Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 3 to EP G-251 Re Notification of Onsite Emergency Organization & Rev 7 to EP G-3 Re Notification of Offsite Organizations
	ML20137X193
Person / Time
Site:	Diablo Canyon
Issue date:	11/15/1985
From:	; PACIFIC GAS & ELECTRIC CO.
To:	;
Shared Package
ML20137X180	List: DCL-85-344, Forwards Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 3 to EP G-251 Re Notification of Onsite Emergency organization.W/851206 Release Memo; ML20137X193;
References
	PROC-851115, NUDOCS 8512100435
	Download: ML20137X193 (375)
	v • d • e

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PGandE Letter No.: DCL CURRENT ENERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3A a

TITLE REV E-0 Reactor Trip or Safety Injection 0 E-0.1 - Reactor Trip Response O E-0.2 ' Natural Circulation Cooldown 1

-E-0.3 Natural Circulation Cooldown with Steam Void in Vessel 1 (with RVLIS)

E-0.4 Natural Circulation Cooldown with Steam Void in Vessel 0 (Without RVLIS)

E-1 Loss of Reactor or Secondary Coolant 0 E-1.1 SI Termination 0 E-1.2 Post LOCA Cooldown and Depressurization 0 E-1.3 Transfer to Cold Leg Recirculation 0

, E-1.4 Transfer to Hot Leg Recirculation 0 E-2 Faulted Steam Generator Isolation 0-E-2.1 Alternate Auxiliary Feedwater Supplies 0 E-3 Steam Generator Tube Rupture O E CA-0. 0 Loss of All AC Power 0 ECA-0.1 Loss of All AC Power Recovery Without SI Required 0 ECA-0.2 Loss of All AC Power Recovery with SI Required 0 ECA-0.3 Restore. Vital Bus 0 ECA-1.1 Loss of Emergency Coolant Recirculation 0

.ECA-1.2 LOCA Dutside Containment 0 ECA-2.1 Uncontrolled Depressurization of All Steam Generators 0 ECA-3.1 SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired 0 ECA-3.2 SGTR with Loss of Reactor Coolant - Saturated Recovery Desired 0 ECA-3.3 SGTR Without Pressurizer Pressure Control 0 F-0 Critical Safety Function Status Trees 0

. ilt -S .1 . Response to Nuclear Power Generation /ATWS 0 FR-S.2 Response to Loss of Core Shutdown 0 FR-C.1 Response to Inadequate Core Cooling 0 FR-C.2 Response to Degraded Core Cooling 0 191-C.3 Response to Saturated Core Conditions 0 3 FR-H.1 Response. to Loss of Secondary Heat Sink 0 Response to Steam Generator Overpressure FR-H.2- 0 FR-H.3 -Response to Steam Generator High Level 0 FR-H.4 ' Response to Loss of Normc1 Steam Release Capabilities 0 8512100435 851115 -

PDR ADOCK 05000275 F PDR - . -

0603S/0038K , 11/15/85

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TABLE OF CONTENTS (Continued)

FR-H.5 Response to Steam Generator Low Level 0 FR-P.1 Response to Imminent Pressurized lhermal Shock Condition 0 FR-P.2 Response to Anticipated Pressurized Thermal Shock Condition 0 FR-Z.1 Response to High Containrent Pressure. O FR-Z.2 Response to Containment Flooding 0 FR-Z. 3 Response to High Containment Radiation Level 0 FR-I.1 Response to High Pressurizer Level 0 FR-I.2 Response to Low Pressurizer Level 0 FR-I.3 Response to Voids in Reactor Vessel 0 R-1 Personnel Injury or Illness (Radiologically Related) 15 and/or Overexposure R-2 Release of Airborne Radioactive Materials 5 R-3 Release of Radioactive Liquids 4 R-4 High Radiation (In Plant) 3 R-5 Radioactive Liquid Spill , 3 R-6 Radiological Fire >

9 R-7 Offsite Transportation Accidents 5 M-1 Employee Injury or Illness (Nonradiological) 13 M-2 Nonemployee Injury or Illness (Third Party) 11 M-3 Chlorine Release . 5 M-4 Earthquake 9 M-5 Tsunami Warning 5 H-6 Nonradiological Fire 11 M-7 Oil Spill Isolation and Clean Up Procedure 7 H-8 Containment Emergency Personnel Hatch 0 M-9 Hazardous Waste Management Contingency Plan 2 M-10 Fire Protection of Safe Shutdown Equipment, Unit 1 4 M-10 Fire Protection of Safe Shutdown Equipment, Unit 2 1 G-1 Accident Classification and Emergency Plan Activation 5 G-2 Establishment of the On-Site Emergency Organization 7 G-2 S1 Hotification of the On-Site Emergency Organization 3 G-3 Notification of Off-Site Organizations 7 G-4 Personnel Accountability and Assembly 6 G-5 Evacuation of Nonessential Site Personnel 3 m

s 0603S/0038K 11/15/85 e

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NUMBER EP G-251

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7Gsu3 Pacific Gas and Electric Company REVISION. 3

,m DATE 10/14/85.

OEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 2 1 2 OIABLO CANYON POWER PLANT UNIT NO(S)

EMERGENCY PROCEDURE nTLE: NOTIFICATION OF THE ON-SITE EMERGENCY ORGANIZATION IMPORTANT TO APPROVED: 77. E lo-lb UAlt 85 SAFETY .:

FLANI MANAbtM SCOPE This procedure supplement provides the call sequence for the notification of the on-site emergency organization, and indicates the preferred candidates to fill each position as required by ,

Administrative Procedure NPAP A-5. , ,

This procedure and changes thereto require PSRC review.

PROCEDURE Notification of required personnel in an emergency is made using the Rapid Alert Notification System (RANS) or call sequence of this supplement, Fonn 69-10297; " Emergency Organization Call List." RANS is'not intended for Unusual Event notification.

GROUP Call paging shall be initiated for the Emergency Organization Pager System intnediately upon activating RANS or the Emergency Organizati uring nonnel working hours, transmit the all l call signa 'er both the Health Physics repeater and local radio y a voice me aff nonnal working hours, transmit the all call signa refi'all three off site Health Physics frequency transmitters , TASSAJARA, TEPESQUET) and the MET building radio. These transmissions must be done separately to ensure complete area coverage.

I When using Form 69-10297, the preferred position holders should be contacted when possible. An "On-Call" rotation for essential positions in the emergency organization is maintained in accordance l with NPAP A-3, Supplement 1. The on-call person may be called if the

! preferred position holder is not intnediately available or whenever judged- necessary by the Shift Foreman. The primary means of notification during "off hours" or when the site emergency signal is

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V NUMSER EP G-251 t DIA8LO CANYON POWE4PtANT UNIT NO(S) 1 AND 2

REVISION 3 1 s' DATE - 10/14/85 PAGE 2 0F 2 _

TITLE: EMERGENCY ORGANIZATION CALL LIST FORM 69-10297 not sounded during normal working hours is the telephone. A backup means of notification is the pager for those individuals designated "0N CALL". Key plant managers have UHF radio equipped cars which can be used for initial contact and two way communications whfie enroute to the plant. Because these persons are essentially on-call at all times, use of these vehicles is warranted in off hours to ensure rapid .

consnunication and response.

SUPPORTING PROCEDURES NPAP A-5, " Organizational Control Of Emergencies" NPAP A-3, Supplement 1. "On Call System & Personnel Avatiability" ~

ATTACHMENTS

1. Description and Activation of the Rapid Alert Notification System.

2. Form 69-10297. " Emergency Organization Call List"

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10/85- PACIFIC GAS AND ELECTRIC COMPANY Page 1 of A DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 ATTACHMENT 1 TITLE: DESCRIPTION AND ACTIVATION OF THE RAPID ALERT NOTIFICATION SYSTEM (RANS)

The RANS will begin the onsite emergency organization call-out when activated and deliver a pre-selected message. The person called should respond with an acknowledgement code. The RANS has the capacity to contact up to 512 individual people. There are ei The RANS dials numbers sequentially'ght by listlists andand within up to 64 groups each list, sequentially in each list. by group. When a call is made, it is either logged acknowledged or not acknowledged.. If the

. call is logged not acknowledged, RANS will continue to call the remaining numbers in that group until an acknowledgement or the programed number of notification attempts is reached. Once a call is acknowledged, the system will no longer attempt to call anyone else in that group. The system can deliver up to eight different messages. For Diablo Canyon these messages are:

1.

2. Alert '

Diablo Canyon has declared ari Alert. Dial - *

, acknowledgement code.

3. Site Area - Diablo Canyon has declared a Site Area Emergency Emergency. Dial acknowledgement code.

4. Generai - Diablo Canyon has declared a General Emergency.

Emergency Dial acknowledgement code.

5. Test - This is the Diablo Canyon call-out system test. Dial acknowledgement code. No response is required.

6. This is - Alert - Diablo Canyon is simulating an Alert. Dial a Drill acknowledgement code.

7. This is - $1te Area Emergency - Diablo Canyon is simulating a Site a Drill Area Emergency. Dial acknowledgement code.

8. This is - General Emergency - Diablo Canyon is simulating a

, a Drill General Emergency. Dial acknowledgement code.

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TITLE: DESCRIPTION AND ACTIVATION OF THE RAPID ALERT NOTIFICATION SYSTEM (RANS)

ACTIVATION OF THE RANS SYSTEM:

There are two parts to the RANS, the data terminal and the front panel. The system is located in the Control Room Shift Foreman's Office.

There are two ways that the RANS system can be activated:

1. Through the Data Terminal

2. Through the Front Panel Keyboard Before the system is activated, the user should know the access code, which lists to be called, and what message is to be delivered. The access code can be obtained by contacting the Shift Foreman. The message to be delivered is determined by the emergency classification.

EMERGENCY CLASSIFICATION LISTS TO BE MESSAGE TO BE SELECTED , DELIVERED ,

ALERT 1, 2, 3 2 SITE AREA EMERGENCY 1, 2, 3 3 GENERAL EMERGENCY 1,2,3 4 g: THE RANS IS NOT INTENDED FOR UNUSUAL EVENT NOTIFICATIONS.

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10/85 .

Page 3 of 4 TITLE: DESCRIPTION AND ACTIVATION OF THE RAPID ALERT NOTIFICATICN SYSTEM (RANS)

To Activate From The Data Teminal:

1. Verify that power is available to the printer.

The green light at the bottom right corner should be on. If this light is not on;

a. Check to make sure printer is on. The switch on the top of the printer should be in the on position. You should see a red dot.

b. Check to make sure the printer is on-line. The switch next to the green light is the on-line switch. It should be pushed down on the side that has the red dot.

2. Enter the Access Code and press the " return" key.

! 3. The system will proceed through a "self-test." It will print the j number of operative phone Ifnes and the time.

4. To start the notification process, type "S." .-

S. The teminal will then request which ifsts are to be called. Enter the correct lists and press the " return" key.

6. The teminal will request which message is to be delivered. Enter the appropriate message number and press the " return" key.

5 The system is activated and will begin the call-out sequence.

g: If, during the activation, you need help, type " shift 7" and the syt tem will respond with more infomation.

i To STOP the system at any time, press the BREAK key. The RANS will automatically reset. The user must again enter the access code to activate the system.

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10/85 Page 4 of 4 TITLE: DESCRIPTION AND ACTIVATION OF THE RAPID ALERT NOTIFICATION SYSTEM (RANS)

To Activate From the Panel Keyboard: ,

The Automatic Notification Mode can be activated by entering the access code into the front panel keyboard. Be sure to use slow, deliberate strokes. If the access code was accepted, the " Wait" light should start blinking. If this light is not on, depress the BREAK key on the Data Terminal and try entering the access code again.

1. When the " Ready" light appears, the system is ready to accept conmands.

2. To select the phone lists to be called, type the

and then the appropriate .

list. .

3. Repeat this for each list to be called.

4. To select the message to be delivered, type the number key "#" and then the message number.

5. The phone lists and the message number should light up on the front panel.

If they are not correct, type the " H" key twice and reenter the phone =

lists and message.

6. If the lights are correct, type the ** key twice to start the call-out process.

g: To STOP the system at any time, press the BREAK key. The RANS will automatically reset. The user must again enter the access code to .g activate the system. ,

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69-10297 10/85 (100) f EE RGENCY ORGANIZATION CALL LIST DATE:

TIME EVENT CLASSIFIEL:

EVENT CLASSIFICATION:

EVENT DESCRIPTION:

CALL OUT INSTRUCTIONS

1. Contact one person for each position.

2. First name on list is preferred position holder; if unavailable contact next available person.

3. Persons with a

are designated for "on-call" rotation.

4. Give emergency classification and describe event if requested.

M)1E: Personnel to report to assigned locaticn for Alert classification or higher; optional for Unusual Event.

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EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ.

ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME d!LL BE IN POSITION AVAILABLE UN-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Site Emergency *1. R.C. Thornberry 3

Coordinator Plant Manager l

Assigned - TSC

2. J. M. Giscion Tech Services Mgr

3. W. B. McLane -

l Materials & Project

Coordination Manager 1

*4. J. A. Sexton Operations Ma' nager __

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ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN-POSITION AVAILABLE ON-3LL NAME/NON-EMERGENCY TITLE PLANT PHONE CROUP CALL # CONTACTE0 YES NO Emergency *l. R. Patterson Operations Plant Superintendent

. Coordinator Assigned - *2 S. R. Fridley Control Room Gen Operating foreman

! *3. J. R. Tinlin j Sr Trng Instructor i

{ *4. R. L. Fisher i Sr Power Prod Eng _

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OF:GANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL DE IN PLANT PHONE GROUP CALL # CONTACTED YES NO POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE Emergency 1. J. M. Gisclon ]i Evaluation Tech Services Manager .

& Recovery -

Coordinator

! *2. L. F. Womack Engineering Manager l .

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. Sr Power Prod Eng Assigned - TSC

4. M. J. Angus Power Prod Eng .

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ORGANIZATION DATE NOT DATE HOME P110NE/ PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Emergency *l. J. V. Boots Radiological Chem & Rad Prot Mgr Advisor Assigned - TSC *2. R. P. Powers Sr Chem & Rad Prot Engr

3. H. W. C. Fong Chem & Rad Prot Eng _.

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l TIME WILL BE IN j ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL #

AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO

POSITION Emergency *l. T. J. Martin Liaison Training Manager Coordinator

2. J. E. Holden I

Assigned - TSC Ops Trng Supervison

3. W. F. Steinke Sr Trng Instructor ___

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EMERGENCY TIME WILL BE IN DATE NOT DATE HOME PHONE / PAGER CALL #

ORGANIZATION CONTACTED YES NO AVAILABLE ON-CALL NAME/NON-EHERGENCY TITLE PLANT P110NE GROUP CALL i POSITION Adviso.r to the *l. W. B. Kaefer County Emerg. Support Services Ngr Organization Assigned - EOF *2. W. J. Keyworth Sr Power Prod Engr (Emergency Planning)

3. W. S. Joiner Coordinator (Emergency Planning)

4. Tom Brake Sr Power Prod Engr (PIMS) _

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EMERGENCY DATE NOT DATE HOME Pil0NE/ PAGER CALL f TIME WILL BE IN ORGANIZATION NO ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE _ _ GROUP CALL # CONTACTED YES POSITION AVAILABLE Emergency Hone 1. J. A. Sexton Operatices Operations Manager Advisor Assigned - TSC 2. S. R. Fridley Gen Oper ning Foreman ___

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4. R. L. Fisher Sr Fower Prod Eng (Operations) 1 I

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ORGANIZATION ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL _f C0hTACTED YES NO .

POSITION AVAILABLE f Emergency Main- *l. D. 8. Miklush tenance Coor- Maintenance Manager dinator

2. W. G. Crockett l Assigned - OSC i I&C Maintenance Mgr I

3. R. Nanninga Sr Pow Prod Eng (Maint)

4. D. L. Bauer -

l Sr Power Prod Eng (Maint) t l

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ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # T!HE WILL BE IN' POSITION AVAILABLE ON-CALL NAME/NON-EHERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES N0 Media Information , ,

Specialist None 1. Ron Weinberg News Services Diablo Canyon

2. David Honfried (Home)

News Services Manager (PG&E)

San Francisco, G.O.

3. Don Hanes (Home)

News Services Director (PG1E)

San Francisco, G.O.

4. Jim Kilpatrick (Home)'

News Services Director (PG&E)

San Francisco, G.O.

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STOP CALL-0UT AT THIS FOINT FOR TE IMJSUAL EVENT CLASSIFICATION - Q]NTIME FOR HIGER CLASSIFICATION, l

DETEIMIE IF llE SITE EPDGENCY 000HDINATOR EQUIES ADDITIONAL KRS0MEL.

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ORGANIZATION DATE NOT DATE HOE PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILA8LE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL f CONTACTE0 YES NO Operational None 1. S. J. Foat Support Center Electrical Engineer Supervisor :

2. R. 8. Willis Assigned - OSC Mechanical Engineer

3. R. T. Hanson Electrical Engineer

4. D. R. Stupi Welding Engineer

5. R. P. Warren Maintenance Engineer i

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DATE NOT DATE HOME P110NE/ PAGER CALL i TIME WILL BE IN ORGANIZATION NO NAME/NON-EMERGENCY TITLE PLANT Pil0NE GROUP CALL # CONTACTED YES POSITION AVAILABLE ON-CALL Site Chemistry *l. H. A. Ferguson

& Radiation Chem & Rad Pret Foreman Protection Coordinator *2. L. T. Moretti Chem & Rad Prot Foreman Assigned -

Access Control *3. R. L. Johnson Chem &' Rad Prot Foreman

4. F. A. Guerra Chem & Rad Prot Foreman

5. J. A. Robbins Chem & Rad Prot Foreman i

i *6. L. Vulchev Chem & Rad Prot Foreman l

.s NOTE: The person assigned this position also assures that adequate Chemistry and Radiation Protection Technicians are available. As a minimum this includes:

l l Six C&RP technicians for on-and-off site monitoring teams.

! Six C&RP technicians for in-plant monitoring and chemistry.

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-ORGANIZATION DATE NOT DATE GROUP CALL # CONTACTED YES NO ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE POSITION AVAILABLE

1. C. D. Lampert l TSC/E0F None l Clerical Office Supervisor !

Assistance l

2. E. G. St. John Asst Office Supervisor l I

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3. D. W. Swearingen Asst Office Supervisor l l

NOTE: Request supervisor to dispatch three (3) clerks to the TSC and two (2) clerks to the E0F.

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ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE, ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Interim None 1. S. J. Fahey-Benson i Radiological Chem & Rad Prot Eng

Emergency Recovery Manager 2. D. Chen Chem & Rad Prot Eng

Assigned - EOF l

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GRGANIZATION DATE NOT DATE HOE PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO

1. M. W. Mak l Interim None EOF-EAAS Computer Specialist ,

I Operator

2. D. R. Clifton Assigned - EOF Maint Trng Supervisor 5

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DATE NOT DATE HOME Pil0NE/ PAGER CALL # TlHE WILL BE IN ORGANIZATION N0 AVAILA!:tE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES POSITION Interim None 1. W. T. Rapp Operations Sr Nuclear Gen Engr and Analytical Recovery 2. K. C. Doss Manager Sr Nuclear Gen Engr Assigned - EOF 3. D. D. Christensen Nuclear Gen Engr j

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l 69-10297 10/85 (100) ,,,

EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EHERGENCY llP FREQ.

' ORGANIZATION DATE NOT DATE HOME PHONE / PAGER (,ALL # TIME WILL BE IN PLANT PiiONE GROUP CALL i CONTACTED YES NO POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE Hobli 1. Roland Richardson Environrnental Dept of Engr Research Monitoring *

,- Laboratory Operator 2. Mike Kunde Dept of ErJr Research -

/

e, DC0234 CONTROL R00H ASSISTANT-22Vil 1. Insert date pert is not available. Page 20 0F

2. Insert Date per.s'oi~a.ssumes G

- no .- .. . . . . . .. .".on-call"

.. responsibility.,soog

, , ,, i , .m , i

69-10297 10/85 -(100) , ,,

EMERGENCY OPGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EHERGENCY llP FREQ.

0RGANIZATION I DATE NOT DATE Il0HE Pil0NE/ PAGER CALL # TlHE WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PliONE GROUP CALL # CONTACTED YES . N0

EARS Operator *l. R. H. Garacci TSC Sr C&RP Analyst Assigned - TSC

2. E. R. Psoter '

C&RP Analyst ,-

3. J. N. Johnson C&RP Analyst l

ll l

J I

DC0234 C0liTROL R00H ASSISTANT:

23Vil 1. Insert date person is not available. Page 21 0F 32 y 2. Insert Date person assumes "on-call" responsibility.

(Porson on call will possess the paner for this position)

4 69-10297. 10/85 (100) '

EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISr.LOSURE EMERGENCY HP FREQ.

ORGANIZAIl0N DATE NOT DATE HOME PHONE / PAGER CALL i TIME WILL BE IN POSITION AVAILABLE' ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Emergency 1. J. E. Holden Liaison- Training Supervisor -'

Assistant il /

2. B. E. Terrell Training Instructor

3. W. E. Weems Training Instructor

4. G. W. Hamann -

Training Instructor

5. J. M. Welsch l , Training Instructor __

NOTE: . Contact Two people from this list. l I

Only one "on-call" person for this position.

i .

4

. DC0234 CONTROL ROOH ASSISTANT-24VII 1. Insert date pars , . not available. Page 22 0F -

2. Insert Date person ossumes "on-call" responsibility. _,

i toa-ena an call will oncencs tho naner for this position)

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69-10297 10/85 (100) , ,

EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE I EMERGENCY llP FREQ.

- DATE NOT DATE 110ME PHONE / PAGER CALL # TIME WILL BE IN

.0RGANIZATION No AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT Pil0NE GROUP CALL # CONTACTED YES i POSITION Emergency *1 R. L. Graham Liaison Sr Trng Instructor

, Assistant #2

2. B. A. Lewis A'ss.igned - TSC Asst Trng Coordinator

3. L. R. Sawyer Asst Trng Coordinator

4. J. H. Becerra Training Instructor i

l

S. C. J. Leach Training Instructor

6. N. M. Bennett Training Instructor ____

NOTE: ' Contact THREE people from this list.

Only one "on-call" person for this position.

.s DC0234 CONTROL R00H ASSI$ TANT:

25VII 1. Insert date person is not available. Page 23 Of 32

2. Insert Date person assumes "on-call" responsibility.

IPerson on call will nnssess the nacer for this positinni ,

.- j

,. i

.69-10297 10/85 (100) '

I

[HERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ.

DATE NOT DATE Il0HE PHONE / PAGER CALL # TIME WILL.BE IN ORGANIZATION NO ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES POSITION AVAILABLE Data Processer *l. T. H. Black Ho. 1 Power Prod Engr (Computer)

Assigned - TSC

- *2. G. V. Johnson Power Prod Engr (Computer)

3. J. K. Bigelow Power Prod Engr (Computer)

4. J. D. Lodge Power Prod Engr (Computer)

S. D. A. Remington Power Prod Engr (Computer)

6. G. R. Wescom Appitchttons Analyst _ . _ _ .

DC0234 CONTROL R00H ASSISTANT:

1. Insert date perr, is not available. Page 24 0F 26VJI x..s

<- 2. Insert Date per'Sw.. assumes "on-call" responsibility. .

l toarena na call will nnscats the naner for this nnsition) j

~

69-10297 10/85 (100) ,, s EMERGENCY.0RGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ.

ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL F TIME WILL BE IN POSITION AVAILABLE OH-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO .

~~

Data Processor *l. P. W. Baum No. 2 & No. 3

. *2. W. A. Ginter Assigned - TSC l

3. P. E. Rigney I

4. R. D. Thurston l *5. K. W. Wallace I

{ *6. W. H. Yip l *7. C. N. Pendleton

! *8.~ J. I. Hjalmarson ,

9. P. G. Sarafian f

10. D. L. Efron

11. C. H. Beall .

l *12. J. C. Nolan NOTE: Contact TWO people from this list.

Only one "on-call" person for this position. ,.

l 1

i e'

4 DC0234 CONTROL ROOM ASSISTANT:

27VII 1. Insert date person is not available. Page 25 0F 32 i

2. Insert Date person assumes "on-call" responsibility, (Person on call will possess the paner for this position)

m 69-10297 10/85 (100) .. s EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EHERGENCY HP FREQ.

ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL f TIME WILL BE IN

' POSITION AVAILABLE ON-CALL HAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Instrument *l. H. P. Hanrahan Haintenance Sr I&C Supervisor Coordinator

2 D. D. Halone Assigned.- OSC Sr. I&C Supervisor

3. N. A. Regolf I&C Supervisor 1

l t

DC0234 CONTROL R00H ASSISTANT-28VII 1. Insert date persg ; not available. Page 26 0F c' 2. I.nsert Date pe.rsos.a'ssumes ".on-call".. responsibility.

- . , i ...... .u. ... <-. 6 , --......;

1 69-10297 10/85 (100) ,. s EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE' EMERGENCY HP FREQ.

ORGANIZATION DATE NOT DATE HOME Pil0NE/ PAGER CALL i TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME.'NON-EMERGENCY TITLE PLANT Pil0NE GROUP CALL # CONTACTED YES NO Electrical *l. G. M. Zocher Maintenance Gen Elec Foreman Coordinator

2. J. M. Rappa Assigned - OSC Elec Foreman

3. Clay R. Beck -

Electrical Foreman

4. Larry D. Cobbs Electrical Foreman l

l t

t c ;

DC0234 CONTROL R00H ASSISTANT:

29VII 1. Insert date person is not available. Page 27 0F 32

<' 2. Insert Date person assumes "on-call" responsibility.

(Person on call will possen the paqer for this position)

T 69-10297 10/85 (100) .. s EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE

'EMERdENCY HP FREQ. .

ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL DE IN-POSITION AVAILABLE OH-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL i CONTACTED YES NO Mechanical *l. W. R. Ryan Maintenance Gen Maint Foreman Coordinator

2. J. D. Albers Assigned - OSC Mech Foreman

. *3 J. E. Strahl I Mech Foreman

4. G. H. Brodnick Mech Foreman I

5. J. D. Askins Mech Foreman i *6. R. J. Gilman Mech Foreman _

l l

's DC0234 CONTROL ROOM ASSISTA"T:

30VII 1. Insert date per( is not available. Page 28 Of ? ,.

2. Insert Date pe.rson.'.a.ssumes ".on-call"... responsibility.

- . . .u. .. a.. .us. ...s.t..s

_ _ _ __ ____ __ {

69-10297 10/85 (100) ,

l EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ.

ORGANIZATIDH DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL DE IN .

AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO POSITION Radiological None 1. A. O. Taylor Data C&RP Engineer Processor

2. R. S. Snyder Assigned - TSC C&RP Foreman

3. D. R. Unger C&RP Engineer 4

t

. 1 DC0234 CONTROL ROOM ASSISTANT:

31Vil 1. Insert date person is not available. Page 29 0F 32

2. Insert Date person cssumes "on-call" responsibility.

f (Person on call will possess the pager for this position)

, s

69-10297 10/85 (100)

EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ.

DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL GE IN

' ORGANIZATION PLANT PHONE GROUP CALL i CONTACTED YES NO POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE

~ '

, Radiological None 1. K. R..Bie'ze Data - Sr Trng Insttuctor Processor .

2. G. P. Monk .'

Assigned - EOF Trng Instructor

3. C. J. Hansen Trng Instr'uctor

. E : . Contact TWO people from this list.

J s.

1 4

l g

'd

,c..

DC0234 CONTROL ROOM A.SSISTANT:

32VII 1. Insert date not available. Page 30 0F T

2. Insert Date'personperson(_jumes "on-call" responsibility. ( e,. ' T.

i.]

L '- '

(Person on call will possess the pager for this position) ;

.-m..,-- . t 1 AND 2 NUMBER EP FS-15 ,

DIASLO GANYON POWER PLANT UNIT NO(S) REVISION 2 l

. DATE 8/26/@S PAGE 2 0F 4 TiTm POST ACCIDENT SAMPLING SYSTEM

c. Remote Containment Hydrogen Analysis This general procedure is made up of several specific procedures detailing Sentry access / egress, the steps to obtain the required samples for the initial sample exercise following an accident and disposal or storage of samples. This procedure may be used again for subsequent sample exercises if the same information is required at a later time. For any other type of a sample, procedure EP RB-16 will give full details on the types of sample and the various analyses that can be performed as well as the specified procedures for obtaining samples.

This procedure and the procedure listed below, and changes thereto, r g ire PSRC review.

PROCEDURE -

1. Specific Procedures ',

The detailed instructions for performing the sampling outlined in the Scope of this procedure are covered in the following sub-procedures:

EP RB-15:A -- Initial Actions l This procedure details necessary steps for accessing and egressing the lab, Gas Chromatograph I

startup, initial system lineup, and annunciator testing.

EP RB-15:B -- Reactor Coolant Samolino l

This procedure details the steps required for sampling any one of 5 diffemnt sample sources and obtaining a stripped gas sample and making available for gas chromatographic analysis.

EP R8-15:C -- Containment Air Samolino I

This procedure details the steps required to make containment air available for gas chromatographic analysis and to dilute containment air fer isotopic analysis.

~

l l OC0124 2VI i

vv -

m +m-w - - w- -- = - - ,- -----n- - - - - - - - - - = - - - - , - - - - - -----,4--* - - --, r w- --- - --

- NUMBER EP RS-15 T G5143 Pacific Gas and Electric Company REVISION 2

<- ame DATE 8/26/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS I AND 2 DIA8LO CANYON POWER PLANT UNIT NO(S)

I EMERGENCY OPERATING PROCEDURE Titts. POST ACCIDENT SAMPLING SYSTEM ,

APPROVED Y. b b SAFETY PLANTMANAGEp DATE SCOPE Nureg 0737 requires samples to be taken and anal,yzed within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months after the decision is made to take a sample. Th.'s procedure is designed to ensure safe and reliable methods to 6eet this requirement.

The samples that will be collected and analyzed from this procedure are as follows:

1. For RC (Reactor Coolant) Samples:

a. In-line pressurized flask with off-gassing for:

1) Gas Chromatograph Analysis

2) Diluted stripped gar M41as for isotopic analysis

b. Diluted RC samples:

1) Baron analysis

2) Isotopic Analysis

c. In-Line analyses:

1) Ion chromatographic analyses for chloride

2) pH/ conductivity / dissolved oxygen

2. For CA (Containmer.t Air) Samples:

a. Diluted CA samples for isotopic analysis

b. Gas Chromatograph Analysis l

DC0124 IVI j l

i l

f

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

69-9259 7/85 (1000) Page 3 c' 2 TITLE: EMERGENCY ENVIRONMENTAL MONITORING FIELD DATA SHEET

9. LIQUID SAMPLES TIME OF SURVEY VOLUME OF IP9tERSION DATA

_ SAMPLE DESCRIPTION SAMPLE COUNTED GR055 CPM - 5CKG(60)

NET CPM

10. MISCELLANE0US REMARKS

- If 240/270 probe is used, cpm BCKG equals 60 tt - If R0-2 is used BCKG = 0

- - If 240/270 probe is used, e equals 0.0003 t - If 240/270 probe is used, e equals 0.08 f

G M

d O

I 4

DC0182 40!II

69-9259 7/85 (1000) Page 2 of 3 4 .. TITLE: EMERGENCY ENVIRONMENTAL: M0'NITORl'NG FIELD DATA SHEET

3. PARTICULATE DETERMINATION l com (WINDOW OPEN) (2)- (uci/cc) i TYPE cit E VOLUME (1) X 1.59 X 10 11 0F PROBE GROSS 8CKG*(50) = NET (1) (0.10)(0.I9) (ft 3

) (0.10) X (0.99) I (2)

4. IODINE DETERMINATION com (WINDOW OPEN) (2)

TYPE e ** E C

VOLUME ((uCf/cc)1) X 1.59 X 10~ -

0F PRO 8E GROSS 8CKG(50) NET (1) (8.003)(O94) (ft 3) (0.003) I (0.94)X(2)

5. PIC READING CAL DUE DOSERATE(uR/hr) ,

6. GROUNO SURVEYS TIME DESCRIPTION - mR/hr (At meter) fuCf/m2 }

F TOtXTTON sness scKutt(.015) = NET 1 (1? x (238)

)

7. VEGETATION SAMPLES TIME OF SURVEY _

ege (WINDOW OPEN) (uC1/kg)

SAMPLE DESCRIPTION unuss - scKs(60) = nei (1) 1 x (z.5 x 10 '

8. SMEAR SAMPLES TIME OF SAMPLE cpm (5HIELD0FF) (dpm/dn} 2 t (1?

SAMPLE DESCRIPTION GROSS - 8CKG*(50) = NET (1) c;0.10) ( (0.LO) _.

DC0182 39111

- - - - -- y we,-r- v -r-r--=-*eem ,'ww-=w--wr" * * * - ' ' " = - - - - ' ' - ' - ' - ' - - - - - ~ - - - - - - ' - - - - - - - - - - - - - - - - ^ - - - - - -

69-9259 7/85 (1000) pase 1 of 3 p

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: EMERGENCY ENVIRONMENTAL MONITORING FIELD DATA SHEET DATE TEAM LEADER MEMBER MONITORING LOCATION ($)

' Count Rate Cal. Due Serial #

Dose Rate Cal. Due Serial #

M: Performance Test all portan1e monitoring equipment prior to entering fieid.

1. BETA /GA M A RADIATION FIELD MEASUREMENTS

a. COUNT RATE com (WINDOW DOWN) com (WINDOW UP)

TYPE OF PROSE TIME GROSS - BCKG*(50) = NET GROSS - BCKG*(50) = E N.ET

'l

b. DOSE RATE mR/hr CWINDOW OPENl mR/hr (WINDOW CLOSED) i INSTRUMENT TIE GROSS - scKsttt .oI5) = ntl Gross - scKsttt.015) = E

c. INTEGRAL DOSE (3) (5)

(1) (2) DURATION (4) DOSE RATE TIME TIME (H0URS) TOTAL DOSE er/h.-)

INSTRUMENT STARTED COMPLETED (2) - (1) (mR) 4) * (3) l l

2. AIR SAMPLE (1) (2) (1) x (2)

TIME- TIME DURATION FLOW RATE SAMPLE VOL SAMPLER STARTED COMPLETED (MINUTES) (CFM) (FT3 )

l l

1 l

l DC0182 38III l

l

DAss.o canyon POWER PLANT UNIT NO(S) -

1 AND 2 lPRB-8 DATE 8/2/85 PAGE 37 0F '37 EMERGENCY OFFSITE RADIOLOGICAL Tiu ENVIRONMENTAL MONITORING TABLE 4 PIC LOCATIONS LOCATION DESCRIPTION Site 1 DCPP North Gate Guard Post Site 2 SSW Corner of Target Range i Site 3 715 Harbor Street. Morro Bay. Small fenced yard on NE corner of Harbor Street and Piney Street intersection.

Site 4 Montana de Oro State Park. At the Park #

Ranger's residence, adjacent to the emergency stren.

Site 5 Los Osos Fire Department Site 6 Outside rear entrance to (South side of Building) EOF Site 7 SLO Police Department. Intersection of Santa Rosa Street and Walnut Street.

l Behind fence SW of Walnut Street driveway.

! Site 8 SLO Service Center Site 9 PGandE Energy Information Center l Site 10 DCPP Front Gate

$1te 11 Pismo Beach. From 8ellow Street go N.E. turn between Veterans's Memorial and St. Paul's Church and proceed up dirt road. PIC is on top of hill north of pump house and west of water storage tank inside a locked chain link fence. Combination available from MEML personnel or RERM in the EOF.

Site 12 SLO County Building. Grover City. Exit

Hwy.101 at 4th street. Take 4th to i Longbranch and proceed NE on Longbranch.

County Social Services Building is on corner of 16th and Longbranch.

DC0182 37IX

o

, DIASLO CANYON POWER PLANT UNIT NO(S) -

1 AND 2 NUMBER EP RB-8 REVISION 5 DATE 8/2/85

M ' EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 3 LOCATIONS OF SELECTED DAIRIES DAIRY HERO LOCATION RELATIVE TO DCPP L.F. Domenghini (500 cows) NME, 12.5 miles RoemerandJones(200 cows) NME, 11 miles Dutch Maid Farm (100 cows) NE, 8 miles Don Warden (200 cows) NE, 8 miles JimSpreafico(150 cows) E, 9.5 miles ,

SLO Cal Poly Farm ENE, 10 miles Albertant Farm SE, 23.5 miles (Guadalupe)

DC0182 36IX

a DIA8LO CANYON POWER PLANT UNIT NO(S) -

1 AND 2 l SON5 DATE 8/2/85 PAGE 35 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE.

ENVIRONMENTAL MONITORING TABLE 2 (Continued)

Radial Radial Distance

Code Description Direction 0* (Miles) 8S2 Southwes t Si te Bounda ry ( Sta ti on 7 ) . . . . . . . . . . . . . . 128 1.1 951 South Cove (Station 37).......................... 167 0.4 DCC Diablo Creek at Diablo Cove (Station 21)......... 270 0.1 DCM Diablo Cove (Station 19)......................... 270 0.2 ICO Iodine Cartridge Composite....................... 0 0.0 LO L ompoc (a t Ci ty Ha 11 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 154 44.6 MT1 Meteorological Tower (Station 1).... . . . . .. ... . . .. 185 0.2 SM Santa Ma ri a (a t Heal th Dept. ) . . . . . . . . . . . . . . . . . . . 127 29.7 SV Sol vang (at Sheri ff 's Subs tation) . . . . . . . . . . . . . . . . 144 56.7%

WN1 Northwes t Guard Shack (Station 2) . . . . . . . . . . . . . . . . 290 0.2 l

i_

DC0182 35IX l

DIASLO CANYON POWER PLANT UNIT NO(S) ' 1 AND 2 S ON DATE 8/2/85 .

PAGE 34 0F 37 l tit a EMERGENCY OFFSITE RADIOLOGICAL I ENVIRONMENTAL MONITORING TABLE 2 DER ENVIRONMENTAL SAMPLING LOCATIONS Radial Radial Distance Code Description Direction 0* (Miles) 081 Poi nt 8uchon (Sta tion 18) . . . . . . . . . . . . . . . . . . . . . . . . 325 3.6 051 320 0.1 052 1A1 North Ga te (S ta tion 31) . . . . . . . . . . . . . . . . . .

Crowba r Canyon ( S ta ti on 13) . . . . . . . . . . . . . . . . . . . . . .

320 . 0.5

.. ).....E 327 1.6 1C1 Mon ta na de Oro Campground ( S ta ti on 38 ) . . . . . . . . . . . 336 4.7 151 Was tewa ter Pond (Station 32) . . . . . . . . . . . . . . . . . . . . . 330 0.4 201 Sunnys i de School (S ta tion 10) . . . . . . . . . . . . . . . . . . . .

4 2F1 Morro Bay (Station 26)...........................

10 6.A 0 10.9 2F2 Morro Bay Power Plant (Station 9). . .. . . . .. ..... . . 358 11.2 251 301 Back Road-300 m North of Plant (Station 33)...... 0 0.2 Cla rk Val ley (Station 40) . . . . . . . . . . . . . . . . . . . . . . . . 24 6.2 3S1 Road NW of 230 kV Switchyard (Station 34)........ 23 0.4 4C1 Cla rk Val ley - Gravel Pit. . . . . . . . . . . . . . . . . . . . . . . . 45 5.8 ,

401 Los Osos School (Sta ti on 11) . . . . . . . . . . . . . . . . . . . . . 36 7.6 /

451- Back Road Between Switchyards (Station 35)....... 43 0.5 SC1 Junction Perfumo/See Canyon Roads (Station 39)... 64 4.7 SF1 SLO Zone 1 Subs ta t ion (S ta tion 12) . . . . . . . . . . . . . . . 68 11.2 SF2 Cal Poly Fa rm (S ta tion 25) . . . . . . . . . . . . . . . . . . . . . . . 60 12.6 5F3 551 SLO County Health Department (Station 29)........

400 kw Swi tchya rd ( S ta ti on 4) . . . . . . . . . . . . . . . . . . . .

70 12.7 58 0.4 552 Diabl o Creek Wei r (Station 20) . . . . . . . . . . . . . . . . . . . 65 0.6 553 Microwave Tower Road (Station 8) . . . . . . . . . . . . . . . . . 70 0.7

', 601 Junction See/ Davis Canyon Roads (Station 41)..... 89 7.5 651 Microwave Tower (Station 5 ) . . . . . . . . . . . . . . . . . . . . . . 94 0.5 7C1 Pecho Creek Rui ns (Sta tion 16) . . . . . . . . . . . . . . . . . . . 118 4.1 701 Avi l a Ga te ( S ta tion 27) . . . . . . . . . . . . . . . . . . . . . . . . . . 120 6.6 7D2- Avila Beach S ta ti on 14 . . . . . . . . . . . . . . . . . . . . . . . . . 110 7.6 7F1 7F2 Shell Beach Station 17 ......................... 110 10.8 Pismo Beach S ta ti on 22 . . . . . . . . . . . . . . . . . . . . . . . . . 115 12.6 7G1 Arroyo Grande (S ta tion 23) . . . . . . . . . . . . . . . . . . . . . . . 115 16.8 7G2 Oceano Subs ta tion (S ta tion 15) . . . . . . . . . . . . . . . . . . . 118 17.3 7G3 751 Woodland Dairy (Station 30)...................... 122 17.9 Overlook Road (Station 36) . . . . . . . . . . . . . . . . . . . . . . . 112 0.3 7S2 D ia blo Pea k ( S ta ti on 28 ) . . . . . . . . . . . . . . . . . . . . . . . . . 103 1.1 851 Ta rge t Range ( S ta tion 6) . . . . . . . . . . . . . . . . . . . . . . . . . 125 0.5 DC0182 34IX

DMLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ff0N 5 DATE 8/2/85 PAGE 33 0F 37 EMERGENCY OFFSITE RADIOLOGICAL

ENVIRONMENTAL MONITORING TABLE 1 (Continued)

Straight Line Distance From AC Power t

Coordinate Plant (KM) Description Available hNW,8,A 5.8 Parking lot near end of No, road at southern park during boundary (near gate to daylight Fields' property). Good hours.

radio.

NNW,8,B 7.6 Ranger station over- Yes looking Spooner's Cove.

Good radio on road south "

of Ranger Station at

" Locked Gate Ahead" sign i

(near parking overlook of

(- Spooner's Cove). Public phone i

at Ranger Station. Power available below phone booth.

s I

l DC0182 33IX l

0 AaLO CANYON POWER PLANT UNIT NO(Sf , .1 AND 2 S ON 5 DATE 8/2/85 PAGE 32 0F '37 ENERGENCY OFFSITE RADIOLOGICAL TITLE.

ENVIRONMENTAL MONITORING I

TABLE 1 (Continued)

Straight Line Distance From AC Power Coordinate Plant (KM) Descriotion Available ESE,20,A 15.3 Pismo Beach Fire Dept. Yes on Shell Beach Road 1/4 mile South of Shell Beach Freeway (101) Exit. Phone available.

ESE.20.8 19.2 0.5 miles northwest of Yes, the Shorec11ff Inn on Available at Shell Beach Road. Inter- nearby section of Cliff Street residences, and Shell Beach Road in *=

field. Phone availabla at nearby residences.

SE.2.A 1.3 Turnout on access road, Yes 0.8 miles from Security Buf1 ding near meteorological )

Tower A. Marked with red / ^

white fence post. Between mile markers 6.5 - 6.6. Phone in tower building. Good radio.

NW,2.A 1.6 0.6 miles north from No Field's property gate (1 mile north from plant, just ENE of Lion Rock).

NW,4,A 3.5 Fields' road near No large watering pond.

i l NW,8,A 6.1 Near residence by park Yes, gate. Phone available at Available at I nearby residence, nearby I residence.

NNW,4.A 2.7 Near wood paneled house. Yes, Phone available at nerby Available at l residences. nearby i

residence, i

DC0182 32IX l

0iAsto CANYON POWER PLANT UNIT NO(S) -

1.AND 2 fSf0N DATE 8/2/85 PAGE 31 0F 37 EMERGENCY OFFSITE RADIOLOGICAL m LE. ENVIRONMENTAL MONITORING TABLE 1 (Continued)

Straight Line Distance From AC Power Coordinate Plant (KM) Descriptien Available l

ESE,4,A 2.6 Turnout on access road, No 1.6 miles from Security Building. Marked with red / white fence post.

(at mile marker 5.8). Radio [

near plant or near location ESE.10,A.

ESE,6,A 4.5 Turnout on acces's road No 2.8 miles from Security

Building. Marked with red / white fence post.

(between mile markers 4.5 - 4.6). Radio near plant or near location

, ESE 10,A.

ESE.8,A 6.9 Gate next to shack at No scad to ruins, 4.3 miles from Security Buildf g

. along access road.

Marked with red / white fence post. (between mile 1

markers 3.0 - 3.1) Radio 3 near plant or near location ESE.10,A ESE 10,A 9.6 Access Road at Gate, 6.2 miles from the Security Buf1 ding. (between mile markers 1.4 - 1.5) Marked with red / white fence post.

ESE 10,8 10.0 Port San Luis Gate. Yes p Radio on road to Pirates Cove. (Phone at guardhouse). l ESE.15,A 11.6 Parking lot behind Avila Yes Beach Post Office. Radio on road to Pirates Cove.

Public phone on side of post office.

DC0182 31IX 1

k

, oiAsto CANYON POWER PLANT UNIT NO(S) , - 1 AND 2 Sf0N5 DATE 8/2/85 PAGE 30 0F '37 N EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 1 (Continued)

Straight Line Distance From AC Power Coordinate Plant (KM) Description Available ,

ENE,20,E 15.8 The Spirit Nightclub Yes parking lot (formerly YancyMcFadden's).Los Osos Valley Road South on Calle Joaquin past Howard Johnson, End of Road. Goed Radio. Phone available during restaurant working hours.

E 15,A 14.5 PG&E Infomation Center. Yes Good radio.

E 15,8 13.4 Bellevue-Sante Fe School. Yes, during Fair Radic. Phone school hours. .

available during school _)

hours.

E.15,C 11.3 See Canyon Road, 1.7 Yes, miles up from San Luis Available at 8ay Drive intersection. nearby Survey at intersection of residences.

See Canyon Road and Davis Canyon Road. Good radio. Phone available at nearby residences.

E.25,A 20.2 SLO County Airport. The Yes field on the right of the road to the parking

, lot. Good radio. Phone l ,

in airport teminal.

E,25,B 21.5 SLO Country Club. East Yes, during side of parking lot in working hours, the fairway. Good radio. otherwise at Phone available during nearby working hours otherwise residences, at nearby residences.

DC0182 30!X

,. . - , , . . . .,,.,,_,g, , - , . - , _ _ , , _ _ , . , , . , , - - - - - . - _ _ . , , . _ _ _ - . _ . , . - , _----,,_.,e -.m.

s oiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 lff0N 5

,. CATE 8/2/85 PAGE 29 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE-ENVIRONMENTAL MONITORING TAB _LE 1 (Continued)

Straight Line Distance Frcal AC Power Coordinate Plant ( Q Description . Available 3 ENE 8,A 9.0 h See Canyon Road 4.2 Yes, miles up from San Luis Available at

, Bay Drive intersection, nearby '

(Intersection of See residences.

Canyon Road ard Black Walnut Road) Good radio.

Telephone available. ~

Rattlesnake hazard.

ENE 20,A "

14.8 Laguna Jr. High School Yes, during N

\ at intersection of Los school hours

Osos Road and Perfumo otherwise at Canyon Road. Good radio, nearby

~

Phone available during residences.

school hours, otherwise

. nearby residences.

ENE.20,8 16.0 Fire station at intersection Yes of Los Osos Valley and Madonna Roads. Goods radio. Phone availabler (Public phone across the strech at

, the gas stacion).

ENE 20,C 18.6 PG8EInformation-Zonil' Yes substation at corner of Walker and Higuera Streets.

Public phone across the -

i street at Ben Franklins.

l Good radio.

ENE.20,0 15.6 Corner of Foothill Yes, Boulevard and O' Conner Available at Way. Good radio, nearby

, Phone available at residences.

I nearby res!dences.

l l

l DC0182 29IX s.

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, O!A8LO CANYON POWER PLANT UNIT NO(S) -

1 AND 2.

DATE

[M 8/2/85 PAGE 28 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE.

ENVIRONMENTAL MONITORING l

TABLE 1 (Continued)

Straight Line Distance From AC Power Coordinate Plant (KM) Description Available NNE,15,A 11.3 Intersection of Los Osos No Valley Road and Clark

) Valley Road (under PG&E F -

transmissionIfnes).

v Good radio Jawa from transmission Ifnes. Phone and power avaliable at residence 1/4 mile West.

NNE,15,8 12.9 Los Osos Jr. High School ' Yes.

on South Bay Boulevard at during school end of Access Road. Good hours, radio. Phone available -

during school hours.

i i

NNE,20,A 17.5 0.3 miles north along San Bernardo Creek Road on the nortneast side of Yes, Avaffable at nearby

)

Highway 1. Good radio, residences.

