ML20081A816

Public Version of Revised Emergency Plan Implementing Procedures A.2-101 Re Classification of emergencies,A.2-105 Re General Emergency & A.2-702 Re Response to Emergency at Prairie Island

ML20081A816
Person / Time
Site:	Monticello
Issue date:	09/28/1983
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML113190951	List: ML20081A816
References
PROC-830928, NUDOCS 8310260438
Download: ML20081A816 (70)

Text

,I f 09/27/83 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES

, LIST OF CURRENT PAGES .. .

PROCEDURE PROCEDURE TITLE REVISION NUMBER 000 Series Organization '

A.2-001 Emergency Organization 7 100 Series Activation A.2-101 Classification of Emergencies 6-A.2-102 Notification of an Unusual Event 4 A.2-103 Alert 4 A.2-104 Site Area Emergency 3 A.2-105 General Emergency 4 A.2-106 Activation of Technical Support Center 4 A.2-107 Activation of Operations Support Center 6 A.2-108 Access Control During Emergencies 0 200 Series Assessment A.2-201 On-Site Monitoring and Protective Action Criteria 3 A.2-202 Off-Site Monitoring During an Emergency 1 A.2-203 Deleted 3-1-82 A.2-204 Off-Site Protective Action Recommendations 3 A.2-205 Personnel Accountability 2 A.2-206 Deleted 3-1-82 A.2-207 Sampling Priorities During an Emergency 0 A.2-208 Core Damage Assessment 0 A.2-209 Responsibilities of Radiological Emergency Coordinator 0 300 Series Protective Actions A.2-301 Emergency Evacuation 2 A.2-302 Assembly Point Activation 3 A.2-303 Search and Rescue 3 A.2-304 Thyroid Prophylaxis 3 400 Series Radiological Surveil'ance and Control l

A.2-401 Emergency Exposure Control 2 A.2-402 Contamination Control 2

A.2-403 In-Plant Emergency Surveys 3 l A.2-404 Airborne Iodine Sampling and Analysis 3 A.2-405 Release Rate Determination 3

, A.2-406 Off-Site Dose Projection 7 l A.2-407 Personnel and Vehicle Monitoring 2 l A.2-408 Sample Coordination During an Emergency 1 l A.2-409 Self-Contained Breathing Apparatus (SCBA) Use Ouring An Emergency 0 i

A.2-410 Out-of-Plant Surveys 2

! A.2-411 Establishment of Secondary Access Control 1 A.2-412 Deleted 1-6-83 A.2-413 Small Volume Liquid Sample Obtained at the

! Post Accident Sampling System 1 l A.2-414 Large Volume Liquid Sample and/or Dissolved l

Gas Sample Obtained at Post Accident Sampling System 1 A.2-415 Containment Gas Sample Obtained at Post Accident Sampling System 2

-i- -

l AAA056 l 8310260438 831021 PDR ADOCK 05000263 F PM ,

.=  ?

09/27/03 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES

. LIST OF CURRENT PAGES __ .

PROCEDURE PROCEDURE TITLE REVISION NUMBER 400 Series Radiological Surveillance and Control (Cont'd.)

A.2-416 Containment Iodine and Particulate Samples Obtained at Post Accident Sampling System 2 A.2-417 Draining the Trap, Sump and Collector of Post Accident Sampling System 1-A.2-418 Post Accident Sampling Station Demin Water Tank Fill Procedure 0 A.2-419 Liquid Radiochemical Analysis 1 A.2-420 Containment Atmosphere Radiochemical Analysis 0 A.2-421 Containment Atniosphere Iodine / Particulate ~

Analysis 0 A.2-422 Stack Iodine / Particulate Sampling & Analysis 1 A.2-423 Reactor Building Vents Iodine / Particulate Sampling and Analysis 1 A.2-424 EOF Count Room Counting Procedure 0 A.2-425 Post-Accident Gas Sample Line Heat Trace 0 500 Series Communications and Documentation A.2-501 Communication During an Emergency 1 A.2-502 Recordkeeping During an Emergency 0 A.2-503 Deleted - 04/28/83 600 Series Re-Entry and Recovery A.2-601 Re-Entry 0 A.2-602 Deleted 11-19-81 A.2-603 -

Deleted 5/19/83 700 Series A.2-702 Response to an Emergency at Prairie Island 3 A.2-703 Response to Off-Site Situation Involving Radioactive Materials 0

. jj _ 0 AAA056 -

r - - - - , -- - - r -- ,, .- , ,

q t Procedure A.2-101

, Revision 6

[' .

Page 1 of 45 .

Op. Com. Rev. Reg'd. Yes X No Q.A. Review Reg'd. Yes No X

ALARA Review Reg'd. Yes __,No X j CLASSIFICATION OF EMERGENCIES i -

~

t A.2-101 i

-Prepared by: C.d /N' i s_- ALARA Review: Revision 0 Date 03/31/81 f Reviewed by: D 'M!d R .Q. A. Review: Revision 0 Date 03/31/81 l  : Operations'ComNitteeFin eview: Meeting Number /f f.l.0 Date C9 /.M /93 Approved by: sue 2a4,/ Date 9hAdU Op. Com. Results Review:~ -Not Require Mtg. # 946 Date 3/2d/81 0

.}

PURPOSE The purpose of this procedure is to specify conditions or groups of conditions that 1 indicate an emergency exists and the actions to be taken by the Operations personnel

to verify and classify the type of emergency condition.

CONDITIONS AND PREREQUISITES i An off-normal condition corresponding to one of the initiating events described in the appendices of this procedure is occurring or has occurred.

PRECAUTIONS J

l A. There are many indications of an emergency condition that may occur either

individually, in group events ~or sequentially. The operator must be careful not to rely on any one indication as being absolutely indicative of an

emergency condition. Although the operator should believe indications and take action based on those indications, he shall attempt to verify J indications by checking secondary or coincident indicators. Continued L surveillance and assessment of plant conditions is necessary to enst!re that

• the emergency classification is appropriately revised as conriitions change, or as more definitive information is obtained.

B. None of the actions specified in the EPIP's shall take precedence over the actions that are necessary to comply with Technical Specifications.

ORGANIZATION A. Overall Responsibility - Emergency Director

, ?8. In Charge Control Roon - Site Superintendent 1:

gt WP/kk 1

• vvy - gy+wy-- 3.-r.,w, y-- y v, - e r y -ye,- -

.r,.r-r,-- s e , s-+-, - v e v w ,r,.mw _,r-9. vv,.-,a-ww,-r-w e ~ err-n-wwwwe

Procedure A.2-101 Revision 6 Page 2.of 45 h

C. Assistance 4 .

Reactor Operator ,

Shift Technical Advisor when assigned ' l Shift Emergency Communicator ,

OISCUSSION i A. Definitions

1. Emergency Condition - An occurrence, or combination of events and indica-tions that fall into one of the following classifications:

a. Notification of Unusual Event Unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs.

b. ALERT Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any raleases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

c. SITE AREA EMERGENCY Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of

! the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near site boundary.

d. GENERAL EMERGENCY 4

Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels l_ off-site for more than the immediate site area.

2. Emergency Action Levels (EAL) - Numerical or qualitative values for the operational or radiological parameters, (radiological dose rates; 4

water borne or surface deposited concentrations of radioactivity; specific instrument indications or changes in indications) that may i- be used as threshholds for' initiating procedures or actions to assess and verify plant conditions and may require initiating specific emergency procedures as designated by a particular class of emergency.

i b

WP/kk -

Procedure A.2-101 Revision 6 Page 3.of 45

8. Recognition Attached to this procedure is Attachment 2, Event Recognition Guidelines (1-30). These guidelines identify the four emergency classifications, the possible initiating event (s), emergency action levels for each classifica-tion, and, where applicable, specific instruments and indicati6ns to be used to detect and classify an emergency. The identified instruments and alarms are a representative listing of various instruments that may be used to verify an emergency condition. There are many process variables referred to in the guidelines.

The instruments, indications, or alarms listed for any particular event are not necessarily a complete list of all those that will show abnormal indi-caticas or be useful in classifying the event. There is typically more than one instrument or instrument channel that monitors a specific parameter.

The redundant channels and coincident indicators should all be used to verify the emergency condition.

The emergency action levels specified in the guidelines do not necessitate initiation of any particular phase of the emergency plan but rather signify a need for assessment and classification of conditions. In many cases, the proper classification will be immediately apparent from in plant instrumen-tation. In other.s, further assessment is necessary to determine the appli-cable emergency classification.

The plant operating staff should consider the effect that combinations of initiating events have, that if taken individually would constitute a lower emergency classification but collectively may exceed the criteria for a higher classification.

In the Unusual Event classification, numerous EALs are related to limiting conditions for operation (LCOs) as specified in Technical Specifications.

In these cases, the EAL is not considered exceeded and an emergency condition does not exist if the appropriate corrective action for exceeding the LC0 is taken. The EAL is exceeded and an Unusual Event has occurred if the event results in a forced shutdown by the LC0.

I h

WP/kk -

%ncurre A.2-101

. Tedtu'om 5 71ce 4 .nf 45 .

RESPONSIBILITIES A. Emergency Director (Site Superintendent)

1. Prior to E0F activation, the Emergency Director shall dmfwe the appropriate emergency condition as soon as the event 1aa famn indicated and verified.

After EOF activation, the Emergency Director shall noMy the Imergency Manager when change in classification is indicated and wr+ Pied.

2. After the emergency condition has been declared, the lar~ancy Ilirector is responsible for implementing the actions as specif'et in the foUow-ing procedures:

a. Notification of an Unusual Event, A.2-102

b. Alert, A.2-103 .

c. Site Area Emergency, A.2-104

d. General Emergency, A.2-105 B. Control Room Operator

1. The control room operator shall immediately notify ttu site superin-tendent of any events that may be classified as emergency camdiitiians.

2. The operator shall attempt to verify any indications.

3. The operator shall assist the Site Superintendent in assassi'mp the indications and determining the classification of eme gancy..

4. The operator shall take immediate actions as dictated b3 ;nilnnt grocedures and his general knowledge to control the event and placa tie ini' ant in a safe condition.

, C. Shift Technical Advisor i

The Shift Technical Advisor shall advise the Site Superintanaant Cn 5denti-i fying the event.

l D. Shift Emergency Communicator The Shift Emergency Communicator shall assist the Site Sum 67tancumt in event classification.

PROCEDURE STEP 1: Verify the initial indication by comparing the indicticn, tu madandant instrument channels or to related parameters, physicaF cdsrculttiinns, and j field reports, as applicable.

i l 4 WP/kk l

1

i Procedura A.2-101 Revision 6 ~

Pagg'E.of 45 STEP 2: If the situation is clearly an emergency at this point and the SEC is likely asleep in the SEC Trailer, contact the SEC and instruct the SEC to make initial notifications to the State and Counties from the SEC Trailer. (These notifications shall be made within 15 minutes of

. emergency declaration.) -

. Summon the STA and the SEC, if not already notified.

STA:

DELETED SEC: ,rJ M 7 3 .

STEP 3: Use Attachment 1 to identify any Guidelines applicable to the initiating condition.

STEP 4: Locate the applicable guideline sheets in Attachment 2.

STEP 5: Determine the appropriate emergency classification by comparing the verified plant parameters to the EALs for each emergency condition. If more than one guideline is applicable to the initiating condition, use the guideline which indicates the most severe classification.

Initiate Form 5790-101-1, EMERGENCY CLASSIFICATION CHECKLIST (Attachment 3).

