Text

Revision to Emergency Plan Implementing Procedures
	ML032320016
Person / Time
Site:	Ginna
Issue date:	08/08/2003
From:	Watts R; Rochester Gas & Electric Corp
To:	Clark R; Document Control Desk, NRC/NRR/DLPM/LPD1
References
	Download: ML032320016 (71)
	v • d • e

RE { I An Energy East Company ROCHESTER GAS AND ELECTRIC CORPORATION

89 EASTAVENUE, ROCHESTER, N.Y 14649-0001

585 546-2700 wwwrge.com August 8, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Robert Clark (Mail Stop 0-8-E9)

Project Directorate 1-1

Subject:

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

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

We have determined, per the requirements of 10 CFR 50.54(q), that the procedure changes do not decrease the effectiveness of our Nuclear Emergency Response Plan.

Very truly yours, Richard J. Watts Manager, Nuclear Training Department Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)

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

RG&E Nuclear Safety and Licensing (1 copy of letter)

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

RJW/jtw A

August 8, 2003 Page 2 of 2 PROCEDURE REVISION NUMBER EPIP 1-9 25 EPIP 2-1 21 EPIP 2-4 15 EPIP 3-1 23 EPIP 3-3 10 EPIP 4-1 7 EPIP 4-3 13

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 13 PROCEDURE NO. EPIP 1-9 REV. NO. 25 TECHNICAL SUPPORT CENTER ACTIVATION RES&ONSIBLE MA ER EFFE TIV DATE CATEGORY 1.0 THIS PROCEDURE CONTAINS 9 PAGES

EPIP 1-9:2 EPIP 1-9 TECHNICAL SUPPORT CENTER ACTIVATION

1.0 PURPOSE

The purpose of this procedure is to designate actions and responsibility of individuals who would report to the Technical Support Center upon a decision to activate at an Alert level or greater.

2.0 RESPONSIBILITY

2.1 The first qualified person to arrive is responsible for initiating this procedure.

2.2 The TSC Director is responsible for activation of the TSC upon arrival.

2.3 The TSC Director becomes the TSC Emergency Coordinator upon assuming Command and Control.

2.4 If the Severe Accident Management Guidelines (SAMG's) are entered, the following TSC staff assume SAM duties:

Decision Maker - TSC Emergency Coordinator Evaluators - TSC Operations Manager, TSC Technical Manager, TSC Nuclear Assessment

3.0 REFERENCES

3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

3.2 Implementing References 3.2.1 EPIP 1-10, OSC Activation 3.2.2 EPIP 1-11, Survey Center Activation 3.2.3 EPIP 3-3, Immediate Entry 3.2.4 EPIP 1-5, Notification 3.2.5 EPIP 5-7, Emergency Organization 3.2.6 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.7 EPIP 2-13, Iodine and Particulate Activity Determination from Air Samples 3.2.8 RP-JC-AMS4, Routine Operation of the Eberline AMS-4 Air Monitoring System

EPIP 1-9:3

4.0 PRECAUTIONS

As noted in this procedure.

5.0 PREREQUISITES

5.1 An Alert, Site Area Emergency, or General Emergency has been declared in accordance with EPIP 1-0, Ginna Station Event Evaluation and Classification.

5.2 The TSC could be activated anytime at the discretion of the TSC Director/Emergency Coordinator.

6.0 ACTIONS

6.1 Personnel Responding from Offsite 6.1.1 Personnel shall report to the TSC using normal security site access procedures.

6.1.2 If a hazardous condition prevents normal site access (e.g., release of radioactivity, security event, HAZMAT), responders may be directed by Community Alert Network to report to the designated staging area (Ontario Fire Department Exempt Hall, located on Route 104 between Route 350 and Knickbocker Road) or, upon arrival to the site, informed by Security to report to the Survey Center or designated location. Refer to EPIP 3-3, Immediate Entry, for site access.

6.2 Personnel Arriving at TSC CAUTION FRISK BEFORE ENTERING IF RP DETERMINES THAT FRISKING IS REQUIRED.

NOTE: DEPENDING ON THE NUMBER OF ARRIVING PERSONNEL, PERFORM STEPS CONCURRENTLY TO MINIMIZE ACTIVATION TIME.

6.2.1 Place your name under appropriate emergency position on magnetic organization chart and display associated job function badge.

6.2.2 If you leave the TSC, contact the RP/Chemistry Manager to determine if an electronic dosimeter is required.

6.2.3 Perform responsibilities as described in EPIP 5-7, Emergency Organization.

6.3 TSC Director perform the following:

6.3.1 Ensure minimum staff listed below is available to activate the TSC:

a. Emergency Coordinator

EPIP 1-9:4

b. Radiation Protection/Chemistry Manager

c. Dose Assessment Manager

d. Technical Assessment Manager

e. Operations Assessment Manager

f. Maintenance Assessment Manager

g. Communicator

h. Survey Center Manager 6.3.2 If position is not staffed, notify personnel to report to the assigned duty location.

Qualified responders are found in their position checklist in EPIP 5-7. The status of the call-in process can be monitored by obtaining a report from the incoming fax machine at 30 minutes into the event.

6.3.3 Ensure Technical Assessment Manager establishes ERDS link to NRC within one hour per duties in EPIP 5-7.

6.3.4 Receive briefing from the Shift Supervisor on Plant conditions.

6.3.5 Obtain notification forms sent by the Control Room from the TSC fax machine.

Use these forms and brief response staff on plant conditions using Attachment 2 (TSC meeting agenda).

CAUTION IF DOSE RATES EXCEEDS 50 mR/HR, CONSIDER RELOCATION OF TSC PERSONNEL.

IF AIR SAMPLE RADIOIODINE ACTIVITY IS GREATER THAN 1E-8 yCVcc, CONSIDER RELOCATION OF TSC PERSONNEL.

6.3.6. Obtain results of radiation survey and air activity of TSC.

6.3.7 If TSC is uninhabitable, relocate the following personnel to the Shift Supervisor's office:

a. Operations Assessment Manager

b. Radiation Protection/Chemistry Manager

c. TSC Director/Emergency Coordinator

d. Technical Manager

e. Nuclear Assessment

EPIP 1-9:5 Direct remaining personnel to the Survey Center or alternate location as directed by the TSC Director/Emergency Coordinator.

6.3.8 Obtain status of manpower from managers.

NOTE: THE TSC DIRECTOR ASSUMES THE ROLE AND TITLE OF TSC EMERGENCY COORDINATOR WHEN TSC TAKES COMMAND AND CONTROL.

6.3.9 Assuming Command and Control 6.3.9.1 Ensure minimum activation staff (Step 6.3.1) is available to assume command and control.

6.3.9.2 Confer with Emergency Coordinator (Control Room Shift Supervisor) on shifting command and control of the emergency from the Control Room to the TSC.

Normally, when command and control is transferred, the TSC assumes:

a. Overall direction for the emergency

1. Emergency Classification

2. Protective Action Recommendations

b. Notifications to New York State, Wayne and Monroe counties

c. Dose Assessment

d. Notifications to the NRC However, certain conditions may warrant transferring a given responsibility area (or communications) at different times, per the discretion of the Emergency Coordinator (Shift Supervisor and TSC Director).

6.3.9.3 Brief the TSC on plant status using Attachment 2 for meeting agenda and inform them that command and control will be assumed at the agreed upon time.

6.3.9.4 At agreed upon time, call the Control Room (Emergency Coordinator) and state that, unless he has any objections, the TSC is assuming command and control at this time.

6.3.9.5 Announce to the TSC that the TSC has assumed command and control of the emergency.

EPIP 1-9:6 6.3.9.6 Upon assuming command and control, direct the Administrative/Communications Manager to provide RECS line updates every 30 minutes using EPIP 1-5, Attachment 3.

6.3.9.7 Notify EOF that the TSC has assumed command and control and to make preparations to transfer command and control to the EOF.

6.3.9.8 Conduct PORC meetings as required to support emergency operations. PORC meeting minutes are stored under S:\Forums\Forums\PORC\PORC minutes then choose year of interest.

6.3.9.9 If the TSC will be activated for more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , direct managers to complete Attachment 1 for continuous staffing.

6.3.10 Shift Turnover 6.3.10.1 If a turnover to another shift is needed, contact the personnel identified on Attachment 1 and inform them of the time and location to assemble.

6.3.10.2 When the responders for the next shift have arrived, have them perform a detailed turnover with the person they are relieving. Have them log the turnover in their log book.

6.3.10.3 When the individual turnovers are complete, have the on-coming crew perform a briefing for each other using the standard meeting agenda (Attachment 2). The off-going crew should also be at the briefing to ensure that the information that is shared is correct and complete.

6.4 TSC Managers perform the following:

6.4.1 Check communications at work location.

6.4.2 Determine status of manpower and report to the Emergency Coordinator.

6.4.3 Radiation Protection/Chemistry Manager check survey results and air activity for TSC and report to TSC Director/Emergency Coordinator.

CAUTION IF AIR SAMPLE RADIOIODINE ACTIVITY IS GREATER THAN 1E-8 pCI/cc, INFORM THE EMERGENCY COORDINATOR.

IF DOSE RATES EXCEEDS 50 mR/HR, CONSIDER RELOCATION OF TSC PERSONNEL.

6.4.3.1 If TSC is uninhabitable, the following personnel shall relocate to the Shift Supervisor's office:

a. Operations Assessment Manager

b. Radiation Protection/Chemistry Manager

EPIP 1-9:7

c. TSC Director/TSC Emergency Coordinator

d. Technical Manager

e. Nuclear Assessment 6.4.3.2 Direct remaining personnel to the Survey Center or other locations as directed by the Emergency Coordinator.

6.5 Radiation Protection Technician perform the following:

6.5.1 Place step-off pad and frisker at each entrance to the TSC.

6.5.2 Start up TSC AMS-4 per RP-JC-AMS4.

CAUTION IF AIR SAMPLE RADIOIODINE ACTIVITY IS GREATER THAN 1E-8 pCIcc, INFORM THE RADIATION PROTECTIONICHEMISTRY MANAGER AND THE EMERGENCY COORDINATOR.

6.5.3 Take an air sample in accordance with EPIP 2-13, Iodine and Particulate Activity Determination from Air Samples, and report results to Radiation Protection/Chemistry Manager.

6.5.4 Perform a survey of the TSC.

CAUTION IF DOSE RATES EXCEEDS 50 mR/HR, INFORM THE RADIATION PROTECTION/CHEMISTRY MANAGER AND EMERGENCY COORDINATOR.

6.5.5 Report results of all TSC surveys to Radiation Protection/Chemistry Manager 6.5.6. Monitor the TSC radiation and contamination levels and air activity at the discretion of the Radiation Protection/Chemistry Manager.

6.6 TSC Support Personnel 6.6.1 Perform job functions in accordance with EPIP 5-7, Emergency Organization.

7.0 Attachments

1. TSC Continuous Staffing Schedule

2. TSC Meeting Agenda

EPIP 1-9:8 Attachment 1, Rev. 25 Page 1 of 2 TSC CONTiNUOUS STAFFING SCHEDULE (Consult EPIP 5-7 position checklists for qualified personnel and phone numbers to fill positions.)

Shift A Shift B hrs. hrs.

to _ hrs. to _ _ hrs.

