ML20079L662

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure EPIP 1.1 Re Initial Classification,Epip 1.3 Re Estimation of Source Term & EPIP 1.4 Re Radiological Dose Evaluation

ML20079L662
Person / Time
Site:	Point Beach
Issue date:	11/11/1983
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20079L618	List: ML20079L655 ML20079L662
References
PROC-831111-01, NUDOCS 8401260262
Download: ML20079L662 (112)

Text

e -

q

+wo 11-11-83 A

fS).

W TABLE OF CONTENIS, Revision Date 1.0- CLASSIFICATION & ASSESSMENT '

1.1 Initial Classification . . . . . . . . . . . 6 11-G4-83 i 1.2 Plant Status .. .............. 1 07-01-83 1.3 Estimation of Source Tern. . . . . . . . 8 11-04-83 1.4 Radiological Dose Evaluation . . . . . . . 9 11-04-83 1.5 Protective Action Evaluation . . . . . . . . 5 11-04-83 1.6 Radioiodine Blocking & Thyrcid Exposure Accounting . .......... . . . . 2 09-09-83 1.7 Evaluation of Core Damage . . . . . . . . . . 3 11-04-83 1.8 Emergency Off-Site Dose Estimations . . . . 4 08-26-83 2.0- UNUSUAL EVENT IMPLEMENTING PROCEDURES 2.1 Unusual Event - Immediate Actions . . . . . . 2 09-09-83 2.2 Unusual Event - Plant and Company Personnel Notification ............. . . 2 09-09-83

, ~g 2.3 Unusual Event - Off-Site Agency Notification 4 09-09-83 i )

- U 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Immediate Actions . . . . . . . . . . 3 09-09-83 3.2 Alert - Plant & Company Personnel Notification ........... . . . 2 09-09 3.3 Alert - Off-Site Agency :fotification . . . . 4 11-04-83 4.0 SITE EMERGENCY -IMPLEMENTING PROCEDURES 4.1 Site Emergency - Imme'iate d Actions . . . . . 3 09-09-83 4.2 _ Site Emergency - Plant & Company Personnel Notification .. . . . . . . . . . . . . 2 09-09-83 4.3 Site Emergency - Off-Site Agency Notification 2 11-04-83

-5.0 GENERAL EMERGENC'I - IMPLEMENTING PROCEDURES 5.1 General Emergency - Immediate Actions . . . 3 09-09-83

[ 5.2 General Emergency - Plant & Company Personnel Notification . . . . . . . . 2 09-09-83 5.3 General Emergency - Off-Site Agency Notification' . . . . . . . . . . . . . 2 11-04-83

'6.0' EVACUATION

[N 6.1 Limited Plant Evacuation . . . . . . 3 09-09-83

( , ). 6.2 Plant Evacuation ... . . . . . . . . 3 09-09-83 8401260262 840119 FPDR AD(}CK 05{N)0264 .

pgg ,

Page 2

-t

/'"*N . s Revision Date

.6.3- Exclusion Area Evacuation . . . . . . . . . . 2 09-09-83 6 .' 4 -Energy Information Center Evacuation . . . . 'O 03-31-81 6.5 TSC & OSC Activation - . . . . . . . . . . . . 3 09-09-83 6.6 Plant' Evacuation for Personnel Using North Gate . . . . . . . . . . . . . . . . . . . 0 08-26-83 7.0 CHEMISTRY-& HEALTH PHYSICS RESPOMSE & PREPAREDNESS 7.1 Internal' Chem & HP Group Personnel Notification /

Initial Response 7.i.. Chem & HP Group Personnel Notification ,,

& Initial Response when Chem & HP .

Personnel 'are On-Site . . . . . . . 3 09-09-83 7.1.2 Chem & HP Group Personnel Notification

& Initial Response when Chem & HP Personnel are'Off-Site . . . . . . . 1 03-17-82 7.1.3 HP Frotective Actions by Operations

. Personnel Prior to Arrival of Chem

('S & HP Group Personnel . . . . . . . . 1 05-15-81 1

\ /

7.2 Health Physics Facility Activation 7.2.1 Activation of HP Facilities at Site Boundary Control Center . . . . . 3 09-09-83 7.2.2 . Activation of HP Facilities at operations Support Center . . . . 3 08-26-33 7.2.3 DELETED 7.2.4- Health Physics Communications . . . 3 09-09-83 7.2.5 DELETED 7.3 Radioloaical Surveys 7.3.1 Airbotne Sampling & Direct Dose Rate Survey Guidelines . . . . . 3 03-17-82 7.3.2 Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant . . . . . . . . . . . . . 9 11-04-83 7.3.3 Post-Accident Sampling of Contain- .

ment Atmosphere . . . . . . . . 8 11-04-83 7.3.4 Movement of Required Chemistry Equip-ment & Material'to the Technical Support Center Counting Room &

Mini-Laboratory . . . . . . . . 1 11-04-83 7.3.5 Post-Accident Sampling of the Auxiliary Building & Drumming Are Vent Stacks

.s- Using the Isokinetic Stack Sampling System . . . . . . . . . . . . . . 0 09-09-83

[E e * *-

l Page-3

f. n\ '

V Rev4sion D, ate 7.4 Emergency Equipment

. 4 '.1 ' DELETED

.7.4.2 . DELETED 7.4.3 Use of_Baird Model 530 Single Channel Iodine Spectrometer to

' Determine Airborne Iodine Activities . . . . . . . . . . . . 1 05-15-81 7.4.3.1 Use of Canberra Model 3100 Series 30

' Multichannel Analyzer to Determine

-Airborne Iodine Activities . . . 0 02-26-82 7.4.4 AMS-2 Air Particulate, Iodine &

LNoble Gas Sampler / Detector . . . 0 03-31-81

~8 .1 - Personnel Assembly & Accountability . . . . 4 09-09-83 9.1 Security. .. . . . . . . . . . . . . . . . . 0 03-31-81 .

10.0 Firefighting . . . . . . . . . . . . . . . . 0 03-31-81 11.0 FIRST AID & MEDICAL. CARE

=v 11.1 On-Site First Aid Assistance . . . . . . . . 4 09-09-83 11.2 Injured Person's Immediate Care . . . . . . . 2 09-09-83 11.3 _ Hospital Assistance . . . . . . . . . . . . . 4 09-09-83 11.4 Personnel Decontamination . . . . . . . . . . 0 01-29-82

-12.0 REENTRY & RECOVERY PLANNING 12.1 Reent'ry. Procedures for Emergency Operations 2 08-26-83 12.2 Personnel Exposure & Search & Rescue Teams . . . . . . . . . . . . . . . . . . 3 08-26-83 I

12 3 Recovery Planning . . . . . . . . . . . . . 0 03-31-81 12.4 Personnel Monitoring Exposure Guidelines . 0 01-29-82 13.0 PRESS 13.1 Crisis Communications . . . . . . . . . . . 2 09-10-82

'14.0 COMMUNICATIONS 14.1 DELETED

.14.2 Paging System Operation . . . . . . . . . . 0 '09-09-83 s- <

7. .

P' age 4 i

~15 0 TRAINING, DRILLS-& EXERCIS_ES Revision

. Date r

-- .15 .1 DELETED, '

15.2' DELETED l

'15.3 -DELETED ,

- 15.4 : DELETED-

-16.0-WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES i

e r s- .,

.16.1 . Nuclear Engineering'Section Notification'&-

l* l 4'

!. . Response .* . . . . . . . . - . . . . . . . . 4 07-01-83 l t '. t l t 4

!.- +

! s ,

k.

! ,I i'

k. k t

L@

}:

[

r I

! a l

, e i

[

i 1

I, i

i i i

l I

{

f L'

+

i -

l r- ,

l N Lg .

/

i~

t te- = rM '--' -T M *v y -"w NP * * ^ ' ~ ~ ~ '

4A~ ~~

y

,s 11-11-83

"/ T:

'Aj'-

+

TABLE OF EPIP FOR!!S W k

.EPIP EPIP

• Form Title' Procedure-1 J01 Emergency Plan Airborne Radiation'3urvey Record Site Boundary Control' Center (01-83)- 7.3.1 02 Emergency Plan Survey Record Site Boundary Control Center (01-83) .

7.3.1 03 Dose Factor Calculations for Specific Noble Gas Analysis Results (03-81) 7.3.1

.04 StatusLReport on Plant ~ Systems & Controls for Affected Unit (01-83) -1.2 05; RMS System Status-(Release Point IIonitors) (10-83) 1.2 _

06' . R!!S ' System Status ( Area Type Monitors) ~ (10-83) 1.2

'06a -RMS' System Status-(Process IIonitors) (10-83) 1.2 07 .For X/Q Determination (09-83) 1.4 08 Estimated Whole Body _& Thyroid Projected Doses (09-83) 1.4 09 Estimated Whole Body Dose Calculation Worksheet for

-Specific Noble Gas Releases (09-83) ._

1.4 10 Estimated Ground Deposition Calculation Worksheet for

. Particulate Radionuclide Releases'(09-83) 1.4 4

[(_, '}/. 10a . Estimated Population Dose (09-82) 1.8 11 Summary of Radiological Dose Evaluation Calculations (09-83) 1.4 12 Incident Report Form'(09-82)~ 2.3, 3.3, 4.3, 5.3 13' Status Update Form (09-82) 2.3, 3.3 4.3, 5.3.

'14 Unused 15 Unused ~

16 Event Data Checklist (03-81) 5.3 17 -Accounting Short Form ~(04-82) 8.1 18 Assembly Area Roster (03-81) 8.1 19 Unused 120 Unused 21 ~ Unused 22 Plant & Company Emergency Call List (09-83) Call List Tab 23 Offsite Agency Emergency Call List (11-83) Call List Tab

!24 Unused 25 Unused 26 Unused

'27 Unused.

28 Unused 29- Unused

-\ s_-l' t

- ll

. . , , - - - , - - . -me. _ , ,--m., .., ~.~.- -_.-,,,,-~,_..-,s.,-- ,y, - - - - - - - , , , - , - , . . - , ,

n _ . . . .; , - . - ,- - .-.. . . - . . . ~ . - . - - . ~ . . - . . - . , - . . . . . - . ~ . - . . . . . . . .-

i

.i

, Page 2

. . .t

.(

EPIP EPIP j- Forms Title- Procedure 30 Reactor Coolant Post-Accident Sampling. Analysis Report (08-83) 7.3.2

+ -31 -Containment Atmosphere Post-Accident Sampling Analysis Report (10-83) 7.3.3 ,

32 - Search & Rescue and Emergency Operations Checklisti(04-82) 12.2

-33 Estir.;ation of Core Damage -(09-82) 1.7 -

34 ' Calculation of Xe-133 Equivalent. Release Rates (09-83) 1.8 >

i. -35 Dose. Calculations (09-83)- 1.8 36'

~

Unused

37 Medical Assistance Call List (09-82) 11.1, 11.2 e i

11.3 1

i j ' --

g t

l' .

i i

j.-

L h L

[ i l

(-

f l.:

4

[

J-)

~

i i

,-,,e.,,,..%. , , --,~.....,,,,.,,_,_.,.,__,_m,..-. . _ , , , , .._,,,o_.___..wr,..,m.-_,,_,.,mw..,,- , , , _ , . , ,

7---

),

EPIP 1.1 '

{. ~ MINOR Revision 6

-(' -

11-04-83 INITIAL CLASSIFICATION

/

1.0 GENERAL The purpose of this procedure is to provide a means of classifying an event or condition at the Point Beach Nuclear Plant into one of four emergency ,

classifications as described in the Point Beach Nuclear Plant Emergency Plan. Each emergency classification requires emergency organization noti-fications, mobilizations, and actions to be performed in order to appro-priately react to the situation and provide for the health and safety of plant and public personnel. They are listed in order of increasing severity.

1.1 - Unusual Event An unusual plant condition which either has occurred or might occur.

This condition could possibly lead to a degradation in overall safety.

This condition does not represent a significant radioactivity release,

'~'s involves no offsite response, and may require no augmentation of plant personnel. In spite of the above, prompt notification of the

- ..gV,) counties and state is required.

1.2 Alert Plant conditions in which events are in progress or have occurred which involve an octual or potential degradation of plant safety.

Radiation releases are not likely to cause an offsite hazard. Prompt offsite notification is necessary and the plant organization may have to be augmented.

i 1.3 Site Emerqcncy l

l Plant conditions in which events are in progress or have occurred which involve actual or probable major failures of plant functione.

Potential radioactive releases may have an impact on offsite people.

Prompt notification of offsite agencies is required. The plant organization must be augmented and the technical support center,

-onsite operations support center, and emergency support center will be operational. An evacuation may be necessary.

1.4' General Emergency l Plant c'onditions in which events are in progress or have occurred which involve actual or imminent substantial core degradation and a

[ -[h ~~ potential for loss of containment integrity. Potential radioactive i ( ,/ releases may have an impact on offsite people. Prompt notification L .

4 EPIP 1.1

% Page 2 d

of offsite agencies is required. The plant organization must be augmented and the teclinical support center, ~ onsite operations support center, and emergency support center will be operational. An evacu-ation may be necessary. The emergency news centar will be opened.

The Shift Superintendent has t!.e responsibility and authority to take namediate action to mitigate the consequences of the emergency. He will consult with the Duty & Call Superintendent and assign the appropriate emergency classi-fication and initiate the necessary Emergency Plan implementing procedures.

2.0 REFERENCES

2.1 Nuclear Regulatory Commission NUREG-0654, Revision 1, published November, 1980.

2.2 Point Beach Nuclear Plant Emergency Plan Sections 4.1 and 5.1.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged.

3.2- Emergency Plan implementing procedures are not to be used to respond to security threats. One hour notification of the NRC il required

.'- using the red phone for security threats.

3.3 Certain events require notification to the NRC within one hour.

~

These items are included on Table 1-1. Those items which are noted as "NRC Only" means that there is no classification for the events and no notification other than the NRC is required. These notifi-cations are not considered as starting the Emergency Plan.

3.4 The " Indications Used" in Table 1-1 are those which one may expect if that level of emergency occurs very quickly. For more slowly developing situations, other indications may be judged appropriate.

For example, a primary system leak rate of 40 gpm is an Unusual Event. Subsequently, charging may be lost and, in addition, the leak may worsen. One may not see charging flow 50 gpm greater than letdown flow when in fact an Alert should be declared.

3.5 For classification purposes where radiological dose is the primari parameter leading to a classification, use EPIP 1.8, " Emergency Off-Site Dose Estimation" for determination of dose.

N_-

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

EPIP 1.1

.- (~N Page 3 k

4.0 INITIAL CONDITIONS None.

NOTE: APPENDIX 1 0F NUREG-0654 (PAGE.1-3) CONTAINS THIS SENTENCE: "THE TIME IS MEASURED FROM THE TIME AT WHICH OPERATORS RECOGNIZE (EMPHASIS ADDED) THAT EVENTS HAVE OCCURRED WHICH MKE DECLARATION OF THE EMER-GENCY CLASS APPROPRIATE.

5.0 PROCEDURE 5.1 Call the Duty & Call Superintendent for consultation to establish the initial classification. If he is unavailable, the Shift Superintendent j

is responsible for classification.

5.2 Select affected categories related to plant events or conditions at this timc. Check (/) all applicable categories.

Refer to Page Category in Table 1-1

( l. Safety System Functions 1 4

'-') 2. Abnormal Primary Leak Rate 1

3. Abnormal Coolant Temperature /

Pressure 2

4. __ Abnormal Primary / Secondary Leak 2

5. Core Fuel Damage ,

3

6. Secondary Coolant Anor &ly 4

7. Abnormal Effluent 5

8. Major Electrical Failures 5

9. Control Room Evacuation 6 I

10. Fire 6

11. Plant Shutdown Function 7 i

12. Abnormal Radiation Levels at Site Boundary 8 O

EPIP 1.1 p Page 4 L)

Refer to Fage Category in Table 1-1

13. Fuel Handling Accident 8 1

-14. Serious or Fatal Injury 9

15. Security Threat 9

16. Hazards to Plant Operations 9

17. Natural Events 10

-18. Reactivity Transient 10

19. Load Transient 11 2 0 . __ Other 11 5.3 Beginhing at the indicated page in Table 1-1 (attached), review initiating conditions for all categories checked above.

()ty 5.4 Record most severe emergency classification at this time.

l l

5.5- Record date/ time of initial classification (subsequent columns for i reclassification at a later date and time are provided if reclassifi-cation is required).

Initial Subsequent Subsequent Date/ Time Date/ Time Date/ Time l NOTE: IF THE SHIFT SUPERINTENDEhr CANNOT COMMUNICATE WITH A DUTY &

CALL SUPERINTENDENT, THE SHIFT SUPERINTENDENT MUST NOTIFY THE STATE AND TWO COUNTIES WITHIN 15 MINUTES OF THE DECLARATION OF ANY CLASS OF EMERGENCY.

l 5.6 If events or conditions are classified as an Unusual Event, perform

'EPIP 2.1, " Unusual Event - Immediate Actions."

l 5.7 If events or conditions are classified as an Alert, perform EPIP 3.1,

" Alert - Immediate Actions."

( 3 V

e

EPIP 1.1 Page 5

, 5. 8 ' If events or conditions are classified as a Site __ Emergency, perform EPIP 4.1, "Siti. Emergency - Immediate Actions."

5.9 If events or conditions are classified as a General Emergency, perform EPIP 5.1, " General Emergency - Immediate Actions."

NOTE:

"One hour" refers to th.2 requirement to notify NRC within one hour (10 CFR 50.72).

"One hour - Open line" refers to the requirement to notify NRC within one hour and maintain ar. open line for continuous communication (10 CFR 50.72).

s i

i l

i

m h j j ~

f ) \v I \w/ .

Nofy: DCS - Duty & Call Superintendent DSS - Duty Shift Superintendent Table 1-1 FSAR - Final Safety Analysis Report MASP - Modified Amended PBNP Security Plan ,

EMERGENCY CLASSIFICATION C*ttoory Emergency Initiating Condition Indication Used Classification

1. Stfety System Unplanned initiation of emergency core cooling Any of the following first-out rea.: tor trip

_ Unusual Event Functions with injection to the primary system , panel annunciation with indicator confir- (7) mation noted:

1. " Containment press hi",

[PI-945, PI-947, PI-949 (2/3 >5 psig)]

2. " Steam line loop A lo-lo press"

[PI-468, PI-469, PI-482 (2/3 <530 psig)] .

_....y...

3. " Steam line loop B lo-lo press" 4

[PI-478, PI-479, PI-483 (2/3 <530 psig)]

4. " Pressurizer lo press SI" ,

[PI-429, II-430, PI-431 (2/3 <1735 psig)}

5. Wide range pressure <1500 psig Loss of containment integrity requiring When shutdown commences as determined by DSS Unusual Event shutdown by Technical Specifications l and DCS (5) , l, . , ,

Loss of engineered safety feature requiring When shutdown commences as determined by DSS Unusual Event l shutdown by Technical Specifications and DCS (5) i Loss of fire protection system function When shutdown commences as determined by DSS Unusual Event requiring shutdown by Technical Specifi- and DCS (5) catic.'s (i.e., both fire pumps inoperable) and no backup fire suppression system

2. Abnormal Primary Exceeding Technical Specification primary system When shutdown commences as determined by DSS Unusual Event Leak Rate leak rate (10 wn) and DCS (5)

, (5) (7) See DCS 1.12.1 for 10 CFR 50.72 Notifications.

I e

y^ ^' .

I \ b d .

Table 1-1 Page 2 i' Category Initiating condition Emergency Indication Used . Classification.

1.

Leak rate >50 gie Ali l of the following; Alert

1. " Volume cot. trol tank level hi-lo"

[LI-141 and/or LI-112 <8%]

2. Decreasing pressuriser level

[LI-426,LI-427,LI-428]

f 3. " Charging pusy speed hi" s

i 4. Charging line flow (FI-128) >SO gia more than letdown flow (FI-134)

L.

J Leak rate in' excess of available pump - A of the following:

J Site Emergency I capacity includirg charging, high head SI j and low head SI 'I.' " Volume control tank level hi-lo -

[L1-141 and/or tI-112 <8%]

1 2. No pressuriser level indicated ,

l [LI-426,LI-427,LI-428]

l

. 3. All available pumps running as indicated by

the red light at the switch

-- - -

4. Increasing core exit T/C temp as indicatgd f by P-250 and confirmed on local readout.

l l- 3. Abnormal coolant Unexpected decrease in subcooling margin Both of the follovbq: Unusual Event

{ Temperature / Pressure

1. Alarm on P-250, if operable i

j 2. Confirmation by manual calculation 4 -

f Both of the following:

1 4 Presst.re >2735 psig 1. Pressure >2735 pcig on PR-420, and NRC only i '

(2)

DNBR <1.30 2. Code safety, or PORY not closed indication (2) See DCS 1.12.1 for 10 CFR 50.72 Notification.

I i

i 2

p~ .

, {

Table 1-1 Page 3 Emergency category initiating condition Indication Used classification

4. Abnormal Prtenary/ ExctPding Technical Specification primary-secondary When shutdown comumences as determined by DSS Unusual Event Secondars Leak leak rate and DCS (5)

Gross failure of 1 SG tube (>400 g e) & loss of All of the following first-out reactor panel Alert offsite power (FSAR 14.2.4) annunciation with confirmation indication:

1. " Pressurizer Lo Press SI,"

[PI-429, PI-430, PI-431 (2/3 <1735 psig)]

2. a. " Steam generator & level hi" ,

[LI-M 1, LI-M 2, LI-M 3 (2/3 >70%)] og

b. " Steam generator B level hi"

, , , [LI-471, LI-472, LI-473 (2/3 >70%)]

3. 3. "4.16 KV bus undervoltage"

& 0 V on 403 & A04 voltmeters,

b. XO4 to A03 ammeter on CO2 (0 amps) 4 c.

