Text

Revised Epips, Including Revision 16 to RP/0/A/5700/012, Revision 3 to SR/0/B/2000/003, Revision 2 to HP/0/B/1009/002 and Revised Indexes. with Letter Dated December 14, 1999
	ML993550375
Person / Time
Site:	Mcguire, McGuire
Issue date:	12/14/1999
From:	Barron H; Duke Energy Corp
To:	; NRC/OCIO/IMD/RMB
References
	-nr, -RFPFR
	Download: ML993550375 (201)
	v • d • e

Duke Energy Corporation Duke E e McGuire Nuclear Station e rgW . SEn 12700 Hagers Ferry Road Huntersville, NC 28078-9340 (704)875-4800 om*cE H. B. Barron (704) 875-4809 FAX Vice President December 14, 1999 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Emergency Plan Implementing Procedures Enclosed for NRC staff use and review are the following Emergency Plan Implementing Procedures:

EPIP Index Page 1 EPIP Index Page 2 EPIP Index Page 3 RP/0/A/5700/012 SR/0/B/2000/003 HP/0/B/1009/002 HP/0/B/1009/020 (Deleted)

No privacy information is contained in these procedures. This correspondence does not contain any regulatory commitments.

Two copies are also being forwarded to NRC Region II, Atlanta, Georgia.

Very truly yours, H. B. Barron Vice President McGuire Site HBB:jcm Attachments

U.S. Nuclear Regulatory Commission December 14, 1999 Page 2 XC: (w/attachment)

Mr. Luis Reyes, Regional Administrator U.S. Nuclear Regulatory Commission Region II 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 (w/o attachment)

NRC Resident Inspector Frank Rinaldi, USNRC Lee Keller (EC050)

Electronic Licensing Library (EC050)

EP File 111

DUKE McGUIRE NUCLEAR SITE EMERGENCY PLAN IMPLEMENTING PROCEDURES APPROVED:- MAAE SAFt VSSURANCE MANAGER DATE APPROVED (I- z3 -11 EPIP Index Page 1 Dated 11/23/99 EPIP Index Page 2 Dated 11/23/99 EPIP Index Page 3 Dated 11/23/99 HP/O/B/1009/002 Dated 11/23/99 HP/O/B/1009/020 DELETED RP/O/A/5700/012 Dated 11/23/99 SR/O/B/2000/003 Dated 11/23/99

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE # TITLE REVISION NUMBER RP/O/A/5700/000 Classification of Emergency Rev. 004 RP/O/A/5700/001 Notification of Unusual Event Rev. 012 RP/O/A/5700/002 Alert Rev. 012 RP/0/A/5700/003 Site Area Emergency Rev. 012 RP/O/A15700/004 General Emergency Rev. 012 RP/O/A/5700/05 Care and Transportation of Contaminated Injured DELETE Individual(s) From Site to Offsite Medical Facility RP/0/A/5700/006 Natural Disasters Rev. 005 RP/O/A/5700/007 Earthquake Rev. 006 RP/0/A15700/008 Release of Toxic or Flammable Gases Rev. 003 RP/0/A/5700/09 Collisions/Explosions Rev. 000 RP/O/A/5700/010 NRC Immediate Notification Requirements Rev. 009 RP/O/A/5700/011 Conducting a Site Assembly, Site Evacuation or Containment Rev. 005 Evacuation RP/O/A/5700/012 Activation of the Technical Support Center (TSC) Rev. 016 RP/O/A/5700/013 Activation of the Emergency Operations Facility (EOF) DELETE RP/O/A/5700/14 Emergency Telephone Directory DELETE RP/0/A/5700/015 Notifications to the State and Counties from the EOF Rev. 007 RP/0/A15700/16 EOF Commodities and Facilities Procedure DELETE RP/0/A/5700/17 Emergency Data Transmittal System Access DELETE RP/0/A/57001018 Notifications to the State and Counties from the TSC Rev. 005 RP/0/A/5700/019 Core Damage Assessment Rev. 003 RP/0/A/5700/020 Activation of the Operations Support Center (OSC) Rev. 010 RP/0/A/5700/21 EOF Access Control DELETE RP/0/A/5700/022 Spill Response Procedure Rev. 009 RP/0/A/5700/024 Recovery and Reentry Procedure Rev. 001 RP/O/A/5700/026 Operations/Engineering Technical Evaluations in the Technical Rev. 000 Support Center (TSC)

RP/0/B/5700/023 Community Relations Emergency Response Plan Rev. 000 OP/O/B/6200/090 PALSS Operation for Accident Sampling Rev. 009 I November 23, 1999 Rev. 3

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE # TITLE REVISION NUMBER HP/O/B/1009/002 Alternative Method for Determining Dose Rate Within Rev. 002 the Reactor Building HP/O/B/1009/003 Recovery Plan Rev. 002 HP/0/B/1009/05 Initial Evaluation of Protective Action Guides Due to DELETED Abnormal Plant Conditions HP/0/B/10091006 Procedure for Quantifying High Level Radioactivity Rev. 004 Releases During Accident Conditions HP/O/B/1009/010 Releases of Radioactive Effluents Exceeding Selected Rev. 004 Licensee Commitments HP/l/11009/015 Unit 1 Nuclear Post-Accident Containment Air Sampling Rev. 003 System Operating Procedure HP/2/B/1009/015 Unit 2 Nuclear Post-Accident Containment Air Sampling Rev. 003 System Operating Procedure HP/0/B/1009/016 Distribution of Potassium Iodide Tablets in the Event of Rev. 001 a Radioiodine Release HP/O/B/1009/020 Manual Procedure for Offsite Dose Projections DELETED HP/0/B/1009/021 Estimating Food Chain Doses Under Post-Accident Conditions Rev. 001 HP/O/B/1009/022 Accident and Emergency Response Rev. 001 HP/0/B/1009/023 Environmental Monitoring for Emergency Conditions Rev. 002 HP/O/B/1009/024 Personnel Monitoring for Emergency Conditions Rev. 000 HP/0/B/1009/029 Initial Response On-Shift Dose Assessment Rev. 004 SH/0/B/2005/001 Emergency Response Offsite Dose Projections Rev. 000 SH/0/B/2005/002 Protocol for the Field Monitoring Coordinator During Emergency Rev. 000 Conditions Standard Procedure for Public Affairs Response to the SR/0/B/2000/01 Rev. 001 Emergency Operations Facility SR/0/B/2000/002 Standard Procedure for EOF Commodities and Facilities Rev. 000 SR/0/B/2000/003 Activation of the Emergency Operations Facility Rev. 003 2 November 23, 1999 Rev. 3

EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE # TITLE REVISION NUMBER McGuire Site Site Assembly/Accountability and Evacuation/Containment DELETED Directive 280 Evacuation EP Group Manual Section 1.1 Emergency Organization Rev. 017 MNS RP Manual: Section 18.1 Accident and Emergency Response DELETED Section 18.2 Environmental Monitoring for Emergency Conditions DELETED Section 18.3 Personnel Monitoring for Emergency Conditions DELETED Section 18.4 Planned Emergency Exposure DELETED 3 November 23, 1999 Rev. 3

(1) ID No. RP/O/A/5700/P012 (Ro6-97)

Duke Power Company Revision No. 016 PROCEDURE PROCESS RECORD PREPARATION (2) Station McGuire Nuclear Station (3) Procedure Title Activation of the Technical Support Center ([SC)

Date I 1 1 cI (4) Prepared By (5) Requires 10CFR .59 evaluation?

Yes (New procedure or revision with major changes)

[No (Revision with minor changes)

[No (To incor rate previously approved changes)

D ate -1;.

(6) Reviewed By f (QR)

Date -1//

Cross-Disciplinary'Review By (QR) NA Date Reactivity Mgmt. Review By (QR) NA (7) Additional Reviews Reviewed By Date Date Reviewed By (8) Temporary Approval (if necessary)

Date By (SRO/QR)

By kwh) D e (9) Approved By Date (//Z-_/gI PERFORMANCE (Compt re wi h Control Copy every 14 calendar days while work is being performed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification El Yes El N/A Check lists and/or blanks initialed, signed, dated or filled in NA, as appropriate?

E] Yes nl N/A Listed enclosures attached?

EL Yes El N/A Data sheets attached, completed, dated and signed?

LI Yes EL N/A Charts, graphs, etc. attached, dated, identified, and marked?

EL Yes LI N/A Procedure requirements met?

Verified By Date (13) Procedure Completion Approved Date (14) Remarks (attachadditionalpages, if necessary)

I Procedure No.

Duke Power Company McGuire Nuclear Station RPI/OA/5700/012 Revision No.

016 Activation of the Technical Support Center (TSC)

Electronic Reference No.

Multiple Use MC0048MF

RP/O/A/5700/012 Page 2 of 4 Activation of the Technical Support Center (TSC)

1. Symptoms Conditions exist where events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant and activation of the Emergency Response Organization (ERO) has been initiated.

2. Immediate Actions None

3. Subsequent Actions NOTE: This procedure is not intended to be followed in a step-by step sequence. Sections of the procedure are to be implemented as the applicable action becomes necessary.

3.1 The TSC is required to be activated for an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY declaration. It may also be activated for an UNUSUAL EVENT if deemed necessary by the Operations Shift Manager/Emergency Coordinator.

3.2 The TSC must be activated within ONE (1)HOUR AND 15 MINUTES (75 MINUTES) of an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY declaration.

This time frame must be met anytime it is deemed necessary to activate the TSC.

3.3 Upon notification to activate, the station manager or designee shall report and notify Operations Shift Manager in the Control Room of arrival.

3.3.1 Personnel in the Emergency Response Organization (ERO) assigned to the TSC shall report to the facility upon notification to activate.

3.3.2 The initial responders shall be responsible for the completion of their appropriate group enclosures and having Operational Responsibilities reviewed.

3.4 Each represented group is responsible for ensuring their appropriate initial checklist is completed.

Rev. 16

RP/O/A/5700/012 Page 3 of 4 3.5 The following definitions are applicable to the Emergency Notification Form for "Plant Condition": {PIP O-M97-4210 NRC-1}

" Improving: Emergency conditions are improving in the direction of a lower classification or termination of the event.

" Stable: The emergency situation is under control. Emergency core cooling systems, equipment, plant, etc., are operating as designed.

" Degrading: Given current and projected plant conditions/equipment status, recovery efforts are not expected to prevent entry into a higher emergency classification or the need to upgrade offsite Protective Action Recommendations.

3.6 Upon termination of the drill/emergency, the Emergency Coordinator/designee shall assume responsibility for ensuring the proper resolutions to all completed copies of the McGuire Operations Configuration Control Card(s) prior to the TSC/OSC being deactivated. The Emergency Coordinator/designee shall have overall responsibility for ensuring all cards are properly resolved or items logged prior to plant turn-over to the Operations Shift Manager. Once the items/cards have been properly resolved, the TSC/OSC may be deactivated. All completed cards shall be filed by Emergency Planning with other drill/emergency paperwork.

4. Enclosures 4.1 Emergency Coordinator Initial TSC Activation Checklist/Operational Responsibilities 4.2 Assistant Emergency Coordinator Initial TSC Activation Checklist/Operational Responsibilities 4.3 Radiation Protection Manager Initial TSC Activation Checklist/Operational Responsibilities 4.4 Offsite Dose Assessor Initial TSC Activation Checklist/Operational Responsibilities 4.5 Offsite Agency Communicator Initial TSC Activation Checklist/Operational Responsibilities 4.6 NRC Communicator Initial TSC Activation Checklist/Operational Responsibilities 4.7 Reactor Engineer Initial TSC Activation Checklist/Operational Responsibilities 4.8 Operations Manager in the TSC Initial TSC Activation Checklist/Operational Responsibilities Rev. 16

RP/O/A/5700/O 12 Page 4 of 4 4.9 Operations Procedure Support Initial TSC Activation Checklist/Operational Responsibilities 4.10 System Engineering Manager Initial TSC Activation Checklist/Operational Responsibilities 4.11 Emergency Planner Initial TSC Activation Checklist 4.12 Status Coordinator Initial TSC Activation Checklist 4.13 IAE Communications Initial TSC Activation Checklist 4.14 Operations Manager in the Control Room Activation Checklist/Operational Responsibilities 4.15 Data Coordinator Initial TSC Activation Checklist/Operational Responsibilities 4.16 Site Assembly Coordinator Initial TSC Activation Checklist 4.17 Emergency Coordinator / Emergency Operations Facility Director Turnover Checklist 4.18 Emergency Classification Termination Criteria 4.19 Fitness For Duty Questionnaire 4.20 Site Evacuation Coordinator Initial TSC Activation Checklist Rev. 16

Enclosure 4.1 RP/O/A/5700/012 Page 1 of 5 EMERGENCY COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

ESTABLISH a log of activities.

NOTIFY the Operations Shift Manager in the Control Room of arrival.

RECEIVE turnover from the Control Room as soon as practical utilizing Enclosure 4.17.

ASSURE the following TSC positions as a minimum are filled and prepared to assume their function prior to declaring the TSC activated:

-Emergency Coordinator -NRC Communicator

-Offsite Dose Assessor -Reactor Engineer

-Offsite Agency Communicator IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-1869}

CONDUCT a Time Out prior to activating the TSC.

DECLARE the TSC activated and announce the following via the TSC/OSC public address system: "This is _. I am the Emergency Coordinator. The TSC is officially activated as of The plant status is as follows:

OR "This is I am the Emergency Coordinator. The TSC is officially activated as of . I will give an update in __ minutes.

Rev. 16

Enclosure 4.1 RP/O/A/5700/012 Page 2 of 5 EMERGENCY COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL ANNOUNCE over the TSC/OSC public address system the following:

"Anyone who is reporting to this facility outside of your normal work hours and has consumed alcohol within the past five (5) hours, notify either the Emergency Coordinator in the TSC or the OSC Coordinator in the OSC."

ENSURE the Data Coordinator has synchronized the clocks in the TSC. {PIP O-M98-3522 }

NOTE: The following step should be repeated following each shift turnover.

ANNOUNCE to TSC a reminder to complete a "Work Hour Extension Form" if applicable. {PIP 0-M98-2099).

TURN OFF the plant page volume in TSC.

DISCUSS with the Radiation Protection Manager any radiological release or offsite radiological concerns.

ANNOUNCE over the TSC/OSC Public Address System the following if a release has occurred:

-Assume areas are contaminated until surveyed by RP.

-No eating or drinking until the TSC and OSC are cleared by RP.

EVALUATE with TSC personnel and the Radiation Protection Manager the need to conduct evacuation at this time based on the following criteria.

- Alert- determine by actual plant conditions

- Site Area Emergency- consider evacuation/relocation of non-essential personnel.

- General Emergency- evacuate all non-essential personnel

- Notify EOF anytime personnel are relocated onsite or evacuated from the premises.

Rev. 16

Enclosure 4.1 RP/O/A/5700/012 Page 3 of 5 EMERGENCY COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL REQUEST all TSC and OSC Managers to have FAXED to the OSC the name, social security number and RP badge number of any person(s) who may be left onsite after evacuation of non-essential personnel but are located in an area other than the OSC.

UPON declaration of a General Emergency the Emergency Coordinator shall IMMEDIATELY RECOMMEND to offsite authorities the following:

IF containment radiation levels exceed the levels on Offsite Dose Assessor, Enclosure 4.4, page 5 of 6, THEN:

Evacuate the 5-mile radius AND 10 miles downwind AND Shelter remaining zones as shown on Offsite Dose Assessor, Enclosure 4.4, page 4 of 6 using wind direction.

OR IF wind speed is less than or equal to 5 MPH THEN:

Evacuate zones L, B, M, C, N, A, D, 0, R AND Shelter zones E, F, G, H, I, J, K, P, Q, S.

OR IF wind speed is greater than 5 MPH THEN:

Evacuate the 2-mile radius AND 5 miles downwind AND Shelter remaining zones as shown on Offsite Dose Assessor, Enclosure 4.4, page 4 of 6 using wind direction.

Rev. 16

Enclosure 4.1 RP/O/A/5700/012 Page 4 of 5 EMERGENCY COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL DIRECT the Assistant Emergency Coordinator to FAX the turnover checklist (Enclosure 4.17) to the EOF Director (if time and situation permit). {PIP-0-M97-4112}

CONDUCT turnover to the EOF Director (EOFD) utilizing Enclosure 4.17.

NOTE: Provide periodic updates to the EOFD concerning plant status and request EOFD to provide assessment and field monitoring data on a periodic basis.

REQUEST the NRC Communicator to notify the NRC the EOF is activated.

ANNOUNCE to the TSC and OSC the EOF is activated.

REVIEW Operational Responsibilities (Enclosure 4.1, page 5 of 5).

ENSURE ALL completed copies of the McGuire Operations Configuration Control Cards are properly resolved prior to deactivation of the TSC/OSC.

IF the TSC becomes environmentally uninhabitable due to radiological or other conditions and the Control Room remains secure (habitable), THEN:

SELECT individuals to move inside the Control Room.

INSTRUCT all other TSC personnel to go to the EOF.

IF the Control Room also becomes uninhabitable due to radiological or other conditions, THEN INSTRUCT TSC personnel to report to the Simulator at the Training and Technology Center or EOF.

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.1 RP/O/A/5700/012 Page 5 of 5 EMERGENCY COORDINATOR OPERATIONAL RESPONSIBILITIES

1. Assure the TSC is maintained in a professional manner. Remind all groups to minimize noise and congestion.

2. Approximately every thirty (30) minutes, conduct a "Time-out" with the TSC staff to obtain current plant status. Ensure the OSC is aware of when "Time-outs" will take place.

3. Ensure all unnecessary communications are put on hold during "Time-outs". {PIP 0-M95-0160 }

4. Establish priorities.

5. Following time out, announce to the TSC and OSC the emergency classification, plant status, and priorities via the TSC/OSC public address system.

6. Institute procedures necessary to allow the Control Room to maintain control of the emergency condition.

7. Establish communications with the EOF Director at the Emergency Operations Facility.

8. Establish communications with Federal, State and Local authorities at county warning points or Emergency Operations Centers.

9. Maintain line of communications with these agencies to ensure they are informed of plant emergency conditions at all times.

10. Make decisions concerning all aspects of the emergency situation including alternate strategies (outside of procedures) as plant conditions necessitate.

11. Periodically assess the need for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months staffing and have the managers prepare as needed.

12. Establish a Recovery Organization PER (RP/O/A/5700/024, Recovery and Reentry Procedure) once the Emergency has been terminated. Applicable primarily for Site Area Emergency and General Emergency classifications. Refer to Enclosure 4.18 for Termination Criteria.

13. Make decisions on emergency classifications, mitigation strategies, contingency plans and protective actions for plant personnel and the general public.

14. Serve as Lead Decision Maker upon entry into Severe Accident Management Guidelines (SAMG).

Rev. 16

Enclosure 4.2 RP/O/A/5700/012 Page 1 of 2 ASSISTANT EMERGENCY COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-1869 }

ESTABLISH a log of activities.

ASSIST the Emergency Coordinator in gathering information to facilitate the activation of the Technical Support Center.

FAX turnover checklist (Enclosure 4.17) to the EOF Director when directed by the Emergency Coordinator. (PIP-0-M97-41121 PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.2 RP/O/A/5700/012 Page 2 of 2 ASSISTANT EMERGENCY COORDINATOR OPERATIONAL RESPONSIBILITIES

1. Assist the Emergency Coordinator in all aspects of Emergency Response.

2. Act as a receiver of information when the Emergency Coordinator is unavailable and relay the information to the Emergency Coordinator in a timely manner.

3. Proactively seek information when the Emergency Coordinator is in a reactive mode.

4. Make face-to-face confirmation of information provided when the Emergency Coordinator is unavailable.

5. Serve as the Emergency Coordinator when needed.

6. Assist in making decisions on emergency classifications, mitigation strategies, contingency plans and protective actions for plant personnel and the general public.

7. Assist Emergency Coordinator as a Decision Maker upon entry into Severe Accident Management Guidelines (SAMG).

Rev. 16

Enclosure 4.3 RP/O/A/5700/012 Page 1 of 5 RADIATION PROTECTION MANAGER INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster and ENSURE all Radiation Protection personnel reporting to the TSC also sign the roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm.{ PIP 0-M96-1869}

ESTABLISH a log of activities.

ESTABLISH communications with RP personnel in the OSC, Shift Lab and EOF using the cell phone, dial 4980. (Let it ring until you hear a beep. This connects you to the bridge line.).

COMMUNICATE through Emergency Coordinator that dosimetry is required and a dose card shall be filled out if necessary (drill SRWP is 33). {PIP 0-M94-1495}

DISCUSS the following with Emergency Coordinator:

1) Any release in progress including dose rates (especially at the site boundary)

2) Field Team status/data

3) Onsite radiological concerns ESTABLISH contamination control in the TSC, OSC and Control Room as necessary.

1. COMMUNICATE through the Emergency Coordinator that frisking of hands and feet is required prior to entry. {PIP 0-M94-1495 }

2. ESTABLISH smear survey frequency with OSC RP Supervisor (i.e., every 30 minutes).

Rev. 16

Enclosure 4.3 RP/O/A/5700/012 Page 2 of 5 RADIATION PROTECTION MANAGER INITIAL TSC ACTIVATION CHECKLIST INITIAL EVALUATE with the Emergency Coordinator the need to:

1) Move any Assembly Points in the release path

2) Conduct site and/or area evacuation

3) Recommend protective actions for emergency workers

4) Recommend protective actions for the public.

Rev. 16

Enclosure 4.3 RP/O/A/5700/012 Page 3 of 5 RADIATION PROTECTION MANAGER INITIAL TSC ACTIVATION CHECKLIST INITIAL UPON declaration of a General Emergency the Emergency Coordinator shall IMMEDIATELY RECOMMEND to offsite authorities the following:

IF containment radiation levels exceed the levels on Offsite Dose Assessor, Enclosure 4.4, page 5 of 6, THEN:

Evacuate the 5-mile radius AND 10 miles downwind AND Shelter remaining zones as shown on Offsite Dose Assessor, Enclosure 4.4,page 4 of 6 using wind direction.

OR IF wind speed is less than or equal to 5 MPH THEN:

Evacuate zones L, B, M, C, N, A, D, 0, R AND Shelter zones E, F, G, H, I, J, K, P, Q, S.

OR IF wind speed is greater than 5 MPH THEN:

Evacuate the 2-mile radius AND 5 miles downwind AND Shelter remaining zones as shown on Offsite Dose Assessor, Enclosure 4.4, page 4 of 6 using wind direction.