POSITION Date: Date:

Emergency Coordinator*

Assistant Emergency Coordinator Radiation Protection/Chemistry*

Manager Dose Assessment Manager*

Technical Assessment Manager*

Operations Assessment Manager*

Maintenance Assessment Manager*

Communicator*

Survey Center Manager*

Admin./Comm. Manager Security Manager TSC Survey Team Coordinator Dose Assessment Support Messenger/Status Board Keepers Note: All positions need not be filled. Select those

Minimum staff needed as a resources for the event and the minimum staff required for TSC activation.

EPIP 1-9:9 Attachment 1, Rev. 25 Page 2 of 2 TSC CONTINUOUS STAFFING SCHEDULE (Consult EPIP 5-7 position checklists for qualified personnel and phone numbers to fill positions.)

Shift A I Shift B

_________hrs. hrs.

to hrs. to _ _ hrs.

POSITION Date: Date:

RP/Chemistry Technicians Nuclear Assessment I&C Electrical Assessment Mechanical/Hydraulic Assessment Computer Analysts Discipline Planners Manager of OSC Satellite Maintenance Personnel Assistant Survey Center Manager OSC Assignees Inventory Control Supervisor/Analyst Inventory Control Support Personnel OSC Director Note: All positions need not be filled. Select those

Minimum staff needed as a resources for the event and the minimum staff required for TSC activation.

EPIP 1-9:10 , Rev. 25 Page 1 of 1 Meeting Date: Time:

NOTE: IF THE EOF IS ACTIVATED OR ACTIVATING, ATTEMPT TO INCLUDE NUCLEAR OPERATIONS MANAGER, OR AN ASSISTANT, IN THE TSC BRIEFING VIA CONFERENCE CALL.

1. Emergency Coordinator

Purpose of Meeting

Classification Level

Time Classification Declared

Brief Event Description (use EAL reference manual)

Injury/Fire Status

2. Operations Assessment Manager

Plant activities in progress

Safety Related Equipment Status

Operational needs required for plant safety

Operational manpower needs

3. Technical Assessment Manager

Status of Plant Conditions

Core Conditions

Core Cooling capabilities

4. Maintenance Assessment Manager

Equipment out of service

Status of repairs in progress

Manpower needs required to support Maintenance

Supplies and Materials needed to support Maintenance activities

5. Dose Assessment Manager

Offsite areas of concern (downwind areas affected)

Protective Actions Recommended

Releases in progress

Status of radiological conditions outside the plant fence

Brief status of Survey Team activity

6. Administrative/Communications Manager

Status of notifications to State and Counties

Status of notifications to NRC

7. Security Manager

Status of accountability of plant personnel

Status of Site Security

Status of search and rescue operations

8. RP/Chemistry Manager

Status of TSC habitability

Status of radiological concerns inside the plant fence

Status of PASS operation and availability

Status of exposure to plant personnel (Ops, Maintenance, RP)

9. EOF Concerns

10. Review of Open Items Please write on these pages. New pages will be provided after each use.

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 23 PROCEDURE NO. EPIP 2-1 REV. NO. 21 PROTECTIVE ACTION RECOMMENDATIONS TECHNICAL REVIEW EFFE VE ATE CATEGORY 1.0 THIS PROCEDURE CONTAINS 15 PAGES

EPIP 2-1:1 EPIP 2-1 PROTECTIVE ACTION RECOMMENDATIONS

1.0 PURPOSE

1.1 The purpose of this procedure is to provide guidance to the Emergency Coordinator or EOF/Recovery Manager in making protective action recom-mendations to offsite authorities.

2.0 RESPONSIBILITY

2.1 The Shift Supervisor, Emergency Coordinator (TSC) or EOF/Recovery Manager is responsible for making protective action recommendations to Wayne County, Monroe County and New York State, depending on command and control status.

2.2 The decision to implement any protective actions is solely the responsibility of the local authorities.

3.0 REFERENCES

3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 EPA-400, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (1991) 3.1.3 Evacuation Travel Time Estimates - Ginna Emergency Planning Zone, September 1992.

3.1.4 NUREG/BR - 0150 Response Technical Manual (RTM-93) 3.1.5 Food and Drug Administration (FDA) 'Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies", December 2001.

3.1.6 NUREG-1633, "Assessment of the Use of Potassium Iodide (KI) as a Supplemental Public Protective Action During Severe Reactor Accidents".

3.1.7 NRC RIS 2003-12 "Clarification of NRC Guidance for Modifying Protective Actions" 3.2 Implementing References 3.2.1 EPIP 1-0, Ginna Station Event Evaluation and Classification

EPIP 2-1:2 3.2.2 EPIP 1-5, Notification 3.2.3 EPIP 2-3, Emergency Release Rate Determination 3.2.4 EPIP 2-4, Emergency Dose Projections - Manual Method 3.2.5 EPIP 2-18, Control Room Dose Assessment 3.2.6 EPIP 2-5, Emergency Dose Projections - Personal Computer Method 3.2.7 EPIP 2-6, Emergency Dose Projections - MIDAS Program

4.0 PRECAUTIONS

None

5.0 PREREQUISITES

None.

6.0 INSTRUCTIONS

NOTE: PROTECTIVE ACTION RECOMMENDATIONS (PARs) WILL ONLY REFLECT RG&E RECOMMENDATIONS, NOT ACTIONS IMPLEMENTED BY OFFSITE OFFICIALS.

6.1 Obtain the event classification using EPIP 1-0.

6.2 UNUSUAL EVENT. ALERT and SITE AREA EMERGENCY.

6.2.1 Report on EPIP 1-5, Attachment 3a, Item 7:

A. No need for protective actions outside the site boundary.

6.3 GENERAL EMERGENCY 6.3.1 Protective Action Recommendations shall be issued with the initial declaration of a General Emergency.

6.3.2 Using Attachment 1, Page 1 of 2, and the current wind direction, determine the initial ERPAs to be evacuated. The Counties will implement their KI plans for any evacuated ERPA. Any ERPA not evacuated will be sheltered.

6.3.3 Record in EPIP 1-5, Attachment 3a, Item 7 the Protective Actions Recommended.

EPIP 2-1:3 NOTE: ONCE AN ERPA HAS BEEN RECOMMENDED TO EVACUATE, THAT RECOMMENDATION WILL CONTINUE. AN ERPA PAR STATUS CANNOT BE CHANGED FROM "EVACUATE" TO "SHELTER".

6.3.4 Re-evaluate the PARs based on the following to determine if secondary PARs are required or if initial PARs need to be modified.:

a. Dose Assessment*

b.' Survey Team data*

c. EPA Protective Action Guidelines (Attachment 2)

d. Wind shifts

= If exposures in non-evacuated areas indicate that evacuation is warranted, use Attachment 1 page 2 of 2 to expand Protective Action Recommendations to an evacuated area of 5 mile radius and 10 miles downwind.

6.3.5 The Evacuation Travel Time Estimate information (Attachment 3) is used by offsite agencies to determine the correct Protective Action Decision (PAD).

6.3.6 If the EPA guidelines for evacuation or sheltering are exceeded beyond the 10 mile emergency planning zone and protective actions are required, specify the areas using roads, rivers, bodies of water or town boundaries.

7.0 ATTACHMENTS

1. Evacuation Areas by Zones.

2. Projected Dose to the Population and Recommended Actions.

3. Evacuation Travel Time Estimates.

4. Emergency Response Planning Areas (ERPA's).

EPIP 2-1:4 Attachment 1, Rev. 21 Page 1 of 2 EVACUATION AREAS BY ZONES PROTECTIVE ACTION RECOMMENDATIONS BY ERPA FOR GENERAL EMERGENCY CLASSIFICATION Wind From (Degrees) Initial Protective Action Recommendations (Evacuation based on 2 mile radius & 5 miles downwind)

N 349 to 11 Evacuate: W (1,2,3) and implement KI plan Shelter: All remaining ERPAs NNE 12 to 33 Evacuate: W (1.2) M (1) and implement Ki plan Shelter: All remaining ERPAs NE 34 to 56 Evacuate: W (1,2) M (1) and implement Ki plan Shelter: All remaining ERPAs ENE 57 to 78 Evacuate: W (1,2) M (1) and implement KI plan

____________________________ Shelter: All remaining ERPAs E 79 to 101 Evacuate: W (1,2) M (1) and implement KI plan Shelter: All remaining ERPAs ESE 102 to 124 Evacuate: W (1) M (1) and implement Ki plan Shelter: All remaining ERPAs SE 125 to 146 Evacuate: W (1) and implement KI plan Shelter. All remaining ERPAs SSE 147 to 168 Evacuate: W (1) and implement KI plan Sheiter All remaining ERPAs S 169 to 191 Evacuate: W (1) and implement KI plan Shelter All remaining ERPAs SSW 192 to 213 Evacuate: W (1) and implement KI plan Shelter All remaining ERPAs SW 214 to 236 Evacuate: W (1,3) and implement Ki plan Shelter: All remaining ERPAs WSW 237 to 258 Evacuate: W (1,3) and implement Ki plan Shelter: All remaining ERPAs W 259 to 281 Evacuate: W (1,3) and implement Ki plan Shelter: All remaining ERPAs WNW 282 to 303 Evacuate: W (1,2,3) and implement Ki plan Shelter: All remaining ERPAs NW 304 to 326 Evacuate: W (1,2,3) and implement KI plan Shelter: All remaining ERPAs NNW 327 to 348 Evacuate: W (1,2,3) and implement Ki plan Shelter: All remaining ERPAs

C (

EVACUATION AREAS BY ZONES

,' 2-1:5 Attachment 1, Rev, 20 PROTECTIVE ACTION RECOMMENDATIONS BY ERPA FOR Page 2 of 2 GENERAL FMERGENCOY Ci ASIFICATION Wind From (Degrees) Initial Protective Action Recommendations Secondary Protective Action Recommendations (Evacuation based on 2 mile radius & 5 miles downwind) (Evacuation based on 5 mile radius & 10 miles downwind)

