Text

Forwards Rev 3 to Certificate of Compliance 9793,for Model M-140 Shipping Package
	ML17349A961
Person / Time
Site:	07109793
Issue date:	06/08/1993
From:	Chappell C; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Engel W; ENERGY, DEPT. OF
Shared Package
ML17349A962	List: ML17349A961; ML20045A497;
References
	NUDOCS 9306100390
	Download: ML17349A961 (58)
	v • d • e

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101 A ail 9

. 1992

1.0 Title

DUTIES OF EMERGENCY COORDINATOR 2.0 royal and List of Effective Pa es:

2.1 roval

Chang dated:~4 9 92 Reviewed by Plant Nuclear Saf and Approv by Plant General Manager

~4 9 92 ty Committee:

92-056 Period Review

~3 31 95 Implementation ga 4//13 92 2.2 List of Effective P

es:

e

~Pa e

Date 1

04/09/92 2

04/09/92 3

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~Pa e

Date 26 0

09/92 27 04/

92 28 04/09 29 04/09/9 30 04/09/92 31 04/09/92 32 04/09/92 33 04/09/9 34 04/09/9 35 04/09/

2 36 04/0 /92 37 04/

/92 38 04 09/92 39 0 /09/92 40 4/09/92 41 04/09/92 42 04/09/92 4

04/09/92 4

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~Pa e

51 5

54 55 56 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 Date 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92

/09/92 04 9/92 04/

/92 04/09 2

04/09/

04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92 04/09/92

~Pa e

Date 76 04/09/92 77 04/09/92 78 04/09/92 79 04/09/92 80 04/09/92 81 04/09/92 82 04/09/92 83 04/09/92 84 04/09/92 85 04/09/92 86 04/09/92 87 04/09/92 ~~

88 04/09/92 ~M 89 04/09/92 Q 90 04/09/92 91 04/09/92 92 04/09/92 93 04/09/92 4

04/09/92 RTSs 86-1584, 87-0332 7-1665, 87-2051, 88-0761, 89-0622, 89-1733, 8

Ss 90-0402,90-229, 90-2941; 90-2952, 91-0483, 91-1226, 91-2427, S 91-3106 SC 4660 9-1793, 89-3433 91-2117, 92-0109

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F

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101 A ril 9 1992

1.0 Title

DUTIES OF EMERGENCY COORDINATOR 2.0 A

royal and List of Effective Pa es:

2. I

~Arova 1:

Change dated:

4llg 92 Reviewed by Plant Nuclear Safety Committee:

92-056 and Approved by Plant General Manager 4//9 92 Period Review Oue:

~3 31 95 Implementation Gate:

~4 13 92 2.2 List of Effective Pa es:

0

~

C3

~O 4

~ 0

~ Qe

~

s VO&e L

4S3 ORB

~Pa e

Date, 1

04/09/92 2

04/09/92 3

04/09/92 4

04/09/92 5

04/09/92 6

04/09/92 7

04/09/92 8

04/09/92 9

04/09/92 10 04/09/92 11 04/09/92 12 04/09/92 13 04/09/92 14 04/09/92 15 04/09/92 16 04/09/92 17 04/09/92 18 04/09/92 19 04/09/92 20 04/09/92 21 04/09/92 22 04/09/92 23 04/09/92 24 04/09/92 25 04/09/92

~Pa e

Date 26 04/09/92 27 04/09/92 28 04/09/92 29 04/09/92 30 04/09/92 31 04/09/92 32 04/09/92 33 04/09/92 34 04/09/92 35 04/09/92 36 04/09/92 37 04/09/92 38 04/09/92 39 04/09/92 40 04/09/92 41 04/09/92 42 04/09/92 43 04/09/92 44 04/09/92 45 04/09/92 46 04/09/92 47 04/09/92 48 04/09/92 49 04/09/92 50 04/09/92

~Pa e

Date 51 04/09/92 52 04/09/92 53 04/09/92 54 04/09/92 55 04/09/92 56 04/09/92 57 04/09/92 58 04/09/92 59 04/09/92 60 04/09/92 61 04/09/92 62 04/09/92 63 04/09/92 64 04/09/92 65 04/09/92 66 04/09/92 67 04/09/92 68 04/09/92 69 04/09/92 70 04/09/92 71 04/09/92 72 04/09/92 73 04/09/92 74 04/09/92 75 04/09/92 Pa<ac Date 76 04/09/92 77 04/09/92 78 04/09/92 79 04/09/92 80 04/09/92 81 04/09/92 82 04/09/92 83 04/09/9 84 04/09/92 85 04/09/92 86 04/09/92 87 04/09/92 88 04/09/92 89 04/09/92 90 04/09/92 91 04/09/92 92 04/09/92 93 04/09/92 94 04/09/92 O

Ls o.'?

CQ

~ Qfts qp 0 P V

~ p

~ C Eu CJ W esp tf') L Q

Cl.

P,AB RTSs 86-15 TSs 90-04 S91-310 84, 87-0332,87-1665, 87-2051, 88-0761 02, 90-2294, 90-2941, 90-2952,91-048 6

OTSC 4660

, 89-0622, 89-1733, 89-1793, 89-3433 3, 91-1226, 91-2427, 91-2117, 92-0109

/1:4/ms/dt/bsm

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 2

DUTIES OF EMERGENCY COORDINATOR 4/9/92 0

~Sco e:

3.1

~Pop ose:

3. 1 J.

Thi s procedure provides the gui de 1 ines to be fol lowed by the Emergency Coordinator when an emergency occurs'hat requires initiation of the Emergency Plans.

3.2 Discussion

3.2.1 This procedure provides. guidance for actions that the Emergency Coordinator will take in a plant emergency.

3.2.2 For planned evolutions such as safeguards, this procedure does not apply.

However, if a deviation from the planned evolution (i.e.,

any unplanned evolution)

occurs, this procedure should be consulted.

