¹3 Containment Hydrogen Concentration vs. Zirconium Water Reaction

EPIP 2-16:12 POSSIBLE CORE DAMAGE STATES AS CORE TEMPERATURE INCREASES, Rev. 9 Page 1 of 1 5100'"

t30BB KI

.VIf I TING QF FUEL PEL'TS IVOR)

+RELEASE OF ALLVOLATII.EFISSION PROOUCTS FROM FUEL 4+g a,g4 g48

~44C 4E~

ggo 3600iF FQRMATION OF "LIQUEFIE0 FUEL" - F UEL OISSQLVES IN l2255 KI MELTEO COMPONENTS VERY RAPIO RELEASE QF IOOINE, CESIUM, ANO NOBLE GASES FROM FUE 4

CI CIC

~ab4l 2200 F STEAM ZIRCALLQYREACTION RELEASES H~

(1477 K) 2000'F (13N. K)

CLAOOINQ BURST: RELEASE OF QAP INVENTORY FROM FUEL PIN 1400 F

{1')

1200'F (920 K)

CLAOOINQ COLLAPSE PQSSIBI.E NORMALOPERATINQ TEMPERATURE

GJ EPIP 2-16:13, Rev. 9 Page 1 of 2 R-29 DOSE RATE VERSUS TIME AFTER SHUTDOWN 100 Gao Release (RG l.~-")

1DDZ Gap Release

(~CAP 7B23)

X 100 Coolant Release 1

Fuel Release 10K Fuel Release 100% Fuel Release 10 10 103 10 O

10 10'0 b

T<m (hours)

Containaent High Range Detettor 1

Dose Rates. (g 21)

EPIP 2-16:14 10, Rev. 9 Page 2 of 2 R-30 DOSE RATE VERSUS TIME AFTER SHUTDOWN 100 Cap Release (RG 1.25)

Qa 100'an Release

("Gas 707a)

X 100 Coolant Release 1% Fuel Release a

10 Fuel Release 0

100 Fuel Release 105 10 10 O

CI 10 10 10 I

0 I

Time (hours)

Cnntainment high Range tOeteern7 0nse Rates.(g

EPIP 2-16:15, Rev 8 Page 1 of1 Containment Activity (uCI/cc) for a 100% Release of the Coolant Activity ISOTOPE SUBCRITIGAL TIME (hours)

Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Br-84 l-131 l-132 I-133 I-134 I-135 Rb-88 Cs-138 TOTAL 0.0 1.31-2*

1.75-2 7.59-3 2.03-2 0.00+0 0.00+0 1.54+0 0.00+0 5.13-2 2.92-1 1.22-4 6.10-3 2.69-3 7.90-3 1.59-3 6.'I 0-3 0.00+0 0.00+0 1.97+0 0.5 1.21-2 1.77-2 5.79-3 2.03-2 6.51-8 3.14-6 1.54+0 4.60-5 4.97-2 6.79-2 6.38-5 6.09-3 2.31-3 7.77-3 1.07-3 5.79-3 1.56-3 1.53-1 1.89+0 2.0 9.54-3 1.82-2 2.58-3 1.40-2 2.59-7 1.21-5 1.52+0 5.42-5 4.51-2 8.56-4 9.13-6 6.06-3 1.47-3 7.39-3 3.26-4 4.95-3 1.64-3 3.78-2 1.67+0 8.0 3.69-3 1.95-2 1.01-4 3.15-3 1.02-6 4.23-5 1.48+0 2.91-5 3.05-2 2.16-11 3.83-9 5.93-3 2.39-4 6.04-3 2.82-6 2.65-3 3.74-4 1.65-5 1.55+0

  • Note 1.31-2 denotes 1.31 x 10'

EPIP 2-16:16, Rev. 9 Page1 of1 Containment Activity (uCI/cc) for a 100% Release of the Gap Activity (RG 1.25)

ISOTOPE SUBCRITICALTIME (hours)

Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 I-131 I-132 I-133 I-134 1-135 Rb-88 TOTAL 0.0 3.64+2*