N 349 to 11 Evacuate: W (1, 2,3) and implement KI plan Evacuate: W (1, 2, 3, 5, 6, 7) M (1, 2, 4, 5) and implement KI plan Shelter All remaining ERPAs Shelter All remaining ERPAs NNE 12 to 33 Evacuate: W (1, 2) M (1) and implement KI plan Evacuate: W (1, 2, 3, 6, 7) M (1, 2, 3, 4, 5, 6, 7, 9) and implement KI plan Shelter. All remaining ERPAs Shelter All remaining ERPAs NE 34 to 56 Evacuate: W (1, 2) M (1) and Implement KI plan Evacuate: W (1, 2, 3, 7) M (1, 2, 3, 4, 5, 6, 7, 8, 9) and implement KI plan Shelter All remaining ERPAs Shelter All remaining ERPAs ENE 57 to 78 Evacuate: W (1, 2) M (1) and implement KI plan Evacuate: W (1, 2,3, 7) M (1, 2, 3, 4, 5, 6, 7, 8, 9) and implement KI plan Shelter. All remaining ERPAs Shelter. All remaining ERPAs E 79 to 101 Evacuate: W (1, 2) M (1) and implement KI plan Evacuate: W (1, 2,3) M (1. 2, 3, 4, 6, 7, 8, 9) and implement KI plan Shelter AN remaining ERPAs Shelter All remaining ERPAs ESE 102 to 124 Evacuate: W (1) M (1 and Implement KI plan Evacuate: W (1, 2, 3) M (1, 3, 6, 8, 9) and implement KI plan Shelter All remaining ERPAs Shelter. All remaining ERPAs SE 125 to 146 Evacuate: W (1) and Implement KI plan Evacuate: W (1, 2, 3) M (1) and implement KI plan Shelter. All remaining ERPAs Shelter All remaining ERPAs SSE 147 to 168 Evacuate: W (1) and implement KI plan Evacuate: W (1, 2,3) M (1) and implement KI plan Shelter. All remaining ERPAs Shelter: All remaining ERPAs S 169 to 191 Evacuate: W (1) and implement KI plan Evacuate: W (1, 2, 3) M (1) and implement Ki plan Shelter. All remaining ERPAs Shelter. All remaining ERPAs SSW 192 to 213 Evacuate W (1) and implement KI plan Evacuate: W (1, 2,3) M (1) and Implement KI plan Shelter: All remaining ERPAs Shelter. All remaining ERPAs SW 214 to 236 Evacuate: W (1, 3) and implement KI plan Evacuate: W (1, 2,3,4) M (1) and implement KI plan Shelter: All remaining ERPAs Shelter: All remaining ERPAs WSW 237 to 258 Evacuate: W (1, 3) and implement KI plan Evacuate: W (1, 2,3,4,5) M (1) and implement Ki plan Shelter: All remaining ERPAs Shelter: All remaining ERPAs W 259to 281 Evacuate: W (1, 3) and implement KI plan Evacuate: W (1, 2, 3, 4, 5, 6) M (1) and Implement KI plan Shelter: All remaining ERPAs Shelter All remaining ERPAs WNW 282 to 303 Evacuate: W (1, 2,3) and implement KI plan Evacuate: W (1, 2, 3, 4, 5, 6, 7) M (1) and Implement KI plan Shelter: All remaining ERPAs Shelter. All remaining ERPAs NW 304 tO 326 Evacuate: W (1, 2, 3) and implement KI plan Evacuate: W (1, 2, 3, 4, 5, 6, 7) M (1, 2) and implement KI plan Shelter An remaining ERPAs Shelter: All remaining ERPAs NNW 327 to 348 Evacuate: W (1, 2,3) and implement KI plan Evacuate: W (1, 2, 3, 4, 5, 6, 7) M (1, 2, 5) and implement Kl plan

Secondary Protective Actions are recommended when dose projections or field teams indicate 2 1 REM TEDE beyond 5 miles.

( E. 2-1:6 Attachment 2, Rev, 20 Page 1 of 1 PROJECTED DOSE TO THE POPULATION AND RECOMMENDED ACTIONS PROJECTED DOSE TO THE RECOMMENDED ACTIONS COMMENTS POPULATION l Total Whole Body < 1 REM* No planned protective actions. Local authorities None.

or State may issue an advisory to seek shelter and await further instructions. Monitor environmental radiation levels.

Total Whole Body 2 1 REM* Conduct evacuation.* Evacuation (or for some situation, Monitor environmental radiation levels and sheltering**) should be initiated at one Committed Dose Equivalent to the thyroid adjust area for mandatory evacuation based on REM. Seeking shelter would be an (child) 2 5 REM. these levels. alternative if evacuation were not Control access. immediately possible.

Implement KI plan.

Project Dose (REM) to Emergency Team Workers Total Whole Body 25 REM Control exposure of emergency team members None.

to these levels except for lifesaving mission.

(Appropriate controls for emergency workers include time limitations, respirators and stable iodine.)

Total Whole Body 75 REM Control exposure of emergency team members None.

performing lifesaving missions to this level.

(Control of time of exposure will be most effective.)

NOTES:

The sum of the effective dose equivalent resulting from exposure to external sources and the committed effective dose equivalent incurred from all significant inhalation pathways during the early phase.

- Sheltering may be the preferred protective action when it will provide protection equal to or greater than evacuation, based on consideration of factors such as source term characteristics and temporal or other site-specific conditions.

EPIP 2-1:7 Attachment 3, Rev. 21 Page 1 of 8 EVACUATION TRAVEL TIME ESTIMATES

1. When discussing an evacuation, use this attachment to resolve conflicts.

2. 1992 Permanent Resident Population Estimates EPRA Population ERPA Population W-1 3207 M-1 2421 W-2 5395 M-2 435 W-3 1200 M-3 258 W-4 2092 M-4 6681 W-5 3855 M-5 1253 W-6 2425 M-6 6943 W-7 4924 M-7 4750 M-8 3033 M-9 3285

3. Use the following curves to assist in estimating evacuation decisions.

Figure Weather Conditions Time of Week 41 Summer, Good Weather Midweek, Midday 43 Summer, Rainy Weather Midweek, Midday 45 Summer, Good Weather Midweek, Evening 49 Summer, Good Weather Weekend, Midday 53 Winter, Good Weather Midweek, Midday 55 Winter, Rainy Weather Midweek, Midday 57 Winter, Snowy Weather Midweek, Midday

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FIGURE 41 Evacuation Travel time Estimates GInna Nuclear Power Station Summer, Midweek, Midday Good Weather 100 N

a. g0 80 a'

70

'C 5 60 C

50 4'

0.

40 0

a.

30 0

0 20 1!

0 a.1 10 0

0 1 2 3 CD~ m 4 5 0<

Time - Hours

-WAYNE CO. MONROE CO. '- FULL EPZ *bb

( f

1. .

FIGURE 43 Evacuation Travel Time Estimates Ginna Nuclear Power Station Sunnner, Midweek, Midday Rainy Weather 100 I I I I a A I I I I I I I I- I f .a I - I I I IU-. I . -

N 90 I1 I M

s0 e 70 -I Lj 0

C 60 so a-LT 50 Vt'-W a

a-tL 0.

U-'-4 -u a-40 a

30 H0-0 C 20 0hl TIM EPZ papubtin to be ec d dufin tt. scenb Is 59,577.

0. 10 -- - ~Th* tOW W"Mn Co"it popiAtk to bo evacute Is23.?M.

.n- _ _ _ _ - - - _ - The MM PMMro.___-- Ca"d popuiflon to be revacae Is 35.81bsl7 (D

0 I ! 2 3 4 5 6 7 (0 (D

lo M :5 Time - Hours C, (D ">

I

WAYNE CO. 0-- MONROE CO. - FULL EPZ

.1 I

-I CO 5

Nt

-A

\)

CD

l:

FIGURE 45 Evacuation Travel Time Estimates Ginna Nuclear Power Station Summer, Midweek, Evening Good Weather 100

.N

0. g0 wu 80 C

70

.C 60 00

.5 50 0.

40 a

0. 30 4-20

0. 0 10 0 -:3-~ m-a 0 1 2 3 4 (0 G

-u Time - Hours 0<

.* 1 I a WAYNE CO. Wo MONROE CO. ' FULL EPZ 0 I

( ,.

FIGURE 49 Evacuation Travel Time Estimates GInna Nuclear Power Station Summer, Weekend, Midday Good Weather 100 90 0

80 0'

70 C 60 0

rW 50 0

0.

40 0

CL 3C a.

20 10 0

0*

a 1 2 3 .4 5 6 -3.

Time - Hours I -- WAYNE CO. - - MONROE CO. ---- FULL EPZ -

-I

-I I

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FIGURE 53 Evacuation Travel Time Estimates Ginna Nuclear Power Station Winter, Midweek, Midday Good Weather 100 N

g0 0.

80 40 C" 70

.C 60 0

'U aC 50 40 0

30 0

20 C,

6I 10 0 6~~_

0 0 1 2 3 4 5 Time - Hours

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ROCHESTER GAS & ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER __3 PROCEDURE NO. EPIP 2-4 REV. NO. 14 EMERGENCY DOSE PROJECTIONS - MANUAL METHOD RESPONN6BLE'GER EFFEWTIV DATE Category 1.0 This procedure contains j16 pages

EPIP 2-4:1 EPIP 2-4 EMERGENCY DOSE PROJECTIONS - MANUAL METHOD 1.0 PURPOSE 1.1 The purpose of this procedure is to provide a manual method for performing projections of downwind doe rates and doses. Such information is needed to decided upon protective actions to be recommended to limit the exposure of the general public and emergency workers. This procedure is intended as a backup to EPIP 2-5.

2.0 RESPONSIBILITY The TSC or EOF Dose Assessment Manager is responsible for implementing this procedure.

3.0 REFERENCES

3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 EPA-400, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (1991) 3.1.3 Ginna UFSAR, Chapter 15 3.1.4 Regulatory Guide 1.109 3.2 Implementing References 3.2.1 EPIP 2-1, Protective Action Recommendations 3.2.2 EPIP 2-2, Obtaining Meteorological Data and Forecasts and their use is Emergency Dose Assessment 3.2.3 EPIP 2-3, Emergency Release Rate Determination 4.0 PRECAUTIONS None.

EPIP 2-4:2 5.0 PREREQUISITES 5.1 The following equipment and data sources are available for use in performing manual dose projections.

5.1.1 Xu/Q tabulated values (Attachment 2) 5.1.2 Wind and temperature indications from the Control Room 5.1.3 Plant Process Computer System (PPCS) - EVENT 2 Report 5.1.4 Control Room Radiation Monitor System (RMD) Panel read-outs of effluent monitors 5.1.5 Personal Computer in TSC and EOF (for obtaining 15 minute meteorological data average from Ginna Primary Weather Tower) 5.1.6 Back-up wind speed and direction indications at Station 13A (accessible from TSC or EOF IBM terminals) and National Weather Service.

6.0 ACTIONS 6.1 Preliminary Downwind Dose Estimates 6.1.1 For initial notifications purposes, a preliminary estimate of potential offsite doses and releases may be obtained by the Control Room using EPIP 2-18.

6.1.2 For calculations performed by the Control Room, TSC and EOF staffs,a 4-hour release duration should be used if the duration is not known. A 4-hour release duration is consistent with the value used by Wayne and Monroe Counties.

6.1.3 If iodine effluent monitor or isotopic data are unavailable, a default value of 1.E-4 should be used to reflect the estimated release concentration ratio of gross iodine to noble gas. (See Attachment 1)

NOTE: WHEN DATA IS AVAILABLE, CALCULATE AN IODINE-TO-NOBLE GAS RATIO THAT REFLECTS PRESENT CONDITIONS.

6.1.4 Determine the classification of the emergency with respect to plant releases and site boundary doses from the criteria provided in EPIP 1-0.

6.2 Use of Meteorological and Release Data with EPA Dose Factors Manual Method

EPIP 2-4:3 NOTE: ANY PRELIMINARY DOES ESTIMATES USED AS A BASIS FOR EMERGENCY CLASSIFICATION OR PROTECTIVE ACTION RECOMMENDATIONS SHOULD BE REFINED AS FOLLOWS USING RELEASE MEASUREMENTS AND ACTUAL METEOROLOGICAL SAMPLING DATA AS THEY BECOME AVAILABLE.

6.2.1 Meteorological Data (15 min. averages) can be obtained by modem from the MIDAS storage computer in the Meteorological Tower Trailer by using the Personal Computer. (See EPIP 2-2 for instructions.)

6.2.2 Determine Pasquill Stability Class (A-G), using Attachment 2, in this procedure.

6.2.3 Obtain concentration or particulate, noble gas or iodines and vent flow to determine release rate. Refer to EPIP 2-3 or refer to the listing of effluent monitor calibration factors provided in Attachment 6 to this procedure.