XO4 to A04 ammeter on CO2 (0 amps)

4. SI flow >400 gn indicated by FI-924 &

FI-925 and pump discharge pressare corresponding to flow.

' 5. Stesa line release monitor 1(2)RE-231 or 1(2)RE-231 100 x alarm setpoint.

Rapid failure of >10 SG tubes (4000 gn) with All of the following first-out reactor panel Site Emergency or withost offsite AC annunciation with confirming indicatior :

1. " Pressurizer lo press SI"

[PI-429, PI-430, PI-431 (2/3 <1735 psig)]

2. a. " Steam generator a level hi"

[LI-461, LI-M 2, LI-M 3 (?/3 >70%)]

or

b. " Steam generator B level hi"

[LI-471, LI-472, LI-473 (2/3 >70%)]

3. ':I flow >4,'00 pm indicated by FI-Wt ,

FI-928, FI-924 & FI-925 (5) See DCS 1.12.1 for 10 CFR 50.72 Notification.

- 2

6 Table 1-1 Page 4 1,

i c*ttoory Emergsacy Initiating Condition Indication used classification ,

1

5. Ccre Fuel Damage Gross fuel damage in core indicated Nos. 1 & 3 or Nos. 2 & 3 of the following: Unusual Event

1. Letdown line radiation monitor (RE-116)'

(sample line 1(2)RE-106) 100 m alarm setpoint.

l 2. Failed fuel monitor (2RE-109) 100 x alarm setpoint.

3. Sustained offscale & chemical analysis shows fission product concentration in-crease by 100X.

i -

Massive fuel damage C.

300 pCi/cc iodine-equivalent as determined by Alert

• by chemical analysis a

j 1. Massive loss of fuel clad integrity Initiating Conditions Nos. 1, 2, 4 & 5 General Emergency i 2. With simultanenus loss of primary system in-i exist and No. 3 is possibles (3) tegrity

, 3. With potential loss of contahiment integrity 1. 300 pci/cc iodine-equivalent determined by .

~

chemical analysis .a.

2. Primary system leak >1000 gis indicated by SI flow >1000 gun (FI-924 & FI-925) and

]; pimup discharge pressure corresponding to *~

flow I

3

?

3. Minimum contairiment pressure suppression equipment is not available (any of the

! following):

a. No fan cooler operating and <2 spray pumps.

F b. No spray ptemp operating and <4 fan

! coolers

c. <2 fan coolers running with 1 spray 2 Pump 1

4. " containment press hi"

} [PI-945, PI-947, PI-949 (2/3 >5 psig)]

j 5. " Containment spray" with 2/3 + 2/3 >25 psig j lPI-945,PI-947,PI-949]

]

[PI-946,PI-948,PI-950]

1 l

1 (3) Sae DCS 1.12.1 for 10 CFR 60.72 Notification.

i i

% [5

[]5

\s .\ w/ .

Table 1-1 Page 5 i

Emergency Category Initiating Condition Indication Used Cla=sification '

6. Secondary Coolant Reouction in feedwater enthalpy incident 1. a. Decreasing feedwater temp indicatea by Unusual Event Anomaly (FSAR 14.1.7) 70-4184 & 70-438A on P-250 and

b. confirmed by local temperature indicator on outlet of No. 5 feedwater heater.

2. Ur*xpected increasing power on excore nuclear instrumentation a steam line break with primary-to-secondary leak 1 3 of the following first-out reactor trip Alert rate in excess of 10 gm (FSAR 14,.2.5) panel annunciation with confirmations (3)

1. Either

a. " Steam line loop A Lo-Lo press"

[PI-468, PI-469, PI-482 (2/3 <530 psig)]

or

b. " Steam line Foop 8 Lo-Lo press"

[FI-478, PI-479, PI-483 (2/3 <530 psig)]

2. Confirmed primarr-to-secondary hak rate of at least 10 pm.

3. Either

.a. " Steam line loop & isol channel alert"

[FI-464, FI-465 (1/2 >3.9x10s lb/hr)]

or

b. " Steam line ic,op Fisol channel alert"

[FI-474, FI-475 (1/2 >3.9x108 lb/hr)]

Transient initiated by loss of feedwacer, followed A J of the following: Site Emergency by loss of auxiliary feedwater for >1 hour (3)

(FSAR 14.1.11) 1. Decreasing SG levels -

"A" SG [LI-461, LI-462, LI-463]

"B" SG [LI-471, LI-472, LI-4i,:'

2. No t.uxiliary feedwater flow -

[FI-4002, FI-4007, FI-4014]

[FI-4036, FI-403']

(3) See DCS 1.12.1 for 10 CFR 50.72 Notificatic1.

l

>>-- y ,

J .

a ~ .

Tatle 1-1 Page 6 Category Emergency

Initiating Condition Indication used Classification. i j 7. Abnormal Effluent Radiological effluent Technical lpecification Airborne effluents only ~ Unusual Event limits exceeded but <10 times the limit (8) 1 ,

(FSAR 14.2.3)

Radiological effluent Technical Specification Liquid effluents only Unusual Event j

limits exceeded (FSAR 14.2.2) (8) 4:

[ Radiological effluents >10 times Technical Airborne effluents only Alert '

i Specification instantaneous limits. (An.instan- . (8)

' teneous rate which, if continued fcr >2 hcurs, would result in a dose of about 1 mR at the site boundary under average meteorological conditions.)

l.

8. Major Electrical sustained loss of offsite power >11 minutes All of the following: Unusual Event Failures (FSAR 14.1.2)

1. "4.16 KV bus underroltage"

& 0 V on A03 & A04 voltmeters.

. 2. E04 to A03 ammeter on CO2 (0 amps).

4

3. 204 to A04 ammeter on CO2'(0 amps)

Sustained loss of onsite AC power capability Both of the following: Unusual Event I '

(>15 minutes) (5)

l. "4.16 KV bus undervoltage" &

f 0 V on AOS and A06 voltmeters

2. " Emergency Diesel Starting System Disabled" for both Diesels i

I Loss of all vital onsite DC power >15 minutes Both of the following: Site Emergency

1. " Annunciator power failure" on

. C01, CO2, CO3, and C04 i

a

2. <100 V on the voltmeters for all batteries 4

(8) (5) See DCS 1.12.1 for 10 CFR 50.72 Notification.

9

~4

r\ f'% r3 ,

(%) (~) (%d [ .

Table 1-1 Page 7 i

Category Emertency i Initiating Conditior. Indication Used Classification Loss of ofiaite power and loss of all onsite AC AJ of the following: Sita Emerger.cy power for >15 minutes

1. "4.16 KV bus undervoltage" 0 V on A03, A04, A05, A06 & "Emerg Diesel starting system disabled" for both Diesels

2. XO4 to A03 ammeter on CO2 (0 amps)

3. XO4 to A04 ammeter on CO2 (0 amps) l Loss of offsite and all onsite AC power with loss of l A of the following: Site Energtncy all auxiliary feedwater for >2 hours 4

1. Unit aux W meter XO2 e.) CO2 (0 W )

', 2. Station aux W meter XO4 on CO2 (0 W )

3. XO4 to A03 ammeter on CO2 (0 amps)

4. XO4 to A04 ammeter on CO2 (0 amps)

6. XO2 to A01 ammeter on CO2 (0 amps)

7. a. No auxiliary feedwater flow

[FI-4036, F1-4037]

b. Decreasing SG level -

"A" SG [LI-461, LI-462, LI-463]

"B" SG [LI-471, LI-472, LI-473]

9. Control Roon Evacuation of control coom >15 minutes & As required by DSS Site 1;mergency.

Evacuation no control at remote shutdown station (3) 1

10. Fire Fire in vital area or on the controlled side of As reported by Fire Brigade Chief Unusual Event plant lasting >10 minutes after initial use of fire extinguishing equipment.

i

Fire affecting one train of safety systems. As reported by Fire Brigada Chief Alart Fire affecting 2 trains of Safety systems As repotted by Fire Brigade Chief Site Emergency (3) See DCS 1.12.1 for 10 CFR 50.72 Notification.

a

[] \

- "d . .

Table 1-1 Page 8

} Emergency category Initiating Condition Indication Used Classification 4

11. Plant Shutdown Nonfunctional indications or alarms in the control Both of the following: Unusuai Event j Function room on primary system parameters requiring plant (5)

, shutdown. 1. " Annunciator power failure" on C04.

2. Faihd indication as determined by DSS.

t Turbine mechanical failure with consequences' All l of the following:

1. Anntaciator " Turbine supervisory." Unusual Event

2. Indication on TR-6019 of bearing vibration

>7 mils.

} 3. Bearing vibrr. tion alarm on back of CO3.

4. Visual confirmation of turbine housing penetration by a blade or disc.

Significant loss of effluent monitoring capability & l. Loss of RE-22J during a release Unusual Event

, meteorological instruments which impairs ability to or i perform emergency assessment'. Loss of effluent 2. Loss of RE-218 during a release monitoring may/may not require plant shutdown. or I 3. a. Loss of wind speed indication or wind direction indication and

b. Loss of RE-315, RE-317, RE-319 or

c. Loss of RE-215, RE-225, RE-226 or

d. Loss of RE-221, RE-325, RE-327 or

e. Loss of RE-224 (5) See DCS 1.12.1 for 10 CFR 50.72 Notification.

i l

J

% N ..

t) G .

Table 1-1 ,

Page 9 Emergency category Initiatino condition :ndication Used Classificatisq-Failure of reactor protection system to A of the following:

y Alert complete a trip which brings reactor subcritical (3)

1. Unplanned first out annunciator on C04 with confirmation from associated indicator

2. Intermediate range detector output not decaying

3. >l RCC RPI indicates fully withdrawn All alarms (annunciators) lost >15 minutes while 1. " Annunciator power failure" on Col, CO2 & Alert unit is not in cold shistdown 1(2)C03, 1(2)C04

• ' Loss of functions needed for cold shutdown for >4 Any of the fcIlowing: Alert

~~i 1.ours while at cold shutdown

1. Loss of service water Unit 1 = south & west header Unit 2 = north & west header

2. Loss of both trair.s of RHR

3. Loss of component cooling

12. Abnormal Radiation a. Effluent monito-rs detect levels corresponding to Airborne effluents only Site Emergency Levels at Site any of the following:

' .. : . , < (. (1) >50 mR/hr for \ hour (2) >250 mR/hr for \ hour for the thyroid (3) >500 mR/hr whole body for 2 minutes (4) >2500 mR/hr to the thyroid for 2 minutes at the site boundary for adverse meteorology

b. Any of the above doses measured in the environs As reported to DSS by HP Sipervisor

c. Any of the dose rates projected, based on plant parameters (3) See DCS 1.12.1 for 10 CFR 50.72 Notification.

J

N% ..

C U U[N .

Table 1-1 Page 10 Emergency category Initiating cond! tion Indication used classification

a. Effluent monitors detect levels corresponding to Airborne effluents only General Emergency eithers (1) 1 R/hr whole body (2) 5 R/hr thyroid at the site boundary under actual meteorological conditions

b. Either of the above doses measured in environs As reported to DSS by HP Supervisor

c. Either of above dose rates projected based on other plant parameters

13. Fuel Handling Major damage to irradiated fuel in containment Both of the following: Alert Accident

1. As reported to DSS by Core 1,oading Supervisor

2. Alarm on Victoreen on manipulator & alarm on R211 Fuel daary accident with release of radioactivity Both of the following: Alert to auxiliary building (FSAR 14.2.1)

1. As reported to DSS by Supvr in charge of fuel handling & drumming area vent (R221)

2. Alarm on Victoreen on spent fuel pit bridge.

14. Serious or Fatal Transportation of seriously or fatally injured Reported as judged by DSS Unusual Event Injury individual from site to hospital (Reference (empect hospitalization for at least EPIP 11.1) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)

15. Security Threat Security threat or attempted sabotage Per MASP Per MASP & Appen-or dices (4) ongoing security compromise (4) See DCS 1.12.1 for 10 CFR 50.72 Notification.

Y

q , N .

, Nj %l s Table 1-1 Page 11 Emergency category Initiating Conoition Indication Used classification

'16. Hazards to Plant Unusual aircraft activity over facility Visual obsetvation cf Operations Supervisor g Unusual Event 4 operation security force Near or onsite explosion or flammable or toxic gas As reported to DSS by plant personnel making Unusual Event release visual observation Missile impacts frca any source on fact.lity Visual observation by Operations supervisor Alert Missile impact causing damage to two trains of safety systems Visual observation by operations supervisor Site Emergency

' v, -

Aircraft crash in protected area (within the fence) visual observation by Oparations supervisor Alert I

Known explosion damage to facility affecting plant Visual observation by operations supervisor Alert operation. Toxic or flassnable gases in facility environment excluding normal process gases a

Toxic or fl - hle gases entering into vital areas Visual observation by operations supervisor Site Emergency (co trol room, auxiliary building, etc.) excluding

m .y normal process gases '

17. NatLral Events Any earthquako Activation of >2 accelerographs and verified Unusual Event by actual physical ground shaking or by con-tacting University of Wisconsin, Milwaukee Seismic Center at 1-414/963-4602.

Any tornado visible from site Verification by Operations supervisor hasual Event Low Lake Michiga. water level With no CW pumps running, water level is 3.9' Unusual Event below O' on surge chamber level & confirmed by measuring forebay level at 10.9' below pumphouse floo- (7' level}

t I

I J

J

f**' ] ,.;

k. .

Table 1-1' Page 12

. Emergency Category Initiating condition Indication Used Classification Earthquake greater than operLting basis earthquake Earthquake with attendant structural damage of Alert containment or spent fuel pit Any tornado striking the facility visual observation by DSS or Operations supvr. Alert l

Seiche near design level >6" of water in turbine hall Alert Winds in excess of design levels Wind speed indicated as >100 mph Alert

F Wind with damage Structural damage to containment Site Emergency Failure of protection tur vital equipment at low A.ny n of the following: Site Emergency levels (i.e., caused by seiche > design levels)

1. >3' water in both EDG rooms.

2. >2' water in vital switchgear room.

3. >2' water in auxiliary feed pump room.

. .c. .

18. Reactivity Transient Uncontrolled rod withdrawal (FSAR 14.1.1 & 14.1.2) Unusual Event CVCS Malfunction (FSAR 14.1.5) Unusual Event Accidental, Criticality Mtc Only (3)

19. Load Transient Loss of Electrical Load (FSAR 14.1.9) Unusual Event

20. Other Condition that warrants t ate and/or local official DCS & DSS concurrence Unusual Event awareness Ccadition that warrants establishment of technical DCS & DSS concurrence Alert support center & emerp ncy support center (3) See DCS 1.12.1 for 10 CFR 50.72 Notification.

)

/ )

v , x/ .

, Table 1-1 Tage 13 Emergency Category Initiating Condition Indication Used classification ,

Condition that warrants use of monitoring teams DCS & DSS concurrence Alert Personnel contamination Health Physicist & DCS concurrence NRC-only 1-hour (10)

Any unplanned reactor trip DCS & DSS concurrence NRC-only 1-Hour (7) i Strike by employees or guard force DCS & JSS concurrence NRC-only 1+ Pour (12)

{ Loss of red phone (ENS) DCS & DSS concurrence IEtC-only

, 1-Hour (13)

Personnel or procedural error DCS & DSS concurrence NRC-only 1-Hour (6) i 10 CFR 20.403 DCS & DSS concurrence NRC-only i

. 1-Hcur (11)

(10) (7) (12) (13) (6) (11) See DCS 3.12.1 for 10 CFR 50.72 Nctification.

J I

5 r

4 4

)

1 c:p -

4':

EPIP 1.3 q <

MINCR Revision 8 11-04-83 ESTIMATION OF GOURCE TERM 1.0 GENERAL-The purpose of this procedure is to estimate _ the source term (stack release rate in Ci/second) using the low range operational stack monitors, the Eberline RMS II Radietion Monitoring Systems or direct contact radia' tion measurements on the plant effluent vents. The plant effluent vent stacks are:

1.1 Auxiliary Building Vent, (ABVNT) 1.2 Drumming Ares Vent, (DAVNT) 1.3 Gas Stripper Building Vent, RE-224 (GSBVNT) f' 's 1.4 Unit 1 Containment Purge, 1RE-305

'.) 1.5 Unit 2 Containment Purge, 2RE-305 1.6 Combined Air Ejector Decay Duct, RE-225 (CAE)

< 1.7 Main Steam Safety Valves and Atmospheric Dump Valves, 1(2)RE-231 and 1(2)RE-232 2.0 ' REFERENCE 2.1 EDS Report to Wisconsin Electric Power Company concerning NUREG-0578, March 7, 1980.

3.0 I'RECAUTIONS 3.1 If fuel damage or loss of reactor coolant system integrity has occurred, some or all of the following would be present:

3.1.1 The letdown radiation monitor (1RE-109) or the failed fuel radiation monitor (2RE-109) may be unusually high or offscale. ,

I 3.1.2 The containment radiation monitors (1RE-211 and 1RE-212 or 2RE-211 and 2RE-212) may be unusually high or offscale.

3.1.3 The containment area monitors (1RE-102 and 1RE-107 or p(_,). 2RE-102 and 2RE-107) may be unusually high or offscale.

.c  : ,.

3

, EPIP 1.3

, Page 2 T..

3.1.4 The charging pump area monitor (1RE-104 or 2RE-104) may be unusually high or offscale.

I 3.2 Health physics procedures and requirements must be followed when applicable (i.e., entering a high. radiation area).

3.3 Evalua. tion of.the radiation monitoring system readouts and radio-logical hazards must be completed prior to any attempt to enter the

. auxiliary building or facade to take a contact reading on any stack.

3.4 If this procedure is being used for determination of emergency classification, use EPIP 1.8 " Emergency Off-Site Dose Estimations" for determination of projected dose off-site. EPIP 1.8 is a shorter, however more conservative procedure for determination of projected dose.

4.0 INITIAL CONDITIONS 4.1 Applicable porticns of EPIP 1.2, " Plant Status", is completed.

r . 5.0 PROCEDURE FOR Xe-133 EQUIVALENT RELEASE RATE ESTIMATE - WORKSHEET NO. 1 l

l f\~ / 5.1 Chemistry / Health Physics Supervisor or Designated Alternate '

L . .

5.1.1 Obtain EPIP-05 and EPIP-06 of EPIP 1.2, " Plant Status," for the radiation monitoring systems. 'l F

NOTE: IF EPIP-05 AND EPIP-06 IN EPIP 1.2, " PLANT l STATUS," ARE NOT COMPLETED, OBTAIN THE METER l READINGS FOR EACH PLANT EFFLUENT VENT STACK FROM  !

THE REMOTE CONTROL ROOM READOUT MD RECORD THIS l

• l ON WORKSHEET NO. 1 AND THEN PROCEED WITH STEP l 5.1.3.

(' NOTE: PL4NT EFFLUENT VENT STACK MONITOR READINGS ARE ALSO AVAILABLE FROM THE TECHNICAL SUPPORT CENTER ,

DATA LOGGER. SEE ATTACHMENTS 1.3-1, 2 & 3. '

5.1.2 Enter the meter readings in the appropriate column on Work-sheet No. 1 for the indicated vents. If the readings are

. offscale, not monitored, or the monitors are inoperable, enter the appropriate word "offscale," "not monitored," or

[: " inoperable" in the meter reading column for the vent

affected.

9 n+*yr-- --

-r-+we- e p -en-, p~,-. rWw

v o

EPIP 1.3 O Page 3 5.1.3 Designate individuals in accordance with ALARA concepts to

obtain meter readings of the vents whose Eberline RMS monitor readings are unavailable by performing Section 5.2 of this procedure, if required.

NOTE: IF STEP 5.1.3 NEEDS TO BE COMPLETED BECAUSE EBERLINE RMS MONITOR READINGS ARE UNAVAILABLE, THEN PERFORM SECTION 5.3 0F THIS PROCEDURE AFTER APPROPRIATE MEASUREMENTS HAVE BEEN TAKEN IN SECTION 5.2.

5.1.4 Perform Section 5.3 of this procedure to determine the estimated Xe-133 equivalent release rate.

-- 5. 2 Direct St.ack Survey Team Designees l NOTE: THE FOLLOWING SECTION WILL NOT BE INITIATED UNTIL THE.

EVALUATION DISCUSSED IN PRECAUTION 3.3 HAS BEEN COMPLETED AND THE SITE MANAGER (DUTY & CALL SUPERINTENDENT),.THE DUTY &

CALL HEALTH PHYSICS SUPERVISOR, AND-THE DUTY SHIFT SUPERINTENDENT HAVE APPROVED. INITIATION. THIS SECTION WILL BE ACCOMPLISHED UNDER THE DIRECTION OF HEALTH PHYSICS SUPERVISION.

O 5.2.1 . Determine the most direct and desirable route to the plant effluent stack to be-monitored.

5.2.2 Determine the Health Physics requirements to be met for the i passage to the vent areas.

5.2.3 Determine the appropriste survey , instrument to be used for the plant effluent vent to be monitored.

5.2.4' Proceed by the route determined in Step 5.2.1 to the stack and record the survey instrument reading in contact with the L

stack in the columns provided on Worksheet No. 1, Part C, Plant Effluent Vent Stack Contact Readings.

j NOTE: IN THE CASE 0F=THE MAIN STEAM SAFETY VALVES AND f

ATMOSPHERIC STEAM DUMP VALVES, THE READING WILL BE TAKEN IN' CONTACT WITH THE CENTERLINE OF THE MAIN STEAM. HEADER, THREE FEET FROM THE MAIN STEAM LINE.