STEP 6 If the EOF is not activated, declare the appropriate emergency and implement the corresponding response procedure. If the EOF is activated, contact the Emergency Manager for consultation on whether or not to change the emergency classification. If a change is to be made, implement the corresponding proce-dure. (The Emergency Manager will declare the new classification.)

a. Notification of Unusual Event, A.2-102

b. Alert, A.2-103

c. Site Area Emergency, A.2-104

d. General Emergency, A.2-105 STEP 7: Continue to assess the events and, if necessary, the emergency classifi-cation, as more definitive information becomes available or if plant conditions change significantly.

REFERENCES

1. NSP Monticello Nuclear Generating Plant, Plant Emergency Plan

2. NUREG-0654/ FEMA-REP 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plan and Preparedness in Support of Nuclear Power Plants"

3. Title 10, Code of Federal Regulation Part 50, Appendix E ATTACHMENTS h 1. Attachment 1, List of Initating Condition Categories '

2. Attachment 2, Guidelines for Classification of Emergency Co<n'ditions

3. Example of Emergency Classification Checklist -

WP/kk

-.y -

, . - , , . .,-..,.__-_.,,.-.~,y - _ - - , - . _ . ,. _,__m .. -- ,

Procedure A.2-101 Revision 6 Page.-6'of 45

. Attachment 1 L, List of Initiating Condition Categories W Initiating Condition __. Guideline Radioactive effluents-high release rate or unmonitored ---

~

1 Increase in plant radiation levels ----------------------- 2 Release or loss of control of radioactive material within plant ---------------------------------------------------- 2 Fuel handling accident ---------- ,------------------------ 2 Reacto r p res s u re hi gh ------------------------------------ 3 Re acte r cool ant l ea k ------------------------------------- 4 Ma i n s team l i ne b re a k ------------------------------------ 5 Fuel cladding degradation -------------------------------- 6 High coolant or off gas activity ------------------------- 6 FSAR transient (Control Rod Drop) ------------------------ 6 Sa fety re l i e f val ve fai l u re ------------------------------ 7 ECCS initiation ------------------------------------------ 8 Loss of primary containment ------------------------------ 10 Loss of engineered safety or fire protection features ---- 11 Failure of RPS to initiate or complete scram ------------- 12 Loss of plant shutdown or shutdown cooling capability ---- 13 Loss of indicators or alarms (annunciators) -------------- 14 Control room evacuation ---------------------------------- 15 I,oxic or flammable gas ----------------------------------- 16 Security compromise -------------------------------------- 17 Lo s s o f A C p owe r - -- ---- -- --- ------------------- - -- ----- - - 18 Loss of DC power ----------------------------------------- 19 Tornado or sustained winds ------------------------------- 20 Fl o o d o r l ow wate r --------------------------------------- 21 Earthquake ----------------- ----------------------------- 22 Fire ----------------------------------------------------- 23 Explosion ------------------------------------------------ 24 Aircraft or missiles ------------------------------------- 25 Train accident ------------------------------------------- 26 WP/kk

Procedure A.2-101 Revision 6 Page 7.of 45 .

1 Attachment 1 (Cont'd.)

List of Initiating Condition Categories

~

Initiating Condition _ . . Guideline

(

Contaminated injury -------------------------------------- 26 Turbine failure ------------------------------------------ 26 General emergency ---------------------------------------- 28 Other plant conditions ----------------------------------- 29 Spent fuel , majo r damage to ------------------------------ 30

]

Y

~

WP/kk -

-,, , . , , . , , . - - . . - , , . . - . , , - - - ,n, - . - - , , ,,e.,, --

N:ceci:tre A.2-101 levistaan @

hge T .trf 45 .

ATTACHMENT 2 Guideline 1 RADI0 ACTIVE LEL'ENT UNUSUAL EVENT -

Radiological effluent technical specification limits exceedidL EAL's

1. Discharge Canal Monitor exceeds 20 cps.

(High alarm annunciated on C04-A-22, DISCHARGE CANAL R)D1E'IN, and

, recorded by C02-17.358)

E

2. Unmonitored liquid release to river which exceeds 10 CRC 8 A m. B limits.

E

3. Stack Effluent Monitor (Ch A or B) exceeds 90,000 pCihmn (Hi-Hi alarm annunciated on C259-A-1, STACK EFFLUENT H3--tE iMDIATION; recorded on C257 and C258 (RR 7858A and RR 7858B), STAIE WlHLE SAS RELEASE RATE; and alarmea by computer point D-061.)

E

4. Reactor Building Vent Noble Gas Monitor exceeds 4500 pli'4m E

5. Unmonitored gaseous release to the atmosphere which is asdibrated or suspected to exceed Appendix I Tech. Spec. limits.

ALERT Radiological effluents greater than 10 times technical specffartfon instan-taneous limits (an instantaneous rate which, if continued war 2. hours, would result in about 1 mR at the site boundary under average metten21'aigdr.a] condi-tions).

EAL's

1. Discharge Canal Monitor exceeds 200 cps.

E c

WP/kk

Procedure A.2-101 Revision 6 Page 9.of 45 .

ATTACHMENT 2 (Cont'd.)

~

Guideline 1 (Cont'd.) RADIOACTIVE EFFLUENT ,

2. Unmonitored 1-iquid release to river which is 10 times the limits in 10CFR20 Appendix B.

2E

3. Stack Effluent Monitor (Ch A or B) exceeds 9:0E+5 pCi/ soc.

2E

4. Reactor Building Vent Noble Gas Monitor exceeds 45,000 pCi/sec.

2E

5. Unmonitored gaseous release to the atmosphere which is estimated or expected to exceed 10 times Appendix I Tech Spec limits.

SITE AREA

a. Effluent monitors detect levels corresponding to greater than 50 mR/hr for hour gr greater than 500 mR/hr Whole Body for two minutes (or five times these levels to the thyroid) at the site boundary for adverse meteorology, -

b. These dose rates are projected based on other pl:r.t p:rameters (e.g.,

radiation level in containment with leak rate appropriate for existing containment pressure) or are measured in the environs; or

c. EPA Protective Action Guidelines are projected to be exceeded outside the Site Boundary.

EAL's V

l 1. Stack Effluent Monitor (Ch A or B) exceeds 9.0E+5 pCi/sec for 30 minutes l

SE l 2. Stack Effluent Monitor (Ch A or B) exceeds 9.0E+6 pCi/sec for 2 minutes E

3. Stack release rate of radioiodines exceeds 1.7E+4 pCi/sec for 30 minutes l EE

4. Stack release rate of radioiodines exceeds 1.7E+5 pCi/sec for 2 minutes EE

5. RBVNobleGasMonitorexceeds2.1E+4pCi/secfor30mihutes i

WP/kk -

, a - - - .- - - --- - -

Proceduro A.2-l01 Revision 6 Page la of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 1 (Cont'd.) RADI0 ACTIVE EFFLUENT ,

gp

6. RBV Noble Gas Monitor exceeds 2.1E+5 pCi/sec for 2 minutes.

5E

7. RBV release rate of radiciodines exceeds 2100 pCi/sec for 30 minutes EI

8. RBV release rate of radioiodines exceeds 2.1E+4 pCi/sec for 2 minutes EI

9. Whole body doses greater than 1 Rem or thyroid doses of greater than 5 Rem are projected beyond the site boundary.

EE

10. Containment Radiation Monitor reading indicates above the .01% curve when plotted versus time after shutdown on the graph shown in Figure 1.

EI

11. Measured W.B. dose rates at site boundary or beyond exceed 50 mR/hr for 30 minutes or 500 mR/hr for 2 minutes EE

12. Radioiodine concentrations measured at site boundary or beyond exceed l 7.0E-8 pCi/cc for 30 minutes or 7.0E-7 pCi/cc for 2 minutes.

GENERAL As specified in Guideline 28.

l t

I c

l WP/kk -

Proceduro A.2-101 Revision 6 Page 11 of 45

.l 1

FIGURE 1 l Percent of Fuel Inventory Airborne in the Containment gt -

n~

100t Fuel Inventory = 1004 Noble Cases

, + 25% lodine '

2 "I + 11 particulates 4  ;

e le 2004 r

g g *1 lot

$b5 14 L- .

o .

3 -

c o lo' 1_ 0.1 e

• e h 10 q 6  : 0.01 e b ~

j io' ,-

o 0.001%

u  :

o' l 10 ) 3 ib bbVitf i .i ihhhW1o' i 5 iib Mto' i 3 ibb G io' Time After Shuldatun (Hrs)

% Fuel Inventory Apprcximate Source and Damage Estimate Released 100. 1004 TID-14844, 100% fuel damage, potential core melt.

50. 50t TID noble gases, TMI source.

10. 10% TID, 100% NRC gap activity, total clad failure, partial core uncevered.

3. 34 TID, 100% WASH-1400 gap activity, major clad failure.

1. It TID, 10% NRC gap, Max. 10% clad failure.

.1 .1% TID, 14 NRC gap, 11 clad failure, local heating of 5-10 fuel assemblies.

.01 .01% TID, .It*NRC gap, clad failure of 3/4 fuel element (36 rods).

10-3 .01% NRC gap, clad failure of a few re'.s.,

10-4 1004 coolant release with spiking.

WP/kk 5x10-8 2004 coolant inventory release.- -

10-6 Upper range of nor=al airborne noble gas activity in containment.

Procedure A.2-101 Revision 6 Page 12 of 45 .

ATTACHMENT 2 (Cont'd.)

~

Guideline 2 IN PLANT RADIATION LEVELS ,

UNUSUAL EVENT -

Not Applicable ALERT Severe degradation in control of radioactive materials. .

EAL

1. Increase by factor of 1000 in plant radiation levels as indicated by Area Radiation Monitoring System:

Panel Description Normal EAL C-11 A-1 Refuel Floor Low Range 2 Full scale C-11 A-2 Refuel Floor High Range 5 5000 I

C-11 A-3 Refuel Floor S.W. Stairway 1 1000 C-11 A-4 New Fuel Storage 20 Full scale C-11 A-5 Fuel Pool Skimmer Tk Area 20 Full scale C-11 A-6 1001' Rx South 3 Full scale C-11 A-7 985' Sample Hood 5 Full scale C-11 A-8 Rx Cleanup System Access 0.25 250 C-11 A-9 962' Rx Tool Storage Area 0.8 800 C-11 A-10 East CR0 Module Area 7 Full scale C-11 A-11 West CR0 Module Area 3 Full scale C-11 A-12 TIP Drive Area 2 Full scale C-11 A-13 TIP Cubicle 30 Full scale C-11 A-14 HPCI Turbine Area 2 Full scale C-11 A-15 Rx. Bldg Drain Tk Area 25 Full scale C-11 A-16 RCIC Pump Area 1 1000 C-11 A-17 East C.S. and RHR Area 10 Full scale C-11 A-18 West C.S. and RHR Area 5 Full scale C-11 A-19 Hot Lab 0.25 250 C-11 A-20 Control Room Low Range 0.02 20 0

WP/kk

o .

