ML022970444

Revisions to Farley Emergency Plan Implementing Procedures

ML022970444
Person / Time
Site:	Farley
Issue date:	10/15/2002
From:	Hudspeth J Southern Nuclear Operating Co
To:	Mcknight J Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML022970444 (158)

Text

SOUTHERN Z.a Energv to Se* ,e' }'our liId FNP- 160-NRC-DC DESK OCTOBER 15, 2002 DIRECTOR, OFFICE OF NRC ATT: DOCUMENT CONTROL DESK C/O JIM MCKNIGHT US NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555 DEAR SIR, ATTACHED IS A NEW REVISIONS FOR THE FOLLOWING PROCEDURES. PLEASE REPLACE YOUR COPY WITH THE ATTACHED REVISED COPY.

FNP-0-EIP-7.0 VERSION 13 (1 COPY)

FNP-0-EIP-9.1 VERSION 10 (3 COPIES)

FNP-0-EIP-9.3 VERSION 14 (1 COPY)

FNP-0-EIP-10.0 VERSION 33 (1 COPY)

FNP-0-EIP-14.0 VERSION 17 (1 COPY)

IF YOU HAVE ANY QUESTIONS PLEASE CALL ME AT 334-899-5156 EXTENSION 3439.

SINCERELY, 4EYHUDPETH DOCUMENT CONTROL SUPERVISOR DCH:IIb CC: FILE RTYPE A4.54 Memo Disk 4 - NRC

k7-k FNP-0-EIP-14.0 09/24/02 12:23:52 September 24, 2002 Version 17 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE FNP-0-EIP-14.0 AS F

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Y AND PERSONNEL MOVEMENT, RELOCATION, RE-ENTRY SITE EVACUATION R

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PROCEDURE USAGE REQUIREMENTS per FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use linformation Use Approved:

Nuclear Plant General Manager Date Issued____________

UNCONTROLLED COPY CAUTIrrent Do not use inThha Szti~y copy is not maintained lp-oiated Activity Current.

09/24/02 12:23:52 FNP-0-EIP-14.0 LIST OF EFFECTIVE PAGES PROCEDURE CONTAINS NUMBER OF PAGES Body................................................................................................................................................ 11 Table I ............................................................................................................................................. 1 Table 2 ............................................................................................................................................. 1 Figure 1............................................................................................................................................ 1 Figure 2 ............................................................................................................................................ 1 Figure 3 ............................................................................................................................................ 4 Figure 4 ............................................................................................................................................ 1 Figure 5 ............................................................................................................................................ 1 Figure 6 ............................................................................................................................................ I Figure 7 ............................................................................................................................................ 1 I Page 1 of I

09/24/02 12:23:52 , -- FNP-0-EIP-14.0 PERSONNEL MOVEMENT, RELOCATION, RE-ENTRY AND SITE EVACUATION TABLE OF CONTENTS Section Title Page 1.0 Purpose I 2.0 . References 1 3.0 Definitions 1 3.1 Movement 1 3.2 Relocation 1 3.3 Re-entry 2 3.4 Site Evacuation 2 4.0 Exemptions to the Guidance of This Procedure 2 5.0 Requirements for Movement 3 6.0 Requirements for Relocation 3 7.0 Requirements for Re-entry - General Guidance 4 8.0 Requirements for Re-entry - Specific Guidance 6 9.0 Site Evacuation 7 Table 1 References Table 2 Risks Associated with Acute High Level Radiation Exposure Figure 1 Relocation Guideline Figure 2 Relocation Log Figure 3 Re-entry Guideline Figure 4 Re-entry log Page 1 of 2 Version 17

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Section Title Page Figure 5 On-Site Evacuation Routes, Assembly Areas, and Operations Support Centers Figure 6 Off-Site Evacuation Routes Figure 7 Location of Reception Centers in Houston County I Page 2 of 2 Version 17

09/24/02 12:23:52 - '-- . FNP-0-EIP-14.O PERSONNEL MOVEMENT, RELOCATION, RE-ENTRY AND SITE EVACUATION 1.0 Purpose This procedure provides the guidelines for movement, relocation, re-entry and evacuation of personnel after the initial sounding of the plant emergency alarm. A fire emergency shall be considered a special re-entry and procedures for re-entry during this type of emergency are addressed in FNP-0-EIP-13.0, Fire Emergencies.

2.0 References See Table 1 3.0 Definitions 3.1 Movement Personnel movement within the same assembly area building e.g. Service Building Auditorium to Document Control Visitors Center Auditorium to EOF 3.2 Relocation

a. The transfer of an individual (includes re-assigning designated assembly area) from one assembly area to another.

e.g. Service Building Auditorium to Visitors Center Auditorium Service Building Maintenance Shop to TSC

b. Assignment of personnel from their assembly area to a location (non assembly area) in the plant or on the plant site.

e.g. Control Room to Radiochemistry Labs Service Building Auditorium to WTP 4-1 Version 17

09/24/02 12:23:52 FNP-0-EIP-14.0 3.3 Re-entry Entry into an area of elevated personnel hazards due to an emergency condition.

e.g. Entry into the piping penetration room to isolate an ECCS leak following a major loss of coolant accident Entry into an area where the TEDE whole body annual dose limit of 5 rem can be exceeded during the expected time to perform the job (normally 30 minutes can be assumed to perform the job) 3.4 Site Evacuation Organized withdrawal of personnel offsite.

4.0 Exemptions to the Guidance of This Procedure 4.1 Radiation Monitoring Teams (RMTs) are not required to be tracked or be authorized to move from one location to another by this procedure.

4.2 Personnel reporting to the site for duties in the TSC, EOF or the OCS are not required to be tracked or be authorized to report to their designated emergency response facility.

4.3 When the Emergency Director has Security informed of the emergency classification, he will inform Security of any access route restrictions, if necessary. Security will be issued a controlled copy of the on call memo for Security Post Gate 95 North and Security Post Gate 95 South. Personnel on the on-call memo, in any position or as an alternate, will be granted access to the site during an emergency unless specifically restricted by the Emergency Director.

4.4 Security will inform arriving personnel of access route restrictions, if necessary.

4.5 Personnel moving between the Control Room and the TSC are not required to be tracked or authorized by this procedure.

4.6 Personnel moving between the TSC and the breakroom outside the TSC are not required to be tracked or authorized by this procedure, unless the HP Manager has determined that a hazardous condition exists in the breakroom.

4.7 Personnel in the protected area delivering accountability logs to the PAP or the SAP are not required to be authorized by this procedure, but should be tracked by the senior individual in their assembly area.

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09/24/02 12:23:52 .* FNP-0-EIP-14.0 5.0 Requirements for Movement 5.1 The senior individual in the assembly area shall authorize the movement of personnel.

5.2 The senior individual or his designee in the assembly area shall be responsible for tracking the movement of personnel.

6.0 Requirements for Relocation 6.1 The senior individual in the assembly area shall authorize the relocation of personnel, when requested to relocate individuals by the TSC, OSC or EOF.

6.2 The relocation guideline/log (Figure 1/2) may be used as a tracking mechanism for relocations.

6.3 The Control Room/TSC/OSC/EOF will inform the senior individual of any personnel hazards (toxic gas, radioactive release, etc.) that may exist. The senior individual in the assembly area shall provide a transit route for the relocation as appropriate.

6.4 Personnel who are being relocated from one designated assembly area to another designated assembly area will be tracked by the senior individual in the assembly area from which they are departing, until arrival at the new assembly area.

6.5 Personnel who are being relocated to an area outside of a designated assembly area will be tracked by the Control Room/TSC prior to the arrival of the OSC Manager, who will then have the responsibility.

6.6. Tracking and authorization for relocations involving personnel in the TSC/Control Room/OSC will be performed by the OSC Manager. If the OSC Manager is unavailable, the relocation responsibilities may be performed by the Maintenance Manager or Control Room.

6.7 Personnel who have been relocated outside of an assembly area will report to their assembly area, should the plant emergency alarm resound--unless specifically authorized to remain on station by the ED.

6.8 The following applies to security, regarding relocation of personnel:

6.8.1 Remain on station until relocation is required.

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09/24/02 12:23:52 FNP-0-EIP-14.0 6.8.2 When relocation becomes necessary, security supervision shall:

Determine the route, with assistance from Control Room/TSC/OSC (Shift Supervisor/Maintenance Manager, or OSC Manager)

• Implement appropriate compensatory measures.

• Inform the ED of the compensatory measures taken.

6.9 Exposure limits for a re-location shall be limited to five rem TEDE, including the current dose to date.

6.9.1 Exposures in excess of one rem for a relocation, exclusive of current dose, shall be approved by the HP Manager, or the ED in his absence.

6.9.2 If an internal hazard is present, the limit for the relocation should be reduced by a factor of two.

7.0 Requirements for Re-entry - General Guidance 7.1 TLD badges of personnel who receive an emergency exposure in excess of the IOCFR20 limits of step 7.10 will be pulled and read prior to receiving further non emergency exposure.

7.2 Re-entry personnel shall not deviate from a planned route unless unanticipated conditions such as rescue, performing an operation which would minimize the emergency condition, etc., require such a deviation.

7.3 If emergency dose rates observed during re-entry exceed the limits established by the re-entry guideline or other adverse conditions are encountered, re-entry personnel shall return to a safe area and contact the OSC/TSC/Control Room for further instructions.

7.4 If the Plant Emergency Alarm (PEA) is sounded while a re-entry team is involved in their assigned tasks, the re-entry team shall call the Control Room/TSC/OSC and request further instructions for assembly requirements.

7.5 The re-entry guideline/log (Figures 3/4) will serve as a tracking mechanism for re entries. One copy of the guideline will remain with the OSC and, if desired, another copy will be given to the re-entry team leader. The guideline may be photocopied, or a two-part form may be used. The re-entry guideline will be sequentially numbered.

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09/24/02 12:23:52 " " , FNP-.-EIP-14.O 7.6 Individuals listed on the re-entry guideline as responsible for completion of guideline items are not required to personally initial the guideline, but are responsible for ensuring that each requirement is performed and initialed by the person performing or ensuring performance of the task.

7.7 Radiological monitoring will be established for each re-entry. The following parameters will be considered when determining the degree of radiological monitoring:

Releases in progress Dose rates, airborne and contamination levels Stability of plant radiological conditions 7.8 Re-Entry is the responsibility of the Emergency Director, and requires verbal ED approval to execute a re-entry. Re-entries may be authorized and executed by the OSC Manager or Maintenance Manager, with ED approval. Approval to exceed 10CFR20 radiation exposure limits listed in step 7.10 must be approved by the Emergency Director. Approval to exceed plant administrative dose limits listed in step 7.10 must be approved by the HP Manager, or the Emergency Director in the HP Manager's absence.

7.9 An Emergency Repair Party which functions as a re-entry team shall consist of at least two (2) persons.

7.10 Farley Nuclear Plant personnel who have completed the onsite radiation protection training may be required to receive an exposure up to the following IOCFR20 limits:

IOCFR20 Administrative limit limit Whole body (TEDE) - 5 rem - 2 rem Lens of the eyes - 15 rem - 6 rem Skin of the whole body - 50 rem - 20 rem Extremities - 50 rem - 20 rem Internal organs - 50 rem - 20 rem 7.11 Dosimetry records for potential re-entry team members are available in the Dosimetry Lab.

CAUTION: EMERGENCY EXPOSURE LIMITS SHALL ONLY BE AUTHORIZED BY THE E.D.

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FNP-0-EIP-14.0 09/24/02 12:23:52 7.12 Emergency situations may transcend the normal requirement of maintaining personnel exposures below 10CFR20 limits, as noted in step 7.10. Emergency exposures shall be minimized to every degree practicable. Farley Nuclear Plant personnel who have completed the onsite radiation protection training may be required to receive an exposure up to 25 rem TEDE for the activity and conditions described below. For those same personnel to receive in excess of 25 rem, they must voluntarily agree to receive an emergency dose in excess of 25 rem, but less than 100 rem. Persons volunteering to receive in excess of 25 rem must be made fully aware of the risks involved. Emergency exposure limits are as follows:

TEDE ACTIVITY CONDITION DOSE 10 REM PROTECTING VALUABLE LOWER DOSE NOT PRACTICAL PROPERTY 25 REM LIFE SAVING OR PROTECTION LOWER DOSE NOT PRACTICAL OF LARGE POPULATIONS

>25, <100 LIFE SAVING OR PROTECTION VOLUNTEERS ONLY THAT ARE REM OF LARGE POPULATIONS FULLY AWARE OF THE RISKS INVOLVED Limit the dose to the lens of the eyes to 3 times the listed value. Limit the dose to other organs, including skin and extremities to 10 times the listed values.

NOTE: THERE IS CURRENTLY NO METHOD AVAILABLE TO ASSESS INTERNAL EXPOSURE ON A REAL TIME BASIS; THEREFORE, FARLEY NUCLEAR PLANT WILL UTILIZE AN ADMINISTRATIVE DEFAULT CORRECTION FACTOR OF TWO TO RELATE DEEP DOSE TO EXTERNAL EXPOSURE.

7.13 If an internal hazard is present, the limit for the re-entry should be reduced by a factor of two, unless a compensatory measure has been used to eliminate the internal hazard.

8.0 Requirements for Re-entry - Specific Guidance 8.1 The Emergency Director must verbally approve all re-entries.

8.2 The ED must approve doses that exceed the 10CFR20 limits of step 7.10.

8.3 The HP Manager or ED will complete the applicable portions of section II of the re-entry Guideline.

8.4 The HP Manager or designee will complete section IV of the Re-Entry Guideline.

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09/24/02 12:23:52 FNP---EIP-14.0 8.5 The OSC Manager or Maintenance Manager (or ED, if OSC and Maintenance Manager are not available) will coordinate the re-entry and complete sections III and VI of the Re-Entry Guideline.

8.6 Re-Entry personnel shall:

8.6.1 Don necessary protective/emergency clothing and devices as prescribed in the re-entry guideline.

8.6.2 Perform assigned duties in the emergency area as quickly and safely as possible.

8.6.3 Report to the OSC Manager or TSC staff any unexpected conditions which may seriously affect their assigned duties.

8.6.4 Without delaying the mission or causing unnecessary exposures, monitor the dose rate along the route followed to obtain radiological information, as appropriate.

8.6.5 Frequently observe personal dosimeters and withdraw to a safe area prior to reaching an established dose limit, as applicable.

8.6.6 Upon exiting, follow established self-monitoring and personnel decontamination procedures, as necessary, under the supervision of the individual charged with health physics monitoring.

8.6.7 Record and report to the OSC Manager or TSC staff the radiological conditions, damage assessments, or any actions taken in the emergency area.

8.6.8 Complete applicable sections of the re-entry guideline.

9.0 Site Evacuation 9.1 Site Evacuation can be accomplished in one of the following two ways:

9.1.1 Site dismissal of non-involved personnel without monitoring.

This method can be used to perform an organized withdrawal of personnel that are not involved in combating the casualty to an offsite location during an emergency condition when there is no emergency radioactive release in progress.

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09/24/02 12:23:52 -* FNP-0-EIP-14.0 9.1.2 Site dismissal of non-involved personnel with monitoring.

This method can be used to perform an organized withdrawal of personnel that are not involved in combating the casualty to an offsite location during an emergency condition when there is an emergency radioactive release in progress.

9.2 Involved personnel that should remain on site. Those individuals that will be required for relief and long term staffing should be released as appropriate.

"* Personnel on the on call memo as Emergency Response Organization staff.

"* Health Physics staff, including contractors that are qualified to perform HP technician duties.

"* Chemistry staff that are qualified to'perform Chemistry technician duties.

"* Operations staff that are required for safe operation of the plant.

"* Maintenance personnel necessary to mitigate the consequences of the event.

"* Warehouse personnel necessary to support maintenance activities.

"* Security staff required to maintain appropriate site security.

"* Personnel that have been augmented to any of the emergency response facilities or other areas of the plant to help control the plant.

9.3 Non-involved personnel that should routinely be dismissed from the site include:

"* Personnel that are not currently qualified as radiation workers.

"* Contractors and vendors except as noted above.

", Visitors

"* Individuals that will be required for relief and long term staffing.

"* Personnel that are not required for safe operation of the plant or mitigating the effects of the event.

9.4 Site dismissal should be considered any time there is a declared emergency with a potential for escalating to the point where there is hazard to on site personnel.

9.5 Emergency Director shall authorize site dismissals and appoint an individual to coordinate the dismissal.

9.6 If the EOF is staffed when a site dismissal is required, the Emergency Director should normally request that the EOF coordinate the dismissal.

9.7 If there is an emergency radiological release in progress, go to step 9.9 to conduct a site dismissal of non-involved personnel with monitoring.

9.8 If there is no emergency radiological release in progress, conduct a site dismissal of non-involved personnel without monitoring as follows.

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09/24/02 12:23:52 r"T T T *, FNP-0-EIP-14.0 9.8.1 Confer with Houston County EMA and Early County EMA and determine if there are any off-site concerns with dismissing personnel from the site at this time.

9.8.2 Determine off site routes. Unless there have been restrictions placed on routes by the Houston County or Early County EMA, there should be no restrictions on off site routes.

9.8.3 Determine the on site exit routes using Figure 5. The roads leading to the north and south gates may have road blocks in place to prevent unauthorized access. Contact security to open access to these routes if they will be used. Access can be opened rapidly if it is required.

9.8.4 Contact management/supervision for groups or departments on site and determine who is considered to be non-involved in the current emergency, using the guidance of steps 9.2 and 9.3.

9.8.5 Inform security of the intent to dismiss personnel and authorize their exit from the site.

9.8.6 Inform the personnel that have been designated as non involved of:

"* The on site exit routes

"* Off site route restrictions

"* Directions on what to do after exiting the site such as stand by home phones, call in at a specific time, etc

"* Provide any other specific guidance required based on plant conditions.

9.8.7 Inform designated non-involved personnel that they are dismissed with the instructions of step 9.8.6.

9.9 If there is an emergency radiological release in progress, conduct a site dismissal of non-involved personnel with monitoring as follows.

9.9.1 Prior to ordering a site dismissal of non-involved personnel with monitoring, the following items should be considered along with other extenuating circumstances:

"* Will individual dose be greater for leaving the site or sheltering?

"* When will the off-site authorities be able to cope with the traffic flow?

"* When will the off-site authorities be able to cope with the influx of people to the de-contamination and reception centers?

"* What is the availability of food and supplies if no dismissal is ordered?

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09/24/02 12:23:52 TT A- FNP-O-EIP-14.

"* What will be the effect on plant personnel and families if no dismissal is ordered?

"* What personnel will be required on site for effective plant operation and recovery?

9.9.2 Confer with Houston County EMA and Early County EMA and determine the off-site concerns with dismissing personnel from the site at this time.

Coordinate the dismissal time with Houston County EMA and Early County EMA.

9.9.3 Determine the off site routes and the reception center locations to send plant personnel to for monitoring and possible decontamination from Houston County EMA and Early County EMA. The reception center in Houston County will normally be the Wiregrass Recreation Center or the Houston County Farm Center. The reception center in Early County will normally be the Early County High School. Figures 6 and 7 can be used as aids.

9.9.4 Determine the on site exit routes using Figure 5. The roads leading to the north and south gates may have road blocks in place to prevent unauthorized access. Contact security to open access to these routes if they will be used. Access can be opened rapidly if it is required.

9.9.5 Contact management/supervision for groups or departments on site and determine who is considered to be non-involved in the current emergency, using the guidance of steps 9.2 and 9.3.

9.9.6 Confer with Health Physics to determine if on site monitoring prior to leaving the site is ALARA and appropriate, or if dispatch to the reception centers off site without on site monitoring is appropriate.

9.9.7 If on site monitoring is appropriate prior to being dismissed, designate locations for the on site monitoring to be accomplished for personnel from the protected area and personnel from outside the protected area.

9.9.8 Inform security of the intent to dismiss personnel and authorize their exit from the site.

9.9.9 Inform personnel that have been designated as non involved of:

• where to go to get monitored on site if appropriate.

• the on site exit routes.

• off site route and what reception center to go to.

• directions on what to do after leaving the reception center such as stand by home phones, call in at a specific time, etc.

• provide any other specific guidance required based on plant conditions.

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09/24/02 12:23:52 _ ,, T¢ 7> FNP-0-EIP-14.0 9.9.10 Inform designated non-involved personnel that they are dismissed with the instructions of step 9.9.9.

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FNP-0-EIP-14.0 TABLE 1 PERSONNEL MOVEMENT, RELOCATION, RE-ENTRY AND SITE EVACUATION REFERENCES 0 Joseph M. Farley Nuclear Plant Emergency Plan S EPA Emergency Worker and Lifesaving Activity Protective Action Guide 0 IE Information Notice No. 84-40: Emergency Worker Doses 0 NCRP No. 91 0 SNC EPA 400 Manual Interpretation Document J. D. Woodard to D. N. Morey, June 7, 1994 TABLE 1 Page 1 of 1 Version 17

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FNP-0-EIP-14.0 TABLE 2 PERSONNEL MOVEMENT, RELOCATION, RE-ENTRY AND SITE EVACUATION RISKS ASSOCIATED WITH ACUTE HIGH LEVEL RADIATION EXPOSURE HEALTH EFFECTS ASSOCIATED WITH WHOLE BODY ABSORBED DOSES RECEIVED WITH A FEW HOURS*

WHOLE BODY ABSORBED Forewarning Symptoms of More Serious Health Effects DOSE (RAD) Associated with Large Doses of Radiation (PERCENT AFFECTED) 50 2%

100 15%

APPROXIMATE CANCER RISK TO AVERAGE INDIVIDUALS FROM 25 REM EFFECTIVE DOSE EQUIVALENT, DELIVERED PROMPTLY*

AGE AT EXPOSURE APPROXIMATE RISK OF AVERAGE YEARS OF LIFE (YEARS) PREMATURE DEATH LOST IF PREMATURE (DEATHS PER 1,000 DEATH OCCURS PERSONS EXPOSED) (YEARS) 20 TO 30 9.1 (.91%) 24 30 TO 40 7.2 (.72%) 19 40 TO 50 5.3 (.53%) 15 50 TO 60 3.5 (.35%) 11 PROMPT EFFECTS OF ACUTE RADIATION EXPOSURE**

ACUTE DOSE REM PROBABLE CLINICAL EFFECT 0-25 No observable effects.25-100 Slight blood changes, no other observable effects.

100-200 Vomiting may occur in 5 to 50% within three hours, with fatigue and loss of appetite. Moderate blood changes are likely. Except for the blood forming organs, recovery will occur in essentially all cases within a few weeks.

• REFERENCE EPA 400 MANUAL

• • REFERENCE INPO GUIDANCE TABLE 2 Page 1 of 1 Version 17

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• FNP-0-EIP-14.0 FIGURE 1 RELOCATION GUIDELINE RELOCATION #

DESCRIPTION:

RELOCATION FROM:

RELOCATION TO:

DUTIES:

ESTIMATED TIME TO COMPLETE:

TRANSIT ROUTE:

HP REQUIREMENTS: THE MAXIMUM ALLOWED DOSE FOR THE RE-ENTRY IS FIVE REM, INCLUDING PREVIOUS EXPOSURE FOR THE YEAR.

IF AN EXTERNAL HAZARD IS INVOLVED, EXTERNAL DOSE LIMIT SHOULD BE REDUCED BY A FACTOR OF TWO.

DOSE LIMIT: HP MGR/ED APPROVAL IF >1 REM:

(N/A IF NO RAD HAZARD)

OTHER HP REQ:

PERSONNEL:

Continued on Additional Sheet APPROVAL:

TIME OUT:____________ TIME IN:.

CALL BACK PHONE NUMBER:

COMMENTS:

FIGURE 1 Page 1 of 1 Version 17

09/24/02 12:23:52 FNP-0-EIP-14.0 FIGURE 2 RELOCATION LOG SHEET #

TIME Start Return from DESCRIPTION Re-Loc Re-Loc FIGURE 2 Page 1 of 1 Version 17

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, g 7....' FNP-0-EIP-14.0 x FIGURE 3

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RE-ENTRY GUIDELINE RE-ENTRY FOR: RE-ENTRY #

UNIT # DATE/TIME W* 8*w

/

THE STEPS OF THIS GUIDELINE MAY BE DONE IN ANY ORDER PRIOR SNOTE: I TO DISPATCHING THE RE-ENTRY TEAM.

INOE OSC MANAGER SECTION I A. Obtain ED verbal approval for the reentry.

OSC MGR B. Select qualified personnel for the re-entry.

OSC MGR

• team leader C. Specify duties for re-entry:

OSC MGR (notes if desired)

D. Specify transit route (discuss):

OSC MGR (notes if desired)

E. Specify communications and actions OSC MGR to take if communications cannot be established:

call back number 1. 2.

gaitronics radio F. Dispatch re-entry team when HP requirements OSC MGR per page 2 are met and brief per page 3 is complete.

FIGURE 3 Page 1 of 4 Version 17

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. FIGURE 3 HEALTH PHYSICS SECTION II A. Specify dose and dose rate limits.

HP APPROVED DOSE:

APPROVED DOSE RATE:

B. Authorize dose limits less than 10CFR20 limits and greater than admin limits per HP MGR paragraph 7.10.

C. Authorize dose limits greater than I0CFR20 limits in paragraph 7.10.

ED E. Have re-entry personnel complete appropriate sections of re-entry individual HP exposure record including signing the form if IOCFR20 limits will be exceeded and complete Re-Entry Individual Exposure Record.

D. Verify that the approved dose will not cause the individual(s)to exceed FNP HP HP admin limits unless approved by HP manager or IOCFR20 limits unless approved by the ED.

E. For doses in excess of 25 rem, the following two steps must be performed:

I. Verify that the individual to receive the dose is a volunteer.

HP MGR

2. Ensure that the individual to receive the dose has been briefed and is fully HP MGR aware of the risks involved. (Use table 2 as guidance for the brief.)

F. Are Thyro Block (KI) tablets required? []yes []no (Ref FNP-0-EIP-4.0, Fig 3)

HP MGR G. Specify appropriate protective clothing and monitoring devices.

HP STREET CLOTHES f SINGLE W/B TLD STD LABCOAT DRESSOUT MULTIBADGE STD CVRALL DRESSOUT EXT TLDJI HANDS ] FEET

] CLOTH D PAPER [] PLASTICPICS [] 200MR [j 2R [ 5R SCBA DDAD OTHER RESPIRATOR OTHER FIGURE 3 Page 2 of 4 Version 17

09/24/02 12:23:52 FNP-0-EIP-14.0 FIGURE 3 COMBINED BRIEF SECTION Conduct a pre-job brief of the Re-Entry. The following information must be included:

"* Duties for the re-entry including required procedures and safe work practices. Reference the OSC managers section and the re-entry duties section.

