ML17311A069

From kanterella
Jump to navigation Jump to search
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)
v • d • e


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 POLFLETT,P.S.

RECIP.NAME VISSING,G.S.

AUTHOR AFF1LIAT1'ON Rochester Gas a Electric CorP. Pe.Vi/PJ g Q RECIPIENT AFFILIATION f

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 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL: AEOD/HAGAN,D 1 1 E CENTER 01 2 2 NRR/DRPM/PERB 1 1 1 1 EXTERNAL: NOAC 1 1 NRC PDR 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

~ me' i'm//

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 of our 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 of letter and 2 copies of each procedure)

Resident Inspector. Ginna Station (1 copy of letter and 1 copy of each procedure)

RGkE Nuclear Safety and Licensing (1 copy of letter)

Dr. Robert C. Mecredy (2 copies of letter only)

PSP/jem

'P'P0203033i 9'POi25 PDR ADQCK 05000244

~j. I V.

I 4'>

PROCEDURE REVISION NIJMBER E P 1-5 35 I'PIP

~

g"g

,;~

y~~~ggQ pg Rw~~ < 8'~~i x N // ~lwwwo~~ >>>>~

ROCHESTER GAS 8 ELECTRIC CORPORATION GINNA STATION

~

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 Attachment 5 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 Shift Su ervisor Emer enc Coordinator EOF/Recove Mana er 4

6.1.1 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. If the event is an Alert or higher, implement section 6.2.2.

6.1.4 If additional 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 Notifications

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 Attachment 1, Rev. 33 Page 1 of 3 UNUSUAL EVENT NOTIFICATIONS

1. Report information to NEW YORK STATE, WAYNE and 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 UNUSUAL EVENT 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? If not, 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.

Joe Widay Business 3250 Will Report (YES/NO)

Home, 716-586-2679 Pager 716-528-3977 Cellular 716-748-4681 OR Dick Marchionda Business 3699 Will Report (YES/NO)

Home 315-926-0324 Pager 716-464-4403 Cellular 716-748<682 OR Jack St. Martin Business 3641 Will Report (YES/NO)

Home 716-586-5676 Pager 716-464-7045 OR Tom Alexander Business 3898 Will Report (YES/NO)

Home 315-524-8084 Pager 716-783-7045

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

Jeff Wayland Business 3317 Will Report (YES/NO)

Home 315-524-2899 Pager 716-464-5445 OR Tom Harding Business 3384 Will Report (YES/NO)

Home 716-671-8756 Pager 716464-5485 OR Ron Ploof Business 3673 Will Report (YES/NO)

Home 716-381-9379 Pager 716-921-1722 OR Brian Flynn Business 3734 Will Report (YES/NO)

Home 716-293-1 565 Pager 716-464-5134 OR Peter Bamford Business 3832 Will Report (YES/NO)

Home 716-924-0490 Pager 716-528-3166 Operations Assessment Manager: Report to the TSC to support the Control Room with offsite communications.

Terry White Business 3667 Will Report (YES/NO)

Home 716-226-9381 Pager 716-464-7382 Cellular 716-748-4683 OR Pete Sidelinger Business 3509 Will Report (YES/NO)

Home 716-671-3198 Pager 716-463-9830 OR Mike Ruby Business 3572 Will Report (YES/NO)

Home 716-872-6559 Pager 716-783-6435

EPIP 1-5:6 Attachment 1, Rev. 33 Page 3 of 3 UNUSUAL EVENT NOTIFICATIONS D. USNRC Resident Inspector: Informational call only Pete Drysdale Business 3265 Home 716-385-6210 518-877-6103 Pager 1-800-994-2337 (then dial personal ID¹ 53133)

OR Clyde Osterholtz Business 3265 Home 716-785-4872 Pager: 1-800-994-2337 (then dial personal ID¹ 51578)

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 OR Frank Orienter Business 2265 Home 716-288-8076 Pager 716-527-5685 Cellular 716-729-7517 If the 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 Attachment 2, Rev. 33 Page 1 of2 ALERT OR HIGHER NOTIFICATIONS 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:

(Time from REGS form)

f. Message to deliver (circle one):

Drill Alert Site Area Emergency General Emergency

g. My current time is: . Please start notifications now.

Report information to NEW YORK STATE, WAYNE and 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.