Phone available at nearby residences.

NE,15,A 10.6 Intersection of Los Osos Yes, 3

Valley Road and Turri Available at i

Road. Good radio at nearby intersection. Phone residences.

available at nearby h

residences.

NE,20,A 1h.4 Sheriff's headquarters. Yes t

(E0F) Turn south on Highway 1 at sign indicating Sheriff's Operational Center. Good Radio. Phone available.

NE.20,8 19.2 PG&E substation near Men's Yes Colony, adjacent to northeast side of Highway 1.

Good Radio. Phone available.

DC0182 28IX

\

. l NUMBER EP RS-8 OtA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2

. REVISION 5 OATE 8/2/85 PACE 25 0F .37 EMERGENCY OFFSITE RADIOLOGICAL I' M ENVIRONMENTAC MONITORING FIGURE 1 EMERGENCY OFFSITE MONITORING LOCATIONS

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DC0182 251X

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m . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _______________.___._? .E

f

. , CIA 8LO CANYON POWER Pt. ANT UNIT NO(Si ,,1 AND 2 R Sf0N 5 DATE 8/2/85 PAGE 24 0F 37 EMERGENCY OFFSITE RADIOLOGICAL I'IM-ENVIRONMENTAL MONITORING TABLES

1. Description of Emergency Offsite Monitoring Locations.

2. DER Environmental Sampling Locations.

3. Locations of Selected Dairies. *

4. PIC Locations.

p, ATTACHMENTS

1. Form 69-9259 " Emergency Environmental Monitoring Field Data Sheet", 7/85. ,

SUPPORTING PROCEDURES

EP G-1 Accident Classification and Emergency Plan Activation EP EF-4 Activation of the Mobile Environmental Monitoring Laboratory EP R8-7 Emergency On-Site Environmental Monitoring ')

. .)

DC0132 24IX

l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N 5 DATE 8/2/85 l PAGE 23 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE.

ENVIRONMENTAL MONITORING

4) Place the probe (beta window open using the HP-240/270 probe, face down using the HP-210 probe).within one-half inch of the used side of the smear pad (in the same manner as when counting particulate filters) and wait for the meter reading to stabilize (about 20 seconds). Record the reading obtained in section 8 of the Field Data Sheet in the Gross column.

5) Calculate the net count rate by subtracting the background value from the gross count.

GM probe Background Count Rate (window open)

HP-240/270 60 cpm HP-260 50 cpm "

HP-210 50 cpm

6) Put the smear pad into a labeled holder and save it for .

later analysis in the MEML.

I -- 7) Calculate the smearable contamination as follows:

dpm/dm2 (CRnet)

(c) 3 where:

net = net cpm on smear pad CE c robe efficiency factor 3 = p(see gross particulate procedure)

8) Report the type of surface smeared, instrument used, and the smearable contamination level to the EOF or TSC as is appropriate.

FIGURES

1. Emergency Offsite Monitoring Locations.

2. Locations of DER Offsite Environmental Sampling and Monitoring Locations.

E DC0182 231X

)

- ___m_ - _ _ _ _ _ _ _ _ _ _

, DIA8LO CANYON POWER PLANT UNIT NO(S) . *1 AND 2 R S ON 5 DATE 8/2/85 PAGE 22 0F 37 EMERGENCY OFFSITE RADIOLOGICAL N

ENVIRONMENTAL MONITORING i

4) Calculate the net dose rate value by subtracting the l background value given on the data sheet. I 1 1

5) Estimate the ground deposition from the following i equation:

l Ground deposition (uCf/m2 ) = 238 x ERnet where: 1

, I 238 = Cs-137 ground deposition conversion factor 2

(uCf/m/mR/hr)

ERnet = Net dose rate obtafr)e4 at the 1 meter level (mR/hr) , , ,

6) Report location of measurement, ground deposition and the type of instrument used to the Emergency Evaluations and Recovery Coordinator or Radiological Monitoring Director.

8. Determination of Smearable Contamination

a. Equipment Required

1) Smear Pads with holders. l

2) Eber11ne E-140/N survey meter equipped with an HP-240/270 Standard Probe, an HP-260 pancake probe, or

'an HP-210 shielded pancake GM probe. (HP-210 probe preferred). l

b. Procedure

1) Select a representative smooth horizontal surface to ,

smear-test. Examples are tops of cars, store windows or sills, and walls of buildings.

2) Wipe the area with a smear pad using a uniform, 2

moderatg)fingertippressure.

(100 cm . This is an area 4"Cover approximately x 4" or1 10" S motionI dm with a smear pad. '

3)~ Identify the type of probe used and enter the data in section 8 of the Field Data Sheet. Include the time of the survey and the calibration due date of the instrument.

DC0182 22IX

b otAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 h0N DATE 8/2/85 PAGE 21 0F 37 EMERGENCY OFFSITE RADIOLOGICAL N- ENVIRONMENTAL MONITORING

2) GM Survey Meter '

E-140/N equipped with either an a) HP-240 probe b) HP-270 probe

b. Procedure

1) Hold the genna survey instrument or HP-240/270 GM probe (window closed) approximately 1 meter (3 feet) above the ground and measure the exposure rate.

2) The following precautions should be followed when making these measurements.

a) This section should only be performed after plume passage, since plume contributions to external exposure rates may invalidate the ground survey.

b) Make the measurement over short grass on I undisturbed land (common grazing, permanent -

pasture).

c) Make the measurement at least 20 yards from any building, road, railway, bridge, or heaps of material such as gravel,' rubble, or road-cut.

These all contain varying amounts of naturally occurring radionuclides.

d) Haystacks or silos should be avoided because they may contain in an concentrated form the total deposition on grass which originally covered a large ama. Trees and hedges also act as collectors of fallout which is washed out to a variable extent by rain. j e) Care must be taken to avoid any contamination of the instrument. If necessary, wrap the instrument (including probe) in a' plastic bag prior to starting survey.

3) Enter the instrument type used and record the readings in Section 6 of the Field Data Sheet. Include the time the survey was started and the calibration due date of l the instrument.

! DC0182 21!X

, otAal.O CANYON POWER PLANT UNIT NO($ .

1 AND 2 ON DATE- 8/2/85 PAGE 20 0F .37 EMERGENCY OFFSITE RADIOLOGICAL T'T1 ENVIRONMENTAL MONITORING i

4) Sheet plastic or plastic bag.

5) Protective clothing as determined by surveys

b. Procedure

1) WraptheGMprobeandcord(windowopen)inthin plastic to protect it against liquid damage and contamination.

2) Innerse the probe in as large a body of liquid as is available (reservoir, cattle trough,10-gallon milk can, etc.) to obtain the gross open window reading.

Enter the reading in Section 9 of the Field Data Sheet along with the time of survey and calibration due date of the instrument. **

3) Use 60 cpu as a background count rate to detennine the net count rate.

4) Report the type of sample, volume of sample counted, and not count rate to the Emergency Evaluations and ,

4 Recovery Coordinator or Radiological Monitoring /

Director.

Collect and label a 1-11ter sample and retain for later 5) analysis. If readings >200 cpm were obtained during 1 probe innersion, place The 1-11ter sample in a plastic bag and then tape the opening. Survey the exterior of the bag. If contamination is found, place the sample bag inside another bag over it. Note the contamination 4

levels on the sample label.

6) Survey the probe after it has been removed from it's plastic bag. Decontaminate if practical. Otherwise treat it as radioactive material.

7. Ground Surveys

a. Equipment Required

1) Ganna Survey Meter a) HPI-1010

b) R0-2/RO-2A DC0182 20IX q--- ----ev.ye - + - --w- rre- u- -r- --- wv e---7'

oiAsLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2

, , , R f0N DATE 8/2/85 PAGE 19 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE.

ENVIRONMENTAL MONITORING g) The activity level in pCf/kg can be estimated using the following expression:

uCf/kg = 2.5 x 10-1 x CR net where:

CRnet = net cpm on a standard GM tube (HP-240/270)only.

h) Survey the exterior of the bag. If contamination is found, place the sample bag inside another bag.

Note the contamination levels on th,e label.

1) Report the type of vegetation samr'es and the activity level to the EOF or SC , is ,i appropriate.

2) Soil Sampling

~

a) Sample the soil from a Im2 area. Remove only the top surface (to a depth of = 4" or less) using the t , trowel. Stay upwind ard wear appropriate protective clothing when scraping.

b) Place the sample in a bag, seal, and label, c) No field counting of soil samples is mquired.

The samples are taken for follow-up analysis only.

Scan the bag to determine if there is a high count rate (>1,000 cpm). Survey the exterior of the bag. If contamination is found, place the sample bag inside another bag. Record any high count rates on Section 10 of the Field Data Sheet.

6. Liquid Sampling and Counting

a. Equipment Required

1) Sample bottle (1 liter)

2) Labels.

3) Eberifne E-140/N survey meter equipped with HP-240/270 standard GM probe.

DC0182 19IX

l

. o AaLO CANYON POWER PLANT UNIT N'O(S) . 1 AND 2 Sf0N DATE 8/2/85 PAGE 18 0F 37 N EMERGENCY OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORING

6) Eberifne E-140/N survey meter with HP-240/270 standard GM probe.

7) Protective clothing as determined by surveys.

b. Procedure

1) Vegetation Sampling and Counting a) Cut the vegetation ccver from at least a 1 r12 area of ground; the aim being to collect approximately one pound. Cut the vegetation at a height of I-2 cm from base of vegetation to approximate what a grazing animal would consume. Avoid contaminating the sample with dirt.

b) Place the vegetation in the plastic bag, top end first. Slowly compress the air out of the bag and seal it with tape. One pound of material will -

norinelly fill the bag about half full.

~

WARNING: DO NOT PLAG BG)Y OVER BAG OPENING WHILE -

CD R ESSING IT'S CONTENTS. )

c) Label the bag with the following information

1) Location of sample

2) Date and time of sample. The time is expressed using the ceilitary (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period) standard.

3) Name of person who took sample d) Using Table S. pick the standard background for the HP-240/270 probe and record it on Section 7 of

, the Field Data Shet.t.

e) Flatten the bag and lay the probe (window open) on the center of the bag.

f) Fold the bag over the probe and note the reading.

Record the reading on the field data sheet along with time of survey and instrument calibration due data.

DC0182 18IX .

s A

1 AND 2 NUMBER EP RB-8

. DiAsto CANYON POWER PLANT UNIT NCHS)

REVISION 5 DATE 8/2/85 PAGE 17 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE.

ENVIRONMENTAL MONITORING 4 l

)

9) If it is necessary to calculate the activity of the '

sample in the field, use steps 10 and 11 below.

10) Calculate gross iodine concentration from the following )

expression:

l (1.59 x 10'11) (CR net I

" ICC * (c2 I II cI III where:

CRnet = net pm on cartridge c2 = probe efficiency: s HP-240/270 0.0003 counts / dis HP-260 0.003 HP-210 0.003 EC = cartridge collection efficiency, assumed to be 0.94 l V = volume of airborne sample (ft3 )

11) Record the. calculated data in section 4 of the Field Data Sheet.

5. Soil and Vegetation Sampling

! a. Equipment Required

1) Trowel.

2) Grass cutters or knife.

3) IS*'x 24" plastic bags.

4) Masking tape.

5) Labels.

l l i

l DC0182 17IX l

t

) ' *

, oiAeLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 8/2/85 i PAGE 16 0F 37 l EMERGENCY OFFSITE RADIOLOGICAL l 787

ENVIRONMENTAL MONITORING i

l

b. Procedure

1) EnsurethemainvaTveontheaircylinderisshut.

Open the flow control valve and back off the regulator control. Then shut the flow control valve.

2) Open the main valve on the air cylinder. The cylinder

pressure should read about 1800 psi. Replace the cylinder if it reads <300 psi.

3) Slowly adjust the regulator until the delivery pressure gauge reads 5 psi. Open the flow control valve to ensure 5 psi is maintained. Then shut the flow control valve.

4) Insert the remaining half of the sample head containing ' '

the halogen cartridge into the adapter. Ensure that the particulate filter has already been removed. .

5) Open the flow control valve and allow air to blow through the cartridge in the reverse direction until the cylinder pressure gauge drops 200 psi. Shut the i flow control valve. This technique removes noble gases )

from the halogen cartridge.

6) Remove the cartridge from the sample head and place the probe within one-half inch of the upstream side of the cartridge. Wait for the meter to stabilize (about 20 seconds) and then record the type of probe and the gross counts in Section 4 of the Field Data Sheet.

7) Report the sample time, flow rate, volume, type of probe used, and the initial gross sample counts to the E0F or TSC as appropriate.

8) Place the cartridge in a plastic ziploc bag. Label the i bag with the necessary infomation and then place this l bag along with the particulate filter coin envelope in another bag. The outside of this package should be verified to be uncontaminated by either direct survey or smear survey (if the contamination level on the sample inside the package is too high). This package will be taken to the MEML in accordance with instructions from the E0F.

i-,

DC0182 161X s

I

_ . . . _ . - --_ _.. _ _,,_...,,.__.,_..._ _ _ . _ ___._.___,,,_,_...,-_-.-_,_,_,..._..,.-.__..,..__m. _ _ - - - - - . _ . - _ - . . . , . - _ -

o otAsLO CANYON POWER PLANT UNIT NO(S) 1,dND2 S{0N5 DATE 8/2/85 PAGE IS OF '37 EMERGENCY OFFSITE RADIOLOGICAL TITLE. ENVIRONMENTAL MONITORING

8) Detemine the net count rate and calculate the gross particulate activity from the expression:

(1.59x10~h) (CR g)

CC "

(c3 ) (E f) (V) ,

where:

CR net

= net cpm on filter c3 = probe efficiency:

HP-240/270 0.08 counts (window dis open) 0.06 (closed)

HP-260 0.10 . -

HP-210 0.10 Ef = cartridge collection efficiency, assumed to be 0.99 l

l V = volume of airborne sample (fts)

9) Record the calculated data in Section 3 of the Field Data Sheet.

4. Determination of Gross Iodine (Field Technique)

a. Equipment Required

1) Eberline E-140/N survey meter equipped with either an HP-240/270 standard GM probe, an HP-260 pancake GM probe, or an HP-210 shielded pancake GM probe. The HP-210 probe is preferred.

M: Field measurements should be performed in a low background location, if possible, outside contaminated areas or plume (<100 cpm).

2) Cylinder of dry air equipped with regulator.

3) Plastic bags.

4) Forceps or tweezers DC0182 ISIX

._ _ r_. . . , _ . ,, r. , - _ , . _ . , -.. _.%..,_.._,m_.,._,,m7 ,m_.c_m,_m ,.,._w ,_.,,.-.,. _~.,,_w,,,..,_m,._,e,,,._..,,__.,.____., _ . - . _ - . . .

. otAaLO CANYON POWER PLANT UNIT NO(S) ,

1 AND 2 ON DATE 8/2/85 PAGE 14 0F 37 EMERGENCY OFFSITE RADIOLOGICAL I'T*

ENVIRONMENTAL MONITORING

3. Determination of Gross Particulate (Field Technique)

a. Equipment Required

1) Eber11ne E-140/N survey meter equipped with either an HP-240/270 standard GM probe, an HP-260 pancake GM probe, or an HP-210 shielded pancake GM probe. HP-210 probe is preferred.

M: Field measurements should be performed in a low background location if possible, outside contaminated areas or plume (<100 cpm).

2) Coin envelope.

3) Forceps or tweezers. #

b. Procedure

1) Find an area shielded from the wind or rain. The rear of the vehicle may be used if absolutely necessary.

Label the coin envelope to be used for storage of the filter with the necessary information.

2) Remove the filter from the air sample head.

3) Place the probe (beta window open if using the HP-240/270. probe face down using HP-210/260 probe) within one-half inch to the upstream side of the filter. Filters should be handled with forceps (or >

tweezers) and the probe should not touch the filter, in order to avoid contamination of the probe.

4) Wait for the meter reading to stabilize (about 20 seconds). Record the type of probe and the gross count rate in section 3 of the Field Data Sheet.

5) Place the filter in the labeled coin envelope.

6) Report the sample time, flow rate, volume, type of probe used, and the initial gross sample counts to the EOF or TSC, as appropriate.

7) If it is necessary to calculate the activity of the sample in the field use steps 8) and 9) below.

l DC0182 14IX

l 1

{

. DIABLO CANYON POWER PLANT UNIT NO(S) 1,AND 2 Sf0N5 DATE 8/2/85 ,

PAGE 13 0F 37 l EMERGENCY OFFSITE RADIOLOGICAL T87LE: {

ENVIRONMENTAL MONITORING I

3) For an HD-288, proceed as follows: I a) Plug in the sampler, turn on the power, and simultaneously start a stopwatch (or reset the i

timer on the sampler itself, if a sampling time of several hours is contemplated).

4) For an H-809C, proceed as follows:

a) Attach the sampler to the car battery by attaching the red cable to the positive battery terminal and

the black cable to a chassis ground.

M: Try to position the air-sampler away from the vehicles cooling fan, if possible.

b) Turn the vehicle engine on. Start the sampler.

Note the airflow. Do not attempt to adjust the airflow by turning the setscrew on the top of the i flommeter, p

5) Periodically check the flow indicator to verify that

, the flow rate is being maintaired. If the flow rate changes significantly during sample collection, note the value at the end of the sample period and determine the average value of the flow rate. This average value

,' should be used to determine the size of the sample collected.

6)

Allow the sampler preferably 30-50 ft tS)run untti at least is collected. 10 ft3 (but The greater the volume sampled, the better.

7) Stop the sampler and remove the filter head. If using' a vehicle as the power source, stop the vehicle's i

engine.

8) Make the halogen and particulate measurements discussed in steps 3 and 4 below, if desired.

9) If excessive dose rates make it necessary to leave the area prior to making the measurements in steps 3 and 4 below place the filter head in a plastic ziploc bag and

. label the bag.

10) Enter the collection data in Section 2 of the Field Data Sheet.

DC0182 13IX 1

, DIA8LO CANYON POWER Pt. ANT UNIT k(S) . - 1 AND 2 ON DATE 8/2/85 PAGE 12 0F 37 EMERGENCY OFFSITE RADIOLOGICAL T'T* ENVIRONMENTAL MONITORING data can be entered in Section 1.c. of the Field Data Sheet. Report the integral dose and the time period over which it was collected to the EOF or TSC, as is I appropriate.

2. Collection of Air Samples

a. Equipment Required

1) One of the following air samplers, equipped with sample head for two-inch filters:

a) RADECO Model H0-288 (120V AC-powered).

b) R' DECO Model H-809C (12V DC-powered, without butterv).

2) Two-inch diamater particulate filter paper.

3) Coin envelope for retention of filter.

4) HI-Q 2-1"-afe. meter charcoal cartridge or AgZ (Silver )

Zeolite) cartridge.

)

S) Plastic ziploc bag with label for retention of cartridge.

6) Wristwatch or stopwatch.

b. procedure

1) Assemble the filter and halogen cartridge in the sampling head. The particulate filter is mounted on E the holder such that the side with the wovan cloth or grid is upstream of the flow, i.e. the collection side. l

2) Place the filter head on the sampler.

i l

DC0182 121X

a oiAsto CANYON POWER PLANT UNIT NO(5) -

1 AND 2

[fSf0N 5 DATE 8/2/85 PAGE 11 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE.

ENVIRONMENTAL MONITORING E: When using the HP-210 probe, take both GM window up and GM window down readings.

These readings may be required later to account for sky shine. Be sure to note the correct reading under the correct headings

, ontheDataSheet-cpm [windowup]orcpm

[windowdown].

b) Record the type of instrument (or probe) used, time survey was star ad, highest value obtained during the survey, instrument R.P.# and l calibration due date of the instrument on Section 1 of the Field Data Sheet.

c) Report to the EOF or TSC:

1) Time of survey

2) 8 eta and Gasua dose / count rates

3) Instrument used b 2) Pressurized Ion Chamber (PIC) a) The PICS may be read directly by pressing the

" READ" pushbutton installed on the front panel face of the equipment.

b) Dose rate trending may be performed by reviewing the strip chart. One trace on it (usually a straight line) matches one of the markings inmediately below the chart. This indicates the j range. The second trace will normally fluctuate.

l This trace indicates the actual dose rate. It

should correspond with that shown on the digital display.

c) Record data in section 5 of the Field Data Sheet.

i Report the reading to the EOF or TSC as is appropriate.

3) Integral Dose

< The HPI-1010 has the capability for dose integration if desired. If an integrated measurement is made, the DC0182 111X i

e

. DIA8LO CANYON POWER PLANT UNIT NO($[ 1 AND . 2 ON

' DATE 8/2/85 }

PAGE 10 0F '37 i W- EMERGENCY OFFSITE RADIOLOGICAL '

ENVIRONMENTAL MONITORING MONITORING PROGRAM External dose rate measurement should be performed and an air sample collected at each offsite monitoring location unless otharwise l l directed by tne Radiological Monitoring Ofrector. I :

If the Pressurized Ion Chambers (PICS) are located in an affected sector, they should be read. PIC locatiors are described in Table 4, and may be remotely interogated using the EARS terminals. I 1

Collection of any other types of samples (i.e., ground deposition measurements, vegetation, soil, water or milk samples) will be at the direction of the Emergency Evaluations and Recovery Coordinator or the Radiological Monitor!ng Director, and are usually considered foliowup actions. [

.=

1. External Dose Rate and/or Count Rate Measurements

a. Equipment Required

1) Any of the following instruments can be used for external dose rate measurements:

a) HPI-1010 b) R0-2/RO-2A

2) For measuring an external count rate, use an Eberline E-140/N survey meter equipped with either an HP-240 standard GM probe. HP-260 pancake GM probe, or an HP-210 shielded GM probe. (The HP-210 probe is preferred). l

b. Procedure

1) Dose or Count Rate Measurements a) Make 6 dose rate and/or count rate measurement with the detector held about three feet off the

! ground (f.e., approximately at waist level). If i

the detector is so equipped, take the data with the beta window open and closed.

DC0182 10!X ~

i

L , , oiAsi.O CANYON POWER Pt. ANT UNIT WS) ,

1 AND 2

, $h0N DATE 8/'/85 _

PAGE 9 0F 37 EMLRGENCY OFFSITE RADIOLOGICAL tit e ENVIRONMENTAL MONITORING

c. Field Data Sheets

1) Field data should be recorded on the Emergency Environmental Monitoring Field Data Sheets (Fom 69-9259). Each monitoring team shall maintain a i

notebook with the data sheets and other pertinent instructions.

S. Monitoring Instrumentation Performance Testing All portable monitoring instrumentation should be checked prior -

to entering the field. This check should include at least the i following. -

a. General Appearan.a The instrument should have no visible signs of damage.

b. Calibration The instrument should be in calibration as verified by the calibration sticker attached to the instrument.

2 ( -

c. Battery l

, The batteries should be good as verified by turning the l instrument to the Battery Check position and ensuring proper meter indication.

l d. Response If the meter has an attached source, the meter should be response checked by holding the probe to the source and monitoring for a response.

e. Zero Adjust If the meter is equipped with a zero adjust, it should be adjusted to read zero when the selector switch is in the zero adjust position.

I DC0182 91X

d DiAaLO CANYON POWE3 PLANT UNIT NO(St 1 AND 2 Sf0N 5 DATE 8/2/85 PAGE 8 0F 37 N- EMERGENCY OFFSITE RADIOLOGICAL

! ENVIRONMENTAL MONITORING

b. Dairies Because the milk pathway is often the Ifmiting pathway it may be necessary to collect milk samples if directed to do so by the Radiological Monitoring Director. The locations of dairies in the DCpP area are described in Table 3

" Locations of Selected Dalries".

, 4. Sample Identification and Data Sheets

a. Identification and Retention of Samples Samples or ffiters which are collected in the field should be placed in a sealed plastic bag, envelope, or bottle, as appropriate, and identified with a fimly attached label which states the following information: .

1) Date and time of start and end of sample collection.

The time is expressed using military time (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock).

2

2) Sampler flow rate (afr samples only).

3) Location of sample. _

)

4) Name of person who collected the sample. The exterior of the bag should be surveyed. If contamination is found, place the bag inside another bag and note

contamination levels on the outside of the second bag.

b. Recordkeeping All records generated by the utilization of this procedure for an exeref.se or emergency shocid be forwarded the next working day to the Assistant Plant Manager / Support Services for review and retention. l 4

1) Records generated from exercises will be categorized as non. permanent and retained for a minimum of five years.

2) Records generated from actual emergency events will be i

categorized as lifetime and placed into lifetime storage in accordance with procedure " Requirements for Retention and Extended Storage of Operation Phase Activity Records (AP-E-1-51)."

DC0182 8IX t

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oiAaLO cANv0N POWER Pt. ANT UNIT NO(S) 1 $ND .2

{P RB-8 DATE 8/2/85 .

PAGE 7 0F 37 EMERGENCY OFFSITE RADIOLOGICAL N ENVIRONMENTAL MONITORING l

t

b. Respirators should be donned if loose surface contamination levels exceed 100.000 dps/100 caz (>10,000 cpm above background using the equipment in 2.a.1) or an airborne particulate sample indicates >3 x 10 8 uCi/cc (>15 cpm /ft3 using the equipment and proce' dure in 3.b under Monitoring Program). l

c. Team members should survey themselves, their equipment, and l l the exterior package of their samples if loose surface contamination is found during their surveys.

d. Field monitoring personnel should read their pocket I dosimeters at intervals not to exceed 30 minutes outside the i plume and 15 minutes while in the plume. Report the highest i team member's dosimeter reading to the' ERA or Radiological Monitoring Director (RMD) when requested to do so. .

l e. Immediately evacuate the area you are in, without orders i from the EOF, if the dose rate increases to a point that ,

exceeds the upper limit of the instrument you are using, i.e.,1000 mr/hr when using the HPI-1010 or 5000 mr/hr when using the R0-2. Report your actions to the E0F as soon as

( practicable.

l 3. Environmental Sampling Stations i

a. There are a number of environmental monitoring and sampling stations which are part of the continuing program conducted by the Department of Engineering Research. For reference, these stations are shown in Figure 2. " Location of Departments of Engineering Research Environmental Monitoring and Sampling Stations", and described in Table 2. " DER l' Environmental Monitoring Locations."

l E: Field monitoring teams will not collect data from DER monitors unless expressly directed by the Radiolo at the E0F)gical Monitoring Director (located E: The TLD's are located in a grey plastic container. Opening the container requires an 1/8-inch Allen wrench which is in the emergency kits.

DC0182 7!X

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, DiAsLO CANYON POWER Pt. ANT UNIT NO(Sf , 'l AND 2 Sf0N 5 DATE 8/2/85 PAGE 6 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE:

ENVIRONMENTAL MONITORING

c. Identification of Emergency Monitoring Locations

1) Monitoring locations used in this procedure are identified in Figure 1 " Emergency Offsite Monitoring Locations". Table 1 " Description of Emergency Offsite Monitoring Locations" is included for reference.

2) Coordinate System Each monitoring location is identified b coordinates as follows (e.g., NNE, 8. A)y: three I

a. Sector designation >

b. Radial distance in kilometers to the farthest sector element boundary (not true radial distance .

toplant).

c. Letter designations to distinguish between different sample locations contained in the same sector elements.

In cases where samples are taken at locations other than those previously labeled, some other )

identification means must be used. Thus, the following might be typical sample location designations:

ESE.15. Avila Post Office)

ENE, 20 Corner of Marsh and Broad Streets, SLO)

NNW, 8.CampgroundatsouthofIslayCreek)

2. Radiological Precautions

a. Protective clothing should be donned if loose surface cortamination levels exceed the following criteria:

1) Hand and foot protection should be donned if contamination surveys indicate >1000 dpm/100 cm2 but

<10,000 dps/100 2cm . This wouli result in a direct frisk of the surface within 1 cm or a smear covering 100 cea (4" x 4" or 10" S motion) reading >100 cpm but

<1000 cpm above background on an E140/E140N equipped with an HP 210/260 probe.

2) A full set of protective clothing should be donned if contamination surveys indicate >10,000 dpe/100 caz ,

This would result in >1000 cpm above background using the same equipment as in 2.a.1) above.

DC0182 6IX l

L

otAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N 5 DATE 8/2/85 PAGE 5 0F 37 EMERGENCY OFFSITE RADIOLOGICAL 7'TLE-ENVIRONMENTAL MONITORING

2. DayShift(Weekdays)

a. PGandE personnel will be dispatched from DCPP.

b. One team should obtain a hand-held radio and an emergency -

kit from the Training Buf1 ding and initiate monitoring in l

accordance with procedure RB-7. The other teams will obtain equipment at the MEML Garage (PG&E Service Center).

c. Mobilization and dispatch on the day shift is expected to take approximately 45 minutes. I

3. Back Shifts and Weekends

a. Teams notified on a call-out basis may be directed to assemble at the Training Buf1 ding (on-site team) or the San Luis Obispo Service Center MEML Garage (offsite teams).

I

b. Mobtifration and dispatch on a backshift or weekend is expected to take approximately one hour.

GENERAL INSTRUCTIONS

1. Locations to Monitor l a. Affected Sectors The 360' of the compass have been divided into sixteen 22.5*

sectors which are identified by the compass point of their centerifne: 1.e., N NME, NE, ENE, E, etc. In this procedum, all directions are referenced to true (not magnetic) north,

b. Distance Downwind The areas to be surveyed will depend on such factors as the quantity of radioactivity released, wind speed, steadiness of wind direction, and the time elapsed since the release started. For initial positionin EARS computer, manual overlays (g of theinfield as described EP RB-11) teams,orthe meteorological information may be used to estimate the distance the plume has traveled downwind.

DC0182 SIX

. , otAet.O CANYON POWER Pt. ANT UNIT NO Si , , 1 AND 2 R ON '

DATE 8/2/85 PAGE 4 0F 37 EMERGENCY OFFSITE RADIOLOGICAL T'" ENVIRONMENTAL MONITORING

d. At least once per hour to verify continued radio operability (if contact has not been made during that period).

MONITORING TEAMS

1. Composition

a. Equipment for a minimum of four teams plus the MEML is available for offsite envitenmental monitoring. Three emergency kits are located at the PGandE Service Center on South Higuera in San Luis Obispo (MEML garage) and two emergency kits are located at the plant off the entrance foyer to the Training Building Room 126. One of the kits in the Training Building is reserved for the on-site monitoring team. Access to the MEML Garage requires a Cypher Pad Code to open the door. If the field monitoring i team members require the code, it is atailable from either the ERA in the TSC or the RERM in the EOF.

M: If the MEE garage burglar alaru defeat key is not available (see Emergency Procedure EF-4), notify plant security to expect an diers, and to dispatch someone to clear it. .

,j

b. Each team should have at least two members.

c. Teams should be comprised of 1 (one) PGandE C&RP Technician as the team leader and 1 (one) additional person trained in the use of this procedure. This additional person should be a PGandE C&RP technician but may be a SLO County (SLOCO)

Environmental Sanitarian.

d. MEML personnel will assist in organizing and dispatching the field teams from the MEML garage.

e. SLO County and/or PGandE field teams should wait for the other team members to arrive before departing the MEML garage (unless directed otherwise by the Emergency Radiological Advisor (TSC) or Radiological Monitoring Director (EOF)).

f. If personnel and vehicle / equipment availability permits, a

" runner" may be used to transport samples from field monitoring locations back to the MEML for analysis.

DC0182 4IX

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9 otABLO CANYON POWER PLANT UNIT NO(S) - 1 AND* 2

, Sf0N5 DATE 8/2/85 ,

1 PAGE 3 0F 37 EMERGENCY OFFSITE RADIOLOGICAL TITLE: ENVIRONMENTAL MONITORING M)TE: Offsite field teams should obtain hand-held radios from I the MEML garage. Other locations should be used as a I back-up only,

a. For ease of communication with the radios, the offsite field monitoring teams will be given call names using the International (ICA0) Phonetic Alphabet:

A - Alpha E - Echo I - India B - Bravo F - Foxtrot J - Juliett C - Charlie G - Golf K - Kilo 0 - Delta H - Hotel L - Lima

b. Radio Technique t0TE: The "T" switch is set on "1", "F" set on 5 (nomal position) for repeater, 6 (only if directed) for local.

1) Hold the radio upright, directly in front of the mouth.

q' 2) Before transmitting, make certain that someone "else is

'- not already transmitting ~ rc the frequency.

3) After pushing transmit button, wait two seconds to

j. allow automatic radio encoding to occur.

2. Comunications back-up would be by telephone: _.

TSC or Control Room:

l l' ~

UDAC: Rad. Monitoring RERM MEML:

.t

3. Each monitoring team leader and the MEML should contact the EOF t or TSC under the following conditions:

a. After ' obtaining hand held radios to verify radio operabihty and obtain initial instructions from the EOF or TSC.

b. Upon arriving at a monitoring location, to report initial radiological conditions (dose rate. count rate).

c. . After completion of sampling at a monitoring location to i report results or obtain additional instructions.

DC0182 3IX

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DiAeLO CANYON POWER PLANT UMT Ms) ,

1 AND 2 Sf0N 5 DATE 8/2/85 PAGE 2 0F 37 EMERGENCY OFFSITE RADIOLOGICAL 7" ENVIRONMENTAL MONITORING TABLE OF CONTENTS SU8 JECT PAGE Communication 2 Monitoring Teams 4 !

General Instructions 5 '

External Dose Rate / Count Rate 10 Air Sample Collection 12 Gross Particulate Determination 14 Gross Iodine Detemination 15 Soil and Vegetation Sampling 17 Liquid Sampling and Counting 19 l Ground Survey 20 Smearable Contamination 22 Off-Site Monitoring Locations 25 DER Monitoring Locations 26 Description - Off-Site Monitoring Locations 27 DER Sampling Locations 34 Dairy Location 36 PIC Locations 37 COP 9tVNICAT!0NS

)

1. The primary casuunication links between the TSC, EOF, MEML, and field monitoring teams will be by radio communications on the Health Physics frequency. The field monitoring teams will use hand-held radios. The location and numbers of available radios are listed below:

Location Radio Type Number Training Building H 3 l PGandEServiceCenter(MEMLGarage) H 4 E0F H 2 P 1 MEML P 1 DER Vehicle P 1 H= Hand-held. P= Permanent.

l l

DC0182 2!X

. _ . . . . - - . __-_.._._. ....,-- ,-._.____..__ __..~...__ ,_ ._. ,, -..___ -.__ . ._ _ , _ _ . _ - - - ,

. NUMBER EP RB-8

?G5I43 Pacific Gas and ElecOic Company REVISION 5 CEPARTMENT OF NUCLEAR PLANT OPERATONS 1 AND 2 N 1 0F 37 DIASLO CANYON POWER PLANT UNIT NO(S)

EMERGENCY PROCEDURE EMERGENCY OFFSITE RADIOLOGICAL TITLE. ENVIRONMENTAL MONITORING ,MPORTANT To APPROVED: Wd AA= 10-Ilo46 SAFETY . :

PLANT MANAGEMENT) T DATE SCOPE This procedure describes the emergency offsite radiological environmental monitoring program which would be undertaken in the event of an airborne release of radioactive materials from the Diablo Canyon Power Plant. The procedure provides instruction for =

implementation of the program. Also provided are instructions to monitoring teams for locating sample points, collecting samples, and performing field analyses of samples.

This procedure and' changes thereto require PSRC review.

INITIATING CONDITIONS

The Site Emergency Coordinator declares a Site Area or General Emergency in accordance with EP G-1, " Accident Classification and Emergency Plan Activation". Offsite environmental monitoring teams may be dispatched for an Alert classification if judged appropriate by the Site Emergency Coordinator.

DIRECTION AND CONTROL

1. Offsite teams may be initially dispatched by the Emergency Evaluations and Recovery Coordinator (EERC) either in the TSC or Control Room.

2.

Upon activation instructions of the from the EOF, teams Emergency will receive Radiological operating Advisor (ERA ).

3. On-site or near-site monitoring activities are continuously coordinated by the TSC.

DC0182 IIX

_ _Y

4 69-11589 5/85 (10) Page I cf ;

PACIFIC GAS AND E'.ECTRIC COMPANY '

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: K! INVENT 0'Y R DATE: PERFORMED BY:

ON-SITE VENDOR EXPIRATION DATE QUANTITY (100 Battles / Box)

TSC (Minimum) (Actual)

a. Office Area North end, in cabinet I box

b. Computaticn Center cabinet located on north wall I bcx SECURITY BUILDING Triple 5 office i

14 bottles TRAINING BUILDING Storage Room >

Kits 4 & 5 2 bottles -

ACCESS CONTROL

a. Chem Lab Storage Room 4 boxes

b. First Aid Room 2 boxes CONTROL ROOM Cabinet located I

on east wall 2 bottles OFF-SITE MEML Garage

a. Kits 1.2 & 3 3 bottles

b. Van 2 bottles EOF RERM Office 5 boxes PGandE ENERGY INF0 CENTER Decon Facility storage cabinet 4 bottias

When recording K!, obtain a certificate from the vendor, I copy for Emergency Planning. I copy for CARP files. '

g: Any discrepancies should be recorded on the Problem Tracking Form.

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. 69-11575 (12) 2/85 . Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: ISOTOPIC MEASUREMENT EQUIPMENT CHECKLIST DATE PERFORMED BY ISOTOPIC MEASUREMENT EQUIPMENT

1. Gamma Spectrometer (located in the Cal Poly Physics Building, Room #E128)

2. ROLM Phones; (verify by calling)

NOTE ANY PROBLEMS:

i i i N)TE: Any discrepancies should be recorded on the Problem Tracking Fom.

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I DC0118 107XX

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. 69-10866 2/85 -

Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DIA8LO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: ASSEMBLY AREA CHECKLIST DATE PERFORMED BY BULLHORHS (Change Batterfes Quarterly)

Conununications Coordinator Security Shift Superviser Emergency Planning Group ASSEMBLY AREA PACKETS (Update Monthly in Each Area) '

Radiological Access Control *

=

Cold Machine Shop TechnicalSupportCenter(TSC)

Security Building

\

Training Building, Room 107 Training Building, Room 109 Training Butiding, Room 121 Training Building, Room 122 Training Building, Room 123 Training Building, Room 222 g: Any discrepancies should be recorded on the Problem Tracking Form.

0C0118 106XX

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, '69-10865 2/85 (12) , Page 3 of 3 TITLE: MEDIA CENTER PHONE CHECKLIST RUMOR CONTROL CENTER / PHONE ASST. CENTER (Women's dressing room, cont'd):

TYPE NUMBER DIAL TONE COMMENTS PT&T

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YELLOW NET ation 06 l

PUBLIC INFORPATION REPRESENTATIVES OFFICE (Lobby):

TYPE NUMBER . DIAL TONE COMMENTS PT&T YELLOW NET Station 03 i .

l N]TE: Any discrepancies should be recorded on the Problem Tracking Fom.

8 s

DC0118 105XX s

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s 69-10865 2/85 (12)

Page 2 of 3 TITLE: MEDIA CENTER PHONE CHECKLIST

> SOUTH END TYPE .,

NUMBER DIAL TONE COMMENT EUE PTIT WHITE PT&T

' ~'

AUDITORIUM:

Public Information Center

)'

(Men's dressing room): '

TYPE _\ NUMBER DIAL TONE COMMENTS PT&T RUMOR CONTROL CENTER / PHONE ASST. CENTER

,(Women's dressing room):

TYPE \ ER DIAL TONE COMMENTS PT&T DC0118 104XX .

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I 69-10865 2/85 (12) . Page 1 of 3

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNIT N05. I AND 2 ,

TITLE: MEDIA CENTER PHONE CHECKLIST DATE PERFORMED BY INSTRUMENT CHECK Take one group of phones per month and check to ensure they call out and ring.

Phones for the newsroom are grouped by color and those for the auditorium are grouped by location name. Check yellow net every month. All phones are located in oak cabinets at the EOF. There are three phone groups and all groups must be +

checked at least once a quarter. Group one is the yellow and red phones for the news room. Group two is the blue and white phones for the newsroom. Group three is the phones for the auditorium.

GROUP NUMBER:

Note any problems or comments:

NUMBER COMMENTS

\ -

i l LINE CHECK:

Check all lines every month to make certain all lines are still working.

Newsroom (Psychology trailer across from auditoriun) l NORTH END: NUMBER DIAL TONE COMMENT TYPE YEEEDW __

PT&T RED:

FTIT I

I i

DC0118 103XX 'N l l

1 .. .

, 69-10864 2/85 (12) . Page 1 of 1

, PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: DECONTAMINATION FACILITY CHECKLIST DATE PERFORMED BY:

CONTAMINATED SOLID WASTE DISPOSAL SUPPLIES ,

2 (33 gal.) Plastic Garbage Cans 2 Boxes Plastic Trash Bags with Ties - Min. 3 Mil Thick PERSONAL DECONTAMINATION SUPPLIES 20 Bars of Soap 8 12 oz/ Containers of Shampoo 10 Bars Lava Soap ,

4 Scissors 6 Brushes (for Scrubbing Skin and Nails) 4 Boxes of Q-tips (100/ box) 10 Rolls Paper Towels Lanolin (Hand Cream) -

REPLACEMENT CLOTHING. TOWELS 4 doz. Terrycloth Towels 4 dor. Disposable Coveralls (Assorted Sizes) 4 doz. Zorries (Assorted Sizes) 4 dor. Washcloths MiSCELLANE005 EQUIPMENT 2 Rolls of Magenta and Yellow Barricade Tape 100'/ro11 4 Radiation Caution Tags 4 Radiological Contamination Caution Signs 1 Roll Perforated Radioactive Material Warning Tape 5 Boxes Su qical Gloves 4 BottlesKITablets(14 Tablets / Bottle) 1 First Aid Kit 4 Blankets 10 Rolls Masking Tape 10 Rc11s Duct Tape Absorbent Paper g Any discrepancies should be recorded on the Problem Tracking Form.

OC0118 102XX

69-10582 2/85 (12) .

Page 2 of 2 TITLE: EMERGENCY FACILITY FORMS FILE LIST CURRENT 4

FORM (APPROXIMATE QUANTITY)

DATE NUMBER TITLE T-1 T-2 T-3 E-1 E-2 69-10861 PopJ1ation Dose Calculation 5 5 5 5 69-11105 Release Rate Determination for a Steam Generator Type Rupture 5 5 5 5 69-11510 Radiation and Contamination Survey 10 10 10 10 Record 69-11512 Controlled Area and Airborne Area 10 10 20 5 5 Entry Log 69-11590 Special Work Permit Request 10 10 20 5 5 None Personnel List Diablo Canyon Power Plant Department of Nuclear Plant Operations 1 1 R-2 Appendix 2 - Instructions for Estimating Noble Gas Release Rate .

Using Plant Vent Monitors RE-14 or 5 5 5 5 5 RE-29 R-2 Appendix 3 - Instructions for .

Estimating todine Release Rate Using Plant Vent Monitor RE-24 5 5 5 5 5 R-2 Appendix 4 - Use of Containment Air Sample Data 5 Estimate Release Rate , 5 5 5 5 5 R-2 Appendix 5 - Use of RCS Coolant Sample During 5/G Tube Rupture 5 5 5 5 5 -

Accident

RS-14 Attachments-Water Entrained Inventory 2 2 2 2 2 j

Worksheet. Airborne Inventory Worksheet. Calculations of Power Corrected Source Inventories for Constant Power Levels. Source Inventory Power Correction for Variable History.

Comparison of Expected and Actual Source Inventories. Qualitative Assessment File Locations:

T-1 = TSC-1 = Office Area File

} T-2 = TSC-2 = Operations Area Fife T-3 = TSC-3 = Computation Area File E-1 = E0F-1 = ELRM Office File E-2 = E0F-2 EARS Office File

,=

g: Any discrepancies should be recorded on the Problem Tracking Form.

}

DC0118 101XX l

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. 69-10582 2/85 (12) . . Page 1 of 2

. PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS 0!A8LO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: EMERGENCY FACILITY FORMS FILE LIST CURRENT

! FORM (APPR0XIMATEQUANTITY)

DATE NUMBER TITLE T-1 T-2 T-3 E-1 E-2 '

i 69-9221 Emergency Notification Record 20 20 20 20 20 69-9248 Post-Earthquake Evaluation Summary 5 69-9249 Post-Earthquake Level Indication 5 Checklist

69-9250 Post-Earthquake Area Inspection 5 69-9251 Post-Earthquake Surveillance Test 4

Check List 5 i

3 69-9252 Electrical Power Check List 5 69-9259 Emergency Environmental Monitoring Field Data Sheet 20 10 10 20 20

69-9260 Work Sheet for Detemination of Release Rate or Total Release from Plant Vent Monitoring 5 5 20 5*40

! 69-9283 Data Sheet for T-G Peak Recording l Accolograph 5

! 69-9284 Work Sheet for Estimation of Curie Release 5 5 20 5 20 69-9310 Post-Evacuation Vehicle Monitoring Data 10 10 10 5 69-9311 Evacuee Monitoring Data 10 10 10 5 i .I 69-9320 High Radiation Area Entry Log 10 5 5 69-9321 Containment Entry Log 5 5 5 69-9370 Site Emergency Organization Assignment 10 5 5 69-9371 Environmental Monitoring Data Sussury 5 5 5 5 69-9392 Skin and Clothing Decontamination 10 10 5 69-9395 Record of Distribution of Potassium 10 10 10 10 todine 4 69-10059 Individual Accountability Record 20 69-10060 Summary of Personnel Accountability 10

69-10262 Radiological Emergency Status Fom 20 5 20 20 20 t 69-10295 Plant Status Emergency Fom 20 20 5 20 20 69-10296 Onsite/0ffsite Rad. Field Monit3 ring and P!C Status Form 20 5 20 20 20

)

69-10297 Emergency Organization Call List. 5 5 5 (On-site) i

! 69-10298 5 5 5 i Emergeacy)OrganizationCallList (Off-Site I t 69-10554 Emergency Exposure Pemit 10 10 10 69-10555 Work Sheet for Release Rate Estimation from Containment High Range Area 5 5 20 5 10 1 Monitors 69-10556 Release Rate Susanary 5 5 20 5 10 69-10566 Worksheet for Manual Off-Site Dose calculations 5 5 5 5 69-10581 Initial Emergency Notification Form 5 5 5

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DC0118 100XX 1 i l

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69-10771 2/85 (4) ,

Page 5 of 5 TITLE: CMERGENCY OPERATIONS FACILITY INVENTORY CHECKLIST LUNCHROOM (Continued) 1 Kitchenette 1 Clock 2 100-cup Coffee Pots Misc. Supplies (Coffee, Cups, etc.)

2 Folding Tables 2 Pictures STATE / FEMA 5 Chairs 4 Desks 1 Table 4 Multi-line Phones 1 Single-line Phone 2 Yellow-Net Phones 2 Status Boards (STATE, FEMA) 1 50 Mile Map 1 BEPZ Map 1 Easel PE 13 Chairs 2 Desks

('

3 Tables 1 10' Table 4 Multi-line Phones 1 Red Phone 1 Blue Phone 1 Black-Net Phone 1 Yellow-Net Phone 2 White Boards 1 50 Mile Map 1 BEPZ Map 1 Clock DC0118 99XX

69-10771 2/85 (4) Page 4 of 5 j TITLE: EMERGENCY OPERATIONS FACILITY INVENTORY CHECKLIST RADIOLOGICALMONITORINGDIRECTOR(Continued) l 1 Speedcall Motorola 434 Display 4 Clipboards (White)

1 Count Rate Meter

1 Multi-line Phone 1 Cork Bulletin Board UNIFIED DOSE ASSESSMENT CENTER I 19 Chairs 6 Desks 7 Tables 10 Multi-line Phones

6 50 Mile Maps 6 BEPZ Maps i 5 Modular Shelves with Lights

1 Overlay Base Map with 7 Overlays (Stability Classes A-G) {

1 Coat Rack 2 Clocks .

1 Savin 5040 Copter !

1 IBM Selectric !!! !

1 Aerovironmental Model 324 Telephone Line Receiver j 1 Stamp Clock l Correct Time and Day 1 Hewlett-Packard 2621P Terminal 1 Hewlett-Packard 9845C Desk-Top Computer ,

1 Hewlett Packard 98041 Disc Interface l

1 Hewlett-Packard 7906 Disc Drive l l 1 Hewlett-Packard 13037C Disc Controller 2 5-drawer files l EmergencyProceduresVol3A438(3 binders)

Emergency Plans Vol 11 (2 binders)

Nuclear Emergency Response Casuunications Directory (5) 4 controlled Copy #517-520 and 527 4 status boards (Significant Events, UDAC Duty Roster, Field Monitoring ;

Data,RadiologicalStatus)

16 Clipboards '

1 First-Aid Kit '

i 1 Savin Copier Table 3 Cork Sulletin Boards

, 3 TI-30!!! Calculators

2 Giltronix Selectro-Switch

1 Data Circuit to PGandE Engergy Info Center i 1 Black Box 1 Digital Decwriter IV i i 1 HP 2624A Teminal l LUNCH ROOM l

1 28 Chairs !