"* Hazards associated with the assigned tasks (Radiological and Non Radiological)

"* Dose and dose rate limits while performing the re-entry (per Health Physics section)

"* Personnel protective equipment required (per Health Physics section if radiological)

"* Isolation and control of energy sources (Clearance)

"* Special support needs and precautions

"* Transit route. It is acceptable for the team to modify the transit route based on the conditions encountered during the re-entry. If the route is modified, the OSC or control room should be notified as soon as possible if the change places the team in areas that are not on the route.

"* Communications and actions to take if communications cannot be established The following information may be considered in the pre-job briefing:

"* Industry experience

"* Plant or equipment conditions including potential radiological or industrial safety hazards and precautions

"* Each person's job or task assignment

"* Expected sequence of events and results

"* Problems to be anticipated

"* Criteria to be used to stop the evolution

"* Contingencies if the evolution is stopped or the expected result is not achieved

"* Potential distractions and how they will be minimized

"* Housekeeping and fluid system cleanliness requirements

"* Chemical control and disposal requirements

"* Foreign Material Exclusion (FME) Controls FIGURE 3 Page 3 of 4 Version 17

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• FNP-0-EIP-14.0

- .... -, - - - i- j.. FIGURE 3 RE-ENTRY TEAM SECTION IT IS NOT REQUIRED FOR THE RE-ENTRY TEAM TO KEEP A COPY OF I INOTE:

I NOTE THIS FORM WITH THEM DURING THE RE-ENTRY. I A. Monitor dose and dose rate and retreat to a safe area if limits are exceeded.

Team B. Report unexpected conditions to the TSC or OSC as applicable.

Team C. Monitor and record dose rates along re-entry route without delaying the Team mission or causing unnecessary exposure.

D. Report to the TSC or OSC as applicable, radiological conditions, damage Team assessment or any actions taken during the re-entry.

E. Perform the task assigned to the re-entry team.

Team DEBRIEF SECTION A. Debrief re-entry personnel.

OSC MGR B. Report debriefed information to the appropriate staff in the TSC.

OSC MGR FIGURE 3 Page 4 of 4 Version 17

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FNP-0-EIP-14.0 s-- .

FIGURE 4 RE-ENTRY LOG SHEET#

TIME Start Return from DESCRIPTION Re-entry Re-entry FIGURE 4 Page 1 of 1 Version 17

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FIGURE 5 ON-SITE EVACUATION ROUTES, ASSEMBLY AREAS, AND OPERATIONS SUPPORT CENTER LEGEND OPERATION SUPPORT CENTER ALTERNATE ASSEMBLY AREAS 1 BREAKROOM OUTSIDE TSC 11 PARKING LOT SOUTH OF S.B.

12 CONTRACTOR PARKING LOT ASSEMBLY AREAS 13 SWITCHHOUSE PARKING LOT 14 BETWEEN 2A & 2B COOLING 2 CONTROL ROOM TOWERS 3 TSC 15 UTILITY BUILDING 4 SERVICE BUILDING AUDITORIUM 16 SE CORNER OF CONTROL ROOM 5 MAINTENANCE SHOP 17 EMPLOYEE PARKING LOT 6 CSC 18 BREAKROOM NEAR PAP 7 VISITORS CENTER AUDITORIUM 19 HP OFFICE AREA 8 EOF 9 SWITCH HOUSE EVACUATION ROUTES 10 FABRICATION SHOP 20 21 WAREHOUSE RECEIVING AREA OUTAGE SUPPORT BUILDING 4-@h FIGURE 5 Page 1 of 1 Version 17

09/24/02 12:23:52 Ac -1 7-1 -4 FNP-0-EIP-14.0 FIGURE 6 OFF-SITE EVACUATION ROUTES

-25 Dothan Airport Flowers Hospital Al Chattahoochee River FIGURE 6 Page 1 of 1 Version 17

09/24/02 12:23:52 *{7 FNP-0-EIP-14.0 FIGURE 7 LOCATION OF RECEPTION CENTERS IN HOUSTON COUNTY FIGURE 7 Page 1 of 1 Version 17

09/24/02 10:47:04 r ~~- FNP-0-EIP- 10.0 September 24, 2002 Version 33 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE FNP-0-EIP- 10.0 S

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PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use Reference Use Sections 8.5, 8.7, 9.3, 9.4, 9.5, 9.6, 9.7, 9.8 Information Use Remainder of Procedure UNCONTROPLLED COPY CAUTION: Th-h-c i3not maintaine Approved: Current. Do not use in a Saiýty Related Activity Nuclear Plant General Manager Date Issued" 'O

- S I - -'- FNP-O-EIP-10.0 09/24/02 10:47:04 INDEX BY SECTION Procedure Contains Number of Pages Body Table 1 13 1 I 1

Figure 1 1

Figure 2 1

Figure 3 1

Figure 4 1

Figure 5 1

Figure 6 Page 1 of 1

09/24/02 10:47:04 t-ý 7,- FNP-0-EIP- 10.0 EVACUATION AND PERSONNEL ACCOUNTABILITY TABLE OF CONTENTS Section Title Page 1.0 Purpose 1 2.0 References 1 3.0 Designated Assembly Areas 1 4.0 Assembly Area Assignments 2 5.0 Individual Responsibility 6 6.0 General Evacuation 6 7.0 Accountability 7 8.0 Operations Support Center and Protected Area Assembly 7 Areas Accountability - Initial Accountability 9.0 Outside Protected Area Assembly Areas Accountability - 10 Final Accountability 10.0 Local Evacuation 12 11.0 Evacuation of Plant Site 12 12.0 Use of the Plant Emergency Alarm (PEA) Warble Tone, 12 Siren, and Pulse Tone 13.0 Eating, Drinking, and Smoking Policy for Assembly Areas 13 Table 1 References Figure 1 Onsite Evacuation Routes/Operations Support Centers/

Assembly Areas Figure 2 Protected Area Accountability Page 1 of 2 Version 33

09/24/02 10:47:04 NP-0-EIP- 10.0 EVACUATION AND PERSONNEL ACCOUNTABILITY TABLE OF CONTENTS Section Title Page Figure 3 Protected Area Accountability Contingency Plan Figure 4 Outside Protected Area Accountability Figure 5 CSC Final Accountability Log Figure 6 Accountability Flow Chart

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09/24/02 10:47:04 ' FNP-0-EIP-10.0 g

EVACUATION AND PERSONNEL ACCOUNTABILITY 1.0 Purpose This procedure describes the action to be taken for the evacuation and accountability of all personnel onsite, in the event of an emergency at the Farley Nuclear Plant.

2.0 References See Table 1 3.0 Designated Assembly Areas For purposes of site evacuation and personnel accountability, the following areas (as shown in Figure 1) are designated as Assembly Areas:

OPERATIONS SUPPORT CENTER PAX EXT

1. Break Room Outside TSC 2448 PRIMARY ASSEMBLY AREAS Protected Area Assembly Areas

2. Control Room 2353

3. Technical Support Center (TSC) 6018

21. Outage Support Building (OSB) 4873 Outside Protected Area Assembly Areas

4. Service Building Auditorium 2236

5. Service Building Maintenance Shop 4357/2240

6. Central Security Control (CSC) 2438

7. Visitors Center Auditorium 6158

8. Emergency Operations Facility 6156

9. Switchhouse 2321

10. Fabrication Shop 3578/3468

20. Warehouse Receiving Area 4645

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09/24/02 10:47:04 T7 A' T -%, Tt FNP-0-EIP- 10.0 Alternate Assembly Areas NOTE: EXTRA PERSONNEL FROM THE OSC MAY BE RELOCATED TO THE BREAKROOM NEAR THE PAP, THE SE CORNER OF THE CONTROL ROOM, AND THE HP OFFICE AREA BY THE OSC MANAGER. OTHER ALTERNATE ASSEMBLY AREAS MAY BE USED AT THE ED's DISCRETION.

11. Parking Lot South of Service Building

12. Contractor Parking Lot

13. Switchhouse Parking Lot

14. Area between the 2A and 2B Cooling Towers

15. Utility Building 4502

16. SE Comer of Control Room 2306

17. Employee Parking Lot

18. Breakroom near PAP 2405

19. HP Office Area 2334 4.0 Assembly Area Assignments 4.1 On-Call Personnel assigned to a position with the emergency response organization will report to their designated emergency response facility as described in FNP-0-EIP-6.0 or FNP-0-EIP-27.0, instead of assembling with their work group.

4.2 Personnel that are on site and assigned to a position with the emergency response organization on the on-call memo, but not currently in an on-call status will also report to their designated emergency response facility. After it has been determined if these individuals are needed to augment the facility staff or will be required to be available for a long term relief they may be relocated or evacuated offsite as necessary.

4.2.1 Accountability in the EOF shall include those personnel that are in the on call memo assigned to the EOF that are known to be on-site at the time of accountability or other personnel that have been augmented or assigned to the EOF for duty.

4.3 On-shift personnel with a specific function assigned in FNP-0-EIP-0.0 will report to the area described, or perform the described function instead of assembling with their work groups.

4.4 Escorted visitors will remain with their escort and report to the sa.me assembly area as their escort.

4.5 Other visitors/contractors on site will report to the assembly area designated for the on-site work group with whom they are working.

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09/24/02 10:47:04 FNP-0.EIP.10.0 S4.6 Personnel assigned to training at the Training Center or the Fire Training Facility will assemble in the Visitors Center Auditorium instead of with their work groups.

4.7 Operations, Chemistry, Environmental and Health Physics On Shift staff involved in training anywhere on site except the Training Center or Fire Training Facility will report to the breakroom outside the TSC.

4.8 Personnel who have been assigned to augment the TSC or EOF staffs will remain at that location for accountability. The senior individual in their normal assembly area should be notified as soon as possible, when time permits.

4.9 On shift security will remain on station until relocation is required. Relocation will normally be controlled by FNP-0-EIP-14.0. If, due to a personal hazard, security personnel must evacuate their station, security supervision will be notified as soon as possible to implement the guidance of FNP-0-EIP-14.0.

4.10 NRC Inspectors will assemble in any one of the assembly areas as appropriate for plant and emergency conditions.

4.11 Individuals in the following work groups who are not described above will report to the designated assembly area as indicated by the number that corresponds to the assembly area numbers assigned in step 3.

Work Group Assembly Area Administrative Staff assigned to 4 Administrative Assistant Administrative Staff assigned to Support Building 10 Cafeteria Staff 4 Chemistry and Env. Staff (Off Shift) 4 Chemistry and Env. Staff assigned to the EOF 7 Chemistry and Env. Staff (On Shift) 1 Contractor Personnel Assigned to Outage and Modification 10 Document Control Staff 4 Engineering Support Staff 10 EOF Staff (as assigned in FNP-0-EIP-27.0) 8 Version 33

09/24/02 10:47:04 ,? . V- -' 7 FNP-0-EIP-10.0 Facilities Staff 4 Financial Services 10 Fitness for Duty Facility Staff 7 Health Physics Staff 1 Health Physics Support Staff (On & Off Shift) 1 Information Management Systems Staff 4 Maintenance Contractor (not Williams) 5 Maintenance Supervision and Staff 5 Maintenance Teams 1 through 8 5 Maintenance Team 9 10 Material Dept. Personnel not assigned to the SB Cold Tool Room 20 Material Dept. Personnel assigned to the SB Cold Tool Room 5 NRC Administrative Staff 4 Operations Staff (off shift) 4 Operations-OATC (assigned post) 2 Operations-Shift Supervisors (assigned post) 2 Operations-Shift Technical Advisor 2 Operations-Unit Operators (assigned post) 2 Operations Staff (other on shift) 1 Outage and Modification - Outage Staff 4 Outage and Modification - Modification Staff 10 Quality Control Personnel 20 Version 33

09/24/02 10:47 ~:04 F1NP-0-EIP- 10.0 4

Safety Audit and Engineering Review 10 Satellite Document Control Staff 6

Security Staff Off Shift 10 Special Projects Staff 7

State and County Agency Personnel 5

Students participating in Training Activities at the Maintenance Training Area (SAER 2001-Q&T/14-2) 7 Students participating in Training Activities at the Training Center or Fire Training Facility 9

Switchboard Operator (assigned station)

Switchhouse Staff 9 7

Training Center Staff 5

Training Center Staff assigned to the Maintenance Training Area 3

TSC Staff (as assigned in FNP-0-EIP-6.0) 7 Visitors in the Visitors Center (Responsibility of the VC Staff) 7 Visitors Center Staff 5

Siemens-Westinghouse Turbine Group Personnel 10 Westinghouse NSSS Personnel 10 Williams Personnel Personnel, in a non-work status, engaged in sporting or other recreational activities 7

if the Visitor Center is open 4

if the Visitor Center is closed 4

Any other personnel on site and not previously listed in this procedure Version 33

09/24/02 10:47:04 TY , 7 FNP-O-EIP-0.0 5.0 Individual Responsibility 5.1 All personnel shall familiarize themselves with the location of their particular assembly area.

5.2 Personnel who report to an assembly area shall assemble according to groups to facilitate accurate and timely accountability.

5.3 When reporting to an assembly area, personnel should avoid any route or area of the plant which has been declared part of the emergency or which could result in excessive radiation exposure or personal injury.

5.4 Personnel who have been in the emergency area shall remain segregated from other personnel in the assembly area until they have been monitored for possible contamination, if applicable.

5.5 Each plant supervisor or senior individual onsite from each group shall be responsible for accounting for all persons working in or visiting his group.

5.6 When evacuating the Radiation Control Area (RCA), attempt to remove the outer layer of protective clothing before proceeding to the assembly area.

5.7 Personnel exiting the RCA wearing protective clothing during an evacuation should make every reasonable effort to avoid contaminating equipment, walls, floors and other personnel.

5.8 When accountability is required, personnel who enter the Fabrication Shop assembly area are not required to have on hard hat and safety glasses as long as they stay between the yellow lines of the walkway within the building. The senior individual in the assembly area can relax the requirements for hard hat and safety glasses within the rest of the assembly area after determining that there is no safety hazard present that would require their use.

6.0 General Evacuation 6.1 A general evacuation is initiated by sounding the plant emergency alarm (warble tone) for approximately 30 seconds and announcing for all personnel to report to their designated assembly areas.

6.2 If extenuating circumstances prohibit sounding the plant emergency alarm, a general evacuation can be initiated by announcing it over the public address system.

6.3 A general evacuation is required any time a Site Area Emergency or a General Emergency have been declared.

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09/24/02 10:47:04 it ,

T TFN*--0-EIP-10.0 "6.4 The Emergency Director can, at his discretion, initiate a general evacuation at any time as a precautionary measure.

6.5 When a general evacuation has been announced, all plant personnel will report to their designated assembly areas as described in steps 3, 4 and 5 of this procedure.

6.6 When a general evacuation has occurred, accountability will be performed per step 7.0 of this procedure.

7.0 Accountability Accountability shall be performed whenever a general evacuation has been ordered by the Emergency Director and announced over the public address system. The announcement of a general evacuation will normally be followed by activating the Plant Emergency Alarm (warble tone) for a minimum of 30 seconds.

8.0 Operations Support Center and Protected Area Assembly Areas Accountability Initial Accountability Technical Support Center Control Room Breakroom Outside TSC Outage Support Building NOTE: DUE TO THE REQUIREMENT FOR REPORTING ACCOUNTABILITY IN 30 MINUTES AND THAT ANY MOVEMENT IN THE PLANT MUST BE GUIDED BY FNP-0-EIP-14.0, DO NOT DELAY REPORTING "ACCOUNTABILITY COMPLETE" TO THE EMERGENCY DIRECTOR WHILE SEARCHING FOR MISSING INDIVIDUALS.

8.1 Initial accountability will be considered complete when the individuals who are missing in the protected area are reported to the Emergency Director by the total number of missing personnel and their names.

8.2 Initial Accountability must be complete for the protected area within 30 minutes of announcing a general evacuation.

8.3 Individuals that are to assemble in a Protected Area Assembly Area shall swipe into the Biometrics card readers with their Protected Area Badge in their designated assembly area when the plant emergency alarm has been actuated or a general evacuation has been announced.

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09/24/02 10:47:04 '7 T' f " FNP-0-EIP-10.0 8.4 Personnel that are required to remain at a particular location that is within the Control Room, can have their Protected Area Badge swiped into the biometrics card reader by security when accountability is required. The Protected Area Badge should be returned to the owner as soon as possible.

8.5 Security shall:

8.5.1 Account for security at posts in the protected area by direct communication or messenger.

8.5.2 Dispatch security to the Control Room to assist in accountability. Security may collect the protected area badges from those individuals in the control room that may not be able to leave their post, and swipe those individuals into the biometrics card reader in the control room. The badges should be returned to the individuals as soon as possible.

8.5.3 Note the time that the plant emergency alarm was activated or when a general evacuation was announced to determine when the report of accountability should be sent to the TSC.

8.5.4 Twenty minutes after the plant emergency alarm has been actuated or assembly and accountability have been announced, provide the Emergency Director with an emergency accountability report per FNP-0-SP-36 (PLANT SECURITY COMPUTER SYSTEM AND CENTRAL ALARM STATION/SECONDARY ALARM STATION OPERATIONS).

8.5.5 In the event of a failure of the computer that would prevent performing accountability, inform the OSC, TSC, and outside the protected area assembly areas listed in step 3 that protected area accountability must be performed per the Protected Area Accountability Contingency Plan specified in step 8.7.

8.5.6 Ensure that no one except those with emergency duties enters the protected area without the permission of the Emergency Director or designee.

8.5.7 Take other actions for general evacuation and accountability as described in FNP-0-EIP-7.0.

8.6 The Emergency Director shall:

8.6.1 Upon receipt of the initial accountability report, have the location of the missing individuals determined.

8.6.2 Have teams activated to search for the missing individuals, using the guidance of FNP-0-EIP- 14.0.

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09/24/02 10:47:04 FNP-0-EIP-10.0 8.7 Protected Area Accountability Contingency Plan The following steps shall be performed when the Protected Area Accountability Contingency Plan is required:

8.7.1 The senior individual in each of the outside the protected area assembly areas will perform accountability in the normal manner, but will ensure the results are reported within approximately twenty minutes of the time that the plant emergency alarm was activated or the public address announcement was made.

8.7.2 The senior individual in the OSC will have the senior individuals for Operations, Chemistry, Health Physics, and Health Physics Support report the names of individuals that are on site for their group, should have assembled in the protected area and are missing. The senior individuals for these groups should take into account personnel that may be in the TSC or Control Room. (Figure 3 may be used as an aid.)

8.7.3 The senior individual in the OSC will determine from the TSC staff any individuals from the TSC staff that may not be accounted for. (Figure 3 may be used as an aid.)

8.7.4 The senior individual in the OSC will determine from the Control Room staff any individuals from the control room that may not be accounted for.

(Figure 3 may be used as an aid.)

8.7.5 The senior individual in the OSB shall report to the OSC the names of individuals that are on site for their group, should have assembled in the protected area and are missing.

8.7.6 Within twenty minutes after the plant emergency alarm is activated or the public address announcement is made, the senior individual in the OSC will report to the ED or the Shift Supervisor the names of personnel that are missing. (Figure 3 may be used as an aid.)

8.7.7 Accountability for the protected area and outside the protected area, will be complete when names of the missing individuals from all assembly areas are reported to the Emergency Director.

8.7.8 The ED or Shift Supervisor will take steps to locate any missing individuals per step 8.6. All missing personnel may be in the protected area for this type of accountability.

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09/24/02 10:47:04 - 10:47:04 09/24/02 -* L

-, FNP-0-EIP- 10.0 V ]

9.0 Outside Protected Area Assembly Areas Accountability - Final Accountability Service Building Auditorium 2236 Service Building Maintenance Shop 4357/2240 Central Security Control (CSC) 2438 Visitors Center Auditorium 6158 Emergency Operations Facility 6156 Switchhouse 2321 Fabrication Shop 3578/3468 Warehouse Receiving Area 4645 NOTE: DUE TO THE REQUIREMENT FOR FINAL ACCOUNTABILITY BEING REPORTED AS SOON AS POSSIBLE AND ANY MOVEMENT ON THE PLANT SITE MUST BE GUIDED BY FNP-0-EIP-14.0, DO NOT DELAY REPORTING "ACCOUNTABILITY COMPLETE" TO THE EMERGENCY DIRECTOR WHILE SEARCHING FOR MISSING INDIVIDUALS.

9.1 Final accountability will be considered complete when the individuals who were known to be on site and are missing are reported to the Emergency Director by the total number of missing personnel and their names.

9.2 Final accountability should be completed for the plant site as soon as possible after announcing a general evacuation.

9.3 The Recovery Manager Assistant or senior individual in the EOF will report the names of individuals who are known to be on site, who are assigned to the EOF and are missing, to the CSC. Figure 4 may be used as an aid.

9.4 The senior Outage and Modification (0 & M) individual in the Fabrication Shop will coordinate with the contractor supervision and management to identify all contractors on site who should have reported to the Fabrication Shop and are missing. Time cards, personnel knowledge or other documentation may be used.

When the list of missing individuals has been compiled, the senior 0 & M individual will report the names of the missing to the CSC. Figure 4 may be used as an aid.

9.5 The senior individual in the Visitors Center Auditorium should contact the EOF or TSC staff to arrange evacuating visitors in the Visitors Center Auditorium as soon as possible.

9.6 The senior individual in an assembly area for each work group will determine the accountability of the individuals in their work group or visiting their work group, and report any missing individuals to the senior individual in the assembly area.

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09/24/02 10:47:04 ( FNP-0-EIP--0.0 9.7 The senior individual in each assembly area will compile a list of names of individuals known to be on site who are missing from their assembly area, when the list of missing individuals has been compiled, the senior individual will report the names of the missing to the CSC. Figure 4 may be used as an aid.

9.8 Security shall:

9.8.1 Account for security on posts outside the protected area by direct communication or messenger.

9.8.2 Contact the following locations and inform them of assembly requirements.

Outage Modification - 3545 Westinghouse - 2479 Warehouse - 3391 9.8.3 Account for security assembled in the CSC.

9.8.4 Assemble the names of persons missing from all of the assembly areas outside the protected area. Figure 5 may be used as a guide.

9.8.5 Report that security has completed final accountability to the Emergency Director, providing the ED with the number of individuals who are missing on the plant site outside of the protected area, and the names of the missing individuals. Figure 5 may be used as an aid.

9.8.6 Take other actions for general evacuation and accountability as described in FNP-0-EIP-7.0.

9.9 The Emergency Director shall:

9.9.1 Upon receipt of the final accountability report, have the location of the missing individuals determined.

9.9.2 Have teams activated to search for the missing individuals using the guidance of FNP-0-EIP-14.0.

NOTE: INITIAL AND FINAL ACCOUNTABILITY DO NOT NEED TO BE COMPLETED PRIOR TO PERFORMING THE REMAINING SUBSTEPS OF STEP 9.9 BELOW.

9.9.3 Authorize release of News Media Center personnel.

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09/24/02 10:47:04 FNP-0-EIP-10.0 9.9.4 Direct non-essential personnel (including children and casual visitors) to depart from the site. Limit the exposure of visitors and pregnant females consistent with the radiation exposure situation.

9.9.5 Provide for transportation for persons without vehicles.

9.9.6 Provide clothing for personnel found to be contaminated.

10.0 Local Evacuation 10.1 All personnel in the affected area shall stop work, render safe any hazardous equipment and leave the area by the most direct route to the assembly area unless otherwise instructed by the Control Room.

10.2 The Shift Supervisor or ED will activate emergency teams as required to locate and ensure the evacuation of personnel.

10.3 Accountability:

10.3.1 For radiological side Auxiliary Building or Containment evacuation, Health Physics may utilize the Access Control section of the HIS 20 system to account for personnel if requested.

K...' 10.3.2 In the event of local evacuations other than the containment or the radiological side Auxiliary Building, the senior SNC employee present will account for all personnel and notify the Shift Supervisor.

10.3.3 For areas where the number of personnel who may be in the area is not known (e.g., a floor of the turbine building or entire turbine building),

accountability may be affected by a systematic search of the affected area to ascertain all personnel have evacuated.

11.0 Evacuation of Plant Site 11.1 At the Emergency Director's discretion, he can have the plant site evacuated of all unnecessary personnel during an emergency condition.

11.2 If the plant site is to be evacuated, it will be done per FNP-0-EIP-14.0.

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09/24/02 10:47:04 FNP-0-EIP-10.0 12.0 Use of Plant Emergency Alarm (PEA) Warble Tone, Siren, and Pulse Tone 12.1 The warble tone on the plant emergency alarm is reserved for announcing a general evacuation which requires all personnel to report to their designated assembly areas.

12.2 When announcing a general evacuation, a public address announcement should be made providing specific instructions; then, the warble tone should be actuated for approximately 30 seconds. The public address announcement should be repeated.

12.3 The siren on the plant emergency alarm may be used to muster the fire brigade for a drill or an actual fire. The siren may, at the discretion of the Shift Supervisor, be used in unusual circumstances when it is important to get the attention of all personnel on plant site.

12.4 When announcing a fire or other unusual circumstance, a public address announcement should be made providing specific instructions; then, the siren should be actuated for approximately 30 seconds (10 seconds for security events).

The public address announcement should be repeated.

12.5 The pulse tone on the plant emergency alarm may be used to notify the security group of a specific contingency event or events. The pulse tone may be initiated from the Security Secondary Alarm station (SAS), or from the Control Room (at the direction of the Shift Supervisor) if SAS is unable to perform the function.

Security personnel will respond to the pulse tone; no further actions are required by plant personnel unless directed by a public address announcement.

13.0 Eating Drinking and Smoking Policy for Assembly Areas 13.1 Any time the plant emergency alarm (PEA) has been actuated there is a possibility of a radioactive release being in progress. Due to the health risks involved when the PEA has been actuated, eating, drinking, and smoking should be terminated by all personnel on plant site as they go to their designated assembly areas.

13.2 Eating drinking and smoking should not be allowed in the assembly areas until there has been confirmation that there is no radiological release in progress.

13.3 When it has been confirmed that there is no radiological release in progress, eating and drinking in assembly areas may be allowed within normal plant policies and guidelines.

13.4 Personnel should not be allowed to leave the assembly area to go outside and smoke.

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09/24/02 10:47:04 (TT FNP-0-EIP-10.0 TABLE 1 REFERENCES

1. Joseph M. Farley Nuclear Plant Emergency Plan

2. FNP-0-EIP-14.0 - Personnel Movement, Relocation, Re-Entry and Site Evacuation

-° TABLE 1 Page 1 of I Version 33

09/24/02 10:47:04 FNP-0-EIP- 10.0 Ij FIGURE 1 ON-SITE EVACUATION ROUTES, ASSEMBLY AREAS, AND OPERATIONS SUPPORT CENTER LEGEND OPERATION SUPPORT CENTER ALTERNATE ASSEMBLY AREAS I BREAKROOM OUTSIDE TSC 11 PARKING LOT SOUTH OF S.B.