3.2.3 3.2.4 The Nuclear Plant Supervisor becomes the Emergency Coordinator upon declaration of an emergency

and, as

such, directs the On Site Emergency Organization actions to bring the emergency under control.

A member of the plant management staff may later assume the role of;Emergency Coordinator when he/she reaches the Control Room or TSC and becomes familiar with the emergency.

The Nuclear Plant Supervisor will then concentrate on control of the units.

During an emergency of Alert or higher, the Emergency Coordinator should confer with the TSC Security Supervisor concerning the impact of the emergency on plant security.

During an emergency of Site Area Emergency or

higher, and dependent on the degree of airborne

release, the TSC Security Supervisor may recommend a

complete or partial suspension of safeguards which may include (but is not limited to) any of the following:

NOTE:

Vital area doors unlocked by the computer will relock automatically after they are closed.

1.

Unlocking vital area doors through the security computer.

2.

Suspension of designated security patrols or activities.

3.

Maintenance of protected area access control only (suspension of all field patrols).

4.

A partial evacuation of on-duty Security personnel.

5.

Closinq one or both Alarm/Communications Stations (CAS/SAS).

6.

Complete suspension of site security safeguards.

3.2.5 The titles Nuclear Energy Duty Officer, and Nuclear Division Duty Officer are used interchangeably.

/1:4/ms/dt/bsm

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 3 DUTIES OF EMERGENCY COORDINATOR 4/9/92 3.3

~Authorit:

c 3.3.1 Turkey Point Plant Radiological Emergency Plan 3.4 Definitions

. for Emergency Action Level Classification and Radiological Emergency Planning, the following definitions apply:

3.4.1 Hot Rin Down Tele hone (HRD) the dedicated link between tate Loca agencies an urkey Point.

3.4.2 Emer enc Notification S stem (ENS) the circuit tying the NRC and Turkey Point.

3.4.3 Local Government Radio (LGR) - the communications network used as a

ac up to t e D.

3.4.4 State of Florida Notification Messa e

Form the form used to

initiate, update, and terminate emergency notifications to State/Local agencies.

3.4;5 3.4.6

.National Warnin S stem,(NAWAS) -. the.communications network used as a backup when the HRD, and'commercial phones are not available.

Power Block - structures comprising all permanent

nuclear, power generation, and cooling structures,

systems, and components within the Protected Area; and permanent Safety Related or quality Related utilities (e.g.

air, water, and and electric) both inside and outside the Protected Area.

/1:4/ms/dt/bsm

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101$

PAGE 4

DUTIES OF EMERGENCY COORDINATOR 4/9/92 3.4.7 Securit Trainin Area Section of land that was originally used as a Boy Scout Camp in the Land Utilization Area.

3.a:8

~Emer enc Any off-normal event or condition which is classified into one of the four event categories in Table 1 of this procedure.

3.4.9 Onsite within the Protected Area.

3.4.10 Offsite Power - power supplied from the grid through the Startup or Auxiliary Transformers (backfeed),

or power supplied by the Auxiliary Transformer during normal operation.

3.4.11 Unrestricted Area - as defined in Technical Specifications.

3.4. 12 Onsite Power - Power supplied by any of the four emergency diesel generators.

3.4.13 Owner Controlled Area That portion of the FPL property surrounding and including the Turkey Point Plant which is subject to limited access and control as deemed appropriate by FPL.

3.4.14 Release During any declared emergency any effluent monitor increase of approximately 10 times/one decade above pre-transient

values, or Health 'Physics'detected airborne radioactivity levels in excess of 25 percent MPC outside of.plant buildings due to failure of equipment directly associated with the declared plant emergency.

3.4.15 S~i d

1 d

i hi I1 di f th ff d

unit.

3.4. 16 Emer enc Res onse Director ERD the directory containing names and phone numbers of Emergency

Response

Organization personnel.

/1:4/ms/dt/bsm

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 5

DUTIES OF EMERGENCY COORDINATOR 4/9/92 Precautions:

4.1 4.2 The Emergency Coordinator (EC) can delegate his responsibilities to his subordinates with the exception of classification, the decision to notify state and local authorities and the issuing of Protective Action Recommendations.

The actual notification can be done by the ECs designee.

Notification to offsite agencies and PARs become the responsibility of the Recovery Manager when the EOF is manned and operational.

The EC documents his decision to notify state and local authorities and his concurrence with PARs by initialing the State of Florida Notification Message Form.

During exercises, drills or tests, ALL MESSAGES shall begin and end with "THIS IS A DRILL".

4.3 4.4 4.5 In any case where a

GENERAL EMERGENCY has been

declared, the minimum protective action recommendation shall be:

"Shelter all people within a 2

mile radius from the plant and 5 miles in the downwind sectors" (except as delineated in Section 4.4).

If the GENERAL EMERGENCY has been declared due to loss of physical control of the plant to intruders, including the Control Room or any other area(s) vital to the operation of, the reactor system (as defined in the Security Plan),

the minimum Protective Action Recommendation (PAR) shall be:

"Evacuate all people within a 2 mile radius from the plant",

and determine 2-5 and 5-10 mile PARs on other existing General Emergency Conditions (there may be no 2-5 and 5-10 mile PARs based on conditions).

Plant conditions, plume dose projection calculations, (from EPIP-20126, Offsite Dose Cal cul ations),

and offsite moni toring resul ts should be evaluated when making Protective Action Recommendations.

If significant discrepancies exist between field monitoring results and plume dose projection calculations,,

an evaluation should be

made, and the most conservative approach used in the determination of Protective Action Recommendations.

