ML023370018

Emergency Plan Offnormal Occurrence Procedure RA-EP-02870, Revision 2

ML023370018
Person / Time
Site:	Davis Besse
Issue date:	11/13/2002
From:	FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
0211-17050
Download: ML023370018 (88)

Text

Davis Besse Power Station Transmittal / Receipt Acknowledgement

(

To:' DOC. CONTROL DESKZ

'.Mal.S I6j /Address: ý" USNRC DIVISION OF EMERGENCY PREPARDNESS WASHINGTON, D.C. 20555 Document holders are responsible for control and maintenance of documents in accordance with the actions specified by this transmittal. Outdated material shall either be removed and destroyed or marked to reflect that it is superseded or voided and is no longer considered controlled.

Note: Destroy Safeguard information by shredding.

File documents in tab order as identified on the Table of Contents Contact Document Control with any questions at (419)-321-7483 Control Copy Number: 1665 Transmittal Number:

0211-17050 Transmittal Date:

11-13-2002

(i Davis Besse Power Station Transmittal / Receipt Acknowledgement 1665 0211-17050 11-13-2002 Document TOC 1 TOC 2 Type Number old PIA PROC new EPIA B-01900 old PROC RA.EP-01900 new f,-Tr-old EPOC EPON PROC RA-EP-02870 new EPOC EPON PROC RA-EP-02870 Sht/Sec Changes Rev Status 0001 APPROVED 0002 APPROVED Control Copy Number:

Transmittal Number:

Transmittal Date:

Page 1 of 16 Davis-Besse Nuclear Power Station EMERGENCY PLAN OFFNORMAL OCCURRENCE PROCEDURE RA-EP-02870 STATION ISOLATION Revision 02 Prepared by:

Procedure Owner:

Effective Date:

Craig Stachler Manager - Security NOV 13 2002 '

Procedure Classification:

Safety Related Quality Related X

Non-Quality Related LEVEL OF USE:

IN-FIELD REFERENCE

2 RA-EP-02870 Revision 02 TABLE OF CONTENTS Page 1.0 PURPOSE.............................................................................

3

2.0 REFERENCES

3 3.0 DEFINITIONS..................................................................................................

3 4.0 RESPONSIBILITIES...................................................................................

4 5.0 INITIATING CONDITIONS........................................................................

4 6.0 PROCEDURE..............................................................................................

5 6.1 Isolation Watch...............................................................................

5 6.2 Isolation Warning............................................................................

6 6.3 Station Isolation..............................................................................

9 6.4 Deactivation.....................................................................................

10 7.0 FINAL CONDITIONS.................................................................................

11 8.0 RECORDS.........................................................................................................

11 ATTACHMENT 1 Minimum Supplemental Station Isolation Staffing................ 12 ATTACHMENT 2 Emergency Vehicle List.......................................................

13 ATTACHMENT 3 Inventory Sign Out/Sign In Checklist.....................................

14 ATTACHMENT 4 Terms Commonly Used During Adverse Weather Conditions..............................................................

15 COMMITMENTS.......................................................................................................

16 I

3 RA-EP-02870 Revision 02 1.0 PURPOSE This procedure describes measures to be taken if the Davis-Besse Nuclear Power Station (DBNPS) is or is likely to become isolated.

2.0 REFERENCES

2.1 Developmental 2.1.1 Davis-Besse Nuclear Power Station (DBNPS) Emergency Plan 2.1.2 Emergency Plan Telephone Directory 2.1.3 Human Resources Letter 513: Pay in Adverse Weather/Emergency Situations 2.2 Implementation 2.2.1 NOP-LP-1002, Fitness for Duty Program 2.2.2 RA-EP-00600, Emergency Facilities and Equiprmeni Maintenance Program 3.0 DEFINITIONS 3.1 ADVERSE WEATHER CONDITIONS - Weather conditions which can disrupt normal vehicular transportation to and from DBNPS. These conditions are primarily winter storms and flooding.

3.2 CONTINUOUS STATION ISOLATION PREPARATIONS - Actions taken in' advance to minimize discomfort for persons who are stranded at DBNPS. These preparations include storage and maintenance of isolation supplies and the staging of Isolation Supply Trailers.

3.3 ISOLATION WATCH - Adverse weather has formed and is approaching the area.

3.4 ISOLATION WARNING - A formal notice that DBNPS may be isolated from normal vehicular transportation by adverse weather conditions.

3.5 STATION ISOLATION - DBNPS will be considered isolated when normal vehicular transportation to and from the station is no longer possible.

3.6 ISOLATION SUPPLY TRAILER(S) - Three trailers contain basic supplies for 50 people for two days; and one trailer contains supplies for 100 people for two days.

3.7 STAGING - The act of relocating one or more of the Station Isolation Supply Trailers in preparation for use.

3.8 EMERGENCY VEHICLES - Any vehicle which may be utilized during an emergency (salt truck, ski-dozer, etc.).

3.9 DISMISS - As used in this procedure, dismissed personnel are not required for continued station operation. Dismissed personnel may stay at DBNPS or they may leave if they wish.

4 RA-EP-02870 Revision 02 4.0 RESPONSIBILITIES 4.1 The Supervisor - Emergency Preparedness shall maintain food supplies and sleeping facilities as defined in RA-EP-00600, Emergency Facilities and Equipment Maintenance Program.

4.2 The Shift Manager is responsible for declaring Isolation Watches, Warnings and Station Isolations when weather conditions necessitate these declarations.

4.3 Other positions with responsibilities in this procedure are: The Emergency Plant Manager, the Shift Engineer, the Supervisor - Security Shift, and the Isolation Coordinator.

4.4 Davis-Besse Nuclear Power Station Personnel:

a.

should monitor local television and radio stations for weather and road conditions.

b.

shall not contact the Control Room for weather and road reports.

c.

shall carry their Company identification card whenever performing Company business.

d.

are responsible for leaving their work area in a safe condition.

5.0 INITIATING CONDITIONS This procedure shall be utilized by the Shift Manager during station isolation. Station isolations are typically caused by adverse weather conditions such as snow storms, ice storms, and flooding.

I

5 RA-EP-02870 Revision 02 6.0 PROCEDURE r -------------------------------------------------

I NOTE 6.1

1. An Isolation Watch is used to increase station and On Call Management's'awareness of the potential for adverse offsite Sroad conditions, and to prestage equipment and personnel.

2. Refer to Attachment 4, Terms Commonly Used During Adverse Weather Conditions.

6.1 Isolation Watch 6.1.1 The Shift Manager and Emergency Plant Manager, utilizing available information, evaluate projected severe weather conditions which may impact access to station.

Note:

Available Information-Sources are:

Distribution Dispatcher (Delaware Service Center)

System Dispatcher (System Operation Center),

Periodic weather reports received on Control Room fax machine Looal weather reports Reports from staff Other 6.1.2 If the assessment determines that projected weather may impact access, the following should occur:

a.

Evaluate consumable resources: fuel oil, compressed gases, gasoline, etc.,

necessary for continued plant operation and, as appropriate, arrange delivery prior to the storm.

b.

Ensure proper staging of an Isolation Suppiy Trailer as needed for the Protected Area. Primary staging for the Protected Area is the north side of Service Building 6. Consideration should be given to staging the trailer out of the weather if possible (inside Service Building 6 or the Turbine Building Train Bay).....

c.

Fuel and shelter designated enmergency vehicles, e.g., snow plows.

d.

Notify the following continuous service personnel: Maintenance, Security, Radiation Protection-and Chemistry.

6 RA-EP-02870 Revision 02 NOTE 6.1.2.e

1. Call-outs of personnel are subject to the requirements of NOP-LP-1002, Fitness for Duty Program.

2. As appropriate, establish conference calls between selected personnel.

e.

Evaluate plant needs and place on standby those personnel which may be called in. At a minimum, call in the following on-call personnel when an isolation warning is issued:

Emergency Plant Manager Emergency Assistant Plant Manager Emergency Offsite Manager 6.2 Isolation Waming 6.2.1 When the Distribution Dispatcher (Delaware Service Center), the System Dispatcher (System Operation Center) or any other credible source indicates that weather conditions will impact or are impacting station access to the point that conditions will result in a Station Isolation the Shift Manager shall:

a.

Issue an Isolation Warning with the concurrence of the Emergency Plant Manager.

NOTE 6.2.1.b

1. Call-outs of personnel are subject to the requirements of NOP-LP-1002, Fitness for Duty Program.

I

2. As appropriate, establish conference calls between selected personnel.

b.

Call in the Emergency Plant Manager (EPM), Emergency Offsite Manager (EOM), and the Emergency Assistant Plant Manager. The EOM and EPM may elect to call in additional staff.

c.

Call in or retain Operations, Security, Radiation Protection, Chemistry and Maintenance personnel.

7 RA-EP-02870 Revision 02

d.

Notify all personnel on the Integrated On Call Report of the Isolation Warning.

e.

Notify the Supervisor - Security Shift of the Isolation Warning.

f.

Appoint an Isolation Coordinator to assist the Shift Manager by maintaining a current status of activities associated with the isolation. Ordinarily the EOM is appointed Isolation Coordinator upon arrival at the site.

6.2.2 The Supervisor - Security Shift shall:'

a.

As appropriate, seek information from personnel reporting to the Station as to the road conditions.

b.

Establish contacts with local law enforcement agencies to gather information on road conditions.

c.

Periodically advise the Shift Manager as to current road conditions.

6.2.3 The Shift Manager or designee shall:

a.

Ensure proper staging of an Isolation Supply Trailer as needed for the Protected Area. Primary staging for the Protected Area is the north side of Service Building 6. Consideration should be given to staging the trailer out of the weather if possible (inside Service Building 6 or the Turbine Building Train Bay).

b.

Ensure proper staging of two Isolation Supply Trailers as needed for the Owner Controlled Area Primary staging for the Owner Controlled Area is the east parking lot between the Davis-Besse Administration Building and the Davis-Besse Administration Building Annex.

c.

Ensure emergency vehicles and snow removal equipment are ready for use, as appropriate.

d.

If station warning is due to snow, ensure that Maintenance Services personnel keep station roadways accessible.

6.2.4 The Emergency Plant Manager should:

a.

Confer with the On Call Emergency Director to determine the disposition of non-essential personnel. The following issues should be considered:

1.

Staffing requirements for continuous station operation.

2.

Staffing requirement for the Emergency Response Organization.

b.

IF non-essential personnel are to be dismissed, THEN, Human Resources Letter 513, Pay in Adverse Weather/Emergency Situations, should be reviewed. An appropriate message should then be prepared and communicated to non-essential employees.

8 RA-EP-02870 Revision 02 NOTE 6.2.5

1. The need and ability to arrange for transportation is dependent upon the duration and severity of the storm, and the need for personnel. In some cases, it may be more appropriate from a personnel safety perspective to wait out the storm.

2.

Call-outs of personnel are subject to the requirements of NOP-LP-1002, Fitness for Duty Program.

3. As appropriate, establish conference calls between selected personnel.

4. Utility employees with a valid Company Identification Card are permitted to travel "closed roads" when performing Company business or when returning directly home from work. As always, personnel should exercise good judgment when traveling_on weather impacted roads..............

6.2.5 The Isolation Coordinator shall:

a.

Use Attachment 1, Minimum Supplemental Station Isolation Staffing, and the Emergency Plan Telephone Directory, to assure the minimum staffing is called in.

b.

Arrange transportation for required staff members that can not reach the Station. Transportation resources should be considered in the following order:

1.

Station resources 0

4 Wheel Drive Vehicles o

Various Trucks o

Ski-dozer

2.

First Energy resources 0

Materials/Fleet Management Director

c.

Contact personnel to advise them of the location of the pickup point.

Contacted personnel shall be informed of the impending isolation, and should be told to prepare to remain onsite for several days

d.

Arrange for staging of Protected Area and Owner Controlled Area Isolation Supply Trailers.

e.

Coordinate eating and sleeping arrangements for all isolated personnel with the On Call Emergency Facilities Services Manager (Owner Controlled Area) and the Shift Engineer (Protected Area), as appropriate.

9 RA-EP-02870 Revision 02 6.3 Station Isolation NOTE 6.3.1 Flooding is a local problem which generally affects all access routes, winter weather may only impact employees in a given community.

6.3.1 When vehicle access to the plant is no longer possible, the Shift Manager shall:

a.

Declare station isolation based on the current weather conditions and with the concurrence of the Emergency Plant Manager.

b.

Make an announcement over the Gaitronics advising all station personnel of the station isolation.

c.

Develop a shift schedule utilizing all available personnel based on the estimated duration of the station isolation.

d.

Notify the NRC if the isolation is considered to be a reportable condition under 10 CFR 50.72(b)(1)(v). At a minimum this notification should occur if minimum staffing of the Emergency Response Organization has been called for, and the isolation has lasted longer than four hours. The On Call NRC Liaison should be consulted, as appropriate.

e.

Evaluate ongoing and planned work activities and, as appropriate, suspend work which has the potential to impact plant operations.

6.3.2 The Isolation Coordinator shall:

a.

Establish a center to collect information and station a communicator.

b.

Advise the Shift Manager, Emergency Plant Manager and Emergency Assistant Plant Manager of your location and keep them informed as to the isolation status.

c.

Contact each office area in the Owner Controlled Area and advise personnel to keep you appraised as to the number of personnel present in the structure.

d.

