ML20235E220

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Revised Public Versions of Emergency Plan Implementing Procedures,Including EPIP-04, Status Rept on Plant Sys & Controls for Affected Unit, EPIP-06, RMS Status,Area Type Monitors & EPIP-6.10c, Assembly Area Designations..
ML20235E220
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 09/09/1987
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20235E198 List:
References
PROC-870909-01, NUDOCS 8709280025
Download: ML20235E220 (43)


Text

- _ - - _ _ - _ _ _ _ -

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August 28, 1987 U.S. NRC-Washington, Document Cntl Desk POINT BEACH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES (EPIPs) - ~~~-~~~~ ~ ~ ~

~~~ ~

The following revised and new forms are attached and should be inserted into your EPIP manual according to instructions provided.

1.

EPIP-04

" Status Report on Plant Systems & Controls For Affected Unit,"

(Insert behind EPIP 6.5).

2.

EPIP-06 "RMS Status, Area Type Monitors," (Insert behind EPIP 6.5) 3.

EPIP-6.10c

" Assembly Area Designations," (Insert behind EPIP 6.10).

4.

EPIP-7.2.la " Radiation Control Team Equipment Inventory & Functional Test Checklist," (Insert behind EPIP 7.2.1).

5.

EPIP-7.2.lb "Offsite Sampling Team Equipment Inventory & Functional Test Checklist," (Insert behind EPIP-7.2.la).

6.

EPIP-7.2.1c " Shuttle Team Equipment Inventory & Functional Test Checklist,"

(Insert behind EPIP-7.2.Ib).

7.

EPIP-13

" Status Update Form," (Insert behind EPIP 1.3).

8.

EPIP-14 "NRC Event Notification Worksheet," (Insert behind EPIP 1.3).

9.

EPIP-22

" Plant Personnel Emergency Call List," (Insert behind call list tab) 10.

EPIP-23 "Offsite Agency Emergency Call List," (Insert behind call list tab).

8709200025 070909 PDR ADOCK 05000266 F

PM

s t

08-28-87

/

TABLE OF EPIP FORMS EPIP EPIP j

Form Title Procedure

-01 Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center (10-86.)

7.3.1

-02 Emergency Plan Survey Record Site Boundary Control Center (10-86) - -

7.3.1

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

-04 Status Report on Plant Systems & Controls for Affected Unit (08-87) 6.5

-05 RMS Status (Release Point Monitors) (01-87) 6.5 l,

-06 RMS Status (Area Type Monitors) (08-87) 6.5 l

-06a RMS Status (Process Monitors) (05-84) 6.5

-6.10a Accountability Short Form (07-87) 6.10

-6.10b Assembly Area Roster (07-87) 6.10

-6.10c Assembly Area Designations (08-87) 6.10

-07 For X/Q Determination (03-85) 1.4

-7.2.la Radiation control Team Equipment Inventory & Functional Test Checklist (08-87) 7.2.1

-7.2.lb offsite Sampling Team Equipment Inventory & Functional Test Checklist (08-87) 7.2.1

-7.2.1c Shuttle Team Equipment Inventory & Functional Test 7

k Checklist (08-87) 7.2.1

-08 Estimated Whole Body & Thyroid Projected Doses (03-85) 1.4

-09 Estimated Whole Body Dose Calculation Worksheet for Specific Noble Gas Releases (03-85) 1.4

-10 Estimated Ground Deposition Calculation Worksheet for Particulate Radionuclides Releases (03-85) 1.4

-10a Estimated Population Dose (03-85) 1.4

-11 Summary of Radiological Dose Evaluation Calculations (03-85) 1.4

-12 Incident Report Form (07-87) 1.3

-13 Status Update Form (08-87) 1.3

-14 NRC Event Notification Worksheet (08-87) 1.3

-20 Technical Support Center Activation Checklist (04-87) 6.5

-21 Emergency Operations Facility Activation Checklist (01-87) 6.7

-22 Plant Personnel Emergency Call List (08-87)

Call List Tab

-23 Offsite Agency Emergency Call List (08-87)

Call List Tab

-24 Emergency Response Facility Telephone Directory (08-87)

Call List Tab

-25 Wisconsin Electric Headquarters Support Personnel Emergency Call List (08-87)

Call List Tab

~30 Reactor Coolant Post-Accident Sampling Analysis Report (06-86) 7.3.2

-31 Containment Atmosphere Post-Accident Sampling Analysis Report (06-86) 7.3.3 (2)-32 Search & Rescue and Emergency Operations Checklist (02-87) 12.1, 12.2

-33 Estimate of Core Damage Worksheet (08-87) 1.7

-34 Calculation of XE-133 Equivalent Release Rates (08-87) 1.8

-35 Dose Calculations (09-85) 1.8 l

L i-i e

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POINT BEACH NUCLEAR PLANT l

STATUS REPORT ON PLANT SYSTEMS AND CONTROLS FOR AFFECTED UNIT PPCS

.Page #

1.