Rev. 16

Enclosure 4.3 RP/O/A/5700/012 Page 4 of 5 IF a situation, which is immediately hazardous to life or valuable property, exists, THEN evaluate potential dose rates by one of the following methods:

1. Contact RP shift at Ext. 4282

2. Assess area monitors AND Ensure a Request for Emergency Exposure is completed in the OSC prior to dispatch of emergency workers.

REVIEW RP/O/A/5700/000 criteria (EMFs, offsite dose, etc.) for emergency classification changes and discuss with OPS Procedure Support position.

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.3 RP/O/A/5700/012 Page 5 of 5 RADIATION PROTECTION MANAGER OPERATIONAL RESPONSIBILITIES

1. Provide and coordinate Radiation Protection resources as necessary.

2. Assure RP responders complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting outside their normal working hours.

3. Ensure all TSC personnel are wearing dosimetry and using dose cards (SRWP 33).

4. Ensure all necessary precautions of the Radiation Protection Manual Emergency Procedures are adhered to (i.e. administer Potassium Iodine tablets as required.)

5. Discuss with Operations Support Manager information regarding plant conditions such as power failures, valve closures as necessary.

6. Ensure responders are aware of the need for frisking prior to entry into the TSC as conditions dictate.

7. Prepare for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage as necessary.

8. Determine if persons with special radiological exposure limits need to be evacuated (e.g. declared pregnant women, people with radio-pharmaceutical limitations).

Rev. 16

Enclosure 4.4 RP/O/A/5700/012 Page 1 of 6 OFFSITE DOSE ASSESSOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm.{ PIP O-M96-1869}

__ESTABLISH a log of activities.

TURN ON dose assessment and data acquisition computers and acquire necessary information. If data acquisition programs are unavailable, information may be obtained from SDS or the Control Room (EMF and Met data).

OBTAIN copies of the following procedures:

"* RO/O/A/5700/000 (Classification Of Event)

"* SH/O/B/2005/001 (Emergency Response Offsite Dose Projections).

Rev. 16

Enclosure 4.4 RP/0/A/5700/012 Page 2 of 6 OFFSITE DOSE ASSESSOR INITIAL TSC ACTIVATION CHECKLIST INITIAL to offsite UPON declaration of a General Emergency, IMMEDIATELY RECOMMEND authorities the following:

4.4, IF containment radiation levels exceed the levels on Offsite Dose Assessor, Enclosure page 5 of 6, THEN:

Evacuate the 5-mile radius AND 10 miles downwind AND Shelter remaining zones as shown on Offsite Dose Assessor, Enclosure 4.4, page 4 of 6 using wind direction.

OR IF wind speed is less than or equal to 5 MPH THEN:

Evacuate zones L, B, M, C, N, A, D, 0, R AND Shelter zones E, F, G, H, I, J, K, P, Q, S.

OR IF wind speed is greater than 5 MPH THEN:

Evacuate the 2-mile radius AND 5 miles downwind AND Shelter remaining zones as shown on Offsite Dose Assessor, Enclosure 4.4, page 4 of 6 using wind direction.

NOTE: Be aware of the effects of loss of power on critical EMFs.

VERIFY operability and validity of EMFs through the Shift Lab.

necessary.

VERIFY effluent discharge alignment with Shift Lab, RPM, or RP Support as Rev- 16

Enclosure 4.4 RP/O/A/5700/012 Page 3 of 6 OFFSITE DOSE ASSESSOR INITIAL TSC ACTIVATION CHECKLIST INITIAL VERIFY the status of on-shift Dose Assessment with the shift lab and accept the responsibility for dose assessment.

IF the TSC is not activated and the EC has not received turnover from the Control Room, THEN:

Establish contact with and inform the OSM that the Duty dose Assessors in the TSC have assumed responsibility for Dose Assessment.

AND Provide off-site dose calculations and resultant protective action recommendations for radioactive material release to the OSM until the TSC is activated.

ESTABLISH communications with dose assessment personnel at the EOF. Compare information, projections and strategies with the EOF. Turn over dose assessment for offsite communication purposes to EOF Dose Assessors as soon as the EOF becomes officially activated.

RETAIN all computer printouts or manually calculated enclosures.

TURN ON the EMFs (54A and 54B) in the TSC from the OAC computer room by pressing the start button on each EMF control.

ENSURE EMF22 (TSC Area Monitor) is functional.

NOTE: If a safety injection has occurred, the TSC air intakes sampled by EMF-54A and 54B will open and the filter train is placed in service. One of the air intakes must be reope**ed if both EMFs are in trip 2. {PIP 0-M97-4278}

IF EMF54A and 54B exceed the trip 2 setpoint, THEN raise the trip 2 setpoint on the lowest reading EMF to reopen the air intake.

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.4 RP/O/A/5700/012 Page 4 of 6 INITIAL TSC ACTIVATION CHECKLIST Protective Action Zones Determination For Cnntainment Radiation Levels Exceeding GAP Activitv Wind Direction (deg from N)

Chart Recorder 1EEBCR9100 Point # 8 Average Upper Wind Evacuate Direction {PIP 0-M98-3522 } 5 Mile Radius-10 Mile Downwind Shelter 0 - 22.5 L,B,M,C,N,A,D,O,R,E,S,F G,H,I,J,K,P,Q 22.6 - 45.0 L,B,M,C,N,A,D,O,R,E,Q,S F,G,H,I,J,K,P 45.1 -67.5 L,B,M,C,N,A,D,O,R,E,Q,S F,G,H,I,J,K,P 67.6 - 90.0 L,B,M,C,N,A,D,O,R,P,Q,S E,F,G,H,I,J,K 90.1 - 112.5 L,B,M,C,N,A,D,O,R,K,P,Q,S E,F,G,H,I,J 112.6- 135.0 L,B,M,C,N,A,D,O,R,I,K,P,Q,S E,F,G,H,J 135.1 - 157.5 L,B,M,C,N,A,D,O,R,I,K,P,Q E,F,G,H,J,S 157.6- 180.0 L,B,M,C,N,A,D,O,R,I,J,K,P E,F,G,H,Q,S 180.1 - 202.5 L,B,M,C,N,A,D,O,R,G,H,I,J,K,P E,F,Q,S 202.6 - 225.0 L,B,M,C,N,A,D,O,R,G,H,I,J,K,P E,F,Q,S 225.1 - 247.5 L,B,M,C,N,A,D,O,R,F,G,H,I,J E,K,P,Q,S 247.6 - 270.0 L,B,M,C,N,A,D,O,R,F,G,H,I,J E,K,P,Q,S 270.1 - 292.5 L,B,M,C,N,A,D,O,R,E,F,G,H,J I,K,P,Q,S 292.6 - 315.0 L,B,M,C,N,A,D,O,R,E,F,G H,I,J,K,P,Q,S 315.1 - 337.5 L,B,M,C,N,A,D,O,R,E,F,G H,I,J,K,P,Q,S 337.6 - 359.9 L,B,M,C,N,A,D,O,R,E,F,S G,H,I,J,K,P,Q Wind Speed Greater than 5 Miles per Hour Wind Direction (deg from N)

Chart Recorder 1EEBCR9100 Point # 8 Average Upper Wind Evacuate Direction {PIP 0-M98-3522} 2 Mile Radius-5 Mile Downwind Shelter 0-22.5 L,B,M,C,D,O,R A,E,F,G,H,I,J,K,N,P,Q,S 22.6 - 45.0 L,B,M,C,D,O,R A,E,F,G,H,I,J,K,N,P,Q,S 45.1 - 67.5 L,B,M,C,D,O,R A,E,F,G,H,I,J,KN,P,Q,S 67.6 - 90.0 L,B,M,C,D,O,R,N A,E,F,G,H,I,J,K,P,Q,S 90.1 - 112.5 L,B,M,C,O,R,N A,D,E,F,G,H,I,J,K,P,Q,S 112.6- 135.0 L,B,M,C,O,N,R,A D,E,F,G,H,I,J,K,P,Q,S 135.1- 157.5 L,B,M,C,O,A,N D,E,F,G,H,I,J,K,P,Q,R,S 157.6 - 180.0 L,B,M,C,A,N D,E,F,G,H,I,J,K,O,P,Q,R,S 180.1 - 202.5 L,B,M,C,A,N D,E,F,G,H,I,J,K,O,P,Q,R,S 202.6 - 225.0 L,B,M,C,A,N,D E,F,G,H,I,J,K,O,P,Q,R,S 225.1 - 247.5 L,B,M,C,A,D E,F,G,H,I,J,K,N,O,P,Q,R,S 247.6 - 270.0 L,B,M,C,A,D E,F,G,H,I,J,K,N,O,P,Q,R,S 270.1 - 292.5 L,B,M,C,A,D E,F,G,H,I,J,K,N,O,P,Q,R,S 292.6 - 315.0 L,B,M,C,A,D E,F,G,H,I,J,K,N,O,P,Q,R,S 315.1 - 337.5 L,B,M,C,D,R A,E,F,G,H,I,J,K,N,O,P,Q,S 337.6 - 359.9 L,B,M,C,D,R A,E,F,G,H,I,J,K,N,O,P,Q,S Rev. 16

Enclosure 4.4 RP/O/A/5700/O 12 Page 5 of 6 OFFSITE DOSE ASSESSOR GUIDANCE FOR OFFSITE PROTECTIVE ACTIONS GUIDANCE FOR DETERMINATION OF GAP ACTIVITY INITIAL NOTE: Fission product inventory inside containment is greater than gap activity if the containment radiation level exceeds the levels in the table below.

If the OAC is available, call up the following computer points based on need Unit 1 OAC Unit 2 OAC M1A0829 1EMF51A M2A0829 2EMF51A M1A0835 1EMF51B M2A0835 2EMF51B Time Containment Monitor Reading (R/HR)

Shutdown (Hours) EMF51A or 5IB 0 2,340 0-2 864 2-4 624 4-8 450

>8 265 Rev. 16

Enclosure 4.4 RP/O/A/5700/012 Page 6 of 6 OFFSITE DOSE ASSESSOR OPERATIONAL RESPONSIBILITIES

1. Provide technical expertise to the OSM, the Emergency Coordinator, and other members of the TSC as required.

2. Provide initial offsite dose calculations and resultant protective action recommendations for releases of radioactive material until assumed by the EOF.

3. Perform offsite dose projections and determine protective action recommendations. Dose projections shall be run at least every 30 minutes or as directed by the RPM.

4. Evaluate dose projections and protective action recommendations. Make recommendations to the RPM and/or Emergency Coordinator.

5. Provide emergency communication personnel with dose assessment and other pertinent technical data through the preparation of the Emergency Notification Form and other offsite communications.

6. Obtain all pertinent information including plant status, emergency classification, meteorological data, and release potential.

Rev. 16

Enclosure 4.5 RP/O/A/5700/012 Page 1 of 2 OFFSITE AGENCY COMMUNICATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

__CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP O-M96-18691 ESTABLISH a log of activities.

NOTE: ANY information sent to the EOF other than ENF FORMS (TSC/EOF Turnover Sheet, SAMG Strategy Sheets, etc) should be faxed to Fax Machine in EOF Director Area. Fax number 382 - 1825. {PIP 0-M98-2065}

OBTAIN a copy of RP/O/A/5700/018, (Notifications to the State and Counties from the Technical Support Center), from the procedures cabinet.

EXECUTE RP/O/A/5700/018, (Notifications to the State and Counties from the Technical Support Center).

PROVIDE copies of all notifications to Offsite Agencies (NRC, State, Counties, etc.) to the following: {PIP-0-M-99-09 11 }

0 NRC Communicator S Emergency Coordinator 0 Emergency Planner 0 Site Evacuation Coordinator.

PROVIDE all completed paperwork to Emergency Planning upon deactivation of emergency facility.

Rev. 16

Enclosure 4.5 RP/0/A/5700/012 Page 2 of 2 OFFSITE AGENCY COMMUNICATOR OPERATIONAL RESPONSIBILITIES

1. Establish communications with State and Local authorities at County Warning Points or Emergency Operation Centers.

2. Maintain line of communications with these agencies to ensure they are informed of plant emergency conditions at all times.

3. Inform Emergency Coordinator of status of offsite communications (e.g., next message due).

4. Prepare for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage as necessary.

5. Assure offsite agency communicators in the EOF are aware of information affecting offsite agencies even after turnover has occurred (e.g. fire in the motor control center has been put out.)

Rev. 16

Enclosure 4.6 RP/O/A/5700/012 Page 1 of 3 NRC COMMUNICATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-18691 ESTABLISH a log of activities.

OBTAIN a copy of the current classification procedure from the procedure cabinet:

-Notification Of Unusual Event, RP/O/A/5700/001

-Alert, RP/O/A/5700/002

-Site Area Emergency, RP/O/A/5700/003

-General Emergency, RP/0/A15700/004.

NOTE: e The only turnover from the Control Room the TSC NRC Communicator takes is responsibility for communications to the NRC. {PIP 0-M94-14961 0 For drills use the plant phone system to call the simulator at ext. 5597.

CONTACT Control Room of arrival and determine if initial (1 hr.) NRC communication has been completed.

PERFORM (if necessary) initial (1 hr.) NRC notification using the Emergency Notification System (ENS).

Rev. 16

Enclosure 4.6 RP/O/A/5700/012 Page 2 of 3 NRC COMMUNICATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL ESTABLISH continuous communications upon request by the NRC using the cell phone by dialing 9-1-301-816-5100.

INFORM NRC of TSC/EOF activations and plant status as requested.

INFORM the NRC when the TSC is deactivated. This requires an additional call using ENS when the NRC does not require continuous communications be maintained.

CONTACT Regulatory Compliance Duty Person if the NRC is going to arrive on site.

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.6 RP/O/A/5700/012 Page 3 of 3 NRC COMMUNICATOR OPERATIONAL RESPONSIBILITIES

1. Establish communications with Federal (NRC) agency at the Emergency Operations Center.

2. Maintain a line of communications with the NRC to ensure they are informed of plant emergency conditions at all times.

3. Provide for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage as necessary.

Rev. 16

Enclosure 4.7 RP/O/A/5700/012 Page I of 4 REACTOR ENGINEER INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-18691 ESTABLISH a log of activities.

OBTAIN a copy of RP/O/A/5700/019 (Core Damage Assessment) from the procedure cabinet.

OBTAIN a copy of affected Unit(s) Data Book. {PIP 0-M98-3522}

Rev. 16

Enclosure 4.7 RP/O/A/5700/012 Page 2 of 4 REACTOR ENGINEER INITIAL TSC ACTIVATION CHECKLIST INITIAL MONITOR core conditions as appropriate using either APD, SDS or the OAC Critical Points and Steam Tables as follows:

NOTE: If the OAC is not available, core conditions may need to be obtained from the Operations Manager in the TSC who is in contact with the Control Room.

1. Core Subcooling.

2. Reactor Vessel Water Level (RVLIS).

3. Power level if Reactor not tripped.

4. Ask the Operations Liaison to verify all rods at bottom on Reactor Tripped.

5. Source Range Trends following Reactor Trip.

6. Compare each loop T-hot, T-cold and T-avg.

7. What is the most recent boron concentration, and has there been any safety injection.

8. Reactor coolant pumps On/Off Natural or Forced circulation.

9. Pressurizer Level.

10. Containment EMFs.

11. Injection flow and letdown flow (NC inventory).

12. Containment Pressure.

13. Current burnup and previous 2 cycles EFPD.

14. The number of failed rods and DEI prior to transient.

15. Fuel Pool Temperature (Phase A or Phase B Isolation).

Rev. 16

Enclosure 4.7 RP/O/A/5700/012 Page 3 of 4 REACTOR ENGINEER INITIAL TSC ACTIVATION CHECKLIST INITIAL REVIEW the above parameters with an immediate focus on the trends of the following:

1. State of criticality and shutdown margin.

2. Core voiding.

3. Core uncovery.

4. Challenge to the fuel pellet fission product barrier.

5. Challenge to the cladding fission product barrier.

6. Challenge to the NCS pressure boundary.

7. NC cooldown rate.

8. Fuel Pool Heatup.

On a Safety Injection Signal the Auxiliary Building KC cooled loads are isolated by a phase A containment isolation signal. This includes KC cooling of the KF heat exchangers. A conservative estimate of the time for the spent fuel pool to reach saturation without forced cooling is approximately 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Within approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a loss of forced cooling of the spent fuel pool, contact Accident Assessment (Nuclear Engineering General Office) in the EOF for a recommendation regarding initiating KC cooling to KF or alternate means of supplying fuel pool cooling.

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the Emergency facility.

Rev. 16

Enclosure 4.7 RP/O/A/5700/012 Page 4 of 4 REACTOR ENGINEER OPERATIONAL RESPONSIBILITIES

1. Provide System Engineering Manager and/or Operations Superintendent with information concerning any abnormal core conditions.

2. Prepare for 24-hour staffing as necessary.

3. Assist Operations Procedure Support as an Evaluator upon entry into Severe Accident Management Guidelines (SAMG).

Rev. 16

Enclosure 4.8 RP/O/A/5700/0 12 Page 1 of 2 OPERATIONS MANAGER IN THE TSC INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-1869}

ESTABLISH a log of activities.

ESTABLISH communications with the Control Room, OSC and EOF using the cell phone by dialing 4500 (let it ring until you hear a beep).

NOTE: If a Security event occurs while the TSC is activated, the OPS Manager in the TSC will serve as the focal point for the coordination of activities between the OSC, TSC and Security. The information and actions decided upon should be handled through the normal communication channels with the TSC Emergency Coordinator.

IF a Security event occurs (i.e. bomb threat, sabotage, etc.) or additional communications are needed with Security personnel, have the OSC Security Officer request the SAS Security Officer to dial into the OPS bridge line (4500).

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the Emergency facility.

Rev. 16

Enclosure 4.8 RP/O/A/5700/012 Page 2 of 2 OPERATIONS MANAGER IN THE TSC OPERATIONAL RESPONSIBILITIES

1. Provide main communication link between the TSC and Control Room.

2. Provide accurate and current status information to Emergency Coordinator and during time-outs.

3. Assist in making decisions on emergency classifications, mitigation strategies, and contingency plans.

4. Support Control Room personnel by providing resources and consultation as required.

5. Evaluate and prioritize requests for information from the TSC staff, EOF staff, NRC and others.

6. Evaluate and consult with Control Room personnel on suggested mitigation strategies.

7. Coordinates with the Operations Liaison requested priorities of activities in the plant.

8. Has the authority to override normal controls on activities directed by the OSC.

9. Assist Emergency Coordinator as a Decision Maker upon entry into Severe Accident Management Guidelines (SAMG).

Rev. 16

Enclosure 4.9 RP/O/A15700/012 Page 1 of 2 OPERATIONS PROCEDURE SUPPORT INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site ssembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-1869 }

ESTABLISH a log of activities.

OBTAIN a copy of RP/O/A/5700/000 (Classification of Emergency), from the procedures cabinet.

OBTAIN a copy of the current classification procedure from the procedure cabinet.:

-Notification Of Unusual Event, RP/O/A/5700/001

-Alert, RP/O/A/5700/002

-Site Area Emergency, RP/O/A/5700/003

-General Emergency, RP/O/A/5700/004.

___ OBTAIN a copy of RP/O/A/5700/026 [Operations/Engineering Technical Evaluations In The Technical Support Center (TSC)] from the procedure cabinet and begin system/plant parameter evaluation.

NOTE: The following step provides a listen only connection - leave headset switch in the mute position (position is taped).

ESTABLISH communications with OPS bridge line using the cell phone by dialing 4500.

(Let it ring until you hear a beep.)

PROVIDE completed paperwork to Emergency Planning upon deactivation of the Emergency facility.

Rev. 16

Enclosure 4.9 RP/O/A/5700/012 Page 2 of 2 OPERATIONS PROCEDURE SUPPORT OPERATIONAL RESPONSIBILITIES

1. Provide emergency organization with broad oversight of current conditions and direction.

2. Ensure correct emergency classifications are made by following the current plant status and procedures in use.

3. Provide back-up service to Control Room personnel ensuring the correct procedural flowpath is followed.

4. Advise Emergency Coordinator on the anticipated course of the event.

5. Prepare Control Room personnel of possible difficult points in the procedures by a look ahead.

6. Consult the EOF for possible solutions if procedural adequacy becomes a concern.

7. Provide information to Offsite Agency Communicator and the NRC Communicator as requested regarding changes in plant conditions.

8. Prepare for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage as necessary.

9. Serve as Lead Evaluator upon entry into Severe Accident Management Guidelines (SAMG).

Rev. 16

Enclosure 4.10 RP/O/A/5700/012 Page 1 of 2 SYSTEM ENGINEERING MANAGER INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. IPIP 0-M96-18691 ESTABLISH a log of activities.

ENSURE PC is on and displaying plant status.

ESTABLISH communications with the following and provide the SEM phone number:

"* TSC Engineering Support, Ext. 4917

"* EOF Accident Assessment, 382-0762

"* OSC Equipment Engineering, Ext. 497 1.

NOTE: The following step provides a listen only connection. Leave head set switch in the "mute" position.

ESTABLISH communication with the OPS bridge line, using the cell phone by dialing 4500.

(Let it ring until you hear a beep.)

OBTAIN a copy of RP/O/A/5700/026 [Operations/Engineering Technical Evaluations In The Technical Support Center (TSC)] from the procedure cabinet and begin system/plant parameter evaluation.

VERIFY Engineering Support Group is connected to the Operations headset network (listen only) after the Operations Manager in the TSC ties in the OSC and EOF.

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.10 RP/O/A/5700/012 Page 2 of 2 SYSTEM ENGINEERING MANAGER OPERATIONAL RESPONSIBILITIES

1. Coordinate accident mitigation strategy and engineering support through effective communications with the Engineering Support Group, Accident Assessment in the EOF, and the OSC.

ESE,

2. Contact the on-duty EP Support Leader and request appropriate duty personnel from M/NS, and MCE when outside of normal hours.

support.

3. Continually communicate with TSC personnel, identifying areas needing Engineering

4. Report all accident mitigation strategies to the Emergency Coordinator.

Management

5. Assist Operations Procedure Support as an Evaluator upon entry into Severe Accident Guidelines (SAMG).

Rev. 16

Enclosure 4.11 RP/O/A/5700/012 Page 1 of 2 EMERGENCY PLANNER INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-18691 ESTABLISH a log of activities.

OBTAIN time out forms from the procedure cabinet.

ASSIST the Emergency Coordinator as required to achieve a timely turnover to the EOF. {PIP 0

M98-3522}

ESTABLISH communications with EOF Emergency Planner using the cell phone by dialing 831-4010, or another available bridge line.

