ML20100H137

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Public Version of Revised Emergency Plan Implementing Procedures,Including RP/O/A/5000/02, Notification of Unusual Event & RP/O/A/5000/03, Alert
ML20100H137
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 02/26/1985
From: Bolch M, Leroy P, Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
PROC-850226-01, NUDOCS 8504080601
Download: ML20100H137 (200)


Text

_ _

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  • Form 34731 (10 81)

(Formerly SPD 10021)

DUKE PUJER COMPANY (1) ID No: RP/0/A/5000/02 PROCEDURE PREPARATION Change (s) 3 to PROCESS RECORD 4 Incorporated (2) STATION: CATAWBA (3). PROCEDURE TITLE: NOTIFICATION OF UNUSUAL EVEh*I (4) PREPARED BY: Mv& __ _ DATE: 2-15-85 (5) REVIEWED BY: DATE: .7-/f-Ff V

. Cross-Disciplinary Review By: L 2,. @ -- 2h r/tf N/R:

g a - -

(6) TEMPORARY APPROVAL (IF NECESSARY):

/ By
(SRO) Date:

By: , . Date:

(7) APPROVED BY:

  • Date: Si ihkI~

9 (8) MISCELLANEOUS:

Reviewed / Approved By: Date:

Reviewed / Approved By: Date:

hDR h 13 F PDR l

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RP/0/A/5000/02 DUKE POWER COMPANY CATAWBA NUCLEAR STATION NOTIFICATION OF UNUSUAL EVENT 1.0 SYMPTOMS ,

1.1 This condition exists when events are in process or have occurred which indicate a potential degradation of the level of safety of the plant.

2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to individuals and organizations.

2.1.1 Complete Enclosure 4.2 an i Part I of Warning Message Form.

(See example Enclosure 4.J.) Record receivers name and time (initial contact).

NOTE: Emergency Coordinator shall initial forms when message is approved for transmission.

NOTE: Warning Message Forms are kept in a notebook in the

. Control Room and TSC, ensure that all used forms are returned to the back of the notebook.

2.1.2 Notifications shall be as the order of Enclosure 4.1 indicates. See RP/0/B/5000/13 for NRC Notification.

NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency.

3.0 SUBSEQUENT ACTIONS 3.1 Close out or Follow up Notifications.

3.1.1 Close out the Emergency with a follow-up message 9R 3.1.2 Give follow-up messages to agencies listed in 4.1.3 of Enclosure 4.1, use the following schedule:

e If the Unusual Event Situation lasts longer than one hour, then repeat each hour until closed out.

9.R.

e if there is any significant change to the situation. '

1

.)

. . l

'1 RP/0/A/5000/02 '

l Page 2 of 2 .

1 o As agreed upon with the individual agencies.

NOTE: The close out message shall be made approximately 30 minutes after the last transmitted message. Indicate on ,

the message form, Part I #11b. that this is a close out message.

3.2 Augment shift resources to assess and respond to the emergency situation as needed.

3.3 Assess the emergency condition, then remain in a Notification of Unusual Event, escalate to a more severe class or terminate the emergency.

3.4 The Compliance Engineer or delegate shall follow up with a written summary to county and state authorities, notified in 4.1.3 of Enclosure 4.1, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.0 ENCLOSURES 4.1 Telephone Notification List 4.2 Emergency Message Format

[' 4.3 Example Warning Message: Nuclear Facility to State / Local Government I 3 e

f 3

\

4 I

RP/0/A/5000/02 k .r.

L5 Enclosure 4.1

(G# Page 1 of 2 TELEPHONE NOTIFICATION LIST 4.1.1 CNS Emergency Personnel Initial i 1. Operations Duty E r - Plant Page P & T Pager A
See Current Operations ork List for Home Phone Number.

i

2. Station Man r - J. W. Hampton Offic

]

Hee-

)

mw 1st Alternate - C. W. Graves l l

2nd Alternate - J. W. Cox ]

i p 3rd Alternate - G. T. Smith 4th Alternate - B. F. Caldwell )

oe

3. Compliance En ineer - C. L. Hartzell Offic i Hom 1st Alterna Bolch Offic Hom

=w t 2nd Alternate - P. G. LeRoy l

4.1.2 Nuclear Production Du

, P & T Pa

    • USE ENCLOSURE 4.

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'i RP/0/A/5000/02 Enclosure 4.1 Page 2 of 2 4.1.3 State & County Warning Points (Within 15 minutes)

1. N.C. Sta Raleigh
      • SURE 4.3 ***
2. S.C. olumbia 7:30 a.m. - 5:00 p.m. Weekdays P:

A After hours, Weekends & Holidays US ENCLOSURE 4.3 ***

1

3. Mecklenburg County P: gnal Back-up: Emergency Radio, Code:
      • USE ENCLOSURE 4.3 ***
4. York County P: Selective Signal A .6 -

Back-up; Emergency Radio, Code:

      • USE ENCLOSURE 4.3 ***
5. Gaston County P: Selective Signal -

A Bac@k-up: Emergency Radio, Code

      • USE ENCLOSURE 4.3 ***

4.1.4 NRC Operations Center, Bethesda, Md. (RP/0/B/5000/13) l P: ENS hone (red phone)

A:

t 0 .

RP/0/A/5000/02 Enclosure 4.2 )

Page 1 of 1 ,

DUKE POWER COMPANY CATAWBA NUCLEAR STATION TO NUCLEAR PRODUCTION DUTY ENGINEER EMERGENCY MESSAGE FORMAT

1. This is at Catawba Nuclear Station. -

(Name and Title)

2. This is is not a drill. An X Unusual Event Alert Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit e .

(Time)

3. Initiating Condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status.)
4. Corrective measures being taken:

l

5. There have have not not been any injuries to plant personnel.
6. Release of radioactivity: is taking place is not taking place
7. NRC Yes No; State Yes No; Counties Yes No; have been notified.
8. The Crisis Management Team should should not be activated.

Corporate Communications and Company Management should be notified.

9. I can be reached at for follow-up information.

(Telephone Number)

10. Additional Comments:

Name of Person Contacted Date Time 4

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

e

  • RP/0/ AiS000/02 Enclosure 4.3 Page-1 of 4 EXAMPLE WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Instructions:

A. For Sender:

1. Complete Part I for the initial Warning Message.
2. Complete Parts I L ll for follow-up messages.

B. For Receiver:

1. Record the date, time and your name in the area below.
2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part 1.5) l Time: Date:

i Message Received By:

l PARTI

1. This is: Catawba Nuclear Station
2. My name is: John Doe, Shift Supervisor
3. This message (number J ):

X (a) Reports a real emergency.

(b) is an exercise message. ,

4. My telephone number / extension is
5. Message authentication: USE MESSAGE AUTHENTICATION LIST (Verify code word or call back to f acility)
6. The class of the emergency is: X (a) Notification of Unusual Event (b) Alert (c) Site Emergency (d) General Emergency
7. This classification of emergency was declared at: (a.m./p.m. ) on

) (date).

i

8. The initiating event causing the emergency classification is: _ Loss of l Offsite Power i

?

I

9. The emergency condition: X (a) Does not involve the release of radioactive materials from the plant.

(b) Involves the potential for a release, but no release is occurring.

(c) Involves a release of radioactive material.

e RP/Of A/5000!02 Enclosure 4.3 Page 2 of 4

10. We recommend the following protective action:

X (a) No protective action is recommended at this time.

(b) People living in zones remain indoors with the doors and windows closed.

(c) People in zones evacuate their homes and businesses.

(d) Pregnant women and children in zones remain indoors with the doors and windows closed.

(e) Pregnant women and children in zones evacuate to the nearest shelter / reception center.

(f) Other recommendations:

11. There will be:

't (a) A followup message X (b) No further communications Approved for Release.

12. I repeat, this message:

X (a) Reports an actual emergency Emerg. Coord. Time (b) is an exercise message

13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NOCLEAR FACILITY.
      • END OF INITIAL WARNING MESSAGE ***

PART 11

1. The type of actual or projected release is: N/A (a) Airborne V

(b) Waterborne (c) Surface spill (d) Other

2. The source and description of the release is: N/A 3.. N/A (a) Release began /will begin at a.m./p.m.: time since reactor trip is hours.

N/A (b) The estimated duration of the release is hours. 1 i

I 1

RP/0/ A/5000/02 Enclosure 4.3 Page 3 of 4 Dose projection base data:

4.

Radiological release: N/A curies, or curies /sec.

Windspeed: 5 mph Wind direction: From 180 Stability class: D ( A, B,C,D,E.F, or G)

Release height: N/A Ft.

Dose conversion factor: N/A R/hr/Ci/m3 (whole body)

N/A R/hr/Ci/m' (Child Thyroid)

Precipitation:

0 Temperature at the site: 72 *F

5. Dose projections: N/A .
  • Dose Commitment
  • Whole Body (Child Thyroid)

Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles 5 miles r 10 miles

~

  • Projected Integrated Dose in Rom *  ;,

D stance Whole Body Child Thyroid t Site boundary ,

2 miles '

5 miles -

10 miles ,

6. Field measurement of dose rate or contamination (if available): N/A
7. Emergency actions underway at the facility include: N/A y f
8. Onsite support needed from offsite organizations: NONE L r

F

9. Plant status:

(a) Reactor is: not tripped / tripped (b) Plant is at: 100 % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: stable / imp re,vi n g/ deg radi n g/u n k nown

RP/0/A/5000/02 Enclosure 4.3 -

Page 4 of 4

10. I repeat, this message:

X (a) Reports an actual emergency. Approved for Release (b) is an exercise message.

Emerg. Coord. Time

11. Do you have any questions?
      • END OF FOLLOW-UP MESS AGE ***

NOTE: Record the name, title, date, time, and warning point notified. (Senders)

Record tha name, title, date, time, and persons notified per alert procedure. (Receivers) 1.

(name) ,

(title)

(date) (time) (warning point) 2.

(name) (title)

(date) (time) (warning point) c

3. -

(name) (title)  ;

(date) (time) (warning point) .

4.

(name) (title) [

(date) (time) (warning point)

5. ,

(name) (title)

(date) (time) (warning point) 6.

(name) (title)

(date) (time) (warning point)

- 7.

(name) (title) 1 Idate) (time) (warning point) l

Form 34731 (10-81)

(Formerly SPD 10021)

DUKE POWER COMPANY (1) ID No:RP/0/A/5000/03 PROCEDURE PREPARATION Change (s) 3 to PROCESS RECORD a Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: ALERT (4) PREPARED BY: TVI'M 6 DATE: 2-15-85 (5) REVIEWED BY: DATE: 2-/6~-85 Cross-Disciplinary Review By:

g a . /. b ,1- __ 2,)/ 7//f N/R:

(6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: _

, Date:

(7) APPROVED BY: id Date: 1 //

(8) MISCELLANEOUS:

Reviewed / Approved By: Date:

Reviewed / Approved By: Date:

i RP/0/A/5000/03 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ALERT 1.0 SYMPTOMS 1.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.

2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to indivitaais and org:anizations.

2.1.1 Complete Enclosure 4.2 and Part I of Warning Message Form (see examp!a Enclosure 4.3). Record receiver's name and time (initial contact).

NOTE: Emergency Coordinator shall initial forms when message is approved for transmission.

NOTE: Warning Message forms are kept in a Notebook in the Control Room and TSC, ensure that all used forins are returned to the back of the notebook. .

2.1.2 Notifications shall be as the order of Enclosure 4.1 indicates. See RP/0/B/5000/13 for NRC Notification. 1 NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. l l

2.1.3 Advise station personnel to activate TSC and OSC. l 2.1.4 Advise the Nuclear Production Duty Engineer to bring the CMC to standby. .

3.0 SUBSEQUENT ACTIONS 3.1 Accident Assessment:

3.1.1 Dispatch on site monitoring teams with associated 1 communications equipment, see HP/0/B/1009/09.

3.2 Follow up Notifications. -

n 3.2.1 Give Follow-up Messages to offsite agencies listed on 4.1.3 of Enclosure 4.1, use the following schedule:

e Every half hour until the emergency is closed out.

95 i

o o .

j 1

1 1

RP/0/A/5000/03 Page 2 of 2 e if there is any significant change to the situation.

O.C e As agreed upon with the individual agencies.

3.2.2 Use parts 1 r,11 of Warning Message Form as applicable.

Mark all spaces "N/A" when information is "Not Applicable" and mark "Later" when information is not currently available.

3.3 Recommand Protective Action Offsite NOTE Protective Action Recommendations are obtained from: OAC Program " Nuclear-23" or RP/0/A/5000/11, if the OAC is not operational, for Operations Personnel.

1 3.4 If the emergency situation is rapidly degrading then conduct a Site {

Assembly, see RP/0/A/5000/10. i 3.5 Augment shift resources to assess and respond to the emergency

, situation as needed. -

3.6 Assess the emergency condition, then remain in an Alert, f escalate to a more severe class, reduce the Emergency Class or close out the emergency.

3.7 The Compliance Engineer or delegate shall close out the emergency with verbal summary to county and state authorities, notified in 4.1.3 of Enclosure 4.1, followed by written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

l 4.0 ENCLOSURES 4.1 Telephone Notification List 4.2 Emergency Message Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government

l . . .

i l

l l RP/0/A/5000/03 i Encieeure 4.11~

Page 1 of 2 l TELEPHONE l NOTIFICATION LIST 4.1.1 CNS Emergency Personnel .

Initial

1. Operations Duty En - Plant Page P & T Pager A: See Current Operations Work List for Home Phone Number.  ;

I

2. Station Man er - J. W. Hampton -

l Offic Home -

1st Alternate - C. W. Graves 2nd Alternate - J. W. Cox 3rd Alternate - . T. Smith Office Home

[

4th Alternate - B. F. Caldwell e

3. Compliance En inser - C. L. Hartzell Offic
H 1st Alternate - M. E. Bolch

, 2nd Alternate - P. G. LeRoy o

4.1.2 Nuclear Production Du I P& age

    • USE ENCLOSURE 4.2 4

RP/0/A/5000/03 .

Enclosure 4.1 Page 2 of 2 4.1.3 State & County Warning Points (Within 15 minutes) .

1. tate Raleigh ,

, CLOSURE 4.3 ***

l

2. S.C. St lumbia 7:30 a.m. - 5:00 p.m. Weekdays P:

After hours, Weekends & Holidays l A:

      • U SE LOSURE 4.3 ***
3. Mecklenburg County ignal P:

A:

Bac -up: mergency Radio, Code

      • USE ENCLOSURE 4.3 ***
4. York County Back-up: Emergency Radio, Cod
      • USE ENCLOSURE 4.3 ***
5. Gaston County P: 've Signal A:

Back-up: mergency Radio, Cod

      • USE ENCLOSURE 4.3 ***

f 4.1.4 NRC Operations Center, Bethesda Md. (RP/0/B/5000/13)

P: El red phone)

A:

RP/0/A/5000/03 Enclosure 4.2 Page 1 of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION TO NUCLEAR PRODUCTION DUTY ENGINEER EMERGENCY MESSAGE FORMAT

1. This is at Catawba Nuclear Station.

(Name and Title)

2. This is is not a drill. An Unusual Event X Alert Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit *

(Time)

3. Initiating Condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status.)
4. Corrective measures being taken:
5. There have have not not been any injuries to plant personnel.
6. Release of radioactivity: is taking place is not taking place
7. NRC Yes No; State Yes No; Counties Yes No; have been notified.
8. The Crisis Management Team should should not be activated.

Corporate Communications and Company Management should be notified.

9. I can be reached at for follow-up information.

(Telephone Number)

10. Additional Comments:

Name of Person Contacted Date Time i

8 RP/0/A/5000/03 Enclosure 4.3 Page 1 of 4 -

4 EXAMPLE .

WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Instructions:

A. For Sender:

1. Complete Part I for the Initial Warning Message.
2. Complete Parts I t, il for followup messages.

B. For Receiver:

l 1. Record the date, time and your name in the area below.

2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part 1.5)

Time: Date:

Message Received By:

PARTI ,

7 1. This is: Catawba Nuclear Station

2. My name is: John Doe, Shift Supervisor
3. This message (number 1):

X (a) Reports a real emergency.

(b) is an exercise message.

4. My telephone nur.,ber/ extension is:
5. Message authentication: USE MESSAGE AUTHENTICATION LIST (Verify code word or call back to f acility)
6. The class of the emergency is: (a) Notification of Unusual Event

< X (b) Alert (c) Site Emergency (d) General Emergency

7. This classification of emergency was declared at: (a.m./p.m. ) on (date).
8. The initiating event causing the emergency classification is: Fire potentially affecting safety system
9. The emergency condition: X (a) Does not involve the release of radioactive materials from the plant.

(b) Involves the potential for a release, but no release is occurring.

(c) Involves a release of radioactive material.

t

RP/0/A/5000/03 Enclosure 4.3 Page 2 of 4

10. We recommend the following protective action:

X (a) No protective action is recommended at this time.

(b) People living in zones remain indoors with the doors and windows closed.

(c) People in zones evacuate their homes and businesses.

(d) Pregnant women and children in zones remain indoors with the doors and windows closed.

(e) Pregnant women and children in zones evacuate to the nearest shelter / reception center.

(f) Other recommendations:

11. There will be:

X (a) A followup message (b) ~ No further communications

12. I repeat, this message: APPROVED FOR RELEASE X (a) Reports an actual emergency (Emerg. Coord. Time. )

(b) is an exercise message

13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
      • END OF INITIAL WARNING MESSAGE ***

PART ll

1. The type of actual or projected release is: N/A (a) Airborne (b) Waterborne (c) Surface spill (d) Other ,

The source and description of the release is: N/A 2.

4 l 3. N/A (a) Release began /will begin at a.m./p.m.: time since reactor trip is hours. ,

N/A (b) The estimated duration of the release is hours.

i l

l RP/0/A/5000/03 l Enclosure 4.3 '

Page 3 of 4

4. Dose projection base data:

. Radiological release: N/A curies, or curies /sec.

Windspeed: 5 mph j Wind direction: From 180' Stability class: D ( A, B,C, D,E, F, or G)

Release height: N/A Ft.

Dose conversion factor: N/A R/h r/Ci/m3 (whole body)

N/A R/hr/Ci/m' (Child Thyroid)

Precipitation: 0 Temperature at the site: 72*F

5. Dose projections: N/A
  • Dose Commitment
  • i Whole Body (Child Thyroid) -

Distance Rem / hour Rem / hour of inhalatio'n 6 Site boundary D 2 miles 5 miles 10 miles

  • Projected Integrated Dose in Rem
  • Distance Whole Body Child Thyroid Site boundary 2 miles 1 5 miles l 10 miles
6. Field measurement of dose rate or contamination (if available): N/A

)

a

7. . Emergency actions underway at the facility include: Extinguised the

.1 fire

8. Onsite support needed from offsite organizations: None j:

'I

9. Plant status:

]

.(a) Reactor is: not tripped / tripped 1

\

(b) Plant is at: 100% power / hot shutdown / cold shutdown / cooling down l l

(c) Prognosis is: s table / improving /deg rading/u'n known I l

RP/0/A/5000/03 Enclosure 4.3 Page 4 of 4

10. I repeat, this message: APPROVED FOR RELEASE X (a) Reports an actual emergency.

(Emers. Coord. Time)

(b) is an exercise message.

11. Do you have any questions?
      • END OF FOLLbW-UP MESS AGE **'

NOTE: Record the name, title, date, time, and warning point notified. (Senders)

Record the name, title, date, time, and persons notified per alert procedure. (Receivers) 1.

(name) (title) '

(date) (time) (warning point) 2.

(name) (titte) ,

f:f'

% (date) (time) . (warning point) 3.

(name) (title)

(date) (time) (warning point) 4.

(name) (title)

(date) (time) (warning point) 5.

(name) (title) -

(date) (time) (warning point) 6.

(name) (title)

(date, (time) (warning point)

- s 7.

(name) (titte)

(date) (time) (warning point)

  • - .v.

P .c f Ef$

Form 34731 (10 81)

(Formerly SPD 10021)

DUKE POWER C,0MPANY (1) ID No: RP/0/A/5000/04 PROCEDURE PREPARATION Change (s) 3 to PROCESS RECORD 4 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: SITE AREA EMERGENCY (4) PREPARED BY: M [ DATE: 2-15-85 (5) REVIEWED BY: [ DATE: c7-/f-87 v

. Cross-Disciplinary Review By: ),/, b - .2////X f N/R:

y F I / *

(6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

hg,,;

e ~By: , Date:

(7) APPROVED BY: s'- Date: 7(!86~

(8) MISCELLANEOUS:

Reviewed / Approved By: Date:

Reviewed / Approved By: Date:

I l

1 i

1

._.s RP/0/A/5000/04 DUKE POWER COMPANY CATAWBA NUCLEAR STATION SITE AREA EMERGENCY 1.0 SYMPTOMS 1.1 Events are in process or have occurred which involve an act'ual or likely major failures of plant functions needsd for protection of the public.

2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to individuals and organizations.

2.1.1 Complete Enclosure 4.2 and Part I crf Warning Message Form (see Example Enclosure 4.3). Record receiver's name and  ;

time (initial contact).

NOTE: Emergency Coordinator shall initial forms when message is approved for transmission. -

NOTE: Warning Message forms are kept in a notebook in the Control Room and TSC, ensure that all used forms are returned to the back of the notebook.

2.1.2 Notifications shall be as the order of Enclosure 4.1 indicates. See RP/0/B/5000/13 for NRC Notification.

NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency.

2.1.3 Advise station personnel to activate TSC and OSC. ,'

2.1.4 Advise the Nuclear Production Duty Engineer to 9

- activata the CMC.

2.2 Protective Action Offsite 2.2.1 Recommend to Offsite Agencies that the Alerting Sirens be sounded and that the EBS be activated to inform the public of a potential for later protective actions.

2.3 Protective Action Onsite 2.3.1 Conduct a Site Assembly, see RP/0/A/5000/10.

4

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4. x =;

RP/0/A/5000/04 Page 2 of 3 3.0 SUBSEQUENT ACTIONS 3.1 Accident Assessment:

3.1.1 Dispatch field monitoring teams with associated  :

communications equipment, see HP/0/B/1009/04. -

3.2 Follow up Notifications.

3.2.1 Give follow-up message to offsite agencies listed on 4.1.3 of Enclosure 4.1, use the following schedule:

o Every half hour until the emergency is closed out.

E e if there is any significant change to the situation.

E e As agreed upon with the individual agencies.

3.2.2 Use Parts i T, il of Warning Message Form as applicable.

  • Mark all spaces "N/A" when information is "Not Applicable" and mark "Later" 'when information is not currently available.

3.3 Follow-up Recommend Protective Action Offsite NOTE Protective Action Recommendations are obtained from: OAC Program."Nucleer-23" or RP/0/A/5000/11, if the OAC is not available, for Operations personnel.

3.3.1 The Emergency Coordinator shall make Protective Action Recommendations to the affected county warning points and to both SC and NC state warning points (Emergency Operations Center if established) or the designated state department as per the state's Radiological Emergency Response Plan. See Enclosure 4.4 for aid in protective action decision making.

NOTE This authority shall not be delegated to other elements of the emergancy organization.

r-__

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

t RP/0/A/5000/04 Page 3 of 3 3.3.2 If actual release of radioactive material will result in a projected dose to the population of:

Whole Body Thyroid Recommendation

<1 Rem <5 Rem No Protective Action is Required.

I to <5 Ram 5 to <25 Rem Recommend seeking shelter and wait for further instruction. Consider evacuation particularly for children

& pregnant women. Control access to affected areas.

> 5 Rem > 25 Rom Recommend mandatory evacuation of population in the affected areas.

Control access to affected areas.

NOTE Monitor environmental radiation levels to verify and adjust recommendations as necessary.

3.4 Follow-up Protective Actions On-site. .

3.4.1 Consider evacuation of non-essential station personnel, -

7 see RP/0/A/5000/10.

3.5 Augment shift resources to assess and respond to the emergency situation as needed.

3.6 Assess the emergency condition, then remain in a Site Area Emergency, escalate to a more severe class, reduce the emergency class, or terminate the emergency. ,

3.7 The Recovery Manager at the Crisis Management Center shall close out or recommend reduction of the emergency class, by briefing i

of offsite authorities at the Crisis Management Center or by phone if necessary, followed by written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

4.0 ENCLOSURES 4.1 Telephone Notification List 4.2 Emergency Message Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government 4.4 Protective Action Recommendation Flow Chart 4.5 10 Mile Emergency Planning Zone (EPZ) Map and Wind Direction Determination Worksheet.

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RP/0/A/5000/04 . *~..

Enclosure 4.1 J$l Page 1 of 2 i

~

TELEPHONE NOTIFICATION LIST l

l 4.1.1 CNS Emergency Personnel initial

1. Operations Duty -

lant Page P & T Pager .

]

i A: Sea Current Operations Work List for Home Phone Number. I

2. Station M r - J. W. Hampton Offic Home -

1st Alternate - C. W. Graves e

2nd Alternate - J. W. Cox 3rd Alternate - G. T. Smith mw

! 4th Alternate - B. F. Caldwell

3. Compliance 'neer - C. L. Hartzell Offic Hom 1st Alternate - M. E. Bolch e

2nd Alternate - P. G. LeRoy 4.1.2 Nuclear Production Dut P r, age

      • USE ENCLOSURE .
  • i

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RP/0/A/5000/04 ,

l

- Enclosure 4.1 V Page 2 of 2 21

k

'E

..f' l 4.1.3 State & County Warning Points (Within 15 minutes) N s >

i 1.

h "P { ,

e

      • USE ENCLOSURE 4.3 ***
2. S.C. State Columbia P: 7:30 a.m. - 5i00 p.m. Weekdays A: Afterhours, Week-ends & Holidays
      • USE ENCLOSURE 4.3 ***
3. Mecklenbu Cou ,

P:

A:

Back-up: cy Radio, Code:

      • USE ENCLOSURE 4.3 ***
4. York County P: ' Selective Signal A:

Back-u . ergency Radio, Code:

      • USE ENCLOSURE 4.3 ***
5. Gaston County P: 've Signal A: -

Back-up: mergency Radio, Cod

      • USE ENCLOSU RE 4.3 ***

4.1.4 NRC Operations Center, Bethesda Md. (RP/0/B/5000/13)

P: ENS (red phone)

A:

l

RP/0/ A/5000/ 04 .

Enclosure 4.2 Page 1 of 1

. DUKE POWER COMPANY  !

CATAWBA NUCLEAR STATION TO NUCLEAR PRODUCTION DUTY ENGINEER EMERGENCY MESSAGE FORMAT

1. This is at Catawba Nuclear Station.

(Name and Title)

2. This is is not a drill. An unusual Event Alert I Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit e (Time)
3. Initiating Condition: (Give as close to the emergency plan description as

. possible together with station parameters used to determine emergency ~ status.)

e

4. Corrective measures being taken:
5. There have have not not been any injuries to plant personnel.
6. Release of radioactivity: is taking place is not taking place
7. NRC Yes No; State Yes No; Counties Yes No; have been notified.
8. The Crisis Management Team X should should not be activated.

Corporate Communications and Company Management should be notified.

9. I can be reached at for follow-up information.

(Telephone Number)

10. Additional Comments:

Name of Person Contacted Date Time u

AP/Gr A/3000,04 .

WARN NG MESSAGE: NU

'+ m .

A. For Sender: . . ,

1. Complete Part i for the initial Warning Message.
2. Complete Parts i L ll for followup messages.

B. For Receiver:

1. Record the date, time and your name in the area below.
2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part 1.5)

Time: Date:

Messa,ge Received By:

PART I ,

1. This is: Catawba Nuclear Station
2. My name is: John Doe, Shift Supervisor
3. This message (number 1):

X -

(a) Reports a real emergency.

(b) is an exercise message.

4. My telephone number / extension is:
5. Message authentication: USE MESSAGE AUTHENTICATION 1.lST (Verify code word or call back to facility)
6. The class of the emergency is: (a) Notification of Unusual Event

. (b) Alert X (c) Site Emergency (d) General Emergency This classification of emergency was declared at: (a.m./p.m. ) on 7.

(date) .

8. The initiating event causing the emergency classification is: Transient requiring operation of shutdown system with failure to trip.
9. The emergency condition: X (a) Does not involve the release of radioactive materials from the plant.

(b) Involves the potential for a release, but no release is occurring.

(c) Involves a release of radioactive material.

RP/0, A/5000/04 Enclosure 4.3 Page 2 of 4

10. We recommend the following protective action:

(a) No protective action is recommended at this time.

(b) People living in zones remain indoors with the doors and windows closed.

(c) People in zones evacuate their homes and businesses.

(d) Pregnant women and children in zones remain indoors with the doors and windows closed.

(e) Pregnant women and children in ::ones evacuate to the nearest shelter / reception center.

X (f) Other recommendations: Activate offsite notification system r, EBS to inform public

11. There will be:

X (a) A follow-up message Approved for Release ,.

(b) No 'further communications

12. I repeat, this message: Emerg. Coord. Time (a) Reports an actual emergency (b) is an exercise message
13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
      • END OF INITIAL WARNING MESSAGE ***

PART ll

1. The type of actual or projected release is: N/A (a) Airborne (b) Waterborne (c) Surface spill (d) Other
2. The source and description of the release is: N/A 1
3. N/A (a) Release began /will begin at a.m./p.m.; time since reactor trip is 1/2 hours.

N/A (b) The estimated duration of the release is hours.

i RP/0/ A/5000/04

. Enclosure 4.3 Page 3 of 4

4. Dose projection base data:

Radiological release: N/A curies, or curies /sec.

Windspeed: 5 mph Wind direction: From 180' Stability class: D ( A, B,C,D,E,F, or G)

Release height: N/A Ft.

Dose conversion factor: N/A R/hr/Ci/m' (whole body)

N/A R/hr/Ci/m8 (Child Thyroid)

Precipitation: 0 Temperature at the site: 72*F

5. Dose projections: N/A
  • Dose Commitment
  • Whole Body (Child Thyroid)

Distance Rem / hour Rem / hour of inhalatioh Site boundary

(': 2 miles n 5 miles 10 miles

  • Proiscted Integrated Dose in Rem
  • Distance Whole Body Child Thyroid Site boundary 2 miles 5 miles 10 miles
6. Field naasurement of dose rate or contamination (if available): Later
7. Emergency actions underway at the facility include: Replacing breaker
8. Onsite support needed from offsite organizations: None
9. Plant status:

(a) Reactor is: not tripped / tripped t'

(b) Plant is at: 0 % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is:. sta ble/ imp rov i n g/deg radi n g/u n k nown l

I RP/0/A/5000/04 Enclosure 4.3 Page 4 of 4

10. I repeat, this message:

Approved for Release X (a) Reports an actual emergency.

(b) is an exercise message. Emers. Coord. Time

11. Do you have any questions?
      • END OF FOLLOW-UP MESSAGE ***

NOTE: Record the name, title, date, time, and warning point notified. (Senders)

Record the name, title, date, time, and persons notified per alert procedure. (Receivers) 1.