NOTE: Standard Release Rates*

Plant Vent = Normal = 77,854 cfm, Emergency = 71,289 cfm Containment = Normal and Emergency = 15,300 cfm Air Ejector = Normal and Emergency = 6.00E2

Verify values with Dose Assessment Manager 6.2.4 To calculate the downwind concentration of noble gas, particulates or radioiodine, multiply the release rate of radioactivity (Cisec) from the plant times the X/Q (sec/i 3) dispersion coefficient determined in Attachment 1. The resultant concentration will be pCicc. Perform these calculations on Attachment 1.

6.2.5 Obtain an initial release estimate of release duration from the TSC Emergency Coordinator or Recovery Manager. If this estimate is unavailable, use an initial release duration estimate of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for dose projection purposes.

6.2.6 Whole body gamma dose rate due to noble gas and radioiodine isotopes is estimated using Attachments 3 and 4 and using the listed factor corresponding to the approximate time after shutdown. Multiply this factor times the concentration calculated in Step 6.2.4 to get Rem/hour.

EPIP 2-4:4 6.2.7 Whole body gamma dose is obtained by multiplying the dose rate calculated in Step 6.2.6 times the integrated exposure determined in Step 6.2.5.

6.2.8 Thyroid dose rate to the child (actually, the thyroid dose commitment per hour of inhalation) is estimated using Attachment 5 and using the listed factor corresponding to the time after shutdown. Multiply this factor times the concentration calculated in Step 6.2.4 to get Rem/hour. Project dose rates are always determined for child thyroid as they are the most critical population group.

To determine the dose or dose rate for adults (which would only be necessary for emergency workers) divide the dose or dose rate for the child by 2.

6.2.9 Thyroid dose is found by multiplying the dose rate calculated in step 6.2.8 times the exposure time determined in step. 6.2.5.

6.3 Protective Action Recommendations 6.3.1 Recommend the appropriate measures for the general public in accordance with EPIP 2-1.

6.3.2 Weather forecast information should be considered when planning protective actions. Refer to EPIP 2-2 for instructions to obtain weather forecast information.

7.0 ATTACHMENTS

1. Dose Assessment Calculation

2. Pasquill Stability Class Criteria

3. Noble Gas Whole Body Dose Conversion Factors

4. Radioiodine Whole Body Dose Conversion Factors

5. Radioiodine Thyroid Dose Conversion Factors

6. RMS Process Monitor Calibration Factors

EPIP 2-4:5 Attachment 1, Rev. 14 Page 1 of 5 DOSE ASSESSMENT CALCULATION GENERAL INFORMATION:

Current Time:

Shutdown Time:

Release Start Time:

Release Vent: Plani I Vent Air Ejector ARV or Safety Containment Vent Other Stability Class: A B C D E F G able Neutral Stable Vent Flow (CFM):

See Step 6.2.3 for flow rates VENT CONCENTRATION FROM EFFLUENT MONITOR READING:

NOTE: Vent concentration can be Input directly from SPING monitors, If available.

Noble Gas (Monitor Number ):

cpm X _Ci/CC = pCVcc*

(count rate) (calib. factor) cpm (vent cond.)

Radlolodine (Montior Number :

hours (later counts) (initial counts) (time between readings) x pCicc (A cpm/hr from monitor) (calib. factor) (vent cond.)

Particulate (Monitor Number ):

cpm X WuCi=cc = IJCicC*

(count rate) (calib. factor) cpm (vent cond.)

Flowrate Conversion (Convert CFM to cclsec) (Step 6.2.3)

_ CFM X 2.8E4 cc/ft X 1 min/60 sec = cc/sec

EPIP 2-4:6 Attachment 1, Rev. 14 Page 2 of 5 NOBLE GAS:

To calculate release RATE in Ci/sec from monitors:

pCi/cc x cc/sec x 1E-6pCicc = C/sec NOTE: TO PREDICT DOWNWIND CONCENTRATION, OBTAIN FIRST VALUE FROM ATTACHMENT 2.

NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.

sec-mph x Ci/sec x 1/( ) mph = pCVcc at S.B. 500 meters m3 (windspeed) sec-mph x Cl/sec x 1/( ) mph = pC/cc at 2 miles m3 (windspeed) sec-mph x Ci/sec x 1/( ) mph = pCi/cc at 5 miles m3 (windspeed) sec-mph x Cl/sec x 1/( ) mph = pC/cc at 10 miles m3 (windspeed) sec-mph x Cl/sec x 1/( ) mph = pCi/cc at m3 (windspeed) (distance)

Hours after shutdown Rem/hr. per pCi/cc (Attachment 3):

Distance SB 2 miles 5 miles 10 miles Noble Gas Whole Body Dose Rate (REM/hour)

Projected duration (Hours)

Noble Gas Projected Whole Body Dose (REM)

(Extemal Dose Equivalent - EDE)

EPIP 2-4:7 Attachment 1, Rev. 14 Page 3 of 5 RADIOIODINE:

To calculate release RATE in Cl/sec from monitor:

(or use appropriate NG to I Default 1:1 E-4) pCVcc x _ _ cc/sec x 1E-6pCi/cc = . . Ci/sec NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.

To predict downwind concentration:

sec-mrh x Ci/sec x 1/( ) mph = .. pCVcc at S.B. 500 meters ms3(windspeed) sec-mph x Cl/sec x 1/( ) mph = .. pCi/cc at 2 miles m3 (windspeed) sec-mph x Cl/sec x 1/( ) mph = .. pCi/cc at 5 miles m3 (windspeed) sec-mph x Ci/sec x 1/( ) mph = .. pCi/cc at 10 miles m3 (windspeed) sec-mph x Cl/sec x 11( ) mph = .. PCVcc at m3 (windspeed) (distance)

Hours after shutdown Rem/hr. per lCi/cc (Attachment 4):

Distance SB 2 miles 5 miles 10 miles Radioiodine Whole Body Dose Rate (REM/hour)

Projected duration (Hours)

Radioiodine Projected Whole Body Dose (REM)

(Committed Effective Dose Equivalent - CEDE)

+ PLUS +

Noble Gas Projected Whole Body Dose (REM) from previous page (External Dose Equivalent - EDE)

+ EQUALS +

TOTAL Projected Whole Whole Body Dose (REM)

(Total Effective Dose Equivalent - (TEDE)

EPIP 2-4:8 Attachment 1, Rev. 14 Page 4 of 5 RADIOIODINE: (continued)

To calculate release RATE in Ci/sec from monitors:

(or use appropriate NG to I DEFAULT 1:1 E-4) pCicc x cc/sec x 1E-6 pCi/cc = Ci/sec Rem/hr. per pCVcc (Attachment 5):

Distance 3B 2 miles 5 miles 10 miles _

Radioiodine Whole Body Dose Rate (REM/hour)

Projected duration (Hours) _

Radioiodine Projected Thyroid Dose (REM) _

(Committed Dose Equivalent - CDE)

EPIP 2-4:9 Attachment 1, Rev. 14 Page 5 of 5 PARTICULATE:

To calculate release RATE in Cisec from monitors:

pCi/cc x cc/sec x 1E-6 pCi/cc = Ci/sec NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.

To predict downwind concentration:

sec-mph x _ _ Ci/sec x 1/( ) mph = _______ pCi/cc at S.B. 500 meters m3 (windspeed) sec-mph x _ _ Ci/sec x 1/( ) mph = ______ pCi/cc at 2 miles m3 (windspeed) sec-mph x _ _ Ci/sec x 1/( ) mph = _______ pCVcc at 5 miles 3

m (windspeed) sec-mph x __ CVsec x 1/( ) mph = ______ pCi/cc at 10 miles m3 (windspeed) sec-mgh x _ _ Cisec x 1/( ) mph = ______ pCi/cc at m3 (windspeed) (distance)

Hours after shutdown Rem/hr. per pCi/cc:

Distance 2 miles 5 miles 10 miles Particulate Whole Body Dose Rate (REM/hour)

Projected duration (Hours)

Particulate Projected Whole Body Dose (REM)

NOTE: THE APPROPRIATE DOSE CONVERSION FACTOR FOR PARTICULATES WOULD BE BASED UPON THE RESULTS OF AN ISOTOPIC ANALYSIS OF THE MIXTURE AND REFERENCING EPA-400-R-92-001.

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EPIP 2-4:10 Attachment 2, Rev. 14 Page 1 of 2 PASQUILL STABILITY CLASS CRITERIA PASQUILL 150 FT - 33 FT 250 FT - 33 FT STABILITY DELTAT (DEG F/100 FT) DELTAT (DEG F/117 FT) DELTAT (DEG F1217 CLASS FT)

GREATER LESS THAN GREATER LESS THAN GREATER LESS THAN THAN OR EQUAL TO THAN OR EQUAL TO THAN OR EQUAL TO l A -- 1.0 _- -1.17 --- 2.17 B -1.0 -0.9 -1.17 -1.05 -2.17 -1.95 C -0.9 -0.8 -1.05 -0.94 -1.95 -1.74 D -0.8 -0.3 -0.94 -0.35 -1.74 -0.65 E -0.3 0.8 -0.35 0.94 -0.65 1.74 F 0.8 2.2 0.94 2.57 1.74 4.77 G 2.2 2.57 . 4.77

EPIP 2-4:11 PASQUILL STABILITY CLASS CRITERIA Attachment 2, Rev. 14 Page 2 of 2 GINNA SITE VALUES OF Xu/Q AS A FUNCTION OF STABILITY AND DISTANCE UNSTABLE NEUTRAL (D) STABLE (F)