APPRISE Emergency Coordinator of TSC/OSC announcements.

IF Emergency Planning support is needed in the OSC, THEN contact additional Emergency Planning personnel and request they respond to the OSC.

SUPPORT Emergency Coordinator activity (e.g., keep in procedure).

PROVIDE support for the activation and operation of the TSC.

PROVIDE necessary NRC/State/County interface.

ASSIST Off-site Agency Communicators in preparation of emergency notifications as needed.

SHARE copy of NRC Notification forms, and Emergency Notification forms with the Status Coordinator. {PIP-0-M-99-0911}

PROVIDE support to other members of the TSC as requested.

Rev. 16

Enclosure 4.11 RP/O/A/5700/012 Page 2 of 2 EMERGENCY PLANNER INITIAL TSC ACTIVATION CHECKLIST INITIAL PREPARE for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage as necessary.

COLLECT all completed paperwork upon deactivation of the emergency facility.

PERFORM Enclosure 13.1 of PT/O/A/4600/091 (TSC/OSC Inventory and TSC Manuals) at the completion of the drill or event Rev. 16

Enclosure 4.12 RP/O/A/5700/012 STATUS COORDINATOR Page 1 of 3 INITIAL TSC ACTIVATION CHECKLIST

{PIP 0-M94-14911 INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

in the TSC for If a site assembly is in progress or is conducted USE the badge reader located personnel accountability.

of the site CONTACT your site assembly point and report your location upon activation assembly alarm. {PIP 0-M96-1869 }

cabinet.

OBTAIN the remote control for the overhead projector from the TSC supply INOTE: The overhead projector takes several minutes to warm up 7 remote).

TURN main switch of remote control to ON position (located on right side of POINT remote to overhead projector and depress power on button.

TURN on Status Coordinator computer monitor.

LOG on using your user ID.

DOUBLE CLICK on Plant Status.doc.

SAVE as current date activation.doc (e.g. 22498 activation.doc).

Rev. 16

Enclosure 4.12 RP/O/A/5700/012 STATUS COORDINATOR Page 2 of 3 INITIAL TSC ACTIVATION CHECKLIST INPUT classification information on the electronic message board using the remote control as follows:

1. To turn "ON": Press Shift and Program.

2. To select programmed messages:

a. Unusual Event Press Program then Run then "1" then RUN.

b. Alert Press Program then Run then "2" then RUN.

c. Site Area Emergency Press Program then Run then "3" then RUN.

d. General Emergency Press Program then Run then "4" then RUN.

3. To Turn "OFF": Press Shift and Program.

ENTER plant/equipment status as appropriate on electronic document.

PRINT the current display prior to announced time outs.

NOTE: The Emergency Planner is provided copies of all NRC Notification forms and Emergency Notification forms. These may be useful in maintaining the TSC log. {PIP-0-M-99-091 11 ESTABLISH a log of all activities to ensure the following:

"* Record the time of entry

"* List entries in chronological order and include enough detail to reconstruct event series at a later date.

LOG entries should include but are not limited to the following examples:

- Emergency Coordinator and any change in Emergency Coordinator

- Time at which the TSC is operational

- Present emergency classification, changes in classification, time of declaration Rev. 16

Enclosure 4.12 RP/O/A/5700/012 STATUS COORDINATOR Page 3 of 3 INITIAL TSC ACTIVATION CHECKLIST

- Plant Conditions (Unit 1 and 2):

- Core Cooling information (i.e., Time To Boiling, etc.)

- Safety Systems Degraded:

- Power Supply Status:

- Fission Product Barrier Degradation

- Radiation Releases

- Procedures in effect and any transition to another procedure.

- Actions taken that are not a part of an approved procedure.

- Any abnormal or unexpected plant response.

- Major equipment manipulations.

- Major mitigation actions taken.

- Site assembly or evacuation of all or any part of the plant.

- Personnel Injuries

- Recovery Action(s) in Progress

- Expected time of next Time-Out.

ENSURE the status board is maintained with current information:

3 or 4 highest priority "recovery actions" set by the Emergency Coordinator.

relevant plant status information captured under "General Infor*nation."

TRACK established priorities.

PREPARE for 24-hour coverage.

PROVIDE all completed paperwork (Activation checklist and status board printouts) to Emergency Planning upon deactivation of the emergency facility.

SHUTDOWN computer, monitor and remote control.

RETURN remote control to supply cabinet.

Rev. 16

Enclosure 4.13 RP/O/A/5700/012 Page 1 of 1 IAE COMMUNICATIONS INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-1869 }

ESTABLISH a log of activities.

ENSURE all necessary equipment needed to support the TSC is operable.

"* Video Conferencing

"* Phones

"* Faxes

"* Headsets

"* Page System.

IF IAE Communications support is needed in the OSC, THEN contact additional IAE Communications personnel and request they respond to the OSC.

PREPARE for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage as necessary.

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.14 RP/O/A/5700/012 Page 1 of 2 OPERATIONS MANAGER IN THE CONTROL ROOM INITIAL TSC ACTIVATION CHECKLIST Initial NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

RECEIVE a verbal report from the OSM detailing plant status, emergency class, and shift staffing level.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm. {PIP 0-M96-18691 ESTABLISH a log of activities.

ESTABLISH communications with the TSC, OSC and EOF using the cell phone by dialing 4500. (Let it ring until you hear a beep.) (Each time a party connects, a beep will be heard.)

IF time critical tasks are designated by the OSM, THEN request the OSC OPS Liaison immediately make available an operator/team for prompt dispatch by the OSM via hand-held radio. {PIP 0-M96-1576}

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facilities.

Rev. 16

Enclosure 4.14 RP/O/A/5700/012 Page 2 of 2 OPERATIONS MANAGER IN THE CONTROL ROOM OPERATIONAL RESPONSIBILITIES

1. Provide main communication link from the Control Room or Simulator to the TSC, OSC and EOF.

2. Provide accurate and current task status information to the OSM as needed for non-time critical tasks.

3. Assist in making decisions on emergency classifications, mitigation strategies and contingency plans.

4. Support Control Room personnel by directing resources and providing consultation as required.

5. Expedite time critical tasks for the OSM by clear communication to the OSC via the OPS Liaison.

The OSM is responsible for designating time critical tasks originating from the Control Room.

Once a task originating from the Control Room is designated time critical, the OSM, or designee, shall direct the OPS Manager in the Control Room to request the OSC OPS Liaison to immediately make available an operator (or team) from the OSC contingent for prompt dispatch into the plant via hand held radio. Completion of OSC Task Work Sheet paperwork shall not delay time critical task dispatches. Such time critical dispatches shall receive prior verbal approval from the OSC Coordinator. Time critical task dispatches originating from the Control Room shall remain under direct control of the Control Room crew until the subject task is complete and the person (or team) has returned to the OSC and completed debriefing. {PIP 0-M96-1576} {PIP 0-M98-3522}

6. Evaluate and prioritize for the Control Room requests for information from TSC, OSC, EOF, NRC and others.

7. Evaluate and consult with Control Room personnel on suggested mitigation strategies.

8. Coordinate with the Operations Liaison requested priorities of activities in the plant.

9. Has the authority to override normal controls on activities directed by the OSC as necessary.

10. After the shift NLOs have been dispatched to the OSC, inform the OSM of your responsibility to make NLOs available to the Control Room for time critical tasks as needed.

11. Notify the TSC OPS Procedure Support position of all Emergency Procedure transitions.

{PIP 0-M97-4112}

Rev. 16

Enclosure 4.15 RP/O/A/5700/012 Page 1 of 3 DATA COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the reader located in the TSC for personnel accountability.

CONTACT your site assembly point and report your location upon activation of the site assembly alarm.{ PIP 0-M96-1869}

ESTABLISH a log of activities.

ACCESS SDS in the TSC.

NOTE: ERDS can only be activated / deactivated from designated computer terminals with SDS access. These are located in the Shift Work Manager's Office, the Data Coordinators' room in the TSC and all within the Control Room horse shoe area.

ERDS is NOT activated for a Notification of Unusual Event. {PIP-0-M-99-2929 }

IF the Emergency Response Data System (ERDS) is not activated, THEN activate ERDS as follows:

Ensure SDS is running on the selected terminal.

___ Click on MAIN.

___ Click on GENERAL.

___ Click on ERDS.

___ Click on ACTIVATE.

Record the date and time ERDS was activated in the log section of the Data Coordinator notebook located at the OAC terminals in the TSC.

Rev. 16

Enclosure 4.15 RP/O/A/5700/012 Page 2 of 3 DATA COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL Inform the OSM that ERDS was activated.

IF ERDS failed to activate after five (5) attempts, THEN have an Offsite Communicator notify the NRC via ENS or other available means.

TERMINATE ERDS once the event is over by performing the following:

Click on Terminate.

__ENSURE facility clocks are synchronized as follows:

Using a network connected PC, enter "NETTIME\\MNSF1" at a command prompt.

The time returned should match the PC's time.

"* Verify that the time appears accurate.

"* Use the returned time to sync the clocks with the large red digits mounted on the walls of the TSC.

"* Synchronize the wall clocks of the OSC with the wall clocks of the TSC.

"* Contact the EOF Data Coordinator to ensure the EOF clocks match the TSC/OSC clocks. {PIP-0-M-99-091 1, PIP-0-M-99-2301 }

PROVIDE all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.15 RP/0/A/5700/012 Page 3 of 3 DATA COORDINATOR OPERATIONAL RESPONSIBILITIES

1. Provide support in the area of Computer Services and data acquisition.

2. Provide computer support for both software and hardware applications of data review in the TSC and the transfer of data to offsite locations.

3. Terminate ERDS when the event is terminated.

4. Prepare for 24-hour coverage as necessary.

Rev. 16

Enclosure 4.16 RP/O/A/5700/012 Page 1 of 4 SITE ASSEMBLY COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

GET TLD and pocket dosimetry.

COMPLETE dose card SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress, or is conducted, SWIPE your ID badge in the badge reader located in the TSC for personnel accountability.

CONTACT your site assembly point, report your location upon activation of the site assembly alarm. (PIP 0-M96-1869 }

ESTABLISH a log of activities.

ESTABLISH and maintain communications with the SAS by calling Ext. 2191 to obtain status of the site assembly.

INOTE: Extension 4458 and 4977 are forwarded to Security at 4550 when the TSC is not activated.

CLEAR the forward feature from extension 4458 and 4977 (located in the Site Assembly Coordinator office) by following the instructions located on the desk..

RECORD site assembly start time (announced from Control Room or available through the Operations Manager in the TSC.)

NOTE: Approximately 20 minutes into the site assembly, the assembly locations will contact the Site Assembly Coordinator with names and badge numbers of personnel who were unable to swipe at the assembly locations.

WHEN Security provides a printout of unaccounted personnel, THEN CHECK OFF personnel who could not swipe at their assembly point (request this from security about 20 to 25 minutes into the site assembly).

Rev. 16

Enclosure 4.16 RP/O/A/5700/012 Page 2 of 4 SITE ASSEMBLY COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: During Drills, the number of personnel at each assembly point should be determined if time permits. This information is necessary in the event of an evacuation.

CONTACT the various assembly points to determine the approximate number of personnel at each location.

RECORD the approximate number of personnel at each assembly point on the board located in the Site Assembly Coordinators office.

NOTE: During a TSC "time out" a Site Assembly or Evacuation Coordinator SHALL report to the designated location at the Emergency Coordinator's Table to provide status/updates. {PIP-0 M98-2065 }

RECORD site assembly completion time

__REQUEST the OPS Manager in the TSC have the Control Room to STOP site assembly alarms and announcements.

___ DISCUSS standing down from site assembly with the Emergency Coordinator. If okay to stand down, REQUEST Ops Manager in the TSC have the Control Room to give the stand down from site assembly. If NOT okay to stand down from site assembly, Site Evacuation coordinator will make announcements as directed by Enclosure 4.20.

NOTE: The following message will be communicated to the site at the conclusion of site assembly by the control room.

___ IF requested to do so by the control room, ANNOUNCE the stand down message below:

Drill Message for standing down from Site Assembly: Dial 710; at the beep, dial 80, begin speaking "Attention all station personnel. This is a drill message. This is a drill message. You have been assembled as part of an emergency exercise. If this were an actual emergency, you would be asked to remain assembled waiting on further information, or given instructions to leave the site in accordance with our site evacuation plan. You may now return to your normal work assignments. Thank you for your participation.

Rev- 16

Enclosure 4.16 RP/O/A/5700/012 Page 3 of 4 SITE ASSEMBLY COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL

__AFTER the drill message for standing down from site assembly is announced, EVALUATE the need to initiate search and rescue of missing personnel and discuss with Emergency Coordinator.

___ POST periodic site assembly updates on site assembly/evacuation board as needed.

'PROVIDE periodic updates to the Emergency Coordinator, as needed and during time outs, concerning site assembly status.

PREPARE for 24-hour coverage for your position as necessary.

NOTE: If the Site Assembly portion of the Emergency / Drill is complete. The Site Assembly Coordinator should assist the Site Evacuation Coordinator with Emergency/ Drill message updates and evacuation coordination.

WHEN the TSC is deactivated, then FORWARD extension 4458 and 4977 to Security at extension 4550.

REPLACE the signs on the extension 4458 and 4977 warning personnel about using the two extensions.

PROVIDE all completed paperwork to the Emergency Planner upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.16 RP/0/A/5700/012 Page 4 of 4 SITE PAGING SYSTEM INDIVIDUAL PAGING NUMBERS NOTE: 710 covers all of these areas.

711, then speak MOC 712 , then speak Garage 713 , then speak Medical 714, then speak NAB 715 , then speak MTF 718 , then speak Cowans Ford 719 , then speak Plant 720, then speak Island Training Center 721 , then speak Island Environmental Center 722 , then speak Island Tech Services Center 723 , then speak Island Energy Explorium Rev. 16

Enclosure 4.17 RP/O/A/5700/012 Emergency Coordinator/Emergency Page 1 of 1 Operations Facility Director Turnover Checklist PLANT CONDITIONS Time Date Plant and Unit(s) Affected Status of Unaffected Unit Reactor Power Level (or Operating Mode if shutdown) Unit 1 Unit 2 Emergency Classification List the problems ongoing at this time Status of off-site and onsite power supplies (including diesels):

D/G A SATA BUSS Line A D/G B_ SATB BUSS Line B RADIOLOGICAL STATUS Onsite and off-site radiological status Site Assembly conducted: Yes __ No Site Evacuation: Yes No __ Time of Evacuation Evacuation Location Number of field monitoring teams assembled Number of field monitoring teams deployed Protective Action Recommendations provided to state/counties

"* Evacuate

"* Shelter OFF-SITE COMMUNICATIONS Off-Site Communicators' next Emergency Notification Form Due (Time)

Communications checks complete and ready for turnover (Yes/No)

TSC Activation Time/Date: /

Rev. 16

Enclosure 4.18 RP/O/A/5700/012 Emergency Classification Termination Page 1 of 2 Criteria Page 2 Page 2 Rev. 16

Enclosure 4.18 RP/O/A/5700/012 Emergency Classification Termination Page 2 of 2 Criteria Have the yTerminate the current requirements of Table Yes classification and declare the 1 been satisfied? plant in recovery Continue with the current classification until a recovery can be declared Table 1 Recovery Conditions

_ No new evacuation or sheltering protective actions are anticipated Containment pressure is less than design pressure Decay heat rejection to the ultimate heat sink has been established and either:

"* Injection and heat removal have redundancy available (2 trains of injection/DHR or a train of DHR and S/G cooling)

OR

"* No additional fission product release or fission product barrier challenges would be expected for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months following interruption of injection. (PIP 0-M96-1645)

The risks from recriticality are acceptably low Radiation Protection is monitoring access to radiologically hazardous areas Offsite conditions do not limit plant access The News Manager, NRC officials, and State representatives have been consulted to determine the effects of termination on their activities The recovery organization is ready to assume control of recovery operations Go to RP/0/A/5700/024, (Recovery and Reentry)

Rev. 16

Enclosure 4.19 RP/0/A/5700/012 Fitness for Duty Questionnaire Page 1 of 1 Print Name: Employee ID #:

Sign Name: ERO Position:

HAVE YOU CONSUMED ALCOHOL IN THE LAST FIVE (5) HOURS?

MARK THE APPROPRIATE BOX No LIZ If No, stop here and fold this form and drop it in the box provided.

YES If your answer is Yes, take this form to a member of management for observation.

OBSERVATION DETERMINATION What did you have?

How much did you have?

Can you perform your function unimpaired? YES [-] NO ]

In my opinion, observation of this individual indicates the individual is capable of performing his/her ERO function.

Signature of Management Observer Date Fold the form and drop it in the box provided.

Rev. 16

Enclosure 4.20 RP/O/A/5700/012 Page 1 of 7 SITE EVACUATION COORDINATOR INITIAL TSC ACTIVATION CHECKLIST INITIAL NOTE: You are only required to complete Enclosure 4.19 (Fitness for Duty Questionnaire) when reporting to the facility outside of your normal work hours.

GET TLD and pocket dosimetry.

COMPLETE dose card SIGN in on the TSC staffing board and put on position badge.

SIGN the TSC roster.

IF a site assembly is in progress or is conducted SWIPE your ID badge in the badge reader located in the TSC for personnel accountability.

CONTACT your site assembly point, report your location upon activation of the site assembly alarm. I PIP 0-M96-1869}

ESTABLISH a log of activities.

DISCUSS with the Site Assembly Coordinator the status of the site assembly in preparation for emergency/drill message updates and possible site evacuation.

Rev. 16

Enclosure 4.20 RP/O/A/5700/012 Page 2 of 7 SITE EVACUATION COORDINATOR INITIAL TSC ACTIVATION CHECKLIST NOTE: If the Site Assembly portion of the Emergency / Drill is complete. The Site Assembly message Coordinator should assist the Site Evacuation Coordinator with Emergency/ Drill updates and evacuation coordination.

over the IF site assembly is still in progress ANNOUNCE the following Initial communication speaking:

P.A. for the appropriate situation by dialing 710, at the beep, dial 80 and begin message. This For an Actual Emergency: "Attention all site personnel. This is an emergency

"(emergency is an emergency message. At the present time, we have a Obtain this classification). (Report general information of the event/information of importance.

informationfrom the Offsite agency communicator).

All personnel All personnel inside the protected area shall remain at your site assembly location.

further instructions.

outside of the protected area shall remain in your work area until you receive Information will be provided to you as conditions change."

a drill message. At For a Drill: "Attention all site personnel. This is a drill message. This is the present time, we have a "(emergency classification). (Report from the general informationof the event/information of importance. Obtain this information Offsite Agency Communicator.):

All personnel All personnel inside the protected area shall remain at your site assembly location.

an actual outside of the protected area may continue normal work activity. If this were to remain at your work emergency, personnel outside the protected area would be instructed location."

RECORD time of announcement Rev. 16

Enclosure 4.20 RP/O/A/5700/012 Page 3 of 7 SITE EVACUATION COORDINATOR INITIAL TSC ACTIVATION CHECKLIST NOTE: An additional worksheet for Emergency/Drill Message Updates is on page 6 of 6.

OBTAIN off site notification information from the Off-site Agency Communicator each time an off-site notification is made and prepare an Emergency/ Drill Message Update as follows:

NOTE: If it is determined that an announcement should be made to the plant outside of the normal offsite agency communication, get the Emergency/ Assistant Emergency Coordinator's approval prior to the announcement. Use the message format as follows. After the notification is made, provide a copy of the announcement to the Offsite Agency Communicators.

Emergency Message/Drill Message Update: Dial 710; at the beep, dial 80, begin speaking "Attention all site personnel. This is a/an emergency/drill message. This is a/an emergency drill message." (General Information of the event/information of importance. Obtain this information from the Off-site Agency Communicator.):

RECORD time of announcement Emergency Message/Drill Message Update: Dial 710; at the beep, dial 80, begin speaking "Attention all site personnel. This is a/an emergency/drill message. This is a/an emergency drill message." (GeneralInformation of the event/information of importance. Obtain this information from the Off-site Agency Communicator.):

RECORD time of announcement Rev. 16

Enclosure 4.20 RP/O/A/5700/012 Page 4 of 7 SITE EVACUATION COORDINATOR INITIAL TSC ACTIVATION CHECKLIST EVALUATE with the Radiation Protection Manager, the Emergency Coordinator and other TSC personnel the need to conduct a site evacuation or relocation of on-site personnel based on the following Event Classification criteria:

Alert- determine by actual plant conditions.

Site Area Emergency- consider evacuation/relocation of non-essential personnel.

General Emergency- evacuate all non-essential personnel.

NOTE: The following information may be provided to the EOF via the Offsite Agency Communicators. {PIP-0-M-99-091 11 NOTIFY EOF anytime personnel are relocated onsite or evacuated from the premises.

NOTE: Evacuations planned inside the Protected Area should be made by contacting Security in the OSC with instructions. Evacuations outside the protected area should be made by contacting Security in the OSC and instructing them to coordinate activities with C&F representatives in the OSC. When giving evacuation instructions be sure to identify the area for evacuees to relocate to (using best judgement, advice from RP, etc.).

EVALUATE with the Radiation Protection Manager, Emergency Planner and Emergency Coordinator the following:

Recommendations on the need, path and transportation options for relocation of on-site personnel.

Recommendations on need, path and transportation options for evacuation of non-essential personnel off-site (Training Center lobby / Cowans Ford Dam or offsite / home.)

Recommendations on need to restrict vehicle (site transportation shuttle, etc.) movement on site. {PIP 0-M97-287 11 Rev. 16

Enclosure 4.20 RP/O/A/5700/012 Page 5 of 7 NOTE: During a TSC "time out" a Site Assembly or Evacuation Coordinator SHALL report to the

{PIP-0 designated location at the Emergency Coordinator's Table to provide status/updates.

M98-2065 }

outs on site PROVIDE periodic updates to Emergency Coordinator as needed and during time evacuation or on site relocation of personnel.

Agency IF the decision is made to evacuate personnel from the site, THEN INFORM Off-site Communicators to notify appropriate offsite agencies.

Rev. 16

Enclosure 4.20 RP/O/A/5700/012 Page 6 of 7 SITE EVACUATION COORDINATOR INITIAL TSC ACTIVATION CHECKLIST NOTE: Security may need to notify the Mecklenburg Police (911) requesting them to assist in traffic control, if deemed necessary by the Emergency Coordinator or Security Shift Supervisor.