12 CONTRACTOR PARKING LOT ASSEMBLY AREAS 13 SWITCHHOUSE PARKING LOT 14 BETWEEN 2A & 2B COOLING TOWERS 2 CONTROL ROOM 3 TSC 15 UTILITY BUILDING 4 SERVICE BUILDING AUDITORIUM 16 SE CORNER OF CONTROL ROOM 5 MAINTENANCE SHOP 17 EMPLOYEE PARKING LOT 6 CSC 18 BREAKROOM NEAR PAP 7 VISITORS CENTER AUDITORIUM 19 HP OFFICE AREA 8 EOF 9 SWITCH HOUSE EVACUATION ROUTES 10 20 FABRICATION SHOP WAREHOUSE RECEIVING AREA 4-@0 21 OUTAGE SUPPORT BUILDING FIGURE 1 Page 1 of 1 Version 33

09/24/02 10:47:04 FNP-0-EIP-10.0 I

A tL FIGURE 2 PROTECTED AREA ACCOUNTABILITY This figure may be used by security as an aid to report the completion of Protected Area Accountability to the Emergency Director when using the Biometrics system. The report can be made by a phone call to the TSC or sending a runner to the TSC with this figure, a Biometrics computer printout or a blank piece of paper with the names of the missing personnel.

THE PERSONNEL LISTED BELOW ARE IN THE PROTECTED AREA ACCORDING TO THE BIOMETRICS SYSTEM AND ARE MISSING (PRINTED LEGIBLY)

SECURITY BADGE NUMBER LAST NAME FIRST NAME FIGURE 2 Page 1 of 1 Version 33

09/24/02 10:47:04 'e, --.- , FNP-O-EIP-10.O FIGURE 3 PROTECTED AREA ACCOUNTABILITY CONTINGENCY PLAN This figure should only be used for Protected Area Accountability in the event that the Biometrics System has failed and the Protected Area Accountability Contingency Plan is required.

The OSC Manager or senior individual in the OSC is responsible for completing Protected Area Accountability Contingency Plan per procedure step 8.7 if informed that it is required by security.

Determine from the senior individuals for each of the groups or locations listed below any individuals that are on site for their group, should have assembled in the protected area and are missing.

M] Operations LI Chemistry F] Health Physics F-' Health Physics Support 1] TSC MI Control Room EL Outage Support Building (Steam Generator Replacement Group)

LIST THE NAMES OF MISSING PERSONNEL THAT SHOULD BE IN A PROTECTED AREA ASSEMBLY AREA AND ARE MISSING FROM THAT ASSEMBLY AREA.

PRINT LEGIBLY BADGE NUMBER (ifknown) LAST NAME FIRST NAME LIST THE NAMES OF MISSING PERSONNEL THAT SHOULD BE IN AN ASSEMBLY AREA OUTSIDE THE PROTECTED AREA AND ARE MISSING FROM THAT ASSEMBLY AREA PER THE SECURITY FINAL ACCOUNTABILITY REPORT. THESE INDIVIDUALS MAY BE CONSIDERED TO BE IN THE PROTECTED AREA UNTIL DETERMINED OTHERWISE.

PRINT LEGIBLY BADGE NUMBER (if known) LAST NAME FIRST NAME F- Report to the Emergency Director that initial accountability has been completed using the contingency plan, and provide the Emergency Director with a list of any personnel who are missing and presumed to be in the Protected Area.

FIGURE 3 Page 1 of 1 Version 33

09/24/02 10:47:04 FNP-0-EIP-10.0 FIGURE 4 OUTSIDE PROTECTED AREA ACCOUNTABILITY Service Building Auditorium Maintenance Shop E-- Operations F Maintenance Teams Except Team 9

-- Chem & Env not on Shift []Maintenance Supervision and Staff Fl SAER Personnel [-Maintenance Training Staff and Students El Cafeteria Staff E"] Materials Dept Staff in Cold Tool Room

-- IMS ' Maintenance Contractors (not Williams)

E Document Control El Siemens-Westinghouse Turbine Personnel

[-I Admin Staff Fabrication Shop

[- Facilities Staff 0 & M (Modification Staff) 0 & M (Outage Staff) - Williams Personnel

[-- NRC Admin Staff Eli Contractors Assigned to O&M or Williams El Personnel Engaged In Non-Work Activities ] Support Building Admin Staff El Other Personnel - Engineering Support Staff Visitors Center Auditorium El Satellite Document Control staff El Training Staff El Westinghouse NSSS Personnel

[ Training Students [* Maintenance Team 9 l--

Chem & Env Personnel [1 Financial Services F-1 Fitness For Duty Staff F-1 Special Projects Staff El Visitors Center Staff F-1 Other ElI Visitors In VC (VC Staff Responsibility)

[-] Personnel Engaged in Non-Work Activities E-l Other EOF CSC E EOF Assigned Staff (On Call Crew) El] Security Personnel Not On Shift El Augmented EOF Staff (Includes Off Call in El Security Personnel assigned Outside PA EOF)

E-l Alabama/Houston Co. Personnel Warehouse Receiving Area E-] Georgia/Early Co. Personnel El Materials Dept Staff not in Cold Toolroom

[El Florida Personnel El QC Personnel E-l NRC Staff Switch House El Other _-_ Switchhouse Personnel Missing Personnel Accountability Reported To CSC(2438) by FIGURE 4 Page 1 of I Version 33

09/24/02 10:47:04 TI 1 & FNP-0-EIP-10.0 FIGURE 5 CSC FINAL ACCOUNTABILITY LOG ASSEMBLY AREA ACCOUNTABILITY COMPLETED DATE/TIME SERVICE BUILDING AUDITORIUM t MAINTENANCE SHOP

/

CSC

/

VISITORS CENTER AUDITORIUM

/

SWITCHHOUSE

/

FABRICATION SHOP

/

EOF

/

WAREHOUSE RECEIVING AREA

/

ALTERNATE ASSEMBLY AREAS (IF USED)

MISSING PERSONNEL REPORT TO THE EMERGENCY DIRECTOR THAT SECURITY HAS COMPLETED FINAL ACCOUNTABILITY OUTSIDE THE PROTECTED AREA AND PROVIDE THE EMERGENCY DIRECTOR WITH A LIST OF ANY PERSONNEL THAT ARE MISSING. (ED PHONE # 6016, MM PHONE # 6018, TM PHONE # 6010 OR OM PHONE #6017. IF THE ED OR TSC CANNOT BE REACHED AT ANY OF THE FOUR LISTED NUMBERS, SEND A RUNNER, CONTACT THE PAP OR SAP TO SEND A RUNNER TO THE TSC TO MAKE THE REPORT.)

ACCOUNTABILITY REPORTED TO ED BY /

DATE/TIME FIGURE 5 Page 1 of 1 Version 33

09/24/02 10:47:04 FNP-0-EIP-10.0 FIGURE 6 ACCOUNTABILITY FLOW CHART FIGURE 6 Page 1 of 1 Version 33

09/23/02 13:41:27 AV~ *11*7;. FNP-0-EIP-9.3 September 23, 2002 Version 14 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE FNP-0-EIP-9.3 S

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Y PERSONAL COMPUTER-AUTOMATED DOSE ASSESSMENT METHODS R

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PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use Reference Use All Information Use Approved:

Nuclear Plant General Manager Date Issued IO0 0"- .....

UNCONM' , ULLt. ký Ur- I CAUTION:ueiz aope isa t maintained Current. Do not use in r, Sai,,-y Related Activity

09/23/02 13:41:27 FNP-0-EIP-9.3 LIST OF EFFECTIVE PAGES PROCEDURE CONTAINS NUMBER OF PAGES Body............................................................................................................................................... 14 Attachm ent 1.................................................................................................................................... 1 Table I ............................................................................................................................................. 1 Table 2 ............................................................................................................................................. 3 Table 3 ............................................................................................................................................. 3 Table 4 ............................................................................................................................................. 3 Table 5 ............................................................................................................................................. 2 Table 6 ............................................................................................................................................. 3 Figure 1............................................................................................................................................ 1 Figure 2 ............................................................................................................................................ 1 Page 1 of 2 Revision 13

09/23/02 13:41:27 FNP-0-EIP-9.3 I-R'.~

PERSONAL COMPUTER - AUTOMATED DOSE ASSESSMENT METHODS TABLE OF CONTENTS Section Title Page 1.0 Purpose 1 2.0 References I 3.0 General 1 4.0 System Startup 2 5.0 Initial Data Input and Report 2 6.0 Updating Scenario Information 7 7.0 Viewing More Reports 11 8.0 Using Current Scenario No Edit 13 9.0 Evaluating the Results and Completing the Notification Form 13 10.0 Using the Farley (State) Program 14 ATTACHMENT 1 RELOADING MIDAS SOFTWARE ON A DESIGNATED MIDAS PC TABLE 1 REFERENCES TABLE 2 KEYBOARD/MOUSE MANIPULATIONS TABLE 3 MAP/REPORT FUNCTIONS TABLE 4 PLOT AND REPORT DESCRIPTIONS TABLE 5 RELEASE POINTS TABLE 6 OBTAINING MET/RAD DATA FIGURE 1 MET/RAD DATA FIGURE 2 DBA ACCIDENT MIX SELECTION Page 2 of 2 Revision 13

09/23/02 13:41:27 .. . FNP-0-EIP-9.3 PERSONAL COMPUTER-AUTOMATED DOSE ASSESSMENT METHOD 1.0 Purpose The purpose of this procedure is to provide a method of projecting off-site radiation exposure as a result of a release of radioactive material. The Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose equivalent (CDE) calculated from the computer program can be used to classify Site Area Emergencies or General Emergencies.

2.0 References See Table 1.

3.0 General 3.1 Description of the mouse and keyboard control of the system is described in Table 2.

3.2 ENTRY CONDITIONS 3.2.1 TSC Entry. This procedure will be entered in the TSC when FNP-0-EIP 9.1 Automated Dose Assessment Method is not operable, or is operable but has not Auto actuated when the proper alarms exist from the following:

a. FNP-0-EIP-9.0, step 4.2.5

b. FNP-0-EIP-9.0, step 4.2.6 3.2.2 TSC Entry. This procedure will be entered in the TSC if long term dose assessment is to be performed in the TSC from the following:

a. FNP-0-EIP-9.0, step 4.2.2 3.2.3 EOF Entry. This procedure will be entered in the EOF as soon as the EOF is activated and dose assessment has been transferred to the EOF from the following:

a. FNP-0-EIP-9.0, step 4.2.2

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09/23/02 13:41:27 2 " T, FNP-0-EIP-9.3 4.0 System Startup 4.1 If the PC is not currently running the Midas system, then perform the following:

4.1.1 Ensure that the computer, printer and the monitor are all turned on.

4.1.2 Reboot the computer by pressing control, alternate, and delete at the same time, or by turning the computer off and on again to start it up.

4.1.3 If the computer is not on the Midas system, then exit to DOS and type "midas", then press Enter.

4.1.4 When the prompts for date and time verification come up on the screen, press Enter to accept the date/time (if correct), or enter the correct date and time.

4.1.5 Wait for the title screen to clear, or press the space bar.

4.2 There is a backup PC in the document room as a backup to the MIDAS PC in the TSC 4.3 If, a MIDAS PC software has failed and it is desired to reload the software on a designated MIDAS PC then use Attachment 1. The MIDAS system cannot be loaded on a PC that has Windows NT as the operating system.

4.4 If no MIDAS system can be started, then dose assessment should be performed using FNP-0-EIP-9.1 Automated Dose Assessment Method per FNP-0-EIP-9.0, step 4.2.3.

NOTE: DUE TO THE LARGE AMOUNT OF DISK ACTIVITY AND THE COMPLEXITY OF THE PROGRAM, DELAYS AFTER MAKING SELECTIONS CAN BE A MINUTE OR MORE.

5.0 Initial Data Input and Report NOTE: THE SELECTION OF FARLEY (STATE) PLACES THE SYSTEM IN THE MODE THAT IS PROVIDED TO THE STATE AND LOCAL AGENCIES.

THIS OPTION SHOULD ONLY BE SELECTED IF ATTEMPTING TO HELP THE STATE SOLVE PROBLEMS WITH THEIR SYSTEM. OPERATION IN THIS MODE IS DESCRIBED IN STEP 10.0. FARLEY DRILL IS USED WHEN DEVELOPING DRILLS AND SHOULD NOT BE USED FOR DOSE ASSESSMENT 5.1 From the SITE SELECTION screen, select and confirm PLANT FARLEY.

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09/23/02 13:41:27 - FNP-O-EIP-9.3 NOTE: SELECTING "RECAP DOSE CALCULATIONS" CAN ONLY BE USED AFTER DATA HAS ALREADY BEEN INPUT. ITS USE IS DESCRIBED IN STEP 6.1.

5.2 From the FUNCTION SELECTION screen, select and confirm ACCIDENT DOSE CALCULATIONS.

NOTE:THE OTHER SELECTIONS ON THIS SCREEN ARE RESERVED FOR FUTURE USE AND SHOULD NOT BE SELECTED AT THIS TIME.

5.3 From the ACCIDENT DOSE CALCULATION screen, select and confirm ENHANCED DOSE PROJECTION (MENU B).

5.4 Determine the release points. Record the release points for use when updating the scenario (Figure 1 may be used as an aid).

NOTE: THE RELEASE POINTS ARE DESCRIBED IN TABLE 5.

5.4.1 On the MISCELLANEOUS PARAMETERS screen, verify that only the following selections are highlighted:

a. SCENARIO MET DATA

b. REL PT I UI VENT

c. REL PT 2 U1 SG

d. REL PT 3 U2 VENT

e. REL PT 4 U2 SG

f. FLOW (EX VEL) (FOR RELEASE POINTS 1 THROUGH 4)

SET TO 0.0E+00

g. AUTO SCENARIO INTEGRATION

h. MAX DIST DOWNWIND (MILES) (SET TO 1.1OE + 01) 5.4.2 On the MISCELLANEOUS PARAMETERS screen, leave all four release points selected and confirm.

NOTE: THE USE OF THE OTHER 2 SELECTIONS ON THIS SCREEN ARE DESCRIBED IN STEPS 6.5 AND 6.6.

IT IS APPROPRIATE TO HAVE THE PROGRAM DELETE THE DATA FROM PREVIOUS SCENARIOS, IF THIS IS THE FIRST RELEASE FOR THIS INCIDENT.

5.5 From the SCENARIO DATA TABLE CONTROL screen, select and confirm START A NEW SCENARIO.

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09/23/02 13:41:27 FNP-0-EIP-9.3 5.6 Enter the meteorological data on the spreadsheet screen, for all four inputs.

5.6.1 Figure 1 may be used as an aid to collect the data.

5.6.2 Table 6 describes the methods of collecting the data.

5.6.3 WHEN all of the data has been entered on the spread sheet, THEN press "x" to save the data and exit the spread sheet.

5.7 Determine which type of accident to select. Figure 2 provides guidance if necessary.

5.8 From the DBA ACCIDENT TYPE SELECTION screen, select and confirm the accident type. Record the selections for use when updating the scenario (Figure 1 may be used as an aid).

CAUTION: DO NOT ENTER BOTH SPING AND R-14 FOR VENT STACK RELEASES. THIS WOULD CAUSE THE SOURCE TERM TO BE DOUBLE ITS ACTUAL VALUE.

5.9 Enter the radiation monitor and release point flow data on the spreadsheet screen for all release points that currently have an emergency release. An emergency release is defined as a release greater than 10 times normal. Normal release levels are average release levels for steady state operation.

5.9.1 If failed fuel is indicated and SPING iodine is not available, or reading greater than 1E-6 jtc/ml, then enter a value for SPING iodine that is the SPING noble gas value multiplied by 1E-3.

5.9.2 If failed fuel is indicated and SPING particulate is not available, or reading greater than 1E-6 [tc/ml, then enter a value for SPING particulate that is the SPING noble gas value multiplied by 1E-3.

5.9.3 If a stuck open SG relief or safety is the cause of the release enter actual steam pressure for that generator. The program will assume that one valve is open on that steam line if any SG pressure is entered below the 1035 PSIG normal setpoint of the SG relief.

5.9.4 Figure 1 may be used as an aid to collect the data.

5.9.5 Table 6 describes the methods of collecting the data.

5.9.6 When all of the data has been entered on the spreadsheet, then press "x" to save the data and exit the spreadsheet.

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• FNP--EIP-9.3 5.9.7 If the cursor is moved back to the first column, the program will automatically go to the previous page. If this occurs, return to step 5.7.

5.10 If any of the selected release points have no radiation monitor or flow inputs, then a warning screen will appear warning of which release points have a zero source term. This is normal after selecting multiple release points and there is only an emergency release from one of those release points.

5.10.1 If the release point(s) with zero source term is correct, then select continue.

5.10.2 If the release point(s) with zero source term is wrong, then select reset and proceed to step 6.4 to confirm selections made.

5.11 From the RELEASE TIMING SELECTION screen, verify the remaining duration of release is set to 240 and confirm or enter a different remaining duration per step 5.11.1. Record the selection for use when updating the scenario (Figure 1 may be used as an aid).

5.11.1 If a remaining duration other than 240 is desired, select REMAINING DURATION (MIN) using the numpad; set the number of minutes from the current time that the release will continue. Confirm the selection. Record the selection for use when updating the scenario (Figure 1 may be used as an aid).

NOTE: THE TIME TO DO THE CALCULATIONS, PRINT THE NOTIFICATION FORM, AND DRAW THE SCREEN DISPLAY MAY TAKE IN EXCESS OF 4.5 MINUTES DEPENDING ON THE NUMBER OF RELEASE POINTS AND THE DURATION OF THE RELEASE.

5.12 The printer will now print out an Emergency Notification Form with the radioactive release data printed on it. Give this form to the Technical Manager (TM) in the TSC or the Dose Assessment Director (DAD) in the EOF.

5.13 The screen will display the Total Effective Dose Equivalent (TEDE) 11 mile plume map with scenario information. Verify that the map is a four-hour projection that has the 10 mile EPZ zones displayed and any other information that is desired by the TM or the DAD.

5.14 Inform the TM or DAD that the map is being displayed and if the TM or DAD desire to have the TEDE map printed, then print (SHIFT & PRINT SCREEN) the map described in step 5.13 and give it to the TM or DAD.

5.15 From the TEDE map, sequentially select CONTINUE, then NEXT REPORT, then THYROID CDE DOSE PLOT.

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09/23/02 13:41:27 --, I " FNP-0-EIP-9.3 5.16 The screen will display the Thyroid Committed Dose Equivalent (CDE) I I mile plume map with scenario information. Verify that the map is a four-hour projection that has the 10 mile EPZ zones displayed and any other information that is desired by the TM or the DAD.

5.17 Inform the TM or DAD that the map is being displayed and if the TM or DAD desire to have the Thyroid CDE map printed then Print (SHIFT & PRINT SCREEN) the map described in step 5.16 and give it to the TM or DAD.

5.18 The individual evaluating the radiological release (SS, TM, DAD or other qualified individual) should go to step 9.0 after receiving the Emergency Notification Form and the information from the TEDE and Thyroid CDE plots to evaluate the data.

5.19 From the CDE map, sequentially select CONTINUE, NEXT REPORT, then MORE REPORTS.

5.20 Coordinate with the RMT controller and the DAD or TM, to determine which maps and what features need to be printed. Recommended maps are the Field Monitor (FM) GAMMA + BETA DOSE RATE PLOT (equivalent to open window dose rate readings), FM GAMMA DOSE RATE PLOT (equivalent to closed window dose rate readings) and the EDE DOSE RATE PLOT (equivalent to closed window dose rate readings) 5.21 Select one plot determined in step 5.20 from the more reports screen and confirm.

5.22 Verify projection time of .25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> and confirm 5.23 Set the map scale at 11.0 miles or other value desired by RMT controller and confirm.

5.24 Select the map features desired by the RMT controller and confirm any changes made.

5.25 Use the select area feature to provide as much detail about the projected dose rates as possible.

5.26 Print (SHIFT & PRINT SCREEN) the map displayed in step 5.25 and give it to the RMT controller.

5.27 Select "continue", then MORE REPORTS.

5.28 If additional maps are required for the RMT controller return to step 5.21 to print these maps Version 14

09/23/02 13:41:27, FNP-EIP.9.3 5.29 The scenario should be updated at approximately 30 minute intervals, or other times as specified by the Technical Manager or DAD, to coincide with issuing follow-up reports. The scenario should also be updated if there is a drastic change in release information that could cause a change in emergency classification.

5.30 If more information is desired about this scenario prior to updating, then go to step 7.

5.31 To update this scenario, select EXIT twice and proceed to step 6.0.

6.0 Updating Scenario Information 6.1 If more information is desired about this particular scenario prior to updating, including printing additional emergency notification forms, then perform the following three steps.

6.1.1 From the FUNCTION SELECTION screen, select and confirm RECAP DOSE CALCULATIONS.

6.1.2 From the RECAP DOSE CALCULATIONS screen, select and confirm ENHANCED DOSE PROJECTION (MENU B).

6.1.3 Go to step 7.0.

6.2 To update the scenario, from the FUNCTION SELECTION screen, select and confirm ACCIDENT DOSE CALCULATIONS.

INOTE: THE OTHER SELECTIONS ON THIS SCREEN ARE RESERVED FOR FUTURE USE AND SHOULD NOT BE SELECTED AT THIS TIME.

6.3 From the ACCIDENT DOSE CALCULATION screen, select and confirm ENHANCED DOSE PROJECTION (MENU B).

6.4 Select the same release points that were selected in step 5.4 when initially inputting data.

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" 1 T' FNP-,-EIP-9.3 6.4.1 On the MISCELLANEOUS PARAMETERS screen, verify that only the following selections are highlighted:

a. SCENARIO MET DATA

b. RELEASE POINT 1 UNIT 1 VENT

c. RELEASE POINT 2 UNIT 1 SG

d. RELEASE POINT 3 UNIT 2 VENT

e. RELEASE POINT 4 UNIT 2 SG

f. FLOW (EX VEL) (FOR RELEASE POINTS 1 THROUGH 4)

SET TO O.OE+00

g. AUTO SCENARIO INTEGRATION

h. MAX DIST DOWNWIND (MILES) (SET TO 1.10E+01) 6.4.2 On the MISCELLANEOUS PARAMETERS screen, leave all four release points selected and confirm.

CAUTION: IF START A NEW SCENARIO IS SELECTED AND CONFIRMED, ALL OF THE MET AND RADIATION DATA FROM THE CURRENT SCENARIO WILL BE ERASED.

6.5 To continue updating, proceed to step 6.6 or if it is desired to print out another Emergency Notification Form and return to the TEDE map with the current MET and RAD information, then from the SCENARIO DATA TABLE CONTROL screen, select and confirm CURRENT SCENARIO NO EDIT and proceed to step 8.0.

6.6 From the SCENARIO DATA TABLE CONTROL screen, select and confirm CURRENT SCENARIO EDIT.

6.7 Enter the new meteorological data on the spreadsheet screen, for all four inputs.

6.7.1 Enter a value for the current time and the blank spaces for times that were skipped, due to not updating the scenario every 15 minutes 6.7.2 Figure 1 may be used as an aid to collect the data.

6.7.3 Table 6 describes the methods of collecting the data.

6.7.4 When the data has been entered on the spreadsheet, press "x" to save the data and exit the spreadsheet.

6.8 Determine which type of accident to select. Figure 2 provides guidance if necessary.

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09/23/02 13:41:27 r FNP--EIP-9.3 6.9 From the DBA ACCIDENT TYPE SELECTION screen, select and confirm the accident type. Record the selections for use when updating the scenario (Figure 1 may be used as an aid).

CAUTION: DO NOT ENTER BOTH SPING AND R-14 FOR VENT STACK RELEASES. THIS WOULD CAUSE THE SOURCE TERM TO BE DOUBLE ITS ACTUAL VALUE.

6.10 Enter the radiation monitor and release point flow data on the spreadsheet screen for all release points that currently have an emergency release. An emergency release is defined as a release greater than 10 times normal. Normal release levels are average release levels for steady state operation.

6.10.1 Enter a value for the current time and the blank spaces for times that were skipped due to not updating the scenario every 15 minutes. This includes updating the accident type for the blank time spot.

6.10.2 If failed fuel is indicated and SPING iodine is not available, or reading greater than lE-6 jic/ml, then enter a value for SPING iodine that is the SPING noble gas value multiplied by lE-3.

6.10.3 If failed fuel is indicated and SPING particulate is not available, or reading greater than 1E-6 ic/ml, then enter a value for SPING particulate that is the SPING noble gas value multiplied by lE-3.

6.10.4 If a stuck open SG relief or safety is the cause of the release enter actual steam pressure for that generator. The program will assume that one valve is open on that steam line if any SG pressure is entered below the 1035 PSIG normal setpoint of the SG relief.

6.10.5 Figure I may be used as an aid to collect the data.

6.10.6 Table 6 describes the methods of collecting the data.

6.10.7 When all of the data has been entered on the spreadsheet, then press "x" to save the data and exit the spreadsheet.

6.10.8 If the cursor is moved back to the first column, the program will automatically go to the previous page. If this occurs return to step 6.8 6.11 If any of the selected release points have no radiation monitor or flow inputs, then a warning screen will appear warning of which release points have a zero source term. This is normal after selecting multiple release points and there is only an emergency release from one of those release points.

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09/23/02 13:41:27 j jLi e FNP-O-"IP-9.

60 Jn th s n tinuE".3 6.11.1 If the release point with zero source term is correct, then select "continue".

6.11.2 If the release point(s) with zero source term is wrong, then select "reset" and proceed to step 6.4 to confirm selections made.

6.12 From the RELEASE TIMING SELECTION screen, verify the remaining duration of release is set to 240 and confirm or enter a different remaining duration per step 6.12.1. Record the selection for use when updating the scenario (Figure 1 may be used as an aid).

6.12.1 If a remaining duration other than 240 is desired, select REMAINING DURATION (MIN), using the numpad, set the number of minutes from the current time that the release will continue. Confirm the selection.

Record the selection for use when updating the scenario (Figure 1 may be used as an aid).

INOTE: THE TIME TO DO THE CALCULATIONS, PRINT THE NOTIFICATION FORM, AND DRAW THE SCREEN DISPLAY MAY TAKE IN EXCESS OF 4.5 MINUTES--DEPENDING ON THE NUMBER OF RELEASE POINTS AND THE DURATION OF THE RELEASE.