7 Tables

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!I DC0118 98XX f

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69-10771 2/85 (4) - -

Page 3 of 5 TITLE: EMERGENCY OPERATIONS FACILITY INVENTORY CHECKLIST 1

PG&E LAW 0FFICE i

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1 Chair 1 Desk #

1 Multi-line Phone 1 Clock 3 Clipboards

, 1 Nuclear Emergency Response Communications Directory-Controlled Copy #530 1 Single-line Phone 1 Folding Table PG4E PU8LIC INFORMATION 4 Chairs 1

2 Desks

1 Table i 2 Multi-line Phones 1 Single-line Phone -

4 1 Yellow-Net Phone .

1 50 Mile Map -

1 SEPZ Map 1 IBM Selectric !!!

j 1 Sanyo AM-FM Cassette Radio 2 Typewriter Stands l 1 White Board

, 5 Clipboards Sony Television Nuclear Emergency Response Casuunications Directory-Controlled Copy #528 & 529 l 1 T! Silent 700 Portable Data Terminal

! 1 IBM PC Keyboard i 1 IBM PC Disk Drive 1 Clock 1 Tool Box 1 Sony Remote Caumender M-71 1 Cork Bulletin Board 1 Video 3104 Monitor i 1 Epson Printer ;

1 Coat Rack RADIOLOGICAL MONITORING O! RECTOR 2 Chairs 1 Desk -

1 Table i 1 Motorola Radio set

! 3 Motorola Nandi-Talkies j 3 Motorola Mendi-Talkie Chargers 1 5-drawer File 1 50 mile map 1 SEPZ Map

{ 1 Radeco Particulate Air Sampler with Cartridges and Envelopes 1 County Health Team Radio (Motorola Series 90) ;

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DC0118 97XX 4

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O Page 2 of 5 69-10771 2/85 (4)

TITLE: EMERGENCY OPERATIONS FACILITY INVENTORY CHECKLIS ENGINEERING ANO LOGISTICS RECOVERY MANAGER (C

)

~2

_ 3 Status Scards (Significant Events, Plant Status, Radiolo Operating Procedures Vol 2 (10 binders) Instrument Locations (1 Binder

~~~~ Orawing 102037 --

2 Panafax Phones

~~"""" 1 Harris Table

""~""~

1 Panafax Table

~~~~~

2SPDSChannelSelectors(A48) 1 SPOS Table 1 Harris Terminal 0900-000 2 SPDS Computers (A48)InstrumentReference(1 Binder)

Drawing 102038 -- )

_ Emergency Procedures Vol 3A & 38 (3 binders

~"""~

Licenses and Permits Vol 4 Radiation and Control # Stan Correct Time and Day on Rapidprint Time ClockChemic Z Temporary Emergency Plans Vol 11 (2 Sinders)

Procedures and Instructions Vol 9 (2 Sinders) l k)

~ Electrical Drawings Unitsorange) d 1 & 2 (4 Binders, blue)~'~~

_,_,,,_, Piping Schematics Units 1 & 2 (2 Sin ers, Instrument ) Sch

~~~~"~ Hosfri Seismic(1)ControlledCopy#277 Evaluation (7 Sinders)Z Nuc e

501-506 l

_,_,__ Corporate Emergency Response P an 3 Clipboards !

REC 0VERY MANAGER'S OFFICE 11 Chairs 1 Desk 1 8' Table

~ 1 Wite Board 1 50 Mile Map

""~~~ 1 8EPZ Map

~~"""" 1 Multi-line Speaker Phone 1 Black-Net Phone Z 1 Yellow-Net1 Bookcase Phone

~~~"" 1 5-drawer File' 1 Coat Rack

~ 1 Clock Emergency Procedures Vol 3A & 38 (3 81nders)

Emergency Plans Vol 11 (2 8tnders) #278 and #279 Z Corporate Emergency Response tions Directory Plan (2) Controlled Copy (

, ___,,,,, Nuclear Emergency Response Communica

_ 4 Clipboards DC0118 96XX 1

-- y --,_y___ ---.,,--.--,.,--,,_,.~.y...- _.m.._.-.m_.- . - - _ . _ _ _ . _ _ _ . _ - - . . . - - - - , . .--__-,v._,-

69-10771 2/85 (4) Page 1 of 5 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: EMERGENCY OPERATIONS FACILITY INVENTORY CHECXLIST OFFICE SUPPLIES Check contents of all desks and file cabinets for ample quantities of stationary supplies, sucit as: ball point pens, erasers, felt pens (various colors), rubber bands, paper clips, pencils, scissors, rulers, ruled note paper, stapler removers, scotch tape, carbon paper, assorted plain paper, etc.

OPERATIONS AND ANALYSIS RECOVERY MANAGER 1 Chair 1 Desk 1 50 Mile Map 1 BEPZ Map 2 Motorola Radio Sets with Encoder 1 Multi-line Phone Emergency Procedures Vol 3A 438 (3 Binders)

Emergency Plans Vol 11 (2 Binders) g Corporate Emergency Response Plan (1) Controlled Copy #299 Nuclear Eme.gency Response Connunications Directory (1) Controlled Copy #500 4

3 Clipboards 1 Key Box 1 First-Aid Kit 1 Bookcase 1 Cork Bulletin Board 1 Half Table State of California Nuclear Power Plant Emergency Response Plan (7 binders)

ENGINEERING AND LOGISTICS REC 0VERY MANAGER 6 Chairs 3 Desks 1 Table 3 Half Tables 2 Motorola Radio Sets with Encoder 4 Multi-line Phones 1 IBM Selectric !!!

2 Panafax Machines 1 Savin 5040 Copfer 2 Bookcases 2 SPDS Video Monitors with Display Generators (A48) 2 SPOS Giltronix Selector Switch (A48) 1 Tektronix 4631 Hard Copy Machine 1 IT Intermediate Terminal ADM-31 1 Tanberg TDC 3000 Olgital Cartridge Recorder 1 Tektronix 4006-1 Tenninal 1 Olgital Deewriter !!!

1 Recall Recorder (plus Giltronix Selectro Switch) 1 Coat Rack Tektronic Table DC0118 95XX

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Page 4 of a 69-10770 ~7/85) ,

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TITLE: EMERGENCY OPERATIONS FACILITY EQUTPMENT FUNCTION CHECKLIST ERFDS / SPDS Verify the operability of the EOF ERFDS/SPDS.

a. Look at the Video Monitors and observe that the time and date are correct a that the data is updated every 1-5 seconds. Toggle the switch on the VIDEO SWITCHER and observe the same,

b. At the RECALL DISPLAY COMPUTER initializa the unit by pressing the AUTO LOAD button on the microcessette tape transport. Observe the red BUSY light blinking for 3-5 minutes as the program loads. Then observe on the ADM31 Terminal to the right of the computer the following message: "R)EAL TIME, D)ELOG OR Q)UIT." Press "R" and observe the data displayed on the screen.

Observe that the data is updated every 3-5 seconds.

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. 69-10770 7/85 , , .Page 3 of 4 TITLE: EMERGENCY OPERATIONS FACILITY EQUIPMENT FUNCTION CHECKLIST PHONE LIST TITLE PHONE # GOOD BAD SPDS [] []

ESE [] []

LAW [] []

MET [] []

RMD [] []

UDAC [] []

DCPP [] []

UW [] []s MET [] []

MD [] []

UDAC [] []

ELRM [] .

[]

'- RM [] []

OARM [] [']

RERM [] []

EARS [] []

PIRM [] 4

[]

ELRM [] []

RM [] []

0 ARM [] []

RERM [] []

EARS [] []

'PIRM

[ ]. []

SPos [] []

ESE [] []

SEC []

[]

M: Any discrepancies should be recorded on the Problem Tracking Fom.

.0C0118 93XX N

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. 69-10770 7/85 (12)~ .

Page 2 of 4 TITLE: EMERGENCY OPERATIONS FAP'LITY EQUIPMENT FUNCTION CHECKLIST a

LIGHTS Make sure that all lights trrn on and off. (Second floor only)

Note any problems below:

COPIERS There are 2 Savin 5040 copy machines in the EOF. One is located in the ELRM office, the other is in the UDAC office. Turn on main power switch located at right side of machine. Then push "on" button on top of the machine. Wait for copier to warm.up.

A beeping sound will call when machine is ready. Also, the word " READY" will appear on LED display. Set number of copies at 30. Place original in auto-feed. Lighted sign will verify that original is inserted. Press PRINT. Copier should accept original, print 30 copies, and return original. Turn copier off when finished.

Check for supplies of copy paper (at least 6 packages). Check for copy machine dispersant and toner (at least 2 bottles of each). ..

~

Note any problems or concents below- )

i PANAFAX Turn on power. Call Admin. Operato nd ask Operator for someone to help test Panafax System. Transmit I message rom EOF to office. Receive 1 message from office. ~

Note any problems or consnents, below:

DC0118 92XX s .

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69-10770 7/85 (12) .I Page 1 of 4 i PACIFIC GAS AND ELECTRIC COMPANY

{

DEPARTMENT OF NUCLEAR PLANT OPERATIONS '

S DIABLO CANYON POWER PLANT UNIT NOS.1 AC 2 TITLE: EMERGENCY OCERATIONS FACILITY EQUIPMENT FUNCTION CHECKLIST DATE PERFORMED BY:

PHONES Check only those phones that exist on the second floor of the building. Check by using the multi-line phone on the Engineering and Logistics Recovery Manager's desk.

Lift the receiver, push each button, lo light and listen for the dial tone. Now push the button label Dial all of the 549-xxxx numbers. Then push the button labele Dial all of the 69-xxxx numbers (dial just the last 4 digits). or eac the numbers dialed listen for a ringing tone in the earpiece. NOTE: Not all of the phones have an audible telephone bell so listen only for the ringing tone in the earpiece. Check that each phone can maintain two-way comunications, using the phone checklist on page 3.

Check the phones in the NRC Office and in the State / FEMA Office following the same fonnat as stated above. .

Verify opera the NRC Red Phone to Bethesda, Maryland. Notify the plant Shift Foreman rior to perfonning this check. Lift the receiver and verify the phone rings answered by NRC in Bethesda and two-way comunication can be maintained. Request the NRC person answering to ring back. Verify the telephone rings and establishes two-way comunication. .

Verify operability of the NRC Health Physics Phone (blue) by dialing extension 22 and establishing two-way comunication with Bethesda, Maryland.

Note any problems or coments below:

RADIOS

Check the radios in the OARM Office ELRM office, and in the Radiological Monitoring Director's Office. Check handie-talkies in RND's Of reise batteries at least quarterly. Call Diablo Canyon Unit 1 by phone to let Control Operators know you are going to check the radios. Turn rad o on. For the OARM and ELRM office radios with frequency selection, select F2. Pick up handset (radios in OARM Office). Use encoder to call Of ablo Canyon Control Room: code 41, push button

. 4 and then button 1. Push transmit button on handset or desk top microphone.

Transmit message, "Diablo Control, this is the EOF. Radio check." Release transmit button and wait for response. If there is no response within 20-30 seconds, repeat i encode and mestage. Make sure power is turned off when finished. For handie-talkies select FS and (sil the Radiological Monitoring Director's office, repeat using F6 to '

check the local receiver.

Note any problems or connents below:

,[ ] Check if hai di-talkie batteries are exercised.

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DC0118 91XX

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4 69-10769 8/84 Page 1 of 1

. PACIFIC GAS AND ELCCTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYCN POWER PLANT UNIT NOS. 1 AND 2 TITLE: OPERATIONAL SUPPORT CENTER CHECX LIST DATE PERFORMED BY Operational Support Center (Access Control / Cold Machine Shop Area)

1. Check emergency C8X extension by calling Unit 1 Control Room.

Verify the Control Room answers. []

General Maintenance Foreman's Office Access Control

2. Check ATL to CR/TSC by lifting receiver, verify Control Room answers. []

3. Nuclear Emergency Response Cannunications Directory - Controlled []

Copy #521 and #522. ,

4. Status boards []

Emergency Team Radiological

5. Security Building Ready Room i

Check C8X extension by calling Unit 1 Control Room. Verify the []

Control Room answers.

g: Any discrepancies should be recorded on the Problem Tracking Fonn.

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69-10768 6/85 (12) Page 2 of 2 TITLE: TECHNICAL SUPPORT CENTER EQUIPMENT OUANTITY CHECKLIST RECORDS OFFICE (CONTINUED)

Teledyne Geo Tech Auto Met V Computer IBM PC 3270 Teminals Remote Ofsplay System Construction OWG Index Books 1 and 2 7 Phone Books Panafax Document Transmitter - PX-100 Micro-fiche Printer / Viewer Hewlett Packard Computer Terminal (1)

Instruction Manuals - Hard Copy in Cabinets Plant Manuals .

Volume 2 Operating Procedures A-8, C, 0-F, G-J K, L-0 Volume 3 Emergency Procedures, #66, 67, 79 Volume 3A Emergency Procedures, #66, 67, 79 Volume 38 Emergency Procedure, #66, 67, 79 Volume 4 Licenses & Pennits, #67 Volume 7 Radiation Control Standards, #67 Volume 9 Temporary Procedures & Instructions, #67 Volume 11 Emergency Plans, #66, 67, 79 Volume 16 Annunciator Response, #67 *=

Volume 1-11 Final Safety Analysis Report RMS Handbook - TSC Equipment Record Number Index Corporate Emergency Response Plan, Control #271-273 Nuclear Emergency Response Connunications Directory (2 binders)

Controlled Copy #271 and #531 Emergency Resources Manual - INPO RP/EP-19/80 Report on Small Break Accidents for Westinghouse MSSS System. Vol. I, II, !!!

Reference Dwg. 102037, 102038 - Instrument Locations Reference Dwg. 101876 Main Annunciator Input List 101900 - List of Equipment Location Codes - Unit 1 Operating)

Folders Valve Identification Diagrams, Control Copy #31 - Unit 1 (Black Instrument Schematics, Control Copy #24 (Green Folders)

Electrical Diagrams, Logic Diagrams & Electrical Arrangements, Control Copy

27 Unit 1 and 2 (Blue Folders)

Piping Schematics, Control Copy #3 (0 range Folders)

NRC OFFICE NRC " Red" " ENS" Phone NRC Blue HPN Phone.

E: Any discrepancies should be recorded on the Problem Tracking Fam.

OC0118 89XX

l 69-10768 6/85 (12) Page 1 of 2 PACIFIC GAS AND ELECTRIC COMPANY l DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 l TITLE: TECHNICAL SUPPORT CENTER EQUIPMENT QtANTITY CHECKLIST OFFICE 50 Mile Emergency Planning Zone Map Basic Emergency Planning Zone Map 1 Rolm Telephone Console with Handset Status Boards (6) 1 Telephone Number Board 5 MSA SCBA's 6 Calculators 6 Extra Calculator Batteries Emergency Forms per Forn 69-10582 1 Emergency Equipment Cabinet (with following items inside):

1 Headset Box of Office Supplies (Verify ample Stationary Supplies)

Emergency Telephone (NERC) Directory (9) Controlled Copies #508-516 15 Nameplates 1 Case of K!

10 Dosimeters 1 Dosimeter Charger .

OPERATIONS CENTER Closed Circuit TV Monitors - 5 Color 1 Black and White Portable Video Camera Tape Drive & Disc Harris Processor - Computer

' Harris Terminal Harris Key Stations - 2 Harris Line Printers (1)(Terminals)

Emergency Forms per Form 69-10582 SPDS and Related Equipment IBM PC 3270 Terminal EARS OFFICE l -

EARS Computer and Operating Terminal - HP 9845C 1 Status Board 1 Set Otspersion Overlays and Map in Holder TI OMN! 800 Printer Oose Rate Meter Count Rate Meter Emergency Forw per Forn 69-10582 50 Mil? Emergency Planning Zone Map Basic Emergency Planning Zone Map 1 Case of K! -

RECORDS OFFICE -

Aperture Card Viewer Aperture Card Files with Cards Microfilm Printer / Viewer with Reels i DC0118 88XX

, 'i 9

k 69-10767 7/85 (12). Page 4 of 4 i

TITLE: TECHNICAL SUPPORT CENTER CHECKLIST

> b. Open the cabinet labeled RSPSC-12. Look on the front panel display of the Recall Recorder Computer for the message "8 & W - RECALL RECORDER - OPERATING Dx-Ty" (where x indicates the tape drive and y indicates the track where the -

data is currently being recorded). Look at the drive that is currently being recorded on and observe that the tape moves approximately once every 3 seconds,

c. Open cabinet labeled RSPSC-21. Look on the front panel displays of the Data Handler Computers for the message "8 & W RECALL - Data Handler OPERATING".

d. Open the cabinet labeled RSPSC-22. Look on the front panel display of the Recall Recorder Computer for the message "8 & W - RECALL RECORDER - OPERATING Dx-Ty" (where x indicates the tan drive and y indicates the track where the data is currently being recorded). Look at the drive that is currently being recorded on and observe that the tape moves approximately once every 3 seconds,

e. Look at the Video Monitors and observe that the time and date are correct and that the data is updated every 1-5 seconds. Toggle the switch on the VIDEO SWITCHER and observe the same.

f. At the RECALL DISPLAY COMPUTER initialize the unit by pressing the AUTO LQ&p button on the microcassette tape transport. Observe the red BUSY light blinking for 3-5 minutes as the program loads. Then observe on the ADM31 ,

Terminal to the ri D)ELOG or Q)UIT." ght of the Press "R"computer the the and observe following message:on data displayed "R)EAL TIME, the screen.

Observe that the data is updated every 3-5 seconds.

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. 69-10767 7/85 (12) .

Page 3 of 4 TITLE: TECHNICAL SUPPORT CENTER CHECKLIST Verify functioning of one SLO off premise extension by calling any plant extension using 8-69-ext. number.

Office

[]

Operations Center

[]

EARS Office , []

3. Verify functioning of the Black Net Telephone by calling any

extension.

[]

4. Verify functioni the NRC Red Phone to Bethesda, Maryland. Notify the plant Shift Foreman rior to performing this check. Lift the receiver and verify the phone rings, s answered by NRC in Bethesda and two-way communication can be maintained. Request the NRC person answering to ring back. Verify the telephone rings and establishes two-way comunication. []

5. Check functioning of the Control Room Closed Circuit TV's as follows (Refer to operating instructions in the TV desk drawer): -

Color monitors 1 - 5 receive pictures from cameras 1 - 7 []

Black and White monitor f6 receives pictures from cameras 8 and 9., []

k Pan, zoom and focus controls on cameras'1 -'7 function '

i. []

g; Close the iris on cameras ~l - 7 following check.

6. Equipment Quantities - Check per Form 69-10752 Note discrepancies below:

g: Any discrepancies should be recorded on the Problem Tracking Form.

7. Verify the functioning of the Emergency Response Data System / Safety Parameters Display System (ERFDS / SPDS) as follows:

a. Open cabinet labeled RSPSC-11. Look on the front panel displays of the Data Handler Computers for the message "8 & W RECALL - Data llandler OPERATING".

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69 1 767 7/85 (12) .

Page 2 of a TI. : TECHNICAL SUPPORT CENTER CHECKLIST

'a Note any problems with the radio console:

2. Telephones NDTE: CBX Telephones not in routine use need to be checked.

Check functioning of tt ROLM Console by turning on, calling the plant emergency number

rom any phone and receiving the call at the console. E e call to any extension and verify connections between the originating phone and the ringing phone. []

TURN OFF CONSOLE AFTER CHECKING .,

Verify the ATL to San Luis Obispo County Sheriff's Dispatch Center by verifying the phone is answered at that office and two-way communication can be maintained.

Verify the ATL to the State Office of Emergency Services by verifying the phone is answered at that office and two-way cmununications cap '

1 be maintained. Check both extensions (Site Emergency Coordinator's -

desk and dARS office) []

Check functioning of the following A'TL's by verifying they ring when selected. Allow to ring long enough so someone in the vicinity can answer, if available: []

0FFICE OPERATIONS CENTER EARS OFFICE CR-1 [] [] []

CR-2 [] [] []

OSC [] []

EOF [] [] []

s DC0118 85XX

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l' 69-10767 7/85 (12) Page 1 of 4 o , PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: TECHNICAL SUPPORT CENTER CHECKLIST 1 .

DATE PERFORMED BY

1. Radios Check operability of the following: (Use Operating Procedure K-9

" Instructions for Operation of DCPP Radio Systems")

Operations Modules Check operability of the Repeater / Local, Backup and Remote Modules by receiving available selecting traffic or by one and check calling module functioning the Information Center by(encode 22 on F1) or Morre 8ay (encode 33J. []

g: Transmitter functioning is checked by operations using STP I-29 Security Modules ,

Check function of the Repeater / Local, Backup and Remote Modules by selecting one and check module functioning by receiving local traffic. []

g: Transmitter functioning is checked by Security.

Division Radio Check module functioning of the Division Radio Modules by selecting each and receiving available Traffic.

g: Transmitter functioning is checked by Operations using STP I-29.

g: If no traffic is available note that below.

H/P Radio Check functioning of the Repeaters, Local and HP Remote Modules by

" selecting one at a time and activating an Emergency Organization pager unit. []

g: Pager must be outside the TSC to receive the signal.

CDF Radio - Check that radio is located in Emergency Eqaipment Cabinet. []

g: Transmitter functioning is checked by Operations using STP I-29.

g: Any discrepancies should be reported on the Problem Tracking Fom.

DC0118 84XX s

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o 69-10766 (12) 2/85 Page 1 of 1

. PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: CONTROL ROOM CHECKLIST DATE, PERFORMED BY I CONTROL ROOM

1. Dose Projection Equipment (1) Base Map (7} Jverlays (Stability Class A-G)

2. (2) Nuclear Emergency Response Consnunica.tions Directory -

Controlled Copy #272 and #273

3. (6) Microphone / Amplifier Units (Improves voice communications while wearing MSA breathing masks) Change 9V Alkaline Batteries Quarterly

=

OPERATOR READY ROOM

1. (8)SCBAUnits t

hyTE: Any discrepancies should be recorded on the Problem Tracking Form.

DC0118 83XX

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69-9043 2/85 (5) Page 3 of 3 TITLE: EMERGENCY PLAN PHONE NUpBER VERIFICATION CHECKLIST CHECKED BY DATE PROCEDURE NO. PAGE NO. AGENCY COMMENTS (Note How Checked)

EP EF-1 p. 2. Attachments Hot Shutdown Panel, Dedicated Shutdown Panel, 1, 2, 4 Control Room EOF, CIRC, Dosimetry Personnel EP EF-3 p. l' E0P Checklist and Phone Numbers EP EF-4 Attachment 1 PT&T and PGandE Attachment 4 Cal Poly Police EP EF-5 Attachment 1 EOF, UDAC TSC, DCPP EP EF-7 p. 10 CIRC Harris Computer Help EP EF-8 p. 1 Hewlett-Packard EARS Hardware EP RB-3 p. 2 Corporate Materials Coordinator EP RB-8 p. 3 UDAC EOF, TSC EP G-2 Attachment 1 Emergency Organization Call List

p. 1-31 EP G-3 Attachment 2 Emergency Offsite Organization Call List Attachment 3 Nobile Phone and Pager Instructions EP G-4 p. 5 Emergency Conference Line

p. 5 Emergency Conference Line

p. 8, 9 Control Room, TSC, Cold Nachine Shop.

Access Control

p. 10 Security Butiding, Training Building, Biology Lab NOTE: Any discrepancies should be recorded on the Problem Tracking F8rm.

DC0ll8 82XX

Page 2 of 3 1

69-9043 2/85 (5)

TITLE: EDERGENCY PLAN PHONE IRMBER VERIFICATION CHECKLIST-l DATE CHECKED BY ComENTS (Note How Checked)

AGENCY PAGE NO.

PROCEDURE NO. ,

Appendix Z Supervising Nuclear Generation Engr.

EP M-2

Division Field Claims Investigator P. 5, 9, and UC Berkeley Seismograph Station

! EP M-4 Attachment

Security Extensions I

EP M-6 p. 3 l

p. 9 Fire Assistance Communications List Plant Phones (p. 1.2 - 37.2) i '

Attachment 2 PGandE Law Department, Mr. David Williamson EP M-7 p. 2 l Organizations to be notified in the event of

p. 2 an oil spfli

- California State Office of Emergency Service 1

p. 2 i

p. 3 California State Land Cossatssion

p. 3 State Executive Officer i

' California Regional Water Quality Control Board

Central Coast Region j

San Luis Ambulance and French Hospital

p. 5 Supervising Nuclear Generation Engr.

I / EP M-9 Attachment PG&E Law Department J SLO Ambulance, French Hospital, Fire Assistance i EP OR-1

p. 2 Table 1-OffsiteEmergencySupportOrganization Attachment 2 Attachment 1 Media Notification List

! EP OR-2 D00118 81XX i

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n PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABL3 CMYON POWER PLANT

. TITLE: EERGENCY PLAN PHONE INSWER VERIFICATION CECKLIST E

CHECKED BY DATE PROCEDURE NO. PAGE NO. AGENCY C0ftlENTS (Note How Checked)

EP OP-8 p. 8 TSC Operator, dedicated shutdown panel, 480V vital switchgear area, 4 KV vital switchgear area EP R-1 Attachment 7 Safety. Health & Claims (Personnel Injuries) i p. 1 & 2 -

p. 11 San Luis Ambulance and French Hospital

p. 16 Supervising Nuclear Generation Engr.

EP R-3 p. 3 State Executive Officer, Calif. Regional Water Quality Control Board, Central Coast Region EP R-6 p. 10 Appendix 1

, Appendix 2 (1.2R - 20.2R) .

EP R-7 p. 9 Supervising Nuclear Generation Engr.

a

p. 10 Lac Padres District Manager EP M-1 Attachment 10 Supervising Nuclear Generation Engr.

Attachment 7 List of Physicians, Hospitals & Ambulances serving the inusediate area of Diablo Canyon.

, Attachment 8 List of Physicians Hospitals, and Ambulances I serving the immediate area of Diablo Canyon Attachment 9 Safety. Health and Claims. **

DC0118 80XX '

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69-10507 6/85 (5) Page 7 of 7 POST-LOCA SAMPLING KIT INVENTORY CHECK LIST DATE PERFORMED BY CONTENTS OF POST-ACCIDENT SAMPLE KIT

~~

CHECKED PART 2. THE POST LOCA ROOM (Continued) DEFECTIVE NORMAL OR REPLACEMENT ITEM ,

QUANTITY OK MISSING REPLACED LOCATION i

12. Under Sink I Boric Acid Standard'- 200 ppa (50 ml ,, ,? ,, Prepared in Chem Lab

, 4 10 ppe (50ml ,, ,,, ,,

1 6 ppe (50 ml ,, ,, ,,

i - 4 ppm 50 ml ,, ,, ,,

- 2 Ppm 50 ml ,, ,, ,,

]

- 1 ppm 50 mi) ,, ,, ,,

1 Concentrated hcl 100 ml

Chem Lab -

Concentrated H SO 100 ml

Chem Lab Carminic ht4,b18 tion 100 ml Prepared in Chem Lab j Caustic Cleaning Solution 1/2 gal ,l ll ,l "

Acid Cleaning Solution 1/2 gal ,, ,, ,,

i Squeeze bottle with desin water 1 ,, ,, ,, Chem Lab Acetone 1/2 liter Chem Lab 101 Metha %1s 1/2 liter 1/2 liter ll ll ll Prepared in Chem Lab i

' Dilute NaHCO HNO3(rcidwash) 200 g Chem Lab 3

13. Near Sink Oxygen reagenc >100 psig [.] [] [] G.C. Warehouse

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a i 900118 79xX

69-10507 6/85 (5) Page 6'of 7 POST-LOCASkINGKITINVENTORYCHECKLIST DATE PERFORMED BY CONTENTS OF POST-ACCIDENT SAMPLE KIT CHECKED PART2.THEPOSTLOCAROOM(Continued) DEFECTIVE NORMAL OR REPLACEMENT ITEM QUANTITY OK MISSING REPLACED LOCATION

10. D4 Sealing Tape (roll') 1 ,, ,, ,, Count Room L&N recorder paper (rolls) 3 ,, ,, ,, Chem Lab CCP printer paper (rolls) 3 ,, ,, ,, Chem Lab / Access Control Radioactive Sample Tape (roll) 1 ,, ,, ,, Access Control Allen wrenches (sma11 set) 1 Screwdrivers - one flathead 1

- one phillips 1 -

Dionex wrench (5/16)

Septum adapter 1

1 ll ll ll -

I & C Shop Cap for septum port 1 I & C Shop

11. Door next to drawers Pipets w/ tips 1 5 ml 1 Chem Lab 2

3 1 al/1000 p1 100p1 1

1 ll ll ll "

4 "

10u1 1 5 0-S m1 "

1 6

7 2 mi volumetric pipet 5 mi volumetric pipet 1

1

'l

'l ll "

Pipet bulb 1 ,, ,, ,,

50 mi erlenmeyer w/ rubber stoppers 4 ,, ,, ,,

Tongs 1 ,, ,, ,

100 mi volumetric flask 4 Chem Lab 100 m1 beakers 2 I

pent 1H 7RXX

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69-10507 6/85 (5) Page 5 of 7 POST-LOCA SAMPLING KIT INVENTORY CHECK LIST DATE PERFORMED BY 1

CONTENTS OF POST-ACCIDENT SAMPLE KIT CHECKED PART 2. THE POST LOCA ROOM (Continued) DEFECTIVE NORMAL OR REPLACEMENT ITEM QUANTITY OK MISSING REPLACED LOCATION

7. D1(TopDrawer)(Continued)

Ruler w/ millimeter graduations 1 ,, ,, ,,

Safety Glasses

~

2 ,, ,, ,, Chem Lab / Machine Shop Single Edged Razor Blades 1 , ,,

Machine Shop Scotch tape 1 Office Supplies

8. D2 -

l Hand operated vacuum pump 1 ,, ,, , ll -

Prelabeled 60 mi sample bottle 5 ,, ,, ,, Cabinet - West Wall Prelabeled 15 mi sample bottle 5 ,, ,, ,, Cabinet - West Wall 20 cc liquid scint vials 5 ,, ,, ,, Chem Lab 1 cm spec cells w/ plugs 5 Chem Lab

9. D3 Loaded filter assembly 5

Precut septums for CASP SF-5 5 .

Chem Lab Prelabeled 14cc gas sample vial Keys for FCV's 6%-700 5

1 ea

l ll

'l Chem Lab Control Key Locker to Copy Gas tight Scc locking syringe 2 ,, ,, , Chem Lab i G.C. Chart recorder paper (rolls) 3 ,, ,, ,, Access Control Needles for gas tight syringe 5 Chem Lab

10. D4 Wrenches 2 ' '

Extra Ziploc bags 5

Chem Lab Small screwdriver 1 l -

l .

i neniin 77ry

4 69-10507 6/85 (5) page 4 of 7 POST-LOCA SA M LING KIT INVENTORY CHECK LIST DATE PERF0fttED BV

! CONTENTS OF POST-ACCIDENT SAMPLE KIT CHECKED PART2.THEPOSTLOCAROOM(continued) DEFECTIVE NORMAL OR REPLACEMENT

ITEM QUANTITY OK, MISSING REPLACED LOCATION 1

5. North Vestibule (between N. Submarine doorandkeycarddoor)

GE Post Accident Sampling Shipping Package 1 [] [] [] -

1

6. Cabinet - in or near !

' t 5 ton come-a-long w/ extension strap 1 ,, ,, ,l Machine Shop E-140N 1 Access Control Storage ,

Issued for use procedures: '

1 EP RS-15 1 ,, ,, ,, MaintaipdbyChes&RadClerk i EP RB-16 1 CAP G-3 "

1

Extra 15 and 60 m1 sample bottles Needle flush tool 20 each 1

ll ll ll -

idyp-Alls or Paper Towels (pkg)

Flashlight, extra batteries 2

1 ll ,'l ,',' Chem Lab Access Control Desk

Klawipes (boxes) 2 ,, ,, ,, Chem Lab i j Large plastic bags 10 Access Control 2

7. D1 (Top Drawer) j Pens - Sanford 4 ,, ,, ,, Office Supplies

- Ball Point 4

Labels (sheet) 1 Gloves (pairs)

Scissors 5

1 ll l, l, Chem Lab Office Supplies Stopwatch / clock 1 ,, ,, Radiation Foreman's Office ;

]

Calculator 1 l -

l l

l

! ncnina 76xx C

O 69-10507 6/85 (5) Page 3'of 7 POST-LOCA SAMPLING KIT INVENTORY CHECK LIST DATE PERFORMED BY CONTENTS OF POST-ACCIDENT SAMPLE KIT CHECKED PART 2. THE POST LOCA ROOM DEFECTIVE NORMAL OR REPLACEMENT ITEM QUANTITY OK MISSING REPLACED LOCATION

1. Motor Repair Shop Argon Gas >1000 psig ,, ,[ ,, G.C. Warehouse # 930679 2000 ppe Hydrogen Span Gas >100 psig ,, ,, ,, G.C. Warehouse # 930677 101 Hydrogen Span Gas >100 psig G.C. Warehouse # 930678

2. Located around the room

~

CASP cart / cask 1 PI-1109/PI-1116 1 each Buffer: pH7, 4 or 10 Meter-long reach rod

>2 gallons 1

'l

'l ll Chem Lab LSP cart / cask 1 -

-60 m1 bottle lift rod assembly

-15 mi bottle lift rod assembly 1

1 l'

',l l',

-auxiliary shield 1 SCBA air bottles 6 kux. Bldg. or Access Control

3. Hot flie Boron Calibration graph 1 ,, ,, ,, Prepared by CARP Tech.

Chloride Calibration graph 1 ,, ,, ,

i Hydrogen Calibration graph - CA 1 ,, ,, ,,

Hydrogen Calibration graph - off gas 1 J ,1 a

4. Hot Cell / Sink Area 1 [] [] []

Fully operable hot cell 1 , ,ll ,,

Shielded sample holder brick 1 , ,, ,,

Spectrophotometer 1 , ,

Chem Lab Demineralized water in 5 gallon carboy 1 . Chem Lab e*

DC0118 75XX

PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS v DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 POST-LOCA SAMPLIKG KIT INVENTORY CHECK LIST DATE PERFORMED BY CONTENTS OF POST-ACCIDENT SAMPLE KIT CHECKED PART 1. THE 85' LOCKER DEFECTIVE NORMAL OR REPLACEMENT ITEM QUANTITY g MISSING REPLACED LOCATION

1. Instruction Binder

a. Sanford Marking Pens 2 ,, ,, ,; Maintained by

b. Red Marking Pens 2

Chem and Rad Clerk

c. Black Marking Pens 2

d. EP R8-15 " Sentry Post Accident Sampling System - Initial Sampling 1

l' "

Exercise (Part A) "

e. EP RB-15 Data Sheets 5 [] [] []

2. Monitoring Equipment

a. Teletector (Eberline 6112) 2 Access, Control Storage Room

b. Dose Rate Meter (HPI-1010 or R0-2 2 l' or R0-2A)

c. Pocket Dosimeters (0-SR) 6 l Issued at Access Control d.

e.

PocketDosimeters(0-200mR)

Dosimeter Charger ,

6 1

ll ll ll Issued at Access Control Radiation Protection Foreman

f. Lapel air samplers 1 Air Pumps 6 ,, ,, ,,

Respirator Issue Room 2 Filter Holders 6 Access Control Cabinet 3 Filters I box

4 Connecting tubing 6 .I I

^

. DC01111 73XX

~

Page 2 of 7 69-10507 6/85 (5)

POST-LOCA SAMPLING KIT INVENTORY CHECK LIST PERFORMED BY DATE CONTENTS OF POST-ACCIDENT SAMPLE KIT CHECKED DEFECTIVE NORMAL PART 1. THE 85' LOCKER (Continued) OR REPLACEMENT HISSING REPLACED LOCATION OUANTITY OK ITEM

4. Protective Clothing.

Aux. Bldg.Dressout Stations F'

6

F '

a. Coveralls 6

ti. Hood 6 Access Control Cabinet WHf 56-5020 c c. Surgeon's Cap

d. Plastic Booties 24 l' l] l' Aux. Bldg.Dressout Stations l l

e. Rubber Shoe Covers Rad. Waste Bldg.

1 Giant 2 pair [l ,,

,l 2 pair 2)p Extra Large 4 pair

3) Large 2 pair

Medium 2 pair

4)) Small 5

12 pair f.

g.

Cotton liners Rubber gloves 12 pair 'l ', l ll "

Access Control Cabinet WHf 56-2230

h. Masking tape 3 rolls

Access Control Cabinet WHf 56-9320 Small plastic bags (for matches, 12

1. -

dostreters, etc) [] Access Control Locker Room

j. SCBA with full bottle 3 [] [] .

5. Miscellaneous

,l ', Access Control WHf 70-1200 Large plastic bag 10 l

a. 3 Access Control WHf 20-1234

b. Flashlight with batteries '

Access Control WHf 56-3001 c '. Extra batteries 6 .- l' e'

e i

ntnaen last

69-10598 10/85 (10) Page 3 of 3

- .

TITLE: HOSPITAL KIT INVENTORY CHECK LIST f

KIT NO. DATE PERFORMED BY l

l CHECKED DEFECTIVE OR ITEM OUANTITY OK MISSING REPLACED 36.' Forceps 1 [] [] []

37. Smear Pads 8" x 8" Cotton (Pkg. of 10) 2 [] [] []

38. Medical Referral Form (69-6015) 3 [] [] []

39. .ight Duty Letter 3 LJ [] []

40. Plastic Bag, 18" x 24" 12 [] [] []

41. 80X-60 Air Sampler or equiv. 1 [] [] []

RP#

O REVIEWED BY DATE

(

i I

l

.s DC0118 72XX i

ie m . -_ y ,., a r .-__,,-.._..m.___~..,-.---m-_

_ , - - - , - - , g ,.y._ h y,-w.-y-y- n,v-w,- -.- ---=y.ew- * - , - , - - - - - - - - - - - - ' '

69-10598 10/85 (10) Page 2 o9 3 0 ,

TITLE: HOSPITAL KIT INVENTORY CHECK LIST i

KIT NO. DATE PERFORMED BY l

CHECKED l DEFECTIVE i OR ITEM QUANTITY OK MISSING REPLACED

19. Spare Detector 1 [] [] []

20. Allen Wrench, 1/16" 1 [] [] []

21. HP!-1010 or equivalent RP# 1 [] [] []

CAL DATE

22. 0-20C mR Pencil Dosimeters 2 [] [] []

CAL DATE

23. 0-5A Pencil Dosimeters 2 [] [] []

CAL DATE

~

24. Dosimeter Char 9er w/ Battery 1 [] [] []

RP# **

25. 2" 5.aears w/ packet 250 [] [] []

26. 2" Air Sample Filter w/ Envelopes 50 [] [] []

27. 39mnAirFilterforBendix8DX-60(box) 1 [] [] [] )

28. Plastic Envelopes, 3" x 5" 30 [] [] []

29. Gununed Labels , 40 . [] [] []

30. Plastic 8ags. 38" x 65" 6 [] [] []

31. Grease Pencil 2 [] [] []

32. Ballpoint / Felt Tip Pens 3 [] [] []

33. Waterproof Pen 2 [] [] []

34. PersonnelDecon. Records (69-9392) 6 [] [] []

35. Radiation and Contaminat' ion 12 [] [] []

Survey Sheet 4

DC0118 71XX l

. 69-10598 10/85 (10) ., Page 1 of 3 PACIFIC GAS AND ELECTRIC COMPANY l

DEPARTMENT OF NUCLEAR PLANT OPERATIONS I

DIA8LO CANYON POWER PLANT UNIT NOS. 1 AND 2 I

TITLE: HOSPITAL KIT INVENTORY CHECK LIST '

XIT NO. DATE , PERFORMED BY ;

CHECKED DEFECTIVE OR ITEM OUANTITY K 0_K, MISSING REPLACE 0 *

1. Full Face Respirator w/ Type H or Equivalent Filters 2 [] [] []

2. Dis'posable Coveralls 4 [] [] []

3. Hood 4 [] [] []

4. Disposable Shoe Covers (pr.) ,

4 [] [] []

5. Surgical Latex Gloves (box) 1 [] [] [ ] .'

6. Rubbers (pr.) 4 [] [] []

7. MaskingTape,2" width (roll) 2 [] [] []

8. DuctTape,2" width (roll) 2 [] [] []

~

9. " Radioactive Material Area" Sign 5 [] [] []

~

10. " Surface Contamination Area" Sign 5 [] [] []

11. "High Radiation Area" Sign 2 [] [] []

12. " Radiation Area" Sign 5 [] [] []

13. Barricade Tape,100 yd Roll 2 [] [] []

14. Ty-wraps 30 [] [] []

15. " Radioactive Material" Labels, 4"x6" 10 [] [] []

16. " Radioactive Material" Labels,1"x3" 1 [] [] []

(roll)

17. E-140/N w/HP-210T or equiv. RPf 1 [] [] [3 CAL DATE

18. HP-260 or equiv. APf 1 [] [] []

4 DC0118 70XX

69-9369 2/85 (4) Page 1 of 2 PACIFICGASANDEiECTRICCOMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS -

DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: EVACUATION KIT INVENTORY CHECK LIST KIT NO. DATE PERFORMED BY CHECKED DEFECTIVE OR ITEM QUANTITY M MISSING REPLACED

1. Binder Contents

a. Emergency Procedures G-4, G-5 1 each [] [] []

b. Form 69-9310 50 [] [] []

c. Fom 69-9311 100 [] [] []

d. Form 69-9369 5-10 [' J - [] [].

2. Ballpoint Pens 4 [] [] []

3. Calculator (I.D.No. ) 1 [] [] []

Battery 1 . []

4. Flashlight 1 [] [] []

Batteries 2 []

5. PlasticBags(14"x24") 3 [] [] []

6. Bu11 horn (I.D. No. ) 1 []

Batteries 1 [] [] []

7. Packages of 2" Filters (10 filters Per package) 50 [] [] []

8. Barricade Tape, 100 ft rolls 2 [] [] []

9. Dosimeter Chgr. (RPf ) 1 [] [] -

[]

Battery ,

[3

10. Dosimeter Pencils, 0-200 mR 4 [] [] [] '

CAL DATE DC0118 68XX , ,

N

+ e

1 _ _ . .

, 69-9369 '2/85 (4) Page 2 of 2 TITLE: EVACUATION KIT INVENTORY CHECK LIST

- CHECKED DEFECTIVE OR ITEM OUANTITY OK MISSING REPLACED

11. Rad Owl 1 [] [] []

(Replacement Inst. RPf )

CAL DATE

12. Eberline E-140 Survey Meter or E140N 1 [] [] []

or equivalent (Replacement Inst. RPf ) l l

CAK DATE

13. HP-240 GM Probe or HP-210 or equivalent (RPf ) 1 [] [] []

14. Corporation Ke . 1 [] [] []

15. Information Center Emergency Room Key 1 [] [] []

REMARKS

. )

APPROVED DATE I

I DC0118 69XX g I _ _ _ _ _ _ _ _ _ __Ah x a .A

, 69-9823-3 6/85 (25) 80x C Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: EMERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION QUARTER DATE PERFORMED BY BOX C . QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED

1. Monitoring Equipment

a. Dose Rate Meter Rad Dw1/RO-2 *

(or equiv.)

RP# CAL DATE

b. Dose Rate Meter HP!-1010

s.

(or equiv.)

RPf CAL DATE

c. Survey Meter (Eber. E-140 or E-140/N or equiv.) 1 RP# CAL DATE i

d. Standard G-M Probe (Eber.

he-240/HP-270orequiv.) 1 RPf

e. Pancake G-M Probe (Eber. HP-210 or HP-260 or equiv.) 1 RP#

f. Dosimeter Charger 1 RPf

Check with appropriate inventory list located in information binder for kit requireme .ts.

DC0118 67XX

. _. _ _____ _ _ __ _ ___ __. . . . _ . _ . ~ _ _ _ _ _ . _ _ _ _ _

69-9823-2 /0/85 (25) 80X 3 o

Page 4 of 4 TITLE: EMERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION I QUARTER DATE PERFORMED BY 80X 8 QUANTITY DEFECTIVE

5. Miscellaneous Equipment REQUIRED PRESENT OR MIS $ LNG REPLACED

a. First Aid Kit (5fra 10) I

b. Masking Tape (2" wide rolls) 2

c. Battery Powered Lantern (w/6V Battery) 1

d. " Kwik-Kold" Packs 4

6. Signs + Barriers *

a. Radiation Signs (w/3 inserts) * *

b. Radiation Barricade Tape

(100' Rolls) 2 i

9

Check with appropriate inventory Ifst located in information binder for kit requirements .

4 DC0118 66XX

69-9823-2 /0/85 (25) B0x s a

TITLE: EMERGENCY KIT INVENTORY CHECK l!ST

KIT NO. KIT LOCATION QUARTER DATE PERFORMED BY BOX 8 QUANTITY DEFECTIVE REQUIRED PRESENT OR MIS $!NG REPLACED

4. Protective Clothing / Decontamination

a. Protective Clothing Sets (Coveralls, hood, booties, rubbers, gloves) 2

b. Full Face Mask 2

c. Type GMR-S Filters or GMI-H (orequiv.) .

for Face Masks (min.) 2 ,,

d. Smear Pads 8" x 8" cotton *

(Pkg of 10)

e. Paper Towels (pkg)

g

f. Plastic Sags (38" x 65") 3 i

Check with appropriate inventory list located in infonnation binder for kit requirements.

DC0118 65XX l

69-9823-2 10/85 (25)

BOX a TITLE: EMERGENCYKITINVENTORYCHECKLIST KIT NO. KIT LOCATION QUARTER DATE PERFORMED BY BOX 8 QUANTITV DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED

o. Emergency Environmental Monitoring Field Data Sheet ,

(Fonn 69-9259) 100

p. ComputationPaper(Packet) 1

q. Calculator S/N 1

2. A1r Sampiing Equipuent

a. Iodine Filter Cartridges

3 pkgs of 10 filters each: 9.

1 pkg-AgZ 1 2 pkg-TEDA 2

3. Sampling Equipment l

a. PlasticBajisApprox. 15 '

(18" x 24"a

b. Sample bottles (1 liter) *

Check with appropriate inventory list located in information binder for kit requirements.

~

DC0118 .64XX .

. O e

~

l

< a . , - .u

60-9823-2 fo/85- (25) 80x e PACIFIC GAS AND ELECTRIC COMPANY y DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: ENERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION QUARTER DATE PERFORMED BY BOX B QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED

1. Instructions. Procedures, and Supplies

a. Instruction Binder 1

b. Tables of Contents 1

c. Sanford Marking Pens 2 %

d. Red Marking Pens 2

e. Black Marking Pens 2

f. Ball Point Pens 2

{

g. SLO County Map I

h. Equipment Location Drawings (Set) Unit 1 1

1. Corporation Ke --

1

j. Information Center Key

k. " Emergency Onsite Environment

- Montr. Prog." RS-7 1

1. " Emergency Offsite Environment Montr. Prog " RS-8 ,

I

m. " Emergency Eauip., Instr..

and Supplies . EF-5 1

n. Record of Pota ssir e Iodide Distribution, r i;,#69-9395 o 1

Check with appropriate inventory list located in infonnation binder for kit requirements.

DCOI18 63XX 0 6 3

69 9823-1 10/85 (25) BOX A TITLE: EMERGENCYKITINVENTORYCHECKLISTkcontinued)

KIT NO. KIT LOCATION QUARTER DATE PERFORMED BY BOX A QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACE 0

4. Monitoring Equipment ,

a. Pocket Dosimeter (0-5R) 2 CAL DATE

b. Pocket Desimeter (0-200MR) 2 CAL DATE

5. Miscellaneous

a. GummedLabels(sheet) 5 .

b. Flashlight w/ Batteries *

c. Extra Batteries *

d. Roll of Dines 1

( e. Stopwatch I

f. Scissors 1 ,

g. CrescentWrench(8") I

h. Screwdriver 1

1. Grass Shears 1

j. K! Tablets (bottle) 1 Expiration Date

k. Casio digital watch 1

1. Bolt Cutter Two are available on well in storeroom of Training Building.

Check with appropriate inventory list located in information binder for kit requirements.

DC0118 62XX

69-9823-1 10/85 (25) 20x A TITLE:

Page 2 of 3 EMERGENCY KIT INVENTORY 6[Ecx (IST (continued)

KIT NO. KIT LOCATION QUARTER DATE PERFORMED BY 80X A QUANTITY DEFECTIVE REOUIRED PRESENT OR MISSING REPLACED

h. Paper Envelopes for Parti-culateSamples(AirSample) 25

1. Smear Packets 45 smear /pkt) 250

j. Plastic Envelopes for Iodine Cartridges (Ziploc 8 aggies) 30

k. Forceps 1

3. Protective Clothing / Decontamination .

a, s Radiacwash Decontamination Agent (1 Gal.orEquiv.) I

b. Skin Decontamination Soap (1 pt. or Equiv.) 1

c. Hand Brush 1 i

d. Floor Scrub Brush *

e. Bucket (10qt)

I 4

Check with appropriate inventory list located in inforisation binder for kit requirements.