IF the decision is made to evacuate, NOTIFY Security to assist with traffic control as needed.

to IF evacuation of non-essential personnel is planned, REQUEST Managers, during a time out, identify and inform their own essential personnel to remain, as all others will be evacuated.

IF the decision is made to evacuate, NOTIFY the chosen Evacuation-Relocation site of the expected arrival of personnel.

__Technical Training Center - 379-3210 This is a cellular telephone carried by an industrial security guard who roams the site seven days a week, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day, Powerhouse at Cowans Ford Dam. This phone rings throughout the dam site. This location is staffed Monday through Friday, 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months per day. The assess code to the Cowans Ford Dam is 3308.

NOTE: Inform Control Room that you have already contacted Security and the Evacuation site with information about the evacuation of personnel.

IF the decision is made to evacuate, DIRECT the Control Room to evacuate the site per (RP/0/A/5700/01 1) by calling the Control Room SRO at extension 4138 (then select option 3) and giving the following evacuation route information for non-essential personnel:

Non-essential personnel should:

A. Proceed to (Training Center lobby / Cowans Ford Dam / Home / Other)

-- RECORD the time the site evacuation begins Ends

- PREPARE for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage for your position as necessary.

POST updates to the site assembly / evacuation board located in the Site Assembly Coordinators office as needed.

PROVIDE completed paperwork to the Emergency Planner upon deactivation of the emergency facility.

Rev. 16

Enclosure 4.20 RP/O/A/5700/012 Page 7 of 7 SITE EVACUATION COORDINATOR INITIAL TSC ACTIVATION CHECKLIST ADDITIONAL WORKSHEET FOR EMERGENCY/DRILL MESSAGE UPDATES Emergency Message/Drill Message Update: Dial 710; at the beep, dial 80, begin speaking "Attention all site personnel. This is a/an emergency/drill message. This is a/an emergency drill message." (GeneralInformation of the event/information of importance. Obtain this information from the Off-site Agency Communicator.):

RECORD time of announcement Initial Emergency Message/Drill Message Update: Dial 710; at the beep, dial 80, begin speaking "Attention all site personnel. This is a/an emergency/drill message. This is a/an emergency drill message." (GeneralInformation of the event/information of importance. Obtain this information from the Off-site Agency Communicator.):

RECORD time of announcement Initial Rev. 16

(R06-97)

Duke Power Company (1) ID No. SR/0/B/2000/003 PROCEDURE PROCESS RECORD Revision No. 3 FOR STANDARD PROCEDURES PREPARATION (2) Procedure Title Activation of the nergency Operations Facility (3) Prepared By )ate (4) Applicable To: E] ONS [ MNS [ CNS (5) Technical Advisor _A 111A____,_

(6) Requires 10CFR50.59I El Yes El No ED Yes [: No Yes E] No Evaluation? YES = New procedure or revision with major changes at applicable site NO = Revision with minor changes NO = To incorporate previously approved changes (7) Review (QR) By By -,- By , /

Date _ate...._' ,Date Date Cross-Disciplinary By By By Review (QR) NA Date NA.._ Date "zr! "t NA &AW Date_____

Reactivity Mgmt. By By By Review (QR) NA Date NA Date ,,// zi/ VI NA

Date____/-/_

(8) Additional By (QA) By (QA) By Q(A)

Reviews Date Date Date By By By Date Date Date (9) Approved By By By Date Date_________-at ( Date (10) Use Level PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)

(11) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (12) Date(s) Performed Work Order Number (WO#)

COMPLETION (13) Procedure Completion Verification "O Yes 0 NA Check lists and/or blanks properly initialed, signed, dated, or filled in NA, as appropriate?

"O Yes 0 NA Listed enclosures attached?

"O Yes 0 NA Data sheets attached, completed, dated, and signed?

"0 Yes 0 NA Charts, graphs, etc. attached and properly dated, identified, and marked?

"0Yes 0 NA Procedure requirements met?

Verified By Date (14) Procedure Completion Approved Date (15) Remarks (Attach additionalpages, if necessary.)

Duke Power Company Procedure No.

McGuire Nuclear Station SR/0/B/2000/003 Revision No.

Activation of the Emergency Operations Facility 003 Electronic Reference No.

Multiple Use MC007003

SRIO/B12000/003 Page 2 of 5 Activation of the Emergency Operations Facility

1. Symptoms Conditions exist where events are in progress or have occurred which resulted in the activation of the Emergency Operations Facility (EOF) Emergency Response Organization (ERO).

2. Immediate Actions 2.1 Upon notification to activate, ERO personnel assigned to the EOF shall report to that facility.

3. Subsequent Actions NOTE: This procedure is not intended to be followed in a step-by-step sequence. Sections of the procedure are to be implemented, as the applicable action becomes necessary.

3.1 The EOF must be operational using 75 minutes as a goal for the minimum staff to be in place following declaration of an Alert or higher classification.

3.2 Turnover should occur with the TSC at a time that will not decrease the effectiveness of communications with the off-site agencies.

3.3 Each represented group is responsible for ensuring their appropriate checklist is completed.

SR/O/B/2000/003 Page 3 of 5 3.4 The following SDS Group Displays have been established for emergency response use.

To access these group displays, type GD (space)"Group Display Name" in the white box at the upper right portion of the screen.

Catawba Specific Group Display Name Grout Displav Description EROCONT Selected values associated with containment EROCORE1 Incore temperature values EROCORE2 Additional incore temperature values EROCORE3 Additional incore temperature values EROEMF Selected EMF instantaneous values EROEMF 15 Selected EMF 15 minute average values EROPRIM Selected primary system values EROSECND Selected secondary system values EROENV Selected meteorological values EROINJCT Selected letdown/charging values EROPLEAK Selected primary to containment leakage values EROSLEAK Selected primary to secondary leakage values McGuire Specific Group Display Name Group Display Description ERG-i Selected plant parameters ERO-2 Selected EMF values 3.5 To resolve equipment problems, contact the following:

0 Computer problems - EOF Data Coordinator 0 Other equipment problems - EOF Commodities and Facilities Manager 3.6 Definitions 3.6.1 The following definitions are applicable to the Emergency Notification Form, Line 8: {11

"* IMPROVING - Emergency conditions are improving in the direction of a lower classification or termination of the event.

"* STABLE - The emergency situation is under control. Emergency core cooling systems, equipment, plant, etc., are operating as designed.

"* DEGRADING - Given current and projected plant conditions/equipment status, recovery efforts are not expected to prevent entry into a higher emergency classification or the need to upgrade off-site Protective Action Recommendations

SR/OB/2000/003 Page 4 of 5 3.6.2 The following definitions are applicable to the Emergency Notification Form, Line 10:

" EMERGENCY RELEASE - Any unplanned and quantifiable discharge to the environment of radioactive effluent ATTRIBUTABLE TO A DECLARED EMERGENCY EVENT. A release is considered to be in progress if any one or more of the following occurs:

" Reactor Building EMF monitors reading indicates an increase in activity (Catawba and McGuire 38, 39 or 40).

OR Containment High Range EMF monitors reading greater than 1.5 R/hr.

(Catawba 53A or 53B) (McGuire 5lA or 51B)

AND Pressure inside the containment building is greater than Tech. Specs.

(Catawba and McGuire 0.3 psig)

OR An actual containment breach is determined.

"* Increase in activity monitored by Unit Vent EMF (Catawba and McGuire 35, 36, or 37).

"* Steam generator tube leak monitored by EMF (Catawba and McGuire 33)

"* Field Monitoring Team results.

"* Knowledge of the event and its impact on system operation and resultant release pathways.

3.6.3 ACTIVATED - The Emergency Operations Facility has accepted turnover and has direction and control of assigned emergency response functions.

3.6.4 OPERATIONAL - The Emergency Response Facility (e.g. Technical Support Center Operations Support Center, Emergency Operations Facility) is staffed and ready to perform assigned emergency response functions.

sRIOB/2ooo/oo3 Page 5 of 5

4. Enclosures 4.1 EOF Director/Assistant EOF Director Checklist 4.2 Catawba Protective Actions 4.3 McGuire Protective Action 4.4 Emergency Classification Downgrade/Termination 4.5 Radiological Assessment Manager Checklist 4.6 EOF Dose Assessor Checklist 4.7 Field Monitoring Coordinator Checklist 4.8 Radio Operator Checklist 4.9 EOF Off-Site Agency Communicator Checklist 4.10 Access Control Director Checklist 4.11 Accident Assessment Manager Checklist 4.12 Accident Assessment Interface Checklist 4.13 Operations Interface Checklist 4.14 Administrative Support Checklist 4.15 Reactor Physics Checklist 4.16 EOF Emergency Planner Checklist 4.17 EOF Log Recorder/Status Keeper Checklist 4.18 EOF Data Coordinator Checklist 4.19 EOF Commodities and Facilities Manager Checklist 4.20 Meteorologist Checklist 4.21 Fitness for Duty Questionnaire 4.22 Commitments for SR/0/B/2000/003

Enclosure 4.1 SR/0/B/2000/003 EOF Director/Assistant EOF Director Checklist Page 1 of 8 INITIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire, when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

NOTE: The EOF Log Recorder will maintain the official log for the EOF Director/Assistant EOF Director. The EOF Director/Assistant EOF Director may maintain an additional log if desired.

Establish a log of activities.

Establish communications with the Emergency Coordinator in the affected site's TSC as follows:

"* Video conference OR

"* Use the affected site's EOF Director to Emergency Coordinator Ringdown phone OR

"* Catawba TSC, dial 8-831-5870 OR

"* McGuire TSC, dial 8-875-4950 Verify the following EOF positions, as a minimum, are filled, have checked out their assigned equipment/procedures and are prepared to assume their EOF duties prior to declaring the EOF operational:

EOF Director Accident Assessment Manager Radiological Assessment Manager Access Control Director Off-Site Agency Communicator Off-Site Agency Communicator NOTE: For all drills, messages should be preceded with "This is a drill. This is a drill."

Announce over the EOF public address system the following:

"Anyone who is reporting to this facility outside of your normal work hours and has consumed alcohol within the past five (5) hours, notify either the EOF Director, Assistant EOF Director, or the appropriate lead in each functional area."

Enclosure 4.1 SR/O/B/2000/003 EOF Director/Assistant EOF Director Checklist Page 2 of 8 Declare the EOF operational. EOF operational time:

NOTE: For all drills, messages should be preceded with "This is a drill. This is a drill" Announce the following over the EOF public address system:

"Attention all EOF personnel. This is and as of hours, (EOF Director's Name) the EOF is operational."

Inform the Emergency Coordinator that the EOF is:

- Operational

- Gathering plant status information

- Ready to receive turnover at the Emergency Coordinator's convenience.

Read the definitions for the following terms contained in Steps 3.6.1 and 3.6.2 in the body of this procedure:

"*Stable - Degrading

"*Improving - Emergency Release NOTE: The following step may be accomplished by conducting a Time Out or by verifying the level of readiness with the individuals in the positions.

Verify the following positions, at a minimum, are ready to activate (i.e. have received the necessary information from their TSC counterpart, etc.) and are positioned to perform the next off site agency communication via the Emergency Notification Form (ENF).

Accident Assessment Manager Radiological Assessment Manager Lead Off-Site Agency Communicator NOTE: Emergency Coordinator faxes copy of EOF Director Turnover Form to EOF. A copy of the "EOF Director Turnover Form" is provided on page 8 of this enclosure for use if needed.

Receive turnover from Emergency Coordinator utilizing the "EOF Director Turnover Form."

Enclosure 4.1 SR/0/I/2000/003 EOF Director/Assistant EOF Director Checklist Page 3 of 8 NOTE: The EOF Director is responsible for determining Emergency Classifications, approving Protective Action Recommendations, and approving Off-Site Agency Emergency Notification Forms after the EOF is activated. These responsibilities remain with the EOF Director and shall not be delegated.

Inform the Emergency Coordinator that the EOF is ready to activate.

NOTE: For all drills, messages should be preceded with "This is a drill. This is a drill."

Announce over the EOF public address system the following:

"Attention all EOF personnel. The EOF was activated at hours. This is

. I am the EOF Director and have taken responsibility for emergency management from the Emergency Coordinator in the Technical Support Center. The current emergency classification is . The following is a summary of the plant status.....

Additional information will be provided to you as conditions change. The next off-site agency notification shall be transmitted by hours. The EOF staff shall prepare for a time-out and a roundtable discussion at hours."

Log on to the Emergency Notification Form by following the instructions in the EOF Directors Logbook behind the ENF Logon Instructions tab.

Discuss current emergency classification with the EOF staff and verify that it meets the criteria of:

" Catawba RP/O/A/5000/O01 OR

" McGuire RP/O/A/5700/O00 Upon declaration of a Site Area Emergency, consult with the Accident Assessment Manger and the Radiological Assessment Manager to determine potential zones for protective action recommendations should the event progress to a General Emergency.

Upon declaration of a General Emergency, the EOF Director shall IMMEDIATELY (within 15 minutes) recommend Protective Actions to off-site authorities via the Emergency Notification Form (ENF) using:

"* Catawba Enclosure 4.2, Page 1

"* McGuire Enclosure 4.3

Enclosure 4.1 SR/0/B/2000/003 EOF Director/Assistant EOF Director Checklist Page 4 of 8 Evaluate specific plant conditions, off-site dose projections, field monitoring team data, and assess need to update Protective Action Recommendations made to states and counties in the previous notification.

"* Catawba Enclosure 4.2, page 2

"* McGuire Enclosure 4.3 Discuss, or delegate to the Assistant EOF Director the responsibility to discuss, plant status with the County Directors of Emergency Preparedness (CDEP), the State Liaisons or the State Directors of Emergency Preparedness (SDEP) as necessary/requested using one of the following methods:

"* The EOF State Liaisons will communicate information from the EOF Director to County/State representatives using the Decision Line.

" Use the EOF/Assistant EOF Director telephone speed dial to contact the appropriate states/counties OR obtain the telephone numbers from the appropriate Emergency Telephone Directory.

Catawba Site Specific Name York CDEP Mecklenburg CDEP Gaston CDEP NC SDEP SC SDEP McGuire Site Specific Name Mecklenburg CDEP Gaston CDEP Lincoln CDEP Iredell CDEP Catawba CDEP Cabarrus CDEP NC SDEP

Enclosure 4.1 SR/0/B/2000/003 EOF Director/Assistant EOF Director Checklist Page 5 of 8 IF Duke Power has provided Protective Action Recommendations to the States and Counties, THEN request SDEPs and CDEPs to inform the EOF Director of the decisions for actual Protective Actions for the plume exposure pathway populations. Record SDEPs and CDEPs protective action decisions below:

Zones Evacuated:

Zones Sheltered:

Information Received from:

Inform Emergency Coordinator of SDEPs and CDEPs protective actions decisions and other off-site conditions.

Perform the following steps as needed throughout the event:

"* Conduct a time-out and hold a roundtable discussion approximately every 30 minutes with the EOF staff to discuss:

- Emergency Classification

- Protective Action Recommendations

- Emergency Notification Form status

- Off-site dose projections

- Mitigation strategies

- Termination criteria as defined in Enclosure 4.4

"* Announce to the EOF the emergency classification, plant status, and priorities via the EOF public address system following EOF time-outs.

" The Emergency Coordinator updates may be broadcast on the EOF public address system.

" Advise Emergency Coordinator of the following:

- All aspects of the emergency situation, including alternate strategies outside of procedures as plant conditions dictate.

- Emergency Classification changes

- Protective Action Recommendations changes

- Mitigation strategies

- Contingency plans

Enclosure 4.1 SR/0/B/2000/003 EOF Director/Assistant EOF Director Checklist Page 6 of 8

"* Ensure that 10CFR50.54(x) actions are approved prior to performing the action.

(Reasonable actions that depart from a license condition or technical specification may be performed in an emergency, per 10CFR50.54(x), when this action is immediately needed to protect the health and safety of the public and no action consistent with the license condition or technical specification that can provide adequate or equivalent protection is immediately apparent. Deviation from an Emergency Procedure constitutes a 10CFR50.54(x) action. Actions taken per 10CFR50.54(x) shall be:

-Approved, as a minimum, by a Licensed Senior Reactor Operator prior to taking such action, and

-Documented in the Reactor Operators Logbook, and

-Documented in the TSC Logbook, and

-Reported to the NRC within one hour using RP/O/B/5000/013, "NRC Notification Requirements" {31

"* Authorize emergency worker extensions if the radiation exposure doses are expected to exceed the blanket dose extension limits authorized by the Radiation Protection Manager using:

- Catawba RP/O/A/5000/018

- McGuire System Radiation Protection Manual Section VI-6

"* Approve personnel with training deficiencies prior to their participation as an EOF staff member. This approval shall be documented in the EOF Log.

"* Assist Emergency Coordinator as requested upon entry into Severe Accident Management Guidelines.

"* Turn over EOF Director duties to the Assistant EOF Director prior to leaving the EOF Director's Area.

Verify that the EOF Emergency Planner completes the "EOF 24-Hour Staffing Log" located in Enclosure 4.16.

NOTE: The Off-Site Recovery Organization will stay at the EOF and work with the counties and states if radiological conditions exist beyond the site boundary. The On-Site Recovery Organization will be established by the Emergency Coordinator.

Establish Recovery Organization if needed using:

"* Catawba RP/O/A/50001025

"* McGuire RP/O/A/5700/024 Conduct a critique following termination of a drill or actual event.

Enclosure 4.1 SR/0/B/2000/003 EOF Director/Assistant EOF Director Checklist Page 7 of 8 Provide all completed paperwork to Emergency Planning following termination of a drill or actual event.

Close out the emergency event in accordance with the applicable procedure:

Notification of Unusual Event Catawba - RP/O/A/5000/002 McGuire - RP/O/A/5700/001 Alert Catawba - RP/O/A/5000/003 McGuire - RP/O/A/5700/002 Site Area Emergency Catawba - RP/O/A/5000/004 McGuire - RP/O/A/5700/003 General Emergency Catawba - RP/O/A/5000/005 McGuire - RP/O/A/5700/004

Enclosure 4.1 SR/O/B/2000/003 EOF Director/Assistant EOF Director Checklist Page 8 of 8 EOF Director Turnover Form {5)

PLANT CONDITIONS Time Date Plant and Unit Affected Status of Unaffected Unit Reactor Power Level (or operating mode if shutdown) Unit 1 Unit 2 Emergency Classification:

List the problems ongoing at this time:

Status of off-site and on-site power supplies (including diesels):

D/G A SATA BUSS Line A D/G B SATB BUSS Line B RADIOLOGICAL STATUS On-site and off-site radiological status is as follows:

Site Assembly conducted: Yes No 1

Site Evacuation: Yes No _ Time of Evacuation Evacuation Location:

Number field monitoring teams assembled Number field monitoring teams deployed Protective Action Recommendations provided to states/counties:

"* Evacuate

"* Shelter OFFSITE COMMUNICATIONS Off-Site Communicators' next Emergency Notification Form Due:

(Time)

Communications checks complete and ready for turnover (Yes/No)

EOF Activation Time/Date: /

Enclosure 4.2 SR/O/B/2000/003 Catawba Protective Actions Page 1 of 4 Make an immediate PROTECTIVE ACTION RECOMMENDATION (PAR) to be entered on Line 15 of the Emergency Notification Form using one of the following tables:

WIND SPEED LESS THAN OR EOUAL TO 5 MPH Evacuate zones: AG, A 1, B 1, C 1, D 1, E 1, F 1 AND Shelter In-Place zones: A2, A3, B2, C2, D2, E2, F2, F3 WIND SPEED GREATER THAN 5 MPH Wind Direction (Degrees from North) 2 Mile Radius - 5 Remainder of EPZ miles Downwind EVACUATE SHELTER IN-PLACE 348.75-11.25 AO, Bl,C1, DI Al, A2, A3, B2, C2, D2, El, E2, F1, F2, F3 11.26 -33.75 AG, Cl, D1 A1, A2, A3, B1, B2, C2, D2, El, E2, Fl, F2, F3 33.76 -56.25 AG, C1, Dl, El A1, A2, A3, B1, B2, C2, D2, E2, F1, F2, F3 56.26 -78.75 AG, Cl, Dl, El, F1 A1, A2, A3, B1, B2, C2, D2, E2, F2, F3 78.76 -101.25 AO, C1, Dl, El, F1 A1, A2, A3, B1, B2, C2, D2, E2, F2, F3 101.26 -123.75 AO, Dl, El, F1 A1, A2, A3, B1, B2, C1, C2, D2, E2, F2, F3 123.76 -146.25 AG, El, F1 A1, A2, A3, B1, B2, C1, C2, D1, D2, E2, F2, F3 146.26 -168.75 AG, Al, El, Fl A2, A3, B1, B2, C1, C2, D1, D2, E2. F2, F3 168.76 -191.25 AG, Al, El, Fl A2, A3, B1, B2, C1, C2, D1, D2, E2. F2, F3 191.26 -213.75 AO, Al, BI, El, F1 A2, A3, B2, C1, C2, D1, D2, E2, F2, F3 213.76 -236.25 AG, Al, Bl, Fl A2, A3, B2, C1, C2, Dl, D2, El, E2, F2, F3 236.26 -258.75 AG, Al, B1, F1 A2, A3, B2, Cl, C2, Dl, D2, El, E2, F2, F3 258.76 -281.25 AG, Al, Bl, Cl A2, A3, B2, C2, Dl, D2, El, E2, Fl, F2, F3 281.26 -303.75 AG, Al, B1, Cl A2, A3, B2, C2, Dl, D2, El, E2, Fl, F2, F3 303.76 -326.25 A0, Bl, C1 Al, A2, A3, B2, C2, Dl, D2, El, E2, F1, F2, F3 326.26 -348.74 AO, Bl, Cl, D1 Al, A2, A3, B2, C2, D2, El, E2, F1, F2, F3

Enclosure 4.2 SR/0/B/2000/003 Catawba Protective Actions Page 2 of 4 Guidance for Protective Actions Protective Action Recommendation Flowchart LARGE FISSION PRODUCT RECOMMEND EVACUATION OF 5 INVENTORY GREATER THAN YES MILE RADIUS AND 10 MILES GAP ACTIVITY IN CONTAINMENT? DOWNWIND AND RECOMMEND IN PLACE SHELTER FOR ZONES NOT (L(ENCL. 4.2 PAGE 4)

NO DOSES PROJECTED TO BE: YES RECOMMEND EVACUATION OF

> 1 REM TEDE IDENTIFIED ZONE(S) WITH DOSE AND/OR > 5 REM CDE PROJECTIONS> I REM TEDE THYROID IN ANY ZONE THAT AND/OR > 5 REM CDE HAS NOT BEEN PREVIOUSLY CALCULATIONS, CONTINUE ASSESSMENT OF LARGE FISSION PRODUCT INVENTORY IN CONTAINMENT, DOSE PROJECTION FOR EVACUATION.