6.13 The printer will now print out an Emergency Notification Form with the radioactive release data printed on it. Give this form to the Technical Manager (TM) in the TSC or the Dose Assessment Director (DAD) in the EOF.

6.14 The screen will display the Total Effective Dose Equivalent (TEDE) 11 mile plume map with scenario information. Verify that the map is a four-hour projection that has the 10 mile EPZ zones displayed and any other information that is desired by the TM or the DAD.

6.15 Inform the TM or DAD that the map is being displayed and if the TM or DAD desire to have the TEDE map printed, then print (SHIFT & PRINT SCREEN) the map described in step 6.14 and give it to the TM or DAD.

6.16 From the TEDE map, sequentially select CONTINUE, then NEXT REPORT, then CDE THYROID PLOT.

6.17 The screen will display the Thyroid Committed Dose Equivalent (CDE) 11 mile plume map with scenario information. Verify that the map is a four-hour projection that has the 10 mile EPZ zones displayed and any other information that is desired by the TM or DAD.

6.18 Inform the TM or DAD that the map is being displayed and if the TM or DAD desire to have the Thyroid CDE map printed then Print (SHIFT & PRINT SCREEN) the map described in step 6.17 and give it to the TM or DAD.

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• '°*""*'" *-*.FNP-0-EIP-9.3 09/23/02 13:41:27 FNP-0*,IP-9.3 6.19 The individual evaluating the radiological release (SS, TM, DAD or other qualified individual) should go to step 9.0 after receiving the Emergency Notification Form and the information from the TEDE and Thyroid CDE plots to evaluate the data.

6.20 From the CDE map, sequentially select CONTINUE, NEXT REPORT, then MORE REPORTS.

6.21 Coordinate with the RMT controller and the DAD or TM, to determine which maps and what features need to be printed. Recommended maps are the Field Monitor (FM) GAMMA + BETA DOSE RATE PLOT (equivalent to open window dose rate readings), FM GAMMA DOSE RATE PLOT (equivalent to closed window dose rate readings) and the EDE DOSE RATE PLOT (equivalent to closed window dose rate readings) 6.22 Select one plot determined in step 6.21 from the more reports screen and confirm.

6.23 Verify projection time of .25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> and confirm 6.24 Set the map scale at 11.0 miles or other value desired by RMT controller and confirm.

6.25 Select the map features desired by the RMT controller and confirm any changes made.

6.26 Use the select area feature to provide as much detail about the projected dose rates as possible.

6.27 Print (SHIFT & PRINT SCREEN) the map displayed in step 6.26 and give it to the RMT controller.

6.28 Select "continue", then MORE REPORTS.

6.29 If additional maps are required for the RMT controller return to step 6.22 to print these maps 6.30 The scenario should be updated at approximately 30 minute intervals, or other times as specified by the Technical Manager or DAD, to coincide with issuing follow-up reports. The scenario should also be updated if there is a drastic change in release information that could cause a change in emergency classification.

6.31 If more information is desired about this scenario prior to updating, then go to step 7.0 6.32 To update this scenario, select EXIT twice and proceed to step 6.0.

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09/23/02 13:41:27 0 1ý r I FNP-0-EIP-9.3 7.0 Viewing More Reports 7.1 When it is desired to leave this portion of the program, return to the MORE REPORTS screen and select exit. The program will return to the FUNCTION SELECTION screen. Go to step 6.0 to update the scenario.

7.2 There are two screens of available plots and reports. Select next screen or previous screen to view the other screen. The plots and reports are described in Table 4.

7.3 From the MORE REPORTS screen, select and confirm the desired plot or report.

7.4 From the REPORT PARAMETER SELECTION screen, perform the following:

7.4.1 If this is not the report that is desired, then select EXIT to return to the MORE REPORTS screen and return to step 7.0.

7.4.2 Select on the PROJ TIME box until the desired projection time is displayed.

7.4.3 Select CONFIRM to go to the selected plot or report

[NOTE: AFTIER A REPORT OR PLOT IS DISPLAYED, IT CAN BE PRINTED BY NOTE: PRESSING "SHIFT-PRINT SCREEN".

7.5 If a report was selected, then the report will be displayed.

7.5.1 Manipulation of the report is described in Table 3.

7.5.2 After exiting the report, return to step 7.0.

7.6 If a plot was selected, then the MAP SCALE SELECTION screen will come up.

7.6.1 If the map scale in the highlighted box is not correct, then select the box and set the desired map scale to a maximum of 50 miles using the numpad.

7.6.2 If the map scale in the highlighted box is correct, then confirm to go to the map.

7.6.3 Manipulation of the map is described in Table 3.

7.6.4 After exiting the map, return to step 7.0.

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09/23/02 13:41:27 e 7 T 7 T---FNP-0-EIP-9.3 7.7 Printing additional emergency notification forms.

7.7.1 Select and confirm SEND STATE REPORT TO THE PRINTER...'The current emergency notification form will now be sent to the printer.

7.7.2 To print additional reports or plots select MORE REPORTS and return to step 7.0.

7.7.3 To update the scenario select EXIT twice. The program will return to the FUNCTION SELECTION screen. Go to step 6.0 to update the scenario.

8.0 Using Current Scenario No Edit 8.1 This section of the procedure is used after CURRENT SCENARIO NO EDIT has been selected from step 6.5.

CAUTION: THE PROJECTION NUMBERS PRINTED ON THE EMERGENCY NOTIFICATION FORM AND THE VALUES DISPLAYED ON THE PLOTS AND REPORTS WILL BE DIFFERENT FROM THE ORIGINAL, BASED ON THE TIME DIFFERENCE FROM WHEN THE ORIGINAL I CALCULATIONS WERE DONE.

8.2 Selecting CURRENT SCENARIO NO EDIT will allow a printout of another Emergency Notification Form and return to the TEDE map with the current MET and RAD information.

8.3 Return to step 6.6.

9.0 Evaluating the Results and Completing the Notification Form 9.1 The printed Emergency Notification Form and the TEDE and Thyroid CDE information should all be used to evaluate the release.

9.2 Additional information is available from the More Reports section (step 7.0).

9.3 The 10 mile EPZ zones on the TEDE and Thyroid CDE plots that exceed the Protective Action Guidelines (PAGs) for General Emergency are high-lighted.

9.4 Zones adjacent to the high-lighted zones should also be considered for protective actions, based on meteorological conditions and how close the plume is to these zones.

9.5 The data from the printed form may be transcribed to the FNP-0-EIP-9.0, Figure 6, or the printed form may be completed for transmission.

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09/23/02 13:41:27 , FNP-0-EIP-9.3 9.6 If the emergency classification determined from this data is higher than the current emergency classification, then the emergency classification should be upgraded per FNP-0-EIP-9.0, Step 6.

9.7 If this is an initial or upgrade notification, then the DAD, TM or SS should return to FNP-0-EIP-9.0, step 4.2.8.

9.8 If this is a follow-up notification, then the DAD, TM or SS should complete the Emergency Notification Form, transmit over the FAX using FNP-0-EIP-8.3, and return to FNP-0-EIP-9.0.

9.9 If a General Emergency or Site Area Emergency cannot be declared based on this calculation, the dose assessment per EIP-9.5 should be performed.

10.0 Using the Farley (State) Program 10.1 The FARLEY (STATE) program is provided to the state and local agencies to allow them to evaluate the plume based on the data provided to them on the Emergency Notification Form.

10.2 Operation of the FARLEY (STATE) program is similar to the procedure described in step 5 and step 6, with the exception of the spreadsheet data.

10.2.1 The spreadsheet data that is entered in this program is the release rate from the plant site in jiCi per second, as displayed on the Emergency Notification Form, line 12.

CAUTION: THE COMPUTER THAT IS BEING USED TO ASSESS PLANT CONDITIONS AND GENERATE DATA AND FORMS FOR CONTINUED DOSE ASSESSMENT SHOULD NOT BE USED TO PERFORM THE FOLLOWING STEP.

10.3 If information or help is requested by state or local agencies, then this portion of MIDAS may be selected from the SITE SELECTION screen to help in answering their questions.

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j. -_L . ATTACHMENT 1 RELOADING MIDAS SOFTWARE ON A DESIGNATED MIDAS PC 1.0 The designated MIDAS PCs are in TSC (2), EOF (2) and the Alternate EOF(2). These PCs have a label on them that says MIDAS. There are also MIDAS PCs in Birmingham.

2.0 This procedure should only be performed on a designated MIDAS PC that uses DOS as the operating system. MIDAS will not run under the Windows NT.

3.0 If it is desired to load MIDAS on a computer that is not a designated MIDAS PC then contact the Emergency Planning Group.

4.0 This attachment should be performed if there is a failure of the MIDAS software on any designated MIDAS PC and it is desired to load either the identical software on the PC or to load the previous version of software on the PC.

5.0 Exit any programs to return to DOS for the computer 6.0 If you desire to load a backup copy of the current MIDAS software that is stored on the C:\ hard drive then perform the following steps:

6.1 At the DOS prompt enter "c:\reload\setnew 6.2 Follow the screen instructions 7.0 If you desire to load a new copy of the current MIDAS software that is stored on CD ROM then perform the following steps:

7.1 Verify that the CD ROM for MIDAS is in the CD drive.

7.2 At the DOS prompt enter "c:\reload\setcd 7.3 Follow the screen instructions NOTE: The only time that it is recommenced to try to use the previous MIDAS software is if there is a problem and the current version cannot be run from any location.

The old MIDAS software will not have the current updates and there may be procedure conflicts. In some cases the old software will not be available.

8.0 If you desire to load a copy of the previous version of MIDAS software that is stored on the C:\ hard drive then perform the following steps:

8.1 At the DOS prompt enter "c:\reload\setold 8.2 Follow the screen instructions ATTACHMENT 1 PAGE 1 OF I Version 14

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'S.

TABLE 1 REFERENCES

1. FNP-0-EIP-9.0, Emergency Classification and Actions

2. FNP-0-EIP-9.2, Obtaining Meteorological Information

3. FNP-0-CCP-1300, Chemistry and Environmental Activities During a Radiological Accident

4. MIDAS Users Manual for Southern Nuclear Operating Company

5. MIDAS Users Guide for Accident Calculations

6. FNP-0-CCP-645

7. FNP-0-CCP-647

8. FNP-1-CCP-643

9. FNP-2-CCP-643 TABLE 1 PAGE 1 OF 1 Version 14

09/23/02 13:41:27 . FNP-0-EIP-9.3

. _*,.* . \ .. TABLE 2 KEYBOARD/MOUSE MANIPULATIONS 1.0 Mouse operations for Main MIDAS screens 1.1 Use the mouse to position the cursor on the desired box of the screen.

1.2 Click the left mouse button once to select the item.

1.3 If there is a number that must be input for the selected item, the numpad will appear in the upper right hand comer. You must enter a value on the numpad before proceeding. The numpad is described below.

1.4 If there is a date/time that must be input for the selected item, the date enter pad will appear in the upper right hand comer. You must enter a value on the date enter pad before proceeding. The date enter pad is described below.

1.5 After selecting an item, it will be highlighted. Click once on the CONFIRM BOX to perform the action selected.

1.6 To exit a screen, click twice on the EXIT BOX. Clicking on the CONFIRM BOX when exit is selected will not perform the exit.

1.7 After the first click on EXIT, you can select another item if you change your mind about exiting.

1.8 When RESET is available as a selection, it will have different functions on different screens.

1.9 If reset is not highlighted, generally it will delete the selections that you have made, or return to the previous selections.

1.10 When reset is highlighted, generally it will return you to the previous screen.

2.0 Keyboard Operation 2.1 The cursor can be moved from one location to another by using the cursor keys.

2.2 The space bar will perform the same function as the left mouse button.

2.3 With numlock off, the number pad will function as cursor keys.

2.4 With numlock on, the keyboard can be used to enter values on the main screen numpad.

TABLE 2 PAGE 1 OF 3 Version 14

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• TABLE2 2.5 Pressing q, then ENTER, from the main screens will generally cause the program K*_i to return to the function selection screen or return to the DOS prompt, depending on where you are in the program.

3.0 Numpad Operation 3.1 Once the numpad has been displayed, you must select EN (or enter on the keyboard or numpad) to return to the main screen.

3.2 Selecting BS (or backspace on the keyboard) will delete the last number entered.

3.3 Selecting CL (or Esc on the keyboard) will delete all numbers entered.

3.4 Selecting - (or - on the keyboard or numpad) before entering the value will yield a negative number.

3.5 Placing a "-" sign anywhere but before the first number will prevent the enter key from working. You must clear the entry and enter a valid number.

3.6 Selecting E (or E on the keyboard) is used for exponents. A "-" behind the E will cause the exponent to be negative.

3.7 If a number is input that is out of the allowable range, the numpad will go away when entered. But the value in the selected item will remain the same as it was before selecting.

4.0 Date Entry Pad 4.1 Once the date entry pad has been displayed, you must select CONFIRM) to return to the main screen.

4.2 The only way to input on the date entry pad is with the mouse.

4.3 Position the mouse on the + or - above or below the number that you want to change.

4.4 Pressing Q, then ENTER will not allow you to leave the date entry pad.

4.5 Once you have the proper date input, select confirm.

5.0 Spreadsheet Data Entry Screens 5.1 The mouse will not function in the spreadsheets.

TABLE 2 PAGE 2 OF 3 Version 14

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_FA:\J~LJ TABLE 2 5.2 The allowable keys and their functions are displayed on the bottom of the spreadsheet screens.

6.0 Maps and Plots 6.1 A single click will cause the action to occur, confirmation is not required except to activate a newly selected projection time.

6.2 Pressing Q and ENTER has inconsistent results.

7.0 Printing Plots and Reports 7.1 Pressing SHIFT and PRINT SCREEN simultaneously will print whatever is currently on the screen.

7.2 Pressing CTRL and PRINT SCREEN simultaneously will print all text as it appears on the screen. Pressing the same keys again will stop printing text.

TABLE 2 PAGE 3 OF 3 Version 14

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• r- *,*TABLE3 MAP/REPORT FUNCTIONS 1.0 The TEDE map will automatically be displayed after entering the scenario data. The following information will be displayed on the screen:

An 11 mile radius plume map (includes locations of power block, RW structure, SW structure, met tower and roads)

The type of map (i.e., TEDE, CDE, etc.)

The projection time Scenario details (start/stop times, peak values, etc.)

A color code for the values in the plume Selection boxes for the first map screen 2.0 First TEDE Map Screen Selections 2.1 POINT OF INTEREST - after selecting this item, place the cursor anywhere on the map and click on the mouse. The value at that point will be displayed on the screen. The units displayed are the same as the units for the peak value on the map.

To exit the point of interest function, select CURSOR HERE TO EXIT.

2.2 MAP FEATURES - after selecting this item, a menu will be displayed next to the plume map, with the following selections:

ZONES - displays 10 mile EPZ zones FIELD MONITORS - displays predesignated sampling locations AIR SAMPLERS - displays air sampler locations TLDS - displays locations of posted TLDS COUNTY BOUNDARIES - displays county boundaries TEXT - displays text for city names, etc.

WIND SPIDER - displays the wind spider used in EIP-4.0 Select or deselect as many of these features as you desire and confirm. Too many selections will clutter the drawing and make it difficult to read.

The map will be redrawn with these selections.

2.3 SELECT AREA - after selecting this item, you must select two points on the map at diagonal comers (upper right and lower left or upper left and lower right) of a square that you want enlarged. After selecting the second point, the map will be redrawn for the area selected. A new selection will be available, RESTORE.

Choosing this new selection will redraw the map with the original scale.

TABLE 3 PAGE 1 OF 3 Version 14

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,l*,**i,,*.,*TABLE 2.4 CONTINUE - after selecting this item, the selections will change to the second "mapscreen selections.

3.0 Second TEDE Map Screen Selections 3.1 Projection Time - selecting this item causes the projection time in the selection to cycle between 2, 4, 8 and 60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> projection time. After selecting the desired projection time, select CONFIRM to have the map redrawn with the new projection item.

3.2 NEXT REPORT - after selecting this item, the selections will change to the third map screen selections.

4.0 Third TEDE Map Screen Selections 4.1 THYROID CDE DOSE PLOT - after selecting this item, the map will be redrawn as the Thyroid CDE 11 mile plot with similar information as described for the TEDE map.

4.2 SKIP TO NEXT REPORT - will cause the selections to change to EXIT (exits scenario and return to function selection screen) and MORE REPORTS (exits map and goes to MORE REPORTS screen).

4.3 MORE REPORTS - exit to MORE REPORTS screen.

5.0 THYROID CDE MAP SCREEN SELECTIONS 5.1 These screens are similar to the TEDE screens except that there is no third screen and the next report on the CDE second screen does the same thing as skip to next report on the TEDE third screen.

6.0 MAP SCREEN SELECTIONS FROM MORE REPORTS 6.1 These screens are identical to the CDE map screen selections.

7.0 Report Screen Selections From More Reports 7.1 From the MORE REPORTS screen, select and confirm the desired report.

7.2 The REPORT PARAMETER SELECTION screen has three selections available:

PROJECTION TIME - click on this item to cycle through the available projection times until the desired projection time is displayed.

TABLE 3 PAGE 2 OF 3 Version 14

09/23/02 13:41:27 * " A " FNP-O-EIP-9.3 k, h1 I. .. . TABLE 3 CONFIRM - click on this item to display the selected report with the desired projection time.

MORE REPORTS - click on this item to return to the MORE REPORTS screen.

7.3 The screen with the report displayed on it has three selections available:

CONTINUE - click on this item to show the next screen of the report. At the last screen of the report, the selections will change to the ones described in step 7.2.

SKIP REST OF THIS REPORT - clicking on this item will keep the same report screen and change the selections to the ones described in step 7.2.

EXIT TO MORE REPORTS - click on this item to return to the MORE REPORTS screen.

8.0 Printing Plots and Reports 8.1 Pressing SHIFT and PRINT SCREEN simultaneously will print whatever is currently on the screen.

8.2 To print an entire report, each screen of the report must be displayed and printed individually.

8.3 Pressing CTRL and PRINT SCREEN simultaneously will print all text as it appears on the screen. Pressing the same keys again will stop printing text.

TABLE 3 PAGE 3 OF 3 Version 14

09/23/02 13:41:27 FNP-0-EIP-9.3

~m z L i TABLE 4 PLOT AND REPORT DESCRIPTIONS REPORTS - Numerical representations of the parameter that is selected, can be printed (SHIFT - PRINT SCREEN) as a graphic. Each page of the report must be printed separately.

PLOTS - Graphical representation of the parameter that is selected, can be printed (SHIFT - PRINT SCREEN) as a graphic.

4-PLOTS - Special case of plot where the plots for the four allowed projection times are displayed on the same screen.

RPPQP TS/PLOTS AVAILABLE FROM MORE REPORTS SCREENS PARAMETER - DESCRIPTION TYPE TEDE 4-DAY DOSE - Integrated Total Effective Dose Equivalent to an REPORT individual, assuming that individual is not evacuated for four days. Units for PLOT the display is MREM. TEDE is a criteria for making General Emergency and 4-PLOT Site Area Emergency classifications, and for Protective Action Guidelines THYROID CDE DOSE - Integrated Thyroid Committed Dose Equivalent. REPORT Units for the display is MREM. Thyroid CDE is a criteria for making General PLOT Emergency and Site Area Emergency classifications, and for Protective Action 4-PLOT Guidelines.

TEDE DOSE RATE - TEDE dose rate is displayed in MREM/HR. This is REPORT useful for evaluating the TEDE for an individual who will be in the area for a PLOT short period of time. This is not the same reading that you would see with a 4-PLOT meter at the specified location.

THYROID CDE DOSE RATE - Thyroid CDE dose rate is displayed in REPORT MREM/HR. This is useful for evaluating the Thyroid CDE for an individual PLOT who will be in the area for a short period of time. This is not the same reading 4-PLOT that you would see with a meter at the specified location.

EDE DOSE RATE - Effective Dose Equivalent dose rate is displayed in PLOT MREM/HR. This is useful for evaluating the expected dose rate that one might see with a meter at the specified location. The .25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> projection should REPORT provide the most accurate indication of current dose rate.

MET AND RAD

SUMMARY

- Provides a summary of the meteorological and REPORT radiological data that has been input into the program to do the projections PROJECTED DOSE

SUMMARY

- Provides a summary of dose projection REPORT from the start date of integration. The top half of each page is for dose and the bottom half is for dose rate. First page has break at or beyond site boundary and at location, the PAG limit, and the most distant location where the limit is exceeded. The second page is a summary of the pathway doses at the grid point nearest the peak.

TABLE 4 PAGE 1 OF 3 Version 14

09/23/02 13:41:27 A TJ '7 t FNP-0-EIP-9.3 V. I TABLE 4 MULTIPLE PLUME TRACT - Provides a straight line gausian projected PLOT plume segment plot showing each 15 minute track of the plume release for a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> projection time.

TIME OF ARRIVAL - Provides multiple pages of data tables showing plume REPORT arrival time at the varying locations. The first page provides a summary of arrival time in hours by direction and sector for site boundary, 2, 5, 10, 25, and 50 miles. Subsequent pages provide time of arrival predictions for only affected sectors in detail.

SKIN DE - Provides data in mr for integrated skin dose equivalent (1 year) REPORT useful for evaluating the skin dose an individual is receiving for 10CFR20 limit purposes PLOT POPULATION DOSE - Provides TEDE 4 day dose MANREM projections. PLOT Total population dose is based on total population in affected site regions.

Projection time defaults to .25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, but can be modified to provide forecast REPORT capability.

FM GAMMA AND BETA DOSE RATE - Report provides field monitor PLOT gamma and beta open window dose rate predicted values in mr/hr for varying direction and distance. The first page of the report provides a summary by PRINT direction and sector for site boundary, 2, 5, 10, 25, and 50 miles. Subsequent pages provide detailed time of arrival predictions for affected sectors.

Projection time defaults to .25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, but can be modified to provide forecast capability. Plot contour legends provide converted open window (mr/hr) and frisker (cpm) predicted readings.

FM GAMMA DOSE RATE - Report provides field monitor gamma closed PLOT window dose rate predicted values in mr/hr for varying direction and distance.

The first page of the report provides a summary by direction and sector for site PRINT boundary, 2, 5, 10, 25, and 50 miles. Subsequent pages provide time of arrival predictions for only affected sectors in detail. Projection time defaults to .25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, but can be modified to provide forecast capability. Plot contour legends provide converted closed window (mr/hr) and frisker (cpm) predicted readings.

FM IODINE DOSE RATE - Report provides field monitor thyroid CDE dose PLOT rate predicted values in mr/hr for varying direction and distance. The first page of the report provides a summary by direction and sector for site boundary, 2, 5, PRINT 10, 25, and 50 miles. Subsequent pages provide time of arrival predictions for only affected sectors in detail. Projection time defaults to .25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, but can be modified to provide forecast capability. Plot contour legends provide calculated silver zeolite cartridge readings (cpm) and particulate filter (cpm) predicted readings.

AIR CONCENTRATION - Provides a projection of what the air concentration REPORT will be in gCi/m3 for the projection time selected for 1-131, Cs-134, Cs-137, Sr 89, and Sr-90. PLOT TABLE 4 PAGE 2 OF 3 Version 14

09/23/02 13:41:27 <-" " A i"T " " FNP-0-EIP-9.3 LV TABLE 4 GROUND CONTAMINATION - Provides a projection of what the ground REPORT contamination will be in jtCi/m2 for 1-131, Cs-134, Cs-137, Sr-89, and Sr-90. PLOT COW MILK CONTAMINATION - Provides a projection of the REPORT contamination in tCi/liter of cow's milk for an animal that has been in the area during the course of the accident for 1-131, Cs-134, Cs-137, Sr-89, and Sr-90. PLOT VEGETATION CONTAMINATION - Provides a projection of the REPORT contamination in ptCi/kilogram of vegetation during the course of the accident for 1-131, Cs-134, Cs-137, Sr-89, and Sr-90. PLOT MEAT CONTAMINATION - Provides a projection of the contamination in REPORT p.Ci/kilogram of meat for an animal that has been in the area during the course of the accident for 1-131, Cs- 134, Cs-137, Sr-89, and Sr-90. PLOT UNDEPLETED X/Q - Provides data on the calculated undepleted relative air PLOT concentration in sec/m3 (Ci/me per Ci/sec). PRINT DEPLETED X/Q (DVI) - Provides data on the depleted 1-131 relative air PLOT concentration in sec/m3. PRINT DEPLETED X/Q (DVC) - Provides data on the depleted cesium-137 relative PLOT air concentration in sec/m3. PRINT D/Q (DVI) - Provides data on the Iodine-131 relative deposition in I /m2 (Ci/m2 PLOT deposited per Ci/sec released). Assumed deposition rate is .Olm/sec. PRINT D/Q (DVC) - Provides data on the Cesium-137 relative deposition in l/m2 PLOT (Ci/m2 deposited per Ci/sec, released). Assumed deposition rate is .0 1 m/see.

COMMITTED GROUND - Provides data on 1 meter ground shine air dose PLOT rate in mrad/hr, with an initial ground commitment and with a ground commitment for I day, 4 days, 1 year, 2nd year, and 50 years. PRINT PROJECTED INGESTION

SUMMARY

- Provides a summary of ingestion pathway data for affected organs/pathways as previously described for the following isotopes: 1-131, CS-134, CS-137, SR-89, SR-90. Ground shine PRINT committed dose is computer using dose factors without weathering. The results are slightly different from the doses integrated over the commitment time. Air dose assumes 0.7 reduction for ground roughness.

SEND STATE REPORT TO THE PRINTER - Provides an additional printout of the emergency notification form that is identical to the one that was printed for the current update.

TABLE 4 PAGE 3 OF 3 Version 14

09/23/02 13:41:27 Y A '7" f- \ FNP-.-EIP-9.3

.i. . . . .TABLE5 RELEASE POINTS 1.0 THERE ARE FOUR RELEASE POINTS BUILT INTO THE MIDAS PROGRAM:

Release point I - Unit 1 plant vent stack Release point 2 - Unit 1 steam release points Release point 3 - Unit 2 plant vent stack Release point 4 - Unit 2 steam release points 2.0 RELEASE POINT 1 - UNIT 1 PLANT VENT STACK Selecting release point 1 allows radiation monitor inputs from the unit 1 SPING (R29B) for noble gas, iodine and particulate and from unit 1 R14. Inputs from SPING or R14, but not both, must be entered for release point 1 to have a valid source term. In addition to the radiation monitor input, plant vent stack flow must also be input.