(name) (title)

(date) (time) (warning point) 2.

(name) (title) ,

(date) (time) (warning point) 3.

, (name) (title)

(date) (time) (warning point) 4.

(name) (title)

(date) (time) (warning point) 5.

(name) (title)

(date) (time) (warning point) 6.

(name) (title) l (date) - ( time) (warning point) 7.

(name) (title) i (date) (time) (warning point) l i 1

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8 9 t

ENCLOSURE 4.4 RP/0/A/5000/04

( PROTECTIVE ACTION RECOhtdENDATION I SITE AREA DERGEiCY FLOW CMART Page 1 of 1 le to emergemey elseeNied "L9eutuAL gv m.-e No ressenendations reevered Eygs?" er ALERT"? -

Me Recommend that people en the j .

10 male EPZ be modo swore of

-=- A the estustion.

Y I le to amargeney eteessfied

  • SITE e 2. Conduct e Site Assentply.

AREA EREAGENCY*7 3. Consider e Precaut. Evac. of a non-eneential station pereennel.

re- --

m a E JAL "S- Y" I Mas phh control sf 5,e plant been leetf

,y,g, me n--

"2 m. R. T Precest. Eves)

<> i

1. launediately reeennend that pesole in the 2 mi. R. and 5 m. DW seek shelter inoeors
2. Evesuete non eesential station pereennel. 3. Fellow up with a . _ .detson l bened on en estensive evolustaen of the two erese listed below:

ip '

ip le Field Monitoring Team l Core tenit Analveie

  • De*te Aveelablef. 1. , Eveivate.: e Meestee Gore,, ,

, b. NC System "g c. Centeenment Integrity

/ Campere protested DW doses and AR V' 2. Campere witu the following field measurements with EPA PAG *e _ .eetiens where significeet (see 3.3.2). -

]

'r - retenees from conteenment are Comoero the reessenendetiene eeweioped not yet takmg piese:

from these snelvee and deterunne the meet operepriets. I,f, dose protestmens or field _

massieremente are not eveelable. determee I. Are large amounts of Fiessen esteene beoed setely en aere meet onetyees.

Prodwate in Centeinsnont? (* GAP)

L e.

Ree where

n. e it for t,,es. o eveneetten eennet be esgm.
, w . ,t a-5 mi. DW*

before plume arrival. f ,, '

18. le conteensnont facture issunenent? l

' QR " : - _ : - u ' _ ;t

& 05.

Presset. eveev.

I to 5 mi. R. and assankataan:

amanen - -- se es samme ene sena*3aesana 10 mi. OW.

asummen namens as immesnammaa en een so. m amusussias samas esammee se o ame amamos assessee. Dessee unname e tsana - --- . -e- eness . - _ - -

L. se est enemises she gehnas tf summasaan sammet to engaaeed befose estemment p&ama esTges&. (Casase enemmasses tame ameaanse ensame emeammand passmo esTlema tame.)

3.
  • se . ed asume amuseos ese plana.

i t 3. se totase and soms amasseamme possums an ' to ad

6. vtu .amese --a maae ==minanant R Redews 'l S. Can sense eszisy asummans agenet ens - samt ,
s. Laseas a"redf"ee te&ammal F. See may asemaneams. summmmmme amateureme fee tem pugnamanam na che 94mme w se met esammmune.
s. pUuWe&f schemens em punhemmamm effeness D9 est enemma

^ - SeMautse ph Dammags.

M / VI Al JuWVs we CATNw'BA NUCLEAR STATION nelosure 4.5

  • Page 1 of 2 10 MILE EMERGENCY PLANNING ZONE (EPZ) MAP [

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M Eene Nunner  !

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Dage 2 of 2 DUKE POWER COMPANY CATAWBA NUCLEAR STATION RP/0/A/5000/04 ENCLOSURE 4.5 WIND DIRECTION DETERMINATION WORK SHEET Based on wind direction (WD), cetermine the affected zones from sne tables celow. Circle tne wind direction and affectec zones.

NOTE: Upper tower winc direction is preferred. If not available, use lower WO, then use WO from National Weatner Service.

A. IF WINO SPEED IS < 5 MDH, THE AFFECTED ZONES ARE A-0, A-1, 6-1, C-1, 0-1, E-1 and F-1.

B. IF WINO SPEED IS > 5 MPH, SELECT THE AFFECTED ZONES FRCM THE TABLES BELOW AS APPLICABLE.

Taele 2.1 .

Table 2.2 0-5 Mile Radius Affected 5-10 Mile Radius Affected Wind Direction Zones Wind Direction Zones 0.1' - 360'  ; A-0 E .

0.1* - 22' C-1, 0-1 0.1 - 27' t C-2, 0-2 * .

n 22' - 73* O C-1, 0-1. E-1 27' - 69' ----9'C-2, 0-2, E-2 b.~ 73* - 108*----g>C-1, 0-1 E-1, F-1 69' - 95* :10-2. E-2, F-2 108' - 120'  :- 0-1, E-1. F-1 95* - 132* ---e=0-2 E-2, F-2, F-3 120' - 159' -E-1, F-1 132' - 144'  ;-E-2, F-2, F-3 159' - 207' 01E-1 F-1, A-1 144' - 160* ---9*E-2, F-2, F-3, A-2 207' - 247' t-F-1, A-1, B-1 160' - 201*  ;:-F-2, F-3, A-2 247' - 2658 A-1, B-1 201' - 229'---9=F-2, F-3, A-2, B-2 265' - 298* 5:A-1, B-1, C-1 229' - 249'  ;;F-3, A-2, B-2 298* - 338'  ::B-1, C-1 249' - 259'  ;; A-2 A-3, B-2 338* - 360' 1 B-1, C-1, 0-1 259' - 2908---an A-2, B-2, C-2, A-3 290* - 304'  ;; A-3, B-2, C-2 304' - 333"  ;;B-2, C-2 333' - 360'  ::B-2, C-2, 0-2

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Form 34731 (10 81)

(Formerly SPD 10021)

DUKE POWER COMPANY (1) ID No: RP/0/A/5000/05 PROCEDURE PREPARATION Change (s) 3 to PROCESS RECORD 4 Incorporated (2) STATION: CATAWBA ,

(3) PROCEDURE TITLE: GENERAL EMERGENCY (4) PREPARED BY: kl'b bed.d_, DATE: 2-15-85 (5) REVIEWED BY: ) DATE: 2-/f-85~

-Cross-Disciplinary Review By: S g. k _ _ M/ar/p/ N/R:

a v < i (6) TEMPORARY APPROVAL (IF NECESSARY):

,. By: (SRO) Date:

[%'-E/ 4, By: , Date:

(7) APPROVED BY: l^/- / Date: 2!/s!f (8) MISCELLANEOUS:

Reviewed / Approved By: Date:

Reviewed /Appr'oved By: Date:

6

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RP/0/A/5000/05 DUKE POWER COMPANY CATAWBA NUCLEAR STATION GENERAL EMERGENCY 1.0 SYMPTOMS 1.1 Events are in process or have occurred which involve an actual or imminent substantial core degradation or melting with potential for loss of containment integrity.

2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to individuals and organizations.

2.1.1 Complete Enclosure 4.2 and Part I of Warning Message Form (see example Enclosure 4.3). Record receiver's name and time (initial contact).

NOTE: Emergency Coordinator shall initial forms when message is approved for transmission.

NOTE: Warning Message forms are kept in a notebook in the Control Room and TSC, ensure that all used forms; are returned to the back of the notebook.

[? '/ 2.1.2 Notificat. ions shall be as the order of Enclosure 4.1 e

indicates. See RP/0/B/5000/13 for NRC Notification.

NOTE: The State and County notification must be made within 15 minutes of decbration of the emergency.

2.1.3 Advise station personnel to activate TSC and OSC.

2.1.4 Advise the Nuclear Production Duty Engineer to activate the CMC. -

2.2 Protective Actions Offsite 2.2.1 Recommend to Offsite Agencies that all residents of the 2 mile radius zone (A-0) and any zone 5 miles downwind of the plant seek immediate shelter and await futher instructions.

2.3 Protective Action Onsite 2.3.1 Conduct a Site Assembly, see RP/0/A/5000/10.

2.3.2 Evacuate non-essential personnel to the Evacuation Relocation Centers, see RP/0/A/5000/10.

I

RP/0/A/5000/05 Page 2 of 3 3.0 SUBSEQUENT ACTIONS 3.1 Accident Assessment:

3.1.1 Dispatch field monitoring teams with associated communications equipment, see HP/0/B/1009/04.

3.2 Follow up Notifications.

3.2.1 Give follow-up messages to offsite agencies listed on 4.1.3 of Enclosure 4.1, use the following schedule:

e Every half hour until the emergency is closed out.

Of e if there is any significant change to the situation.

E .

e As agreed upon with the individual agencies.

3.2.2 Use Parts I r, ll of Warning Message Form as applicable. .

Mark all spaces "N/A" when information is "Not Applicable

and mark "Later' when information is not currently available.

3.3 Follow-up Recommend Protective Action Offsite NOTE Protective Action Recommendation are obtained from: OAC Program " Nuclear-23" or RP/0/A/5000/11, if the OAC is not operational, for Operations personnel. '

3.3.1 The Emergency Coordinator shall make Protective Action Recommendations to the affected county warning points and to both SC and NC state warning points (Emergency Operations Center if established) or the designated '

state department as per the state's Radiological Emergency Response Plan. See Encloture 4.4 for aid in protective action decision making.

NOTE This authority shall not be delegated to other elements of the emergency organization.

s.

O'T M .. d *f %ae,.eMa -

1 RP/0/A/5000/05 l

. Page 3 of 3 l l

3.3.2 If actual release of radioactive material will result in a projected dose to the population of:

i Whole Body Thyroid Recommendation  !

<1 Rem <5 Ram No Protective Action is Required. ,

1 to <$ Rem 5 to <25 Rem Recomniend seeking shelter and wait for further instruction. Consider evacustion- particularly for children

& pregnant women. Control access to affected areas.

>5 Rom >25 Rem Recommend mandatory evacuation of population in the affected areas.

Control access to affected areas.

NOTE Monitor environmental radiation levels to verify and adjust recommendations as necessary.

3.4 Augment on shift resources to assess and respond to the emergency situation as needed.

3.5 Assess the emergency condition, then remain in an General Emergency, reduce the emergency class or close out the emergency.

3.6 The Recovery Manager at the Crisis Management Center shall close out the emergency or recommend reductien,of the emergency class by briefing the offsite authorities at the Crisis Management Center or by phone if necessary, followed by written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

4.0 ENCLOSURES 4.1 Telephone Notification List 4.2 Emergency Message Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government  ;

4.4 Protective Action Recommendation Flow Chart 4.5 10 Mile Emergency Planning Zone (EPZ) Map and Wind Direction Determination Worksheet

1 RP/tVA/5000/tB -

l Easleeure 4.1 i Pope 1 of 2 l TELEPHONE NOTIFICATION LIST 4.1.1 CNS Emergency Personnel Initial

1. Operations Duty E inser - Plant Page P s T Pager .

A: See Current Opera k List for Home Phone Number.

2. Station Mana r - J. W. Hampton Offi Home - _

1st Altern - C. W. Graves Offic Home _.

2nd Alternate - J. W. Cox ,

l e -

l I i 3rd Alternate - G. T. Smith 4th Alternate - B. F. Caldwell e -

3. Compliance r - C. L. Hartzell l Offic Home _

1st Altern te - M. E. Bolch Offic Home ,

2nd Alternate - P. G. LeRoy a

4.1.2

    • USE ENCLOSURE 4.2 **

l RP/0/A/5000/05 Enclosure 4.1 Page 2 of 2 4.1.3 State & County Warning Points (Within 15 minutes)

1. gh
      • USE ENCLOSURE 8.3 ***
2. S.C. State, Columbia P: 7:30 a.m. - 5:00 p.m. Weekdays A: After hours, Weekends & Holidays
      • U S E NCLOSURE 4.3 ***
3. Mecklenburg County P: igna Back-up: Emergency Radio, Code
      • USE ENCLOSURE 4.3 ***
4. York County P: Selective Signa A:

Back-up. mergency Radio, Code

      • USE ENCLOSURE 4.3 ***

e

5. Gaston County -

P: S ~ e Signal i A:

Back-up: mergency Radio, Cod

      • USE ENCLOSURE 4.3 ***

4.1.4 NRC Operations Center, Bethesda Md. (RP/0/B/5000/13)

P: e (red phone)

A:

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RP/0/A/5000/05  ;

Enclosure 4.2 '

Page 1 of 1 l 1

DUKE POWER COMPANY '

CATAWBA NUCLEAR STATION TO NUCLEAR PRODUCTION DUTY ENGINEER EMERGENCY MESSAGE FORMAT

1. This is at Catawba Nuclear Station.

(Name and Title)

)

2. This is is not a drill. An Unusual Event j Alert i Site Area Emergency i X General Emergency I was declared by the Emergency Coordinator at on Unit * .

(Time) i

3. Initiating Condition: (Give as close to the emergency plan description as $

possible together with station parameters used to determine emergency status.) '

9 b

n f

Il

4. Corrective measures being taken: h S

i t

(

5. There have have not not been any injuries to plant personnel. [y
6. Release of radioactivity: is taking place '

is not taking place  !

7. NRC -Yes No; State Yes No; [I Counties Yes No; have been notified. y
8. The Crisis Management Team should should not be activated.

Corporate Communications and Company Management should be notified. I i

9. I can be reached at for follow-up information. i.

(Telephone Number)

[

10. Additional Comments: i Name of Person Contacted Date Time

e .

RP /0. A. 5000,05 Enclosure 4.3

[ Page 1 of 4 EXAMPLE WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Instructions:

A. For Sender:

1. Complete Part I for the initial Warning Message.
2. Complete Parts I L ll for followup messages.

B. For Receiver:

1. Record the date, time and your name in the area below.
2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part 1.5)

Time: Date:

Message Received By:

PART I .

1. This is: Catawba Nuclear Station
2. My name is: John Doe, Shift Supervisor
3. This message (number 1):

I X (a) Reports a real emergency.

l (b) is an exercise message.

4. My telephone number / extension is:

t

5. Message authentication: USE MESSAGE AUTHENTICATION LIST (Verify code word or call back to facility)
6. The class of the emergency is: (a) Notification of, Unusual Event (b) Alert (c) Site Emergency X (d) General Emergency
7. This classification of emergency was declared at: (a.m./p.m.) on (date).
8. The initiating event causing the emergency classification is: Large loss of coolant accident with failure of Emergency Core Cooling System
9. The emergency condition: X (a) Does not involve the release of radioactive materials from the plant.

(b) involves the potential for a release, but no release is occurring.

(c) Involves a release of radioactive material.

I RP/0/ A/5000/05 Enclosure 4.3 Page 2 of 4

10. We recommend the following protective action:

(a) No protective action is recommended at this time.

X (b) People living in zone, A-O

  • X (5 mi. DW) remain indoors with the doors and windows closed.

(c) People in zones evacuate their homes and businesses.

(d) Pregnant women and children in zones remain indoors with the doors and windows closed.

(e) Pregnant women and children in zones evacuate to the nearest shelter / reception center.

(f) Other recommendations:

11. There will be:

X (a) A followup message ,

(b) No further communications

12. I repeat, this message: APPROVED FOR RELEASE X (a) Reports an actual emergency (Emers. Coord. Time.)

(b) is an exercise message

13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT l PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY. "
      • END OF INITIAL WARNING MESSAGE ***

PART ll

1. The type of actual or projected release is: N/A (a) Airborne (b) Waterborne (c) Surface spill (d) Other

, 2. The source and description of the release is: N/A I

3. N/A (a) Release began /will begin at a.m./p.m. ; time since reactor trip is 1/2 hours.

_ N/A (b) The estimated duration of the rele'ase is hours.

RP/0/ A/5000/05 Enclosure 4.3 Page 3 of 4

4. Dose projection base data:

Radiclogical release: N/A curies, or cu ries /sec.

Windspeed: 5 mph -

Wind direction: From 180' Stability class: D ( A, B,C D,E, F, or G)

Release height: N/A Ft.

Dose conversion factor: N/A R/hr/Ci/m* (whole body)

N/A R/hr/Ci/m3 (Child Thyroid)

Precipitation: 0 Temperature at the site: 72*F

5. Dose projections: N/A
  • Dose Commitment
  • Whole Body (Child Thyroid) ,

Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles 5 miles 10 miles

  • Projected Integrated Dose in Rem
  • Distance Whole Body Child Thyroid Site boundary 2 miles 5 miles 10 miles
6. Field measurement of dose rate or contamination (if available): Later
7. Emergency actions underway at the facility include: Cooling down primary system to depressurize
8. Onsite support needed from offsite organizations: None i
9. Plant status:

(a) Reactor is: not tripped / tripped (b) Plant is at: 0 *6 power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: s ta b l e/imo rovi n g/deg radi n g/u n k now n l

l

RP/0/ At 5000/05 Enclosure 4.3 Page 4 of 4

10. I repeat, this message:

x (a) Reports an actual emergency.

(b) is an exercise message. APPROVED FOR RELEASE

11. Do you have any questions?

(Emerg. Coord. Time)

      • END OF FOLLOW-UP MESS AGE ***

NOTE: Record the name, title, date, time, and warning point notified. (Senders)

Record the name, title, date, time, and persons notified per a:ert procedure. (Receivers) 1.

(name) (title)

(date) (tit.ie) (warning point)

2. -

(name) (title)

(date) (time) (warning point) 3.

(name) (title)

(date) (time) (warning point) 4.

(name) (title)

(date) (time) (warning point) 5.

(name) (title)

'l i

(date) (time) (warning point)

6. ')

(name) (title)

-l (date) (time) (warning point)

7. <

( (name) (title) )

I (date) (time) (warning point)

E '

ENCLOSURE 4.4 RP/0/A/5000/05 PROTICTIVE ACTION RECOMMENDATION Ggyg3AI,ggggggycy

! FLOW CNAAT p,g, g 4

1 le #be Y 4 reeenumendations reeusrod

! EvtNT*9 er ALERT eteese6ed *7 "UNWSUAL Rese==nend enet sessie in in.

i j -

10 mi6e EPZ be made owere of

ur A the satuetsen.

le Wie emergoney sleessfled " SITE Y e 2. Conduct a lite Assameely.

! AREA EbERGENCY"? 3. Consider a Preceut. Evac. of i non essentsee statsen personnel.

I e - - C_^__ _ se e -E_ :--AL EBE" 5 CY" I I Mas petyeesel sentret v - ' 2 ens. R.

af Ste plant been loot? m-- Precaut. Evac i

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! 3. Inunediately rosessmond that pesole en the 2 me. R. and S me. DW seest shelter indeers

2. Evesuete non essential station peesennel. 3. Fe46ew-up with a . ___ c.detion i} beoed on en estensive evolueteen of the two erees listed beoew:

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i is Field Monitoring Team l Core Meet Anaivene j

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Dete Aveliablef. f. Eveivate:, s. Beestee Gero ., ,, .

g Yee b. NC System *

c. Centeinment integrity

! Campere protested OW deses and AN,$g field measurements with EPA PAG's 2. Comoere with the felleanne (see 3.3.21. recenenencations where significant o a ro6eeses from senteenment are Campero the resenumenesteens deve6esed not yet taking plese:

from these snelyse and determine the meet l

espegeriets. jf dose protections er field _

l meseuremente are not eveelable. deterseine Are large amounts of Fiessen eatsene beoed seeely en more me6t onetyees. l-Prodveto in Centainment? (> GAP) v u.

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11. Is senteenment feature munenent? I QA Rolessa 'ir Gewsw? _

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  • CATAWBA NUCLEAR STATION Enclosure !. 5 10-MILE EMERGENCY PLANNING ZONE Page 1 of 2 (EPZ) MAP

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a;e 2 of 2 CUKE POWER COMFANY CATAWBA NUCLEAR STATION RP/0/A/5000/05 ENCLOSURE 4.5 WIND DIRECTION DETERMINATION WORK SHEET Based colow. on wind directicn (WD), cetermine tne affectec :nes from :ne tacies Circle ne winc direction and affectec ::nes.

NOTE:

Upcer tower winc direction is = refer ec. If no:

lower WD, then use WO fecm National Weatner Service.available, use A.

C-1, 0-1 E-1 and F-1.IF WIND SPEED IS < 5 WDH, THE AFFECTED ZO B.

BELOW AS APPLICABLE.IF WIND SPEED IS > 5 MPH. S Taele 2.1 0-5 Mile Radius Affectec Taele 2.2 Wind Direction Zones 5-10 Mile Radius Affected 0.l' - 360*  ; A-0 Wind Direction Zones M

0.1* - 22'  ? C-1, 0-1 22' - 73* 0.1 - 27' t C-2, 0-2 * .

A C-1, 0-1, E-1 27' 69' W C-2, 0-2, E-2 73' - 108*---->C-1, 0-1, E-1, F-1 698 -

95* 20-2, E-2, F-2 108' - 120'-- 5 0-1 E 1. F-1 120' - 159' O E-1, F-1 95* - 132* -->0-2. E-2, F-2, F-3 132* - 144 A E-2, F-2, F-3 159' - 207' A E-1 F-1 A-1 207' - 247* t F-1, A-1, B-1 144* - 160* *E-2, F-2, F-3, A-2 247' - 2658 160' - 201'-  ? F-2, F-3, A-2

A-1, B-1 2658 - 29B' L A-1, B-1, C-1 201' - 2298-->F-2 F-3, A-2, B-2 '

298' - 33B' 2298 - 249' L F-3, A-2, B-2 L B-1, C-1 338' - 360' 249' - 259' R A-2, A-3, B-2 1 B-1. C-1, 0-1  ;

259' - 290 ---> A-2, B-2, C-2, A-3 290* - 304' e A-3, B-2, C-2 304* - 333* L B-2, C-2 1 333' - 360'- >B-2, C-2, 0-2 u l

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l Form 34731 (1041)

(Formerly SPD-10021)

DUKE POWER COMPANY (1) ID No: RP/0/B/5000/13 PROCEDURE PREPARATION Change (s) 2 to PROCESS RECORD 3 Incorporated

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(2) STATION:

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(3) PROCEDURE TITLE:

(4) PREPARED BY: k' DATE: 2-4-85 (5) REVIEWED BY: DATE: 4 ~ 44I

' "ross-Disciplinary Review By y

O./.OCa - 2./F/E7 i

N/R:

v (6) TEMPORARY APPROVAL (IF NECESSARY):

(Iu; By: (SRO) Date:

By: , 1 Date:

(7) APPROVE 9 BY: 'M' Date: 1 8I

( ' /

(8) MISCELLANEOUS: l}

Reviewed / Approved By: Date:

Reviewed / Approved By: Date:

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t RP/0/8/5000/13 DUKE POWER COMPANY CATAWBA NUCLEAR STATION NRC NOTIFICATION REQUIREMENTS 1.0 SYMPTOMS

~

1.1 Plant conditions requiring NRC notification in accordance with:

10 CFR50.72,10 CFR20.205,10 CFR20.403,, and 10 CFR73.71.

1.1.1 Immediate, I Hour and 4 Hour Notifications.

1.1.2 24 Hour Notifications for Operating License Condition Deviations.

1.2 See Enclosure 4.1 for determination of appropriate notification requirement.

2.0 IMMEDI ATE ACTIONS 2.1 Complete one of the following enclosures:

2.1.1 Enclosure 4.2 " Checklist for Significant Event Notification" oC 2.1.2 Enclosure 4.3 " Report of Serious Physical Security Events" When reporting from Section 4.1.2.7 of Enclosure 4.1 2.2 Notify the NRC Operations Center by the following means:

2.2.1 Pri. - Emergency Notification System Phone 2.2.2 t 2.3 Notify the NRC Region 11 Office at 404-221-4503 of any event listed in Section 4.1.1.5 of Enclosure 4.1.

NOTE: No Enclosure for reporting to Region 11 from Section 4.1.1.5 of Enclosure 4.1 3.0 SUBSEOUENT ACTIONS 3.1 Provide follow-up notification as described below:

3.1.1 Emergency Classes 3.1.1.1 Any further degradation in level of safety of the plant including those that require declaration of any Emergency Class, if such a declaration has not been previously made.

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RP/0/ S/5000/13 c,., Pope 2 W 2 -

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3.1.1.2 Any change in the Emergency Cless - $ 'M

s. ;6 3.1.1.3 Termination of the Emergency - t (:;f.

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3.1.2 Results of ensuing evaluations or assessments of plant conditions 3.1.3 Effectiveness of response or protective measures taken 3.1.4 Information related to plant behavior that is not understood 3.2 Maintain an "Open", continuous, communications channel with the NRC Operations Center, upon request by the NRC.

3.3 Notify the following individual:

3.3.1 Compliance Engineer P rima ry Alternate

  • C. L. Hartzell Duty Compliance Office: or

~

Engineer Home: (See current Station

, , Duty List) 3.3.2 If neither the Compliance Engineer nor the Duty Compliance Engineer can be reached then call directly to the:

NRC Resident inspector P rima ry Alternate e e l 3.4 Upon completion of this procedure, attach a completed Procedure .

! Process Record Form and forward to the Compliance Engineer for review prior to submission to Master File.

4.0 ENCLOSURES 4.1 Events Requiring NRC Notification 4.2 Checklist for Serious Event Notification 4.3 Report of Serious Physical Security Events l

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1 RP/0/B/5000/13 i- Events Requiring NRC Notification Enclosure 4.1

.- Page 1 of 6 1

4.1.1 Events R3 quiring "lMMEDI ATE NOTIFICATIONS":

Immediately after notification to states and counties and not'later than one hour after the time the Emergency Class l was declared.

4.1.1.1 The declaration of any of the Emergency Classes specified in the Catawba Emergency Plan 4.1.1.2 - Any change from one Emergency Class to another

  • 4.1.1.3 TermMation of the Emergency

] 4.1.1.4 For any incident involving byproduct, source or i special nuclear material which may have caused or threatens to cause the following:

4.1.1.4.1 Individual Exposure

) 125 Rom Whole Body

} or

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3150 Rem Skin of Whole Body-

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f. ,j O.C f 3 375 Rom Extremities 4.1.1.4.2 Release of radioactive material in 1

concentration which if averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period would exceed 5,000 times i the applicable concentration of the l . limits specified in 10 CFR 20, l Appendix B, Table ll.

4.1.1.4.3 Loss of one working week or more of the operation of any unit.

1 4.1.1.4.4 Damage to property in excess of $200,000.

4.1.1.5 Notification to NRC Reginal Office, Region 11, 4 Atlanta, G A. (see Step 2.3). Receipt of a package j of radioactive materials with:

4.1.1.5.1 >0.01 uCi/100cm2 loose radioactive inatorial on the external surface 1

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

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RP/0/ B/5000/13 Events Requiring NRC Notification Enclosures 4.1

Page 2 of 6

, 4.1.1.5.2 >200 MR/hr. on external surface or 4.1.1.5.3 >10 MR/hr at three (3) feet from the 1 external surface 4.1.2 - Events Requiring "ONE HOUR REPORTS":

As soon as practical and within one hour of the s

occurrence.

4.1.2.1 The initiation of any nuclear plant shutdown required by Technical Specifications (i.e.

Safety Limit Violation). See notes:

NOTE: 1. The initiation of a Shutd-wn is defined as, A reduction in PoweF7equired by an action statement of Tech. Specs, of any unplanned trip (automatic or manual) to t

Mode 3."

i 2. Shutdown is defined (for reporting requirements) as, " Mode 3 and below".

i 4.1.2.2 Any deviation from a plant License Condition or '

Technical Specification authorized in 10CFR50.54(x) .

(Licensee may take reasonable action that departs from a license condition or a technical specification in an emergency when this action is i immediately needed to protect the health and safety of the public and no action consistent 4

j with license conditions and technical specifications that can provide adequate or l

equivalent protection is immediately apparent.)

i 4.1.2.3 Any event or condition during operation that results in the condition of the plant, including the principle safety barriers, being seriously degraded, or results in the plant being:

, 4.1.2.3.1 in an unanalyzed condition that significantly compromises plant safety.

. 4.1.2.3.2 In a condition that is outside the

, design basis of the plant.

4.1.2.3.3 In a condition not covered by the plant's operating and emergency procedures.

4.1.2.4 Any event that results or should have resulted j in Emergency Core Cooling System (ECCS) i discharge into the reactor coolant system as a l' result of a valid signal.

\ _

t n RP/0/B/5000/13 Events Requiring NRC Notification Enclosure 4.1

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Page 3 of 6 4.1.2.5 Any event that results in a major loss of i emergency assessment capability, offsite response capability, or communications capability (e.g., i significant portion of control room indication, Emergency Notification System or Offsite Notification System).

4.1.2.6 Any natural phenomenon or other external l condition or any event that poses an actual 4

threat to the safety of the plant or significantly j hampers site personnel in the performance of

, duties necessary for the safe operation of the

! plant, including fires, toxic gas releases or radioactive releases.

3 4.1.2.7 Safeguard events as determined by Security personnel and Station Management.

4 4.1.2.7.1 A trace investination of a lost or '

unaccounted for shipment pursuant to 10

CFR 73.27. '

4.1.2.7.2 An attempt (actual or suspected) to commit a theft or unlawful diversion of

4.1.2.7.3 Any event which significantly 4

threatens or lessens the effectiveness of '

the physical security system Uncompensated one (1) hour safeguards events j a. Confirmed intrusion or Sabotage i

attempt (explicit threat).

t

b. Attempted entry of unauthorized

. . Incendiary devices into Protected l Area.

c. Bomb Threat / Extortion Threat .

(Explicit Threat, includes entry into vital ares (s)). '

d. Mass Demonstration, Picketing,

' Civil Disturbance (Explicit .

Threat, Event occurs inside the Protected Area).

j e. Loss of both CAS/SAS (Major loss of physical security effectiveness).

f. Loss of Offsite Communications to

) LLEA (Local Law Enforcement Agency). I g.. Loss or Degradation of Power Supply to Security Systems.

4

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RP/0/ B/5000/13 Events Requiring NRC Notification Enclosure 4.1 Page 4, of 6

h. Unavailability of minimum number of Security Force Members.
i. Decreased effectiveness of the Physical Barriers (Vital or Protected Area) creating a major loss of physical security effectiveness.

4.1.3 Events Requiring "FOUR HOUR REPORTS" As soon as practical and within four hours of the occu rrence.

4.1.3.1 Any event found while the reactor (s) is/are shutdown, that had it been found while the reactor (s) was/ wore in operation would have resulted in the plant, including its principle safety barriers, being seriously degraded or being in an unanalyzed condition that signifi-cantly compromises plant safety.

4.1.3.2 Any event or condition that results in manual or automatic activation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS).

(However, activation of an ESF including the RPS, that results from and is part of the preplanned sequence during testing or reactor operation need not be reported).

4.1.3.3 Any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to:

4.1.3.3.1 Shutdown the reactor and maintain it in a safe shutdown condition.

4.1.3.3.2 Remove residual heat.

4.1.3.3.3 Control the release of radioactive

material.