4 OC0118 61XX l

4 1

O l

I l

69-9323-1 10/85 (25) B0x A PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OFNUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 l

TITLE: EMERGENCY KIT INVENTORY CHECK LIST KIT NO. KIT LOCATION QUARTER DATE PERFORMED BY BOX A QUANTITY DEFECTIVE REQUIRED PRESENT OR MISSING REPLACED

1. Sampling Equipment

a. Trowel 1

2. Air Sampling Equipment

a. 12V Air Sampler + Sample -

Head (w/ Battery. Radeco .

H-8098 or equiv.) *

RPf CAL DATE

b. 12V Aiv Sampler + Sample Head (w/o Battery Radeco H-809C or equiv.)

RPf CAL DATE I

c. 120V Air Sampler + ! ample Head (Radeco HD-288 or equiv.)

RPf CAL DATE

d. Air Cylinder Regulator 1

e. Compressed Air Cylindert (at 1700 psi) 2

f. Sample Head w/ Adapter ta fit Air Cylinder 1

g. Air Sample Particulate Filters (pkg of 10) . 10

Check with appropriate inventory list located in infomation binder for kit requirements.

DC0118 60XI

oiABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 S ON 8 DATE 9/23/85 PAGE 59 0F 59

yiTts. EMERGENCY EQUIPMENT INSTRUMENTS & SUPPLIES I

TABLE 17 ISOTOPIC MEASUREMENT EQUIPMENT ITEM SURVEILLANCE TYPE / FREQUENCY

a. Ganna Spectrometer located Surveillance by Emergency at Cal. Poly Physics building Planning / Quarterly room E128

b. Rolm ne (verify by calling , ,

Surveillance by Emergency Planning / Quarterly O

0C0118 59XXI!!

N 9

..,s.

'~

.

I

1 AND 2 NUMBER EP EF-5 DIA%O CANYON POWER Pt. ANT UMT NO(S)

REVISION 8 DATE 9/23/85 PAGE 58 0F '59 7:Ti,g. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 16 ASSEMBLY AREA EQUIPMENT ITEM SURVEILLANCE TYPE / FREQUENCY

a. Bu11 horns Battery change and operability checked by Emergency Planning / Quarterly 1

b. Assembly Area Packets UpdatedbyEmergjncy -

Planning / Monthly

~

c. fieldTeamRadios(2) Operability check and battery ,

exercise by C&RP/ Quarterly -

_)

I Use form 69-10866 DC0118 58XXI!!

4

\

-} _

1, NUMBER EP EF-5

} DiAsLO CANYON POWhR PLANT UNIT NO(S) I AND 2 REVISION 8 DATE 9/23/85 PAGE 57 0F.59 yir a EMERGENCYEQUIPMENT,INSTRUME$TS& SUPPLIES r

/ TABLE 15 MEDIA' CENTER EQUIPMENT a,

ITEM SURVEILLANCE TYPE / FREQUENCY Newsroom (Psychology Building)

> aa Black rotary, phones (31) Operability checked by Emergency Planning / Quarterly 1

~

I yb. Phone directories Replaced by Emergency e -

Planning / annually 3

Public Infor1 nation Center '

(Auditorfum - Men's dressing ruom) .-

a. Black rotary phones (5) Operability checked by g Emergency Planning / Quarterly

'b. g Yellow net phone (1)

, Rumor' Control Center (Auditorium g - Women's dressirg room)

a. Black rotary phones (10) Operability checked by y l , Emergency Planning / Quarterly I

Public Infor1 nation Representatives Office (Auditorium-Lobby) i -

a. Black rotary phoners(2) '

Operability checked by y 3

Emergency Planning / Quarterly

b. Yellow net phone (1)

T I Use form 69-10865 s

e DC0118 57XXIII , s I

i

1 AND 2 otAaLO CANYON POWER Pt. ANT UNIT NO(S)

$lSf0N DATE 9/23/85 PAGE 56 0F 59 Tins. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE 14 PG&E ENERGY INFORMATION CENTER DECONTAMINATION FACILITY EQUIPMENT ITEM SURVEILLANCE TYPE / FREQUENCY

a. Contaminated Solid Waste InventorybyEmerggncy Dicposal Supplies (for Planning / Quarterly contaminated clothing)

1) Plastic garbage cans and bags.

b. Personnel Decontamination Supplies InventorybyEmerggncy Planning / Quarterly .

1) Soap =

2) Brushes

c. Replacement Clothing Towels InventorybyEmergjncy Planning / Quarterly

' 1) Coveralls

2) Towels

d. Miscellaneous Equipment InventorybyEmerggncy Planning / Quarterly 1 Contamination caution signs 2 First Aid Kit 3 Blankets 4 Tape 1

0se Form 69-10864

'_ DC0118 56XXI!!

. i

1 AND.2 D'AsLO CANYON POWER PLANT UNIT NO(S) [fff0N DATE 9/23/85 PAGE 55 0F 59 riytg. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 13 (Continued)

EMERGENCY OPERATIONS FACILITY EMERGENCY PLAN EQUIPMENT ITEM SURVEILLANCE TYPE / FREQUENCY Volume 2 - Operating Procedures Volume 3 - Emergency Procedures (3 copies)

Volume 4 - Licenses & Pemits Volume 7 - Radiation Control Standards and Procedures

Volume 9 - Temporary Procedure (Curves & Misc Data) .

Volume 11 -(3Emergency) copies Plans

2) Piping Schematics g 3) Instrument Schematics

4) Electrical Drawings

5) Operating Valve Identification Diagrams

6) Drawing 102037 - Instrument Locations

7) Drawing 102038 - Instrument Reference

8) Corporate Emergency Response Plan

9) Nuclear Emergency Response Cosuunications Directory

10) Cypher Pad Code for San Luis Obispo Service Center Garage ,

DC0118 55XXI!!

otAaLO CANYON POWER PLANT UNIT N($1 - 1.AND 2

[fSf0N DATE 9/23/85 PAGE 54 0F 59 rirm. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 13 EMERGENCY OPERATIONS FACILITY EMERGENCY PLAN EQUIPMENT ITEM SURVEILLANCE TYPE /FRE0VENCY

a. Emergency Assessment See GOAP W-302 and Response System (EARS)

1) 984ST Computer

2) Chromatics Colorgraphics Display

b. Manual Dose Projection Equipment InventorybyEmeggency Planning / Monthly s

1) Base Map

2) Seven Overlays a

c. Communications Operability Checg by Emergency Planning / Monthly 1) 2)

Radio Telephone

d. Consumables

1) Emergency Forms InventorybyEmeggency Planning / Monthly

2) Office Supplies CheckbyEmergengy Planning / Monthly

e. Documents

1) Plant Manuals Normal Document Control Practice, Inventory by Emergen p Planning /

Monthly 1

Use Forn 69-10770 2

Use Forz 69-10771 3

Use Form 69-10582 t

DC0118 54XXIII

. - _ _ _ . _. . _ _ _ _ - _ - - _ _ _ _ _ _ - - _ _ , . _ - - . . - _ - . _ _ __- .,_ -_. - _- - __-_n

NUMBER EP EF-5 DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND, 2

. REVISION 8 DATE 9/23/85.

PAGE 53 0F 59 riy a EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 12 OPERATIONAL SUPPORT CENTER EMERGENCY PLAN EQUIPMENT ITEM SURVEILLANCE TYPE /rRE0VENCY Operational Support Center .

(Access Control / Cold Machine Shop)

Connunications

1) Telephone a) Direct line to TSC/CR OperabilityCheckgyEmergency Planning / Quarterly b) Rolm phone Operability Check gy Emergency Planning / Quarterly e E: One set of phones located in General Maintenance Foreman's office and one set located in Access Control.

2) Status Boards Operability Check by l Emergency Planning / Quarterly 7

3) Portable Radios In normal use, none required.

1 Use Form 69-10769 DC0118 53XXIII 5

1 AND 2

. , ciAaLO CANYON POWER PLANT UNIT NO(S) .

[lSf0N 8 DATE 9/23/85 PAGE S2 0F 59 TIT a EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 11 (Continued)

TECHNICAL SUPPORT CENTER EMERGENCY PLAN EQUIPMENT ITEM SURVEILLANCE TYPE / FREQUENCY

2) Piping Schematics

3) Instrument Schematics

4) Electrical Diagrams, Logic Otagrams and Electrical Arrangements

5) Operating Valve Diagrams .-

I

6) Drawing 102037 - Instrument Locations

7) Drawing 102038 - Instrument Reference -

8) Complete Set of Drawings

9) Complete Set of Documents

10) Cypher Pad Code for San Luis Obispo Service Center Garage

11) Corporate Emergency Response Plan

12) Nuclear Emergercy Response Communications Directory l

l l DC0118 52XXI!!

l i

1 AND 2 oiAsLO CANYON POWER PLANT UNIT NO(S) Sf0N8 DATE 9/23/85' PAGE 51 0F 59 riytg. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE 11 TECHNICAL SUPPORT CENTER EMERGENCY PLAN EQUIPMENT ITEM SURVEILLANCE TYPE / FREQUENCY

a. Control Room Closed Circuit Operability Checg by Emergency TV Monitors Planning / Monthly

b. Communications OperabilityChecgbyEmergency Planning / Monthly 1,1 Radio 2h Telephone

c. Emergency Assessment and See GOAP W-302 Response System

d. Manual Dose Projection Inventory / Monthly 2 Equipment

1) Dose Map

2) Seven Overlays

( e. Computerized Records Inventory Equipment by 2

Management System . Emergency Planning / Monthly

f. Documents Normal Document Control Practices. Inventory by 2 Emergency Planning / Monthly

1) Plant M:;nuals Vol 2 - Operating Procedures Vol 3 - Emergency Procedure Vol 4 - Licenses & Permits Vol 7 - Radiation Control Standards & Procedures Vol 9 - Temporary Procedures (Curves & Misc Data)

Vol 11- Emergency Plans 1

Use Form 69-10767 2

Use Forn 69-10768 e

e DC0118 51XXIII

- a e

NUMBER EP EF-5 DiAsLO CANYON POWER PLANT UNiy ($r ' I AND 2 REVISION 8 DATE 9/23/85 PAGE 50 of 59 yertg.

EMERGENCY EQUIPMEhT, INSTRUMENTS & SUPPLIES TABLE 10 CONTROL ROOM EMERGENCY PLAN EQUIPMENT ITEM SURVEILLANCE TYPE / FREQUENCY

a. Emergency Assessment and See GOAP W-302 Response System

1) 9845C Computer

b. Manual Dose Projection Equipment Inventory by Emergency Planning / Quarterly)

(Use fone 69-10766 Base Map .

, 1) -

2) Seven Overlays

c. Closed Circuit TV Cameras Refer to the Technical Support Center

d. Connunications See STP I-29 1 Radio 2 Telephone 3 Emergency Signal

e. Radiological Display See STP I-44

f. Radiation Monitoring Ofsplay See STP I-18 DC0118 50XXI!!

O I AND g NUM8ER EP EF-5

. DIABLO CANYON POWER PLANT WT W($) REVISION 8 DATE 9/23/85' PAGE 49 0F 59 TITLE. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE 9 (Continued)

EWS STREN LOCATIONS SIREN NO. LOCATION 568 Off Highway 101, .3 miles off Highway on dirt road in front of Bob's Big Boy billboard sign.

57 On Valley Road (Highway 1) about 7000 ft.

South of 53 and 1 mile south of Halcyon Road.

58 At end of Stanton Road South of Los

, Berros Road.

59 On Los Berros Rd between Stanton and -

Pomeroy.

60 On Pomeroy Road 1 mile south of Los Berros Road near Camino-Perrillo.

( 61 On Willow Road at Black Lake County Club.

l i

~

j DC0118 49XXI!!

I

d otAaLO CANYON POWER PLANT UNIT h5) 1 AND 2 fSf0N8 DATE 9/23/85 PAGE 48 0F .59 rifts, EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES i TA8LE 9 (Continued)

EWS STREN LOCATIONS SIREN NO. LOCATION 52D On Corbett Canyon Road at the intersection of Corbett Canyon Road and Royal Oak Place.

53 On Valley Road (Highway 1) about 7000 ft.

south of 51A and just north of Halcyon Road. /

54 On Corbett Canyon Road, .65 miles north of Tiffany Ranch Road.

54A On Highway 227, .9 miles north of Noyes .

Road.

548 On Verde Canyon Road, .45 miles off Corbett Canyon Road.

54C On Highway 227, .85 miles south of Noyes )

Road.

540 On Bee Canyon Road, right off cf Corbett Canyon Road.

54E At the intersection of Deer Canyon Road and Corbett Canyon Road.

55A On Corralitos Canyon Road,1 mile off Lopez Drive.

i 558 On Lopez Drive next to Blue Sky Drive.

55C On Corralitos Canyon Road, .55 miles off Lopez Drive.

55E .

. On School Road, .4 miles off of Huasna Road.

56 Near intersection of El Campo & Clark Way.

56A On Highway 101, .4 miles south of El Campo Road.

DC0118 48XXI!! '

rm-. - -, nn--.- -,e-,,.-.-.,--..,,,..- --m,. .n.-. ,,,,., . - -_- -._ , ,,.., ,_ - ,,- , ,,_v,-. ,e,n_ .~,,,n--

oiAst.O CANYON POWER PLANT UNIT NO(S) 1 ANQ 2 ON 8 DATE 9/23/85 PAGE 47 0F 59 tarts. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE 9 (Continued)

EWS SIREN LOCATIONS

$1REN NO. LOCATION 44 In Ptsmo Beach on a water tank in subdivision above Pismo Beach.

45 In Pismo Beach on Bello Road near Veteran's Hall.

46 On Highway 1 in So. Pismo Beach 1/2 mile north of Grand Ave.

47 In Grover City - 4th and Manhattan.

48 In Oceano on Railroad Avenue.

49 In Grover City at Water Tower on Hillcrest Drive

498 On Oak Park 81vd. In Arroyo Grandt

.3 miles from Noyes Road.

49C In Arroyo Grande near intersection of Oak Park Blvd. and Vista Del Robles.

50 Near Oceano on The Pike between LaVista and So. Elm.

51 In Arroyo Grande near new Fire Station.

51A At PGandE Oceano substation on Valley Road south of Arroyo Grande.

52 In Arroyo Grande Road on Huasna Rd east of Stagecoach Road 52A On Printz Road north of Arroyo Grande.

528 -

On Noyes Road north of Printz Road.

52C On Highway 227, between Shannon Lane -

and Phillips Road DC0118 47XXI!!

1,AND 2

-NUM8ER EP EF-5 DiAeLO CANYON POWER PLANT UMT %3) . REVISION 8 DATE 9/23/85 PAGE 46 0F 59 ritu. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE 9 (Continued)

EWS $!REN LOCATIONS SIREN NO. LOCATION 36 Off Highway 101 Frontage Road near intersection of Shell Beach Road and Landing Road.

36A Off highway 101 Frontage Road near intersection of Ontario Road and Avila Road.

37A At Shell Beach Fire Station.

38 On Mattie Road near McClintock's .

restaurant.

38A On Shell Beach Road near Price Street intersection.

39 In San Luis Obispo on Santa Fe Road j south of Tank Farm Road. .

40 On private property south of San Luis Airport.

40A On Orcutt Road, 1.75 miles south of the intersection of Orcutt and Johnson 41 On afddle Ranch Road just east of Edna Road.

41A On Orcutt Road, half a mile south of Briddle Ranch Road 418 On Righetti Road 1.1 miles off of Orcutt Road 42 On Price Canyon Road on Grace 011 property.

43 On Price Canyon Road about 1 mile north of Ptsmo Beach.

l DC0118 46XXI!!

1 ANQ 2 oiAaLO CANYON POWER PLANT UMT NO(5) [lSf0N DATE 9/23/85 PAGE 45 0F 59 Ting EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE 9 (Continueo)

EWS SIREN LOCATIONS SIREN N0., LOCATION 30 In San Luis Obispo on Prado Road.

31 In PG4E's Service Center yard on So.

Higuera.

31A On Jesperson Road, south of Buckley Road.

318 On Highway 101 Frontage Road 1 mile south of Higuera off ramp.

31C On Highway 101 Frontage Road, just off .

Higuera off-ramp, about 2000' north of 500KV right of way.

310 Near end of private dirt road west of Higuera off-ramp.

31E Near 12KV Ifne off Castro Canyon Road 1/2 mile off Highway 101 Frontage Road.

32 On Squire Canyon Road east of Highway 101 near intersection of San Luis Bay Drive and Monte Rd.

33 Across street from Bellvve - Santa Fe Elementary School on See Canyon Road off San Luis Bay Drive.

34 In Avila Beach near DCPP security gate.

l 34A Light house local coverage.

8348 4 miles off See Canyon Road near 500 KV

. right of way, by John Niemier's house.

35 In downtown Avila Beach near San Antonio Street.

l DC0118 45XXI!!

l t

L

l 1.AND 2 [l5 ON '

DATE 9/23/85 otAaLO CANYON POWEm PLANT UMT NO(st 44 0F $9

, PAGE EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES 7Ta TABLE 9(Continued)

EWS STREN LOCATIONS _

t,0 CATION SIREN NO.

Near intersection of See Canyon Road and 26 Davis Canyon Road about 3.6 miles off of San Luis Bay Drive.

On See Canyon Road about 4.6 miles off 26A of San Luis Bay Drive.

On See Canyon Road about 1.2 miles off 27 of San Luis Bay Drive.

On See Canyon Road about 2.4 miles off 27A of San Luis Bay Drive.

On See Canyon Road about 3 miles off 278 of San Luis Bay Drive.

On Davis Canyon Road about 1/2 mile off 27C of See Canyon Road.

On Davis Canyon Road about 1.6 miles off 8270 of See Canyon Road.

On Davis Canyon Road about 1 mile off of 27E See Canyon Road.

On Davis Canyon Road, 3.3 miles off See 27F Canyon Road On Los Osos Valley Road about 2000' south 29 of Madonna Road by Pacific Beach Continuation School Off Los Osos Valley Road in Laguna Lake 29A area by Descanso Drive.

On Calle Joaquin next to Madonna shopping 298 center parking tot in San Luis Obispo.

DC0118 44tXI!!

1 AhD 2 oimaLO CANYON POWER PUWT UNIT %$) Sf0N8 DATE 9/23/85-PAGE 43 0F 59 TITLE. EMERGENCY EQU!PMENT, !NSTRUMENTS & SUPPLIES TABLE 9 (Continued)

EWS SIREN LOCATIONS t

j $1REN NO. LOCATION 19C Los Osos - near the end of Valley View Place.

190 In Los Osos - on Niposo Avenue East of South Bay Soulevard between Willow Dr and Andre Ave.

19E In Los Osos near the Fire Station on Calle l Cardoney. , !

20 On Los Osos Valley Road near the 500 kV right of way west of Turri Road.

21 On Los Osos Valley Road east of Turri Road.

d g 22 On Los Osos Valley Road about 2 miles west of Foothill 81vd.

23 Near the intersection of 0'Connor Way and Foothill Blvd.

23A On O'Connor Way about 2 miles west of Footh111 81vd.

24 On Perfumo Canyon Road about 2 miles from Los Osos Valley Rd.

24A At end of private dirt road about 2000' south from point that Perfumo Canyon Rd pavement ends.

248 Near the end of Sycamore Canyon Road off

- Clark Valley Rd.

, 25 At the top of Perfumo Canyon Road.

25A On Andres property along Coon Creek Road about 1-3/4 miles west of upper end of See

. Canyon Road.

DC0118 43XX!!!

. - - - , . - + , - , , - - , . , _ , . , . - - . . _ _ _ , _ . , . . . , , , - - - - , , , , . - , - . . _ _ _ , . _ . , - . , , , - - -_~,-_,---_n-_ ,. , - -, -- ,_. ,, ,-- - --- - - ,------._

. NUMBER EP Er-5 DiAaLO CANYON POWER PLANT UNIT NOt5r 1.AND 2

. REVISION 8 OATE 9/23/85 PAGE 42 0F 59 TITLE. EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES TA8tE 9 (Continued)

EWS 5!REN l.0 CAT!0NS 5!REN NO. LOCATION .

14 On Highway 1 about 1/2 mile west of the California Division of Forestry.

14A On Stenner Creek Road.1.7 miles off of Highway 1.

15 In San Luis Obispo across the street from City Fire Station on No. Chorre Street.

15A On Foothill 81vd. just outside San Luis

Obispo. 3/10 mi southwest of Rosita St.

16 In San Luis Obispo near Grand Avenue and Slack Street.

16A On Poly Canyon Road. 9 miles from the ,

North Perimeter Road on the Cal Poly Campus.

168 In San Luis Obispo. on Highway 101. 3 miles west of Reservoir Canyon Road.

16C on Highway 101 at the bottom of Cuesta Grade.

17 In San Luis Obispo parking lot next to the Fim Station on Garden Street.

18 In San Luis Obispo on Augusta St. near 5fnsheimer School.

18A On Orcutt Road.1 mile south of the intersection of Johnson and Orcutt.

19A On Clark Valley Rd. off Los Osos Valley Rd. near PGandE 500kV right-of-way.

DC0118 42XXI!!

osasLO CMYON #0MR Pt.MT UMT NO(S) I ANO 2

, 5 ON 8 DATE 9/23/85.

PAGE 41 0F 59 rga EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 9 (Continued) ,

EWS STREN t.0 CAT!0NS 5!REN NO. LOCATION 5F On Little Morro Creek Road. 2.1 miles from Radcliff Street 5G On Little Morro Creek Road. 3.7 miles from Radcliff Street 6 In Saywood Park near the intersection of Santa Ysabel and 2nd,St.

6A In Saywood Park near the intersection -

of El Morro Avenue and 8th Street.

7 In Los Osos on Pecho Valley Road several blocks west of Pine Avenue.

8A Montana de Oro Park near the Ranger

\

Station.

88 Montana de Oro Park near the Ranger's residence.

8C On the Field's property south of the

gate.

80 On the Field's property near the Field's residence.

9 Near Highway 1 on PG8E's laywood substat< on yard.

9A On San Bernardo Creek Road.1.8 miles from Highway 1 10 Near Highway 1 west of San Luisito Creek Road.

12 On Highway 1 just north of Cuesta College.

13 On Highway 1 northwest of Animal Shelter.

OC0118 41XXI!!

i o.--. _ -- - . - .- - - - --- - _ . - - _ . -. . .

.-.,y_, _ . _ . _,__-..-mm,,,a ._,,,_,,9 _,,.,y,-,-,, - - ,,-_ ______.,r_ , _ , , , _.- _--,_,y,,n,- y,.,__ . _ _ ______#>

1 AND 2

. Diaato CANYON POWER M. ANT UNet NCHS) ' [lSf0N DATE 9/23/85 PAGE 40 0F 59 rir a EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 9 EWS $!REN LOCATIONS SIREN NO. LOCATION 1 North Morro Bay - near the intersection of Sequoia and Alder.

1A Near intersection of 50. Ocean and Chaney Ave. off Highway 1.

18 Near the Cayucos Cemetary on Highway 1.

1C Cayucos near the intersection of 4th &

Park =

2 On PG4E property at the Morro Bay Power Plant, near Highway 1 2A On PG4E property at the Morro Bay Power ,

Plant, near the Edercadero ,

)

3 In Morro Bay, on Morro Avenue north of Olive.

3A In Morro Bay, near the intersection of Ridgeway Street and Fairview Avenue.

5 Near the Cayucos Substation, off Cypress Mountain Road 5A On Montecito Road, 1.1 miles off Cypress Mountain Road 58 On Torro Creek Road 2.8 miles from Highway 1 SC On Torro Creek Road, 1.4 miles from H!ghway 1 50 On Highway 41, 1.95 miles from Highway 1

~

5E On H1ghway 41,. 9 miles from Highway 1

~

DC0118 40XXI!! .

., i

s

. CIABLO CANYON POWER Pt. ANT UNif NO(S) I AN.D 2 P EF-5 DATE 9/23/85

'* y,ygg, EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES TABLE 8.a (Continued)

ENERGENCY ORGANIZATION RADIO PAGERS Pager Group Page Dnergency Position Encode Number Encode Number .

Mobil Environmental Monitoring Lab Operator Interim Public Infonnation Recovery Manager Ron Weinberg Missie Hobson _

e e

9 E

DCol!8 39XXIII' ,

w

o ,

e w a Nn A __ A . _ . _ _ _ _ &

1 I .

NUMBER EP EF-5 DIAaLO CANYON POWER Pt. ANT UNIT NO(S) . . 1.AND 2 REVISION 8 CATE 9/23/85 PAGE 38 0F 59 Tirts, ENERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 8.a EMERGENCY ORGANIZATION RADIO PAGERS Pager Group Page Emergency Position Encode Number Encode Number Site Emergency Coordinator R I

Emergency Operations Coordinator (PlantSuperintendent)

Emergency Evaluation and Recovery Coordinator Emergency Radiological Advisor #

Emergency Liaison Coordinator Advisor to the County Emergency Organization Emergency Maintenance Coordinator Site Chemistry and Radiation Protection

")

Coordinator ,'

Emergency Liaison Assistant #1 Emergency Liaison Assistant #2 Data Processor No. 1 Data Processor No. 2 ,

Instrument Maintenance Coordinator Electrical Maintenance Coordinator Mechanical Maintenance Coordinator ,

Fire Marshal EARE Operator - TSC t

DC0118 38XXI!!

f

?

.)

' e .___._a .m E _ . en. _ J h_

3 e NUMBER EP EF-5

oiAeLO CANVON POWER PLANT ON:T NCHS) *1 AND 2 REVISION 8 DATE 9/23/85 PAGE 37 0F '59 7,y a EMERGENCY EQU!PMENT, !NSTRUMENTS & SUPPLIES TABLE 8 (Continued)

DIABLO CANYON POWER PLANT PLANT VEHICLE t,!$T G=7926 22=474 1991 F0A0 t/2 TON P/U MCH MetNT STRAML, J. 2G74627 G-7864 22-476 8984 FORO Pu/RA*eMR OARAGE SUMA647, R. 2>47052 G=7926 22=476 19e4 FORO PU/ MANGER SECURITV RYAN, BILL 2p W6ve G-7940 22*476 1994 FORD PU/ RANGER MCURITY RYAN, DlLL 2D Wee 4 5 7956 22*474 8984 FOAO PU/hANGEN SECURITY RVAN, glLL 26 W787 9-7964 22*474 19f34 FORD PU/ RANGER SECURITV RVAN, SILL D'eQ789 e

D=7971 22-476 1994 FORD PU/ R A*eM R SECURITV RVAN, BILL 2960789 G*7977 22-476 8994 FORO l Pu/ RANGER MCURITY RVAN, SILL 29 W elu*. i G*0150 22-476 195l PLVM0uTH RELIANT OFFICE SERVICES POC4. IJPA499 S-9134 22*476 1994 PLVMoufH RELIA *ef PLANT MA8 EAGER THOR *stERRY lJPA703 9-9464 22=474 1994 PLNMOUTH RELlasef 981.0PERTNS.SuPR FRIOLEY, S. IJPA702 S-4247 le=257 1994 PtVMouTH HORi!0N COMMUNICAfl0NS JOHNSON, D. IJEE206 9-9329 27=476 19e4 FURO Pu/RAes0ER CHEM & RAO SNVDER, DOS 2HS7943 G-6338 22=476 1994 FLAD PU/ RANGER MCURITV HAVES, JOHN 2HS7994 6-4332 22*476 1994 FCRO Pu/ RANGER OPERAfl0NS MCLARNEY, C 2HS7999 S-9333 22=476 1994 FORh PU/ RANGER ELEC MetNT 20CHER, S. 2HS79'e l D=4334 22-476 8994 FORD PU/RAmesER CMM& RAD SNv0ER, DOS 2HS7994 l G=4334 22-476 19e4 FORD PU/RAesGER CMM 6 RAO SNYM R, DOS 2HS7994 9-9337 ll=476 19e4 PORD PU/RApetER MECM MelMT 'STRAHL, J. 2HS79'S D=9452 22-583 19eS FORD VAN SC/RNS DACFFIT OmuM. 00N884 2MS733 9-9560 22=476 1998 FORD PU/F=290 MATERIALS TEWALT, D. 2MStoS3 9-9676 22 474 19e5 FORD Dm0NCO MCURITY HAVES, JOHN 2P37909 9-4250 22-476 8979 CMVROLET PU/4:4 OPERAfl0NS MCLAmosEY, C IN2020S S-88 83 22-476 199S CHEVROLET SIER#4 P/U 1/2 TON MCURITV HAVES, JOHN 2S24322 D 9280 2.1-4/6 199S CHEVROLET 3/4 TON P/U MECM MAINT STRAMt., J. 2P68739 G-9288 22-476 1995 CHEVROLET 3/4 TON P/U tulLOING SVCS. JOHNSON, D. "Pel738 S-9282 22=476 1998 CteVROLET 3/4 TON P/U GPERAYl0NS MCLA8WeEY, C P44139 9 92l1 22a474 1995 CHEVROLET 3/4 TON P/u CHEM & RAO SeeVDER, 000 2P64840 S=9340 22-476 1999 FORD VAN OFFICE SERVICES POOL ILDE!22 Sattet 22=474 1995 GMC t/2 TON P/U IbC DEPARTMENT PETERSON, 9 2R93139 D=D69e 22476 8995 PLYMOUTH RELIAsef teme0N OPPICE MRVICES POOL IMSJ168 9-4319 22 476 1983 SMC SAFARI MINIVAN OPPICE MRVICES POOL 2P39808 t

i DC0!!8 37XXI!!

9 8 0 t

DiAaLO CANYON POWER PLANT UNif Not$). ' 1 AND 2 Q0N DATE 9/23/85 PAGE 36 0F 59 !

fiful. EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES TA8LE8(Continued)

O!ABLO CANYON Polder PLANT PLANT VEHICLE LIST l'J RC YEAR MANur MOML LOCAf!ON Atele8 SED Ltc ,

4-032S22-474 1975 CAT PORsILIPT.ELEC CHEM & RA0 SNVDER, DOS NA 4-0016 22-474 1948 00008 FIRE PUMPER TRUCN SAFETY M RVICES JOHNSON, C.

4-1873 22-474 4990 NORDSWOG ELECTRIC CAmf NPO teAREMouSE-4 SMlfH, Duo 4-4800 22-474 49e8 peOM098(08 ELECTRIC CAmf OPPICE SERVICES POOL 4-8101 22 474 1999 NOROSkoe ELECTRIC CART OPPICE SERVICES POOL 4 8254 22-474 1992 NOR0ehAG ELECTRIC.CAmf OPPICE SERVICES POOL pee 4-1257 22-474 8992 Pe0R0ekAS ELECTRIC CART NPO teAREMoueE-A SMlfH, DUD NA 4-1480 22*474 6942 teMITE FORAL IP f. Pm0Paset MATERIALS TEWALf, D. NA 4-1982 22-474 1975 POR*LIPf/AC0lESEl. MECH MalNT STRAML, J. NA 4-4929 22-474 6998 YALE PommLIPT OPERAf tcess MCLAANEY, C N/A' 4-4929 22 474 1999 VALE FORmLIPT OPERATIONS MCLAAteEV, C N/A 4-4932 22*474 1999 VALE PO M IPT MATERIALS TEbeALT, D. N/A

4-4940 22-474 8995 OAACALL. LOED S42 MECH MalNf STRAML, J.

4 9077 22-474 1945 PORO TELELECT CRANE ELEC MelNT 20CHER, G. NA 4-9444 22-474 1974 PH CRant MECH MAINf STRAML, J. pea 7-0353 22-474 1973 P0puLIPf/ PALLET CHEM 6 R40 SNVDER, DOS NA 7*1093 22-474 HVOROLAIER CHEM h RA0 SNVMR, Das NA 7-8704 1972 HOMEMADE FIRED 0s SAFETY MRVICES J0Mee90N, C.

5 0043 22-474 4904 PORD Pu/AA*eeER SECURITY HAVES, JOHN 2k40407 g e-00S4 22-474 1999 CHEVROLET VAN /e Poem NSER McLMITV RYAN, SILL 2Ml4309 ,

5-0044 22*474 1999 PORO VAN /l2 PAG MpetER MCURITV RYAN, etLL lLOAeft ' '

G-0388 22-474 6983 PORO ESCORT 500 kV VAA0 COOPER, 904 LPfv538 '

G-0349 22-474 1903 PORD LSCORT OPPICE M RVICES POOL iPfv993 0-e 1 22-474 1993 PORO ESCORT OPPICE M RVICES POOL IPf!*02 G*vevs22-474 1903 PORO ESCORT MATERIALS /MOR McLApet, W. IPft e3 9-0402 22 474 1993 PORO ESCORT APM/ PLT SUPT PAffEPSON,R SPf!204 G-0400 22-474 1983 PORO ESCORT POOL ST. JOHN iPft299 ,

0-0477 22-474 1999 CHEVROLET Cif4fl0N MetNTENA8eCE Men MlWLUSH, D. IMM8el4 S-v477 22*474 1995 CHEV ClfAfl0N MAINT Men DMIFLUSH IMMuel4 0-0494 22-474 6905 CHEVROLET ClfAfl0N thC MECH MAINT CROCPEff, W LMMsel3 5-07S4 10-259 1979 CHEVROLET Pu/LUV COMMUNICAfl0Ne JOHNSON, D. If4Sito 9-0898 22-474 8995 CHEVROLET ClfAfl0M CHEM b R40 00079. J.V. IMMt004 5-0947 22-474 1998 CHEVROLET ClfATION OPERAtloses M470N, J.A iMMie$e 4-1079 le=278 1977 CHEVROLET P/u S00av YARD COOPER, eQs 1094!a0 0-2833 22-509 1995 PLVMoufM Homt!DN OCPR PutLicifV teEINMme, R l>VP*44 D*2900 le-let 4904 CHEVROLET SPORTVAN COMMUNICAfl0Ne JOHNeom. D.

9-3758 22-909 1994 0000E OMN! Soo kV VARD COOPER, 00s kNDe!4 6-9037 22-474 1994 PLYMoufM HELI Asef / tea 00M Ate? PLf SUPT 70temeMNO, J IJAt931 S-9424 22-474 1999 PLVMoufM REl.l Asef / tea 00N SUPPORf SVCS DAEPER, tem. ILOAe77 6-9443 22-474 1999 PLVM0ufM RELI Apef / tea 40N TECHNICAL eVCS DISCLON,J.M ILOAetS S-9478 22-474 199e PLVMoufM RELIANT /te400N OPPICE MRVICES POOL lLO48th 5*S497 22*S83 1998 PLVMoufM N0484 MATERIALS LEVlf f, 8(, A IDN8s439 G-5984 22-474 1995 CHEVROLET Pu/S 80 OPER4flopes MCLAmte4Y, C .N34052 0-6845 22-474 1994 PORO TEMPO MCURify 700AAO, MON LHON330 S-4107 22-474 1979 PORO LTO OPPICE SERVICES P00L 470whP S-4294 22 474 1964 PORO e#0NCO/4e4 MCumifv HAVES, JOHN 80H 984 6-45Se 22 474 1944 CHEVm0LET Pu/de2 MECH MAINT STRAML, J. 2P74074 6 4940 22 474 4904 CHEVROLET Pu/4e2 Mir" MAINT STRAHL, J. 2H09478 5-7020 22*474 6904 PORO ESCORf TECHNICAL SVCS WOMACM, L.P LMON227 9-7028 22 474 6 9e4 PORD F9CORf TRelNl884 MA*flN, flM IW'4 OC0118 36XXI!!

1 AND 2 otAaLO CANYON POWER M. ANT UNIT N0(S) [lSf0N DATE 9/23/85 PAGE 35 0F 59 rir a EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES TA8LE 8 DIA8LO CANYON POWER PLANT PLANT VEHICLE LIST Primary position holders of certain emergency response positions are provided with VHF radio-equipped company vehicles. Because these persons are essentially on call at all times, use of these vehicles is warranted in off hours to ensure rapid communication and response. These personnel are identified in EP G-2. " Establishment of the On Site Emergency Organization."

O i

1 OC0118 35XXI!!

NLM8ER EP EF-5 OLASLO CANYON POWER PLANT UNif Not$)

1.AND 2 REVISION 8 OATE 9/23/85 PAGE 34 0F 59 rirts. EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES TABLE 7(Continued)

CONTENTS OF POST-ACCIDENT SAMPLE K!T PART 2. THE SENTRY CA81 NETS AN0 LOCKER (Continued)

ITEM QUANT!TY

8. Procedure: Part I

a. Printer paper at CCD 1

9. Procedure Part J

a. GE Post-Accident Sampling Shipping Pa'kage c 1

10. Tools / Misc.

a. Screwdriver - flathead, long shaf t 1

b. Screwdriver - phfitps 1

c. Allenwrenches(smallset) 1

d. Wrench (5/16") 1 e.

f.

Stopwatch / clock Flashlight with batterfes 1

1

')

g. Single sided razor blades I

h. Scissors 1

f. Plastic ruler with stilimeter graduations 1

j. Scotch tape 1

k. SCBA air bottles 6

1. Marks all pens 4

m. Razor Point / ball point pens 4

n. Safety glasses 2 i

)

l DC0118 34XXI!!

, - , , - , , , . _ __ -__,. __ _ . . _ _ _ _ _ r_-.__ ___ - _ . _ . _ ,

1 AND 2 NUMBER EP EF-5

. DIASLO CANYON POWER PLANT UMT NO(Si REVISION 8 DATE 9/23/85 PAGE 33 0F 59 rira EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE 7 (Continued)

CONTENTS OF POST-ACCIDENT SAMPLE KIT PART 2. THE SENTRY CA8! NETS AND LOCKER (Continued)

! TEM QUANTITY

d. 50 m1 erlenmeyer flasks w/ stoppers 5

e. I cm spectrophotometer cells w/ caps 5

f. Pipets w/ tips 1 5 al 1 2)J 1 m1/1000ul 1 100ul *

3) 1

4) 10ul 1

5) 0 5m1 w/tip 1 6 2 mi volumetric pipet 1 7)p 5 al volumetric pipet 1

g. Pipet bulb 1

h. 100ml volumetric flask 1

1. Tongs: 14-16" in length 1

j. Spectrophotometer 1

k. Boric Acid Standards 1

1. Dominere11 red water in 5 gallon carboy 1 at least half full

m. Concentrated hydrochloric acid, HCL 100ml

n. Concentrated sulfuric acid. H,504 10h1

c. Carminic acid solution. prepared weekly 100n1

p. Calibration graph of absorbance vs ppe boron 1

q. Large plastic bags 5

r. Causticcleaningsolution(1/2 gallon) 1

s. Acidcleaningsolution(1/2 gallon) 1

t. Acetone or a' cohol (1/21) 1

7. Procedures: Part G - lon Chromatograph

a. LAN recorder paper (roll) 1

b. Calibration graph, chloride vs peak height 1 DC0118 33XXI!!

L

oiAaLO CANYON POM7 PuMT UNIT NO(S) ! AND 2 fSf0N OATE 9/23/85 PAGE 32 0F 59 Tir u EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 7 (Continued)

CONTENTS OF POST-ACCIDENT SAMPLE K!T PART 2. THE SENTRY CA8! NETS AND LOCKER (Continued)

! TEM QUANTITY

d. Surgeons gloves 5 parts

e. Prelabeled 60ml sample bottles 5 with new septums

f. Prelabeled 15m1 sample bottles 5 with new septums

g. Prelabeled 14cc gas vtals with 10 new septums

h. Needle flush tool 1 .

1. Sample ziploc bags 5

j. Sealing tape 1 rol)

k. Labels 1 sheet

1. Gas bottle grip tong 1

m. Squeeze bottle with domin water 1

n. 100 m1 beakers 2

o. Paper tomls or equivalent fbox) 2

p. Kimwfpes or equivalent (box) 2

4. ProcedJrest Part C - Containment Air Sampling

a. Keys for FCV-698, 699, 100 1 set

b. Gas tight 5cc locking syringe 2

c. Needles for gas tight syringe 5

5. Procedures: Part 0 - Gas Chromatograph

a. G.C. chart paper (rolls) 3 .

b. L&M Speedomax chart paper (rolls) 3

c. Calibration graph - CA 1

d. Calibration graph-offgass 1

6. Procedures Part E - Sample Handling

' a. Fully operable hot cell 1

b. Shielded sample holder brick 1

c. 20cc liquid scintillation vial w/ cap 5 k

OC0118 32XXI!!

l L

1 AND 2

- NUMBER EP EF-5

. 01A84.0 CANYON Power uf UMT es REVISION 8 DATE 9/23/85.

l PAGE 31 0F $9 riri,g EMERGENCY CQUIPMENT. INSTRUMENTS & SUPPLIES TABLE 7(Continued)

CONTENTS OF PO$f-ACCIDENT SAMPLE K!T PART 2. THE SENTRY CA8! NETS ANO LOCKER JT[M, QUANTITY

1. In Motor Repair Shop

a. Argon gas >1000 psig

b. 2000 ppm Hydrogen Span Gas >100 psig

c. 101 Hydrogen Span Gas

2. Procedures Part A - Initial Startup General Semple Handling *

a. 5 ton come a long with extension strap 1

b. Cresent wrenches (8" or longer) 2

c. Zip lock bags - small size 5

d. CA5P cart / cask . 1

e. P!-1109 (MIS 4 channel pressure monitor) 2

f. Septums, procut for CASP 5F-5 5

g. Buffer - pH 7. 4 or 10 Cal Tank > half full

h. Small jewelers screwdriver 1

1. Chloride Calibration Standard Cal Tank > half full

j. Dionex - !.C. Elvent Bag > half full 1 J1 H 50 2 Sag > half full DominwaIer Bag > half full

k. Filtrant packed U tubes 5 (sealedinplasticbagswithdessicant)

1. Septum adapter 1

m. Cap for septum port 1

3. Procedures Part 8 - Liquid /0ffgas Saapling

a. Meter long reach rod 1

b. L5P cart / cask 1

- 60 m1 bottle lift rod assembly 1

- 15 al bottle lift rod assembly 1

- auxiliary shleid 1

c. Hand operated vacuum pump 1 DC0118 31XXI!!

- - - - _ . . - - - , - - _ , - - - - . - . - - - - - - - - - - - . , . . - - - , - - - - . - . . - _ - - . , . - ,- - - , - . , - - - -.,.,..,-e e

l

. \

1 AND 2 otAaLO CANYON POWER PLANT UMT NO(Si

[lSf0N 8

, DATE 9/23/85 PAGE 30 0F 59 riTLs. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE7(Continued)

CONTENTS OF POST-ACCIDENT SAMPLE KIT PART1.THE85' LOCKER (Continued)

! TEM QUANT!TY

3. Protective Clothing

a. Coveralis 6

b. Hood 6

c. Surgeon's cap 6

d. Plastic booties

24

e. Rubber shoe covers .

, 1 Giant 2 pair

2) Extra large 2 pair 3,)1 Large 4 pair Medium 2 pair 4)J 5 Small 2 pair

f. Cotton liners 12 pair

g. Rubber gloves 12 pair }

h. Masking tape 3 rolls

1. Small plastic bags (for matches, l

dostmeters, etc.) 12

j. SCSA with full bottle 3

4. Miscellaneous

a. Large plastic bag 10

b. Flashitght with batteries 3

c. Extra batteries 6 e

G DC0118 30XXI!!

l 9

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

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3

~* E 1 AND 2 *

, DIASt.O CANYON POWER Pt. ANT UNIT NO(S) [f3ON t

\

('

DATE 9/23/85

- PAGE 29 0F 59 I EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES

'l TITu.

L TABLE 7 CONTENTS OF POST-ACCIDENT SAMPLE KIT t

., PART 1. THE 85' LOCKER ,

ITEM QUANTITY

1. Instruction Binder Labelled " Sentry"

a. Sanford marking pens 2

b. Red marking pens 2

c. Black marking pens 2

d. EP RB-15 Sentry Post Accident Saspling System -

Initial Sampling Exercise (Part A) I

e. EP RB-15:F data sheets 5 *

2. Monitoring Equipment

, a. Teletector (Eberifne 6112) 2

b. Dose rate meter (HPI-1010 or R0-2 or R0-2A) 2

' c. Pocketdosimeters(0-5R) 6

d. Pocket dosimeters (0-200mR) 6

e. Dosimeter charger 1

f. Lapel air samplers

1) Air pumps 6

2) Filter holders 6

3) Filters 1 box

,. 4) Connecting tubing 6 l

t l

E ,' s t

1 4

. _ . . _ _ _ _ _ _ , , _ . , . . - . . _ _ , , , , . - - ,. .,__._.,._-__m. . , _ . _ -

l DIA8LO CANYON POWER PLANT UNIT iC(S), - 1.AND 2 fE

, S ON 8 DATE 9/23/85 ,

PAGE 28 0F 59 l tittg. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES l TABLE 6 PORTABLE DOSE RATE INSTRUMENTS Instrument Detector Radiation Primary (Model No.) Type Measured Range Use HPI-1010 ion chamber Garuna Dose rate: Low dose Ganna 0-1000 mr/hr rate !

Ion Chamber Intergrate measurements 0-0.01, 0-0.1 0-1 mrad l Portable REM BF Neutron. 0-5, 0-50 Neutron 3 l Counter thennel to 0-500, 0-5000 dose rate (PNR-4) 10 MeV mrem /hr %

Teletector Twin G-M Beta 0-2 mR/hr Beta, Ganna tubes Ganna 0-50 mR/hr dose rate 30 mg/cm2 0-2 R/hr beta window 0-50 R/hr 0-1000 R/hr i R0-2 ton chamber Beta 0-5, 0-50 Dose rate .

3.5 mg/cm2 Ganna 0-500 mR/hr beta window 0-5 R/hr air fill gas R0-2A fon chamber Beta 0-50, Dose rate 3.5 mg/cm2 Ganna 0-500 mR/hr air fill gas 0-5, 0-50 R/hr DC0118 28XXIII h

\

. otAaLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 R S ON DATE 9/23/85 PAGE 27 0F '59 ina EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 5 PORTABLE COUNT RATE METERS Instnanent Detector Radiation Typical Primary (Model No.) Type Measured Range Use Beta-Gasuna Survey 0-700, 0-7000 General Meter (E-14G), with 0-70,000 CPM contamination the following surveys detectors; a) Hand probe (HP-260) GM Beta Gamma b)Handprobe,and window.

(HP-2304) GM Beta,Gasuna c)Handprobe (HP-240) GM Beta.Gasuna d) Shielded hand probe (HP-210) GM Beta, Gamma Count rate meter 0-500,0-5K, Personnel (RM-15) for use with 0-50K, 0-500K contamination GM probes listed CPM surveys above, and:

a)alphascintil- ZnS(Ag2)' AIPh

1ation probe 59 cm (AC-38-7) sensitive area

) h) gasuna scintil- NaI(TI), Gasuna lation 2" x 2" (SPA-3) probe Count rate meter 0-500, 0-5K. General (PRM-6) for use with 0-50K, 0-500K contamination GM probes listed CPM surveys above AC-38-7 and See See SPA-3 probes above above DC0118 27XXIII b -

4

\

otAst.O CANYON POWER PLANT UNIT NO(S).

I ANO 2 S ON 8 DATE 9/23/85 PAGE 26 0F 59 TTm EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TA8LE 4 (Continued)

CONTENTS OF HOSPITAL KITS ITEMS QUANTITY Contamination Survey Sheet (69-9315) 6 each Radiation Survey Sheet (69-9316) 6 each Forceps -

1 each Smear pads 8" x 8" cotton (pkg of 10) 2 pkg Medical referral form 62-6015 3 each Light duty letter 3.each Plastic bags 18"x24" 12 each DC0118 26XXIII

DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 5 ON DATE 9/23/85 PAGE 25 0F -59 TITLE. EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES TA8LE 4 l CONTENTS OF HOSPITAL KITS Each of two hospital kits shall contain the following minimum items:

ITEMS QUANTITY Full face respirators w/ Type H or equivalent filters 2 each Disposable coveralls 4 each Hood 4 each Disposable shoe covers 4 pair Surgical latex gloves 1 box Rubbers , - 4 pair Masking tape. 2" width -

2 rolls ==

Duct tape, 2" width 2 rolls

" Radioactive Material Area" sign 5 each

" Surface Contamination Area" sign 5 each "High Radiation Area" sign 2 each

" Radiation Area" sign 5 each Barricade tape,100 yd. roll 2 each Ty raps Minimum 30

" Radioactive Material" labels 4"x6" 10 each

" Radioactive Material" labels 1"x3" I roll E140N/HP-210T or equivalent 1 each HP-260 or equivalent 1 each Spare detector 1 each 1 Allen wrench 1/16" I each 1 HPI-1010 or equivalent 1 each 0-200 mR pencil dosimeters 2 each 0-5R pencil dosimeters 2 each dosimeter charger 1 each 2" smears w/ packets 250 each 2" air sample filters w/ envelopes 50 each Plastic envelopes 3"x5" 30 each Gwuned labels -

40 each Plastic bags 38"x65" 6 each Grease pencil 2 each Ballpoint / felt tips pens 3 each Waterproof pen 2 each l

Personnet-Decon Record Sheet (69-9392) 6 each Bendix BOX-60 Air Sampler 1 each 38mm air filters / holders for 8DX-60 1 box DC0118 25XXIII -

e

% 9

, ,r - . ,- - -

,---.-,-,_____--._.-,,y-,-,-._4-- - - - - - , . - - - - - - - - ww

, OLA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2

, 5 ON 8 DATE 9/23/85 PAGE 24 0F 59 m ts: EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 3 LOCATIONS OF FIRST AfD SUPPLIES LOCATION EQUIPMENT

1. Administration Building First Aid Station

2. Security Building First Aid Station

3. Training Building First Afd Station

4. Intake Structure First Aid Kit Basket Stretcher

5. Cold Machine Shop First Aid Kit ,

6. Access Control (First Aid Room) First Aid Locker, Stretcher, Gurney, Scoop Stretcher, Backboard, Oxygen, Splints

7. Turbine Building .

104' Elevator Landing First Aid Station )

119' Elevator Landing First Aid Station 140' Elevator Landing First Aid Station

8. Control Room First Aid Kit, Burn Kit

9. Auxiliary Building 85' Elevation First Aid Station.

Stretcher, Gurney 64' Elevator Landing First Aid Station 100' Elevator Landing First Aid Station 115' Elevator Landing First Aid Station

10. Hot Machine Shop First Aid Station

11. Containment Personnel Hatch First Aid Kit, Basket Stretcher DC0118 24XXIII

1 AND 2 NUMBER EP EF-5

'

OIABLO CANYON POWER PLANT UNIT NO(S) REVISION 8 DATE 9/23/85.