Notify USNRC immediately after the notification of the State and Counties, using procedure 0-9.3, NRC Immediate Notification NRC Resident Inspector: Informational call only Pete Drysdale Business 3265 Home 716-385-6210

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

OR Clyde Osterholtz 'usiness 3265 Home 716-785-4872 Pager 1-800-994-2337 (then dial personal ID¹ 51578)

EPIP 1-5:8 Attachment 2, Rev. 33 Page 2 of 2 ALERT OR HIGHER NOTIFICATIONS If the 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. If requested by the TSC or EOF, the Control Room will fax 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 Attachment 3, Rev. 34 Page 1 of2 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICALEMERGENCY DATA FORMS 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 INDICATORAT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.

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

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

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

The communicator will initial the "prepared by" line at the bottom of the form. The SS/EC (or designee) will approve the form at the bottom prior to transmission. The communicator will ensure 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 if the 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)

Attachment 3a.

EPIP 1-5:10 Attachment 3, Rev. 34 Page 2 of 2 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICALEMERGENCY DATA FORMS

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)

Attachment 3b 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 9-1-315-946-9721 Monroe County 9-2564355 New York State 9-1-518<57-9942 TSC 3927 EOF 9-262-5788 Survey Center 3612 Joint Emergency News Center 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 if conditions change or when the event is terminated, check with the State/County warning points to see if they agree. If they all agree, note this in section 8 of the next Part 1 Form notification. The facility with 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. Attachment 3a, 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: 2. This is:

Date Time Via: A. REGS B. Other A. NOT an exercise B. An exercise

3. Facility providing information:

C. Ginna

4. Classification:

A. UNUSUAL EVENT D. GENERAL EMERGENCY G. TRANSPORTATION INCIDENT B. ALERT E. EMERGENCY TERMINATED C. SITE AREA EMERGENCY F. RECOVERY

5. Classification Time:

This Emergency Classification declared at: Date Time

6. Release of Radioactive Materials: (Refer to P-9l A. No Release above Technical Specifications C. Release to a Body of Water above Technical Specifications B. Release to the Atmosphere 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 E. Cold Shutdown A. Not Applicable B. Date Time B. Improving D. Hot Shutdown
11. Wind Speed: 12. Wind Direction:

A. Miles/hour at elevation feet From: dee eee at etoeattoo feet ~

13. Stability Class: Do NOT REPORT 14. Reported By:

Stability Class Work Sheet Unstable, Neutral, Stable Name Temperature at 250 feet 'F Temperature at 33 feet 'F Area Code Number Temperature Difference 'F

-1.74 -0.65 Unstable Neutral I Stable

-3 -2 -1 0 1 Temperature Difference Roll Call Response: New York State Warning Point 0 Monroe County 0 Wayne County 0 FOR RG8rE USE ONLY:

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

EPIP 1-5:12 Attachment 3b, Rev. 34 Page 1 of1 NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (PART II)

Telefax this data form to: 0 New York State 0 Monroe County G Wayne County

15. Message transmitted at:

Date Time Location/Facility Transmitted From:

16. General Release Information A. Release > Tech Specs started: Date Time B. Release > Tech Specs expected to end: Date Time OR 0 Unknown C. Release > Tech Specs ended: Date Time D. Reactor Shutdown: N/A OR Date Time E. Wind Speed: miles/hour at elevation feet F. Wind Direction from: degrees at elevation feet G. Stability Class: PASQUILL A B C D E F G OR Other
17. Atmospheric Release Information A. Release from: 0 Ground 0 Elevated D. Noble Gas Release Rate Ci/sec B. Iodine/Noble Gas Ratio E. Iodine Release Rate Ci/sec C. Total Release Rate Ci/sec F. Particulate Release Rate Ci/sec
18. Waterborne Release Information A. Volume of Release gal or liters C. Radionuclides in Release B. Total Concentration yci/ml D. Total Activity Released
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) A. Atmosphere Release B. Waterborne Release Dose Distance Xu/Q TEDE (rem) CDE - Child Thyroid Irem)

Site Boundary 2 Miles 5 Miles 10 Miles Miles 20.Field Measurements of Dose Rates or Surface Contamination/Disposition Dose Rate OR Miles/Sector OR Location OR Sampling Point Time of Reading Contamination Miles/Degrees Ilnclude Units)

FOR RG8E USE ONLY: Time Prepared: Time Approved:

By: By:

Completed form sent to CNEP - 49/2

EPIP 1-5:13 Attachment 3c, Rev. 34 Page 1 of1 INSTRUCTIONS FOR EVENT 1 AND EVENT 2 PRINTOUTS AND PLANT STATUS REPORT Assure the Plant Process Computer System (PPCS) is operational. If PPCS is not operational, go to step 5.