WIND SPEED AND WIND DIRECTION TO DETERMINE IF ADDITIONAL ZONES SHOULD BE RECOMMENDED NOTE:

CHANGES IN WIND SPEED AND/OR WIND DIRECTION MAY REQUIRE THAT ADDITIONAL ZONES BE RECOMMENDED FOR EVACUATION. THESE ADDITIONAL RECOMMENDATIONS ARE BASED ON THE FOLLOWING:

GAP ACTIVITY IN IF WIND SPEED IS LESS THAN OR EQUAL TO 5 MPH AND LARGE FISSION PRODUCT INVENTORY IS LESS THAN RECOMMENDED CONTAINMENT THEN RECOMMEND EVACUATION OF ZONES AO, Al, BI, CI, DI, El, AND Fl IF NOT PREVIOUSLY FOR EVACUATION IF WIND SPEED IS GREATER 5 MPH AND LARGE FISSION PRODUCT INVENTORY IS LESS THAN GAP ACTIVITY IN CONTAINMENT THEN USE ENCLOSURE 4.2 TO DETERMINE IF EVACUATION OF ADDITIONAL ZONES SHOULD BE RECOMMENDED ENCLOSURE 4.2 IF LARGE FISSION PRODUCT INVENTORY IS GREATER THAN GAP ACTIVITY IN CONTAINMENT THEN USE PAGE 4 OF 4 TO DETERMINE IF EVACUATION OF ADDITIONAL ZONES SHOULD BE RECOMMENDED

Enclosure 4.2 SR/0/B/2000/003 Catawba Protective Actions Page 3 of 4 Guidance for Protective Actions Guidance for Determination of Gap Activity Fission product inventory inside Containment is greater than gap activity if the containment radiation level exceeds the levels in the table below:

TIME AFTER SHUTDOWN HIGH RANGE CONTAINMENT MONITOR READING (HOURS) EMF 53A and/or EMF 53B 100 % GAP Activity Release 0 2,340 R/Hr 0-2 864 R/Hr 2-4 624 R/Hr 4-8 450 R/Hr

>8 265 R/Hr

Enclosure 4.2 SR/0/B/2000/003 Catawba Protective Actions Page 4 of 4 Protective Action Zones Determination Table (This Table Used For Large Fission Product Inventory Greater Than Gap Activity In Containment Only)

Use this table to determine the recommended zones for evacuation within the 5 mile radius and 10 miles downwind for any windspeed.

PROTJTITIVE A CTION ZONES DETERMINATION TABLE Wind Direction (Degrees from North) 5 Mile Radius - 10 miles Downwind Remainder of EPZ EVACUATE IN-PLACE SHELTER 348.75 -11.25 AG, Al, B1, B2, Cl, C2, Dl, D2, El, F1 A2, A3, E2, F2, F3 11.26 -33.75 AO, Al, BI, Cl, C2, Dl, D2, El, F1 A2, A3, B2, E2, F2, F3 33.76 -56.25 AO, Al, B1, Cl, C2, Dl, D2, El, E2, F1 A2, A3, B2, F2, F3, 56.26 -78.75 AO, Al, B1, C1, C2, Dl, D2, El, E2, Fl, F2 A2, A3, B2, F3 78.76 -101.25 AO,Al, B1, Cl, DI, D2, El, E2, Fl, F2 A2, A3, B2, C2, F3, 101.26 -123.75 AO,Al, B1, Cl, Dl, D2, El, E2, Fl, F2, F3 A2, A3, B2, C2 123.76 -146.25 AO,Al, B1, Cl, DI, El, E2, Fl, F2, F3 A2, A3, B2, C2, D2 146.26-168.75 AO, A1,A2, B 1, Cl, Dl, El, E2, Fl, F2, F3 A3,1B2,C2,E2 168.76 -191.25 AO,A1,A2,Bl,C1,D1,El,Fl,F2,F3 A3, B2, C2, D2, E2 191.26 -213.75 AO, Al, A2, A3, B1, B2, Cl, D1, El, Fl, F2, F3 C2, D2, E2 213.76 -236.25 AG, Al, A2, A3, BI, B2, Cl, Dl, El, F1, F2, F3 C2, D2, E2 236.26 -258.75 AG, Al, A2, A3, B1, B2, Cl, D1, El, Fl, F3 C2, D2, E2, F2 258.76 -281.25 AG, Al, A2, A3, B1, B2, Cl, C2, D1, El, Fl D2, E2, F2, F3 281.26 -303.75 AG, Al, A2, A3, B1, B2, Cl, C2, D1, El, Fl D2, E2, F2, F3 303.76 -326.25 AG, A1, A3, B1, B2, Cl, C2, Dl, El, Fl A2, D2, E2, F2, F3 326.26 -348.74 AG, Al, B1, B2, C1, C2, Dl, D2, El, F1 A2, A3, E2, F2, F3

Enclosure 4.3 SR/OJB/2000/003 McGuire Protective Actions Page 1 of 3 Make an immediate PROTECTIVE ACTION RECOMMENDATION (PAR) within 15 minutes to be entered on line 15 of the Emergency Notification Form (ENF) using the following information as appropriate.

NOTE: {5) 1. To obtain the wind speed, use chart recorder 1EEBCR9100, point # 5 ( Average Lower Wind Speed).

2. To obtain the wind direction, use chart recorder 1EEBCR9 100, point # 8 ( Average Upper Wind Direction).

3. If either point on 1EEBCR9 100 is unavailable, obtain needed data from one of the following sources in order of sequence:

A. DPC Meteorological Lab (8-594-0341).

B. National Weather Service in Greer, S.C. (864-879-1085 or 1-800-268-7785).

C. Catawba Nuclear Station Control Room (8-831-2338).

IF containment radiation levels exceed the levels on Enclosure 4.3, page 2 of 3, THEN:

Evacuate the 5-mile radius AND 10 miles downwind AND

___ Shelter remaining zones as shown in the table on Enclosure 4.3, page 2 of 3, using wind direction.

OR IF wind speed is less than or equal to 5 MPH, THEN:

Evacuate zones L, B, M, C, N, A, D, 0, R AND Shelter zones E, F, G, H, I, J, K, P, Q, S OR IF wind speed is greater than 5 MPH, THEN:

Evacuate the 2-mile radius AND 5 miles downwind AND

___ Shelter remaining zones as shown on Enclosure 4.3, page 3 of 3, using wind direction.

Enclosure 4.3 SRIO/B/2000/003 McGuire Protective Actions Page 2 of 3 NOTE: Fission product inventory inside containment is greater than gap activity if the containment radiation level exceeds the levels in the table below IF the OAC is available, THEN call up the following computer points based on need:

Unit 1 OAC Unit 2 OAC M1A0829 IEMF51A M2A0829 2EMF51A M1A0835 1EMF51B M2A0835 2EMF51B Time After Containment Monitor Reading (R/HR)

Shutdown (Hours) EMF51A or 51B (100% Gap Activity Release) 0 2,340 0-2 864 2-4 624 4-8 450

>8 265 PROTECTIVE ACTION ZONES DETERMINATION For Containment Radiation Levels Exceeding GAP Activity Wind Direction (deg from N)

Chart Recorder IEEBCR9100 Point # 8 Average Upper Wind Evacuate Direction({ 5} 5 Mile Radius- 10 Mile Downwind Shelter 0 - 22.5 L,B,M,C,N,A,D,O,R,E,S,F G,H,I,J,K,P,Q 22.6 - 45.0 L,B,M,C,N,A,D,O,R,E,Q,S F,G,H,I,J,K,P 45.1 - 67.5 L,B,M,C,N,A,D,O,R,E,Q,S F,G,H,I,J,K,P 67.6 - 90.0 L,B,M,C,N,A,D,O,R,P,Q,S E,F,G,H,I,J,K 90.1 - 112.5 L,B,M,C,N,A,D,O,R,K,P,Q,S E,F,G,H,I,J 112.6 - 135.0 LB,M,C,N,A,D,O,R,I,K,P,Q,S E,F,G,H,J 135.1 - 157.5 L,B,M,C,N,A,D,O,R,I,K,P,Q E,F,G,H,J,S 157.6 - 180.0 L,B,M,C,N,A,D,O,R,I,J,K,P E,F,G,H,Q,S 180.1 - 202.5 L,B, M,C,N,A,D,O,R,G,H,I,J,K,P E,F,Q,S 202.6 - 225.0 L,B,M,C,N,A,D,O,R,G,H,I,J,K,P E,F,Q,S 225.1 - 247.5 L,B,M,C,N,A,D,O,R,F,G,H,I,J E,K,P,Q,S 247.6 - 270.0 L,B,M,C,N,A,D,O,R,F,G,H,I,J E,K,P,Q,S 270.1 - 292.5 LB,M,C,N,A,D,O,R,E,F,G,H,J I,K,P,Q,S 292.6 - 315.0 LB,M,C,N,A,D,O,R,E,F,G H,I,J,K,P,Q,S 315.1 - 337.5 L,B,M,C,N,A,D,O,R,E,F,G H,I,J,K,P,Q,S 337.6 - 359.9 L,B,M,C,N,A,D,O,R,E,F,S G,H,I,J,K,P,Q

Enclosure 4.3 SR/O/B/2000/003 McGuire Protective Actions Page 3 of 3 Wind Speed Greater than 5 Miles per Hour Wind Direction (deg from N)

Chart Recorder 1EEBCR9100 Point # 8 Average Upper Wind Evacuate Direction{5 } 2 Mile Radius-5 Mile Downwind Shelter 0- 22.5 L,B,M,C,D,O,R A,E,F,G,H,I,J,K,N,P,Q,S 22.6 - 45.0 L,B,M,C,D,O,R A,E,F,G,H,I,JK,N,P,Q,S 45.1 - 67.5 L,B,M,C,D,O,R A,E,F,G,H,I,J,K,N,P,Q,S 67.6 - 90.0 LB,M,C,D,O,R,N A,E,F,G,H,I,J,K,P,Q,S 90.1 - 112.5 LB,M,C,O,R,N AD,E,F,G,HI,J,K,P,Q,S 112.6 - 135.0 LB,M,C,O,N,R,A D,E.F,G,H,I,J,K,P,Q,S 135.1 - 157.5 L,B,M,C,O,A,N D,E,E,G,H,I,J,K,P,Q,R,S 157.6 - 180.0 L,B,M,C,A,N D,E,FG,H,I,J,K,O,P,Q,R,S 180.1 - 202.5 L,B,M,C,A,N D,E,F,G,HI,J,K,O,P,Q,R,S 202.6 - 225.0 L,B,M,C,A,N,D E,F,G,H,I,J,K,O,P,Q,R,S 225.1 - 247.5 L,B,M,C,A,D E,F,G,H,I,J,K,N,O,P,Q,R,S 247.6 - 270.0 L,B,M,C,A,D E,F,G,H,I,J,K,N,O,P,Q,R,S 270.1 - 292.5 L,B,M,C,A,D E,F,G,H,I,J,K,N,O,P,Q,R,S 292.6 - 315.0 L,B,M,C,A,D E,F,G,H,I,J,K,N,O,P,Q,R,S 315.1 - 337.5 L,B,M,C,D,R A,E,F,G,H,I,J,K,N,O,P,Q,S 337.6 - 359.9 L,B,M,C,D,R A,E,F,G,H,I,J,K,N,O,P,Q,S GUIDANCE FOR OFFSITE PROTECTIVE ACTIONS PAGs (Projected Dose)

Total Effective Committed Dose Dose Equivalent Equivalent (CDE)

(TEDE) Thyroid Recommendation

< 1 rem < 5 rem No Protective Action is required based on projected dose.

> 1 rem > 5 rem Evacuate affected zones and shelter the remainder of the 10 mile EPZ not evacuated.

Protective Action Guides (PAGs) are levels of radiation dose at which prompt protective actions should be initiated and are based on EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

Enclosure 4.4 SR/O/B/2000/003 Emergency Classification Downgrade/ Page 1 of 2 Termination Criteria

Enclosure 4.4 SR/O/B/2000/003 Emergency Classification Downgrade/ Page 2 of 2 Termination Criteria Yes Terminate the current classification and declare the plant in recovery Table 1 No new evacuation or sheltering protective actions are anticipated.

Containment pressure is less than design pressure.

Decay heat rejection to the ultimate heat sink has been established and either:

"* Injection and heat removal have redundancy available (2 trains of injection/DHR or a train of DHR and S/G cooling),

OR

"* No additional fission product release or fission product barrier challenges would be expected for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months following interruption of injection. { 2}

The risks from recriticality are acceptably low.

Radiation Protection is monitoring access to radiologically hazardous areas.

Off-site conditions do not limit plant access.

The Public Information Coordinator, NRC officials, and State representatives have been consulted to determine the effects of termination on their activities.

The recovery organization is ready to assume control of recovery operations:

"* Catawba - RP/O/B/5000/025

"* McGuire - RP/0/A/57001024

Enclosure 4.5 SR/0/B1/2000/003 Radiological Assessment Manager Checklist Page 1 of 2 INITIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Notify EOF Director that the Radiological Assessment Manager (RAM) position is operational.

Ensure all Radiation Protection personnel reporting to the EOF also sign in on the staffing board.

Power up the Radiological Assessment Computer.

Verify EOF Off-Site Agency Communicators have opened an electronic Emergency Notification Form.

Log on to the Emergency Notification Form by following the instructions in the EOF Radiological Assessment Managers Logbook behind the ENF Logon Instructions tab.

Verify the electronic Emergency Notification Form can be accessed.

Establish a log of activities.

Discuss the following with the EOF Director:

1) Any release in progress, including dose rates (especially at the site boundary)

2) Field Team status/data

3) On-site radiological concerns Review Criteria in "Classification of Emergency" procedure for emergency classification changes and discuss with Accident Assessment personnel plant conditions including power failures, valve closures, etc.

Catawba RP/O/A/5000/O01 OR McGuire RP/O/A/5700/O00 Catawba Specific Obtain HP/0/B/1009/009, "Guidelines for Accident and Emergency Response,"

and perform duties as described in the procedure.

Establish communications with the TSC via the RP Loop; communication established after beep. {4 }

Enclosure 4.5 SR/0/B/2000/003 Radiological Assessment Manager Checklist Page 2 of 2 NOTE: Radiological dose projection information is not required for Emergency Notification Forms that are sent as initial notification of an emergency classification or initial notification of a change to the emergency classification.

Provide radiological information on the electronic Emergency Notification Form as appropriate.

Evaluate with the EOF Director recommendations for public protective actions.

Assist Public Affairs and/or Public Spokesperson with dose comparisons based on computer model or field data.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.6 SR/O/B/2000/003 EOF Dose Assessor Checklist Page 1 of 2 Initial EOF Activation Checklist INITIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Initiate a Log of Activities.

Turn on dose assessment and data acquisition computers and acquire necessary information. IF data acquisition programs are unavailable, THEN request from TSC information obtained from SDS or the Control Room (EMF and Met data).

Log on to the Emergency Notification Form by following the instructions in the EOF Dose Assessors Logbook behind the ENF Logon Instructions tab.

NOTE: Be aware of the effects of loss of power on critical EMFs.

Verify operability and validity of EMFs through the TSC.

Verify effluent discharge alignment with Shift Lab, RP Manager (TSC), or RP Dose Assessors (TSC) as necessary.

Establish communications with dose assessment personnel at the TSC. Compare information, projections and strategies with the TSC.

Catawba Specific

__ Set up video conferencing with the TSC Dose Assessors, if desired.

Obtain turnover from the TSC.

Verify operability of the Health Physics Network (HPN) phone by placing a call to the NRC using the number listed on the HPN phone NOTE: The NRC Regional Office will request the activation of the HPN phone through the Emergency Notification System (ENS) telephone if desired.

IF requested during a drill or actual event, THEN activate the HPN phone by placing a call to the NRC using the number listed on the HPN phone.

Enclosure 4.6 SR/0/B/2000/003 EOF Dose Assessor Checklist Page 2 of 2 NOTE:

1. Perform off-site dose projections and determine protective action recommendations.

2. Dose projections shall be run at least every 30 minutes or as directed by the RPM.

Analyze source term data, formulate source term mitigation strategies, and provide information to the Radiological Assessment Manager, members of the EOF and TSC Dose Assessors as required.

Perform dose projections as appropriate to plant conditions.

Interact with Field Monitoring Coordinator to compare off-site dose projections to actual field readings.

NOTE: Radiological dose projection information is not required for Emergency Notification Forms that are sent as initial notification of an emergency classification or initial notification of a change to the emergency classification.

Transfer (and review) data from Raddose V to the electronic Emergency Notification Form.

Evaluate dose projections and provide protective action recommendations to the Radiological Assessment Manger and the EOF Director.

Restore equipment to a "Ready Status" and notify appropriate personnel of conditions that would cause a less than operational status.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.7 SR/O/B/2000/003 Field Monitoring Coordinator Checklist Page 1 of 1 NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire, when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Obtain a copy of SH/O/B/2005/002 (Protocol for the Field Monitoring Coordinator During Emergency Conditions).

Establish a log of activities.

Catawba Specific Perform duties as described in the following:

"* HP/O/B/1009/004, "Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of CNS"

"* HP/O/B/1009/009, "Guidelines for Accident and Emergency Response"

"* HP/O/B/1009/019, "Emergency Radio System Operation, Maintenance, &

Communication" Restore equipment to a "Ready Status" and notify appropriate personnel of conditions that would cause a less than operational status.

Provide all completed procedures and copies of logs to the EOF Emergency Planner upon deactivation of the EOF.

Enclosure 4.8 SR/O/B/2000/003 Radio Operator Checklist Page 1 of 1 INITIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire, when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities.

Obtain a copy of SH/0/B1/2005/002 (Protocol for the Field Monitoring Coordinator During Emergency Conditions), Enclosure 5.3 (Field Monitoring Survey Data Sheet) and Enclosure 5.4 (Meteorological Update for Field Monitoring Teams). {6 }

Establish contact with Field Teams.

Relay instructions obtained from the Field Monitoring Coordinator to the Field Teams.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.9 SR/O/B/2000/003 EOF Off-Site Agency Communicator Checklist Page 1 of 1 NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities Perform the duties as described in the following:

"* Catawba RP/O/A/5000/006C

"* McGuire RP/O/A/5700/015 Ensure emergency notification times are satisfied.

Provide all completed paperwork to Emergency Planning upon deactivation of emergency facility.

Enclosure 4.10 sIRJO/B/2000/O03 Access Control Director Checklist Page 1 of 2 NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the staffing board located in the EOF Director's area.

Establish a log of activities Conduct turnover with Corporate Security to enable them to return to their normal jobs.

Process responders found on the Access List as follows:

"* Request a photo ID from all personnel entering the EOF.

"* Verify the identity of all personnel by comparing the photo ID to facial features.

"* Direct all personnel to sign the Emergency Planning Exercise/Drill or Drill Observer Training Attendance Sheet.

"* Direct all personnel to obtain the appropriate EOF position badge.

McGuire Specific Process responders with "NO ACCESS" appearing beside their names as follows:

Call an FFD contact listed in RP/O/A/5700/O14, Tab 8, to verify if "NO ACCESS" is for a positive drug screen.

NOTE: Verification by the FFD contact of no positive drug screen indicates that the responder is Fit for Duty and "NO ACCESS" is related to a training deficiency.

" Ask EOF Director to waive training requirement and allow access. Document waiver in the EOF Log.

" Ask Emergency Coordinator to waive training requirement if the EOF Director has "NO ACCESS" due to expired training. Document waiver in the EOF log.

Enclosure 4.10 SR/0/B/2000/003 Access Control Director Checklist Page 2 of 2 Process responders not found on the Access List as follows:

"* Request EOF access from the appropriate EOF group primary, EOF Director, or Assistant EOF Director, if prior approval has not been given.

"* Request approved credentials from Federal, State and Off-Site Agency officials desiring EOF access and direct them to sign the Drill Observer Training Attendance Sheet, if applicable.

"* Request picture ID from any Duke Power observers and direct them to sign the Drill Observer Training Attendance Sheet, if applicable.

Notify Corporate Security to secure EOF following deactivation of the emergency facility.

Notify Facility Services at 382-4948 to clean the EOF following deactivation of the EOF.

Place new EOF Access List in appropriate box at EOF Access Control desk.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.11 sR/O/B/2000/O03 Accident Assessment Manager Checklist Page 1 of 3 INITIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities IF additional positions are needed to support the emergency, THEN staff the Administrative Support and the Reactor Physics positions as appropriate.

"* Catawba Home phone numbers are located in the Catawba Nuclear Site Qualified Emergency Response Organization Members Listing located on the Catawba Emergency Planning Home Page. Office phone numbers are located in the electronic Duke Power telephone directory.

"* McGuire NOTE: To access the McGuire Emergency Planning Home Page you must first select the Safety Assurance Home Page from the "Site Web Pages" menu on the McGuire Web Page.

Home and work phone numbers are located in the McGuire Nuclear Site Data Verification & Facility Org. listing located on the McGuire Emergency Planning Home Page. Office phone numbers are also located in the electronic Duke Power telephone directory.

Obtain a copy of the "Classification of Emergency" procedure for the affected station.

Catawba: RP/O/A/5000/001

McGuire: RP/O/A/5700/000

Enclosure 4.11 SR/0/B/2000/003 Accident Assessment Manager Checklist Page 2 of 3 Obtain a copy of the current classification procedure for the affected station from the procedure cabinet:

Notification of Unusual Event Catawba - RP/O/A/5000/002 McGuire - RP/O/A/5700/001 Alert Catawba - RP/O/A/5000/003 McGuire - RP/O/A/5700/002 Site Area Emergency Catawba - RP/O/A15000/004 McGuire - RP/O/A/5700/003 General Emergency Catawba - RP/0/A/5000/005 McGuire - RP/O/A/5700/004 Ensure PC is on and displaying plant status.

Log on to the Emergency Notification Form by following the instructions in the EOF Accident Assessment Managers Logbook behind the ENF Logon Instructions tab.

Verify electronic Emergency Notification Form can be accessed.