PAGE 23 0F 59 7,7g EMERGENCY EQUIPMENT INSTRUMENTS & SUPPLIES TABLE 2 (Continued)

CONTENTS OF EVACUATION KITS QUANTITY ITEM PER KIT

d. Form 69-9369, " Evacuation Kit Inventory Checklist" 5-10

e. Emergency Procedure G-4, " Personnel Accountability and Assembly" 1

15. Information Center Decontamination Shower Key (A53) 1

~

6 l

t N-OC0118 23XXIII l

l

)

1 l 1 AND 2 NUMBER EP EF-5

. DIASLO CANYON POWER PLANT UNIT NO(S) . REVISION 8 DATE 9/23/85 PAGE 22 0F 59 TITLE; EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 2 CONTENTS OF EVACUATION KITS QUANTITY ITEM PER KIT ,

1. Eberline E-140/N Survey Meter with HP-240/HP-210 Standard G-M Probe or equivalent 1

2. Dose Rate Meter 1

3. Self-Reading Dosimeter Pencils, 0-200 mR Range 4

4. Dosimeter Charger w/ extra battery 1

5. Barricade Tape,100-Foot Rolls 2 -

6. Packages of 2-Inch Filters (10 filters / package) 50

7. Bullhorn w/ extra battery . I

8. Plastic Bags (14' X 24") 3 ,

9. Ballpoint Pens 4

10. Flashlight w/two extra batteries 1

11. Pocket Calculator w/ extra battery 1

12. Corporation Key (3A90909) 1

13. Information Center Emergency Room Key 1

14. Instruction Binder:

a. Emergency Procedure G-5, " Evacuation of Nonessential Site Personnel" I

b. Fory 69-9310. " Post-Evacuation Vehicle Monitoring Data" 50

c. Fom 69-9311. " Evacuee Monitoring Data" 100 DC0118 22XXIII

1 AND ', NUMBER EP EF-5 o ,

oiAaLO CANYON POWER PLANT UNIT NO(S) , REVISION 8 DATE 9/23/85 PAGE 21 0F .59 EMERGENCY EQUIPMENT, INSTRUMENTS & SUPrLIES ru TABLE 1 (Continued)

CONTENTS OF RADIOLOGICAL EMERGENCY KITS OUANTITY

, KIT f ITEM 1 2 3 4, 5

5. Signs / Barriers 4

a. Radiation Signs (w/3 inserts) 2 4 2 4 4

b. Radiation Barricade Tape (100' rolls) . 2 2 2 2 2

6. Sagling Equipment ,

a. Sample Bottles (1 liter) 2 6 2 4 4

b. Plastic Bags Approx. 15 15 15 15 15 (18"x24")

c. Trowel 1 1 1 1 1

. 7. Miscellaneous Equipment

a. First Aid Kit (size 10) 1 1 1 1 1

b. Screwdriver 1 1 1 1 1

c. Crescent Wrench (8") 1 1 1 1 1

d. Scissors 1 1 1 1 1 l e. Stopwatch 1 1 1 1 1

, f. Roll of Dimes 1 1 1 1 1

g. Masking Tape (2" wide rolls) 2 2 2 2 2

h. Flashifghts w/8atteries 1 2 1 2 2

1. Extra Batteries 2 4 2 4 4

j. Battery-Powered Lantern w/6 V 84ttery 1 1 1 1 1

k. " Kwik-kold" Packs 4 4 4 4 4

1. Grass Shears 1 1 1 1 1

m. KI Tablets.(bottle) 1 1 1 1 1

n. Gussed Labels (sheet) 5 5 5 5 5

o. Bolt Cutters Two are available on well in storeroom l of training building.

DC0118 21XXIII l

Q 4

1 AND 2 NUMBER EP EF-5

. DIA81.0 CANYON POWER Pt. ANT UNIT NO(S) REVISION 8

, DATE 9/23/85 PAGE 20 0F 59 TiTa EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES i

4

' TA8LE 1 (Continued)

CONTENTS OF RADIOLOGICAL EMERGENCY KITS QUANTITY KIT #

ITEM 1, 2 3 4 5

1. Plastic Envelopes for '

Iodine Cartridges (Ziploc baggies) 30 30 30 30 30

j. Forceps 1 1 1 1 1

k. Cogressed Air cylinder. 2 2 2 2 2 1700 psi

1. Sagle Head w/ Adapter to .

fit Air Cylinder 1 1 1 1 1,

m. Air Cylinder Regulator 1 1 1 1 1

4. Protective clothing /

Decontamination

a. Protective Clothing Sets (coveralls, hood. ,

booties, rubbers, gloves) 2 2 2 2 2 )

b. Full Face Mask 2 2 2 2 2

c. Type GMR-S or GMI-H (orequivalent)

Ultra- Filters for Face Masks (min.) 2 2 2 2 2

d. Skin Decontamination Soap (pt. bottle) 1 1 1 1 1 .

e. Hand Brush 1 1 1 1 1

f. Floor Scrub Brush 0 1 0 1 1

g. Paper Towels (pkg.) 0 1 0 1 1

h. Smear Pads 8"x8" cotton (pkg of 10) 1 3 1 1 1

1. Plastic Bags (38"x 65") 3 3 3 3 3 ,

j. Bucket (10 quart) 0 1 0 1 1

k. Decontamination Agent l (gallon. bottles) 1 1 1 1 1 DC0118 20XXIII l

94

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1 AND 2 NUMBER EP EF-5

DLASLO CANYON POWER PLANT UNIT NO(S) REVISION 8 DATE 9/23/85 PAGE 19 0F 59 3

EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES 7,7 7 TABLE 1 (Continued)

CONTENTS OF RADIOLOGICAL EMERGENCY KITS QUANTITY ,

KIT #

ITEM 1 2 3 4 5

2. Monitoring Equipment *

a. Dose Rate Meter 1 2 1 1 1

b. Survey Meter 1 1 1 1 1

c. Standard G-M Probe 1 1 1 1 1

d. Pancake G-M Probe 1 1 1 1 1

, e. Pocket Dosimeters (0-5R) 2 2 2 2 2

f. Pocket Dosimeters (0-200mR) 2 2 2 2 2

g. Dosimeter Charger 1 1 1 1 1

3. Air Sampling Equipment

, a. 12 V Air Sampler and Sample Head (w/o Battery) 1 1 1 0 0

b. 12 V Air Sampler and Sample Head (w/ Battery) 0 0 0 1 1

c. 120 Y AC Air Sampler and Sample Head 0 1 1 0 0

d. Air Sample Particulate Filters (pkg. of 10) 10 10 10 10 10

e. Iodine Filter Cartridges (pkg. of 10) 2 pkg - TEDA, 3 3 3 3 3 1 pkg - AgZ

f. Swar Packets (5 smear /

Packet) 250 250 250 250 250

g. Paper Envelopes for AIR Particulate Samples 50 50 50 50 50

h. Casio digital watch 1 1 1 1 1

Equipment of equivalent function may be substituted.

DC0118 19XXIII

h , OtA8>.0 CANYON POWER PLANT NNIT NO('S) ,. -1 AND 2 fPEF-5 DATE 9/23/85 PAGE 18 0F 59 T TITLE. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES TABLE 1 CONTENTS OF RADIOLOGICAL EMERGENCY KITS QUANTITY KIT #

ITEM 1 2 3 4 5

1. Instructions, Procedures and Suppites

a. Instruction binder 1 1 1 1 1

b. Table of contents 1 1 1 1 1

c. Sanford Marking Pens 2 2 2 2 2

d. Red Marking Pens 2 2 2 2 2

e. Black Marking Pens Ball Point Pens 2 2 2 2 2"

f. 2 2 2 2 2

g. San Luis Obispo County Map 1 1 1 1 1

h. Equipment Location Dwgs.

(sets) Unit 1 1 1 1 1 1

1. Emergency Environmental - I Monitoring Field Datr -

Sheet (Form 69-9259) 100 100 '100 100 100

j. " Emergency Onsite Radiological Environ-mental Monitoring Program" EP RB-7 1 1 1 1 1

k. " Emergency Offsite Radiological Environ-mental Monitoring Program" EP RS-8 1 1 1 1 1

1. " Emergency Equipment, Instruments and Suppites" 1 1 1 1 1 EP EF-5

m. Corporation Key (3A90909) 1 1 1 1 1

n. Information Center Key 0 1 0 1 1

o. Pocket Calculator 1 1 1 1 1

p. Record.of' Potassium Iodine p D.istribution.

Form #69-9395 1 1 1 1 1

q. Computation paper (packet) 1 1 1 1 ~1 DC'0118 18XXIII s

I

' NUMBER EP EF-5 '

,- otAsto CANYON POWER PLANT UntT NO(S) 1.AND 2 REVISION 8 DATE 9/23/85 PAGE 17 0F 59 .

TITm. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES FIGURE 3 MEDIA CENTER NEWSROOM (CUESTA COLLEGE)

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REVISION 8 f DATE 9/23/85 s )

> PAGE 16 0F 59 7,7g, EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES I i

l FIGURE 2 MEDIA CENTER AUDITORIUM (CUESTA COLLEGE)

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NUMBER EP EF-5 1 AND 2 DiAsLO CANYON POWER PLANT UNIT NO(S) REVISION 8 DATE 9/23/85 PAGE 14 0F 59 7,7 a EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES

17. 69-10866 Assedly Area Checklist

18. 69-11575 Isotopic Measurement Equipment Checklist

19. 69-11589 K! Inventory O

-]

OC0118 14xxIII j 1

l i

NUMBER EP EF-5 1 AND 2 otAaLO CANYON POWER PLANT UNIT NOW REVISION 8

- DATE 9/23/85 PAGE 13 0F 59 EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES 7,7 g

13. Emergency Operations Facility Emergency Plan Equipment *

14. PG4E Energy Information Center Decontamination Facility Equipment l

15. Media Center Equipment

16. Assembly Area Equipment

17. Isotopic Measurement Equipment ATTACMENTS l 1. 69-9823-1 Emergency Kit Inventory Checklist Box A [

2. 69-9823-2 Emergency Kit Inventory Checklist Box B

~

3. 69-9823-3 Emergency Kit Inventory Checklist Box C 4

j 4. 69-9369 Evacuation Kit Inventary Checklist i

5. 69-10598 Hospital Kit Inventory Checklist

6. 69-10507 Post-LOCA Sampling Kit Inventory Checklist

7. 69-9043 Emergency Plan Phone Number Verification Checklist

8. 69-10766 Control Room Checklist

9. 69-10767 Technical Support Center Checklist

10. 69-10768 Technical Support Center Equipment Quantity Checklist i 11, 69-10769 Operational Support Center Checklist

12. 69-10770 Emergency Operations Facility Equipment Function Checklist i

13. 69-10771 Emergency Operations Facility Inventory Checklist

14. 69-10582 Emergency Facility Forms File List

15. 69-10864 Decontamination Facility Checklist

16. 69-10865 Media Center Phone Checklist ,

1

i

. DC0118 13XXI!! ,

NUMBER EP EF-5 DIASLO CANYON POWER PLANT UNIT NO(S) - 1 AND 2 REVISION 8 DATE 9/23/85 PAGE 12 0F 59 7,7tg, EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES EMERGENCY DOCUMENTS

1. Emergency Plan The emergency plan is reviewed and updated annually in accordance .

with the requirements of Administrative Procedure AP E-4519.

FIGURES

1. MEML Garage Layout and Access

2. Media Center Auditorium (Cuesta College)

3. Media Center Newsroom (Cuesta College)

TA8LES *

1. Contents of Radiological Emergency Kits

2. Contents of Evacuation Kits

3. Locations of First Aid Supplies i

)

4. Contents of Hospital Kits '

5. Portable Count Rate Meters

6. Portable Dose Rate Instruments

7. Contents of Post-Accident Sample Kit

8. Plant Vehicle List

a. Emergency Organization Radio Pagers

9. EWS Siren Locations

10. Control Room Emergency Plan Equipment

11. Technical Support Center Emergency Plan Equipment

12. Operational Support Center Emergency Plan Equipment DC0118 12XXIII l

1 AhD 2 NUMBER EP EF-5

. DiAsto CANYON POWER PLANT UNIT NO(S) REVISION 8 DATE 9/23/85 PAGE 11 0F ~59 rir a EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES

5. Emergency Procedure Phone Numbers i

Telephone numbers in the emergency procedures are verified quarterly by the emergency planning staff, using Form 69-9043.

6. PG&E Energy Information Center Decontamination Facility Equipment is available at the PG&E Information center for personal decontamination purposes. The surveillance performed on this equipment is listed in Table 14.

7. Media Center Equipment is available at the Media Center.for information updates and communications with the media during an emergency. .*

The surveillance performed on this equipment is listed in Table 15.

8. On-Site Assembly Areas The Training Building will be the main assembly area for all personnel leaving the protected area. Those remaining in the protected area will have an assigned area for accountability.

The surveillance performed on the equipment in the areas is listed in Table 16.

l

9. California Polytechnic State University l Equipment is available to perform isotopic measurements of samples taken from the environment. The surveillance performed on this equipment is listed in Table 17.

10. Mobile Environmental Monitoring Laboratory (MEML) Garage The MEML garage contains the emergency kits and the off-site field team radios. The emergency kits are addressed elsewhere in this procedure. The MDt. is in nomal use under DER procedures.

The field team radios are operability checked and battery exercised by the CARP Department quarterly.

DC0118 11XXIII l

l

l NUMBER EP EF-5

, 0iAsLO CANYON POWE7 PLANT UNIT PeO(S) .

I.AND 2 REVISION 8 DATE 9/23/85 PAGE 10 0F 59 TTa EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES FIXE 0 EMERGENCY EQUIPMENT

1. Early Warning System Testing and maintenance for the EWS Siren Units, listed in Table ,

9, shall be performed by Los Padres District personnel according j to the following schedule:

~

a. Bi-weekly: A test cancel signal will be initiated, counter readings will be taken and a visual inspection made,

b. Quarterly: The inside of the compressor and the control and receiver cabinets will be inspected, and the sirens will be growl tested.

c. Annually: A complete inspection of all major components, as well as lubrication and cleaning of the unit will be done.

EMERGENCY FACILITY EQUIPMENT ;

1. Control Room Equipment available in the Control Room for radiological \

emergency assessment and communication and the surveillanco perfomed on this equipment is listed in Table 10.

2. TechnicalSupportCenter(TSC)

Equipment available in the TSC for emergency assessment, comunication and other emergency functions of the facility and the surveillance perfonned on this equipment is listed in Table 11.

3. Operational Support Center (OSC)

Equipment available in the OSC for emergency functions and communications and the surveillance perfomed on this equipment is listed in Table 12.

4. Emergency Operations Facility (EOF)

Equipment available in the E0F for emergency assessment, connunication and other emergency functions of the facility and the surveillance perfonned on this equipment is listed in Table 13.

)

l DC0118 10XXIII

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o 1 AND 2 i

DIASLO CANYON POWER PLANT UNIT NO(S) f5ON DATE 9/23/85 PAGE 9 0F 59 riytg. EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES l

b. ige Detector l

1

c. HP 9845C Computer

d. Multichannel Analyzer I

e. High-Volume Air Sampler

f. Pressurized Ion Chamber (3)

g. High-Pressurs Gas Sampler

h. TLD Reader

1. Instrument-Grade Electric Generators

10. Plant Vehicles Plant vehicles shall be inventoried by the General Services I Department. The plant vehicle list shall be updated annually.

The plant vehicle list can be found in Table 8.

11. Portable Radio and Pagers Portable radios are available for emergency use. Radios are nomally located at Radiological Access Control and the Control Room. Radios dedicated for emergency use are identified in the check lists for the facility where stored.

Radio pagers are assigned to selected positions of the emergency organization, as a convenience, for use when the on-call person for the position is not available at their normal telephone numbers. Nomal pager assignments are given in Table 8.a. A group page and test message is given on the first of each month at about 8:00 p.m. to provide a check on peger operation.

12. KI Potassium Iod.ide is inventoried quarterly by Emergency Planning.

It is replaced when the shelf life is exhausted. When reordering K! obtain a certificate from the vendor, one copy for Emergency Planning and one copy for C&RP files. Inventory is documented on fo m 69-11589 "KI Inventory".

DC0118 9XXIII

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

o DIA8LO CANYON POWER PLANT UNIT NO(S) -

1.AND 2 NUMBER EP EF-5 REVISION 8 DATE 9/23/85 rirm.

PAGE 8 0F 59 EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES 2)

The cabinets contain sample handling and analyzing equipment. Reagents are under the sink. Additional SCBA air supply is available in the Sentry Room.

c. Surveillance Frequency j 1)

C&RP Sentry personnel.Both parts of the kit will be inventoried 2)

Each time a part of the kit is used, that part will be inventoried by the Chemistry and Radiation Protection Department without imposing the requirement that the other unused parts be inventarfed.

8. Protective Clothing Protective clothing for emergency use is located at Access Control.

found are: Other locations where clean protective clothing may be

a. Plant Warehouse

b. PGandE Energy Information Center s

c. Technical Support Center (TSC)

d. Training Building Storage Room 126

e. Plant locations as specified by C&RP.

9.

Mobile Environmental Monitoring Laboratory (MEML)

The following equipment is avaf fable in the MENL for use in routine and emergency environmental monitoring. Surveillance is performed during normal use, i

a. Na! Detector

~

DC0118 8XXIII

, . DIASLO CANYON POWER PLANT UNIT NO(S)

I ANO 2 ON DATE 9/23/85 PAGE 7 0F 59 EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES ,

77g

6. Portable Survey and Dose Rate Instruments A variety of portable count rate and dose rate instruments are '

available at the plant for routine radiological monitoring, and also for use in emergencies, if necessary. The general types and approximate quantities of this equipment are sunenarized in Table

5 and 6. It should be noted that this list is intended only to be illustrative of the plant's capabilities; precise quantities and models of specific equipment may vary from time to time as conditions change, different products appear on the market, etc.

The equipment listed in the table is normally located at Access Control when not in use.

7. Post-Accident Sample Kit The kit consists of 2 parts, Pre-entry and Sentry, which are used .

in conjunction with each other when post accident sampling is perfonned. Contents are listed in Table 7.

a. Part 1 the 85' Locker (Pre-entry)

1) Located in the Turbine Building elevator vestibule 85'

\ elev., it is easily accessed from the Cold Machine Shop, which may be the emergency assembly area for Chemistry and Radiation Protection.

2) This locker provides initial equipment, primarily protective clothing, for personnel preparing to access the Sentry System.

b. Part 2. Under Counter Cabinets and Locker (Sentry)

I

1) Cabinets art located under the counters in the Sentry room where analyses will be performed. The locker is next to the air conditioner.

DC0118 7XXI!!

1 AND 2

, oiAsto CANYON POWER PLANT UNIT NO(S) [lSf0N 8 9/23/85 DATE PAGE 6 0F 59 riyog. EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES

3) Dosimeter charger batteries will be replaced quarterly by the C&RP Department.

5. Respirators (Self-contained Breathing Apparatus or SCBA)

a. Location - The SCBA units should be located in the following locations under normal conditions. The number shown is the minimum number of units required.

SCBA 30-Minute Tanks LOCATION 00ANTITY QUANTITY

1) Operator Ready Room 8

2) 85' Fire brigade locker 16

3) Technical Support Center 5 5 .

', 4) Intake Structure 6

5) Access Control (or at filling 25 20 station)

6) Auxiliary Building stairwell 7 on the 90' elev.

i

7) Unit 2 Auxiliary Operators 1 Office -)

8) 85' Turbine butiding vestibute 3 (Post-Loca sample kit locker)

9) Unit 1 Sentry room cabinet 6

10) Unit 2 Sentry room cabinet 6 71 37 M: Approximately 30 additional SCBA and 15 air bottles are available on-site, if required.

b. Surveillance

1) SCBA units will be inspected by the Chemistry and Radiation Protection Department monthly.

2) The thirty SC8A's stored in other locations should be inspected prior to use.

' 3) All SCBA units will be inventoried semiannually by the C&RP Department.

DC0118 6XXI!! -

i

1 AND 2 NUMBER EP EF-5 oiAsto CANYON POWER PLANT UNIT NO(S) REVISION 8

DATE 9/23/85 PAGE 5 0F 59 7,72 EMERGENCY EQUIPMENT. INSTRUMENTS & SUPPLIES .

3. First Aid Supplies

a. Location The location of first aid supplies are listed in Table 3.

b. Surveillance First aid supplies are inventoried monthly by the Emergency and Safety Services Organization,

c. All other Department First Aid Kits are the responsibility of the department supervisor.

d. First Aid Kits in company vehicles are .the responsibility of the assigned driver or the General Services Department for .

" pool" vehicles. .

4. Hospital Kits Each kit consists of a box, clearly identified. The contents of each hospital kit are given on Table 4.

a. Location The two hospital kits are located at French Hospital.

b. Use The kits are available for use in the event an injured victim. involving radioactive contamination or overdose, is

sent to an offsite location for treatment or decontamination.

c. Obtaining a Hospital Kit The kits can be obtained by going to French Hospital.

d. Surveillance Frequency

1) Kit inventory will be performed by the Chemistry and Radiation Protection Department quarterly and after each use.

2) Survey meters and dose rate meters will be replaced or recalibratto in accordance with the normal practice established by the IAC Maintenance Department.

DC0118 SXXIII

l'AND 2 DiAaLO CANYON POWER Pt. ANT UMT NO(S) fSf0N 8 DATE 9/23/85 PAGE 4 0F 59 riya EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES

2. Emergency Evacuation Kits Each kit consists of a box, clearly identified. The contents of each emergency evacuation kit are given in Table 2. The contents of each box can be found on the inside cover of the box. In addition, two cases of protective clothing and two cases of shoe covers are stomd near the evacuation kits for use in case personal effects are contaminated. Additional protective clothing is also available at the Energy Infomation Center.

a. Location The two emergency evacuation kits are located in the Training Building, Storage Room 126. -

b. Use -

The kits are available for use in the event site evacuation is ordered by the Site Emergency Coordinator. The Evacuation Coordinator would then have the kits and clothing issued to the evacuation team leaders. ,

c. Obtaining an Emergency Evactation Ki' .)

The emergency evacuation kits can be obtained by going to the Training Building.

d. Surveillance Frequency

1) Kit inventory will be perfomed by the Chemistry and Radiation Protection Department quarterly and after l each use. Fom 69-9369 is used to document the j inventory.

2) Survey meters and dose rate meters will be replaced or recalibrated in accordance with the nomal practice

established by the C&RP Department.

3) Dorimeter charger, bu11 horn, calculator, and flashlight

! batteries will be replaced quarterly, by the C&RP Department.

l l

OC0118 4XXIII l

l l

l

1 AND 2 NUMBER EP EF-5

oiAst.o CANYON POWcA Pt. ANT UNIT NO(S)

, REVISION 8 DATE 9/23/85 PAGE 3 0F 59 7,7 g EMERGENCY EQUIPMENT INSTRUMENTS & SUPPLIES E: If the RERM cannot be reached at the EOF, then contact the Emergency Radiological Advisor (ERA) at the onsite Technical Support Center. The phone number is listed in Attachment 1.

If the RERM or the ERA require issnediate deployment of the MEML and/or the field monitoring teams, and access to the garage is still not available, inform the RERM/ ERA that access is not available and request the Cypher Pad Code that will open the door. Also, request the ERA to dispatch an individual from the plant to reset the alam.

Call DCPP security to inform them the MEML garage will be entered, and that the alarm will e be actuated. The phone number is listed in Attachment 1.

E: When the alam is actuated a loud electronic warbler will sound locally, until reset.

2) Kits No. 4 and 5 can be obtained by the designated monitoring teams from the Training Building, Storage Room 126.

d. Su.ve111ance Freq9ency

1) Kit inventory will be perfomed by the Chemistry and Radiation Protection Department quarterly and after each use. Fom 69-9823-1, 69-9823-2, and 69-9823-3 are used to document the inventory.

2) Kit radiological instruments will be replaced or 1

recalibrated in accordance with the normal practice established by the !&C iisintenance Department.

t

3) Dosimeter charger and flashlight batteries will be replaced quarterly by the C&RP Department. ,

4) The kits have a Chemistry and Radiation Protection seal

. to prevent tampering and insure the completeness of their inventory.

OC0118 3XXI!!

1 AND 2 ON oiAaLO CANYON POWER PLANT UNIT NO(S)

DATE 9/23/85 PAGE 2 0F 59 EMERGENCY EQUIPMENT, INSTRUMENTS & SUPPLIES 7 TLE.

c. Obtaining an Emergency Kit

1) Kits No. 1, 2 and 3 can be obtained by the designated monitoring teams from the PG&E San Luis Obispo Service Center, in the Mobile Envianmental Monitoring Laboratory (MEML) Garage. ;he personnel dispatched to -

the MEML garage will generally consist of Chemistry and Radiation Protection Technicians (C&RP), the MEML Operators from PGandE Department of Engineering Research, and San Luis Obispo County Environmental Health Department Personnel.

g: If the MEM. garage is locked, personnel should not open the door without a burglar alam defeat key available. The front door is the only access that has a 45 second time delay to pemit .

=

use of the defeat key (see Figure 1). The defeat key is available from the plant if the DER personnel are not available. The DER personnel will be called out as part of the call-out list in Emergency Procedure EP G-2.

idhen PGandE personnel have reached the MEML 3 garage, establish telephone contact with the Radiological Emergency Recovery Manager (RERM) -)

i at the Emergency Operations Facility (EOF). The phone number is posted on the MEML Garage door.

If the IER. garage is locked and access cannot be obtained from the DER personnel assigned to the van, then use the telephone in the division '

office building.

I-f l

DC0118 2XXIII g l

l

s ,

. 7Gv43 ,

Pacific Gas and Electric Company NUMBER REVISION 8 EP EF-5 OEPARTMENT OF NUCLEA.it PLANT OPERATIONS DATE 9/23/85-D'A8LO CANYON POWER PLANT UNIT NO(S) PAGE 1 0F 59 1 AND 2 )

yi7g' EMERGENCY PROCEDURE M,, EMERGENCY EQUIPMENT INSTRUMENTS & SUPPLIES ,

ApenovED. W. d lo-1% M PLANT MAN R DATE l

~

SCOPE This procedure provides an inventory of emergency equipment, instruments, and supplies (both portable and fixed) with inspection frequencies. ,

s This procedure and changes thereto require PSRC review.

PORTABLE EMERGENCY EQUIPMENT

1. Radiological Emer'gency Kits The kits consist of three boxes each. Each box is clearly identified first by kit numbers, and second by box letter A, B or C. The contents of each emergency kit are given in Table 1. The contents of each box of an individual emergency kit can be found in the ' notebook of each box. In addition, protective clothing and shoe covers iare' located at the Energy Infonnation Center and the DCPP Training Building for use in case personal effects are 1

contaminated.

! a. Location i Kit Mos.1,'2 and 3 - PG8E San Luis Obispo Service Center Mobile Environmental Monitoring ,

Laboratory (MEML) Garage

' Kit Nes.,4 and 5 - Diablo Canyon Power Plant Training 1

Building, First Floor Storeroom b.

Usa' The kits are available for use by a designated monitoring

' team in case of a radiological emergency.

D DC0118 1XXIII -.

O w-.--,e--i---wwe a -- ,, -

---rw,- --w, ,+m -r- ---m--

SITE EMERGENCY COORDINATOR I

I I LIAISON ' MAINTENANCE OPERATIONS EVALUATIONS COORDINATOR COORDINATOR COORDINATOR AND RECOVERY-COORDINATOR I I I i . _ .._,.._._. _..__._ _._._..__._,.__._.__SuirjFOREMAN i l i OPERATORS l

OSC RESERVE FIRE BRIGADE SilPERVISOR OPERATORS LEADER EMERGENCY l ,

l s

. RADIOLOGICAL ADVISOR -

l FIRE '!

l j . sRiGADE I I I . l ,

I&C ELECTRICAL MECHANICAL *l COORDINATOR C00R0lNATOR COORDINATOR l*

l

. SITE CHEM l & RADIATION

.! l

! ! ! ].- . -. _.-.-. L. - PROTECTION C00?.DINATOR.

FIGURE 1 LINE AUTHORITY

.__. COMMUNICATION

/

' NUMBER EP EF-2 oiAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

REVISION 6 DATE 9/30/85 PAGE 7 0F 7 ACTIVATION AND OPERATION OF THE rara OPERATIONAL SUPPORT CENTER I ATTACHMENT A. OSC organization chart SUPPORTING PROCEDURES A. EP G-1. Accident Classification and Emergency Plan Activation

8. EP G-2 Establishment of the Onsite Emergency Organization C. EP G-4, Personnel Accountability and Assembly t

DC0026 7X

a jr DiAaLO CANYON POWER PLANT UNIT N0(S) 1 AND 2 Sf0N6 DATE 9/30/85 Tu ACTIVATION AND OPERATION OF THE PAGE 6 0F 7 OPERATIONAL. SUPPORT CENTER D.

Radiation Monitoring Eufpment C&RP will as individuals provide radiation monitoring equipment to teams and appropriate.

E. Protective Clothing MSA's (self contained breathing apparatus) are also .

specifically designed for fire fighting activities. Fire briga F. First Aid Medical Supplies Firstafd first aidroom.

medical supplies are located at the access control G. Decontamination .

Access disposal,control provides showers, soaps, shampoos towels, waste extra clothing event personnel become co,ntaminated while in the plant. friskers H. Sampling Equipment

-)

Routine air and 11guld sampling equipment is avaliable at access control.

system and containment atmosphere is located in a mar in the hallway between access control and cold machines shop.

I. Maintenance Equipment adjacent to the OSC. Maintenance equipment is located in the r.old mac A lar equipment is located there.ge inventory of tools, parts and heavy The cold machine shop has the capability to fabricate some parts which may not be readily available.

J. Fire Fighting Equipment Fire fighting equipment for the fire brigades is stored at the north end of the Unit 1 turbine building on the 85' elevation, the auxilfary building stairwell landing approximately 90' elevation, and the control operator readyroom. A plant fire truckready area and two hose ifne trailers are located within the protected for use.

the cold machine shop.A fire brigade status board is located in DC0026 6X

- . otAaLO CANYON POWER PLANT UNIT NCHS) 1 AND 2

[0N DATE 9/30/85' PAGE 5 0F 7 ACTIVATION AND OPERATION OF THE 7'E3 OPERATIONAL. SUPPORT CENTER OSC Equipment Description

1. Comunications The OSC has the capability to comunicate with the control room.

TSC, appropriate response teams and other plant extension via telephone. It is equipped with extensions of a dedicated telephone tie line to the control room and TSC and also has a CBX telephone extension with emergency facility priority access to telephone circuits, as well as normal in-plant telephone capability.

Both the Access Control Area and General Maintenance Foreman office are also equipped with extensions of the dedicated telephone tie line to the control room and TSC and also have a CBX telephone extension with emergency facility priority access .

to telephone circuits.

The telephone is the primary means of communicating with maintenance teams dispatched into the plant. During emergency response situations, maintenance teams will carry radios to provide back-up comunications. Radios are available to the OSC 1 and have OPS /SEC/NP frequency capability. These radios are maintained at access control. This ensures the radios are charged and imediately available for use. Operations and the fire brigade also have radios which can be utilized.

2. Status Boards An OSC status board is maintained whenever the OSC is activated and operational. It provides infomation on plant emergency status, radiologi.al conditions, work assignments, team member names, team locations, radio call signs and phone extensions as appropriate. The OSC status board is in addition to those routinely used by C&RP.

C. Reference Materials A current controlled copy of P&ID's is available in the cold machine shop adjacent the OSC. Maintenance plant manuals.

Emergency Procedures, and other reference materials are available from the foremen office area of the cold machine shop. A set of Emergency Procedures is located in the office at access control.

Plant layout drawings may be " marked-up" on the window glass using felt markers to identify team locations and to brief on the most expeditious, lowest radiation level, and safest routes to a f response location.

DC0026 SX

. =

0iAaLO CANYON POWER PLANT UNir NO(S) 1 AND 2 h0N DATE 9/30/85 PAGE 4 0F 7 ACTIVATION AND OPERATION OF THE Tir a OPERATIONAL SUPPORT CENTER

3. The OSC Supervisor reports to the Emergency Maintenance Coordinator. In an emergency, the Emergency Maintenance Coordinator responds to requests from the control room (initially) or the Technical Support Center (TSC) for repairs, ascertains manpower needs, and makes assignments to maintenance groups as needed. To support him in this role, an OSC Supervisor is delegated the responsibility for assuring teams responding to emergency plant conditions are properly equipped and prepared.

The OSC Supervisor maintains communications with the control room and TSC. He will brief response teams on plant status and other plant evolutions in progress that might affect them. He assures they receive briefings from Chemistry and Radiation Protection (C&AP) on job requirements and radiation protection provisions for the job. He will provide teams with radios for back-up communications and insure telephone connunications are established so teams can be informed of significant changes in plant conditions (such as changes in emergency classification or radiological conditions in the vicinity). He will maintain an OSC log as a permanent record of activities.

The OSC Supervisor is responsible for information flow to the TSC and Emergency Maintenance Coordinator concerning reconnended .

safety measures and status of response teams in the plant. In )

performing these duties he will communickte with the site C&RP l coordinator, the emergency maintenance cooroinator, the emergency operations coordinator and the emergency liaison coordinator as needed to exchange information and be aware of plant conditions.

This relationship is shown in figure 1.

Record Keeoing All records generated by the utilization of the OSC for an exercise or emergency shall be forwarded the next working day to the Assistant Plant Manager / Support Services for review and retention.

1. Records generated from exercises will be categorized as non-pemanent and retained for a minimum of five years.

2. Records generated fram actual emergency events will be categorized as lifetime and placed into lifetime storage in accordance with procedure AP E-1 SI. " Requirements for Retention

and Extended Storage of Operation Phase Activity Records."

DC0026 4X

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

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f0N

, DATE 9/30/85 1 PAGE 3 0F 7' l ACTIVATION AND OPERATION OF THE 1 7'T

OPERATIONAL SUPPORT CENTER l Immediate Actions - Normal Hours

1. When the site emergency signal is sounded, all personnel not engaged in critical operations or emergency recovery actions will report to their assigned assembly locations in accordance with Emergency Procedure G-4 " Personnel Accountability and Assembly."

Personnel designated for immediate emerewcy response will report to the Operational Support Center. This includes the Operational Support Center Supervisor, the Site Chemistry and Radiation Protection Coordinator, the Emergency Safety Supervisor support staffs and the Maintenance Fire Brigade.

Ismediate Actions - Off Normal Hours

1. OSC personnel required for emergency response will be notified in accordance with Emergency Procedure G-2 "Establishesnt of the .c

, Onsite Emergency Organization."

2. The Security Shift Supervisor will be notified of the personnel responding to their emergency response roll and assure they are permitted access to the site.

(- 3. Personnel notified to report to the OSC may proceed directly to the OSC and be inmediately available for fire fighting, emergency maintenance, search and rescue or radiological monitoring, as appropriate. '

4 Personnel notified, but not given a p ecific emergency response location should initially report to the security building lunch room (ready room) for further instructions.

Subsequent Actions

1. The Emergency Liaison Coordinator assigned to the TSC will dispatch a liaison assistant to the security building ready room as soon as man power permits. This liaison assistant will act as coordinator for individuals reporting to the plant, but not having a specific response location. Otherwise the senior person in the ready room will coordinate activities.

2. Following the initial response, personnel called from offsite or plant assembly areas will be directed by the Liaison Coordinator (or his assistant) to remain on stand-by at the security building ready room or report to the OSC.

DC0026 3X

l

. , oiAsto CANYON POWER PLANT UNIT nom 1 AND 2 ON DATE 9/30/85

' PAGE 2 0F 7 N ACTIVATION AND OPERATION OF THE !

OPERATIONAL SUPPORT CENTER

3. Provides an assembly point for reserve licensed and non-licensed i plant operators who may respond as directed to emergency 1 mitigation efforts. '

Minimus Staffine The OSC should be considered operational at a minimum level when:

1. A Maintenance Coordinator has established contact with the Sita Emergency Coordinator to determine requirements for immediate maintenance activities.

2. An OSC supervisor is available and stationed to brief the team or teams.

3. The manning requirements are met for the team or teams required .'

to perfom imediate maintenance. !

E: The repair team may consist of members of the Maintenance Fire Brigade.

4. The Site Chemistry and Radiation Protection Coordinator has established contact with the Emergency Radiological Advisor and )

has sufficient Chemistry and Radiation Protection Technicians to support imediate requirements for maintenance, inplant sampling, surveys or onsite monitoring.

If no teams are immediately required, then the OSC should be declared operational when a haintenance Coordinator, an OSC Supervisor and the Site Chemistry and Radiation Protection Coordinator are positioned and 1 comunications have been established with the Technical Support '

Center. i Initiatino Conditions The Shift Foreman declares that the plant is in an Alert. Site Area Emergency, or General Emergency status as defined in Emergency Procedure G-1, " Accident Classification and Emergency Plant Activation", or detemines that activation of onsite emergency centers is warranted and sounds the Site Emergency Signal or orders call out j of plant staff personnel in accordance with Emergency Procedure G-2 '

" Establishment of the Onsite Emergency Organization". l I

l DC0026 2X l

NUMBER EP EF-2

?Gv43 Pacific Gas end Electric Company REVISION 6 DEPARTMENT OF NUCLEAR PLANT OPERATONS DATE 9/30/85 DIGLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 7 EMERGENCY PROCEDURE

[j ACTIVATION AND OPERATIOL OF THE TITLE: OPERATIONAL SUPPORT CENTER g

APPROVED: W-

i fb' "b PLANTMANAGEM DATE SCOPE This procedure describes the actions taken in the event it becomes necessary to activate the Operational Support Center.

This procedure and changes thereto require PSRC review. .

GENERAL The Operational Support Center (OSC) provides a place separate from the control room and Technical Support Center where designated support personnel assemble and await specific assignment during an emergency.

(- The OSC is designated as the Chemistry and Radiation Protection access control entry hallway, locker room and break room located on the plant 85' elevation entrance to the auxiliary building, and adjacent radiological access control and cold machine shop areas. These areas contain a variety of emergency support equipment which is immediately available for emergency use. It is equipped with dedicated tie line telephone extensions to the control room and TSC and also has a CBX telephone emergency facility priority access to telephone circuits.

An OSC supervisor will coordinate OSC activities and report directly to the Emergency Maintenance Coordinator.

Functions of the OSC

1. Serves as an initial assembly location for plant staff responding to the site emergency signal.

2. Provides a location for the staging of trained manpcwer for assignment to relief and special emergency positions on an as-needed basis to facilitate the following functions:

- emergency maintenance, repair and damage control

- fire fighting, search and rescue and first aid

- emergency sampling of plant fluids

- a location for storage of selected emergency response I equipment

- provide facilities for personnel decontamination l

l DC0026 1X i

a.

TITLE REV RB-15C SPASS Containment Air Sampling 3 RB-150 SPASS Gas Chromatographic Analysis 3 RB-15E SPASS RCS Liquid and Gas Sample Handling 3 RB-15F SPASS Data Analysis 2 RB-15G SPASS Ion Chromatographic Chloride Analysis 2 RB-15H SPASS pH/ Conductivity / Dissolved Oxygen 2 RB-15I SPASS Sample Storage and Disposal 1 RB-15J SPASS Undiluted Liquid Sampling From Reactor Coolant 0 RB-15K SPASS Diluted Liquid Sampling From Radwaste O RB-15L SPASS Undiluted Liquid Sampling From Radwaste 0 RB-15ti SPASS Undiluted Containment Air Sampling 0 0

0603S/0038K 11/15/85

O PGandE Letter No.: OCL CURRENT EMERGENCY PLAN IMPLEf'ENTING PROCEDURES TABLE OF CONTENTS Volume 38 TITLE REV OR-1 Offsite Support & Assistance 5 OR-2 Release of Information to the Public 3 EF-1 Activation and Operation of the Technical Support Center 6 EF-2 Activation and Operation of the Operational Support Center 6 EF-3 Activation and Operation of the Emergency Operations Facility 5 EF-4 Activation of the Mobile Environmental Monitoring Laboratory 6 EF-5 Emergency Equipment, Instruments & Supplies 8 EF-6 Operating Procedures For EARS 9845C Controlling Stations 5 EF-6S1 Transfer of EARAUT Control 1 EF-7 Activation of the Nuclear Data Communications System 2 EF-8 EARS Operating Procedures for TSC-CC HP-1000 Station 1 RB-1 Personnel Dosimetry 1 RB-2 Emergency Exposure Guides 1 RB-3 Stable Iodine Thyroid Blocking 1 RB-4 Access to a Estabitshment of Controlled Areas Under Emergency Conditions 2 RD-5 Personnel Decontamination 2 RB-6 Area & Equipment Decontamination 2 RB-7 Emergency On-Site Radiological Environmental Monitoring 4 RB-8 Emergency Off-Site Radiological Environmental Monitoring 5 RB-9 Calculation of Release Rate & Integrated Release 3 RB-10 Protective Action Guidelines 1 RB-11 Emergency Off-Site Dose Calculations 4 RB-12 Mid and High Range Plant Vent Radiation Honitors 1 RB-13 Improved In-Plant Air Sampling for Radiofodines 1 RB-14 Core Damage Assessment Procedure 2 RB-15 Sentry Post Accident Sampling System (SPASS)

Initial Sampling Exercise After An Accident 2 RB-15A SPASS Initial Actions During An Emergency 4 RB-15B SPASS Reactor Coolant Sampling (Stripped-Gas and Diluted RCS) 3 0603S/0038K 11/15/85

8 -

69-9311 7/80 (500)

DEPARTMEri 0F NUCLEAR PLA,4T OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 & 2

, EVACUEE MONITORING DATA LOCATION DATE INSTRUMENT USED BACKGROUND CPM PERSON READING SURVEY VEHICLE DIRECT SURVEY 1 RESULTS (MAX) g DOSI-NAME LICENSE TIME 1st 2nd READING METER TIME NO. LOCATION R 0 NG RELEASED NET CPM dom /dm2 NET CPM dom /dm2 ,

( .

1 Multiply net epm by 91 for HP-240 (window open), for HP-210 and HP-260, multiply by 25 in order to convert CPM to dpm/dm2,

69-9310 7/83 (500) ,

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 & 2 POST-EVACUATION VEHICLE MONITORING DATA LOCATION DATE INSTRUMENT USED BACKGROUND CPM PERSON MAKING SURVEY

' Direct Sun evi Results Emear Survov2 Results NUMBER lst 2nd 1st 2nd TIME LICENSE OF TIME NET dom NET d VEHICLE NET NET dem NUMBER PERSONS com dm' com hd arp RELEASED 4

J

(

i 1

l l

i l

l 1

Multiply net cpm by 91 for HP-240 (window open), for HP-210 and 260, multiply l by 25 to convert CPM to dpm/dm2 A = area smeared, square feet c = 0.018 for HP-240 2 Smearable dpm/dm2 . (0.11)(cpmnet); c = 0.20 HP-210 and 260 g,)(4) l

Attach:::e:.c 6.a ?!-39 Roi. 1 "Pu APPENDIX .3e 2 of 2

WAREHOUSE

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SHOCTTING RANGE V saren N ,

SWITCHYARD ACCES

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A::achment 6.4 .

Page 1 of 2 P

APP 10mTY D Timen Twinnumes Veloose to Diablo Canyon -

As a visitor to this . site, there are several rules and procedures which you aware of. They have been designed for wa=

1. If you have been issued a hard hat, wear it la all hard hat areas.

T (In

2. The visitor badge issued to you is to be vera in= plain vi will be provided with another badge in eschange.)

3 Persons cleared to enter the operating areas of the

' entry.

I.

( ) e i .

3hould a situation arise which requires the evacuation of this site, the Flaat Signal will,be activated. D e Signal is produced by electreate warblers plac 9

auserous locations throughout the plaat. De sound cycle is repeated continuously for as '

' rise is pitek followed by a slower drop. :

long as the signal remains easegised. len Flashing red lights have been provided in the Containment since the bac

! would not permit audible perception of the electreate warblers.

a L

Under an energener situaties the alare should sound for a minimum of one for a f

The Energency Signal vill be actuated for test purposes every Friday at 12

~

period of approzinately tea (10) seconds. d on i

l Should the Signal be activated during your visit othe no....,+.a vt.itaca.

If uncertain as to the location of Assembly Area 'D' ask any Security Officer.

re*-tad vtattaea will be taken to Assembly Area "D' by their seeort.

l 1 -

Rty . 4 1/20/84 i

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! APPENr"X C .

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UPPER PARK 1006. LOT ~

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~ ARROWS IMOICATE ROUTE TO ASSEM8LY AREAS TFOR TEAM AND P.T.G.C.( AL ,

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i CONTRACT PERSONNEL ( JOB SHOP PERSONNEL ) WORMING / .

! ALL OTHERS ASSIGNED TO AREA "C" i

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- RFV.0 I/20/84!

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. ARROWS INDICATE ROUTE TO ASSEMBLY- 2 o

I AREAS FOR CONTRACTOR PERSONNEL i f *

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ASSIGNID ASSEM3LY AREAS "A" AREA .

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3echtel (G-Bec)

Planthorpe N

Pullman Power Products and their subcontractors "3" ARIA H. P. Foley and their subcontractors "C" AREA "C" AREA

, P Cl. General Construction Centractors General services (PT-GC) Waltek .

Quality Control Group (PT-GC) Cataract Mechanical Group (PT-GC) Innova -

Startup Group (PT-GC) Wisco OnSite Engineering Group (OPEG) Code-3

, f Instrumentation Group (PT-GC) Pace

\. Electrioni Group (CPT-GC) Bisco

( Civil Group (PT-GC) Krystal Klean Civil-Hydro Group (PT-GC) G. O. Personnel Administration Group (PT-GC) assigned to project Station Construction /Line Dept.

"D" AREA "D" AREA Construction Force Assembly Visitors (Escorted and Unesc=rted)

Coordinator Common Carriers

. PT-GC Management Vendors and Service Companies

PT-PC Management "E" AREA Barnes Construction Co.

1 .

~

PA3I 1 0F 1* DATE 1-20-86 i *

. DIABLO CANYO,N PROJECT NUMBER FI-39 REVISION 1 DATE 2/24/84 TLE Personnel Accountability & Site Evacuation ourins A sie. Emergency PAGE 8 0F 8 4.5.6 In the event of an evacuation on foot, guards or P.G.4Z.

personnel with radios and first aid kits will be interspersed at appropriate intervals in the group to maintain consunication and provide first aid, if necessary.

5.0 ,

REZEEEEES i

5.1 Department of Nuclear Plant Operations Emergency Procedure G-4

' Personnel Accountability and Assembly'. ,

5.2 Department of Nuclear Plant Operations Emergency Procedure Gej.

" Evacuation of Nonessential site Personnel'.

. 6.0 ATT1 CEMENTS -

6.1 Appendiz-A

List of Assigned Assembly Areas 3 i j

6.2 Appendiz-Et Location Map of Assembly Areas 6.3 Appendiz-c Maps of Routes to Assembly Areas

6.4 Appendiz-D

Yisitor Information on site anergencies 4

O e

4 l

l a

o DIABLO CANYCN ,

PROJECT NUMBER PI-39 REVISION 1 Forsonnel Accountability & Site Evacuation.