4.26+0 6.92+1 1.06+2 0.00+0 7.28+0 2.88+2 0.00+0 5.46+1 8.00+1 1.09+2 1.46+2 1.68+2 1.31+2 0.00+0 1.53+3 0.5 3.36+2 1.01+1 5.28+1 9.36+1 8.54-4 7.29+0 2.90+2 9.88-1 5.81+1 7.99+1 9.37+1 1.44+2 1.13+2 1.24+2 7.21+0 1.41+3 2.0 2.65+2 2.50+1 2.35+1 6.45+1 3.40-3 7.32+0 2.94+2 1.16+0 6.88+1 7.94+1 5.95+1 1.37+2 3.45+1 1.06+2 7.54+0 1.17+3 8.0 1.03+2 5.92+1 9.20-1 1.45+1 1.34-2 7.36+0 3.09+2 6.26-1 8.30+1 7.78+1 9.70+0 1.12+2 2.98-1 5.68+1 1.73+0 8.35+2

  • Note 3.64+2 denotes 3.64 x 10'

EPIP 2-16:17, Rev. 9 Page 1 of 1 Containment Activity (uCI/cc) for a 100% Release of the Gap Activity (WCAP 7828)

ISOTOPE SUBCRITICALTIME (hours)

Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 l-131 I-132 l-133 I-134 I-135 Rb-88 TOTAL 0.0 1.06+0*

3.63+0 1.52+0 3.06+0 0.00+0 1.00+0 5.81+1 0.00+0 3.44+0 1.98+1 3.17+0 1.22+1 3.01+0 6.42+0 0.00+0 1.16+2 0.5 9.79-1 3.65+0 1.16+0 2.70+0 2.11-4 9.99-1 5.81+1 4.84-2 3.59+0 1.98+1 2.73+0 1.20+1 2.03+0 6.09+0 2.08-1 1.14+2 2.0 7.72-1 3.69+0 5.16-1 1.86+0 8.42-4 9.94-1 5.83+1 5.70-2 4.03+0 1.97+1 1.73+0 1.14+1 6.18-1 5.21+0 2.18-1 1.09+2 8.0 2.99-1 3.79+0 2.02-2 4.19-1 3.31-3 9.69-1 5.85+1 3.07-2 4.48+0 1.92+1 2.82-1 9.33+0 5.33-3 2.78+0 4.98-2 1.00+2 "Note 1.06+0 denotes 1.06 x 10'

EPIP 2-16:18, Rev. 9 Page 1 of 1 Containment Activity (uCI/cc) for a 1% release of the Fuel Inventory ISOTOPE SUBCRITICALTIME (hours)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe135m Xe-135 X3-138 Br-83 Br-84 l-131 I-132 I-133 I-134 l-135 Rb-88 Cs-138 TOTAL 0.0 1.20+0*

3.60+0 1.40-1 7.00+1 1.00+1 1.20-1 1.80+1 2.90+1 8.00+0 5.50+0 2.90+1 3.00-2 7.20-2 3.90+0 5.60+0 7.40+0 8.50+0 6.60+0 0.00+0 0.00+0 1.44+2 0.5 1.01+0 3.33+0 1.98-1 5.34+0

8.83+0 1.20-1 1.79+1 2.92+1 2.16+0 1.13+1 6.75+0 2.60-2 3.77-2 3.89+0 4.81+0 7.28+0 5.72+0 6.26+0 6.80-1 1.52+1 1.30+2 2.0 5.93-1 2.62+0 3.45-1 2.38+0 6.08+0 1.20-1 1.76+1 2.96+1 9.75-2 1.29+1 8.50-2 1.69-2 5.39-3 3.87+0 3.06+0 6.92+0 1.74+0 5.36+0 7.12-1 3.76+0 9.78+1 8.0 7.26-2 1.01+0 6.83-1 9.31-2 1.37+0 1.18-1 1.63+1 3.1 1+1 3.15-2 1.02+1 2.14-9 3.00-3 2.26-6 3.79+0 4.98-1 5.66+0 1.51-2 2.86+0 1.63-1 1.64-3 7.40+1 "Note 1.20+0 denotes 1.20 x 10'or 10% release multiply values x 10 For 100% release multiply values x 100