4.6 Protective Action Recommendations for a

child (most conservative considerations) have been incorporated into Table 2,

"Protective Action Recommendations Based on Plant Conditions and Offsite Dose Estimates."

4.7 4.8 If a condition which meets the Unusual Event or Alert criteria of the Emergency Classification Tables is identified and subsequently rapidly

resolved, the emergency classification shall be declared and immediately terminated.

All required notifications shall be completed.

Activation of the Onsite Emergency

Response

Facilities is not required.

If a condition which meets the Site Area Emergency or General Emergency criteria of the Emergency Classification Tables is identified and subsequently rapidly resolved, the emergency shall be declared and all notifications completed.

De-escalation from the Site Area Emergency and General Emergency classifications may only be authorized by the Emergency Control Officer.

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EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 6 DUTIES OF EMERGENCY COORDINATOR 4/9/92 4.9 Protective Action Recommendations based upon offsite dose calculations shall be determined by comparing projected offsite doses to the action levels in Table 2.

If the period of exposure is expected to be less than two hours the doses should be projected for the expected duration of the exposure.

For longer duration exposures, the offsite doses should be projected for two hours and PARs should be based upon the two hour projections.

Protective Actions for the child are incorporated into PARs listed in this procedure.

4. 10 The Emergency Coordinator responsibilities shall reside with the E.C.

in the Control Room until they have been formally transferred to the E.C. in the TSC.

4. 11 Emergency notification to State/Local agencies is required within 15 minutes of declaring an emergency.

4. 12 Emergency notification to the NRC is required immediately following notification of State/Local

agencies, but not later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the

'declaration of an emergency.

4. 13 If, during the notification process, it becomes necessary to upgrade the emergency

. classification, stop the'. current notification

process, and proceed.to make notification of the new classification.

4. 14 PA messages to site personnel do not have to be made verbatim; they are "example" messages only.

4. 15 The Emergency Coordinator has the authority to waive individuals emergency response training requirements, as needed.

4.16 Procedural notification steps may be performed out of sequence in order to meet State of Florida and/or NRC notification time requirements.

4.17 Alternate commercial telephone numbers for State of Florida and NRC notification are listed in the Emergency

Response

Directory (ERD).

4. 18 Collection of Release Rate Data shall not delay State of Florida and NRC notifications.

If the data is not available, notification shall be made and followed up as soon as the information is available.

/1:4/ms/dt/bsm

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 7

DUTIES OF EMERGENCY COORDINATOR 4/9/92 4.19 The Emergency Coordinator shall consider plant and radiological conditions as they relate to the emergency prior to ordering an evacuation.

As conditions warrant, the Emergency Coordinator may delay, postpone or make spdcial requirements on the evacuation.

Some examples of special circumstances are as follows:

4. 19. 1 Radiological conditions (puff releases) when large doses may be received during an evacuation.

4. 19.2 Security events when unknown hazards or dangers are perceived.

4. 19.3 Plant conditions where additional personnel are necessary to put the plant in a

safer configuration (i.e;,

equipment hatch

open, primary system open for repair, etc.)

4.19.4 Onsite hazards such as toxic gas,

fires, or explosions where the movement of personnel would be placing them in additional risk.

4.19.5 Risks to plant personnel due to the inability to use the evacuation route (construction, traffic accidents, etc.).

4;"19.6 Other similar events.

The Emergency Coordinator should consider the event with regard to duration of

release, plant conditions, and meteorological information prior to determining if special instructions should be given (retention of additional essential repair personnel, an alternate evacuation

route, or in place onsite sheltering).

4.20 Important plant page announcements (such as changes in classification or plant status) should be made firmly, clearly, and distinctly so that the message can be heard throughout the plant.

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0 0

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 8 DUTIES OF EMERGENCY COORDINATOR 4/9/92 0

Res onsibi lities:

5. 1 The. Nuclear Plant Supervisor (NPS) assumes the responsibilities of the Emergency Coordinator in the initial phases of a plant emergency.

If the Nuclear Plant

- Supervisor (NPS) is incapacitated, the Emergency

. Coordinator shall be (in order of succession):

5.1. 1 Assistant Nuclear Plant Supervisor 5.1.2 Nuclear Watch Engineer

5. 1.3 Any other member of the plant staff with an active Senior Reactor Operator license.

5.1.4 One of the Reactor Control Operators on shift.

5.2 A

member of the Plant Management staff may later assume Emergency Coordinator (EC) duties when he/she reaches the Control Room or TSC and becomes familiar with the emergency.

The NPS will at that. time return to the normal responsibility of control of the units.

Turnover between ECs should be performed in the Control Room if possible, with the new EC taking the Emergency Log Book to 'continue records of the event.

5.3 The Emergency Coordinator shall only grant permission for watch relief, including his

own, when a

proper turnover has been given and in his judgment, it is safe to do so.

5.4 The Emergency Coordinator shall authorize any radiation exposures in excess of regulatory limits.

This authorization should be in accordance with EPIP-20111, Reentry.

Authorization should be given only after consultation with the TSC Health Physics Supervisor and the Recovery Manager, if time permits.

Previous written authorization is not required for rescue of personnel.

5.5 The Emergency Coordinator shall authorize personnel exposures in excess of regulatory limits only for volunteers who are familiar with the risks involved and the tasks to be performed.

Women capable of reproduction shall not take part in these actions.

/1:4/ms/dt/bsm

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 9 DUTIES OF EMERGENCY COORDINATOR 4/9/92 6.0

References:

6. 1 Turkey Point Plant Radiological Emergency Plan 6.2 EPIP-20126, Offsite Dose Calculations 6.3 EPIP.-20106, Natural Emergencies 6.4 EPIP-20107, Fire/Explosion Emergencies 6.5 EPIP-20104, Duty Call Notification/Staff Augmentation 6.6 EPIP-20110, Criteria for and Conduct of Owner Controlled Area Evacuation e

6.7 EPIP-20111, Reentry 6.8 AP-0103.12, Notification to NRC of Significant Events 6.9 AP-0103.43, Duty Call Responsibilities

6. 10 Emergency

Response

Directory.