4.1.3.3.4 Mitigate the consequences of an accident.

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1

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RP/0/B/5000/13 Events Recuiring NRC Notification Enclosure 4.1 ,

Page 5 of 6 '

L 4.1.3.4 Any airborne radioactive release that ,'

exceeds 2 times the applicable

  • concentrations of the lirnits specified in 4

10CFR20, Appendix B, Tablg ll in .

unrestricted areas when avelaged over a l time period of one hour.

4.1.3.5 Any liquid effluent release that exceeds 2 times the limiting combined MPC (See '

10CFR20, Appendix B, Note 1.) at the point of entry into the receiving water .

(unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one -

hour. (Immediate Notifications made under this requirement also satisfy the require-  :

ments of 10CFR20.403, Paragraph (a)(2) and (b)(2)). (See 4.1.1.4.2) . .

4.1.3.6 Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment.

4.1.3.7 Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a News Release is planned I t

or (

s Notification to Other Government Agencies I has been or will be made. Such an event "

may include an onsite fatality or

. inadventent release of radioactively contaminated materials.

5 4.1.4 Operating License Conditions Deviations Requiring "24 Hr. Notifications":

  • I 4.1.4.1 Refer to Operating License I l

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RP/0/B/5000/13 Events Requiring NRC Notification Enclosure 4.1 Page 6 of 6 4.1.4 Follow-up Notifications 4.1.4.1 During the course of the event, report:

4.1.4.1.1 Any further degradation in the level of safety of the plant or other worsening plant conditions, including those that require the declaration of any of the Emergency Classes, if such a dolcaration has not been previously made or Any change in the Emergency Class or Termination of the Emergency.

4.1.4.1.2 The results of ensuing evaluations or assessments of plant conditions

  • 4.1.4.1.3 The effectiveness of response or .-

protective measures taken, ,

4.1.4.1.4 Information related to plant '

behavior that is not understood.

1 k

. RP/0/B/5000/13 ENCLOSURE 4.2 PAGE 1 OF 3 CHECKLIST FOR SIGNIFICANT EVENT NOTIFICATION Complete the applicable. portions of this enclosure and transmit to the NRC Operations Center as r6 quired by Enclosure 4.1.

State the following to the NRC Operations Center:

"THIS NOTIFICATION IS MADE IN ACCORDANCE WITH 10CFR50.72. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION IN NRC REGION ll MAKING THE NOTIFICATION."

1. A. My Name is: My title is:

e I can be called-back at B. "Your Name Please"

2. Time of Notification Event Time EDT.

Event Date / /

M TT

3. This Notification is: Check appropriate box (s).
a. -Emergency Plan Declaration -Other immediate Notification O- Notification of Unusual Event O - Alert O- Site Area Emergency O- General Ergergency b.[-A "ONE-HOUR" Notification I
c. -A "FOUR-HOUR" Notification d.}A "24-HOUR" Notification
4. Event description and cause:

l 1

l j

RP/0/ B/5000/13 ENCLOSURE 4.2 PAGE 2 OF 3 4

5. Plant Status:
a. Uni,t affected: 1/2/ Both .
b. Power prior to event:
c. Power at time of report:
d. Unit tripped: yes/no. Initiating Trip Signal:
e. Mode description:
f. ESF Acutation; yes/no.
g. S.fety injection or ECCS: yes/no initiating Signal
h. Primary System Temperature: tHot ,

t Cold

i. NC Flow: yes/no, NC Pump Status: A: on/off, B: on/off, C: on/off, 0: on/off.
j. Heat Sink:
k. Pressurizer Level:
1. Steam Generator Level (s): A B C D
m. Feedwater Status: Main Aux
n. Containment Pressure: Sump Level:
o. Equipment Failures (include Status of Safety Systems):
p. Electrical Power Supplies available:

Normal Offsite: yes/no, -

Busses / Loads Lost:

D/G Running: yes/no, Loaded: yes/no

6. Status of unaffected unit:

~

7. Radioactive Release: yes/no (if yes complete this paragraph)
a. Release: Liquid / Gas -
b. Location / Source:
c. Release Rate:
d. Duration of Release: -
e. Stopped: yes/no

, f. Monitored: yes/no

g. Estimated Amount Released:

RP/0/B/5000/13 I ENCLOSURE 4.2 l Page 3 OF 3 l

h. Affected Plant /Offsite areas affected:
i. Areas Evacuated:
j. Other Actions Taken
8. Other major problems (include anything unusual or not understood):
9. Planned actions / Press releases / Emergency Centers activated:
10. Outside Agency / Personnel Notified:

Counties: State (s):

York ves/no N.C. Yes/no Gaston ves/no S.C. yes/no Mecklenburg yes/no NRC Resident: yes/no Corporate Headquarters: ves/no, Others:

4

RP/0/B/5000/13 ENCLOSURE 4.3 PAGE1 OF1 REPORT OF SERIOUS PHYSICAL SECURITY EVENTS i

DATE/ TIME OF NOTIFICATION NRC PERSON NOTIFIEb State the following to the NRC Operations Center:

"THIS NOTIFICATION-IS MADE IN ACCORDANCE WITH 10C FR73. 71. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION IN NRC REGION ll MAKING THE NOTIFICATION".

My Name is: My title is:

I can be reached at .

"Your Name Please" .

1. *DATE OF OCCURRENCE: 3.* POWER LEVEL OF UNITS:
2.
  • TIME OF OCCURRENCE: Unit 1 Unit 2
  • lf date and time of occurrence are not known, indicate the date and time of 4

discovery.

4. DESCRIPTION OF EVENT:
5. SECURITY RESPONSE / COMPENSATORY MEASURES ESTABLISHED:
6. LLEA (Local Law Enforcement Agency) NOTIFIED 7 YES NO (if Yes, name organization and telephone number)
7. VITAL /.REA(S) AFFECTED? YES NO -

Description of Equipment Systems ATTEted

Form 34731 (10 81)

(Formerly SPD.10021) 4 DUKE POWER COMPANY (1) ID No:HP/0/8/1009/04 PROCEDURE PREPARATION , Change (s) O to PROCESS RECORD 0 7 Incorporated 4 2-tv-36 m

(2) STATION: Catawba Nuclear Station (3) PROCEDURE TITLE: Environmental Monitoring For Emergency Conditions.Within The Ten I:lle Radius Of Catasha ?!uclear Station (4) PREPARED BY: J u l.e/ 7 ) 4.4., DATE: 2 -//-/J-(5) REVIEWED BY. M Ma < , M M ' '1 " DATE: M~M- M Cross-Disciplinary Review By: N/R: d "'

(6) TEMPORARY APPROVAL (IF NECESSARY):

  • ..t

'? By: (SRO) Date:

. By: n , Dates (7) APPROVED BY: W Date: 1 17, 8 F ' *

(8) MISCELLANEOUS: ,

y  ?

Reviewed / Approved By: Date:

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Reviewed / Approved By: Date: -

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HP/0/B/1009/04 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ENVIRONMENTAL MONITORING FOR EMERGENCY CONDITIONS WITHIN THE TEN MILE RADIUS OF CATAWBA NUCLEAR STATION 1.0 PURPOSE To provide a method for identifying gaseous plumes or liquid effluent, and obtaining field data indicative of the radiation exposure to the general public following a suspected uncontrolled release of radioactivity.

This procedure shall also be Laplemented by the Crisis Management Center once it is activated.

2.0 REFERENCES

2.1 HP/0/B/1000/06 Emergency Equipment Functional Check and Inventory 2.2 HP/0/B/1002/04 Collection of Operational Environmental Weekly Samples

, 2.3 HP/0/B/1002/05 Collection of Operational Environmental Monthly Samples 2.4 ~

HP/0/B/1002/06 Collection of Operational Environaental Quarterly Samples 2.5 HP/0/B/1002/08 Collection of Operational Environmental Semimonthly Samples 2.6 HP/0/B/1002/10 Collection of Operational Environmental Semiannual Samples 2.7 HP/0/B/1003/05 Operating and Calibration Procedure: Eberline Model PIC-6A Portable Ion Chamber 2.8 HP/0/B/1003/12 Operating and Calibration Procedure: Eberline Model E-520 Portable Beta-Gamma Geiger Counter

2.9 HP/0/B/1003/17 Operation and Calibration Procedure
Canberra Series - 10 Portable MCA i

2.10 HP/0/B/1003/31 Operation and Calibration: Eberline Model E140N Portable Count Rate Meter 2.11 HP/0/B/1009/16 Distribution of Potassium Iodide Tablets in the

, ~ Event of a Radiciodine Release 2.12 HP/0/B/1009/19 Emergency Radio System Operations, Maintenance and Communications

HP/0/B/1009/%

Page 2 of 6 o - . . .

' 4 f1 3.0 LIMITS AND PRECALTTIONS -

3.1 The Field Monitoring Teams (FMT) should park vehicles completely off the road when sampling and use vehicle emergency flashers while stopped.

3.2 Four (4) FNTs consisting of two (2) technicians per team and one (1) helicepter team (1 person) if necessary shall be formed as follows:

Team Call Signs Transportation Alpha I.and Vehicle Bravo Land Vehicle Charlie Land Vehicle i Delta Land Vehicle Echo Helicopter 3.3 Each FMT shall usa particulate masks and protective clothing whenever activity justifier it or when directed by the Field Monitoring Coordinator (FMC).

3.4 If the team members are expected to be exposed to I-131 in excess of 70 MPC (6.1 x 10 pCi/ml), and directed by the FMC, each team

sember should ingest a tablet of potassium iodide per Reference 2.11.

3.5 Environmental sampling during emergency conditions shall not replace, but rather supplement normal environmental monitoring.

l 3.6 Minimum labeling requirements for all samples are as follows:

3.6.1 Date and time. l l

3.6.2 Location.

3.6.3 Volume of the sample (if applicable).

3.6.4 Name of person sampling.

3.7 Each FNr shall maintain open radio communications with the FMC per Reference 2.12. If radio becemes ino rable, call in sample results on a one s Lake Wylie/ Charlotte),

Gaston County) Rock Hill and Fort Mill).

3.8 If any equipment becomes inoperable, notify the FMC and wait for further instructions.

3.9 Annual training in the u:.e of this procedure and the associated equip-m at and instrumentation shall be conducted and documented on TSR-10.

3.10 Portable MCA's shall be picked up at the Health Physics instrument issue point when directed by the FMC. Ensure that the dewars are adequately filled per Reference 2.9.

HP/0/B/2009/04 Page 3 of 6 3.11 When returning kits to the Emergency Kit Storage Room, perform an ,

equipment inventory check using the Environmental Survey Kit Checklist (Reference 2.1). Note deviations and forward to the .

Respiratory / Instrument Calibration Supervisor.

4.0 PROCEDURE 4.1 Activation i

4.1.1 Upon notificaton and assembly (FMC), the FMT members shall:

4.1.1.1 Report to the Health Physics area on the 609' elevation (on back shifts report to Administration Building) and wait for further instructions from the FMC.

4.1.1.2 Report to the Emergency Kit Storage Room in the Temporary Administration Building to get Environmental Survey Kits.

4.1.1.3 Ensure the Portable Power Generator is operational and the gas can is fully fueled (Reference 2.1).

4.1.1.4 Ensure the tamper seal on the Environmental Survey kits have not been broken and inventory any that have (Reference 2.1).

4.1.1.5 Don TLD and pocket dosimetry and fill out dose cards.

4.1.1.6 Battery and source check survey instruments and portable MCA for proper operation (References 2.7, 2.8, 2.9, 2.10) if applicable.

  • 4.1.1.7 Ensure the portable radios are functional before leaving (Reference 2.12).

4.1.1.8 Obtain emergency vehicles as directed in Enclosure 5.9.

4.1.1.9 Each-FMT will proceed to the survey point assigned by the FMC (Enclosure 5.3).

4.1.1.10 The radio operator in the TSC shall complete Radio Operators Log Field Monitoring Data Sheet (Enclosure 5.4), with the appropriate information. .

f 4.2 Locating and Tracking the Plume L 4.2.1 At the assigned survey point, the FMT shall perform a

' general-area Beta vs. Beta-Gamma survey. This method should be used to locate center and width of plume.

HP/0/B/1009/04 Page 4 of 6 i

i 4.2.1.1 Record date, time, location and dose rate l (ar/hr) on the Field Monitoring Data Sheet (Enclosure 5.5).

4.2.2 If survey results are less than or equal to expected background, call in the results to the FMC and wait for further instructions.

' i 4.2.3 If survey results are greater than background, take l protective actions as necessary. Then, if directed, take '

an air sample (volume should be > 10' al) equipped with a Silver Zeolite Cartridge and particulate filter.

4.2.3.1 Insert cartridge with arrow pointing in.

i 4.2.3.2 Insert filter paper with smooth side facing out.

4.2.3.3 Calculate required sample time per Enclosure 5.6. ,

4.2.3.4 Place the generator and air sampler in a safe location (i.e. away form wet areas and off the roadway) ensuring the sampler is approximately two feet above the ground or higher and begin sampling.

Cq 4.2.3.5 When air sample is completed, place the Silver

. 'n- ' Zeolite Cartridge'in a poly bag for analysis.

4.2.3.6 Place filter in a separate poly bag and label.

4.2.3.7 As directed by the FMC, transport the completed sample to a vehicle that is carrying a Canberra Series - 10 Portable MCA for analysis per Reference 2.9.

4.2.3.8 Ensure the correct information is annotated on the Field Monitoring Team Work Sheet.for Determining Iodine Activity (Enclosure 5.7).

4.2.3.9 Wait for further instructions from the FMC.

4.3 Special Sampling, as directed:

4.3.1 All sampling outside of Auxiliary, Service and Turbine '

Buildings should be done in conjunction with Operations Support Center (OSC) personnel. -

4.3.2 Take smears and place them in separate poly bags,_ label  ;

.and retain for later analysis.

, 4.3.3 Count smears on E140N and record on Field Monitoring Data gy Sheet (Enclosure 5.5). Call in results to FMC. ,

Ceea' 4.3.4 Collect water samples in cubitainers using good Health Physics practices and label and retain for later analysis. .

f

. U l a rnv -- -

O O HP/0/B/1009/04 Page 5 of 6  ;

/dl3 h/' 4.3.5 Place TLD's in the environment.

4.3.6 Retrieve and replace air sample and/or TLD's that are already located in the environment. Locations are listed in Enclosure 5.1. Place samples in separate poly bags, label and retain for later analysis.

4.3.7 Collect broad leaf vegetation sample label and retain for later analysis (Reference 2.12).

4.3.7.1 Cut vegetation in a one square meter area approximately two inches above the ground.

NCTE: Vegetation which leaves are not in the shape of needles, i.e. pine or spruce needles.

4.3.8 Collect shoreline sediment sample (one liter) label and retain for later analysis (Reference 2.6).

4.3.9 Collect milk sample (one full cubitainer) label and retain for later analysis (Reference 2.5). Locations are listed in Sample Enclosure 5.2.

4.4 Turnover 4.4.1 Each FMT shall be relieved as directed by the FMC.

$l.*

TOS* 4.4.2 Inform the relief FMT on the status of the following:

4.4.2.1 Radiation surveys and dose rates in the plume area.

4.4.2.2 Kit Inventory consumed.

4.4.2.3 Equipment operating status.

4.4.2.4 Any sampling problems.

4.4.2.5 Plant status information.

4.4.3 Direct the relief FMT to don TLD's and pocket dosimetry and fill out dose cards.

4.4.4 Return all samples to the Emergency Kit Storage Room as directed by the FMC.

4.4.5 Turn in all data sheets to the FMC or his designee.

! 5.0 ENCLOSURES 5.1 Air Samp'ler, TLD, and Water Sample Locations cc. .5.2 Milk Sample Locations.

l De f

,H,* *W({~

, a- em-'

HP/0/B/1009/04 Page 6 of 6 4

5.3 Predetermined Sampling Locations 5.4 Sample of Radio Operators Los Field Monitoring Survey Data 5.5 Sample of Field Monitoring Data Sheet 5.6 Sample Time Required For Minimus Sample Volume 5.7 Sample of Field Monitoring Team Work Sheet For Determining Iodine Activity 5.8 TSC Field Monitoring Organizatien 5.9 Emergency Vehicles S

4

Page 1 of 5 DUKE POWER COMPANY CATAWBA ECLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATIR SAMPLE LOCATIONS Air Sample Locations (need key CPD-1)

Zone & Radius (M1) No. Description A0 1 1 Hwy 274-N, right Liberty Hill Rd., right in fork to end (Air CNS #200, need key).

A0 1 5 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd., left '

on Blue Bird Ln., through gate to end (Air CNS #201, need key).

B1 3 '

1 Hwy 49-N, right Hwy 160, right at Tega Cay sign (98), right before Tega Cay entrance into Duke Power Company substation (Air CNS #212, need key).

C2 10 5 Hwy 274-S, left Hwy 161, right Mt. Gallant Rd.

(195), right Hwy 21-121 By-Pass, right on Hwy 72 - 121 By pass, left on dirt road (Trash Pile Rd.) across from Wayne's Auto Service, go to Duke Power Company substation (Air CNS #217, need key).

A0 1 26 Behind Catawba Nuclear Station overlook (Air CNS #205, need key).

~

TLD Locations I. Site Boundary TLD's o

Zone & Radius (Mi) No. Descriotion  ?

A0 44' 1

Hwy 274-N, right Liberty Hill Rd., right in fork, pass softball field to large rocks at fence on right. TLD is on fence (TLD CNS #222).

A0 1 1 Hwy 274-N, right Liberty Hill Rd., right in fork to end (TLD CNS #200, need key).

I A0 1 5

! Left at Steam Production entrance on Concord Rd.,'left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd.,

left on Blue Bird Ln., through gate to end (TLD CNS #201, need key). -

A0 1 8 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd. Go to first drive on-right past Paradise Pl.,

TLD across road (TLD CNS #202).

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Page 2 of 5 DUKE POWER COMPANY CAT &"dA @ LEAR STATION HP/0/B/1009/04 ENCLOSURE 5.1 AIR SAMPLER, TLD. AND WATER SAMPLE LOCATIONS Zone & Radius (MI) No. Description A0 1 11 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd.,

right on Acacia Rd., left on Crepe Myrtle Rd. TLD is .1 miles on left in curve (TLD CNS #223).

A0 1 14 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd.,

right on Acacia Rd. TLD .2 miles on right (TLD CNS #224).

A0 1 45 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd. to end. TLD on fence on left (TLD CNS #203).

AO. 1 17 Left at Steam Production entrance on Concord Rd. to first transmission tower on left after bridge (TLD CNS #225).

- A0 1 20 Left at Steam Production entrance on Concord Rd., TLD on left across bridge just past fence (TLD CNS #226).

A0 1 23 Left at Steam Production entrance on Concord Ed., TLD on left at beginning of guardrail posts (TLD CNS #204).

A0 1 26 Behind Catawba Nuclear Station overlook (TLD CNS #205).

A0 1 29 Left at Steam Production entrance on Concord Rd., TLD at Shady Shore Dr. on  ;

right corner at Bethel Community Clubhouse  !

sign (TLD CNS #227).

l A0 32 Right at Steam Production entrance on Concord j Rd., TLD at first dirt left (Valelake Dr.) on q right corner (TLD CNS #228).  !

A0 1 35 TLD on top of hill at Catawba Nuclear d Station Construction entrance on North side of street (TLD CNS.#206). j

.t A0 1 38 Hwy 274-N, right at Liberty Hill Rd., right in fork to third power line on right, walk j>

about 200 yds. South along boundary fence.

TLD on fence (TLD CNS #229).

A0 1 41 Hwy 274-N, right at Liberty Hill Rd., go  !

.8 miles (right in fork) TLD on fence on l right (TLD CNS #207).

Page 3 of 5 DUKE POWER COMPANY CATAWBA EILEAR STATION HR/0/B/1009/04 ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS Zone & Radius (Mi) No. Description II. 4-5 Mile TLD's F1 4 4 Hwy 49-N to River Hills Plantation rear entrance at Robinwood Rd. TLD behind green building on right corner (TLD CNS #230).

F1 4 6 Hwy 49-N to River Hills Plantatica front entrance guardhouse (TLD CNS #231).

A1 4 2 Hwy 49-N to intersection of Pleasant Hill Rd. (1109), TLD on power line (TLD CNS #232).

A1 4 4 Hwy 49-N, right Pleasant Hill Rd. (1109),

right Youngblood Rd.(1102), left Zoar Rd.

(1105), right Thomas Rd. (1104), TLD behind second house on right (TLD CNS #233).

B2 4 2 Hwy 49-N, right Hwy 160 to Home Federal Savings and Loan on left. TLD on left rear corner of building. (TLD CNS #234).

B1 4 3 Hwy 49-N, right Hwy 160, right on Dam Rd.

(99), last gravel right in sharp curve before Lake Wylie Dam, left through fence to substation, TLD on right of inner substation fence (TLD CNS #235).

C1 4 1 Hwy 274-S, left Mt. Gallant Rd. (195),

left India Hook Rd. (30) to S.C. Wildlife Resources Dept (TLD CNS #236).

C1 4 3 Hwy 274-S, left Mt. Gallant Rd. (195),

right Homestead Rd. (657) to end, TLD straight across intersection of Twin Lakes Rd. (TLD CNS #237).

C1 4 5 Hwy 274-S, left Mt. Gallant Rd. (195),

right W. Oak Dr. (962) to end at fork, TLD on left at fence (TLD CNS #238).

r D1 5 1 Hwy 274-S to Carter Lumber Co., TLD on fence near gate (TLD CNS #239).

D1 4 2 Hwy 274-S, right Campbell Rd. (80), left on Paraham Rd. (54) to transmission tower on right, TLD on brown power pole (TLD CNS #240).

D1 5 4 Hwy 274-S, right Campbell Rd (80) for about 3 miles TLD on left at beginning of .

horse fence (TLD CAS #241).

<J .

l Page 4 of 5 DUKE POWER COMPANY CATAWBA R'SLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS Zone & Radius (M1) Noi Description El 5 2 Hwy 49-S, right Paraham Rd, (54) to transmission tower on left after bridge (TLD CNS #242).

El 5 3 Hwy 274-N, left Hwy 55, left Kingsberry Rd. (114) to transmission tower on left (TLD CNS #243).

F1 4 1 Hwy 274-N, left Hwy 55 to Bethel School, TLD on side of small building in back (TLD CNS #244).

F1 4 3 Hwy 274-N left on Glenvista Rd. to Crowder Creek Boat Landing, TLD to East of parking lot (TLD CNS #245).

B2 8 1 Hwy 49-N, right Carowinds Blvd. (1441), left Choate Cir. , TLD on inside of fence left of the guardhouse (TLD CNS #246).

B1 3 1 Hwy 49-N, right Hwy 160, right Tega Cay sign (98), right before Tega Cay entrance into Duke Power Company substation (TLD CNS #212).

B2 7 6 Hwy 49-N, right Hwy 160 to Fort Mill, right Lee St., left Self St., TLD at Fort Mill Municipal Water Supply behind Springs Mill (TLD CNS #247).

C2 7 3 Hwy 274-S, right on Herlong Ave. to Piedmont Medical Center emergency entrance to back of hospital. TLD on fence at back right corner of Liquid Oxygen storage area (TLD CNS #248). 1 l

C2 10 5 Hwy 274-S to Newport, left at stop light, right on Rawlinson Rd., left Hwy 5, right on Heckle Blvd. (901) to end, left on Hwy.

72, right on dirt road just across from Wayne's Auto Service, go to Duke Power Company Substation (TLD CNS #217).

C2 8 6 Hwy 274-S, lef t Hwy 161, right Rawlinson Rd.

(56), left Hwy 5 to Rock Hill Career

- Development Center, TLD on transmission tower (TLD CNS #249).

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Page 5 of 5 DUKE POWER COMPANY CATAWBA hTOLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS Zone & Radius (Mi) No. Description D2 10 4 Hwy 274-S, right Campbell Rd. (80), left Ewy 49-S, left Rd. 64, left Hwy 5. Go to Duke Power Company Appliance Center on left. TLD on fence in back (TLD CNS #250).

E2 10 2 Hwy 55 into Clover, TLD at Duke Power Company Appliance Center in rear lot on inner fence (TLD CNS #251).

Water Sample Locations F3 14 4 Hwy 274-N, right Pole Branch Rd. (279), right Hwy 273 into Belmont, right Catawba St.,

left at next light to Belmont Municipal Water Supply (Water CNS #218). .

C2 7 2 Hwy 274-S, left Hwy 161, right Mt. Gallant Road (195) to end. Rock Hill Municipal Water Supply across intersection on left r (Water CNS #214).

~

B2 7 6 Hwy 49-N, right Hwy 160 to Fort Mill, right Lee St., left Self St., go to Fort Mill Municipal Water Supply behind Springs Mill (hater CNS #213).

A0 1 46 Left exiting Steam Production entrance on Concord Rd., left just after canal bridge.

Go to pier (water CNS #208, need key).

B1 4 5 Hwy 49-N, right Hwy 160, right Dam Rd.

(99), left Gray Rock Rd. (251) to Lake Wylie Dam. Walk through plant to upstream ,

side of the dam (water CNS #211). .

B1 4 6 Ewy 49-N, right Hwy 160, right Dam Rd.

(99), left Gray Rock Rd. , (251) to Lake Wylie Dam. Ride or walk to river access on downstream side of dam.

E C2 7 8 Hwy 274-S left Mt. Gallant Rd. (195), left Hwy 161, left Cherry Rd. (Hwy 21), left on dirt road at Fort-Rock Drive-In to end, go right to Rock Hill Municipal water intake.

Al 4 6 Hwy 49-N, left at Camp Steere sign after

, crossing Buster Boyd Eridge (Water CNS #215).

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Page 1 of 1 DUKE PC'.73 COMPANY CATAWBA NUCLEAR STATION I HP/0/B/1009/04 ENCLOSURE 5.2 MILK SAMPLE LOCATIONS Zone Radius (MI) Milk D1 6 M Hwy 274-S, right Hwy 161, left Rd. 1080 to Pursley Dairy.

D2 8 M Hwy 274-S, right Hwy 161, left Scism Dairy and Equipment Co. (CASE sign).

E2 6 M Hwy 274-N, left Hwy 55, left Clinton Dairy Rd.

F1 3 M Hwy 274-N, right Lake Wylie Rd. (1099) to {

first house on left, (Ingram Richmond residence).

F2 7 M Hwy 274-N, Hwy 55, right Paraham Rd. (54),

left Hwy 557. Barnett Dairy 1 mile on left.

D1 7 M Hwy 274-5 to Newport, left at stop light, right Adnah Church Rd. (81). Woods Dairy 1.5

( miles on left.

F2 13 M Hwy 274-N, left Hwy 55, go through Clover,SC. Right on Lloyd White Rd. (148), left on Crowders Creek Rd. (1103), next paved right '

(1125). Oates Dairy is half mile on left.

9

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Page 1 of 10 DUKE POWER COMPANY CATAWBA bl'fJ.AR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description A0 1 1 Hwy 274-N, right Liberty Hill Pd., right in fork to end (TLD & Air CNS #200, need key).

A0 1 2 Hwy 274-N, right Lake Wylie Rd. (1099),

right at Hudson Rd. fork, right at Commodore Pl. fork, left on Tioga Rd. to end.

A0 2 3 Hwy 274-N, right Lake Wylie Rd., (1099),

left fork after pavement ends, on Hudson Rd. to end.

A0 2 4 Hwy 49-N, right Pleasant Hill Rd. (1109),

right Youngblood Rd. (1102) to dead end at Catawba Yacht Club.

AD 1 5 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd.,

left on Blue Bird Ln. through gate to end (sg (TLD ST Air _CNS #201, need key).

A0 1 6 Hwy 49-N, right Pleasant Hill Rd. (1109),

right Youngblood Rd. (1102), left on Snug Harbor Rd. (1357), right Coze Cove Rd.

(1434) to end.

A0 2 7 Hwy 49-N, right Pleasant Hill Rd. (1109),

right Youngblood Rd. (1102), to intersection of Snug Harbor Rd. (1357).

A0 1 8 Left exiting Steam Production entrance on -

Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd. Go to first drive on right past Paradise Pl.,

TLD across road (TLD CNS #202).

A0 1 9 Hwy 49-N, right Pleasant Hill Rd. (1109),

right Youngblood Rd. (1102), left Snug  ;

Harbor Rd. (1357) to end.

A0 2 10 Hwy 49-N, right Pleasant Hill Rd. (1109), -

right Youngblood Rd. (1102), left Snug Harbor Rd. (1357), stay on Snug Harbor at Kalabash Rd. Fork, take first gravel left (Crosshavens Dr.) after fork to the end

, (Beware of dogs).

O O

Page 2 of 10 m DUKE POWER COMPANY "gO CATAWBA h1TLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description A0 1 11 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Road.

TLD is .1 miles on left in curve (TLD CNS

  1. 223).

AD 1 12 Hwy 49-N, right Pleasant Hill Rd. (1109),

right Youngblood Rd. (1102), left McKee Rd (1100), right Bankhead Rd. to end.

A0 2 13 Hwy 49-N, right Pleasant Hill Rd. (1109),

right Youngblood Rd. (1102), left McKee Rd.

(1100), right Bankhead Rd. to intersection -

4 of Bessbrook Rd.

A0 1 14 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd. TLD .2 miles on right (TLD CNS #224).

p.

(sij A0 1 15 Left axiting Steam Production entrance on Concord Rd., take first dirt fork to left on Kingsberty Dr. , Stop at Commodore Yacht

, Civb.

A0 1 16 Left' exiting Steam Production entrance on Concord Rd. to last big curve before pave-ment ends.

A0 1 17 Left axiting Steam Production entrance on Concord Rd. to first transmission tower on left after bridge (TLD CNS #225).

A0 1 18 Left exiting Steam Production entrance on Concord Rd., go to end and turn right on Sandlapper Rd. Stop at transmission tower.

A0 2 19 Hwy 274-S, left Allison Creek Rd. (1081) to end of pavement. '

A0 2 20 Left exiting Steam Production entrance on Concord Rd. TLD on left across bridge, just past fence (TLD CNS #226).

A0 1 21 Left Hwy-274-S, left Allison Creek Rd.

(1081), left Spratt Rd., to end (Beware of ye dogs). ,

A0 2 22 Hwy 274-S, left Allison Creek Rd. (1081) to i intersection of Bardale Rd. '

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Page 3 of 10 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/3/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Descriotion A0 1 23 Left exiting Steam Production entrance on Concord Rd. TLD on left at beginning of guardrail posts (TLD CNS #204).

A0 1m. 24 Hwy 274-S, left Allison Creek Rd. (1081), left at Spratt Rd., left Morrison Rd., then right in next 2 forks, left in next fork to end.

A0 2 25 Hwy 274-S, left Allison Creek Rd. (1081),

to intersection of Spratt Rd.

A0 1 26 Behind Catawba Nuclear Station overlook (TLD and Air CNS #205, need key).

A0 1 27 Right exiting Steam Production entrance on Concord Rd., first dirt left on Valelake Rd., left in fork to end.