!. SHIELD THE PROBE (WITH A MINIMUM OF .25 INCHES OF i' LEAD) ON T3iE SIDES FACING THE MAIN STEE! LINE AND THE CONTAINMENT.

l' L *3 -

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

EPIP 1.3 O Page 4

.5.3' Chemistry / Health-Physics Supervisor or Designated Alternate

'5.3.1 Choose the appropriate vent stack readouts in Part A, B, or C of Worksheet No. 1 to convert readings to a Xe-133 equiva-lent. release rate. That'is if the low range monitors go offscale, use the high range monitors. Conversely, if the normal monitors are onseale, use the normal monitors, or if both normal and high range monitors are offscale or inoper-able, use the vent stack contact readings.

'5.3.2 ~ Use .the appropriate conversion factors for each of the plant i effluent vent to convert the chosen vent stack readout, (pCi/cc or R/ hour) from Step 5.3.1 to an Xe-133 equivalent release rate in Curies /second and record the value on Worksheet No.-1, Part F, Estimate of Gross Xe-133 Equivalent .

Release Rate. Enter the appropriate word "offscale," "not -

monitored," or " inoperable" for the cases where the plant '

effluent vent was not monitored, offscale, or inoperable.

NOTE: THE FOLLOWING QUALIFYING NOTES MUST EH RECOGNIZED.

1. If the actual flow rate is different than the assumed conversion factor flow rate, a ratio of:

Actual Flow Rate Assumed Flow Rate should be applied to determine the release rate.

(Ratio) x Release Rate Value = Adjusted Xe-133 Release Rate

2. Determine the steam line atm'ospheric vent, or the main steam header vent release rate in accordance with the following:

a. Obtain from the Shift Superintendent an esti-

. mated flow rate through the main steam header in Ibm / hour of steam being dumped to the environ-ment and the specific volume (v) of the steam.

NOTE: AT 1000 PSIA, SPECIFIC VOLUME IS 0.446 FT3 /LBM. AT 500 PSIA, SEECIFIC VOLUME IS 0.928 FT3/LBM.

3 e lbm/hrxvft x 7.86 gt 3 ec.

2 .a * ,a . _ u - - , _ . . . m , mm.,

& 4 J . m.

l l

, EPIP 1.3 1 Page 5 r

b. Convert contact reading, if required, tue main steam header to pCi/cc using the bipropriate conversion factor (Worksheet No. 1 Sect. C).

pCi/cc NOTE: ACTUAL pCI/CC READINGS ARE AVAILABLE i

' FROM STEAM LINE MONITORS 1RE-231.,

1RE-232, 2RE-231 AND 2RE-232.

c. Multiply flow rate obtained in Step (a) by the

, concentration obtained in Step (b) to obtain i the release rate (Xe-133 equivalent) from the raain steam header.

Flow Rate

• Concentration (pCi/cc) _ MainRelease

~

Steam Rate Header (cc/sec.)

1 5.3.2 Sum the values (1) through (5) on Workcheet No. 1, Part F, '

or use grab sample results #7 on Worksheet No. 1, Part F, to determine the gross Xe-133 equivalent release rate.

C-s NOTE: IF GRAB SAMPLE RESULTS ARE AVAILABLE, THE RESULT Or SUCH SAMPLES SHOULD BE MORE ACCURATE THAN GROSS j MONITOR READINGS AND HENCS SHOULD BE USED IN LIEU l OF THE RELEASE RATES CALCULATED ABOVE OR IN ADDITION l TO THE ABOVE IF THE RELEASE IS FROM AN IMMONITORED l RELEASE PATH.

l .

l 5.3.3 Report the calculated gross Xe-133 equivalent r elease rate  ;

! to the Shift Superintender' and the Technical Support Manager.

{

l l

l  !

1 1

! O l

1 l

sa- a a m'm. a+- 3 . - , ,4 <

i i m EPIP 1.3 Page 6 I

WORKSHEET NO. 1 XE-133 EQUIVALENT RELEASE RATE 4

a A. OPERATIONAL LOW-RANGE RELEASE MONITORS READOUTS Xe-133 Equiv.

Assumed Flow Rate Conversion Relcase Rate (cfm) Reading Factor Ci/sec Auniliary Building Vent 70,000 pCi/cc x 33 , f

=

Drumming Area Vent 43,100 pCi/cc x 20.3 , =

Unit 1 Containment .

Purge, 1 fan 12,500 pCi/cc x 5.9 , =

2 fans 25,000 pCi/cc x 11.8 sec p i Unit 2 Ccatainment d Purge, 1 fan 12,500 pCi/cc x 5.9

• sec pCi I 2 fans 25,000 pci/cc x 11.8 .=

sec pC1 g

i Gas Stripper Building  !

Vent 13,000 _

pCi/cc x 6.1 , =

-Combined Air Ejector 25 pCi/cc x 1.2 x 102 =

Steam Line Atmospheric  ;

Vent Refer to pCi/cc Section"E" O

4

,wr--w ------g,---n mynn,p ~ -,-w -e--- --wp,-+ . - - ,------a

- , , ---,,,e, - e , e---s- . , , - - - wr, n w w .- e-g ,- ,,vw,,e ,-y,-,,e,- ,-e-w .,

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

s EPIP 1.3 [

Lage 7

'B. PLANT EFFLUENT VENT STACK CONTACT READINGS Assumed Xe-133 Equiv.

Flow Rate Meter Reading Conversion Release Rate Vent (cfm) (R/ hour) Factor (Ci/sec) .

Auxiliary Building 70,000 x 300 =

Drumming Area 43,100 x 2.3 x 102 =

Unit 1 Containment Purge 12,500 x 8.0 x 101 =

25,000  :: 1.6 x 102 =

Unit 2 Containment Purge. 12,500 _

x 8.0 x 101 =

25,000 x 1.6 x 102. =

' Gas' Stripper Building 13,000

[

x8 x 104 =

Corbined Air Ejector ,

25 x 1.6 x 102 =

Main Steam Header Refer to Section "E" T

l t

I

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

] EPIP 1.3

\ Page 8 C. ACTUAL VERSUS CONVERSION CURVE FLOW RATE RATIO l e ease Rate Value = Adjusted Release Rate s ed w R te.x

( )x =

D. STEAM HEADER XE-133 EQUIVALENT RELEASE RATE CALCULATION

1. lbm/hr x specific volunie, f t 3 /lbm x 7.86 cc-hr/ft 3-sec NOTE: At 1000 psia specific volume = .446 ft 3/lbm At 500 paia specific volume = .928 't 3/lbm lbm/hr x ft 3/lbm x 7.86 cc-hr/ft -sec 3 l =

_ cc/sec I

) 2. Contact reading from Section C (if contact reading used):

l v .

R/hr x 8.0 x 102 C/ = Ci/cc

NOTE

IF 1RE-231, 1RE-232, 2RE-231 OR 2RE-232 (STEAM LINE MONITORS) ARE I

AVAILABLE, THE CONCENTRATIONS CAN BE USED DIRECTLY IN E.3.

i

3. Steam header release rate:

l Flow rate cc/sec x Concentration pCi/cc = Release Rate i 6 l .,cc/see x x 10 C1/cc = Ci/sec l Step E.1 Step A.7 or E.2 l

l.

!O

m EPIP 1.3 Page 9 E. ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEASE RATE Xe-133 Equivalent Release Rate '

Vent (Curies /Sec.)

1. Auxiliary Building i

2. Drununing Area

3. Gas Stripper Building

4. Combined Air Ejector Decay Duct

5. Main Steam Header

6. Unit 1 Containment Purge

7. Unit 2 Containment Purge

! 8. Sum (Gross Xe-133 Equiv. Release Rate)

O 9. Grab Sample Results =

=

Ci/sec.

4 f

i i

Completed By time Date O

- - , .g- >, -,gr-- * ---e -* m v wem- e- e-*W e--r -w-+ + *-

s 4

EPI? 1.4 MINOR

, Revision 9 11-04-83

• RADIOLOGICAL DOSE EVALUATION 1.0 GENERAL The purpose of this procedure is to provide a method to quickly estimate (1) X/g using meteorological overlays, (2) thyroid and whole body dose using X/Q and (3) ground deposition using an approximation of D/Q. .

2.0 REFERENCES

2.1 U. S. NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man

, from-Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1,"

October 1977.

2.2 U. S. EPA, " Manual of Protective Action Guides and Protective Actions s

g for Nuclear Incidents," EPA-520/1-75-001, September 1975. See

' Appendix D " Technical Bases for Methods that Estikaate the Projected Thyroid Dose and Projected.Whole Body Gamma Dose from Exposure to l Airborne Radioiodines and Radioactivo Noble Gases."

2.3 U. S. NRC Regulatory Guide 1.4, "Arsumptions used for Evaluating the Potential Radiological Consequences of a Loss-of Coolant Accident for Pressurized Water Reactors," Revision'2, June 1976.

2.4 TID 14844, " Calculation of Distance Factors for Power and Test 4

~ Reactor Sites," March 23, 1962.

3.0 PRECAUTIONS & LIMITATIONS 3.1 For' classification purposes where radiological dose is the primary parameter. leading to a classification, use EPIP 1.C, " Emergency Off-Site Dose Estimation" for determination of dose.

3.2 Ensure that all PBNP maps to be used by.this procedure and their corresponding meteorological overlays are based on the same scale.

3.3 -This procedure will be accomplished in the technical support center by a person designated by the Shift Supervisor or the Technical Support Manager. It will utually be done in conjunction with the Chemistry / Health Physics Supervisor when available.

3.4 The responsibility for implementation of this procedure will be O assumed by-ESC personnel after activation of the ESC.

. - . - = - - _- _ . . - . - _-

+

~

k,. .

EPIP 1.4

( Page 2 k

3.4 Wind speed and wind direction'must be average values obtained from the. analog recorders in the control room.

NOTE: DO NOT USE INSTANTANEOUS VALUES.

3.5 'If the-radiological release' duration is unknown, assume a duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

4

-3.6 If the meteorological. parameters cannot be obtained from the control l room, obtain the data from the following priority backup list.

3.6.1 Kewaunee Nuclear Power Plant. See EPIP-23, "Offsite-Agency Call List."

7dational Weather Service in Green Bay. Ask for Two Rivers 3.6.2 Coast Guard information, if available. See EPIP-23, "Offsite Agency Call List."

l 4.0 INITIAL ~ CONDITIONS 4 -4.1- A release of airborne radioactivity has occurred or a release is I anticipated.

i i 4.2 An emergency or potential emergency condition is anticipated to have.

. offsite. dose consequences.

~5.0 PROCEDURE / CHEMISTRY & HEALTH PHYSICS SUPERVISOR OR DESIGNEE 4

5.1 petermination of X/0, Atmospheric = Dispersion Factor 5.1.1 Obtain the-following information from the indicated source

-and enter this data in the appropriate space on form EPIP-07 (attached).

, Source Data

{ 'EPIP-04 (a) wind speed in-mph EPIP-04 (b) wind direction EPIP-04 (c) time of reactor shutdown '

EPIP-04 (d) time of release to centainment EPIP-04 (e) time of release from the plant Health Physics or Operating (f) duration or estimated oura-logs or projected estimate tion of the release in-hours .!

EPIP 1.3 results (see note) l (g) gross Xe-133 equivalent release rate in Ci/sec l EPIP-04 (h) Stability class in as degrees ,

l NOTE: IF. RELEASE DURATION IS UNKNOWN, ASSUME 8 HOURS.

l

D EPIP 1.4 Page 3 l 1

5.1.2 Determine stability class by use of the 00 or AT chart recorder values in the control room and Attachment 1.4-1.

Enter the stability class (h) on form EPIP-07.

NOTE: DO NOT USE 00 FOR WIND SPEEDS <3 MPH.

)

'5.1.3 Backup stability class detertination. Visually check cloud cover and incoming solar radiation. With this information, use Attachesnt 1.4-3 to ascertain the appropriate stability class. Enter the stability class (h), on form EPIP-07 NOTE: IF INCOMING SOLAR RADIATION IS STRONG AND WINDS ARE FROM THE EAST OR SOUTHEAST, IT IS A POSSIBILITY THE WIND IS PRODUCED BY A LAKE EFFECT. CALL THE GREEN BAY NATIONAL WEATHER SERVICE FOR AID IN THIS DETER-MINATION. IF A LAKE BREEZE IS SUSPECTED, OFFSITE SURVEY TEAMS MUST BE REMINDED TO PAY CLOSE ATTENTION TO WIND DIRECTION.

5.1.4 Place the overlay correspending to the stability class on f ~si the map. Using the plant location as a pivot point, align I the centerline of the overlay to the downwind direction from the plant.

NOTE: THE " TICK" MARKS ON THE CENTERLINE OF THE OVERLAYS ARE ONE MILE APART. .

5.1.5 Determine the distance (i) to the dose projection location if different from the standard centerline distances listed on form EPIP-07. Note the location description, sector, and distance on form EPIP-07.

Enter the Xu/Q value (j) for the distances of site boundary, two miles, five miles, and ten miles on EPIP-07. The Xu/Q '

values (j) can be obtained from the overlay in the table in the lower righthand corner of the overlay. If a possible location other than the standard specified location is on a line, enter the Xu/Q (j) value for that line from the overlay on form EPIP-07. If the location is not on a line, move to the next inner-most line (toward the centerline) and enter the Xu/Q (j) value for that line on form EPIP-07.

Example:

Class "C" Xu/Q for 5 miles equals 1.21 x 108 m2 O

G

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

i t 1 EPIP 1.4-Page 4 5.1.5 Calculate the X/Q value from tha Xu/Q value by using the '

equation:

-X ..sec. = 2.24(sec./m)- Xu/O (m 2)

Q' m3 (hrs./mi) Wind Speed (mi/hr.)

Enter the X/Q values on form EPIP-07.

15.2. Whole Body Dose Estimate NOTE: IF THE NOBLE GAS SOURCE TERM IS DETERMINED BY GRAB SAMPLE L_ .RESULTS WHICH GIVES AN INVENTORY OF. SPECIFIC NUCLIDES, THEN i- A CONSERVATIVE WHOLE BODY DOSE ESTIMATE CAN BE MADE BY COMPLETING FORM EPIP-09.

5. 2.1. Enter the gross Xe-133 equivalent release rate (g) on form EPIP-08 from form EPIP-07.

5.2.2 Enter the estimated release durati,on, ERD, in hours (f) on form EPIP-08 from form EPIP-07.

~

5.2.3 Calculate the projected whole' body dose on form EPIP-08 by using the equation

,

4 (k)- (g)

D(Rem) = X/Q (sec/m3) x Q (Ci/sec) x Kr (Rem i

m3/Ci - Hrs) i ;x ERD (Hrs)

L where:-

D = whole body dose (Rem) ,

.X/Q = atmospheric dispersion coefficient determined in' Step 5.1.5 (sec/m3) (k)

Q = release rate (Ci/sec) (g)

~

) Attachment 1.4-2 Kr=DoseFactor('['1h 4

ERD = Estimated Release Duration (Hours) (f) 5.3 Thyroid Dose Estimate 5.3.1 . Calculate the projected thryoid dose by using the whole body O

3 5.3.2 -

dose calculated in Section 5.2 of this procedure.

Record the. projected whole body-dose on form EPIP-08 in Section 2.

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

1 5 4 EPIP 1.4 g Page 5 5.3.3 Choose the appropriate figure based upon the type of L accident which has occurred.

a. Loss of Coolant Accident (LOCA) - Figure 1.4-1.

b. Gap Activity Accident - Figure 1.4-2.

c. Fuel Handling Accident - Figure 1.4-3.

d. Steam Generator Tube Rupture - Figure 1.4-4.

NOTE: IF THE TYPE OF ACCIDENT IS UNKNOWN, USE THE LOCA FIGURES.

5.3.4 Obtain the ratio factor that relates the whole body dose to a thyroid dose from the figure chosen with the corresponding appropriate time after the accident and record on form EPIP-08, Section 2.

5.3.5 Calculate the projected thyroid dose my multiplying the (x) whole body dose by the_ ratio factor obtained in Step 5.3.4 t on form EPIP-08, Section 2.

\s /

5.4 Radionuclide Ground Deposition Estimation NOTE: FORM EPIP-10 CAN BE COMPLETED ONLY IF IODINE GRAB SAMPLE RESULTS OR PARTICULATE RELEASE RATES ARE AVAILABLE. IF FORM EPIP-10 CANNOT BE COMPLETED, PROCEED WITH STEP 5.4.5 0F-THIS SECTION.

5.4.1 Enter the Xe-133 equivalent release rate or the specific particulate release rate on form EPIP-10 from grab sample results or frcm environmental monitoring results.

5.4.2 Enter the estimated duration of release (f) from form EPIP-07 on form EPIP-10.

5.4.3 Enter the value of X/Q (k) on form EPIP-10 as determined in Step 5.1.5.

l

i s EPIP 1.4 Page 6 5.4.4 Complete Section 2 of form EPIP-10 to calculate the ground deposition using the equation:

Dep (pci/m2) = F x .05_(m/sec) x 3600 (sec/hr) x 10 8 (pci/Ci) x X/Q (sec/m3) x Q (C1/sec) x ERD (hrs)

(k) 8 x X/Q x (g) (f)

Dep = F x 1.8 x 10 Q x EIP Dep = ground deposition (pci/m3)

X/Q = atmospheric dispersion factor from Step 5.1.5 (sec/m 3) (k)

Q = radionuclide release rate (Ci/sec) (g)

ERD = er.timated release duration (hrs) (f)

F = fraction of isotope subject to deposition (unitless) 3600 = conversion (sec/hr)

(w.')\ _

108 = conversien (pCi/Ci) 0.05 = assumed deposition velocity (m/sec) 5.4.5 Complete form EPIP-11 from available data and calculations just performed.

5.4.6 Enter the date and time of these calculations and sign form EPIP-11.

l 5.4.7 Forward completed attachments to the Technical support l Manager'for review. The Technical Support Manager will relay results to the Site Manager.

5.5 Population Exp^sure I

, 5.5.1 Calculate projected population exposure by using form EPIP-10a.

5.5.2 Enter from EPIP-08 whole body dose from center line on form EPIP-10a.

f-wg.

v

, ,y- . --- ,v .,e w, -- .._--,3---.--.,-.---,y.,,e----,-----u-. - eys,,-,.--..,,,,s-.w - -

c- ,

I t

> EPIP 1.4 l Page 7 I

t 5.5.3 Enter population figures from Attachment 1.4-4. Use pcpulation

, number corresponding to the quadrant and distance categories I for dose.

5.5.4 Total population dose from each radius to find total population dose.

f' I

i 4

l 4

+

l i

5 i

I j-t

)'

4 i

f 3

+~a a,mv --nc-~~,.., vr ~ ~a,---n--,------n

, / ^. ,

(

x ,/

) FIGURE 1.4-1 '

(s) k v -

THYROID DOSE RATIO FACTOR IDCA 4

10 m g ( 10, . - - - ~ -

.;p p,,

6 U,4 4 j ..;p; q

j 7, -

'  ;['

-h-

i

,m . nt

' q; ,

.. , , 4 --

4: I -

l .

ibib nii

,u!' ' . g. I .,

1:

.i

'2

'i+r.

.i l 1 4

l li l I i

!!:1 g

u.

T fj...  ; .,,,

.p

.j f.I 1llj 1

' p .'

1. l*.

-{- t . d -

9:

gW.h it !j,i p! i l /'

A t p, 3 4, j ca d'l .';

i I:

i,l- l d

un l i i .

/

8 il

't i

?

tU p

I-

i I p

/ '

I

'.}

> ii' i

} t f a  :.

u :d ij: f

^

i / ~ ~

8 tJ 1

/ l

@hi g

m 3  :

h d!' H ij

/ l  !

J i I d '

l

• I li s 10 -

r f j.  :

! I ilI I - -

1 d  ! j  ! I i  ! .! _

8 4

! I j g [  :

[ 1 o

H T., t:T, !-1 i

i f

1: ..!-

o

+ - - -

o m .

111,1Il;;

l I l

T. I .

..l g ni -I .I:.

y/

11

,1 l' }- 1

}.

[- 7 .

t I.' f! :l l ii! b

• 4 Ih y f'l

.. )t i l j

'... , . 't. - , '!!

I 3

j; ---I- I

':;. :j ,:

4 I .,li l i

i

[ .

7 -

l ili.

I i ill , n, ,.

.... ,  !. Ii l

4 i--

M, h,-

,t n

l,-i.

o l

II,;, In II 1l i

t i i t' i ii ,o

.!:

• i l.;jll.e di I i t

!' t "p '>

4 . , ,

.t ,;+ * *n* f~' +~ ~4'

]  ?.'e,

'T~~'

p, ';;p, t'

,tp 6p ., <,,

'i '. , jI i

+

• f q l i l

+

+l: 14! i }  :! in l t

• , Ptf ot! >- im !!D  :' H' 't

' I*'( !!'l

! i t in; M t 't  !

' ' 'd {t ' J hi' d I U I I!

l 2 1F 10 '

'~"'2d I

I II 10 '  :'- l - - " ~

O 4 8 12 16 20 24 28 32 36 40 44 40 52 56 L [INIM gvr6p 6 a

O  ?(,."'"N%

{.< .)

i FIGURE 1.4-2 Q) 4 U) l vl .

GAP ACTIVITY 140 "- - -- -

.' .i. '

tU: u  :, 1

M..

.'.; 'j. ,c

m. a', p: .,

.t!

,. ,: ... a. . .a;  ; ...  ;

p- :a.  ; . .. .a _. 4 .p .; '..