MILES A B C D E F G 0.1 4.48E-5 2.32E-4 6.44E-4 9.16E-4 9.35E-4 1.18E-3 1.22E-3 0.2 1.91 E-5 7.88E-5 2.29E-4 3.89E-4 4.37E-4 6.30E-4 7.35E-4 0.3 SB 1.16E-5 4.20E-5 1.25E-4 2.36E-4 2.80E-4 4.36E-4 5.46E-4SB 0.4 8.12E-6 2.68E-5 8.15E-5 1.65E-4 2.04E-4 3.35E-4 4.43E-4 0.5 6.17E-6 1.90E-5 5.84E-5 1.26E-4 1.60E-4 2.74E-4 3.76E-4 0.6 4.93E-6 1.43E-5 4.45E-5 1.OOE-4 1.31 E-4 2.32E-4 3.29E-4 0.7 4.08E-6 1.12E-5 3.54E-5 8.29E-5 1.11E-4 1.60E-4 2.94E-4 0.9 2.99E-6 7.60E-6 2.43E-5 6.08E-5 8.40E-5 1.60E-4 2.44E-4 1.0 2.63E-6 6.45E-6 2.08E-5 5.33E-5 7.49E-5 1.46E4 2.26E-4 1.1 2.34E-6 5.56E-6 1.80E-5 4.74E-5 6.74E-5 1.34E-4 2.11 E-4 1.2 2.1OE-6 4.86E-6 1.58E-5 4.26E-5 6.13E-5 123E-4 1.98E-4 1.6 1.47E-6 3.11 E-6 1.03E-5 2.99E-5 4.47E-5 9.50E-5 1.60E-4 1.9 1.19E-6 2.38E-6 7.98E-6 2.41E-5 3.70E-5 8.12E-5 1.41E-4 2.0 1.12E-6 2.20E-6 7.39E-6 2.27E-5 3.50E-5 7.75E-5 1.36E-4 22 9.95E-7 1.89E-6 6.41 E-6 2.01 E-5 3.15E-5 7.11 E-5 1.27E-4 2.5 8.50E-7 1.55E-6 5.30E-6 1.72E-5 2.74E-5 6.33E-5 1.1 6E-4 2.8 7.39E-7 1.30E-6 4.47E-6 1.50E-5 2.42E-5 5.71 E-5 1.06E-4 3.0 6.79E-7 1.17E-6 4.04E-6 1.37E-5 2.24E-5 5.36E-5 1.01E-4 3.5 5.62E-7 9.20E-7 3.21 E-6 1.14E-5 1.90E-5 4.66E-5 9.04E-5 3.7 5.24E-7 8.44E-7 2.95E-6 1.06E-5 1.78E-5 4.43E-5 8.68E-5 4.0 4.76E-7 7.47E-7 2.63E-6 9.63E-6 1.64E-5 4.41 E-5 8.20E-5 4.2 4.49E-7 6.93E-7 2.44E-6 9.07E-6 1.55E-5 3.95E-5 791 E-5 4.5 4.12E-7 6.22E-7 2.20E-6 8.33E-6 1.44E-5 3.71 E-5 7.52E-5 4.8 3.81 E-7 5.63E-7 2.OOE-6 7.69E-6 1.34E-5 3.50E-5 7.17E-5 5.0 3.62E-7 5.28E-7 1.88E-6 7.31 E-6 1-28E-5 3.37E-5 6-98E-5 5.2 3.45E-7 4.97E-7 1.78E-6 6.96E-6 1.23E-5 3.25E-5 6.76E-5 5.5 3.22E-7 4.55E-7 1.63E-6 6.50E-6 1.1 5E-5 3.09E-5 6.49E-5 5.8 3.01E-7 4.19E-7 1.51E-6 6-09E-6 1.09E-5 2.94E-5 6.24E-5 6.0 2.98E-7 3.98E-7 1.44E-6 5.84E-6 1.05E-5 2.85E-5 6-09E-5 6.2 2.78E-7 3.78E-7 1.37E-6 5.60E-6 1.01 E-5 2.77E-5 5.95E-5 6.5 2.62E-7 3.51 E-7 1.27E-6 5.29E-6 9.61 E-6 2.65E-5 5.74E-5 6.8 2.48E-7 3.27E-7 1.19E-6 5.OOE-6 9.15E-6 2.55E-5 5.56E-5 7.0 2.39E-7 3.13E-7 1.14E-6 4.82E-6 8.86E-6 2.48E-5 5.44E-5 7.2 2.31 E-7 3.OOE-7 1.09E-6 4.66E-6 8.59E-6 2.42E-5 5.33E-5 7.5 2.20E-7 2.81 E-7 1.03E-6 4.43E-6 8.22E-6 2.33E-5 5.17E-5 7.8 2.09E-7 2.65E-7 9.71E-7 4.22E-6 7.87E-6 2.25E-5 5.03E-5 8.0 2.03E-7 2.54E-7 9.35E-7 4.09E-6 7.66E-6 2.20E-5 4.93E-5 82 1.§7E-7 2.45E-7 9.01 E-7 3.97E-6 7.45E-6 2.15E-5 4-85E-5 8.5 1.88E-7 2.31 E-7 8.54E-7 3.80E-6 7.16E-6 2.08E-5 4.72E-5 8.8 1.80E-7 2.19E-7 8.11E-7 3.64E-6 6.90E-6 2.01 E-5 4.60E-5 9.0 1.75E-7 2.12E-7 7.84E-7 3.54E-6 6.73E-6 1.97E-5 4.53E-5 9.2 1.71E-7 2.05E-7 7.59E-7 3.44E-6 6.57E-6 1.93E-5 4.45E-5 9.5 1.64E-7 1.95E-7 7.23E-7 3.31 E-6 6.34E-6 1.88E-5 4.35E-5 9.8 1.58E-7 1.85E-7 6.91E-7 3.18E-6 6.13E-6 1.83E-5 4.25E-5 10.0 1.54E-7 1.80E-7 6.70E.7 3.1 1E-6 5.99E-6 1.79E-5 4.19E-5 SB = Site Boundary

EPIP 2-4:12 Attachment 3, Rev. 14 Page 1 of 1 NOBLE GAS DOSE CONVERSION FACTORS FOR WHOLE BODY (EDE)

Time After Shutdown (Hours) Rem/Hour Per pCi/cc 0 470 1 434 2 331 3 265 4 221 6 159 12 65 NOTE: MULTIPLY MCI/CC BY THE LISTED FACTOR TO OBTAIN REMIHOUR.

EPIP 2-4:13 Attachment 4, Rev. 14 Page 1 of 1 RADIOIODINE DOSE CONVERSION FACTORS FOR WHOLE BODY (CEDE)

Time After Shutdown (Hours) Rem/Hour Per jCi/cc 0 1.73E4 1 1.57E4 2 1.76E4 3 1.92E4 4 2.05E4 6 2.24E4 12 2.65E4 NOTE: MULTIPLY MCVCC BY THE LISTED FACTOR TO OBTAIN REM/HOUR.

EPIP 2-4:14 Attachment 5, Rev. 14 Page 1 of 1 RADIOIODINE CONVERSION FACTORS FOR THYROID (CDE)

Time After Shutdown (Hours) Rem/Hour Per VCVCC*

0 4.4E5 1 5.4E5 2 6.4E5 3 7.4E5 4 7.8E5 6 8.8E5 12 1.1E6 NOTE: MULTIPLY MCI/CC BY THE LISTED FACTOR TO OBTAIN REM/HOUR.

These conversion factors have been increased by a factor of two. EPA-400 uses the adult thyroid. New York State has increased EPA-400 factors by two to adjust for child thyroid.

EPIP 2-4:15 Attachment 6, Rev. 14 Page 1 of 2 RMS PROCESS MONITOR CALIBRATION FACTORS R-10A CONTAINMENT IODINE:

pCi/cc lodine-131 = (Acpm/hour) (1.10 E-11)

RIOB PLANT VENT IODINE:

pCicc lodine-1 31 = (Acpmlhour) (9.02 E-12)

R-i1 CONTAINMENT PARTICULATE:

pCi/cc as Cs-137 = ( cpm) (3.12 E-12)

R-12 CONTAINMENT GAS:

pCi/cc Xe-I 33 = ( cpm) (5.6 E-8)

R-13 PLANT VENT PARTICULATE:

pCVcc as Cs-137 = ( cpm) (2.91 E-12)

R-14 PLANT VENT GAS:

Calibration factors calculated based on Kr-85 and Xe-1 33 calibration factors.

pCicc as Xe-133 = ( cpm) (5.6 E-8)

R-15 AIR EJECTOR AND GLAND STEAM EXHAUST GAS:

pCi/cc Xe-133 = ( cpm) (4.6 E-8) pCVcc as normal gas mixture * = ( cpm) (5.0 E-8)

Based on the mixture of noble gas present in the reactor coolant during the 01/25/82 tube rupture which is representative of normal operations.

R-16 CONTAINMENT FAN COOLER SERVICE WATER:

pCi/cc as Cs- 37 = ( cpm) (1.5 E-8)

R-17 COMPONENT COOLING:

pCi/cc as Cs-137 = ( cpm) (1.4 E-8)

EPIP 2-4:16 Attachment 6, Rev. 14 Page 2 of 2 RMS PROCESS MONITOR CALIBRATION FACTORS R-18 RADWASTE SYSTEM DISCHARGE::

pCVcc as Cs-137= ( cpm) (1.4 E-8)

R-19 STEAM GENERATOR BLOWDOWN:

pCVcc as Cs-137= ( cpm) (1.4 E-8)

R-20A SPENT FUEL POOL HEAT EXCHANGER SERVICE WATER:

pCVcc as Cs-137 = ( cpm) (2.4 E-8)

R-20B SPENT FUEL POOL HEAT EXCHANGER SERVICE WATER pCVcc as Cs-137 = ( cpm) (1.7 E-7)

R-21 RETENTION TANK:

pCi/cc as Cs-137 = ( cpm) (1.5 E-8)

R-22 HIGH CONDUCTIVITY WASTE TANK:

pCVcc as Cs-137= ( cpm) (1.2 E-8)

R-31 STEAM LINE RADIATION MONITOR:

mr/hr = ( cpm) (2.11 E-2)

R-32 STEAM LINE RADIATION MONITOR:

mr/hr = ( cpm) (2.02 E-2)

R-36 CONTROL ROOM NOBLE GAS MONITOR:

pCicc as Kr-85 = ( cpm) (1.75 E-8) pCVcc as Xe-133 = ( cpm) (1.41 E-7)

R-37 CONTROL ROOM PARTICULATE MONITOR:

pCi/cc as Cs-137 = ( cpm) (1.68 E-12)

R38 CONTROL ROOM IODINE MONITOR:

pCi/cc as 1-131 = ( cpm) (2.51 E-12)

ROCHESTER GAS & ELECTRIC CORPORATION GINNA STATION Controlled Copy Number _ _3 Procedure Number EPIP 3-1 Revision Number 23 Emergency Operations Facility (EOF) Activation Responsi

()Pj~qn7 Eff~ctivefDate Category 1.0 This procedure contains 9 pages

EPIP 3-1:1 EPIP 3-1 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION 1.0 PURPOSE The purpose of this procedure is to designate actions and responsibility of individuals who would report to the Emergency Operations Facility upon a decision to activate the facility.

2.0 RESPONSIBILITY 2.1 The first qualified person to arrive is responsible for initiating this procedure.

2.2 The EOF/Recovery Manager is responsible for activation of the EOF upon arrival.

3.0 REFERENCES

3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 NUREG-0654 "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".

3.2 Implementing References 3.2.1 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.2 EPIP 1-5, Notifications 3.2.3 EPIP 3-3, Engineering Support Center (ESC) Activation 3.2.4 EPIP 3-6, Corporate Notifications 3.2.5 EPIP 4-6, Joint Emergency News Center (JENC) Activation 3.2.6 EPIP 5-7, Emergency Organization 4.0 PRECAUTIONS As noted in this procedure.

EPIP 3-1:2 5.0 PREREQUISITES 5.1 An Alert, Site Area Emergency or a General Emergency has been declared in accordance with EPIP 1-0.

5.2 The EOF could be activated anytime at the discretion of the EOF/Recovery Manager.

6.0 ACTIONS 6.1 Arriving Personnel NOTE: Depending on the number of arriving personnel, perform steps concurrently to minimize activation time.

6.1.1 Sign in at the Security Desk at the entrance to the EOF.

6.1.2 Place your name under the appropriate emergency position on the magnetic organization chart.

6.1.3 Perform responsibilities as described in EPIP 5-7, Emergency Organization 6.1.4 Personnel arriving from the Ginna plant should perform a whole body frisk to check for contamination if there has been a release of radioactivity.

6.2 EOF/Recovery Manager perform the following:

NOTE: In the event of power loss at the EOF, contact the TSC Emergency Coordinator and discuss the need for the TSC to re-assume or maintain command and control, as appropriate.