T E Durins A stee Emergency PAGE 7 0F a 4.4 3 Personnel 14aving the site will badge out and back in at the Guard Post whsre they normally enter the Project, except personnel (such as Station Construction, Line Dept., and Centractor road work crews) leaving the site in Company Yehicles for off site work who will leave their badges with the guards at the plantaite entrance to

the lower parking lot, and retrieve them from there upon

their return.

4.5 Evanuation

4 51 Any evacuation of the Diablo Canyon Site will hagin fr.at the EMERCERCY ASSEMRLY AREAS as shown in the Diablo Canyon Power Plant hersency Procedure 0-4 ' Personnel

Accountability and Assembly *. All personnel covered by I

this procedure are instructed to proceed to these areas on foot upon activation of the Emergency Signal and to g wait there for further instructions.

I 4.5 2 The Construction Force issembly Coordinator will

( implement the Site hersency Coordinator's evacuation decision and see that various groups are accounted for and released sequentially and la sa orderly amaner so that traffic congestion is minimized and traffic flows smoothly away from the site.

4.5 3 0.C. Seourity personnel will assist by dirooting traffio eut of the lots and controlling key intersections during

! the evacuation as dirooted by the Evacuation Coordinator.

4.5.4 All evaeustions mother by vehicle or on foot, will be :

1ed by soeurity personnel. Acocopanying each assembly area group will be a person who will be in charge of personnel sooountabilt.ty and release at the off site

. assembly areas. Security personnel will be radio equipped and in contact with the Evacuation Coordinator

.and the Site Energency Coordinator.

4.5.5 Caoe ett the site, the evacuation will be led to the off

, site assembly area by a Sheriff's vehicle (if available).

Cae of the lead stards will transfer to the vehicle with his portable radio and ride to the off site assembly area la the Sheriff's vehicle so that continuous communications are asiatained.

. - _ , . , . , _ . , . - _ . - - - . . _ , _ - . . . . . _ _ , _ . _ _ _ _ _ _ _ , , _ , , , . _ , _ _ _ , _ , , , , _ . ,7.._,_ , _ _ _ , _ , , _ _ . . . __ ,,_,___,,,,...y_,_,__,m

d OIABLO CANYC,N PROJECT NUMBER FI-39

. REVISION 1 DATE 2/25/84 TITLE Pirsonnel Accountability & Site Evacu'ation Duffne A Site 5ertenev PAGE , Op ,

with Depts. of Administration, Electrical, Mechanical, Civil, Startup, Instrumentation, General Services, Quality Control, Communications, Ca-site Engineering, Project Control), Pu11aan (Magnafluz), Seleet H.P. Foley, assigned job shop personnel (Pace Eng., Code III, Cataract, Waltek, Wisce, Innova, Eto.), Erystal Elean personnel.

4 3 1.2 N==

f at mad == at t av h*==: Alleys #1 thru #9 '

and #11 thru #14 assigned to personnel of H.P.

Poley Co. , Fullama Power Products Co. , Plant Thorpe, Beektel G.P.M.A.

4 3 1 3 t'w " fet **d*= 1" " Ga t* 810. 3 Assigned to mis-oollaneous PTOC and Contractor personnel. %

4 3 1.4 nanar t.at maad statinar P.0.43. osap/ warehouse personnel, Mechania Services group.

4 3 1.5 plantaita cuard statient (lower Lot Entrance)

(.. Assigned management of: 5.P. Foley, Fullaan Power l

j Plant 1horpe, Lundeen, Parnes Constructica, a .d select employees of 3.L.O. Garbage Co. , Able Main-teennee, Western Santitation, Santa Maria Yending.

Coperbest, P.T.47. Co. , Bechtel 0-boo, Ieroz, IBM, E.P. Richards, S & M 3prinkler, Bisco, Santa Crus Research Group.

4.4 andge cantcal i

4.4.1 At the beginning of a shift personnel will pick up their photo badges at the appropriate Guard Station where they normally enter the Project. Immediately after shift abange esob of the guards at the controlling entry stations will determine the status of the employees severed by their posts.

4.4.2 On moraal work days, the day shift guards will till out a fore listing the employees McT ON SnT, by name & badge ausber, swing shift guards will do likewise for their i shift. Da other than normal work days, (holidays,

! weekends, other thaa normal work hours) guards will fill l out a fers listing the employees ALAZ3, by name & badge j

amber. These listings will be kept current at all times during the shifts by additions or deletions of those entering or leaving the Project, and will be supplied to the Field Construction Manager or his designate when requir

l DIASLO CANYON PROJECT NUMSER p:_39

'o . REVISION t Personnel Accountability & Site Evacuation D 2/24/84 TITLE Durins a site Emersency PAGE 5, OF 8 4.2 7 Lina crews (aff-mita c. c. amt ntstetet) Mae ammten.d ?s Diablo Canvent Crews working on site or on tower line work gaat of the site who gained access to their work through the site) will check in and report their personnel and work location to the upper lot road guard station daily. These crews will stay in the area of their work.,

4.2.8 Pinkartan G.C. Security Quards In as auch as possible G.C. Pinkerton Security personnel will remain at their posts. Mobile & Building Foot Patrols and the Sergeant, will report to the Sergeant's/

Captain's Trailer which will serve as the G.C. Security, oceaand post. The G.C. Security Office will immediately, upon the initiation of the signal, contact the G.C.

Force Captain and relay information to the Shift hourity Supervisor on the specific location of the guards remaining en post to determine the necessity of immediate evacuatica C- of these posts. Guards on post to be included la the

( evacuation will be notified by radio and ordered to their Sergesat's Trailer for ressaignment. Parking lot guards remaining on post will limit necess to personal vehicles until instructions for orderly evacuation are received.

The Security Guard Captain is responsible for the secountability of all guards assigned to construction t activities and will report directly to the Field Construc-tructica h anger or his designate.

4.2 9 Tnatruations k Emereenett Upon arrival at assigned assembly areas, all personnel will receive further instructions on the nature of the emergency. As soon as possible after the signal sounding, an accurate tally must be available to the Field Construction Manager or l his designated alternate indicating missing personnel and their last known location on the Project.

i 43 PEnscNNEL ACCcmtTABILITY 4 3 1 Gamaral All personnel will be accounted for by the issuance and

, control of the individual's Project photo I.D. badge.

I I.D. badges will be issued and controlled at one of the l following designated Project " Points of Entry's 4 3.1.1 Administration.Jttildina cuard station: General Construction Project Team (All esployees associated i

I

o

CIABLO CANYON PROJECT

- NUMBER p:.39 REVISION 1 TITLE DATE Durine A Site E*ernemeyPersonnel Accountability & Site Evacuation 2/:c/ei PAGE 4 0F a e

4.2 3 '===*=d visitaaa proceed along with their escorts to their visitor assembly area.

be maintained by checking off those escorted visitor at the assembly tained areasoffice.

at the security against the visitor sign in-log a n- m i Escorts themselves will proceed to their assigned their visitors to the visitor assembly assembly area areas after escortin g,3,4 ffnamaa-tad vinttapa. En t eem anne. vandam san-am-nemetvan.

fman1 Ba11vacima & Ma niteseturavas'_

The area. above perseas will also report to their assigned Upon arrival and check in at the Project, these persons will be provided with a map and written instrue-(~ tions explaining what they are to do and where they are to 30 diz in the event D, Attaahasat of a site evacuation (refer to .Appen 6.4).

Aeoountability will be main-areasoffice.

soeurity against the visitor sign-indog asinta i

-)

parked and proceed os foot to their designated areas.

4.2 5 caaman carriara Common carriers will be bandled in the same mann usescorted visitors with the exceptf as that they will be -

lossed la and out and provided wit +. a map and instruction at the plaatsite guard peat rather than the security office.

Drivers will leave their designated theirarea.

assently vehicles and proceed on foot to 4.2.6 P---

Paranaa-'

Paaaaa--' ==d M aa'a *= micam- I=="a ' ea t i ea a <

otha=a working in the switch yards, clarifier, osep & assesLAy to their appropriate back project area. areas will report directly persons from these outlying areas may be drives to theVehicles c upper lot road area, via the camp road, and parked.

These perseas will cheek in at the upper lot guard station upon arrival.

The ausber of vehicles used to move perseas from outlying areas to the assembly areas should be kept at a ainlaus.

J

~

o DIABLO CANYON PROJECT NUMSER p: 39 REVISION i Personnel Accountability & Site Evacuation DATE 2/24/84 l

{

l TITLE Du' ring A Site Emergency PAGE 3 0F s l l

Placed at numerous locations throughout the plant.

i It has a skaracteristie sound which is a rapid rise la pitch followed by a slower drop. The sound eyele is repeated oentinuously for as long as the

} signal remains energized.

4.1.1.2 Flashing Bad Limhta have been provided in the

Containment and other high noise areas since the l

background meise level would not permit audible percepties of the electronto warblers.

i 4.1.13 Under an emergency situation the alam abould sound for a minimum of ese minute.

i

! 4.1.2 Tantina i ,

! The hergeasy Signal will be actuated for test purposes ==

l overy Friday at 12:10 p.m. for a period of approzinately ,

tea (10) seconds. -

1

( 5.2 RESEQESE :

i . 3,3,j DPa4aat team DePanmaaf. PanatPuntian PantPantaPa anA he'- =tmaa tapa. =d athme ammatPuation faPaa Palated

narananal will evacuate from the plaat buildings and

! adjaeost work areas, emit through their respective assigned badge alleys and preeeed immediately to their I assigned assembly areas, is response to the Emergency Signal. Assigned alleys are these estrances tdiere the site photo badge is kept for ensk estegory of worker. A listing of all estegories of personnel governed by this Zastruettes, and assigned assembly areas is found in Appeedix A (Attaehment 6.1). A map showing the location of assembly areas is shows os Appendiz 3 (Attachment 6.2).

Soutes to be takes to assembly areas is shown on appendis C (Attaehment 6 3).

l .

' 4.2.2 All nait I ammatruatina marannaal will esit through the l plaat soeurity buildings leaving their Unit I badges but not their site photo I.D. badges. hployees will procard to their assigned badge alley leaving their atte photo I.D. badge, i

and them to their assigaod assembly area. All personnel i will be aseounted for by issuanos and sentrol of the individual atte phete I.D. badges. Eseh contreetor will assign a staff member to report to the badge alley to l assist la the aseounting of their personnel and resolu-I tion of any diserepaneles.

l

4 DLABLO CANYON PROJECT NUMBER PI-39 REVISION -

1 1

Personnel Accountability & Site Evacuation OATE 2/24/s4 I e TITLE ourins A site Emergency PAGE 2 CF 8 i

i 2.1.5 Provide required traffio control measures.

2.1.4 The decision to evacuate, the type of evacuation s (immediately, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ), the evacuation route (North or South), the off site asseab1y area, and the method (by vehicle or foot) will be made by the Site Energesey Coordinator and conveyed to the Constructica Force Assembly Coordinator.

2.2 Imah cantraatar is responsible for the eecountability of all l their employees working at the site. As accountability program must be implemented by esek Contractor to enable the yield Construction Maanger/ Construction Toroe Assembly Coordinator to know how amar esastructica personnel.are on alte at aar given l

time, and their general location on the Projoet. .

i 23 Suhaantraataca vill be responsible for impienenting their main Centrastor's asseustability progras. Eaoh subcontractor will be responsible for the aeoonatability of their employees. ;

l J

{ *

) '

2.4 *=^h Ps'a4aat ?--- Banar*= at "--' is responsible for the #

)

j sooeustability of all their subordinates. As asseustability j

program must be implemented to easbie each supervisor to know how assy of their people are os site at any gives time and i

their saaeral location. Esek employee sust be indoctrinated on his/her required response to this procedure and details of what is deae in the event the Snergency Signal is activated.

30 N CAT M d

31 This Instruotion applies to all construction force-related 4

perseasel working is all areas and elevations of the Flaat Site and Project.

l I

4.0 22012DEM i

i 4.1 m anEncT SIamAL 1

! 4.1.1 Idantifiaatina i

4.i .i., - is ,,oduced by stoot,o$o us,.ters

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n.: 3 DIABLO CANYON PROJECT etvisics. :

I jy DATE: 2/26 i- l PROJECT INSTRUCTION ME8 PERSONNEL ACCOUNTA3ILITY & SITE IVACUATION OURING A SITE EMIR 0ENCY APP 4OVEOe '

M ~

nfc...,..i........, o. .

1,. 0 EQ?!K 1.1 This Instruction describes the Plant Energency Signal and the lasediate action to be taken by F.C.&E. Construction and #

Service Personnel, Project Team and Contractor Personnel (including Job Shoppers and subcontractors) and their visitors and service representatives, for an orderly evacuation of the site in response to the Emergency Signal and accountability of

,. all personnel during such an evacuation.

(

2.0 RESPo!LtIRILITY 2.1 While construction activities remain in progress, the Field Construction Manager or his designated alternate (Contact GC Security for assigned alternate) have responsibilities and authority over the above personnel, General Construction visitors, and Security Force personnel assigned to construction activities.

In this capacity, he or his alternate will be designated as the Construction Force Assembly Coordinator with the following responsibilities:

2.1.1 Communicating with the Site Emergency Coordinator to determine the conditions of any Site Deersency. This communication is normally with the Unit I Security Buil-ding through the Shif t Security Supervisor.

2.1.2 Tranmitting information to Contractors and other construction force related persocnol.

2.1 3 Construction force assembly and personnel accountability at the site in the event of an energency and prior to any site evacuation.

2.1.4 Evacuation of construction force personnel frca the site as may be directed by the Site Emergency coordir.ater it.

cooperation with the Ivacuation Coordinator.

e DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-5 REVISION 3 1 DATE 10/14/85 PAGE 13 0F 13 I T8TLE EVACUATION OF NONESSENTIAL SITE PERSONNEL I

APPENDIX 2 (Cont'd) FIGURE 1

g EVACUATION ROUTES I

'% FOR ONSITE PERSONNEL

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assume Say

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STATE pman k s Paitspos

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. OtAsLO cANVON POWER PLANT UNIT NO($)1MD2 OE Uy REVISION 3 OATE 10/14/85 m ts.

EVACUATION OF NONESSENTIAL SITE PERSONNEL u

2.

Northern Route through Montana de Oro State Park If radiationanlevels undesirable, make alternate routethe use to the of isthe north southern evacuation available. route The routetowill road theinvolve park. traveling through private property up thfs (

L There are two locked gates and one normally unlocked gate which must be passed through on this route.

The locks are a combination security. type and the combination should be available from plant boundary gate may be cut and the gate re-secured with aIf t company lock.

State Park boundary can be obtained from people at the ranch ( orThe it may be similarly cut and re-secured.

The assembly point may be either the State Park parking area or preferably further north to the Morro Bay Power Plant and Switching Center via South Bay Boulevard to Highway 1, then exit at Main Street and enter the Switching Center gate off Main Street. These areas are also show on Figure 1.

CRITERIA FOR SELECTION OF EVACUATION ROUTE )

The southern route is the preferred route because the quality of the )

road is better, the route is shorter, the bulk of the southern route traverses land to which access is controlled by the Company, and because side of the theplant.

nomal onsite parking lots are located on the southern following circumstances:The southern route shall be utilized under the 1.

All evacuations where the dose rate is <500 mR/hr or the M.P.C.

concentration is <200 (i.e., all cases where the dose rates were not high enough to require imediate evacuation should be carried out over the southern route).

2.

All from evacuations the south. carried out when the winds are calm, variable, or 3.

Any time t't is raining (the northern road may be impassable under adverse weather conditions).

The or thenorthern southern routeroute shall is not be used passable when for any .he reason. above criteria are not met DC0100 12IV 6

~. _ _ _ _ _ . _ _ __

l

. DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-5 REVISION 3 DATE 10/14/85 PAGE 11 0F 13 TITLE EVACUATION OF NONESSENTIAL SITE PERSONNEL

,APPPENDIX 2 EVACUATION ROUTE DETERMINATION EVACUATION ROUTE DESCRIPTION I

There are two basic evacuation routes which may be utilized when an evacuation is required. The specific route to be followed shall be detemined by the Site Emergency Coordinator on the basis of wind direction, dose rates, and other pertinent factors existing at the time. These routes are shown on Figure 1.

Description of Routes and Assembly Areas

1. Southern Route to Port San Luis Gate The preferred route if evacuation from the site is required, is south along the access road to the Port San Luis Gate, and then to an appropriate assembly area. The assembly area will depend on the number of vehicles involved, the availability of space at the assembly area, and the extent of decontamination of vehicles anticipated. The suggested assembly areas in order of preference

( are:

a. PGandE Visitors' Infomation Center - room for around 60 cars, can be cleared out on short notice when open. A

" corporation key" is required to enter the parking lot at l

off hours,

b. Frontage Road along U.S. 101 north of Information Center -

room for several hundred cars, seldom used and easily controlled. Decontamination may require movement of vehicles into the Visitors' Center Parking Lot or the PSEA clubhouse parking lot.

, c. Port San Luis Parking bt - room for around 250 cars, l parking lot is crowded on nice days and during summer.

d. Parking ' lot behind Avila Beach Post Office - room for around 250 cars, is crowded on pleasant sumer days, but is empty most of the time.

I The general locations of these areas are shown in Figure 1.

DC0100 111V

otAat.O CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 NUMBER EP G-5 REVISION 3 DATE 10/14/85 PAGE 10 0F 13 TITLE EVACUATION OF NONESSENTIAL SITE PERSONNEL APPENDIX 1 (Cont'd)

The decision to evacuate or not must include the following considerations:

a. Whether or not the emergency can be mitigated prior to a dose of 500 mrem or 200 MPC-hrs. being reached.

b. If personnel involved are not imediately essential for ,

handling the emergency, they should be evacuated at levels near the low end of each range to minimize their doses.

This will prevent giving unnecessary doses to personnel who may be needed for assistance later in the emergency.

c. Any time personnel are to be evacuated, the dose expected .

during evacuation must be weighed against that expected if the person is not evacuated. In some cases, (i.e.,

personnel assembled in access control, or the security building) evacuation may give personnel a higher dose than remaining in a shielded or protected area.

d. Depending on conditions, the Site Emergency Coordinator may y )

elect to allow selected personnel to exceed those guidelines j to accomplish critical actions.

2. Radiation Workers Not Engaged in Recovery Actions In general, nonessential radiation workers should be evacuated right along with nonradiation workers in the event of a general site evacuation under the provisions of 1 above. If their assistance is anticipated to be required, these persons should not be allowed to exceed their occupation quarterly or annual exposure Ifmits (3 rem W8 or 5 rem thyroid per quarter, 5 rem WB or 15 rem thyroid per year). Since many of these persons will have received some occupational exposure prior to the accident, the maximum" exposure which can be permitted may vary depending on the date in the quarter and the exposure history from one person to another. Therefore, the considerations of b and c above must be' weighed in the decision.

Essential radiation worker may be authorized to receive exposures in excess of established quarterly and annual limits. -The Site Emergency Coordinator has the sole onsite authority to authorize emergency exposure limits. However, if time permits, such authorization should be made by the Corporate Recovery Manager.

DC0100 10!V i

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DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ff0N DATE 10/14/85 PAGE 9 0F 13 TITLE. EVACUATION OF NONESSENTIAL SITE PERSONNEL APPENDIX 1 EVACUATION CRITERIA The decision to evacuate any, or all, of the personnel covered by this procedure shall be made by the Site Emergency Coordinator.

Personnel shall not evacuate an assembly area unless instructed to do so by the person in charge in the area, and this individual shall, in turn, receive his instructions from the Site Evacuation Coordinatorl who, in turn, receives instructions from the Site Emergency Coordinator.

1. Unit 2 Construction Personnel, Visitors, Clerical Plant Personnel (Nonradiation Workers)

In keeping with " low as reasonably achievable" philosophy, .

personnel who are not contributing substantially to recovery actions (which generally includes visitors, contractors and clerical personnel) should be evacuated if such action can prevent significant exposure, provided that trained personnel are available to conduct the evacuation and can be spared for this task without jeopardizing accident mitigation activities.

( However, the following should be considered as upper limit evacuation criteria:

^

CONSIDER AIRBORNE EVACUATION WHOLE BODY DOSE RATE ACTIVITY CONCENTRATION 2 WITHIN 2-10 arem/ hour 1-4 x MPC 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 10-50 mres/ hour 4-20 x MPC 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 50-100 mrem / hour 20-40 x MPC 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 100-500 mres/ hour 40-200 x MPC 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 500 mrea/ hour 200 x MPC Immediately 1The person in charge in an assembly area may order the movement of personnel from an assembly area to prevent injury to the assembled personnel. This action shall be reported to the Site Emergency Coordinator as soon as practical.

2Where MPC is the maximum permissible concentration for areas as defined in Column 1. Table I, Appendix B to 10CFR20. This calculation will allow 200 MPC-hrs which conservatively limits internal exposure. This criteria is based on personnel not wearing respiratory equipment.

DC0100 91V

a 1

01A8LO CANYON POWEM Pt. ANT UNIT NO(S) 1 AND 2 NUMBER EP G-5

i

REVISION 3 i DATE 10/14/85 PAGE 8 0F 13 TITLE; EVACUATION OF NONESSENTIAL SITE PERSONNEL

b. If public parking lots are utilized as evacuee assembly areas, and the lots cannot be completely cleared prior to arrival of evacuees, the owners names and/or vehicle license numbers of cars still in the lot will be recorded and the vehicles will be surveyed before being allowed to leave.

c. As a minimum, the names and addresses of any evacuees suspected of having received doses in excess of 250 mR and those requiring any decontamination shall be obtained before the persons are allowed to leave the assembly area,

d. In general, personnel shall be given permission to leave the assembly are only after the following conditions are met:

1) The person and his vehicle have been surveyed or a sufficient .4 umber of persons in the group have been ."

surveyed in order to determine that radioactive -

contamination is not a factor.

2) Self-reading dostmeter results have been recorded and the naams of exposed persons recorded.

3) The above results have been reported to the Site )

Emergency Coordinator for his evaluation. /

APPENDICES .

1. Evacuation Criteria

2. Evacuation Route Determination ATTACHMENTS

1. PI-39 Personnel Accountability and Site Evacuation During a Site Emergency

2. Form 69-9310. " Post Evacuation Vehicle Monitoring Data"

3. Fons 69-9311; Evacuee Monitoring Data" SUPPORTING PROC'EDURES G-3. " Notification of Offsite Emergency Organizations" G-4, " Personnel Assembly and Accountability" ~

1 j

OC0100 8IV

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. Diasto CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 10/14/85 PAGE 7 0F 13 TITLE. EVACUATION OF NONESSENTIAL SITE PERSONNEL

6. Determine from the Site Emergency Coordinator if site assistance is requested by the County to notify members of the general public along the north access road. If assistance is requested, dispatch a second vehicle along the north access road to notify members of the general public of the evacuation ard their .

assembly area as designated by county personr.e1. If the north road is to be used as the site evacuation route, they should be so informed by the lead vehicle. If conditions warrant, a qualified monitor should be assigned to this vehicle to monitor personnel and their vehicles.

g: There are dwellings occupied along this road between the plant site and Montana de Oro State Park,

7. Inform each evacuation leader of the following: ,

a. Route to follow

b. Offsite assembly area

c. Onsite traffic pattern (one or two lane egress)

( d. Sequence of evacuation (generally this will be 1) warehouse area, 2) General Contractor (G.C.) parking lot, 3) Training Building.

e. Instructions for personnel evacuating. These generally are:

1) Proceed in caravan fashion along the designated route i

to the offsite assembly area.

l

2) Personnel without transportation should obtain a ride l

with a driver in their assembly area. Arrangements to get home can be made at the offsite assently area.

3) At the offsite assembly area, each assembly area evacuation leader should assure that personnel are

, accounted for, and remain to be monitored and cleared before release.

l

( 8. Activities at Assembly Area j' a. Upon arrival at the evacuation area, the monitor (s) shall begin a program of surveying personnel and vehicles for contamination. The results should be recorded on Form 69-9310 and 69-9311, and the overall results should be reported to the Site Emergency Coordinator.

I j DC0100 71V

\

l otAeLoi:ANYON POWEQ PLANT UMT 1 AND %S) 2

[0N

~

DATE 10/14/85 in12. PAGE 6 0F 13 '

EVACdATION OF NONESSENTIAL SITE PERSONNEL 1.

Contact the Emergency Radiological Advisor (or Emergency Evaluation monitoring and perso Recovery Coordinator) and assure that qualified assembly area (s)nnel are dispatched to monitor at the offsite (either from onsite or offsite).

monitor for each major assembly area will be utilized. Generally one should accompany each group if dispatched from onsite. Monitors Monitors or the Assembly Area Leader should be equipped with permanent and self-readin evacuation,g dosimeters to determine doses received during g:

Operations personnel assembled in the Training Building may be assigned monitoring duties if not otherwise needed onsite.

2.

each Unit I assembly area to move personnel to be eva =P the, Training Building. Personnel to remain onsite should generally be located at the Security Building Ready Room.

3.

Appoint an evacuation leader for each major assembly The area.

Construction under his control. Force Assembly Coordinator will assist for areas frequency portable radioThe leader should be provided a plant if not already equipped. Generally, )

the upper parking lot, and 3this will provide a super, visor for 1) the Trainin ';

assembled at all of these are)as.the warehouse Notify the Emer area if personnel are Coordinator of the leader assigned to each area. gency Liaison 4.

Send one assembly emergency area. kit or one evacuation kit to each offsite These may be dispatched with the vehicles evacuation group. 5 and 6 or may be sent with the lead described in steps E: Additional emergency kits are located at the Information Center, and Morro Bay Power Plant and SLO Sheriff's Offfee.

5.

Dispatch a vehicle to clear the south access road of any personnel working along the road, or farm workers.

i If conditions l warrant, e qualiffed monitor should be assigned to this vehicle

< to monitor these personnel and their vehicles.

This vehicle should proceed to the offsite assembly area for traffic control.

~

DC0100 6IV %

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, -, --m , . - - - , , -e - pm.-

DIA8tO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP G-5

, , REVISION 3 DATE 10/14/85 PAGE 5 0 F, 13 TITLE: EVACUATION OF NONESSENTIAL SITE PERSONNEL

5) The anticipated need for decontamination of personnel or vehicles and whether any assistance required for this function (fire trucks or medical assistance) will be involved at the assembly area.

6) Any assistance needed to monitor and/or decontaminate farin workers, or other visitors at the assembly area POTE: All notifications should be logged on Fom 69-9221

" Emergency Notification Record."

5. If the PGandE Infomation Center is to be used as an assembly area, the Director of this facility should be notified (during hours it is open) so that this person can begin clearing the parking lot. When this facility is closed a corporation key may be used to gain access to the parking lot. -

6. Determine the personnel to be retained onsite and personnel to be assigned to offsite emergency response locations or relief shift duty. In general personnel retained onsite will have chemistry and radiation protection, maintenance or clerical assignments for the site emergency organization.

I

7. Provide evacuation instructions to the Evacuation Coordinator.

These instructions should include:

a. Evacuation route

b. Offsite assembly area

c. Anticipated vehicle or personnel monitoring and decontamination requirements.

d. Arrangements with offsite response agencies.

e. Personnel to remain onsite.

GUIDANCE FOR THE EVACUATION COORDINATOR The Evacuation Coordinator, after receiving instructions on the evacuation route and assembly location from the Site Emergency Coordinator, shall:

DC0100 SIV

.,-o -, __ - , _ _ . _ , . . - _ . _ . -

m - --

otAato CANYON POWER PLANT UNIT NO(S) 1 AND 2

, ON DATE 10/14/85 PAGE 4 0F 13 TITLE. EVACUATION OF NONESSENTIAL SITE PERSONNEL

3) Notify guard force to direct traffic on and off of the site to assure that personnel stay on the proper ,

evacuation route and that members of the general public i do not get involved unnecessarily.

e. Connunicating with the Emergency Radiological Advisor (or the Emergency Evaluation and Recovery Coordinator) to obtain qualified personnel to direct monitoring and/or decontamination at the offsite evacuation assembly area.

3. The Site Emergency Coordinator will designate the evacuation route and offsite evacuation assembly area. Appendix 2

" Evacuation Route Determination" provides guidance in this detennination.

g: If possible. San cuis Obispo County Emergency Organization should be consulted prior to implementation.regarding traffic control problems or impediments on the evacuation routes.

4. The Site Emergency Coordinator will direct notification of the ..

San Luis Obispo County Sheriff's Office or San Luis Obispo County )

Emergency Operations Center (if activated) of the evacuation. i This notification should include the following infonnation: >

a. Update on plant emergency status including the information on Form 18-10262 " Radiological Emergency Status Form." (See Emergency Procedure G-3, " Notification of Offsite Emergency Organizations.")

g: The status information should permit determination of the need for protective actions for the general public in the near site area.

b. Notification of the intent to evacuate personnel including:

1) The intended evacuation route

2) The designated offsite asses 61y area

3) The need for traffic control or clearing of parking areas

4) The approximate number of personnel and vehicles to be evacuated ~

DC0100 4IV

$ - - - - -- - . . , ,wy w, - ---.- + . + ., -,

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. DiAeLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

((0N i DATE 10/14/85 PAGE 3 0F 13 TITLE EVACUATION OF NONESSENTIAL SITE PERSONNEL GUIDANCE FOR THE SITE EMERGENCY COORDINATOR

1. The Site Emergency Coordinator will assess the need for, or the

. potential need for, evacuation of nonessential personnel.

Appendix 1 " Evacuation Criteria" provides guidance in making this determination for radiological emergencies. Generally evacuation will be conducted for incidents at the Site Area Emergency or General Emergency Classification Levels regardless of whether a release is occurring. The assessment for radiological emergencies may be delegated.

2. The Site Emergency Coordinator will assure an Evacuation Coordinator is available to supervise the evacuation. The person assi preference)gned will beon

depending one of the following availability and whether (in order a security of event is contributing or the cause of the emergency

a. Security Supervisor

b. Senior Security Shift Supervisor

( c. Security Shift Supervisor

! d. Senior Power Production Engineer (Emergency Planning)

The responsibilities of the Evacuation Coordinator are as follows:

a. Communicating with the Site Emergency Coordinator to determine the conditions of the emergency and the evacuation plan,

b. Providing information on the number of vehicles and personnel involved in the evacuation and any further personnel accountability required at the site prior to the evacuation,

c. Transmitting information to assembled personnel and l coord.inating the evacuation with General Construction.

l

d. Providing required onsite traffic control measures such as:

1) Notifying Avila Gate of the evacuation.

i

2) Sequencing the depa~rture of personnel to avoid i congestion.

1 -

DC0100 3IV

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i DIA8LO CANYON POWER PLANT UMT NO(S) 1 AND 2 o .

S ON DATE 10/14/85 PAGE 2 0F 13 m LE. EVACUATION OF NONESSENTIAL SITE PERSONNEL .

M: This procedure is intended to apply to evacuations where persons may receive abnormal external exposure and/or persons <

or automobiles may be contaminated (i.e., a release above rechnical Specification limits has occurred). It is recognized that in the event of an emergency it may be desirable to send persons home before they are exposed to significant radiation and/or contamination levels. A case of this nature would be handled as an early dismissal from work. The provisions of this procedure for offsite assembly are not required in such a case. (items 2e, 5, portions of 3 and 7 under " Guidance for the Site Emergency Coordinator" and items 1, 3, 4, 7, 8 under

" Guidance for the Evaluation Coordinator"). The term "early dismissal" instead of " evacuation" may be used for such a case.

INITIATING CONDITIONS ,

', The Shift Foreman declares that the plant is in an emergency condition (Unusual Event. Alert, Site Area Emergency or General Emergency) or detemines that personnel assembly and accountability are desirable, and sounds the site emergency alam.

1 Personnel on site will assembly at their designated assembly areas following sounding of the site emergency alam in accordance with )

2 Emergency Procedure G-4, " Personnel Assembly and Accountability." )

This action will result in essentially all personnel onsite assembling in one of eight locations.

1. Control Room

2. Technical Support Center

3. Cold Machine Shop l 4. Radiation Access Control l

S. Security Building l 6. Training Building

7. Biology Lab

8. Contractor and Site Visitor Assembly Areas r

A list of plant staff personnel assembled in, or ad,Jacent to,' Unit 1 l

will be developed as will a list of unaccounted for personne1

' assembled in the contractor and visitor assembly areas in accordance

' with Emergency Procedure G-4, " Personnel Assembly and Accountability."

l l

DC0100 2IV P

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. - - - - --- z - - . . . _ _ _ - _ _ - _ . - - __ --

NUMBER EP G-5 o . 7G5143 Pacific Gas and Electric Company REVISION 3 pum DATE 10/14/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS I I PAGE 1 0F 13 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE j TITLE. EVACUATION OF NONESSENTIAL SITE PERSONNEL APPROVED- YS U ~

SAF -

PLANTMANAGy DATE SCOPE This procedure provides guide 51ne infor1 nation pertinent to evacuation of onsite personnel including Company, contractor, and visitors, who are not engaged in recovery actions following an emergency. This l procedure and changes thereto require PSRC review. ,.

GENERAL In the event of an emergency situation at Unit 1, it may be desirable to minimize the number of nonessential personnel onsite. If the emergency involves a radiological release or the potential for a g release then evacuation of nonessential personnel is desirable, or may be required, to minimize exposure to radioactive material.

The organization of this procedure provides guidance in three distinct areas: 1) Determination of the need for. site evacuation,

2) detemination of the evacuation route and assembly area, and 3) conducting the evacuation and subsequent assembly, monitoring and release of personnel in an orderly manner. The first two of these areas era orovided in the section " Guidance for the Site Emergency Coordinator". The latter is provided in the section " Guidance for the Evacuation Coo *dinator".

This proc <soure assumes the emergency occurs during nomal working hours when the greatest numbers of nonessential personnel are onsite.

It is also applicable however, during off-normal hours, weekends and holidays.

I l

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1 I ,

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l DC0100 IIV l

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p y . , - . -, - - . - - - - -

k Form et-10296 g/81(100) Status # '

Date: / / Part 8: Onsite/Offsite Radiological Field Monitoring and Plc fuergency Status Form .

Sheet I olT .

Location '

Time Data Collected .

a.m. a.m. a.m. a.m. a.m. a.m.

p.m. p.m. p.m. p.m. p.m. p.m.

Team _R/br R/hr R/hr _R/hr _R/hr _R/hr a PIC cpu cpm cini cgia cpm cpm 3 3 3 pCf/cg pCl/ce i.C l i.Cl/cq pCl/c,3 pCl/c ,3 pCf/m pCl/mZ pCI pCl/sc pCl/m2 ocl/mc pct /gm pCl/gn pCl/gm pCl/gm pCl/gm pCl/gm a.m. a.m. a.m. a.m. a.m. a.m.

p.m. p.m. p.m. p.m. p . m .* p.m.

Team ,

_R/br _R/hr R/hr R/hr R/hr R/hr Plc cpm cpm cgui cgmi 3 3 cini cgmi pct /cg pCl/ pCl/ca' pCl/ pCl/ 3 pCl/mc pCl/ pCl/m2 pC1/ pCI/ pCl/cg pCi/m pCi/gm pCl/gm pCl/gm pCl/gm pCl/gm -

pCl/gm a.m. a.m. a.m. a.m. a.m. a.m.

p.m. p.m. p.m. p.m. p.m. p.m.

Team _R/hr _R/hr _R/hr _R/hr _R/hr _R/hr PTC com 3 cp cp cgia cpm cpm 3 3 3 pCI/cg 901/ pCI/cq i.Cl/cq pCf/cm 3 pCl/mc pct / pCl/mc pCf/mc pct /m' 901/c!

pCl/m pCl/gm pct /gm pCl/gm pCl/gm pCl/gn pCl/gm a.m. a.m. a.m. a.m. a.m. a.m.

~

p.m. p.m. p.m. p.m. p.m. p.m.

_R/hr Team _R/hr PIC

_R/hr _R/hr R/hr R/hr cpm cpu cpm cgia cgui cgui 3 3 3 3 pCl/cg pCl/cg pCl/cq pct /cq pCl/cq 3 3 pCl/mF pCl/ac pC1/mz pCf/mc pCl/mc pCl/c!

pcl/gm sci /m pC1/p act/gm pcl/ spa pCl/p pct /g=

I

- . a.m. a.m. a.m. a.m. a.m.

p.m.

a.m.

p.m. p.m. p.m. p.m. p.m.

Team _R/br _R/hr _R/hr R/hr R/hr

~

_R/hr PTC com cgia cgia cgmi 3 cgmi cpm pCl/cg pCf/cm3 pCl/cg 3

pCl/cg 3 3 -

pCl/cm 3 pCl/mc pCl/m2 pCl/cg pCl/m' pCf/m' pCf/m-

~

pCl/m2 1

pC1/gm pCl/gm

, pCl/gu pCl/gm pCf/gm pCf/gm i Data Transmitted Ry: DISTRIBilTION LIST This Data Sheet Filled Out Ry: TSC Dist. (5) EOF Dist. (6) EOF Status File Udle: Time

Site Emerg. Coord. Rec. Hgr. E0F Emerg. Status Ril.

a.m._ J.M. Emerg. Rad. Advisor Rad. Emerg. Rec. Mgr.

ISC File llDAC ISC Status 8d. Adv. To County Emerg. Org.

69-10295 7/82 (100) Page 3 of 3 TITLE: PLANT STATUS EMERGENCY FORM

8. Steam Generators:

a. Level: 1 %2 %3 1 4 %

b. Pressure: 1 psig 2 psig 3 psig 4 psig l

c. Auxiliary Feedwater Pumps On: [] Turbine []2[]3 Total gpm:

d. Feedwater Source: [ ] Cond Tk % [ ] Raw Water %

[] Fire Water %

e. Steam Dump: [ ] Atm [ ] Condenser

f. Safety Valves Closed: []1 []2 []3 []4

g. MSIV's Closed: []1 []2 []3 []4

h. Est. Primary to Sec. Leakage: apm Cooling:

a. CCW Pumps Flow, gpm: 1 2 ,3

b. ASW Pumps On: []1 []2

10. Electrical:

a. 4KV Bus Energized: []F []G []H g,f b. Offsite Power Available: []YES []N0

c. Diesel Generators On: []1 []2 []3

11. Other Information:

i Data Received By:

Date / / Time AM/PM RETAIN THIS FORM FOR EVENT EVALUATION i

s d

OC0042 12 XVII

69-10295 7/82 (100) Page 2 of 3 TITLE: ' PLANT STATUS EMERGENC'r FORM

c. RCP Running: []1 []2 []3 []4

d. IncoreThermocouple(s): F Hottest, F Average 8

e. Reactor Vessel Level: %

f. Boron Concentration: ppm

g. Margin to Subcooling: degrees F

h. RCS Activity Sample Available: [ ] YES Activity uci/cc[]N0

1. RV Head Temp. F

5. Pressurizer:

a. Level: %

b. PORV/ Safety Valves: []Open [] Closed

6. ECCS:

a. Operating: []Yes []No Letdown Flow, gpm.

VCT Level, %

b. Actuation Auto Man,

c. Cent. Chg. Pumps On: []1 []2 Total gpm:

d. SI Pumps On: []1 []2 Total gpm:

e. RHR Pumps On:

[]1 RHR Disch. Temp. F.

[]2 Total gpm:

f. Accumulators Discharged: []YES []NO

g. Mode: []InjectRWST % [] Recirculation % Contmt. Level

7. Containment:

a. Pressure / Temperature / Humidity: psig/ F/ dew point

b. Containment Isolation: []Ph.A []Ph.8

c. Integrity:

d. Containment Spray Pumps On: []1 i

[]2

e. Fan Coolers On: []1 []2

[]3 []4 []5

f. Rad Monitor: R/hr (Hi Range) l

/ mR/hr (Entry / Seal Table)

DC0042 11 XVII l

l l

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

69-10295 7/82 (100) Page 1 o' 3

' PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: PLANT STATUS EMERGENCY FORM Provide as much infonnation as is available and appropriate at the time of the status report.

Date: __,

/ / Time: AM/PM Status Report #

(Form Completed) (Number Sequentially)

[ Person Authorizing Report:

(DCPPonly) 51te Emergency coordinator Person Transmitting Report: Location (DCPPonly)

TSC 0157: 9 COPIES EOF DIST: 10 COPIES

1. Site Emergency Coordinator 1. Recovery Manager

2. Emergency Evaluation & Recovery Coord. 2. UDAC

3. Emergency Liaison Coordinator (2) 3.

4. Emergency Maintenance Coord.

Advisor To The County

4. Radiological Emerg. R.M.

5. Emergency Operations Coordinator S.

6. Emergency Radiological Advisor Operations and Analytical M.

6. Engineering and Logistics M.

7. NRC Office 7

8. TSC File Pubite Infonnation M.

8. Corporate Law Dept. Coord.

9. TSC Status Board 9. E0F Status File

10. EOF Emerg. Status Board

1. . Emergency Classification: ; ; Unusual Event [

General Emergency] Alert []SiteAreaEmergency Time Data Collected: AM/pH

2. Plant Status -

Description:

i i

! 3. Reactor Status: [] Unit 1 [ ] Unit 2 (Provide a separate fonn for the other unit)

a. Power Level: Before 5 Current % Power Range amp Int. Range f Source Range 4

b. Fuel Damage: []None [] Minor [] Major

, 4. Reactor Coolant System:

P

a. Pressure: osig Est. RCS Leakage opm. where .

-b. Loop Status 1 2 3 4

Temp. (hot / cold) F / / / /

Flow %

DC0042 10 XVII 1

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69-10262 7/84 RADIOLOGICAL RELEASE STATUS PERSON AUTHORIZING REPORT PERSON ORIGINATING REPORT AND LOCATION DATE TIME AM PM STATUS #

IhERGENCY CLAS5IFICATION UE L j ALERT L j RELEASE: OCCURRING 5AE L J GE L j ANTICIPATED NONE WHEN AM PM LOCATION OF RELEASl: PLANT VENT STEAM SURFACE LIQUID DISCHARGE EST. DURATION OF RELEASE: HC INCIDENT TIME / DESCRIPTION:

NOBLE GA5E5: C1 Ci/Sec 10 DINES: Ci Ci/Sec PARTICULATES: Cf C1/Sec BASIS FOR RELEAME CALC.

MtIEOROLOGICAL DATA (U5E 10m ELEVATION ON PRIMARY MET TOWER OR DESIGNATE OTHER SOURCE IF USED):

WIND SPEED: M/SECx(2.2)= MPH DIRECTION (FROM): deg.

STABILITY class (VERT.) SIGMA A (DEG): AT: C/M (HORIZ.) x 800m = MIIING DEPTH M U

WEATHER CONDITIONS: RAIN / CLEAR / FOG / CLOUDY CENTER LINE DO5E RATE INTEGRAIED 005E DOSE PROJECTIONS W.8. THYR. W.B. THYR. AFFECTED PROJECTION TIME: n>R 'HR mR SECTOR /PAZ 5ITE BOUNDARY (0.5mt) s.. 2 MILES 5 MILES 10 MILES 15 MILES

- PG&E RECunntNDED EMERGENCY ACTION /PRUIECTIVE MEASURE 5 TO 5LO CDUNTY:

- EMERGENCY RE5PON5E ACTIgns UNDERWAY BY PGAE:

- EMERGENCY RE5 PUN 5E ACTION 5 UNDERWAY BY SLO COUNTY:

- FROGN05I5 FOR ESCALATION OR TERMINATION OF ACCIDENT:

COMMENTS:

OC0042 13 XVII ,

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i 69-10581 4/85 (100) Page 2 of 2 TITLE: INITIAL EMERGENCY NOTIFICATION FORM Message Classification (for SLO County / Calif. OES) ,

[C] Site Area Emergency Insnediate mobilization of emergency (Consider protective actions response personnel is required.

[B] or [C]) PGandE is activating the EOF.

[0] General Emergency Insnediate mobilization of emergency (Recommendprotectiveaction[0] response personnel is required.

or [E]) PGandE is activating the EOF.

7. Affectedsector[checkone)-WindSpeed mps(x2.2)= mph [Completecalculation]

WIND FROM WIND TOWARD AFFECTED DEGREE 5 DIRECTION AFFECTED SECTOR PAZ's (Basic EPZ)

'A'-----------349-11-----------N-------------------S----------

'B' ----------- 12-33-----------NNE-----------------SSW--------

,C, ----------- 34-56-----------NE------------------SW---------

,D ----------- 57-78-----------ENE-----------------WSW--------

,'E[----------- 79-101----------E-------------------W----------

F ----------102-123----------ESE-----------------WNW-----1,2

,G, -----------124-146----------SE------------------NW------1,2

,H, -----------147-168----------SSE-----------------NNW-----1,2.5.9

,I,

169-191----------5-------------------N-------1,2.5.9

. f, ---------- 192-213----------SSW-----------------NNE-----1,2,5,9 K ---------- 214-236----------SW------------------NE------1,2,4,8

,L, -----------237-258----------WSW-----------------ENE-----1,2,3,4,8

,M, -----------259-281----------W-------------------E-------1,2,3,4.7.8.11 , ,

. ;N; -----------282-303----------WNW-----------------ESE-----1,2,3.6.7,10,11,12 N.

0 -----------304-326----------NW------------------SE------1,2,12 lP-----------327-348----------NNW-----------------SSE--------

8. Recommended General Public Protective Actions (Refer to Table 1 and Figure 1ofEPG-3)[Checkone]

[A]None

[B] Evacuation of the site, and PAZ 1. [ConsidernotifyingU.S.CoastGuard per EP G-3 pg. 3]

[C] Evacuate transients (Montana de Oro visitors, agriculture workers, etc.)

in the low population zone (PAZ's 1 and 2) starting with the affected sector and two adjacent sectors.

[D] Evacuate the low population zone (PAZ's 1 and 2)) starting with the affected sector and two adjacent sectors.

Alert the public in the basic emergency planning zone using the Early Warning System Sirens and EBS Broadcasts. [ConsidernotifyingU.S.

Coast Guard per EP G-3 pg. 3]

[E] Take actions specified in [D] and shelter personnel in the affected sector ar.d two adjacent sectors in the basic EPZ.

~~ ~ ~ - - ~ -~ -

YETATflWIT 70NCFUR ETENT EVATlMTON - - - -~ - - - - - - - - - - - -

DC0249 741

a 69-10581 4/85 (100) Page 1 of 2 PAC 8FIC GAS AND ELECTRlC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: INITIAL EMERGENCY NOTIFICATION FORM Date / / Time AM/PM Status #

(Form completed) (Number Sequentially)

Person Authorizing Report (DCPP Only)

Site Emergency coordinator Data Sheet Completed By (DCPP Only)

-Identify yourself, state the call is to provide notification of an emergency condition at Diablo Canyon Power Plant, and provide the following infomation:

1. Describe what happened:

2. Unit Involved [A] 1 [8] 2 [NRCONLY: Docket # Unit 1(50-275) Unit 2(50-323)]

3. Time emergency declared AM/PM

4. Situation Involves [Checkone]

', [A] No Release [C] Inninent Release [E]Releasehasoccurred.

[8] Potential Release [D]ReleaseisOccuring

5. Offsite Assistance [Checkone]

' Fire Cal. Dept. of Forestry) 'AN Has been requested MedTTaT ( (SLO Ambulance / French l8[ Hospital)

Has been requested Law Enforcement (SLO County Sheriff) ,, Is/has been requested None

6. ,.

Emergency Classification - Provide standard message or m1dify as required by the j situation. Note any modification made. [ Select one]

l Message Classification (for SLO County / Calif. OES)

[A] Unusual Event Notification of key emergency organization personnel is required at this level, but l no further response is necessary.

I i

l

[B] Alert Notification of all emergency response organizations and activation of the EOC and other response centers is required.

PGandE is activating the EOF.

OCO249 73I

10/85 Page 1 of 1 -

l

' ATTACHMENT 3 RECOVERY MANAGER MOBILE PHONE AND PAGER INSTRUCTIONS

l. Mobile Phone Instructions RecoveryManager'smobileradiotelephonenumbeb

a. Dial "0" for operator and ask for the Nobile Conference Operator; then 9.ve the phone number and general location f aytomobile.

When calling from within General Office, dia nd ask PGandE operator to connect with PT&T operator and repeat as above. ,

l

2. Pager Instructions--Nuclear Power Generation

a. Message to be left with the General Office Communications PBX Operator (short tone):

Cal ahd request that the particular indi-vidua / beeper code paged. Leave message with operator for the individual you are paging. The Communications PBX Operator will activate the radio pager rce that individual by dialing the unique PT&T number (50 mile radius of San Francisco) pager or the extended coverage PT&T number (if in San Luis Obispo area) assigned to that pager,

b. Message to be left with the Intrastate Radio-Telephone Comercial Message Operator (long tone):

CaH request that the particular beeper code b be paged. Leave message with operator for the individual you are paging.

c. If you want both short and long tones to be paged for one beeper, you may request the operator in Step 2.a above to pass the message to the operator in Step 2.b above, or vice-versa. Both operators are capable of paging in either tone. The type of tone denotes where the person being paged is to call to receive his message (s).

Unique Extended Coverage

d. Name Beeper Code PT&T Number PT&T Number

. V. .