Procedure A.2-101 Revision 6

, Page 13 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 2 (Cont'd.) IN-PLANT RADIATION LEVEL ,

Panel -

Description Normal EAL

(

C-11 A-21 Control Room High Range 3 3000

, C-11 B-1 Turbine Operating Floor 20 Full scale C-11 B-2 Turbine Front Standard 10 Full scale C-11 B-3 Cond Demin Operating Area 1 1000 C-11 B-4 Mechanical Vacuum Pump Rm 9 Full scale C-11 B-5 Feedwater Pump Area 1 1000 C-11 C-1 Radwaste Control Room 0.2 200 C-11 C-2 Sample Tank Area 2 Full scale C-11 C-3 Conveyor Operating Area 0.2 200 C-11 0-1 Hot Machine Shop 0.2 200 C-252 E-1 Recombiner Instrument Room 2 Full scale C-252 E-2 Recombiner Pump Room 2 Full scale C-252 F-1 Offgas Storage Foyer 0.1 100 C-11 F-2 Offgas Storage Foyer High Range (100 100 C-257 & C-258 Containment Radiation Monitor 50 R/hr ,

NOTE: EAL's shown as FULLSCALE indicate that an increase by a factor of 1000 is beyond the range of the particular monitor. In these cases, a fullscale reading combined with the Site Superintendent's concurrence, shall meet the criteria for the ALERT classification.

9E

2. Direct measurement of radiation levels corresponding to an increase by a ,

factor of 1000.

SITE AREA Not applicable GENERAL As specified in Guideline 28.

0 WP/kk s - _ - . - . ., , - , . - , - - - - ~ - ,,,g -- -- - - - . -.n-- -,m-- ,---.,,,,------,w n-- w---<, . - r -, -- -

~

ProcedureA.2-[01 Revision 6

' Page 14 of .45 .

ATTACHMENT 2 (Cont'd.) -

Guideline 3 REACTOR PRESSURE HIGH

~

UNUSUAL EVENT

1. Reactor Pressure exceeds safety limit (1335 psig).

Instrument Description EAL C05-FPR 6/97 Reactor Wide Range Pressure Recorder 1200 C05-6.90 A/B Reactor Pressure Indicators 1200 Verify 1335 psig exceeded by checking pressure indicator PI 2-3-608 on C56.

ALERT Not Applicable SITE AREA EMERGENCY Not Applicable GENERAL EMERGENCY

.As specified in Guideline 28.

t f

L

~

~

WP/kk i

~,

Procedure A.2-101 Revision 6

. Page 15 of 45 .

ATTACHMENT 2 (Cont'd.)

i

~

Guideline 4 REACTOR COOLANT LEAK ,

--' ~

UNUSUAL EVENT Primary system leak rate exceeds technical specification.

EAL's

1. Unidentified leakage calculated from C4-FQ2543 or by computer point 0-122, Floor Drain Sump Rate of Change, exceeds 5 gpm S3

2. Identified leakage calculated from C4-FQ 2544 or from computer point D-120, Equipment Drain Sump Rate of Change, exceeds 20 gpm.

93

3. Unidentified leakage rate increases 2 gpm within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period as determined from Test #0381, CONTAINMENT COOLANT LEAKAGE LOG.

ALERT Primary coolant leak rate greater than 50 gpm.

EAL

1. Total leakage calculated from C4-FQ2543 and FQ-2544 or from computer points D-120, Equipment Drain Sump Rate of Change, D-122, Floor Drain Sump Rate of Change, exceeds 50 gpm.

SITE AREA Known loss of coolant accident greater than makeup pump capacity.

EAL's

1. Reactor water level (C05-2.3.85 A/B) decreasing below 1 foot above active fuel (-114 inches)

GENERAL As specified in Guideline 28.

0

~

WP/kk -

Procedure A.2-l01 Revision 6 Page 16 of.45 .

ATTACHMENT 2 (Cont'd.)

~

Guideline 5 MAIN STEAMLINE BREAK ,

- ~ ~

UNUSUAL EVENT Not Applicable ALERT Steamline break with MSIV malfunction causing leakage to secondary containment.

EAL's 1.'

Site Superintendent's opinion that MSIV is malfunctioning or continuing steam flow with evidence that steam line break is outside of primary containment (e.g. visual observation, radiation or temperature),

and 2a. Annunciator alarms on MAIN STEAM LINE HIGH FLOW A/B (C05-A-25/26) and RX WATER LEVEL HI/LO (C05-B-24),

or 2b. Annunciator alarm' MAIN STEAM TUNNEL HIGH TEMPERATURE A/B (C05-A17/18) or 2c. - Annunciator alarm MAIN STEAM LINE LEAKAGE (C05-B-32).

SITE AREA Main steam line break with failure of MSIV's to isolate leak and causing leakage outside of secondary containment.

EAL's

1. Site Superintendent's opinion that MSIV is malfunctioning or continuing steam flow with evidence that steam line break is outside of primary containment and 2a. Annunciator alarms on MAIN STEAM LINE HIGH FLOW A/B (C05-A-25/26) and RX WATER LEVEL HI/LO (C05-B-24) or G

WP/kk

8 -4 Procedure A.2-101 Revision 6

, Page 12 of 45 .

ATTACHMENT 2 (Cont'd.)

~

Guideline 5 (Cont'd.) MAIN STEAMLINE BREAK ,

2b. Annunciator alarm on MAIN STEAM TUNNEL HIGH TEMPERATURE (C-5-A-17/18) or 2c. Annunciator alarm on MAIN STEAM LINE LEAKAGE (C05-B-32) ,

and 3a. Annunciator alarm on TURBINE BUILDING HIGH RADIATION ALARM (C04-A-21) or 3b. High airborne radioactive material levels in Turbine Bldg. indicated by air monitors or direct measurement or 3c. Visual observation that blow-out panels between steam chase and turbine building have been ruptured.

GENERAL As specified in Guideline 28.

0

' WP/kk

, , . - , , . --n . a r-- - - n--~~-- ,,.c .-- - -- - ~- , c ,,- .- , -r - - , - ,- g - ,--c-,-- - r-- -en,~

Procedure A.2-101 Revision 6 Page 18 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 6 FUEL CLADDING DEGRADATION ~

UNUSUAL EVENT Fuel damage indication EAL's

1. Offgas Radiation Monitor exceeds 20,000 mR/hr or- .

2. Offgas Radiation Monitor increases by 4000 mR/hr within 30 minutes at steady power or

3. Reactor coolant I-131 dose equivalent exceeds 5 pCi/ gram as determined by sample and analysis.

ALERT Severe loss of fuel cladding.

a. High offgas at air ejector monitor (greater than 5 ci/sec; corresponding to 16 isotopes decayed 30 minutes) or

b. Very Tiigh coolant activity sample (e.g. , 300 pCi/cc equivalent of I-131)

EAL's

1. Offgas Radiation Monitor exceeds 200,000 mR/hr

2. React coolant I-131 dose equivalent exceeds 300 pCi/gm as determined by sample and analysis.

or

3. Main 5 team Line monitor initiates trip due to high radiation.

NOTE:

Resin intrusion may cause hign radiation without fuel cladding damage.

SITE AREA Degraded Core with possible loss of coolable geometry EAL's

1. More than 1/3 of core uncovered as indicated by reactor water level below

-174 inches and

2. a. Reactor coolant I-131 dose equivalent exceeds 3000 pCi/gm as i determined by sample and analysis. ,

or '

b. InabiTity to insert control rods fully 1

c. InabiNtytopositionSRM'sorIRM'swithincore. I GENERAL g As specified in Guideline 28. -

WP/kk

Procedure A.2-101 Revision 6 Page 19 of 45  :

~

ATTACHMENT 2 (Cont'd.)

Guideline 7 SAFETY RELIEF VALVE FAILURE .

~~ ~

UNUSUAL EVENT Failure of a safety relief valve to close following reduction of applicable pressure.

EAL's Auto Blowdown Relief Valve Leakage Alarm, C03-A-09 of SRV Open Alarm, C05-A-54 t

ALERT Not applicable SITE AREA EMERGENCY Not applicable GENERAL EMERGENCY As specified in Guideline 28.

O

~

~

i WP/kk p , -- , - , - - - w , - v - ~ - - - - - - . . - - - . . , , - -

, Procedure A.i-101 2

Revision 6 Page 20 of 45 .

ATTACHMENT 2 (Cont'd.)

~

Guideline 8 ECCS INITIATION .

UNUSUAL EVENT Emergency Core Cooling System (ECCS) initiated and discharge to vessel.

EAL's lu. RHR flow to reactor as indicated by RHR FLOW A/B Indicator, C03-10.139A/B or lb. Core spray flow to reactor as indicated by CORE SPRAY FLOW A/B Indicator, C03-14.50A/B ar i

Ic. HPCI flow to reactor as indicated by HPCI FLOW Indicator, C03-FIC 23-108 or ld. APRS actuation as indicated by annunciator AllTO R10WDOWN TIMERS ACTIVATE (3-A-25) and subsequent S/RV OPEN (5-A-54) annunciator and -

2. Site Superintendent's opinion that an emergency should be declared.

ALERT Not Applicable SITE AREA EMERGENCY Not Applicable GENERAL EMERGENCY See Guideline 28.

0 l ~ '

~ '

WP/kk

l . .

~

Procedure A.2-101 Revision 6 Page 21 of 45 ATTACHMENT 2 (Cont'd.)

Guideline 10 LOSS OF CONTAINMENT INTEGRITY ,

UNUSUAL EVENT Loss of containment integrity requiring shutdown in accordance with Technical Specifications.

EAL's Plant shutdown is required by any one of the following limitir.g conditions for operation:

a. TS 3.7.A - Primary Containment; or

b. TS 3.7.8 - Standby Gas Treatment System; or

c. TS 3.7.C - Secondary Containment; or

d. TS 3.7.D - Primary Containment Isolation Valves l ALERT Not Applicable SITE AREA EMERGENCY l

- Not Applicable GENERAL EMERGENCY As specified in Guideline 28.

i i

G WP/kk -

i t

Procedure A.2-101 Revision 6 Page 22. of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 11 LOSS OF ESF OR FIRE PROTECTION SYSTEM UNUSUAL EVENT

1. Loss of Engineered Safety Features (ESF) or fire protection system requiring shutdown by Technical Specificatioris. The following is a list of operable ESF and fire protection subsystems necessary to meet LC0:

Core Spray System Low Pressure Coolant Injection Subsystem Containment Cooling Capability (RHR Service Water System)

High Pressure Coolant Injection System Automatic Pressure Relief Diesel Generator System Fire Protection System Standby Liquid Control System ALERT Not Applicable l

SITE AREA EMERGENCY

.Not Applicable i

GENERAL EMERGENCY As specified in Guideline 28.

e 0 WP/kk -

i Procedure A.2-101 Revision 6 Page 23 of.45 .

ATTACHMENT 2 (Cont'd.)

Guideline 12 REACTOR PROTECTION SYSTEM FAILURE ,

l UNUSUAL EVENT Not Applicable ALERT .

Failure of the reactor protection system to initiate and complete a scram which brings the reactor subcritical.

.EAL's Valid Scram Signal and Neutron count rate indicates reactor critical.

SITE AREA EMERGENCY Transient requiring operation of shutdown systems with failure to scram (continued power operation but no core damage immediately evident.)

EAL's Failure to bring reactor subcritical with control rods and 4 Failure of the. standby liquid control system and Site Superintendent's opinion that a transient is in progress and No indication of core damage (if core damage indicated, call a general emergency)

GENERAL EMERGENCY As specified in Guideline 28.

l 0

WP/kk -

Procedure A.2-101 Revision 6

, Page 24 of 45 ,.

ATTACHMENT 2 (Cont'd.)

Guideline 13 LOSS OF PLANT SHUTDOWN OR '

SHUTDOWN COOLING CAPABILITY UNUSUAL EVENT -

Not Applicable ALERT Complete loss of ability to achieve or maintain cold shutdown.