Basic Accident Information (Unit

)

a.

Status Report Date/ Time:

/

Report #

(Date)

(Time-24 Hours) b.

Emergency Classification:

c.

(If applicable) Time of Reactor Shutdown:

hrs d.

(If applicable) Time of Radiological Release to Containment:

hrs (If applicable) Time of Radiological Release from Plant:

hrs c.

2.

Status of Reactivity Control Suberitical Yes No 3.

Status of Core cooling a.

Highest Th

  • F Coldest Tc
  • F 210 l

b.

Incore Thermocouple: Average Temperature

'F 210 i

c.

Pressurizer Heaters Available Yes No N/A d.

Subcooling Margin:

  • F 210 i

4.

Status of Reactor Coolant System Integrity f

a.

Pressurizer or Reactor System Pressure psig 220 b.

Pressurizer Level 220

{

c.

Primary System Relief Valves Closed Yes No N/A d.

Letdown Flow gpm 210 e.

Charging Pump Flow gpm 210 1

(

5.

Status of Secondary Systems q

1 a.

Steam Generator Pressure "A"

psig "B" psig 230

j b.

Steam Generator Level "A"

"B" 230

.I c.

Feedwater Flow Aux / Main "A"

gpm "B"

gpm 331 I

6.

Containment

,a a.

Pressure psig 250 b.

Containment Spray Pumps Running Yes No 250 1

c.

NaOH Addition Yes No Time Level N/A j

d.

Containment Recirculation Coolers Running (Circle) 1 2 3 4 N/A N

e.

Sump level inches 250 4

f.

H2 concentration 250

)

g.

Containment Isolation Valve (Note any not closad)

N/A

.l i

1 l

l EPIP-04 Page 1 of 2 (08-87) l t

U--__ _-_

b

Status Report Time:

PPCS 7.

Safeguards Systems a.

Safety Injection Train A Train B High head gpm gpm N/A Low head gpm gpm 240 b.

Accumulators Level N/A Pressure psig psig N/A Isolation Valve Open Yes/No Yes/No N/A c.

Refueling Water Storage Tank Level N/A d.

Component Cooling Water Temperature

  • F Flow gpm 260 e.

Service Water No.of pumps running Temp.

F N/A 8.

State of Meteorology Primary Tower Inland Tower

'l a.

Wind Direction (avg.)

351 b.

Wind Speed (avg.)

mph mph 351 c.

ce 351 d.

AT/6H

  • F
  • F 351 9.

Status of Power Supplies g

a.

Offsite Power Unit 1 Y/N Unit 2 Y/N Gas Turbine Y/N

(

b.

Diesel Running 3D Y/N 4D Y/N s"

Diesel Loaded 3D Y/N 4D Y/N Other Equipment Remarks:

Completed By Time Date EPIP-04 Page 2 of 2 y

(08-87) a

.s

POINT BEACH NUCLEAR PLANT 5

RMS STATUS

+

Area Type Monitors Time Date DAM Channel No.

No.

RMS No.

Location Range Reading 7

1 RE-101 Control Room E E+04 mR/hr 3

1 1RE-102 U1 Cont. El. 66' E E+04 mR/hr 4

1 2RE-102 U2 Cont. El. 66' E E+04 mR/hr 5

6 RE-103 Chemistry Lab E E+04 mR/hr 1

1 1RE-104 U1 Charging Pump E E+04 mR/hr 2

1 2RE-104 U2 Charging Pump E E+04 mR/hr 6

5 RE-105 SFP El. 668 PAG E E+04 mR/hr 3

4 1RE-106 U1 Sample Room E E+04 mR/hr 4

4 2RE-106 U2 Sample Room E E+04 mR/hr 1

9 1RE-107 U1 Seal Table E E+04 mR/hr

[

2 9

ERE*107 U2 Seal Table E E+04 mR/hr 7

7 RE-108 El. 26' PAB DA E E+04 mR/hr 5

1 1RE-109 Post Accident Sample Line E E+04 mR/hr 6

1 2RE-109 Post Accident Sample Line E E+04 mR/hr 8

9 RE-110 SI Pump El. 8' PAB E E+04 mR/hr 8

7 RE-111 C59 E E+05 mR/hr 8

4 RE-112 El. 8' PAB Central E+00 - E+06 mR/hr 8

1 RE-113 El. -19' PAB E E+04 mR/hr 7

8 RE-114 CVCS Holding Tank E E+04 mR/hr 5

5 RE-116 Letdown Valve Gallery E -E+05 mR/hr 3

8 1RE-134 U1 Charging Pump E+01 - E+07 mR/hr 4

8 2RE-134 U2 Charging Pump Area E+01 - E+07 mR/hr 8

8 RE-135 SFP - High Range E+01 - E+07 mR/hr EPIP-06 (08-87)

Page 1 of 2 u_______------_-_--_-_-------_--

i

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f1

.t.