A0 2 28 Hwy 274-S, left Allison Creek Rd. (1081) to intersection of Colina Rd.

(;;

\n' A0 1 29 Left exiting Steam Production entrance on Concord Rd. TLD at Shady Shore Dr. on right corner at Bethel Community Clubhouse sign (TLD CNS #227).

A0 1 30 Right exiting Steam Production entrance on Concord Rd., first dirt left on Valelake Rd.,

right in fork to end.

A0 2 31 Hwy 274-S to intersection of Campbell Rd. (80).

A0 1 32 Right exiting Steam Production entrance on Concord Rd. TLD at first dirt left (Valelake Dr.) on right corner (TLD CNS #228).

A0 1 33 Right exiting Steam Production entrance on Concord Rd., left on dirt road (Pine Pt.

Dr.) just before Granny's Restaurant, stop

.5 miles.

A0 2 34 Hwy 274-S to Big Allison Creek bridge.

A0 1 35 TID on top of hill at intersection of Catawba Nuclear Station Construction entrance and Road 1132 (TLD CNS #206). ,

A0 1 36 Right exiting Steam Production entrance to transmission line just before Granny's '

Restaurant on Concord Rd. (1132).

Page 4 of 10 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description A0 2 37 Hwy 274-N, left Liberty Hill Rd., take -

first left and go to end.

A0 '

1 38 Hwy 274-N, right at Liberty Hill Rd., right ~

in fork to third transmission line on right, walk about 200 yds. South along boundary fence. TLD is on fence (TLD CNS #229). -

A0 1 39 Hwy 274-N, right at Liberty Hill Rd., right ,

in fork to third transmission line on right.

A0 2 40 Right exiting Steam Production entrance on Concord Rd. to end. Right on Hwy 274-N for 1 mile.

A0 1- 41 Hwy 274-N, right at Liberty Hill Rd., go .8 miles (right in fork), TLD on fence on right (TLD CNS #207).

A0 1 42 Hwy 274-N, right at Liberty Hill id., right in fork, go. co softball field entrance.

A0 2 43 Hwy 274-N, right Lake Wylie Rd. (1099),

right Beaver Creek Trail to end. '

A0 1 44 Hwy 274-N, right at Liberty Hill Rd., right in fork, pass softball field to large rock piling on fence. TLD is on fence (TLD CNS

  1. 222).  ;

A0 1 45 Left exiting Steam Production entrance, left on Old Concord Rd. to end. TLD on fence on '

left (TLD CNS #203).

A0 1 46 Left exiting Steam Production entrance on Concord Rd. Turn left just after canal bridge. Go to pier (water CNS #208, need key).

1 Al 3 1 Hwy 49-N to NC side of Buster Boyd Bridge.

A1 4 2 Hwy 49-N to intersection of Pleasant Hill Rd. (1109), TLD on transmission tower (TLD CNS #232).

A1 5 3 Hwy 49-N to Steele Creek Vol. Fire Dept. on right.

M #

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Page 5 of 10 l DUKE POWER COMPANY CATAWBA NUCLEAR STATION l HP/0/B/1009/04 ,

ENCLOSURE 5.3 i PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description A1 4 4 Hwy 49-N, right Pleasant Hill Rd (1109),

right Youngblood Rd. (1102), left Zoar Rd.

(1105), right Thomas Rd. (1104, TLD behind second house on right in pines (TLD CNS

  1. 233).

A1 5 5 Hwy 49-N, right Pleasant Hill Rd. (1109, right Youngblood Rd. (1102), left Hamilton Rd. (1106) to intersection of Hwy 160.

A1 4 6 Hwy 49-N, left at Camp Steere s'ign after crossing Buster Boyd Bridge (Water CNS #215).

A2 10 1 Hwy 49-N, stop one mile past Westinghouse Blvd. at Roberts-Systems 8500 on left.

A3 10 1 Hwy 49-N, right Carowinds Blvd. (1441),

left Hwy 51 to Pineville, stop near Sugar Creek bridge.

B1 3 1 Hwy 49-N, right Hwy 160, right on Gold Hill Rd. (98) at Tega Cay sign, right before Tega Cay entrance on gravel road into Duke Power Company substation (TLD & Air CNS #212,

need key).

B1 2 2 Hwy 49-N, right Pleasant Hill Rd. (1109),

right Youngblood Rd. (1102), left McKee Rd (1100)., left Bankhead Rd., left Bessbrook Rd. to end.

B1 4 3 Hwy 49-N, right Hwy 160, right on Dam Rd.

(99), last gravel right in sharp curve before Lake Wylie Dam, left through fence to substation, TLD on right of inner substation fence (TLD CNS #235).

B1 2 l'+ Hwy 49-N, right Hwy 160, right on Gold Hill

' Rd. (98) at Tega Cay sign, enter Tega Cay following Tega Cay Dr., right Windjammer Dr. ,

6 miles, Right at circle, Left Kiwi Point to end.

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

, e Page 6 of 10 DUKE POWER COMPANY CATAVBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (M1) No. Description B1 4 5 Hwy 49-N, right Hwy 160, right Dam Rd.

(99), left Gray Rock Rd. (251) to Lake Wylie Dam. Walk through plant to upstream side of the dam (water CNS #211).

B1 4 6 Hwy 49-N, right Hwy 160, right Dam Rd.

(99), left Gray Rock Rd. (251) to Lake Wylie Dam. Go to river access on downstream side of dam.

B2 8 1 Hwy 49-N, right Carowinds Blvd. (1441),

left Choate Circle, TLD on inside of fence left of the guardhouse (TLD CNS #246).

B2 4  :

2 Hwy 49-N, right Hwy 160 to Home Federal Savings and Loan on left. TLD on left rear corner of building (TLD CNS #234). e B2 5 3 Hwy 49-N, right Hwy 160, left on Gold Hill .

Rd. (98) at Home Federal Savings and Loan, '

stop at intersection of Whitley Rd.

B2 10 4 Hwy 49-N, right Carowinds Blvd. (1441), [

1 eft Hwy 51 to Pineville, right Hwy 521 .

(Polk St.) in Pineville, right on Dorman Rd., stop at state line. [

b B2 5 5 Hwy 49-N, right Hwy 160, right Sutton Rd. '

(49) to intersection of Gray Rock Rd. (251),

B2 7 6 s Hwy 49-N, right Hwy 160 to Fort Mill, Right -

Lee St., left Self St. TLD at Fort Mill Municipal Water Supply on right behind (

Springs Mill (TLD CNS #247, also Water CNS

  1. 213). -

B2~ 10

!i 7 Hwy 49-N, right Hwy 160 through Fort Mill to the Sugar Creek bridge.

I e

I C1 4 i 1 -Hwy 274-S, left Mt. Gallant (195), left India Hook Rd. (30) to SC Wildlife e Resources Dept. (TLD CNS #236).  ;'

C1 5 2 Hwy 274-S, left Mt. Gallant Rd. (195), go beyond India Hook to Red Burketts Body Shop on right.

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i DUKE POWER COMPANY U CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description C1 4 3 Hwy 274-S, left Mt. Gallant Rd.'(195),

right Homestead Rd. (657) to end. TLD straight across intersection of Twin Lakes Rd. (TLD CNS #237). '

C1 5 4 Hwy 274-S, left Mt. Gallant Rd. (195), '

right Homestead Rd. (657) to end. '

'l C1 4 5 Hwy 274-S, left Mt. Gallant Rd. (195),  %

right W. Oak Dr. (962) to end at fork. TLD a on left at fence (TLD CNS #238). i C1 i 5 6

' Hwy 274-S, left Mt. Gallant Rd. (195),

right at York County Museum (658) to end at p 1

SC National Guard Armory. E C1 5 7 Hwy 274-S to_ Carter Lumber Co.

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C2 10 -1 Hwy 274-S, left Hwy 161, left in fork on j Celanese Rd. (50) to intersection of o Springdale Rd. k C2 7 2 Hwy 274-S, left Hwy 161, right Mt. Gallant h E

Rd. (195) to end. Go to Rock Hill (

Municipal Water Supply across intersection I on left (Water CNS #214). Y C2 7 3 l

Hwy 274-S, right on Herlong Ave, to I Piedmont Medical Center emergency entrance 9 to back of hospital. TLD on fence at back right corner of Liquid Oxygen storage area I (TLD CNS #248). i 0

C2 10 4 Hwy 2T4-S, left Hwy 161, right Mt. Gallant I Rd. (195), right Ley 21-121 By pass to Fast b Fare on left at intersection of Springsteen $

Rd. #

C2 10 5 Hwy 274-S to' Newport, left at stop light, h right on Rawlinson Rd., left Hwy 5, right h on Heckle Blvd. (901) to end, left on Hwy fi 72, right on dirt road across from Wayne's J

' Auto Service. Go to Duke Power Company *

, substation (TLD & Air CNS #217, need key). i C2 8 6 Hwy 274-S,-left Hwy 161, right Rawlinson Rd. (56), left Hwy 5 to Rock Hill Career Development Center, TLD on transmission tower (TLD CNS #249).

n

Page 8 of 10 DUKE POWER COMPANY CATAWBA NUCLF.AR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description C2 10 7 Hwy 274-S, left Hwy 161, right Adnah Church Rd. (81), right on hwy 5, left on Eastview Rd. (102) to intersection of Oak Park Rd.

(103).

C2 7 8 Hwy 274-S, left Mt. Gallant Rd. (195), left Hwy 161, left Hwy 21, left on dirt road at Fort-Rock Drive-In to end, go right to Rock Hill Municipal Water Intake.

D1 5 1 Hwy 274-S to Carter Lumber Co. TLD on fence near gate (TLD CNS #239).

D1 4 2 Hwy 274-S, right Campbell Rd. (80), left Paraham Rd. (54) to transmission tower on right, TLD on power pole (TLD CNS #240). s D1 5 Hwy 274-S, right Campbell Rd. (80), left

~

3 Paraham Rd. (54), next right on.Rd. 815 to Allison Creek bridge.

D1 5 4 Hwy 274-S, right Campbell Rd. (80) for about 3 miles, TLD on left at beginning of horse fence (TLD CNS #241).

P T

D2 10 1 Hwy 274-S, left Hwy 161, right Adnah Church Rd. (81), right. Hwy 5, quick left on Eastview.Rd. (102), right Holland Rd. (157), -

right Turkey Farm Rd. (1172), left Russell Rd. (536), go .2 miles.

D2 10 2 Hwy 274-S, left Hwy 161, right Adnah Chruch Rd. (81), right Hwy 5, left Billy Wilson Rd. (1451), right Turkey Farm Rd. (1172) to Fishing Creek bridge.

D2 10 3 Hwy 274-S, right Campbell Rd. (80), left Hwy 49-S, stop at Pantry before entering York.

D2 10 4 Hwy 274-S, right Campbell Rd. (80), left Hwy 49-S, left Rd. 64, left Hwy 5. Go to Duke Power Company Appliance Center on left. TLD on fence in back (TLD CNS #250).

k

Page 9 of 10 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description D2 10 5 Hwy 274-S, right Camebell Rd. (80), left 49-S, right Old Lima a tone Rd. (172) to end.

El> 5 1 Hwy 274-S, right Campbell Rd. (80) to intersection of Hwy 49.

El 5 2 Hwy 49-S, right Paraham Rd. (54) to transmission tower on left after bridge (TLD CNS #242).

El 5 3 Hwy 274-N, left Hwy 55, left Kingsberry Rd.

(114) to transmission tower on left (TLD CNS #243).

El 5 4 Hwy 274-N, left Hwy 55 to intersection of Kingsberry Rd. (114).

E2 5 1 Hwy 274-S, right Campbell Rd. (80), right Paraham Rd. (54) to intersection of Dr. Nichols Rd. (819).

E2 10 2 Hwy 274-N, left Hwy 55 into Clover, go to Duke Power Company Appliance Center on left. TLD on fence in back (TLD CNS #251).

E2 10 3 Hwy 274-N, left Hwy 55 to Pantry at intersection of Hwy 321 in Clover (behind Pantry).

F1 4 1 Hwy 274-N, left Hwy 55 to Bethel School.

TLD on side of small building in back (TLD

'CNS #244).

F1 5 2 Hwy 274-N, left Hwy 55, right Bethel School Rd. (152) to intersection of Hollandale Dr.

F1 4 3 Hwy 274-N left on Glenvista Ed. to Crowder Creek boat landing, TLD to east of parking lot (TLD CNS #245).

i F1 4 4 Hwy 49-N to River Hills Plantation rear entrance at Robinwood Rd. TLD behind green building on right corner (TLD CNS #230).

Page 10 of 10 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description F1 5 5 Hwy 49-N, left Sherer Church Rd. to end.

F1 4 6 Hwy 49-N to River Hills Plantation entrance guardhoose (TLD CNS #231).

F1 5 7 Hwy 49-N, left Montgomery Rd. at the River Rat Restaurant. Stop in horseshoe curve near lake.

F2 10 1 Hwy 274-N, left Hwy 557, right Ridge Rd.

(27) to Bowling Green Presbyterian Chruch.

F2 5 2 Hwy 274-N, left Hwy 557 to Pine Grove Bdptist Chruch.

F3 10 i Hwy 274-N, left Hwy 557, next paved right on Oakridge Rd. at Bethel Fire Dept.'(Rd. 435) to intersection of Hwy 274 (in NC).

F3 10 2 Hwy 274-N, right Pole Branch Rd. (279) to -

Friencship Baptist Church on left.

F3 10 3 Hwy 274-N, right Pole Branch Rd. (279),

right Hwy 273 to Allen Steam Plant Bridge.

F3 14 4 Hwy 274-N, right Pole Branch Rd. (279),

right Hwy 273 into Belmont, right Catawba St., left at next light to Belmont Municipal Vater Supply (Water CNS #218).

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DUKE POWER COMPA.W CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.5 -l FIELD MONITORING DATA SHEET l

l Date Team Members / Call Sign / Inst. Type /No. /

Smear Sample Location Time Survey Taken Dose Rate (mR/hr) Activity (CCPM) .

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DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.6 SAMPLE TIME REQUIRED FOR MINIMUM SAMPLE VOLUME FLOW RATE MINIMUM REQUIRED SAMPLING TIME IN MINUTES CFM LPM

.5 = 14 . . ... . . . . .. ... . . . 71 1.0 = 28 . . ... . . . . .. ... . . . . 36 1.5 = 42 . . ... . . . . . . . . . . . . 24 2.0 = 56 . . ......... . . . . . . 18 2.5 = 70 . . ... . . . . .. . .. . . . . 15 3.0 = 84 . ... . . . . .. .. .. . . . 12 3.5 = 99 . . ... . . . . .. ... . . . . 11 4.0 = 113 . . ..... . . .. ....... 9 4.5 = 127 . . ... . . . . .. .... . . . 8 NOTE: When estimating time required to get a minimum volume of 1 x 10' al if flow rate for the air sampler in use is not on table, go to next ~

Lower flow rate. The LPM are rounded off to the conservative side. ,

Example: Air Sampler flow rate = 106 LPM. Minimum time 11 minutes 3

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l DUKE POWER COMPANY Page 1 of 2 CATAWBA NCULEAR STATION HP/0/B/1009/04 ENCLOSURE 5.7 FIELD MONITORING TEAM WORK SHEET FOR DETERMINING IODINE ACTIVITY j 1

Team Members l Date Air Sampler No.  ;

Team Call Sign Canberra No. I AIR SAMPLE INFORMATION ANALYSIS RESULTS A B C D E F Sample ID. Air Sampler Flow Rate Iodine Activity Dose Rate Results No./ Time / Location Run Time (Min) (LPM) Microcuries/ml mrom/hr Reported By:

/ /

/ /

/ /

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/ /

/ /

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/ /

/ /

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/ /

/ /

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Column A) Number of Sample / Time it was Taken/ Sampling Location (ex. A0-2-10). l Column B) Length of time .the air sampler ran.

Column C) Air sampler meter flow rate.

i Column D) Activity from Canberra. '

Column E) Dose rate from Canberra.- .

},;lumn F) Signature of person that calls in results to FMC.

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.3 DUKE P3WER COMPANY Page 2 of 2 CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.7 OPERATOR GUIDELIhTS 5.6.1 MCA and Detector Set-Up 5.6.1.1 Disconnect DC power cord from unit.

5.6.1.2 Turn the contrast switch on the front of the unit clockwise to the ON mode.

5.6.1.3 Place sample holder with Na-22 check source onto the detector.

5.6.1.4 ' Press TEST SYSTEM.

5.6.1.5 Press ENTER to begin test.

5.6.1.6 If test failed, press CLEAR ENTRY and remove the instrument from service.

5.6.1.7 If test passed, press ENTER.

5.6.2 Collecting and Measuring Filter Cartridges NOTE: Record data on Field Monitoring Team Work Sheet for Determining Iodine Activity (Sample Enclosure 5.6).

5.6.2.1 Press ANALYZE FILTER SAMPLE. ,

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't; 5.6.2.2 Press ENTER.

5.6.2.3 For each sample:

5.6.2.3.1 Place cartridge with the recognizable side toward the detector (in small poly bag) in sample holder.

5.6.2.3.2 Put detector and sample holder in shield.

5.6.2.3.3 Press ENTER to accept ID number.

5.6.2.3.4 Press ENTER to accept current Flow Rate '(LPM). '

Otherwise, change number and press EhTER.

5.6.2.3.5 Press ENTER to accept current Flow Time (min).

Otherwise, change number and press ENTER. '

5.6.2.3.6 If the volume is determined to be too small, resample, press ENTER and return to Step 5.6.2.3.

l 5.6.2.3.7 Press ENTER to start Collect / Analyse.

! 5.6.2.3.8 Report / Record Iodine activity (uCi/ml) and

dose rate (ares /hr).

~

5.6.2.3.9 Press NEXT SAMPLE.

5.6.2.3.10 Label the cartridge and retain for later analysis. <

( 5.6.3 After sampling completion, turn the contract ' switch counter-clockwise to the STAND-BY mode.

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l Page 1 of 1 ,

DUKE POWER COMPANY I CATAWRA NUCIZAR STATION  !

HP/0/3/1009/04 "

- I ENCICSURE 5.8 -

TSC FIELD MONITORING ORGANIZATION i

POSITION NAME BUSINESS PHONE HOME PHONE Field Monitoring Coordinators:

Primary: C. V. Wray Alternates: R. L. Rivard -

J. E. Threatt TSC Radio Operators:

Primary: D. E. Sexten . I Alternate: T. W. O'Donohue L

Field Monitoring Teams:

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All Health Physics personnel with Field Monitoring Training.

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DUKE POWER COMPANY c.$ -

' CATA'n'BA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 3.9 EMERGENCY VEHICLES The two designated emergency vehicles are the Operations pick-up truck and the Technical Services vehicle used primarily by Chemistry. These two vehicles are to be obtained.(as directed by the FMC) by getting the keys from the front desk Security Officer. A set of all keys to station vehicles shall be maintained by Security at the Personnel Access Portal (PAP).

Obtain any other Station vehicles (if available) as directed by the FMC.

Voluntary use of personnal vehicles is another alternative that may be considered.

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Ny Form 34731 (10 81)

(Formerly SPD 10021) ,

DUKE P0k*ER COMPANY (1) ID No:HP/0/B/1009/13 PROCEDURE PREPARATION Change (s) o to

. PROCESS RECORD 2 Incorporated (2) STATION: Catawba e J

(3) PROCEDURE TITLE: Offsite Dose Proiection - Uncontrolled Release of Radioactive Material Through the Unit Vent (4) PREPARED BY:

DATE: '/!30 ST (5) REVIEWED BYi' 7 '

%[ ~ ' ~ ~ DATE~: [ -/-T f Cross-Disciplinary RI.'s. 4i N/R: [dM

e. (BJ HKEWM MPS6N (IF NECESSARY):

'y'1*

By: (SP3) Date: _

1 By: Date:

(7) APPROVED BY: D-t Date: k[

(8) MISCELI.ANEOUS:

Reviewed / Approved By: Date:

Reviewed / Approved By: Date:

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I HP/0/B/1009/13 DUKE POWER COMPANY .

CATAWBA. NUCLEAR STATION OFFSITE DCSE PROJECTION - UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL THROUGH THE UNIT VE.NT 1.0 PCRPOSE -

This procedure describes the method for projecting the potential offsite -

dose followtag an uncontrolled release of radioactive materials through the unit. vent. ---

2.0 REFERENCES

2.1 Letter from Civil / Environmental Division CN-1108.1, 1434.00, 1227.00 Atmospheric Dispersion Factor for Emergency Planning l

2.2 EPA-520/1-75-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.3 Regulatory Guide 1.109, Calculation of Annu'al Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating f Compliance with 10CFR50, Appendix I 2.4 Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors 3.0 LIMITS AND PRECACTIONS 3.1 Use actual sample data when possible. Radiatica monitor readings are susceptible to several sources of error. When radiation menitor .

readings are used for downwind concentrations, note this in the report of offsite dose assessment.

3.2 Environmental data should be collected and analyzed to verify these calculations. This procedure considers all releases to be ground

level releases.

3.3 This procedure applies to releases made from Catawba Nuclear Station only. Many of the values contained in this procedure are site specific.

3.4 Reporting requirements of Station Directive 2.8.1 and HP/0/3/1009/02 shall be evaluated to ensure that the Shift Supervisor and/or the Licensing Engineer are informed of the requirements.

4.0 PROCEDURE

(?; 4.1 Obtain the following information from the Control Room and record it on Enclosure 5.1 (Vent Release Data Sheet).

. s

, ,' Os 5,, u HP/0/B/1009/13 Page 2 of 5 4.1.1 Time of reactor trip.

4.1.2 Tower wind speed in MPH.

(Lower tower wind speed preferred.) ,

4.1.3 Direction from which the wind is blowing in degrees from t North. (Upper tower wind direction preferred.) .

?

4.1. 4 - Temperature gradient (AT) in degrees C.

4.1.5 Vent discharge flow rate in CFM.

r 4.1.6 Available weather forecast information.

4.2 Determine the release concentration as follows: .

4.2.1 If vent sample analysis is not available, go to Step 4.2.4.

4.2.2 Obtain the following vent samole en: lysis results-and -- -

r.. - :: * .  :: 1 . '.

4.2.2.1 Date/ time of sample.

4.2.2.2 Gross noble gas concentration in WCi/ml.

4.2.2.3 Iodine equivalent concentration (or data for calculation). -

4.2.2.4 Gamma E-bar value in mev/ dis (or data for calculation).

4.2.3 Go to Step 4.3 '

4.2.4 Obtain the following unit vent' data and record on '

sample Enclosure 5.1: .

4.2.4.1 Date/ Time of collection. .

4.2.4.2 EMF 36 Low and High range readings in epm (gas monitor).

4.2.4.3 AEMF37 reading in cpm (iodine monitor). '

4.1.4.4 At in minutes for AEMF37 reading.

4.2.4.5 Calculate release concentrations as shown on Enclesure 5.1.

4.3 Project the impact of the release on the downwind population by using the manual calculations outlined below.

_" 4.3.1 Determine the X/Q values for each point of interest

, downwind as follows.

NOTE: If no points have been requested, use the .5, 2, 5 and 10 mile values.

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HP/0/3/1009/13 Page 3 of 5 4

4.3.1.1 From Enclosure 5.2 (Table of Two-H8ur Relative Concentration Factors), locate the relative two hour concentration value (CH) for each point

, -- and record on sample Enclosure 5.3 (Manual Calculation Worksheet), (Reference 2.3).

4. :t.1. 2 Convert these. values to.X/Q 'oy, r CH(MPH-Sec /m * )-
  • Wind Speed (MPH) 4.3.1.3 Record results on Enclosure 5.3 (Manual Calculation Worksheet).

4.3.2 Calculate the gas and iodine downwind concentrations for each point using the equation, Conc

  • k'. C-a .. -

Conc = downwind concentration (uCi/ml)

DW Coney = vent discharge concentration (uCi/ml)

Fy = vent discharge flow rate (CFM)

X/Q = dispersion factor in sec/m i U

DWC = unit c nversions derived from, (2.832E-2m*/ft') (0.017 min /sec) = 4.8E-4 " * **"

ft*

  • see Sample Enclosure 5.3 provides work space for this calculati n.

4.3.3 Determine the potential whole body gamma dose downwind '

using the gas ~~ '

concentrations calculated in 4.3.2 and the equation, ~

Dg =U g

  • E
  • Conc *
  • DW where, D

VB = whole body gamma dose due to submersion in a cloud of radioactive gas (rem)

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HP; 0/ B,1:]J,1" Page 4 of 5 s

U " '" "* #* #8 ' "# #* #

G 3.7E4 (dis /sec-uCi)(lec/1.2E-3g)

(1.602E-6 erg /MeV) (g - rem /100 ergs)

  • ~#**'"

( ., . ._ ._ ,1 dis-rem-cm')(3600 see) pCi-sec-Mev hr

  • ~#**"""

= 9.00 E2 pCi-hr-Mev SOTE: 1/2 is the constant used (in the case of gamma radiation) when assuming that the receptor is exposed to only one-half the ,

cloud owing to the presence of the-ground,- -

(Reference 2.4).

Conc3g = downwind concentration (uCi/ml)

Time = projected duration of exposure (hrs); use 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless otherwise directed.

1 E = average gamma energy per disintegration (:!ev/ dis) I NOTE: If 5 cannot be obtained from the sample results, i the followirg values may be used:

Hours from Trio 5 (Mev/ dis) -

0-12 0.40 '

12-48 0.20 48-= 0.10 4.3.3.1 Record results on Enclosure 5.3.  ;

I 4.3.4 Determine the potential child thyroid dose' downwind using h the iodine concentrations esiculated in 4.3.2 and the p equation, p

D =U

  • Time I Th'Y I
  • Conc.W u i-r where, #

1

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D THY = thyroid dose due to uptake of radioactive iodine (tam) h O

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HP/0/3/1009/13 Page 5 of 5 '

Ug = constants derived from a child's breathing rate -

(1.17E2 cc/sec.), I-131 dose conversion factor

~ (4.39 E-3 mrem /pCi), and coversion of pCi to 6

uCi (10 ), mram to rem (10 ~8), and hrs. to sec (3600 secs /hr) =. 1.86E6 uci

  • hr Conc D = doynwin Soncentration of iodine (uCi/ml)

Time = projected exposure time (hrs); use 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />' t

unless otherwise directed.

(

4.3.4.1 Record results on sample Enclosure 5.3. h 4.3.4.2 Project the adult' thyroid dose by dividing

_ the ch.ild dose by two (2). . j 4.3.4.3 Record results of all calculations on ~i Enclosure 5.5 (Dose Assessment Report). i 4.4 Determine the potentially affected area using the method outlined in Enclosure 5.4 J I

4.4.1 tp Record sectors on Enclosure 5.5.

4.5 's Complete sample Enclosure 5.5 and sub~mit' it to the Station Health Physicist. Include any comments and information pertinent to the l r

evaluation of offsite hazards. 'l, r

4.6 Maintain a file of all worksheets and printouts used in dose calculations. h e

5.0 ENCLOSURES b

5.1 Sample of Vent Release Data Sheet -

r 5.2 Sample of Table of Two Hour Relative Cancantration~ Factors k p

5.3 Sample of Manual Calculation Worksheet Y

[c 5.4 Sample of Evaluation of Plume Location t' ,

5.5 Sample of Dose Assessment. Report t f

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Page 1 of 1 ENCLOSURE 3.1 HP/0/B/1009/13 VENT RELEASE DATA SHEET Unit Date/ time of Rx trip /

METEOROLOGICAL DATA

1) Lower Tower Wind Speed MPH
2) Upper Tower Wind Direction From *
3) Temp. Gradient (AT) 'C
4) Vent Flow CFM
5) Date/ time /

VENT SAMPLE ANALYSIS - -- - -

1) Total Gas uCi/mi
2) I-131 Equiv. uCi/mi
3) Gas 5 Mev/ dis (Gamma)

VENT MONITOR DATA

~

1) EMF-36L (lo range) CPM
2) EMF-36H (hi range) CPM

, 3) AEMF-37 (iodine) CPM; At min ,

CALCULATED DI.SCHARGE CONCENTRATICN

1) Ggs (Use hi readings if EMF-36H is > 100 CPM) '

Cone y ,y,y =r (EMF 36L CPM) = pC1/ml, or Conc V-hi = (EMF-3 H CPM)

=

2.~0E7 CPM-ml 4.0E3 "*I pCi pCi uCi/ml

2) Icdine Coney ,7 = (AEMF-37 CPM) (2.4E-10 uCi - min) = VCi/mi At al - cpm 4

i ENCLOSURE 5.2 '

IIP /0/8/1009/I3 .. .

TWO-HOUR RELATIVE CONCENTRAIION FACTORS (CH)

Tempe ra ture Stability ,  ; '; Distanco (Miles);  : .1 t

(C a f fe rence Class -

~

('C)

.5 1 -2 3 4 5 ,

6 7 8 ' (9 -s 10 5

9,1 s- (

1) < .6 A 1.4E-5 1.2E-6 5.9E-7' 4.1E-7 3.2L-7 2.5E-1 e 2.0E-7 1.9E-1 1.SE-7 1.60-T 3.5E-7 f

f i '

2) .6 to .5 is-C 1.5E-4 4.5E-$ 1.'3E*5
  • 6.3E-6 3.9L-6 2.TE-6 1.9E-6 1. 8e E-6 1.lE-6 8'3E-7

, 7.8E-7.

i. $ . , ,

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, i  :

3) -0.4 to-0.2 0 3.8E-4 1.4E-4 4*9E-5' 2. 7E-5 ' l.7E-5 1. 2[-5 , 9.2E-6 7'.3E-6 6.OE-6 5.,0E-6 4.3E-6;

, i l '..

4) -0.1 to + . 88 E 6.9E-4 2.5E-4 9.6E-5! 5.5E-5! 3j5[-5 2.5E-5 2.0E-5 1;6E-5

. 1.3E-5 ' 1.1E-5 l 9.7E-6 .

5) *.5 to +1.2 f 1.1[-3 5.1E-4 2,0E-4: h.2E-4 8.2E-5 6.3E-5 5.1E-5 4 3E-5 3.8E-5 3J3E-5 3.0E-5 3 ,

[ l

0) > 1.2 C 1.8E-3 1.1E-3 4.3E-4 2.7E-4 2.0[-4 1.7E-4 1.3E-4 1.2E-4 8.6E-5 '8. EMS 7.3E-5!