EAL's

1. Loss of both RHR SW Loops or Loss 37 both RHR Systems Shutdown cooling mode of operation or Loss ET both RHR LPCI modes of operation and loss of both core spray systems.

AND/0R

2. Site Superintendent's opinion that plant cannot reach or maintain cold shutdown.

SITE AREA Complete loss of ability to achieve or maintain hot shutdown EAL's

1. Inability to SCRAM and inoperable Standby Liquid Control System and

2. Loss of all safety relief valve capability or Inoperable RHR System or Inoperable RHR heat sink and

3. Loss of main condenser cooling or No makeup capability from either HPCI or RCIC systems.

AND/0R

4. Site Superintendent's opinion that plant cannot reach or maintain hot shutdown.

GENERAL EMERGENCY As specified in Guideline 28.

WP/kk -

4 p Procedure A.2-101 Revision 6

. Page 25 of 45 -

ATTACHMENT 2 (Cont'd.)

Guideline 14 (OSS OF INSTRUMENTATION NOTE: Indication of 'alare;, or instrumentation failure may be difficult to 4

determine. A failure of normally lighted indicators or the failure of certain alarms to annunciate during a surveillance procedure may provide an initial warning. A cause of annunciator failure, and thus an indication of failure, could be a loss of the uninterruptable MG set and no transfer to CKT Y10.

UNUSUAL EVENT Indications or alarms on process or effluent parameters not functional in the Control Room to an extent requiring plant shutdown.

ALERT Loss of most or all annunciators (on panels C03, C04, C05, C08) sustained for

> 15 minutes with the plant not in cold shutdown.

SITE AREA EMERGENCY

1. Loss of most or all annunciators (on panels C03, C04, COS, C08) > 15 minutes and plant transient initiated or in progress.

GENERAL EMERGENCY As specified in Guideline 28.

~

~

WP/kk e-- , ---

,, -, ,,----,.--,e-,..,, e. .- - - , , +,--- ---------,..y-e-- , - - , -,,s,-,--- - - - -e-- .-- , . . - - . - - - -

Procedura A.2-101 Revision 6 Page 26 of.45 ATTACHMENT 2 (Cont'd.)

Guideline 15 CONTROL ROOM EVACUATION ,

~

~~~

UNUSUAL EVENT Not Applicable ALERT Evacuation of the Control Room is required or anticipated and control of shutdown systems has been established at local stations. (If local control has not been established in 15 minutes, go to SITE AREA.)

EAL As determined by on-duty Shift Supervisor.

SITE AREA EMERGENCY Evacuation of Control Room and control of shutdown systems not established from local stations in 15 minutes.

EAL t

As determined by on-duty Site Superintendent.

GENERAL EMERGENCY As specified in Guideline 28.

l

~

WP/kk ~

e .

~

Procedure A.2-101 Revision 6 Page 22 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 16 T0XIC/ FLAMMABLE GASES .

- - ~

UNUSUAL EVENT Near or onsite toxic or flammable gas release.

EAL Gaseous hazards being experienced or projected onsite (out-of plant) as indicated by visual observation, physical measurement or notification.

ALERT Entry into facility environs of uncontrolled toxic or flammable gases.

EAL's Gaseous hazards being experienced or projected within the plant as indicated by measured concentrations equal to or greater than:

(a) 10 ppm chlorine;'or l (b) explosive levels (as detected by explosive meter).

NOTE: Chlorinator House is not considered to be within the plant.

SITE AREA Entry of uncontrolled flammable gases into vital areas oor entry of uncontrolled toxic gases into vital areas where lack of access to the area constitutes a safety problem and plant is not in cold shutdown.

EAL's

1. Gaseous hazards being experienced or projected within vital areas of the plant as indicated by measured concentration equal to or greater than:

a) 10 ppm chlorine; or b) explosive levels (as detected by explosive meter) and

2. Plant not in cold shutdown.

GENERAL EMERGENCY As specified in Guideline 28.

0

-WP/kk -

I t

, -. ,----y . -

r r... - y . ,_ . .. . , - . , y . ,- . .,m.w..- ..v, , ...-

v-w- v.--- + -.

Procedure A.2-101 Revision 6 Page 23 of 45 ,,

ATTACHMENT 2 (Cont'd.)

Guideline 17 SECURITY COMPROMISE NOTE TO EMERGENCY DIRECTOR: For acts of sabotage against plant equipment, refer also to SCPIP-12. -

(

UNUSUAL EVENT Security threat or attempted entry or attempted sabotage.

EAL Site Superintendent's opinion.

ALERT Ongoing security compromise.

EAL Security safeguards contingency event that results in adversaries commandeering an area of the plant, but not controlling shutdown capability or any vital arp's.

SITE AREA Imminent loss of physical control of the plant.

EAL Physical attack on the plant involving imminent occupancy of the control room, auxiliary shutdown panels, and any other vital areas.

GENERAL Loss of physical control of the facility.

EAL Physical attack on the plant has resulted in unauthorized personnel occupying the control room or any other vital areas.

0 WP/kk -

o .

Procedure A.2-101 Revision 6 Page 29 of 45 .

ATTACHMENT 2 (Cont'd.)

LOSS OF AC POWER Guideline 18 .

~

~

URJSUAL EVENT Loss of offsite power or loss of onsite AC power capability.

EAL's

1. Loss of all offsite power as indicated by annunciators:

C08-B-7 No. 1R Res Trans to No. 13 Bus Bkr Trip; and C08-C-08 No. lAR Res Trans to No. 15 Bus Bkr Trip; and C08-C-11 No. lAR Res Trans to rio.16 Bus Bkr Trip; and C08-C-19 No. 14 4160V Bus to No. 16 Bus Bkr Trip and verified by zero voltage indicated on Bus 11, Bus 12, Bus 13, Bus 14, and 1AR Transformer voltage meters on panel C8.

2.C

2. Loss of both Emergency Diesel Generators when they are required to be operable by Technical Specifications.

ALERT Lov, of offsite power and loss ofall onsite AC power. (see Site Area Emergency for extended loss)

EAL's

1. hss of all offsite ' power as indicated by annunciators:

C08-B-7 No.1R Res Trans to No.13 Bus Bkr Trip; and C08-C-08 No. lAR Res Trans to No. 15 Bus Bkr Trip; and C08-C-11 No. lAR Res Tras to No. 16 Bus Bkr Trip; and C08-C-19 No. 14 4160V Bus to No. 16 Bus Bkr Trip and verified by zero voltage indicated on Buss 11, Bus 12, Bus 13, Bus 14 and 1AR Transformer voltage meters on panel C8.

and

2. Loss of both Emergency Diesel Generators when they are required to be operable by Technical Specifications.

r; WP/kk

~' - _ - _ _ - - _ _ _ _ _ _

Procedure A.2-101 Revision 6 Page 30 of.45 .

ATTACHMENT 2 (Cont'd.)

Guideline 18 (Ccnt'd.) LOSS OF AC POWER SITE AREA Loss of all offsite power and loss of onsite AC power for more than 15 minutes.

EAL's

1. Loss of all offsite power as indicated by annunciators:

C08-B-7 No. 1R Res Trans to No. 13 Bus Bkr Trip; and C08-C-08 No. lAR Res Trans to No. 15 Bus Bkr Trip; and C08-C-11 No. lAR Res Tras.to No. 16 Bus Bkr Trip; and C08-C-19 No. 14 4160V Bus to No. 16 Bus Bkr Trip and verified by zero voltage indicated on Buss 11, Bus 12, Bus 13 Bus 14 and 1AR Transformer voltage meters on panel C8.

and l

2. Loss of both Emergency Diesel Generators when they are required to be operable by Technical Specifications.

and

3. 15 minute time lapse.

l GENERAL EMERGENCY As specified in Guideline 28. l "l

0 WP/kk -

r

,?

Procedure A.2-101 Revision 6

, Page 31 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 19 LOSS OF DC POWER

~

UNUSUAL EVENT Not applicable.

ALERT Loss of all vital DC power. (See Site Area Emergency for extended loss.)

EAL's Loss of both 125V DC power sources and loss of 250V DC power source as indicated by:

1. Annunciators C08-A-20 250V Bus Low Voltage; and C08-B-13 No.12125V DC Bus Low Voltage; and C03-C-13 No. 11 125V DC Bus Low Voltage AND

2. Site Superintendent's opinion that all vital DC power is lost or degraded voltages are measured at battery terminals.

SITE AREA Loss of all vital Gnsite DC power for more than 15 minutes.

EAL's Loss of both 125V DC power sources and loss of 250V DC power source as indicated by:

1. Annunciators C08-A-20 250V Bus low Voltage; and C08-B-13 No. 12 125V 00 Bus low Voltage; and C08-C-13 No. 11 125V DC Bus Low Voltage AND

2. Site Superintendent's opinion that all vital DC power is lost or degraded voltages are measured at battery terminals.

AND

3. Lapse of 15 minutes.

GENERAL EMERGENCY As specified in Guideline 28.

WP/kk

Procedure A.2-101 Revision 6 Page 32 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 20 TORNADO OR '

SUSTAINED WINDS UNUSUAL EVENT Any tornado on-site.

EAL's A tornado is observed to touch down within site boundary EE Sustained winds above 75 mph for greater than 10 minutes at the site.

ALERT Tornado striking facility.

EAL's A tornado strikes a vital plant structure -

EE Sustained winds above 90 mph for greater than 10 minutes at the site.

SITE AREA Sustained winds or tornadoes in excess of design levels.

EAL's Tornado causes damage to vital plant equipment or structures EE Sustained winds above 100 mph for greater than 10 minutes at the site.

GENERAL EMERGENCY As specified in Guideline 28.

0 WP/kk

Procedure A.2-101 i Revisidn 6

. Page 33 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 21 RIVER WATER HI/ LOW

~

~~~

UNUSUAL EVENT

1. River water level in excess of 918 Feet

2. River flow below 240 CFS (about 902.4 FT river level)

ALERT

1. River water level between 921 and 930 FT.

2. River flow below 220 CFS (about 902.3 FT).

SITE AREA EMERGENCY

1. River water level exceeds 930 FT.

2. River water level below 899 FT.

3. Flood or low water causes damage to vital equipment.

GENERAL EMERGENCY As specified in Guideline 28.

c WP/kk -

.- - .--..,.w. .- . ...--,n. , , , , . - - , . . . . . - . , - . . . - .

Procedure A.2-101 Revision 6 Page 34 of.45 .

ATTACHMENT 2 (Cont'd.)

Guideline 22 EARTHQUAKE ,

~~ ~

UNUSUAL EVENT (

Any earthquake felt in plant. or detected on station seismic instrumentation, and subsequently confirmed by one or more off-site sources.

EAL's

1. Alarm C06-C-8, EARTHQUAKE SI

2. Site Superintendent's opinion ALERT Confirmed earthquake greater than OBE levels.

EAL Alarm C06-C-13, OPERATIONAL BASIS EARTHQUAKE SITE AREA Confirmed earthquake greater than DBE levels and plant not in cold shutdown.

EAL's Alarm C06-C-18,-DESIGN BASIS EARTHQUAKE and Plant not in cold shutdown.

I GENERAL EMERGENCY As specified in Gudeline 28.

i l

l 0

~

~

WP/kk r . ,--- ,-e,, -e, , - , , - - ,,r-e n-----,- nw,v,y-. , , , , , - - - . - , , . , - , . - , . - . ----.a,-. n.,-,-, -~- .,- g ,--- - , - , - - - -

l ,P

• Procedure A.2-101 Revision 6

. Page 35 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 23 FIRE .