1.

Dade Co. Fire Department 2.

Homestead Air Force Base 8.1.9 Inform Security of the pending arrival of offsite assistance if requested.

8.1.10 Ci if fi f P1 1

d 1.

d P f 1 ti 8.2 if injuries occur or have occurred.

8.2 Medical Emergency?

Yes No CAUTION:

Due to minimal Contract Medical

Response

Staff of one (1) individual on back shifts and

weekends, manpower requirements should be monitored by the Control Room.

8.2.1 If NO, proceed to Step 8.3.

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0 0

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 12 DUTIES OF EMERGENCY COORDINATOR 4/9/92 8.2.2 Medical Emergency reported Name of victim Employer Location of victim Nature/extent of injuries Fractures?

Burns?

Hemorrhages?

i tI 8.2.3 Activate First Aid Team by contacting Chemistry personnel and Contract Medical

Response

Personnel.

Provide Operations Department assistance as needed.

1.

Cross connect page and make the following announcement twice:

"Attention all personnel.

There is emergency in Unit (3

or 4)

All personnel in stand clear.

All First Aid Team (location) a reported medical (location) the immediate area members report to 8.2.4 Notify Health Physics if injury is inside the RCA.

1.

If the injured is also contaminated or potentially contaminated, ensure EPIP 20131, Transfer of Contaminated Injured Personnel Offsite is performed.

8.2.5 Request off-site Medical Assistance if needed.

See phone numbers listed in the Emergency

Response

Directory.

(1)

Dade Co. Fire/Rescue (2)

Randle Eastern Ambulance (3)

Homestead Air Force Base (4)

U.S. Coast Guard 8.2.6 Inform Security of the pending arrival of off-site assistance.

8.2.7 Transport victim to hospital if necessary.

/1:4/ms/dt/bsm

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 13 DUTIES OF EMERGENCY COORDINATOR 4/9/92 Time 8.2.8 If POTENTIALLY CONTAMINATED, notify receiving hospital.

See phone numbers listed in the Emergency

Response

Directory.

(1)

Notify Baptist Hospital or (2)

Notify Mercy Hospital or CAUTION:

REAC/TS shoul d only be uti 1 ized if Bapti st Hospital and/or Mercy Hospital requires additional assistance or cannot support the treatment of the patient.

The patient should be stabilized by Baptist or Mercy and arrangements should be made with REAC/TS prior to transport.

(3)

Notify REAC/TS, Oak Ridge, TN for additional assistance, if necessary, or

.if Baptist Hospital and/or Mercy Hospital. cannot.support injury.

8.2.9 Rl if i

i hospital notified in 8.2.7 and report:

Contamination Levels and Body areas affected Radioisotopes involved Type of transport vehicle Departure time from plant 8.2.10 IF NOT CONTAMINATED:

Notify receiving hospital.

See phone numbers listed in the Emergency

Response

Directory.

(1) James Archer Smith Hospital (2) Deering Hospital (3) Jackson Memorial Hospital and report:

Injury information in Step 8.2.2 and:

Type of transport vehicle Departure time from plant 8.2.11 If contaminated and transported

offsite, classify Medical Emergency per Table 1.

8.2.12 Obtain status of victim after transport, as required.

/1:4/ms/dt/bsm

EMERGENCY PLAN IMPLEMENTING PROCEDURE 20101, PAGE 14 DUTIES OF EMERGENCY COORDINATOR 4/9/92 Time 8.3 Mitigating Actions and Classification of Off-Normal Event

" 8.3. 1 Direct initial investigative and mitigating actions to correct Off-Normal event.

8.3.2 Direct Chemistry Personnel to implement EPIP-20126, Offsite

'Dose Calculations if a

Release (see definitions) is in progress.

NOTE:

If conditions meeting the Emergency Classification criteria are known to have existed but have been terminated, proceed with required classification and notification activities.

An Unusual Event or Alert may be terminated by the Emergency Coordinator.

A Site Area Emergency or General Emergency may only be de-escalated by the Emergency Control Officer.

Activation of the Onsite Emergency

Response

Facilities is not required for events that have been terminated by the responsible official.

NOTE:

' f the event.

does not quali fy as an Emergency per Table 1, proceed to AP-0103.12 "Notification to NRC of Significant Events" Appendix A

and Appendix C for further classification of event.

8.3.3 Classify Off-Normal event using present available information.

Declare most conservative emergency class using Table 1

and proceed to step number and page listed on bottom of Table 1.

/1:4/ms/dt/bsm

LE 1

EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 15 4/9/92 Primary Depressurization

- ECCS Initiated Manually or Automatically UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL,EMERGENCY Safety Injection initiated AND High-head Si pump flowto the core Fl-943 Possible Control Room Indicators

-ACTION Complete actions listed in Step 8.4, Page 37.

Complete actions listed in Step 8.5, Page 50.

Complete actions listed in Step 8.6, Page 64.

Complete actions listed in Step 8.7, Page 79.

/20101/Pt2/sr/dt/bsm

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0

2.

Primary Leakage/LOCA LE 1

EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 16 4/9/92 UNUSUALEVENT Plant in Mode 1-2-3-4 AND A.

RCS Leakage in excess of Technical Specifications 3.4.6.2, Reactor Coolant System Operational Leakage as indicated by either:

1)

Unidentified RCS Leakage

>1 gpm, OR 2)

Identified RCS Leakage greater than ten (10) gpm, of 3) 4)

RCS Pressure Isolation Valve Leakage greater than allowable, or I

Any Pressure Boundary Leakage B.