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

Obtain Event 1 and Event 2 printouts by entering:

GASR <return>

Computer response - Enter Group Name EVE NT1 <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 Verify with 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. If the 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.

If the 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, if the 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 Attachment 3d, Rev. 34 Page1 of1 EVENT 1 SUPPLEMENTAL INFORMATION FORM 61 Aux Feedwater System In service Standby QOS 62 Safety Injection System Inservice Standby OOS 63 Diesel Generators In service Standby OOS 64 Containment Fan Cooler Inservice Standby OOS System 65 Service Water System Insewice Standby OOS 66 Post Accident Charcoal Inservice Standby OOS Filters 67 Containment Spray Pumps Inservice Standby OOS 68 Component Cooling System In service Standby OOS 69 DC System B v 70 NaOH Tank Level Time Completed:

Completed By:

EPIP 1-5:15 Attachment 3e, Rev. 34 PLANT STATUS REPORT PPCS NOT AVAILABLE) Page1 of1 Plant Parameters Plant Parameters Radiation Monitoring Auxiliary Feedwater Inservice R-1 Control Room Reactor Shutdown YES/NO TIME System Standby Mrem/hr OOS Inservice R-2 Containment RCS Pressure PSIG Safety Injection Standby Mrem/hr OOS Inservice R-9 Letdown PRZR Level Diesel Generators Standby Mrem/hr OOS Inservice. R-10 "A" Containment Iodine Core Circulation Forced/Natural Service Water System Standby CPM OOS

'F Cnmt Fan Coolers System Inservice R-11 Containment Particulate Subcooled Standby CPM OOS A" S/G Level Post Acc. Charcoal Filter Damper Damper R-12 Containment Gas CPM Open / Closed "8" S/G Level Cnmt. Spray Inseivice R-10 "B" Plant Vent Iodine Standby CPM Cnmt. Spray Inservice Pumps Standby OOS Comp. Cooling System Inservice R-13 Plant Vent Particulate "A" S/G Pressure PSIG Standby CPM OOS "8" S/G Pressure PSIG D.C. System R-14 Plant Vent Gas Volts CPM Safeguard Train B (16/17) NaOH Tank Level R-29 Containment High Range EDG/Turbine/Offsite Offsite Power Available/Unavailable RWST Level R-30 Containment High Range Cnmt Pressure PSIG B.A. Tank Level R-15 Air Ejector Gas CPM Sump "A Level FT Wind Speed 'R-12A SPING Containment Gas MPH Sump "8" Level IN Wind Direction (From) 'R14A SPING Plant Vent Gas Degrees IiCi/cc RCS Temp 'F Temperature 33 FT 0F 'R-15A SPING Air Ejector Gas pCi/cc RVLIS Temperature 250 FT 0F R-31 Steam Line "A" Mrem/hr CET R-32 Steam Line "B" Mrem/hr R/hr = Roentgen/Hour 'SPING Unit readigs may be deleted if Date pCi/cc =Microcuries/Cubic Centimeter radiation monitors R-12 and R-14 onTime Completed Mrem/hr = Millirem/Hour scale. Completed By

EPIP 1-5:16 Attachment 4, Rev. 34 Page1 of5 SPECIALIZED NOTIFICATION LIST Medical

1. Ontario Volunteer Emergency Squad 769-911 (Ginna Control Room Only)

(To request ambulance)

.9-1-315-524-5757 (Business number)

2. Wayne County Emergency Dispatcher 9-1-315-946-5304
3. Rochester General Hospital, 9-338-2300 Emergency Department Triage Nurse
4. Rochester General Hospital Main Switchboard 9-338-4000
5. RG8E Medical Services Office 8600 Alternate Office 4616 Answering Service 9-226-3800 Dr. Robert W. George Dr. T. K. Oates Dr. Alexander Kurchin
6. Newark-Wayne Community Hospital 9-1-315-332-2267 Police
1. New York State Police Warning Point 9-1-518<57-2200 9-1-315-457-6811
2. Canandaigua State Police 9-398-3200
3. Williamson State Police 9-1-800-962-0810
4. Wayne County Sheriff 9-1-315-946-9711
5. Monroe County Sheriff 9-428-5511 Fire
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 Attachment 4, Rev. 34 Page 2 of 5 SPECIALIZED NOTIFICATION LIST 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.