;:'  ;.. n:'

.. ,' ,;.p

!'h-q ::a:: .r- .. . .h lj u du q;i '.

l';;

]l

.!ji -l;;

, i !' !. l:'

! ,38 t; h' t 1

,.: . ,1 ;h; M

.' ! !.:. ., r:!' ,

'.t,_  : '.: '!; . 11 f, t  :

i !.:

.6

....7 .. 1.

. ,I., ;I ,

7,7, 7 .7 ,

, q; , , ,

k, j g.

.p y ,i}

11*: I 4,

,I . .h. ,1.! s i j : }'p! ....l!

=

! 1

-1 .' -,I  :  ;

> .,7 t.

i.4' ;.4'j q -.,1 -.I . ..

l}._

l.-

.l..;14.l~ t 4 - .

4' 3r

! lpl' 120 .

, i j

l c ;.

l 1f I!

^

t; i

lIl;. 7g!

!! '! t l l l l l l l l l  !  : ;I ~' :

' [,! f,,,! l l l I  !,l.

..

1' , . i .;I r p .

.H, yf a q _.

l ! . .., .: .

l' l l l .l 1

,l , -

l l l l l .II '!.

o

.m , . -

n, l.

l .

l .. i u.

I 1 .

j

.g .. .e q _ .i .

_j .. .t J .. [.. J .

1:.

7 I' !

i '

'j l't ' j  ! lb; 30- J a;100

'll

';  ; I ' - -

[ I g -l t I n

i lS ;$; 9:

l J p , ,.. - e+- a q$

m nl: ,ii 1' l ':: lb

.... int *- ..

j i: y , ,,

,- ;i; 8 'l  :;:  ! I l

l --  ;

Hli l'p

>. .i. H. . h. .-

- E 4fil 4 -

t.

4- --

L -

1.a 6.:. ::h. l.

I o 80 ,'  !; .  : s J "

,, 1 I .

_.", . 7 _ _

__u_. __ _.- _ _I_ .

t i i t n.7,_ _

I t . 1l!  ; l ~f l '

l ';"

( y

, l .

g _

+

-y  ;

7;

/ ,I 7;

Ih 3 , y 3 gq 1 i . l. . ' il q t l ll .

I t t  : it, '

I J N

8 60 -!i ut h.! Ih ':': d.,N it .

h

h. t ,

hi,!! hi

, ll  ! #

l t1~

li  ! i.  : 'n:-- l

~

l  ;

I .! nh ',,-

~~

l . . ,7--tt,-;ln i .

- - + - +- y'.,h

+- '

p.

'.h,8 :

.; I;

..'l l;,.. ,1l I ;, .t a i.

n; l

pt, ..;1.' iq; n,

.I,

! 'ui . .

p, t

ilh. I

}..p' , I -

p 1l , d, .

,.l, H ftj ]

M! I' ;h.h o. ;;;) .' l' p ,4.l {' d j 4' t j y l

y

+ -l {'

l

]'

y~g i ,

-j -7_

t g

il ;l. 77 g

.. i 10 ,' ;.

{ ,

{f+,l 7 m!: "JU.f .i hij .

t o,

, ...: !. . h.f

. e. j .o. ha t

.: j ... - jU,.,

g !.

l g ,l 1 ,l;'

i  !

, l .

l l ...

h i ;l,

.. . li .

..h,j t

[lo l j .j t j r T.j.

., a.- q.:

'e

!c

!ll ;tI'lh ': U 4 I

! :1- C' .jl: , I .! ;1 4  !

j h. ; i dh j'

_i,_ t

'"i  ;

i :gcj:

., I E4 '. U! t h 1; ,

j p*

8' ; . . 't, I l I hj; i !

n 1,

I l"l l tu. ( : f n" ' :i:

i'l:

n tt:4

.:.- m *:n !q r p Ilj1 p.

t},

l' Uf!! j 7 ~j j !6,;, ni- [ti,i :; p. l t'r 9t' 1 1

! p' t1

~

11 tn; -

, li

p. r". i . ,4; p'

' i; pl. i l *!l. h' hl"hi "l ; ;

h j*u l j' h;*l' 'l "

it q' i : i g';i.f ,l l . gd{ h p' l' l

-a l j pyf l 40 $ l

-.- 4  ;

jl-j- '; .

- -+--

. ' . . .. .i .: O. t : i: 1.

.un.. . ,

'. j}  !, .

y nn

I j l

lq h

.J. n ..t h.!n: j '1; lt jlI m I  !. '

.l [

! _j } 4',, l h.h.l .:.- jt. ,h l

n, , y lg!!

er

.J q'I

.n m . g;p i p U. . . lp p i hl 1

ju . ly ',U i! n4 Inj l j l , l ,l '

Nh .: p;l yl p -

._ . .__ 2_. ___.. . . . .2 ._ . . ,;

,u'  ;}!l g!l pl: :!n g'1 g ,

li u_ _

!h: ih: tN' i

[.r l

' '- i;n l:

' 'i It i ..,, l l g .

.:h t ,* "" n t,

.: L' i , i ;: ih' *m!?. :n; h [: t

,1: tt

• t't h+j r"- ** t- {*;dI ~

/n

tf it;- .

.; ..! p:* ! 'i! t; 'h. . ,' '

p' l " ! *"! l ! .-

ith:

.* U l,r 'li pt lg i  :

+5lti,I:: [d;lj

+ 1. 1;- ; -i l;l C 'j :al 42 20 - - - .- - - - - ---- -- -. m- - - . . 4.L a- "

-  : b o  :.: ' ' ' "

/-

". H '

ih::; n' ' 't;-' il  !:' Hi

1:' ti .g:: ' . '.; 7' i ; plj

, ,f' /'

Ipn

. j:i .. . n: I ' U.'

lij

' ;i  : h;

!{j: in l !!

l} : l.1l:b1  ! .i ;

..r. .

p' l 1

.. ' .!

ltil!it y> lip E @ t'h d:';; hii illi i}h 11}:Jiy iiij J'ii Ijii

~~'

M: y!' i ~'

je a

, ipi  !! , - II p

,,,e' . . ..

. . _ .. ._. .... q .. . .. . .. ., . _ . . ..; . . . _

g ;_na ;u.. - _. . . . _ .. . . .

I # l i;  ;;:  :.. .:t .n "i. :t it.h ,e !

l  :; . ..

b-l dy n.:n:h;;: un

,  :. u. .; "' "h i l l 'l}i p'is : p;l !: ;jh: . .

O - . l i l ln - '- ' '

u'"' '? ' 'n % _h . lllr 4 8 12 16 20 24 28 32 36 HOURS SINCE REACTOR SHUTDOWN _

.4

7 '

-w= ### *S '@

\Y ' #- - :.

\ :n;"

. i n-' . : in: . . ';

\

1 i

. :.nr- :t= ;: * )

__ !- . l

'\.t" _

\,

- - p:J._ .. . = p=- = =p=- = p.__ _ ._._. p_ . . ._ _ t .

__a.__ . . _g .

.. . L. . .

-h : - 11 .- $...

i _ _,__ _ _ . _ _.. . .. _ _ . . . . .. .

.q .5 5-3 f[;.

b-35.:$ h_ . . b_k

( ~~-

' ! . _ _ - ~ J- -

g ._ ..

k ([ . . _ .

g m

,. . .._3_ = _ . .-_7 _

.=. ; _. . _ . .

_(

4- . . _ .-.g _ _ ;.

j

- _. . + . . . . 7. . i E j = =ir..= y ===:r ~v t = = ==. .:s: a. n .

n_

=:=r-

\~ ==  := = =, --2 _ =t= =:= r =t g--- - - - gu.-m -- -..: .=... .z .g. : _;- :- ,:

. _ _ - _; a g-- _--~+- \ ..}

g:_ ;

..~...__ . ., . . ..

J. q._g_:. .=_7.= . . . . : n; m=4 .--

C. Ci=

= .

...=.. n M

's, _.__f=___1.= -.- .,

- r!_ _ .

.2 - I r___Z Z_ +C

_. tr . .i

"-~1

-'d u i

A -L=_. L .* 2nt.r Ir { =q

'q - . . _ _ . . . . . - _

.;* =__ --m . - __ __[-- , _. =$= j. g_ . . - . .(: -

i_WN. w$ww. &-6 ...e{

F --

... .- tI: _ _;: 1. .

...a_-.

L=. ;_ =

_. .. __ . -. .

.__n_".r_ . !z._:._. w

._._-w._._.!.. . g

_  ; . _ _ _ , __ _ . _ _ . _ . _; .g...._ ._- _

N

7. . _ _ _ _

'n

_ _ _. . . _ . -I -*~ l

!. - ! =.

. " . _ _71*!-- _ _ . . ,

$, - . . L .-,

I

_._m_9.___. . .

Wy e. . - . ..e_ w . + + - 4 .y. y

= . --w $N . .- .e

=:==.__u= = ._- l=.- . . . n == : .=::::. .d._ ;:

i _ r. = r = '

-+- t ,

=a - \* -r--- .=- -=; = "

1:.

?r=:=r_  ; = trr;= t = = .d.=--~22...: u :..= tu - .

!: . rj G g_ . _ . . _ _ .

.__.___p=-._..._ 47 , . . . , ,

_n'3--

.... ~ .

I ~ I-M

= c--i_~ =i= n:: -

• t

\ _ _ _ _ .

. . :; = .--t-  ; i-- __p_._

- ~

- - - ~ - -

._-g_-g_g_1n; . _ . . . _ ._]

=_ _.____

1 _

. r _....

t----  :---- -- - - + - - - ; I- ----  : - --- - l : . . . , , 1-

f o~ -

,7-. 1

__. ~ ~--* - ~ '-- ! C CC: -- [: - .

__ _ -- --._.-m. - - . . . . . ..

[ j T-'-i f;n, * - -

EN1_

X- m- ..,

k "

J~--[= 25[5 i- - d

. ~4...._.. _ ,- .. ..

..-e_-_.. .5. I.

,g , ( :

-t---u-_-----

--+ -- j g :._ 5.+L . _ _ . . __. ___

t :- --j e rA

_..__.n__._. __

. - . - ..... - p

- r==x == :- : =.

i _

Fu ^= .L.- i===I =. . I .-- - h : .

. .I i

- t =;=:== = = u ..: . t- -

.1, + '

--[___.-._.{_., 7_

I 1.

_+.__..__.L._.._.4.. .

_.. . . - . . . . . - - - . . -6 ,

4 ,._ _

1 - } __ __e-__.._ __.__. .._ . ._. _

s m u v4 4

- +- - -

_I .

e a j

? 5 g --y ----=7,=,.._... = . .= r.1 -

8 .g > ___m- _.2 = -i-_.__

_.gshg. 2-l 1 -

y h q :. { =___.

rr  :

__ -;\,-- __ ._: . .

4. ._ : . J' .

t j

j . : p, , \r- --

nun . -.. . n . :- --  ;-

.h m n

: k- ._.__

t . . _ _= n r =r- . x.. . : I- t b b -

i--- I: .: 1~_..J =;=nn;. .L : .- .

V~~- ~ ,: 'CL= =.2 *_ X1.-'~l:- _T. .$

. _ .  : _. - '.~_Z~~' 1 .

-l ;___ -+- )- ---n_. = -  : / ;= r - j

=_!__ __ _ w t\ _._+__. ..-t--~ m.p- - '=r: n h. .:

-r - '

--r---

i t x *:-_ ..__

1,xg__ 3.:31_ _ _ _ _ ____

=u\.n;;r'= E. _:1 ._._m_ ___

_ g3_ p_._ .. 4. .

.. . _ , ___. _. _ _ .___ - ..... _. ,___ _ 7 j v

-" y __ *--  !

. ;; __. , .. _-i --*-- _

{..~. _. : {_Z. .22 !,_Z:. .. .._

J . . - .

,{

'~ ~ - ~

.-~ C !I. l-

/

^

g -~T'~~- ._j. '.4 ,;

--'..-~C f

'\

I' i

. [Il!:{ ;

l .

_:{,. !k. l. .

?

:)E_*-

. .  ; _. _ .~  :\  !

t  :  : :t n.*.u:

" 2::. - c .. \1 i  !

l t -4: .

_ :t: . .

\ . I O D o CD & n u - asoa Acos a'Iom/asoa aIoum

, ,.  ? (m ..

> i

( /

( ,

) FIGURE 1.4-4 '\,s/, 'N~ ,' .

THYROID DOSE RATION FACTOR STEAM GENERATOR TUBE RUPTURE 1000 '

-ii i

.n hT m VI 'i liif T l F "T  ! j i 3 . .

I[ IIt!,!!!- tr- r- ~

! !, ll i Ild .

! '. i ; .I n' ' l li![

.... i. . 1 l -

,t l:

mitt ,; i n .

4

!D U;! i: i  !  ! 1 [I li' i .-

llf ,I

.. . .. .-f-- I I

l* f .

Ti i!!! :

L., p' =[

pn,. tr m.

4}1n .p I

i. 1 l' f n . .

6 T,i" l

p. r i.,,., i 4

g

,:. UF hl'i i 1 t I i:

8

!!P lili po lI

! I

,,. I

!i -

..p I ,

f, q,. , *l . . 1i,  !

o hh !H ti

I

!1l /

h ', '

h

c4 'i ti j '! I v g :h p i n/

t-e l!! l 4 I, 100 pg g'ifl/-7 7

0 g h./Id  ! i I

.j -.i ; l!.l.l ll l .. .

O d!! !!h h!l  ;

h '!il i IIIIlII'.

I!': u! d' . l .' ,.

I i l I i 8 ll Iil[i i

' " ~

n I . i fli 'ili

!ili j j l i p

.j g  !.

g g. , _.,

p .._ d. ~

4' jj?!g fQ[b iu :pi lil  ! i f ,

T-I  !! !!

7

t"!I Gl;  !! lll l l

f. ll Ih!

}'s.

i 1 El

,;p'.,f,;

1;L 4i; 4 ,.

' I l

,, ., . l , ,

i i. .i j ,; I;l I jl l 1 .

i. .i l r . {

'i, .l1 it, l. h I' .I i '

!H  !-

7te. t'

[*

e-ti  ! tt tt t- ~1 J'~

+- -

• t' tet }, t" "

7'

t. '

l

{i! f!i n; I .' l lth i'I;

, l1j ,

jn

'i i i  : n  ! in  ; i i en '

p

• t; , f p. :

t,

;It' Illt l:! !?'l ,4 8 8 ;l l Ih!! "j' lllt ff' fit i'l O

lb I;h ll !'

Y'

- l f > , llt --

f! - l !fl 'l b'? - !flI 0 4 6 12 16 20 24 28 32 36 40 44 48 52 56

, HOURS LINCE REACTOR SHUrIDOWN j

a ATTACHMENT 1.4-1 ,

CLASSIFICATI6N OF ATMOSPHERIC STABILITY BY SIGMA THETA & AT/6H Stability Pasquill c0 dT/6H

' classification Categories (degrees) (*F)  ;

Extremely unstable- A 00

• 22.5 _< -1.2 Moderately unstable B 22.5 > 00

• 17.5 -1.2 to -1.1

. Slightly unstable C 17.5 > 00

• 12.5 -1.1 to -0.9

, 1 Neutral- D 12.5 > 00

• 7.5 -0.9 to -0.3 l

Slightly stable .

E 7.5 > 00

• 3.8 -0.3 ta 0.9 c in . -

l Moderately stable -F 3.8 > 00 2.1 0.9 to 2.5 Extremely stable G 2.1-> 00 >2.5 ,

4 NOTE: WHEN WIND SPEED IS BELOW 3 MPH, DO NOT USE 00 FOR STABILITY CLASS DETERMINATION.

I L

e O

)

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

p 9

ATTACHMENT 1.4-2 WHOLE BODY DOSE RATE CONVERSION FACTORS l,  :

N ,/

30 1 1

N N i

^ .

25 x ,

x i

\ l i

1. \ t l \ j 3

\ '

\

20 - '

\

\ .-

g g

\

~

_ 15 x to ' \ t e X ~

~  !

o '

N 1 x I

U ,

! \

N p N g x .

< 3 .c ,

x e g i 10 M " U  ! 'x x ,

o i N  !

C i N .

' 'A c N i O .

1%  !

CC w 5 p z,

g  :

= ,

I i l l .

l l -

I ,

0 ,, .

i l i ,

0 2 4 6 8 10 12 I

\.

TIME SINCE REACTOR SHUTDOWN (HOURS)

4 i

O t

ATTACHMENT 1.4-3. $

BACKUP DETERMINATION OF ATMOSPHERIC STABILITY CLASS s'

i Surface Wind Speed, Day Night (at 50 meters) Incoming Solar Radiation Thinly Overcast

. mph Strong Moderate plight > 1/2 low cloud < 1/2 cloud

<4 A A-B B F G 4-7 A-B

• B -C E F

'7-11 B B-C C D E 4

11-13 C' C-D D D D

>13 C D D D D

- The neutral class D, should be assumed for overcast conditious during day or

' night.

" Strong" incoming solar radiation corresponds to a solar altitude greater than 60' with clear skies; " slight" incoming. solar radiation corresponds to a solar altitude from 15*-35' with clear skies. Cloudiness will decrease incoming solar radiation and should be considered along with solar altitude when determining solar radiation. - Incoming radiation that woula be strong with clear skies can

-be expecter' to reduce to moderate with broken (5/8 to 7/8 cloud cover) middle ,

? clouds and to-slight with broken low clouds. Night refers to the period from one hour before sunset _to one hour after sunrise.

1 a

?

4 9

a w-p , -e r., -..a----, ,....,.-,4 -

,_,e,.--,,_mev. .m-,-,w,, m,,,,,e,-rv ,,,,,,,3y,v.,-w.m,m.w-,,r,,.., yc, . ,,% =,m,.e-,.,-,,--,.ven,- -,-em,.g-.,re---

1

.i 1. : .4

.. . .amey Pw::aw m3 PCPULAIMN C ATA

.g3 j. u Yr 10-miles D t ,  :.gn[' h h,4.N .

i6 C h;&\) b( W l;$ o &

o s

,6 q.

'[E n y. -J,ld % 2 f, Ul'

- .]Lb l t.I;

.i= .ii 4 .j,, _. 35 - .'d 1 l lI_ . Di sli 2#.

. :s'..'5 47 l

"0-

==

A Q ,J.ZEr.. Tr_ ">HT~{ ~ T~\ \ ~.~jT_li_ G]i.3g "

kN li i G !"' s *I \ _ ji G f i : /;

I

t! ..- --

m 2. Ji - --. . - - s _. .,j ,

d i ---4ij,l b l.- : -- \- .[ i-.. . _ ,[_  % ~ ~ [.- 5- miles M

gg d6D%* -w1 -

C_ .u __

W- -'1' S_. -

,j .s, 6.f{, .

b, i33 =i

-I d1 ,. \s y

7 1

0.. 3 8

630 l , f.. ,f ...

,N, ,,,, =

, s fi U $' 9 1b0 1Y .

5'$.g .

Q'._ --

$ k ?6

n. gf-o y~[.. s.r

... 1

.f ,

J,K O a.- - .p w: + . ,n

( ) 3 .C 10 -

x ,/ .

f .G I B S!O,N } ,

f.:.c:w:z.P .p- j-, _ .7 . - 4,-z3a [.

.:= r. w . , ( 130 J '2

... a ,.c.e.s___ =

s .-

4 j'

5 ,y 5 fj. i iSIflIl COT

~

g .] 270[k

'" ' ~

N' '* 100

{n1~"*',Ld 7 ' ^ ~]E,7{ /

Io 4E:=A} .*. ====t- C -

S Y. t. '% \

.- a /

g 3, \t ' I

,7 ;'- %3 r l 120

... . i 1._.. ,7.( . .' @$' .,

95

!h g 120  :- . _

r. 7- lg .! l -. . .. I. l. i jn T d T, j 120 ' .' - .:.-

lv _f-

.- 2300)/.0.gfk;k.,,,].

m

~~

(  : ..

f, , ( Y . g\

~

M\I,p'tW. U_ia )!= ad!"7MQf ~f .};

v

.. 2 -9 I

% 0.~.

_bfi d 'eW O

._....l

/ i.:

he.rt.l r 12opg Mi. Q ;-

e-t 2.-

a lg e130 i (,

~ 't.

. :e bl p.f m :. }%. ? 5 40 [l . qj

(_) [

~2 hf  : (~ ~

N f f, m

. g~

Q.) ~~'*

,, j b

N~ ' '

. - Tv. o ~;i s u es

?

s. t..

g EPIP 1.5 fv HINOR

(

\

Revision 5

\m- 11-04-83 PROTECTIVE ACTION EVALUATION 1.0 PURPOSE The purpose of this procedure is to provide a basic guide to determine protective action recommendations to b9 given to the public authorities and to provide a method to transmit these recommendations and other essential data for assessment to the appropriate public authorities.

2.0 REFERENCES

2.1 NUREG-0654, Revision 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," November, 1980.

2.2 NUREG-0654, Appendix 1, " Emergency Action Level Guidelines for Nuclear Power Plants."

73 i

4 PRECAUTIONS & LIMITATIONS

'b d 3.0 3.1 Ask for the name and title of the person or agency being contacted prior to transmitting any information.

3.2 If unable to contact an individual or agency, continue with the transmissions to the other individuals or agencies and then attempt to contact the persons or agencies who have not been contacted.

3.3 All actions and recommendations should be appropriately logged.

3.4 If the radiological release duration is unknown, assume a duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for use during an evaluation of the need for a protective action recommendation.

3.5 When protective action recommendations are made, consider the recom-mendation over a 90* sector centered on the average wind direction and a full 360' area near (2 miles) the plant.