6.2.1 Ensure minimum response staff listed below is available (as indicated by the red dots on the sign in board):

a. Nuclear Operations Manager (NOM)

b. Engineering Manager

c. Dose Assessment Manager

d. News Center Manager 6.2.2 If a position is not staffed, call in personnel. Qualified responders are found in their position checklist in EPIP 5-7. The TSC will fax the status of the call-in process to the incoming fax machine (located in the Administrative area across the hall) when they are staffed.

EPIP 3-1:3 6.2.3 Obtain a briefing from the TSC Director on plant conditions. If the Ginna responders have been directed to the Ontario Fire Department Exempt Hall (located on Route 104 between Route 350 and Knickerbocker Road, phone number 315-524-8078), have the EOF responders obtain the checklists for their counterparts in EPIP 5-7. Ensure that all functions required by the onsite emergency organization are performed by the EOF responders to the extent practical.

6.2.4 Obtain notification forms from EOF fax machine that the Control Room and TSC have sent to notify offsite agencies. Use these forms and brief the response staff on plant conditions. Ensure that the staff makes contact with their counterparts.

The counterparts are:

a. EOF/Recovery Manager - TSC Director

b. EOF Dose Assessment Manager - TSC Dose Assessment Manager

c. Nuclear Operations Manager - TSC Operations Manager

d. Engineering Manager - TSC Technical Manager 6.2.5 If the Ginna responders will not be allowed site access for greater than four (4) hours, have the Ginna Engineering, Operations and Dose Assessment personnel report to the EOF to assist in technical evaluations.

6.2.6 Brief Federal, State and County Representatives in the EOF on the status of the emergency. Request that they contact their respective emergency operation facilities and determine if the county response organizations have any concerns.

NOTE: IF ONE OF THE INDIVIDUALS CANNOT BE CONTACTED, HAVE ONE OF THE OTHER CONTACTS ASSUME THE RESPONSIBILITY.

6.2.7 Contact RG&E management and notify them that you are the EOF/Recovery Manager and that the EOF is activated in response to a Ginna emergency.

Inform them of the following:

'This is the EOF/Recovery Manager. Ginna has declared an emergency and we are activating our emergency facilities. Can you be the management contact for this event? You are to act as the liaison between RG&E and our parent company, Energy East.'

Primary Notifications Jim Laurito Work: (585) 724-8077 Home: (585) 218-9528 Cellular: (806) 306-7917

EPIP 3-1:4 Primary Notifications (Cont'd.)

Wes von Schack Work: (607) 762-4550 Energy East Home: (212) 396-9792 Cellular: (607) 760-5200 Ken Jasinski Work: (607) 762-4315 Energy East Home: (914) 738-3065 Cellular: (914) 441-5770 "This is the EOF/Recovery Manager. Ginna has declared an emergency and we are activating our emergency facilities. Can you be the financial contact for this event?"

I Joe Syta Work: (585) 724-8003 I Controller and Treasurer Home: (585) 425-4474 I Pager: (585) 528-8712 Debbie Merwin Work: (585) 771-2212 I Cellular: (585) 329-6148 "This is the EOF/Recovery Manager. Ginna has declared an emergency and we are activating our emergency facilities. Can you be the RG&E outside/government agencies liaison for this event?"

Robert Bergin Work: (585) 771-2294 Assistant General Counsel Home: (585) 377-4399 Government and Community Cellular: (585) 315-0040 Relations 6.2.8 Contact INPO at (800) 321-0614 and inform them of the declared emergency.

6.2.9 Request the Facilities and Personnel Manager contact hotels and food service providers for support of TSC and EOF responders.

6.2.11 Assuming Command and Control of the Emergency 6.2.11.1 Ensure minimum activation staff listed below is available to assume command and control:

a. EOF Dose Assessment Manager

b. Dose Assessment Support (3)

c. Nuclear Operations Manager (NOM)

EPIP 3-1:5

d. Technical Assistant to the NOM

e. Administrative Assistant to the NOM

f. Communicator

9. Engineering Manager

h. Facilities and Personnel Manager

i. EOF/JENC Security Manager

j. Offsite Agency Liaison

k. Technical Representative Liaison I. Corporate Spokesperson

m. News Center Manager 6.2.11.2 If a position is not staffed, call in personnel. Qualified responders are found in their position checklist in EPIP 5-7.

6.2.11.3 Confer with the TSC Emergency Coordinator on shifting command and control of the emergency from the TSC organization to the EOF. Normally when command and control is transferred, the EOF assumes:

a. Overall direction for the emergency

1. Emergency Classification

2. Protective Action Recommendations

b. Notifications to New York State, Wayne and Monroe Counties

c. Dose Assessment and Offsite Survey Team coordination However, certain conditions may warrant transferring a given responsibility area (e.g. survey team coordination) at different times, per the discretion of the Emergency Coordinator and EOF/Recovery Manager.

6.2.11.4 Brief EOF personnel on plant status and notify them that command and control will be assumed at the agreed upon time using Attachment 2 for meeting agenda.

EPIP 3-1:6 6.2.11.5 At the agreed upon time, call the TSC Emergency Coordinator and state that, unless he has any objections, the EOF is assuming command and control at this time.

6.2.11.6 Announce to the EOF that the EOF has assumed command and control of the emergency.

6.2.11.7 Upon assuming command and control, direct the NOM to provide RECS line updates every 30 minutes using procedure EPIP 1-5, Attachment 3.

6.2.11.8 Direct the Federal, State and County representatives in the EOF to contact their emergency management organizations and inform them that the EOF has assumed command and control.

6.2.11.9 Ensure the EOF Dose Assessment Manager notifies the Survey Center Manager that the EOF has assumed command and control.

6.3 Shift Tumover 6.3.1 If the EOF will be activated for more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , direct the Facilities and Personnel Manager to complete Attachment 1 for continuous staffing.

6.3.2 When the responders for the next shift have arrived, have them perform a detailed turnover with the person that they are relieving. Have them log the turnover in their log book.

6.3.3 When the individual turnovers are complete, have the on-coming crew perform a briefing for each other using the standard meeting agenda (Attachment 2). The off-going crew should also be at the briefing to ensure that the information that is shared is correct and complete.

6.3.4 To terminate the emergency or to transition to the recovery phase use EPIP 3-4.

7.0 ATTACHMENTS

1. EOF Continuous Staffing Schedule

2. EOF Meeting Agenda

EPIP 3-1:7 Attachment 1, Rev. 23 Page 1 of 2 EOF CONTINUOUS STAFFING SCHEDULE (Consult EPIP 5-7 position checklists for qualified personnel and phone numbers to fill positions.)

Shift _A I Shift B_~~

hrs hrs to hrs to hrs POSITION Date: Date:

EOF/Recovery Manager Secretary, Recovery Mgr Nuclear Operations Manager Technical Asst. to NOM Admin Asst to NOM Corporate Spokesperson Assistant to Corporate Spokesperson Technical Advisor to Corporate Spokesperson News Writer Engineering Manager Offsite Agency Liaison EOF Technical Representative Monroe County Tech. Rep.

Wayne County Tech. Rep.

Albany Tech. Rep.

Facilities and Personnel Mgr EOF/JENC Security Manager

EPIP 3-1:8 Attachment 1, Rev.23 Page 2 of 2 EOF CONTINUOUS STAFFING SCHEDULE (Consult EPIP 5-7 position checklists for qualified personnel and phone numbers to fill positions.)

Shift A Shift B hrs hrs to hrs to hrs POSITION Date: Date:

Clerical Supervisor Fax Operator Copier Operator Courier Dose Assessment Manager Assistant DA Manager Dose Assessment Liaison Calculator Calculator Radio Operator Communicator Plotter Weather/Status Board Survey Team Survey Team Communicator Communicator Status Board Keeper

EPIP 3-1:9 Attachment 2, Rev. 23 Page 1 of 1 EOF MEETING AGENDA Meeting Date: Time:

1. Recovery Manager

Purpose of Meeting

Classification level

Time classification declared

Brief event description (use EAL reference manual)

Injury/Fire Status

2. Dose Assessment

Offsite Areas of concern (downwind areas)

Protective Actions Recommended

Abnormal radiation levels

3. Nuclear Operations Manager (Ginna to report if on conference calls)

Plant Status

Maintenance

Equipment out of service

Repairs planned or in progress

4. Engineering Manager (Ginna to report if on conference calls)

Brief technical issues

5. Security

Accountability of plant personnel

Movement of response personnel to and from site.

6. Facility and Personnel Manager

Staffing of facilities

Transportation of personnel

Food

Requests received

7. Corporate Spokesperson

Media questions

8. Other RG&E Concerns

9. County Concerns

Wayne County

Monroe County

10. State Concerns

State Emergency Management Office (SEMO)

Department of Health (DOH)

Department of Environmental Conservation

11. Federal Concerns

Nuclear Regulatory Commission (NRC)

Federal Emergency Management Agency (FEMA)

Department of Energy (DOE)

12. Review of Open Items Please write on these pages. New pages will be provided after each use.

9 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER t7-?

PROCEDURE NO. EPIP 3-3 REV. NO. 10 IMMEDIATE ENTRY RESPONSER RESPONSIBLE M ER EFFEC IVE IATE Category 1.0 This procedure contains 6..j pages

EPIP 3 -3:1 EPIP 3-3 IMMEDIATE ENTRY

1.0 PURPOSE

1.1 To provide instructions for immediate entry to the Ginna site from the Survey Center as required by the Emergency Response Organization.

2.0 RESPONSIBILITY

2.1 The Survey Center Manager is responsible for providing entry teams as requested by the Ginna Station TSC and/or Control Room and assisting in immediate entry preparation.

2.2 Entry team members are responsible for implementation of this procedure.

3.0 REFERENCES

3.1 Developmental References None.

3.2 Implementing References 3.2.1 EPIP 1-12, Repair and Corrective Action Guidelines During Emergency Situations 3.2.2 EPIP 1-8, Search and Rescue Operation 3.2.3 EPIP 1-9, Technical Support Center Activation 3.2.4 EPIP 1-10, Operational Support Center (OSC) Activation 3.2.5 EPIP 1-11, Survey Center Activation

4.0 PRECAUTIONS

4.1 Designated personnel may be required to enter the site as members of Emergency Response Organization or Emergency Support Organization (EPIP 1-12, EPIP 1-9, EPIP 1-8, EPIP 1-10).

4.2 The size of entry teams shall be two individuals or more.

EPIP 3 -3:2

5.0 PREREQUISITES

5.1 The Emergency Coordinator has requested the dispatch of Entry Teams to the Ginna Site.

5.2 A current EPIP 1-5 NEW YORK STATE (NYS) RADIOLOGICAL EMERGENCY DATA FORM (PART I), (Attachment 3a) should be provided to the Survey Center by the RG&E emergency facility (Control Room, TSC or EOF) which has command and control.

6.0 ACTIONS

6.1 Survey Center Manager 6.1.1 Using the NYS Part I Form that was faxed to the Survey Center, determine wind direction, wind speed, initiating event conditions and pertinent plant conditions and post information on status board at the Survey Center.

6.1.3 Assemble the Entry Teams.

6.1.3.1 Designate an Entry Team Leader.

6.1.3.2 Obtain the names of the Entry Team Members.

6.1.3.3 Request a Radiation Protection Technician or Survey Team member to escort the team; otherwise, designate an Entry Team Member to perform the Radiation Protection function.

6.1.3.4 Provide the Entry Team Leader with a portable radio.

6.1.3.4.1 Ensure the Entry Team Leader understands the use of the portable radio.

6.1.4 If the TSC has assumed command and control, notify the TSC Security Manager (or the TSC Radio Communicator) that personnel, by name, will require entry to the Ginna Site.