Supervise issue of supplies from Isolation Supply Trailers for the Protected Area and the Owner Controlled Area using Attachment 3, Inventory Sign Out/Sign In Checklist located in each trailer, as appropriate.

e.

Coordinate use of the berthing areas in the DBAB.

10 RA-EP-02870 Revision 02 6.3 3 The Isolation Coordinator should coordinate the recovery effort to establish priorities following the isolation.

a.

Shift relief and staff augmentation b

Re-establishment of site access and parking

c.

Additional and replacement material, as needed.

64 Deactivation 64.1 The Shift Manager shall contact the Emergency Plant Manager and obtain concurrence to deactivate Station Isolation.

6.42 The Shift Manager, when the isolation is terminated, shall:

a.

Notify the Supervisor - Security Shift that the isolation is terminated.

b.

Return shiftworkers to their normal hours and rotation.

c Release extra personnel from duty.

d.

Advise NRC that Station Isolation has been deactivated.

6.4.3 The Isolation Coordinator shall:

a.

Ensure that all equipment is returned to the appropriate Isolation Supply Trailer(s) for the Protected Area

b.

Forward all Inventory Sign Out/Sign In sheets to the Supervisor Emergency Preparedness.

6.4.4 The Supervisor - Security Shift shall:

a Reevaluate Security staffing and return to normal as appropriate.

64.5 The Isolation Coordinator shall:

a.

Ensure that all equipment is returned to the appropriate Isolation Supply Trailer(s) for the Owner Controlled Area.

b.

Forward all Inventory Sign Out/Sign In Checklist sheets to the Supervisor Emergency Preparedness

' 11 RA-EP-02870 Revision 02 6.4.6 The Supervisor -Emergency Preparedness -shall:

a.

Inventory all Isolation Supply Trailers in accordance with RA-EP-00600, Emergency Facilities and Equipment Maintenance Program.

b.

Order/replenish immediately all supplies needed to restock all Isolation Supply Trailers to ensure a continuous state of readiness.

c.

Ensure restaging of Isolation Supply Trailers to specified locations.

d.

Ensure any soiled linen is laundered and replaced in the appropriate Isolation Supply Trailer(s).

7.0 FINAL CONDITIONS Normal access to the Station has been restored, extra personnel have been released, normal shift manning restored housekeeping supplies inventoried and stored, and replacement supplies ordered.

8.0 RECORDS 8.1 The following quality assurance records are completed by this procedure and shall be listed on the Nuclear Records List, captured, and submitted to Nuclear Records Management in accordance with NG-NA-00106:

8.1.1 None 8.2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Nuclear Records Management, in accordance with NG-NA-00106.

8.2.1 None j

12 RA-EP-02870 Revision 02 ATTACHMENT 1: MINIMUM SUPPLEMENTAL STATION ISOLATION STAFFING Page 1 of I Required*

Recommended Control Room 1

Shift Manager 1

Unit Supervisor 2

Reactor Operators 2

5 Equipment Operators I

Emergency Assistant Plant Manager (as required by Technical Specifications) 5 Fire Brigade Team 1

2 First Aid Team Operations Support Center (OSC) 1 OSC Manager 1

2 Chemistry Tester 1

OSC Briefer 2

Mechanical Maintenance Personnel 2

I&C Technicians 2

Electrical Maintenance Personnel 1

OSC Materials Manager 1

OSC RP Coordinator 5

RP Testers 2

Maintenance Services Personnel Technical Support Center (TSC)

I Emergency Plant Manager I

TSC Engineer Manager I

Core/Thermal Hydraulic Engineer 1

I&C System Engineer 1

Electrical Engineer 1

Mechanical Engineer 4

Operations Engineer 1

Computer Technician 1

Emergency RP Manager I

Emergency Security Manager 1

DBAB Access Security Supervisor Emergencv Control Center/Emergencv Operations Facility (ECC/FOF)

I Emergency Director 1

Emergency Offsite Manager 1

Emergency Planning Advisor I

Dose Assessment Coordinator 1

Dose Assessor I

RMT Coordinator 1

RTL Coordinator 3

6 Radiological Monitoring Team Personnel 1

NRC Liaison I

State/County Communicator 1

Emergency Facilities Manager

• Required in accordance with the DBNPS Emergency Plan Table 5-1

RA-EP-02870 Revision 02 "AT Vehicle Isolation Supply Trailers

• RMT Vehicles Ski-dozer Maintenance Services Dump Truck "TACHMENT 2: EMERGENCY VEHIC Page lofI Storage Location Outside Service Building 4 Parking Lot between DBAB and DBABA Outside Service Building 4 Service Building 6 LE LIST Location of Keys ECCEOF Dose Assessment Area, Security, and Shift Manager ECCIEOF Dose Assessment Area Shift Manager Maintenance Services Key Box

• 4-Wheel Drive Pick-up Outside the Personnel Processing Maintenance Services Facility (PPF)

Station Services Tractors Service Building 6 Maintenance Services Forklift Service Building 6 Maintenance Services I

• Denotes vehicles which are equipped to tow the Isolation Supply Trailers NOTES:

1. Fuel is available at Service Building 4. If the pumps are locked, contact Security for the key.

2. Back-up locations for all keys are the Security locksmith or Mobile Central.

3. This list is correct as of November 2002 and changes may occur.

Cey Box Key Box Key Box S1 13

14 RA-EP-02870 Revision 02 ATTACHMENT 3: INVENTORY SIGN OUT/SIGN IN CHECKLIST Page 1 of 1

15 RA-EP-02870 Revision 02 ATTACHMENT 4 TERMS COMMONLY USED DURING ADVERSE WEATHER CONDITIONS Page 1 of 1 NOTE Experience has found that these terms are not consistently used by all media and governmental agencies.

1.

Blizzard Warning - The worst of all winter warnings, with winds speeds of at least 35 MPH. Heavy snow, dangerous wind chills and blowing snow.

2.

Blowing Snow Advisory - Snow already on the ground being wind blown and intermittently reducing visibility to 'A mile or less.

3.

Freezing Rain or Drizzle Advisory - Light amounts of freezing rain or drizzle enough to cause some travel problems. A winter storm warning is issued for severe freezing rain events.

4.

Snow Advisory - Snow fall in amounts sufficient to cause significant travel problems (usually several inches).

5.

Snow Emergency - Bans parking on streets identified as snow-routes. A Snow Emergency may be classified as one of the following levels:

Level l Roadways are hazardous with blowing and drifting snow. Roads are also icy. Drive very cautiously.

Level 2 Roadways are hazardous with blowing and drifting snow. Only those who feel it is necessary to drive should be out on the roadways. Contact your employer to see if you should report to work.

Level 3 All roadways are closed to non-emergency personnel. No one should be out during these conditions unless it is absolutely necessary to travel. All employees should contact their employer to see if they should report to work. Those traveling on the roadways may subject themselves to arrest.

6.

Storm Warning - Bad weather is imminent and actions shall be taken immediately to protect life and property.

7.

Storm Watch - Bad weather has formed and is approaching the area.

8.

Wind Chill Advisory - Wind chill levels in the dangerous category (-30' or below).

9.

Winter Weather Advisory - Used for a combination of snow, freezing rain or sleet and cold temperatures which reduce visibility and cause problems for travelers.

16 RA-EP-02870 Revision 02.

COMMITMENTS Section Reference Comments None None None

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Davis Besse Power Station Control Copy Number: 1665 Transmittal / Receipt Acknowledgement Transmittal Number:

0211-17543 Transmittal Date:

11-20-2002 To: -DOC-CONTROL DESK Mail Stop Addies:*'USNRCDIVISION OF EMERGENCY PREPARDNESS WASHINGTON, D.C. 20555 Document holders are responsible for control and maintenance of documents in accordance with the actions specified by this transmittal. Outdated material shall either be removed and destroyed or marked to reflect that it is superseded or voided and is no longer considered controlled.

Note: Destroy Safeguard information by shredding.

File documents in tab order as identified on the Table of Contents Contact Document Control with any questions at (419)-321-7483

(

Q

.Davis Besse Power Station Transmittal / Receipt Acknowledgement TOC 1 TOC 2 EPIB EPIB EPIA EPIA EPIB EPIB EPIC EPIC Type PROC PROC PROC PROC PROC PROC PROC PROC Sht/Sec Changes COO-0388, C94-0669 C00-0388, C94-0669 C99-1350, E01-2780 Number HS.EP-02240 HS-EP-02240 RA-EP-01900 RA-EP-01900 RA-EP-02240 RA-EP-02240 RA-EP-02710 RA-EP-02710 Control Copy Number: 1665 Transmittal Number:

0211-17543 Transmittal Date:

11-20-2002 old new old new old new old new Rev 0004 0004 0000 0001 Status APPROVED SUPERSEDED APPROVED APPROVED APPROVED APPROVED APPROVED 0000 0000 0001 U..........

I I

Page 1 of 11 Davis-Besse Nuclear Power Station EMERGENCY PLAN IMPLEMENTING PROCEDURE RA-EP-01900 GENERAL EMERGENCY REVISION 01 Prepared by:

Procedure Owner:

NOV.

20102 Effective Date:

Nov_____M Procedure Classification:

X Safety Related Quality Related Non-Quality Related Paul F. Timmerman Manager - Security LEVEL OF USE:

STEP-BY-STEP

2 RA-EP-01900 Revision 01 TABLE OF CONTENTS Page 1.0 PURPOSE.......................................

3 20 REFERENCES............................

3 30 DEFINITIONS 3

40 RESPONSIBILITIES......

4 50 INITIATING CONDITIONS...........................................

4 6.0 PROCEDURE...........................

5 7.0 FINAL CONDITIONS..............................................

10 80 RECORDS.............................................................................

10 COMM ITM ENTS.............................

11

3 RA-EP-01900 Revision 01 1.0 PURPOSE This procedure outlines the course of actioni and protective measures required to mitigate a General Emergency.

2.0 REFERENCES

2.1 Developmental 2.1.1 Davis-Besse Nuclear Power Station Emergency Plan 2.2 Implementation 2.2.1 RA-EP-01500, Emergency Classification 2.2.2 RA-EP-01600, Unusual Event 2.2.3 RA-EP-01700, Alert 2.2.4 RA-EP-01800, Site Area Emeigency S2.2.5 l R-EP-02010, Emhergency Management "2.2.6 RA-EP-021 10, Emergency Notification 2.2.7 RA-EP-02240, Offsite Dose Assessment, 2.2.8 RA-EP-02245, Protective Action Guidelines, 2.2.9 RA-EP-0252O, Assembly and Accountability 2.2.10 RA-EP-02530, Evacuation 2.2.11 RA-EP-027 10, Reentry 2.2.12 RA-EP-02720, Recovery Organization 3.0 DEFINITIONS 3.1 GENERAL EMERGENCY - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

3.2 TRANSITORY EVENT - An event which is classifiable in accordance with RA-EP-01500, Emergency Classification, but becomes a lower - classification or non-classifiable event before being declared.

4 RA-EP-01900 Revision 01 40 RESPONSIBILITIES 4.1 The Emergency Director shall be responsible for the implementing of this procedure 4.1.1 The Shift Manager shall become the Emergency Director during activation of the Davis-Besse Emergency Plan and shall be responsible for coordinating the actions of the emergency organization until relieved.

4.1 2 The Unit Supervisor may assume the Emergency Director duties only if the Shift Manager is not in the Control Room, or is incapable of performing those duties.

4.1.3 The Shift Engineer (Shift Technical Advisor) may assume the Emergency Director duties only if neither the Shift Manager nor the Unit Supervisor is in the Control Room and capable of performing those duties.

4.1 4 Upon arrival in the Control Room, the Emergency Assistant Plant Manager or Emergency Plant Manager may relieve the Emergency Director.

4.1 5 The Emergency Plant Manager may assume the Emergency Director duties from the Technical Support Center (TSC) if the TSC and Emergency Control Center/Emergency Operations Facility (ECCJEOF) are activated.

4.1 6 The Emergency Director shall remain in the Control Room until the TSC and ECC/EOF have been activated.

50 INITIATING CONDITIONS This procedure shall be utilized whenever a General Emergency has been classified in accordance with RA-EP-01500, Emergency Classification.

5 RA-EP-01900 Revision 01 NOTE 6.0 The following procedure steps may be performed simultaneously.

6.0 PROCEDURE DATE:

TIME INITIALS The Emergency Director shall direct performance of the following:

CAUTION 6.1

1.

If the General Emergency is due to a security event obtain security management concurrence prior to sounding the Station alarm.

6.1 Sound the appropriate Station alarm (fire, access evacuation, and/or initiate emer gency procedures) and make the following announcement over the public address system, TWICE.

6.1.1 Upgrading

"AITTENTION ALL PERSONNEL; ATTEN TION ALL PERSONNEL, A GENERAL EMERGENCY HAS BEEN DECLARED. NO EATING, DRINKING; OR SMOKING UNTIL FURTHER NOTICE. ALL MEM BERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY RESPONSE FACILITIES. ALL NONESSENTIAL PERSONNEL IMMEDIATELY EVACUATE TO THE LINDSEY SERVICE CENTER. THE REASON FOR THE GENERAL EMERGENCY IS (STATE REASON)

(SEE RA-EP-02520, ASSEMBLY AND ACCOUNTABILITY FOR FURTHER DETAIL.)