4 L

4 i

LDAM Channel-l:/ '

No.

No.

RMS No.

Location Range Reading 1

'8 1RE-136 U1 Sample Room E+01 --E+07 mR/hr 2

S 2RE-136 U2 Sample Room E+00 - E+06.mR/hr 5

9 RE-140 SI Pump Room El. 8" PAB E+01 - E+07 mR/hr 1

4 1RE-211B-U1 Facade El. 52'

'E+00 - E+06 cpm 2

4 2RE-211B U2 Facade El. 52' E+00 - E+06 cpm 1

6 1RE-216B Slightly South C59 E E+04 mR/hr 2

6 2RE-216B Slightly North C59 E E+03 mR/hr 7'

3 RE-218B U2 PAB El. 8' E E+03 mR/hr 5

4 1RE-219B Outside U1 Sample Room E E+03 mR/hr 6

4 2RE-219B Outside U2 Sample Room E E+03 mR/hr 7

6 RE-220B PAB El. 468 E+00 - E+06 mR/hr 1.

7 1RE-222 U1 Facade El. 26' E E+04 mR/hr

,.~

1(. !

~2 7

2RE-222 U2 Facade El. 26' E E+04 mR/hr 8

6 RE-223B CCW HX El. 46' PAB E E+03 mR/hr 3

3 1RE-229B U1 El. 8' PAB E E+04 mR/hr 4

3 2RE-229B U2 Aux Feed TB El. 8' E E+03 mR/hr 8

3 RE-230B U2 TA El. 8' WT Area E E+03 mR/hr 6

8 RE-234B Turbine Hall El. 74' E+00 - E+06 epm EPIP-06

~(08-87)

Page 2 of 2

NA'MES AND TELEPHONE. NUMBERS i

le ASSEMBLY _ AREA DESIGNATI,03 ADMINISTRATIVE ASSEMBLY LOCATION: El. 18.5' TSC Status Name l

d l

0, l

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l '

i f

/

i EPIP-6.10c PAGE 1 0F 10 (08-87)

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L ASSEMBLY AREA DESIGNATIONS CHEMISTRY ASSEMBLY LOCATION: HP Station Status.

Name

.e EPIP-6.10c PAGE 2 0F 10 (08-87)

b i

e a

1

. ASSEMBLY AREA DESIGNATIONS l

EQRS ASSEMBLY LOCATION:

El. 18.5' TSC Status Name-o 4

I l

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l

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EPIP 6.10c PAGE 3 0F 10 (08-87) l

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[

' ASSEMBLY AREA DESIGNATIONS l

i HEALTH PHYSICS ASSEMBLY LOCATION: HP Station Status Name i

l 1

EPIP-6.10c PAGE 4 0F 10 (08-87)

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6 ASSEMBLY AREA DESIGNATIONS INSTRUMENT & CONTROL ASSEMBLY LOCATION:

El. 18.5' TSC Status Name 1

i l

i i

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l EPIP-6.10c PAGE 5 0F 10 (08-87)


o

A 4

ASSEMBLY AREA DESIGNATIONS MAINTENANCE ASSEMBLY LOCATION:

El. 18.58 TSC Status Name Status Name 1

1 l

1 EPIP-6.10c PAGE 6 0F 10 (08-87)

7.___

a,-'

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.s

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l(i ASSEMBLY' AREA DESIGNATIONS-l.

[-

o:

GPERATIONS 1'.

'. ASSEMBLY LOCATION:

El. 18.5' TSC l

t-

. Status Name-Status-Name 4

l

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.c

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4 EPIP-6.10c PAGE 7 0F 10 (08-87) i

ASSEMBLY AREA DESIGNATIONS REACTOR ENGINEERING ASSEMBLY LOCATION:

El. 18.58 TSC Status Name

/.

i l

l j

EPIP-6.10c P.hGE 8 0F 10 (08-87) 4

l ASSEMBLY AREA DESIGNATIONS TECHNICAL SUPPORT CENTER l

ASSEMBLY LOCATION:

TSC

~ ~ - ~

~ ~ ~ ~ ~ ~

Status Name l

EPIP-6.10c PAGE 9 OF 10 (08-87)

e ASSEMBLY AREA DESIGNATIONS l

l' TRAINING ASSEMBLY LOCATION: El. 18. 5 '-TSC -

l Status Name t

EPIP-6.10c PAGE 10 0F 10 (08-87)

POINT BEACH NUCLEAR PLA!C RADIATION CONTROL TEAM SQUIPMENT IPTVENTORY AND FUNCTIONAL TEST CHECKLIST 1.