~

~ ~~

UNUSUAL EVENT Fire within plant lasting more than 10 minutes after initiation of fire fighting.

EAL Fire Brigade Leader's determination.

ALERT Fire potentially affecting safety systems.

EAL's Observation that fire could affect safety system; and Site Superintendent's opinion.

SITE AREA Fire compromising the functions of safety system.

EAL's Observation of fire that affects safety systems or functions; and Site Superintendent's opinion.

GENEAL EMERGENCY As specified in Guideline 28.

WP/kk

_---,..__.-.,,...-..wm .- ...-.. .#_.-* ,, . - - . -- -

-..yv.

Procedure A.2-l01 Revision 6 Page .36 of.45 .

ATTACHMENT 2 (Cont'd.)

Guideline 24 EXPLOSION

~

UNUSUAL EVENT

,Near or On-site explosion.

EAL

. Visual observation or notification received; and -

Site Superintendent's opinion.

ALERT Known explosion damage to facility affecting plant operation.

EAL 1

Site Superintendent's opinion. ,

SITE AREA

. Severe damage to safe shutdown equipment from explosion or missiles.

EAL's Plant not in cold shutdown and Site Superintendent's opinion GENERAL EMERGENCY As specified in Guideline 28.

O WP/kk -

l

Procedure A.2-101 Revision 6

, Page 37 of 45 .

~

ATTACHMENT 2 (Cont'd.)

Guideline 25 AIRCRAFT & MISSILES ,

~

UNUSUAL EVENT

1. Aircraft crash onsite or suspicious aircraft activity over facility.

EAL Visual observation or notification is received.

ALERT Aircraft crash on the facility or missile impacts on facility.

EAL Visual observation SITE AREA

a. Aircraft crash affecting vital structures by im,7act or fire.

b. Severe damage to safe shutdcwn equipment from missiles or explosion.

EAL As determined by Site Superintendent with plant not in cold shutdown.

GENERAL EMERGENCY As specified in Guideline 28.

0 WP/kk

Procedure A.2-101 Revision 6 Page:38 of.45 .

t ATTACHMENT 2 (Cont'd.)

Guideline 26 MISCELLANEOUS ,

UNUSUAL EVENT

a. Transportation of contaminated injured individual from site to offsite hospital.

b. Train derailment on site.

c. Turbine rotating component failure causing rapid plant shutdown.

EAL's

1. Visual observation SE

2. Site Superintendent's opinion ALERT Turbine failure causing casing penetration.

EAL's l

1. Visual observation and

2. Site Superintendent's opinion

SITE AREA EMERGENCY Not Applicable

(

GENERAL EMERGENCY As specified in Guideline 28.

i I

D WP/kk -

Procedure A.2-101 Revision 6

, Page 39 of 45 .

ATTACMENT 2 (Cont'd.)

Guideline 28 ALL GUIDELINES - GENERAL EMERGENCY GENERAL EMERGENCY ,

a

a. Effluent monitors detect levels corresponding to 1 rem /hr W.B. or 5 rem /hr thyroid at the site boundary under actual meteorological conditions,

b. These dose rates are projected based on other plant parameters (e.g., radiation levels in containment with leak rate appropriate for existing containment pressure with some confirmation from effluent monitors) or are measured in the environs.

EAL's

1. Stack Effluent Monitor (Ch. A or B) exceeds:

1.3E+8 pCi/sec in stability class A 1.9E+8 pCi/sec in stability class B 1.0E+9 pCi/sec in stability class C 1.0E+9 pCi/sec in stability class D 1.0E+9 pCi/sec in stability class E 1.0E+9 pCi/sec in stability class F E

2. RBV Effluent Monitor exceeds:

9.6E+7 pCi/sec in stability class A 3.1E+7 pCi/sec in stability class B 1.5E+7 pCi/sec in stability class C 7.1E+6 pCi/sec in stability class D 4.4E+6 pCi/sec in stability class E 2.8E+6 pCi/sec in stability class F E

3. Stack radioiodine release rate exceeds:

2.3E+6 pCi/sec in stability class A 2.6E+6 pCi/sec in stability class B 3.4E+6 pCi/sec in stability class C 4.9E+6 pCi/sec in stability class 0 4.9E+6 pCi/sec in stability class E 3.9E+6 pCi/sec in stability class F E

c WP/kk

._ - 4

Procedurg A.2-l01 Revision 6 Page 40 of.45 .

ATTACHMENT 2 (Cont'd.)

Guideline 28 (Cont'd.) ALL GUIDELINES - GENERAL EMERGENCY

4. RBV radioiodine release rate exceeds: -

(

1.9E+6 pCi/sec in stability class A 6.0E+5 pCi/sec in stability class B 3.0E+5 pCi/sec in stability class C 1.4E+5 pCi/sec in stability class D 8.6E+4 pCi/sec in stability class E 5.6E+4 pCi/sec in stability class F or

5. Elease rate projection based on Cont.tinment Radiation Monitor exceeds any of the values in 1 or 2 above ,

or

6. Ese rates of l rem /hr W.B. are measured at the site boundary or beyond or

7. Edioiodine concentrations measured at the site boundary or beycnd exceed 7E-6 pCi/cc.

NOTE: Consider evacuation only within about 2 miles of the site boundary unless these levels are exceeded by a factor of 10 er projected to continue for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or EPA Protective Action Guideline exposure levels are predicted to be exceeded at larger distances.

c. Loss of 2 of 3 fission product barriers with a potential loss of 3rd barrier, (e.g., loss of primary coolant boundary, clad failure and high potential for loss of containment).

EAL's

1. Failure of fuel cladding as evidenced by gap activity in reactor coolant (> 300 pCi/ gram I-131 dose equivalent) or presence of gap activity in primary containment atmosphere.

and Failure of primary coolant boundary as evidenced by:

high drywell pressure; or high drywell temperature; or failure of MSIV's to isolate; or safety relief valve stuck open; or t gap. activity in primary containment atmosphere and 0 l WP/kk -

. 1

Procedure A.2-101 Revision 6 Page _41 of 45 ATTACHMENT 2 (Cont'd.)

Guideline 28 (Cont'd.) ALL GUIDELINES - GENERAL EMERGENCY Potential loss of containment as evidenced by: .

containment temperature or pressure approaching design limits (281'F and 56 psig) and increasing; or loss of containment cooling; or Site Superintendent's opinion that loss of containment is likely.

i-

- NOTE 1: Failure of MSIV's to. isolate constitutes a loss of both primary coolant boundary and containment. When this is combined with .

cladding failure,-all three barriers have been lost.

NOTE 2: In situations of:

a) Small or large LOCA with failure of ECCS to perform, or b) Loss of requisite decay heat removal systems (RHR and other heat sinks) following shutdown,

. loss of containment should be judged to be likely.

2. Failure of fuel cladding (per guideline 6) and Failure of containment es evidenced by all containment penetrations required for isolation not valved off or closed; or Site Superin-tendent's opinion that containment has failed and Potential loss of primary coolant boundary as evidenced by reactor pressure near design limits and increasing or loss of ECCS.

3. Failure of containment as evidenced by all containment penetrations required for isolation not valved off or closed or Site Superin-tendent's ooinion and Failure of primary coolant boundary as evidenced by high drywell pressure or temperature or failure of MSIV's to isolate or stuck open safety relief valve l

and

Fotential for loss of cladding as evidenced by ECCS failure or reactor water level low and decreasing.

0 l

WP/kk -

, n - - - - - . ~ - , ~ , , , - -+ , -,,,_..y , , -

n-~a.-. --,.,,m--,-, .y, , , .-,- ,,-- m, e --, a ---,

. . + .

Procedure A.2-101 Revision 6 Page .42 of.45 .

ATTACHMENT 2 (Cont'd.)

GUIDELINE 28 (Cont'd.) ALL GUIDELINES - GENERAL EMERGENCY NOTE: Consider 2 mile precautionary evacuation. If more tfian fuel gap activity released, extend this to 5 miles downwind.

d. Loss of physical control of the plant.

NOTE: Consider 2 mile precautionary evacuation.

e. Other plant conditions exist, from whatever source, that make release of large amounts of radioactivity in a short time period possible, e.g., any core melt situation. See the example BWR sequences.

l Example BWR Sequences

1. Transient (e.g., loss of off-sita power) plus failure of requisite core shutdown systems (e.g., scram or standby liquid control system). Could lead to core melt in several hours with containment failure likely. More severe consequences if pump trip does not function.

2. Small or large LOCA's with failure of ECCS to perform, leading to core degradation or melt-in ninutes to hours. Loss of containment integrity may be imminent.

3. Small or large LOCA occurs and containment performance is unsuccessful -

affecting longer term success of the ECCS. Could lead to core degradation or melt in several hours without containment boundary.

4. Shutdown occurs but requisite decay heat removal systems (e.g., RHR) or non-safety systems heat removal means are rendered unavailable. Core degradation or melt could occur in about ten hours with subsequent containment failure.

5. Any major internal or external events (e.g., fires, earthquakes, substantially beyond design basis) which could cause massive common damage to plant systems resulting in any of the above.

O WP/kk -

- . . _ _ _ _ _ . . . . _ _ . _ _ _ _ _ _ _ _ _ - w

Procedure A.2-101  ;

Revision 6

, Page _43 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 29 OTHER PLANT CONDITIONS ,

UNUSUAL EVENT

l. Plant conditions exist that warrant increased awareness on the part of plant operating staff or State and/or local offsite authorities.

2. Plant conditions exist that require shutdown under technical specifi-cation requirements.

3. Plant conditions exist that involve other than normal controlled shutdown (e.g. cooldown rate exceeding technical specification limits or pipe cracking found during operation).

I ALERT Plant conditiont exist that warrant precautionary activation of TSC and place-ment of E0F and other key emergency personnel on standby.

I SITE AREA EMERGENCY Other plant conditions exist that warrant activation of emergency centers and monitoring teams or precautionary notification to nearsite public.

i G

WP/kk -

l.

f

- -. . - - . = - . . - . . . . ~,,_..-m..-- y- -- -.- # , . . . ~ ~ _ - . - . - , , - , , . . - . . . . . , - , - , . , ,, y-, . . . .

ProcedureA.2-lb1 Revision 6 Page 44 of 45 .

ATTACHMENT 2 (Cont'd.)

Guideline 30 ' MAJOR DAMAGE TO SPENT FUEL

-' ~

UNUSUAL EVENT Not applicable ALERT Fuel damage accident with release of radioactivity to containment.

EAL's

1. Dropping, bumping or otherwise rough handling of a spent bundle or individual fuel rods.

and

2. Fuel Pool Radiation Monitor Ch A or B exceeds 50 mR/hr (confirmed by annunciator 5-A-1 or 5-A-2).

SITE AREA Major damage to spent fuel in containment (e.g., large object damages fuel or water loss below fuel level). .

EAL's

1. a. Decrease in fuel pool level below 36'9" confirmed by LT-2767, Spent Fuel Pool Level Hi/Lo alarm .

or

b. Dropping of heavy object onto spent fuel confirmed by direct observation

and l

l

2. Fuel Pool Radiation Monitor Ch A or B exceeds 50 mR/hr.

(Confirmed by annunciator 5-A-1 or 5-A-2) l GENERAL As specified in Guideline 28.

l i- (/

l WP/kk -

.e .- .

Procedure A.2-101 Revision 6

, Page 45 of 45 .