Perform the following steps as needed Coordinate the following functions:

"* Accident Assessment Interface

"* Operations Interface

"* Reactor Physics (As needed)

"* Administrative Support (As needed)

Enclosure 4.11 SR/O/B/2000/003 Accident Assessment Manager Checklist Page 3 of 3 Work closely with the Radiological Assessment Manager and be prepared to discuss the following topics during the EOF staff time-outs or earlier as appropriate:

"* Emergency classification recommendations utilizing the "Classification of Emergency" procedure for the affected station:

- Catawba: RP/O/A/5000/001

- McGuire: RP/O/A/5700/000

"* Protective action recommendations

"* Current plant status

"* Accident mitigation strategies with priorities

"* Anticipated course of the event

"* Possible solutions if procedural adequacy becomes a concern

"* Prioritization of key issues Provide information contained in Sections 5 through 9 of the Emergency Notification Form. Refer to Step 3.6 in the main body of this procedure for definitions associated with the Emergency Notification Form.

Coordinate with the Radiological Assessment Manager to provide the information contained in Section 15 of the Emergency Notification Form.

Assist TSC Emergency Coordinator as requested upon entry into Severe Accident Management Guidelines (SAMGs).

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.12 SR/O/B/2000/003 Accident Assessment Interface Checklist Page 1 of 4 IN1TIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities.

Ensure PC is on and displaying affected station and unit plant status.

Catawba Specific Establish bridge line for Operations Loop. Communication is established after the beep.

McGuire Specific Establish bridge line for Operations Loop by dialing 8-875-4500. Communication is established after the beep.

Establish communication link with System Engineering Manager in the TSC, as needed by dialing 8-875-4954.

Obtain a copy of the Classification of Emergency procedure for the affected station.

"* Catawba: RP/O/A/5000/001

"* McGuire: RP/0/A/5700/000

Enclosure 4.12 SR/0/B/2000/003 Accident Assessment Interface Checklist Page 2 of 4 Obtain a copy of the current classification procedure for the affected station from the procedure cabinet.

Notification of Unusual Event Catawba - RP/O/A/5000/002 McGuire - RP/0/A/5700/001 Alert Catawba - RP/O/A/5000/003 McGuire - RP/O/A/5700/002 Site Area Emergency Catawba - RP/O/A/5000/004 McGuire - RP/O/A/5700/003 General Emergency Catawba - RP/O/A/5000/005 McGuire - RP/O/A/5700/004 Obtain a copy of the Core Damage Assessment procedure for the affected station from the procedure cabinet.

"* Catawba: RP/O/A/5000/015

"* McGuire: RP/O/A/5700/019 Obtain a copy of Accident Assessment Technical Manual Gather plant status information using the Accident Assessment Initial Information Request Form found on page 4 of this enclosure.

Upon declaration of a General Emergency IMMEDIATELY RECOMMEND to Accident Assessment Manager protective actions using:

"* Catawba: Enclosure 4.2

"* McGuire: Enclosure 4.3 Perform the following steps as needed throughout the event:

IF condition warrants, THEN determine analysis of the reactor core and containment conditions in regard to:

"* Core sub-cooling

"* Decay heat generation

"* Heat removal capabilities (core and containment)

"* Fission product release potential (core and containment)

Enclosure 4.12 SR/0/B/2000/003 Accident Assessment Interface Checklist Page 3 of 4 IF condition warrants, THEN provide:

"* Estimates of core uncovery times

"* Interpretations of reactor water level data Follow status of the Emergency Operations Procedures (EOPs) and discuss with the Accident Assessment Manager.

Maintain communication with the Radiological Assessment group in the EOF.

Advise Operations Interface of the anticipated course of events.

Provide information for status board in the Accident Assessment Group room and maintain the appropriate logs.

Advise Accident Assessment Manager on the following:

"* Anticipated course of events

"* Diagnosis of the accident and mitigation strategies

"* Analysis of core and containment

"* Core damage and fission product release potential

"* Background information of system design

"* Emergency classifications Support Systems Engineering Manager in the TSC in accident and mitigation strategies.

Assist TSC as requested upon entry into Severe Accident Management Guidelines.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.12 SR/O/B/2000/003 Accident Assessment Interface Checklist Page 4 of 4 Initial Information Request Initial Information Request Results Emergency Classification Status EAL Declaration Chronology Protective Actions Status Reactor/Turbine Status Power Level Time of Trip & On What Signal Any Abnormal Response NC Pump Status Core Cooling Status (subcooled margin/

RVLIS/natural circulation)

Orange or Red CSFs Alarms Received Safety Injection When Actuated & on What Signal NV, NI, ND, Ice Condenser Status Feedwater CF and CA Status Main Steam Isolation Status SMSV, SM PORV, SB Status Electric Power 600V, 4160V, D/G Status Containment Isolation Status NS and VX Status Security/Fire/Flooding/IHZMAT/Other Hazards Plant Conditions Status Off-site Releases Status

Enclosure 4.13 SR/O/B/2000/003 Operations Interface Checklist Page 1 of 1 INITIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities.

Catawba Specific Establish communications for Operations Loop. Communication is established after the beep.

McGuire Specific Establish bridge line for Operations Loop by dialing 8-875-4500. Communication is established after the beep.

Perform the following steps as needed throughout the event:

Serve as the communications interface with the Accident Assessment Group and the TSC Operations Group.

Advise Accident Assessment Group on the following:

"* Emergency Operations Procedures (EOPs)

"* Diagnosis of the accident and mitigation strategies

"* Emergency classification Advise TSC of the anticipated course of events.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.14 SR/0/B/2000/003 Administrative Support Checklist Page 1 of 1 INITIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Obtain a copy of Accident Assessment Manual, Emergency Operating Procedures and affected plant PRA manual from Nuclear Engineering office area.

Put on position badge.

Sign in on the EOF staffing board.

Ensure PCs are on and functional.

Establish a log of activities.

Notify other positions of the Accident Assessment Group at the direction of the Accident Assessment Manager.

Record recommendations of the Accident Assessment team and plant status as appropriate on the status board in the Accident Assessment group room.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.15 SR/0/B/2000/003 Reactor Physics Checklist Page 1 of 1 INITIAL NOTE: You are only required to complete enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities.

Obtain any applicable nuclear design calculations from the Nuclear Engineering office area.

Establish communications with the TSC Reactor Engineer.

IF conditions warrant, THEN determine analysis of the reactor core and the fuel with respect to:

"* Reactor Physics parameters

"* Core subcriticality Provide Accident Assessment Manager with information concerning any abnormal core conditions.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.16 SR/O/B/2000/003 Emergency Planner Checklist Page 1 of 9 INITIAL NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of your normal work hours.

Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities.

NOTE: The Public Address amplifier is in the Janitor Storage Room across from the bathroom. The controls are in a yellow box mounted on the wall on the right side of the room.

Turn on the EOF Public Address system.

Power up and log on Emergency Planner Computer as follows.

Log on using "EOFWS" as the USER ID.

Leave the Password field blank and click OK.

Display Autolog-EP by performing the following:

Double click on Emergency Planning icon.

Double click on AutoLog(EP).

Enter your User ID.

Enter the password (PASSWORD).

Click "Login as Current SS".

Click OK.

the appropriate station log is not displayed, THEN select the appropriate

_..__..F station log by clicking on "File" and then "Open" on the menu bar.

Obtain the Emergency Planner headset from the Emergency Planner Desk area and dial into the EP bridge line using 831-4010 or another available bridge line.

Support EOF Director with the following:

_ Complete EOF Director Checklist items as requested.

Enclosure 4.16 SR/0/B/2000/003 Emergency Planner Checklist Page 2 of 9 Clarify Emergency Plan and Emergency Plan Implementing Procedure information.

Interface with the NRC.

Interface with federal, state and local agencies.

Assist Off-Site Agency Communicators in preparation of emergency notifications as needed.

Compile a 24-Hour Staffing Log for each EOF position. The log is contained in this enclosure.

Verify that EOF Public Affairs personnel have considered 24-hour staffing.

Upon deactivation of the EOF, collect all completed paperwork and forward to the appropriate Emergency Planning Manager.

Upon deactivation of the EOF, complete "EOF Post Event Checklist."

Enclosure 4.16 SR/lO/B/2000/O03 Emergency Planner Checklist Page 3 of 9 EOF DIRECTOR AREA 24 HOUR REQUIRED POSITION EOF STAFFING LOG Primary Relief Name Shift Name Shift Position (Last, First, MI) Schedule (Last, First, MI) Schedule EOF Director Assistant EOF Director Lead EOF Off-Site Agency Communicator EOF Staff Support/

Status Keeper EOF Log Recorder EOF Emergency Planner Radiological Assessment Manager _

Accident Assessment Manager

Enclosure 4.16 SR/O/B/2000/003 Emergency Planner Checklist Page 4 of 9 DOSE ASSESSMENT AREA 24 HOUR DESIRED POSITION EOF STAFFING LOG Primary Relief Name Shift Name Shift Position (Last, First, MI) Schedule (Last, First, MI) Schedule EOF Dose Assessor EOF Dose Assessor EOF Dose Assessor EOF Dose Assessor (HPN)

Field Monitoring Coordinator Radio Operator Meteorologist

Enclosure 4.16 SR/0/13/2000/003 Emergency Planner Checklist Page 5 of 9 ACCIDENT ASSESSMENT AREA 24 HOUR DESIRED POSITION EOF STAFFING LOG Primary Relief Name Shift Name Shift Position (Last, First, MI) Schedule (Last, First, MI) Schedule EOF Data Coordinator EOF Data Coordinator (As Needed)

Accident Assessment Interface Accident Assessment Interface (As Needed)

Reactor Physics (As Needed)

Administrative Support (As Needed)

Operations Interface

Enclosure 4.16 SRIO/12000/003 Emergency Planner Checklist Page 6 of 9 OFF SITE AGENCY COMMUNICATOR 24 HOUR DESIRED POSITION EOF STAFFING LOG Primary Relief Name Shift Name Shift Position (Last, First, MI) Schedule (Last, First, MI) Schedule EOF Off-Site Agency Communicator EOF Off-Site Agency Communicator

Enclosure 4.16 SR/I/B/2000/003 Emergency Planner Checklist Page 7 of 9 ACCESS CONTROL AREA 24 HOUR DESIRED POSITION EOF STAFFING LOG Primary Relief Name Shift Name Shift Position (Last, First, MI) Schedule (Last, First, MI) Schedule EOF Access Control Director EOF Commodities and Facilities Manager

Enclosure 4.16 SR/0/B/2000/003 Emergency Planner Checklist Page 8 of 9 EOF FACILITY POST EVENT CHECKLIST Obtain printed copy of EOF Log Archive Log by selecting the "Archive" button Shutdown the AutoLog program.

When prompted to "Log off and remain Shift Supervisor" select NO.

Retrieve:

Completed Procedures Notes SNOTE: The Ericsson Cellular phones need to remain on to charge properly.

Turn off:

__ Copiers

__ Computers (Leave EOF Director PC and Dose Assessment on with video conferencing running as well as the Data Coordinators Server Computer.)

Video Monitors

__ Public Address Components

__ Projectors Perform:

__ Applicable sections of SR/O/B/4600/086 to replenish supply cabinet and procedure inventories:

Clean Tables Off Put all Trash In Containers Erase Status Boards Verify all Fax machines have paper supply replenished (5 Fax machines)

Verify all copiers have paper supply replenished (2 Copiers)

Replenish:

Position Specific Notebooks (Procedure, Checklist, Log Sheets)

EOF Director Radiological Assessment Manager EOF Dose Assessor Field Monitoring Coordinator Radio Operator EOF Off-Site Agency Communicator Access Control Director Accident Assessment Manager Accident Assessment Interface EOF Operations Interface EOF Administrative Support

Enclosure 4.16 SR/O/B/2000/003 Emergency Planner Checklist Page 9 of 9 Reactor Physics EOF Emergency Planner EOF Log Recorder/Status Keeper EOF Data Coordinator EOF Commodities and Facilities Manager Meteorologist EOF Access List in Access Control Director's area

Enclosure 4.17 SR0/B3/2000/003 EOF Log Recorder/Staff Support/ Page 1 of 1 Status Keeper Checklist NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of our normal work hours.

INITIAL Put on position badge.

Sign in on the EOF staffing board.

Ensure PC is on.

NOTE: Instructions for the use of the AutoLog program are provided in the EOF.

Establish an official log of all significant EOF activities and EOF Director decisions using the AutoLog computer program.

__IF the AutoLog computer program is not available, THEN establish a manual log of all significant EOF activities and EOF Director decisions.

Maintain EOF status boards.

Track established priorities on EOF status board as requested by EOF Director.

Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.18 SR/O/B/2000/003 EOF Data Coordinator Checklist Page 1 of 1 NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of our normal work hours.

INITIAL

___ Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities.

Verify EOF computer hardware, software, and data display equipment is operational per Section I of the Data Coordinator's Reference Manual.

__Provide the following computer support as required:

"* Software and hardware applications support

"* Data acquisition support

"* Communication with TSC Data Coordinator

___ Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.19 SR/0/B/2000/003 EOF Commodities and Facilities Manager Page 1 of 1 Checklist NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of our normal work hours.

INITIAL Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities.

Perform the duties as described in SR/0/B/2000/002.

Contact additional positions as needed to support the emergency.

Ensure positions have signed the board in C&F area.

___ Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.20 SR/O/B/2000/003 Meteorologist Checklist Page 1 of 1 NOTE: You are only required to complete Enclosure 4.21, Fitness for Duty Questionnaire when reporting to the facility outside of our normal work hours.

INITIAL Put on position badge.

Sign in on the EOF staffing board.

Establish a log of activities.

__Discuss changing meteorological conditions with Field Monitoring Coordinator.

___ Refer to step 3.4 in the main body of this procedure for instructions on obtaining meteorological information from the appropriate plant SDS computer screens.

__Provide all completed paperwork to Emergency Planning upon deactivation of the emergency facility.

Enclosure 4.21 SR/0/B/2000/003 Fitness for Duty Questionnaire Page 1 of 1 Print Name: Employee ID #:

Sign Name: ERO Position:

HAVE YOU CONSUMED ALCOHOL IN THE LAST FIVE (5) HOURS?

MARK THE APPROPRIATE BOX No --1 If No, stop here and fold this form and drop it in the box provided.

II ILi Yes If your answer is Yes, take this form to a member of management for observation.

OBSERVATION DETERMINATION What did you have?

How much did you have?

Can you perform your function unimpaired? YES LIII NO L-I In my opinion, observation of this individual indicates the individual is capable of performing his/her ERO function.

Signature Of Management Observer Date Fold the form and drop it in the box provided.

Enclosure 4.22 SR/I/B/2000/003 Commitment for SR/O/B/2000/003 Page 1 of 1

{1} PIP O-M97-4210 NRC-1

{2} PIP O-M96-1645

{3) PIP 2-C96-0273

{4} PIP O-C98-3123

15) PIP 0-M98-3522

{6} PIP-O-M98-2065

(R06-97) Duke Power Company (1) ID No. HP/O/B/1009/002 PROCEDURE PROCESS RECORD Revision No. 002 PREPARAT ION (2) Station McGuire Nuclear Station (3) Procedur e Title Alternative Method for Determining Dose Rate Within the Reactor Building Date (4) Prepared By (5) Requires 10CFR50.59 evaluation?

9' Yes (New procedure or revision with major changes)

"D No (Revision with minor changes)

"o No (To incorporate previously approved changes)

(QR) Date 1oiref (6) Reviewed By C..

ew y (QR) NA Date /0 / tq ciq Cross-Disciplinary Re (QR) NA Date l i -l Reactivity Mgmt. Review By (7) Additional Reviews Date /ý" _q Reviewed By Date 23 Reviewed By . > > N (8) Temporary Approval (if necessary)

By (SROIQR) Date (9) Approved By Qd&4-* P .izm., Date Izt 1 f 9 PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification o Yes 0] NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

El Yes El NA Listed enclosures attached?

o Yes 0 NA Data sheets attached, completed, dated, and signed?

El Yes 0 NA Charts, graphs, etc. attached dated, identified, and marked?

El Yes El NA Procedure requirements met?

Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additionalpages, if necessary)

7 Procedure No.

Duke Power Company McGuire Nuclear Station HP/O/B/1009/002 Revision No.

002 Alternative Method For Determining Dose Rate Within The Reactor Building Electronic Reference No.

Reference Use MC0045FV

HP/O/B/ 1009/002 Page 2 of 3 Alternative Method For Determining Dose Rate Within The Reactor Building

1. Purpose This procedure describes an alternative method for determining the approximate dose rate within the reactor building in the event the reactor building monitors (1EMF51A & B or 2EMF5 1A & B) are inoperable.

The level for this procedure is Reference Use. This procedure must be at the job site at all times.

2. References None

3. Limits and Precautions 3.1 This procedure is written for use under abnormal conditions which could involve extremely high radiation levels. Only the Radiation Protection Manager (RPM) or designee shall authorize the use of this procedure when needed.

3.2 Appropriate Surveillance and Control coverage shall be used under the direction of the Operations Support Center (OSC).

4. Procedure 4.1 Determination of Dose Rate 4.1.1 Call Security for permission to open Alarm Door 6111 for Unit 1 or 6211 for Unit 2 at the respective uppe containment personnel hatches.

4.1.2 Contact the OSC to obtain necessary keys and instructions to open the VE alarm door.

4.1.3 Ensure that the high range survey instrument (Teletector or Extender) to be used is in calibration and a daily response check has been performed.

4.1.4 Standing outside the alarm door if possible, obtain a reading by placing the detector in contact with the exterior center of the outer personnel air lock door.

HP/O/B/1 009/002 Page 3 of 3 4.1.5 Calculate the reactor building dose rate by use of the following equation:

Ra = 740.0 x RH Where:

RB = Reactor Building Dose Rate (R/hr)

RH = Dose Rate at Upper Personnel Hatch Air Lock Door (R/hr) 4.1.6 Forward the following information to the Radiation Protection Technician in the Shift Lab (ext. 4282), TSC Dose Assessors (ext. 4976) or EOF Dose Assessors (382-0744, 0745).

4.1.6.1 Dose rate reading from instrument.

4.1.6.2 Instrument 'MCHPS' number.

4.1.6.3 Your name.

4.1.6.4 RB doserate calculated in 4.1.5.

4.2 Record all necessary information and results on Enclosure 5.1.

4.3 The Reactor Building dose rate shall be determined as directed by the Radiation Protection Manager or designee.

5. Enclosures 5.1 Reactor Building Dose Rate Data Sheet

Enclosure 5.1 HP/O/B/1009/002 Page 1 of 1 Reactor Building Dose Rate Data Sheet DATE/TIME DOSE RATE (R/HR) x 740.0 = RX BUILDING SURVEYING INSTRUMENT DOSE RATE (R/HR) TECHNICIAN MCHPS #

x 740.0 =

x 740.0 x 740.0 =

x 740.0 =

(R06-97) Duke Power Company (1) ID No. HP/0/B/1009/002 PROCEDURE PROCESS RECORD Revision No. 002 PREPARATFION (2) Station McGuire Nuclear Station (3) Procedur *eTitle Alternative Method for Determining Dose Rate Within the Reactor Building (4) Prepared By Date / 'jz/t '9 (5) Requires 10CFR50.59 evaluation?

Ef" Yes (New procedure or revision with major changes) o No (Revision with minor changes) o No (To incorporate previously approved changes)

(6) Reviewed By C. (QR) Date io l Cross-Disciplinary Re ew By (QR) NA Date /0//q Iqq Reactivity Mgmt. Review By (QR) NA Date lo

_ iq 1,1q1 (7) Additional Reviews Reviewed By Date JŽv L"V Reviewed By Date 3(I19<

(8) Temporary Approval (if necessary)

By (SRO/QR) Date By __(QK) Date (9) ApprovedBy /-A 4ý* *:. Date I 117- Th PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification o Yes 0] NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

o Yes 0 NA Listed enclosures attached?

o Yes 0 NA Data sheets attached, completed, dated, and signed?

o Yes 0 NA Charts, graphs, etc. attached dated, identified, and marked?

o Yes 01 NA Procedure requirements met?

Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additionalpages, if necessary)

I Procedure No.

Duke Power Company McGuire Nuclear Station HP/O/B/1009/002 Revision No.

002 Alternative Method For Determining Dose Rate Within The Reactor Building Electronic Reference No.

Reference Use MC0045FV

HP/O/B/1009/002 Page 2 of 3 Alternative Method For Determining Dose Rate Within The Reactor Building

1. Purpose This procedure describes an alternative method for determining the approximate dose rate within the reactor building in the event the reactor building monitors (1EMF5lA & B or 2EMF51A & B) are inoperable.

The level for this procedure is Reference Use. This procedure must be at the job site at all times.

2. References None

3. Limits and Precautions 3.1 This procedure is written for use under abnormal conditions which could involve extremely high radiation levels. Only the Radiation Protection Manager (RPM) or designee shall authorize the use of this procedure when needed.

3.2 Appropriate Surveillance and Control coverage shall be used under the direction of the Operations Support Center (OSC).

4. Procedure 4.1 Determination of Dose Rate 4.1.1 Call Security for permission to open Alarm Door 6111 for Unit 1 or 6211 for Unit 2 at the respective upper containment personnel hatches.

4.1.2 Contact the OSC to obtain necessary keys and instructions to open the VE alarm door.

4.1.3 Ensure that the high range survey instrument (Teletector or Extender) to be used is in calibration and a daily response check has been performed.

4.1.4 Standing outside the alarm door if possible, obtain a reading by placing the detector in contact with the exterior center of the outer personnel air lock door.

HP/O/B/I 009/002 Page 3 of 3 4.1.5 Calculate the reactor building dose rate by use of the following equation:

Ra = 740.0 x RH Where:

RB = Reactor Building Dose Rate (R/hr)

RH = Dose Rate at Upper Personnel Hatch Air Lock Door (R/hr) 4.1.6 Forward the following information to the Radiation Protection Technician in the Shift Lab (ext. 4282), TSC Dose Assessors (ext. 4976) or EOF Dose Assessors (382-0744, 0745).

4.1.6.1 Dose rate reading from instrument.

4.1.6.2 Instrument 'MCHPS' number.

4.1.6.3 Your name.

4.1.6.4 RB doserate calculated in 4.1.5.

4.2 Record all necessary information and results on Enclosure 5.1.

4.3 The Reactor Building dose rate shall be determined as directed by the Radiation Protection Manager or designee.

5. Enclosures 5.1 Reactor Building Dose Rate Data Sheet

Enclosure 5.1 HP/OIB/1 009/002 Reactor Building Dose Rate Data Sheet Page 1 of 1 DATE/TIME DOSE RATE (R/HR) x 740.0 = RX BUILDING SURVEYING INSTRUMENT DOSE RATE (R/HR) TECHNICIAN MCHPS #

x 740.0 =

x 740.0 x 740.0 =

x 740.0 =

(R06-97)

Duke Power Company (I) ID No. HP/OIB/1009/002 PROCEDURE PROCESS RECORD Revision No. 002 PREPARAT ION (2) Station McGuire Nuclear Station (3) Procedur-e Title Alternative Method for Determining Dose Rate Within the Reactor Building (4) Prepared By 4;_* Date ,I/g/!9 (5) Requires 10CFR50.59 evaluation?