4.0 INITIAL CONDITIONS 4.1 Applicable portions of EPIP 1.2, " Plant Status," completed.

4.2 EPIP 1.3, ." Estimation of Source Term," completed.

} 4.3 EPIP 1.4, " Radiological Dose Evaluation," completed.

- (J 4.4 Site Emergency or General Emergency has been declared.

~ , -. . .

[ r-EPIP 1.5

-, Page 2

[D .

1 5.0 PROCEDURE 5.1 Technical Support Manager-5.1.1 Obtain the completed attachments of EPIP 1.4, " Radiological Dose Evaluation," from the person completing them.

5.1.2 Review the results of the dose projection calculations and deposition calculations for all affected areas.

5.1.3 Review Attachments 1.5-1 and 1.5-2.

5.1.4 Based on actual plant conditions, expected plant conditions in the future, weather conditions, local protection avail-able to the public, evacuation times and any other constraints, determine the most appropriate Protective Actions to reduce exposure to the public and relay the information to the emergency support center.

5.2 Emergency Support Manager NOTE: THE FOLLOWING STEPS MUST BE DONE BY THE EMERGENCY SUPPORT MANAGER OR HIS DESIGNATED ALTERNATE. UNTIL HE ARRIVES IN C s\ THE EMERGENCY SUPPORT CENTER, THE SITE MANAGER IS ACTING AS EMERGENCY SUPPORT MANAGER. UNTIL THE TSC IS ACTIVATED THE SHIFT SUPERINTENDENT HAS THE RESPONSIBILITY FOR MAKING A RECOMMENDATION FOR PROTECTIVE ACTION IF APPROPRIATE.

5.2.1 Review the recommendation of the Technical Support Manager and/or Rad / Con Waste Manager.

5.2.2 Complete Section 2 (status update form) of the incident report form contained in the offsite agency notification procedures.

5.2.3 Contact the NRC and the persons and agencies notified or.

NAWAS of the emergency and provide the information contained in the status update form to them.

5 . 2 .'4 For a General Emergency, form EPIP-16 in EPIP 5.3, " General Emergency - Offsite Agency Notification," shall be used as the basis for. followup messages to offaite technical per-sonnel such as NSSS vendor and corporate engineering staff.

s s s .

.?

ATTACHMENT 1.5-1 4

Recommended protective actions to reduce whole body and thyroid dose from exposure to a gaseous plume i Projected Dose (Rem) to

Individual in General Public Reconmended Action (* Comments Whole body <1 No planned protective actions.( } Previously recommended l or State may issue an advisory to seek protective actions may Thyroid <5 shelter and await further instructions. be reconsidered or terminated.

I Whole body 1 to <5 Seek shelter as a minimum. If constraints exist, special or Consider evacuation. Evacuate unless consideration si.ould be given Thyroid 5 to <25 constraints make it impractical. for evacuation of children Monitor environmental radiation levels. and pregnant women.

Whole body 5 and above Conduct mandatory evacuation. Seeking shelter would be'an or Monitor environmental radiation levels alternative if evacuation Thyroid 25 and above and adjust area for mandatory evacuation were not immediately possible.

j based on these levels.

! Control access.

(a)These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take into consideration existing conditions and the dangers associated with certain protective actions.

9 (b)At the time of the incident, officials may implement low-impact protective actions in keeping with the principle of maintaining radiation exposure as low as reasonable achievalle.

Reference:

Abstracted from EPA 520/1-75-001, "Hanual of Protective Actions Guides and Protective Actions for Nuclear Incidents," Table 5.1 (Revised 6/79)

'M g.

(]

s j

/

, 1-

/

?% %J %d 9 ATTACHIENT 1.5-2 SUsetARY OF PERSONNEL DOSE RATE /PIOJECTED DOSE CO9MI1?ENT ACTION LIMITS Declare Evacuate R/hr - Dose Rate Action Limits

, , Consider Limited or Plant e I Evacuation - Monitor and Contryo)b Plant b Emergency R - Projected Dose Comunitment Action Liwits to D Cvacuation Workers m

u en

$ 8g.n" "

Maximum

' $~ '88 Non-Voluntary

'$a C$ 8"

>MPC Spill Cen. Areas 1.5 R (or 3 R Beta Limit for Emergency Workers d

$ 5:0 M Fire >40,MPC/ hrs 0.1 R/hr Skin Dose)

I e l ,

I I I I 0.01 R/hr 1R SR 25 R o

u

$] u$ ( Advise Population to Seek Shelter H i Recosamend Evacurtion of General t

/

g @, $ 0 M, L Public in Effected Area u

f"8 G 4#*

j o

Consider evacuation of Y j , women and children 4c- 8*H g ,e o umM 0 p. W k Monitor an.1 Control ) .-

un g y Y - r~

D N U'o Consider  ! Evacuate 8

Consider Luited or u N. . evacuation of W I Emergency A 2 W

g Plant Evacuation - p o '^ j ewrgency Workers g Monitor and control a ,,, ,ogg ,,,,

H d

• e, uu O

h EYdE E E Maximum

" "~v I""IY

% E se f m260 MPC - Kr..

(I-lil MPC = 9E-9)

Limit for  %

Emergency Workers M >MPC >40 f1PC/ hrs .9 R 3R I I l l l l l g se .9 R SR 25 R 125 R Recommend Use

$o of KI - Emergency Advisu public to seek / Recomunend Evacuation of General oga shelter. Consider i Public in Ef fected Area rkers M1y gge evacuation of women e so 4 and children.

Nmc

• 4uoB E3 EEo k Monitor and Control '

$$u .' NOTE: EXPOSURE LINES FT 10 SCALE

A.

r EPIP 1.7 p MINOR Revision 3

~\-}

e 11-04-83 EVALUATION OF CORE DAMAGE (

1.0 PURPOSE The purpose of this procedure is to estimate core damage using a mathema-tical model based on an actual primary coolant sample activity, estimated volume introduced into the primary system through safety injection and a correction' factor based on the time since reactor shutdown. This evaluation should be performed by the Core Physics Cc dinator or a Duty Technical Advisors and routed to the Technical Support Manager and Site Manager.

2.0 REFERENCE Calculations performed by the Nuclear Engineering Section of Wisconsin Electric Power Company documented in a report to G. A. Reed dated October 5, 1981 "C & HP Items Related to NUREG-0737."

3.0 PRECAUTIONS 3.1 If fuel damage or loss of reactor coolant system integrity has occurred, (d')

some or all of the following would be present:

The letdown radiation monitor (1R9) or the failed fuel radiation 3.1.1 , monitor (2RE-109) may be unusually high or offscale.

3.1.2 The containment radiation monitors (1Rll & 1R12 or 2RE-211 &

2RE-212) may be unusually high or offscale.

3.1.3 The containment area monitors (lR2 & 1R7 or 2RE-102 & 2RE-107) may be unusually high or offscale.

3.2 Health Physics p'rocedures and requirements must be followed when applicable (e.g., when entering a high radiation area).

3.3 Evaluation of the radiation monitoring system readouts and radiological hazards must be completed prior to any attempt to enter the auxiliary building to take a primary sample.

4.0 INITIAL CONDITIONS 4.1 Applicable portions of EPIP 1.2, " Plant Status," are completed.

O.

t x

EPIP 1.7 i

, -(\ Page 2 3

v/

4.2 A reactor coolant sample has been taken and a contact reading of the sample bomb has been taken or a final total sample activity has been completed by implementing EPIP 7.3.2 " Post-Accident Sampling &

Analysis of Potentially High Level Reactor Coolant."

4.3 A contact reading of the sample bomb in R/hr was taken and listed on form EPIP-30 or an actual sample activity has been received from lab analysis.

5.0 PRIMARY COOLANT SAMPLE ACTIVITY ESTIMATE PROCEDURE 5.1 Note the time of the sample contact reading taken in Section 4.3 on form EPIP-33.

5.2 Determine the amount of time since reactor shutdown to sample contact reading using the equation:

Reactor Shutdown Time - Contact Reading Time = Time Since Shutdown 5.3 Convert the R/hr reading obtained using the teletector to Ci/ml using Attachment 1.7-1.

, css 5.4 Enter the conversion factor from Section 5.3 on form EPIP-33.

(J) 5.5 Determine the estimated Sample Activity using the equation:

Estimated Sample Activity (Ci/ml) =

Sample Bomb Contact Reading * (R/hr) x Conversion Factor .j "

i

" Contact reading is on shielded sample bomb which incorporates j 3 inches of external solid lead shielding.

5.6 Enter the estimated Sample Activity on form EPIP-33.

6.0 EXAMPLE Coolant Sample Activity Estimate (Shielded Bomb)

Teletector reading = 2.75 R/hr Reading time = 1700 l

l Reactor Shutdown Time = 0900 Time since shutdown: 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> - 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> = 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> h 2.75'R/hr x 5.93 x 10 Cip ml = 1.63 x 10' Ci/ml

I .

,- s-

.n-%,.k

( s. +

M- '~ EPIP 1.7 Page 3

.p ,.

i  ;

G 7.0 CORE DAMAGE ESTIMATE PROCEDURE 7.1 Calculate the estimated percentage of core damage using the following formula and table of correction factors. Interpolate correction fac-tors for times between those listed. Use best estimate for safety injection voltime.

7.1.1 Estimated Sample Activity (ESA) Ci/ml 7.1.2 Estimated Safety Injection Volum'e (ESIV) gallons T

Available safety injection dilution sources are:

7 Acchmulators: 2 at 8,000 gallons each Refueling water storage tanki 275,000 gallons Boric. acid storage tank: 1 of 3 at 5,000 gallons each Spray additive tank: 2,574 gallons 7.1.3 Correction FactT:ir for Time Since, Shutdown [CF(t)] hours

(,

7.1.4 Enter the values from Sections 7.1.1, 7.1.2, and 7.1.3 on

• form EPIP-33. Calculate the percent core damage using the following formula aLd Attachment 1.7-2 and enter the result on form EPIP-33. ..

+

Percent Core Damage (%) = ESA x (3 C t 7.1.5 Route form.EPIP-33 to.the Site Manaq r and Technical Support Manager.

8.0 EXAMPLE ..,-

Percentage Core Damage Estimate

! 1 Estimated Sample Activity = 1.63 x 10 Ci/ml Time since shutdown = 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Estimated safety injection volume = 2,000 gallons Percentage core damage (%) = 1.63 x 10- Ci/ml x (32,500 + 2,000) 547 Percentage core damage (%) = 9%

\.j

\

i 1~

ATTACHMENT 1.7-1 i ':

\

10

e

~,

F s

l_ g .

3 e

2%.d.-

i .1i I ... I I 1

I i 3.

J

' 2 T r 1 1. .!

Ill I  ! l!. 1 1 i 'I!

l  !  !. I!

ii i # # i1. 6 r ; e i 1 3 1

-~

e

--.

7 X^ g gN .h ,

.w

~

4 -_ . _

~

N '

rp hg a l - -'

f M% 12 1!

ms .

pw .

ZU .

8w i .

~ l f e

I I

I=I Ifi i i II 117 i

I I I

. I

. t M 6 !!

r-

'E i ' ...

I' Ii.e

!]!

i a i

1 e . i il1.

i

! t i F I i J 4 III I y 6 + e l1  ! 6 {'i i i 13e I i 1 --

e -

9 sr 4 _

^ * > '- _. .

I 4 _

g 'N

_ i l

a

G.

l

,.. R ,

L ., s 1 ,i  ! 2 !ili I If ( l i i 11:1 .I !

[ i r ri iii . g , I ,I '

i g r i I

e i j i  ; a i j i i

~2

• a a . . e a r e e so a a l 10 , e e i a e io a a . a e r e e se 1 10 100 1000 TIME SINCE REACTOR SHUTDOWN (HOUdS) 4 '

I c\ w

1 1'

e

, i ATTACHMENT 1.7-2

,/ \.

\ )

LJ 1000 *

~

• S

'w:-

7 .-

l

-s

+_r.

-m ~-..-. g

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

.w 7 7 ... . . . -

-_. ._ 2 .._

=m - _. __ _- _-------

.6 4

_.'s.M-

. . _ .._. ,'+_ .

=

. .-d.- -

l M."48-K,.

m'. W

, 1 l..: i. ! % N" y 0++ +  !

iii i . 1 . 1 i

, mo ri; i i . , i A

100 '

d *

.7d - ,1 '

\

r- x .

8 + .. .~~- --w- _

_4 4 ;-

. 1 g *~~*

D4 m e im; '

ZM O-my' '

F-+

l

(

f'g N 04 3 - :e j

-i O

l

.g

-\s -

O "

O

,r%---+; i i i ...i ... . .. .

] 'I'. i 1 i f i fI' I'. !il' I I [ l l' l '

i 10 ' ' ' ' ' ' ' ' ' '

(

. r a 1 f

h _ _ _ . . . ,,- . .__ - . . _y ---e- - _ . - - -- . - - - - --

l ,

i 4

l*

8 _ . _ . ._ .___ _ _ . - .- _ _ . ,_ -- - - - . .

2;._.  ;

• I

-. .=Z ZT*'

+...

i . . . . . l Ti'.

i I i i : 1i- .1 . i1 oi- 1..i r

is r 1

1 i r 1 i  !:i 1

1 1

- 1 l ,.i r!! I - l 'l I 3 3 4 4 6 e S te 4 4 4 e e e . 50 3 3 4 6 6 8 91C l

1 1 10 100 1000 TIME SINCE REACTOR SHUTDOWN (HOURS) i

/^Ni

\v/

. - _ . _ _ - i

EPI? 3.3 MINOR Revision 4 11-04-83 ALERT - 0FFSITE AGENCY NOTIFICATION 1.0 PURPOSE The purpose of this procedure is to establish the initial offsite agency

. notification responsibilities in response to plant conditions classified as an Alert in accordance with epi 2 1.1, " Initial Classification." Necessary phone numbers are included in form EPIP-23, "Offsite Agency Emergency Call List."

2.0 -REFERENCES None 3.0' PRECAUTIONS AND LIMITATIONS 3.1 This procedure and its completion in a timely msnner should not prevent

! the operators from bringing the plant to a safe condition. This priority

, will protect the health and safety of the general public to the greatest degree.

3.2 Obtain the name and title of the person being contacted prior to i transmitting any information.

, 3.3 .If unable to contact an individual or agency, continue with the notification of the other individuals or agencies and then attempt to

[

contact the persons or' agencies who have not been notified.

3.4 All actions and notifications should be appropriately logged on form EPIP-23,-"Offsite Agency Emergency Call List," or form EPIP-12 (attached), " Initial Incident-Report Form."

3' 5

. The. notification of State and local emergency government agencies must be made within 15 minutes of the initial classification as an alert, 4.0 INITIAL CONDITIONS

. Alert emergency conditions exist.

l-L 5.0 . PROCEDURE 5.1 -Designee 5.1.1 Complete the initial incident report form (form EPIP-12,

. attached) using the information given by the Shift Superin-tendent. Examples of emergency response include: shut the unit down, call;in additional firefighters, and secure the

( doors against high wind.

l f . . - . . _ , - _ . _ . . . , _ _ . _ _ . _ _ _ . . _ . _ _ . . _ _ _ _ . _ _ . . . . _ _ _ _ . _ . . _ _ _ . _ _ . _ _ _ _

7st# }

.. p EPIP 3.3 f .

Page 2 5.2 Security Lieutenant or Designee

.5.2.1 Pick up the NAWAS handset and make the following transmission:

THIS IS POINT BEACH CALLING WARNING CENTER 2, MANITOWOC COUNTY, AND KEWAUNEE COUNTY. THIS IS POINT BEACH CALLING WARNING CENTER 2, HANITOWOC COUNTY AND KEWAUNFE COUNTY.

NOTE: THE THREE CENTERS SHOULD RESPOND. NOTE ANY CENTERS NOT RESPONDING AND PROCEED WITH THE PROCEDURE.

J f

5.2.2 Transmit the initial incident report form over the NAWAS system. Ensure that the three centers fully understand the transmission. i 5.2.3 Contact by telephone, the centers (noted in Step 5.2.1 of this procedure) which vere unable to be contacted over the

\- NAWAS system (phone numbers listed on EPIP-23, "Offsite

. d Agency Emergency Call List").

5.2.4 Read the initial incident report form. Ensure that the information given is fully understood.

5.2.5 Pick up the NRC Operations Center, Bethesda, dedicated line.

When a response is heard, read the initial incident report form.

5.2.6 If no response is heard, contact the NRC Cperations by

, telephone (telephone number listed on form EPIP-23,

, "Offsite Agency Emergency Call List") and repeat the appli-cable portion of Step.5.2.1.

5.2.7 Have the Shift Superintendent make an appropriate entry into the NRC Operations Center, Bethesda, phone log.

5.2.8 Attempt to contact the NRC Resident Inspector (telephone number listed on EPIP-23, "Offsite Agency Emergency Call

~

List"). Inform him of the Alert emergency condition.

5.2.9 Notify Kewaunee Nuclear Power Plant (telephone number listed on EPIP-23, "Offsite Agency Emergency Call List"). Inform them of the alert emergency condition.

l

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

1

- il%

4_,

F EPIP 4.3 MINOR Revision 2 s_/ 11-04-83 SITE EMERGENCY - 0FFSITE AGENCY NOTIFICATION 1.0 PURPOSE The purpose of this procedure is to establish the initial offsite agency notification responsibilities for response te plant conditions classified as a site emergency in accordance with EPIP 1.1, " Initial Classification."

Necessary telephone numbers are included in form EPIP-23, "Offsite Agency Eaargency Call List."

2.0 REFERENCES

None 3.0 PRECAUTIONS & LIMITATIONS 3.1 This procedure and its completion in a timely manner should not prevent the operators from bringing the plant to a ssie condition. This priority will protect the health and safety of the general public

'~') to the greatest degree.

[V 3.2 Obtain the name and title of the person being contacted prior to

transmitting any information.

3'. 3 If unable to contact an individual or agency, continue with the l notification of the other individuals or agencies and then attempt to i contact the persons or agencies who have not been notified.

3.4 All actions and notifications should be appropriately logged in form EPIP-23, "Offsite Emergency Call List," ~ at:d form EPIP-12 (attached) .

3.5 The notification of State and local emergency government agencies, i using primary communications systems, must be made within 15 minutes

! of the initial classification as a site emergency.

1 14.0 INITIAL CONDITIONS Site emergency conditions exist.

1 I 5.0 PROCEDURE 5.1 Designee A 5.1.1 Complete the initial incident report form (form EPIP-12, attached) using tne information supplied by the Shift j

j Superintendent. Examples of emergency response include

'~s- unit shutdown and limited plant evacuation.

. . .. J

l' EPIP 4.3 Page 2 5.2 Security Lieutenant or Designee

.~ 5. 2.1 Pick up the NAWhS handset and make the following trans-mission:

THIS IS POINT BLACH CALLING WARNING--CENTER 2, STATE PATROL

'IN FOND DU LAC, MANITOWOC COUNTY, AND KEWAUNEE COUNTY. THIS IS POINT BEACH CALLING WARNING CENTER 2, STATE PATROL IN FOND DU LAC, MANITOWOC COUNTY, AND KEWAUNEE COUNTY.

<- NOTE: THE FOUR CENTERS SHOULD RESPOND. NOTE ANY CENTERS

, NOT RESPONDING AND PROCEED WITH THE PROCEDURE.

P #

NOTE: IN THE EVENT OF AN EXERCISE OR DRILL, THE ABOVE MESSAGE MUST BEGIN.AND END WITH THE PHRASE "THIS

. IS A DRILL, REPEAT, THIS IS A DRILL."

5.2.2 Transmit the initial incident report form over the NAWAS system. Ensure that the four centers fully understand the transmission.

5.2.3 Contact by-telephone, the centers (noted in Step 5.2.1 of this procedure) which are unable to be contracted over the

(; NAWAS system (telephone numbers listed on form EPIP-23, Offsite Agency Emergency Call List").

i e

5.2.4 Read the initial incident r.3 port form. Ensure that the information given is fully understood.

5.2.5 Pick up the NRC Operations Center, Bethesda, dedicated line.

When a response is heard, read the initial incident report form.

5.2.6 If no response is heard, contact the NRC Operations by L telephone (telephone number listed on form EPIP-23, "Offsite. Agency Emergency Call List").

5.3 Designee B 5.3.1 Complete the initial incident report form (forr EPIP-12) using the information supplied by the Shift Superintendent.

, Examples of emergency response include unit shutdown and l

. limited plant evacuation.

l :-

l'

4 ,

1 g.

EPIP 4.3 Page 3 5.3.2 Determine with the Site Manager or designated representative which of the additional agencies listed on form EPIP-23, "Offsite Agency Emet Jency Call List," should be notified at this time.

5.3.3 Contact, by telephone, the agencies identified above and read the initial incident report form.

5.3.4 Ensure that the information given is fully understood.

5.3.5 Have the Shift Superintendent make an appropriate entry into the NRC Operations Center, Bethesda, phone log.

5.3.6 Attempt to notify the NRC Resident Inspector (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). Inform hiin of the site emergency.

O a

, n, ,-w,, -

e--, e w,- ~ , -

y,--m,,,, -w,+ - - - , ,-- -

'A

./'

i EPIP 5.3 MINOR Revision 2

~O 11-04-83 GENERAL EMERGENCY - OFFSITE AGENCY NOTIFICATION 1.0- PURPOSE  ;

4 The purpose of'this procedure is to establish the initial offsite agency notification responsibilities for response to plant conditions classified as a general emergency in accordance with EPIP 1.1, " Initial Classification."

!- Necessary phone numbers are included in form EPIP-23, "Offsite Agency JEmergency Call List."

2.0 REFERENCES

j None 3.0 PRECAUTION & LIMITATIONS 3.1 This procedure and its completion in a timely manner should not prevent the operators from bringing the plant to a safe condition.