6 RA-EP-0 1900 Revision 01 DATE:

TIME INITIALS 6.1.2 If there is a localized emergency (e.g, fire), then announce its type and location and instruct per sonnel to stand clear of the area.

6 2 Notify the Emergency Response Organization (ERO) in accordance with RA-EP-021 10, Emergency Notification.

6 3 Protective action recommendations shall be made in accordance with RA-EP-02245, Protective Action Guidelines.

6 4 Notify Ottawa County, Lucas County and the State of Ohio within 15 minutes of any emergency classification using the Initial Notification Form in accordance with RA-EP-021 10, Emergency Notification.

6.5 Notify the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using the Event Notification Worksheet in accordance with RA-EP-021 10, Emergency Notification.

6 6 Initiate a general evacuation of the site in accordance with RA-EP-02530, Evacuation.

Nonessential personnel evacuated from the station.

6 7 Initiate personnel accountability (unless previously accomplished) in accordance with RA-EP-02520, Assembly and Accountability.

Accountability completed.

6.8 Terminate all radwaste releases.

69 Increase surveillance of Control Room instrumentation. Indications of core status (e g., incore thermocouple readings, etc ) shall receive particular attention 6.10 Ensure the following emergency response facilities are activated 6.10.1 The Operations Support Center 6.10.2 The Technical Support Center

7 RA-EP-01900 Revision 01 DATE:

TIME INITIALS 6.10.3 The Emergency Control Center/Emergency Operations Facility 6.10.4 The Joint Public Inforrnation'Center 6.10.5 The Corporate Emergency Response Organization 6.11 Continue dose assessment activities in accordance with RA-EP-02240, Offsite Dose Assessment, with increased ermphasis on determining the need for protective actions.

6.12 Make periodic updates to offsite agencies as conditions change, or hourly at a minimum, using the Periodic Update Form in accordance with RA-EP-021 10, Emergency Notification. These updates may be omitted by mutual agreement with the offsite agencies.

6.13 When plant conditions change review RA-EP-01500, Emergency Classification, to determine if the event should be reclassified..

6.13.1 Once a General Emergency has been declared the event shall NOT be downgraded without reviewing Downgrading Guidelines in RA-EP-01500, Emergency Classification.

6.13.2 If the event is reclassified then implement the appropriate procedure.

6.14 When the General Emergency is downgraded make the following notifications in accordance with RA-EP-02110, Emergency Notification:

6.14.1 'Ottawa County, Lucas County, and the "

State of Ohio using the Initial Notification Form

8 RA-EP-0 1900 Revision 01 DATE.

TIME INITIALS 6.14.2 The NRC using the Event Notification Worksheet 6.15 If a Transitory General Emergency condition has occurred notify Ottawa County, Lucas County, State of Ohio, and the NRC in accordance with RA-EP-021 10, Emergency Notification.

6.16 The individual assuming the responsi bilities of Emergency Director shall complete Emergency Director Turnover Data Sheet contained in RA-EP-02010, Emergency Management, using information provided by the Control Room log, unit log, and status boards.

6 17 If the emergency situation is mitigated and completely declassified, then perform the following:

6 17 1 Make this announcement over the public address system "ATTENTION ALL PERSONNEL, ATTEN TION ALL PERSONNEL: THE EMER GENCY SITUATION HAS BEEN TER MINATED. I REPEAT, THE EMER GENCY SITUATION HAS BEEN TERMINATED."

6.17 2 Notify Ottawa County, Lucas County, and the State of Ohio using the Initial Notification Form in accordance with RA-EP-021 10, Emergency Notification.

6.17 3 Notify the Nuclear Regulatory Commission using the Event Notification Worksheet in accordance with RA-EP-021 10, Emergency Notification.

6.17 4 Notify the Emergency Response Organization (ERO) in accordance with RA-EP-021 10, Emergency Notification.

9 RA-EP-01900 Revision 01 DATE:

TIME INITIALS 6.18 Perform any necessary reentry actions in accordance with RA-EP-027 10, Reentry.

6.19 Perform recovery actions in accordance with RA-EP-02720, Recovery Organization.

6.20 Records, other than Safeguards Records, shall be collected and forwarded to the Emergency Preparedness Supervisor who shall submit them to Nuclear Records Management.

Safeguards Records shall be collected and forwarded to the Supervisor - Security Shift.

Section 6.0 completed by:

Date:

10 RA-EP-0 1900 Revision 01 7.0 FINAL CONDITIONS 7 1 The emergency condition has been downgraded and actions are being taken in accordance with RA-EP-01800, Site Area Emergency, RA-EP-01700, Alert or RA-EP-01600, Unusual Event OR 7.2 Emergency conditions no longer exist and actions are being taken in accordance with RA-EP-027 10, Reentry, and/or RA-EP-02720, Recovery Organization 8.0 RECORDS 8.1 The following quality assurance records are completed by this procedure and shall be listed on the Nuclear Records List, captured, and submitted to Nuclear Records Management in accordance with NG-NA-00106.

8 1 1 None 8 2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Nuclear Records Management, in accordance with NG-IM-00 106:

8 2 1 RA-EP-01900, General Emergency (when steps have been completed) 8 2 2 Emergency Director Turnover Data Sheet 8 2 3 Initial Notification Form 824 Periodic Update Form

RA-EP-01900 Revision 01 COMMITMENTS Reference TERMS 0 13532, TERMS 0 13969, TERMS 0 15211, TERMS 0 15212 TERMS 0 13600 TERMS 0 13670 TERMS 0 13584, TERMS 0 15210 TERMS 015209 TERMS Q 00785 TERMS Q 03113 Comments Addresses 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification capability Addresses assembly, accountability, and evacuation or sheltering Specifies conditions under which STA may assume Emergency Director duties Concerns protective action recommendations Dose Assessment Sounding Station Alarms Activating the ERO II Section 6.3, 6.4, 6.12 6.5 4.1.3 6.11 6.10 6.1 ALL

Table of Contents EPIB RA-EP-02010 EMERGENCY MANAGEMENT RA-EP-02110 EMERGENCY NOTIFICATION RA-EP-02220 EMERGENCY CONTROL CENTER ACTIVATION AND RESPONSE RA-EP-02230 DOSE ASSESSMENT CENTER ACTIVATION AND RESPONSE RA-EP-02240 OFFSITE DOSE ASSESSMENT RA-EP-02245 PROTECTIVE ACTION GUIDELINES RA-EP-02250 RADIATION MONITORING TEAM SURVEYS RA-EP-02260 RADIOLOGICAL CONTROLS IN THE DBAB RA-EP-02270 FACILITIES SUPPORT RA-EP-02310 TECHNICAL SUPPORT CENTER ACTIVATION AND RESPONSE RA-EP-02320 EMERGENCY TECHNICAL ASSESSMENT

Page 1 of 45 Davis-Besse Nuclear Power Station EMERGENCY PLAN IMPLEMENTING PROCEDURE RA-EP-02240 (Supersedes HS-EP-02240, R4, C-2)

Offsite Dose Assessment REVISION 00 - TOTAL REWRITE Prepared by:

Procedure Owner:

Effective Date:

NOV 2 0 2002 Procedure Classification:

X Safety Related Quality Related Non-Quality Related Paul F. Timmerman Manager - Security F

I LEVEL OF USE:

IN-FIELD REFERENCE

2 RA-EP-02240 Revision 00 TABLE OF CONTENTS Page 10 PURPOSER 3

230 REFERENCES......................................................

3 3.0 DEFINITIONSI........T..........

4 40 RESPONSIBILITIES..............................

... 4 50 INITIATING CONDITIONS..............................................

4 6.0 PRO CED URE..................

..................................................... 5 6 1 Projection of Offsite Dose Rates Using Plant Data............................... 5 6 2 Projection of Offsite Dose Rates Using Field Monitoring Data................

5 6.3 M eteorological Data...

5 64 Protective Actions...........................

.6 6 5 Total Population Dose......

............................. 6 7.0 FINAL CONDITIONS......

7 8 0 RE C O RD S.........

............................................................ 7 ATTACHMENT I Dose Calculations Using SPDS.................................

8 ATTACHMENT 2 Instructions for Offsite Dose Assessment Nomogram..................

10 ATTACHMENT 3 Station Vent Release Calculations.............................

12 ATTACHMENT 4 Secondary Side Release Calculations...................

18 ATTACHMENT 5 Calculations for Containment Releases Using RE 4596A or RE 4596B 27 ATTACHMENT 6 Calculations for Releases From Containment Using RE 4597AB or RE 4597BB...........................

.............. 33 ATTACHMENT 7 Dose Projections Based on Field Monitoring Data...................

34 ATTACHMENT 8 Estimation of Total Population Dose..............................

.. 38 ATTACHMENT 9 Meteorological Data......

42 COMMITMENTS........................................................

45

3 RA-EP-02240 Revision 00 1.0 PURPOSE 1.1 This procedure is intended to estimate offsite dose rates from noble gases and radioiodides during accidental, uncontrolled airborne releases.

2.0 REFERENCES

2.1 Developmental "2.1.1 NRC Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Consequences of a Loss of Coolant Accident for Pressurized Water Reactors 2.1.2 NRC Regulatory Guide 1.109, Calculation of Annual Dose to Man From Routine Releases or Reactor Effluents for'the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I 2.1.3 NRC Regulatory Guide 1.145, Atmosphieric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants 2.1.4 EPA-400-R-92-001 'May 1992, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.1.5 Letter; Correction Factor for Noble Gas Measurements Assuming All Activity as Xem, from Gregory Stoetzel, Battelle Pacific Northwest Laboratories, September 24, 1984 2.1.6 BT-10372, Letter from Bechtel to Toledo Edison concerning Quantification of Radiation Release from Main Steam Line, June 4, 1980 2.1.7 Davis-Besse Nuclear Power Station Emergency Plan 2.2 Implementing 2.2.1 DB-OP-0253 1, Steam Generator Tube Leak 2.2.2 RA-EP-02230, Dose Assessment Center Activation and Response 2.2.3 RA-EP-02245, Protective Action Guidelines 2.2.4 RA-EP-02320, Emergency Technical Assessment 2.2.5 Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory

4 RA-EP-02240 Revision 00 3.0 DEFINITIONS 3.1 DADS - The Data Acquisition and Display System (DADS) provides plant parameters, meteorology data, and dose calculations DADS updates MODCOMP data at 30-second intervals and Validyne data at 1 second intervals The meteorological data is provided at 15 minute intervals, and is an average over that time period. DADS stores information from the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3 2 LAKE BREEZE - A meteorological condition that may occur on clear, sunny days. During a lake breeze, a radioactive release can travel inland, rise, reverse course in an overhead return flow, and then return to land in a convoluted path.

3.3 MODCOMP - The station computer which monitors plant instruments and systems 3.4 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) - The SPDS is a group of graphic displays developed to assist with monitoring plant operations 3 5 SECTOR - One of the 16 areas bounded by radii 221/2 degrees apart into which the 10 mile EPZ is divided Sectors are designated by the letters A through R, excluding I and 0.

Sector A lies north of DBNPS, Sector E lies east, Sector J lies south, and Sector N lies west.

3.6 VALIDYNE - A high speed data acquisition system that monitors 100 critical plant parameters.

4.0 RESPONSIBILITIES 4 1 Emergency Director shall:

4.1 1 Direct calculation of the release and dose rates using available, qualified dose assessment personnel including Licensed Reactor Operators and Senior Reactor Operators 4.2 Qualified Dose Assessment Personnel shall 4 2.1 Perform dose calculations in accordance with Section 6 0 of this procedure 4.2.2 Report the results of dose calculations to the Emergency Director or Dose Assessment Coordinator, as applicable.

50 INITIATING CONDITIONS This procedure shall be implemented at the request of the Emergency Director, or Dose Assessment Coordinator when an accidental airborne release of radioactivity is in progress or immnent.

5 RA-EP-02240 Revision 00 6.0 PROCEDURE 6.1 Projection of Offsite Dose Rates Using Plant Data 6.1.1 Determine the release pathway of the radioactive release.

-a,.-

IF the release is from more than one point [e.g., Steam Jet Air Ejector (SJAE) and Atmospheric Vent Valve (AVV)],

THEN sum the resulting dose rates for each point to obtain the total dose rate.

6.1.2 Dose Assessment Instructions using In-Plant Radiation Detector Data

a.

The Safety Parameter Display System (SPDS) Process Book

1.

Select the Dose Calculation tab.

2.

Double click the "Dose Rate Calculation an PARs" display title.

• . _3.

Refer To Attachment 1, Dose Calculations using SPDS.

b.

The Offsite Dose Assessment Nomogram per Attachment 2, Instructions for Offsite Dose Assessment Nomogram.

c.

The appropriate hand calculation below:

RELEASE INDICATIONS ATTACHMENT RE 4598 (Station Vent) 3 Secondary Side Releases 4

RE4596 (Dome Monitors) 5 RE 4597 (Containment Atmosphere) 6 6.1.3 Refer To RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations.

6.2.

Proiection of Offsite Dose Rates Using Field Monitoring Data

!6.2.1 Refer To Attachment 7, Dose Projections Based on Field Monitoring Data, when using field data., I 6.2.2 Refer To RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations.

6 RA-EP-02240 Revision 00 6.3 Meteorological Data 63.1 Obtain 15 minute average meteorological data from any of the following:

• Access the SPDS Process Book to access the meteorological data.