EPIP 2-16:19 LIQUIDSAMPLE WORKSHEET, Rev. 9 Page 1 of 1 Kr 87 Xe 131m Xe 133 Sample Number:

Sample Location:

Time of Analysis:

Temperature, 'F:

Pressure, PSIG:
  • Sample Activity uCi/gm at time of reactor shut-down Mass of x liquid sampled (gm) x 1E-6 Ci/uCi 1E-6 1E-6

= Corrected total Activity Released (Ci)

I 131 1EW 32 1E-6 133 1E-6 I 135 1E-6 Cs 134 Rb 88 1E-6 Te 129 Te 132 Ba 140 La 140 La 142 Pr 144 Cs 137 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6

  • Use reactor shutdown as T,

EPIP 2-16:20 CONTAINMENTATMOSPHERE WORKSHEET, Rev. 9 Page 1 of 2 Kr 87 Xe 131m e 133 31 I 132 I 133 I 135 Cs 134 Rb 88 Te 129 Te 132 Ba 140 La 140 La 142 Pr 144

$ 137 Sample Number:

Sample Location:

Time of Analysis:

Temperature, F:

Pressure, PSIG:

Total

~leoto e

Act, Activity Atmosphere, Atmos.,

uCi/cc*

CV Volume 2.75E10 cc x

2.75E10 2.75E10 2.75E10 2.75E10 2.75E10 2.75E10 2.75E10 2.75E10 2.75E10 2.75E10 2.75E10 2.75E10 2.75EI0 2.75E10 2.75E10 2.75E10 1E-6 Ci/uCi 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 1E-6 CV Ci

EPIP 2-16:21, Rev. 9 Page 2 of 2

  • Act.(atm) = Act. (Sample) x P,~xT,~+460 P,

(T2 + 460)

TP, = sample temp ('F), sample pressure (psia)

T,, P, = CV temp ('F), CV pressure (psia)

Sample activity has been decay corrected back to time of reactor shutdown.

EPIP 2-16:22, Rev. 9 Page1 of 1

SUMMATIONRECORD OF RELEASE QUANTITY

~teoto e

Kr 87 Reactor Coolant Sample Containment Sump Number

+ Sample Number Act. x RCS Mass Act. x Sump Mass Ci Ci Ci Containment

+ Atmosphere Sample Act. x C.V. Vol.

Number

= Total Quantity.

Ci Xe 131m Xe 133 I 131 I 132 I 133 I 135 s 134 88 Te 129 Te 132 Ba 140 La 140 La 142 Pr 144's 137 A

C D

CORRECTED SOURCE INVENTORY EPIP 2-16:23 0, Rev. 9 Page 1 of 1

~leoto e

Equilibrium Source Invento Ci Power Correction Corrected Source Fraction Invento Ci Kr 87 Xe 131m Xe 133 I 131 I 132 I 133 I 135 1.6 x 1E3 38 x 1E2 7.6 x 1E4 1.2 x 1E5 2.0 x 1E4 8.3 x 1E4 4.2 x 1E4 Fuel Pellet Invento Kr 87 Xe 131m Xe 133 I 131 I 132 I 133 I 135 Cs 134 Rb 88 Te 129 Te 132 Sr 89 Ba 140 La 140 La 142 Pr 144 Cs 137 1.7 x 1E7 2.7 x 1E5 8.5 x 1E7 4.2 x 1E7 6.1 x 1E7 8.5 x 1E7 7.7 x 1E7 1.0 x 1E7 25 x 1E7 1.4 x 1E7 6.1 x 1E7 34 x 1E7 7.3 x 1E7 7.7 x 1E7 6.5 x 1E7 5.3 x 1E7 4.6 x 1E6 Additional information is available from Westinghouse Core Damage Assessment Methodology tables 2-2; 2-3; 2-3-1.