From other sources or meteorological ' data:(Section 4.1) use the wind speed and time or day to determine which row or Cal values ta ase:

g D en_er 0 1 win ts.esed an a I 1%:00 A.H. - 4:00 P.M. N/A 3 4:00 P.M. -

10:00 A.H. > 15 HPJi 4i 4:00 P.H. - 10:00 A.H. 5 15 HP11 6' l

O *

.p ,

Page 1 of 1 1NCIOSURf 5.3 ,

ilP/0/ll/1009/ I 3 ,

MANUAL CALCulAllON WORKSilIII

1) Disclearge Concentration (conc y): 2) YgnLDj htj!a r9u_Lj 9V_Hi!S9: llWilld Jp_egtl Ca s = 441/mi I V = _ , __ , __ CIM

_ MPil lodiese = mci /mi

4) Ive .!!9ttr_!tctatlye Con.c,Jactora '

(CH e sec-sple/m s X/Q = Cll/iple =' soc /ms Cil =  ; X/Q = Sec/ msg gg $g any,yg'nd Concentrations:

Cil =  ; X/Q = _-Sec/m* 9 Mi Conc LH = Cone y a tv o x/Q o ta.a s t-4) 011 =  ; X/Q = 8 Sec/m @ Mi A) Casi it ) lodino Cil = _  ; X/4 = Sec/ms e Mi Conc IN = sci /mi conc IM = vCi/mi Conc EM = aCl/ml Conc IM = pCl/ml Conc DW = afi/ml Conc DW = ACi/mi Conc Did = .Ci/mi Conc (M = #,l/mi

6) Potential Wisole Body Camma Duso: "
7) Pott'ntial Child Thyroid Doso:

DWs = (9.00I2) o Conc EM o E o Ilmo Timo = hours D ))[Y = (1.8606) o Cone DW o Timo f= Mov/ dis DW8 = Hem 8 _ Mi . D lily = Hom DW8 :s Rem M Mi. D Illy =

_ Hem IWil = Hem W D Illy = *

. _ _ Mi. Hem "

DWB = Hem 8 , __ _ M i , D 1HY = Hom t

i  ;

y. , ,_ _ _ _ _ _.__

. Page 1 of 2

. ENCLOSURE 5.4 HP/0/B/1009/13

, EVALCATION OF PLCME LOCATION

1. Acquir0 the following information from Enclosure 3.1 and record on Enclo- e 5.5.

a) wind direction in degrees from north b) wind speec (mph) c) AT ('C) d) Stability Class .

e) thyroid and whole body doses

2. Protective action guides submitted to the Station Health Physicist are to be made based on the calculated dose on Enclosure 5.3 and.the following information. _ . -- . - - --

a) For doses:

> 5 Rem Whole Body or,-

> 25 Rem Thyroid Recommend Evacuation of Population in Affected Area.

B) For doses:

1-5 Rem Whole Body or, 5-25 Ram Thyroid Recommend evacuation of children and pregnant women, and sheltering of remainder of personnel in the affected area.

C) For doses: .

< 1 Rem.Whole Body or,

< 5 Rem Thyroid Recommend no action.

3.

Determine the affected zones, based on wind direction and wind speed, with the following tables.

Table 3.1 0-2 Mile Affected Zones t* --

Wind Direction Affected Zone 0' - 360' A0

Page 2 of 2

.' . ENCLOSURE 5.4 HP/0/B/1009/13 EVALCATICN OF PLUME I,0 CATION Table 3.2 2-3 Mile Affected Zenes Wind Speed $ 5 ,tph Wind Speed > 5 mph i

Wind Direction Affected Zones Wind Direction Affected Zones O' - 360* A1,B1,C1,DI,E1.F1 0.1* - 22' C1, D1 22.1* - 73* C1, D1, El l 73.1* - 108* C1,D1,El,F1 108.1* - 120' D1, El, F1 120.1* - 159" El, F1 159.1* - 207* El, F1, Al 207.1* - 247* F1, A1, El 247.1* - 265* A1, B1 265.1* - 298*

A1, B1, C1 l 298.1* 338* B1, C1 -

{

338.1* - 360* B1,C1,D1 A

Table 3.3 3-10 Mile Affected Zones Wind Direction Affected Zones 0.1* - 27* C2, D2 27.1* - 69* C2, D2, E2 69.1* - 95* D2, E2, F2 95.1* - 132' D2, E2, F2, F3 132.1* - 144' E2, F2, F3 144.1* - 160* E2, F2, F3, A2 160.1* - 201* F2, F3, A2 201.1* - 229' F2, F3, A2, B2 229.1* - 249' F3, A2, B2 249.1* - 259' A2, A3, B2 239.1* - 290* A2, A3, B2, C2 290.1* - 304* A3, B2, C2 304.1* - 333' B2, C2 333.1* - 360* B2, C2, D2 4.

Record sectors requiring protective action on Se=ple Enclosure 5.5 along with the recommended protective action. E i

.t e

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

i -

  • ENCLOSURE 5.5

' DOSE ASSESSMENT REPORT i EP/0/B/1009/13

{

Duke Power Company Crisis Management Plan Off-Site Dose Repcrt - Catawba Prepared By Date/ Time r , Emergency Drill (Circle One)

Meteorology Vind Speed MPH Wind Direction Degrees from North Vertical Temp. Diff. Degrees C/100ft.

Stability Class (Circle One) ABCDEFE ~

Source Term Time Noble Gas

  • 1-31 es.

Containment Rad. Monitor R/hr. R/hr Containment Sample UCi/ml uCi,mi Unit Vent (Sample or EMF) pC1/ml Curie Release Rate uC1/mi Corresponds to:

Ci/sec Ci/sec LOCA .--

LOCA-through filter ---

Core Damage Core Damage through filter Tube rupture Gas Decay Tank New Euel Old fuel Other j , Dose Projections i

.5 mi 2 mi 5 mi 10 mi 2 hr Dose (rem) based Wbole Body on Containment release Child thyroid

@ ml/hr -

2 hr Dose (rem) based Whole Body-

. ca Unit Vent release Child thyroid

@ cfm 2 hr Dose (rem) based Whole Body I

on Steam release Child thyroid 2 hr Dose (rem) based Whole Body

! on release Child thyroid '

Field Monitcring Data

Location Distance Direction Dose Rate (mrem /hr)

< Contamination (mi) Whole Body Child Thyroid (dpm/100 cm2) 1 Affected Zones 0-2 mi 2-3 mi 5-10 mi 9-10 mi (Circle Zones) - A0 Al B1 Cl D1 El F1 A2 B2 C2 D2 E2 F2 A3 F3 Comments:

XC: Data Analysis Coordinator, Station Health Physicist ' '

~ - . - - 3

l l

/

Form 34731 (10-81) -

(Formerly SPD-10021)

DUKE POWER COMPANY (1) ID No: HP/0/B/1009/14

/ PROCEDURE PREPARATION Change (s) o to PROCESS RECORD 1 Incorporated (2) STATION: carnuba (3) PROCEDURE TITLE: Health Physics Actions Following an Uncontrolled Release of Liouid Radioactive Material (4) PREPARED BY: -

m M. -DATE: '!Jodf~

/

(5) REVIEWED BY: .b o oh DATE: .7-/- $ [

Cross-Disciplinary Review By: N/R: [d , .

M

"""DORARY A***m'At (I? NECESSARY):

By: (SRO) Date: -

By: , , Date:

(7) APPROVED BY: M' Date:

(8) MISCELLANEOUS:

Reviewed / Approved By: Date:

Reviewed / Approved By: Date: ,

O 1

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

. o f~, Fom ISS33 (3-80)

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DUKE POWER COMPANY ALARA EVALUATION CHECKLIST l (1). Station Catawba Unit: 1 2 3 Other: Unit I and 2 (2) Checklist Applicable to: Procedure HP/0/B/1009/14 j (3) ALARA Evaluation l

Check those items belok which were considered applicable during the preparation and review of this document.

i

^

Flushing and draining were used to minimize source - strength and con-tamination levels prior to performing an operation..

Permanent and/or movable shielding was specified for reduction of levels.

Use'of permanent or temporary local exhaust ventilation systems was yy used for control of airborne contamination.

~'

Operation was designed to be completed with the least practicable time spent in the radiation field.

Appropriate tools and equipment were specified for the operation to be performed.

The operation was designed considering the minimum number of people necessary for safe job completion.

e'

}. Remote handling equipment and other special tools were specified to.

reduce external dose.

Contamination - control techniques were specified.

The operation was designed to be conducted in areas of as low an exposure as practicable.

Additional ALARA considerations were:

4 i

l 1

i d

! ALARA Principles were not considered since the procedure did not involve work in a ' radiation area.

~

l (5) Prepared by: L. Date / 3C 9 3 u,) Reviewed by: d A Lp Date ;-/- e

~ _ . ,

i-Form 34634 (4 81) SPD-10012 DUKE POWER COMPANY NUCLEAR SAFETY EVALUATION CHECK LIST (1) STATION: Catawba UNIT: 1 2 3 OTHER: Unit I and 2 -

(2) CHECK LIST APPLICABLE TO: Procedure HP/0/B/1009/14 -

l .(3) SAFETY EVALUATION - PART A i

- The item to which this evaluation is applicable represents

Yes No X A change to the station or' procedures as described in the FSAR; 4

or a test or experiment not described in the FSAR7 4

If the answer to the above is "Yes", attach a detailed description of the item being evaluated and an identification of the affected section(s) of the FSAR.

(4) SAFETY EVALUATION - PART'B Yes No X Will this item require a change to the. station Technical

Specifications?
  • If the answer to the above is "Yes," identify the specification (s) affected

/.~~

and/or attach the applicable pages(s) with the change (s) indicated.

(5) SAFETY EVALUATION - PART C -

i As a result of the item to which this evaluation is applicable:

l Yes No X Will the' probability of an' accident previously evaluated i in the FSAR be increased?

Yes No X Will the consequences of an accident-previously evaluated -

" in the FSAR be increased?

Yes No X May the possibility of an accident which is different '

than any already evaluated in the FSAR be created?

{ Yes No X Will the probability of a malfunction of equipment 1

important to safety previously evaluated in the FSAR be increased?

Yes LNo X Will the consequences of a malfunction of equipment important ' to safety previously evaluated in the FSAR be increased?

Yes No X May the possibility of malfunction of equipment i

important to safety different than any already evaluated .

in the FSAR be created? 4

? Yes- No _ X i Will the margin of safety as defined in the bases to any Technical Specification be reduced?

t; If the answer to any of the preceding is "Yes", an unreviewed safety question is involved. Justify the conclusion that an unreviewed safety #

question is or is not involved. Attach additional pages as necessary.

l (6) PREPARED BY: [4ebvr DATE: /[3O[85*

.m , . / '

(7) REVIEWED BY: ( /l j. [ _

DATE: -

~

-/-IY' l -

(8) Page 1 of 2 4

4

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<  ? age : ci :

HP/0/3/1009/II.

DUKE POWER COMPANY NUCLEAR SAFETY EVALUATION Applicable to: Procedure HP/0/B/1009/14 As this revision only involves a correction of a typographical error and a change of the term " boxcar" to the more common term contamination, it will not require a change to the FSAR or the Technical Specifications and will not involve an unreviewed safety question.

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.) HP/0/B/1009/14 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HEALTH PHYSICS ACTIONS FOLLOWING AN UNCONTROLLED RELEASE OF LIQUID RADI0 ACTIVE MATERIAL 1.0 PURPOSE This procedure describes the methods to be used for calculating the radio-nuclide concentration at area water intakes following an uncontrolled

, release of liquid radioactive material, and the subsequent actions to be-taken when the concentration exceeds Technical Specifications.

2.0 REFERENCES

1 2.1 HP/0/B/1009/04, Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Station 2.2 Control Room Unit Data Book

{ 2.3 10CFR20, Appendix B, Table II, Column 2 4

2.4 .CNS FSAR Sections 2, 11, 12 and 15 g,

?$j:  ;. :C !. ..a_;;_

eps..ficatt::s Sections 3/4.3, 3/4.11 and 5.0-2.6 Letter To Master File CN-1227.00 Dilution Factor - Rock Hill Intake from Design Engineering dated February 23, 1983 2.7 CNS Emergency Plan 3.0 LIMITS AND PRECAUTIONS I

3.1 The full implementation of this procedure should'ba used in emergency situations that could result in the contamination and 1

possible shutdown of area water supply intakes.

3.2 Full implementation of the protective actions in this procedure require station management authorization.

3.3 This procedure is for use under abnormal conditions and results in '

conservative recommendations. Care must be exercised to ensure only appropriate actions are taken. '

3.4 Conservatism exists in the calculations utilized in this procedure '

and includes, but is not limited to:

j -

} 3.4.1 Decay i

t I

-3.4.2 Dilution factor '

3.5 Transit time from CNS to the nearest municipal water intake is reduced from three days to one-half day under extreme meteorological conditions (Ref CNS FSAR 2.4'.12).

- 4

._ ..s -: - _._ _

'> a?' MM: ^ V ' ' ^ ~ " " ~ ~ '

$ o 1

i

/1'. "

HP/0/B/1009/14 Page 2 of 3 3.6 Reporting requirements of Station Directive 2.8.1 and HP/0/B/1009/02 shall be evaluated to ensure that the Shift Supervisor and/or the  !

Licensing Engineer are informed of the requirements.

4.0 PROCEDURE

'4.1 Health' Physics will determine concentration of effluent released from site boundary by the following method (s):

4.1.1 Determine effluent concentration from EMF-49 if possible.

I Concentration may be determin'ed from analysis of sample j . drawn directly from EMF sample tap, if necessary.

l NOTE: Conversion graph for EMF data from CPN to uCi/ml located in Control Room Unit Data Book.

~

4.1.2 Determine effluent concentration from volume and activity if release is made from other than through Waste Liquid

, System, if possible.

j 4.1.3 Collect representative sample from Environmental Sampling -

i Pier (Location Site #A0 1 46) at Station Service Water i i;1 , Discharge ' Canal .and analyze sample for concentration.

i Y'J 4.'1.4 Should utilize most restrictive (highest) concentration from applicable procedure Steps 4.1.1, 4.1.2, 4.1.3 above.

2 4.2 Determine the potential for contamination of area water supplies using Enclosure 5.1 (Transit Time /Radionuclide Concentration Calculations) and sampling data from Health Physics.

4.3 If data indicates that a release made through the Station Service

Water Discharge Canal to Lake Wylie will exceed 10CFR20, Appendix B, Table II, Column 2 limits at affected area water intakes, Health Physics shall recommend the following to the Emergency Coordinator
4.3.1 Request minimum flow at Lake Wylie Hydro Station from System Load Dispatcher (to extend transit time).

4 NOTE: Transit time to Rock Hill water intake is approximately 14 days with NO FLOW through Lake t Wylie Dam,'(based on das leakage rate).

4

4.3.2 Request Field Monitoring Teams (FPfr) to track the release 4

by sampling and evaluation of sample concentrations taken ,

from discharge point at Environmental Sampling Pier

  • (Location Site # A0'1 46), above Lake Wylie Dam (Location Site # B1 4 5),-directly below Lake Wylie Dam (Location
, Site # B1 4 6), and at Rock Hill municipal water intake t

structure (Location Site #C2 7 8), per Ref. 2.1, as deemed

j. necessary '

NOTE: Transit ' time is calculated as three. days under normal meteorological conditions with all units l

in operation'at Lake Wylie Hydro Station.

.. - -_ . --  % .s ~ :.L _ .- - , _ . - , . . . - . - - - . . . - , - - - , - - - , . - - . -

. - y-7.nn.: , , ~:

. r HP/0/B/1009/14 Page 3 of 3 4.3.3 Notify (through the State) the area water supply pumping stations that a release of radioactive materials to Lake Wylie has occurred and that limited protective actions (sampling and analysis) are being taken.

4.3.3.1 In the event the sampling confirms the contam-ination levels at area water intakes will exceed 10CFR20, Appendix B, Table II, Column 2 limits, request (through the state) that area water pumping stations cease operations during ,

the period of _ time contaminated water is passing '

the pumping station intakes.

4.3.4 Request System Load Dispatcher regulate flow through dam f as required.

NOTE: Maximum flow through dam will allow contamination to pass critical areas in least time.

4.4 Discontinue environmental surveillance efforts when concentration (contamination levels) indicate that protective actions are no

. longer appropriate.

5.0 ENCLOSURES 5.1 Transit Time /Radionuclide Concentration Calculation O

3 x

- * ~ ~

.;4;p. j !dg ,

DUKE POWdR COMPA.NT Page 1 of 2 CATAWBA NUCLEAR STATION .

HP/0/B/1009/14 SAMPLE ENCLOSURE 5.1 TRANSIT TIME /RADIONUCLIDE CONCENTRATION CALCULATION DESCRIPTION Transit time (s) and radionuclide concentration (s) for an uncontrolled release of liquid radioactive materials from a Catawba Nuclear Station release point to the municipal (or industrial) water intake structures of Rock Hill, Celanese Fibers Company (Rock Hill), Fort Mill and Springs Mills, Inc. (Fort Mill).

NOTE #1: All municipal or industrial water intake concentration calculations e e based on Rock Hill water intake sampling point unless specified otherwise by Station Health Physicist or Emergency Coordinator.

CNS Discharge Formula Test Water Point Transit Time- Dilution ( 1 ) Formula Criteria Intake (NOTE #2) Factor ft' Required via WL System Conc and Vol Rock Hill 3 days 4 x 10

(dischg header) known #1 other than Cone and Vol Rock Hill 3 days 4 x 10 #2 WL System known via WL System Conc and Vol Rock Hill 3 days 4 x 10

(dischg header) unknown #3 other than Cone and Vol Rock Hill 3 days 4 x 10 #3 WL System unknown NOTE #2: Transit time assumes all units in operation at Lake Wylie Hydro Station.

RR,

' l FORMULAS: #1 -

C,= C, x D x (time (RR, + RRd)

  • d
  1. 2 -

C, = C, x D x Yk

  1. 3 -

C, = C, x D x Vc (see NOTE #3)

Where:

[

C, = Radionuclide concentration at municipal water intake (uci/ml) -

C, = Undiluted discharge point concentration (uCi/ml)

D = dilution factor (4 x 10 1 )

ft' time = taken from WL Release Worksheet (sec) - (time WMT pump is running)

  • l s

4 .w.

+ - - - -

- = ,. 9, . ,,,.,

.=L ,

.[y - ,

. i DUKE POWER COMPANT Page 2 of 2 4 CATAWBA NUCLEAR STATION 1 HP/0/B/1009/14 SAMPLE ENCLOSURE 5.1 4

TRANSIT TIME /RADIONUCLIDE CONCENTRATION CALCULATION

  • d'

,. RR e = effluent release rate (cfs) - (from WL Release Worksheet)

RR d = RL (and RN) flow rate (s) (cfs) _

RR, = dilution variable (no ur.its)

RR d

8 d

Vk = known volume (ft )

V,= 13,268,000 ft8 (discharge canal volume)

Conversion Factors: cfs = (2.22 x 10 ~8 cfs/gpm (Xgpe) ,

a ft' = gal /7.481 NOTE #3: When using formula #3, must assume entire contents of discharge i canal as effluent release and evaluated sample concentration as C, (Undiluted effluent concentration). i o

d 4

e 4

l *s i

d 1

k 4

E a

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f:

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  • O l l:

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t t'

t Form 34731 (10-81) .

(Formerty SPD 100211 d

DUKE PO!ER COMPANY (1) ID Nc: :?/0/3/10: .2 A PROCEDURE PREPARATION Change (s) o to PROCESS RECORD 1 Incorporated ,

(2) STATION: Catauba [

L (3) PROCEDURE TITLE: Uncontrolled Release of Gaseous Radioactive Material .

Other Than Through the Unit Vent E (4) PREPARED BY: 2_bM DATE: //3c /85' (.

(5) TEVIEWED BY:- 77 /} ~ A -

  • DATE: d-/= J 3' -

Cross-Disciplinary Review By: N/R: [,/ O' i

(6) TEMPORARY APPROVAL (IF NECESSARY):

t Ey: (SRO) Date:

By: Date:

[

(7) APPROVED BY: Lv' * ./<

Date: f

// j, (8) MISCEI.IANEOUS: F Reviewed / Approved By: Date:

Reviewed / Approved By: Dite:

t C

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f Y.M *N h jfw ? . " ' ". ] b

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HP/0/3/1009/15 DUKE POWER COMPANY CATAWBA NUCLEAR STATION OFFSITE DOSE PROJECTIONS UNCONTROLLED RELEASE OF GASEOUS RADICAC~:', : :: C.'.: A' OTHER THAN THROUGH THE LWIT VE.NT 1.0 PURPOSE To describe an. approved method for projecting dose commitment from a noble gas or iodine release, other than a unit vent rele' ase, during an emergency.

2.0 REFERENCES

2.1 HP/0/B/1009/06, Alternative Method for Determining Dose Rate Within the Reactor Building i

~ ~

2.2 Variables used in HP/3/B/1009/15, Letter Fi1e Number CN.: 134510 2.3 Reg Guide 1.4  ;

3 2.4 Reg Guide 1.109 -

3.0 LIMITS AND PRECACTIONS ,

3.1 It is assumed that the whole body dose from a release is very small compared to the iodine thyroid dose. Thus, iodine whole body dose is not considered here. ,.L 3.2 Th'is procedure applies to releases made form Catawba Nuclear Station only. Many of the values contained in this procedure are site specific.

l 3.3 This procedure considers all releases to the ground level releases.

3.4 Reporting requirements of Station Directive 2.8.1 and HP/0/B/1009/02 shall be evaluated to ensure that the Shift Supervisor and/or-Licensir.g Engineer are informed of the requirements.

t 4.0 PRCCEDURE 4.1 Acquire the following information and record on sample Enclosure 3.1.

, NOTE: Should site meteorological data be unavailable, obtain i

wind speed and wind direction from the National Weather i

Service (United States Government'- National Oceanic &

Atmospheric Administration).

i NOTE: If appropriate, obtain advance meteorological data,to calculate dosed due to changing meteorological conditiens.

l l

EP/0/3/1009/15 Page 2 of a 4.1.1 Reactor Unit, date and time of reactor trip.

4.1.2 Lower tower wind speed (mph).

4.1.3 Tower wind direction in degrees frem . orth (North = 0').

4.1.4 Temperature gradient (AT*C).

4.1.3 Radiation Monitor (EMF 53A or 533) reading (R/hr) or calculated per Reference 2.1.

4.1.6 Date and time of calculations.

4.2 Determine the Containment Building leakage rate (LR) and record it on sample Enclosure 5.1. .

4.2.1 LR (ml/hr) is the total leak rate for the containment which is one of the following:

4.2.1.1 a "best guess' assumption.

4.2.1.2 the measured leak rate where suitable means are Available; 4.2.1.3 The design leakage rate (LRDLR) which is determined by:

LR DLR " #***'""*"* *** '818 " ** *"***#'*

to

= 2.83 x 10 ml

  • 0.0023
  • day day 24 hr 6

2.95 x 10 ml/hr 4.3 Determine the X/Q values for each point of interest downwind and record on sample Enclosure 5.1.

If no points have been requested, use the .5, 2, 5 and 10 mila values.

4.3.1 Locate the relative two-hour downwind concentratien value (CH) for each point frem sample Enclosure 5.2 and record onto sample Enclosure 5.1.

4.3.2 C nver: :h2sa values to X/Q by, X/Q = CH (MPH-Sec/m8 )

Tower Wind Speed (MPH) 4.4 Determine the potential whole body dose from submersien in a cloud of noble gas and record on sample Enclosure 5.1.

4.4.1 Calculate the whole body two (2) hour dose commitment, Dg =D

  • ADC
  • LR
  • X/Q
  • Ugg i

1

, e i 4

HP/0/B/iOO9/15 Page 3 of 4 Where, Dg = Whole body two (2) hour dose commitmer.: ( r em'-

DR3 = Monitor dose rate (R/hr)

ADC = Average Decay constant for noble gases =

2.2622E-2 uCi

  • MeV - hr*- --

ml

  • d
  • R LR = Containment leakage rate in al/hr X/Q = dispersion
  • factor in sec/m*

U * ** *" **

  • NG *
  • 2 (100 ergs /g-rad) (1.2E-3g/ca') (1E6cm'/m*)

' ' ~

= 2.5E-7 ' rad *m'ad

~

sec*uCi=MeV 5.7E 9 hr 8 'm'* rad = ADC

  • U NG m1*R*sec c a.5 Determine the potential thyroid dose from uptake of radioiodine and record on sample Enclosure 5.1.

4.5.1 Locate the time plus one (1) hour after trip on Enclosure 5.3 and record the corresponding Decay Constant on Enclosure 5.1.

4.5.2 Calculate a child's thyroid two (2) hour dose commitment using time plus one (1) hour, DT = DR3

  • LR
  • X/Q
  • U g Where, DT = thyroid :co (2) hour dose commitment.(rem)

DR g = monitor dose rate (R/hr) ,

t.Ci

  • mremahr8 DC = Decay Constant in a1
  • pCi
  • R for time plus '

one (1) hour (see sample Enclosure 5.3)

LR = Leak rate in ml/hr X/Q dispersion in sec/m 8 Ug = breathing rate for child times uCi to pCi conversien ftetor 8

(1.17E-4 m /sec)

  • 1E3 oCi-rea = 1.17E-1 m 8-oCi-rem UCi-aren Sec-pCi-arem

57/0/3/1009/15 Page a of 4 4.6 Determina the potentially affec:ed area c:ing Enclosure 5.4 Recor:

the affected zones on Enclosure 5.5.

4.7 Complete sample Enclosure -5.5 and submit it to the Data Analysis Coordinator. Include any comments pertinent to the evaluati n of offsite hanards.

5.0 ENCLOSURES 5.1 Sample Projected Cffsite Dose Released Fr m Contain=ent 5.2 Sample Table of Two Hour Relative Cencentration Factors (C )

H 5.3 Sample Table of Iodine and Noble Decay Constant (DC) 5.e Sample of Evaluation of Plume Location 5.5 Sample Dose Assessment Report 5.6 Estimation of Containment Leak Rate b

o 4

e e

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

, . . . . . Page 1 of 2 ENCLOSURE 5.1 EP/D/3/1009/13 -

~~

PROJECTED OFFSITE DOSE RELEASED FROM COSTAISHENT 4

. Unit Date/ Time of Reacter Trio /

1 METEOROLOGICAL DATA

1. . Lower Tower wind speed sph e .. - -
2. Upper Tower wind direction *

.s .e .

3. Temperature gradient (AT) _ *C MONITOR DATA i

4

1. EMF 53A or 33B/ Survey Inst. # , DR = --

R/hr 3

. (Circle One)

{ NOTE: If containment monitor information is not use.tble, refer to 4

Reference 2.1.

r ,

, DOSE CALCULATION DATE/ TIME i

1. LR ml/hr
2. Cy@ mi. = , t/Q = sa:lm 8 CH@ mi. = , X/Q = sec/m 8

, mi. = , X/Q = sec/m 8 CH@

CH@ mi. = , X/Q = .sec/m 8 A. Whole Body 2 hr. Jose projection from noble gases: ,

by Dg3 = DR3 'LR * .X/Q

  • 5.7E-9, 4

Miles Out D.. 2 hr Desa Commitment t' rem as-P 4 me f

I t

i i

I i

4 I . - _ y - ,- ,, , , . , . -

, . , , . , - . y ,wws-

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4 Page 2 of 2 ENCLOSURE 5.1 HP/0/B/1009/15 PROJECTED OFFSITE DOSE RELEASED yROM CONTAIh?!EST B. Thyroid 2 hr. dose projection frem iodine:

DC ,

by DT = DR3

  • LR
  • X/Q * (1.17E-1),

Miles Out DT 2 hr Dose Committment frem) i i

DEFINITIONS fWB= whole body 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose commitme.nt from noble gases (rem)

D T= thyroid 2 hr dose commitment from iodine (rem)

LR = containment leakage rate (ml/hr) ~

X/Q =- " Chi over-Q" is downwind concentration correction factor (sec/m8 )

) .

C =

H 2 hr rela'ive t downwind contentration (X/Q

  • MPH).

DC = Decay constant from Enclosure 5.3 DR = dose rates at the containment monitor (R/hr) 3 i

.e- /

6 ow b

4 +

4 b i i '

=s e v. , _.- --4 --

~

I Picl 05tfitt 's . 2 IIP / 0/II/1009/ I's

  • IWU-IDtift stiI ALIVE ColectGiltAlinN I ACIUltS (C ]

11

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

I) < .6 A l.4f-5 1.2E-6 5.9F- "

8e.lE-T 3.2E-T  ?.5E-1 2.0E-l 1. 91 - T l.81-1 1.61-1 1.5[-1

?) .6 in */S B-c 1.5E-4 4.5E-5 1.3E-5 6. :-6 3.9E-6  ?.7E-6 f.9E-6 1. 8el -6 f . lf -6 8.30-1 f.8E-T

3) -se.4 tr4 -fr. ?' D 3.RL-4 1. 4 E-'s r.9E-5 e 2.7E-5 f.7E-5 1.2E-5 9.2E-6 7.3r-6 6 nI-6 5.Or-6 8s.30-6

. _ _ . _ . . . . ~ . _

43 -o.I lw %4 r 6. 9 E-te 2.5E-4 9.60-5 5.5E-5 3.5E-3 P.5E-5 2.0E-5 1. 6[. 5 1.3E-5 f.IE-5 9. FI-6 _

5) +.5 to *).? I 1.lE-3 5. l E-8s  ?.00 te 1. 2 E-8s 8.2E-5 6.3E-5 5.lE-5 4.31-5 3.3E-3
3. n 8.-5 3.0E-5
6) > I.2 C 3.8E-3 1.lE-3 4.3E-4 2.7E-4 2.0E-4 1.7E-4 1.3E-4 1.?[-4 n.60-5 T.80-5 T.30-5 f rom other sources or er*teorological data (Section 4.1) use the wind speed and time or day to deteernine which row or C valves to use:

il ,

I I 8'e_o r_ Day W13d_5 peed Row ] _.

10:00 A.H. -

4:1HI P.M. N/A 3 4:00 P.H. -

10:00 A.M. > 15 Hl'Il 4 4:00 P.M. - 10:00 A.M. $ IS MPil 6 l

4 t

. ENCLOSURE 5.0 FACI 1 or 1 TAELE ICDINC & NOBLE DECAY CONSTMT(DC) 0 - 490 HRS HP/0/B/1009/15 HOUR DC HOUR DC HOUR DC HOUR UC HOUR i. C G 2. I:99E-05 100 5.6125E-04 200 6.8707E-04 300 7.443DC-04 400 7.~4199C 04 2 5.7902E.-05 102 5.6595E-04 202 6.0925E-04 302 7.4537E-04 '! O 2 7. v i '. 7C+'

4 8.1506E-O'; 204 5.7050E-04 204 6.9060E-04 304 7.4636E-04 404 7. ?2ZC- 04 6 J . 0296fi-04 106 5.7492E -04 '206 6.9194E-04 306 /.di735E 04 406 7.va73E-04 0 1 2295E-09 100 5.7920E-04 200 6.9326E-04 309 7.4833E-04 400 7.0460E-04 10 3 4170E-04 110 5.8335E-04 210 6.9457E-04 310 7.4932C-04 410 7.V5'luli-04 12 1 5'J23E-04 a ll' 5.3737E-04 212 6.9506E-04 312 7.5029E-04 412 7. W OGC- 0" 14 1.7591E-04 114 5.9127E-04 214 6.9714E-04 314 7.5127E-Oet 414 7.v722C-04 16 1 91L9E-04 116 5.9504E-04 216 6.9040E-04 316 7.5224E-Del 410 7. "'? 0 9E- 0 ".