Failure of any primary system safety or relief valve to close resulting in an uncontrolled RCS depressurization.

ALERT Plant in Mode 1-2-3-4 AND RCS leakage >50 gpm AND RCS leakage withinavailable charging pump capacity CAUTION: This section should not be used for events involving a steam generator tube leak/rupture or faulted/ruptured steam generator SITE AREA EMERGENCY Plant in Mode 1-2-3-4 AND R<5 feakage > 50gpm AND R 50gpm AND RCS leakage greater than available charging pump capacity AND Containment pressure > 20 psig CAUTION: This section should not be used for events involving a steam generator tube leak/rupture or faulted/

~~ruptured steam generator B.~~

~~Plant in Mode 1, 2, 3, 4, AND RCS leakage > 50 gpm AND RCS leakage greater than available charging pump capacity AND Loss of containment integrity which provides a flowpath to the environment.~~

~~CAUTION: This section should not be used for events involving a steam generator tube leak/rupture or faulted/~~

~~ruptured steam generator CAUTION: Consult Table 2, page 33 for required protective action recommendations.~~

~~ossI e~~

ontro oom n lcators TI-465, 467, 469 TEC Flow Indicators Charging/Letdown Flow Mismatch RCS pressure Containment Pressure ARM' Charging/Letdown Flow Mismatch RCS pressure Containment Pressure PRMS R-14 Complete actions listed in Step 8.4, Page 37.