ATTACHMENT 3 ,

Form 5790-101-1 Rev. 1, 10/20/81- -

( Page 1 of 1 --

Example of EMERGENCY CLASSIFICATION CHECKLIST (For Use With Procedere A.2-101)

1. Initiating Condition:

ED Initials Time Date

2. Attachment 1 directs use of Guideline !;uz.ber(s): .

ED Initials Time Date

3. Attachment 2 classification:

Declared

ED Initials Time Date

4. Implemented Procedure A.2- .

ED Initials Time Date NOTE: If reclassification becomes necessary, start a new. Emergency Classification Checklist.

NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.

4 WP/kk

A Procedure A.2-105 Revision 4 Page 1 of 18. -

Op. Com. Rev. Req'd. Ves- X No Q.A. Review Reg'd. Yes No X ALARA Review Req'd. Yes No x GENERAL EMERGENCY

._ A.2-105 Prepared by: Lbuhc r ALARA Review: Revision 0 Date 3/29/81 Reviewed by: GdN/adc < -- Q. A. Review: Revision 0 Date 3/29/81 Operations Committee Final Review: Meeting Number /fLEdo Date Cf / C." /?1 Approved by: N Date Y /47 /D Op. Com. Results Review: Not Required Mtg. # 950 Date 3/27/81 PURPOSE This procedure describes the actions to be taken in the event that a General Emergency has been declared at the Monticello Nuclear Generating Plant. This procedure also designates the prescribed pre planned response actions necessary to contend with the emergency condition and references applicable procedures that describe the necessary supplementary actions.

The Emergency Director (Site Superintendent until properly relieved by a l designated alternate) is responsible for the completion of the prescribed actions in this procedure. The Emergency Director may delegate responsibility for performance of the prescribed tasks available qualified NSP personnel, except where otherwise specified in this procedure.

CONDITIONS AND PREREQUISITES A. A General Emergency has been declared based on the occurrence of events which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Events classified as General Emergencies are described in A.2-101 (Classification of Emergencies).

OR B. A lesser emergency had been declared and emergency measures are being performed; and on the basis of subsequent information or upon a deter-ioration in plant conditions, the emergency has been reclassified as a

( General Emergency.

l l PRECAUTIONS A. Continued surveillance and assessment of plant conditions are necessary to ensure that the emergency classification is revised appropriately as conditions change or more definitive information is obtained.

I G

l

~

WP/kk

Procedure A.2-105 Revision 4 Page 2 of 18. .

B. -The General Emergency classification includes actual or imminent events for which off-site protective actions will be needed. In consideration of the lead time necessary to implement off-site protective actions, notifi-cation to off-site authorities must be made as soon as possible following the initiating event and immediately after declaration of General Emergency.

ORGANIZATION A. Overall Responsibility - Emergency Director (Site Superintendent, until relieved)

8. In Charge Control Room - Site Superintendent Technical Support Center - Emergency Director Emergency Operations Facility - Emergency Manager

• Assembly Point - Assembly Point Coordinator C. Assistance

• Technical Support Center - Plant Management, Technical & Enginearing Support Control Room - Lead Plant Equipment & Reactor Operator; Shift Technical Advisor

When assigned, & Shift Emergency Communicator

• After augmentation RESPONSIBILITIES A. Emergency Director (Site Superintendent, until relieved) l l 1. Ieplement appropriate Emergency Plan Implementing Procedures.

2. Ensure that appropriate Emergency Operating Procedures are implemented.

t

3. Determine what support is required and assign the Shift Emergency Communicator to make necessary calls.

4. Implement any assessment, protective or corrective actions necessary on-site l and make recommendations for any necessary off-site protective actions. .

5. Respond to situation with the objective of returning plant to normal status (or cold shutdown if this is determir.ed to be necessary). ,

6. Watch the situation closely to determine when the threat to plant safety has passed.

7. Recommend reduction to a lower class or terminate emergency condition.

NOTE: Emergency Director responsibilities that may NOT be delegated include:

a. Decision to notify off-site emergency management agencies.

b. Making protective action recommendations as necessary " to off-site emergency management agencies.

~

WP/kk

, , ,.-- , - - . n-, - - . - - - ., .., . . . - - ,

Procedure A.2-105 Revision 4 Page 3 of .18".

c. Classification of Emergency Event.

d. Determining the necessity for on-site evacuation. >

e; Authorization for emergency workers to exceed normal radiation expdiure limits.

B. Site Superintendent (Shift Supervisor, if Superintendent'is not availabl'e)

1. Implement appropriate Emergency Operating Procedures.

2.- Assist the Emergency Director as requested.

C. Control RooY Personnel

'1. Assist the Site Superintendent as requested.  !<

2. Monitor control room instruments continually for any sign of increasing radiation, system degradation or any new developments.

Notify the Site Superintendent immediately in any of these cases, j D. Shift Technical Advisor .

Provide the Emergency Director and the Site Superintendent with technical 3 advice.

E. Shift Emergency Communicator

1. Report to the Control Room.

2. Notify off-site personnel, Federal, State and Local Agencies.

3. Coordinate communications from the Emergency Director as equired.

F. Shift Radiation Protection Specialists l

1. Report to Access Control. Be prepared to assist the Site Superin-tendent with any immediate matters as requested.

l 2. Be prepared to implement procedures which may be required if the situation l

desrades.-

PROCEDURE [

I STEP 1: As necessary, contact the Shift Technical Advisor and the Shift Emergency Communicator using the following numbers:

STA: gQ- py ,

SEC: --

m r4 m.

I Initiate General Emergency Checklist Form 5790-105-1 Qttachment1).

1

~

~

WP/kk i

r

, 1

_ - . _ - - - . - - _ _ _ . . - - - - - - - - - ~-

l Procedure A.2-105 Revision 4 -

Page 4 of ,18 ,

STEP 2: Using the public address system, announce or have announced, a message advising plant personnel of the situation.

For example:

" ATTENTION ALL PLANT PERSONNEL: A GENERAL -

EMERGENCY HAS BEEN DECLARE 0".

- If appropriate add:

"ALL MEMBERS OF THE EMERGENCY ORGANIZATION REPORT TO YOUR EMERGENCY DUTY STATIONS.

Repeat message slowly.

NOTE 1: During drills or tests, the message will begin and end with the phrase, "THIS IS A DRILL" or "THIS IS A TEST".

NOTE 2_;, Messages may be modified to give more information or to fit the situation. ,

STEP 3 Ensure that appropriate Abnormal Operating Procedures have been implemented.

i STEP 4 Ensure implementation of Procedure A.2-106, Activation of Technical Support Center, and Procedure A.2-107, Activation of Operational Support Center.

STEP 5 Initiate a plant evacuation (if it has not been executed) unless extreme circumstances make it inadvisable. Implement procedure h

A.2-301, Emergency Evacuation.

STEP 6: Until the REC position is activated, ensure that onsite and inplant radiation surveys are conducted as necessary and that appropriate radiochemistry samples are taken as necessary.

STEP 7: SEE NOTE 2 BELOW. If the initial notifications have not been made

. under a previous procedure, direct the SEC to compose Emergency Notification Report, Form 5790-102-2 (Attachment 2) and submit for Emergency Director approval, transmit initial notification using Emergency Call List-General Emergency, Form 5790-104-4 (Attachment 4).

Ensure that recommendations include activation of public notification system and sheltering out to 2 miles in all directions and 5 miles downwind (45* to 90* sector).

STEP 8: SEE NOTE 2 BELOW. If the initial notifications have been made and the emergency is being reclassified, direct the SEC to compose Emergency Classification Change, Form 5790-102-7 (Attachment 7) and submit for

,, Emergency Director approval, transmit classification change using Emergency Call List-General Emergency Form 5790-104-4 (Attachment 4).

Ensure that a recommendation for activation of public notification system and sheltering out to 2 miles in all directions and 5 miles downwind (45 to 90* sector) is made. ,

NOTE 1: Communications should be per Procedure A.2.-501, Communications During an Emergency.

~

~

kP/kk

m. .

Procedure A.2-105 Revision 4 Page 5 of,12 ,

NOTE 2: When the EOF is fully activated, the plant will be relieved of the responsibility for offsite notifications (STEPS 7 and 8).

STEP 9: If federal, state or local off-site support is required, direct the

~

Shift Ecergency Communicator to request assistance. Use Form 5790-102-6 (Attachment 5) to compile list.

STEP 10: Augment on-shift personnel. As required, direct the Shift Emergency Communicator to contact appropriate individuals or agencies as required from the Monticello Emergency Augmentation List, form 5790-102-5.

STEP 11: Direct the REC to imolement the following procedures:

a. A.2-201 (On-3fte Monitoring During an Emergency)

b. A.2-202 (Off-Site Monitoring During an Emergency)

NOTE: Off-site monitoring is the responsibility of the on-site emergency organization only until the EOF attains the capability to perform this task.

c. A.2-204 (Off-site Protective Action Reccmmendations).

Consider implementation of strict plant status controls in accordance with 4 ACD-4.7. If it is a radiological emergency, implement high radiatic,n area controls.

STEP 12: Consider augmentation of Radiation Protection Staff. If appropriate call Prairie Island Plant 612/388-1121 and have the Shift Supervisor initiate Procedure F3-22 (Prairie Island Radiation Protection Group F.esponse to Monticello Emergency). If additional contract health physics support is required, contact Institute for Resource Management Inc. C-LfiEt STEP 13: Direct the REC (or SEC until the REC is activated) to preoare ceriodic

~

followup information messages, using form 5790-102-3, EMERGENCY NOTI-FICATION FOLLOWUP MESSAGE. Review and approve the message content and direct the SEC to transmit the information to the State E0C and the two county E0C's.

NOTE 1: The minimum frequency of followup messages should be every 30 minutes.

NOTE 2: As specified on the message form, protecive action recommendations should not be given to local or county officials once the State EOC is activated.

NOTE 3: When the EOF becomes operational, tne followup information messages shall be forwarded to the EOF for transmission to offsite officials.

T NOTE 4: Senior technical and management personnel on the plant staff

,-f should be made available for consultation .with NRC and State personnel on a periodic basis. '"

~

WP/kk y

. i.. .

, Procedure A.2-105 Revision 4 Page 6 of 18-STEP 14: Based upon assessment of plant conditions either: gj

a. Recommend reduction in class, or

b. CTose-out.,the General Emergency, .

per Procedure A.2-101 (Classification of Emergencies).

STEP 15,: Should reclassification of the emergency be necessary, initiate a new procedure (A.2-102, 103 or 105).

STEP 16: In the event of a close-out, ensure that all appropriate agencies and individuals are promptly notified. The message snould include a brief summary of the event, the fact that it has been terminated, whether or not a recovery will be initiated, and any organizational changes.

REFERENCES

1. Monticello Nuclear Generating Plant Emergency Plan

2. Monticello Nuclear Generating Plant Operations Manual

3. NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" ATTACHMENTS h

1. Example of Site Area Emergency Checklist

2. Example of Emergency Notification Report Form

3. Example of Emergency Notification Followup Message

4. Example of Emergency Call List - General Emergency

5. Example of Secondary Notification List

6. Example of Emergency Classification Change l

~

~

WP/kk

Procedure A.2-105 Revision 4 Page 7 of 18. .