3.0 RELEASE POINT 2 - UNIT 1 STEAM RELEASE POINTS Selecting release point 2 allows an input from any one or more of the five unit 1 radiation monitors that monitor steam release paths. Those monitors are:

R60A unit I A steam generator safeties/relief R60B unit 1 B steam generator safeties/relief R60C unit 1 C steam generator safeties/relief R60D unit I TDAFW steam exhaust R 15C unit 1 high range SJAE exhaust For any of the above monitors that have an emergency radioactive release in progress, the monitor reading should be input to the program.

For any monitor that has a radiation reading input, there must also be a flow input. For the SJAE exhaust and the TDAFW exhaust, there is a default value that should be input.

The flow for the steam generator safeties is input as a steam generator pressure. Using the steam generator pressure, the program will determine how many safeties/reliefs are open for that generator and calculate the flow through them. In the event of a stuck open safety or relief valve, enter the actual steam pressure for the generator with the failed safety or relief. The program will assume one valve is open.

4.0 RELEASE POINT 3 - UNIT 2 PLANT VENT STACK Selecting release point 3 allows radiation monitor inputs from the unit 2 SPING (R29B) for noble gas, iodine and particulate or from unit 2 R14. Manipulation of the data is identical to that described for release point 1.

TABLE 5 PAGE 1 OF 2 Version 14

09/23/02 13:41:27 k A FNP-0-EIP-9.3 TABLE 5 5.0 RELEASE POINT 4 - UNIT 2 STEAM RELEASE POINTS Selecting release point 2 allows an input from any one or more of the five unit 1 radiation monitors that monitor steam release paths. Those monitors are:

R60A unit 1 A steam generator safeties/relief R60B unit 1 B steam generator safeties/relief R60C unit 1 C steam generator safeties/relief R60D unit 1 TDAFW steam exhaust R15C unit 1 high range SJAE exhaust Manipulation of the data is identical to that described for release point 2.

6.0 SELECTING RELEASE POINTS WHEN ENTERING DATA The procedure has you select only the two release points for the affected unit, unless both units are affected.

The release points selected when starting a new scenario are the only release points that can be used throughout the entire scenario. For that reason, the procedure has you select both of the release points for the affected unit. If this were not done and a release started on a second release point some time after the first release started, all of the data entered for the initial scenario would have to be hand copied on to a new scenario to provide accurate readings. Whenever possible, the number of release points is kept to the affected unit only to minimize the input and calculation time.

TABLE5 PAGE 2 OF 2 Version 14

09/23/02 13:41:27 .... A% . ) -7 FNP-0-EIP-9.3 TABLE6 OBTAINING MET/RAD DATA Data can be obtained using any combination of the following methods:

GENERAL METHODS 1.0 An emergency release is defined as a release greater than 10 times normal. Normal release levels are average release levels for steady state operation.

2.0 If it is desired to maintain hardcopy of the data input, Figure 1 may be used to list the radiation and meteorological data collected.

3.0 If the ERDS system is available, then the required data can be collected from the ERDS system.

4.0 If the Radiological and Meteorological Data Acquisition (RMDA) system is available, then the required data can be collected from the RMDA.

5.0 If the plant computer is available, then the required data can be collected from the plant computer.

METEOROLOGICAL SPECIFIC INFORMATION 6.0 If meteorological information is not available from the above sources, then FNP-0-EIP 9.2 may be used to obtain meteorological data.

7.0 Rainfall in the last 15 minutes may be estimated by entering L, M or H for light, medium or heavy rain on the spread sheet. If there is no rain, then 0 inches should be entered.

8.0 Delta temperature may be entered as a number or as stability class designator (A through G).

9.0 Values from the 35 foot elevation are preferred for wind speed and direction.

10.0 The wind direction is the direction from which the wind is blowing.

RADIATION MONITOR SPECIFIC INFORMATION 11.0 SPING data is the preferred data for plant vent stack releases; if SPING data is not available, enter R14 data in the spread sheet.

12.0 If failed fuel is indicated and SPING iodine or particulate are not available or reading greater than 1e-6 gtc/ml, then enter a value for SPING iodine and/or particulate that is Ie3 less than the SPING noble gas value.

TABLE 6 PAGE 1 OF 3 Version 14

09/23/02 13:41:27 0// 1T 7 FNP-0-EIP-9.3 TABLE 6 13.0 If SPING data is not available from the above sources, then FNP-0-CCP-641 may be used to poll the high range vent stack monitor (R29B) for the SPING data.

14.0 If SPING and R14 data is not available, have a vent stack sample drawn per FNP-0-CCP 1300, Appendix G.

15.0 If required radiation monitor data is not available from the above sources, obtain the readings directly from the monitors in the control room.

CAUTION: PRIOR TO HAVING THE FOLLOWING STEP PERFORMED, EVALUATE THE RADIOLOGICAL HAZARD AND OBTAIN THE EMERGENCY DIRECTOR'S APPROVAL.

16.0 If none of the above sources are available for R60A/B/C/D, have dose rate readings performed per FNP-0-RCP-25, Appendix G, or have a grab sample taken and analyzed per FNP-0-CCP-645.

CAUTION: PRIOR TO HAVING THE FOLLOWING STEP PERFORMED, EVALUATE THE RADIOLOGICAL HAZARD AND OBTAIN THE EMERGENCY DIRECTOR'S APPROVAL.

17.0 If none of the above sources are available for R15C, have dose rate readings performed per FNP-0-RCP-25, appendix H, or have a grab sample taken per FNP-1 (or 2)-CCP-643 and analyzed per FNP-0-CCP-647.

RELEASE FLOW SPECIFIC INFORMATION 18.0 If plant vent stack flow is not available from the above sources, obtain the value from the flow recorder in the Control Room.

19.0 If plant vent stack flow is not available from the above sources, assume the following default values based on system air balance ventilation flow technical report: (REA 98 1906)

One Auxiliary Building fan running - 94,000 scfm Two Auxiliary Building fan running - 136,000 scfm Zero Auxiliary Building exhaust fans, one train PRF - 5,000 scfm Zero Auxiliary Building exhaust fans, two trains PRF - 10,000 scfm 20.0 For the TDAFW flow, use the default value of 11,175 cfm.

21.0 For the SJAE flow, use the default value of 1,050 cfrn.

TABLE 6 PAGE 2 OF 3 Version 14

09/23/02 13:41:27

?'-1 FNP-0-EIP-9.3 TABLE 6 22.0 If steam generator pressure is not available, obtain the information from the control room instruments.

23.0 If there is a stuck open safety or relief valve associated with a steam generator that has a radioactive release, enter actual pressure for that steam generator which will cause the program to assume that one valve is open for that steam generator.

TABLE 6 PAGE 3 OF 3 Version 14

09/23/02 13:41:27 FNP-0-EIP-9.3 FIGURE 1 MET/RAD DATA MET DATA Wind Speed mph E3 35 ft (Preferred) E3 150 ft E3 Other Wind Dir From deg O 35 ft (Preferred) El 150 ft E3 Other Delta Temp/Stability Class (Most Positive Delta T/Closest To G)

Rainfall (inches in 15 minutes or L,M,H)

VENT STACK DATA El UNIT 1 (release point 1) [E UNIT 2 (release point 3)

ENTER SPING VALUES R29B(I) [tCi/cc R29B(NG) pCi/cc R29B(P) pCi/cc Or Enter R- 14 Value R-14 cpm PLANT VENT STACK FLOW El As Read cfm El Default 1 Fan 94,000 cfm 13 Default 2 Fans 136,000 cfm El Default 0 Fans/I tm PRF 5,000 cfm 13 Default 0 Fans/2 trns PRF 10,000 cfm STEAM RELEASE POINT DATA [E UNIT 1 (release point 2) El UNIT 2 (release point 4)

(Enter 1040 psig for a SG with a stuck open valve)

R-60A rem/hr R-60B rem/hr psig SG A Flow (pressure). psig SG A Flow (pressure)

R-60C rem/hr R-60D rem/hr psig TDAFWFlow 11,175 cfmn SG C Flow (pressure)

R-60D rem/hr SJAE Flow 1,050 mcfm RELEASE POINTS SELECTED El land2(UNIT1) El 3and4(UNIT2)

DBA ACCIDENT SELECTION El Unknown Mix El Fuel Handling Accident E3 WGDT Rupture El LOCA normal RCS with spray El LOCA/SGTR normal RCS without spray El LOCA failed fuel with spray El LOCA/SGTR failed fuel without spray LOCA/SGTR melted fuel without spray El LOCA melted fuel with spray El RELEASE TIMING Remaining Duration - (default 240 minutes)

PAGE I OF Version V 14

09/23/02 13:41:27 FNP-0-EIP-9.3 FIGURE 2 DBA ACCIDENT MIX SELECTION Select LOCA melted fuel with spray I. Indications of failed fuel are sample results, Gross Failed Fuel Detector valid alarm, the results of performing an evaluation of core damage With FNP-0-EIP-30.Oor other indications that the SS, TM or DAD use to evaluate if failed fuel has occurred.

2. Indications of melted fuel are the results of performing an evaluation of core damage with FNP-0-EIP-30.0.

PAGE I OF 1 Version 14

09/23/02 14:04:07 tAl FNP-0-EIP-9.1 September 23, 2002 Version 10 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 9.1 FNP-0-EIP-9.1 S

A F

E T

Y AUTOMATED DOSE ASSESSMENT METHOD R

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A T

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PROCEDURE USAGE REQUIREMENTS per FNP-0-AP-6 SECTIONS Continuous Use Reference Use ALL IInformation Use 1_

Approved:

Nuclear Plant General Manager Date Issued IO iOC9-..

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UNCONTRPOLLED COPY CAUTION: This cpy i5not maintained Current. Do not uss in aiTfty Related Activity I.

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09/23/02 14:04:07 j FNP-0-EIP-9.1 L) -J _. L .* -~-1--1 September 23, 2002 LIST OF EFFECTIVE PAGES PROCEDURE CONTAINS NUMBER OF PAGES Body ................................................................................................................................................. 8 Table l ............................................................................................................................................. 1 Figure l ............................................................................................................................................ 1 Figure 2 ............................................................................................................................................ I Figure 3 ............................................................................................................................................ I Figure 4 ............................................................................................................................................ I Figure 5 ............................................................................................................................................ I Figure 6 ............................................................................................................................................ I Figure 7 ............................................................................................................................................ I Page 1 of I

k 1-L 09/23/02 14:04:07 FNP-0-EIP-9.1 AUTOMATED DOSE ASSESSMENT METHOD TABLE OF CONTENTS Section Title Page 1

1.0 Purpose 1

2.0 References 1

3.0 Entry Conditions General Non-Regulatory ERDS Information 2 4.0 Operation of NON-REGULATORY ERDS 3 5.0 ARDA Function Description 5 6.0 Dose Assessment Following Automatic ARDA Startup 6 7.0 7

8.0 Override Dose Assessment Inputs Using ARDA 8

9.0 If ARDA has NOT Automatically Started and it is Desired to Perform an EDCM Offsite Dose Calculation, Then Perform the Following Steps Table 1 References FIGURE 1 NON REGULATORY ERDS SCREEN FUNCTIONS FIGURE 2 NON REGULATORY ERDS ARDA SCREEN FUNCTIONS FIGURE 3 ERDS GROUP 1 FIGURE 4 ERDS GROUP 2 FIGURE 5 ERDS GROUP 3 FIGURE 6 ARDA DISPLAY FIGURE 7 ERDS MIDAS DATA Page 1 of 1

09/23/02 14:04:07 J _s1-J . J.- FNP-0-EIP-9.1 AUTOMATED DOSE ASSESSMENT METHOD 1.0 Purpose To provide a method for rapid projection of estimated offsite radiation exposures as a result of a release of radioactive material using Emergency Dose Calculation Method (EDCM) methodology. This procedure provides the guidance for use of the Non Regulatory Emergency Response Data System (ERDS) Including the Automatic Rapid Dose Assessment (ARDA) system 2.0 References See TABLE 1 3.0 Entry Conditions 3.1 Entry for using the Non Regulatory ERDS Computer system.

This procedure is entered when it is desired to operate the Non Regulatory ERDS system to provide plant data in the TSC, EOF or the EOC in Birmingham.

3.2 Entry for using the ARDA portion of Non-Regulatory ERDS.

This procedure is entered when it is desired to use the ARDA portion of Non Regulatory ERDS as a separate method of performing off site dose projection 3.2.1 When dose assessment has been performed using the ARDA system, return to FNP-0-EIP-9.0, step 4.2.8 to evaluate the dose levels against the emergency classification criteria.

3.2.2 If ARDA has not automatically started, it can be manually started at any time for dose assessment per step 9.0 of this procedure.

3.2.3 Refer to step 7.0 of this procedure for a more detailed explanation of what occurs during an ARDA auto start. The auto start setpoints are listed below.

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L Jt 09/23/02 14:04:07 FNP-0-EIP-9.1 3.2.4 ARDA will automatically start when any of the following monitors go into alarm for two consecutive system polls one minute apart on either unit and use the latest 15 minute average monitor value to perform the calculations:

Monitor Setpoint Plant Vent Stack R29 (SPING)

Noble Gas 4.44e-4 gic/ml Iodine 1.20e-6 .tc/ml Particulate 4.00e 5 jic/ml Steam Jet air Ejector R15C .027 R/hr TDAFW Exhaust R60D .038 R/hr Steam Generator A R60A .038 R/hr Steam Generator B R60B .038 R/hr Steam Generator C R60C .038 R/hr 3.2.5 ARDA will also automatically start when any of the following monitors go into alarm for two consecutive system polls one minute apart on either unit. The ARDA system will use the plant Vent stack SPING latest 15 minute average monitor value to perform the calculations when these monitors activate the system:

Monitor Setpoint Plant Vent stack Monitors Gas monitor R 14 13000 (Ul) 11571 (U2) CPM Gas monitor R 21 1800 (U1) 4280 (U2) CPM Particulate monitor R 22 156 (Ul) 143 (U2) CPM 4.0 General Non-Regulatory ERDS Information 4.1 Non-Regulatory ERDS terminals are located in the Technical Support Center (TSC), Emergency Operations Facility (EOF) and the Birmingham Emergency Operations Center (EOC).

4.2 Operation of the Regulatory ERDS is provided in FNP-0-EIP-8.3 (Communication Equipment Operating Procedure) at step 10.0.

4.3 The information that the Non-Regulatory ERDS terminals receives comes from the same plant computer points that send data to the Regulatory ERDS system.

There is additional information on the Non-Regulatory ERDS terminals that is not located on the Regulatory ERDS database.

4.4 Operation of the Non-Regulatory ERDS system will not effect the Regulatory ERDS operation.

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09/23/02 14:04:07 FNP-0-EIP-9.1 4.5 Starting data transmission to the NRC on the Regulatory ERDS will start the automatic 15 minute print function on the Non-Regulatory ERDS.

4.6 Figures 1 and 2 provide a graphical representation of the menus associated with the Non-Regulatory ERDS.

4.7 Figures 3 through 7 provide a representation of the Non-Regulatory ERDS output displays.

4.8 Operation of the menus associated with the Non-Regulatory ERDS is described in step 6.

4.9 If the Non-Regulatory ERDS fails to operate properly it can be rebooted by turning the computer off then back on again. The reboot process may take up to five minutes or more. Rebooting a terminal in one location will have no effect on the other terminals. If the system is still not operating properly contact computer services.

4.10 The normal method to control the ERDS terminals is through the use of a trackball or mouse by moving the cursor over the desired menu item, as shown in figures 1 and 2, and pushing the left button.

4.11 The keyboard can also be used to control the ERDS. To access the menu hold K,_ down the Alternate key and press the key for the menu item you desire that is underlined as shown in figure 1 or 2. Once in the menu press the underline key for the item that you want or use the cursor keys to move from one part of the menu to another and press enter.

4.12 The ERDS has two monitors that will show the same information, a large screen remote monitor and a small monitor at the terminal.

4.13 A screen saver will activate after long periods of inactivity on the terminal.

Moving the cursor or pressing any key on the keyboard will return to the normal display.

4.14 The monitors may be turned off during extended periods of inactivity. To reactivate the ERDS turn on the monitors. The terminals themselves should normally be left on.

5.0 Operation of NON-REGULATORY ERDS The following items as shown on Figures 1 and 2 are available on the ERDS menu:

5.1 UNIT - allows the selection of either Unit or the simulator to be used by the terminal.

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"* UNIT 1 -selects unit 1 as the input.

"* UNIT 2 -selects unit 2 as the input.

"* SIMULATION - selects the simulation as the input. This function may be used during drills.

5.2 GROUP DISPLAY -selects which group will be displayed.

"* Group I -selects group 1 for continuous display.

"* Group 2 -selects group 2 for continuous display.

"* Group 3 -selects group 3 for continuous display.

"* ARDA - selects the ARDA screen for continuous display.

" SCROLL -scrolls between groups 1, 2 and 3 leaving each screen on for approximately 20 seconds - this is the normal mode for display during accidents or drills. If ARDA has been activated, the ARDA page will scroll with the other pages for 15 seconds each instead of 20 seconds 5.3 PRINT -allows selection of print options. Figures 3 through 7 are examples of the displays that can be printed.

" DEMAND - causes the MIDAS input page, all three groups and the ARDA screen, if ARDA has been started, to be printed out with the current data; this will not have any effect on the timing of the auto printout.

" START (or STOP) AUTOMATIC PRINTOUT - will start or stop the automatic printout of the MIDAS input page, all three groups and the ARDA screen, if ARDA has been started, every 15 minutes - when the menu item is selected the display of START or STOP will tell you what function you can perform.

5.4 START (STOP) DOSE ASSESSMENT - allows ARDA to be manually started and stopped if ARDA has not automatically started and there are no radiation monitors in alarm.

START DOSE ASSESSMENT allows starting ARDA manually. Requires selecting a release point from the release point selection prior to starting.

STOP DOSE ASSESSMENT - allows manually stopping ARDA if ARDA has not automatically started and there are no radiation monitors in alarm.

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09/23/02 14:04:07 -K* f -lL) FNP-0-EIP-9.1 5.5 RELEASE POINT - allows the manual selection of a release point that has not automatically started ARDA.

"* The Unit that a release is from must first be selected. The Unit selection and ARDA display on the top menu line must be selected to view the release data.

"* Once the unit has been selected then the release point must be selected.

"* If a steam generator has been selected then the number of safeties and/or reliefs that are open must be selected.

5.6 MET INFORMATION - selecting this item allows manually overriding the computer generated meteorological data values using the Manual Value Window.

5.7 RADIATION MONITORS - selecting this item allows manually overriding the computer generated radiation monitor values for a specified Unit.

5.8 PLANT PARAMETERS - selecting this item allows manually overriding the computer generated plant parameters values of steam generator pressure, plant vent stack flow and reactor trip time for a specified Unit.

5.9 PREVIOUS HISTORY - selecting this item allows printing out the ARDA display for the three previous fifteen minute time blocks.

5.10 INVENTORY - selecting this item allows inputting a condition of failed fuel for a selected Unit. This item defaults to normal fuel unless an input of failed or melted fuel is selected.

6.0 ARDA Function Description 6.1 When ARDA has been started it will take meteorological data and radiation monitor data from those monitors that are in alarm or monitors that have been manually selected and display the off-site release magnitude, TEDE dose and Thyroid CDE dose.

6.2 The release magnitude is in uCuries per second for noble gas, iodines and particulates.

6.3 Offsite doses, in mrem TEDE and mrem Thyroid CDE, are given for the site boundary and for 2 miles, 5 miles and 10 miles from the site.

6.4 The calculation done by ARDA is for a 15 minute time block starting at each new quarter hour. The data that is used is the average data for the last complete 15 minute time block.

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FNP-0-EIP-9.1 7.0 Dose Assessment Following Automatic ARDA Startup CAUTION: The ARDA system will automatically start dose assessment based on real time values for the monitor in alarm. However it will use the 15 minute average data from the last complete 15 minute time block to perform the dose calculations. The dose assessment will not show dose values based on the alarming instrument until the next 15 minute time block is complete.

7.1 ARDA will automatically start when the set points as described in step 3 of this procedure are exceeded. It requires two consecutive polls that are one minute apart be above the alarm setpoint to automatically start.

7.2 When ARDA has automatically started, the following will occur:

7.2.1 The displayed page will be the ARDA page for the Unit or simulation that has just had the alarm.

7.2.2 The data used for the calculation will be from the last completed 15" minute time block. The time that this time block was completed is displayed in the upper right hand corner.

7.2.3 The auto print function is started. Nothing will be printed out immediately. The system will print out the five pages specified in step 5.3 at the end of each new 15 minute time block.

7.2.4 Once the system has started, any manual overrides that are put in will not take affect until the end of the 15 minute time block that you are currently in.

7.2.5 When ARDA has automatically started, it cannot be stopped until all of the radiation monitors for the specific unit are below the alarm set point.

7.3 If it is known that a fuel failure or melt has occurred, then select failed or melted fuel per step 8.2.

7.4 If it is known that there are any failed inputs to the ARDA system, then override these inputs per step 8.0.

7.5 Wait until the ARDA screen has updated to the 15 minute time block that the alarm occurred in, then obtain a printout from ARDA.

7.6 Return to FNP-0-EIP-9.0 step 4.2.8 to evaluate emergency classification criteria.

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• FNP-0-EIP-9.1 8.0 Override Dose Assessment Inputs Using ARDA CAUTION Once the system has started, any manual overrides that are put in will not 1 take affect until the end of the 15 minute time block that you are currently in.

Overrides that are put in prior to the start of ARDA will take affect as soon as the ARDA is started.

NOTE: IF CANCEL IS SELECTED FROM THE MANUAL VALUE WINDOW, THE CURRENT OR PREVIOUS MANUAL OVERRIDE VALUE WILL BE LOST AND THE COMPUTER VALUE WILL BE USED.

8.1 IF the computer generated input data for ARDA as displayed in groups 1, 2 or 3 is known to be incorrect THEN manually override the data per the following steps:

8.1.1 Manually override failed wind speed, wind direction or delta T by: 1) selecting MET INFORMATION, 2) selecting the parameter to overide, 3) entering the correct value in the manual override window, and 4) selecting enter.

8.1.2 Manually override the failed radiation monitors by: 1) selecting RADIATION MONITORS, 2) selecting the correct Unit or simulator, 3) selecting the specific monitor to override, 4) entering the correct 15 minute average value in the manual override window, and 5) selecting enter.

8.1.3 Manually override the failed plant parameter by: 1) selecting PLANT PARAMETERS, 2) selecting the correct Unit or simulator, 3) selecting the specific parameter to override, 4) entering the correct value in the manual override window, and 5) selecting enter.

8.1.4 If a steam generator safety valve or relief is stuck open and the steam generator pressure is below 1035 psig, then override the safety or relief open by: 1) selecting Release Point, 2) selecting the appropriate unit or simulation, 3) selecting Steam Generator A, B, or C, and 4) selecting the number of safeties open or the PORV open.

8.1.5 Manually override the Plant Vent Stack (PVS) flow if the computer value is not correct or available with the following value: (REA 98-1906)

a. Obtain PVS flow from NRERDS, RMDA, PVS flow recorder in the CR or use one of the below default values

b. One Auxiliary Building Fan.. .94,000 scfm

c. Two Auxiliary Building Fans... 136,000 scfm

d. Zero Auxiliary Building Exhaust Fans, one train PRF.. .5,000 scfim

e. Zero Auxiliary Building exhaust fans, two trains PRF ... 10,000 scfmn Version 10

09/23/02 14:04:07 10 fJ 1 . ,- ,I,** * --- : FNP-0-EIP-9.1 8.2 Select fuel status per the following criteria:

8.2.1 Failed fuel should be selected if Dose Equivalent Iodine is in excess of 300 icuries per gram as determined by performance of an RCS sample or by comparison of R27A or B monitor readings with Figure 8 of FNP-0-EIP-9.0 or Figure 18 of FNP-0-EIP-30.

8.2.2 Melted fuel should be selected if an FNP-0-EIP-30.0 calculation has determined that there is melted fuel.

8.2.3 IF melted or failed fuel is indicated THEN select INVENTORY, the unit with the fuel problem and then select failed or melted fuel as appropriate.

NORMAL is the default value.

9.0 If ARDA has NOT Automatically Started and it is Desired to Perform an EDCM Offsite Dose Calculation, Then Perform the Following Steps:

9.1 Select UNIT, then in the drop down window select the appropriate Unit or simulator.

9.2 Override any failed parameters for the selected Unit per step 8.1.

9.3 Select fuel status for the selected Unit as appropriate per step 8.2.

9.4 Select RELEASE POINT. Next select the appropriate Unit and then select the appropriate release point.

9.5 IF a steam generator was selected as a release point THEN specify the number of reliefs and/or PORVs that are open.

9.6 Select START DOSE ASSESSMENT.

9.7 Start automatic printout by selecting PRINT then selecting Start Automatic Print.

9.8 If the Radiation Monitor that is being used for dose assessment has been overridden, then select PRINT and Demand Print and go to step 9.10.

9.9 If the Radiation Monitor that is being used for dose assessment has not been overridden, wait until the ARDA screen has updated to the 15 minute time block that ARDA was started in, then obtain a printout from ARDA.

9.10 Obtain a copy of the ARDA printout with offsite dose values and go to FNP-0 EIP-9.0 (Emergency Classification and Actions) step 4.2.8 to evaluate the emergency classification.