• Access the DADS nongraphic terminal to call up the meteorological data.

6.3 2 IF the systems in 6.3.1 cannot be accessed, THEN monitor meteorological data in accordance with Attachment 9, Meteorological Data.

6.3.3 IF a lake breeze is occurring while an airborne radioactive release is in progress or

imminent, THEN the Dose Assessment Coordinator should:

a.

Refer To Attachment 9, Meteorological Data, for lake breeze conditions.

_ b Inform the Ohio EMA of the lake breeze and that the plume may not follow the course indicated by the meteorological tower wind direction c

Inform the Radiation Monitoring Teams (RMTs) that higher-than-projected dose rates may occur in the plume pathway.

6.4 Total Population Dose NOTE 6.4 1 The Radiation Protection Section will provide a more definitive estimate of the total population dose after more detailed population and radiological data have been obtained.

6.4.1 During Recovery from an emergency event, obtain an estimate of the total population dose using Attachment 8, Estimation of Total Population Dose.

7.0 FINAL CONDITIONS 7 1 Dose assessment personnel have been relieved of all emergency support duties

-7 2

All equipment and supplies have been returned to their normal storage locations.

7.3 Records have been collected and forwarded to the Emergency Preparedness Unit which will subsequently forward them to Nuclear Records Management I

I I

7 RA-EP-02240 Revision 00 8.0 RECORDS 8.1 The following quality assurance records are completed by this procedure and shall be listed on the Nuclear Records List, captured, and submitted to Nuclear Records Management in accordance with NG-NA-00106:

8.1.1 Printouts from the Dose Assessment computer program 8.1.2 Offsite Dose Nomograms 8.1.3 Data Sheet 1:

Total Effective Dose Equivalent (TEDE) Rate

-,-8.1.4 Data Sheet 2:

Thyroid Dose Rates from Radioiodines 8.1.5 Data Sheet 3:

Release Rate from Main Steam Line Monitor Readings 8.1.6 Data Sheet 4:

Release Rates from Noble Gases and Radioiodines Using Primary Parameters 8.1.7 Data Sheet 5:

Release Rate from Unisolated Once Through Steam Generator (OTSG) Steam Sample

--8.1.8 Data Sheet 6:

Release Rates from Steam Jet Air Ejector (SJAE) Releases 8.1.9 Data Sheet 7: - Estimated Release Rate with Solid OTSG 8.1.10 Attachment 5: Calculations for Containment Releases Using RE 4596A or 4596B 8.1.11 Attachment 6: Release Rate Calculations for Releases from Containment Using RE 4597 AB or RE 4597 BB 8.1.12 Attachment 7: 'Dose Projections Based on Field Monitoring Data 8.1.13 Attachment 8: "Estimation of Total Population Dose 8.2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Nuclear Records Management, in accordance with NG-NA-00106:

8.2.1 None

8 RA-EP-02240 Revision 00 ATTACHMENT 1: DOSE CALCULATIONS USING SPDS Page I of 2 NOTE Ensure that the correct instrument is selected. The Drop Down boxes allow different instruments to be selected.

Instrument readings that are applicable to the selected release paths will appear.

Some instrument readings do not have a corresponding computer point.

These inputs require manual entry per Section B, using Manual Inputs A.

USING COMPUTER INPUTS

____ 1.

CLICK the Release Path(s) determined in Step 6.1 1

2.

VERIFY instrument readings for the Release Path(s) selected are correct.

a.

IF instrument readings are not displayed or appear incorrect, (1)

VERIFY the computer selection box is checked for the instrument.

(2)

VERIFY the correct instrument(s) is selected (3)

IF the instrument reading is now correct, GO TO step A.3 (4)

IF the instrument reading(s) requires manual input, GO TO step B.2.

3.

ENTER the hours since reactor trip (0-24) AND PRESS the Enter Key 4

ENTER the release start (HH MM) AND PRESS the Enter Key

_5 ENTER the projected release duration (in hours, default is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) AND PRESS the Enter Key.

6.

IF a General Emergency has been declared, THEN click GENERAL EMERGENCY DECLARED

7.

REVIEW the Dose, Dose Rates and Protective Action.

8 REFER TO RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations

9.

GO TO step A.3 to repeat dose assessment and protective action calculations, if required.

9 RA-EP-02240 Revision 00 ATTACHMENT 1: DOSE CALCULATIONS USING SPDS

ý - -Page 2 of 2 NOTE 0

Ensure that the correct instrument is selected. The Drop Down boxes allow different instruments to be selected.

Instrument readings that are applicable to the selected release paths will appear.'-

Some instrument readingsdo not have a corresponding computer point.

These inputs require manual entry per Section B using Manual Inputs.

B. USING MANUAL INPUT

° -_1.

CLICK the Release Path(s).

2.

CLICK the computer selection box for the radiation instrument(s) AND VERIFY that the computer selection box is empty.

a.

To calculate an Iodine value when the Station Vent Radiation Monitors (RE4598 AB or RE4598 BB) are in the accident range, perform the following calculation:

Iodine = (NG) x (R)

Where: NG

=

RE4598 AB or RE 4598 BB Channel 1 or 2 Noble Gas value R

=

RE4598 I:NG ratio value

3.

CLICK the computer selection box for the met tower instruments AND VERIFY that the computer selection box is empty.

4.

ENTER the selected instrument reading(s) in the instrument box(s).

5.

ENTER the hours since reactor trip (0-24) AND PRESS the Enter Key.

6.

ENTER the release start (HH:MM) AND PRESS the Enter Key.

7.

ENTER the projected release duration (ini hrs.; default is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) AND S-PRESS the Enter Key.

8.

-IF a General Emergency has been declared, "THEN click GENERALEMERGENCY DECLARED.

9.

REVIEW the Dose, Dose Rates and Protective Actions

10.

REFER to RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations.

11.

GO TO step B.3 to repeat dose assessment and protective action calculations, if required.

10 RA-EP-02240 Revision 00 ATTACHMENT 2 INSTRUCTIONS FOR OFFSITE DOSE ASSESSMENT NOMOGRAM Page 1 of 2

1.

Obtain a Nomogram (Figure 1)

2.

Record Name, Date, and Time on the Nomogram

3.

Determine monitor reading:

3.1 IF the release is from the Station Vent, THEN plot the appropriate RE 4598 noble gas reading in #Ci/cc on Scale B (AA/BA Channel 1 - Normal Range, AB/BB Channel 1 - Mid-Range, or AB/BB Channel 2 - High Range) 3.2 IF the release is from the Main Steam Safety Valve (MSSV), Atmospheric Vent Valve (AVV), or AUXILIARY FEEDWATER PUMP TURBINE (AFPT),

THEN plot the cpm reading of RE 600 or RE 609 in the Gross Mode on Scale B.

4 Determine Total Effective Dose Equivalent (TEDE) rates.

NOTE 4 1 Flowrate given on nomogram are conservative values for each release pathway 4 1 Plot the flow rate on Scale (A) 4 2 Draw a line from the monitor reading on Scale (B) to the flow rate on Scale (A) This line intersects Scale (C) at the release rate.

4 3 Determine lower delta T or stability class, and windspeed.

Resources available for determining lower delta T, stability class and windspeed are:

SPDS Plant Process Computer RTVAX 44 Plot lower delta T or stability class on Scale (1) 4 5 Plot windspeed on Scale (2).

4.6 Draw a line from the lower delta T or stability class on Scale (1) to the wind speed on Scale (2). This line intersects Scale (3) at the X/Q value.

4.7 Draw a line from the release rate on Scale (C) to the ZIQ value on Scale (3)

This line intersects Scale (4) at the TEDE rate for the Site Boundary (0 75 miles).

4 8 Determine TEDE rates at 2, 5, and 10 miles by dividing the Site Boundary TEDE rate by 5, 15, or 40.

4.9 IF the 0.75 mile dose for the release is _> 1 rem TEDE or _> 5 rem thyroid, REFER TO RA-EP-02245, Protective Action Guidelines, to determine protective action recommendations

11 RA-EP-02240 Revision 00 ATTACHMENT 2: INSTRUCTIONS FOR OFFS1TE DOSE ASSESSMENT NOMOGRAM SP age 2 o f2 Figure-1. Offsite Dose Assessment Nomogram Offsite Dose Assessment Nomogram Al-U A

-Z.1-ATS-24 I

-1*ATS-lj c

-U(MS-84 D

-41&JIU E

tJ--- -7.& * ( F 4?LTcT "

.

7

[-

\\**

12 RA-EP-02240 Revision 00 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 1 of 6 NOTE The following Total Effective Dose Equivalent (TEDE) calculation is based solely on Noble Gas The contribution from radioiodides and particulates have been neglected to expedite calculations I

CAUTION Use DATA SHEET 1 and DATA SHEET 2 for dose calculation only if SPDS is not available.

DATA SHEET I TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) RATE

1.

Record the date and time Date Time Record the appropriate Noble Gas activity from RE 4598 in Step 4 (AAIBA Channel I - Normal Range, AB/BB Channel 1 - Mid Range, or AB/BB Channel 2 - High Range)

3.

Record the Unit Vent flow rate from Computer Point F885 (or F883) in Step 4

a.

IF flow rate is NOT available, THEN use 146 KCFM AND contact the TSC to verify the flow rate

4.

Calculate the estimated release rate for Noble Gas by multiplying the values below and entering in Column (E) of Table 2.

____ c' x KCFM x 0 472 cc Ci Ci cc sec KCFM jiCi sec (From 2.)

(From 3)

(Release Rate) 5 Record the wind speed Convert the wind speed to -__m and enter in Column (C) of Table 2 see mph x 0 447 rn/sec m

mph sec WSnd)

SWind)

S peed)

(,Speed)

I

13 RA-EP-02240 Revision 00 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS

- - -- Page 2 of 6

'DATA SHEET 1 (Cont.)

Table 1. "Q (m'i) for Stability Classes as a Function of Downwind Distances

- STABILITY CLASS MILES A

B C -.

D E-F G

0.75 2.1E-6 1.4E '3.5E-5

,9.9E-5, 2.0E-4 4.5E-4 1.3E-3 2

1.1E-7 2.OE-6 5.8E-6

'2.2E-5 4.6E-5 L.0E-4 2.8E-4 5

.7.1E-9 3.2E-7 1.1E-6 5.5E-6 1.3E-5 3.1E-5 8.2E-5 10 8.9E-10 8.0E-8 3.2E-7 2.OE-6 5.1E 1.3E-5 3.4E-5

6.

Record Stability Class. (circle one) A B C D E F G (From-Attachment 9)

7.

Using Table 1 of this attachment, enter E (m"2) at distances of 0.75, 2, 5, and 10 miles for the Stability Class circled above in Column (B) of Table 2.

8.

In Table 2, divide Column (B) by Column (C), and enter result in Column (D).

9.

In Table 2, multiply Column (D) by Column (E) and enter result in Column (F).

10.

Determine the appropriate Noble Gas Correction Factor from Table 3 and enter result in Colun (G) of Table 2.

11.

Multiply Column (F) by Column (G) and enter in Column (H) of Table 2.

rnI Table 2. Total Effective Dose Equivalent (TEDE) Rate Column (A)

Column (B)

Column (C)

Column (D)

Column (E)

Column (F)

Column (G)

Column (H)

Downwind x

Release Noble Gas Noble Gas TEDE Distance W (m-)

Windspeed Q

Rate conc.

Correction Rate (Miles)

Q (C')

eec)

(cJ

('C)

Factor (Rem.

From From From From N/A' Table I Step5 B/C=D Step4 DxE=F Table 3 FxG=H 0.75 2.00 5.00 10.00

14 RA-EP-02240 Revision 00 ATTACHMENT 3" STATION VENT RELEASE CALCULATIONS Page 3 of 6 DATA SHEET I (Cont.)

Table 3 Noble Gas Correction Factor (NGCF)

(Round time to the nearest value) 1 IF fuel damage or cladding failures have occurred, THEN use the following Table to obtain the Noble Gas Correction Factor (NGCF).

OTHERWISE, use 10 0 for the Noble Gas Correction Factor (NGCF).

Hours After NGCF Hours After NGCF Reactor With Fuel Reactor With Fuel Shutdown Damage Shutdown Damage 0

1540 31 228 05 892 32 226 1

673 33 224 1.5 565 34 222 2

491 35 220 2.5 432 36 21 9 3

381 37 21 8 35 338 38 21 6 4

301 39 21 5 45 268 40 214 5

240 41 214 6

193 42 21.3 7

158 43 21.2 8

130 44 21.1 9

108 45 21.1 10 90.6 46 21.0 11 77.0 47 21.0 12 66.3 48 20.9 13 578 49 20.9 14 510 50 20.8 15 455 51 20.8 16 412 52 20.8 17 377 53 20.7 18 348 54 20.7 19 325 55 20.7 20 307 56-60 206 21 29 1 61-65 20.5 22 279 66-75 204 23 269 76-96 20.3 24 26.0

>97 20.2 25 25.3 26 24.7 27 24.2 28 23.8 29 234 30 23 1

15 RA-EP-02240 Revision 00 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 4 of 6 NOTE The following Thyroid calculation is based on the inhalation pathway for radioiodides. The external dose from radioiodide is neglected to expedite calculations.

DATA SHEET 2:

THYROID-DOSE RATES -FROM RADIOIODIDES

1.