ATTACHMENT 1 Form 5790-105-1 Revision 3, 03/01/82 Page 1 of 1 Example of ~

GENERAL EMERGENCY CHECKLIST (For Use With Procedure A.2-105)

1. STA and SEC summoned.

ED Initial Time Date

2. Announced emergency classification.

ED Initial Time Date

3. Abnormal Operating Procedures implemented.

ED Initial Time Date

4. TSC and OSC activated.

ED Initial Time Date

5. Plant evacuation initiated.

ED Initial Time Date

6. Onsite and inplant rad surveys -

chemistry samples directed as n ry. .

E al Time Date

7. Offsite notifications di.

itial Time Date

8. Directed SEC to re (Form 5790-102-6 _

ED Initial Time Date

9. Directed SEC to contact P f as required for Shift Augmentation 0-102-5.

ED Initial Time Date

10. Assessment: impleme d the following procedures:

A.2-201 (On-Site Monitoring)

A.2-202 (Off-Site Monitoring) _

A.2-204 (Off-Site Pratective Actions ED Initials Time Date

11. Rad. Prot. Staff augmentation implemented.

ED Initial Time Date

12. Followup notification initiated.

ED Initial Time Date

13. (Closed Out/down grade to a lower class) based upon Procedure A.2-101.

ED Initial Time Date NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for emergency records.

0 WP/kk

Procedure A.2-105 '

Revision 4 Page 8 of 13 ,

l ATTACHMENT 2 l Form 5790-102-2 Revision 3, 02/19/82 Page 1 of 1 Example of

- EMERGENCY NOTIFICATION REPORT

• Verify that the organization / person called is correct prior to relaying emergency information.

THIS IS (Name), (Title) AT THE MONTICELLO NUCLEAR GENERATING PLANT.

WE HAVE DECtARED A(N) AT HOURS.

(Emergency Class) (Time)

Pick one of the following, based on information from Control Room Personnel or Shift Supervisor:

( ) WE HAVE NOT HAD A RADI0 ACTIVE RELEASE.

( ) WE HAVE RAU A(N) quid or Airborne) RADIOACTIVE RELEASE.

ATMOSPHERIC CONDITIONS AT THE PRESENT S E AS FOLLOWS:

(Speed) MPH.

WIND DIRECTION IS FROM THE ) (Dire n) AT THE AFFECTED SECTOR ( & ,

1l) by letter designation as by map in TSC.)

Protective Action Reco (

THE PROTECTIVE ACTION R ENDED A TIME IS (From Emer. Dir./ Procedure A.2-204):

( ) None 9v

( ) SHELTER OUT T0 a ance) MILES

( ) EVACUATE OUT T0 istance) MILES

( ) ACTIVATE PUBLIC XB37 a IFICATION SYSTEM

( ) CLOSE MINNEAPOLIS AND ST. PAUL WATER INTAKES Give a brief description of the emergency.

PLEASE RELAY THIS INFORMATION TO YOUR EMERGENCY ORGANIZATION PERSONNEL.

Emergency Director Approval (Name/Date)

Emergency Communicator (Name/Date) l NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.

• Complete as much of the form as information available or time allows. All blanks need not be filled out. i 0

WP/kk -

Procedure A.2-105 Revision 4 <

Page 9 of 18.

ATTACHMENT 3 Form 5790-102-3 Revision 5, 05/17/83 '

Page 1 of 2

~

Example of (

EMERGENCY NOTIFICATION FOLLOWUP MESSAGE

• Date

1. Location of incident: Monticello

2. Class of emergency:

3. Type of release: ( ) airborne

( ) actual ( ) waterborne

( ) projected ( ) surface spill

4. Current release data:

Time: hour Release rate: # sec Height of release: round level 00 meters (stack)

Relative quantity:

sk M s pCi/sec L' s" pCi/sec a culates pCi/sec Estimated quantity o ive material released or being released curies

5. Meteorological Co ions: Wind Velocity mph Wind Direction (from): degrees Temperature "C M.mospheric Stability Class Form of Precipitation

6. Release is expected to continue for hours.

7. Dose Projections based on a release rate of ,_ pCi/sec at hours am/pm.

Projected Whole Body Thyroid Sectors Affectea dose rate at: S.B. mrem /hr mrem /hr 2 miles mrem /hr mrem /hr 5 miles mrem /hr mrem /hr 10 miles mrem /hr mrem /hr Projected S.B - mrem mrem integrated 2 miles mrem _ mrem dose at: 5 miles mrem mrem 10 miles mrem mrem Complete as much of the form as information availability an.d time allows.

All blanks need not be completed. '"

WP/kk -

Procedure A.2-105 Revision 4 Page 10 of 18.. .

ATTACHMENT 3 (Cont'd.)

Form 5790-102-3 Revision 5, 05/17/83 Page 2 of 2 Survey Results

8. -

SURVEY TIME POINT READING 4

2

9. Estimate of any surface radioacthh tamination: dpm/100 cm

10. Chemical and physical form r@6ased mate

11. Emergency response ac  : A_

_A A \\\W AF \W A\U

12. For liquid relea the Ri ate release volume, release activity and estimated time for cor on to reach public water:

13. See the CAUTION. R d emergency actions, including protective actions:

CAi! TION: Do NOT relay this information to local or county officials once the State E0C is activated.

14. Request for any needed support by off-site organizations:

15. Progncais for worsening or termination of event based on plant information:

Emergency Director (or Designee)

NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for emergency records. ,

WP/kk

Procedure A.2-105 l Revision 4 I Page 11 of 18 .

l ATTACHMENT 4 Form 5790-104-4 Revision 8, 04/15/83 Page 1 of 5 -

Example of EMERGENCY CALL j.IST - ALERT / SITE AREA / GENERAL NOTE 1: The Shift Emergency Communicator shall make notifications to the individuals and organizations listec on the appropriate Emergency Call List.

NOTE 2: For those notifications made by telephone, make the call as follows:

a. Contact each organizati individual using the contact informa-tion listed in the at for the appropriate emergency class.

b. When the party an r read the the notification.

c. Note the na ivid acted and the time of the contact.

d. Procee e next the call-list.

e. If a party can n ntacted in two attempts, bypass that party and proc c

• the list. After the other notifications are complete empt to contact any bypassed parties. If a party stil ,ot be reached, consider other msans such as dispatching courier, relay through another party or similar actions.

. f. If the parties call back for further information, note the time and the name of the individuals.

g. If a party not specified on the call list requests information, refer the party to the NSP Communications Department or to the local emergency services organization in his/her community, as appropriate.

NOTE 3: Some of the below listed individuals may be on site when the emergency is declared. They will not require additional notification if it is known that they are at their designated emergency duty stations.

E.

st WP/kk -

Procedure A.2-105 Revision 4 Page12of-16; -

ATTACHMENT 4 (Cont'd.) L  ;

Form 5790-104-4 W Revision 8, 04/15/83 ~

Page 2 of 5 .

EMERGENCV ' CALL LIST - ALE 9T/ SITE AREA / GENERAL (Cont'd. )

NOTIFICATIONS

1. Nati.fy the.Eianesota Division of Emergency Services. The telephi e number is >2 L*": 121-night or day (ask for the Duty Officer). Request Emergency Services to notify the Capartment of Health.

Contact Time Initial Notification Verification Person SEC Initials SEC Initials NOTE 1: This notification sh made within 15 minutes of declaration of emergency class NOTE 2: This call will, rified vi L e : E D,ine. If no verifica-tion within co e State again.

2. Notify the local itie one as follows:

t Natificationh

a. Wright Coun Before EOC acti notify:

Wright eriff 3.3 CL:.4 20 (or)

(oflELETICTime SEC Initials After EOC activation, notify:

. Wright County EOC --y.ELETC Time SEC Initials

b. Sherburne County: -

, Before ECC activation, notify:

Sherburne County Sheriff -OZLEE8me i SEC Initials Af ter EOC activation, notify:

Sherburne County EOC --- DELZT1'Ume SEC Initials NOTE: These notifications shall be made within 15 minutes of declaration of emergency class.

ananamanananaamanzanamanamanaamanamanawaxa***xxxxxe**xa**xanan**=anxxa NOTE WELL: IF THIS CHECKLIST HAS PREVIOUSLY BEEN USED TO MAKE * '

• NOTITlTATIONS, THE FOLLOWING STEPS NEED NOT BE

• REPEATED FOR FURTHER ESCALATIONS. .

xa*****mannaxxxxx*=xx-naxxxxxxx*maxx*xxxxxxxxxxxxx*=waxxxx*wx*x****xxx

~

WP/kK

Procedure A.2-105 Revision 4 Page 13 of-18 ATTACHMENf 4 (Cont'd. )

Form 5790-104-4 Revision 8, 04/15/83 Page 3 of 5 ,

EMERGENCY' CALL LIST - ALERT / SITE AREA / GENERAL (Cont'd.)

3. Notify the Local Civil Defense.

Working Nights /

Hours Holidays Monticello Civil Defense g,j: g7p CZI 2TC SEC Initiais

4. See the NOTE.

Using the telephone pager system, n ify the group of individuals listed below by dialingCELETEcalm m nsmit the following message entire group.

"ATTENTICt: EMERGENCY P ORGANI PLEASE REPORT TO THE PLANT IttiEDIATELY. , PLEAS TO THE PLANT IMMEDIATELY."

If anyone calls into t or clarification, calmly indicate that an emergency hat the emergency organization should report t nt i .

Persons Contacted ith Pace _ Call:

Emergency Director and te Radiological Emergen inator and Alternate Operations Group Lea Maintenance Group Lead and Alternate Engineering Group Leader and Alternate

. Support Group Leader and Alternate Security Group Leader and Alternate EOF Coordinator NOTE: This step not required if the entire Emergency Response Organization has already been activated.

5. See the NOTE.

Using the tone-activated radios, notify the remainder of the ERO, local officials and near-site resider.ts according to the following steps:

a. Insert the prerecorded tape designated 'ERO Callout' into the TRANSMITTING UNIT.

b. Set the selector switch on the TRANSMITTING UNIT to ' ANSWER'

c. On the CONTROL UNIT, turn the key in the ' TRANSMIT ENA,BLE' switch.

The red 'XMIT' lamp should light.

~

WP/kk m

Procedure A.2-105 Revision 4 Page 14 of-18 .

ATTACHMENT 4 (Cont'd.) { j Form 5790-104-4 V Revision 8, 04/15/83 Page 4 of 5 EMERGENCY CALL LIST - ALERT / SITE AREA / GENERAL (Cont'd.)

d. Enter 06 on the ENCODER UNIT and press 'P'. (The tape will be trans-mitted 3 times autcmatically.) If the system is working proper?y, the tone-activated unit in the TSC will be activ.ated.

e. When the transmissions have ended, remove the tape and insert the tape designated ' Local Notifications' into the TRANSMITTING UNIT.

f. Enter 01 on the ENCODER UNIT and press 'P'. When the series of tont.r stops enter 04 and press 'P'.

g. The tape will be transmitted ree times. When the transmissions have ended, turn the key in the " MIT ENABLE' switch. The green ' TEST' lamp shall light.

h. Remove the message ca t from the ITTING UNIT and insert it into the ANSWERIN ERO Personnel Wi,th ts __

13 6

SEC's Site Super 1 5

idents 8 EOF Coordinators 16 SR0's h

3 Maintenance upervis 17 Rad. Prot./ Chem. Personnel 2 Electricians 4 I&CS Personnel 12 STA's NOTE: This step no required if the Emergency Response Organization (ER0) and the local officials have aleeady been notified.

6. Notify the System Dispatcher using the hotlThe (in the Control Room), the low-band radio link (TSC and Control Room), or normal telephone line((II._37ECnight or day).