1. Hank Sepp 9-1-412-374-5282 Director ESBU Emergency Response Home 9-1-412-856-4036 Hotline 9-1-412-856-6121
2. Dan Lipman 9-1-412-374-6920 ESBU Service Response Manager Home 9-1-412-744-3244
3. Rose Cotton 9-1-412-374-6805 ESBU Emergency News Home 9-1-412-963-6129 Communications ENC Manager
4. Mike Young 9-1-412-374-5081 ESBU Emergency Response Home 9-1-412-243-7996 Technical Support Manager
5. Tom Hart 9-1-412-374-6980 ESBU Emergency Response Home 9-1-412-837-9486 Logistic Manager Hotline 9-1-412-837-1737 Pager 9-1-412-765-8886 Other
1. Ontario Town Supervisor, Office 9-1-315-524-7105 Roy Herrmann Home 9-1-315-524-8087
2. Ontario Water Department 9-1-315-524-2941
3. Plant Protection Department 9-722-2122 Kodak Park
4. Wayne County Emergency 9-1-315-946-5663 Operations Center
5. Director Wayne County Home 9-1-315-597-6291 Office of Disaster Preparedness-Thelma Wideman
6. Monroe County Office of Daytime 9-473-0710 Emergency Preparedness Offhours 9-528-2222 (Nights, Weekends, Holidays)

EPIP 1-5:18 Attachment 4, Rev. 34 Page 3of5 SPECIALIZED NOTIFICATION LIST (Cont'd.)

7. Administrator, Monroe County Home 9-624-3194 Office of Emergency Preparedness- Pager 9-428-5141 Mary Louise Meisenzahl
8. University of Rochester Advance Home 9-275-3788 RAP Team - David Maillie 9-334-2428
9. National Weather Service (Buffalo) 9-1-800<62-7751
10. Radiation Management Consultants Office 9-1-215-824-1300 Emergency 9-1-215-243-2990 Fax 9-1-215-824-1371
11. Helgeson Nuclear Services Inc 9-1-415-846-3453
12. James C. Hutton (NSARB) 9-1-716-381-8473
13. Institute of Nuclear Power Operations 9-1-800-321-0614
14. American Nuclear Insurers 9-1-203-677-7305
15. Emergency Preparedness Canada Phone 9-1-613-991-7000 Fax 9-1-613-996-0995
16. NYPA Environmental Laboratory Daytime 9-1-315-593-5740 Fulton, New York 9-1-315-593-5735 Lab 9-1-800-436-2732 Manager ¹ enter pager 713-6710 pager then your number Mgr Home¹ 9-1-315-342-0015 RES on call 9-1-800-436-2732 pager ¹ enter pager 713-6726 then your number

EPIP 1-5:19 Attachment 4, Rev. 34 Page 4 of 5 SPECIALIZED NOTIFICATION LIST (Cont'd.)

Com an Personnel Thomson, Bill Business 3219 Manager, Radiation Protection Home 315-342-5082 and Chemistry Pager 716-528-8561 Richards, Thomas Business 8299 Chief Executive Officer Home (716) 288-9186 Lappan, George Business 8812 Manager of Corporate Home 716-377-2490 Communications Mecredy, Robert Business 3494 Vice President Home 716-381-6430 Nuclear Operations Pager 716-783-4900 Wilkens, Paul Business 8076 Sr. Vice President Home 716-248-2385 Generation Pager: 716-529-6426 Watts, Richard Business 8706 Manager, Nuclear Training Home 716-425-2644 Pager 716-527-3749 Cellular 716-747-9760 Nuclear Re ulato Commission Nuclear Regulatory Commission 610-337-5000 Region 1 - King of Prussia, PA Radiation Assistance Program 516-282-2200 Dept of Energy Brookhaven National Lab

3. Commercial telephone system to 301-951-0550 NRC Operations Center (via Bethesda Central Office)

Commercial telephone system to 301-427-4056 NRC Communications Center (via Silver Spring Central Office)

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

EPIP 1-5:20 Attachment 4, Rev. 34 Page 5 of 5 SPECIALIZED NOTIFICATION LIST (Cont'd.)

New York State

1. James Baranski, 518-457-8909 State Emergency Management Office (SEMO)
2. SEMO Lake District 315-331-4880
3. NYS Department of Health 716-262-2010 Rochester Office
4. New York State Emergency 518<54-3337 Operations Center (EOC) Albany
5. EOC Albany - Dose Assessment 518-454-3321 518-454-2176 Federal Emergency Management Agency (FEMA)
1. Emergency Information Coordination 202-634-7800 Center 202-646-2400

EP IP 1-5:21 Attachment 5, Rev. 34 Page 1 of 3 NOTIFICATIONS WHEN 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 Notify the 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)

Joe Widay Business 3250 Available (YES/NO)

Home 716-586-2679 Pager 716-528-3977 Cellular 716-748-4681 OR Dick Marchionda Business 3699 Available (YES/NO)

Home 315-926-0324 Pager 716-464-4403 Cellular 716-748-4682 OR Bob Mecredy Business 8069 Available (YES/NO)

Home 716-381-6430 Pager 716-783-4900 The nuclear management representative may call other nuclear managers or members of the Ginna leadership team.