Record the date and time Date Time'

2.

Record the value of 1-131 activity from Channel 3 of RE 4598 AAJBA in Step 4.

a.

- Noble gases can make the 1-131 reading falsely high.- Request that Radiation Protection personnel verify the 1-131 reading.-

b.

IF the release coniinues, THEN insert a silver zeolite cartridges into RE 4598 AA or RE 4598 BA.

c.

• 'IF the RE 4598 AA/BA Iodine-I31 reading exceeds 3.0E"2 jCi/cc, THEN request that RP personnel provide the 1-131 concentration.

3.

Record the Unit Vent flow rate from Computer Point F885 (or F883) in Step 4.

a.

IF flow rate is NOT available, THEN use 146 KCFM AND contact the TSC to verify the flow rate.

4.

Calculate the estimated release rate of 1-131 by multiplying the values below and enter in Column (E) of Table 5.

X KCFM x 0.472 cc Ci C.

cc-seoKCFM pCi sec (From 2.)

(From 3.)

(Release RAte)

5.

Record the-wind speed.

"Conivert the wind speed o6 m and endt f in Colurmn (C) of Table-5.-..

sec

_.....- mph x 0.447 rmtsec m

rn mph sec (Wi~nd~

(W nd)

... Speed)

Spe d....

16 RA-EP-02240 Revision 00 ATTACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 5 of 6 DATA SHEET 2 (Cont.)

Table 4. --

(m-2) for Stability Classes as a Function of Downwind Distances STABILITY CLASS MILES A

B C

D E

F G

075 2 IE-6 I.4E-5 3 5E-5 9.9E-5 2.OE-4 4 5E-4 1.3E-3 2

1 1E-7 2.OE-6 5 8E-6 2 2E-5 4 6E-5 1 OE-4 2.8E-4 5

7 IE-9 3.2E-7 1 IE-6 5 5E-6 1.3E-5 3 IE-5 8.2E-5 10 8.9E-10 8 OE-8 3 2E-7 2 0E-6 5 1E-6 1.3E-5 3 4E-5 6

Record Stability Class (circle one) A B C D E F G (From Attachment 9).

7.

Using Table 4 of this attachment, enter --Q- (m2) for the Stability Class in step 6, at distances of 0.75, 2, 5, and 10 miles in Column (B) of Table 5.

8.

In Table 5, divide Column (B) by Column (C), and enter in Column (D).

9 In Table 5, multiply Column (D) by Column (E) and enter in Column (F) 10 Determine the appropriate Radioiodide Correction Factor from Table 6 and enter in Column (G) of Table 5 Multiply Column (F) by Column (G) and enter in Column (H) of Table 5.

Table 5 Thyroid Dose Rate Column (A)

Column (B)

Column (C)

Column (D)

Column (E)

Column (F)

Column (G)

Column (H)

X Release Radioiodide Thyroid Downwind Windspeed Q

Rate conc.

Radioiodide Dose Rate Distance X

(2)-c see (CC Correction (Rem)

(Miles)('M((M3)

(-hr (Miles) sc) m sec cc Factor From From From From N/A Table 4 Step 5 B/C=D Step 4 DxE=F Table 6 FxG=H 0.75 2 00 5 00 1000

17 RA-EP-02240 Revision 00 AITACHMENT 3: STATION VENT RELEASE CALCULATIONS Page 6 of 6 "Table 6. Radioiodine Correction Factor (Round time to the nearest value)

Hours After Reactor

' Correction Shutdown Factor 0

2.88 E+06 0.5 2.86 E+06 1

2.83 E+06 1.5 2.81 E+06 2

2.79 E+06 2.5 2.77 E+06 3

3.5 4

4.5 5

5.5 6

6.5 7

7.5 8

8.5 9

9.5 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Hours After.....

Reactor, Correction Shutdown Factor 26 2.25 E+06 27 2.24 E+06 28 2.23 E+06 29 2.22 E+06 30 2.21 E+06 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 2.75 E+06 2.73 E+06 2.71 E+06 2.70 E+06 2.68 E+06 2.67 E+06 2.65 E+06 2.64 E+06 2.62 E+06 2.61 E+06 2.59 E+06 2.58 E+06 2.57 E+06 2.55 E+06 2.54 E+06 2.52 E+06 2.49 E+06 2.47 E+06 2.45 E+06 2.43 E+06 2.41 E+06 2.39 E+06 2.37 E+06 2.36 E+06 2.34 E+06 2.32 E+06 2.31 E+06 2.29 E+06 2.28 E+06 2.27 E+06 2.19 E+06 2.18 E+06 2.17 E+06 2.16 E+06 2.15 E+06 2.14 E+06

.2.14 E+06 2.13 E+06 2.12 E+06 2.11 E+06 "2.10 E+6 2.10 E+06 2.09 E+06 2.08 E+06 2.07 E+06 46 - 47 2.06 E+06 48-49 2.05 E+06 50-51 2.04 E+06 52-53 2.03 E+06 54-55 2.02E+06 56-57 2.01E+06 58-59 2.00 E+06 60-61 1.99 E+06 62-64 1.98 E+06 Hours After, Reactor Correction Shutdown Factor 65 67 1.97 E+06 68-70 1.96 E+06, 71--73 1.95 E+06 74 - 77 1.94 E+06 78-81 1.93 E+06, 82-86 1.92 E+06 87-92 1.91E+06 93-98 1.90 E+06 99-107 1.89 E+06 108-11 8 1.88 E+06 119-135 1.87 E+06 136-173 1.86E+06

>174 1.85 E+06

18 RA-EP-02240 Revision 00 ATTACHMENT 4 SECONDARY SIDE RELEASE CALCULATIONS Page 1 of 9

1. lF the release is from more than one point (for example AFPT and SJAE),

THEN add the dose rates from each point to obtain the total dose rate.

2 For Main Steam Safety Valve (MSSV), Atmospheric Vent Valve (AVV), and Auxiliary Feedwater Pump Turbine (AFPT) releases, determine which parameters are available as calculation inputs a IF primary system parameters are available THEN REFER TO DATA SHEET 4.

b IF main steam line monitors (RE 600/RE 609) are available, THEN REFER TO DATA SHEET 3.

c IF the Once Through Steam Generator (OTSG) is solid, THEN REFER TO DATA SHEET 7

d. IF an OTSG steam sample is available, THEN REFER TO DATA SHEET 5.

3.

IF a Steam Jet Air Ejector (SJAE) release occurs AND the Station Vent monitors are functioning, THEN perform Station Vent calculations using DATA SHEET 1 and DATA SHEET 2 of.

4.

IF a SJAE release occurs, AND the Station Vent monitors are NOT functioning, THEN REFER TO DATA SHEET 6

19 RA-EP-02240 Revision 00 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS

-Page2of9.

"DATA SHEET 3 Release Rate from Main Steam Line Monitor Readings NOTE The release rates estimated using this method are gross approximations. More accurate release rates may be determined by using RCS activity and estimated primary to secondary leak rates.

NOTE RE 609 (Computer Point R787) is for OTSG No. 1, and RE 600 (Computer.Point R788) is for OTSG No. 2

1.

Record the date and time

-Date Time

2.

Record average steam flow rate in lbm/hr.

a.

Consult TSC Engineers.

b.

IF a Main Steam Safety Valve (MSSV) or Atmospheric Vent Valve (AVV) release is occurring, THEN use Table 1. of this attachment.

c.

IF an Auxiliary Feedwater Pump Turbine (AFPT) release is occurring, AND duration of release is less than one hour, THEN use 4.4 E4 lbIm/hr OTHERWISE Contact TSC Engineers for release rates from AFPT lasting longer than one hour.

d.

Record in Step 6.

3.

Verify that the Analyze/Gross Mode Switch of RE 600 or RE 609 is in the GROSS MODE position.

4.

Calculate net reading of RE 600 or RE 609 (circle one)

-300cpm = _

cpm RE 600 or RE 609 (circle one)

5.

Calculate radionuclide concentration in the steam by multiplying the net RE 600 or RE 609 reading by the value obtained from Figure 1 of this attachment.

cp m x _

_=

I+/-tC i (From 4.)

(Figure 1 value)

6.

Calculate Release Rate by multiplying the steam flow with the activity concentration then by the given correction factor.

Ibm x LC----pi x 3.5 E-6=

CI hr cc sec (From 2.)

(From 5.)

(Release Rate)

20 RA-EP-02240 Revision 00 ATTACHMENT 4 SECONDARY SIDE RELEASE CALCULATIONS Page 3 of 9 DATA SHEET 3 (Cont.)

Release Rate From Main Stream Line Monitor Readings

7.

Perform one of the following.

a Insert the Release Rate into Step 4 of DATA SHEET 1 of Attachment 3 and complete DATA SHEET 1.

b.

Plot the noble gas release rate on scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2, Instructions for Offsite Dose Assessment Nomogram.

Table 1 Average Main Steam Safety Valve (MSSV) Flow Rate vs. Time After Reactor Trip Minutes after Reactor Trip 1

2 3

4 5

6 8

10 15 20 25 30 35 40 50

>60 Average Steam Flow Rate (Ibm) hr 9 00 E5 7 00 E5 5.97 E5 5.37 E5 4.97 E5 4.70 E5 4 30 E5 4 00 E5 3 59 E5 3 34 E5 3.15 E5 3.00 E5 2.89 E5 2.78 E5 2.59 E5 2 42 E5

21 RA-EP-02240 Revision 00 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS

-,- : -,Page 4 of 9

-" DATA SHEET 4 Release Rates from Noble Gases and Radioiodides Using Primary Parameters NOTE DATA SHEET 4 assumes all activity leaking from the Primary is released to atmosphere. This assumption is accurate if steam is being released directly from the OTSG via an open Main Steam Safety Valve (MSSV), an open Atmospheric Vent Valve-(AVV), an unisolable steam leak to the atmosphere,-or if the-affected Once Through Steam Generator (OTSG) is being used to supply Auxiliary Feed Pump Turbines. In other cases, the calculation is conservative.

Place emphasis on the latest leak rate as it will 'vary throughout the transient. The Slatest leak rate can be obtained by monitoring safety injection flow rate (i.e., BPI and

!...M ak~eu~p)..........

_ 2.....

Record the date and time.

Date __

Time

2.

Obtain the primary to secondary leak rate in gpm from the TSC engineers or ECC Operations Advisor and record in Step 4.

3.

Obtain the latest Reactor Coolant 1-13 land Xe-133 concentration( 40

-1

.cc

a.

IF fuel damage is NOT indicated, AND activity concentrations are NOT known, THEN obtain pre-trip values'from the Emergency RP Manager, and multiply the 1-131 value by 10 (to account for Iodine spiking).

b.

IF fuel damage is indicated, AND activity concentrations are NOT known,

, THEN obtain estimates from TSC Operations Engineers.

c.

Record in Step 4.

4.

Calculate the Release Rate.

Radioiodine:

__ gpm x

_1_

x.3E-5= _______;__

C.

cc sec

-(Fronm-2)

(1-13 1).(Releas&Rate).

-lCl Ci Noble Gas:

._ gpm x,L-.....

x 6.3E-5 =

°_

C CC (X

sec (From 2)

(' Xe-13 (Release Rate)

Perform one of the following:

, I "-4

a.

Insert the Noble Gas Release Rate into Step 4 of DATA SHEET 1 of and comlplete DATA SHEET 1.

b.

Insert the 1-133 Release Rate into Step 4 of DATA SHEET 2 of Attachment 3

.. fid complete DATA SHEET 2.'

c.

Plot the Noble Gas Release Rate on scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.

5.

I I I

22 RA-EP-02240 Revision 00 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS Page 5 of 9 DATA SHEET 5 Release Rate from Unisolated OTSG Steam Sample

1.

Record the date and time Date Time 2

Determine the total steam flow in Ibm/hr, from the following a

Consult TSC Engineers

b.

IF a MSSV or AVV release is occurring, THEN use Table 1 of this attachment

c.

IF an AFPT release is occurring, AND release duration is less than one hour, THEN use 4 4E4 Ibm/hr, OTHERWISE Contact TSC Engineers for release rates from AFPT lasting longer than one hour

d.

Record in Step 4.

3 Obtain the Xe-133 or 1-131 concentration (PC]

of the OTSG steam sample from the Sg-m)

Emergency RP Manager Record in Step 4 (Sample (11C, may be converted directly to ( PC]

provided the sample was analyzed at room temperature.)

4 Calculate the Release Rate by multiplying the steam flow by the concentration then by the correction factor (based on water density).

Ibm X _tCl x 1.27E-7 =

C_

hr gm sec (From 2)

(From 3 )

(Release Rate) 5 Perform one of the following

a.

Insert the Noble Gas Release Rate into Step 4 of DATA SHEET 1 of and complete DATA SHEET I b

Insert the 1-131 Release Rate into Step 4 of DATA SHEET 2 of Attachment 3 and complete DATA SHEET 2.

c.

Plot The Noble Gas Release Rate on scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.

23 RA-EP-02240 Revision 00 ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS

" - Page 6 of 9 "DATA SHEET 6 Release Rate from Steam Jet Air Ejector (SJAE) Releases I

NOTE I

SJAE Releases pass throughth6 Stationý Vent, and will

- contribute to the Station Vent Monitor Renidings.

II I

-Record the date and time Date Time

2.