This priority will protect the health and safety of the general g public to the greatest degree.

3.2 Obtain the name and title of the person being contacted prior to transmitting any information.

3.3 - If unable to contact an individual or agency, continue with the notification of the other individuals or agencies and then attempt to contact the persons or. agencies who have not been notified.

4 3.4 All actions and notifications should be appropriately logged in j- -

form EPIP-23, "Offsite Agency Emergency. Call List," and form EPIP-12 I .

(attached).

3.5' The notification of State and local emergency government agencies, using the primary communications system, must be made within 15 minutes of the initial classification as a general emergency.

4.0 INITIAL CONDITIONS

General emergency conditions exist.

5.0 PROCEDURE

~5.1 Designee A 5.1.1 Complete the initial incident report form (form EPIP-12, O,,

y attached) using the information supplied by the Shift Superintendent.

.re,.-..b-++m-,.. ...,_,o..,,..-,,rwe--.E.%- w,. ,_,.y.,,,..e , , . . .,.[,-,-w,-.4cy,-,. .-% q. ,,ww,mr,, -,,.w,-.y,,-ewr*,,,w.,,., w.x.,, .,y

, . m, ._. . ._ _ . , _ . _ m.

~'

1 _

. 6%

EPIP 5.3

= Page 2 1

.5.2 Shift' Lieutenant or Designee-

~

5.2.1 Pick up the NAWAS handset and make'the following trans-mission:

I: THIS IS POINT BEACH CALLING WARNING CENTER 2, STATE PATROL

, IN FOND DU LAC, MANITOWOC COUNTY AND KEWAUNEE COUNTY. THIS

.IS POINT BEACH CALLING WARNING. CENTER 2, STATE PATROL IN

FOND DU LAC, MANITOWOC COUNTY AND KEWAUNEE COUNTY.  !

- NOTE: THE FOUR CENTERS SHOULD RESPOND. NOTE ANY CENTERS NOT RESPGNDING AND PROCEED WITH THE PROCEDURE.

4-NOTE: IN THE EVENT OF AN EXERCISE OR-DRILL, THE~ABOVE MESSAGE MUST BEGIN AND END WITH THE PHRASE "THIS IS A DRILL, REPEAT, THIS IS A DRILL."

5.2.2 Transmit:the initial incident report form over the NAWAS system. Ensure that the four' centers fully understood the transmission.

5'2.3

. contact by telephone, the centers (noted in Step 5.2.1 of this procedure) which were unable to be contacted over the .

NAWAS system (phone numbers listed in form EPIP-23, "Off- ,

site Agency Emergency Call List"). +

I 5.2.4 Read the initial incident report form. Ensure that the information given is fully understood.

5.2.5 Pick up the NRC Operations Center,.Bethesda, dedicated line.

Wher. a response is heard, read the initial incident report form.

5.2.6 .If no response is heard, contact the NRC Operations Center, 1 Bethesda, by telephone (telephone number listed cn form ,

EPIP-23, "Offsite Agency Emergency Call List").

5.2.7 Have the Shift Superintendent make an_ appropriate-entry

, into the NRC Operations Center, Bethesda, phone log.

, e i

I.

o

.--, , -.l. ---..l,-,. ,,,,..,,,e,e-,,,..,---..--n..,. .,,.,.,,,,,,.,.,;.,,,-,n-.n.,_.--.n.,.

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

I ,

o EPIP 5.3 Page 3 5.3 Designee B 5.3.1 Complete the initial incident report form (form EPIP-12) using the information supplied by the Shift Superintendent.

5.3.2 Determine with the site Manager or designated representative

, which of the additional agencies listed on form EPIP-23, "Offsite Agency Emergency Call List," should be notified at this time.

5.3.3 Contact by telephone, the agencies identified above and read initial incident report form.

5.3.4 Ensure that the information given is' fully understcod.

5.3.5 Attempt to notify the NRC' Resident Inspector (phone aumber listed in form EPIP-23, "Offsite Agency Emergency Call List"). Inform him of the general emergency.

5.3.6 Notify the Kewaunee Nuclear Power Plant.

, g-s 5.3.7 Complete form EPIP-16 (attached).

's_- 5.3.3 Form EPIP-16 will be used as a basis for follow-up messages to offsite technical personnel such as NSSS vendors and corporate engineering staff.

(

i

- - - - , .- - ,,, , , . - - - .- , - - - - - , , - - - . , - - - . , - - , - , ~--,-.--.-+-nw.--en,

/

,J EPIP 7.3.2 iA MINOR-( Revision 9 11-04-83 POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH LEVEL REACTOR COOLANT

1.0 INTRODUCTION

r-1.1 This procedure outlines the steps necessary to collect, handle and analyze a high level reactor coolant sample which could result from gross fuel failure.

1.2 Equipment List Set up the following in the primary sample hood prior to collecting your sample: ,

'1.2.1 The equipment detailed in Figures 2A and 2B, with the exception j

- of.the sample bcmb.

1.2.2 One magnetic stirrer and one 50 ml poly beaker and a 50 ml

l. y .

beaker.

l 1.2.3 A pH/mv meter and pH probe.

1.2.4 A piston burette.

1.2.5 A lead brick wall of sufficient size to store residue from

-analysis.

1.2.6 Automatic pipets, continuously adjustable through 5 ml, or equivalent.

1.2.7 . Remote handling tools located in the cabinet below the

! hood.

1.2.8 Prepare a 1.0 liter sidearm flask with a correctly sized l solid stopper and rubber septum over the sidearm. '

l 1.2.9 Gas syringe The following equipment is also necessary for this procedure and need to be made ready.

1.2.10 The gas partitioner for H2 analysis.

Ov

h w EPIP 7.3.2

,Q Page 2 1.2.11 The special cart used for transport of the sample bomb.

1.2.12 Tools for connecting and disconnecting sample bomb; i.e.,

11/16" open end wrench or equivalent.  ;

1.2.13 Remote valve turning tool. This tool as well as those mentioned in Step 1.2.12 are necessary for sampling

-and should be taken along and placed on the sample bomb transport cart.

1.3 Reagents The following reagents are also necessary and need to be prepared.

1.3.1 0.1N NaOH for boron. Obtain a supply from normal boron analysis.

i 1.3.2 Manitol for boron analysis.

1.4 Preliminary Steps Initials 1.4.1 Standardize the pH meter.

1.4.2 Organize as much of the equipment as possible behind lead brick walls in an arrangement 1 .that allows for unobstructed view of all ,

operations with the aid of the convex mirror. '

(See Figure 2.)

1.4.3 Put new rubber septum on gas bomb.

1.4.4 Check out and prime the piston burette with fresh 0.1N NaOH solution.

- 1.4.5 Make sure that the vacuum line is attached to I the gas collection bomb'at the valve 1 location.

Open valves 1 and 2. Secure valve 3.

1.4.6 Startup the gas chromatograph for hydrogen l- analysis.

1.

2.0 PRELIMINARY EVALUATION NOTE: THIS EVALUATION SHALL BE COMPLETED PRIOR TO ANY ATTEMPf TO ENTER THE AUXILIARY BUILDING OR SAMPLE ROOM TO OBTAIN A REACIOR COOLANT SAMPLE UNDER EMERGENCY CONDITIONS.

O

EPIP 7.3.2 Page 3 J.

Initials 2.1 Possible Indication of Fuel Damage Some or all of the following would be present if fuel damage had occurred:

2.1.1 The letdown radiation monitor (R9) would be unusually high or offscale.

2.1.2 The Unit-2 failed fuel monitor (2RE-109) will be unusually high or offscale.

2.1.3 The Unit 1 containment radiatien monitors (Rll and R12) or the Unit 2 containment radiation

- monitors (RE-211 and RE-212) would be unusually high or offscale.

2.1.4 The Unit-I ccatainment area monitors (R2 and R7) or the Unit 2 containment area monitors +

(RE-102 and RE-107) would be reading unusually high or offscale.

' 2.1.5- The auxiliary building stack monitor (R14) would show a significant increase due to auxiliary building airborne activity from the letdown and charging pump areas.

2.1.6 Evaluation of Sample Room Conditions

a. The sample room area monitor (R6 or RE-106) and charging pump area monitor (R4 or RE-104) would give an indication of conditions in the auxiliary building and sample room.

b. After evaluation of the radiation monitoring system readouts, Health Physics will determine l what airborne and radiation surveys would be appropriate before auxiliary building entry.

c. Verify the requirements for auxiliary building sample room entry, i.e., (1) RWP requirements, (2) clothing requirements, (3) respiratory requirements, and (4) dosimetry requirements including extremity dose monitoring requirements, and (5) health physics coverage requirements p including timekeeping.

o 1

b..

• EPIP 7.3.2 Page 4 v

Initials

'2.2 Possible Loss of Component Cooling 2;2.1 Verify that component cooling is still in service i to the affected unit., Sample cannot be obtained without component cooling to sample room heat

.exchangers.

i . 3.0 REACTOR COOLANT SAMPLING PROCEDURE NOTE: THIS PROCEDURE SHALL'NOT BE INITIATED UNTIL THE EJALUATIONS' DIS-4

~ CUSSED IN SECTION 2.0 HAVE BEEN COMPLETED AND REVIEWED BY DUTY &

F CALL SUPERINTENDENT.(COORDINATOR), DUTY HEALTH PHYSICS SUPERVISION AND THE DUTY SHIFT SUPERINTENDENT, AND THEIR APPROVAL HAS BEEN GRANTED.

i 3.1 Collecting a Pressurized Sample (Refer to Figure 1)

NOTE: THE FOLLOWING STEPS WILL BE ACCOMPLISHED UNDER THE

' DIRECTION OF HEALTH PHYSICS SUPERVISION AND ONLY f AFTER COMPLETING SECTION 1.0 0F THIS PROCEDURE.

4 1 3 .1.1 ' The following steps:(a through i) must be accomplished before. opening the incontainment sample isolation valve 955 (Step 3.1.2) and the

hot leg sample isolation valve 966C (Step 3.1.3).

a. Verify that the demineralized water header pressure is approximately 100 to 120 psi.

NOTE: 'THIS STEP MAY'BE. DELETED IF REACTOR MAKEUP WATER IS USED FOR THE FLUSH.

b. Proceed to the sample room and install the shielded sample bomb on the outside wall of the sample room using the fittings provided.

If the bcab is already installed, verify that the fittings are tight.

- CAUTION: BEFORE REH0VING THE SWAGE LOCK CAPS

! TO INSTALL THE BOMB, OPEN VALVES l 939,.940 AND 941 TO RELIEVE SYSTEM l- PRESSURE. CLOSE VALVES 939, 940 AND 941. PLACE A WASTE BUCKET DIRECTLY UNDER THE BOMB. USE A PAPER TOWEL SHIELD AND RUBBER GLOVES WHEN REMOVING' CAPS. *

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

EPIP 7.3.2 O Page 5 Initials

c. Verify that the dimineralized water line is connected from valva 945 to the de-mineralized water manifold. Open demineralized H2 O valves 945, 947, and 948 and check for' leaks on the bomb fittings.

Shut valves 94's,. 947, and 948.

d. Enter the sample room and close the following valves on the sample panel.

1. 961C - Normal hot leg sample bomb inlet.

2. 964C - normal hot leg sample bomb outlet.

3. 965C - normal hot leg sample bypass.

4. 968 - normal hot leg return valve.

5. 971 - normal hot leg sink sample valve.

e. Notify the control r eca that- the failed fuel monitor (RE-109) will be taken out-of-

, service for sampling; then close:

c 938D - detector RE-109 inlet valve 938A - detector-RE-109 outlet valve

f. .Further verify that there is component cooling flow to the sample room heat exchangers by '

l viewing the local flow indicator (FI-603) on the sample panel.

g. Open the following valves on the sample panel.

1. 969A - sample system purge to volume l control tank.

2. 956C - normal hot leg sample supply valve.

3. 990 - residual heat removal sample supply valve.

h. For Unit 2 verify that the DI water valve (2-991) located on the east wall of the sample room is open.

s

EPIP 7.3.2

- A Page 6 Initials

i. Leave the sample room and position the following valves wide open. These valves are located on the sample room wall.

1. 939 - sample bomb inlet.

- 2. 941 - sample bomb outlet.

NOTE: FOR DRILLS AND TRAINING EXERCISES OPEN VALVES ONLY ONE-QUARTER TURN TO ELIMINATE N-16 GAMMAS.

j. Fully open bomb valves 9B, 9A, 8A & 8B.

3.1.2 Open the incontainment hot leg sample isolation valve (valve 955) and the residual heat retaoval sample isolation valve (valve 959) by means of the switches located outside the No. 1 pipeway for Unit 1 or No. 4 pipeway for Unit 2.

4 CAUTION: IF'THE AFFECIED UNIT IS ALREADY ON RHR, LEAVE THE LREA IMMEDIATELY AFTER OPENING VALVE 959 AS BACK-GROUND RADIATION' LEVELS WILL RISE SHARPLY.

If the valve No. 955 will not open because of containment isolation, perform the following i steps (1 through 3).

1. Request that the Control Room reset the con-tainment isolation signal.

2. Turn the local control switch positions for valves 951, 953, and 955 to the "close"

! position.

3. Turn the local control switch for valve 955 to the "open" position.

NOTE: SECTION 3.1.2 MUST BE ACCOMPLISHED BEFORE SAFETY INJECTION RECIRCULATION HAS BEGUN.

~-

l

,- -, , ,, ,-, ,---- g- y- - - ,-,---r,--.--.~,,.e,,.,--e.- , . . - . , . , , ye - ,- ,m,,,- ,,,e,- - .,_.p-,,, .. -_--w,v. ,-m,n,, - - -

4 EPIP 7.3.2 ff O Page 7 U-Initials 4

3.1.3 Leave the primary auxiliary building and request control room to open the hot leg sample isolation valve (966C).

3.1.4 Verify sample flow by an increase in the radiation level.

3.1.5 After 15 minutes, return to collect the sample.

Close valves 9B and 9A and then valves 8B and 8A using the remote valve operating tool. Make note of the sample collection time.

NOTE: DO NOT DISCONNECT THE SAMPLS BOMB UNTIL SAMPLE FLOW IS SECURED AND THE DI FLUSH 1

, IS COMPLETE AS EVIDENCED BY REDUCTION IN RADIATION LEVELS.

f 3.1.6 Request control room to immediately close the l hot leg sample isolation valve 966C.

NOTE: IT IS VERY IMPORTANT THAT THE HOT LEG

^

SAMPLE ISOLATION VALVE 966C IS CLOSED PRIOR TO STARTING THE DI FLUSH. WAIT FOR CONFIRMATION FROM THE CONTROL ROOM.

4.0 CAMPLE LINE FLUSHING 4.1 Leave valve 939 open, and fully open valves 940 and 941.

Open valves 945 and 946. Allow the lines to flush for at least 15 minutes.

, NOTE: DO NOT REMAIN IN THE AREA 0F THE SAMPLE STATION DURING THIS FLUSH.

7 4.2 After about 15 minutes return and measure radiation levels.

r If e Chemistry & Health Physics Supervisor determines that the levels are satisfactory, close whitey valve 946 and using the remote valve tool, close valve 9_39. Then open valve 947 and valve 948 and allow about a 15-minute DI flush.

4 9

(

v- - c-- ..,w ,, y-,,-, y --w-,., .,-,-,-,-----g-,r---

EPIP 7.3.2

'p . Page 8

\j Initials 4.3 After about 15 minutes,_ close valves 940 and 941 with the remote valve tool and then close valves 945, 947, and 948.

Disconnect valve 945 from the demineralized water manifold and cap both ends. Disconnect the sample bomb from the fittings using a paper towel to prevent spraying. Remove the_ shielded sample bomb from its support. Remove excess liquid from the top and bottom bomb fittings with a syringe and dispose behind lead shielding. Replace the Swagelok caps on the wall fittings and on the' bomb.

Transport the bomb, remote valve tool and wrenches to the chemistry lab on a cart.

NOTE: AFTER DRILLS AND TRAINING EXERCISES, RETURN ALL EQUIPMENT AND VALVE LINEUPS TO NORMAL. (SEE SECTION 4.4).

4.4 Enter the sample room and notify control room that the failed fuel monitor (RE-109) is to be returned to service and that the sample room valving is to be returned ,

to normal.

('~'} .

b' 4.4.1 Close Valves:

1. 961C - Normal hot leg sample bomb inlet

2. 964C - Normal hot leg sample bypass

3. 965C - Normal hot leg sample bypass

4. 971 - Ncrmal hot-leg sink sample valve

5. 939 - High level sample bomb inlet

6. 940 - High level sample bomb bypass

7. 941 - High level sample bomb outlet

8. 945, 946, 947, 948 - Demineralized water flush valves NOTE: DISCONNECT VALVE 945 FROM THE DEMINERALIZED WATER MANIFOLD. ADVISE CONTROL TO REDUCE DEMINERALIZED WATER HEADER PRESSURE TO NORMAL.

v

EPIP 7.3.2

- /"' Page 9 LJ Initials 4.4.2 open Valves:

1. 938B - Failed fuel monitor RE-109 inlet

2. 938A - Failed fuel monitor RE-109 outlet

3. 956C - Normal hot leg sample supply valve

4. 968 - harmal hot leg return valve

5. 969A - Sample system purge to volume control tank

6. 966C - Hot leg sample isolation valve.

5.0 SEPARATION OF THE PRESSURIZED SAMPLE AND ANALYSIS OF THE GASEOUS AND LIQUID COMPONENT (Refer to Figures 2A and 2B) 5.1 . Collecting the Gaseous Sample From the Pressurized Sample l

L g,,) 5.1.1 Place the shielded sample bomb in the sample holder.in the primary sample hood.

5.1.2 Connect the sample bomb to the shielded gas collection bomb by means of the fittings

provided. Place lead bricks in the area of this connection for shielding.

5.1.3 Connect the valve manifold to the opposite end of l the sample bomb and verify that valve 11 on the' l- manifold is open.

5.1.4 Make sure that the vacuum line is attached to the gas collection bomb at the valve 1 location.

Open valves 1 and 2. Secure valve 3. Evacuate the gas bomb and connecting lines. With vacuum still on, secure valve 1. Secure vacuum.

i (D

\_/s i

I

l 1

.. l 1

EPIP 7.3.2 Page 10

{'N A

s_ l l

Initial 5.1.5 Before proceeding, make sure no inleakage has occurred into the gas bomb by observing the vacuum gauge reading. Using the remote valve tool, fully open valves 9A and 9B. Open valve ,

8A one-quarter turn. Crack open valve 8B and control degassing by throttling valve 8B.

Allow the system to degas for 5 minutes.

Check that valves 9A and 9B, 8A and 8B are fully open. Close valve 2.

NOTE: OBSERVE THE VACUUM GAUGE. THE VACUUM SHOULD DROP VERY SLOWLY. IF THE DROP IS TOO RAPID, CLOSE VALVE 8B SLIGHTLY.

DROP SHOULD BE 5-10" HG/ MIN.

5.2 Analysis of Gaseous Sample 5.2.1 Hydrogen

/ Use a syringe to draw a 1 cc sample. Use the k _,T

/ injection port on the g&s partitioner for this analysis.

5.2.2 Radioactive Noble Gas Use a syringe to draw a 1/2 cc sample and inject this into the flask prepared in Section 1.2.8.*

Allow 30 minutes for thermal mixing. Draw a 1 cc sample of this dilution and proceed as l normal.

l

• Additional dilution should be performed if the contact reading is >l mr/ hour.

I NOTE: SEE SECTIONS 7.0 AND 8.0.

! 5.3 Collecting the Liquid Sample From the Pressurized Sample ,

I NOTE: IT IS EXTREMELY IMPORTANT TO VERIFY THAT VALVE 2 HAS BEEN CLOSED BEFORE PROCEEDING.

5.3.1 Open valve 3 slowly. Allow the liquid sample

.to drain into the 50 ml beaker. Direct a slow l stream of air through the vent line on valve 3 j if necessary to recover the total liquid sample.

~_ l ,

5.3.2 Close valves 8A and 8B, 9A and 9B, and valve 3.

EPIP 7.3.2 Page 11 a .

Initials 5.4 Analysis of Liquid Samples 5.4.1 Boron /pH Analysis

a. Transfer a 5 m1 sample using an automatic pipetter into a 50 ml poly beaker containing a stir bar.

b. After transfer is complete, record the pH.

c. Plug in the magnetic. stirrer, add mannitol, and proceed with the boron analysis.

NOTE: IF THE PRIMARY SYSTEM HAS BEEN BORATED, 5 ML OR MORE OF TITRANT MAY BE NEEDED

-TO REACH AN ENDPOINT.

NOTE: AFTER DRILLS AND PRACTICE RUNS, THE BORON TITRATOR HUST BE FLUSHED WITH

[\ DEIONIZED WATER AND PUT IN DRY LAY-(

~Y UP. ALL ELECTRODES SHOULD BE PLACED IN LAYUP SO THEY ARE CONDITIONED FOR IMMEDIATE USE. ALSO PURGE ANY WATER THAT MAY BE HELD UP IN THE 280 ML GAS EXPANSION BOMB.

i 5.4.2 Chloride-Analysis NOTE: THE CHLORIDE ANALYSIS WILL BE PERFORMED BY WE LAB SERVICES USING THEIR ION CHROMATOGRAPHY ANALYZER. ,

5.4.3 Iodine Analysis and Gamma Scan Using the specially prepared 2 cc syringe or adjustable automatic pipet, withdraw 0.3 cc (or less) of the sample from the poly beaker and inject this sample into a 1000 ml poly bottle containing demineralized water. Make additional dilutions in the same manner.* Count as normal.