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09/23/02 14:04:07 i _ . FNP-0-EIP-9.1 TABLE I References

1. FNP-0-EIP-9.0 Emergency Classification and Actions

2. FNP-0-EIP-20.0, Chemistry and Environmental Support to the Emergency Plan

3. FNP-0-EIP-30 Post Accident Core Damage Assessment

4. FNP 1/2 -CCP-213.1 Gaseous Effluent Radiation Monitoring System Set points

5. FNP-0-CCP-1300 Chemistry and Environmental Activities During A Radiological Accident

6. FNP-1/2-RCP-252 Radiation Monitoring System Set points

7. FNP-0-M-007, Emergency Dose Calculation Method

8. Joseph M. Farley Nuclear Plant Emergency Plan 1 ofl Version 10

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FNP-0-EIP-9. 1 FIGURE 1 nit X Group X NON REGULATORY ERDS Date Time Unit Group Display Print Start Dose Assessment Ielease roint Met Informati n Radiation ionitors Plant Parameters Previous History Inventory Unit 1 Group 1 Demand Print This menu item will toggle between Group 2 Start Automatic Print Start and Stop Dose Assessment Unit 2 Simulation Group 3 or Scroll Stop Automatic Print IOfl Version 10

09/23/02 14:04:07 FNP-0-EIP-9. 1 FIGURE 3 ERDS GROUP 1 TAG# DESCRIPTION VALUE UNITS RC3702 HIGHEST R27 HI LEVEL CTMT RADIATION XXXX R/HR RE0050 GROSS FAILED FUEL DETECTOR XXXX CPM WS35FT WIND SPEED 35' ELEV XXXX MPH WS15OFT WIND SPEED 150' ELEV XXXX MPH WD35FT WIND DIRECTION 35' ELEV XXXX DEGFR WDI50FT WIND DIRECTION 150' ELEV XXXX DEGFR STCLASS STABILITY CLASS DELTA TEMP XxXX DEGF REOO14 VENT GAS MONITOR XXXX CPM RE0021 VENT AIR PARTICLE MONITOR XXXX CPM RE0022 VENT GAS MONITOR XXXX CPM RE0029B-12 VENT IODINE (131) GAS (SPING4) XXXX uCi/ML RE0029B-NG VENT NOBLE GAS (SPING4) XXXX uCi/ML RE0029B-P VENT PARTICULATE (SPING4) XXXX uCi/ML FT2879 PLANT VENT STACK FLOW XXXX CFM REOO15C SJAE EXHAUST HIGH RANGE MONITOR xxXX R/HR RE0060A SG A ATMOSPHERIC RELIEF MONITOR XXXX R/HR RE0060B SG B ATMOSPHERIC RELIEF MONITOR XXXX R/HR RE0060C SG C ATMOSPHERIC RELIEF MONITOR XXXX R/HR RE0060D AUX FEED TURBINE EXHAUST MONITOR XXXX R/HR RE0070A SG A N16 LEAK DETECTION SYSTEM XXXX GPD RE0070B SG B N16 LEAK DETECTION SYSTEM XXXX GPD RE0070C SG C N16 LEAK DETECTION SYSTEM xxXX GPD I oflI Version 10

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09/23/02 14:04:07 C FNP-0-EIP-9.1 FIGURE 4 ERDS GROUP 2 TAG# DESCRIPTION VALUE UNITS TE31871 CTMT DOME INSIDE AIR TEMP XXXx DEGF PC3700 HIGHEST CTMT PRESSURE XXXX PSIG LC 1501 ECCS NR CTMT SUMP LEVEL AVG XXXX FT H2MANUAL CTMT HYDROGEN PC1402A RCS PRESSURE AVG IMA XXXX PSIG NC1 100A POWER RANGE FLUX AVG IMA XXXX FC0400A RCS LOOP A FLOW AVG IMA XXXX FC0420A RCS LOOP B FLOW AVG IMA XXXx FC0440A RCS LOOP C FLOW AVG IMA xxxX TMARCETA SUBCOOLING CHAN A XXXX DEGF TMARCETB SUBCOOLING CHAN B XXXX DEGF TC 1200 FIFTH HOTIEST CORE EXIT TC XXXX DEGF LC1600A PRESSURIZER LEVEL AVG IMA XXXX LC1602 LOWEST UPPER HEAD LEVEL XXXX LC1603 LOWEST UPPER PLENUM LEVEL XxXX LT0477 SG A WIDE RANGE LEVEL XXxx LT0487 SG B WIDE RANGE LEVEL XXXX LT0497 SG C WIDE RANGE LEVEL XXXX LT0501 RWST LEVEL CHAN 1 XXxX FT FE0605A RHR LOOP A FLOW XxXX GPM FE0605B RHR LOOP B FLOW XXXX GPM FC4658 CHARGING LINE CORRECTED FLOW IMA xxXx GPM FE0943 HHSI FLOW XXXX GPM FT3229A AUXILIARY FEEDWATER FLOW TO SG A XXXX GPM FT3229B AUXILIARY FEEDWATER FLOW TO SG B XXXX GPM FT3229C AUXILIARY FEEDWATER FLOW TO SG C XXXX GPM IOfl Version 10

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FIGURE 5 ERDS GROUP 3 TAG# DESCRIPTION VALUE UNITS REOO18 WASTE DISPOSAL LIQUID MONITOR XXXX CPM RE0023B SG BLOWDOWN TREATMENT MONITOR XXXX CPM TE3187H CTMT COOLER A AIR INLET TEMP XXXX DEGF TE3187G CTMT COOLER B AIR INLET TEMP XXXX DEGF TE3187F CTMT COOLER C AIR INLET TEMP XXXX DEGF TE3187E CTMT COOLER D AIR INLET TEMP XXXX DEGF NE0031 SOURCE RANGE FLUX CHAN A NE0032 SOURCE RANGE FLUX CHAN B NE0035 INTERMEDIATE RANGE FLUX CHAN A NE0036 INTERMEDIATE RANGE FLUX CHAN B TC0410A RCS LOOP A CL WIDE RNG TEMP IMA XXXX DEGF TC0413A RCS LOOP A HL WIDE RNG TEMP IMA XXXX DEGF TC0420A RCS LOOP B CL WIDE RNG TEMP IMA XXXX DEGF TC0423A RCS LOOP B HL WIDE RNG TEMP IMA XXXX DEGF TC0430A RCS LOOP C CL WIDE RNG TEMP 1MA XXXX DEGF TC0433A RCS LOOP C HL WIDE RNG TEMP 1MA XXXX DEGF PC2300A SG A PRESSURE AVG IMA XXXX PSIG PC230IA SG B PRESSURE AVG 1MA XXXX PSIG PC2302A SG C PRESSURE AVG IMA XXXX PSIG FC4655 SG A FW CORRECTED FLOW IMA XXXX KBH FC4656 SG B FW CORRECTED FLOW IMA XXXX KBH FC4657, SG C FW CORRECTED FLOW 1MA XXXX KBH I oflI Version 10

, .1 1 q 09/23/02 014:04:07 I FNP-0-EIP-9.1 FIGURE 6 ARDA DISPLAY AUTOMATIC RAPID DOSE ASSESSMENT CURRENT FIFTEEN MINUTE ESTIMATE AS OF DATE TIME (all times central)

• • 11. TYPE OF RELEASE: [X] GROUND LEVEL

[C] AIRBORNE: Started: Stopped:

• • 12. RELEASE MAGNITUDE: [X] uCURIES PER SEC.

[E] NOBLE GAS XXXX [F] IODINES xxxx

[G] PARTICULATES XXXX

• • 13. ESTIMATE OF PROJECTED OFFSITE DOSE: [C] ESTIMATED DURATION: 4 HRS.

TEDE THYROID CDE (mrem) (mrem)

SITE BOUNDARY [D] XXXXXX [E] xxxxxx 2 MILES [F] XXXXXX [G] xxxxxx 5 MILES [H] XXXXXX [I] XX)OXX 10 MILES [J] XXO(XX [K] xxxxxx

• • METEROLOGICAL DATA: [A] WIND DIRECTION (from) XXX [B] SPEED (mph) XXX

[C] STABILITY CLASS X IOfl Version 10

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FIGURE 7 ERDS MIDAS Data TAG# DESCRIPTION VALUE UNITS WS35FT WIND SPEED 35' ELEV xxxX MPH WS15OFT WIND SPEED 150' ELEV XXXX MPH WD35FT WIND DIRECTION 35' ELEV xxxx DEGFR WD15OFT WIND DIRECTION 150' ELEV XXXX DEGFR TE31895 CTMT INTAKE OUTSIDE AIR TEMPERATURE XXXX DEGFR STCLASS STABILITY CLASS DELTA TEMP XxxX DEGF RE0029B-NG VENT NOBLE GAS (SPING4) xxxx ptCi/ML RE0029B-12 VENT IODINE( 131) GAS (SPING4) XxXx jICi/ML RE0029B-P VENT PARTICULATE (SPING4) xxxX gCi/ML RE0014 VENT GAS MONITOR xxxX CPM FT2879 PLANT VENT STACK FLOW xxxx CFM RE0060A SG A ATMOSPHERIC RELIEF MONITOR XXXX R/HR PC2300A SG A PRESSURE AVG IMA XXXX PSIG RE0060B SG B ATMOSPHERIC RELIEF MONITOR xxxX R/HR PC2301A SG B PRESSURE AVG IMA XXXX PSIG RE0060C SG C ATMOSPHERIC RELIEF MONITOR XXXX R/HR PC2302A SG C PRESSURE AVG IMA XXXX PSIG REOO 15C SJAE EXHAUST HIGH RANGE MONITOR XXxX R/HR RE0060D AUX FEED TURBINE EXHAUST MONITOR XXXX R/HR I oflI Version 10

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rT-FNP-0-EIP-9. 1 September 23, 2002 Version 10 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 9.1 FNP-0-EIP-9.1 S

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AUTOMATED DOSE ASSESSMENT METHOD Y R

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Approved:

Nuclear Plant General Manager Date Issued iO IO " "Cc:-.

UNCONTROLLED COPY CAUTION: \ Ti. COpYis n~t maintoined Current. Do not use in a SaIeLy delated Activity

09/23/02 14:04:07 T J  ; FNP-0-EIP-9.1 SSeptember 23, 2002 LIST OF EFFECTIVE PAGES

,) PROCEDURE CONTAINS NUMBER OF PAGES Body ......................................................................................................  :.......................................... 8 Table I ............................................................................................................................................. I Figure I ............................................................................................................................................ 1 Figure 2 ............................................................................................................................................ I Figure 3 ............................................................................................................................................ 1 Figure 4 ............................................................................................................................................ I Figure 5 ............................................................................................................................................ 1 Figure 6 ............................................................................................................................................ 1 Figure 7 ............................................................................................................................................ 1 Page 1 of 1

. , ,' t p.- 3; C FNP-0-EIP-9. 1 09/23/02 14:04:07 FNP-0-EIP-9.1 AUTOMATED DOSE ASSESSMENT METHOD TABLE OF CONTENTS Section Title Page 1.0 Purpose 1 2.0 References 1

3.0 Entry Conditions General Non-Regulatory ERDS Information 2 4.0 Operation of NON-REGULATORY ERDS 3 5.0 ARDA Function Description 5 6.0 Dose Assessment Following Automatic ARDA Startup 6 7.0 Override Dose Assessment Inputs Using ARDA 7 8.0 If ARDA has NOT Automatically Started and it is Desired to 8 9.0 Perform an EDCM Offsite Dose Calculation, Then Perform the Following Steps Table 1 References FIGURE 1 NON REGULATORY ERDS SCREEN FUNCTIONS FIGURE 2 NON REGULATORY ERDS ARDA SCREEN FUNCTIONS FIGURE 3 ERDS GROUP 1 FIGURE 4 ERDS GROUP 2 FIGURE 5 ERDS GROUP 3 FIGURE 6 ARDA DISPLAY FIGURE 7 ERDS MIDAS DATA Page 1 of 1

09/23/02 14:04:07 L -- . FNP-0-EIP-9.1 AUTOMATED DOSE ASSESSMENT METHOD 1.0 Purpose To provide a method for rapid projection of estimated offsite radiation exposures as a result of a release of radioactive material using Emergency Dose Calculation Method (EDCM) methodology. This procedure provides the guidance for use of the Non Regulatory Emergency Response Data System (ERDS) Including the Automatic Rapid Dose Assessment (ARDA) system 2.0 References See TABLE 1 3.0 Entry Conditions 3.1 Entry for using the Non Regulatory ERDS Computer system.

This procedure is entered when it is desired to operate the Non Regulatory ERDS system to provide plant data in the TSC, EOF or the EOC in Birmingham.

3.2 Entry for using the ARDA portion of Non-Regulatory ERDS.

This procedure is entered when it is desired to use the ARDA portion of Non Regulatory ERDS as a separate method of performing off site dose projection 3.2.1 When dose assessment has been performed using the ARDA system, return to FNP-0-EIP-9.0, step 4.2.8 to evaluate the dose levels against the emergency classification criteria.

3.2.2 If ARDA has not automatically started, it can be manually started at any time for dose assessment per step 9.0 of this procedure.

3.2.3 Refer to step 7.0 of this procedure for a more detailed explanation of what occurs during an ARDA auto start. The auto start setpoints are listed below.

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Ci I/TAV 7-t 7' 09/23/02 14:04:07 FNP-0-EIP-9.1 3.2.4 ARDA will automatically start when any of the following monitors go into alarm for two consecutive system polls one minute apart on either unit and use the latest 15 minute average monitor value to perform the calculations:

Monitor Setpoint Plant Vent Stack R29 (SPING)

Noble Gas 4.44e-4 jic/ml Iodine 1.20e-6 ltc/ml Particulate 4.00e 5 gtc/ml Steam Jet air Ejector R15C .027 R/hr TDAFW Exhaust R60D .038 R/hr Steam Generator A R60A .038 R/hr Steam Generator B R60B .038 R/hr Steam Generator C R60C .038 R/hr 3.2.5 ARDA will also automatically start when any of the following monitors go into alarm for two consecutive system polls one minute apart on either unit. The ARDA system will use the plant Vent stack SPING latest 15 minute average monitor value to perform the calculations when these monitors activate the system:

Monitor Setpoint Plant Vent stack Monitors Gas monitor R 14 13000 (U 1) 11571 (U2) CPM Gas monitor R 21 1800 (U1) 4280 (U2) CPM Particulate monitor R 22 156 (Ul) 143 (U2) CPM 4.0 General Non-Regulatory ERDS Information 4.1 Non-Regulatory ERDS terminals are located in the Technical Support Center (TSC), Emergency Operations Facility (EOF) and the Birmingham Emergency Operations Center (EOC).

4.2 Operation of the Regulatory ERDS is provided in FNP-0-EIP-8.3 (Communication Equipment Operating Procedure) at step 10.0.

4.3 The information that the Non-Regulatory ERDS terminals receives comes from the same plant computer points that send data to the Regulatory ERDS system.

There is additional information on the Non-Regulatory ERDS terminals that is not located on the Regulatory ERDS database.

4.4 Operation of the Non-Regulatory ERDS system will not effect the Regulatory ERDS operation.

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A- I 09/23/02 14:04:07 1* \ -- FNP-0-EIP-9. 1 4.5 Starting data transmission to the NRC on the Regulatory ERDS will start the automatic 15 minute print function on the Non-Regulatory ERDS.

4.6 Figures 1 and 2 provide a graphical representation of the menus associated with the Non-Regulatory ERDS.

4.7 Figures 3 through 7 provide a representation of the Non-Regulatory ERDS output displays.

4.8 Operation of the menus associated with the Non-Regulatory ERDS is described in step 6.

4.9 If the Non-Regulatory ERDS fails to operate properly it can be rebooted by turning the computer off then back on again. The reboot process may take up to five minutes or more. Rebooting a terminal in one location will have no effect on the other terminals. If the system is still not operating properly contact computer services.

4.10 The normal method to control the ERDS terminals is through the use of a trackball or mouse by moving the cursor over the desired menu item, as shown in figures 1 and 2, and pushing the left button.

4.11 The keyboard can also be used to control the ERDS. To access the menu hold down the Alternate key and press the key for the menu item you desire that is underlined as shown in figure 1 or 2. Once in the menu press the underline key for the item that you want or use the cursor keys to move from one part of the menu to another and press enter.

4.12 The ERDS has two monitors that will show the same information, a large screen remote monitor and a small monitor at the terminal.

4.13 A screen saver will activate after long periods of inactivity on the terminal.

Moving the cursor or pressing any key on the keyboard will return to the normal display.

4.14 The monitors may be turned off during extended periods of inactivity. To reactivate the ERDS turn on the monitors. The terminals themselves should normally be left on.

5.0 Operation of NON-REGULATORY ERDS The following items as shown on Figures 1 and 2 are available on the ERDS menu:

5.1 UNIT - allows the selection of either Unit or the simulator to be used by the terminal.

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"* UNIT 1 -selects unit 1 as the input.

"* UNIT 2 -selects unit 2 as the input.

"* SIMULATION - selects the simulation as the input. This function may be used during drills.

5.2 GROUP DISPLAY -selects which group will be displayed.

"* Group I -selects group 1 for continuous display.

"* Group 2 -selects group 2 for continuous display.

"* Group 3 -selects group 3 for continuous display.

"* ARDA - selects the ARDA screen for continuous display.

" SCROLL -scrolls between groups 1, 2 and 3 leaving each screen on for approximately 20 seconds - this is the normal mode for display during accidents or drills. If ARDA has been activated, the ARDA page will scroll with the other pages for 15 seconds each instead of 20 seconds 5.3 PRINT -allows selection of print options. Figures 3 through 7 are examples of the displays that can be printed.

" DEMAND - causes the MIDAS input page, all three groups and the ARDA screen, if ARDA has been started, to be printed out with the current data; this will not have any effect on the timing of the auto printout.

" START (or STOP) AUTOMATIC PRINTOUT - will start or stop the automatic printout of the MIDAS input page, all three groups and the ARDA screen, if ARDA has been started, every 15 minutes - when the menu item is selected the display of START or STOP will tell you what function you can perform.

5.4 START (STOP) DOSE ASSESSMENT - allows ARDA to be manually started and stopped if ARDA has not automatically started and there are no radiation monitors in alarm.

START DOSE ASSESSMENT allows starting ARDA manually. Requires selecting a release point from the release point selection prior to starting.

STOP DOSE ASSESSMENT - allows manually stopping ARDA if ARDA has not automatically started and there are no radiation monitors in alarm.

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09/23/02 14:04:07 ] FNP-0-EIP-9.1 5.5 RELEASE POINT - allows the manual selection of a release point that has not automatically started ARDA.

"* The Unit that a release is from must first be selected. The Unit selection and ARDA display on the top menu line must be selected to view the release data.

"* Once the unit has been selected then the release point must be selected.

"* If a steam generator has been selected then the number of safeties and/or reliefs that are open must be selected.

5.6 MET INFORMATION - selecting this item allows manually overriding the computer generated meteorological data values using the Manual Value Window.

5.7 RADIATION MONITORS - selecting this item allows manually overriding the computer generated radiation monitor values for a specified Unit.

5.8 PLANT PARAMETERS - selecting this item allows manually overriding the computer generated plant parameters values of steam generator pressure, plant vent stack flow and reactor trip time for a specified Unit.

5.9 PREVIOUS HISTORY - selecting this item allows printing out the ARDA display for the three previous fifteen minute time blocks.

5.10 INVENTORY - selecting this item allows inputting a condition of failed fuel for a selected Unit. This item defaults to normal fuel unless an input of failed or melted fuel is selected.

6.0 ARDA Function Description 6.1 When ARDA has been started it will take meteorological data and radiation monitor data from those monitors that are in alarm or monitors that have been manually selected and display the off-site release magnitude, TEDE dose and Thyroid CDE dose.

6.2 The release magnitude is in uCuries per second for noble gas, iodines and particulates.

6.3 Offsite doses, in mrem TEDE and mrem Thyroid CDE, are given for the site boundary and for 2 miles, 5 miles and 10 miles from the site.

6.4 The calculation done by ARDA is for a 15 minute time block starting at each new quarter hour. The data that is used is the average data for the last complete 15 minute time block.

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09/23/02 14:04:07 K; _ -. .* :.. Ž* FNP-0-EIP-9.1 7.0 Dose Assessment Following Automatic ARDA Startup CAUTION: The ARDA system will automatically start dose assessment based on real time values for the monitor in alarm. However it will use the 15 minute average data from the last complete 15 minute time block to perform the dose calculations. The dose assessment will not show dose values based on the alarming instrument until the next 15 minute time block is complete.

7.1 ARDA will automatically start when the set points as described in step 3 of this procedure are exceeded. It requires two consecutive polls that are one minute apart be above the alarm setpoint to automatically start.

7.2 When ARDA has automatically started, the following will occur:

7.2.1 The displayed page will be the ARDA page for the Unit or simulation that has just had the alarm.

7.2.2 The data used for the calculation will be from the last completed 15 minute time block. The time that this time block was completed is displayed in the upper right hand comer.

7.2.3 The auto print function is started. Nothing will be printed out immediately. The system will print out the five pages specified in step 5.3 at the end of each new 15 minute time block.

7.2.4 Once the system has started, any manual overrides that are put in will not take affect until the end of the 15 minute time block that you are currently in.

7.2.5 When ARDA has automatically started, it cannot be stopped until all of the radiation monitors for the specific unit are below the alarm set point.

7.3 If it is known that a fuel failure or melt has occurred, then select failed or melted fuel per step 8.2.

7.4 If it is known that there are any failed inputs to the ARDA system, then override these inputs per step 8.0.

7.5 Wait until the ARDA screen has updated to the 15 minute time block that the alarm occurred in, then obtain a printout from ARDA.

7.6 Return to FNP-0-EIP-9.0 step 4.2.8 to evaluate emergency classification criteria.

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• FNP-0-EIP-9.1 8.0 Override Dose Assessment Inputs Using ARDA CAUTION Once the system has started, any manual overrides that are put in will not take affect until the end of the 15 minute time block that you are currently in.

Overrides that are put in prior to the start of ARDA will take affect as soon as the ARDA is started.

NOTE: IF CANCEL IS SELECTED FROM THE MANUAL VALUE WINDOW, THE CURRENT OR PREVIOUS MANUAL OVERRIDE VALUE WILL BE LOST AND THE COMPUTER VALUE WILL BE USED.

8.1 IF the computer generated input data for ARDA as displayed in groups 1,2 or 3 is known to be incorrect THEN manually override the data per the following steps:

8.1.1 Manually override failed wind speed, wind direction or delta T by: 1) selecting MET INFORMATION, 2) selecting the parameter to overide, 3) entering the correct value in the manual override window, and 4) selecting enter.

8.1.2 Manually override the failed radiation monitors by: 1) selecting RADIATION MONITORS, 2) selecting the correct Unit or simulator, 3) selecting the specific monitor to override, 4) entering the correct 15 minute average value in the manual override window, and 5) selecting enter.

8.1.3 Manually override the failed plant parameter by-. 1) selecting PLANT PARAMETERS, 2) selecting the correct Unit or simulator, 3) selecting the specific parameter to override, 4) entering the correct value in the manual override window, and 5) selecting enter.

8.1.4 If a steam generator safety valve or relief is stuck open and the steam generator pressure is below 1035 psig, then override the safety or relief open by: 1) selecting Release Point, 2) selecting the appropriate unit or simulation, 3) selecting Steam Generator A, B, or C, and 4) selecting the number of safeties open or the PORV open.

8.1.5 Manually override the Plant Vent Stack (PVS) flow if the computer value is not correct or available with the following value: (REA 98-1906)

a. Obtain PVS flow from NRERDS, RMDA, PVS flow recorder in the CR or use one of the below default values

b. One Auxiliary Building Fan.. .94,000 scfm

c. Two Auxiliary Building Fans... 136,000 scfm

d. Zero Auxiliary Building Exhaust Fans, one train PRF.. .5,000 scfm

e. Zero Auxiliary Building exhaust fans, two trains PRF... 10,000 scfm Version 10

09/23/02 14:04:07 .. . L FNP-0-EIP-9.1 8.2 Select fuel status per the following criteria:

8.2.1 Failed fuel should be selected if Dose Equivalent Iodine is in excess of 300 tcuries per gram as determined by performance of an RCS sample or by comparison of R27A or B monitor readings with Figure 8 of FNP-0-EIP-9.0 or Figure 18 of FNP-0-EIP-30.

8.2.2 Melted fuel should be selected if an FNP-0-EIP-30.0 calculation has determined that there is melted fuel.

8.2.3 IF melted or failed fuel is indicated THEN select INVENTORY, the unit with the fuel problem and then select failed or melted fuel as appropriate.

NORMAL is the default value.

9.0 If ARDA has NOT Automatically Started and it is Desired to Perform an EDCM Offsite Dose Calculation, Then Perform the Following Steps:

9.1 Select UNIT, then in the drop down window select the appropriate Unit or simulator.

9.2 Override any failed parameters for the selected Unit per step 8.1.

9.3 Select fuel status for the selected Unit as appropriate per step 8.2.

9.4 Select RELEASE POINT. Next select the appropriate Unit and then select the appropriate release point.

9.5 IF a steam generator was selected as a release point THEN specify the number of reliefs and/or PORVs that are open.

9.6 Select START DOSE ASSESSMENT.

9.7 Start automatic printout by selecting PRINT then selecting Start Automatic Print.

9.8 If the Radiation Monitor that is being used for dose assessment has been overridden, then select PRINT and Demand Print and go to step 9.10.

9.9 If the Radiation Monitor that is being used for dose assessment has not been overridden, wait until the ARDA screen has updated to the 15 minute time block that ARDA was started in, then obtain a printout from ARDA.

9.10 Obtain a copy of the ARDA printout with offsite dose values and go to FNP-0 EIP-9.0 (Emergency Classification and Actions) step 4.2.8 to evaluate the emergency classification.