Record the SJAE Noble Gas activity in cpm from RE 1003A or RE 1003B in Step 5.

3.

Record the SJAE flowi'ate in cfm from FI 1002 in'Step 5.

4.

Choose the appropriate correction factor and record in Step 5.

For RE 1003A, use 1.3 E-l1 For RE 1003B, use 1.5 E-11

5.

Calculate the Release Rate of Noble gases by multiplying the values below:

--- cpmx _

_cfm x

=

Ci "sec (From 2.)

(From 3.)

(From 4.)

(Release Rate)

6.

Perform one of the following:

a.

Insert the Release Rate into'Step 4 of DATA SHEET 1 of Attachment 3 and complete DATA SHEET 1.

b. ----Plot The Noble Gas Release Rate on scale'(C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.

24 RA-EP-02240 Revision 00 ATTACHMENT 4 SECONDARY SIDE RELEASE CALCULATIONS Page 7 of 9 DATA SHEET 7 Estimated Release Rate with Solid Once Through Steam Generator (OTSG)

NOTE Complete this data sheet for every incident in which the relief valves open The number of MSSVs open and length of time that they are open may only be obtainable by direct observation Record the date and time Date Time 2

Calculate the net reading of RE 600 or RE 609 (circle one) cpm - 300 cpm =

cpm (Gross Reading)

(Background)

(Net Reading) 3 Use time after reactor shutdown to determine the Reactor Coolant activity conversion factor from Figure 1.

PiCi Record in Step 5 & 7 cc cpm

4.

Determine flow rate for MSSVs. (Maximum flow rate of each MSSV is 1.46 E5 cc )

sec Record in Step 5.

x 146E5 C.C

=

c___

C SeC Sec number of MSSVs open)

5.

Determine Release Rate of MSSVs and record in Step 8:

lACI CC x CC__c x

cpm x 1.0 E-6 CL CI sec cpm VaCi sec (From 4.)

(From 3 )

(From 2.)

(Release Rate)

6.

Determine flow rate for AVVs (Check one), and record in Step 7

[] One AVV open 9.5 E4 c.c LI Two AVVs open 1.9 E5._c see see

25 RA-EP-02240 Revision 00

• - ATTACHMENT 4: SECONDARY SIDE RELEASE CALCULATIONS

- TPage 8 of 9

-DATA SHEET 7 (Continued) 7.- Determine Release Rate for AVV and recorld in Step 8.

C__ X-_-___

x

. cpmxl.E-6 C... =

Ci sec cpm..

sec (From 6.)

(From 3.)

(From 2.)

(Release Rate)

8.

Determin Total Release Rate.

Ci C..Ci-Ci

,____sec

+

sec

-sec (From 5.)

(From 7.)

(Total Release Rate)

9.

Perform one of the following:

a.

Insert the Release Rate into Steip 4 of DATA SHEET 1, Attachment 3 and complete DATA SHEET 1.

b.

Plot the release rate on Scale (C) of the Offsite Dose Assessment Nomogram and complete Attachment 2.- -

26 RA-EP-02240 Revision 00 ATTACHMENT 4 SECONDARY SIDE RELEASE CALCULATIONS Page 9 of 9 NORMAL REACTOR COOLANT ACTIVITY (0 1% FAILED FUEL) CONVERSION FACTOR vs TIME AFTER SHUTDOWN Hours after iiCi/cc Shutdown cpm 0

9.OOE-06 0.5 1.20E-05 1

1 42E-05 1 5 1.70E-05 2

1 95E-05 2 5 2 30E-05 3

2 75E-05 3 5 3 30E-05 4

3 95E-05 4 5 4 80E-05 5

5 70E-05 5.5 6 80E-05 6

8 20E-05 6.5 9.50E-05 7

1.10E-04 7 5 1 27E-04 8

1 50E-04 Hours after

[1Ci/cc Shutdown cpm 8 5 1 75E-04 9

2 02E-04 9 5 2.40E-04 10 2.80E-04 10 5 3.40E-04 11 3.90E-04 11 5 4.60E-04 12 5 30E-04 125 6 20E-04 13 7 02E-04 135 8 14E-04 14 9 50E-04 14.5 1 1OE-03 15 1 25E-03 15.5 1 40E-03 16 1 60E-03 Hours after itCi/cc Shutdown cpm 165 1 75E-03 17 1.95E-03 175 2.15E-03 18 2.45E-03 185 2.70E-03 19 3.OOE-03 195 3.45E-03 20 3.75E-03 20 5 4 20E-03 21 4.55E-03 21 5 5.10E-03 22 5 60E-03 225 6 10E-03 23 6 60E-03 23 5 7 20E-03 24 8 OOE-03 FIGURE 1 pCiecc cp.

1012 10' 10-s 10-#

12 16 20 24 HOUtS

27 RA-E]

Revisi ATTACHMENT 5: CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 4596B

- Page I of6 7 7.

NOTE

° Obtain containment radiation level from SPDS, Radiation Trends.

Obtain containment pressure from SPDS, Containment Trends, or by accessing CRT DISPLAYS: points P314, P315, P316, and

""P317. -.

°-------

- - -2 "CAUTION

-Use this'attachment for the following conditions only:.

Vent Monitors are not available or is known that the releaise is bypassing the Station Vent Monitors.

P-02240 on 00

1.

Record the date and time-Date Time

2.

Deter-mine the containment radiation level: RE 4596A or RE 4596B (Circle one) aand record in Step 6.

" Rem hr

3.

Determine the elapsed time since the reactor was tripped or a significant downpower maneuver occurred (i.e., greater than 30%).

hours

4.

IF containment spray is available, Check one THEN use Figure 1, of this attachment, Figure 1. [: spray available OTHERWISE use Figure 2 of this attachment Figure 2. Ol no spray available

5.

Determine the radiation monitor multiplication factor from Figure 1 or Figure 2 and record in Step6_

Xe-133 factor _

_1-131 factor

6.

-Determine the uncorrected release rate.

Re-x

-C hr sec (From 2.)

Xe-133 Factor

. (Xe-133 Release Rate)

(From 5.)

Rein-X_-

__=

C, hr sec

.. (From 2.)-.

1-l31Factor -...

(1-131 Release Rate)

.(From5.)-

28 RA-EP-02240 Revision 00 ATTACHMENT 5 CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 4596B Page 2 of 6 NOTE 7 The prior calculation assumes the Technical Specification leak rate of 0.5% per day at 38 0 PSIG A leak area of 0.13 square inches should be used, unless it is known that additional leak paths from containment exist, and the leak area can be estimated The calculation provided in Step 7 may be utilized to correct for any leak area or containment pressure IF conditions warrant, THEN correct for containment pressure, and leak rate using the following equation:

8 Record the wind speed.

Convert the wind speed from mph to m/sec.

mph x 0 447 n/sec m

mph sec (Wind Speed)

(Wind Speed)

9.

Record Stability Class (From Attachment 9)

A B

C D

E F

G (Circle one) 7.

a XE-133 Uncorrected CTMT XE-133 Release Rate Corrected (from 6)

X Leak Area X

Pressure

=

Release Rate C((

n ]

3 psig]

sec]

X 0.13 1n2 38 pstg_ =

see

"29 RA-EP-02240 Revision 00 ATTACHMENT 5: CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 4596B

.Page 3 of 6

10.

--Using Table 1, enter the.Z (rn 2) at distances of 0.75, 2, 5, and 10 miles for the Stability Class in step 9 in Column (B) of Tables 2 &3.

11.

In Tables 2 & 3, divide Column (B) by Column (C) and enter in Column (D).

12.-

In Tables 2 & 3, multiply Column (D) by Column (E) and enter iri Column (F).

13.

Determine the appropriate Noble Gas Correction Factor and enter in Column (G) of Table 2.

IF fuel damage or cladding failures have occurred, THEN, use Table 3 of Attachriient 3 ico obtain Noble Gas Correction Fac-tor.

Otherwise, use 10.0 for Noble Gas Correction Factor.,

Multiply Column (F) by Column (G) and enter in Column (H) of Table 2.

14.

Determine the appropriate 1-131 Correction Factor from Table 6 of Attachment 3 and enter in Column (G) of Table 3. -Multiply Column (F) by Column (G) and enter in S

.Column (H) of Table 3. -..

4

30 RA-EP-02240 Revision 00 ATTACHMENT 5 CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 4596B Page 4 of 6 TABLE 1. XP (m2) for Stability Classes as a Function of Downwind Distances Q

TABLE 2. Total Effective Dose Equivalent (Tede) Rate Column (A)

Column (B)

Column (C)

Column (D)

Column (E)

Column (F)

Column (G)

Column (H)

Downwind x

Release Nobel Gas TEDE Distance Windspeed Q

Rate Conc.

Noble Gas Rate (Miles)

Xp (M2)

(--

(sec)

Cc(Cs Correction (Rem'h Q ~

~

M "sc i',ClJ Factor hr From From From From Att 3 N/A Table 1 Step 8 B/C=D Step 7 DxE=F Table 3 FxG=H 0-75 2.00 5 00 1000 TABLE 3 Thyroid Dose Rate Column (A)

Column (B)

Column (C)

Column (D)

Column (E)

Column (F)

Column (G)

Column (H)

Downwind x

Release 1-131 Thyroid Distance Windspeed Q

Rate Conc.

1-131 Dose Rate (Miles)

2.

(C (LO)

Correction (em (Q iles V

sec

)

cc)

Factor

\\hrJ From From From From Att 3 N/A Table 1 Step 8 B/C=D Step 7 DxE=F Table 6 FxG=H 0.75 2.00 5.00 1000 STABILITY CLASS MILES A

B C

D E

F G

075 2.1E-6 I 4E-5 3.5E-5 9.9E-5 2 0E--4 4 5E-4 1.3E-3 2

1.1E-7 2 0E-6 5.8E-6 2.2E-5 4 6E-5 1 OE-4 2 8E-4 5

7.1E-9 3 2E-7 1.1E-6 5.5E-6 1 3E-5 3.1E-5 8.2E-5 10 8.9E-10 8.OE-8 3.2E-7 2.OE-6 5 IE-6 1 3E-5 3.4E-5

31 RI Re ATTACHMENT 5: CALCULATIONS FOR CONTAINMENT RELEASES

~-EP-02240

~vision 00 USING RE 4596A OR RE 4596B Page 5 of 6

~FIGURE1I V-4f M-ni i ; 311

3UfltE 0

C'.>

0 C) V:

I iomu-4 uopnfldpInn joiuoW pwrj JfsM~

V--4 qb X)

LLLLLLLL 

III" 11111111 It 1.0

'0 C*4 MINI~

I

-4 2

-L I I I'LL A-I I I I I ýý 11 JA I

A

32 RA-EP-02240 Revision 00 ATTACHMENT 5 CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4596A OR RE 4596B Page 6 of 6 FIGURE 2 4) cr.

0-4 41.)

4-J 0

"v" 0

H

0

-4 0

-4

%0-0 0

.ioloe uuo.oIdtijnN,* jo.uoWAI pgI jjj 0

4) 1' 0 L

7l lIILE Il t

iiiii.,P IIIII I I JJI1 1 I A

!F--

t 111-1 11 IlllA!

I -

I-F DA, II I IF

-T Il l l L

I Ill l liL F

Ill I

III l l i I I ll Iltll i i illl i

t i L, '