Inventory Dosirnetry Devices Min. Required On Hand Date By TLD 90

~

0-500 mR SRDs 50 0-5 R SRDs 50 Issue SRDs and TLDs l

2.

Response Test l

Type of Serial Check Source Check source Instrument Number Used Criteria Results

\\

Ludlum 3 cpm cpm Ludlum 3 cpm cpm Ludlum 3 cpm cpm VAMP mR/hr mR/hr Nuclear Chicago epm cpm 3.

Functional Test Serial Number Date By a.

High volume air sampler (Bendix) b.

High volume air sampler (115 V AC Radeco) c.

Low volume air sampler (115 V AC) d.

SRD charger e.

FH base station radio test with TSC Time hrs f.

Spare 2200 watt and 5000 watt generator 4.

Set up step off pads (one at the north door, one at the northwest door) and establish access control Time hrs Reviewed by Date Off-Site HP Director EPIP-7.2.la (08-87)

POINT BEACH NUCfEAR PLANT OFFSITE SAMPLING TEAM EQUIPMENT INVENTORY AND FUNCTIONAL TEST CHECKLIST Minimum On Item Required Hand Date h

115 V Radeco air sampler 1

Functional Test - Serial #

Scott cartridge holder 1

Silver zeolite cartridge holder 1

Air particulate filter (box) 1 Silver zeolite cartridge 5

Scott charcoal cartridge 5

RO-2 survey meter 1

Response Test Serial Check Source Check Source Number Used Criteria Results mR/hr mR/hr mR/hr mR/hr Water-filled poly bottle 2

(1 liter)

Liquid sample cubitainers 2

(1 liter)

Stop watch with batteries 1

Functional Test Scissors 1

Plastic suit (sets) 2 Gloves, surgecn's (pr) 6 Self-reading dosimeters, 0-5 R 2

Self-reading dosimeter charger 1

Functional Test Plastic bags:

12"x18" 6

5"x8" 6

3"x5" 12 Flashlight with spare bulb &

batteries 1

Functional Test EPIP-7.2.lb Page 1 of 2 (08-87)

a F

e Minimum On Item Required Hand Date By Smears (box of 100) 2 Tuck tape (roll) 1 Sharpie, Flair, grease pencil'

& pencil 1 each Sample ID tag (pad) 1 Sampling procedure:

EPIP 7.3.1 Airborne Sampling

& Direct Dose Rate Survey Guidelines & Attachment 5

Sampling forms:

EPIP-01 Airborne Radiation Survey Record 20 EPIP-02 Emergency Plan Survey Record 20 survey Identification Maps 1 pad CHP-34, SRD Rezero Sheet 5

9 V batteries 4

Cs-137 source 1

Calculator 1

Clipboard 1

Fuses 5

ccin envelopes (pkg) 1 Broadbeam flashlight with 7.5 V battery 1

Functional Test 14 Q bucket 1

Snow sovel-(small) 1 Plastic Petri dishes (2" dia) 10 Key to unlock site barricades 1

Spare site barricade key for shuttle team 1

Equipment Not in Sample Kits But Required For Offsite Sampling 2200 wett generator 1

Functional Test DC powered air sampler 1

Functional Test Traffic cones 4

Positive pressure breathing apparatus with at least one backup air cylinder each 2

Portable FM radio with roof antenna 1

j Functional Test Vehicle gasoline 3/4 tank Reviewed by Date l

Offsite HP Director EPIP-7.2.lb Page 2 of 2 (08-87)

sp POINT BEACH NUCLEAR PLANT-SHUTTLE TEAM EQUIPMENT. INVENTORY AND FUNCTIONAL TEST CHECKLIST Minimum :

On

-Item Required Hand Date By Site barricade key (obtained from Sample Kit) 1 Portable FM radio with roof antenna...

1 Functional Test Positive' pressure breathing

-apparatus with at least one backup-air cylinder

-l' Vehicle gasoline 3/4 tank Reviewed by Date-Offsite HP Director

.i 5..

I l

{l l

l

)

l l

l 1

l EPIP-7,2,1c (08-87).

o POINT BEACH NUCLEAR PLANT

~

STATUS UPDATE FORM LOG NOTIFICATIONS HERE:

Agency Time / Person Notified Initials Manitowoc County

/

Kewaunee County

/

Wisconsin DEG (Warning Center 2)

/

NOTE: THIS (IS/IS NOT) A DRILL.

1.

IDENTIFICATION

~~

o This is the (Name)

(Title) at the Point Beach nuclear power plant reportir.g on the status of the (Unusual Event / Alert / Site Emergency / General Emergency) in progress at on (Time)

(De.te )

2.

STATUS e

The following infonnation is now available:

A.

Plant (1) Description of event l

(Fire, Explosion, Pipe or Tank Rupture, etc.)