10 2 0648E-04 110 5.9670E-04 218 6.9965E-04 310 7.5321E-04 'i10 /. .o6Cm. "

20 2 2071E-04 220 6.0225E-04 220 7.0009E-04 320 7.5410E 04 420 7.'N22E-Oa

. 2 L.3439E-04 122 6.0569E- 04 222 7. 0212E- 04 322 7.551LD 0'f ! 2 2 0 . w ot W. +

24 2.47S7E-04 :24 4. 0903E-04 224 7.0330E-04 324 7.5611E- 04 424 5."iCSC 04 26 2.6034E-04 126 6.1226E-04 226 7.0454E-04"326 7.5707tCD4'l26 U. C240E -04 20 2. 7272E-04 120 6.1540E-04 228 7. 0574E-04 32G 7.5003E-04 #:20 E. 3026E-04 30 2.0475E-04 130 6.1844E-04 230 7.0692E-04 330 7.589?E-04 '!30 B.9dJ2E-0<

32 2. 9o45Er04 ? 32 6.2140E-04 232 7. 0810E-04 332 7.5994E--04 432 G.0197E-04 34 3.0704E-04 134 6.2426E-04 234 7.0926E-04 304 7.6009E-04 434 0.0033E-04

  • ~ .6 0.1993E-04 136 6.2705E-04 236 7.1042E-04 336 7.4104E-04 436 U. :!660E-u d 33 3.2975E-04 130 6.2'775E-04 238 7.1157E-04 333 7.6279E-04 43C G.0733E-ca 90 3.4029E-04 140 6.323GE-04 240 7.1272E-04 340 7.6373E-04 440 E.UC07C-04 42 3.505DE-04 142 6.3493E-04 242 7.1385E-0'i 342 7.6467E-O't 't*:2 E . W22E--04 44 ~ . 6062E-04 144 6.3741E-04 244 7.199BE-04 344 7.6561E-04 444 8.10162-04 46 3.70'tLE.-04 146 6.2933C-04 246 7.1610E-09 346 7.6655E-04 446 0.1070E-04 48 0. 7999E-04 149 4.4219E-04 248 7.1721E-04 340 7.6749E- 04 4'!8 0.1179E -04 50 3.DY33E-04 150 6.4447E-04 250 7.1032E-04 350 7.6842E-04 '150 D . : 2 SC!i-04 52 a 2. 9246E-04 152 6.di670E-04 252 7.1942E-04 052 7.6935E-04 452 e. . " 2C-04

' e. 0730E-04 154 6.4907E-04 254 7. ~:051E-04 354 7.702GE-04 '154 0.1 '*2EE-U*

56 4.1609E-04 156 6.5099E-04 256 7.2160E-04 356 7.7120E-04 456 C.150?E-9*

50 9.2460E-04 158 6 5306E-04 258 7.2269E-04 359 7.7213E-04 4S3 E.1'~.92C-C-90 4.3291E-04 160 6.550BC-04 260 7.2376E-04 360 7.73052- 04 460 E.1675E-0 62 9.4103E-04 162 6.5705E-04 262 7.2493E-04 362 7.7397E-04 462 C. 27E-e-6f 4.40Y6E-04 164 6.5897E-04 264 7.2590E-04 364 7.7409E- 04 464 E. ; e40E-c' ~

66 4.5669E-04 166 6.6085E-04 266 7.2696E-04 366 7.75G1E-04 966 E. ' ' 23E 60 9 6425E-O'l '68 6.6269E-04 26E 7.2002E-01 368 7.7672E-04 463 E. 4C.0 70 ':.7 61E-04 170 6.6450E-04 270 7.2907E-04 37 0 7.7763C-04 VO U.2:0/E-0. ,

72 ~. 7979E-04 172 6 6626E-04 272 7.3012E-04 372 7.7854E-0't 472 E.'.169E-Oe 74 4.057VE-04 174 6.679?E-04 274 7.3116E-04 374 7.7945E- 04 <!?4 e.2250E-04 .

76 . 9262E 04 176 4.6969E-04 276 7.3220E-04 376 7.0036E- 0'i 476 C.2202C-0

70 9.9926E-04 170 6.7135E-04 278 7.3323E-04 373 7.0126E-04 47C 3.2';1*3E-04 30 5.0573E-04 1G0 6.7293E-04 200 7.3427E-04 300 7.8217E-04 400 e.2195E-Oe; C2 C.1202E-04 182 6.745SE-04 282 7.3529E-O'i 302 7.3307E-04 4G2 0.2':.76E-0*

34 5 1015E-04 IE4 4.7615E-04 234 7.3632E-04 3D4 7.C397E-04 48'i S.2657C-Oe ~

Us 5.2810E-04 186 6.7770E-04 236 7.3734E-0'i 306 7.9406C-0 t 4 8 6 U . :. ".". .'E-- d.

du 5. 2"E'.'E-04 133 4.7922E-04 298 7.3935E-04 000 7.05*6C-04 480 E.2318E-0'2 "O U.3*'.51E-04 190 6.8072E-04 290 7.3936E-04 3YO 7.0665E-04 490 8. J"E2-04 92 5.4097E-04 I?2 6.3219E-04 292 7.4037E-O'; 392 7.8754E-O'l 492 2. 2'v7an-0'4 l 91 S.4607E-04 194 6.8369E-04 294 7. 4133E-04 394 /.3842E-04 494 C. MUE -Od

6

5. 51 ':2E-04 196 6.0507E-04 296 7.423GE- 04 396 7.3932C- 04 496 C.0103E- 0*i 98 5.5691E -04 190 ' L.864BE-04 290 7.4338E--04 393 7.?U20E-04 ':90 C.021GE -04 r

Page 1 of 3 DUKE TOWER COMPANY CATAWBA NUCLEAR STATICN ENCLOSURE 5.4 HP/0/B/1009/15 EVALCATION OF PLUME LOCATICN 5.4.1. Acquire the following informatien from sample Enclosure 5.1 and record on sample Enclosure 5.5.

5.4.1.1 Wind direction in degrees from North j 5.4.1.2 Wind'spe'ed (=ph) l l

AT (*C) 5.4.1.3 5.4.1.4 Stability class 5.4.1.5 Thyroid and . hole body dose 5.4.2/ Determine the affected zones, based on wind direction and wind speed, with the following tables:

/

Table 3.1 0-2 Mile Affected Zones i

Wind Direction Affected Zones 0* - 360* A0 Ts51e 3.2 2-! Mile .'.ffected Zenes Wind Speed 5 5 mph _

Wind Direction Affected Zenes Wind Direction Affected 2cnes 0* - 360* A1,31 C1,D1.E1.F1 0.1* - 20' C1, D1

. 22.1* - 73* C1, D1, E1 .

73.1* - 10S' C1,D1,El,F1 108.1* - 120* D1, El, F1 120.1* - 159' El, F1 159.1* - 207* El, F1, Al 207.1* - 247' F1, A1, B1 -

247.1* - 265* A1, B1 265.1* - 298* A1, B1, C1 298.1* - 338' B1, C1 338.1* - 360* B1, C1, D1

<l -

.c Paze 2 of 3 DUKE PCWER C2.MPA.~.*

CATAWBA NUCLEAR STATION ENCLOSURE 5.4 KP/0/B/1009/15 EVALUATION OF PLC.ME LOCATION Table 3.3 5-10 Mile Affected Zones

-Vind Direction Affected Zones 0.1* - 27' C2, D2 27.1* - 69* C2, D2, E2 69.1* - 95* D2, E2, F2 95.1* - 132' D2, 22, F2, F3 132.1* - 144' E2, F2, F3 144.1* - 160* E2, F2, F3, A2 160.1* - 201* F2,-F3, A2 -

201.1* - 229" F2, F3, A2, B2 229.1* - 249' F3, A2, B2 249.1* - 259' A2, A3, B2 259.1* - 290* A2, A3, B2, C2 290.1* - 304* A3, B2, C2 304.1* - 333* B2, C2 (iw' 333.1* - 360*

  • B2, C2, D2 5.4.3 Determine the protective actica guides (PAG) based on the calcu-lated dose (s) on Sample Enclosure 3.1 and the following information:

5.4.3.1 For doses:

< 1 Rem Whole Body or, .

o

< 5 Rem Thyroid Recommend no action.

5.4.3.2 For doses: ,

1-5 Rem Whole Body or, j 5-25 Rem Thyroid .

Recommend evacuation of children and pregnant women and sheltering of remainder cf personnel in the affected area.

%lh l

l i

    • w

fi Page 3 cf 3 DUKE POWER CCMPANY CATAWBA NUCLEAR STATION ENCLOSURE 5.4 HP/0/B/1009/15 EVALUATION OF PLUME LOCATION 5.4.3.3 For deses:

> 3 Rem Whole Body or,

> 25 Rem Thyroid Recommend Evacuation of Population in Affected Area.

5 . 4 . /. . Record only the affected :enes requirit ; protective action on sample Enclosure 5.5 along with the recommende' p.etective action. --

4

. m'

- Qy

,4' d

0 4 m

-s 9

r' . ._. _ _ . _ __

, p..; 7 _ g. _

l l

, 1 l

l DUKE POWER COMPANY Page 1 of 1 CATAWBA NUCLEAR STATION HP/0/B/1009/15 l ENCLOSURE 5.5 l DOSE ASSESSMENT REPORT l

Duke Power Crisis Company Msnagement Plan Off-Site Dese Report -

CATAWBA i Prepared By Date/ Time / Emergency Drill (circle onej Meteorology Wind Speed MPH Wind Direction _

degrees from North Vertical Temp. Diff. degrees C/100 ft.

Stability Class (circle one) A B C D E F G Source Term Time Noble Gas I-131 equivalent

~

Containment Rad. Monitor R/hr R/hr Containment Sample uCi/mi uC1,r1 Unit Vent (Sample of EMF) uCi/ml uCile.

Curie Release Kate Ci/sec Ci/sec ,

Corresponds to: . LOCA - -

- LCCA through filter ---

Core damage (4

Core damage through filter

, Tube rupture Gas Decay Tank New fuel Old fuel Other Dose Projections

.5 mi 2 mi 5 mi 10 mi

[j.

2hr Dose (rem) based Whole Body on Containment release Child thyroid

@ ml/hr 2hr Dose (rem) based Whole Body on Uni Vent release Child thyroid i @ cfm 2hr Dose (rem) based Whole Body on Steam release Child thyroid '

o 2hr Dese(rem) based Whole Body on release Child thyroid [

@~

=Fie:d Monitoring Data j Location Distance Direction Dose Rate (mrem /hr) Contamination 2

(mi) 'Whole body Child thyroid (dpm/100 cm )

Affected Zones 0-2 mi 2-5 mi 5-10 mi 9-10 mi (circle :enes) A0 Al B1 C1 D1 El F1 A2 B2 C2 D2 E2 F1

......;...............................................................................A3 F3 COMMENTS:

l ,

.xc: Data Analysis Coordinator, Station Health Physicist D

'"'{ _, - - - - =r ' ' - ' ' ~

is .s & .

t

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e . .. . . . 1 7.6.... ENCLOSURE 5.6 i s...... page 1 of 5

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Form 34731 (10-81)

(Formerly SPD 10021)

DUKE POWER COMPANY (1) ID No: OP/0/A/6200/21 PROCEDURE PREPARATION Change (s) 2 to PROCESS RECORD 3 Incorporated Revision #2 (2) STATION: Catawba (3) PROCEDURE TITLE: Operating Procedure for the Post Accident Liquid Sanpling Systems (4) PREPARED BY: /j [ u der DATE:  % //.r. <

(5) REVIEWED BY: /?u/d DATE: .7 //5/8f ,

Cross-Disciplinary Review By: [Lt//l (6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: a / Date: ,

(7) APPROVED BY:

Date: 1 /E d5 (8) MISCELLANEOUS:

Re D "-~~aved By: Date:

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OP/0/A/6200/21 DUKE P0h*ER COMPANY CATAWBA NUCLEAR STATION OPERATING PROCEDURE FOR THE POST ACCIDENT LIQUID SAMPLING SYSTEMS ,

1.0 PURPOSE The purpose of the Post Accident Liquid Sampling System is to provide a method for promptly obtaining reactor coolant samples under a nuclear reactor accident condition.

Samples acquired during accident conditions (normal sample points are not usable due to high radiation conditions) will aid in the evaluation of information related to: 1

1) The extent of core damage which has occurred. i j
2) Types and quantities of fission products released to containment liquid.
3) Reactor Coolant Chemistry and Radiochemistry.

2.0 LIMITS AND PRECAUTIONS 2.1 In an accident situation the. decision to collect a post-accident sample will originate from the Technical Support Center. The management involved in this decision should take two factors into consideration in making this decision:

(a) Has the situation stabilized to a degree so as to minimize 1 the risk to individuals involved in the sampling?

(b) From the present information available, has the system stabilized to a degree that a represent' tive a sample may be qbtained?

2.2

The PALS panel should only be used under the following circumstances

(a) Caution: 1/2 EMF 48 must have flow for readings to be valid.

The Reactor Coolant System (NC) Gross Specific Activity is expected to be or is known to be greater than

-200 DCi/ml. This corresponds to a reading on 1/2 EMF 48 of equel to or greater than 1.64 x 108 counts per minute.

(Correlation factor from HP/0/B/1000/10 is 1.22 x 10~8 (yCi/ml)(CPM))

~'

(b) Primary Systems Sample Sinks la and 18 ars inaccessible due to the radiation levels or for other idectified reasons.

i OP/0/A/6200/21 Page 2 of 16

(c) The Station Chemist or his designee has requested that the PALS panel be put in service.

(d) The PALS panel is being run for monthly operational verification, maintenance, or training purposes.

(e) When use of the normal Primary Sample systems will create a Radiation Exposure problem in the NM Lab.

2.3 The undiluted sample volume is 5.2 al and the final dilution volume shall be controlled between 250-3500 al.

2.4 Health Physics personnel must perform continuous radiation j

monitoring during sampling at the liquid sample or control panel.

During an accident situation, Health Physics personnel from the OSC must monitor all personnel entering the Auxiliary Building.

2.5 When handling radioactive samples, good laboratory practices are essential to prevent radioactive contamination of personnel, equipment, and physical structures. Reference applicable SWRP(s) and RWP(s).

2.6 , Individuals that have been trained on this procedure are qualified to use this procedure. Individuals shall be trained at a minimum

,n frequency of (6) months.

V

  • 2.7 Due to the nature of this procedure, a Working Copy shall be used to ensure compliance.

2.8 Do not leave the selector knob in " Grab Sample", Position 4 longer than is required to complete all the necessary steps of that position.

3.0 PANEL PREPARATION .

l 3.1 Initial Conditions 3.1.1 In order to expedite the process, the Primary Supervisor or his designee should send two Chemistry Technicians to collect the sample.

The technicians should be chosen taking into consideration ,

the following:

(a) Being qualified on the PALS procedure (b) Being respiratory qualified ,'

, (c) Age (d) Accumulated Exposure (e) Sex 4

(f) Physical Strength Their responsibilities are outlined below:

\

I l

l

OP/0/A/6200/21 Page 3 of 16 i:v v cv Technician #1 (a) Completes the Initial Conditions Checklist Enclosure 8.1 from OP/0/A/6200/21 at the TSC and returns the checklist to Technician #2.

(b) Informs Health Physics at the OSC that he/she will be traveling to the Hot Lab.

(c) Dresses out as necessary.

(d) Travels to the Hot Lab and prepares for the analyses.

(e) Transports samples from the NM Lab to the Hot Lab, if necessary.

(f) Analyzes the samples.

(g) Reports results by phone to the Station Chemist at the TSC and returns to the OSC.

(h) Transports the completed data sheet to the Station Chemist at the TSC.

Technician #2 (a) Obtains the PALS panel keys. (Location: Secondary Supervisor's Office Key Box or Cold Lab Key Box)

(b) Dresses out as directed by Health Physics at the OSC.

(c) Health Physics plans out a path to be taken to the NM .

Lab, Hot Lab, Count Room and to exit the Auxiliary F; Building.

(d) Travels to the NM Lab and uses the PALS to collect liquid and gas samples.

(e) Transports the samples to the Hot Lab.

(f) Assists La the analysis of samples, if necessary.

(g) Reports results by phone to the Station Chemist at the TSC and returns to the OSC.

3.1.2 (Technician #1) - Complete the Initial Conditions Checklist j

(Enclosure 8.1) at the TSC and return it to Technician #2 at the OSC.

3.1.3 (Technician #1) - Inform Health Physics at the OSC of your plans to travel to'the Hot Lab. Inform Health Physics that travel to the outside east backside of the Auxiliary Building may be required in order to calibrate

, the Gas Chromatograph. Also, inform them that you may transport the sample from the NM Lab to the Hot Lab. '

Dress out as required _by Health Physics. The Hot Lab may I

be locked so bring the key.

3.1.4 (Technician #1) - In the Hot Lab, prepare for the sample J, analyses required in Section 7.0 of OP/0/A/6200/21. E' 3.1.S (Technician #2) - Obtain the PALS panel keys from .he Secondary Supervisor's office Key Box or the Cold Lab n 0 key box.

E

- ,- r<-

1 OP/0/A/6200/21 Page 4 of 16

~~ i Lv 3.1.6 (Technician #2) - Report to the OSC and inform Health  !

Physics of plans to obtain a post-accident liquid sample. l Dress out as required by Health Physics. Health Physics I personnel will decide the route to be taken to the PALS  !

panel, the route to carry sample to the Hot Lab and Count  !

Room, and the axit route back to the OSC. They will also l address stay times (1-2 hours at the PALS Control Panal) and protective radiological dress and equipment. A Health Physics technician must be with any Chemistry personnel s entering the Auxiliary Building at all times. Remember:

The buddy system is in effect.

3.1.7 (Technician #2) , Travel to the NM lab with Health Physics coverage to collect a sample using the PALS panel.

Remember to bring the required equipment listed on Enclosure 8.1, Part III.

3.2 Control Panel Preparation (Technician #2 - 543' Elev. NM Sample Room) 3.2.1 Close the following valves: Unit 1 Unit 2 (Omit during periodic testing)

NC Hot Leg Sepl Hdr to Radiation INM29 2NM29 Monitor

( NC Not Leg Sample HX 1A Dutlet INM264 2NM264 NC Hot Leg Sample HX IB Outlet INM278 2NM278 ND Sepl HX Outlet INM265 2NM265 3.2.2 Open the following Operations valves: Unit 1 Unit 2 Post Accident Liquid Sample

,_ Panel Hx Inlet 1KCA8 2KCA8 Post /.ccident Liquid Sample Panel Hx Dutlet IKCA10 2KCA10 3.2.3 Open 1NM462 (2NM462), PASP Deserator Tank Inlet.

3.2.4 Call the Control Room and obtain the official time on the Control Room clocks. Set the clock near the PALS panel to the correct time.

1 3.2.5 Contact the Control Room and have them open the appropriate valve (s) listed below to obtain the desired sample.

Reference Enclosure 8.1, Part 1(b).

(Omit during periodic testing)

, NC Hot Les A Unit 1 Unit 2 i-Hot Les Supl Hdr Cont Isol. INM26B 2NM26B ,:

Hot Leg A Sepl Cont. Isol. INM22A 2NM22A 4

- - - - - - - ,- v < , - - ,~

p. . .

OP/0/A/6200/21

. Page 5 of 16 NC Hot Les C l

l Hot Leg Sepl Hdr Cont. Isol. INM26B 2NM26B Hot Leg C Sep1 Cont. Isol. INM25A 2NM25A ND Pump 1A Discharge ND Pump la Disch Sep1 Line Isol. INM39 2NM39 ND Pump 1B Discharge -

ND Pump IB Disch Sepl Line Isol. INM40 2NM40 3.2.6 Turn the position selector knob to " RESET" position. Place the key in the keylock power switch and turn to the right.

(" Sample Position"). Press " Reset" button, 3.2.7 Place the toggle switch for the dilution water flow totalizer to "0N".

3.2.8 Place the toggle switch for the radiation monitor to "0N".

Turn the scale switch to " BAT" to check the battery. The needle should travel to full scale. Turn the scale switch to "mR/ hour". The " Rem / hour" scale may be used if readings are off the scale. If the radiation monitor is not functional, rely on Health Physics surveys to determine access to the sample panels.

3.2.9 Push in the pH probe "Stindardize" knob.

3.2.10 Select the system to be sampled with the system selector -

RX COOLANT (refers to NC Hot Leg), RX SUMP (refers to ND Pump Discharge).

3.2.11 Verify that the pH 6.86 buffer solution has been changed within the last 30 days by referencing Enclosure 6.8 from OP/0/A/6200/11. This enclosure is located in a notebook in the PALS drawer.

3.2.12 Jonnect the PALS nitrogren cylinder to the PALS by connecting the quick disconnect to the N SUPPLY 2

line.

Open the cylinder valve and set the pressure regulator to 110 psig.

3.2.13 Flush (Position 6) 3.2.13.1 Turn the SELECTOR RNOB TO " Flush", Position 6.

3.2.13.2 Press the " SELECTION POWER-ACTIVATE" button.

3.2.13.3 Press the " FLUSH STEP" button momentarily and wait 1 minute. The first flush light should i

t be lit. (Gas Tank).

~

OP/0/A/6200/21 Page 6 of 16 3.2.13.4 Press the " FLUSH STEP" button momentarily and

~

i wait for 2 minutes. Second flush light should be lit. (Probes) 3.2.13.5 Press the " FLUSH STEP" button momentarily and a wait 4 minutes. Third flush light should be lit. (Dilution Tank) 3.2.13.6 Press the " FLUSH STEP" button momentarily and wait 1 minute. Fourth flush light should be lit. (Liquid Tank) 3.2.13.7 Press the " FLUSH S1TP" button momentarily. This '

terminates tne flushing cycles and the " COMPLETE" '

light turns on.

3.2.13.8 Turn the selector knob to " DRAIN", Position 7.

3.2.14 Drain (Position 7)

,  ?

3.2.14.1 Press the " SELECTION POWER-ACTIVATE" button.

3.2.14.2 '

Press the " DRAIN STEP" button momentarily and wait 4 minutes. First drain light should be h lit. (Dilution Tank). .

3.2.14.3 Press the " DRAIN STEP" button momentarily and wait 1 minute. The second drain light should be lit. (Gas Line) 3.2.14.4 Press the " DRAIN STEP" button momentarily and wait 1 minutes. The third drain light should be lit. (Gas Tank) 3.2.14.5 Press the " DRAIN STEP" button momentarily and '

wait 1 minute. The fourth drain light should be -l lit. (Probe refill and system vent). I 1

3.2.14.6 Press the " DRAIN STEP" button momentarily. This

-i l

terminates the' draining cycles and the " COMPLETE" light is illuminated.

4.0 PANEL OPERATION (Technician #2) 4.1 Initial Conditions 4.1.1 Section 3.0 is complete with the Enclosure 8.1 signed off. >

4.2 Panel Prep (Position 1) 4.2.1 Turn the selector knob to the " PANEL PREP" position.

4 4.2.2 Press the " SELECTION POWER - ACTIVATE" button.

l

.4.2.3 Press the " PURGE" button, hold for 30 seconds and release.

l

. _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _ _ _ . _ _ _ =

. o 7

OP/0/A/6200/21 Page 7 of 16 4.2.4 Pressthe" DRAIN"Suttonandholdfor 30 seconds then release.

4.2.5 Press the " CALIBRATE" button and hold until the pH meter stabilizes.

4.2.6 Adjust the pH meter to the known pH of the standard.

4.2.7 Press the " PURGE" button for 30 seconds and then release.

4.2.8 Press the " FLUSH" button and hold until the pH meter stabilizes (1 to 3 minutes)-(pH of domineralized water) then release.

4.2.9 Press the " PURGE" button for 30 seconds and release.

4.2.10 Press the " DRAIN" button for 30 seconds and release.

4.2.11 Record the radiation monitor reading on Enclosure 8.2.

(Background) 4.2.12 Turn the selector knob to " SAMPLE", Position 2.

4.3 Sample (Position 2) 4.3.1 Press the " SELECTION POWER - ACTIVATE" button. Record the

' Time Sample Purged Started' on Enclosure 8.2. Verify a [.

flow rate of 0.3-1GPM on 1NMFT5430 Sample Purge Flow i Indicator. (For Periodic Testing, purge for five minutes .

before proceeding.) Refer to Enclosure 8.7 Step 6 for proper purge times in an accident situation.

4.3.2 If TC1 goes above 50*C, turn the selector knob to " Reset" and press the " Reset" button. Call the Primary Supervisor or his designee. At the completion of the purge time, record the radiation reading on Enclosure 8.2.

4.3.3 Press the " PRESSURIZE" button momentarily. When the pressure stabilizes record the reading on Enclosure 8.2.

Record this time as the " Sample Trap Time" ozi Enclosure 8.2.

4.3.4 Press the " TRAP" button momentarily.

4.3.5 Turn the selector knob tt. IPRESSURIZATION AND GAS STRIPPING", Position 3.

4.4 Depressurization and Gas Stripping (Position 3) .

4.4.1 Verify that the vacuum gauge on the control panel shows at least 25 inches mercury.

4.4.2 Press the " SELECTION POWER-ACTIVATE" button. Wait at least 60 seconds and then verify the Incoming Sample Pressure gauge reads less than 400 psig pressure.

_. . .,r. ,-y- -- ,- v

. . - . _ - - . _ _. ___ y

OP/0/A/6200/21 -

Page 8 of 16 4.4.3 Pressthe" GASS $IPPINGSTART"buttonmomentarilybeneath the water totalizer and monitor the vacuum gauge. Press the " GAS STRIPPING STOP" button momentarily when the ~

vacuum gauge needle reads + 15 i 1 inch mercury. If 11 inch is not achieved, a new stripped gas sample will need to be taken (i.e.) start from Section 4.2. _

4.4.4 Turn the selector knob to " GRAB SAMPLE", Position 4.

4.5 Grab Sample (Position 4) f 4.5.1 Press the " SELECTION POWER-ACTIVATE" button.

4.5.2 Press the " GRAB ML" button momentarily. Wait 1 minute.

4.5.3 Preset the dilution water FLOW TOTALIZER to 02500 (for testing). In an accident situation, refer to the Station Chemist's Recommended dilution volumer Enclosure 8.1, '

Part IV. Press the " RESET" on the flow totalizar button. "

Press the " START" button and let the dilution continue to completion. Record the flow totalizer setting on Enclosure 8.2 ~

4.5.4 Press the " MIXING" button and hold for 10 seconds.

i 4.5.5 Press the " GRAB SAMPLE pH" button, momentarily. Allow the meter to stabilize. ,

4.5.6 Record the pH reading on Enclosure 8.2.

4.5.7 Press the " GAS SAMPLE - TRAP OPEN" button momentarily. -

Wait 10 seconds. ^

4.5.8  :

Press the " GAS SAMPLE - TRAP CLOSE" button momentarily.  :-

4.5.9 Turn the selector knob to position 5 " LIQUID SAMPLE".

4.6 Liquid Sample (Position 5) i.

~

4.6.1

(.

Press the " SELECTION POWER-ACTIVATE" button.

4.6.2 Hold the " LIQUID SAMPLE-TRAP OPEN" button for 10 i 3 seconds. _

4.6.3 Immediately after 10 3 seconds, press the " LIQUID SAMPLE-TRAP CLOSE" button momentarily.

{

4.6.4 Turn the selector knob to " FLUSH", Position 6. k y

4.7 Flush (Position 6) 4.7.1 ft Press the " SELECTION POWER-ACTIVATE" button. ,9 4.7.2 Press the " FLUSH S'iEP" button momentarily and wait 1 minute. The first flush light should be lit. (Gas Tank). ,

l R

1.

t. .

F, OP/0/A/6200/21 Page 9 of 16 (s

ji~.

4.7.3 Press the "TwSH STEP" butten momentarily and wait for F 2 minutes. Second flush lidt should be lit. (Probes) 'l 4.7.4 Press the "F WSH STEP" button momentarily and wait 4 minutes. Third flush light should be lit. (Dilution Tank) l

, 4.7.5 Press the "TwSH STEP" button screentarily and wait 1 minute. Fourth flush light should be lit. (Liquid Tank)

, 4.7.6 Press the " FLUSH STEP" button momentarily. This terminates the flushing cycles and the " COMPLETE" light turns on.

s 4.7.7 Turn the selector knc,b to " DRAIN", Position 7. Io 4.8 Drain (Position 7) '

4.8.1 Press the " SELECTION POWER-ACTIVATE" button.  ;

4.8.2 Press the " DRAIN STEP" button. momentarily and wait 4 ,,

minutes. First drain light should be lit. (Dilution Tank). ,,-

3 4.8.3 Press the " DRAIN STEP" button momentarily and wait I h minute. The second drain light should be lit. (Gas Line) p t

4

/-

4.8.4 Press the " DRAIN STEP" button aceentarily and wait 1 D minutes. The third drain light should be lit. (Gas Tank) U t e 4.8.5 Press the " DRAIN STEP" button momentarily and wait I h minute. The fourth drain light should be lit. (Probe  ;

refill and system vent). O N

4.8.6 Press the " DRAIN STEP" button momentarily. This E terminates the draining cyc.las and the " COMPLETE" k light is illuminated. F 4.9 Reset I

{

4.9.1 Turn the selector knob to " RESET" and press the " RESET" button. L, 4.9.2 If the " PUMP SUMP" light is lit, it indicates the sump has k water in it. Turn the SYSTEM POWER KEY to the left to i operate the sump pump. The " PUMP ON" light will light and. U rossin on until the pump has stopped. i 4 m 4.9.3 After the " PUMP COMPLETE" light turns on, indicating that I

the pump has stopped, turn the SYSTEM POWER KEY to the pl J

j right to re-energize the PALS. +

l . y l 4.9.4 Contact the Control Room and have them close the sample s

,, valves opened in Section 3.2.5. (Omit during Periodic 'lM Testing.)

f 1

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o OP/0/A/6200/21 Page 10 of 16 4.9.5 Record the radiation level after flushing on Enclosure 8.2.

If the field at the panel is greater than 3 Rem /hr. (3000

-mR/hr.), go to Section 5.0.

4.9.6 If this is the last sample to be collected this trip, proceed to Section 4.10, Sample Panel Shutdown. If other samples are to be collected this trip proceed to Section 6.0, Sample Retrieval.

4.10 Sample Panel Shutdown 4.10.1 Turn the SYSTEM POWER KEY to the vertical off position and turn the position selector knob to " RESET".