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• 1 / FNP-0-EI ?-9.1 TABLE I References

1. FNP-0-EIP-9.0 Emergency Classification and Actions

2. FNP-0-EIP-20.0, Chemistry and Environmental Support to the Emergency Plan

3. FNP-0-EIP-30 Post Accident Core Damage Assessment

4. FNP 1/2 -CCP-213.1 Gaseous Effluent Radiation Monitoring System Set points

5. FNP-0-CCP-1300 Chemistry and Environmental Activities During A Radiological Accident

6. FNP-1/2-RCP-252 Radiation Monitoring System Set points

7. FNP-O-M-007, Emergency Dose Calculation Method

8. Joseph M. Farley Nuclear Plant Emergency Plan I oflI Version 10

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FNP-0-EIP-9. 1

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4' 4.4 FIGURE 1 Unit X Group X NON REGULATORY ERDS Date Time Unit Group Display PIrint Start Dose Assessment I elease oint Met Informati n Radiation onitors Plant Parameters Previous History Inventory Unit 1 Group I Demand Print This menu item will toggle between Unit 2 Group 2 Start Automatic Print Start and Stop Dose Assessment Simulation Group a or Scroll Stop Automatic Print I oflI Version 10

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09/23/02 14:04:07 FNP-0-EIP-9.1 N I FIGURE 2 Unit X Group X NON REGULATORY ERDS Date Time Unit Group Display Print Start(Stop) Dose Assessment Release Point Met Information Radiation Monitors Plant Parameters Previous History Inventory a I I l I l15 Minute previous' W&I I

-- I 30 Minute Previous/ Unit 1 00 Manual Overr ide *p45 Minute Prev'i-ousl Unit 2 pop Unit 1 I Unit 2 Wind Speed (MPI)EGF) - UnitlI jimulationk[-

SimulationE Wind Direction(

Delta T Unit 2 ?L"it 1 WI IF

,, ~Simul-ation* H uni~t 2. "

a- VALUESimu]-ationo r" Plant Vent Stack Steam Jet Air Ejector TDAFW Exhaust I MANUAL WIND OW DC,;AD7-,

Normal Fuel Failed Fuel Melted Fuel Steam Generator A 1 Safety Manual Override - a Steam Generator B 32 Safeties Safeties SPING Iodine Manual Override Steam Generator C 3 Safeties SPING Noble Gas SG A Pressure a

Saeties SPING Particulate SG A Pressure SJAE Exhaust SG A Pressure MANUAL VALUE WINDOW SG A Atmospheric Relief Plant Vent Stack Flow Enter Manual Value For xxxxx SG B Atmospheric Relief ~eaCtor I ri ipie SG C Atmospheric Relief WINDOW MANUAL VALUE EntlI771 TDAFW Exhaust WINDOW I oflI Version 10

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FNP-0-EIP-9.1 FIGURE 3 ERDS GROUP 1 TAG# DESCRIPTION VALUE UNITS RC3702 HIGHEST R27 HI LEVEL CTMT RADIATION XXXX R/HR RE0050 GROSS FAILED FUEL DETECTOR XXXX CPM WS35FT WIND SPEED 35' ELEV XXXX MPH WS 15OFT WIND SPEED 150' ELEV XXXX MPH WD35FT WIND DIRECTION 35' ELEV XxXx DEGFR WD15OFT WIND DIRECTION 150' ELEV XXxX DEGFR STCLASS STABILITY CLASS DELTA TEMP XXXX DEGF RE0014 VENT GAS MONITOR XXXX CPM RE0021 VENT AIR PARTICLE MONITOR XXxx CPM RE0022 VENT GAS MONITOR XXXX CPM RE0029B-12 VENT IODINE (131) GAS (SPING4) XXxx uCi/ML RE0029B-NG VENT NOBLE GAS (SPING4) XXXX uCi/ML RE0029B-P VENT PARTICULATE (SPING4) XXXX uCi/ML FT2879 PLANT VENT STACK FLOW XxXX CFM RE0015C SJAE EXHAUST HIGH RANGE MONITOR XXXX R/HR RE0060A SG A ATMOSPHERIC RELIEF MONITOR XXXX R/HR RE0060B SG B ATMOSPHERIC RELIEF MONITOR XXXX R/HR RE0060C SG C ATMOSPHERIC RELIEF MONITOR XXXX R/HR RE0060D AUX FEED TURBINE EXHAUST MONITOR XXXX R/HR RE0070A SG A N16 LEAK DETECTION SYSTEM XXXX GPD RE0070B SG B N16 LEAK DETECTION SYSTEM XXXX GPD REO070C SG C N16 LEAK DETECTION SYSTEM XXXX GPD.

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,*",*FNP-0-EIP-9.1I 09/23/02 14:04:07 FIGURE 4 ERDS GROUP 2 TAG# DESCRIPTION VALUE UNITS TE31871 CTMT DOME INSIDE AIR TEMP XXXX DEGF PC3700 HIGHEST CTMT PRESSURE XXXX PSIG LC1501 ECCS NR CTMT SUMP LEVEL AVG XXXX FT H2MANUAL CTMT HYDROGEN PC1402A RCS PRESSURE AVG IMA XXXX PSIG NCI 100A POWER RANGE FLUX AVG 1MA XXXX FC0400A RCS LOOP A FLOW AVG IMA XXXX FC0420A RCS LOOP B FLOW AVG IMA XXXX FC0440A RCS LOOP C FLOW AVG IMA XXXX TMARCETA SUBCOOLING CHAN A XXXX DEGF TMARCETB SUBCOOLING CHAN B XXXX DEGF TC1200 FIFTH HOTTEST CORE EXIT TC XXXX DEGF LC1600A PRESSURIZER LEVEL AVG IMA XXXX LC1602 LOWEST UPPER HEAD LEVEL XxXX LC1603 LOWEST UPPER PLENUM LEVEL XXXX LT0477 SG A WIDE RANGE LEVEL XXXX LT0487 SG B WIDE RANGE LEVEL XXXX LT0497 SG C WIDE RANGE LEVEL XXXX LT0501 RWST LEVEL CHAN 1 XXXX FT FE0605A RHR LOOP A FLOW XXXX GPM FE0605B RHR LOOP B FLOW XXXX GPM FC4658 CHARGING LINE CORRECTED FLOW IMA XXXX GPM FE0943 HHSI FLOW XxXX GPM FT3229A AUXILIARY FEEDWATER FLOW TO SG A XXXX GPM FT3229B AUXILIARY FEEDWATER FLOW TO SG B XXxX GPM FT3229C AUXILIARY FEEDWATER FLOW TO SG C XXXX GPM I oflI Version 10

09/23/02 14:04:07 FNP-0-EIP-9.1 FIGURE 5 ERDS GROUP 3 TAG# DESCRIPTION VALUE UNITS REOO18 WASTE DISPOSAL LIQUID MONITOR XXXX CPM RE0023B SG BLOWDOWN TREATMENT MONITOR XXXX CPM TE3187H CTMT COOLER A AIR INLET TEMP XXXX DEGF TE3187G CTMT COOLER B AIR INLET TEMP XXXX DEGF TE3187F CTMT COOLER C AIR INLET TEMP XXXX DEGF TE3187E CTMT COOLER D AIR INLET TEMP XXXX DEGF NE0031 SOURCE RANGE FLUX CHAN A NE0032 SOURCE RANGE FLUX CHAN B NE0035 INTERMEDIATE RANGE FLUX CHAN A NE0036 INTERMEDIATE RANGE FLUX CHAN B TC0410A RCS LOOP A CL WIDE RNG TEMP IMA XXXX DEGF TC0413A RCS LOOP A HL WIDE RNG TEMP 1MA XXXX DEGF TC0420A RCS LOOP B CL WIDE RNG TEMP IMA XXXX DEGF TC0423A RCS LOOP B HL WIDE RNG TEMP IMA XXXX DEGF TC0430A RCS LOOP C CL WIDE RNG TEMP 1MA XXXX DEGF TC0433A RCS LOOP C HL WIDE RNG TEMP IMA XXXX DEGF PC2300A SG A PRESSURE AVG IMA XXXX PSIG PC2301A SG B PRESSURE AVG IMA XXXX PSIG PC2302A SG C PRESSURE AVG IMA XXXX PSIG FC4655 SG A FW CORRECTED FLOW IMA XXXX KBH FC4656 SG B FW CORRECTED FLOW IMA XXXX KBH FC4657 SG C FW CORRECTED FLOW IMA XXXX KBH I oflI Version 10

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FIGURE 6 ARDA DISPLAY AUTOMATIC RAPID DOSE ASSESSMENT CURRENT FIFTEEN MINUTE ESTIMATE AS OF DATE TIME (all times central)

"*t1. TYPE OF RELEASE: [X] GROUND LEVEL

[C] AIRBORNE: Started: Stopped:

• • 12. RELEASE MAGNITUDE: [X] uCURIES PER SEC.

[E] NOBLE GAS XXXX [F] IODINES xxxx

[G] PARTICULATES XXXX

• • 13. ESTIMATE OF PROJECTED OFFSITE DOSE: [C] ESTIMATED DURATION: 4 HRS.

TEDE THYROID CDE (mrem) (mrrem)

SITE BOUNDARY [D] XXXXXX [E] xxxxxx 2 MILES [F] XXXXXX [G] xxxxxx 5 MILES [H] XXXXXX [I] xxxxxx 10 MILES [J] XXXXXX [K] xxxxxx

• • METEROLOGICAL DATA: [A] WIND DIRECTION (from) XXX [B] SPEED (mph) XXX

[C] STABILITY CLASS X 1loft Version 10

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FIGURE 7 ERDS MIDAS Data TAG# DESCRIPTION VALUE UNITS WS35FT WIND SPEED 35' ELEV xxxx MPH WSI5OFT WIND SPEED 150' ELEV XXXX MPH WD35FT WIND DIRECTION 35' ELEV xxxx DEGFR WD15OFT WIND DIRECTION 150' ELEV xxxx DEGFR TE31895 CTMT INTAKE OUTSIDE AIR TEMPERATURE XXXX DEGFR STCLASS STABILITY CLASS DELTA TEMP xxxx DEGF RE0029B-NG VENT NOBLE GAS (SPING4) XXXX jiCi/ML RE0029B-12 VENT IODINE(131) GAS (SPING4) XXXX ptCi/ML RE0029B-P VENT PARTICULATE (SPING4) xxxx JiCi/ML RE0014 VENT GAS MONITOR XXXX CPM FT2879 PLANT VENT STACK FLOW XXXX CFM RE0060A SG A ATMOSPHERIC RELIEF MONITOR XXXX R/HR PC2300A SG A PRESSURE AVG IMA XXXX PSIG RE0060B SG B ATMOSPHERIC RELIEF MONITOR XXXX R/HR PC2301A SG B PRESSURE AVG 1MA xxxX PSIG RE0060C SG C ATMOSPHERIC RELIEF MONITOR XXXX R/HR PC2302A SG C PRESSURE AVG 1MA XXXX PSIG REOO15C SJAE EXHAUST HIGH RANGE MONITOR XXXX R/HR RE0060D AUX FEED TURBINE EXHAUST MONITOR XXXX R/HR IOfl Version 10

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~ *7t FNP-0-EIP-9.1 September 23, 2002 Version 10 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 9.1 FNP-0-EIP-9.1 S

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PROCEDURE USAGE REQUIREMENTS per FNP-0-AP-6 SECTIONS Continuous Use Reference Use ALL Information Use 1_

Approved:

Nuclear Plant General Manager Date Issued i0 LOC9 -cc;)--,

10 - /0 UNCONTROLLED COPY CAUTION: Thi coqpyis not maintained Current. Do not use in a Re1lated Activity J

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09/23/02 14:04:07 .JfFNP-0-EIP-9.1 3 1- September 23, 2002 LIST OF EFFECTIVE PAGES PROCEDURE CONTAINS NUMBER OF PAGES Body ................................................................................................................................................. 8 Table I ............................................................................................................................................. 1 Figure I ............................................................................................................................................ 1 Figure 2 ............................................................................................................................................ I Figure 3 ............................................................................................................................................ 1 Figure 4 ............................................................................................................................................ 1 Figure 5 ............................................................................................................................................ 1 Figure 6 ............................................................................................................................................ 1 Figure 7 ............................................................................................................................................ 1 Page 1 of 1

T 09/23/02 14:04:07 FNP-0-EIP-9.1 AUTOMATED DOSE ASSESSMENT METHOD TABLE OF CONTENTS Section Title Page 1.0 Purpose 1

2.0 References 1

3.0 Entry Conditions 2

4.0 General Non-Regulatory ERDS Information 3

5.0 Operation of NON-REGULATORY ERDS 5

6.0 ARDA Function Description 6

7.0 Dose Assessment Following Automatic ARDA Startup 7

8.0 Override Dose Assessment Inputs Using ARDA 8

9.0 If ARDA has NOT Automatically Started and it is Desired to Perform an EDCM Offsite Dose Calculation, Then Perform the Following Steps Table 1 References FIGURE 1 NON REGULATORY ERDS SCREEN FUNCTIONS FIGURE 2 NON REGULATORY ERDS ARDA SCREEN FUNCTIONS FIGURE 3 ERDS GROUP 1 FIGURE 4 ERDS GROUP 2 FIGURE 5 ERDS GROUP 3 FIGURE 6 ARDA DISPLAY FIGURE 7 ERDS MIDAS DATA Page 1 of 1

09/23/02 14:04:07 J -- - " FNP-0-EIP-9.l AUTOMATED DOSE ASSESSMENT METHOD 1.0 Purpose To provide a method for rapid projection of estimated offsite radiation exposures as a result of a release of radioactive material using Emergency Dose Calculation Method (EDCM) methodology. This procedure provides the guidance for use of the Non Regulatory Emergency Response Data System (ERDS) Including the Automatic Rapid Dose Assessment (ARDA) system 2.0 References See TABLE 1 3.0 Entry Conditions 3.1 Entry for using the Non Regulatory ERDS Computer system.

This procedure is entered when it is desired to operate the Non Regulatory ERDS system to provide plant data in the TSC, EOF or the EOC in Birmingham.

3.2 Entry for using the ARDA portion of Non-Regulatory ERDS.

This procedure is entered when it is desired to use the ARDA portion of Non Regulatory ERDS as a separate method of performing off site dose projection 3.2.1 When dose assessment has been performed using the ARDA system, return to FNP-0-EIP-9.0, step 4.2.8 to evaluate the dose levels against the emergency classification criteria.

3.2.2 If ARDA has not automatically started, it can be manually started at any time for dose assessment per step 9.0 of this procedure.

3.2.3 Refer to step 7.0 of this procedure for a more detailed explanation of what occurs during an ARDA auto start. The auto start setpoints are listed below.

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09/23/02 14:04:07 FNP-0-EIP-9.1 3.2.4 ARDA will automatically start when any of the following monitors go into alarm for two consecutive system polls one minute apart on either unit and use the latest 15 minute average monitor value to perform the calculations:

Monitor Setpoint Plant Vent Stack R29 (SPING)

Noble Gas 4.44e-4 [tc/ml Iodine 1.20e-6 g~c/ml Particulate 4.00e 5 pgc/ml Steam Jet air Ejector R15C .027 R/hr TDAFW Exhaust R60D .038 R/hr Steam Generator A R60A .038 R/hr Steam Generator B R60B .038 R/hr Steam Generator C R60C .038 R/hr 3.2.5 ARDA will also automatically start when any of the following monitors go into alarm for two consecutive system polls one minute apart on either unit. The ARDA system will use the plant Vent stack SPING latest 15 minute average monitor value to perform the calculations when these monitors activate the system:

Monitor Setpoint Plant Vent stack Monitors Gas monitor R 14 13000 (U I) 11571 (U2) CPM Gas monitor R 21 1800 (U1) 4280 (U2) CPM Particulate monitor R 22 156 (Ul) 143 (U2) CPM 4.0 General Non-Regulatorv ERDS Information 4.1 Non-Regulatory ERDS terminals are located in the Technical Support Center (TSC), Emergency Operations Facility (EOF) and the Birmingham Emergency Operations Center (EOC).

4.2 Operation of the Regulatory ERDS is provided in FNP-0-EIP-8.3 (Communication Equipment Operating Procedure) at step 10.0.

4.3 The information that the Non-Regulatory ERDS terminals receives comes from the same plant computer points that send data to the Regulatory ERDS system.

There is additional information on the Non-Regulatory ERDS terminals that is not located on the Regulatory ERDS database.

4.4 Operation of the Non-Regulatory ERDS system will not effect the Regulatory ERDS operation.

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09/23/02 14:04:07 *. "D*.*.. FNP-0-EIP-9.1 4.5 Starting data transmission to the NRC on the Regulatory ERDS will start the automatic 15 minute print function on the Non-Regulatory ERDS.

4.6 Figures 1 and 2 provide a graphical representation of the menus associated with the Non-Regulatory ERDS.

4.7 Figures 3 through 7 provide a representation of the Non-Regulatory ERDS output displays.

4.8 Operation of the menus associated with the Non-Regulatory ERDS is described in step 6.

4.9 If the Non-Regulatory ERDS fails to operate properly it can be rebooted by turning the computer off then back on again. The reboot process may take up to five minutes or more. Rebooting a terminal in one location will have no effect on the other terminals. If the system is still not operating properly contact computer services.

4.10 The normal method to control the ERDS terminals is through the use of a trackball or mouse by moving the cursor over the desired menu item, as shown in figures 1 and 2, and pushing the left button.

4.11 The keyboard can also be used to control the ERDS. To access the menu hold down the Alternate key and press the key for the menu item you desire that is underlined as shown in figure I or 2. Once in the menu press the underline key for the item that you want or use the cursor keys to move from one part of the menu to another and press enter.

4.12 The ERDS has two monitors that will show the same information, a large screen remote monitor and a small monitor at the terminal.

4.13 A screen saver will activate after long periods of inactivity on the terminal.

Moving the cursor or pressing any key on the keyboard will return to the normal display.

4.14 The monitors may be turned off during extended periods of inactivity. To reactivate the ERDS turn on the monitors. The terminals themselves should normally be left on.

5.0 Operation of NON-REGULATORY ERDS The following items as shown on Figures 1 and 2 are available on the ERDS menu:

5.1 UNIT - allows the selection of either Unit or the simulator to be used by the terminal.

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• UNIT 1 -selects unit 1 as the input.

0 UNIT 2 -selects unit 2 as the input.

0 SIMULATION - selects the simulation as the input. This function may be used during drills.

5.2 GROUP DISPLAY -selects which group will be displayed.

"* Group 1 -selects group 1 for continuous display.

"* Group 2 -selects group 2 for continuous display.

"* Group 3 -selects group 3 for continuous display.

"* ARDA - selects the ARDA screen for continuous display.

" SCROLL -scrolls between groups 1, 2 and 3 leaving each screen on for approximately 20 seconds - this is the normal mode for display during accidents or drills. If ARDA has been activated, the ARDA page will scroll with the other pages for 15 seconds each instead of 20 seconds 5.3 PRINT -allows selection of print options. Figures 3 through 7 are examples of the "displaysthat can be printed.

" DEMAND - causes the MIDAS input page, all three groups and the ARDA screen, if ARDA has been started, to be printed out with the current data; this will not have any effect on the timing of the auto printout.

"* START (or STOP) AUTOMATIC PRINTOUT - will start or stop the automatic printout of the MIDAS input page, all three groups and the ARDA screen, if ARDA has been started, every 15 minutes - when the menu item is selected the display of START or STOP will tell you what function you can perform.

5.4 START (STOP) DOSE ASSESSMENT - allows ARDA to be manually started and stopped if ARDA has not automatically started and there are no radiation monitors in alarm.

START DOSE ASSESSMENT allows starting ARDA manually. Requires selecting a release point from the release point selection prior to starting.

STOP DOSE ASSESSMENT - allows manually stopping ARDA if ARDA has not automatically started and there are no radiation monitors in alarm.

Version 10

TI 09/23/02 14:04:07 17] .* ..... .. ,. FNP-0-EIP-9.1 5.5 RELEASE POINT - allows the manual selection of a release point that has not automatically started ARDA.

"* The Unit that a release is from must first be selected. The Unit selection and ARDA display on the top menu line must be selected to view the release data.

"* Once the unit has been selected then the release point must be selected.

"* If a steam generator has been selected then the number of safeties and/or reliefs that are open must be selected.

5.6 MET INFORMATION - selecting this item allows manually overriding the computer generated meteorological data values using the Manual Value Window.

5.7 RADIATION MONITORS - selecting this item allows manually overriding the computer generated radiation monitor values for a specified Unit.

5.8 PLANT PARAMETERS - selecting this item allows manually overriding the computer generated plant parameters values of steam generator pressure, plant vent stack flow and reactor trip time for a specified Unit.

5.9 PREVIOUS HISTORY - selecting this item allows printing out the ARDA display for the three previous fifteen minute time blocks.

5.10 INVENTORY - selecting this item allows inputting a condition of failed fuel for a selected Unit. This item defaults to normal fuel unless an input of failed or melted fuel is selected.

6.0 ARDA Function Description 6.1 When ARDA has been started it will take meteorological data and radiation monitor data from those monitors that are in alarm or monitors that have been manually selected and display the off-site release magnitude, TEDE dose and Thyroid CDE dose.

6.2 The release magnitude is in uCuries per second for noble gas, iodines and particulates.

6.3 Offsite doses, in mrem TEDE and mrem Thyroid CDE, are given for the site

- boundary and for 2 miles, 5 miles and 10 miles from the site.

6.4 The calculation done by ARDA is for a 15 minute time block starting at each new quarter hour. The data that is used is the average data for the last complete 15 minute time block.

Version 10

09/23/02 14:04:07 - .. . , Y . FNP-0-EIP-9.1 7.0 Dose Assessment Following Automatic ARDA Startup CAUTION: The ARDA system will automatically start dose assessment based on real time values for the monitor in alarm. However it will use the 15 minute average data from the last complete 15 minute time block to perform the dose calculations. The dose assessment will not show dose values based on the alarming instrument until the next 15 minute time block is complete.

7.1 ARDA will automatically start when the set points as described in step 3 of this procedure are exceeded. It requires two consecutive polls that are one minute apart be above the alarm setpoint to automatically start.

7.2 When ARDA has automatically started, the following will occur:

7.2.1 The displayed page will be the ARDA page for the Unit or simulation that has just had the alarm.

7.2.2 The data used for the calculation will be from the last completed 15 minute time block. The time that this time block was completed is displayed in the upper right hand comer.

7.2.3 The auto print function is started. Nothing will be printed out immediately. The system will print out the five pages specified in step 5.3 at the end of each new 15 minute time block.

7.2.4 Once the system has started, any manual overrides that are put in will not take affect until the end of the 15 minute time block that you are currently in.

7.2.5 When ARDA has automatically started, it cannot be stopped until all of the radiation monitors for the specific unit are below the alarm set point.

7.3 If it is known that a fuel failure or melt has occurred, then select failed or melted fuel per step 8.2.

7.4 If it is known that there are any failed inputs to the ARDA system, then override these inputs per step 8.0.

7.5 Wait until the ARDA screen has updated to the 15 minute time block that the alarm occurred in, then obtain a printout from ARDA.

7.6 Return to FNP-0-EIP-9.0 step 4.2.8 to evaluate emergency classification criteria.

Version 10

~-J 't ,

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• F FNP-0-EIP-9.1 8.0 Override Dose Assessment Inputs Using ARDA IICAUTION Once the system has started, any manual overrides that are put in will not take affect until the end of the 15 minute time block that you are currently in.

Overrides that are put in prior to the start of ARDA will take affect as soon as the ARDA is started.

NOTE: IF CANCEL IS SELECTED FROM THE MANUAL VALUE WINDOW, THE CURRENT OR PREVIOUS MANUAL OVERRIDE VALUE WILL BE LOST AND THE COMPUTER VALUE WILL BE USED.

8.1 IF the computer generated input data for ARDA as displayed in groups 1, 2 or 3 is known to be incorrect THEN manually override the data per the following steps:

8.1.1 Manually override failed wind speed, wind direction or delta T by: 1) selecting MET INFORMATION, 2) selecting the parameter to overide, 3) entering the correct value in the manual override window, and 4) selecting enter.

8.1.2 Manually override the failed radiation monitors by: 1) selecting RADIATION MONITORS, 2) selecting the correct Unit or simulator, 3) selecting the specific monitor to override, 4) entering the correct 15 minute average value in the manual override window, and 5) selecting enter.

8.1.3 Manually override the failed plant parameter by-. 1) selecting PLANT PARAMETERS, 2) selecting the correct Unit or simulator, 3) selecting the specific parameter to override, 4) entering the correct value in the manual override window, and 5) selecting enter.

8.1.4 If a steam generator safety valve or relief is stuck open and the steam generator pressure is below 1035 psig, then override the safety or relief open by: 1) selecting Release Point, 2) selecting the appropriate unit or simulation, 3) selecting Steam Generator A, B, or C, and 4) selecting the number of safeties open or the PORV open.

8.1.5 Manually override the Plant Vent Stack (PVS) flow if the computer value is not correct or available with the following value: (REA 98-1906)

a. Obtain PVS flow from NRERDS, RMDA, PVS flow recorder in the CR or use one of the below default values

b. One Auxiliary Building Fan.. .94,000 scfm

c. Two Auxiliary Building Fans... 136,000 scfm

d. Zero Auxiliary Building Exhaust Fans, one train PRF... 5,000 scfm

e. Zero Auxiliary Building exhaust fans, two trains PRF... 10,000 scfm Version 10

09/23/02 14:04:07 . - --

• FNP-0-EIP-9.1 8.2 Select fuel status per the following criteria:

"8.2.1 Failed fuel should be selected if Dose Equivalent Iodine is in excess of 300 ptcuries per gram as determined by performance of an RCS sample or by comparison of R27A or B monitor readings with Figure 8 of FNP-0-EIP-9.0 or Figure 18 of FNP-0-EIP-30.

8.2.2 Melted fuel should be selected if an FNP-0-EIP-30.0 calculation has determined that there is melted fuel.

8.2.3 IF melted or failed fuel is indicated THEN select INVENTORY, the unit with the fuel problem and then select failed or melted fuel as appropriate.

NORMAL is the default value.

9.0 If ARDA has NOT Automatically Started and it is Desired to Perform an EDCM Offsite Dose Calculation, Then Perform the Following Steps:

9.1 Select UNIT, then in the drop down window select the appropriate Unit or simulator.

9.2 Override any failed parameters for the selected Unit per step 8.1.

9.3 Select fuel status for the selected Unit as appropriate per step 8.2.

9.4 Select RELEASE POINT. Next select the appropriate Unit and then select the appropriate release point.

9.5 IF a steam generator was selected as a release point THEN specify the number of reliefs and/or PORVs that are open.

9.6 Select START DOSE ASSESSMENT.

9.7 Start automatic printout by selecting PRINT then selecting Start Automatic Print.

9.8 If the Radiation Monitor that is being used for dose assessment has been overridden, then select PRINT and Demand Print and go to step 9.10.

9.9 If the Radiation Monitor that is being used for dose assessment has not been overridden, wait until the ARDA screen has updated to the 15 minute time block that ARDA was started in, then obtain a printout from ARDA.

9.10 Obtain a copy of the ARDA printout with offsite dose values and go to FNP-0 EIP-9.0 (Emergency Classification and Actions) step 4.2.8 to evaluate the emergency classification.

Version 10

09/23/02 14:04:07 ' - V , f2" FNP-0-EIP-9.1 TABLE 1 References

1. FNP-0-EIP-9.0 Emergency Classification and Actions

2. FNP-0-EIP-20.0, Chemistry and Environmental Support to the Emergency Plan

3. FNP-0-EIP-30 Post Accident Core Damage Assessment

4. FNP 1/2 -CCP-213.1 Gaseous Effluent Radiation Monitoring System Set points

5. FNP-0-CCP-1300 Chemistry and Environmental Activities During A Radiological Accident

6. FNP-1/2-RCP-252 Radiation Monitoring System Set points

7. FNP-0-M-007, Emergency Dose Calculation Method

8. Joseph M. Farley Nuclear Plant Emergency Plan I oflI Version 10

09/23/02 14:04:07 FNP-0-EIP-9.1 PY FIGURE 1 Unit X Group X NON REGULATORY ERDS Date Time Unit Group Display Print Start Dose Assessment elease oint Met Informati n Radiation onitors Plant Parameters Previous History Inventory Unit 1 Group I Demand Print This menu item will toggle between Unit 2 Group 2 Start Automatic Print Start and Stop Dose Assessment Simulation Group or Scroll Stop Automatic Print r i,S l I oflI Version 10

. 1 FNP-0-EIP-9.