EPIP 2-16:24 Attachment 11, Rev. 9 Page 1 of1 RECORD OF FRACTIONALRELEASE

~tsoto e Ga Invento From Attachment 9 Total Quantity From Attachment 10

(¹9/¹1 0)

Available For Release Corrected Source Fraction Ci Gii Released Kr 87 Xe 131m Xe 133 I 131 I 132 I 133 I 135 Fuel Pellet Invento Kr 87 Xe 131m Xe 133 I 131 I 132 I 133 I 135 Cs 134 Rb 88 Te 129 Te 132 Ba 140 La 140 La 142 Pr 144 Cs 137

EPIP 2-16:25 2, Rev. 9 Page1 of1 GUIDANCE TO DATA NEEDED FOR CORE DAMAGEASSESSMENT ESTIMATION Primary System Sample Sump Sample Containment A~+ere Sample Collect Sample Ocgas Amph Hz Noble Gas Act.

Ckkulate total activity available in RCS Core tnventory Correction for Power Operation Sample Dilute Sample Take dilute sample for acl.

Calculate total activily available in RCS Collect Sample Dilute Sample Take dilute sample for act.

Correct forTemp. C Vol.. Calc. Total activity in sump Sum of total activity Released from Core Ca!c. % of Available Core Inventory Released Sample Ior actlvny Cor:eel lo Hain Cv Atmosphere Calc HgO-zr reaction Ill I

I t

I I

I I

I I

I I

I I

II

/

I I

Core jxitThermocouples Fstimate of Core Damage and Type Of Oamage uSing RarfIOiSOtOprC Activrties and available data points and Weitrnghouse Core Damage Assessmenl. Methodology Contarnmerlt Had>ation Monitors

EPIP 2-16:26 3, Rev. 9 Page 1 of 3 Figure I

Ratio of H,O Density to STP Density as a function of temperature 7CO

EPIP 2-16:27 3. Rev. 9 Page 2 of 3 Figure 2 - Gallon in Sump vs Sump Level Indication

~ ss04ISS4 I

>>sJ std %st 4sssls0QO IO CP0 4

~ Os0 0 s0 I0 OI004 I

I I

s

~

I I

I Il'

~ "

~

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I I

I

~

s I

I I

I I

s s

I0 0s000 I

~

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~

j.

'I I0OP00 40s0 II0 440 stS4 4'0 40P 00 O, 40,004 8

)0sOOO c

IOP@4 Nc0 laCOO ss ss Q

4040 IJCQ 4040 SC ~ O

~004.

)~ 00 I

~

=.

~ '

I l

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Sump "A," Full 45000 gallons

~

~

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s

~

~..).~..>> ~,I.

~

s I'

s PR4 J.

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's

~

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00

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IO0 IIIO t00 II~

>>V 0

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4 ~

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ss 4 SIT V ~

0 l04

'g U ZC xs

~ V

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Conversion Factor for gallons to cc is:

3785 cc/gallon s

~ ~s Ij!I I

sump "h" villfillfirst.

Overflow vill go to Sump "5",

then the Continment Basment will flood.,;..'..-,'V

~sC 10I4 44s

. ~.4 0 s

I s

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s

~ 0 t

~

s

>> ~

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l s

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e

~

0 5

10, 15 20 25 30 35 40 45 Sumo Level Readina in feet

EPIP 2-16:28 3, Rev. 9 Page 3 of 3 Figure 3 Containment Hydrogen Concentration vs. Zirconium Water Reaction 2$.0

24. 0 22.0
20. 0 la.a l4.0 l4.0 l2. 0 2 LGt lQ. 0 8.0 4.0 4.4 Z.O lo 2O l4 i4 N

40 7P ao N

100 LlRLNtta utQ aQCTtN (.)

CNTileCt7 ~vNOCQ CONCBTMTlN MQ Oa LIRt&tts WAR REACTlll

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