EPIP 1-5:22 Attachment 5, Rev. 34 Page 2 of 3 NOTIFICATIONS WHEN 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 I

can be reached at ~

Emer enc Plannin (One person required to respond)

Peter Polfleit Business 6772 Home 716-654-5325 Pager 716-527-2207 Cellular 716-733-2207 Frank Cordaro Business 3108 Home 315-524-2924 Pager 716-527-3650 Cellular 716-729-4613 OR Richard Watts Business 8706 Home 716-425-2644 Pager 716-527-3749 Cellular 716-747-9760 OR Frank Orienter Business 2265 Home 716-288-8076 Pager 716-527-5685 Cellular 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 will determine if a media announcement is warranted. The Emergency Planning representative will also contact Wayne County, Monroe County and New York State officials to brief them on offsite resources being used

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

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

OR Clyde Osterholtz Business 3265 Home 716-785-4872 Pager 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 ~PRERE UIEITEE 5.1 Isotopic analysis of primary liquids.

5.2 Data from plant radiation monitors.

5.3 Plant operational status including pertinent core data.

Isotopic analysis of containment atmosphere

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

58 Data from core exit thermocouples.

6.0 ACTIONS 6.1 Initial Assessment of Core Damage 6.1.1 Core damage will be initially classified 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 No Damage Gap Activity Fuel Activity R-9 <2000 mR/hr. 2000 = 1% N/A (if not isolated) 5000 = 5%

R-29/30 <100 R/hr >100 >1000 R/hr (approx: 10 R/hr R/hl'50 for a LOCA)

Core Exit <750 F F - 1650 F >1650 F Thermocouples Containment None detectable None detectable >1%

Hydrogen 6.1.3 Other indications that core damage may be taking place:

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

If there 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 if the core has remained covered.

The top of the core, using RVLIS indication, is 78%. If the core has remained covered, core damage should be limited to gap released from cladding defects. However, if the 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 if the 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 Attachment 2 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 if there 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 Air Activity 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 Isotopes Released No Damage 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 0.022 0.22 I-132/I-131 0.17 1.5 I-133/I-131 0.71 2.1 I-135/I-131 0.39 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 PSIG Temperature F Reactor Vessel level Pressurizer level Containment Building:

Atmosphere Pressure PSIG Atmosphere Temperature oF A. Sump level Feet B. Sump level 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 DETERMINATION OF THE MASS IN THE RCS MUST BE ESTIMATED BY INDICATIONS AVAILABLETO 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 Attachment 13. 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).

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

6.4 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 CALCULATE A 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-LIVES GREATER 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 CONTAINMENT FORMED BY A ZIRCONIUM-WATER REACTION IN THE CORE. IF VESSEL FAILURE HAS OCCURRED FOLLOWING CORE DAMAGE, ADDITIONALH MAY BE GENERATED DUE TO CORE CONCRETE INTERACTION. THIS ADDITIONALH~ IS NOT ACCOUNTED FOR IN THE CALCULATIONS WITHIN THIS SECTION.

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

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

CAUTION THE MAXIMUMVALUE THAT % 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:

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

FZWR = Fraction of Zirconium-Water Reaction V = Containment volume, SCF, approx. 9.7E5 ft'M Total zirconium mass, approx. 23,900 lbs.

I H 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 Attachment 1, Rev. 9 Page 1 of 1 POSSIBLE CORE DAMAGE STATES AS CORE TEMPERATURE INCREASES 5100'" .VI f I TING QF FUEL PEL'TS IVOR) t30BB KI

+RELEASE OF ALL VOLATII.EFISSION PROOUCTS FROM FUEL 3600iF FQRMATION OF "LIQUEFIE0 FUEL" - F UEL OISSQLVES IN l2255 KI MELTEO COMPONENTS 4+g a,g4 g48C

~44 4E~

ggo VERY RAPIO RELEASE QF IOOINE, CESIUM, ANO NOBLE GASES FROM FUE 2200 F STEAM ZIRCALLQY REACTION RELEASES H~

(1477 K) 2000'F (13N. K) 4 CI CI Cab CLAOOINQ BURST: RELEASE OF QAP INVENTORY FROM FUEL PIN

~

4l

{1')