• Additional dilution should be performed until the contact reading is <1 mr/ hour.

d NOTE: SEE SECTIONS 7.0 AND 8.0.

, , . . _- _ _ . - - - .... ~ . . - . _ . _ . _ , . , _ _ _ _ , _ . . . . - . - - . . ,.__,,_ _..

EPIP 7.3.2 Page 12 k

Initials 5.5 Reporting of Results Complete and forward Reactor Coolant Post-Accident i

Sampling _ Analysis Report (EPIP-30).

j 6.0 SAMPLE RESIDUE Place all sample residue in the specially prepared lead pig for disposal.

7.0 SAMPLES TAKEN TO KEWAUNEE NUCLEAR PLANT FOR COUNTING

Reference:

Post-accident counting agreement with Wisconsin Public Service, Kewaunee Nuclear Plant.

Kewaunee Nuclear Plant does not utilize the 5 cc glass vial and 1 cc test tube geometries. -Therefore, " normal" semples will have to be diluted and placed in one liter poly bottles if they are sent to the Kewaunee Nuclear Plant for. analysis.

8.0 LABELING OF SAMPLES i

Label all chloride, noble gas, iodine and gamma scan samples with all pertinent information such as: sample number, name of sample, date and time of sampling, sample volume and dilution (s).

4 3

O i

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

U O 957 W$43[

WTRIAfMgy7 9N3436 70 PoffmW qbst f "1 - Mit "y - are .t l

--f"'d7ex u ws,

> &$a*H'fiEO-MS&j

' g'm,

\ >

lvs fj 9 71 w2 h

v V l t

th

• fSf W *8 lf A E 43SA h

to M i j d%

'i y ['(n' - I p

DI WATEA .cjvg gp g3 gg 93 9

4M M}

4 pq w][ --

g- >< N I

4 146 98 wiscoNSN 8.ECmlC POWER COMPANY Point Beach Nuclear Plant INFIMARY CHAAM7 O .

htt&M LEVfL JM Me*d W 6

["

- ~~

~"

stew Dwe64AM _, _mo ..

mm IIEV DAM

T I CALCULATION SHEET FILE No-

, "T 88#8 MADE BY DATE CHKD.BY DATE Vd.C,a.am 6/M f/EV/

f Ltus'

?' x v&<

~ d AS f C0ueer/GN BCMd 1

K1 c.. ..

X' uno *

. SAMAi ll

'9, / j'# '#%~

%~' , - - - - - . - - - - - - - . .

'h f g I '[N.,')  % '

foxy du ccw Y l

l ,,{ f i r

l v '"'"

8 l

'f~C f V/f 40 i

l

/;).itid l/f) o c w <hes a

l .

i L

{lY *

-f

&Jmele' G rt **/!in f e f}l

, y GAo t i V AM A2/4N j' ~\, '

'z %d Sc oeicr \J L.) "

\ v ') .' iea.> ai,ae qn f SS EA L  !

stN 2 B SMtET OF CALCULATION SHEET FILE Noe

.T

' 5h' ' 7, , gn, ,y MADE BY Md DATE 3, 00

[ I

) i ms / ur' s

CHKD.BY d//// DATE ,O*

m 4 - ,

[h 22 m g

. g- .u n

~

es . --  :

?

_N ta r'

3 e

\

% D

[\ \'

\

s 3 :\ _ /

y  %

+--

p go pp b

r ,

3

,r 7-

@ 4i, ~

k l 2

- P L y

e

%% ~5 _

~N N%h tr -

o y

] D N&=a- er-5 r ph -

!Ls F

• e 3

g u, c

n -

s r-s kEm

.__ , [L c

,% , f *

- ty" 'R P r c -r En,,-eF g A e,

et c

2.,.

f} h 9 . qg" M g

(/ ,

Is- Tp A 5

v

?{_A l-

A S-9 9

[kbll: . l

. _. 5 y

.  ? 'l O {a p= a%

a s

. N 'l a

x i  !'M Q n.,

.a gs

. 2'M mi M

g h

u8 kk 4E x

p$ e 53  % d 9 G

!>@5! i

~

lxk b*

• EG=3 d GE

= wh

" as

- - 9 lWb m

E j*

- " c_

~

=~ng

.- a D

- m C

,' 3 c.

a f x 1

- c.

f l .

o b(

, ~

h $}

' i t i k

o S @ $ a s

t lo II -

a osg,4

=

5

-- ,- . . , , . . . , , - - - - . , . . . ,..,.,----,._.----,a ,, .,_.---.,n., - - - , - - - -

f

<r V;

gs EPIP 7.3.3

-( MINOR

\-

Revision 8 11-04-83 POST-ACCIDENT SAMPLING GF CONTAINMENT ATMOSPHERE

1.0 INTRODUCTION

This procedure outlines the steps necessary to collect, handle and analyze a potentially high radioactive containment atmosphere sample resulting from gross fuel failure and loss of reactor coolant system integrity to

, determine hydrogen and radioactive gas concentrations.

2.0 PRELIMINARY ~ EVALUATION NOTE: THE FOLLOWING EVALUATION SHALL BE COMPLETED PRIOR TO ANY ATTEMPT TO ENTER THE FACADE OR RE-lll/RE-212 CUBICLE'TO PERFORM A VALVE LINEUP OR COLLECT A CONTAINMENI ATMOSPHERE SAMPLE.

2.1 Indications of Possible Fuel Damage Some or all.of the following would be present if fuel damage or l'"'i - loss of reactor coolant system integrity had occurred:

C' /

2.1.1 The valve gallery monitor RE-116 and failed fuel monitor 1(2)RE-109 would be unusually high or offscale.

2.1.2 The containment radiation monitors 1(2)RE-211 and 1(2)2RE-212 would be unusually high or offscale.

2.1.3 The containment area monitors 1(2)RE-102 and 1(2)RE-107 would be unusually high or offscale.

l 2.1.4 The automatic actions of E0P-1A have caused containment isolation.

I 2.2 Evaluation of Radiological Hazards in Access Areas Required for Sampling Initials 2.2.1 After evaluation of the radiation monitoring system readouts, verify with Health Physics that the appropriate airborne and radiation surveys have been made before entering the l facade.

f i

l fs I

(.-)

{

i

4

-~s EPIP 7.3.3

[Ol Page 2 Initials 2.2.2 Verify the requirements for facade and 1(2)RE-211/1(2)RE-212 cubicle entry.

a. Radiation work permit requirements

b. Clothing requirements

c. Respiratory requirements

d. Dosimetry requirements including extremity dose monitoring

e. Health physics coverage requirements including timekeeping.

2.3 Evaluation of Containment Pressure containment pressure must be less than 5 psi in order to initiate sampling.

G 3.0 MISCELLANEOUS CONSIDERATIONS 3.1 Call CAS and inform them that door No. 182, for Unit 1, and door No. 183, for Unit 2, will be blocked open during sampling.

3.2 Take along a flashlight in case area lights are not

, working and a portable FM radio.

4.0 CONTAINMENT ATMOSPHERE SAMPLING PROCEDURE NOTE: THE FOLLOWING PROCEDURE SHALLNOT BE INITIATED UNTIL THE EVALUATION DISCUSSED IN SECTION 2.0 HAS BEEN COMPLETED.

THE DUTY & CALL SUPERINTENDENT (COORDINATOR), THE DUTY &

CALL HEALTH PHYSICS SUPERVISOR AND THE DUTY SHIFT SUPER-INTENDENT SHALL APPROVE THE IMPLEMENTATION OF THIS PROCEDURE.

THE FOLLOWING STEPS WILL BE ACCOMPLISHED UNDER THE DIRECTION OF HEALTH PHYSICS SUPERVISION.

I ,

/~\g d .

4 N  %

EPIP 7.3.3 pl .

Page 3 (O

Initials 4.1 Containment Atmosphere Sampling Using the 1(2)RE-211/

1(2)RE-212 Sampling System, After Containment Isolation 4.1.1 Valve Line-Up NOTE: FOR INTERIM SETUP P707A HAS NO AUTO SECURING. IF CONTAINMENT ISOLATION HAS OCCURRED, FUSES FOR P707A MAY HAVE BLOWN.

a. Secure sample pump, P707A, locally at pallet.

b. Verify with the control room that the following conditions exist:

(1) Valves 3200A, B & C have closed.

(2) Vent control switch in the cable spreading room (CSR) is in

(

g - off and pullout (P707B secured).

(3) Mode select switch in CSR is in septum position (3200E&F closed, 3200D open, 3200G aligned to con-tainment, 3200M aligned to septum).

c. Obtain the designated 100' service air line and pressure regulator from the potable water room.

F

d. Proceed to the potable water room to sample Unit 1 containment or to Unit 2 nonnuclear room to sample, Unit 2 contain-

! ment with the air hose and pressure regulator.

NOTE: FOR RCT TRAINING EXERCISES, DO NOT USE THE POTABLE WATER ROOM OR NON-NUCLEAR ROOM SERVICE AIR H00KUPS, SINCE THEIR USE UNNECESSARILY BURDENS SECURITY. THE SERVICE AIR H00r3PS LOCATED ON EL. 66' CONTROLLED SIDE El"JLDE WALL ARE TO BE USED.

I a

- EPIP 7.3.3

[

V) Page 4 Initials (1) Attach the service air hose to an available turbine hall service air cutlet using the pressure regulator designated for this procedurri.

(2) Lock the Chicago fitting in place, i using the appropriate pins or wires.

d. Proceed to the 1(2)RE-211/1(2)RE-212 cubicle and perform the following:

(1) Connect the service air hose to the Chicago fitting attached to valve

. 1(2)3200Y, and verify that the valve is closed.

NOTE: THE VALVE IS LOCATED ON THE ELEVATOR SIDE OF THE CUBICLE.

') (2) Lock the Chicago fitting in place, using the appropriate pins or wires.

(3) Enter the cubicle and perform the following: '

(a) Verify 1(2)A0V-3200A&B are closed by visual observation.

(b) Manually close valves 1(2)3200N, P, Q, W, EE & FF.

(c) Manually open Whitey valves 1(2)3200J & L.

e. Request the control room perform the following:

NOTE: THE SAMPLE PUMP P707A SEALS ARE RATED FOR 5 PSI. TO PREVENT AN INADVERTENT AIRBORNE RELEASE, THE CONTAINMENT PRESSURE MUST BE LESS THAN 5 PSI BEFORE PRO-CEEDING.

(1) Verify containment pressure is less

/'"') than 5 psi.

N~./I .

4

- - - - , , - r-- -

,, ,,,, --e,e , - . . - - , . ~n -e .-. 4, -- - . - -,--,e , , . - - - , , , -

fx EPIP 7.3.3 Page 5 Initials (2) Open A0V's 1(2)3200A, B & C (contain-ment isolation valves).

f. Start sample pump P707A locally at the pallet.

g. Verify sample flow by observing a flow increase on FIT-3288 and return to the potable water /nonnuclear room.

h. Allow 15 minutes for sample recirculation and return to the cubicle with two (2) 2 cc gas-tight syringes in a hollowed-oat lead brick. One syringe should have 1 cc of AgZ inside the syringe barrel.

4.2.2 Sample Collection

a. Obtain two 1 cc gas samples from the sample

') septum by means of the gas-tight syringes.

s_,/ Withdraw the syringe plunger only once. Do

. not purge the syringe as the AgZ will retain the iodine from each withdrawal.

l NOTE: LOCK THE SYRINGE PLUNGERS PRIOR TO WITHDRAWING FROM THE SEPTUM.

b. Place the syringes in the lead bricks for transport.

l l

CAUTION: CLOSE LEAD BRICK COVER SLOWLY TO l AVOID BREAKING SYRINGES.

l l c. Note the prepurge radiation levels in the I cubicle.

( d. Establish a service air pressure of 5 psi on the regulator and open valve 1(2)3200Y.

4.2.3 Sample Line Purge l

l-

a. Return to the potable water /nonnuclear room and request the control room close valves 1(2)3200B&C.

p>

s _-

s 1

l

=. - - . . . . . - - ---,,.-. . . . . - . - . . - -

EPIP 7.3.3 Page 6 Initials

b. Allow the system to purge forward for 15 minutes, then request the control room perform the following:

(1) Secure the sample pump P707A locally from the pallet.

(2) Place mode select switch to containment position and shut 1(2)A0V-3200A. '

(3) Open 1(2)A0V-3200B&C. "

c. Allow the system to purge backwards 15 minutes and request the control room close valves 1(2)3200B&C.

d. Return to the cubicle and perform the following:

' ('s

\ _,)

(1) Verify the effectivenss of the purge by measuring the reduction of the radiation levels.

(2) Close the service air valve and back off on the regulator. Close valve 1(2)3200i -

and remove the service air hose.

(3) Enter the cubicle and close Whitey valves 1(2)3200J & L.

e. Notify the control room that sampling

• has been completed, and that valves 1(2)3200W, EE & FF are closed.

! NOIE: AFTER ALL DRILLS AND PRACTICE

~

l EXERCISES, ALL EQUIPMENT AND l

VALVE LINEUPS ARE TO BE RETURNED To THE AS-FOUND CONDITION.

l f

O

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

~ . _ _ _ . ._. _ _ _ _ ._ _ _ .

's EPIP 7.3.3 Page 7 (b

i Initials 5.0 CONTAINMENT ATMOSPHERE ANALYSIS 5.1 yolume Adjustments 5.1.1 Before proceeding with the hydrogen, radioactive noble gas and radioactive iodit analyses, the sample contents of both syringes must be brought to atmospheric pressure. Use the shielded sacri-ficial glass bomb for this purpose.

5.1.2 Insert the syringe through the rubber septum of 7 the glass bomb. Unlock the syringe locking device and let the syringe and bomb equilibrate for 4 .

approximately 30 seconds. Relock the syringe and withdraw from the septum. Store the syringe in the lead brick.

5.1.3 Repeat Step 4.1.2 for the other syringe.

5.2 Hydrogen

- V- Assuming normal equipment setup and preparations are complete, use the sample injection port on the gas partitioner, inject a 1 cc gas sample and proceed using normal hydrogen analysis procedures.

5.3 Radioactive Noble Gases & Iodines Noble Gases ,

G.3.1 Use the 2 cc syringe with the 1 cc of AgZ for the noble gas and iodine separation / analysis.

i l 5.3.2 Inject the 1 cc contairaent atmosphere sample l into a one liter poly bottle. Purge the syringe j once or twice while in the poly bottle in order to recover all of the noble gases. Remove the

syringe and store in the lead brick. Tape over L the syringe hole in the poly bottle. Let the gas come to equilibrium for a minimum of 15 minutes while proceeding with the iodine analysis

j. section.

• 9 O

L I

9, v. e *-

--mT f 9 uw-" wgerw--N -+r'r --'r+'- 4*W-'v- M-N-- wvv vvvv--M'-w rw W-V'w'=cww--wy 7em-w y---"rr+vywwgw.--ty wywww *www-'-w--'r v v* "'v*w'- w=-w N W Wire'www--w=--

• l t

S EPIP 7.3.3 Page 8 l

, 5.3.3 Withdraw a 1 ce gas sample from the poly bottle  !

in Step 4.3.2. If the contact reading on.the syringe is less than 1 mR/hr, inject the sample into a 5 cc vial and count as normal. If the contact reading is greater than 1 mR/hr, further dilutions.are necessary.

Dilution procedure: Inject the 1 cc sample into a one liter poly bottle and allow to equilibrate.

i Withdraw 1 cc from the poly bottle. If the contact reading is less than one mR/hr, inject inte a 5 cc vial and count as normal. If the contact reading is greater than 1 mR/hr, dilute further.

i

(

NOTE: FOR EACH DILUTION, USE A NEW SYRINGE OR MAKE CERTAIN THE OLD SYRINGE IS .COMPLETEL'I PURGED.

I LABEL NOBLE ~ GAS SAMPLES AND IODINE SAMPLES WITH ALL PERTINENT INFORMATION SUCH AS: SAMPLE -

j NUMBER, NAME OF SAMPLE, DATE AND TIME OF sal 2LE, SAMPLE VOLUME AND DILUTION (S).  ;

p Iodines 5.3.4 Unscrew the syringe top and remove the internal plunger.

' Pour the silver zeelite into a counting test tube and cap.

5.3.5 . If the silver zeolite / iodine sample is less than one mR/hr contact, count the sample directly en the MCA using the test tube geometry.

5.3.6 If the iodine activity is too high to count directly, determine the radiation level in mR/hr at one foot.

Also, determine the percent isotopic composition using the MCA and attenuating the sc.mple if necessary. ,

- Determine the total iodine activity using the following

- equation; R/hr @ l' C(Cl)- = 6E T'

1 4 #

\

~--w,--w +-mw-e--*m,,v,r,r.r- + w +-~-e e--v,wr---,v+,ewww-weru , -r- -ee -w,-e-y,ew,,g-o-w--woww.e-we g~wt--- m wn e -e m s e mw won n e m-- w~"

. _- ~ - -

o EPIP 7.3.3 O Page 9 T1.e following table can be used as an aid in determining the " Total Average Energy /y" (E T

) f r the above equation.

(1) (2) (1) x (2)

Average y  % Composition Weighted y Isotope Energy (Fraction) Energy I-131 0.380 I-132 0.731 I-133 0.530 I-134 0.857 I-135 1.238 Total Weighted y Energy: (ET )

Each individual iodine isotopic concentrtien (pci/cc) is calculated as follows:

pCi/cc I(g) = C(Ci) x 1 x 10 x (Fractional s Composition) l 6.0 CALCULATIONS 6.1 Pressure & Temperature Correction Ask control room supervision for the temperature and pressure ir.

containment (psig and *F). Determine atmospheric pressure (mm Hg)

, and temperature (*F) from the barometer in the laboratory. Convert j this to psia. Apply the following correction factor to all results:

Initials concentration (pci/cc) x (Pc + 14.7) x (Tc + 459)

P lab ( lab + 459)

P lab (psia) = 14 7 Psi x 760 g Pc = containment pressure, psig Tc = containment temperature, *F i

l. 6.2 Complete and forward Containment Atmospheric Post-Accident Sampling l Analysis Report (EPIP-31).

l r

d' ,

i

5 g .

5 4 -

M  %

A k 25 i

>EA W yl

, ,. (,5) _

U e JL3.,

g -

g" A@qy gf r,

= eo ts s. e r ex g o 4. 3 h I ( w*g D &J h g* 49 N -

b duM-I l

a O b J L g ' ld

<ts <o l b" 8 LTs L2 77 F'w 3*k*

'k= 5 4{R tJ n 4  :

a yw 2 2 'tt*

a El- 2 w g J ks )n J k k2 M

,, v )..

o u T 4 g I

' a

'-*+

• m sih qy -

no '

=a  ? u b nA L

$ $ "U

$ m m x- -

3 4 ,m s m . s: :s m sss4 k s x x x s',

s xms

' e E$'

= 'o Lt A gR l 4

~

b r

e uhw s N q A w

Eh 4 u% %d L

a -

k u

./:

!i q EPIP 7.3.4 MINOR Revision 1 11-04-83 MOVEHENT OF REQUIRED CHEMISTRY EQUIPMENT & MATERIALS '

TO THE TECHNICAL SUPPORT CENTER COUNTING ROOM & MINI-LABORATORY 1.0 GENERAL The purpose of this procedure is to provide a series of actions on the part of chemistry personnel for the movement of required chemistry equipment and materials to the technical support center (TSC) countit.g room and mini-lab in the event this becomes necessary.

This procedure may be implemented in the event that the controlled side chemistry lab is declared radiologically uninhabitable or unfit for MCA analyses.

2.0 ATTACHMEN"'S 2.1 Appendix "A": Ortec Geli Detector Transport Procedure .

2.2 Appendf.x "B": Gas Chromatograph Transport Procedure

,d 2.3 Appendin "C": Chemistry-Related TSC Equipment & Reference Material Inventory List b

, (

s i

V rs, EPIP 7.3.4 I

V) Page 2 APPENDIX "A" ORTEC GELI DETECTOR TRANSPORT PROCEDURE 1.0 PROCEDURE To provide a readily available reference for the timely removal and transport of the Ortec Geli detector to the technical support center counting room.

NOTE: THE ORIGINAL ORTEC GELI DETECTOR IC NOW LOCATEP IN THE TSC AND IS ALREADY HOOKED UP TO THE PACKARD MCA. THE APPENDIX HAS BEEN ADDITIONALLY MODIFIED TO INCLUDE THE TRANSPORT / HOOKUP OF THE NEW ORTEC

, HPGE DETECTOR IN THE EVENT THAT IT IS NEEDED.

2.0 REFERENCES

2.1 " Operating & Service Manual

for Ortec 120 Series Preamplifier and f- s Ortec Model 119 High Voltage Filter, Ortec Inc., 1970

)

(

/ 2.2 " Operating & Service Manual" for Ortec Model 451 Spectroscopy Amplifiar, Ortec Inc., 1969 2.3 " Operating & Service Manual" for Ortec Model 459 5 KV Detector Bias Supply, Ortec Inc., 1971 2.4 " Solid-State Photon Detector Operator's Manucl," for Ortec HPGe detector, Model No. GEM-15180, Ortec Inc., 1982 3.0 PROCEDURE 3.1 Dismantling From Canberra Series 80 MCA 3.1.1 . Slowly remove the bias voltage applied to the Geli detector l- by " stepping down" the gain on the Canberra Model 3105 High l Voltage Power Supply. When the voltage has been reduced to zero, turn the power supply off.