[* Yes (New procedure or revision with major changes) 0] No (Revision with minor changes) 1] No (To incorporate previously approved changes)

(6) Reviewed By C. (QR) Date to/,q I(eq Cross-Disciplinary Re ew'By (QR) NA ( Date Reactivity Mgmt. Review By (QR) NA C Date (7) Additional Reviews J LeqI Reviewed By . Date tlliq Ihq Reviewed By Date (8) Temporary Approval (if necessary)

By (SRO/QR) Date By (QR) Date (9) ApprovedBy QdL ý..

Date 1t1z*17 PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification 0] Yes 0] NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

o1 Yes 0] NA Listed enclosures attached?

[1 Yes 0 NA Data sheets attached, completed, dated, and signed?

o Yes 0 NA Charts, graphs, etc. attached dated, identified, and marked?

[J Yes 0 NA Procedure requirements met?

Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additionalpages, if necessary)

I Procedure No.

Duke Power Company McGuire Nuclear Station HP/OIB/1 009/002 Revision No.

002 Alternative Method For Determining Dose Rate Within The Reactor Building Electronic Reference No.

Reference Use MC0045FV

HP/O1B/ 1009/002 Page 2 of 3 Alternative Method For Determining Dose Rate Within The Reactor Building

1. Purpose This procedure describes an alternative method for determining the approximate dose rate within the reactor building in the event the reactor building monitors (lEMF5 LA & B or 2EMF51A & B) are inoperable.

The level for this procedure is Reference Use. This procedure must be at the job site at all times.

2. References None

3. Limits and Precautions 3.1 This procedure is written for use under abnormal conditions which could involve extremely high radiation levels. Only the Radiation Protection Manager (RPM) or designee shall authorize the use of this procedure when needed.

3.2 Appropriate Surveillance and Control coverage shall be used under the direction of the Operations Support Center (OSC).

4. Procedure 4.1 Determination of Dose Rate 4.1.1 Call Security for permission to open Alarm Door 6111 for Unit 1 or 6211 for Unit 2 at the respective uppe containment personnel hatches.

4.1.2 Contact the OSC to obtain necessary keys and instructions to open the VE alarm door.

4.1.3 Ensure that the high range survey instrument (Teletector or Extender) to be used is in calibration and a daily response check has been performed.

4.1.4 Standing outside the alarm door if possible, obtain a reading by placing the detector in contact with the exterior center of the outer personnel air lock door.

HP/O/B/1009/002 Page 3 of 3 4.1.5 Calculate the reactor building dose rate by use of the following equation:

RB = 740.0 x RH Where:

RB = Reactor Building Dose Rate (R/hr)

RH = Dose Rate at Upper Personnel Hatch Air Lock Door (R/hr) 4.1.6 Forward the following information to the Radiation Protection Technician in the Shift Lab (ext. 4282), TSC Dose Assessors (ext. 4976) or EOF Dose Assessors (382-0744, 0745).

4.1.6.1 Dose rate reading from instrument.

4.1.6.2 Instrument 'MCHPS' number.

4.1.6.3 Your name.

4.1.6.4 RB doserate calculated in 4.1.5.

4.2 Record all necessary information and results on Enclosure 5.1.

4.3 The Reactor Building dose rate shall be determined as directed by the Radiation Protection Manager or designee.

5. Enclosures 5.1 Reactor Building Dose Rate Data Sheet

Enclosure 5.1 HP/O/B/1009/002 Reactor Building Dose Rate Data Sheet Page 1 of 1 DATEFTIME DOSE RATE (RIHR) x 740.0 = RX BUILDING SURVEYING INSTRUMENT DOSE RATE (R/HR) TECHNICIAN MCHPS #

x 740.0 =

x 740.0 x 740.0 x 740.0 =

x 740.0 =

x 740.0 x 740.0 x 740.0 =

x 740.0 =

x 740.0 x 740.0 =

x 740.0 =

x 740.0 x 740.0 =

x 740.0 =

x 740.0 x 740.0 x 740.0 =

x 740.0 =

HP/I/B/1009/020 has been deleted, please remove from your manual.

Multiple Addressees DISTRIBUTION:

E-Mail w/o Enclosures 3 & 4 SCollins/RPZimmerman JJohnson BWSheron DBMatthews SFNewberry GMHolahan WDBeckner RJBarrett RLDennig FMReinhart MLWohl NTSaltos TSB Staff JAZwolinski JFWilliams AWMarkley MACunningham, RES MMarkley, ACRS Staff HARD COPY FILE CENTER PUBLIC TSB R/F NVGilles

December 14, 1999 Mr. Anthony Brooks Nuclear Energy Institute Suite 400 1776 1Street, NW Washington, DC 20006-3708 Mr. Brooks:

The purpose of this letter is to transmit the summary of two meetings with the Risk-Informed Technical Specifications Task Force. The first meeting was held at the San Onofre Nuclear Generating Station on October 6-7, 1999. The second meeting was held at the U.S. Nuclear Regulatory Commission (NRC) Headquarters offices in Rockville, Maryland, on November 10, 1999.

Sincerely, Original signed by:

William D. Beckner, Chief Technical Specifications Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation

Enclosures:

1. Meeting Summary

2. Attendance List

3. October Meeting Presentations

4. November Meeting Presentations cc: See attached list DISTRIBUTION: See attached.

DOCUMENT NAME: G:\RTSB\GILLES\MTGSUMRITSTF111099.WPD OFFICE NRR/DRIP/RTSE NRRIMZTSB NRR/DRIP/RTSB NAME NVGillesl-QV IRLDenhng WDB ckner LWW It)

DATE 1 121/U99 1 Y9 12/ 99 OPFICIAL RECORD CO PY DFC 2 (1c9

UNITED STATES 0 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 two* December 14., 1999 Mr. Anthony Brooks Nuclear Energy Institute Suite 400 1776 1Street, NW Washington, DC 20006-3708 Mr. Brooks:

The purpose of this letter is to transmit the summary of two meetings with the Risk-Informed Technical Specifications Task Force. The first meeting was held at the San Onofre Nuclear Generating Station on October 6-7, 1999. The second meeting was held at the U.S. Nuclear Regulatory Commission (NRC) Headquarters offices in Rockville, Maryland, on November 10, 1999.

Sincerely, William D. Beckner, Chief Technical Specifications Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation

Enclosures:

1. Meeting Summary

2. Attendance List

3. October Meeting Presentations 4' November Meeting Presentations cc: See attached list

Multiple Addressees cc:

Mr. Alan Hackerott Mr. Dennis Henneke Omaha Public Power District San Onofre Nuclear Generating Station Ft. Calhoun Nuclear Station Southern California Edison P.O. Box 399 5000 Pacific Coast Highway Ft. Calhoun, NE 68023-0399 San Clemente, California 92674-0128 Mr. Noel Clarkson Ms. Sharon Mahler Duke Energy/Oconee Cooper Nuclear Station Mail Code: ON03RC Nebraska Pulic Power District Highways 130 & 183 (29678) P.O. Box 98 P.O. Box 14393652 Brownville, NE 68321-0098 Seneca, SC 29679-1439 Mr. Frank Rahn Mr. Greg Krueger Electric Power Research Institute PECO Energy Company P. 0. Box 10412 Mail Code 63A-3 Palo Alto, CA 94303 965 Chesterbrook Boulevard Wayne, PA 19087 Mr. Donald Hoffman EXCEL Services Corporation Mr. Wayne Harrison 11921 Rockville Pike, Suite 100 South Texas Project Electric Generating Rockville, MD 20852 Station STP Nuclear Operating Company Mr. Jack Stringfellow P. 0. Box 289 Southern Nuclear Operating Company Wadsworth, TX 77483 P.O. Box 1295 Birmingham, AL 35201-1295

NRC/INDUSTRY MEETING OF THE RISK-INFORMED TECHNICAL SPECIFICATION TASK FORCE Meeting Summaries October 6-7 and November 10, 1999 Two meetings between the.NRC staff and industry representatives comprising the Risk Informed Technical Specifications Task Force (RITSTF) were held on October 6-7 and November 10, 1999. The attendees are Iistedin Enclosure 2. The meetings were a continuation of earlier meetings where the NRC staff and the industry discussed ongoing risk informed technical specification initiatives and the creation of a fully risk-informed set of standard technical specifications (STS).

The main purpose of the October 6-7 meeting was to have a more detailed discussion of the probabilistic risk analysis (PRA) work done to support the current technical specification (TS) initiatives being prepared for submittal to the staff. There was limited RITSTF representation at this meeting. Southern California Edison has volunteered San Onofre Nuclear Generating Station (SONGS) to be the industry's lead plant for the majority of the seven initiatives currently being pursued by the RITSTF. These include:

1. Define preferred end states for TS actions (e.g., hot shutdown vs. cold shutdown)

2. Increase the time allowed to delay entering required actions when a surveillance is missed

3. Modify existing mode restraint logic to allow use risk assessments for entry into limiting conditions for operation (LCOs) with inoperable equipment based on low risk

4. Develop a risk-informed extension of current allowed outage times based on a configuration risk management program (CRMP)

5. Optimize surveillance requirements (SRs)

6. Modify LCO 3.0.3 actions and timing by extending minimum time to begin LCO 3.0.3 shutdown from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and allowing for a risk-informed evaluation to determine whether it is better to shut down or continue to operate

7. Define actions to be taken when equipment is not operable but is still functional The staff and the industry discussed the meaning of the term "risk-informed" as it relates to regulatory applications. Thetindustry stated that it was their general philosophy to use qualitative risk assessments where they believed the benefits of a proposed change were obvious, and to use quantitative assessments where the outcome was not as obvious. The industry also stated that they take intoaccount other aspects such as defense in depth and safety margins when considering a proposed change. The industry believed such an approach was consistent with the guidance in Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," to use PRA to improve decision making and regulatory effectiveness. The staff reserved judgement of such an approach noting that benefits that are obvious to one person or group might not be obvious to another.

SONGS representatives then presented some details regarding their PRA work in support of some of the RITSTF initiatives. The San Ongfre presentations are contained in Enclosure 3.

.The SONGS representatives presented information regarding their living PRA and Safety Monitor, including the full power, transition, and low power and shutdown risk models. The 1 Enclosure 1

SONGS representatives stated that they had their own transition model development document that would likely be referenced or included in the SONGS plant-specific submittal for Initiative #1.

The staff and the RITSTF discussed some specific submittal and implementation and technical issues related to a few of the initiatives. With regard to Initiative #1 related to safe end states, the RITSTF indicated that the Combustion Engineering Owners Group (CEOG) was preparing a draft report to support this initiative and that the report would accompany an industry request for a generic change to the STS. The RITSTF indicated that changes to the TS end states would be proposed for the vast majority of LCOs in the STS. The RITSTF indicated that uncertainties and sensitivities of PRA results will be investigated. The group diseussed that additional known shutdown issues which may impact the results (e.g., external events and boron dilution) should be addressed.

Representatives from the Boiling Water Reactor Owners Group (BWROG) stated that they are still considering this initiative and that the risk of operating in hot shutdown and in cold shutdown is relatively the same, whereas for the pressurized water reactors there appears to be a clear risk benefit to operating in hot shutdown in most cases. They indicated that they would be more interested in changing the current TS to allow them to use PRA in deciding whether to stay at power or shut the reactor'down. They also indicated that they may be interested in extending the time requirements for going to cold shutdown. This would allow them to operate longer in hot shutdown conditions. The BWROG is considering a pilot plant for this issue.

The RITSTF and the staff discussed how the SONGS assessment results for Initiative #1 could be applied to other plants. The Westinghouse Owners Group (WOG) indicated that they would attempt to show how the SONGS results apply using qualitative assessments and comparisons, and that they did not plan to perform any further plant-specific analyses. The Babcock and Wilcox OwnersGroup indicated that they intended to pursue a similar approach.

The group indicated that they could use the SONGS model to help develop sensitivity studies to address some of the design differences between the plants. The staff stated that they could not make any definitive decisions on what type of submittals they would find acceptable and that the burden of proof of similarity to the CEOG work would rest with the other owners groups.

With regard to Initiative #2 related to missed SRs, the group discussed the PRA aspects of that initiative. In order to assess the increase in risk-it is necessary to make an assumption about the frequency of the various expected missed surveillances. This requires an understanding of the reasons, the nature'and circumstances under which surveillances are missed. The RITSTF pointed out that even if the failure rate of a component is doubled, due to the missed surveillance on that component, the plant risk would not be affected significantly.

The staff agreed that most likely the risk increase would not be significant unless some licensees abuse the proposed flexibility. The development and implementation of an appropriate regulatory oversight process could address this issue. The industry and the staff agreed that the staffs review of this issue would involve more of a policy decision than a technical decision.

With regard to Initiative #3 related to mode restraints, SONGS has been studying this issue by comparing the relative importance of functions and associated systems at various modes of 2 Enclosure 1

operation. The proposed change would allow a licensee to use a CRMP to decide whether to enter into a mode or other specified condition within the applicability with inoperable equipment. The staff agreed that the study of conditions and risks associated with various likely transitions could help focus the issue and identify an appropriate regulatory oversight mechanism.

With regard to Initiative #6 related to changes to LCO 3.0.3, the RITSTF stated that this initiative is very closely tied to the maintenance rule as it addresses what actions to take for a loss of safety function. The industry indicated that the frequency of plant conditions for which this TS change is applicable is low. The staff mentioned that the identification and study of examples of plant specific LCO 3.0.3 entries and conditions that would drive the plant to shutdown, including associated risks, could help focus the issue.

The group discussed the process for plants to adopt approved changes to the STS. The staff briefly discussed processes being considered to make adoption of such approved changes more efficient.

Finally, the group discussed submittal schedules for some of the initiatives. The RITSTF stated that they expected to submit Initiatives #2 and #3 to the staff around October 30, 1999, and that they might be able to submit some of their PRA assessment for Initiative #1 by December 31, 1999. The RITSTF stated that Initiatives #4 and #6 would come sometime in 2000.

The November 10, 1999 meeting was a meeting of the full RITSTF to discuss high-level objectives and the status of the current initiatives. All presentations for the meeting are contained in Enclosure 4. The staff opened the meeting with a general discussion of the status of risk-informed regulatory activities at the NRC. The staff pointed out that there was a high level of interest in the RITSTF activities and that we needed to understand how broad the interest in the industry was. The staff presented several thoughts on a. long-term vision for risk-informed TS and acknowledged that structure and resource issues will need to be worked out. The staff also pointed out that it will need to address the four strategic performance goals identified in the Commission's Nuclear Reactor Safety Strategic Plan. Those performance goals are: (1) Maintain safety; (2) Increase public confidence; (3) Reduce unnecessary regulatory burden; and (4) Make NRC activities and decisions more effective, efficient, and realistic.

The RITSTF presented some of its thoughts on a long-term vision for risk-informed TS. Much of the discussion focused on a slide which presented the Westinghouse Owners Group (WOG) five year risk-informed TS strategy. The grouP discussed at what point rulemaking might be needed to accommodate all of the envisioned changes to TS. The group also discussed the issue of PRA quality and the fact that the ASME PRA standard currently being developed did not address configuration risk management tools like those envisioned as necessary to implement many of the TS changes.under development.

Representatives from the South Texas Project presented a concept of a fully risk-informed set of TS that essentially relies ona CRMP as the backbone of the TS. They likened the proposed risk limits in their concept to radiation protection limits (i.e., ALARA limits). The NRC regulates ALARA limits at a highlevel and licensees control these limits at a lower level administratively. The group also discussed whether there was a need for an instantaneous 3 Enclosure 1

risk cap for TS. The RITSTF stated that the major question is the cost benefit of going to this extreme. For example, if plant PRAs essentially become the TS, then licensees would have to control changes to the PRA model to the same degree as TS changes are currently controlled.

The RITSTF,presented a status of the seven initiatives currently under development. The group discussed Initiative #1 related to safe end states. The RITSTF stated that the expected results were'confirmed by the PRA work done by SONGS. The group again discussed what work the other owners groups'planned to do to justify the changes for their plant types by taking advantage of the SONGS and CEOG work.

Updated schedules for the various initiatives were discussed. The RITSTF stated that they expected to submit Initiative #1 in February or March 2000. Initiatives #2 and #3 were expected to be submitted in the very near future. Initiative #4 was planned for submittal in late 2000. Initiatives 5, 6, and 7 were also expected in mid to late 2000.

The group briefly discussed the staff's planned process for reviewing and adopting these initiatives as changes to the STS. The group also discussed support for the December 16, 1999 meeting with the Advisory Committee for Reactor Safeguards Reliability and PRA Subcommittee and agreed to a possible future meeting in late February 2000.

4 Enclosure 1

Meeting Attendees October 6-7, 1999 Name Affiliation Dennis Henneke Southern California Edison Sharon Mahler Southern California Edison Gary Chung Southern California Edison Brian Woods Southern California Edison Thomas Hook Southern California Edison Ed Scherer Southern California Edison Don McCamy Tennessee Valley Authority Kent Sulton ' Nebraska Public Power District S.. Visweswaran General Electric Thomas Sihko Vermont Yankee Jerry Andr6 Westinghouse Mike Kitlan Duke Power Rick Wachowiak Nebraska Public Power District Frank Rahn Electric Power Research Institute Nicholas Saltos NRC/NRR/SPSB Millard Wohl NRC/NRR/SPSB Nanette Gilles NRC/NRR/RTSB Enclosure 2

Meeting Attendees November 10, 1999 Name Affiliation Ray Schneider ABB-Combustion Engineering Nuclear Fuel Company Alan Hackerott Omaha Public Power District Dennis Henneke Southern California Edison Sharon Mahler Southern California Edison Biff Bradley Nuclear Energy Institute Noel Clarkson Duke Power Wayne Harrison South Texas Project Rick Grantom South Texas Project Donald Hoffman EXCEL Services Jerry Andr6 Westinghouse Jim Andrachek Westinghouse Jack Stnngfellow Southern Nuclear Don McCamy Tennessee Valley Authority E. D. Ingram Southern Nuclear Glenn Warren BWR Owners Group David Stellfox McGraw Hill John Fehringer INEEL J. E. Rhoads Energy Northwest Richard Harris Entergy Mike Kitlan Duke Power Rodney Johnson Detroit Edison.

Bert Morris Tennessee Valley Authority Gregory Norris Entergy Rick Wachowiak Nebraska Public Power District Scott Newberry NRC/NRR/DRIP Rich Barrett NRC/NRR/SPSB Mark Reinhart NRC/NRR/SPSB Mark Rubin NRC/NRR/SPSB Millard Wohl NRC/NRRISPSB Nick Saltos NRC/NRR/SPSB William Beckner NRC/NRR/RTSB Bob Dennig NRC/NRR/RTSB Jack Foster NRC/NRR/RTSB Nanette Gilles NRC/NRR/RTSB Enclosure 2

ENCLOSURE 3 OCTOBER 6-7, 1999 MEETING PRESENTATIONS Enclosure 2

"/ ENCLOSURE 3 OCTOBER 6-7, 1999 MEETING PRESENTATIONS Enclosure 2

-I Risk Informed Technical Specification Task Force SONGS PRA Presentation Dennis W. Henneke SONGS Nuclear Safety Group 10/6/99

SCE Living PRA/Safety Monitor lThe SONGS 2/3 PRA model is developed and maintained on WINNUPRA, and can be solved on either WINNUPRA or Safety Monitor.

- 'Scope of the PRA includes:

....... efu ling and offlae

- All modes 1 to 6, refuefloaded.

- External Events for modes 1-4 (Fire/Seismic)

- Fault Tree Initiating Events for Support systems (e.g., CCW or SDC).

SCE Living PRA/Safety Monitor

/* Differences between WINNUPRA and Safety Monitor include:

WINNUPRA:

Solve individual event trees, sequences etc., or the Safety Monitor top logic model.

. Software helps in troubleshooting results, viewing solution steps, performing sensitivity, etc.

Safety Monitor:

. Solves whole model (top logic model) each time.

. Can easily run selected configurations (3-5 min). 3

SCE Living PRA/Safety Monitor

/Living PRA:

- PRA is constantly being updated, as new PRA information becomes available or modeling enhancements are performed.

- Failure Data for major equipment is updated each plant cycle.

PRA modeling basis and changes are tracked

-::4 electronically 4

t Full Power and Transition Models I The following categories are used for the SONGS 2/3 PRA

- Full power: Mode 1

- Transition: Modes 2, 3, and 4 on AFW

- Shutdown: Mode 4 on SDC, Modes 5,6 and offloaded.

4Full Power and Transition models include both internal and external events (EEs).

. EEs are not used for comparison to shutdown.

5

Full Power and Transition Models - Continued

...:/Transition

' Models are similar to Full Power, with some changes:

- Pressurizer Safety Lift less likely in modes 2,3 and not possible in mode 4.

....... - ATWS Less likely in mode 2 and not possible in modes 3,4.

- Loss of AFW used instead of Loss of MFW for modes 3, 4 (MFW Not Available for SONGS).

. AFW TD Pump not available in mode 4 for SONGS Init-LOP increased for modes 3-6, offloaded. J

I, p

Full Power and Transition Models- Continued

- TT, Rx Trip, etc. set to zero in modes 3/4.

- More time available ( 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months versus 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) for recovery of offsite power and MFW/Condensate.

- LOCA Initiating Events reduced by a factor of 20 for mode 4.

- Loss of MFW increased by 4 in mode 2.

- Other Model adjustments needed for conditional events, such as operator responses, fast bus

..... transfer, or conditional loss of offsite power.

7

Full Power and Transition Models - Continued llHuman actions for modes 1-4 are mostly the same, except time related actions.

a l/Important IEs change from a typical PRA result in mode 1 to dominated by loss of AFW in mode 3-4, or loss of offsite power.

8

Total CDF, all Initiating Events DRAFT-SONGS SONGS Transition Risk Model 10/4/99 Draft, Rev. 2 1.00E-04 9.OOE-05 8.OOE-05 7.OOE-05 1..

6.OOE-05 5.OOE-05 a,

0.