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DC0042 8XVIII s

4

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(.

TABLE 1 page 1 of_1 PG and E Recommended Initial General Public Protective Action Criteria

Emergency

Classification 3 Releasg Site Appropriate Recommended Status Boundary Dose 3 1 Initial Protective Action 4 A-Unusual Event All NA None

8-Alert All NA None

, C-Site Area Emergency All

<500 mR (Total W.B.) None i "

B-Potential Release >500 mR (Total W.8.)

i C-Evacuate transients I

(Montana de Oro Visitors, agricultural workers, etc.) in

, the low population zone (PAZ's l I and 2) starting with the affected sector and two adjacent sectors.

f "

C-leninent Release "

1 or 8-Evacuation of the Site, and I PAZ l.

D-Release is Occuring l

E-Release has Occurred but "

None stopped D-General Emergency A-No Release NA I

or D-Evacuate the site and low 8-Patential Release population zone (PAZ's I and 2) starting with the affected secter and two adjacent

' sectors. Alert the public in i the ba-ic emergency planning '

zone using the Early Warning System Sirens and E85 Broadcasts.

E-General Emergency C-Imminent Release NA or D-(as above) and shelter D-Release is Occuring personnel in the affected or sector and two adjacent sectors

! to the boundary of the Basic E-Release has Occurred but EPZ. Specify a further stopped distance from the plant if a total dose >500 mR is projected at further distances.

1. Refer to item 6 of Form 69-10581.

2. Refer to item 4 of Form 69-10581.

3. Calculate in accordance with EP R-2,

4. Refer to item 8 of form 69-10581.

t DC0042 7 XVII

oi4aLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 10/8/85 PAGE 5 0F 6 TITLE. NOTIFICATION OF 0FFSITE ORGANIZATIONS 4.

Status updates to San Luis Obispo County will be provided by the EOF once it is manned in accordance with Emergency Procedure EF-3 i

" Activation of the Emergency Operations Facility." Updates to California OES and NRC will continue from the TSC until these organizations establish their own communication channels and no longer need status reports.

@E: Changes in emergency classification or information on the estimated potential for time of or extent of a release i will be innediately provided to offsite organizations when authorized.

5.

Status reports to other organizations on Form 69-10298 are only required as determined necessary by the Site Emergency Coordinator for the organization to provide their support function. .

RECOR0 KEEPING All records generated by the utilization of this procedure for an exercise or emergency shall be forwarded the next working day to the Assistant Plant Manager / Support Services for review and retention.

i

, 1. Records generated from exercises will be categorized as non permanent and retained for a minimum of five years.

2. Records generated from actual emergency events will be categorized as lifetime and placed into lifetime storage in accordance with procedure " Requirements for Retention and Extended Storage of Operation Phase Activity Records (AP E-151)."

ATTACletENTS 1.

Table 1 - Initial General Public Protective Action Criteria.

la. Figure 1 " San Luis Obispo County Protective Action Zones and 1

Sectors from Plant"

2. Form 69-10298 " Emergency Offsite Organization Call List"

{ 3. Mobile Phone and Pager Instructions

4. Form 69-10581 " Initial Emergency Notification Form" J

DC0042 SXXI I

_ _ _ _ , . _ , , _ _ _ . . _ . - - . - - - - - - - - - - - - - - - - - - - ~ ~ ~ ' - - - ' ' ~ - ' - ~ ~ ~ ~ " ' ' ' ~

DiAst.o canyon POWER Pt. ANT UNIT No(S) 1 AND 2 f5ON DATE 10/8/85 PAGE 6 0F 6

, Tm.E. NOTIFICATION OF 0FFSITE ORGANIZATIONS

5. Form 69-9221 " Emergency Notification Record"

6. Fom 69-10262 " Radiological Release Status"

7. Fom 69-10295 " Plant Status Emergency Form"

8. Fom 69-10296 "Onsite/Offsite Radiological Field Monitoring and PIC Emergency Status Form" SUPPORTING PROCEDURES

1. EP G-1, " Accident Classification and Emergency Plant Activation"

2. EP EF-1, " Activation of the Technical Support Center"

3. EP EF-3, " Activation of the Emergency Operations Facility".

4. EP R-2, " Release of Airborne Radioactive Materials"

5. AP C-1152, " Supplement 2 to Non-Routine Notification and Reporting to the NRC and Other Governmental Agencies"

}

J" DC0042 6XXI ,

d oiAaLO CANYON POWEA PLANT UNIT NO(S) 1 AND 2 ON DATE 10/8/85 PAGE 4 0F 6 TITLE. NOTIFICATION OF 0FFSITE ORGANIZATIONS In the event a Site Area Emergency (with reconmendation for evacuation) or General Emergency is declared, and the reconnendation for protective action is made within 30 minutes of the initial notification of the emergency condition, the Shift Foreman or the Interim Emergency Liaison Coordinator will call the 24-hour USCG (Marine Safety Office) phone 415/437-307j3 and alert them to PGandE's recomunendations for protection actions. The USCG should also be infomed that San Luis Obispo County has been infomed of the recomunendations and will be calling with a request for assistance with the offshore areas in the vicinity of the plant.

SUBSEQUENT ACTIONS

1. A verbal sununary of actions taken to close out an Unusual Event shall be provided each organization notified by the Site Emergency Coordinator or his designated representative.

2. Isunediate notification of an increase in emergency classification .)

or increase in the potential for a release shall be made to San Luis Obispo County. Status updates should be provided approximatelf every 30 minutes to each organization, for an Alert or higher classification, until the E0F and TSC are manned.

3. Wien personnel are available the TSC will be activated for an Alert or higher classification according to EP EF-1, " Activation of the Technical Support Center." The Emergency Liaison Coordinator shall man his post in the TSC Operations Center and assume responsibility for contact with off-site emergency organizations from the interim Emergency Liaison Coordinator in the Control Room.

i

)

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1 i

DC0042 4XXI s

- , - - <w-,, ,, , , _ , - - - - - - , , .-e-- - - -

DiAaLO CANYON POWED PLANT UNIT NO(S) 1 AND 2 ON DATE 10/8/85 PAGE 3 0F 6 T Ttt NOTIFICATION OF 0FFSITE ORGANIZATIONS

8. Primary position holders of certain emergency response positions are provided with VHF radio-equipped company vehicles. Because these persons are essentially on-call at all times, use of these vehicles is warranted in off hours to ensure rapid connunication and response. These personnel are identified in Attachment 3 and 4

in the call list for on-site personnel in G-2.

9. Per Administrative Procedure AP C-1152, " Supplement 2 to Non-Routine Notification and Reporting to the NRC and Other

' Governmental Agencies", use of any emergency procedure which results in declaration of any emergency classification requires an "Immediate Notification" and must be reported to NRC headquarters within one hour.

The Shift Foreman will follow Administrative Procedure AP C-1152 and its "Significant Event Notification Forin" for Unusual Events.

The Site Emergency Coordinator will assure that the required reporting is accomplished for Alert or higher conditions.

INITIATING CONDITIONS Notification of off-site emergency organizations shall be initiated by the Shift Foreman when he declares an Unusual Event. Alert Site Area Emergency, or General Emergency in accordance with EP G-1, " Accident v Classification and Emergency Plan Activation."

IMEDIATE ACTIONS ,

1. Upon declaration of an Unusual Event, the Shift Foreman, or his designated representative, (The interim Emergency Liaison Coordinator), shall man a telephone in the Control Room and proceed to contact off-site organizations.

2. Upon declaration of an Alert, Site Area Emergency, or General Emergency, the Shift Foreman acting as the interim Site Emergency Coordinator shall appoint the interim Emergency Liaison

Coordinator to perform the initial notification of off-site organizations.

3. The San Luis Obispo County Emergency Plan provides that the Sheriff will make notifications to the United States Coast Guard (USCG). If the situation at the pir.nt requires innediate protective actions on the part of the general pubife, and the County Emergency Organization has not had time to be activated.

l the plant should notify the USCG to place them on standby.

i, l

l DC0042 3XXI

-- - - - - . . - , - , - - -e,, - - - - - . - , _ , - , . . - - - .---+ . - . , . , , . - . _ , . _ , , --------,..,-...-----m. r --,

d otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 1

h0N DATE 10/8/85 PAGE 2 0F 6 TITLE. NOTIFICATION Or 0FFSITE ORGANIZATIONS

. l 2

' 3. The initial contact with an off-site agency should provide as !

l much information concerning the state of the emergency as is available at the time the notification is made. Fonn 69-10581 1 l " Initial Emergency Notification Fom" is provided as a guide to I be used in providing the initial notification of an emergency. !

All available infomation on Form 69-10581 should be orovided the organizations. l l

l

4. It is important that the initial notification of off-site support organizations be made promptly and with as much pertinent infomation as is available. It should not be delayed if all the ,

information contained on Form 69-10581 is not imediately '

available. Complete the reevired initial notifications even if the information provided is changed during the notification 1 Drocess. Provide the updated information as soon as initial nctification is complete.

5. Figure 1 " San Luis Obispo County Protective Action Zones and Sectors from Plant" and Table 1 "PGandE Recomended Initial General Public Protective Action Criteria" are provided to assist in determining appropriate protective actions to reconnend for the general public. Refer to EP R-2 " Release of Airborne Radioactive Materials" for additional protective action exposure criteria.

)

6. Follow-up status reports from the Control Room should also use

' Form 69-10581. Reports from the TSC should include the information that is appmpriate on Form 69-10262 " Radiological Emerpncy Status Form, Forn 69-10295 " Plant Status Emergency Form and Form 69-10296 Onsite/0ffsite Radiological Field Monitoring and PIC Emergency Status Form," where such infonnation is requested and not available to the organization by electronic a

data transmission.

i 7. All notifications and contacts with off-sito emergency organizations made throughout the course of the emergency should be recorded on Form 69-10298 " Required Offsite Organization Call

List" or use Form 69-9221 " Emergency Notification Record" or t

similar log.

.l i

DC0042 2XXI i

l l

l

1 3GV43 Pacific Gas and Electric Company NtJMBER REVISION 7 EP G-3 DEPARTMENT OF NUCLEAR PLANT OPERATCNS DIABLO CAN R T NO(S) 1 AND 2 PAGE 1 0F 6 p

NOTIFICATION OF 0FFSITE ORGANIZATIONS IMPORTANT APPROVED: YA Yh- -

SAFETY PLANT MANAGER ) DATE i SCOPE This procedure describes the steps to be taken to provide both the initial and follow-up notifications to Federal. State. Local, and Company off-site emergency organizations following the initiation of one of the four classes of Emergency Action Levels as described in EP G-1 " Accident Classification and Emergency Plan Activation."

Notification of off-site organizations which would respond on-site to specific emergency situations. (security threat personal in, jury or fire) are discussed in the individual procedures dealing with those specific types of emergencies. If required. requests for this assistance receive priority over notification calls. This procedure Q and changes thereto requires PSRC review.

GENERAL

1. Notification of San Luis Obisoo County should be made within 15

! minutes for the Unusual Event classification and sooner (consistent with the need for other emergency actions) for other j

classes. This time is measured from the time at which the Shift Foreman recognizes that events have occurred which make l declaration of an emergency appropriate.

2. Offsite emergency organizations which require prompt notification in an emergency situation are listed on Fors 69-10298 " Required Offsite Organization Call List. The agencies are listed in the order in which the notifications should be oeeforsned. Where multiple persons are available to assist in the callout process, the notifications may be done in the order determined by the Site Emergency Coordinator or Liaison Assistant. San Luis Obispo i

County should be one of the first notifications made.

1 DC0042 IXXI i

69-10297 10/85 (100)

EMERGENCY ORGANIZATION CALL LIST NOT FOR PU8:'IC DISCLOSURE

~

EMERGENCY HP FREQ.

ORGANIZATION DATE NOT DATE . HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NANF/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CDs.' ACTED YES NO u Security None 1. R. G. Todaro Liaison - Security Supervisor Assigned - TSC 2. J. P. Hubble Sr Security Shift Supvr , ,

3. L. C. Fisher /

Sr Security Shift Supvr

4. D. R. Dysert '

Security Shift Supvr NOTE: CALL SECURITY SHIFT SlFERVISOR (EXT. 33M 20 P11NIDE A LIST OF RRS0W1 COMING ONSITE l#Di CALL 0lfT IS COPf'LETE.

t I

DC0234 CONTROL ROOM ASSISTANT:

34VII 1. Insert date pers 's not available. Page 32 0F

2. Insert Date perst,.. aco m "on-call" responsibility.

(par <nn nn rail wil nnsse s the naner for this nositinni

f l

I o 69-10297 10/85 (100)

EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ.

ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Records None 1. C. Leon Meyers Management Records Analyst Assigned - TSC 2. L. Yamaguchi Records Analyst l

1

3. J. M. Neill Document Control Supv I

1 ,

4 i

=!

f 4

1 i

7 DC0234 CONTROL ROOM ASSISTANT:

33VII 1. Insert date person is not available. Page 31 0F 32

2. Jnsert Date person assumes "en-call" responsibility. ;

j (Person nn call will onssess the raner for this positinni j I _ _ , _ _ _ __ _ _ __ __ - - - - - - - - - - -

I

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2

, ON DATE 8/26/85 PAGE 3 0F 4 m Lg; POST ACCIDENT SAMPLING SYSTEM EP RB-15:0 -- Gas Chromatographic Analysis l

This procedure details the steps required (1) to check the instrument calibration prior to sample analysis and then (2) to load and analyze a gas

. sample from the RC module of the LSP or from the CASP. Sample gas should be available at RC-V-15 before using this procedure.

EP RB-15:E -- Post-Accident RCS Liquid and Gas Sample Handling This procedure details the steps required to prepare (1) a diluted liquid sample for boron analysis, (2) a diluted off-gas sample for isotopic analysis (3) a diluted liquid sample for isotopic analysis, and (4) a diluted containment air sample for isotopic analysis.

1 EP RB-15:F -- Data Analysis l

This procedure provides a standard format to

- record data obtained in the EP RB-15 procedures.

EP R8-15:G -- Ion Chromatographic Chloride Analysis l This procedure details the steps required to i measure the chloride concentrations from the l sample sources available at the LSP.

EP RB-15:H -- pH/ Conductivity / Dissolved Oxygen Analysis This procedure details the steps required to perform pH/ conductivity and dissolved oxygen analysis on a Ifquid sample.

EP R8-15:1 -- Sample Storace and Disposal This procedure provides a means for disposal of stripped gas samples and storage of liquid samples. -

DC0124 3VI

i l

n otAsto CANYON POWER PLANT UMT NO(S) 1 AND 2 Sf0N DATE 8/26/85 l PAGE 4 0F 4 TiTts. POST ACCIDENT SAMPLING SYSTEM l EP R8-15:J -- Undiluted Liquid Sampling from Reactor Coolant This procedure details the steps required to obtain an undiluted liquid sample from reactor coolant.

EP RB-15:K -- Diluted Liquid Sampling From Radwaste This procedure details the steps required to obtain a diluted sample from radwaste sources.

EP R8-15:L -- Undiluted liquid Sampling from Radwaste This procedure details the steps required to obtain an undiluted liquid sample from radwaste sources.

o EP R8-15:M -- Undiluted ~ Containment Air Sampling This procedure details the steps required to obtain an undiluted containment air sample in a cart / cask for isotopic analysis.

-)

REFERENCES J

1. Sentry High Radiation Sampling System Operations and Maintenance Manual

2. Nureg 0737 I y

l l

DC0124 4VI l

NUMBER EP RS-15: A

} Gv43 Pacific Gas and Electric Company REVISION 4 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 PAGE 1 0F 23' DIA8LO CANYON POWER PLANT UNIT NCHS)

EMERGENCY OPERATING PROCEDURE POST-ACCIDENT SAMPLING SYSTEM

, TITLE; -- INITIAL ACTIONS W

APPROVED Y [- IO T DATE PLANTMANAGERg g j PURPOSE The purpose of this procedure is to define some of the actions taken l when a decision is made by the Site Emergency Coordinator to obtain a :

post accident sample using the Post Accident Sample System (PASS). ;

i This procedure guides, with consideration of plant emergency radiation hazards, the Sentry team to access and make operable the Sentry room.

It also guides the team to withdraw from the Sentry room upon sample acquisition. This procedure and changes thereto requires PSRC approval.

(

DISCUSSION This procedure ensures sample recovery with a minimum risk to personnel in a limited time frame.

The movable shield in the 85' penetration area will be closed to block that access route. Therefore ingress and egress will be required across the RCA boundary. Performance of this procedure may require the transfer of radioactive samples to non-RCA's. For these reasons this procedure involves exemptions from certain routine RCA access requirements. Personnel implementing this procedure should be covered by_ an SWP or RWP during an accident, drill, or drill-like training.

Routine use of the Sentry room is covered by the C&RP routine sampling RWP.

Particularly hazardous or unexpected conditions may occur in post accident situations. Direction by appropriate supervision may augment or supercede portions of this procedure because every possibility cannot be anticipated. ~

DC0109 1XII 8--- ---ree-.m-e.a e-wese------o--. -eym.--c-w ,--w --"*se rv-w e =e--g=='a='--- W--ww-N'--D"+wwWP pm'g--*--N'Tvv-vv iw'"T'--'"-""'----*~v-w+-

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DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h h0N DATE 8/26/85 PAGE 2 0F 23 TITLE. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS PREREQUISITES AND PRECAUTIONS

1. The Site Emergency Coordinator should pre-plan post-accident sampling with the Emergency Radiological Advisor and the Site Chemical and Radiation Protection Coordinator prior to ordering a plant entry (i.e., prior to deciding to collect a post-accident sample) when unusually hazardous radiation or contamination .

levels are known or suspected to exist.

2 A sufficient number of properly qualified personnel to complete the task should be available prior to making the post accident sample decision. This might include:

a. Two people on the Sentry team qualified as C&RP Technicians.

b. A sample transporter qualified as an unescorted Radiation l Worker,

c. A count room qualified person in the TSC lab.

3. The Work Permit will specify protective equipment. Unless conditions warrant less stringent requirements, it is suggested i that full PC's, SCBA's and accident dosimetry be worn. Accident dosimetry includes: 0-200 mR PICS, 0-5 R PICS, finger rings (not

necessary during drills).

4. The Sentry team will make a post-accident entry to the plant only when directed by supervision and when possessing a high range portable survey meter to permit surveying into areas of unknown radiological conditions. Normal range survey meters may also be carried.

5. The Sentry team should be informed of plant status as it pertains to significant hazards, both radiological and non-radiological, along access routes.

6. Exposure hazards, both airborne and direct radiation, in the Sentry room should be monitored remotely for pre-entry status and locally for tracking while sampling.

a. Use the Eberline Control Terminal (s) in either Access Control or the cold machine shop to remotely address the SPING air monitor in the Sentry room, which can be read l

locally.

DC0109 2XII

i 1 AND 2 OLABLo cAN'JON POWER PLANT UNIT NO(S) f0N

.: DATE 8/26/85 PAGE 3 0F 23 Tirts.<' POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

b. Area radiation monitor RE-48, in the Sentry room, can be read in the Control Room or locally.

7. Comunications are vital during a plant emergency. Entry teams must be able to comunicate with the Control Room and appropriate supervision.

8. C&RP Technicians have the quired for access to areas and equipment related to this procedure and have security key cards to enter door #116 or #197. If the Sentry team does not possess either of these then take the applicable master k -

9. The contain v Ives FCV-696 697 698, 699 and 700 ,

10. It is important to conduct operations in an expeditious m'anner

' ( to provide timely vital plant status information.

11. Any information disseminated at briefing or any information recorded on Sentry Status Board may allow changes in procedure to reflect a current, transient condition of the system.

l PROCEDURE

! 1. Access to Sentry Room Area The Diablo Canyon Shielding Review indicates that the following routes might minimize exposures.

a. Via Turbine Building at 85' Elevation 4

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l DC0109 3XII

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DIABLO CANYON POWER PLANT UNIT NO(S) l'AND.2 h[lSf0N' s' DATE 8/26/85

.PAGE 4 0F 23 )

TITLE. POST-ACCIDENT SANPLING SYSTEM

-- INITIAL ACTIONS

1) Unit I Starting at the Cold Machine Shop proceed into the hallway to door #125C, proceed north to door #122 and exit building. From here turn south and enter door

192 to the Motor Repair Shop.

FIGURE la

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DC0109 4XII i N

> l olABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

[fSf0N 4

DATE 8/26/85 l PAGE 5 0F 23 TiTLg. POST. ACCIDENT SAMPLING SYSTEM

.. INITIAL ACTIONS

2) Unit II Starting at the Cold Machine Shop prt>ceed into the hallway to door #140, proceed south to door #122 and exit building. From here turn north and enter #192 to the Motor Repair Shop.

FIGURE lb

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( "y n - r'=e .......

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l DC0109 SXII

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 E EP RS-15:A DATE 8/26/85 PAGE 6 0F 23 TITUE. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

b. Around Turbine Building at 85' Elevation

1) Unit I Starting at the Cold Machine Shop proceed west to the outside via door #129, turn right and continue north around the Unit 1 Turbine Building looping around the transfonners at the north end of the plant. Continue south to door #192 between containsnent and the Turbine Building. Enter the Motor Repair Shop via door #192.

FIGURE 2a T

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Y" 0000 j.0 Q,B

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DC0109 6XII

[

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 8/26/85 PAGE 7 0F 23 Tirts. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

2) Unit II Starting at the Cold Machine Shop proceed to the outside via door #129, turn left and contiliue south around the Unit II Turbine Building looping around the transformers at the south end of the plant. Continue north to door #192 between containment and the Turbine Building. Enter the Motor Repair Shop via door #192.

FIGURE 2b e._ e 2 g _7__ -

...ees,,eee---~~... ,_

7g- g- ,,, .eseee.e.

n= w i

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esse:

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ini i =

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.o e e e e e s e m e e e s e e m e e e m e e e m e s e e e e e e e s e e e e e sed DC0109 7XII

OIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:A 8 REVISION 4 DATE 8/26/85 PAGE 8 0F 23 TITLE. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

c. Other Access Routes The Figure la or Ib pathway is preferred. However an access route other than those above may be suggested by actual post accident conditions (a.g., fire, high energy line break, etc.). The final route selected should be directed by appropriate supervisory personnel.

2. Initial Set-up of Sentry Room Equipment

a. Gas Supply Cylinders Check The gas supply cylinders for Sentry Room equipment are located along the east wall of the Motor Repair Shop.

Proceed to the gas storage rack and verify t1e following:

1) The cylinder valves are fully open for []

all three cylinders.

2) The manifold valves are fully open for []

all three cylinders.

}

3) The argon regulator shows tank pressure []

of approximately 1000 psig and the regulator is set to 100 psig.

If argon tank pressure is much less than 1000 psig, then the [

cylinder has to be changed with the spare cylinder located at the storage rack.

4) The 2000 ppm and 101 H span gas cylinders []

shouldhaveatleast180psigandboth I

regulators should be set at 10 psig.

b. Emergency Ventilation System Line-up. (Optional: If proper ventilation is lined up proceed to step 2.c., Steel Shield Door Closure.)

DC0109 8XII t

NUMBER EP RB-15:A D'ASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 8/26/85 PAGE 9 0F 23 Tirts. POST-ACCIDENT SAMPLING SYSTEM '

-- INITIAL ACTIONS

1) Climb the ladder to the cat walk and cross []

to enter the ventilation room. (AC4 or .

909 key required). l 1

POTE: Minimize the time that the vent room doors are open.

2) Proceed to breaker panel PPHRS, 52-1(12/22)J-35 [] i and check all breakers ON. i

3) Proceed to the motor controllers for fans []

and heaters located to the left of the breaker panel and push the STOP and RESET pushbutton on each one.

4) EMER LEAD (IS-150) is the preferred system.

a) Open its supply and exhaust dampers []

and the supply and exhaust vent dampers (a total of 4 dampers) and close all other dampers, b) Push the START pushbuttons on the []

motor controllers for the EMER LEAD supply fan, exhaust fan, and heater 29A, in that order.

5) EMER REDUN (IS-151) is to be used as a backup if EMER LEAD is inoperable.

a) Open its supply and exhaust dampers []

and the supply and exhaust vent dampers and close all other damoers.

b) Push the START pushbutton on the motor []

controllers for the EMER REDUN supply fan, exhaust fan and heater 298, in that order.

6) Return to the 85' elevation. []

0C0109 9XII

O DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON 4'

DATE 8/26/85 PAGE 10 0F 23 m tg. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

c. Steel Shield Door Closure. (Optional. If the shield door is closed proceed to step 2.d., Radiological Assessment.) l l

1) Proceed through door #192-A southofthg []

Unit I Motor Repair Shop, or door #192-A 1 north of the Unit II Motor Repair Shop, and visually check the shield door's winch

cable. If the marked portion of the cable indicates the shield is closed return to the Motor Repair Shop and proceed with step d., Radiological Assessment below.

2) Operate the winch until the marked portion []

of the cable visibly indicates the, shield door is closed.

3) Return to the 85' elevation. []

d. Radiological Assessment of Sentry Room i

1) Enter the Sentry room via the RCA boundary []

(door #116 or #197') and the watertight door. .)

(Key at RP key box) '

2) Perform a general area radiation survey I

a) Note high levels such as' might exist []

. at the auxiliary building end of the J

room due to ECCS piping.

l b) Note low level areas for sample screen []

surveying later.

3) Note the reading of RE-48 on the Process []

Control Panel (PCP). Recheck it intermittently.

4) If SPING is not alarming, the respirator, []

if worn, may be removed at this time.

It should be donned anytime there is a potential for airborne contamination to be introduced into the room.

l 1

DC0109 10XII t

i L

1 AND 2 NUMBER EP RS-15:A OfA8LO CANYON POWER PLANT UNIT NO(S)

REVISION 4 s DATE 8/26/85 PAGE 11 0F 23 TrfLE. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

e. Proceed to the Ventilation Control Panel.

1) Check the alanns.

a) Press TEST and note the red alarm []

indicators flash while the audible alann sounds.

b) Press SILENCE to stop the audible alarm. []

c) Press ACK and note the flashing alann indicators glow steadily.

d) Press RESET and note the red alarm

~

indicators go out.

2) If the NORMAL VENT switch is on, turn it []

off.

3) If the EMER LEAD ventilation system is []

desired and is not operating depress in

(- order the SUPPLY, EXHAUST, and HEATER pushbuttons.

4) Press reset and observe the appropriate []

indicating lights for proper operation of the desired ventilation line-up.

5) If necessary, return to step 2.b., Emergency []

Ventilation Line-up.

f

3. Electrical Line-up Proceed to the breaker panel PYNM, located next to the Vent Control Panel, and check positions of breakers as follows:

BKR #1 - ON

BKR #2 - ON

BKR #3 - ON

BKR #4 - ON

BKR #5 - ON

BKR #6 - ON *'

BKR #7 - ON

BKR #8 - ON

BKR #9 - ON BKR #10 - ON BKR #11 - ON l '.I BKR #12 - ON '[

MAIN BKR - ON ,,

DC0109 11XII l

DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RS-15:A REVISION 4 DATE 8/26/85 I PAGE 12 0F 23 TITLE. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS i

I

4. The Containment Atmosphere Hydrogen Analyzers If hydrogen in containment air is to be analyzed by G.C. proceed to step 5. CMP / CAP power up.

a. Initial Conditions of an Analyzer System

1) Main power switch at remote panel in STAN08Y. []

E: If the power switch is 0FF, then turn it to STAN08Y and give the system six hours to warm up. If both systems have not been in STAN08Y for at least six hours, or are otherwise inoperable, use the gas chromatograph, step 5, below. Record the time of switching from 0FF to

STAND 8Y .

2) Solenoid operated sample line containment []

isolation valve switches CLOSED. (FCV-235, 236,237,238,239,240)

3) 0xygen gas tank connected and isolation valve c'osed. (Tank should be changed at

[] )'

100 psig.)

l b. H2 Analyzer System (s) Operation.

CEL: 8? 83

1) Turn the three sample line switches

to the OPEN position. Observe the l position indicating lights. [][]

I 2) Open the oxygen tank (located next to l

eyewash) isolation valve and adjust regulstor to 27 2 psig. [][]

3) Turn the main power switch from STAN08Y to ANALYZE. [][]

4) Push the REMOTE SELECTOR pushbutton to gain control at this panel and reset C0pm0N ALARM, if necessary. [][]

5) Turn the dual range switch to the 0-101 range. [3[3 DC0109 12XII

otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 {0N DATE 8/26/85 PAGE 13 0F 23 TiTLs POST-ACCIDENT SAMPLING SYSTEM 8

! -- INITIAL ACTIONS l

6) Adjust the ZERO and SPAN potentiometers i until they agree with their respective "

values indicated on calibration stickers located under each potentiometer. [][]

7) Turn the function selector switch to SAMPLE. [][]

TIME (82) (83)

8) Both CEL 82 and 83 are to tm used.

Repeat steps 4.b.1) to 7) for the second system while waiting for the first system to stabilize, which takes approximately 6 minutes. [][]

9) Proceed with step 6.. Initial Valve Line Up, while waiting for stabilization. When 6 minutes have elapsed since switching to SAMPLE, continue with step 10) below. [][]

I 10) Record the analyzer meter reading, the time read, and the scale used. [][]

Meter Reading (%)

. Time Scale Used If the meter reads greater than 9%, the 0-20% scale j should be used.

11) Inform the Control Room of which scale and CEL is used and ask the Control Room if the analyzer (s) am to remain in ANALYZE or be returned to STAND 8Y. [][]

Advise the Control Room of the reagent gas depletion l and the limited lifetime of the sample pumps, which are located in the 100' E1. penetration area.

l

12) If directed to leave the analyzer (s) in ANALYZE proceed with step 5. CMP / CAP Power Up. . . [][]

DC0109 13XII

DIA8LO CANYON POWER PLANT UNir NO(S) 1 AND 2 k[f[0N DATE 8/26/85 PAGE 14 0F 23 rirls. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS i 1

CEL: 82 83

c. Standby

1) Turn the function selector to ZERO and purge the analyzer for 6 minutes. [][]

2) Turn the main power switch to STANDBY. [][]

3) Close the reagent tank isolation valve. [][]

4) Turn the three sample line isolation valve switches to the CLOSED position. [][]

5i Push Common Alam to Reset [][]

5. CMP / CAP Power Up/ Gas Chromatograph Startup

a. At the CAP align V-6 and V-5 to DEMIN WATER. []

b. Open V-8 and V-2. []

c. Open CAP V-11, close V-24 and 18. [] ].

d. Check the three green root valve handles next []

to the CAP down (open) in the vertical position to allow Argon and the Span gases to the CAP.

e. Open or check open CAP-V-10 and adjust []

, instrument air pressure to 80 2 psig.

f. Open or check open CAP-V-14 and adjust argon []

pressure to 25 i i psig.

, g. At the CMP, turn the POWER switch to ON at the []

panel front, and check ON the toggle switche(s) at rear of G.C. unit.

1 Ensure red power light is on. [;

2 The red colon at the G.C. display is on. ,,

3 Full flow lights for conductivity loop and .

IC loop are lit. g DC0109 14XII

DIAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h ON DATE 8/26/85 PAGE 15 0F 23 TTLE. POST-ACCIDENT SAMPLING SYSTEM I

-- INITIAL ACTIONS

h. On the G.C. front panel

1) Select attenuation factor of 250 (25 x 10). [] '

Place all function switches in the 0FF (out) position.

i 2) Depress MAN and CLEAR switches. []

3) Enter "00" initiating G.C. warsup.

Time on

6. Initial Valve Lineup I

a. Valve HCV-21, which is located next to the []

chemical sink, should be positioned to the TO CONTAINMENT position, except during Training or Drill when it should be positioned to the POST LOCA COLL TANK position.

1

b. Post LOCA sample cooler supply valve, next to HCV-21, [] l

( should be turned until indicator shows OPEN.

c. At the CAP, valves should be positioned as follows:

F CAP-V-7 (REXNORDOXYGENANAL) [] ,

CAP-V-6 (0XYGENCALIBSOL'M) []

a CAP-V-5 (CLOSED) []

f CAP-V-1 (open) []

I CAP-V-29(12o' clock) Top of CAL TANKS []

CAP-V-28(12o' clock) Top of CAL TANKS []

CAP-V-27 (12 o' clock) Top of CAL TANKS []

! CAP-V-15(closed) Bottom of CAL TANKS []

i CAP-V-16(closed) Bottom of CAL TANKS []

CAP-V-26(closed) Bottom of CAL TANKS []

l i

CAP-V-30(9o' clock) CAL TANK 1/2 Selector []

CAP-V-25(closed) Bottom of CAL TANKS []

l CAP-V-20(closed) Bottom of CAL TANKS []

4 I

l DC0109 15XII

___._...___-.._,n__-__ _ . , . , , _ . , , . _ - _ _ , . _ _ _ . _ . . _ , _ , _ _ . _ _ _ _ , . _ . . _ . _ , . - _ , _ _ , . . . _ . _ - _ _ . - . _ _ _ . ,

ea N DIA8LO CANYON POWEQ PLANT UNIT NO(S) 1 AND 2 ON r DATE 8/26/85 PAGE 16 0F 23 Tirts POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS CAP-V-19(closed) Bottom of CAL TANKS []

CAP-V-17(closed) []

CAP-Y-9 (clo'ed) []

CAP-V-12(open) []

Adjust nitrogen regulator until nitrogen pressure gauge is 60 2 psig. []

d. At the Demin Module of the LSP, valves should be positioned as follows:

DM-V-1.1 (closed) []

DM-V-1.2 (closed) []

DM-V-1.3 (closed) []

DM-V-3 (closed) []

J DM-VREL-1.1(closed) []

DM-VREL-1.2 (closed) []

e. At the Open Grab Sample panel of the LSP, valves should be positioned as follows:

RW-V-6 (closed) []

DM-V-2.1(closed) []

DM-V-2.2 (closed) []

DM-V-2.3(classd) []

RC-V-17 (closed) []

RC-V-6.1(closed) []

RC-V-6.2(closed) []

RC-V-5.1(closed) []

RC-V-5.2(closed) []

~

f. At the RC Module of the LSP, valves should be positioned as follows:

RC-V-12 (12o' clock) []

RC-V-15 (CLOSED) []

0C0109 16Xff

l CIA 8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N4

DATE 8/26/85 PAGE 17 0F 23 Titts POST-ACCIDENT SAMPLING SYSTEM I

-- INITIAL ACTIONS B RC-V-14 (closed) [] l RC-V-13 (9o' clock) []

RC-V-10 (9o' clock) [3

RC-V-11 (CLOSED) []

RC-DV-2 (9 o' clock) [] .

RC-VREL-1(closed) [3 RC-VREL-2 (closed) [3

, RC-V-3 (closed) [3 RC-V-7 (9o' clock) []

RC-V-2 (closed) []

RC-V-1.1 (closed) [3 RC-V-1.2 (closed) []

RC-V-1.3 (closed) []

RC-V-1.4 (closed) [3

( RC-V-1.5 (closed) [3 RC-V-4 (closed) []

RC-V-8.1 (closed) [3 RC-Y-8.2 (closed) []

RC-V-16 (closed) [3 RC-V-9 (CLOSED) []

RC-V-18 (6 o' clock) []

RC-V-19 (BYPASS) []

RC-Y-20 (closed) []

RC-V-21 (closed) on graduated cylinder [] l RC-DV-1 (8YPASS) []

RC-Y-22 (T0 WASTE) []

g. At the RW Module of the LSP, valves should be positioned as follows:

RW-V-9 (closed) []

DC0109 17XII

OtA3LO CANYON POWER PLANT UNIT NO(S) .1 AND 2 V ON DATE 8/26/85 PAGE 18 0F 23 TITLE. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

l 8

RW-V-10 (closed) []

RW-DV-1 (BYPASS) []

RW-V-8 (BYPASS) []

RW-V-7 (BYPASS) []

RW-V-5 (6o' clock) []

RW-V-4 (closed) []

RW-V-3 (closed) []

RW-V-1.1 through RW-V-1.10 (12 o' clock) []

RW-V-2.1 through RW-2.10 (6 o' clock) []

h. AtthePROCESSCONTROLPANEL(PCP)

Notify the Control Room when any valve alignments are changed during accident.

1) Position or check the position of the following switches for valves: ;

Ouring Drill or Training the next six valves should be left in REMOTE.

FCV-9351A(CLOSE) []

FCV-93518(CLOSE) []

FCV-93508(CLOSE) []

FCV-9350A(CLOSE) []

FCV-9353A(CLOSE) []

FCV-93538(CLOSE) []

FCV-692 (CLOSE) []

! FCV-693 (CLOSE) []

j FCV-694 (CLOSE) []

FCV-1413 (CLOSE) []

FCV-1416 (CLOSE) []

L DC0109 18XII

. i

, otAaLO CANYON POWER PLANT UNIT Nots) 1 AND 2 (%y0N

,8 DATE 8/26/85 PAGE 19 0F 23 Tirts. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS FCV-1417 (CLOSE) []

FCV-1418 (CLOSE) []

FCV-1419 (CLOSE) []

FCV-1412 (CLOSE) []

FCV-1410 (CLOSE) []

FCV-1411 (CLOSE) [] .

FCV-137VCT(CLOSE) []

FCV-1414 (CLOSE) []

FCV-1415 (CLOSE) []

FCV-1420 (CLOSE) []

FCV-1421 (CLOSE) []

FCV-1422 (CLOSE) []

FCV-1423 (CLOSE) []

FCV-1424 (CLOSE) []

k FCV-1425 (CLOSE) []

FCV-624 (CLOSE) []

FCV-1428 (POST LOCA SAMPLING) - During Drill []

or Training this valve should be left in the RE 11/12 position.

2) Position switches for POST LOCA COLLECTION TANK TRANSFER PUMPS 1 and 2 to the STOP position. []

3) At the PCP a) Push the TEST button and verify:

(1) the alarm sounds []

(2) all labeled windows flash []

b) Push the ACK button and verify:

(1) the alarm is silenced []

(2) all labeled windows glow steady []

DC0109 19XII

otAaLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 -

V ON DATE 8/26/85 PAGE 20 0F 23 TITLE POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS c) Push the RESET button and verify that all windows are off. []

7. Monitor Startup and 02-Calibration Tank Recirculation (CAP)

a. Dissolved 02 Calibration Tank Recirculation

1) If calibration has been perfonned within []

one week, proceed to step b.

2) Observe that the level in the oxygen []

calibration tank CAP-CAL-4 is about 1" below top of sightglass. If water must be added to the tank, open CAP-V-24 and fill

, the tank. Close CAP-V-24.

3) Open fully CAP-V-17. []

4) CALIB. SYSTEM pump to ON position.

Turn the T Indicatcr 0,ights for the pump should light on both the CAP and CMP. []

)

5) Recirculate the water for at least I hour. []

Time on

6) Continue to recirculate until the actual calibration is perfonned. []

b. pH Monitor (CMP)

, 1) Check internal S-1 toggle switch to ON (up) position. []

2) Check S-3 to the ON position. []

c. ConductivityMonitor(CMP)

1) Observe that the meter reading is on zero when the sehctor switch is on ZERO. []

2) Turn the selector switch to CHECK. The meter []

~

indicator should move to CHECK on the meter l.

scale. (If it does not move to CHECK, consult the Site Emergency Coordinator for directions.)

F 1 .

DC0109 20X!!

[ .

I l

- \

DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

, ON '

" 0 ATE 8/26/85 PAGE 21 0F 23 ;

TsTts POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

3) Switch the selector switch to MEASURE. The monitor is now ready for operation. []

4) Allow to wam up for 30 minutes.

Time on -

b

d. Ion Chromatograph Startup Proceed with this section only if chloride analyses [

is to be done at this time.

1) Note the level of chloride calibraticn []

standard (2000 ppm 8 as boric acid ar.d 1 ppm chloride) in CAL-3. 5

2) Verify that air bubbles are not visible in []

the sight glass or in tygon capillary tubing.

(If air bubbles are present, refer to Procedure CAP G-3.)

( 3) Verify that the following reagents are available:

E1/E2 Eluent: 2.0 g NaOH/2.4 g Na CO32

[]

1_N, Sulfuric Acid (H2 504 ) []

Detonized Water Rinse []

4) If any of the reagents Ifsted in step 3 is not []

available or has not been prepared within the last 30 days, refer to Appendix 1 for details of reagent preparation.

5) At the CMP place the POWER and AIR switches []

to ON position.

6) Place LOAD / INJECT switch in the LOAD position. []

7) Place the E-2 switch in the UP position. []

8) PlacetheSEPARATORswitchintheSEP-1 position.[]

9) Place the SUPPRESSOR switch in the SUP-1/RGN-2 []

position, g

DC0!09 21XII

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP R8-15:A REVISION 4 .

DATE 8/26/85 PAGE 22 0F 23 TITLE. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS

10) At the CAP set MODE switch to ZERO and verify []

needle points to 0. (If not at ZERO, adjust to ZERO with the screw below the meter face.)

11) Set MODE switch to CAL and verify needle []

swings full scale. (If adjustment is necessary, adjust using the screw at the top of the circuit board labeled METER.)

12) Set MODE switch to zero. []

13) Set the pMHO FULL SCALE switch to 30. []

14) Check if eluent pump setting is 40 percent. []

15) At the CMP turn the aluent pump switch to ' []

ON position.

16) Turn GAUGE switch to ON position. If reading []

on ELUENT PUMP DISCHARGE PRESSURE is very-low, check capillary lines for air (CAP G-3).

)

17) Allow system to warm up and stabilize for 30 minutes.

Time on

8. Sampling may now commence using specific sampling procedures.

APPENDICES

1. Reagent Preparation I

e DC0109 22XII l

-...._..._,-.__.___,,--_-___,.~~--.,_,..-_____.-,.-_.--_,.-m, - _ - - _ _ - - _ _ , _ y .-___ - . - - . - - . . _ _ . _ -

OIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON

DATE 8/26/85 PAGE 23 0F 23 m Ls. POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS APPENDIX 1 REAGENT PREPARATION g: Reagents must be made using demin water with a conductance of less than 1 umho. -

1. E1/E2 Eluent - 2nN NaOH/2.4mM Na 2 CO3 Add 0.32g NaOH and 1.00g Na CO (anhydrous) to 4.0 liters of demineralized water, dissolhe $nd mix.

' 2. IN,, H2 S04 Add with stirring 120 ml of concentrated sulfuric acid to 4 liters of domin water and cool. Transfer the solution of a 4 liter collapsible container, remove excess air, and label container with initials and date. Connect it to the line REGEN SYSTEM-1. Open the container valve and vent pump inlet lines.

( 3. Domineralized Water Rinse Fill a four (4) liter collapsible container with domin water.

Remove excess air from the bottle and label. Connect it to the water line in the reagent storage facility. Open the container valve and vent pump inlet lines.

4. Chloride Standard Add 2m1 of 1000 ppm chloride standard and 22.9 2 0.lg H 3 80 3 to two separate 2 liter volumetric flasks. Dilute es:h flask to the mark, with domin water. The cal tank holds 3.5 liters.

DC0109 23XII

NUP3ER E: R5-15:S T 3st3 Pacific Gas and Electric Company REVISION 3 DEPARTMENT OF NUCLEAR PLANT OPERATCNS 1 AND 2 PAGE 1 0F 13 O!A8LO CggggiT NO(S)

POST-ACCIDENT SAMPLING SYSTEM l Tirts. STRIPPED-GAS AND DILUTED RCS

- iPORTANT l APPROVEO 7f' T /0 W O

- PLANTMANAGEg' DATE SAFETY DISCUSSION The purpose of this procedure is to detail the steps required to sample liquid and to strip gas from the reactor coolant. This

procedure will further detail the steps required to prepare a sample for H, analysis. This procedure requires operations at'the LSP, CAP, and CMP panels. A complete flush of the modules will be' done after the sample has been processed and system will be returned to initial lineup status.

PREREQUISITES

1. System was initially lined up as described in Procedure i( EP R8-15:A.

2. Verify that the following annunciator windows are off on the PCP:

a. REACTOR COOLANT SMPLE COOLING WATER LOW FLOW

' b. REACTOR COOLANT SMPLE COOLING WATER LOW PRESS

c. REACTOR C0OLANT SMPLE C0OLING WATER HIGH TEMP l

d. REACTOR COOLANT PURGE HIGH TENP i e. REACTOR COOLANT SMPLE WATER HIGH TEMP l f. LIQUID SAMPLE PANEL HIGH PLENUM PRESS

g. CHEMANAliSISPANELHIGHPLENUMPRESS

3. The following equipment must be available and operational:

a. Meter-long reach rod

b. Hand operated vacuum pump OC0124 IX

,---,.,----.,-em-.y+-,,..,m-.--.-------w. . . - - . - - - - . _-- w. ---m -----.4

o Asi.O CANYON PCMEO PLANT UNIT NO(Si 1 AND 2 ON

' DATE 8/26/85 PAGE 2 0F 13 m Ls. POST-ACCIDENT SAMPLING SYSTEM STRIPPED-GAS AND DILUTED RCS l

, c. Gas bottka griptorg

.* ,i ,

7

d. Sample cart /cark '

e. A pre-labeled 60 m1 sample bottle with a new septum and ;

14 cc gas sample bottle i The labels should have the sample source, date, time of the sample, and the initials of the person taking the sample, h ,

t

4. ,The gas chromatograph must be in a standby mode with a valid calibration.

Assign one LSP operator to EP R8-15:D to prepare the G.'C.

PRECAUTIONS

1. See EP R8-19:A for details. I

2. This sampling involves processing of water that will be highly radioactive. Precautions should be taken to prevent skin contact )

or ingestion.

3. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush period, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose area.

4. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.

5. The LSP operator must verify that the gas chromatograph is ready to receive a gas' sample before opening valve RC-V-15. Yalve RC-V-15 must be closed after filling all G.C. sample loops arc prior to performing diluted gas sampling and final flushing operations'.

DC0124 2X i

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DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2

[CN DATE 8/26/85 PAGE 3 0F 13 l TTts. POST-ACCIDENT SAMPLING SYSTEM STRIPPED-GAS AND DILUTED RCS l

l PROCEDURE

! 1. Verify RC-DV-1 is turned to BYPASS. Fill reservoir RC-R-1 with domin water from squeeze bottle: []

a. Open RC-V-20 and RC-V-21. []

b. Adjust reservoir RC-R-1 until the water level i in graduated cylinder RC-C-1 is over 100 mis. [] l 4

c. Close RC-V-20. []

d. Turn RC-DV-1 to SAMPLE, allowing some water to i flow to insure meniscus but maintain level above !

100 ml. [] j

e. Return RC-DV-1 to BYPASS. [] l I

f. Close RC-V-21. [] I

2. Verify that the following valves are c1cted:

I RC-V-1.1 through 1.5 l

RC-V-4 Fl '[ (

i F

3. At the PCP verify that the sample cooler water flow, temperature, and pressure annunciator lights are off. []

4. Open the following valves:

RC-V-9 RC-V-8.2 ll RC-V-10 .

5. Drying Expansion Vessel CA(JTS: Adhere to directions for clockwise and counterclockwise movement of valves.

a. Turn RC-V-11 clockwise to 3 o' clock position. []

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b. Pull open RC-VREL-2. When there is a sharp increase in pressure indicated on RC-C-3, release RC-VREL-2. []

c. Adjust RC-VREL-2 until RC-G-3 indicates approximately 20 psig. Dry RC-EV-1 with argon for 1 minute. []

d. Turn RC-V-11 counterclockwise to the 9 o' clock position to pemit RC-EV-1 to Vent, then close RC-V-9. []

6. Gas Extraction and Line Evacuation

a. Install the prelabeled, diluted gas sa~mple bottle on the front panel needle. [] ;

b. Open RC-V-13 and then open RC-V-12 and evacuate until RC-G-2.1 and RC-G-2.2 indicate a minimum of 22" of Hg. []

c. Turn RC-DV-2 to the 6 o' clock position and continue the evacuation until RC-G-2.2 indicates ')

the same reading as RC-G-2.1 or a minimum of 22" of Hg. []

d. Close in order:

RC-V-13 J' RC-V-10 RC-V-12 .'l Wait for a minimum 2 minutes to verify vacuum is holding. []

Record the vacuum on RC-G-2.1 _" of Hg. []

e. Turn RC-V-11 clockwise to the CLOSED position. []

, f. Turn RC-DV-2 to the 9 o' clock position. []

g. Open RC-V-14 and verify the pressure on RC-G-2.2 is approximately 2 psig. []

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h. Close RC-VREL-2. []

7. Reactor Coolant Sample Line Purge i

a. Open RC-V-8.1. []

b. Determine which sample source isolation valves will have to be opened from the list below:

SAMPLE SOURCE CONTAINMENT ISOLA 1:0N VALVES Hot Legs Loops 1 and 4 FCV-9356A and FCV-93568 Pressurizer Steam Space FCV-9354A and FCV-9354B Pressurizer Liquid Space FCV-9355A and FCV-93558 RHR Pumps Discharge N/A Volume Control Tank N/A

c. Call the Control Room and have operations block []

open the appropriate containment isolation valves..

k d. Open the corresponding remote plant isolation []

valve (RPIV) and remote source isolation valve (RSIV) at the PCP (see Appendix 1 for proper valve).

e. Close the remote flush isolation valve (RFIV). []

Check that LSP shield door has been closed prior to initiating purge.