4.10.2 Place the panel keys in a plastic bag with Enclosure 8.1 (NC or ND Loop data). (Omit during periodic testing.)

4.10.3 Turn the toggle switch for the dilution water meter to "0FF".

4.70.4 Turn the toggle switch for the radiation monitor to "0FF".

4.10.5 Pull out the pH probe standardize knob.

4.10.6 Close nitrogen cylinder valve and disconnect the quick disconnect.

4.10.7 Turn System Selector Knob to off.

t l 4.10.8 Enter 00000 on flow totalizer.

l l 4.10.9 Proceed to Section 6.0, Sample Retrieval.

i 5.0 DECONTAMINATION 5.1 Repeat the panel Flush, Drain and Roset Modes: Sections 4.6.4 throuch 4.9.3. ,

'5 . 2 If the level is less than 3 Rem / hour, turn the SYSTEM POWER KEY to the vertical position and continue with Section 4.9.6. If however, the radiation level remains greater than 5 Rem / hour, go back to '

'i Step 4.2 and repeat the sequence using a larger dilution volume-  ;

based on the calculations of Enclosure 8.4. R l

6.0 SAMPLE RETRIEVAL -l

'l 6.1 Initial Conditions i 6.1.1 A gas and dagassed liquid sample are in the gas and liquid '

samplers, respectively through the completion of Section 4.0. H 6.1.2 Health Physics personnel are providing continuous monitoring of the area.

l

l 4 l OP/0/A/6200/21 l s

Page 11 of 16 '

6.2 Sampling 6.2.1 Take two labels from the PALS drawer. Fill out the labels as follows (including the required information):

Label one: " Liquid Sample Name Initials Date Sample Trap Time Dilution Factor "

Label the other: " Gas Sample Name Initials Sample Trap Time "

The " Sample Trap Time" and " Dilution Factor" may be found on Enclosure 8.2.

6.2.2 Take a 50 ml Nalgene sample bottle from the PALS drawer.

Label it as follows:

" Dilution Water ' Sample Date "

6.2.3 Take the completed labels and place each one on a plastic bag. Place another plastic bag inside of_each of the two labeled plastic bags. These will % used later for double bagging the samples.

l CAUTION: Do not approach the samplers on the sample panel until a Health Physics Technician has surveyed the area. Do not relay solely on the PALS panel's radiation monitor (INMM13350) as an indication the radiation in the area. (Omit i

during pa.riodic testing).

' 6.2.4 Approach the samplers located on the sides of the sample panel. -If possible, have the Health Physics Technician take an contact readings on each sample vessel. (Omit during periodic testing).

6.2.5 Detach the. quick-disconnects on each sample vessel. Place '

the samplers in the labeled plastic bags. Seal tightly.

6.2.6 Place the samples'in the sample carrier.

6.2.7 Open valve INM456 (2NM456) and fill the 50 m1 nalgene sample bottle labeled " DILUTION WATER SAMPLE". Then, >

CLOSE INM456 (2NM456). CLOSE INM462 (2NM462).

l 9

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8 OP/0/A/6200/21 Page 12 of 16 6.2.8 After returning to the outer room, record the "On Contact" liquid and gas radiation readings on Enclosure 8.2. (Omit during periodic testing).

6.2.9 If this is the last sample to be collected this trip, take the samples to the Hot Lab in the sample carrier and place in an operating fuse hood behind a lead brick shield to await analysis. However, if another sample is to be collected, call. Technician #1 at the Hot Lab and have his come down and transport the samp4es and the completed portion of Enclosure 8.2 up to the lab. Then proceed with Section 6.2.10 to begin the collection of a second sample.

One of the sample hoods in the Hot Lab should be designated specifically for sample storage. Lead bricks should line the front of the sample hood so that samples may be placed behind them.

6.2.10 In order to begin the process of collecting a second sample perform Steps 3.2.5 and 3.2.10.

6.2.11 Attach new liquid and gas samplers on the side of the PALS panel. New samplers are located in the PALS drawer.

6.2.12 Begin at Step 4.2, Panel Prep. and repeat the procedure for the new sample.

7.0 SAMPLE ANALYSIS l 7.1 Initial Conditions (Technician #1) 7.1.1 A fume hood in the Hot Leb is prepared to accept a post-accident sample: (1) the ventilation fan is on and (2) Lead bricks line the front of the panel.

7.1.2 Two See lochable sample syringes have been verified j workable and evacuated.

7.1.3 A Sec vial has been evacuated and placed in the fume hood.

7.1.4 A clean 50 ml nalgene sample bottle has been placed in the sample hood.

7.1.5 Reagents to run CP/0/A/8100/16 have been prepared and standards have been run.

7.1.6 The Gas Chromatograph has been started up and standardized f per CP/0/A/8100/48, Chemi:' y Procedure for the Determination of Stripped , ' by G. C.

7.2 Stripped Gas Samples CAIT:' ION: Perform all actions involving th. 'nsfer, preparation, or analysis of the gas sample under .e fume hood.

OP/0/A/6200/21 Page 13 of 16 7.2.1 Inject a lockable Sec syringe into the gas sampler and withdraw ice of sample. While still under the fume hood, inject the sample into an evacuated 5cc vial.

7.2.2 Double bag the vial. Seal tightly. Prepare a label for .

the bag as follows:

" Gas Sample Name Initials Date Actual Sample Time Sample Volume "

The " Gas Sample Name" and " Actual Sample Time" may be obtained from the gas sampler label. Calculate the actual sample volume as follows:

Sample Volume = 110 ml x 1 a1 = .42 al 260 al Where: 110 ml = liquid tank volume (including tubing) 260 ml = gas tank volume (including tubing) 1 ml = sample volume injected into vial Complete the Sample Requisition Form using the sample

.7 volume calculated above to fill in the " Sample Volume" blank on the form. This wil3 allow Health Physics to adjust isotopic activities from diluted samples to reflect reactor coolant activity.

7.2.3 Using a sample carrier, transport the sample to the Health Physics Count Room, or elsewhere for gamma spectral analysis.

7.2.4 Inject a lockable See syringe into the gas sampler and {

withdraw Sec of sample. Lock the syringe.  :

7.2.5 Analyze the Sec sample of stripped gas per CP/0/B/8100/48.

7.3 Lio.uid Sample CAUTION: Perform all actions involving the transfer, preparation, or analysis of the liquid sample in the fume hood.

7.3.1 .l

' Take 5 cc of liquid sample and prepare for analysis per J CP/0/A/8200/04, Chemistry Procedure for the Determination of Gamma Isotopic Activity. Dilute 5 cc in a 50 cc bottle per the procedure. Report the actual sample volume being counted on the sample requisition form under " Sample Volume" and submit to Health Physics so that the appropriate adjustment of isotopic ;l activities occurs. The calculation is as follows: ,

Sample Volume = 1/10 x 5 cc -\

)

. ewe .

OP/0/A/6200/21 Page 14 cf 16 Where: 1/10 = Dilution Ratio from 5 cc in a 50 al bottle 5 cc = Diluted Sample Volume Double bag the vial. Seal tightly. Prepare a label for the bag as follows:

" LIQUID SAMPLE NAME INITIALS DATE ACWAL SAMPLE TIME SAMPLE VOLUME The " LIQUID SAMPLE NAME" and "ACWAL SAMPLE TIME" can be . g obtained from the liquid sampler label. The " SAMPLE VOLUME" was calculated above.

7.3.2 Take 50 al of liquid sample and analyze for Baron per CP/0/A/8100/16.

Then, multiply the ppe BORON MEASURED, ie. the value obtained per CP/0/A/8100/16 by the Dilution Factor to obtain the ppe Boron in the Reactor Coolant.

ppe BORON IN THE REACTOR COOLANT =

ppe BORON MEASURED X DILUTION FACTOR Record the " Boron Concentration" on Enclosure 8.2.

7.3.3 Subtract the initial background activity (Section 4.2.111 from sample activity found at purge time completion (Section 4.3.2) and record on Enclosure 8.2. This is the radiation due to the sample. .

7.3.4 Chloride analysis CAUTION: Perform all actions which involve the transfer of the liquid sample to another container under

the fuse hood.

7.3.4.1 Contact the Station Chemist at the TSC

(#2531). Ask him to contact the General Office personnel (at the Crisis Management Center si during an accident situation). Inform them that a post-accident liquid sample is to be ,

transported to the Physical Sciences Building ~l for chloride analysis on the ion-chromatograph. y They should contact A. M. Deak for workload clearance. Also, ar.k the Station Chemist to  ;!

fill out a Chemical Sc_ences Analysis Request '

g* Form, Enclosure 8.9 for the sample.

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OP/0/A/6200/21

, Page 15 of 16 7.3.4.2 A hard copy of the samma spectrum and tritium data as well as the sample volume should be transferred to the Physical Sciences Building Radiation Protection Officer (J. S. Isaacson) or her designee. A telecopy can be sent to the Technical Training Center. g . ,

14 7.3.3.3 Tranfer 20 ml

  • 5 al of sample from the liqufd' , +

sample to a 50 al nalgene bottle.

7.3.3.4 Double bag the bottle. S'eal tightly. Label the bag as follows:

" LIQUID SAMPLE NAME M INTIAL ~

DATE~

ACTUAL SAMPLE TIME -

DILUTION FACTOR i  ;

The "AC'IUAL SAMPLE TIME" and " DILUTION FACTOR" may be obtained from Enclasure 8.2. Place the 1

bag in a shielded containdr for transport.

7.3.3.5 Once the sample shipment has been Authorized by the Radiation Protection Officer, th.' sample shipment should-be sent to the Physical. 5ciences .

Building in care of the k'adiation Protection '

Officer. The dilution water sample tbtained in .

Step 6.2.7 should also be sent for iialysis at this time. a

-14 7.3.3.6 When the semp.le $esults are obtained record the results on Enclosure 8.2. ,

~

! 7.4 If the dilution proves inadequate for any of the shove'proceduram <y j contact the Station Chemist or his designee. , ~ -

s 7.5 Report all results in the Primarr Chemistry Legal Log.<In an accident ,a situation results should be relap d by phone to the Station Chemist 3 l at the TSC as soon as possible. Phone number, 2531. s 7.6 Clean the liquid and gas samplers under the' fume hoodi' Reac'/a 2.nd . .,' g replace the septum in the gas sampler. + Flush the Iiq. aid sampler with ->-l Super Q water. ' ~

l

. .t' 3 , 1 7.7 . With Enclosure 8.2 in a plastic bag, exit the Auxiliary Eailding.',

Check out through the Operation's Support Center. .!

I y 0 ,

7.8 Transport Enclosure 8.2 to the Station Chemist at the TSC. -

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OP/0/A/6200/21 Page 16 of 16 1: i 8.0 E!!CIDSURES I s

8.1

~

Initial Conditions Checklist '

8,2 PAIS Data Sheet 4

8.3 Valve Alignment 8.4 Correction of Dilution Volume I

l s.

.l 8.5 rf3J,S Control Panel Layout ,

i

. 1 8.6 Valve Sequence Table e ..

..  ; l 8.7 General Inf.maation i

. 1 84- Operation's Supply Valvss to the F.U3 Valve Alignment 8.' S' ' Chemical Sciences Analysis Requast Form

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Page 1 of 3 ENCLOSURE.8.1 OP/0/A/6200/21 INITIAL CONDITIONS CHECKLIST Date: / /

PART I. (Verifying the System's Ability to Function) Initial /Date

1. Verify that the Post Accident 'iquid Eampling System / ,

Periodic Test, PT/1/A/42C{fuS .s current prior to fWJ1Jny, (Per19dit ~ot fen 4 tam - Computer Printout) s.

PART II. (Interfacing Groups) Ir..ial/Date

1. Contact Operations (complete at TSC).

(a) If this is an accident situation. the conttins.us /

should have been isolated by an ST signal. Verify that .the signal has been cleared.

Initial /Date CAUTION: Warn Operations not to open any sample lines until Chemistry has realigned valves in the NM lab. Opening containment isolation sample valves too early could increase radiation levels in the NM lab.

([ (b) Request permission to open the desired valves out /

of the list below. Place a check beside the sample point (s) to be used.

  • NC Hot Let A Unit 1 Unit 2 Check Hot Leg Smp1 Hdr Cent Isol INM2613 2NM26B Hot Leg A Smpl Cont Isol INM221 2NM22A -

NC Hot Leg C .J Hot Leg Sep1 Hdr Cont Isol INM26B 2NM26B Hot Leg C Smp1 Cont Isol INM25A 2NM25A ND Pump 1A Discharge Unit 1 Unit 2 q

'l

  • ND Pump 1A Disch Smpl Line Isol 1NM39 2NM39 ,

l ND Pump IB Discharge Unit 1 Unit 2 fj 9

  • ND Pump 1B Disch Sap 1 Line Isol INM40 2NM40 -1 1
  • Verify with Operations that the respective A or B Train is in service. .i
N Initial / Time (c) Verify with Operations that 1KC Essential Supply /

Header "1A" is in op3 ration for Unit 1 Sampling.

[jj For Unit 2: 2KC "2A" is required.

l 1

Page 2 of 3 l ENCLOSURE 8.1 OP/0/A/6200/21 INITIAL CONDITIONS CHECKLIST Date: / /

Initial / Time (d) Request permission to open or to have an oporator open the following Operations valves in order to provide cooling water flow to the panel. These valves are locked closed. The keys should be obtained prior to proceeding to the panel. /

Unit 1 Unit 2 Post Accident Liquid Sample Panel Hx Inlet 1KCA8 2KCA8 Post Accident Liquid Sample Panel Hx Dutlet 1KCA10 2KCA10 (e) Verify Power Panel Boards IKXPA and 1KXPB are energized /

for Unit 1 Sampling. (Unit 2 Later)

2. Contact Radwaste Chemistry (Complete at TSC).

Initial /Date Notify Radwaste Chemistry that the PALS panel will be /

operated. Waste Liquid from the panel is pumped to y WEFT Sump "A".

s::

3. Contact Health Physics (Complete at TSC) Initial /Date .

(a) Request Health Physic's Coverage for obtaining a /

post-accident liquid sample.

Initial /Date (b) Verify Health Physic's ability to count a sample in /

the Count Room or elsewhere.

PART III. (Required Equipment) Check

1. Technician #2 should have the following items before

, departing to the NM lab:

(a) The PALS panel keys (A set of keys are located in the Secondary Supervisor's office and the Cold Lab)

(b) A Working Copy of OP/0/A/6200/21 with Enclosure 8.1 completed. [tl p

(c) A High Radiation Area Key for the NM Lab. f (d) A Shielded Sample Carrier (e) Plastic bags left on Cold Side 9

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Page 3 of 3 ENCLOSURE 8.1

l,"'; , OP/0/A/6200/21 tjj*

INITIAL CONDITIONS CHECKLIST Date: / /

PART IV Recommended Dilution Volume (From Station Chemist at TSC)

Dilution Volumn (al) Flow Totalizer Setting Check One 250.0 02500 500.0 05000 1000.0 10000 -

3500.0 S5000 Station Chemist Initial /Date

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Page 1 of 4 ENCLOSURE 8.2 OP/0/A/6200/21 PALS DATA SHEET

, (Circle One)

NC Loop A - C Data (Page I of II)

Initial /Date

/

PART I. (Complete at Control Panel) TIME

1. Radiation Field (Background) mR/hr
2. Time sample purge started.
3. Radiation field (with sample flow) ,. mR/ hour
4. Radiation due to sample, (#3) - (#1) (Complete after mR/ hour Sample Collection)
5. Pressure at isolation psig
6. Sample Trap Time
7. Flow totalizer setting r' f. pH of sample Q.,;' ,. -
9. Radiation reading after panel flush mR/ hour
10. Radiation reading on contact with samplers.

(Omit during Periodic Testing.) Gas mR/ hour Liquid mR/ hour

.c;

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Page 2 of 4 ENCLOSURE 8.2 OP/0/A/6200/21 PALS DATA SHEET ,

(Circle One)

NC Loop A - C Data (Page II of II)

Initial /Date

/

PART II. (Complete at Hot Lab) TIME ,

1. Hydrogen Concentration ec/kg H '

2

2. Boron Concentration ppe B .' ,

9

3. Dilution Factor Reference Enclosure 8.7, number 7
4. Chloride Concentration ppb Cl

~ 5. Gamma Spectral Analysis (Gas) (Attach H.P. Data Sheet)

6. Gamma Spectral Analysis (Liquid) (Attach H.P. Data Sheet)

In an accident situation, the results from this data sheet should be forwarded to the Station Chemist at the Technical Support Center as soon -

as possible. TSC phone number - 2531.

Initial /Date

/

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Page 3 of 4 ENCLOSURE 8.2 1 l'

OP/0/A/6200/21 PALS DATA SHEET (Circle One)

ND Loop A - B Data (Page I of II)

Initial /Date

/

PART I. (Complete at Control Panel) TIME

1. Radiation Field (Background) mR/hr
2. Time sample purge started.
3. Radiation field (with sample flow) mR/ hour 4 Radiation due to sample, (#3) - (#1) (Complete after mR/ hour After Sample Collection)
5. Pressure at isolation psig
6. Sample Trap Time
7. Flow totalizar setting i
8. pH of sample
9. Radiation reading after panel flush '

mR/ hour

10. Radiation reading on contact with samplers. *

(Omit during Periodic Testing.) Gas mR/ hour Liquid mR/ hour

+

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1 9 Page 4 of 4 ENCLCSURE 8.2

[

OP/0/A/6200/21 - l PALS DATA SHEET (Circle One) ,

ND Loop A - B Data (Page II cf II)

Initial /Date

/

( PART II. (Complete at Hot Lab) TIME

1. Hydrogen Concentration ec/kg H 2
2. Boron Concentration ppm B
3. Dilution Factor Reference Enclosure 8.7, number 7 4 Chloride Concentration ppb Cl" i S. Gamma Spectral Analysis (Gas) (Attach H.P. Data Sheet)
6. Gamma Spectral Analysis (Liquid) (Attach H.P. Data Sheet) >

l In an accident situation, the results from this data sheet should be forwarded to the Station Chemist he Technical Support Center as soon as possible. TSC phone number Initial /Date l /

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DUKE POVER COMPANY -!

Form 18768 (R841) CATAWBA NUCLEAR STATION I' ENCLOSURE 8.3 h OP/0/A/6200/21 (Unit 1)

  • VALVE ALIGNMENT LOCATION [

VALVE NAME POSITION INITIAL J3-543 EF.-54

~

1NM342 PASP Domin Supply Flow Meter Influent Rm. 238 THROTTLD -

h3-543 EE-54 1NM343 PASP Domin. Supply Isol to Sapl Hdr Rs. 238 OPEN a3-543 EE-54 1NM351 PASP Air Eductor Isolation From VI Rm. 238 OPEN aB-543 EE-54

, 1NM298 Nitrogen Supply to PASP Rm. 238 OPEN nB-543 EE-54

, INM393 PASP Effluent to WEFT Sump A Isol Rm. 238 OPEN nB-543 EE-54 I INM321 PASP Liquid Tank Effluent to WEET Rm. 238 THROTTLED ,

aB-543 EE-54 N INM334 PASP Calibration Tank Vent to Aux Bldg Exhaust Rm. 238 CLOSED e r

aB-543 EE-54  ;,

1NM328 PASP Sample Line Nitrogen Supply Isolation Rm. 238 OPEN IJ G

aB-543 EE-54 t INM452 PASP Dilution Tank Sample Rm 238 CLOSED .,

aB-543 EE-54 [

INM449 PASP Calibration Tank Drain Rm. 238 CLOSED ,

i aB-543 EE-54 E 1KCC99 Sample Cooler Outlet Valve Rs. 238 OPEN g t=

aB-543 EE-54 M INM456 PASP Deaerator Tank Sample Rm. 238 CLOSED f.

aB-543 EE-54 ,

1NM453 PASP Liquid Tank Sample Rm. 238 CLOSED AB-543 EE-54 1NM448 PASP Nitrogen Inlet to Liquid Tank Rs. 238 OPEN h aB-543 EE-54 1 INM462 PASP Demerator Tank Inlet Rs. 238 CLOSED J

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ENCLOSURE 8.4 OP/0/A/6200/21 CORRECTION OF DILUTION VOLUME To correct the dilution volume, divide the radiation reading after panel flush by 3 rea/hr. Then multiply this by the initial dilution volume to obtain the desired dilution volume in Section 4.5.3.

1 4

Example:

Initial Dilution Volume = 250 ml Radiation reading after panel flush = 12 res/hr (12000 mR/hr) then 12 res/hr x 250 al = 1000 ml 3

Go back to Section 4.2 and repeat the sample sequence. In Step 4.5.3, j use the new dilution volume which was calculated as in the example above.

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Page 1 of 2 ENCLOSURE 8.5 I OP/0/A/6200/21 PALS CON 11t0L PANEL LAYOUT

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ENCLOSURE 8.5 1

OP/0/A/6200/21 '

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PALS CONTROL PANEL LAYOUT i

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Page 1 of 3 ENCLOSURE 8.6 OP/0/2/6200/21 VALVE SEQUENCE TABLE Pushbutton Function Activation Valves 1.0 Panel Prep 1NM313, INM312, 1NM315 1NMSV0311, INM311, INM310, INM314, INMSV3201 1.1 Calibre.te H INM333, INM332 1.2 Purge- H INM330, 1NM338, 1NM307, INM305 1.3 Flush H INM331, 1NM338, 1NM307, INM309 1.4 Drain H INM338, 1NM307, INM305 2.0 Sample Trap IKCA9, 1NM294, 1NM324 1NM319, 1NM313, INM312 1NMSV0311, 1NM314 2.1 Pressurize M INM319 2.2 Trap M INM324 3.0 Depressurization 1NM317, INH 315 3.1 Gas Stripping Start M INM325, INM327 3.2 Gas Stripping Stop M INM325, 1NM327 4.0 Liquid Sample INM339, INM346 4.1 Grab Sample M INM318, 1NM325, 1NM329, INMSV0336 ,

4.2 D.M. Flow Meter Start M INM341, INM346 4.3 D.M. Flow Meter Stop M INM341, INM346 r_ ,.

)

Page 2 of 3 l ENCLOSURE'8.6 OP/0Q/6200/21 VALVE SEQUENCE TABLE l

Pushbutton ]

Function Activation Valves -

4.4 Mixing H INM340,

\

i 4.5 pH M INMSV0336 .

~  !

4.6 Trap Open M INM315, INM312, INMSV0311, 1NM324, INM319, 1NM345, l 1NM322 4.7 Trap Close M INM315. INM312, 1NMSV0311 5.0 Liquid Sample Prep -

(Step incorporated into Step 5.0) l 6.0 Liquid Sample II INM324, 1NM319, 1NM345, INH 322, INM348 1NMSV0350, INM346 6.1 Trap Open H INM319, 1NM346, 1NM309 1NM304, INM376 6.2 Trap Close M INMSV0350 7.0 Flush 7.1 Gas Tank M INM316, 1NM312, 1NM308, 1NM309 ]) .

7.2 Probes M IMN331, 1NM338, b 1NM307, 1NM309

7.3 Dilute Tank M INM347, 1NM301, INM309 7.4 Liquid Tank M INM331, 1NM329, 1NM325, INM319, INM322 8.0 Drain 8.1 Dilute Tank M 1NM376, INM348, 1NM304, INM305 i

Page 3 of 3 ENCLOSURE 8.6 OP/0/4/6200/21 VALVE SEQUENCE TABLE Pushbutton Function Activation Valves 8.2 Gas Line M INM323, INM315, INM312, INM308, INM305 8.3 Gas Tank M INM323, INM315, INM317, 1NM325, INM329, i

INM338, INM307, INM305 8.4 Probe Refill & System Vent M INM331, INM338, INM307,

' INM309, 1NM312, INM313, 1NM346, INM348, 1NM315, INMSV3200 LEGEND:

M- Momentarily depressing the button initiates the function.

H- The function will o'perate as long as the pushbutton is depressed.

5- Indicates that the valve is de-energized when the pushbutton is depressed.

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1 Page 1 of 2 ENCLOSURE 8.7 OP/0/A/6200/21 GENERAL INFORMATION

1. PALS Panel Location: Unit 1 - (Room 238, Col. FF-55, AB-543)

Unit 2 - (Room 248, Col. FF-59, AB-543)

See page 2 of this enclosure for a general arrangement drawing.

2. Telephone Number at Control Panel - Ext. 2109 (Unit 1) j 3. Breaker Information:

Unit 1 Fdr. Breaker 2

Comp / Breaker Description Location 1KXPA D Post Accident Sampling AB 554' i'

Sample Pump and Sol. CC-57 Vivs. .

1KXPB #34 Post Accident Liquid AB 554

! Sampling Control Panel CC-56

  • 1XXPA #22 Post Accident Air AB 554 Sampling Control Panel CC-57 r,
  • The Post Accident Air Sampling Control Panel is under Health Physic's 1 -control.

Unit 2 (Later)

4. Area Radiation Monitor - 1 EMF-2 is located in Room 238.
5. Station Chemist phone number at TSC - 2531.
6. Sample Line Purge Volumes Unit 1 ,

NC Loop A to PALS - 22.5 gallons (45 minute purge @ .5 GPM)

NC Loop C to PALS - 19.5 gallons (39 minute purge @ .5 GPM)

ND Loop A to PALS - 25.0 gallons (50 minute purge @ .5 GPM)

ND Loop B to PALS - 32.3 gallons (65 minute purge @ .5 GPM)

Unit 2 (Later)
7. Dilution Factors a

Flow Totalizer Setting Dilution Factor Dilution Water Added (al) i' 02500 48.4 250.0 05000 500.0 10000 1000.0 '

35000 3500.0 J

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DUKE POWER COMPANY Form 18768 (R8-81)

CATAWBA NUCLEAR STATION ENCLOSURE 8.8 OP/0/A/6200/21 OPERATION'S SUPPLY VALVfJ - VALVE ALIGNMEhT VALVE NAME POSITION INITIAL.

Unit 1 PALS Supply Valves IVI230- kB-553 GG-56 Root Isol.

Rs. 200- OPEN l

IVI86 <

LB-543 EE-53 Aux. Bldg. 543 Elev. VI Supply Rs. 217 OPEN 1YM436 LB-543 FF-54

\

Post Accident Unit 1 Sample Isol. Rs. 238 OPEN l

1YM256 Ls-543 FT-54 YM Header Isol  !

Rs. 238 OPEN i 1KCA8 Post Accident Liquid Sample Panel Hx Inlet i

.LB 546, EE-56 LOCKED '

Rs. 238 CLOSED L

i 1KCA10 Post Accident Liquid Sample Panel Mx Outlet <LB 546, EE-So LOCKED Rs. 238 CLOSED Unit 2 PALS Supply Valves a

L

!2VI402 AB-543 )

Liquid Sample Panel Supply Isol. .

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OPEN l

2VI230 AB-543 Unit 2 Aux. Bldg. Root Isol. 1 OPEN 2VI86 AB-543 Aux Bldg 543 Elev. VI Supply OPEN 1YM437 aB-543 FF-60 Post Accident Unit 2 Samole Isol. Rm. 248 OPEN lYM140 YM Header Isolation aB-543 FF-57 Rm. 200 OPEN 2KCA8 Post Accident Liquid Sample Panel Hx Inlet aB 543 LOCKED ur-rr an.si mmen 2KCA10 Post Accident Liquid Sample Panel Hx Outlet aB 543 LOCKED i

ar_rr en_es e.vneen NOTE: The valves listed above all belong to H

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a W' l Form 34731 (10-81)  ;

(Formerly SPO 10021)

DUKE POWER COMPANY (1) ID No: HP/0/B/1000/06 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 9 Incorporated ,1 (2) STATION:__ Catawba (3) PROCEDURE TITLE: Emernancy Ecuinment Functional Check snel Inventerv 1

(4) PREPARED BY: /d jYMA DATE: J / j .:r /#s-(5) REVIEWED BY: Mg,/,m MM A s DATE: JI-/J- ((

. Cross-Disciplinary Review By: N/R: e_a (6) TEMPORARY APPROVAL (IF NECESSARY):

/$$. By: (SRO) Date:

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-By: . ,

Date:

(7) APPROVED BY:

  • Date: / (*

(  ! 4 (8) MISCELLANEOUS:

Reviewed / Approved By: Date:

.J Reviewed / Approved By: Date:

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4 HP/0/B/1000/06 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY EQUIPMENT FUNCTIONAL CHECK AND INVENIORY 1.0 PURPOSE ,

To provide for the availability and readiness of Emergency Equipment.

2.0 REFERENCES

1 2.1 HP/0/B/1005/0s.; Respirator waality Assurance 2.2 HP/0/t/1009/19; Emergency Radio System Operations, Maintenance and Communications 2.3 Catawba Nuclear Station Directive 2.11.13 2.4 Catawba Nuclear Station Directive 3.2.2 2.5 Catawba Nuclear Station Directive 3.3.3 l

g. 2.6 Catawba Nuclear Station Smergency Plan v.

2.7 Catawba Nuclear Station Technical Specifications 6.8.1 2.8 Duke Power Company Radio Operator's Manual 2.9 Maintenance of Silver Zeolite Air Sampling Cartridges Letter; File: CN-768.01 2.10 10CTR 50 Appendix E 2.11 Technical Manual for Groban Gasoline Generators 3.0 LIMITS AND PRECAtJTIONS 3.1 Operati.on of Portable Generators 3.1.1 Avoid operating the unit while hands are wet or while standing in water.

i 3.1.2 Generators shall not be started while equipment is plugged into generator.

3.2 Silver zeolite cartridges shall be dir.arded if the seal has been broken.

Sa E0 4

( MP/0/B/1000/06 Page 2 of 7 3.3 Any radiation monitoring equipment (located in an emergency kit) that must be removed from service for any reason shall be replaced within four hours from the time it is removed from the kit.

3.4 Any emergency kit used during training or for drill purposes shall be reinventoried as soon as possible. The individual responsible for the training or drill shall be responsible for inventory and restocking of all on-site kits.

4 3.4.1 Off-site kits shall be reinventoried as above and a list of deviations shall be given to the Respiratory / Instrument Calibration (R/IC) Supervisor. R/IC shall be responsible for restocking off-site kits as soon as possible.

4.0 PROCEDURE ~

4.1 Monthly Emergency Equipment Check / Inventory 4.1.1 Portable Generator Check '

4.1.1.1 Portable generators shall be considered -

acceptable for use if:

4.1.1.1 The oil level is at an acceptable level per Reference 2.11.

4.1.1.2 The generator starts and runs for at least 5 minutes.

4.1.1.3 The generator stabilizes after a portable air sampler is plugged into each of the generator outlets.

4.1.1.2 If generator is acceptable, shut off generator and remove any excess gasoline from the gas tank.

i 4.1.1.3 Document the operability of the generators in the appropriate column on the Monthly / Quarterly Emergency Equipment Check Sheet (Enclosure 5.1).

4.1.2 Two-Wey Low Band FM Radios 4.1.2.1 The radios shall be considered acceptable for use if:

4.1.2.1.1 Each radio transmits a message to another radio.

4.1.2.1.2 Each radio receives a message from another radio.

4.1.2.2 Document the operability of the radios in the appropriate area on Enclosure 5.1.

~~s- -

( HP/0/B/1000/06 Page 3 of 7 4.1.2.3 Inoperable radios shall be removed from service.