1400 F 1200'F CLAOOINQ COLLAPSE PQSSIBI.E (920 K)

NORMALOPERATINQ TEMPERATURE

EPIP 2-16:13 Attachment 2, 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 GJ 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 Attachment 2, 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 10 0 100 Fuel Release 105 10 O 10 CI 10 10 10 I I 0

Time (hours)

Cnntainment high Range tOeteern7 0nse Rates.(g

EPIP 2-16:15 Attachment 3, Rev 8 Page 1 of1 Containment Activity (uCI/cc) for a 100% Release of the Coolant Activity ISOTOPE SUBCRITI GAL TIME (hours) 0.0 0.5 2.0 8.0 Kr-85m 1.31-2* 1.21-2 9.54-3 3.69-3 Kr-85 1.75-2 1.77-2 1.82-2 1.95-2 Kr-87 7.59-3 5.79-3 2.58-3 1.01-4 Kr-88 2.03-2 2.03-2 1.40-2 3.15-3 Xe-131m 0.00+0 6.51-8 2.59-7 1.02-6 Xe-133m 0.00+0 3.14-6 1.21-5 4.23-5 Xe-133 1.54+0 1.54+0 1.52+0 1.48+0 Xe-135m 0.00+0 4.60-5 5.42-5 2.91-5 Xe-135 5.13-2 4.97-2 4.51-2 3.05-2 Xe-138 2.92-1 6.79-2 8.56-4 2.16-11 Br-84 1.22-4 6.38-5 9.13-6 3.83-9 l-131 6.10-3 6.09-3 6.06-3 5.93-3 l-132 2.69-3 2.31-3 1.47-3 2.39-4 I-133 7.90-3 7.77-3 7.39-3 6.04-3 I-134 1.59-3 1.07-3 3.26-4 2.82-6 I-135 6.'I 0-3 5.79-3 4.95-3 2.65-3 Rb-88 0.00+0 1.56-3 1.64-3 3.74-4 Cs-138 0.00+0 1.53-1 3.78-2 1.65-5 TOTAL 1.97+0 1.89+0 1.67+0 1.55+0

  • Note 1.31-2 denotes 1.31 x 10'

EPIP 2-16:16 Attachment 4, Rev. 9 Page1 of1 Containment Activity (uCI/cc) for a 100% Release of the Gap Activity (RG 1.25)

ISOTOPE SUBCRITICAL TIME (hours) 0.0 0.5 2.0 8.0 Kr-85m 3.64+2* 3.36+2 2.65+2 1.03+2 Kr-85 4.26+0 1.01+1 2.50+1 5.92+1 Kr-87 6.92+1 5.28+1 2.35+1 9.20-1 Kr-88 1.06+2 9.36+1 6.45+1 1.45+1 Xe-131m 0.00+0 8.54-4 3.40-3 1.34-2 Xe-133m 7.28+0 7.29+0 7.32+0 7.36+0 Xe-133 2.88+2 2.90+2 2.94+2 3.09+2 Xe-135m 0.00+0 9.88-1 1.16+0 6.26-1 Xe-135 5.46+1 5.81+1 6.88+1 8.30+1 I-131 8.00+1 7.99+1 7.94+1 7.78+1 I-132 1.09+2 9.37+1 5.95+1 9.70+0 I-133 1.46+2 1.44+2 1.37+2 1.12+2 I-134 1.68+2 1.13+2 3.45+1 2.98-1 1-135 1.31+2 1.24+2 1.06+2 5.68+1 Rb-88 0.00+0 7.21+0 7.54+0 1.73+0 TOTAL 1.53+3 1.41+3 1.17+3 8.35+2

  • Note 3.64+2 denotes 3.64 x 10'

EPIP 2-16:17 Attachment 5, Rev. 9 Page 1 of 1 Containment Activity (uCI/cc) for a 100% Release of the Gap Activity (WCAP 7828)