6.1.4.1 If the Control Room has command and control, notify the Control Room Communicator that personnel, by name, will require entry to the Ginna Site.

6.1.5 Request the Emergency Coordinator provide an entry route.

6.1.5.1 If available, request the TSC RP/Chemistry Manager assist with and recommend necessary radiation protection equipment, dosimetry, protective clothing and respiratory protection.

IT EPIP 3 -3:3 6.1.5.2 If available, request the TSC RP/Chemistry Manager assist in briefing the team on the radiological conditions they may encounter.

6.1.6 Brief the team(s) using the NYS Radiological Emergency Data Form (Part I),

which was faxed to the Survey Center, before departure to the Ginna Site.

6.1.6.1 The Departure briefing should include:

a. Name of the Entry Team Leader

b. Names of the members of the Entry Team

c. Weather conditions

d. Radiological conditions

e. Plant status, event classification

f. Radiological protection equipment, dosimetry and protective clothing

g. Respiratory protection

h. Route

i. A reminder that the teams DO NOT enter areas with radiation levels greater than 2 Rern/hr unless directed by the Emergency Coordinator

j. A reminder for the teams to remove their anti-contamination clothing upon arrival at the final destination in accordance with radiation protection procedures.

k. A reminder to perform a whole body frisk upon arrival at their destination.

6.2 Entry Teams NOTE: ENSURE DOSE RATE METER AND RADIO ARE FUNCTIONING PROPERLY PRIOR TO DEPARTURE.

6.2.1 Entry Team Leader 6.2.1.1 Obtain the names of all members of the Entry Team.

6.2.1.2 Obtain a portable radio.

EPIP 3 -3:4 6.2.1.3 The entry team shall obtain necessary equipment as recommended by a Radiation Protection Technician, TSC RP/Chemistry Manager or the Survey Center Manager. In their absence, obtain the equipment listed below:

a. Thermoluminescent dosimeter (TLD)

b. High range self-reading dosimeter (SRD) at least 0 to 1500mR

c. High range dose rate meter (0-1000 R/hr)

d. Anti-contamination clothing

e. Full face mask with charcoal filter

f. Radio 6.2.1.4 Ensure each Entry Team member logs in on Dosimetry Log in accordance with EPIP 1-11.

6.2.1.5 Ensure each Entry Team member is aware of the following:

a) Weather conditions b) Plant conditions c) Event Classification d) Route e) Radiological conditions 6.2.1.6 Just before departure, contact the Emergency Coordinator and brief them on your route and obtain any last minute instructions.

6.2.1.7 Ensure the Entry Team does not enter areas with radiation levels greater than 2 Rem/hr unless directed by the Emergency Coordinator.

6.2.1.8 Ensure Entry Team members remove their anti-contamination clothing upon arrival at the final destination in accordance with radiation protection procedures.

6.2.1.9 Ensure Entry Team members perform a whole body frisk upon arrival at their destination.

A EPIP 3 -3:5 6.2.1.10 Report the arrival of the Entry Team to the Emergency Coordinator.

6.2.1.11 Ensure each Entry Team member records their SRD dose in accordance with EPIP 1-11, using the Dosimetry Log faxed to the TSC RP/Chemistry Manager.

6.2.1.12 Ensure each Entry Team member is accounted for from departure from the Survey Center until arrival at the final destination.

6.2.1.13 Ensure the entire team attends a de-briefing.

6.2.1.14 Ensure all SRDs, radios and survey meters are turned over to the TSC RP/Chemistry Manager for return to the Survey Center.

6.2.2 Entry Team Member 6.2.2.1 Notify Survey Center Manager, if present, and log on status board that team is leaving for the site.

6.2.2.2 Provide name to the Entry Team Leader.

6.2.2.3 Obtain the necessary radiation protection equipment, dosimetry, and respiratory protection equipment.

6.2.2.4 Know the following:

a) Weather conditions b) Plant conditions c) Route d) Radiological conditions 6.2.2.5 Note any unusual conditions encountered during the entry.

6.2.2.6 Do not enter areas with radiation levels greater than 2 Rem/hr unless directed by the Emergency Coordinator.

6.2.2.7 Remove anti-contamination clothing upon arrival at the final destination in accordance with radiation protection procedures.

6.2.2.8 Perform a whole body frisk upon arrival at the final destination.

6.2.2.9 Report any radiation survey results to the TSC Dose Assessment Manager.

EPIP 3 -3:6 6.2.2.10 Record SRD dose on Dosimetry Log that was faxed to the TSC RP/Chemistry Manager and turn over SRD to TSC RP/Chemistry Manager.

6.2.2.11 Attend a de-briefing.

6.3 TSC RP/Chemistry Manager 6.3.1 Assists entry team by providing radiological conditions that they may encounter.

6.3.2 Ensures SRDs, radios and survey meters are returned to the Survey Center.

6.3.3 Turns over Dosimetry Logs to Dosimetry for entry into the Radiation Dose Management System (RDMS).

7.0 ATTACHMENTS

None.

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER A-'

PROCEDURE NO. EPIP 4-1 REV. NO. 7 PUBLIC INFORMATION RESPONSE TO AN UNUSUAL EVENT RESIONBLE M ER EFSFEC 1EDE EFFECTIVE DATE Category 1.0 This procedure contains 2 pages

EPIP 4-1:1 EPIP 4-1 PUBLIC INFORMATION RESPONSE TO AN UNUSUAL EVENT 1.0 PURPOSE To provide instruction for implementing the Public Information response to an Unusual Event at the R.E. Ginna Nuclear Power Plant.

2.0 RESPONSIBILITY 1 2.1 Emergency Preparedness is responsible for notifying the News Center Manager and the Duty Corporate Communications Representative of the Unusual Event.

2.2 The News Center Manager is responsible for informing the appropriate News Center personnel of the Unusual Event condition as deemed necessary.

3.0 REFERENCES

3.1 Developmental References 3.1.1 Rochester Gas and Electric Corporation Nuclear Emergency Response Plan.

3.2 Implementing References 3.2.1 EPIP 4-7, Public Information Organization Staffing 4.0 PRECAUTIONS None.

5.0 PREREQUISITES 5.1 An Unusual Event has been declared at the R.E. Ginna Nuclear Power Plant in accordance with EPIP 1-0, Ginna Station Event Evaluation and Classification.

6.0 ACTIONS 6.1 News Center Manager 6.1.1 Upon notification by Emergency Preparedness, notify the key personnel listed below using EPIP 4-7 and request that they stand-by for further information as the situation develops and as judgement dictates.

EPIP 4-1:2 6.1.2 Use EPIP 4-7, Public Information Organization Staffing, to document calls and responses.

6.1.3 Standby for further information from Emergency Preparedness.

6.2 Joint Emergency News Center Personnel 6.2.1 When notified by the News Center Manager, key JENC supervisory personnel will remain accessible to the News Center Manager.

Key Supervisory Personnel are:

a. Media Monitoring and Public Inquiry Manager

b. Assistant News Center Manager

c. JENC Security personnel

d. Facilities & Materials Coordinator

e. Corporate Spokesperson 6.2.2 A News Announcement is required. The News Announcement will be prepared by either the Duty Corporate Communications Representative and approved by the Manager of Corporate Communications using their normal process.

6.2.3 No further action is required by Emergency News Center Personnel at the Unusual Event Level. All News Announcements of public information will be handled per normal Public Affairs departmental operating procedures.

7.0 ATTACHMENTS None.

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 7-3 PROCEDURE NO. EPIP 4-3 REV. NO. 13 ACCIDENTAL ACTIVATION OF GINNA ALERT AND NOTIFICATION SYSTEM SIRENS RESPONSIBLE MANAGER 66 (6o7 tO EFFECI IVE CATE Category 1.0 This procedure contains 3 pages

EPIP 4-3:1 EPIP 4-3 ACCIDENTAL ACTIVATION OF GINNA EMERGENCY NOTIFICATION SYSTEM SIRENS

1.0 PURPOSE

1.1 To specify the means by which notifications are to be made in the event of an accidental activation of Ginna Alert and Notification System (ANS) Sirens.

2.0 RESPONSIBILITY

2.1 The Ginna Control Room is responsible for initiating this procedure.

3.0 REFERENCES

3.1 Developmental References 3.1.1 IEN 81-34 Accidental Activation of Prompt Public Notification System 3.1.2 NRC NUREG-1022, Event Reporting Guidelines 3.2 Imolementino References None.

4.0 PRECAUTIONS

None.

5.0 PREREQUISITES

5.1 RG&E has been notified that an ANS siren has sounded.

6.0 ACTIONS

NOTE: IF THERE IS AN ACTUAL GINNA EMERGENCY, INSTRUCT THE CALLER TO REFER TO THEIR EMERGENCY PLANNING CALENDAR AND/OR TUNE IN TO THEIR EMERGENCY ALERT SYSTEM STATION (WHAM) 11 80AM, (WVOR) 100.5FM OR (WHEC) TV10 FOR ADDITIONAL INFORMATION.

EPIP 4-3:2 6.1 Obtain the following information from the caller:

a. Name

b. Address

c. Telephone number I 6.2 Verify if a siren has activated. Have the Fire Brigade, l&C Special Projects or System Engineer perform a Silent Test by pushing the Silent Test button at Ginna TSC Controller or applicable County Controller. This will check the status of each siren. A siren with a failure code will show red on the screen. Review report printed on the printer, an "X"in the OVR (Overrun) column indicates that the siren inadvertently activated.

I 6.2.1 If the siren computer indicates no sirens activated, go to 6.5. If the siren computer indicates a siren is activated, go to 6.4.

6.3 Use Siren System Controller at Ginna TSC or at County Controller to attempt immediate siren shutdown. Push CANCEL button, hold until XMIT light comes on indicating that CANCEL signal has been sent out.

6.3.1 To determine if the siren has stopped activation, reset the status of the siren that reported the OVR (Overrun) status by performing the following steps:

- Click on menus item 'Status"

- Click on "Reset Status"

- Enter password-x, click OK

- Enter siren number in three digit form (i.e. 036), SEND.

- This should reset the Overrun Status. Check to see if the siren has stopped Alerting. Single Poll siren. If Overrun Status is cleared, then the siren has reported that it has stopped.

6.3.2 Call one of the following Nuclear Emergency Preparedness personnel and inform them of the situation. Have Emergency Preparedness make contact with the affected county, contact the Duty PIO, and ensure l&C Special Projects is made aware of the problem.

Tim Laursen Peter Polfleit Work: 585-771-6185 Work: 585-771-6772 Pager: 585-528-5982 Pager: 585-527-2207 Home: 585-396-1149 Home: 315-524-7101 Cellular: 585-315-1854 Cellular: 585-315-1201

EPIP 4-3:3 Frank Cordaro Rick Watts Work: 585-771-3108 Work: 585-724-8706 Pager: 585-527-3650 Pager: 585-527-3749 Home: 315-524-2924 Home: 585-425-2644 Cellular: 585-315-1277 Cellular: 585-315-1204 Jill Willoughby Work: 585-771-4033 Pager: 585-528-3295 Home: 585-787-9075 Cellular: 585-315-1205 6.5 If no sirens are activated, ask the caller if there may be a possible source other than a Ginna siren that may be sounding. If there are more than three calls about a siren activation within ten minutes, notify the Corporate Communications Manager at (585) 771-2230 during working hours. During off hours notify the Duty Public Information Officer at (585) 771-2133 to inform them of the situation. The duty public information officer will determine if there is a need to notify the media.