09/23/02 14:04:07 .k FIGURE 2 Unit X Group X NON REGULATORY ERDS Date Time Unit Group Display Print Start(Stop) Dose Assessment Release Point Met Information Radiation Monitors Plant Parameters Previous History Inventory I i maw I 15 Minute previous ide30 Mnute PreviousI Unit 1 I Unit 1 ~l Manual Overr H)d -!5 Minute Previous.[ Unit 2 !oF Unit 2 Wind Speed (MI Simulation]

Simulationo Wind Direction(

Delta T a-Simlaio77 2 Uimltion T

,VALUEIliulto Normal Fuel Plant Vent Stack Steam Jet Air Ejector TDAFW Exhaust I

I MANUAL WIND nrrv7 OWm Failed Fuel Melted Fuel Steam Generator A Manual Override VI I Safety -

Manual Override Steam Generator B 2 Safeties SPING Iodine 3 Safeties SPING Noble Gas SG A Pressure Steam Generator C 4 Safeties SG A Pressure SPING Particulate SJAE Exhaust SG A Pressure Plant Vent Stack Flow MANUAL VALUE WINDOW SG A Atmospheric Relief SG B Atmospheric Relief Reactor Trip Time Enter Manual Value For xxxxx Ene NI SG C Atmosphenc Relief MANUAL VALUE TDAFW Exhaust WINDOW MANUAL VALUE WINDOW m

l Version 10 of 1 1 oflI Version 10

09/23/02 l4:04:07 C

FNP-0-EIP-9. 1 r -t a FIGURE 3 ERDS GROUP 1 TAG# DESCRIPTION VALUE UNITS RC3702 HIGHEST R27 HI LEVEL CTMT RADIATION xxxX R/HR RE0050 GROSS FAILED FUEL DETECTOR XXXX CPM WS35FT WIND SPEED 35' ELEV XXXX MPH WS150FT WIND SPEED 150' ELEV XXxX MPH WD35FT WIND DIRECTION 35' ELEV XXXX DEGFR WD150FT WIND DIRECTION 150' ELEV XXxx DEGFR STCLASS STABILITY CLASS DELTA TEMP XXXX DEGF RE0014 VENT GAS MONITOR XXXX CPM RE0021 VENT AIR PARTICLE MONITOR XxXX CPM RE0022 VENT GAS MONITOR XXXX CPM RE0029B-12 VENT IODINE (131) GAS (SPING4) XXXX uCi/ML RE0029B-NG VENT NOBLE GAS (SPING4) xxxX uCi/ML RE0029B-P VENT PARTICULATE (SPING4) XXXX uCi/ML FT2879 PLANT VENT STACK FLOW XXXX CFM RE0015C SJAE EXHAUST HIGH RANGE MONITOR XXxX R/HR RE0060A SG A ATMOSPHERIC RELIEF MONITOR XXXX R/HR RE0060B SG B ATMOSPHERIC RELIEF MONITOR XXXX R/HR RE0060C SG C ATMOSPHERIC RELIEF MONITOR XXXx R/HR RE0060D AUX FEED TURBINE EXHAUST MONITOR XXXX R/HR RE0070A SG A N 16 LEAK DETECTION SYSTEM XXXX GPD RE0070B SG B N16 LEAK DETECTION SYSTEM XXXX GPD RE0070C SG C N16 LEAK DETECTION SYSTEM xxxX GPD I oflI Version 10

09/23/02 1'4:04:07 FNP-0-EIP-9. 1 FNP-0-EIP-'9.1 14:04:07 09/23/02 /

FIGURE 4 ERDS GROUP 2 TAG# DESCRIPTION VALUE UNITS Xxxx DEGF TE31871 CTMT DOME INSIDE AIR TEMP HIGHEST CTMT PRESSURE XXXX PSIG PC3700 ECCS NR CTMT SUMP LEVEL AVG XXXX FT LC1501 H2MANUAL CTMT HYDROGEN RCS PRESSURE AVG IMA xxXX PSIG PC1402A NC 1100A POWER RANGE FLUX AVG IMA XXXx FC0400A RCS LOOP A FLOW AVG IMA xxxX FC0420A RCS LOOP B FLOW AVG 1MA XXXX FC0440A RCS LOOP C FLOW AVG 1MA XXxx TMARCETA SUBCOOLING CHAN A XXXX DEGF SUBCOOLING CHAN B xxXX DEGF TMARCETB FIFTH HOTTEST CORE EXIT TC XxxX DEGF TC1200 LCI600A PRESSURIZER LEVEL AVG IMA xxxX LC1602 LOWEST UPPER HEAD LEVEL XXXX LC1603 LOWEST UPPER PLENUM LEVEL xxxX LT0477 SG A WIDE RANGE LEVEL XXXX LT0487 SG B WIDE RANGE LEVEL XXXX LT0497 SG C WIDE RANGE LEVEL xxxx RWST LEVEL CHAN 1 xxxX FT LT0501 FE0605A RHR LOOP A FLOW XXxX GPM FE0605B RHR LOOP B FLOW xxxX GPM FC4658 CHARGING LINE CORRECTED FLOW IMA XxxX GPM FE0943 HHSI FLOW XXXX GPM FT3229A AUXILIARY FEEDWATER FLOW TO SG A XXXX GPM FT3229B AUXILIARY FEEDWATER FLOW TO SG B XXXX GPM FT3229C AUXILIARY FEEDWATER FLOW TO SG C XXXX GPM I oflI Version 10

09/23/02 14:04:07 FNP-0-EIP-9.1 FIGURE 5 ERDS GROUP 3 TAG# DESCRIPTION VALUE UNITS REOO18 WASTE DISPOSAL LIQUID MONITOR XXXX CPM RE0023B SG BLOWDOWN TREATMENT MONITOR XXXX CPM TE3187H CTMT COOLER A AIR INLET TEMP XXXX DEGF TE3187G CTMT COOLER B AIR INLET TEMP XXXX DEGF TE3187F CTMT COOLER C AIR INLET TEMP XXXX DEGF TE3187E CTMT COOLER D AIR INLET TEMP XXXX DEGF NE0031 SOURCE RANGE FLUX CHAN A NE0032 SOURCE RANGE FLUX CHAN B NE0035 INTERMEDIATE RANGE FLUX CHAN A NE0036 INTERMEDIATE RANGE FLUX CHAN B TC0410A RCS LOOP A CL WIDE RNG TEMP 1MA XXXX DEGF TC0413A RCS LOOP A HL WIDE RNG TEMP IMA XXXX DEGF TC0420A RCS LOOP B CL WIDE RNG TEMP IMA XXXX DEGF TC0423A RCS LOOP B HL WIDE RNG TEMP IMA XXXX DEGF TC0430A RCS LOOP C CL WIDE RNG TEMP IMA XXXX DEGF TC0433A RCS LOOP C HL WIDE RNG TEMP IMA XXXX DEGF PC2300A SG A PRESSURE AVG 1MA XXXX PSIG PC2301A SG B PRESSURE AVG IMA XXXX PSIG PC2302A SG C PRESSURE AVG IMA XXXX PSIG FC4655 SG A FW CORRECTED FLOW IMA XXXX KBH FC4656 SG B FW CORRECTED FLOW IMA XXXX KBH FC4657 SG C FW CORRECTED FLOW IMA XXXX KBH I of I Version 10

v I .

0 09/23/02 14:04:07 " ' "" FNP-0-EIP-9.1 FIGURE 6 ARDA DISPLAY AUTOMATIC RAPID DOSE ASSESSMENT CURRENT FIFTEEN MINUTE ESTIMATE AS OF DATE TIME (all times central)

• • l1. TYPE OF RELEASE: [X] GROUND LEVEL

[C] AIRBORNE: Started: Stopped:

• • 12. RELEASE MAGNITUDE: [X] uCURIES PER SEC.

[E] NOBLE GAS XXXX [F] IODINES xxxx

[G] PARTICULATES XXXX

• • 13. ESTIMATE OF PROJECTED OFFSITE DOSE: [C] ESTIMATED DURATION: 4 HRS.

TEDE THYROID CDE (mrem) (mrem)

SITE BOUNDARY [D] XXXXXX [E] xxxxxx 2 MILES IF] xxxxxx [G] xxxxxx 5 MILES [H] XXXXXX [I] XXXXXX 10 MILES [J] xxxxxx [K] XXXXXx

• • METEROLOGICAL DATA: [A] WIND DIRECTION (from) XXX [B] SPEED (mph) XXX

[C] STABILITY CLASS X I oflI Version 10

09/23/02 ý,.04:07 (

FNP-0-EIP-9. 1 I.

FIGURE 7 ERDS MIDAS Data TAG# DESCRIPTION VALUE UNITS WS35FT WIND SPEED 35' ELEV XXXX MPH WS15OFT WIND SPEED 150' ELEV XXXX MPH WD35FT WIND DIRECTION 35' ELEV XXXX DEGFR WD15OFT WIND DIRECTION 150' ELEV XXXX DEGFR TE31895 CTMT INTAKE OUTSIDE AIR TEMPERATURE XXXX DEGFR STCLASS STABILITY CLASS DELTA TEMP XXXX DEGF RE0029B-NG VENT NOBLE GAS (SPING4) XXXX giCi/ML RE0029B-12 VENT IODINE(131) GAS (SPING4) XXXX JtCi/ML RE0029B-P VENT PARTICULATE (SPING4) XXxX g.Ci/ML RE0014 VENT GAS MONITOR xxXX CPM FT2879 PLANT VENT STACK FLOW xXXx CFM RE0060A SG A ATMOSPHERIC RELIEF MONITOR XXXX R/HR PC2300A SG A PRESSURE AVG IMA xxxX PSIG RE0060B SG B ATMOSPHERIC RELIEF MONITOR XXXX R/HR PC2301A SG B PRESSURE AVG 1MA XXXX PSIG RE0060C SG C ATMOSPHERIC RELIEF MONITOR XXXX R/HR PC2302A SG C PRESSURE AVG 1MA xxxX PSIG REOOI5C SJAE EXHAUST HIGH RANGE MONITOR XXXX R/HR RE0060D AUX FEED TURBINE EXHAUST MONITOR XXXx R/HR IOfl Version 10

A. .2 L 09/24/02 11:07:36 -

FNP-0-EIP-7.0 September 23, 2002 Version 13 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 7.0 FNP-0-EIP-7.0 S

A F

E T

Y SECURITY SUPPORT TO THE EMERGENCY PLAN R

E L

A T

E D

PROCEDURE USAGE REQUIREMENTS per FNP-0-AP-6 SECTIONS Continuous Use Reference Use Information Use ALL Approved:

Nuclear Plant General Manager 4--:" Date Issued 10-10 ic &-.

10- 1C)- () a--

UNCONTRPOLLED COPY CAUTION: This copy iq not maintained Current. Do not use in a kdaiety RelatedActivity

09/24/02 11:07:36 -- 'A.IHI_ FNP-0-EIP-7.0 LIST OF EFFECTIVE PAGES PROCEDURE CONTAINS NUMBER OF PAGES Body ................................................................................................................................................. 7 Table I ............................................................................................................................................. 1 Figure I ............................................................................................................................................ 1 Figure 2 ............................................................................................................................................ 1 Figure 3 ............................................................................................................................................ 1 Page 1 of 1

09/24/02 11:07:36 ,,FNP-0-EIP-7.0 TABLE OF CONTENTS Section Title Page 1.0 Purpose 1 2.0 References 1 3.0 General 1 4.0 Personnel Emergency 2 5.0 Notification of Unusual Event (NOUE) 2 6.0 Alert 3 7.0 Site Area Emergency 3 8.0 General Emergency 4 9.0 EOF Setup 6 10.0 EOF Access Control 6 11.0 At the Controls Area Accountability 7 12.0 Severe Natural Phenomenon 7 Table 1 References Figure 1 Controlled Area Log Figure 2 General Layout - Owner Controlled Area Figure 3 EOF Personnel Page 1 of 1 Version 13

09/24/02 11:07:3 6 ~J A L lFNP-O-EIP-7.0 SECURITY SUPPORT TO THE EMERGENCY PLAN 1.0 Purpose This procedure delineates the responsibilities of the Security group and the security actions to be taken in support of the Farley Nuclear Plant (FNP) Emergency Plan.

2.0 References See Table 1.

3.0 General 3.1 The primary objective of the security force during the various emergency conditions is to maintain plant security, to provide escort service for offsite emergency personnel and vehicles to facilitate their expeditious arrival at the emergency scene, to assist in evacuation of buildings, structures, or the plant site as necessary, to assist in establishing personnel accountability, call out the on-call ERO staff, and set up the Emergency Operations Facility (EOF) if required.

3.2 The safeguards effectiveness of FNP Security shall not be degraded during drills.

During non-emergency conditions (to include plant drills), all persons, vehicles, hand carried items, packages and materials shall be searched prior to entering a protected area (PA). During non-emergency conditions (to include plant drills),

all persons entering a protected area shall be badged in accordance with existing access control procedures.

During actual emergency conditions, identified emergency response individuals (to include bona fide federal, state, and local law enforcement agency personnel on official business) shall be exempted from the search and badging requirements that might impede their timely response to the emergency.

3.3 Radio use. During an emergency which requires that Radiation Monitoring Teams (RMTs) be dispatched into the environment, the Health Physics Manager will be allowed to use the two-way radio in the Central Alarm Station (CAS) to communicate with the RMTs to such extent that it does not interfere with the execution of the security alarm response function.

Version 13

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• -- INOTE: ACTIVTIES SPECIFIED BELOW ARE NOT REQUIRED TO BE PERFORMED IN THE ORDER SPECIFIED.

4.0 Personnel Emergency 4.1 Contact the Control Room to determine the nature of injuries, number of injured persons, access control requirements and whether or not radiation or contamination is a factor.

4.2 Plant Emergency Vehicle (PEV). If the nature of the emergency is such that the injured person(s) can be safely transported in the PEV, the control room will notify the Nuclear Security Captain or designee to have the PEV proceed to the scene of the accident. If the injured persons are located inside the protected area (PA) the motor patrol will be notified by the Nuclear Security Captain to proceed to the appropriate gate, ensuring that the gate is opened to expedite the entrance and exit of the PEV from the PA If the security staff cannot support driving of the PEV, the Security Captain should contact the OSS or the SS to inform them of the situation.

4.3 Local Ambulance Service. If the number of injured persons is such that outside assistance from local ambulance service is requested by the Emergency Director

"(ED),an SFM will be dispatched to the plant site access point to escort ambulance(s) to the location of injured persons.

4.4 Ambulance Kit. Security personnel will provide an ambulance kit, located in the HVAC room of the CSC, to ambulance personnel arriving on site, if contamination is involved.

4.5 Maintain security of PEV at the hospital. Prevent unauthorized personnel from approaching the PEV to preclude possible contamination by radioactive material.

5.0 Notification of Unusual Event (NOUE) 5.1 Security Group support during a NOUE shall be determined by the nature of the condition which precipitated the event.

5.2 Attempted sabotage. In the event a NOUE is caused by attempted sabotage of vital equipment or attempted unauthorized entry into a vital area (VA), initiate the appropriate Contingency Plan implementing procedures.

5.3 Other Conditions. In the event a NOUE is declared due to other cbnditions such as severe weather, flood conditions, or release of toxic or noxious gas, Security "supportshall normally consist of the following actions:

5.3.1 Establish access control measures to the affected area.

Version 13

09/24/02 11:07:36 . K. FNP-0-EIP-7.0

-~ -1 5.3.2 Provide escorts for offsite emergency support personnel and vehicles.

5.3.3 Assist in evacuation of personnel from the PA and the Controlled Area (CA) if directed by the ED.

5.3.4 Call out the on-call Emergency Response Organization per FNP-0-EIP-8.3 as directed by the Emergency Director.

6.0 Alert 6.1 During an ALERT, Security Group support shall be determined by the nature of the condition which precipitated the ALERT.

6.2 In the event an ALERT is caused by attempted sabotage of vital equipment or attempted unauthorized entry into a vital area (VA), initiate the appropriate Contingency Plan implementing procedures.

6.3 In the event an ALERT is declared due to other conditions such as severe weather, flood conditions or release of toxic or noxious gas, security support shall normally consist of the following actions:

6.3.1 Establish access control measures to the affected area.

6.3.2 Provide escorts for offsite emergency support personnel and vehicles.

6.3.3 Assist in evacuation of personnel from the PA and the CA, if directed by the ED.

6.3.4 Call out the on-call Emergency Response Organization per FNP-0-EIP-8.3 as directed by the Emergency Director.

6.4 When notified of an ALERT classification, the Security Group will dispatch one SFM to the EOF with the EOF keys that are located in the Central Security Control (CSC) and set up the EOF per FNP-0-EIP-27.0.

7.0 Site Area Emergency 7.1 Evacuate non-essential personnel from the plant site after survey by Health Physics and release by the ED.

7.2 In the event that the Plant Emergency Alarm is sounded or a General Evacuation is announced on the public address system, Security will activate motorized patrols with public address systems to tour the roads, and physically enter buildings (Support Building, Westinghouse Site Support Office, OPS Label Shop, Support Building Trailer, Warehouse Office Area, SNC Garage, Fabrication Shop Version 13

09/24/02 11:07:36 T ' V FNP-0-EIP-7.0 and Complex 3) (see Figure 2) within the owner-controlled area (OCA), to inform all personnel outside the areas covered by the fixed position public address system of the need to report to their designated assembly areas. They will provide or assure transportation as necessary.

7.3 Assist in establishing personnel accountability per FNP-0-EIP- 10.0.

7.4 Establish access control with approval by the ED to the plant site via the Highway 95 gate with the lowest radiation level (if significant). SFMs posted at access roads on Highway 95 will maintain a log of all persons entering or exiting the OCA. Such information shall be recorded on Controlled Area Logs (Figure 1). It is understood that initial evacuation of non-essential personnel may proceed prior to implementation of access control measures.

7.5 When notified of a SITE AREA EMERGENCY classification, the Security Group will dispatch one SFM to the EOF with the EOF keys that are located in the CSC and set up the EOF per FNP-0-EIP-27.0.

7.6 Provide escort service for offsite emergency personnel and vehicles.

NOTE: ONLY DOSIMETRY DEVICES OBTAINED FROM EOF, EMERGENCY PLANNING STORAGE SHOULD BE ISSUED TO EMERGENCY PERSONNEL. DOSIMETRY DEVICES USED FOR TRAINING PURPOSES SHOULD NOT BE ISSUED FOR USE.

7.7 Issue Dosimetry. In the event that contamination by radioactive material is a factor and an HP Tech is not present at the EOF, Security Group personnel shall, upon request of the Environmental Supervisor, issue appropriate dosimetry devices to arriving offsite emergency personnel and personnel in the EOF.

7.8 Issue Equipment. In the event that contamination by radioactive material is a factor and a HP Tech is not present, Security Group personnel shall issue appropriate equipment as directed by the HP Manager from the EOF to arriving offsite emergency personnel.

7.9 For severe natural phenomena or other hazards, perform the actions described in step 5.3.

7.10 Call out the on-call Emergency Response Organization per FNP-0-EIP-8.3 as directed by the Emergency Director.

8.0 General Emergaency 8.1 Evacuate nonessential personnel from the plant site after survey by Health Physics and release by the ED.

4- Version 13

09/24/02 11:07:36 Q" Li  ! FNP-0-EIP-7.0 8.2 Plant Emergency Alarm. In the event that the Plant Emergency Alarm is sounded, Security will activate motorized patrols with public address systems to tour the roads, and physically enter buildings (Support Building, Westinghouse Site Support Office, OPS Label Shop, Support Building Trailer, Warehouse Office Area, Fabrication Shop, SNC Garage and Complex 3) (see figure 2) within the owner-controlled area (OCA), to inform all personnel outside the areas covered by the fixed position public address system of the need to report to their designated assembly areas. They will provide or assure transportation as necessary.

8.3 Assist in establishing personnel accountability, per FNP-0-EIP- 10.0.

8.4 Establish access control, with approval by the ED, to the plant site via the Highway 95 gate with the lowest radiation level (if significant). SFMs posted at access roads on Highway 95 will maintain a log of all persons entering or exiting the OCA. Such information shall be recorded on Controlled Area Logs (Figure 1). It is understood that initial evacuation of non-essential personnel may proceed prior to implementation of access control measures.

8.5 Provide escort service for offsite emergency personnel and vehicles.

NOTE: ONLY DOSIMETRY DEVICES OBTAINED FROM EOF, EMERGENCY PLANNING STORAGE SHOULD BE ISSUED TO EMERGENCY PERSONNEL. DOSIMETRY DEVICES USED FOR TRAINING PURPOSES SHOULD NOT BE ISSUED FOR USE.

8.6 Issue Dosimetry. In the event that contamination by radioactive material is a factor and an HP Tech is not present at the EOF, Security Group personnel shall, upon request of the Environmental Supervisor, issue appropriate dosimetry devices to arriving offsite emergency personnel and EOF staff.

8.7 Issue Equipment. In the event that contamination by radioactive material is a factor and a HP Tech is not present, Security Group personnel shall issue appropriate equipment as directed by the HP Manager from the EOF to arriving offsite emergency personnel.

8.8 For severe natural phenomena or other hazards, perform the actions described in Step 5.3.

8.9 Recall off-duty Security personnel as necessary to maintain plant security.

8.10 PAX Operator. During a General Emergency, the PAX Operator function will normally be maintained by the Security Group at CSC. If the CSC must be evacuated, a member of the Security Group at the Emergency Operations Facility Room 106 will carry out this function.

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'-*. 7 FNP-0-EIP-7.0 8.11 When notified of a GENERAL EMERGENCY classification, the Security Group will dispatch one SFM to the EOF with the EOF keys that are located in the CSC and set up the EOF per FNP-0-EIP-27.0.

8.12 Call out the on-call Emergency Response Organization per FNP-0-EIP-8.3 as directed by the Emergency Director.

9.0 EOF Setup 9.1 At the Alert, Site Area Emergency, or General Emergency declaration, the EOF will normally be set up. One SFM will be dispatched to the EOF as soon as any one of the above emergency classifications is declared, to start EOF setup per FNP-0-EIP-27.0.

10.0 EOF Access Control 10.1 During EOF set-up, EOF staff will be arriving. The SFMs involved in the set-up should, as they see people arriving, ensure that the arrivals are company employees. This can be accomplished by observing badges or personnel recognition of the individuals. These company employees are not required to be logged in and out of the EOF. This function of access control should not interfere with the EOF set-up.

10.2 When access control is established in the EOF, company employees (as verified in the previous step) with valid business in the EOF are free to move in and out of the EOF as required to perform their job function. These company employees are not required to be logged in and out of the EOF on figure 1. EOF staff will be issued a name badge and sign in on figure 3 as soon as is practical.

10.3 Representatives of government agencies with valid identification will be logged in to the EOF on the Controlled Area Log, Figure 1, and be issued a name badge.

The Recovery Manager Assistant will be informed at the next opportunity of the arrival of these individuals.

10.4 Other individuals will require permission of the Recovery Manager or the RM Assistant prior to entering the EOF. After permission is obtained, these individuals will be logged in to the EOF on the Controlled Area Log, figure 1, and be issued a name badge.

10.5 Dosimetry is not required to be issued unless the radiological conditions warrant it. The Dose Assessment Director, the HP Manager, or the Technical Manager will make the decision as to when dosimetry is required. When the decision is made to wear dosimetry, the following guidelines should be used:

0 Personnel arriving at the EOF will be issued dosimetry upon their arrival Version 13

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For personnel already in the EOF, the Access Control SFM should deliver Dosimetry to all individuals 10.6 The Access Control SFM should normally remain in the vicinity of the Access Control table. He may, however, move about freely in Room 106, as necessary to perform duties. In the event that the SFM has to leave Room 106, the RM Assistant should be informed.

10.7 After EOF setup has been completed and at shift changes the SFM should complete Figure 3 and provide it to the Recovery Manager Assistant.

10.8 The Access Control SFM reports to the RM Assistant in the EOF for administrative control.

10.9 In the event that accountability is required after EOF setup has been started the SFM responsible for access control will determine if anyone is missing from the EOF staff that is already on site. FNP-0-EIP-10.0 and figures 1 and 3 may be used as an aid in performing this function. The accountability information should be provided to the RMA or the CSC directly if the RMA is not yet in the EOF.

11.0 At the Controls Area Accountabilit 11.1 In addition to the other accountability requirements of FNP-0-EIP- 10.0, the accountability for the TSC and the At-The-Controls Area of the Control Room will be performed by a Security Force Member, per FNP-0-EIP-10.0.

12.0 Severe Natural Phenomenon In the event of a severe natural phenomenon, such as a tornado, the following actions should be taken:

12.1 If time permits, security force members should contact the Nuclear Security Captain for appropriate sheltering actions regarding the safety of the security force member.

12.2 If time does not permit, the security force members should take appropriate shelter and immediately inform the Nuclear Security Captain of those actions.

12.3 The Nuclear Security Captain should immediately implement appropriate compensatory measures for the sheltering activities.

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~C\TABLE 1 REFERENCES Joseph M. Farley Nuclear Plant Emergency Plan Joseph M. Farley Nuclear Plant Security Plan FNP-0-EIP-9.0, Emergency Classification And Actions FNP-0-EIP-10.0, Evacuation and Personnel Accountability FNP-0-EIP-1 1.0, Handling Of Injured Personnel FNP-0-EIP- 13.0, Fire Emergencies FNP-0-EIP-27.0, EOF Setup and Activation Page 1 of 1 Version 13

09/24/02 11:07:36 FNP-0-EIP-7.0 A. FIGURE 1 JOSEPH M. FARLEY NUCLEAR PLANT SECURITY GROUP - NUCLEAR PAGE OF CONTROLLED AREA LOG flATP* NO DATE:

GROUP ASSIGNMENT OR COMPANY NAME REPRESENTED TIME IN TIME OUT SFM INITIALS Reviewed and Approved by:_

Nuclear Security Captain I Page 1 of 1 Version 13

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(-7t t 5 FIGURE 2 GENERAL LAYOUT OWNER CONTROLLED AREA Detail A Houston I County 42 Page 1 of 1 Version 13

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• • ...  : .,iL..*E KA 09/24/0 11:07:6 F FNP-0-EIP-7.0 EOF PERSONNEL Recovery Manager RM Assistant Dose Assessment Director Environmental Supervisor Comp. Ser. Support Reactor Engineer RMT Controller RMT Cont. Assistant RMT 2 HP Tech RMT 3 HP Tech QC Support Communicator Assistant Security Access Control Security EOF Setup Document Control Clerk Status Board Assistant Public Info. EOF Coord.

PIEOF Liaison PIEOF staff Houston Co Liaison at HC -- at EOF Early Co Liaison

[:] at EC [R] at EOF OTHER USE ADDITIONAL SHEETS AS NECESSARY FIGURE 3 Page 1 of 1 Version 13