4.OOE-05 3.OOE-05 2.OOE-05 1.00E-05 O.OOE+00 Mode 1 Mode 2, Initial Mode 3, Initial Mode 4, on AFW Mode 4, on SDC Mode 5, vented Shutdown Shutdown Plant Operational State

Full Power and Transition

..Models - Continued

/ Model Sensitivity:

- MFW assumed available had little affect on the result, since condensate pumps are already assumed available on all non-LOP sequences.

. Feed& Bleed/PORV availability will lower results in mode 1-4, but only slightly.

- SONGS 2/3 Emergency DG Crosstie removal would raise the PRA results for all modes, but

..... the relative risk would remain similar.

10

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v ui sllnsai siLjjjojPAOT-tl3-d -dn3louq DC[S lim

.ioj olqvl!uAv pouinssu si XuidS ju;)wuiejuoD

-MjV t opow ui uoilonpai

'sllns;).i t opow iomol p1nom t opoui ui c)lqul!uAu ý?uioq duinl AAjV (11

XIIAII!SUOS 13POWt ponuiluoo - slopoW,,:,...

uoillsupil puL-3 joAko(I llnj

Full Power and Transition Models - Continued.

vlModel Sensitivity Conclusions.

- Major sensitivities looked at above do not change the general results that mode 4 on AFW has the lowest shutdown risk, and most defense "in depth.

12

Risk-Informed Technical Specifications Low Power Shutdown Risk 1

Agenda

+ Background

+ Low Power Shutdown (LPSD) Risk Assessment Methodology

-+.Major Assumptions

+..Low Power vs. Full Power Success Criteria

+ LPSD Risk Sensitivities

+ Summary I

A4

Background

4q

... AWN."

. LPSD Risk Performed Since 1990

+ Started LPSD PRA Models in 1993

. ,+LPSD Risk Used For Outage Risk Planning and Monitoring, RI-IST, RI-TS, and Outage Safety Significance Determinations 17 Low Power and Shutdown Risk Assessment Methodology

+'Wl NNUPRA/Safety Monitor

+*.::

Full Event Tree/Fault Tree Model

+ Only Internal Events Modeled

-.: Complete System Models

-*

Full Power Models used with LPSD enhancements 2

I LPSD Methodology (con't) 4

+:41 Low Power/ Shutdown Plant 4 Operating States (POS) .4

Vent size and availability, RCS le\ *el, time 4

since shutdown, RCS draining, eq uipment availability

.4

3 - 5 POS dominate risk profile 4

5 6..

Risk Profile 6

UNIT 3 CYCLE 10 REFUELING OUTAGE Safety Monitor V2.Oa : Safety Monitor V2.Oa I.OO1-02 6- Mid-loop, 'I- Mode 5 Entury, 5- Draining io mid-loop.

7- I AI Below RVF, 8- I Fi Below RVF (I lead Off/Swyd Maini),

9. 13 Fi Above RVF, 10. Fuel Offloading. I I- Fuel in Ilhe SIP, 12- Fuel Reloading, 13- I Ft Below RVP, 14- Draining to mid-loop. I 5 RCS al mid-loop, 16- Mode 5 Pzr Normal Venled, I7- Mode 5 Pzr Normal/Solid No Ven;,-, 18. Mode 4 IIoi Shutdown.

I.OOE-03 7 1.OOE-04 6i

'4 W1*-J 12.

3/4/1999 05:48am

--- I I 6/2/1999 0 6 :48am '.OOE-05 INSTANTANEOUS CORE DAMAGE RISK PROFILE

LPSD Methodology (con't)

+ Human Reliability Analysis (HRA)

Methods Are The Same As Full Power (i.e. Dr. Swain's THERP method)

Mission times based on time to core boiling and core uncovery HRA probabilities are conservative

+ System Models And Support System Dependencies Are Essentially The

Same As Full Power Initiating Events

+.:Grid-Related Loss of Offsite Power

+4.Plant-Centered Loss of Offsite Power

+ Loss of Shutdown Cooling

modeled using fault tree (vs point estimate) 4* - includes loss of support system such as CCW, HVAC 4

Initiating Events (con't)

+*..:Loss of Inventory (LOI)

' *event frequency based on NSAC data

-LOIfrequency reduced by factor of 10 (judgement) when not in draining or filling operation

.*System Alignments Salignments for the following systems:

- Component Cooling Water

- Salt Water Cooling

Shutdown Cooling

- Containment Spray High Pressure Safety Injection

CVCS 10 5

Major Assumptions

"*..Core Damage is Defined To Be Core Uncovery

", Large Early Release Not Possible At 4sJ LPSD

"*. Gravity Feed Is Not a Success Path (Surge Line Flooding) Unless RPV MI' Head Is Removed

"*-: Containment Spray Pumps Backup The LPSI Pumps For SDC 1 Full Power vs. LPSD Success Criteria I

_!_Full Powr i LPSD 4A HPS1 2 of 4 injection Kims 1of 4 injection Eims LPSI (SIC) 2 of 4 injection lims I of 4 injection lins I of 2 pumps I of4 pwnps (incl CS pp)

CS I of 2 trains I of 2 pumps (SDC badcup)

CCW I of 2 trains satin I of3 pumps SWC I of4 purrps same I of 2 trains AFW 1 of3 punrps I of 2 ptPs (turbine drive I purp unavailble) i Electrical I of 2 trains sarn Core Damnage Core Uncovery I sane 12 6

LPSD Risk Sensitivities

+".Conservative HRA Leads To Conservative Results

+.Loss of Inventory Event Frequency

Dominant During Draindown POS SInitiating Events Contribute Rather Equally For POSs Other Than Draining 13 Significant Operator Actions

+ Operator Isolates Coolant Diversion Prior To Loss Of SDC SOperator Initiates Backup SDC Prior To i Boiling

+ Operator Initiates RCS Make-Up Prior to Core Uncovery

+.Operator Initiates DG Cross-tie To "OtherUnit

"+ Recovery of Offsite Power 1

SSummary

.. LPSD Risk Analysis Can Give Meaningful, Quality Results Comparable to Full Power Analyses Given:

System Success Criteria Are Accurately Captured Operator Recoveries Are Understood

Sensitivity to Operator Action Probabilities Are Appreciated

° Level of Detail of the System Models Is Equivalent To Full Power Models 8

ENCLOSURE 4 NOVEMBER 10, 1999 MEETING PRESENTATIONS Enclosure 2

Risk-Informed Technical Specification Strategic Vision November 10, 1999 Motivation

How do RI-TSfit in with RIPS0?

How do RI-TS mesh with the Maintenance Rule S0.65(aX4):

"7The second NEI concern addressed the apparent overlapping regulatory requirements of technical specifcations and the proposed maintenance rule." [SECY-99-133]

SResults of GAO Study: 'NRC has not developed a comprehensive strategy that would move its regulation ofthe safety of nuclear power plants from Its traditional approach to an approach that considers risk."

SConmerns about incremental changes without overall vision li/In,,p I

Risk-Informed Alternative Technical Specifications Issues

Bring masinteance nile and seelicnial spedi~caions Wno congnminc - address fundamenWa probem of potentially getting differe ntsmwmrs fom two

Ban~d-add rchatieaaliip of suppout/mppcrsed systemsa in STS

Growing use of fisactionahtiy in 73 viice 'fraire"

STS atruccture that baa a" LCOs aligned by design review and responsible design review organization

Consider what can be actomplished without chaning $0.36 EXAMPLE Reconstruct Currnt Technical SpecficattionSj Category n TSCrit" 1 &2 TS Criteria3& 4 0DOo RM-5 Requi~I~ 3 Safety Lim its Airuse LWOe & Sib by Mode Limiting Safety System Soft shtudown rfqiatnmas fl"Managma.u Etc (thing that armnot modeled initial conditions, Tlirosbeldsf Aedega One or mare Loom not met Arinue by Mode?? I-Asem~apit oteiipation 2-Restor Siwmdq~t 3-Rastore reduntdancy (is.. dt Hardsuton reurm entsi Exceed safety limit OR

[30.36(cXIXiXA)] Use SFDP and qtmail till." 4 2

WOG Five Year Risk Informed Tech Spec Strategy 1999 -- - - -.04UM - 2001 - ..

m -. ... 2005 I' Major Fc Risk Informed rmat

' " Evoluti Integrated I onS I

!' (JOG Safety Specifications (RUSS) STP Lead

) - WWIm-

-Determine appropriate end states

Delete SRs not related Issue 1 (Task 1, MUHP.3015) iceseCnrle 2002-- 2 Rule Changes to safety functions

-Relax requirement for missed SR (Issue 5a)

Risk-inform 50.36 format Issue 2 (Task 2 of MUHP-3015) -Relocate STIs to 50.36 Format/

Content *Risk-inform

Relax mode change requirements :Program (Issue 5b) Criteria 1, 2, 3 Issue 3 (Task 3 of MUHP-3015)

-Risk Informed AOTs I

Issue 4b (MUHP-3010) r *,"Floating" AOTs with a

Extend Time in LCO 3.0.3 j Consistent w.ith I "backstop" based on Issue 6 (Task 4 of MUHP-3015) IMaintenance] Rulel CRMP (Issue 4a)

RTS/ESFAS AOT/STI Extensions , am= -.-- I *SSCs that are Inoperable, (MUHP-3045) but Functional (Issue 7)

Current WOG Programs a New WOG Programs 99S9.PT - Rough Draf-99l3-0--- . .. - 179 5

INITIATIVE 4a AOT EXTENSIONS N Seen as two part Initiative.

4a Generic risk informed AOT's with a backstop

>)FOR EXAMPLE: If-component X is inoperable, restore to operable status within 7 days, or operation may continue for up to [30J days if the configuration is acceptable in accordance with the Configuration Risk Management Program (CRMP).

St S INITIATIVE 4a I AOT EXTENSIONS 1 a"IT *' TI- T* ' I'I .,* r v . .

utGrENERI.C KISK INFORMED AOTS' WITH A BACKSTOP:

EXAMPLE FORMAT Condition Action Completion Time A. One required A. 1 Restore required [subsystem] to Operable status

[subsystem] [ 7 days]

Inoperable or A.2 .1 Determine if the configuration is acceptable for an [ 7days ]

Action A.1 Completion Time extension not to exceed [30 days] in accordance with the CRMP.

And A.2.2 Restore required [subsystem] to Operable status Action A.2 Limit B. Required Action A and associated Completion Time not B. 1 Be in Mode 3 met 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

2.0 Configuration Risk Management Program 2.1 Purpose.- The Configuration Risk Management Program (CRMP) Is used to monitor and assess the risk Impact of equipment out-of-service maintain station risk at desired levels. The CRMP Is used to assess risk and to impacts for planned and unplanned equipment outages that are modeled In the STP Probabilistic Risk Assessment.(PRA). The CRMP Is applicable to systems, structures, and components (SSCs) within the scope of the stationrs PRA as reflected In the Risk Assessment Calculator (RAsCal) for plant Mode I and 2 operation and the Shutdown Risk Assessment for plant Mode 3,4, 5, and 6 operation.

2.2 Description - Licensees shall be capable of determining the risk In terms of core damage frequency associated with all historical and planned plan configurations of defined plant critical safety functions. Plant risk levels shall be managed via the most restrictive concurrently applicable risk limits (i.e., lowest quantitative limits and most stringent associated action levels) prescribed in this section. In Sections 2.3.1 and 2.3.2, the plant configuration risk must meet both weekly cumulative and Incremental risk limit criteria to justify operation under the green action level. In all cases, Incremental risk limits, though calculated over a one-hour time period, apply to any CDP values calculated over time periods of one hour or less (i.e., to meet the risk limit criteria, no instantaneous risk levels greater than the Incremental risk limit values are permitted).

2.3 Requirements - The licensee shall be capable of determining the risk aisoclated with plant wonfig tlons and shall operate the plant In accordance with fth allowable risk limits Identified. In this section.

2.3.1 Allowable risk limits for Modes I and 2:

Risk Significance Region Allowable Weekly Core Damage Allowable Incremental Core Required Action Probability, CDPw.* Damage Probability, CIP,, Leve Non-Risk Significant Region CDPuMm <_ [5.00E-071 CDP.x-. < J5.00E-08J GREEN Potentially Risk Significant Region [5.00E-071 < CDP_..,i,<ci1.00E-06j [5.00E-081 5 CDPim.. - [1.00E-07J YELLOW Risk Signiricant Region [1.0OE-06J < CDP-,-,* < 12.00E-06J [1.00E-071 5,CD-*ma < [2.00E-07] ORANGE Highly Risk Significant-Region 12.00E-060

" COP---. 12.-OE-07 <5 CDP--n- RED 2.3.2 Allowable risk limits for Modes 3. 4.S. and'6:

Risk Significance Region Allowable Weekly Core Damage Allowable Incremental Core Required Action Probability, CDP-a.i.. Damage Probability, CDPI.I., Level Non-Risk Significant Region CDPwe" < [5.OOE-06J CDPFa;* < [2.0E-06.. GREEN Potentially Risk Significant Region [5.OOE-06) S CDP;_.gi < (1.00E-05J 12.O0E-06 _sCDPmam, < [5.00E-06J YELLOW Risk Significant Region 11.00E-05J.<.CDP-w-,- 14.OOE-05J [5.OOE-06J < CDPhno- < [1.00E-05) ORANGE Highly Risk Significant Region [4.OOE-051 I CDP--,* [1.00E-051 I CPknam RED I!

RIISMkBiWp. lO 14

U m

EE 2.3.3 Allowable annual risk lmits for all Modes: ii Risk Significance Region Allowable Outage Core Damage

~Probhability, CDPm- -*

Na,-R1sk-Sigrnlncant Region CDP- < [2.00E.5J Potentially Risk Signi*icant Region [2.00E.05J < CDP. " [5.00E-05J Risk Signiicant Region [5.00E-05J < CDP-.m < [1,00E-04J Highly Risk Significant Region [1 .00E-041 I CDP....

SPlant-speclic values (inb*tcft,[ )to be approved by t*e NRC (Note: Mode transi*is dsk Issubtmed within these lmits.).

2.4 Actions 2.4.1 Green. Polow 'x~flannemopraing and business5 practices 2.4.2 Yellow. The Control Room StW SHALL take the following actlons 2.4.2-1 Notify the Duty Operations and Duty Plant Manage 2.42.2 that the Potentially Risk SgnFiatRegilon has been Identify and Implement compensatory measures as approved entered.'

by the Duty PlaRt Manager. Compensatory measures Ide but are NOT limited to the following may 24.2.21 Reduce the duraton of risk sensitive activitles.

2.4.2.22 Remove risk senstv activities from the planned 2.4.2.23 work scope.

Reschedule work actities to avoid high dsk sensitive equipment outages, or menitenance 24.2.3 Ensure any measures taken to reduce risk are states.

recorded In the Contro Room Logbook.

2.4.3 Orange

Perform Action B and Immediately make notification to NRC.

2.4.4 Red~Perform Action C and transition to a Plan Mode that reduces the overal risk I

In RIDS LMSq) pp Side 15

Initiative 1- Endstate Level of Justification

Determination of Appropriate Endstates Identified as the First "Short Term Success" Initiative at the Initial Meeting in December 1998

"* It was Generally Agreed that it was Intuitively Obvious that Hot Shutdown was a Safer Endstate than Cold Shutdown

"* SONGS Evaluations Confirmed the Intuitively Obvious Endstate Conclusion

"* TSTF Justification will Summarize the Results of these Evaluations to Provide a Basis for the Change

"* Other OGs Intend to Compare their Plants to the SONGS Evaluations and Discuss Significant Differences

"* Do not Intend to Perform Similar SONGS Quantitative Evaluations

"* Determination of Appropriate Endstates Should not Require Quantitative Risk Analyses

I "LU,' .

Initiative 3 LCO 3.0.4 Mode Restraint Flexibility LT 9,1 Example CE Plant

Summary of Technical Specifications Current TS Allows entry into the Mode of Applicability only if associated Actions permit continued operations for an unlimited period of time.

-4.9 Proposed Change In addition to current provision, allows entry into the Mode of Applicability based on appropriate Management Review and Approval (and relying on the associated Actions].

Example

\.>

( er" S - & 4~ .

Cycle 8 Containment Spray Pump SContainment Spray LCO Applicability- Modes 1, 2, and 3.

, Rewuired Completion Time is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for 1 Pumps S* Repair was for seal leakage Repair was begun Mode 4 coming out of the outage.

Example (continuedi

1.,,1' .

Cycle 8 Containment Spray Pump

"* Difficulties with the repair resulted in an 87 hour0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months critical path extension.

"* Major difficulties were encountered in the hi>-* beginning of the repair.

i10.

S :,.*.'**

Example (continued)

Risk Impact

Delta CDF for 1spray pump out in Mode3 is lE.OD.

Delta LERF for 1spray pump out in Mode 3 is 1E-08.

Compared to Regulatory Guide 1.177 or 1.174 Criterion change would he acceptable.

4 Example (continued]

SrPolentiale Cost Savings 1'

While the entire critical Path extension could not have been averted bythe proposed TS change, it is believed that once there was a high confidence that the repair-would be completed well within the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time (e.g., 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ), the proposed TS could 4

have saved critical path, 4

. Example SPole Otial COSt SavingS (continued]

i*Us ing $1million/day for lost revenues.

hours of critical path savings, a>

million dollars.

N*8

STAT!JISRITSTF INITIATIYES 4,5,6and7 (m *

.ril ?.I VE ITIATIVE 4 INITIATIVE 4A

- RISK INFORMED FLOATING AOTS WITH ABACKSTOP IiIN OGS ACTIVELY DEVELOPING

>j~ -

- TSTF INLATE 2000 INITIATIVE 4B

- RISK INFORMED AOTS

-TSTF PURSUING SELECTED AOTS INPARALLEL

- INDIVIDUAL OGs HAVE PROGRAMS ADDRESSING SELECTED AOTS

- RITSTF WILL COORDINATE TO SUPPORT GENERIC APPLICATION

- ONGOING THROUGH 2000

STATUS RITSTF 4,5, 6 and 7 (CONTINUED) INITIATIVES i

INITIATIVE 5

"*INITIATIVE 5A "1>

- RELOCATE SURVEILLANCE REQUIREMENTS (SRS) THAT DO NOT DEMONSTRATE OPERABILITY OF SAFETY FUNCTIONS

- TSTFIRITSTF DEVELOPING

- TSTF INLATE 2000

"*INITIATIVE 50,

- RELOCATE SURVEILLANCE TEST INTERVALS (STIs) TO LICENSEE CONTROLLED PROGRAM

- RITSTF DEVELOPING

- TSTFI N2001

STATUS RITSTF INITIATIVES 4,5,6and7 S-INITIATIVE 6 EXTEND TIME UPON ENTRY INTO LCo 3.o.3 TO INITIATE AND DEVELOP RISK INFORMED COURSE OF ACTION tiI~ -INITIALLY SCOPE WAS TO CHANGE CURRENT LCO 3.0.3 ONE HOUR TO 24 HOURS

- INITIAL EVALUATIONS DID NOT SUPPORT CHANGING ALL SPECIFICATION ENTRIES INTO LCO 3.0.3 TO 24 HOURS

4 p

STATUS RITSTF INITIATIVES A.

4,5,6and7 SINITI'ATIVE 6 (CONTINUEDI)

EXPANDED SCOPE OF INITI ATIVE 6 HAS 3 EFFORTS

- LCO 3.0.3 ONE HOUR TO 24' HOUR CHANGES

- ADDRESSING CONDITIONS IOF INDIVIDUAL SPECIFICATIONS WHICH D0RECT ENTRY INTO LCO 3.0.3 TO PROVIDE ACOMPLETION TIME INTHE INDIVIDUAL SPECIFICATION

STATUS RITSTI INITIATIVES Ind 7 l INITIATIVE 0 (CONTINUE PROVIDING CONDITIONS, REQUIRED ACTIONS AND COMPLETION TIMES FOR1 FHOSE INDIVIDUAL SPECIFICATIONS WHERE IHONE EXIST REQUIRING ENTRY INTO ICO 3.0.3

-PRA EFFORT ONGOING

-TSTF IN2000 w " < ;i, "

STATUS RITSTF INITIATIVES 4,5,6and7 b.

INITIATIVE 7

° DEVELOP ACTIONS. FOR EQUIPMENT THAT IS INOPERABLE BUT FUNCTIONAL

- EVALUATING MAINTENANCE RULE aA AND AVAILABLE

- TSTF INLATE 2000

0 Westinghouse Box 355 Electric Company LLC Pittsburgh Pennsylvania 15230-0355 NSBU-NRC-99-5958 U. S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20555 Attention: Mr. Theodore R. Quay, Chief Quality Assurance, Vendor Inspection Maintenance & Allegations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation

Subject:

Westinghouse Electric Company Reorganization

Reference:

1. Westinghouse Electric Company Letter, ESQ-99-0310, dated March 23, 1999 from H. A. Sepp

2. Westinghouse Electric Company Letter, NSD-NRC-99-5836, dated June 18,1999 from J. S. Galembush.

Dear Mr. Quay:

Reference 1 provided formal notification of the closing of the sale of the former CBS Corporation nuclear and government services businesses to Morrison Knudsen Corporation and British Nuclear Fuels plc on March 22, 1999. The Westinghouse Electric Company was created to operate the former CBS commercial nuclear business.

Figure 1 of the Westinghouse Quality Management System, Revision 3 (reference 2) described the Westinghouse organizations that meet QMS commitments. Effective October 1, 1999, the Westinghouse Electric Company organization was simplified to provide clear lines of responsibility and accountability, revising the organizational structure. None of these organizational changes will reduce or change the commitments of the Westinghouse Quality Management System (QMS).

The operational organizations in the new structure include the prior operational organizations and as well as service and engineering functions from the International Operations support organization. A Global Utility Sales support organization has been created that includes an order entry function. The attached figure illustrates the current Westinghouse organizations that meet the QMS commitments.

0372s.doc

NSBU-NRC-99-5958 December 15, 1999 Page 2 The Nuclear Fuel Business Unit (NFBU) now consists of U.S. Operations (the former Commercial Nuclear Fuel Division) and UK Operations (former British Nuclear Fuels Fuel Business Group). The QMS will apply to NFBU's U.S. Operations only.

If there are any questions, please contact John Papai at (412) 374-2434.

Very truly yours, H. A4 d er Regulatory & Licensing Engineering Attachment 0372s.doc

Attachment to NSBU-NRC-99-5958 Support Organizations Global Utility Sales Finance Operational Organizations Nuclear Fuel Business Unit (U.S. Operations)

Westinghouse I

CEO and President Nuclear Projects Business Unit I

Nuclear Services Business Unit Research and Technology Unit Westinghouse Organizations That Meet QMS Commitments

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