(2)

Corrective action taken:

(3) Condition of Reactor (shutdown /not shutdown).

(Time:

hours)

(4) Major equipment affected:

B.

Plant Personnel (1)

Injuries (yes/no); if yes, number injured (2) Contaminated personnel (yes/no); if yes, number (3) overexposure to personnel (yes/none/ possibility exists);

if yes, number (4) Other potential or actual hazards C.

Meteorological Conditions (Time:

hours)

(1) Wind speed (mph)

(2) Wind direction degrees (from to

)

(Compass)

(Compasc)

EPIP-13 l

(08-87)

Page 1 of 2

s (3) Stability class i

(4) General weather conditions D.

Radiological Conditions Off-Site (1) Release of radioactive material is (not expected / expected /

in progress).

4 (2)

If applicable:

l i

(a) Release of radioactive material (Will start /has started) 1 at on and is expected to continue l

(Time)

(Date) l for (Hour / Minutes)

(b) The radiological release is in (liquid / gaseous) form and is (controlled / uncontrolled).

(c) The release rate is estimated to be:

Iodine Ci/sec Noble gas C1/sec (d) The projected arrival time for the plume at miles down wind is (Time)

(e) The projected dose at miles down wind at plume centerline is Rem to the whole body and Rem to the thyroid.

(f)

(If applicable) Measured surface deposition is 7

(dpm/100 cm2 or Ci/m2) at (Location)

(Time:

hours) 3.

RECOMMENDED PROTECTIVE ACTIONS ARE:

A.

None.

B.

Take shelter in following areas:

(Location, sector and miles radius)

C.

Evacuate the following areas:

(Location, sector and miles radius)

D.

Other in (Recommended Action)

(Location) 4.

PRESS RELEASES from the JPIC in Two Rivers, Wisconsin (are/are not) planned.

5.

ADDITIONAL ASSISTANCE required (yes/no).

If yes:

A.

(Problem Area)

(Agency)

B.

(Problem Area)

(Agency)

Assessment of plant conditions will continue.

further status uptate will l

be transmitted to you periodically, based on the change in plant conditions.

NOTE: THIS (IS/IS NOT) A DRILL.

l EPIP-13 (08-87)

Page 2 of 2 I

L__--- - --

POINT BEACH NUCLEAR PLANT 1*

NRC EVENT NOTIFICATION WOR $ SHEET

'I N!tification Time Unit (s)

Caller's Name NRC Duty Officer PBNP Call Back (C2ntral Time)

POINT BEACH NUCLEAR PLANT Telephone Number Ev:nt Classification 4 Check Applicable Event (s)

Initiation Signal

/

Check Applicable cause(s)

General Emergency Reactor Trip Mechanical Site Area Emergency ESP Actuation Electrical Alert ECCS Actuation Personnel Error Unusual Event Safety Injection Flow Procedure Inadequacy 50.72 Nonemergency LCO Action Statement other Security / Safeguards other Transportation Event Event Time Event Date Systems (Central time zone)

Month Day Year other Component:

Hours EVENT DESCRIPTION

?

l Pow 2r Prior to Event (%):

Did all systems function as required?

Yes/No If No, Explain above.

i i

l Current Power or Mode:

Anything " Unusual" or not understood?

Yes/No If Yes, Explain above.

Outside Agency or Personnel Corrective Action (s) j Natified by Licensee State of Wisconsin Yes No Manitowoc County Yes No Ksw unee County Yes No R3sident Yes No Will Be

]

l Oth2r Mode of operation Till Correction:

Estimate Time to Restart:

' Press Release Planned Yes No Additional Information en Next Page EPIP-14 Page 1 of 3 (08-87)

p 6

ADDITIONALINFORMATIONFORRADIOL0dICALRELEASES-Note: Only if T.S. exceeded or actual contamination Liquid Release Planned Source (s):

Gaseous Release Unplanned Releast Rate (C1/see):

EST Total Activity (C1):

Releasi Duration:

Estimated /Known EST Total Iodine (C1):

T.S. Limits:

Release rate determined by: (J if applicable)

RMS Readinq Contact Reading Are s Evacuated?

l Y l N I List Below Fersornel Exposed / Contaminated } Y l N t Describe Below P Pnt Health Physics Backup Requested?

Y lN l ADDITIONAL INFORMATION f

\\..'.,'

ADDITICHAL INFORMATION FOR REACTOR COOLANT OR STEAM GENERATOR TUBE LEAKS Leak MO DY YR Leak Le k Developmertr Sudden /Lonc term Start date Start Time Hours (Central time)

Lisk Rater Primary Coolant Activity:

MONITOR READINGS Leak Volume Secondary Coolant Activity:

Condenser:

( )RE 215 T.S. Limits:

Main Steam Lines

( )RE 231

( )RE 232 SG Blowdown

( )RE 222 List of Safety-Related Equipment N3 Operational:

Sp cial Actions Taken by Licensee (if any):

)

I' I

i l

\\

l EPIP-14 Page 2 of 3 (08-87)

L_____________

e' ADDITIONAL INFORMATION FOR CIASSITIED EMERGENC1 EVENTS CdncurrentEALs Category Initiating Conditions l '.