ISOTOPE SUBCRITICAL TIME (hours) 0.0 0.5 2.0 8.0 Kr-85m 1.06+0* 9.79-1 7.72-1 2.99-1 Kr-85 3.63+0 3.65+0 3.69+0 3.79+0 Kr-87 1.52+0 1.16+0 5.16-1 2.02-2 Kr-88 3.06+0 2.70+0 1.86+0 4.19-1 Xe-131m 0.00+0 2.11-4 8.42-4 3.31-3 Xe-133m 1.00+0 9.99-1 9.94-1 9.69-1 Xe-133 5.81+1 5.81+1 5.83+1 5.85+1 Xe-135m 0.00+0 4.84-2 5.70-2 3.07-2 Xe-135 3.44+0 3.59+0 4.03+0 4.48+0 l-131 1.98+1 1.98+1 1.97+1 1.92+1 I-132 3.17+0 2.73+0 1.73+0 2.82-1 l-133 1.22+1 1.20+1 1.14+1 9.33+0 I-134 3.01+0 2.03+0 6.18-1 5.33-3 I-135 6.42+0 6.09+0 5.21+0 2.78+0 Rb-88 0.00+0 2.08-1 2.18-1 4.98-2 TOTAL 1.16+2 1.14+2 1.09+2 1.00+2 "Note 1.06+0 denotes 1.06 x 10'

EPIP 2-16:18 Attachment 6, Rev. 9 Page 1 of 1 Containment Activity (uCI/cc) for a 1% release of the Fuel Inventory ISOTOPE SUBCRITICAL TIME (hours) 0.0 0.5 2.0 8.0 Kr-83m 1.20+0* 1.01+0 5.93-1 7.26-2 Kr-85m 3.60+0 3.33+0 2.62+0 1.01+0 Kr-85 1.40-1 1.98-1 3.45-1 6.83-1 Kr-87 7.00+1 5.34+0 2.38+0 9.31-2 Kr-88 1.00+1 8.83+0 6.08+0 1.37+0 Xe-131m 1.20-1 1.20-1 1.20-1 1.18-1 Xe-133m 1.80+1 1.79+1 1.76+1 1.63+1 Xe-133 2.90+1 2.92+1 2.96+1 3.1 1+1 Xe135m 8.00+0 2.16+0 9.75-2 3.15-2 Xe-135 5.50+0 1.13+1 1.29+1 1.02+1 X3-138 2.90+1 6.75+0 8.50-2 2.14-9 Br-83 3.00-2 2.60-2 1.69-2 3.00-3 Br-84 7.20-2 3.77-2 5.39-3 2.26-6 l-131 3.90+0 3.89+0 3.87+0 3.79+0 I-132 5.60+0 4.81+0 3.06+0 4.98-1 I-133 7.40+0 7.28+0 6.92+0 5.66+0 I-134 8.50+0 5.72+0 1.74+0 1.51-2 l-135 6.60+0 6.26+0 5.36+0 2.86+0 Rb-88 0.00+0 6.80-1 7.12-1 1.63-1 Cs-138 0.00+0 1.52+1 3.76+0 1.64-3 TOTAL 1.44+2 1.30+2 9.78+1 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 Attachment 7, Rev. 9 Page 1 of 1 LIQUID SAMPLE WORKSHEET Sample Number:

Sample Location:

Time of Analysis:

Temperature, 'F:

Pressure, PSIG:

  • Sample Activity uCi/gm Mass of x liquid x 1E-6 Ci/uCi = Corrected at time of reactor shut- sampled (gm) total Activity down Released (Ci)

Kr 87 Xe 131m 1E-6 Xe 133 1E-6 I 131 1EW 32 1E-6 133 1E-6 I 135 1E-6 Cs 134 Rb 88 1E-6 Te 129 1E-6 Te 132 1E-6 Ba 140 1E-6 La 140 1E-6 La 142 1E-6 Pr 144 1E-6 Cs 137 1E-6

  • Use reactor shutdown as T,

EPIP 2-16:20 Attachment 8, Rev. 9 Page 1 of 2 CONTAINMENTATMOSPHERE WORKSHEET Sample Number:

Sample Location:

Time of Analysis:

Temperature, F:

Pressure, PSIG:

Total

~leoto e Act, Activity Atmosphere, CV Volume CV Atmos.,

uCi/cc* 2.75E10 cc x 1E-6 Ci/uCi Ci Kr 87 2.75E10 1E-6 Xe 131m 2.75E10 1E-6 e 133 2.75E10 1E-6 31 2.75E10 1E-6 I 132 2.75E10 1E-6 I 133 2.75E10 1E-6 I 135 2.75E10 1E-6 Cs 134 2.75E10 1E-6 Rb 88 2.75E10 1E-6 Te 129 2.75E10 1E-6 Te 132 2.75E10 1E-6 Ba 140 2.75E10 1E-6 La 140 2.75EI0 1E-6 La 142 2.75E10 1E-6 Pr 144 2.75E10 1E-6

$ 137 2.75E10 1E-6

EPIP 2-16:21 Attachment 8, 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 Attachment 9, Rev. 9 Page1 of 1 SUMMATION RECORD OF RELEASE QUANTITY Reactor Coolant Sample Containment Sump Containment Number + Sample Number + Atmosphere Sample = Total Act. x RCS Mass Act. x Sump Mass Act. x C.V. Vol. Quantity.