~~Complete actions listed in Step 8.5, Page 50.~~

~~Complete actions listed in Step 8.6, Page 64.~~

~~Complete actions listed in Step 8.7, Page 79.~~

~~/20101/Pt2/sr/dt/bsm~~
I
LE 1
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 17 4/9/92 3.
Steam Generator Tube Leak/Rupture UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY Either Aor B:
A.
Greater than 500 gpd steam generator tube leakage to any one steam generator per Technical Specification 3.4.6.2, Reactor Coolant System Greater than 1 gpm total steam generator tube leakage per Technical Specification 3.4.6.2, Reactor Coolant System Either Aor B A.
Confirmed steam generator tube leakage )50 gpm AND Steam generator tube leakage withinavailable charging pump capacity AND Loss of offsite power B.
Steam generator tube leakage greater than available charging pump capacity.
Steam generator tube leakage greater than available charging pump capacity AND Loss of offsite power CAUTION: Consult Table 2, page 33 for possible protective action recommendations Possible Control Room Indicators PRMS R-15 PRMS R-19 PRMS R-15 PRMS R-19 Charging/Letdown Flow Mismatch PRMS R-15 PRMS R-19 Charging/Letdown Flow Mismatch Complete actions listed in Step 8.4, Page 37.
ACT Complete actions listed in Step 8.5, Page 50.
ION Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt2/sr/dt/bsm~~
' l
LE 1
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 18 4/9/92 4.
Loss of Secondary Coolant UNUSUALEVENT EitherAor B:
A.
Steamline or feedline break which results in Safety Injection actuation.
B.
Failure of a steam generator safety or steam dump to atmosphere valve to close resulting in uncontrolled secondary depressurization.
ALERT Steamline or feedline break which results in Safety Injection actuation AND Evidence ofsignificant (>10 gpm) steam generator tube leakage in the affected steam generator.
SITE AREA EMERGENCY Steamline or feedline break which results in Safety Injection actuation AND Confirmed RCS DEQ I-131 activity
~ 300 pCi/gm AND Confirmed steam generator tube leakage >50 gpm in the affected steam generator CAUTION: Consult Table 2, page 33 for possible protective action recommendations GENERAL EMERGENCY Possible Control Room Indicators PRMS R-15 PRMS R-19 Charging/Letdown Flow Mismatch PRMS R-15 PRMS R-19 Charging/Letdown Flow Mismatch ACTION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/P t2/sr/dvbsm~~
+LE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Pa~e 19 4/9/92 5.
Abnormal RCS Temperature and/or Pressure UNUSUALEVENT Plant in Mode 1 3-4:
AND Either A, B, or C A.
RCS saturated or superheated ALERT SITE AREA EMERGENCY GENERAL EMERGENCY B.
RCS pressure )2510 psig C.
RCS pressure and /or temperature above Technical Specification 3.4.9, Pressure/
Temperature Limits Possible Control Room Indicators Subcooling Margin Monitor ACTION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt2/sr/dt/bsm~~
ILE 1
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 20 4/9/92 6.
Fuel Handling Accident UNUSUAl.EVENT ALERT Aspent fuel element has been dropped or damaged AND Release of radioactiwty from the damaged spent fuel element has been detected.
SITE AREA EMERGENCY Either A, B or C:
A.
Major damage to one or more spent fuel elements has occurred AND Affected area radiation monitors are >103 mR/hr.
GENERAL EMERGENCY B.
Major damage to one or more spent fuel elements has occurred AND Containment radiation levels
)1.3 E4 Rem/hr Major damage to one or more spent fuel elements due to water level being below top of spent fuel.
Possible Control Room Indicators ARMS R-2, 5,7,8,19,21,22 PRMS R-12, 14 ACT ARMS R-2,5,7,8, 19,21,22 PRMS R-12, 14 SFP Level Indication Rl-6311A RI-63118 ION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt2/sr/dt/bsm~~
)1I
LE 1
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 P'age 21 4/9/92 7.
Loss of Safe Shutdown Functions/ATWS UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Either A, B, Cor D:
Either A, 8, CorD:
Either Aor B:
A.
Reactor critical AND Failure oftFeeeactor Protection System to initiate a tripsignal when a trip setpoint has been exceeded.
B.
Reactor critical AND Reactor faiTsSo trip on automatic signal C.
Reactor critical AND Reactor faifsSo trip on manual signal D.
RCS temperature increasing due to loss of decay heat removal capability from all ofthe following:
~~1).~~
RHR system AND 2)
ForceKK5 circulation AND 3)
Natur'aaaS circulation C.
Inabilityto bring the reactor subcritical with control rods Plant in Mode 1-2-3 AND Loss of steam release capability from all ofthe following:
1) 2)
3)
Condenser steam dumps AND AtmosSpseeric steam dumps AND Allsteam generator safeties Plant in Mode 1-2-3 AND Loss of seconclary heat sink has occurred AND RCS bleed andTeed is required.
Plant in Mode 1-2-3 AND RCS injection capability has been lost from:
1)
Charging pumps AND 2)
High-~ea Sl pumps A.
Inabilityto bring the reactor subcritical AND RCS pressure ) 2485 psig.
B.
Inabilityto bring the reactor subcritical AND Containment pressure ) 4 psig.
CAUTION: Consult Table 2, page 33 for required protective action recommendations.
Possible Control Room Indicators ACTION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8 7 Page 79.
~~/20101/Pt2/sr/dt/bsm~~
LE 1
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 22 4/9/92 8.
Fuel Element Failure UNUSUALEVENT RCS activity is greater than Technical Specification 3.4.8, Figure 3.4-1, limit for maximum RCS activity.
Either A, B or C:
ALERT A.
Confirmed RCS DEQ I-131 activity ~ 300 pCi/gm.
C.
Total fuel failure of 5%.
B.
An increase of > 1% fuel failure in 30 minutes.
SITE AREA EMERGENCY Fuel element failure as indicated by A, B,orC:
A.
Confirmed RCS DEQ l-131 activity ~ 300 pCi/gm.
AND RCS That >620 F.
B.
Confirmed RCS DEQ I-131 activity ~ 300 pCi/gm.
AND Core exit thermocouples
>700'F.
C.
Containment high range radiation monitor reading
>1.3 E4 Rem/hr.
a) b)
c)
LOCAwith loss of containment cooling OR LOCAwith loss of containment integrity which provides a flowpath to the environment OR Steam generator tube rupture with unisolable flowpath from the ruptured steam generator to the environment.
CAUTION: Consult Table 2, page 33 for required protective action recommendations.
GENERALEMERGENCY Fuel element failure as defined in Site Area Emergency of this section AND Any of the followingis imminent or in progress:
Possible Control Room Indicators PRMS R-20 ARMS R-1 through R-6 ACT Core ExitThermocouples Rl-6311A RI-63118 ION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt2/sr/dt/bsm~~
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t (
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EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 23 4/9/92 9.
Uncontrolled Effluent Release UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERALEMERGENCY A release to the Unrestricted Area has occurred or is in progress which exceeds either Aor B:
A.
Technical Specification 3.11 limitsfor gaseous release per 3/4-ONOP-067, Inadvertent Release of Radioactive Gas.
NOTE: Direct Chemistry to perform offsite dose estimates per EPIP-20126, Offsite Dose Calculations.
B.
Technical Specification 3.11 limitsfor liquid release.
1 7