L~~llI1!1111 fli lI i

I ~ t

<11111~ ~

~~~L !

d II II

• Ll~l I IIIII I

!l~

• L~ llI

[

III II

!1 11IT I

I i

i I

i 1

III III III III III Iii I !

I I

I I

I.

33 RA-EP-02240 Revision 00 ATTACHMENT 6: CALCULATIONS FOR CONTAINMENT RELEASES USING RE 4597 AB OR RE 4597 BB Page1 of 1 Record the date and time.

Date -

Time NOTE 2 2

Obtain containment Noble Gas concentration from SPDS Radiation Trends.

2 Obtain containment pressure from SPDS, Containment Trends; or by

-accessing CRT DISPLAYS: points P314, P315, P316 and P317.".

2.

Determine the Containment Noble Gas concentration from RE 4597 AB (Ch. 1 or Ch. 2) OR RE 4597 BB (Ch. 1 or Ch.2)

(Circle instrument and channel used)

AND enter Containment Noble Gas concentration in Step 5.

iCi cc

3.

Determine the containment pressure in psia and convert to psig, if necessary.

psia - 14.7 =

psig

4.

Determine the Containment Leak Rate Fraction by multiplying the square root of containment pressure in PSIG times 8.3 E-4 and enter in Step 5._

L psig x 8.3 E-4= __

_leak rate (From 3.)

(fraction per day)

IF Containment pressure cannot be obtained,-,

THEN use 5.0 E-3 leak rate fraction per day and enter leak rate fraction in Step 5.

5.

Determine the Release Rate from containment.

0.928 ccCi -

._ i C..._..

.-- sec VCi cc sec (From 4),

(From 2)

(Release Rate)

6.

'Perform one of the following:'

- a..

Insert the Noble Gas Release Rate into Step 4 of DATA SHEET 1 of and complete DATA SHEET 1.

b. -- Plot the release rate on Scale (C) of the Offsite Dose Assessment Nomogram and complet6 Attachment 2..

34 RA-EP-02240 Revision 00 ATTACHMENT 7 DOSE PROJECTIONS BASED ON FIELD MONITORING DATA Page 1 of 4 NOTE This calculation does not include that contribution to TEDE from radioiodide internal exposure. The maximum amount of difference associated with this assumption is 3% of the total TOTAL EFFECTIVE DOSE EOUIVALENT (TEDE)

1.

Record date and time Date Time

2.

Record the distance downwind that the sampling location lies from the release point (to the nearest 1/2/2 mile) miles.

3.

Record Stability Class (From Attachment 9, Meteorological Data, Step 4)

(circle one)

A B

C D E F G 4

Record survey meter reading (closed-window)

(A) mREM hr Record 0.75 mile, 2mile, 5 mile, 10 mile values in Column (A) of Table 1 5

Record 2H (meter 2) value at the sampling location (from Table 4 of this attachment)

Q (B)

Z (m2)

Q Record 0.75 mile, 2mile, 5 mile, 10 mile values in Column (B) of Table 1

6.

Record E (in -2) values for 0.75, 2, 5, and 10 miles in column (C) (from Table 4 of this attachment).

Q 7

Divide (A) by (B) and multiply by (C) then divide by 1000 to obtain the TEDE rate for each downwind distance below and record in Column (D).

Table 1. TEDE Rate (A)

(B)

(C)

(D) mREM V (m

2)

X-(m-2 )

REM hr V

W) hr Downwind From Step 4 From Step 5 From Table 4 (A X C-1000 = REM Distance B

hr 0 75 mile 2 mile 5 mile 10 mile I I I

35 RA-EP-02240 Revision 00 ATTACHMENT 7: DOSE PROJECTIONS BASED ON FIELD MONITORING DATA

-Page 2 of 4j THYROID DOSE RATE (CDE)

1.

Record date and time.

Date Time

2.

Record sample: start time.

, stop time.,'

3.

Record net reading of air sampler cartridge _

net cpm.

4.

Record air sampler flow rate _

CFM.

5.

Record sample collection time _

.minutes.

--- 6. -- -Determine Sample volume CFM x

_minutes

=

ft3

..... Flowrate

, Collection Time (Total Volume)

-(From4.).

(From 5.)

ŽC.ft3

7.

Multiply the net cpm reading by 4.2 E-9 cc and divide by the sample volume.

S..

cpm...

netcpmx4.2E +_

.ft3 =

,PIC, cc Net Reading Sample Volume (Iodine Air Conc.)

(From 3.)

(From 6.)

8.

Record the distance downwind that the sampling location lies from the release point (to the nearest 1/2/2 mile) miles.

9.

Record Stability Class (from Attachment 9, Meteorological Data, Step 4)

(circleone) A B

C D E F G

10.

Multiply Iodine Air Concentration by the appropriate correction factor from Table 6. of "Attachinent 3 to obtaifiThjro6id Dose Rate at sampling location.

A._CIx (A)_REM cc (hr Iodine Air Conc.

from Table 6.

(From 7) of Attachment 5 Record above value (A) in Column A of Table 2.

11. -Record 2L (M-2) value at the sampling location (from Table 4. of this' attachment)

Q (B) __-_2_

Q Record above value (B) in Column B of Table 2.

36 RA-EP-02240 Revision 00 ATTACHMENT 7: DOSE PROJECTIONS BASED ON FIELD MONITORING DATA Page 3 of 4 12 Record 2,!j (m 2 ) values for 0 75, 2, 5, and 10 miles in Column (C) (from Table 4. of this attachment)

Q 13 Divide (A) by (B), and multiply times (C) to obtain Thyroid Dose Rate (D)

[Committed Dose Equivalent (CDE)]

Table 2. Thyroid Dose Rate A

B C

D Downwind mREM X

M-Z-L (m-2)

REM Distance hr V(m2)

Q hr From Step 10 From Step 11 From Step 12 (A x C= REM)

B hr 0.75 mile 2 mile 5 mile 10 mile 14 Total Organ Dose Equivalent (TODE) to the Thyroid is equal to:

TEDEr

+

CDEtr

= TODEtr (REM/hr)

(REM/hr)

(REM/hr)

TODEtr = Total Organ Dose Equivalent (TODE) to the Thyroid at distance r TEDEr = Total Effective Dose Equivalent (TEDE) at distance r CDEtr = Committed Dose Equivalent (CDE) to the Thyroid at distance r Table 3 TODE to the Thyroid Downwind TEDEr CDEtr TODEtr Distance REM)

REM (REM )

hr hr hr 0 75 nule 2 mile 5 mile 10 mile

37 RA-EP-02240 Revision 00 ATTACHMENT 7-DOSE PROJECTIONS BASED ON FIELD MONITORING DATA SPage 4 of 4 Table 4. 2L (rni-) for Various Stability Classes as a Function of Distance Q

Stability Class MILES A

B C

D E

F G

0.75 2.1E-6

-1.4E-5 3.5E-5 9.9E-5 2.OE-4 4.5E-4 1.3E-3 1

9.OE-7 8.0E-6 2.1E-5, '"

6.3E-5 1.3E-4 2.9E-4 8.OE-4 1.5 2.6E-7 3.6E-6 9.8E-5 3.3E-5 "

7.OE-5 1,

1.6E-4 4.3E-4 2

1.1E-7 2.OE-6

-5.8E-6

2.2E-5

'4.6E-5 1.OE-4 2.8E-4 2.5 5.7 E-8 1.3E-6 3.9E-6 1.5E-5 3.3E-5 7.7E-5 2.1E-4 3

3.3 E-8 8.9E-7 2.8E-6 1.2E-5 2.6E-5 6.OE-5 1.6E-4 3.5 2.1E-8 6.5E-7 2.1E-6

-9.3E-6 2.1E-5 4.9E-5 1.3E-4 4

1.4E-8 5.OE-7 1.7E-6 7.6E-6 1.7E-5 4.1E-5 1.1E-4 4.5 9.8E-9 4.6E-7 1.3E-6 6.4E-6 1.5E-5 3.5E-5 9.4E-5 5

7.1E-9 3.2E-7

,1.1E-6 5.5E-6 1.3E-5 3.1E-5 8.2E-5 5.5 5.4E-9 2.7E-7

-9.3E 4.8E 1.1E-5 2.7E-5 7.3E-5 6 & 6.5 3.8E-9 2.1E-7 7.5E-7 4.OE-6 9.5E-6 2.3E-5 6.2E-5 7 & 7.5 2.4E-9 1.5E-7 5.6E-7 3.2E-6

-7.8E-6 1.9E-5 5.1E-5 8 & 8.5 1.6E-9

-1.2E-7 4.5E-7 2.6E-6 6.6E-6 1.7E-5 4.3E-5 9 & 9.5 1.1E-9 9.4E-8 3.7E-7 2.2E-6 5.6E-6 1.5E-5 3.8E-5 10 8.9E-10 8.0E-8 3.2E-7 2.OE-6 5.1E-6 1.3E-5 3.4E-5 2333 3

4, ft 4

3 3

3 3

1.

3

38 RA-EP-02240 Revision 00 ATTACHMENT 8" ESTIMATION OF TOTAL POPULATION DOSE Page 1 of 4 NOTE Use this attachment during Recovery, as a first estimate of Total Population dose from the release.

1. IF the Safety Parameter Display System (SPDS) is available, GO TO Step 2, SPDS Calculation, OTHERWISE, GO TO Step 3, Manual Calculation 2

SPDS Calculation a

Click the DOSE CALCU tab on the SPDS Process Book

b.

Double click on the POPULATION DOSE choice c

Select the Total Dose tab and perform the following actions:

(1)

Select desired RE 4598 Channel (A or B)

(2)

Verify Date of Exposure (3)

Verify Time exposure began (HH MM)

(4)

Verify Release duration (5)

Verify Date of Reactor Trip (6)

Verify Time of Reactor Trip (HH MM)

(7)

Click the CALCULATE DOSE button (8)

Select AUTOMATIC or MANUAL calculations (9)

Select the desired sector S.....................................................................................................................

NOTE 2 c (10):

The number of persons per sector can be obtained from local officials or from the "Development of Evacuation Time Estimates for Davis-Besse Nuclear Power Station.

S.....................................................................................................................

(10)

IF MANUAL was selected in step 2.c. (8)

THEN fill-in the Number of Persons for each Mile column on the TOTAL EFFECTIVE DOSE EQUILAVENT table OTHERWISE, N/A this step (11)

Click the ADD TO CUMULATIVE WORKSHEET button (12)

Repeat steps (9) through (11) for desired sector(s)

(13)

Select Cum Exposure tab to determine total cumulative dose for selected sector(s)

(14)

To clear Cumulative Exposure Worksheet:

(a)

Select Total Dose tab (b)

Click the CLEAR CUMULATIVE WORKSHEET button

39 RA-EP-02240 Revision 00 ATTACHMENT 8:'ESTIMATION OF TOTAL POPULATION DOSE "Page 2 of 4 I

-NOTE.

Use this attachment during Recovery, as a first estimate of Total Population dose from the release

3. Sector Worksheet Instructions

a.

Record Total Effective Dose Equivalent (TEDE) or thyroid dose rate for a given release in REM/hr in Column (A).

. (1) Use the 0.75 rile TEDE and thyroid dose rates for the 0-2 mile population, the 2 mile TEDE and thyroid dose ratesfor the 2-5 mile population, and the 5 mile TEDE and thyroid dose rates for the 5:10 mile population for conservatism..

b.

Multiply Coiumn (A) times exposure duration and record in Column (B).

c.

Record the number of persons in the affected sector for the given distance "and time of exposure in Colunimn (C).

(1)

IF an evacuation has occurred, THEN local officials may have the number of individuals remaining in the sector.

(2)

IF an evacuation has not occurred, OR local officials do not have the required information, TIEN take the data from "Development of Evacuation Time Estimates for Davis-Besse Nuclear Power Station".

d.

Multiply Column (B) times Column (C) and record in Column (D).

e.

--Total the Column (D) values.

f.,

Enter the Column (D) values on the appropriate Cumulative Exposure.

Worksheet, of this attachment.

40 RA-EP-02240 Revision 00 ATTACHMENT 8 ESTIMATION OF TOTAL POPULATION DOSE Page 3 of 4 Date of exposure:

Sector:

Time exposure began:

Exposure duration hours TOTAL EFFECTIVE DOSE EOUIVALENT (TEDFE)

Total Effective Dose Equivalent (TEDE) PERSON-REM THYROID (A)

(B)

(C)

(D)

REM Number of Mile hr REM Persons PERSON-REM 0-2 2-5 5-10 Total Thyroid PERSON-REM

1.

2 3

(A)

(B)

(C)

(D)

REM Number of Mile hr REM Persons PERSON-REM 0-2 2-5 5-10

41 ATTACHMENT 8: ESTIMATION OF TOTAL POPULATION DOSE

-Page 4 of 4 Cumulative Exnosure Worksheet RA-EP-02240 Revision 00

1.

Record the total PERSON-REM values from each Sector Worksheet. Sum the total PERSON-REM values to obtain the estimated Total Population Dose.

_ I

_ I _

Total

.4

-- ).

7*-

I Date Completed Name 4-

- TEDE Total Thyroid Date/Time/Sector PERSON-REM PERSON-REM I

0

42 RA-EP-02240 Revision 00 4,

ATTACHMENT 9: METEOROLOGICAL DATA Page 1 of 3 Obtain 15 minute average meteorological data from any of the following

"* Access the SPDS Process Book to access the meteorological data

"* Access the DADS nongraphic terminal to call up the meteorological data 2

IF the systems in Step 1 cannot be accessed, THEN obtain meteorological data from the following a

Access data from the Meteorological Tower using the points listed below:

Parameters MET Tower Points Wind Speed, 612' Elevation, in MPH.........................

M006 Wind Speed, 827' Elevation, in MPH...........................

M005 Wind Direction, 612' Elevation, in degrees....................

M003 Wind Direction, 827' Elevation, in degrees......................

M002 Ambient Temperature, 612' Elevation, in F...................

.M012 Temp. Differential, 827'-612', in F...........................

MOI I Temp. Differential, 917'-612', in 'F..........................

M010

b.

Contact the National Weather Service, or equivalent, using the Emergency Plan Telephone Directory.

3 Use wind speed and wind direction from one of the following elevations of the Meteorology Tower, in order of preference a

10 meters (612 feet above sea level)

b.

75 meters (827 feet above sea level)

c.

100 meters (917 feet above sea level) d Use conservative wind speed of 2 mph (0 9 m/s) 4 Obtain atmospheric Stability Class from one of the following indicators in order of preference.

a Lower delta T (827' - 612') (see Table 1 )

b.

Upper delta T (917'- 612') (see Table 2.)

c.

Standard deviation of wind direction from 10 meter elevation (see Table 3) d Use conservative Stability Class of F

43 RA-EP-02240 Revision 00 4 ATTACHMENT 9: METEOROLOGICAL DATA SPage 2 of 3

5.

For Periodic Updates, contact the National Weather Service (NWS), or equivalent, to investigate upcoming weather conditions.

a.

The NWS telephone number is listed in the Emergency Plan Telephone Directory in the Other Resources Section.

6.

IF in the Emergency Control Center/Emergency Operations Facility (ECC/EOF),

THEN determine if a lake breeze is occurring by looking for the following simultaneous conditions:

a.

Calendar date between March 15 and September 15.

b.

Time of day between sunrise and sunset.

c.

Wind direction from between 0' to 90°.

d.

Wind speed less than 12 mph.,_

e.

Wind speed decreases with height on Meteorological Tower.

f.

Stability Class A through D.

7.

IF a lake breeze is occurring while an airborne radioactive release is in progress or imminent, THEN the Dose Assessment Coordinator should:

a.

Inform the Ohio EMA of the lake breeze and that the plume may not follow the course indicated by the Meteorological Tower wind direction.