6.6 The licensee shall notify the USNRC immediately after notification of Nuclear Emergency Preparedness in step 6.3.2. The notification shall not be later than four hours after the licensee was notified of the accidental activation of the siren(s) using procedure 0-9.3, "NRC Immediate Notification".

7.0 ATTACHMENTS

None.

( ~~~ ( ~ ~~~ V ~

NPSP0200 Ginna Nuclear Power Plant Fri 8/8/2003 8:09:11 am WILLOUGHBYJ PROCEDURE INDE)X Page 1 of 2 INPUT PARAMETERS: TYPE: PREPIP STATUSVALUE(S): EF 5YEARS ONLY:

PREPIP EMERGENC PLAN IMPLEMENTNGPROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE R1V DATE REVIEW REVIW _ ST EPIP-1-0 GINNA STATION EVENT EVALUATION AND CLASSIFICATION 031 06/20/2003 06/20/2003 06/20/2008 EF EPIP-1-1 UNUSUAL EVENT 004 05/23/2003 05/23/2003 05/23/2008 EF EPIP-1-2 ALERT 004 11/02/2001 11/02/2001 11/02/2006 EF EPIP-1-3 SITE AREA EMERGENCY 005 12/09/1996 04/09/2003 04/09/2008 EF EPIP-1-4 GENERAL EMERGENCY 006 05/05/2003 05/05/2003 05/05/2008 EF EPIP-1-5 NOTIFICATIONS 055 06/20/2003 06/20/2003 06/20/2008 EF EPIP-1-6 SITE EVACUATION 017 06/20/2003 06/20/2003 06/20/2008 EF EPIP-1-7 ACCOUNTABILITY OF PERSONNEL 009 11/02/2001 11/02/2001 11/0212006 EF EPIP-1-8 SEARCH AND RESCUE OPERATION 006 05/23/2003 05/23/2003 05/23/2008 EF EPIP-1-9 TECHNICAL SUPPORT CENTER ACTIVATION 025 08/08/2003 08/08/2003 08/08/2008 EF EPIP-1-10 OPERATIONAL SUPPORT CENTER (OSC) ACTIVATION 013 05/23/2003 05/23/2003 05/23/2008 EF EPIP-1-11 SURVEY CENTER ACTIVATION 029 02/25/2003 02/25/2003 02/25/2008 EF EPIP-1-12 REPAIR AND CORRECTIVE ACTION GUIDELINES DURING EMERGENCY SITUATIONS 009 12/20/2001 12/20/2001 12/20/2006 EF EPIP-1-13 LOCAL RADIATION EMERGENCY 004 02/25/2003 02/25/2003 02/25/2008 EF EPIP-1-15 USE OF THE HEALTH PHYSICS NETWORK HPN 005 04/24/1996 03/03/1999 03/03/2004 EF EPIP-1-16 RADIOACTIVE LIQUID RELEASE TO LAKE ONTARIO OR DEER CREEK 005 02/25/2003 02/25/2003 02/25/2008 EF EPIP-1-17 PLANNING FOR ADVERSE WEATHER 004 05/23/2003 05/23/2003 05/23/2008 EF EPIP-1-18 DISCRETIONARY ACTIONS FOR EMERGENCY CONDITIONS 006 05/05/2003 05/05/2003 05/05/2008 EF EPIP-2-1 PROTECTIVE ACTION RECOMMENDATIONS 021 08/08/2003 08/08/2003 08/08/2008 EF EPIP-2-2 OBTAINING METEOROLOGICAL DATA AND FORECASTS AND THEIR USE INEMERGENCY DOSE AS 013 12/03/2002 12/03/2002 12/03/2007 EF EPIP-2-3 EMERGENCY RELEASE RATE DETERMINATION 015 07/01/2002 07/01/2002 07/01/2007 EF EPIP-2-4 EMERGENCY DOSE PROJECTIONS -MANUAL METHOD 014 08/08/2003 08/08/2003 08/08/2008 EF EPIP-2-5 EMERGENCY DOSE PROJECTIONS PERSONAL COMPUTER METHOD 014 05/15/2002 05/15/2002 05/15/2007 EF EPIP-2-6 EMERGENCY DOSE PROJECTIONS - MIDAS PROGRAM 012 02/25/2003 02/25/2003 02/25/2008 EF EPIP-2-7 MANAGEMENT OF EMERGENCY SURVEY TEAMS 011 08/09/2002 08/09/2002 08/09/2007 EF EPIP-2-8 VOLUNTARY ACCEPTANCE OF EMERGENCY RADIATION EXPOSURE 005 05/16/2000 05/16/2000 05/16/2005 EF EPIP-2-9 ADMINISTRATION OF POTASSIUM IODIDE (1<1) 008 05/23/2003 05/23/2003 05/23/2008 EF EPIP-2-10 INPLANT RADIATION SURVEYS 004 08/09/2002 08/09/2002 08/09/2007 EF EPIP-2-11 ONSITE SURVEYS 019 05/15/2002 05/15/2002 05/15/2007 EF EPIP-2-12 OFFSITE SURVEYS 022 05/15/2002 05/15/2002 05/15/2007 EF

( ( (

NPSP0200 Ginna Nuclear Power Plant Fri 8/8/2003 8:09:11 am WILLOUGHBYJ PROCEDURE INDE) Page 2 of 2 INPUT PARAMETERS: TYPE: PiEPP STATUSVALUE(S): EF 5 YEARS ONLY:

riQS:

r-w 1; -1 .fi.-,. :r-z -g I-PREPIP EMERGENCY PLAN IMPLEMENTING PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE DATE REVIEW REVIEW ST EPIP-2-13 IODINE AND PARTICULATE ACTIVITY DETERMINATION FROM AIR SAMPLES 008 0712711999 07/27/1999 07/27/2004 EPIP-2-14 POST PLUME ENVIRONMENTAL SAMPLING E:

015 10/08/2002 10/08/2002 10/08/2007 E:

EPIP-2-15 POST PLUME EVALUATION OF OFFSITE DOSES DUE TO DEPOSITION 006 10/08/2002 10/08/2002 10/08/2007 EPIP-2-16 CORE DAMAGE ESTIMATION E:

013 12103/2002 12/03/2002 12/03/2007 E:

EPIP-2-17 HYPOTHETICAL (PRE-RELEASE) DOSE ESTIMATES 007 03/01/2002 03/01/2002 03/01/2007 a:

EPIP-2-18 CONTROL ROOM DOSE ASSESSMENT 015 05/23/2003 05/2312003 05/23/2008 a:

EPIP-3-1 EMERGENCY OPERATIONS FACIUlTY (EOF) ACTIVATION AND OPERATIONS 023 08108/2003 08/08/2003 08/08/2008 EPIP-3-2 ENGINEERING SUPPORT CENTER (ESC)

E:

010 08/09/2002 08/09/2002 08/09/2007 E:

EPIP-3-3 IMMEDIATE ENTRY 010 08/08/2003 08/08/2003 08/08/2008 E:

EPIP-3-4 EMERGENCY TERMINATION AND RECOVERY 009 02/25/2003 02125/2003 02/25/2008 E:

EPIP-3-7 SECURITY DURING EMERGENCIES 010 10/08/2002 10/08/2002 10/08/2007 E:

EPIP-4-1 PUBUC INFORMATION RESPONSE TO AN UNUSUAL EVENT 007 08/08/2003 08/08/2003 08/08/2008 a:

EPIP-4-3 ACCIDENTAL ACTIVATION OF GINNA EMERGENCY NOTIFICATION SYSTEM SIRENS 013 08/08/2003 08/08/2003 08/08/2008 E:

EPIP46 JOINT EMERGENCY NEWS CENTER ACTIVATION 009 0813112001 08/31/2001 08/31/2006 a:

EPIP-4-7 PUBUC INFORMATION ORGANIZEATION STAFFING 023 05/23/2003 05/23/2003 05/23/2008 a:

EPIP-4-8 SILENT TESTING OF THE GINNA SIRENS FROM THE TECHNICAL SUPPORT CENTER 001 02/25/2003 02/25/2003 02/25/2008 E:

EPIP-4-9 ACTIVATION OF GINNA EMERGENCY SIRENS FROM THE TECHNICAL SUPPORT CENT'ER 002 05/08/2003 05/08/2003 05/08/2008 E:

EPIP4-10 SILENT TESTING OF THE GINNA SIRENS FROM THE COUNTY ACTIVATION POINTS 000 02/25/2003 02/25/2003 02/25/2008 a:

EPIP-4-11 ACTIVATION OF THE GINNA SIRENS FROM THE COUNTY ACTIVATION POINTS 001 05/08/2003 05/08/2003 05/08/2008 E:

EPIP-5-1 OFFSITE EMERGENCY RESPONSE FACIUTIES AND EQUIPMENT PERIODIC INVENTOR Y CHECKS AN 028 06/20/2003 06/20/2003 06/20/2008 a:

EPIP-5-2 ONSITE EMERGENCY RESPONSE FACTES AND EQUIPMENT PERIODIC INVENTORY CHECKS AND 031 06/20/2003 06/20/2003 06/20/2008 a:

EPIP-5-5 CONDUCT OF DRILLS AND EXERCISES 015 05/23/2003 05/23/2003 05/23/2008 a:

EPIP-5-6 ANNUAL REVIEW OF NUCLEAR EMERGENCY RESPONSE PLAN (NERP) 004 05/28/1999 05/28/1999 05/28/2004 E:

EPIP-5-7 EMERGENCY ORGANIZATION 040 05/23/2003 05/23/2003 05/23/2008 E:

EPIP-5-9 TESTING THE OFF HOURS CALL-IN PROCEDURE AND QUARTERLY TELEPHONE NUM BER CHECK 007 10/08/2002 10/08/2002 10/08/2007 a:

EPIP-5-10 EMERGENCY RESPONSE DATA SYSTEM (ERDS) 007 12/03/2002 12/03/2002 12/03/2007 E:

NERP GINNA STATION NUCLEAR EMERGENCY RESPONSE PLAN 022 07/31/2003 07/31/2003 07/31/2005 PREPIP TOTAL: 57 GRAND TOTAL: 57

ML032320016

Contents

Text

Subject:

1.0 PURPOSE

2.0 RESPONSIBILITY

3.0 REFERENCES

4.0 PRECAUTIONS

5.0 PREREQUISITES

6.0 ACTIONS

1.0 PURPOSE

2.0 RESPONSIBILITY

3.0 REFERENCES

4.0 PRECAUTIONS

5.0 PREREQUISITES

6.0 INSTRUCTIONS

7.0 ATTACHMENTS

3.0 REFERENCES

3.0 REFERENCES

1.0 PURPOSE

2.0 RESPONSIBILITY

3.0 REFERENCES

4.0 PRECAUTIONS

5.0 PREREQUISITES

6.0 ACTIONS

7.0 ATTACHMENTS

3.0 REFERENCES

1.0 PURPOSE

2.0 RESPONSIBILITY

3.0 REFERENCES

4.0 PRECAUTIONS

5.0 PREREQUISITES

6.0 ACTIONS

7.0 ATTACHMENTS

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