NOTE: Direct Chemistry to perform release calculation in accordance with Offsite Dose Calculation Manual.
A release to the Unrestricted Area has occurred or is in progress which exceeds either Aor B:
Ten times Technical Specification 3.11 limitsfor gaseous release per 3/4-ONOP-067, Inadvertent Release of Radioactive Gas.
NOTE: Direct Chemistry to perform offsite dose estimates per EPIP-20126, Offsite Dose Calculations.
B.
Ten times Technical Specification 3.11 limitsfor liquid release.
NOTE: Direct Chemistry to perform release calculation in accordance with Offsite Dose Calculation Manual.
Performance of EPIP-20126, Offsite Dose Calculation or offsite surveys indicate site boundary exposure levels have been exceeded as indicated by eitherA,B,C,orD:
A.
~ 50 mRem/hr whole body for 1/2 hour B.
~ 250 mRem/hr thyroid for 1/2 hour C.
~ 500 mRem/hr whole body for 2 minutes D.
~ 2500 mRem/hr thyroid for 2 minutes Performance of EPIP-20126, Offsite Dose Calculation or offsite surveys indicate site boundary exposure levels have been exceeded as indicated by either A, B, Cor D:
A.
~
1 Rem/hr whole body B.
~
1 Rem integrated whole body close C.
~ 5 Rem/hr thyroid D.
~ 5 Rem integrated thyroid dose NOTE: Site boundary equals 1 mile radius from affected unit.
CAUTION: ConsultTable2,page33 for possible protective action recommendations.
Possible Control Room Indicators NOTE: Site boundary equals 1 mile radius from affected unit.
CAUTION: Consult Table 2, page 33 for required protective action recommendations.
A C'I'10 N Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt2/sr/dt/bsm~~
~~L'E 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 24 4/9/92~~
~~10. High Radiation Levels In Plant UNUSUALEVENT Either A, B or C:~~
ALERT SITE AREA EMERGENCY Containment High Range Radiation Monitor reading ) 1.3 E4 Rem/hr.
GENERAL EMERGENCY Containment High Range Radiation Monitor reading ) 1.3 E5 Rem/hr.
A.
Anyvalid area monitor alarm from an undeterminable source with meter greater than 103 mR/hr.
Unexpected plant iodine or particulate airborne concentration ) 1000 MPC as per 10 CFR 20 Appendix B, Table 1.
NOTE: Direct Chemistry to perform offsite dose estimates per EPIP-20126, Off-Site Dose Calculations.
(See Section 9, Uncontrolled Effluent Release)
CAUTION: Consult Table 2, page 33 for possible protective action recommendations.
NOTE: Direct Chemistry to perform offsite dose estimates per EPIP-20126, Off-Site Dose Calculations.
(See Section 9, Uncontrolled Effluent Release)
CAUTION: Consult Table 2, page 33 for required protective action recommendations.
C.
Unexpected direct radiation dose rate reading or unexpected airborne radioactivity concentration from an undetermined source in excess of 1000 times normal levels.
Possible Control Room Indicators Area Radiation Monitors Rl-631 1A RI-6311B RI-631 1A RI-6311 B Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
ACTION Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt2/sr/dt/bsm~~
SLE 1
EMERGENCY CLASSIFICATIONTABLE E PIP 20101 Page 25 4/9/92
~~11. Other Plant Conditions That Could Lead To Substantial Core Damage UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Either Aorb:~~
A Potential core damage indicated by all of the following:
1)
Known LOCAgreater than available charging pump capacity AND 2)
Failure of ECCS to deliver flowto the core AND 3)
Containment High Range Radiation Monitor readqing
) 1.3 E4 Rem/hr.
B.
Potential core damage indicated by all of the following:
1)
Loss of secondary heat sink AND 2)
RCS b~ee and feed required AND 3)
No hig~ead Sl flow available AND 4)
No Reflow forgreater than 30 minutes AND 5)
No AFVTflowfor greater than 30 minutes CAUTION: Consult Table 2, page 33 for required protective action recommendations.
Possible Control Room Indicators Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt2/sr/dt/bsm~~
LE 1
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 26 4/9/92
~~12. Loss Of Power Conditions UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL,EMERGENCY Either Aor B:~~
A.
Loss of offsite power to the:
1)
A4KVbus AND 2)
B 4KVlius EitherAor B:
A.
Loss of all vital onsite DC power.
B.
Loss of offsite power AND A.
Loss of all A/C power for
> 15 minutes.
a)
Loss of all A/C power AND b)
Loss of all ~ee water capability.
Either A, B or Cwith fuel in the Reactor The followi g situation exists for Vessel
>1 hr with fuel in the Reactor Vessel Loss of onsite power capability as indicated by:
1)
Loss of capability to power at least one vital 4KVbus from~an ofthefour'vaila e emergency diesel generator.
Both associated emergency diesel generators failto energize their associated 4KV buses.
NOTE: Refer to Section 7, Loss of Safe Shutdown Function B.
Loss ofall vital onsite DC power for >15 minutes.
C.
Emergency Coordinator leaves Control Room withinthe first 15 minutes of a loss of all A/C power.
CAUTION: ConsultTable2,page33 for required protective action recommendations.
Possible Control Room Indicators 4Kv Bus Voltage 4Kv Bus Amps Complete actions listed in Step 8.4, Page 37.
ACT Complete actions listed in Step 8.5, Page 50.
ION Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt 3/sr/dt/bsm~~
I 0
k
LE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 27 4/9/92
~~13. Contaminated Personnel UNUSUALEVENT Transportation of confirmed externally contaminated injured individual(s) from the site to a medical facility.~~
ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Possible Control Room Indicators Complete actions listed in Step 8.4, Page 37.
ACT Complete actions listed in Step 8.5, Page 50.
ION Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt 3/sr/dt/bsm~~
1 n
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 28 4/9/92 14.
Loss OfAssessment Functions UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Either A, B, or C:
A.
Loss of primary communications with offsite locations AND Loss ofall backup communications with offsite locations Plant in Mode1-2-3-4:
AND Most or all Contro~Room annunciator alarms lost for > 5 minutes Aplant transient is in progress AND AllControl Room annunciator alarms lost for > 15 minutes Loss of primary onsite meteorological instrumentation AND Loss of all backup onsite meteorological instrumentation AND Loss of all communication with Homestead AirForce Base C.
Loss of effluent or radiological monitoring capability requiring plant shutdown.
Possible Control Room Indicators ACTION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt 3/sr/dt/bsm~~
~~LE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 29 4/9/92~~
~~15. Natural Phenomena UNUSUALEVENT Plant in Mode 1-2-3-4 AND either A, B, C or D:~~
C.
D.
Confirmed hurricane warning OR Confirmed tornado in owner controlled area OR Anyearthquake detected onsite OR Hurricane/flood surge that prevents land access to the site C.
D.
Confirmed hurricane warning with maximum wind speeds in excess of 200 mph OR Tornado striVing any power block structure OR Earthquake tTtat could cause or has caused trip ofthe turbine generator or reactor OR Hurricane/flood surge that raises water level >18 feet above MLW ALERT Plant in any mode including defueled AND either A, B, C or D:
SITE AREA EMERGENCY Plant in Mode 1-2-3-4 AND either A, B or C:
Confirmed hurricane warning with maximum wind speeds in excess of 225 mph.
OR Earthquake I1as caused loss of any safety system function OR Hurricane/flood surge that raises water level > 18 feet above MLWand results in shutdown of turbine generator or reactor.
GENERAL,EMERGENCY A major natural event(e.g., high winds, earthquake, flooding) has occurred, which could cause massive damage to plant systems resulting in any of the other General Emergency initiating conditions.
CAUTION: ConsultTable2 page33 for required protective action recommendations.
Possible Control Room Indicators ACTION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page SO.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt 3/sr/dt/bsm~~
"~
'LE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 30 4/9/92
~~16. Hazards To Station Personnel And Equipment UNUSUALEVENT Safety of nuclear plant or personnel threatened by either A, B, C, D, or E:~~
A.
Aircraftcrash onsite B.
Unusual aircraft activity over facility C.
Toxic or flammable gas release ALERT Either A, B or C:
A.
Areduction in the level ofsafety of plant structures or components withinthe protected area due to damage caused by either 1), 2), or 3):
1)
Aircraftcrash OR 2)
Missile impact OR 3)
Explosion 2) 3)
Aircraftcrash OR Missile impact OR Explosion SITE AREA EMERGENCY EitherAor 8:
A.
Plant in Mode 1-2-3-4 AND Safety systems Rave failed or damage to vital structure has been caused by either 1), 2), or 3):
GENERAL EMERGENCY D.
Turbine generator rotating component failure requiring rapid turbine shutdown E.
Onsite explosion NOTE: Explosionisdefinedasarapid chemical reaction resulting in noise, heat, and the rapid expansion of gas.
NOTE: Explosion is defined as a rapid chemical reaction resulting in noise, heat, and the rapid expansion of gas.
B.
Toxic or flammable gas release which threatens plant operation.
C.
Turbine generator failure resulting in casing penetration.
NOTE: Explosion is defined as a rapid chemical reaction resulting in noise, heat, and the rapid expansion of gas.
Toxic or flammable gas release into control or vital areas which renders one train of safety related systems inoperable.
Possible Control Room Indicators ACTION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt 3/sr/dt/bsm~~
lIo 4
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EMERGENCY CLASSIFICATIONTABLE EPIP?0101 Page 31 4/9/92
~~17. Security Threat UNUSUALEVENT Declaration of a "Security Alert" due to either A, 8, C,D, E, F, G; H A.~~
Bomb Threat ALERT Declaration of a "Security Emergency" SITE AREA EMERGENCY Declaration of a "Security Emergency" involving imminent occupancy of the Control Room or other vital areas by intruders.
GENERAL (MERGENCY Physical attack on the plant resulting in occupation ofthe Control Room or other vital areas by intruders.
B.
Attack threat CAUTION: Consult Table 2, page 33 for required protective action recommendations.
C.
Civildisturbance D.
Protected area intrusion E.
Sabotage attempt F.
Internal disturbance G.
Vital area intrusion H.
Security Force strike Possible Control Room Indicators Complete actions listed in Step 8.4, Page 37.
ACT Complete actions listed in Step 8.5, Page 50.
ION Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt 3/sr/dt/ld~~
0 0
I
LE l
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 32 4/9/92
18. Control Room Evacuation UNUSUALEVENT ALERT Control Room evacuation anticipated or required SITE AREA EMERGENCY Control Room has been evacuated AND Local control of shutctown systems has NOT been established from local stations within 15 minutes.
~~GENERAL EMERGENCY Possible Control Room Indicators~~
~~19. Fire UNUSUALEVENT Uncontrolled fire withinthe power block lasting longer than 10 minutes ALERT Uncontrolled fire potentially affecting safety systems AND Offsite support required.~~
SITE AREA EMERGENCY Fire which prevents a safety system from performing its design function.
GENERAL EMERGENCY A major fire has occurred which could cause massive damage to plant systems resulting in any ofthe other General Emergency initiating conditions.
CAUTION: Consult Table 2, page 33 forrequired protective action recommendations.
Possible Control Room Indicators Complete actions listed in Step 8.4, Page 37.
ACT Complete actions listed in Step 8.5, Page 50.
ION Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~Q0101/Pt 3/sr/dt/Id~~
p ~
ILE 1
EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 33 4/9/92 20.
Loss of Engineered Safety Features/Fire Protection UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL~EMERGENCY Power reduction started in accordance with Technical Specifications due to either:
A) TS3.3.1, Reactor Trip System Instrumentation, or B)
TS 3.3.2, Engineered Safety Features Actuation System Instrumentation, or C)
TS 3.5, Emergency Core Cooling Systems, or D)
TS 3.6, Containment Systems, or E)
TS 3.7.2, Component Cooling Water, or F)
TS 3.7.3, Intake Cooling Water,
~ or G) 3.7.5, Control Room Emergency Ventilation System H) T.S. 3.7.8, Fire Suppression Systems.
NOTE:
NotifyFire Protection Department to consult FSAR Section 9.6, forfurther guidance on fire protection system requirements Possible Control Room Indicators ACTION Complete actions listed in Step 8.4, Page 37.
Complete actions listed in Step 8.5, Page 50.
Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt 3/sr/dt/Id~~
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EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 34 4/9/92
~~21. Other Plant Conditions Requiring Increased Awareness (Emergency Coordinator's Judgment)~~
UNUSUALEVENT Emergency Coordinator's judgment that other plant conditions exist which warrant increased awareness on the part ofthe operating staff and/or local offsite authorities.
NOTE: Activation ofthe Emergency Response Facilities does not require declaration of an emergency or entry into a specific emergency classification.
ALERT Emergency Coordinator's judgment that other plant conditions exist which warrant the increased awareness and activation of emergency response personnel.
SITE AREA EMERGENCY Emergency Coordinator's judgment that other plant conditions exist which warrant the precautionary notification to the public near the site and the activation of FPL and offsite agency emergency response personnel.
(Reflects conditions where some significant releases are likelyor are occurring but where a core melt situation is not indicated based on current information)
GENERAL,EMERGENCY Emergency Coordinator's judgment that other plant conditions exist which make release of large amounts of radioactivity, in a short period oftime, possible (Loss of two fission product barriers with potential for loss ofthe third, such as, actual or imminent substantial core degradation or melting with the potential for loss of containment.)
CAUTION: Consult Table 2, page 33 for required protective action recommendations.
Possible Control Room Indicators Complete actions listed in Step 8.4, Page 37.
ACT Complete actions listed in Step 8.5, Page 50.
ION Complete actions listed in Step 8.6, Page 64.
Complete actions listed in Step 8.7, Page 79.
~~/20101/Pt 3/sr/dt/Id~~

ML17349A961

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