2.

3.

4.

5.

6.

1 i

I EPIP-14 Page 3 of 3 (08-87)

E________=____

s '.L

' NAMES AND-

'i tTE[EPHONE NUMBERS..

I DELETED..-

p PLANT PERSONNEL EMERGENCY CALL IIST y ~,

~

' 1.

Duty & Call Superintendents.(Pager Group No. 501).

l Name Pager No.

Plant E.:t.

Home Phone' Time Notified l

l 2.

Shift Superintendents Name Plant Ext.

Home Phone Time Notified i

\\-

wE I

I I

i EPIP-22 4

-(08-87)

Page 1 of 4

t-I

  • l r.

3.

Chemistry (Pager Group Nos. 540 & 530)

Name Pager No.

Plant Ext.

Home Phone Time Notified 1

4.

Health Physics (Pager Group Nos. )

Name Pager No.

Plant Ext.

Home Phone Time Notified 5.

Instrumentation & Control (Pager Group Nos. )

Name Pager No.

Plant Ext.

Home Phone Time Notified EPIP-22 (08-87)

Page 2 of 4

l5 i!14 '

. -s.

4 if ' '

.t
6.

Maintenance (Pager. Group No. ).

[:

E.

Name Pager No.

Plant Ext.

Home Phone

Time Notified

?

ls 1

s

?i a

('

- 7.

Reactor Engineering k.,. f

'.Name' Plant' Ext.

Home Phone Time Notified.

8.

Plant Administration & Security Name Pager No.

Plant Ext.

Home Phone Time Notified

'l 1

l

- EPIP-22 (08-87)

Page 3 of 4 I

4

4 N

,8

,r 9.

Emergency Planning Name Pager No.

Plant Ext.

Home Phone Time Notified t

l l

10.

Duty Technical Advisors (Group Nos. 530, 520, & 530)

Name Pager No Group No.

Plant Ext.

Home Phone Time

  • Notified

,i,..

Public Service Building, Milwaukee

    • Page through system control, Pewaukee 11.

Fire Brigade Members NOTE:

REFER TO PSNP FIRE PROTECTION MANUAL CALL LIST, SECTION FEP 2.0.

EPIP-22 (08-87)

Page 4 of 4

Ll

-1 NAMES AND 1

r f

tTELEPHONE NUMBERS l

^

~

DELETED OFFSITE AGENCY EMERGENCY CALL-LIST-FEDERAL AGENCIES:-

.-y 1.

United States-Nuclear Regulatory Commission Telephone Person Time l

Name-Frequency' Number:

Notified Notified Initials-NRC Operations All hours Red Phone Center NRC Office of All hours Inspection and (Ask for Enforcement, Duty Officer)

Region III NRC Project

Manager, NRC Resident Inspectors: Pager Plant Ext.

Home

~

+

I' 2.

United States Department of Energy Telephone Person Time Name Frequency Number Notified Notified Initials Chicago Operations Weekdays 1-312/972-4800 Center, Region V (8AM-5PM)

(Radiological Assistance Team)

All other 1-312/972-5731 hours 3.

United States Coast Guard Telephone Person Time Name Frequency Number Notified Notified Initials MSO, Milwaukee All hours 1-291-3165 USCG, Sturgeon All hours 1-743-3366 Bay USCG, Two All hours 793-1304 Rivers i

l 1.

.EPIP-23 Page 1 of 5 (08-87)

L

'W

^ 5 4.

' United States-National Weather Service 4

~ ~.

Telephone-Person Time Name Frequency Number Notified Notified-Initials

=-

NWS, Green Bay All hours NAWAS 1-494-7478 1-433-3876 STAiE OF WISCONSIN" AGENCIES Telephone Person Time Name Frequency' Number Notified Notified Initials Wisconsin Dept. of Weekdays 1-608/273-5180 Health and Sociali (9AM-5PM)

Services, Section of Radiation Pro-l tection Wisconsin Division-All hours 1-608/266-3232

,1 of Emergency or NAWAS 1, '

Government v~a -

Wisconsin State All hours 1-608/266-3212 Patrol - Madison or NAWAS Wisconsin State All hours 1-929-3700 Patrol - Fond du Lac Wisconsin National (8AM-4PM) 794-7521 Guard - Two Rivers Armory EPIP-23 Page 2 of 5 (08-87)

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COUNTY AGENCIES:

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1.