SEC Initiais

7. Notify the site NRC Resident Inspector (Extension 1254):

DELETID ,

SEC Initials

8. Notify the NRC Emergency Response Center via the ENS hotline. Use Form 3195 to assemble information which will be requested by NRC. Determine from the NRC whether or not continuous manning is required.

SEC Initiais 0

WP/kk

Procedure A.2-105 Revision 4 Page 15 of -18, ATTACHMENT 4 (Cont'd.)

Form 5790-104-4 Revision 8, 04/15/83 Page 5 of 5 .,.

EMERGENCY CALL LIST - ALERT / SITE AREA / GENERAL (Cont'd.)

NOTE 1: If the ENS is out of order, attempt con. tact in the following order until notification is made:

(a) Commercial Telephone System to NRC Operations Center (via Bethesda Central Office) 202/951-0550 (b) Commercial Telephone System to NRC Operations Center (via Silver Springs tral Office) 301/427-4056 (c) Health Physics N - (HPN) RC Operations Center

• 22 (Touch-Tone c2 (Rota 1)

(d) Commercial ne Sys RC Operator (via Bethesda Central 49 NOTE 2: Notificati e -_ one hour of event declaration, as requi 7 4 ACDM ' V

9. Notify INP0 by co , cial tel at DELE E;.

(Initial notification only Sec. Initials

10. Notify ANI by commerci hone at~ et ---- n

~ ~ '

(Initial notification SEC Initials

11. Inform the Emergency Director of the completion of the notifications. SEC Initials l Completed: Shift Emerg. Communicator Date Time Reviewed by: Emergency Director l

l NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for I Emergency Records.

?

L WP/kk 1

Procedure A.2-105 Revision 4 Page 16 of 18',

Form 5790-102-6 Revision 8, 09/13/83 Page 1 of 2

('

ATTACHMENT 5

~~~ .

Example of SECONDARY NOTIFICATION LIST Backup Agencies That May Be Notified If Necessary

( ) 1. Chicago Operations Office of DOE Radiological Assistance Program

( ) 2. Area Civil Defense Groups a) Region VI Commander (St. Cloud) b) Wright County c) Sherburne County

( ) 3. State Highway Patrol a) St. Cloud b) Golden Valley Emergency h c) St. Paul o al Oper Emergency Radio

( ) 4. Highway Department i

( ) 5. Monticello Police D tment

( ) 6. Monticello Fire Department l ( ) 7. Burlington Northern Railroad

(Chief Dispatcher)

( ) 8. Minneapolis Water Department

( ) 9. St. Paul Water Department

( ) 10. Big Lake-Monticello Ambulance Service l ( ) 11. Monticello-Big Lake Community Hospital l

l  !

0

~

~

WP/kk

Procedure A.2-105 Revision 4 l Page 17 of_18 .

l ATTACHMENT 5 (Cont'd.)

' Form 5790-102-6 Revision 8, 09/13/33 '

Page 2 of 2 -

Example of -

SECONDARY NOTIFICATION LIST (Cont'd.)

( ) 12. EPA Monticello Field Station

( ) 13. Big Oaks Park (During Camping Season)

( ) 14. Minnesota Pollution Control Agency

( ) 15. Northern States Power

. N.W. Division

( ) 16. General Electric

1. A##I #

/

WP/kk -

Procedure A.2-105 Revision 4 Page 18 of 18 , ,

. - i Form 5790-102-7 1 Revision 3, 01/15/83 ATTACHMENT 6 I Page 1 of 1 l Example of EMERGENCY CLASSIFICATION CHANGE Verify that the organization / person called is correct prior to relaying emergency information.

THIS IS , AT THE (Name) (Title)

MONTICELLO NUCLEAR GENERATING PLANT.

WE HAVE RE-CLASSIFIED THE EVENT AND ( ) Escalated

( ) Down graded The Event May Be Terminated T0 a(N)

( ) Notificati Unusual

) ',

( ) 1 Emerg at urs.

(Time)

METEOROLOGICAL CONDITION PRESENT TIME ARE AS FOLLOWS:

Wind Direction is f the AT MPH (Direction)

Form of Precipitation (If applicable)

THE AFFECTED SECTOR (S) IS(ARE)

(List sector (s) by letter designation)

Give a brief description of the emergency:

PLEASE REL4Y THIS INFORMATION TO YOUR EMERGENCY ORGANIZATION PERSONNEL.

Emergency Director / Manager Approval (Name/Date)

Emergency Communicator (Name/Date) 0 WP/kk -

..c.

Procedure A.2-702 Revision 3

.. Page 1 of 5 ~

Op. Com. Rev. Reg'd. Yes J .No Q.A. Review Reg'd. Yes No X ALARA Review Reg'd. Yes No X RESPONSE TO AN EMERGENCY AT PRAIRIE' ISLAND A.2-702 y.

Preparedbyi2L9fuYO ALARA Review: Revision 0 Date 03/29/81 Reviewed by: 6 dll/ M .) ~ _. Q.A. Review: Revision 0 Date 03/29/81 Operations Committee Final Review: Meeting Number /ff5 oate ci /is/ss Approved by: JJ C0~DO oate o //c/?3 Op. Com. Results Review: Not kequired Mtg. # 950 Date 03/27/81 PURPOSE The purpose of this procedure is to provide instructions for the Monticello Nuclear Generating Plant Radiation Protection Group when called upon to respond to an emergency at Prairie Island. Also included is a list of the equipment required and a " priority list" of qualified Radiation Protection Specialists and their

! home telephone numbers.

CONDITIONS AND PRERE0VISITES A declared emergency exists at the Prairie Island site and conditions have made necessary a request for health physics support.

DISCUSSION

-In an emergency situation which includes a release of radioactive materials to the environs, the process of off-site and environmental monitoring is limited by the personnel and equipment available for sampling, and to a lesser degree, i by the facilities available for analysis. In an effort to enhance MNGP's

! capacity to handle this type of emergency, MNGP has made a reciprocal agreement with Prairie Island whereby each plant would supply personnel, equipment and analysis facilities to the other upon request.

PERSONNEL REQUIRED Emergency Response Team i

Supt., Radiation Protection or designee (Radiation Protection Support Supervisor)

Four (4) persons qualified in Radiation Protection Standby Emergency Response Team Supt. , Radiation Protection or designee (Radiation Protection Support Supervisor)

Four (4) persons qualified in Radiation Protection c WP/kk -

r-. . .-r-- c , - , - - , =- - - - -

-g.

1 Procedure A.2-702 Revision 3 Page 2 of 5.,, ,

PROCEDURE STEP 1 Upon notification that Prairie Island has requested assistance, the Supt., Raoiation Protection or designee will organize an Emergency Response Team which will-travel to Prairie Island immediately. The team shall consist of five people, four Radiation Protection Specia-lists and one person qualified as the Radiation Protection Support Supervisor.

NOTE 1: Refer to the " List of Qualified Radiation Protection Specialists / Support Supervisors", Attachment 1.

NOTE 2: A second Emergency Response Team consisting of four Specialists and one supervisor should be organized and standing by at the MNGP site to be dispatched if further assistance is requested.

-STEP 2 The response team members should assemble at the MNGP site to pick up vehicle (s) and equipment.

NOTE 3: Other arrangements may be made if necessary as long as all equipment and personnel arrive at the Prairie Island EOF with a minimum of delay.

STEP 3 Proceed to the Monticello EOF and obtain the Emergency Survey Kits and equipment per " Prairie Island Emergency Support Equipment List",

Attachment 2.

NOTE 4: If the Emergency Response Team is requested during off-normal hours obtain the keys for the Monticello E0F from the guard house.

NOTE 5: Prior to departing the Monticello EOF, response check all survey instruments and verify operability of the portable radios.

l STEP 4 Proceed to the Prairie Island EOF.

i

! NOTE 6: Directions to Prairie Island are as fcilows:

i Highway 194 to I694, I694 to I494, 1494 tc 61, 61 south to 316 (in Hastings), left on l 316 to 61, left on 61 to 18 (NSP-P.I. sign at this intersection), left on 18 to P.I.

l '

l Detailed maps are included in the Emergency Kits.

STEP 5 When approaching the boundary of the Prairie Island 10 mile EPZ, attempt to contact the Prairie Island EOF using the portable radio.

Identify yourself as the Monticello Survey Team.

G WP/kk -

l-

-.*59 Procedure A.2-702 Revision 3

.- Page 3 of 4

.' STEP 6 If determined from the initial radio contact with the Prairie Island EOF that the plume may be encountered while enroute, conduct a search for the plume, in accordance with EPIP 1.1.10, and proceed directly to the EOF.

NOTE 7: If the EOF has NOT been activated or does not r'espond,

• contact the Prairie Island Radiological Emergency Coordinator for further instructions.

STEP 7 Upon arrival at the Prairie Island EOF contact the ' Emergency Manager <

or the Radiological Emergency Coordinator fo'r further instructions.

STEP 8 Perform the required offsite surveys as requested by the Emergency Manager in accordance with EPIP 1.1.10. "Offsite Surveys" :nd EPIP 1.1.11, " Accident Assessment".

NOTE 8: Analysis of field samples should be performed in the Prairie Island EOF Count Room by P.I. Radiation Protection '

Specialists. If this facility becomes unavailable make arrangements to transport the samples to the P.I. Count Room (if available) or to Monticello.

REFERENCES

1. Prairie Island Nuclear Generating Plant Emergency Plan and Implementing Procedures ATTACHMENTS

1. List of Qualified Radiation Protectio'n Specialists / Support Supervisors

2. Prairie Island Emergency Support Equipment List t,

WP/kk -

,-w- -,m._ ,. v e,-

e.

Procedure A.2-702 Revision 3 Page 4 of 4 ' ,

ATTACHMENT 1 QUALIFIED RADIATION PROTECTION SPECIALISTS ne** ME9...._____..______. __________._

s- 9E'.J 5 W W

_._____._....____..__..__..__aw' ea w etv __________________...___.____

.WC-e3s  ;

________________..... e 1___.. Q :: ,la .n.. sa-*

4 re-D c.. ca d .. _________._... ___________

~ -

g39 D _r,,.,, igg ,

L . __.... __..________..._______..

~gg3 saw g QE' ::.; .= eO [_______._...________________ , , , , gen

_________________________ 6 9 :u.* =~"

n.,:1 w

.M. _e_s,y....

QUALIFIED RADIATION PROTECTION SUPPORT SUPERVISORS e-C m-. - ,2:, ..._____. _________________. Dc . . _. . . .;, ,,,, ; . .. ;

...en. as__________es.....e. .an._____.

9

.em-as___..e...._em......48....49

$2

~

~

WP/kk

, o. ' . o, Procedura A.2-702 Revision 3

, , , . - Page 5 of 5. .

ATTACHMENT 2 PRAIRIE ISLAND EMERGENCY SUPPORT EQUIPMENT LIST EQUIPMENT LOCATED AT THE MNGP SITE Personnel TLD's and Direct Reading Dosimeters Vehicle (s) for Offsite Monitoring Purposes EQUIPMENT LOCATED AT THE MONTICELLO E0F Three (3) Emergency Team Kits (including Duffel Bags)

Four (4) Portable Radios with Radio Boosters and Magnetic Antennas NOTE: If the Response Team is requested during off-normal hours, obtain the keys for the E0F from the Guard House.

NOTE: Response check all survey instruments and verify the operability of the portable radios prior to leaving the E0F.

l O

WP/kk -

l '

._ . -. . . _ . . _