3.1.2 Disconnect the black high voltage cable at the high voltage connector of the Ortec Model 119 high voltage filter-which is attached to the Ortec Geli detector (old Geli detector). The new Crtec HPGe detector has an internal high voltage filter and preamp with external cables. Disconnect the HV at the

. , - ~

cable connector.

v

9 6

EPIP 7.3.4 Page 3 3.1.3' Disconnect the Ortec Model 120-4 PREAMP power supply grey cable from the 7-pin connector located on the west wall of the counting room. The new Ortec detector has a similar 7-pin connector on a grey cthle.

~

3.1.4 Disconnect the black cable at the Model 120-4 PREAMP

" OUTPUT-E" connec tor (old Geli detector) or at the " OUTPUT" cable connector (new HPGe Ortec detector).

3.1.5. Disconnect the LN 2 detector cable at the Ortec Detector.

3.1.6 Carefully remove the Ortec detector from the lead shielded

" PIG" by pulling horizontally on the liquid nitrogen (LN2 )

dewar (old Geli detector). The new HPGe detector is removed in a similar fashion after removing the sidewall plug in the roll top shield.

3.1.7 Cover the exposed detector face to protect it from physical

, damage. A cut-off poly bottle stuffed with Kimwipes would be adequate protection.

L

') 3.1.8 Carefully transport the Ortec detector and LN2 dewar to the

~~,/ TSC mini-lab. If transporting by cart, go slowly over bumps 1 to minimize jarring of the sensitive detector.

3.2 Setup to Packard Series 900 MCA l

3.2.1 Connect the_ grey power supply cable from the Model 120-4 PREAMP (Geli), or from the new Ortec HPGe detector, to the 7-pin connector on the back of the Ortec Model 451 Spectroscopy Anglifier.

3.2.2 Connect the black cable (RG-62 A/U) from either the " UNI" connector on the back of the Model 451 or-the " UNIPOLAR INPUT" connector oa the front of the Model 451, to the

" OUTPUT-E" connector on the Ortec Model 120-4 PREAMP (Geli) or to the "3UTPUT" connector on the Ortec HPGe detector.

L 3.2.3 Connect the black cable (RG-59/U) from the "0-5 KV" connector

(- on the back of the Ortec Model 459 gias supply to the "HIGH

! VOLTAGE" connector on the Ortec Model 119 High Voltage Filter .

l (Geli) or to the HV cable connector of the Ortec HPGe detector.

3.2.4 . Connect the black cable from the Ortec Model 729 LN 2 monitor

, to the LN2 connector of the Ortec Geli cr HPGe detector.

() 3.2.5 Turn on the " POWER" switch to the Packard MCA and let it warm up. '

L

1 W

' ~

EPIP 7.3.4 2 Page 4

' 3.2.6 Turn the "HIGH VOLTAGE" switch on the Ortec Model 459 Bias Supply to the "0N" position.

3.2.7 Apply detector bias voltage by slowly turning the." OUTPUT VOLTAGE" pot on the Model 459 to 2.40 (2400 V) for the old Geli detector. The new Ortec HPGe detector requires 3000 V in order to use its specific efficiency curves.

f i

O t

4 4

5 t

t

=

0

EPIP 7.3.4

()/N Page 5 APPENDIX "B" GAS CHROMATOGRAPH TRANSPORT PROCEDURE

-1.0 PURPOSE To provide a rea'dily available reference for the timely removal and transport of the Fisher Model 29 or 1200 Gas Chromatograph (GC) to the TSC mini-lab.

2.0 REFERENCES

2.1 Fisher Model 29 Instruction Manual, Fisher Scientific Co., April, 1974 2.2 Fisher'Model 1200 Instruction Manual, Fisher Scientific Co., May, 1979 3.0 PROCEDURE 3.1 Turn off the " CELL POWER" and " HEATER" on the GC Model 29 or the 4

s " BRIDGE POWER" and " MAIN POWER" on the GC Model 1200. Unplug the AC

, ) line cord.

U 3.2 Secure the Helium and/or. Argon carrier gas at the cylinder and disconnect the carrier gas line at the GC inlet.

3.3 Disconnect the tygon vent tubing from the "T" fitting that connects to the " CARRIER GAS OUTLET" and " SAMPLE OUTLET."

3.4 Disconnect the VARIAN AEROGRAPH recorder cable from the + and - jacks on the RECORDER TRANSFER SWITCH box. Unplug the AC line cord on the VARIAN AEROGRAPH recorder.

3.5 Disconnect the +, - and ground wires on the back of the GC that lead to the RECORDER TRANSFER SWITCH.

l 3.6 Carefully transport the GC and recorder units to the TSC mini-lab.

l NOTE: TAKE ALONG ANY OTHER NECESSARY ITEMS SUCH AS CALIBRATION CURVES, CALIBRATION GASES, SILICON RUBBER INJECTION STOPPERS, DRIRITE, ETC.

3.7 Setup the GC close to the VENT HOOD and connect a tygon line from the SAMPLE and CARRIER OUT to the VENT HOOD.

3.8 Plug in the AC line cord and turn on the " HEATER" on the GC Model 29 or the " MAIN POWER" on the GC Model 1200.

i m- , - _

m EPIP 7.3.4 Page 6  ;

- 3.9 Connect the appropriate carrier gas line to the GC and establish the ,

correct pressure and flow rate.

3.10 Turn on the " CELL POWER" on the GC Hodel 29 or the " BRIDGE POWER" on the GC Model 1200 after allowing sufficient carrier gas purge time.

3.11 Connect the Varian Aerograph recorder cable directly to the jacks on the back of the appropriate GC. Plug in the recorder AC line cerd.

I i

t 1

i e'

+

1 l

f O ,

_ . , _ . . _ - . - - . . _ - , _ _ . _ _ _ . . . _ . - _ . _ _ _ . . _ _ _ . . . . . . . . _ . . , _ . . _ _ . , _ _ _ _ - _ , . _ .._____.____,,.m._,._....-_.,__ - . . - . _ , _ , -

e EPIP 7.3.4

/^N Page 7 V .

APPENDIX "C" TECHNICAL SUPPORT CENTER, MINI-LAB & COUNTING ROOM CHEMISTRY-RELATED EQUIPMENT & REFERENCE MATERIAL INVENTORY LIST 1.0 GAS CHROMATOGRAPH RELATED 1.1 Tygon vent line to vent hood

-1.2 Burret stand and clamps, 250 ml separatory funnel, latex tubing

• 1.3 Carrier gasses (He & Ar), regulators, hoses, cylinder brackets or stands 14 Glass sample bombs 1.5 Syringes (gas tight and liquid)

-1.6 Leak detector

/ 1.7 Dririte 1.8 Silicon rubber injection stoppers 1.9 Hose pinch clamps 1.10 Varian recorder paper

• 1.11 Calibration curve book

• 1.12 Calibration gas cylinders

• Not stocked in TSC, mini-lab or counting room; bring from checistry lab.

2.0 MCA RELATED 2.1 Calibration curve book 2.2 Ortec detector

2.3 LN 2 dewar and fill system 2.4 Detector pig and geometry positioner / holder 2.5 Space ~ to position detector at proper height relative to counter top p .

2.6 Sample bottles, vials and septums I

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

e v

~

EPIP 7.3.4 Page 8 2.7 Teletype

• 2.8 Rod. sources and disc sources

• 2.9 Calculators (2) 2.10 Charcoal filter blowout apparatus 3.0 MISCELLhNEOUS 3.1 . Poly bottles (assorted) 3.2 Pipettes (assorted) and rack 3.3 Bunsen burners, tripods, screens, torch lighter 3.4 Condenser columns, drilled corks, glass tubing 3.5- _ Volumetric flasks, beakers, volumetric cylinders l fr s 3.6 Decon soap and Sparkleen

(

1 U.

3.7 Tygon, latex tubing and cutter 33 Vacuum hose f

3.9 Tuck tape

'*3.10 Tools (assorted) ,

3.11 Eye droppers E 3.12 Tweezers & planchetts (1" and 2")

4.0 POST-ACCIDENT SAMPLING SYSTEM RELATED

• 4.1 Ramp / Gas expansion chamber (gas collection bn.b)

• 4.2 Valve manifold l . *4.3 Lead shielding

• 4.4 Mirror

• 4.5 Specially prepared 2 cc syringes l

l

i..

)

4 i

I i.

i EPIP 7.3.4 Page 9 1

i

*4.8 CAMP procedure book f

- *4.9- All " Equipment List" items from EPIF 7.3.2, Section 1.2

! *4 10 EPIP binder (lab copy) 1 f- l 2

i.

i i

t~

i s I 4 j i

T I

e s

4

\ ,

L h

s s 5 I

}_

i

1. h -

1 i

6

- t E

i t 6 I:

I l

1>

?

i  !

jl .  ;

i e

i i

! f

, i.

l v9 5

i

...a,..

- E. m, ., . - , ,,.e .m.~,.,_.,..,_ __.m_..-__~-w; .-w.m_,-me,,m_w-,g-w.~,.P

7 .-

ff w ,.

> ' POINT BEACH NUCLEAR PLAlfr RMS SYSTEM STATUS i (Release Poinc Monitors)'

Date Time e

DAM Channel No. No. RMS No. Location Range Reading o 003 9 1RE-231- Steam line monitor "A" SG 104-10~1 pCi/cc 004 9 2RE-231 Steam line monitor "

"A" SG 1; 4-10~1 pCi/cc

.005 2 1RE-232 Steam line monitor "B" SG 104-101 PCi/cc 7 RE-221 Drumming area vent 10 8-10 4 pCi/cc

[ 8 .R2-226 High rance combined

! air ejector i

. 006 2 2RE-232 Steam line monitor SG "B" 104-10~1 pCi/cc

-6 RE-224 Gas stripper building vent 10_9-10,5 pCi/cc 007 1. RE-225 Low range combined air -

ejector 10 s-101 pCi/cc 4 RE-214 Auxiliary building vent 109-105 pCi/cc 021 -- --

U1 containment purge exhaust SPING l ,5 1RE-305 Low range gas 108-10~4 pCi/cc f 7 1Re:-307 Mid range gas 103-104 pCi/cc l'

! 9 1RE-309 High range gas 101-104 pCi/cc l-(

h

(

L

'EPIP-05

.(10-83)'

..-- . =. - -- .-,- >

Pag 2 2 i~

DAM Channel No. No. RMS No. Location Range Reading 4

022 -- '--

U2 containment purge exhaust SPING S 2RE-305 Low rar.ge gas 10 s_194 pCi/cc 7 2RE-307 Mid range gas 10~3-108 pCi/cc .,

9 2RE-309 High range gas- 10~1-108 pCi/cc 023 -- --

Auxiliary building vent SPING 5 RE-315 Low range gas 108-10~4 pCi/cc 7 RE-317 Mid range gas 10~3-108 pCi/cc _

9 RE-319 High range gas 10~1-108 pCi/cc '

024 -- ---

Drumming area vent 4 SPING 5 RE-325 Low range gas 108-10~4 pCi/cc '

7 RE-327 Mid range gas 10~3-104 pCi/cc d

l l

ll I

i O

EPIP-05

-(10-83)'

.

es POINT BEACH MUCLEAR PLANT RMS-SYSTEM STATUS '

(Area Type Monitors) ,

, N Date _

Time DAM Channel '

No. No. RMS No. Location Range Reading 001' 1 '1RE-104 U1. charging pumpt 10~1-104 mR/hr

~

6 1RE-216B Slightly scuth C59 10 2_102 mR/hr 7 1RE-222 U1~ facade El. 26' 10~1-104 mR/hr 8 1RE-136 U1 sample room 102 107 mR/hr 002 1 2RE-104 U2 charging pump 10~1-104 mR/hr

~

6 2RE-216B Slightly north C59 10 2-102 mR/hr 7 2RE-222 U2 facade El. 26' 10~1-104 mR/hr 8 2RE-136 U2 sample room 102-307 mR/hr _

9 2RE 107 U2 seal tchle 102-107 mR/hr

. 003 3 1RE-229B U1 El. 8' PAB 10 2 101 mR/hr 4 1RE-106 U1 sample room 10~1-104 mR/hr 8 1RE-134 U1 charging pump 10 2-107 mR/hr 004 1 2RE-102 U2 cont. El. 668 102 107 mR/hr ,

3 2RE-229B U2 aux. feed TB El.' 8' 10 2_102 mR/h:r

[ 4 2RE-106 U2 sample room 10~1-104 mR/hr 005 4 1RE-219B Outside U1 sample room 10 2 102 mR/hr 6 RE-103 Chem Lab 10~1-104 mR/hr 9 RE-140 SI pump room El. 8' PAB 102_107 mR/hr l'

EPIP-06

[ .(10-83) l t

,.~-

Page 2 l DAN Channel

% No. No. RMS No. Location Range Reading

~

006 4 2RE-219B Outside U2 sample room' 10 2-102 mR/hr 5 RE-105 SFP El. 66' PAG 10~1-104 mR/hr 007 3' RE-2188 U2 PAB El. 8' 10 2 102 mR/hr 7 RE-108 El. 26' PAB TA 10~1-104 mR/hr 8 RE-114 CVCS holding tank i El. 26' PAB 100-105 mR/hr 9 RE-101 Control room 10~1-104 mR/hr .

008 1 RE-113 El. -19' PAB 10~1-104 mR/hr 3 RE-230B U2 TA El. 8' WT Area 10 2_102 mR/hr 100-10s'mR/hr 4 RE-112 El. 8' PAB central 6 RE-223B CCW HX El. 46' PAB 10 2 102 mR/hr  !

7 RE-111 C59 100 -10s mR/hr 8- RE-135 SFP 102-107 mR/hr

[ 9 RE-110 SI Pump area El. 8' PAB 10~1-104 mR/hr Completed By Date i-Reviewed By Date l-1 f

h LO EPIP-06

.(10-83) r

POINT BEACH NUCLEAR PLANT RMS SYSTEM STATUS (Process Monitors)

Date Time DAM Channel No. No. RMS No. Location Range Reading 001 3 1RE-212 Cont. noble gas 5 IPE-216 Cont. fan coolers 7 1RE-222 BD tank outlet U1 10 2 101 mR/hr 002 3 2RE-212 Cont. noble gas 108-104 pCi/cc __

5 2RE-216 Cont. fan coolers 108-108 pCi/cc 7 2RE-222 BD tank outlet U2 10 2 101 mR/hr 003 2 1RE-229 Service water discharge 6 1RE-217 Component cooling water 108-10~4 pCi/cc O 004 2 2RE-229 Service water discharge _

. '6 2RE-217 Component cooling water 108-10~4 pCi/cc 005 3 1RE-219 SG blowdown U1 006 3 2RE-219 SG blowdown U2 109 -105 pCi/cc 9 RE-235 Control room noble gas 108-104 pCi/CC J07 :2 RE-218 Waste disposal system 5 RE-220 SFP liquid monitor 10'9-10~5 pCi/cc 008 2 RE-230 Liquid rete.ntion pond 5 RE-223 Waste distillate EPIP-06a (10-83)

4 i_a- .A+-A4 44. 4-. A 2& mid +

b

.p I

OFFSITE AGENCY EMERGENCY CALL LIST

, . FEDERAL AGENCIES:  ;

i

1. United States Nuclear Regulatory Commission '

Telephone Person Time Name Frequency Number Notified Notified Initials NRC Operations All hours Red Phone Center.

or 1-202/951-0550 NRC Office of All hours 1-312/970-5500 Inspection cnd (Ask for

Enforcement, Duty Officer) i Region III NRC Resident Inspectors: Plant Ext. Home

^

a. R. L. Hague

. 294 388-2856

-b. B. E. Fitzpatrick 294 794-8272

.2. United States Department of Energy 1

Telephone Person Time .

'~' Name l-i Frequency- Number Notified Notified Initials 1.

j Chicago. operations Weekdays 1-312/972-4800 l Center, Region V (8AM-SPM)

.(Radiological Assistance Team) All'other 1-312/972-5731 hours l

3. United States Coast Guard l :. Telephone Person Time Name Frequency Number Notified Notified Initials MSO,. Milwaukee 1-291-3788 USCG, Sturgeon All hours 1-743-3366 Bay USCG, Two All hours 793-1304 ~

Rivers l'

7..

i td.

.EPIP-23. Pagef1 of 4 (11-83).

. a. . - . . . -. . -- , ..= . - , _ . _ _ _ . - - . , _ . - - - - . .. - - - - . _ - .. - - _ - -

b e'

' ('"~');a,

\~.

4. United States National Weather Service Telephone Person Time Name Frequency Nun.ber Notified Notified Initials NWS, Green Bay All hours NAWAS 1-433-3876 STATE AGENCIES:

1. State of Wisconsin Telephone Person Time Name Frequency Number Notified Notified Initials

. Wisconsin Dept. of Weekdays 1-608/266-7464 Health and Social (9AM-SPM)

Services, Section of Radiation Pro-tection Lawrence J. McDonnell, Home phone Chief Section of Radiation 1-608/873-5483 Protection

, Wisconsin Division All hours 1-608/266-3232 of Emergency or NAWAS Government Wisconsin State All hours 1-921-0448 Patrol 1-921-0442 or NAWAS COUNTY AGENCIES:

1. Manitowoc County Telephone Person Time Name Frequency Number Notified Notified Initials Manitowoc County All hours 683-4200 Sheriff, County or NAWAS

Traffic or radio

} Nv

\

ik./

)

's.

EPIP-23 Page 2 of 4 (11-83)

/

(Js-

2. Kewaunee County Telephone Person Time Name Frequency Number Notified Notified Initials i Kewaunee County All Hours 1-388-3100 Dispatcher or NAWAS P9.2VATE AGENCIES:

Telephone Person Time Name Frequency Number Notified Notified Initials Kewaunee Nuclear All hours 793-2229 Power Plant -

Institute of All hours 1-404/953-0904 Nuclear Power Operations American Nuclear

( ]j Insurers All hours 1-203/677-7305 Westinghouse Electric Corp.

Operating Plant Regional Mgr., Office 1-412/256-5858 (E. Somers) Home 1-412/856-6927

. Voice Beeper 1-412/765-4318 1st Alternate Home 1-412/256-5409 (C. Spurmont) Office 1-412/462-4509 2r;d Alternate Home 1-412/256-5855 (C. Rowland) Office 1-412/478-3535 Stone & Webster All hours 1-617/973-0008 Engineering Corp.

Bechtel Power All hours 1-415/768-3840 Corporation University of Office 1-414/963-4974 Wisconsin - or 1-414/963-4561 Milwaukee Home 355-6823 Seismic Center (D. Willis) s ,,

V EPIP-23 Page 3 of 4

'(11-83)

-V

.(7A

\

FIRE AND MEDICAL AGENCIES-

1. Fire Emergency Telephone Person Tine Name Frequency Number Notified Notified Initials Two Creeks Fire All hours 684-0133 Department (Emergency line)

2. Medical Assistance Telephone Person Time Name Frequency Number Notified Notified Initials Doctors Clinic, Ltd. 793-1281 S. Lawrence Kaner, M.D.

Stephen L. Weld, M.D.

University Hos-i f' pital, Madison ,

( j/ Emergency Room All hours 1-608/262-2398 Frank C. Larson, M.D. 1-608/262-2718 i

Robert F. Schilling, M.D. 1-608/262-3188 Robert R. Radtke, Ph.D. 1-608/262-8769 (Health Physicist)

Two Rivers All hours 793-1151 Emergency or 1152 i

Vehicle l

Community Hos- All hours 793-1178 _

pital, Two Rivers' 1

l -i t~

l EPIP-23 '

Page 4 of 4 (11-83)

L

o. .,

j,,i g: POINT BEACH NUCLEAR PLANT 7

i

. CONTAINMENT ATMOSPHERE POST-ACCIDENT SAMPLING ANALYSIS REPORT I? N i: I t

i~ 1.0 HYDROGEN ANALYSIS 1.1- Scale used on gas partitioner

, 1.2 Millivolt reading on chart recorder

1.3  % hydrogen from calibration curve 2.0 -RADIOACTIVE NOBLE GAS ANALYSIS i 2.1- . Decay time in minutes p 2.2 Sample count time in seconds

, 2.3 Detector

, 2.4 - Geometry

. 2.5 Number of dilutions : (D) 2.6 Common multiplier

• i

• CM = (D)1 xf x (Pressure-Temperature Correction)

I j ' 2.7 Pressure-Temperature Correction

, (Pc + 14.7)(Tc + 459)

P (T + 459) i

i. Where Pc = Pressure in Containment (psig)

Tc = Temperature in Containment (*F) i

. P = Pressure in Lab (psi) where L

P = 14.7 x ("" N L 760 (mm Hg)

Tg= Temperature in Laboratory (*F)

(1) See Section'4.3.3 of EPIP 7.3.3. One or more dilutions may be necessary.

J EPIP-31 i (10-83)-

o

P

-/

s q' Page 2

\ .

2.7 Results of MCA

• Isotope Concentration (pCi/cc)

Xe-133 Kr-85m Kr-88 Xe-133m Xe-135 Xe-138 Kr-87 Xe-135m __

Ar-41 Kr-85 Xe-131m 3.0* RADIOACTIVE IODINE ANALYSIS 3.1 Decay time in minutes 3.2 Sample count time in seconds 3.3

, 'O

,v/

Detector 3.4 Geometry ,

3.5 Pressure-Temperature Correction (Same as Section 2.7)-

3.6 Results of MCA -

{ Isotope .' Concentration (pCi/cc) l I-131 '.

i I-132 I

I-133 I-134 I-135 40 ROUTINE & APPROVAL Date Initials

4.1 Calculations completed-by' ,

4.2- Analysis completed by l

4.3 Chemistry & Health Physics Supervisor 4.4 Chemistry / Health Physics Supervisor (TSC)

,O\-'

l \s_/ . 4.5 Director (TSC) i EPIP-31, (10-83) a