Hanitowoc County Telephone Person Time Name Frequency Number Notified Notified Initials Manitowoc County All hours 688-911 Sheriff 683-4200 or NAWAS er radio Manitowac County Following 683-4208 EOC Activation or 683-4210 2.

Kewaunee County Telephone Person Time Name Frequency Number Notified Notified Initials Kewaunee County All Hours 1-388-3100 Dispatcher or NAWAS Kewaunee County Following EOC Activation 1-487-5257 OFF-SITE AGENCIES SUPPORTING JPIC ACTIVATION Telephone Person Time Name Frequency Number Notified Notified Initials Phone Service at Community House All Hours 1-800/362-7585 All Hours 1-800/428-6115 Superintendent of Office 388-3230 Schools, Kewaunee City of Two Rivers All Hours 688-911 Police Dept All Hours 793-5511 EPIP-23 Page 3 of 5 (08-87)

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l PRIVATE AGENCIES I

/N Telephone Person Time l

Name Frequency Number Notified Notified Initials Kewaunee Nuclear All hours 793-2229 l

Power Plant I

EOF After Activation Dial Select 23 l

TSC After Activation Dial Select 33 Institute of All hours 1-404/953-0904 Nuclear Power 1-404/953-3600 Operations American Nuclear Insurers All hours 1-203/677-7305 Westinghouse Electric Corp.

Site Services Rep.

Office l

Home i

area Hanager Office

)

Home 1st Alternate Office Home 2nd Alternate Office Home I

s Stone & Webster Office l

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Engineering Corp.

Bechtel Power Corporation office Home Office Home University of office Wisconsin -

Milwaukee Seismic Center Office Home office Office Wisconsin Public Service Corp.

(EOF Power)

EPIP-23 Page 4 of 5 (08-87)

F,,

,s FIRE AND MEDICAL AGENCIES.

l

1. Fire Emergency L

Telephone Person Time Name Frequeny Number Notified Notified Initials Two Creeks Fire All hours 688-911 Department

2. Medical Assistance Telephone Person Time Name Frequency Number Notified Notified Initials Emergency All hours 688-911 or Vehicle 683-4200 Ambulance Community Hos-All hours 793-1178 pital, Two Rivers Doctors Clinic, Ltd.

793-2281 University Hos-pital, Madison Emergency Room All hours 1-608/262-2398 B

EPIP-23 Page 5 of 5 (08-87)

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h

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4

. NAMES AND'

~

- TELEPHDNE NUMsERS' T

DELETED e [....

hm POINT. BEACH NUCLEAR PLANT

.f '

' CMEftGENCY RESPONSE FACILITY TELEPHONE DIRECTORY i.

/,\\

Extension Photh

.. Technical' Support Center Site Manager Plant Operations Manager

(.

Health Thysics Supervisor & Chemists Core Physics Coordinator,

Systems Analysis & Procedural i

Support' Coordinator Offsite Communicator 1,

+'x Operations Support Center.

i g'

Maintenance supervisor

. ~ -

p Health Physics counting Area n

Emergency Operation Facility Emergency Support hanager Offsite Communicator Rad / Con Waste Manager Radiation Dor,e Projection Telecopier i

~

EPIP-24 Page 1 of 2 i

(08-87) l n

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l 8.;

4 r;

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.i [# l f?> :. Site Boundary Control Center E

f 2, Offsite Health' Physics Director L 7;. '

Joint Public Information Center.

JPIC Dirc tor

, Cort > orate Emergency Center Emergency Director

- Alternate Emergency Operations Facility (Two Rivers)-

'l Emergency Support Manager-Rad Con / Waste Manager

' l,... r:' '.

Offsite Communicator JPIC Communicator Telecopier Modem NRC Office 1

EPIP-24 Pace 2 of 2 (08-87)

)

I

  • i NAMES AND POINT BEACH NUCLEAR PLANT.

JELEPHONE. NUMBERS.

WISCONSIN ELECTRIC

. DELETED. ' -

. HEADQUARTERS SUPPORT PERSONNEL EMERGENCY CALL LIST

.\\

NOTE: ALL TELEPHONE NUMBERS WITH A 221 PREFIX HAY BE DIALED FROM POINT BEACH ON THE PBX SYSTEM WITH AN "8" FOLLOWED BY THE LAST 4 DIGITS OF THE NUMBER.

(E.G., WE. SWITCHBOARD'8-2345)

NOTE: ALL TELEPHONE NUMBERS ARE IN THE "414" AREA, UNLESS OTHERWISE INDICATED.

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1.

NUCLEAR POWER DEPARTMENT Time Name Pager No.

Company Ext. Home Phone Notified y-

  • s.,V

)

)

EPIP-25 Page 1 of 3 (08-87)

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l 1.