b.

Inform the Radiation Monitoring Teams (RMTs) that higher-than-projected dose rates may occur in the plume pathway.

44 ATTACHMENT 9 METEOROLOGICAL DATA Page 3 of 3 Table 1. Stability Class from Lower Differential Temperature RA-EP-02240 Revision 00 rl*'zcrintlnn Extremely unstable Moderately unstable Slightly unstable Neutral Slightly stable Moderately stable Extremely stable AT < -22

-22< AT <-20

-20< AT<-17

-17< AT<-06

-06< AT< 17 17< AT< 46 46< AT Table 2. Stability Class from Upper Differential Temperature Stability Class Descrmiontn R-nna, AT°IP/(if10()- 10im Extremely unstable AT < -3 1 Moderately unstable

-3 1 < AT < -2 8 Slightly unstable

-2 8 < AT < -2.5 Neutral

-2.5 < AT < -0.8 Slightly stable

-0.8 < AT < 2.5 Moderately stable 2.5 < AT< 6.6 Extremely stable 6.6 < AT Table 3. Stability Class from Standard Deviation of Wind Direction Stability Class Description Extremely unstable Moderately unstable Slightly unstable Neutral Slightly stable Moderately stable Extremely stable SD > 22 5 22.5 > SD > 17 5 17.5 > SD > 12 5 125>SD> 7.5 75>SD> 38 38>SD> 21 21>SD Stability Cla A

B C

D E

F G

A B

C D

E F

G A

B C

D E

F G

Ss Dýcýnntn.

T?-

ArrOW/ '7r%

In Description

f.

Ran P ATOPI(inti-iri)-

S*

1* *nn-*, AT°V;'/['-/'K_ I *hrn

RA-EP-02240 Revision 00 COMMITMENTS Step Number,

Step 6.3.3 Reference TERMS 0 13593 TERMS 0 13594 TERMS 0 13539 TERMS 0 14992 TERMS 0 13506 Comments Distance calculation methodology has been reexamined for compatibility with RA-EP-02245 Output data (dose rate) has been made consistent throughout this procedure Dose rates based on CTMT dome monitor and CTMT atmosphere sampling system Addresses lake breeze Noble gas correction factor which changes with time after reactor shutdown 45

Page 1 of 11 Davis-Besse Nuclear Power Station EMERGENCY PLAN IMPLEMENTING PROCEDURE

" RA-EP-02710

REENTRY REVISION 01 Prepared by

Procedure Owner:

Effective Date:

B.W. Cop'e Manager - Security NOV 2 0 2002 Procedure Classification:

X Safety Related Quality Related Non-Quality Related LEVEL OF USE:

IN-FIELD REFERENCE

2 RA-EP-02710 Revision 01 TABLE OF CONTENTS Page 1 0 PURPOSE 3

2.0 REFERENCES

3 30 DEFINITIONS....

3 40 RESPONSIBILITIES 3

50 INITIATING CONDITIONS.................................

4 60 PROCEDURE............................................

5 6.1 Emergency Plant Manager/Plant Recovery Manager............

5 6 2 Emergency RP Manager/OSC RP Coordinator.............

6 63 OSC Manager.....................................

6 6 4 Assistant OSC Manager...

7 6.5 OSC Team Briefer/Debriefer 7

6.6 Reentry Team(s)..........

8 70 FINAL CONDITIONS...................................

10 so RECORDS....

10 COMMITMENTS 11

3 RA-EP-02710 Revision 01 1.0 PURPOSE This procedure provides guidance for reentry into the Davis-Besse Nuclear Power Station (DBNPS) after the emergency situation is under control.

2.0 REFERENCES

2.1 Departmental

-2.1.1 DB-HP-01201, Administrative Dose Control Levels 2.1.2 RA-EP-02410, Operations Support Center Activation and Response 2.1.3 RA-EP-02620, Emergency Dose Control and Potassium Iodide Distribution 2.1.4 RA-EP-02640, Station Radiological Surveys and Controls During Emergencies 2.1.5 RA-EP-02720, Recovery 2.2 Manuals 2.2.1 DBNPS Emergency Plan 2.2.2 Corporate Emergency Response (CER) Plan, Davis-Besse Nuclear Power Station (DBNPS) 3.0 DEFINITIONS 3.1 REENTRY - Reentry into the DBNPS site to perform certain essential actions which could not be performed coincident with the immediate response to the emergency.

Reentry is made when the emergency situation is under control and more deliberate planning can be made for the activities to be performed. Reentry may occur before termination of the emergency or it may be conducted as part of the Recovery.

4.0 RESPONSIBILITIES 4.1 For reentry activities conducted before termination of the emergency and the initiation of Recovery, the Emergency Plant Manager shall be responsible for authorizing reentry and implementing this procedure. He shall inform the Emergency Director that reentry is being initiated.

4.2 For reentry activities conducted during Recovery, the Plant Recovery Manager shall be responsible for implementation of this procedure, and shall ensure that the Recovery Director remains informed.

4 RA-EP-02710 Revision 01 4 3 The Emergency Radiation Protection (RP) Manager and the Operations Support Center Radiation Protection (OSC RP) Coordinator shall plan the personnel radiological protection aspects of reentry into the DBNPS and appoint OSC RP Briefer/Debriefers.

4 4 The OSC Manager shall coordinate reentry activities and ensure that all reentry teams have been adequately briefed and debriefed on their return 4.5 The Supervisor - Emergency Preparedness shall be responsible for the accumulation and submittal of Quality Assurance Records and other records deemed necessary to Nuclear Records Management 50 INITIATING CONDITIONS This procedure shall be initiated when the emergency situation is under control and conditions exist which require entry into Station areas that have been evacuated due to adverse conditions or have been closed to personnel during an emergency.

RA-EP-02710 Revision 01 6.0 PROCEDURE 6.1 Emergency Plant Manager/Plant Recovery Manager The Emergency Plant Manager or if recovery has been initiated, the Plant Recovery Manager should:

6.1.1 Consult with the other emergency response personnel before reentry and review the following:.

a.

Available surveillance data to determine the plant areas actually or potentially affected byradiation and/or contamiiiation.

CAUTION 6.1.1.b The use of personnel who have a high cumulative radiation dose shall be minimized. Every effort shall be made to maintain radiation dose within the limits specified in DB-HP 01201. The Emergency Director shall be notified, and his approval obtairied, before any planned radiation dose in excess of applicable limits specified in RA-EP-02620.

b.

Radiation dose of personnel who shall participate in reentry operations to determine additional personnel requirements.

c.

The adequacy of radiation survey instrumentation, equipment and any special dosimetry requirements.

d.

Primary and backup communications methods.

e.

Known or potential hazards to personnel.

6.1.2 Authorize all entries into evacuated areas of DBNPS in accordance with RA-EP-02720, if recovery has been initiated.

6.1.3 Approve and prioritize all reentry team tasks. Initial reentry team goals typically include the following:

a.

Determination of the initial objectives required for recovery operations.

b.

Observation of hazards or potential hazards associated with the recovery.

c.

Obtaining a comprehensive radiation surveillance of DBNPS facilities.

d.

Isolating and posting of radiological and safety hazards.

6 RA-EP-02710 Revision 01 NOTE 6.1 4 Non-emergency limits for radiation dose shall be considered applicable for reentry activities, except under extreme circumstances Refer to DB-HP-01201 6.1.4 Review and approve, as appropriate, any radiation dose in excess of applicable limits 6.1 5 Keep the Emergency Director or Recovery Director informed of significant events.

6 2 Emergency RP Manager/OSC RP Coordinator The Emergency RP Manager and/or the OSC RP Coordinator should:

6 2 1 Establish guidelines to ensure that reentry operations are conducted in a manner to minimize radiation dose to personnel 6.2.2 Provide radiological controls coverage for all reentry teams in accordance with RA-EP-02640 6.2 3 Ensure that the OSC Briefer/Debriefer adequately briefs reentry personnel on radiological hazards before they enter the RRA using the Emergency Team Briefing Form, DBEP-024 6 2 4 Ensure that the OSC Team Briefer/Debriefer is informed of any significant changes in conditions so that all subsequent teams have access to the most current information 6 3 OSC Manager 6.3 1 Oversee the activities of the OSC in accordance with RA-EP-02410 6.3 2 Update the Emergency Plant Manager or Recovery Manager periodically on current plant conditions and the status of the reentry teams

7 RA-EP-02710 Revision 01 6.4 Assistant OSC Manager The Assistant OSC Manager should:

6.4.1 Designate members of the reentry teams.

6.4.2 Reentry Teams shall consist of a minimum of two people:

a.,

One memb~er trained in radiation protection.

b:

The second member will depend on the specific tasks to be accomplished.

6.4.3 A.Standby Team shall be designated and briefed with the reentry team on known or potential hazards, and kept informed of th6 reentry team's location so that they can provide rescue and first aid assistance at all times. The "Standby Team shall consist of at least two members:

"a.

'One trained in radiation protection.

b.

One trained in first aid.'

6.4.4 Ensure the OSC Team Briefer/Debriefer adequately briefs reentry personnel on the maintenance and/or operation objectives of the mission, unsafe conditions and appropriate safety precautions using the Emergency Team Briefing Form, DBEP-024.

6.4.5 After obtaining approval from the Emergency Plant Manager or Plant Recovery Manager, dispatch the Reentry Team(s).

6.4.6 Maintain communications with the reentry teams.

6.4.7 Keep the OSC Manager informed of reentry team activities.

6.4.8 Ensure the OSC Team Briefer/Debriefer interviews teams on their return using the Emergency Team Debriefing Form, DBEP-024.

6.5 OSC Team Briefer/Debriefer The OSC Team Briefer/Debriefer should:

6.5.1 Ensure that reentry teams are adequately briefed using the Emergency Team Briefing Form, DBEP-024:

a.

Areas to be surveyed.

b.

Anticipated routes to the area.

c.

Anticipated radiation and contamination levels expected.

d.

Required equipment.

e.

Shielding requirements and availability.

8 RA-EP-027 10 Revision 01

f.

Protective clothing and equipment required (PCs, SCBA, etc.)

g.

Access Control procedures h

Exposure control limits and personnel dosimetry required

i.

Decontamination requirements.

j Primary and backup communications methods

k.

Known or potential hazards and appropriate safety precautions.

6 5 2 Interview the team(s) on their return, and document all pertinent information on the Emergency Team Debriefing Form, DBEP-024 6 5 3 Ensure that the team(s) are informed of any significant changes in conditions.

6 5 4 Report the results of the reentry to the OSC Manager or the RP Coordinator if the Recovery Organization is in place, for further dissemination to appropriate individuals.

6.6 Reentry Team(s)

Reentry Team(s) should:

6 6 1 Assemble all the necessary equipment according to the Emergency Team Briefing Form, DBEP-024 and verify operability of equipment.

9 RA-EP-02710 Revision 01 WARNING 6.6.2 If dose rates encountered exceed the limits established during reentry planning, reentry personnel shall:

1.

Exit the area immediately.

2.

Return to a safe area.

3.

Contact the OSC Manager for further instructions.

6.6.2 Enter the area when authorized by the Emergency Plant Manager or Recovery Manager.

6.6.3 Conduct a radiation survey of the area in accordance to RA-EP-02640.

6.6.4 Perform first aid and rescue operations, if necessary.

6.6.5 Assess the following items as directed:

a.

Condition of plant equipment and areas

b.

Potential for additional problems

c.

Consequences of damage which occurred during the emergency

d.

Accessibility of affected areas

e.

Radiological, toxic, structural or other hazards

f.

Other potential personnel or equipment hazards 6.6.6 Perform inspections, repairs and operations as directed.

6.6.7 Maintain communications with the Assistant OSC Manager or OSC RP Coordinator, providing observed conditions and dose rates.

6.6.8 Isolate and post appropriate areas with the proper radiation warning signs and barrier ropes as Radiation, High Radiation and/or Contamination areas.

6.6.9 Return to the OSC for debriefing after completion of assigned tasks.

10 RA-EP-02710 Revision 01 70 FINAL CONDITIONS This procedure should be terminated when 7-1 Reentry operations have been completed and all reentry team members have been accounted for 7.2 Debriefing of reentry personnel has been completed and documented.

7.3 Records generated during the emergency are forwarded to the Supervisor Emergency Preparedness after review by the Emergency RP Manager and OSC Manager.

7 4 Emergency equipment has been inventoried and deficiencies identified and reported to the Supervisor - Emergency Preparedness 7 5 Procedural deficiencies have been identified and reported to the Supervisor Emergency Preparedness.

80 RECORDS 8 1 The following quality assurance records are completed by this procedure and shall be listed on the Nuclear Records List, captured, and submitted to Nuclear Records Management in accordance with NG-NA-00106 8.1.1 None 8.2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Nuclear Records Management in accordance with NG-NA-00106 82 1 None

11 RA-EP-02710 Revision 01 COMMITMENTS Step Number None Reference None END

//

Comments None