Contact Toddville Communication Shop Planner for instructions on disposition for repair.

4.1.3 Batteries 4.1.3.1 All batteries shall be considered acceptable for use if:

4.1.3.1.1 The battery tester needle indicates.

" good" when the battery is tested.

4.1.3.1.2 The battery appears to be in good physical condition (no dents, corrosion, etc.).

4.1.3.2 Document battery check on Enclosure 5.1.

4.1.4 Portable Survey Instruments 4.1. 4 .1 Portable Survey Instruments shall be considered acceptable for use if:

4.1.4.1.1 The instrument battery checks.

4.1.4.1.2 The instrument source checks in accordance with the instrument's operation procedura (located in the emergency kit).

4.1.4.1.3 The instrument has no apparent physical damage.

4.1.4.1.4 The instrument's calibration date is current.

J

'4.1.4.2 Document the instrument's operability on Enclosure 5.1. .{

4.1.5 Portable Air Saoplars 4 .1. 5 .1 Air Samplers shall be considered acceptable for use if:

' 4.1.5.1.1 The sampler operates when plugged {

into an electrical outlet. I 4.1.5.1.2 The calibration date on the sampler is~ current.

4.1.5.! ' The sampler has no apparent physical damage.

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( HP/0/B/1000/06 Page 4 of 7 4.1.5.2 Document the sampler s operability on Enclosure 5.1.

4.1.6 Respiratory Equipment 4.1.6.1 Respiratory equipment shall be considered acceptable for use if:

4.1.6.1.1 The equipment is in accordance with criteris stated in Reference 2.1.

4.1.6.1.2 The Esargency Self-Contained Breathing Apparatus (SCBA) are available at the following '

locations:

Locations Minimus Units Control Room 2 Upper Personnel Hatch 2 Lower Personnel Hatch 2 Health Physics Respiratory Storage Area 8 ,

e 4.1.6.1.*3 Six large cylinders of breathing air (minimum of six hours used for [

5 people) are located in the  ;

Control Room along with 5 airline respirators and associated airline hoses.

4.1.6.2 Document operability of respiratory equipment in accordance with Reference 2.1. l 4.2 Quarterly Emergency Equipment Inventory / Inspection

  • 4.2.1 Emergency equipment kits shall be inventoried quarterly and after each use using the appropriate Emergency Equipment Kit Checklist (Enclosures 5.4 - 5.13) 4.2.1.1 Consult the Emergency Equipment Kit Location Sheet (Enclosure 5.2) for the locations of each d kit. P 4.2.1.2 Perform monthly checks as in Steps 4.1.1, fj 4.1.3, 4.1.4, 4.1.5, 4.1.6.

4.2.1.3 The quarterly operability check on two-way low I*

band radios shall be performed as follows:

4.2.1.3.1 Radios shall be checked from a point 10 miles froc the plant in d accordance with heferenc6 a.6.

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( ( HP/0/B/1000/06 Page 5 of 7 .

4.2.1.3,2 Contact shall be made from the base station in ths TOC to each of the radios.

4.2.1.3.3 Each of the radios shall make contact with the base station.

NOTE: Base Call Sign -

Radio Call Signs -

(Alpha, Bravo, Charlie, Delta, Echo Foxtrot) 4.2.1.3.4 Document operability of radios on 1

Enclosure 5.1.

4.2.1.4 Perform a functional check of the dosimeter charger / reader. The charger is acceptable for use if the charger light illuminates.

4.2.1.5 Ensure the.t the leak and source check dates on the dosameters are current. -

4.2.1.6 Ensure that the TLD's are the appropriate ones for the current quarter.

t 4.2.1.7 Ensure the Potassium Iodide tablets have not exceeded their expiration date.

4.2.1.8 Ensure the seal on the silver zeolite cartridge packet is not broken and the cartridges are not '

damaged. -

4 2.1.9 Insure that all procedures are current with the Control Copy.

4.2.1.10 Ensure the flashlight bulb illuminates properly.

4.2.1.11 Che ct- all protective clothing for tears, rips or holes, cra:ks in rubber, oissing snaps, broken zippers, etc.

4.2.1.12 If any deviations are found, they shall be .

noted in the deviation section of the applicable Emergency Equipment Kit Checklist (Enclosure 5.4 - 5.13) .

4.2.1.12.1 Give a brief description of the deviation in this section.

4.2.1.13 Document any deviations on the Emergency Equipment Deviation Authorization Sheet I (Enclosure 5.14).

c -...

  • HP/0/3/1000/06 Pete 6 of 7 4.2.1.14 The Technician shall sign off Enclosure 5.1 and the appropriate checklists (Enclosures 5.4 - 5.13) and forward to the Respiratory / Instrument Calibration (R/IC)

Supervisor.

4.2. 2 Vesther Information Check

~ 4.2.2.1 Quarterly a call shall be placed to the National Weather Service located in Columbia, SC a If these numbers cannot . an alternate number in Charlott ay be used.

Obtain wind direction, wind speed, and cloud cover from one of these sources for the vicinity of Catawba Nuclear Station.

4.2.2.2 Obtain the same information from the Control Roos.

4.2.2.3 Record this information on the Weather l

Information Form (Enclosure 5.3).

l 4.3 Deviation Authorization 4.3.1 'Ibe Station Health Physicist shall be made aware of any I deviation recorded on Enclosure 5.14 4.3.2 The Station Health Physicist shall have evaluated the j consequences the deviation may have upon the capability to l respond to an emergency situation.

6.3.3 Enclosure 5.14 shall be used to state the action taken to remedy the deviation, and to state the justification for taking that action.

4.4 Upon completion of this procedure all required documentation will be filed in the Emergency Equipment Tunctional Check and Inventory log, until the end of the quarter.

4.4.1 At the end of the quarter all of the required documentation will be placed in the Realth Physics Satellite Master Tile.

4.4.2 Sign off the PT printout and forward as per Reference 2.4 5.0 ENC 145URES l

5.1 Sample of Monthly / Quarterly Emergency Equipment Check Sheet 1

5.2 Sample of Emergency Equipment Kit Location Sheet 5.3 Sample of Weather Information Tors 5.4 Sample of Recovery Kit Checklist

i

( ( HP/0/B/1000/06 Page 7 of 7 5.5 Sample of Environmental Survey Kit Checklist 5.6 Sample of Environmental Survey Kit Checklist (Helicopter) J 5.7 Sample of Personnel Survey Kit Checklist 5.8 Sample of Persor.nel Survey Kit Checklist (Evacuation Facility) .

5.9 Sarple of Emergency Medical Kit Checklist (First Aid Room) ,.

5.10 Sample of Emergency Medical Kit Checklist (Piedmont Medical Center) 5.11 Sample of Operations Support Center Kit Checklist 5.12 Sample of Technical Support Center Kit Checklist 5.13 Sample of Fuel Transfer Kit Checklist 5.14 Sample of Emergenwy Equipment Deviation Authorization Sheet g ..

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MT/0/3/1000/06 l

( { Enclosure 5.1 Fast 3 et 2 i

CATAWBA NUCLEAR STATION i

MONTNLY/ QUARTERLY DtERCENCY EQUIPMENT CHECK SHEET

t. 2 x 9~ . ~E ? :r a/  :

~*o s* 4.eE *, E.*s

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+

9 signature /Date Environmental Survey Kit-A Environmental Survey Kit-B i

Environmental Survey Kit-C Environmental Survey Kit-D Environmental Survey Kit-E Recovery Kit-Allen l Transmission '

Recovery Kit-Line Maint.

l

Security

<- Pecovery Kit-Pan Area Construction Recove y Kit-Fersonnel Area Personnel Survey Kit-Allen Transmission Personnel Survey Kit-Line Maint.

l Security Personnel Survey Kit-Pap Area i

Construction Personnel Survey Kit-Fersonnel Area i First Aid j Energency Medical Kit-Room

! Fiedmont Energency Medical Kit % dical Center Operations Support Center Kit Technical Support Center Kit ,

Fuel Transfer Kit i

i I

I I

. . _ . . - ._.-_-._.-.-.-_.-_--_-.._.-----____L._.._---..

( '- Page 2>.of;2 i M0h'THLY/ QUARTERLY EMERGENCY EQUIPMEhT .l CHECK SHEET 1

- s NP/0/3/1000/06

  • ENCLOSURI 5.1 l

i GASOLINE GENERATORS i <

Generator Number Comments Signature /Date 1 i

i J

i

PORTABLE RADIO 11tANSMITTER - RECEIVERS 4

Radio Call Sign Comments Performed At ' Signature /Date 10-Mile On Site I.

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O CATAWBA NUCLEAR STATION E('GENCYEQUIPMENTLOCATIONSHEE(

MP/0/B/1000/06 ENCIASURE 5.2 KITS LOCATION Recovery Kits (4)

Evacuation Facilities (2) Allen Steam. Station i Transmission Line Maintenance Building Security Pap Area Temp. Admin. Building Construction Personnel Access Area Temp. Admin. Building Environmental Survey Kits (Vehicle) (4) Temp. Admin. Building Environmental Survey Kit (Helicopter) (1) Temp. Admin. Building Personnel Survey Kits (4)

Evacration Facilities (2) Allen Steam Station Transmission Line Security Pap Area Maintenance Building Temp. Admin. Building Construction Personnel Access Area Temp. Admin. Building Emergency Medical Kit (2) Aux. Building First Aid Room Piedmont Medical Cancer q, Operations Support Center Kit Operations Support Center Technice) Support Center Kit Technical Support Center Fuel Transfer Kit Temp. Admin. Building

CATAWBA NUCLEAR STATION WEATHER INFORMATION HP/0/B/1000/06 ENCLOSURE 5.3 National Weather Service Control Room Wind Direction Wind Speed _

Cloud Cover Time Signature /Date

.._ y ___

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

1 ..

CATAWBA NUCLEAR STATION

<~ -

RECOVERY KIT 3 CHECKLIST 4 HP/0/B/1000/06 ENC 505URE 5.4 MINIMUM ITEM AMOUNT DEV.*

List of Contents 1 Eberline E-520 w/HP-270 Probe 1 Exempt Source 1 Low /High Range Dosimeters (0-500 mR), (0-!R) 2 each Dose Cards 25 TLD Badges 6 Dosimeter Charger 1 Boundary Ribbon or Rope (50 yd. roll) 1 Masking Tape (roll) 1 Rain Suits (set) 2 Protective Clothing (set) 2 Poly Bags (Various) 12  ;

Caution Signs w/ inserts 2 Legal Pad 1 Instrument / Smear Survey (pad) 1 Pens 2 Grease Pencil 1

, Full Face Respiratior With High Efficiency Filters 2

,First Aid Kit 1 Potassium Iodide Tablets Trans. Line Maint. 275 bottles Security PAP 150 bottles Construction Personnel Area 150 bottles Allen Steam Station 275 bottles KI Distribution Data Sheet 100 Smears (box) 1 NuCon Smears 30 Flashlight 1 Batteries (Size D) 10 Scissors 1 Medication Envelopes Trans. Line Maint. 100 l Security PAP 60

  • Construction Personnel Area 60 Allen Steam Station 100 Crisis Management Team Phone Directory ** 1 SLED Badges (Persennel and Vehicle each)**

100 Emergency Planning Zone Maps ** 3 HP/0/B/1009/16 1 This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed.

Signature /Date N.

  • Any Deviations will be documented on the Energency Equipment Deviation -

Authorization Sheet (Sample Enclosure 5.14).

- **These items are found only in the Recovery Kits located at Allen Steam Station and. Transmission Line Maintenance Building.

( ( Page 1 of 2 CATAWBA NUCLEAR STATION l ENVIRONMEhTAL SutVEY KITS CHECKLIST I HP/0/B/1000/06 ENCLOSURE 5.5

~

MINIMUM ITEM DEV.*

AMOUNT i

'l

-i List of Contents 1 -1 l

Eberline E-520 w/HP-270 Probe 1 Eberline E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 l

Portable MCA** 1 '

Eberline PIC 6A 1 l

Emergency Radio Transmitter / Receiver 1 1 Radeco H809V Air Sampler 1 Gasoline Generator (Gasoline in Safety Cabinet) 1 l

Low /High Range Pocket Dosimeter (0-500 mR), (0-5R) 2 each i Dose Cards 25 .l TLD Badge 6 Dosisater Charger -

, 1 i'

Full Face Respirator With High Efficiency Filter 2 Potassium Iodide Tablets (bottle) 2 Protective Clothing (Full Set) 3

,:' 'f Poly Bags (Various Sizes) 6 9f.. Masking Tape (roll) 1 Limnological Sampler 1 Cubitainers 6 i

1 Liter Wide Mouth Bottles 5 Stopwatch 1 Flashlight 1 Batteries (Size D) 14 Batteries (9 volt) 4 -

Silver Zeolite (CP-100G or GY-130) Filter Cartridges and Particulate Filters 30 Filter Cartridges Labels & Bass 100 Smears (box) 1 NuCon Smears 30 Instrument /Saear Survey (pad) 1 Map of Ten Mile Zone Sectors 1 Legal Pad 1

! Pen 2

  • Permanent Marker 1 ,

Hand Spade 1 c.

Grease Pencil and refills 1 4 Dime Roll 1 J

! Scissors 1 -

Rain Suits 3 Telephone location asps I ri Field Monitoring Data Sheet ,

20

. Field Monitoring Work Sheet 20 O

KI Tablet Distribution Data Sheet 1 Radio Operater Manual 1 CPD1 Key 1 Cotton Liners (pairs) 5 SLED Badges (Personal - Vehicle) 4 '

HP/0/3/1009/04 1

-s ,,

,, Page 2 of 2 b CATAWBA NUCLEAR STATION ENVIRONMENTAL SDEVEY KITS CHECKLIST HP/0/B/1000/06 ENCLOSURE 5.5 MINIMUM ITEM AMOUhT DEV.*

HP/0/B/1009/16 1 HP/0/3/2003/17 1 i HP/0/3/1009/19 1 This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed.

Signature /Date

  • Any Deviations will be documented on the Emergency Equipment Deviation

- ;, Authorization Sheet (Sample Enclosure 5.14).

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    • This instrument is stored and maintained in the Health Physics Counting Room Area.

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,( CATAWBA NUCLEAR STATION I ff;*e- ENVIRONMEhTAL SURVEY KITS CHECKLIST (Helicopter)

HP/0/B/1000/06 QC ENG'ASURE 5.6 MINIMUM ITEM AMOUNT DEV.*

List of Contents 1 Eberline PIC-6A 1 Eberline E-520 w/HP-270 Probe 1 Exempt Source 1 Low /High Range Pocket Dosimeter (0-500 mR), (0-SR) 2 each Dose Cards 25 Field Monitoring Data Sheet 20 TLD Badge 6 Dosimeter Charger 1 Full Face Respirator with High Efficiency Filter 2 Potassium Iodide Tablets (bottle) 2 KI Distribution Data Sheet 1 Stopwatch 1 Flashlight 1

Batte. ries (Size D) 10 Batteries (9 volt) 4 Ear Plugs (pairs) 6 Map of Ten Mile Zone Sectors

1 Legal Pad (2[ Pan 2

1 Rain Suits 2 Instrument /Saear Survey (pad) 1 Emergency Radio Transmitter / Receiver 1 HP/0/B/1009/19 1 HP/0/B/1009/04 1 HP/0/B/1009/16 1 This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed.

.)

Signature /Date  !

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~ *Any Deviation will be document de on the Emergency Equipment Deviation -!

Authorization Sheet (Sample Enclosure 5.14).

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( CATAWBA NUCLLut STATION

( Page 1 of 2 PERSONNEL SURVEY KITS CHECKLIST' HP/0ilr71000/06 ENCI45URI 5.7 MININUM ITEM AMOUNT DEV.*

List of Contents 1 _

Eberline E-140N w/HP-210 Probe (or equivalent)*** 2 Sample Slide Tray *** 'j 1

Exempt Source 1

, Emergency Radio Transmitter / Receiver ** 1 1 Radio Operator Manual 1 Low /High Range Dosimeters (0-500 mR/h), (0-5 R/hr) 2 each 4 l

Dose Cards 25 d TLD Badges 2 Dosimeter Charger 1 s

, Full Face Respirator With High Efficiency Filter 2 Potassium Iodine Tablets (bottle) 2 KI Distribution Data Sheet 1 Protective Clothing (Full set) 6 Boundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 4 Masking Tape (roll) 1 Poly Bass (Various) 6 Seears (box) 1 Nucon Smears 25

Instrument / Smear Survey (pad) 1 Pens 2 Grease Pencil & Refills 1 l Legal Pad 1 Scissors 1 Rain Suits . 3 Decon Kit 1
1) Rad Con l 2) Red Wash -

i

3) Paper Towels
4) Scrub Brush
5) Cotton Swabs
6) Fingernai1 Clippers
7) Phischex (125 al)
8) Personnal Decontamination Forms Batteries (Size D) 10  ;
Station Directive 3.8.3 1 j HP/0/B/1004/06 1 j

i HP/0/B/1009/05 1 j

HP/0/3/1009/16 1 J

HP/0/B/1009/19** 1

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( CATAh'BA NUCLEAR STATION

( Page 2 of 2 PERSONNEL SURVEY XITS CHECKLIST HP/093/2000/06 '

ENCLOSURE 5.7 i

This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if ,

j applicable, have been completed.

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{ Signature /Date

  • Any Deviation will be documented on the Emergency Equipment Deviation t:

Authorization Sheet (Sample Enclosure 5.14).

    • 0nly the Construction Personnel access area shall have an Emergency Radio and procedure.
      • The Security PAP Area shall have (3) E-140N w/HP-210 Probe or equivalent and Sample Slide Tray. The Construction Personnel Access Area shall have 3; (2) E-140-N w/HP-210 Probe or equivalent and shall not have a Sample Slide Tray.

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( CATAWBA NUCLEAR STATION PERSONNEL SURVEY KITS CHECKLIST

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(EVACUATION FACILITY)

HP/0,4/2000/06 ENCLOSURE 5.8 I MINIMUM ITEM AMOUNT DEV.* ,!

1 List of Contents 1 i

1 Eberline E-140N w/HP-210 Probe (or equivalent) 3 Extapt Source, '

1 Iow/High Range Dosimeters (0-500 mR), (0-5R) 4 each Dose Cards 25 TLD Badges .

4 Dosimeter Charger 1 Potassium Iodide Tablets (bottle) 2 K1 Tablet Distribution Data Sheet 1 Medication Envelopes 3 Protective Clothing (Full Set) 6 Boundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 4 Masking Tape (roll) 1 Poly Bass (Various) 6 Sesars (box) 1 Instrument / Smear Survey (pad) 1 Pens 2

Grease Pencil & Refills 1 '

Legal Pad 1

Decon Kit 1

1) Rad Con
2) Rad Wash _
3) Paper Towels -
4) Scrub Brush
5) Cotton Swabs
6) Fingernail Clippers
7) Phischex (125 al)
8) Personnel Decontamination Forms ,

Scissors 1

Disposable Coveralls 40 i

Station Directive 3.8.3 1 Evacuation Personnel Dose Record 50 Catswba Nuclear Station Telephone Directory 1 Batteries (Size D) 10 HP/0/3/1004/06 1 <

HP/0/B/1009/05 1 HP/0/B/1009/16 1 This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if '

applicable, have been completed.

Signature /Date

  • Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).

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( CATAb'BA NUCLEAR STATION EMERGENCY MEDICAL KIT CHECKLIST

( -

l'IRST AID ROOM HP/0((/1000/06 ,

ENCLOSURE 5.9 l

MINIMUM -l ITEM AMOUh7 DEV.* I List of Contents 1 Eberline E-140N w/HP-210 Probe (er equivalent) 1 Exempt Source 1

Poly Bass (various, sizes) 6 Seears (box) i NuCon Smears 25 Protective Clothing (Full Set) 4

Rain Suits 2 '

Tape, Radioactive Material 1 Tape, Hasking 2" 1 Tape, Duct 2" 1 Instrument /Seear Survey (pad)- 1 Pens 2

Legal, Pad 1 Caution Signs w/ inserts 3 Radioactive Material Tags 50 Scissors 1 Poly for Ambulances (bundles) 3 i

Protective Clothing for Ambulance Drivers (Sets) 2 Batteries (Size D) 4 HP/0/B/1004/06 1 HP/0/B/1009/08 I; 1

This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed. t p

i-Signature /Date '

  • Any Deviation will be docusanted on the Em re gency Equipment Deviation t Authorization Sheet (Sample Enclosure 5.14).
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CATAWBA NUCLEAR STATION EMERGENCY MEDICAL KITS CHECKLIST

(

PIEDMOPfr MEDICAL CEhTER }

HP/04B/1000/06  ;

ENCLOSURE 5.10 .

MINIMUM ITEM AMOUNT DEV.*

List of Contents 1 Eberline E-520 w/HP-270 Probe 1 Eberline E-140N W/210 Probe (or equivalent) 1 Exempt Source 1 Poly Bass (various sizes) 14 Smears (box) 1 NuCon Seears 25 Tape, Radioactive Material 1 Tape, Masking 2" 2 Tape. Duct 2" 4 Instrument /Saear Survey (pad) 1 .

Caution Signs w/ inserts 5 i-Rad Rope 1 TLD Badges 10 Pocket Dosimeters (0-500mR)

  • 10 Dose Cards 25 b Dosimeter Charger 1  !

Radioactive Material Tags 50 Floor and Vent Covering 1 t Disposable Coveralls 25 i Disposable Shoe Covers (pairs) 25 i Disposable Hoods 10 ,

Cubitainers 5 Y Decon Kit 1 i

1) Rad Con i
2) Rad Wash
3) Osper Towels
4) Scrub Brush "
5) Cotton Swabs k
6) Fingernail Clippers b
7) Phischex (125 al) !I
8) Personnel Decontamination Forms R Cotton Gloves (pairs) 50 N Rubber Gloves (pairs) 20 Batteries (Size D)

Grease pencils (box) 8 b 1 I.

HP/0/B/1004/06 1 HP/0/B/1009/08 1 '

This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed.

6 i

Signature /Date

  • Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).

a CATAVBA NUCLEAR STATION OPERATIONS SUPPORT CENTER KITS CHICKLIST HP/0/I/1000/06 ENCLOSURE 5.11 MININUM ITEM AMOUNT DEV.*

List of Contents 1 Protective Clothing (Set) 40 Full Face Respirators with High Efficiency Filters 10 Flashlights 11 Batteries (Size D) 34 Batteries (9 volt) 20 Eberline PIC 6A 5 RM-14 w/HP-210 Probe 1 E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Camera (Polaroid) 1 Polaroid Film Pacs 2 Masking Tape (Roll) 2 Dosimeters (0-100R), (0-5R) 5 Dose Cards 25 Dosimeter Charger 1 Small Sample Bottles or Medication Envelopes 10 Rain Suits 5 Poly Bass (various sizes) 50 Radeco H809V Air Sampler 3 Silver Zeolite (CP-100G or GY-130) Filter Cartridges and Particulate Filters 30 Filter Cartridge Labels 30 Potassium Iodide Tablets (bottle) 20 KI Distribution Data Sheet 10 HP/0/B/1004/06 1 Decon Kit 1 )

1) Rad Con
2) Red Wash
3) Paper Towels ;j Scrub Brush
4) *
5) Cotton Swabs
6) Fingernall Clippers
7) Phischex (125 al)
8) Personnel Decontamination Forms i Instrument / Smear Survey (pad) 1 Telephone 2 Post-Accident Containment Air Sampling Equipment Kit 1 Ptn (box) 1 Grease Pencil (and refills) (box) 1 Extension Cord (50 ft.) 2  ;

Extension Cords (25 ft.) 2 Stopwatch 2 ,

t,arge Battery Lanterns 4 i Plant Drawinss 1 4

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CATAWBA NUCLEAR STATION

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OPERATIONS SUPPORT CENITR KITS CHECKLIST HP/0/2/2000/06 ENCLOSURE 5.11 MINIMUM ITEM AMOUNT' DEV.*

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OSC Response Personnel Dose Record Forms 125 Seears (box) 1 This Kit has been intentoried and Steps 4.2.1.4 through 4.2.1.1.4, if applicable, have been completed.

4 Signature /Date

  • Any D'eviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
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( CATAWBA NUCLEAR STATION

( Page 1 of 2 TECHNICAL SUPPORT CENTER KIT CHECKLIST

/ HP/0/I/1000/06 ENCLOSURE 5.12 MINIMUM 117.M AMOUNT DEV.*

1 List of Contents 1 Protective Clothing (Set) 20 Tu'.1 Tace Respirators with High Efficiency Filters 6 _

Eberline E-520 w/HP-270 Probe 1 Eberline PIC-6A 3 E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Radeco H809V Air Sample 1 Dosimeter (0-100R), (0-5R) 6 each Dose Cards 25 Silver Zeolite (CP-100G or GY-130) Tilter Cartridges and Particulate Filters 30 Tilter Cartridge Labels 25

) Dosimeter Charger 1

Potassium Iodide Tablets (bottle) 25 l Soundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 3 Rad Tape 2 Seears (box) 1 Poly less 6 .

Masking Tape (Roll) 1-Pen 2 i Legal Pad 1 Grease Pencil (and refills) 1

{ Tlashlights 8

Batteries (Size D) 30 Batteries (9V) 12 3 Small Sample Bottles or Medication Envelopes 10 i Rain Suits 6 Decon Kit 1
1) Red con '
2) Red Vash
3) Paper Towels i
4) Scrub Brush

, 5) Cetton Swabs  :

6) Tingernail Clippers .
7) Phischex (125 al) ,
8) Personnel Decontamination Toros Instrument /Seear Survey (pad) 1 Request for Exposure Extension Toros 15 Plant Drawings 1 i MP/0/3/1009/16 1

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1 (CATAWBANUCLEARSTATION ( Page 2 of 2

' TECHNICAL SUPPORT CENIT.R KIT CHECKLIST i HP/0/N1000/06 ENCLOSURE 5.12 This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed.

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Signature /Date

  • Any Deviation vill be documented on the Emergency Equipment Deviation
Authorization Sheet (Sample Enclosure 5.14).

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( (Page1of2 CATAWBA NUCLEAR STATION FUEL TRANSFZR KIT CHECKLIST HP/0/3/2000/06 ENCIASURE 5.13 MINIMUM i ITEM AMOUhT DEV.*

List of Contents 1 Shoe Covers: disposable (pair) 20

, rubber (Pair) 6 Gloves: disposable (bundle) 1

,urgeons (box) 1 rubber (pair) 6 Coveralls: disposable 4 cloth 6

, Mcods 4 Wet Suit 2 Mard Hat 3 Full Face Respirators with High Efficiency Tilters 2 Radeco H809V Air Sampler 1 4

Eberline E-140N w/HP-210 Probe (o:t iquivalent) 1 Eberline PIC-6A 1 Eberline E-520 w/HP-270 Probe 1 Exempt Source 1 Silver Zeolite Cartridges and Particulate Filters 10

t Labels for Filters and Cartridges 10 -

Potassius Iodide Tablets (Bottle) 30 TLD Badge 5 Low /High Range Dosimeter W-500 mR), (0-SR) $ each l Dose Card 25 l Dosimeter Charger 1

Weather-Proof Caution Signs with Inserts 4 I Radioactive Waste Signs (4" x 6") 12
Caution
Radistion/ Radioactive Material Tags 12 50 yd. Roll of Barricade Tape (Magenta & Yellow) 4 Step Off Pads 3 Poly Bass 12

! Hand Gardening Spade 1

, Wide Mouth Sample Bottles 4 i

Plastic Sample Bottles or Medicatica Envelopes 12 Kiswipes (box) 2 NuCon hears 100 Copy of NAC-1 Drawings (Prints) 1

'i Copy of Loading and Unloading lastructions 1 Duct Tape (Roll) 2 Maskius Tape (1" and 2" Rolls) leach Contact Pyrometer with Probe 2 Safety Glasses 5 Binoculars 1 Tool Kit -

1 Batteries (9 Volt) '.

Flashlights 2

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Batteries (Size D) 13 Steno Pad with 2 Mechanical Lead Pencils 1 i Pencil Refills 1

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( Page 2 of 2 CATAWBA NUCLEAR STATION FUEL TRANST-2R KIT CHECKLIST WP/0/3/1000/06 ENCLOSURE 5.13 ITEM MINIMUM AMOUNT DEV.*

Grease Pencils All Purpose Marker 2 2

Scotch Tape Roll and Dispenser Roll of Dimes 1 1

Gasoline Generator (Gasoline Stored in Safety Cabinet) 1 Instrument /Seear Survey (ped) _

1 HP/0/3/1009/16 1

This Kit has been inventorted and Steps 4.2.1.4 through 4.2.1.14 applicable, have been completed. , if Signature /Date

  • Any Deviation will be documented on the E Authorization Sheet (Sample Enclosure 5.14).mergency Equipment Deviation k

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o pMirg,(o, UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 h

April 1, 1984

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50-414/413 Catawba MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Division of Rules and Records, ADM

SUBJECT:

REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be mAde public1 available.

/ /

. M. Felton, Director ivision of Rules and Recor 'g/*[

Office of Administration

Attachment:

As stated l

O. .. y Duxe POWER GOMPANY P.O. BOX 33180 CH.ARLOTrE. N.C. 28242 HAL B. TIJCKER TELEPHOST VICS PSERIDSwT (704) 373-4538 mmB ,-crm,. February 26, 1985 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414

Dear Sir:

Enclosed for NRC Staff use and review are two copies of the latest revision to the following Catawba Nuclear Station Emergency Plan Implementing Procedures:

1) RP/0/A/5000/02 7) HP/0/B/1009/13
2) RP/0/A/5000/03 8) EP/0/B/1009/14
3) RP/0/A/5000/04 9) HP/0/B/1009/15
4) RP/0/A/5000/05 10) OP/0/A/6200/21
5) RP/0/A/5000/13 11) HP/0/B/1000/06
6) HP/0/B/1009/04 Please delete privacy material in the form of personal telephone numbers prior to placing any material in the public document room, specifically:
1) RP/0/A/5000/02 Enclosure 4.1
2) RP/0/A/5000/03, Enclosure 4.1
3) RP/0/A/5000/04, Enclosure 4.1 .
4) RP/0/A/5000/05, Enclosure 4.1
5) RP/0/A/5000/13, Section 3.3 1
6) HP/0/B/1009/04, Enclosure 5.8 1

These revisions are being submitted in accordance with 10 CFR 50.54(q) and do not decrease the effectiveness of the Emergency Plan Implementing Procedures. I l

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Document Control Desk February 26, 1985 Page -Two-i By copy of this letter, one copy of each of the above documents is being provided to the NRC, Region II.

Very truly yours, l 1

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Hal B. Tucker RWO: sib Enclosures cc: w/ enclosures Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

[ .w/o enclosures NRC Resident Inspector Catawba Nuclear Station Robert Guild, Esq.

P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 213515 Devine Street Columbia, South. Carolina 29205 ,

Mr. Jesse L. Riley Carolina Environmental Study Group 854.Henley Place Charlotte, North Carolina 28207 1

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