NUCLEAR POWER DEPARTMENT (Cont'd.~)

Ts i

Time

_ ~'

Name Company Ext. Home' Phone Notified I

_ _ _ _ _ _. ~

2.

COMMUNICATIONS DEPARTMENT NOTIFICATION

.(A) 0700 - 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> Monday - Friday (Media Line)

.(B) After Hours Listing:

Call the following list of Communications Department Personnel, in order, tntil one is reached:

l. 'l -/"? N; Home Business Phone Home Personal Phone t

Q.)

\\

3.

COMPANY ADMINISTRATION & DEPARTMENTS Time Name Company Ext.

Home Phone Notified 1

l l

I i

EPIP-25 Page 2 of 3 (08-87)

L__

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e-e 4.

OTHERS

.,x.

1 Time Name Company Ext.

Home Phone Notified

+e

..s EPIP-25 Page 3 of 3 (08-87) l l

l 1

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1 i

POINT BEACH NUCLEAR PLANT

{

1

{~ -

ESTIMATE OF CORE' DAMAGE WORKSHEET This' form should be completed, as required, by the Core Physics Coordinator or his. designate.

1.

Sample Bomb Contact Reading (R/Hr) j Time of Reading Time Since Shutdown (Hr) 2.

Contact Reading Reactor Shutdown

=

=

(24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

(24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) j 3.

. Estimated Sample Activity (ESA):

Sample Bomb Conversion Factor.( }

ESA (Ci/ml)

=

( Ci/ml Contact x

Reading (R/Hr)

R/hr

)

x

=

(1) Attachment 1.7-1 4.

Estimate of Core Damage, b,

ESA x (32,500 + ESIV)

Percent Core Damage (%)

=

Correction Factor [CF(t)) 2) 1

(

x

)

=

ESA 32,500 + ESIV CF(t) i

=

i (2) Attachment 1.7-2 l

CALCULATIONS PERFORMED BY:

TIME /DATE:

SIGNATURE:

I l

I REVIEWED BY:

I Route this form to the Technical Support Manager and site Manager upon completion.

i i

i i

EPIP-33 i

(08-87)

I C-_______-------------

a e

WORKSHEET NO. 1 T-XE-133 EQUIVALENT RELEASE RATE A.

OPERATIONAL LOW-RANGE RELEASE MONITORS READOUTS Flow Rate Conversion ~

Xe-133 Equiv.

Assumed Release Rate (cfm)

Reading Factor Ci/sec Auxiliary Building Vent 70,000 pCi/cc x 33

=

Drumming Area Vent 43,100 pCi/cc x 20.3

=

Unit 1 Containment Purge, (0 or 1 fan) 12,500 pCi/cc x 5.9,

=

C (2 fans) 25,000 pCi/cc x 11.8,

=

p Unit 2 Containment Purge, (0 or 1 fan) 12,500 pCi/cc x 5.9,

=

(2 fans) 25,000 pCi/cc x11.8,{C

=

\\, x' Gas Stripper Building ec Ci Vent 13,000 pCi/cc x 6.1 sec pCi Combined Air Ejector 25

,pci/cc x.012 x see i

Steam Line Vent Atmospheric pCi/cc x 1.09,

=

1 Safety pCi/cc x 2.52,,

=

2 Safeties pCi/cc x 5.04,##

=

g 3 Safeties pCi/cc x 7.56 e

4 Safeties pCi/cc x 10.1

=

l

{

l EPIP-34 (08-87) l L

r T, 0 c

.1P I

Page 2

,n 4

}

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 (0 or i fan) 12,500 x 8.0 x 101

=

(2 fans) 25,000 x 1.6 x 102

=

Unit 2 Containment Purge (0 or 1 fan) 12,500 x 8.0 x 101

=

(2 fans) 25,000 x 1.6 x 102

=

Gas Stripper Building 13,000 x 8.0 x 101

=

Combined Air Ejector 25 x 1.6 x 102

=

Main Steam Header Atmos.

x 8.07 x 102

=

1 Safety x 2.02 x 103

=

2 Safeties x 4.03 x 103

=

3 Safeties x 6.05 x 103

=

4 Safeties x 8.08 x 103

=

C.

ACTUAL VERSUS CONVERSION CURVE FLOW RATE RATIO Ad usted Release Rate, Ci/sec x Re ease Rate Value, Ci/sec

=

s ed w

te fm

,ci/see h

(

)x

,Ci/sec

=

EPIP-34 (08-87)

k 9

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Page 3

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's D.

ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEAS, RATE Xe-133 Equivalent Release Rate Vent (Curies /Sec.)

1. Auxiliary Building
2. Drumming Area
3. Gas Stripper Building
4. Cotabined 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)

(

Completed By Time Date i

I EPIP-34 (08-87)