~teoto e Ci Ci Number Ci Ci Kr 87 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

EPIP 2-16:23 Attachment 10, Rev. 9 Page 1 of 1 CORRECTED SOURCE INVENTORY

~leoto e Equilibrium Source Power Correction Corrected Source Invento Ci Fraction Invento Ci Kr 87 1.6 x 1E3 Xe 131m 38 x 1E2 Xe 133 7.6 x 1E4 I 131 1.2 x 1E5 I 132 2.0 x 1E4 I 133 8.3 x 1E4 I 135 4.2 x 1E4 Fuel Pellet Invento Kr 87 1.7 x 1E7 Xe 131m 2.7 x 1E5 Xe 133 8.5 x 1E7 I 131 4.2 x 1E7 I 132 6.1 x 1E7 I 133 8.5 x 1E7 I 135 7.7 x 1E7 Cs 134 1.0 x 1E7 Rb 88 25 x 1E7 Te 129 1.4 x 1E7 Te 132 6.1 x 1E7 Sr 89 34 x 1E7 Ba 140 7.3 x 1E7 La 140 7.7 x 1E7 La 142 6.5 x 1E7 Pr 144 5.3 x 1E7 Cs 137 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 FRACTIONAL RELEASE From Attachment 9 Total Quantity From Attachment 10 (¹9/¹1 0)

Available For Release Corrected Source Fraction

~tsoto e Ci Gii Released Ga Invento 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 Attachment 12, Rev. 9 Page1 of1 GUIDANCE TO DATA NEEDED FOR CORE DAMAGE ASSESSMENT ESTIMATION Primary System Sample Sump Sample Containment A~+ere Sample Collect Sample Sample Collect Sample Sample Ior Hain Cv actlvny Atmosphere Ocgas Amph Dilute Sample Dilute Sample Cor:eel lo Calc HgO-zr Hz Noble Gas Act. Take dilute Take dilute reaction sample for acl. sample for act.

I l

Ckkulate total activity Calculate total activily Correct for Temp. C l available in RCS available in RCS Vol.. Calc. Total activity I in sump I t

I I

I I

I I

Sum of total activity I Core tnventory Released from Core I I

I Correction for Ca!c. % of Available I Power Operation Core Inventory Released I

/

I I

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

EPIP 2-16:26 Attachment 13, 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 Attachment 13. Rev. 9 Page 2 of 3 Figure 2 - Gallon in Sump vs Sump Level Indication

~ ss04ISS4 I

>>sJ std %st I I 4sssls0QO IO CP0 4 s

I

~ I Il' I I

~ " "' ~ ' I s s

~ Os0 0 s0 I I I I ~

s I0 OI004 I I I I I I ~

. I I ~ j. 'I I0 0s000 I0OP00 40s0 II 0 440 stS4 4'000 40P Sump "A," Full 45000 gallons O, 40,004 8

)0sOOO I ~ 'I ~ I c

IOP@4 N =. ~

I

(

I.. ~ ~ ~ s ~

c l 0 I laCOO I l ~ ..).~..>> ~,I . ~

ss ss Q 4040 s I' s ~ '

IJCQ 4040 PR4 J. I V.J L',

~ I SC ~O

~ 004. 's ~

) ~ 00 I I I ~

0

~

0 s

l040 I- ~: s s

~ ~

0 vill fill IO44

>>ss 4~ 440 ! sump "h" vill first.

V~

J IO0 Overflow go to Sump "5",

ss 4 SIT IIIO then the Continment Basment will t00 flood.,;..'..-,'V V~

'g U 0 l04 Conversion Factor for gallons to cc is: ~ ~s s

ZC xs 3785 cc/gallon

~V II ~

>>V Ij!I I

. ~ .4 0 ~ 0

>> ~

~ ~

~ sC 10I4 44s s I s I I I I t ~

s s

s s I I I  ! I e ~

I I s

l 0 5 10, 15 20 25 30 35 40 45 Sumo Level Readina in feet

EPIP 2-16:28 Attachment 13, 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 2 LGt l2. 0 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

Retrieved from "https://kanterella.com/w/index.php?title=ML17311A069&oldid=2427926"