E 1: The sample source valves are labeled RC-V-1.1 through RC-V-1.5. Throughout this procedure, the fann RC-V-1.X will be used to indicate the source valve to be operated. The sample source used for sampling will have been given at a briefing by the Site Chem and Rad Protection Coordinator. .

1 E 2: Upon implementation of the next step, sample will be flowing into the back of the LSP. The meter-long reach rod should be used to operate valves and a dose rate survey should be done to monitor radiation levels.

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" l DATE 8/26/85 '

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f. Open the sample source valve RC-V-1.X (see Appendix 1 for proper valve). []

g. Open RC-V-3. []

h. Slowly open RC-VREL-1 until RC-FI-I indicates 100% flow or 1900 cc/ min. Purge for 9 minutes. []

8. Cart / cask preparation - while sample is purging.

a. Insert the needle of the hand operated vacuum pump into the septum of the prelabeled 60 m1 sample bottle: []

1. Evacuate to the maximum vacuum achievable with the hand pump. The vacuum must be at least 15" of Hg. []

2. Keep the pump connected to the bottle for 3 minutes to assure that the bottle retains the vacuum. []

b. Turn on the switch to light the diluted bottle fill station. []

c. Remove the bottle from the vacuum pump and place bottle on the cart / cask assembly cavity piston. []

1. Turn the direction valve for the hydraulic piston to the down position and lower the bottle into the cask cavity. []

2. Close and open the cask to verify that the cover is working properly. []

3. Position the cart / cask under the diluted I reactor coolant fill station needly and set l the brake. []

4. Turn the direction valve for the hydraulic piston to the up position but do not raise the bottle onto the needle. []

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STRIPPED-GAS AND DILUTED RCS l

l

9. Continued purge. l

a. Slowly close RC-VREL-1 until RC-FI-1 indicates 36% or 700 cc/ min. Continue the purge for 1 minute. []

b. Close RC-V-3. []

10. Reactor Coolant Sampling

a. Align RC-V-22 to CHEM PANEL. []

b. At CAP align V-6 and V-5 to LIQUID SAMPLE. [] l l

c. Open RC-V-2. []

d. Adjust RC-VREL-2 until RC-FI-2 indicates 100%

flow or 200 cc/ min. Purge for 3 minutes. []

e. Close RC-V-8.2 and record time . []

f. Close RC-V-8.1 []

( g. Open RC-V-7 and continue purge to CAP. []

h. Raise sample bottle in LSP cart / cask up, onto []

needle.

1. Read initial al on buret.

J. Turn RC-DV-1 to SAMPLE. []

11. CAP Analyses

a. One operator can now analyze pH/ Conductivity /00 according to EP RB-15:H Step 3. Sample Analyses. Subsequently chloride can be determined according to EP R8-15:G. i

b. One operator can continue with the ifquid 1 sampling procedure.

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12. Liquid Sample Dilution I

a. Crack open RC-V-21. and add 23 mis of water from the graduated cylinder RC-C-1 to the sample bottle, then close RC-V-21. []

b. Read final ml .

Determine total al added .

c. Turn the RC-DV-1 to BYPASS. []

d. Place the direction valve for the hydraulic piston in the down position and lower the sample into the cask. []

e. Close the cask. []

13. Sample Cask / Cart Removal

a. Release brake and remove the cart / cask from the sample station and place in temporary hold area. [] )

b. Perform a radiation and contamination survey on the cart / cask assembly. []

c. Turn off the diluted fill station light. []

d. Prepare and analyze sagle according to EP RB-15:E. []

14. Gas Stripping Operation

a. Open RC-V-9. wait approximately 5 seconds, and close RC-V-9. []

b. Open RC-V-16. []

c. Snap open RC-V-9 and wait for 1 minute. []

d. Close RC-V-16 and then close RC-V-9. []

1 DC0124 8X

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e. Turn RC-V-11 counterclockwise to the 9 o' clock [] ,

position. The pressure reading is nomally between ,

5 and 10 psig. Record the reading on RC-G-2.1.

RC-G-2.1 psig

15. Diluted Gas Sampling -

a. Turn RC-DV-2 to the 6 o' clock position and wait []

until the pressure on RC-G-2.2 returns to about 2 psig.

b. Turn RC-DV-2 to the 9 o' clock position. []

c. Close RC-V-14. []

4

d. Aemove the griptong containing the diluted gas []

sample double bag, label and store. Infom PASS Supervisor that the diluted offgas sample is available for transfer.

( The sample is now ready for analysis in the Gas Chromatograph. The G.C. should be prepared up to Step 4.f. of EP R8-15:D before analysis can proceed.

16. Stop here and analyze the sample according to EP RS-15:D. []

17. Do not proceed to the next step until the offgas sample is complete and all CAP manipulations are verified complete with main LSP operator. l

18. Call the control room and have operations close []

the containment isolation valves opened earlier if needed.

19. Final Flushing l

a. Verify RC-V-15 is in the CLOSED position. []

b. Turn RC-V-11 counterclockwise to the 6 o' clock ,

position. []

DC0124 9X l

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0iAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f3ON DATE 8/26/85 PAGE 10 0F 13 i TITLE POST-ACCIDENT SAMPLING SYSTEM STRIPPED-GAS AND DILUTED RCS

c. Open the following valves:

RC-V-9 RC-V-7 RC-V-8.1 [l

d. Adjust RC-VREL-2 until RC-FI-2 indicates 100%

flow or 200 cc/ min. Flush with demin water for 1 minute. []

e. Open RC-V-8.2. []

f. Close RC-V-7. [] l

g. Adjust RC-VREL-2 until RC-FI-2 indicates 100%

flow or 200 cc/ min. Flush with demin water for 3 minutes. []

h. Close RC-V-8.1. []

i. Turn RC-V-11 counterclockwise to the 3 o' clock position. [] -)

j. Pull open RC-VREL-2. []

1) When there is a sharp increase in pressure indicated on RC-G-3, release RC-VREL-2. []

2) Adjust RC-YREL-2 until PI-1103 indicates 20 psig. []

3) Flush with argon for 3 minutes. []

k. Close RC-V-9. []

1. Open RC-V-10. []

m. Turn RC-V-11 counterclockwise to the 9 o' clock position and allow RC-EV-1 to vent. []

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1 AND 2 EP RB-15:8 DIA8LO CANYON POWER PLANT UNIT NO(S)

DATE 8/26/85 .

PAGE 11 0F 13 ;

TITLE POST-ACCIDENT SAMPLING SYSTEM l

STRIPPED-GAS AND DILUTED RCS I

n. Close RC-V-10. []

o. Turn RC-V-11 clockwise to CLOSED. []

p. Open RC-V-8.1, V-2 and V-4. []

q. Adjust RC-VREL-2 until RC-FI-2 indicates 100% flow or 200 cc/ min. []

Flush with domin water for 1 minute. []

r. Close RC-V-2. []

F

s. Terminate flushing by closing the following valves. []

RC-V-8.1

RC-V-8.2

RC-VREL-2

RC-V-4 ..

20. Securing system l b

a. Close sample cooler water. []

b. Turn off any fill station lights. []

c. Turn off amergency ventilation. []

d. Process the data according to Procedure EP RB-15:F. []

e. Check with OSC for any changes in conditions []

then exit Post Loca Room with the same precautions as access.

f. When exiting through Motor Repair Shop close the []

bottle Isolation Valves for the Sentry gas supplies.

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', [VfSf0N DATE 8/26/85 PAGE 12 0F 13 mLg. POST-ACCIDENT SAMPLING SYSTEM STRIPPED-GAS AND DILUTED RCS

g. Note the pressures of the gas supply bottles.

Argon psig Cal Gas 2 psig Cal Gas 1 psig

h. If this procedure has been used for a drill or training the following steps should also be included as appropriate:

1) Reopen LSP shield door by attaching come-a-long []

and strap to other end and open.

2) Release brake on wench next to motor repair shop. [ ]

3) Take come-a-long and strap to penetration shield []

door, attach to door and eye ball in floor and open door. Return come-a-long to Sentry Room.

4) Restock Emergency Locker on 85' Elevation with []

any clothing, dosimetry or respirator /facemasks used during the drill.

5) Return keys to Rad Foreman's office. [- ] ./

REFERENCES

1. Sentry Equipment Corp. High Radiation Sampling System Operating and Maintenance Manual.

APPENDICES

1. Valves for Obtaining Samples from Reactor Coolant.

I 1

l l

l i

i DC0124 12X

l 1 AND 2 DIA8LO CANYON POWER PLAN) UNIT NO(S) Sf0N3

- DATE 8/26/85 PAGE 13 0F 13 m LE. POST-ACCIDENT SAMPLING SYSTEM STRIPPED-GAS AND DILUTED RCS i APPENDIX 1 VALVES FOR OBTAINING SAMPLES FROM REACTOR COOLANT REMOTE PLANT REMOTE SOURCE REMOTE FLUSH LSP SAMPLE SAMPLE ISOLATION VALVE ISOLATION VALVE ISOLATION VALVE SOURCE VALVE SOURCE (RPIV) (RSIV) (RFIV) (SSV)

RC Hot Leg 1 FCV-9351 A FCV-692 FCV-1416 RC-V-1.1 RC Hot Leg 4 FCV-9351 8 FCV-692 FCV-1416 RC-V-1.1 PZR Liquid FCV-9350 8 FCV-693 FCV-1417 RC-V-1.2 PZR Steam FCV-9350 A FCV-694 FCV-1418 RC-V-1.3 RHR Pump 1-1 Discharge FCV-9353 A FCV-1413 FCV-1419 RC-V-1.4 RHR Pump 1-2

(. Discharge FCV-9353 8 FCV-1413 FCV-1419 RC-V-1.4 VCT Liquid FCV-137 FCV-1412 FCV-1420 RC-V-1.5 l

DC0124 13X

o l NUMBER EP RB-15:C

/, }3W3 Pacific Gas and Electric Company REVISION 3 DEPARTMENT OF NUCLEAR PLANT OPERAT6ONS PAGE 1 0F 11 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE CONTAINMENT AIR SAMPLING APPROVED Y- b 'b~b SAFETY -

PLANT MANAGg/ DATE DISCUSSION The purpose of this procedure is to detail the steps required to make containment air available for gas chromatography and to dilute a containment air sample for isotopic analysis of noble gases, particulates, and radionuclides. This procedure will also detail the steps for a complete system flush and return to the initial valve line up.

After purging containment air through the G.C. and loading the diluter

? valve, this procedure will direct sampling personnel to EP RB-15:0, 8

for gas analysis and to procedure EP RB-15:E, for preparation of the diluted containment air sample for isotopic analysis.

The containment isolation valves FCV-698, FCV-699 and FCV-700 are controlled from the Containment Isolation Valve Panel in the Sentry Room only. These switches require redundant keys to operate. Copies of the keys are located in the Control Room and in the Sentry Room.

PREREQUISITES

1. System was initially lined up as described in procedure EP RB-15:A.

2. Verify that the following annunciator windows sre off on the PCP:

a. LIQUID SAMPLE PANEL HIGH PLENUM PRESS

b. CHEMICAL ANALYSIS PANEL HIGH PLENUM PRES 5

c. CONTAINMENT AIR SAMPLE PANEL HIGH PLENUM PRESS DC0124 1VIII

DIA8t.O CANYON POWER Pt ANT UNIT NO(S) 1 AND 2 ON DATE 6/21/85 PAGE 2 0F 11 TiTt.s. SENTRY POST-ACCIDENT SAMPLING SYSTEM CONTAINMENT AIR SAMPLING

3. The following equipment must be available and operational:

a. Meter-long reach rod

b. A gas tight Sec locking syringe

c. , A 14cc gas vial with a new septum installed

d. Bags, tape, and labels

e. Four channel MBIS Pressure Monitor (CASP-PI-1109)

f. Two crescent wrenches Spare filter assemblies g.

4. Prior to initiating this analyses procedure the G.C. must be prepared according to EP RB-15:D, and needed Calibration Verifications must be completed.

PRECAUTIONS

1. This sampling involves processing of containment air that may be highly radioactive. Precautions should be taken to prevent releases to the sampling environment.

2. Time in a radiation field should be limited to that necessary to perfonn the required operations. During purge and flush periods, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose rate area.

3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.

PROCEDURE

1. Valve Lineup

a. Containment Atmosphere Sample Line Heating

1) Proceed to the CCP and position the FUNCTION []

SELECT from 0FF to SF1-3/GGO.

2) Observe the following:

a) The POWER on indicator lights. []

OC0124 2VIII

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON la OATE 6/21/85 PAGE 3 0F 11 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM CONTAINMENT AIR SAMPLING b) The flow monitor 20% and 100% flow []

lights turn on for approximately 25 seconds.

3) Press the PILOT LIGHT TEST pushbutton and []

note which lights are not functional.

4) Turn the HEAT TRACE POWER SWITCH to the ON []

position.

5) Place the temperature select switches for []

EHT 196 and EHT 197 to the down position marked 260'.

b. Rear Panel Access Rolling Shield Closure If the panel rolling shield is closed proceed to Step c.

1) Perfom this valve line-up check in the rear of the shielded panels or verify on lamacoid:

( CAP-V-13 CLOSED (above the G.C.) []

CAP-V-31 OPEN (adjacent to the G.C.) []

CAP-V-32 OPEN (adjacent to the G.C.) []

CASP-V-1 OPEN (overhead on cont. atmos. []

supplyline)

CASP-Y-2 OPEN (lower right part of CASP) []

CASP-V-3 OPEN (lower right part of 3SP) []

' Get the come-a-long from the cabinet and

2) []

attach one end to the pad eye on the east wall and the other to the pad eye on the door.

3) Operate the come-a-long until the rolling []

shield door is blocking the doorway.

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c. Unlock the cabinet door and the drawer lock bar []

under the counter, if locked.

1) Locate a loaded filter assembly for the []

containment air sample.

2) Locate wrenches, labels, and bags. []

d. At the CASP

1) Install a loaded filter assembly into the []

containment air dilution system.

The tubing and with the blue dab of paint on it should be on the bcttom. Tighten but do not damaEe the fittings. Retighten if leakage is noced later.

2) CASP cart / cask connection for pressure indication.

a) Engage and lock a cart / cask on its [] )

quick-disconnects.

b) OPEN the INLET and OUTLET valves and []

CLOSE the Eb' ASS valve on the engaged cart / cask.

c) Connect PI-110g (an MBIS pressure []

monitor) to the engaged cart / cask.

Plug it in and turn the selector switch to the proper cart / cask.

3) Check that PI-1116 is plugged in and turn []

ft on.

4) Close or check closed CASP-Y-17. []

5) Align CASP-V-16 to the CASP-DV-1 position. []

6) Align CASP-DV-1 to CASP-SF-5 position. []

7) Install a new septum on CASP-SF-5. []

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e. At the CCP:

1) Adjust N, pressure regulator to 100 psig as []

indicate 5 on CCP-Gl.

E: This pressure will drop to 80 psig when the eductor is on and Low N PRESS 2

alarm will sound.

2) All 11 of the CCP 3 position valve switches should be CLOSED:

AV-1 [] SV-4.1 []

SV-1.2 [] SV-4.2 []

SV-2.1 [] SV-5 []

. SV-2.2 [] AV-2 []

SV-3.1 [] SV-10 []

SV-3.2 []

3) The EXERCISE STOP button should be in the IN []

position. Verify red light in knob is on.

4) Annunciator Test a) Push RESET []

b) Push and hold the TEST button and verify:

(1) The alarm sounds. []

(2) All labeled windows flash except []

ISOLATE SAMPLE FLASK window which glows steady.

c) Release the TEST button and verify that []

the ISOLATE SAMPLE FLASK window goes off.

d) Push the ACK button and verify the alarm []

is silenced.

e) Push the RESET button and verify that []

all windows are off.

f. At the POST LOCA CNT ISOLATION PANEL all five []

key operated valve switches should be CLOSED.

l l

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2. Sample Flask Evacuation F

a. Close outlet valve of the engaged cart / cask. []

b. Verify that any unused CASP ports located at []

the base of the CASP hve been capped on Unit 1 or that other cart /cas: s are engaged on Unit 2.

c. At the CCP, place the switch for CCP-AV-1 to OPEN. []

(This allows containment pressure to be monitored on CASP-PI-1109.)

d. Change the positions of the following valves:

CASP-DV-1 to Containment Supply []

CASP-V-16 to CASP-SF-5 []

e. Contact the Control Room and request permission to open FCV-700, the sample return containment isolation valve. In succeeding steps FCV-698 and 699 and will be operated also.

Inquire whether the Control Room wants to be notified every J time each valve is operated or only when sampling is completed and containment isolation valves are closed. Also obtain and record containment temperature and pressure from the Control Room.

'F psig

f. Evacuate CASP-SF-5 by opening the following valves:

FCV-700 (key operated - keys located in drawer []

by sink)

CASP-V-17 []

CCP-AV-2 []

l CCP-SV-10 []

l g. When CASP-SF-5 pressure is as low as apparently []

achievable as indicated on CASP-PI-1116, align CASP-V-16 to CASP-DV-1. If vacuum is not held, replace the filter assembly or septum and repeat Steps c. through f.

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3. Sample Purge

a. Open containment isolation valves FCV-699 and []

FCV-698 at the Containment Isolation Valve Panel and notify the Control Room, if requested,

b. Containment air is now being purged through []

the sample panel back to containment. Purge for 5 minutes.

c. At the CCP, close CCP-SV-10 and record containment []

air pressure as indicated on CASP-PI-1109 and sample time.

CASP-PI-1109 psig Sample Time

d. Close FCV-698, 699 and 700. []

e. Record the temperature indicated on THT 196.

(_.

C

f. The G.C. should be prepared to accept a sample at point EP RB-15:D Section 4.F.

g. Continue with Sample Analyses, using EP RB-15:D; then return to this point.

4. Sample Dilution

a. Align CASP-DV-1 to CASP-SF-5.7 N will flush []

the sample aliquot into CASP-SF-5 through the removable filter assembly.

b. When the pressure in CASP-SF-5 as indicated on []

CASP-PI-1116 is 14.70 psia, or as high as achievable, whichever is first, close CASP-V-17.

5. Initial G.C. Flushing - after verifying with other operator that all G.C. analyses are complete

a. If the G.C. was used for :ontainment atmosphere analysis then perfonn the following steps, otherwise skip to step b.

1) Open FCV-698, 699 and 700. []

l

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2) At the LSP, align RC-V-15 to CASP TO GAS [] j CHROMAT position.

3) At the G.C. control panel depress SAMP switch' []

and enter "13" to start argon flush of sample line back to CASP. Flush for 2 minutes.

4) Terminate argon flush by entering "14" at []

the G.C. control panel then release SAMP switch.

5) At the LSP, align RC-V-15 to CLOSED position. []

b. Align CASP-V-16 to CASP-SF-5. , []

c. Open CCP-SV-10 and flush removable filter assemtby []

for 1 minute.

d. Close containment isolation valve FCV-699. []

e. Open CCP SV-5. []

f. Change the positions of the following valves:

Align CASP-DV-1 to Containment Supply []

Align CASP-V-16 to CASP-DV-1 []

g. At the CCP, close CCP-AV-2 and CCP-SV-5.

h. Open containment isolation valve FCV-699 and []

flush line with nitrogen for 2 minutes.

4

1. Close CCP-SV-10 and CCP-AV-1. []

6. Sample Handling l a. Survey the removable filter assembly and CASP-SF-5 []

. to determine contact dose rates.

[Under worst case conditions, the_ contact dose rate of the filter, using a teletector, will be about 165 mR/hr. The contact dose rate at centerline of CASP-SF-5 will be about 44 mR/hr.]

b. Position the exhaust duct as close as possible to []

the removable filter assembly.

l DC0124 8VIII

-- _ .--.i - - ,-. , 4--w,-w-w,., ,--.--.ms---- , -y. -.i-..

N DIA8LO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 R S ON

- DATE 6/21/85 PAGE 9 0F 11 SENTRY POST-ACCIDENT SAMPLING SYSTEM !

TITLE.

CONTAINMENT AIR SAMPLING l

c. Using the crescent wrenches, disconnect the []

filter assembly from the system, then separate the assembly into two halves and place the two halves in a double bag, seal, and survey.

1) Place a prewritten label on the bag. The []

label should have the name of the sample, dose rate, time, containment air pressure, and the initials of the sampler.

2) Store the sample to minimize exposure from []

it.

3) Inform PASS Supervisor that CA sample is []

l ready for transport. -

d. Install a new filter assemb'y into the system []

making sure the connections are tight. ,

e. Partially evacuate a septum sealed 14cc gas vial []

.- by withdrawing 2cc from it using a syringe.

. (~

f. Flush a 5 m1 gas tight syringe by inserting its []

, i needle into the septum of CASP-SF-5, withdrawing Ice and injecting it again.

g. Using the flushed syringe withdraw a 2cc sample []

aliquot from CASP-SF-5.

h. Inject the syringe contents into the evacuated []

14cc gas vial.

i. Place the gas vial into a bag, seal and survey it. []

j. Place a prewritten label on the bag. The label []

shall have the name of the sample, dose rate, time, cont. air pressure, volume of 1 ml and the initials of the sampler.

k. Store the sample to minimize exposure from it. []

7. Final G.C. Flushing l

a. Align CASP-V-16 to CASP-SF-5. []

k DC0124 9VIII

\

orAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON ,

DATE 6/21/85 PAGE 10 0F 11 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM CONTAINMENT AIR SAMPLING

b. Open the following valves:

CCP-AV-2 []

CCP-SV-10 []

CASP-V-17 []

c. Evacuate CASP-SF-5 until vacuum is as low as []

achievable as indicated on CASP-PI-1116

d. Close CCP-AV-2 and allow2N to fill CASP-SF-5. []

e. Repeat Steps 6.b. through d. above once more. []

f. Close CCP-SV-10. []

g. Open the OUTLET valve on the engaged cart / cask. []

h. Open CCP-SV-10. []

i. Open CCP-SV-1.2 and allow N to flush the line [] ,)

2 for 2 minutes.

8. Teminate flushing by closing the following valves:

CCP-SV-10 []

CCP-SV-1.2 []

9. Change the positions of the followirg valves:

CASP-V-16 to CASP-DV-1 []

CASP-DV-1 to CASP-SF-5 []

10. Turn 0FF the CASP PI-1116 and CASP-PI-1109. []

11. At the Containment Isolation Valve Panel'CLOSE the following .

valves and notify the Control Room that they are closed and return the keys to the drawer:

FCV-698 []

FCV-699 []

FCV-700 []

DC0124 10VIII

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h ON

'.. DATE 6/21/85 PAGE 11 0F 11 rats. SENTRY POST-ACCIDENT SAMPLING SYSTEM CONTAINMENT AIR SAMPLING l

12. At the CCP turn the FUNCTION SELECT switch to 0FF []

and deenergize the heat tracing.

13. If all CAP manipulations are finished check with LSP []

operutor then turn CMP power switch to 0FF.

14. Process the data according to procedure EP RB-15:F. []

REFERENCES

1. NUREG 0737

2. Diablo Canyon Shielding Review.

(.

DC0124 11VIII

- - - , , c - - , - - - , - , , , - - , . , . , - - - - , - ,w - - , - , - - - -

NUMBER EP RB-15:D

.T. 39G Pacific Gas and Electric Company REVISION 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 11 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY OPERATING PROCEDURE POST-ACCIDENT SAMPLING SYSTEM --

TITLE GAS CHROMAT0 GRAPHIC ANALYSIS APPROVED TE IDOS-66 TO ,

PLANTMANAGE4/

DATE SAFETY DISCUSSION The purpose of this procecure is to detail the steps required to determine the dissolved hydrogen concentration in reactor coolant, the percent hydrogen concentration and oxygen concentration in containment air by gas chromatography. This procedure will detail gas analysis from RC-V-15 on the LSP to the Gas Chromatograph. The sample gas for analysis should be prepared according to any of the following procedures:

EP RB-15:8 EP RB-15:C

(

PREREQUISITES

1. The Gas Chromatograph (G.C.) should be in the ON or STANDBY condition for a minimum of 30 minutes before sample analysis.

2. Carrier gas (Ar) should be available with cylinder outlet pressure 1000 psig.

PRECAUTIONS

1. Monitoring with a dose rate instrument should be done during the transfer of sample to the G.C.

F DC0109 1X

1 AND 2 NUMBER EP RB-15:0 0iAsLO CANYON POWER PLANT UNIT NO(S)

REVISION 3 DATE 8/27/85 I PAGE 2 0F 11 7 rtg. POST-ACCIDENT SAMPLING SYSTEMS --

GAS CHROMAT0 GRAPHIC ANALYSIS PROCEDURE

1. Analysis Program

a. Release all pushbuttons and depress the CLEAR []

button,

b. Check that the following program is in memory []

by entering the two digit STEP number and verify that the TIME and CODE numbers are as shown below. Do this for each STEP. If the memory is correct, proceed to Step 2 Platen Stabilization.

STEP TIME CODE 01 00:01 03 02 00:02 25 03 00:10 01 04 04:00 00

c. If the program is not correct, enter the. program as follows:

')

1) Depress ENTER and CLEAR [] >

2) Enter the above program into meircry, by []

entering the two digit pairs in the sequence shown above, for one iins.

g: If an entry error is made, depress CLEAR to blank display and re-enter the entire line.

3) Release ENTER, depress CLEAR and repeat []

Step 1.b.

4) Repeat Steps 1) through 3) fc, remainder []

of lines as necessary,

d. If technician deems it necessary to change progranning times to acconnodate peaks, they may be varied with identification on trace as to actual program used.

2. Platen Stabilization

a. Depress MAN and CLEAR []

DC0109 2X

l 1

- )

NUMBER EP RB-15:D OlASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 i REVISION 3 DATE 8/27/85 )

PAGE 3 0F 11 7,7g. POST-ACCIDENT SAMPLING SYSTEMS --

GAS CHROMAT0 GRAPHIC ANALYSIS

b. Check to see if the G.C. has stabilized by doing the following:

1) Select attenuation factor of 250 (25 x 10) []

2) Enter "01" and then "35" to display set []

point of platen temp and record for a minimum of 30 seconds.

3) Enter "45" to display actual platen temperature []

and record for a minimum of 30 seconds.

g: Stabilization is complete when platen set-point and actual temperature are within 1/2 grid marking of each other as indicated on the G.C.

chart recorder only.

4) Enter "00" and mark chart recorder on the []

j G.C. with date, time, and initials.

3. Calibration Verification If G.C. Calibration Verifications have been done within the last 7 days, proceed to Step 4. Sample Analyses.

a. Hydrogen Verification - only verification needed when analyzing offgas

1) Select loop No. 1. []

2) Enter "23" to evacuate the G.C. until the []

red HI VACUUM light is on.

a) Cycle loop selector through loops 2, []

3, and 4, pausing at each loop and evacuating until the HI VACUUM light is on.

b) Cycle a minimum of 3 times through []

loops 1, 2, 3, and 4, pausing at each loop.

c) Select loop No. 1. []

DC0109 3X

1 AND 2 NUMBER EP RB-15:0 olA8LO CANYON POWER #LANT UNIT NO(S)

REVISION 3 OATE 8/27/85 PAGE 4 0F 11 TITLE POST-ACCIDENT SAMPLING SYSTEMS --

GAS CHROMAT0 GRAPHIC ANALYSIS

3) Enter "24" to terminate evacuation of the []

G.C.

4) Select attenuation factor of 500 (5 x 100) []

for the 10% H 7 source or 5 (5 x 10) for the 2000 ppm H source.

2

5) Depress CAL-1 switch for 10% H 7 source, or []

CAL-2 switch for 2000 ppm H2 source, and wait 10 seconds after amber LOW VACUUM light is on. Cycle through loops three times.

6) Release CAL-1 or CAL-2 switch and wait 10 []

seconds.

7) Start the LAN recorder. []

8) Depress AUTO switch to on (in) and press []

Cl. EAR. Wait until the G.C. program has completed. During this time interval, identify the L&N recorder trace with the date/ time, gas used. loop number, attenuation j factor and operator initials.

9) Release AUTO switch to off (out) position. []

Press CLEAR and enter "00".

10) Repeat Steps 8) and 9) for subsequent loops. []

11) Stop the L&N recorder. []

12) Calculate the hydrogen peak height on data sheet as follows:

peak height = (Trace peak height - baseline) x attenuation 100 l

l 13) Compare the peak height calculated against []

the value shown on the concentration versus peak height curve for the same attenuation factor and calibration gas. The values should be within 10 percent of each other.

l l

DC0109 4X l

I

i 1 AND 2

" EP RB-15:D OlA8LO CANYCN POWER PLANT UNIT NO(S) R S ON

+

DATE 8/27/85 l PAGE 5 0F 11 TITLE _ POST-ACCIDENT SAMPLING SYSTEMS -- !

GAS CHROMAT0 GRAPHIC ANALYSIS l l

1

b. Oxygen Verification

1) Ensure that a loaded filter assembly is []

installed.

2) Change the positions of the following valves:

CASP-DV-1 to Containment Supply []

CASP-V-16 to CASP-SF-5 []

3) Contact the Shift Foreman and request [] l pemission to open FCV-700, the sample return containment isolation valve.

4) Evacuate CASP-SF-5 by opening the following valves:

FCV-700 (key operated) []

CASP-V-17 []

CCP-AV-2 []

(

CCP-SV-10 []

5) Evacuate CASP-SF-5 until pressure is as []

low as apparently achievable as indicated on CASP-PI-1116.

6) Remove fitting and septum from the end of []

SF-5 to allow ambient air to purge through sample panel and into containment. Purge for 2 minutes.

7) Close CCP-SV-10 and FCV-700. [] }

8) Depress SAMP switch and verify red sample []

light is on.

9) Align RC-V-15 to CASP TO GAS CHROMAT. [] l

10) Select loop No.1. []

DC0109 SX

.. _ . ~ _ _ _ _

1 AND 2 NUMBER EP R8-15:0 "I DIA8LO CANYON POWEQ Pt. ANT UNIT NO(S) REVESION 3

, DATE 8/27/85 PAGE 6 0F 11 TITLE POST-ACCIDENT SAMPLING SYSTEMS --

GAS CHROMAT0 GRAPHIC ANALYSIS

11) Enter "23" to evacuate the G.C. until the []

read HI VACUUM light is on.

a) Cycle loop'selectcr through loops 2, 3, []

and 4, pausing at each loop and evacuating until the HI VACUUM light is on.

b) Cycle a minimum of 3 times through []

loops 1, 2, 3, and 4, pausing at each loop.

c) Select loop No. 1. []

12) Enter "24" te terminate evacuation. []

13) Selectattgnvationfactorof100(1x100). []

14) Cycle. loop selector through loops 1, 2, 3, []

and 4, pausing,at each loop. Cycle 3 times.

a) Select loop No. 1. [] j

15) Align RC-V-15 to the CLOSED position and []

release SAMP switch.

16) Start the L&N recorder, wait 5 seconds. []

17) Depress AUTO to on (in) position and press []

CLEAR.

a) Wait until the G.C. program has completed.

During this time interval identify the recorder trace with sample name, date/tix.s loop number, attenuation factor and operator initials. '

18) Relaase AUTO switch to off (out) position. []

Press CLEAR and enter "00".

19) Select next loop and repeat steps 17 and 18 []

for all four loops.

20) Stop the L&N recorder. []

i l

DC0109 6X

1 AND 2 NUMBER EP RB-15:0 DIA6LO CANYON POWER Pt. ANT UNIT NO(S) PEVISTON 3

. DATE 8/27/85 PAGE 7 0F 11 TITm. POST-ACCIDENT SAMPLING SYSTEMS --

GAS CHROMAT0 GRAPHIC ANALYSIS

21) Calculate the net peak height and detennine []

the oxygen concentration from the appropriate calibration curve, on the data sheet.

22) Record the net peak height on the recorder []

trace.

23) Replace septum at end of SF-5. []

c. Null Verification

1) Depress SAMP switch and enter "23" to evacuate []

the G.C. until the red HI VACUUM light is on.

2) Cycle through each loop and evacuate until []

the red HI VACUUM light is on.

3) Enter "13" to initiate argon purge. []

4) Cycle loop selector through loops 1, 2, 3, []

and 4, pausing at each loop. Cycle 3 times.

g Select loop No.1.

5) Enter "14" to terminate the purge. []

6) Enter "24" to terminate the evacuation. []

7) Enter "00". []

8) Depress AUTO to on (in) position and press []

CLEAR.

a) Wait until the G.C. program has completed. []

During this time interval identify the recorder trace with sample time name, i

date/ time, loop nuter, attenuation factor j

and operator initials.

b) Select subsequent loop. []

j c) Adjust attenuation, if necessary. []

d) Depress CLEAR to reinitiate G.C. program. []

[ e) Repeat 8) for loops 2-4 []

0C0109 7X l .. . _ _ _ .. . .

OlA8LO CANYON POWED PLANT UNIT N0(S) 1 AND 2 ON

. DATE 8/27/85 PAGE 8 0F 11 riytg. POST-ACCIDENT SAMPLING SYSTEMS --

GAS CHROMAT0 GRAPHIC ANALYSIS

9) Release AUTO switch to off (out) position. []

Press CLEAR and enter "00". p

10) If greater than 10% of sampled air oxygen []

concentration is recorded on trace, the system is not thoroughly purged. Repeat Steps 1) through 9) one time.

11) If greater than 10% of sampled air oxygen is []

still present contact C&RP supervision while continuing with analyses.

12) Release SAMP switch to off position. []

13) Stop t'he L&N recorder. []

4. Sample Analysis

a. Depress SAMP switch and verify red sample light []

is on. Check AUTO released (out),

b. For CA sample align RC-V-15 CASP TO GAS CHROMAT. [] l For offgas V-15 remains CLOSED. J

c. Select loop hu. 1. []

d. Depress CLEAR and enter "23" to evacuate the G.C. I until the red HI YACUUM light is on.

1) Cycle loop selector through loops 2, 3, and []

4, pausing at each loop and evacuating until the HI VACUUM light is on.

2) Cycle a minimum of 3 times through loops 1, []

2, 3, and 4, pausing at each loop.

3) Select loop No. 1. []

l

e. Enter "24" to terminate evacuation. []

f. Select attenuation factor of 500 (5 x 100) or []

current attentuation for sample.

0C0109 8X ,

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON i DATE 8/27/85 PAGE 9 0F 11 POST-ACCIDENT SAMPLING SYSTEMS -- l 7,7tg.

GAS CHROMAT0 GRAPHIC ANALYSIS

g. When the offgas sample is available at RC-V-15 []

align RC-V-15 to LSP TO GAS CHROMAT.

h. Cycle loop selector through loops 1, 2, 3, and []

4, pausing at each loop.

1) Cycle 3 times. []

2) Select loop No. 1. []

i. Release SAMP switch and align RC-V-15 to the []

CLOSED position and infonn other operator it is, closed.

J. For offgas analyses record the pressure on RC-G-2.1. Reading: psig

k. Start the LAN recorder, wait 5 seconds. []

1. Depress AUTO to on (in) position and press CLEAR. []

( 1) Wait until the G.C. program has completed. []

During this time interval identify the recorder trace with sample name, date/ time, loop number, attenuation factor and operator initials.

2) Select subsequent loop. []

l 3) Adjust attenuation, if necessary. []

4) Depress CLEAR to reinitiate G.C. program. []

5) Repeat 1. for loops 2-4. []

m. Release AUTO switch to off (out) position. []

Press CLEAR and enter "00".

n. Stop the L&N recorder. []

o. Calculate the net peak heights on worksheets and []

detennine the hydrogen concentration and oxygen concentration from the appropriate calibration curve.

l DC0109 9X l

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fSf0N

. DATE 8/27/85 i PAGE 10 0F 11 TITLE POST-ACCIDENT SAMPLING SYSTEMS --

GAS CHROMAT0 GRAPHIC ANALYSIS

p. Record the net peak height on the recorder trace. []

If another sample still needs to be analyzed return to referencing procedure and complete purging when other analyses is finished,

q. Purge the G.C. residual gas as follows:

1) Depress SAMP and enter "23" and evacuate []

the G.C. until the red HI VACUUM light is on.

2) Cycle through each loop and evacuate until []

the red HI VACUUM light is on.

3) Enter "13" to initiate argon purge.. []

4) Cycle loop selector through loops 1, 2, 3, []

and 4, pausing at each loop. Cycle 3 times.

5) Enter "14" to terminate the purge. []

6) Enter "24" to terminate the evacuation. [] ;

7) Enter "00". []

l 8) Release SAMP switch to off position. []

r. After final use and flush of G.C. by both operators:

l

1) Shutdown the instrument by turning off the []

power to the TCD.

2) Secure the gas supplies for the G.C.

I a) CLOSE the 3 root valves next to the CAP. []

l b) CLOSE CAP-V-14. []

s. Return to the referencing procedure.

For stripped-gas, this is EP RB-15:B. For Containment Air, this is EP RB-15:C.

I l

DC0109 10X e

1 AND 2 DiAaLO CANYON POWEF. PLANT UNIT NO(S) fhf0N 3 DATE 8/27/85 PAGE 11 0F 11 mLa POST-ACCIDENT SAMPLING SYSTEMS --

GAS CHROMAT0 GRAPHIC ANALYSIS REFERENCES

1. Sentry Equipment Corp. High Radiation Sampling System Operating and Hafntenance Manual.

(

i DC0109 11X 1

I --- - . - . . . - - - - . , . _ - - . . . - . . , , - --_. . - _ -

NUMBER EP RS-15:E

. 3GW3 Pacific Gas and Electric Company REVISION 3 ,

A DATE 8/27/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS I l PAGE 1 0F 12 OIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE POST-ACCIDENT SAMPLING SYSTEM l l

TITLE. LIQUID AND GAS SAMPLE HANDLING W IMPORTANT APP OvEO. 7F d 7A4 , ID- M 4 c, TO ,

PLANTMANAGERg DATE - SAFETY !

l SCOPE This procedure provides guidance for safely handling post accident I liquid samples obtained from the Reactor Coolant System (RCS) using the SENTRY PASS. The diluted liquid sample from the RCS is aliquotted. The aliquot may be used for boron or for y-assay.

Further dilutions for y-assay are done in the hot cell. Likewise, steps for preparation of diluted containment air samples for counting are also detailed. This procedure and changes thereto require PSRC review.

( DISCUSSION Based on worst-case post accident assumptions regarding sample radioactivity content, special precautions may be required for

handling RCS and containment air samples acquired using the Sentry PASS. Sample aliquots are transferred by precision pipets to a dilution vial for radiological counting or an appropriate reaction flask for chemical analysis. These flasks may be kept inside the hot cell throughout the procedure to minimize personnel exposures and also

to contain the airborne radioactivity generated within the hot cell l area. Control of airborne activity is accomplished by use of an

! overhead ventilation duct which creates a slightly negative pressure inside the enclosure. After all sample manipulations are completed, the radioactive waste solutions may be flushed down the Sentry Room sink via the receiver funnel drain valve and, if necessary, the inside surfaces of the hot cell may be sprayed down to reduce the contamination levels within the sample handling area.

l PREREQUISITES AND PRECAUTIONS

1. Personnel assigned to conduct this procedure should be familiar with the considerations of handling highly radioactive liquid and

. gas samples and shall be experienced with the analytical chemistry techniques employed in this procedure. Also, any individual perfoming this procedure should be capable of:

DC0294 IX

ciAst.o CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 ON DATE 8/27/85 2 0F 12 PAGE TiTut POST-ACCIDENT SAMPLING SYSTEM LIQUID AND GAS SAMPLE HANDLING

a. Making doses rate measurements with portable survey instruments.

b. Assessing response and basic trends of continuous air monitoring equipment.

c. Taking actions based on items 1.a and 1.b.

2. Unless conditions are known to warrant less stringent precautions, complete protective clothing and accident dosimetry (including high range and extremity dosimeters) will be required.

Lapel air samplers are also recommended. Full respiratory protection equipment (SCBA) may also be necessary.

3. To minimize time spent in hot sample handling, ensure availability of the required equipment for performing applicable portions of this procedure. This includes sample vessels, pipets, handling tools, reagents, etc. A comprehensive listing of these supplies is provided in a check list format in Appendix 1 to this procedure to facilitate the review.

4. When the liquid sample is handled, there is a possibility that local radiation levels and airborne radioactivity could increase. )

Since the sample is to be contained within the hot cell, the j increases should not be too high; however, as precautionary measure, all individuals within the Sentry Room should have functioning respirators. Monitorin survey instruments (for dose rates)g andshould be performed any available using CAM system (for airborne) for early identification of potential problems.

5. This procedure is designed to permit all sample handling to be

! performed by the use of tongs or other remote handling devices.

! Unless the samples are surveyed and known not to present a l

significant source of exposure to the Tiiigers, hands or other extremities, no sample manipulations involving direct hand contact should be attempted.

l l

t

{

OCO294 2X l

^O DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RS.5:E REVISION 3

. DATE 8/27/85 PAGE 3 0F 12 Ting POST-ACCIDENT SAMPLING SYSTEM LIQUID AND GAS SAMPLE HANDLING PROCEDURE

1. Preparation of Sample Enclosure and Sink Area This section covers the preliminary steps required beford performing actual liquid sample manipulations. It is important that all required handling equipment and reagents to be employed are available prior to handling the liquid sample in order to minimize time spent working around hot samples within the hot cell.

a. . Turn on spectrophotometer and allow it to warm up. []

Note the time .

b. Initial Survey of Sample Enclosure and Sink Area

1) Perform a radiation survey of the hot cell []

area to verify that no highly radioactive sample material remains inside or around the enclosure from a previous use. If an indication f of radioactive sample materials is found, these

,. materials should be promptly removed as set l forth below under " Clean-Up" in Section 6 of this procedure.

I

2) Visually inspect the inside of the hot cell []

for unwanted material and for cleanliness.

- If material remains, remove and store or discard it, whichever is appropriate.

c. Acquisition of Required Supplies Assemble the necessary supplies, equipment, etc. to perform the required steps. A listing of these supplies is presented in Appendix 1 to this procedure for the following preparation 3nd analysis categories.

1) General Sample Handling and Manipulations []

2) Radioactive Sample Dilution Supplies. []

3) Boron Sample Analysis Supplies []

All glassware needs to be clean and dry prior to use.

i If necessary to clean, rinse with acetone and dry with instrument air, i

l DC0294 3X

DIA8tO CANYON POWED PLANT UNIT NO(S) 1 AND 2 NUMBER EP RS-15:E REVISION 3 DATE 8/27/85 PAGE 4 0F 12 Tiru! POST-ACCIDENT SAMPLING SYSTEM LIQUID AND GAS SAMPLE HANDLING

4) Dilution of offgas for isotopic analysis []

c. Preparation of Hot Cell Area for Use

1) Open the access door to the hot cell. []

2) Carefully position shielded sample holder []

br!ck for use in conjunction with pipet operations.

3) Install an uncapped, clean 20 cc liquid []

scintillation vial into its appropriate [

sample port within the sample holder brick.

Leave the cap and sealing tape outside the hot cell for later use. -

4) Install two 50 ml Erlenmeyer flasks into [] [

their appropriate sample ports within the sample holder brick. Leave rubber stopper caps (one for each 50 m1 flask) outside the hot cell for later use.

5) Install two clean, uncapped, prewiped 1 cm [] [

path length photocells into the appropriate sample port within the sample holder brick, Keep the cap plugs available outside the hot cell for later use.

[Becarefulnottoscratchthetransmissionsurfaces nor to deposit extraneous material (e.g. - powder or lint) especially from gloves.]

6) Verify air flow (a piece of paper is suggested) []

into the elephant trunk vent shroud.

7) Connect ventilation shroud to top of hot cell. [] -

8) Prepare remaining equipment, materials, []

reagents, etc. required for the planned sample manipulations and analyses.

I l

l OCO294 4X l

a O c AsLo canyon PcWEQ PLANT UMT No(S? 1 AND 2 ON

. DATE 8/27/85 PAGE 5 0F 12 TITLE POST-ACCIDENT SAMPLING SYSTEM LIQUID AND GAS SAMPLE HANDLING

2. Obtaining a Liquid Sample from the cart / cask I

a. Place an R0-2A over the hot cell and determine the ambient

background response of the R0-2A. Note the reading and then remove the R0-2A.

R0-2A Reading: mR/hr (ambient background)

b. Move the cart / cask to the sink area and set the []

brake,

c. Uncover the sample vial by rolling the radiation []

shield away from the sample cavity.

1) Transfer the bottle containing the diluted []

reactor coolant to the hot cell and remove the lid.

2) Close the cask and move it away. []

3) Close the access door to the hot cell. []

!I

d. Measure the radiation level with the teletector one foot above sample and record the reading.

mR/hr (ambient background plus sample)

e. Calculate the net sample reading by subtracting the value of Step 2.a. from the value of Step 2.d.

, mR/hr (Step 2.d.)

mR/hr (Step 2.a.)

j mR/hr (net sample reading)

Analysis of Liquid Sample for Baron b 3.

Do not use glass pipets for following analyses.

a. Pipet 2 ml each of the 2 and 10 ppm boron standard []

~

t solution into separate 50 ml Erlenmeyer flasks.

, Pipet 2 al of domin water into a third 50 ml Erlenmeyer flask. (These flasks should be outside the hot cell.)

DC0294 SX r

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

DIA8tO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 NUMBER EP RS-15:E REVISION 3 DATE 8/27/85 PAGE 6 0F 12 TITLE. POST-ACCIDENT SAMPLING SYSTEM LIQUID AND GAS SAMPLE HANDLING

b. Open the access door on top of the hot cell. []

c. Pipet a 2 ml aliquot of the RCS Ifquid sample []

solution from the sample bottle into each of p the 50 ml Erlenmeyer flasks within the hot cell.

d. Pipet 10 ul of concentrated hcl to each flask, [J stopper and swirl. Allow flasks to cool (s 2 minutes).

e. Add 10 rr.1 of concentrated H SO into each flask, []

stopper and swir1. Allow f$ asks to cool to room temperature (s 15 minutes).

f. Add 10 ml of carminic acid solution into each flask. []

', g. Stopper again and, using tongs, swirl to mix well. []

f

h. Between approximately 40 and 55 minutes after the []

carminic acid addition, transfer solutions to clean, prewiped 1 cm cuvettes and carefully cap them.

This may be accomplished using a 5 ml pipet set for 4 m1, and, in the case of the " hot" sample y the capping and cuvette transfer must be perfonned using tongs.

While color is developing perform liquid isotopic dilution.

1. Set the spectrophotometer to a wavelength of []

585 nm and adjust the blank for 0% absorbance.

Absorbance should be read 45 to 60 minutes after carminic acid is added.

l J. Read the boron standard to verify agreement with []

calibration graph within 5%. If this agreement is not obtained continue the analysis but inform supervision imediately.

~

l l

t .

DC0294 6X -

i -

D J

oiAsto canyon POWER PLANT UNIT No(S) 1 AND 2

, [0N 3 DATE 8/27/85 PAGE 7 0F 12 TITLE. POST-ACCIDENT SAMPLING SYSTEM 1 LIQUID AND GAS SAMPLE HANDLING

k. Read the absorbance of the sample (s). Record []

results and return the sample (s) to the hot cell.

(AbsorbanceRCS)

Calibration Graph (Standard Curve) ppmBoronRCS(diluted)= ppm Record this inforination on the data sheet in EP RB-15:F.

1. Notify the PASS Supervisor of results of sample []

analysis.

m. Turn the spectrophotometer off. []

4. Dilution and Preparation cf Liquid Sample for Radioassay This step involves selection and r"lution of a sample aliquot to j , obtain a counting geometry of 10 mis liquid in a 20 m1 vial. The sample volume is based on the exposure rate recorded in Step 2.e.

a. Select the appropriate pipet tip size and pipet volume as follows:

r Pipet Approx. Step 2.g. Reading Check 5 ml < 1.6 mR/hr ;;

I m1 > 1.6 mR/hr but < 16 mR/hr 100 ul > 16 mR/hr but <~ 160 mR/hr 10 ul > 160 mR/hr ll

b. Open the access docr on top of shielded sample []

enclosure.

t

c. Using the pipet volume setting chosen in Step 4.a. []

above, obtain this volume of RCS liquid sa gle from the sample bottle, keeping hands as far away as possible from the " hot" sample liquid.

4

! DC0294 7X

DIA8LO CANYON POWEQ PLANT UN!T NOIS) 1 AND 2 NUMBER EP R2-15:E REVISION 3 DATE 8/27/85 l PAGE 8 0F 12 TITLE POST-ACCIDENT SAMPLING SYSTEM LIQUID AND GAS SAMPLE HANDLING

d. Slowly discharge the aliquot into the empty 20 cc []

liquid scintillation vial previously placed within the shield brick. Discard the pipet tip.

[ Dispose of materials that have contacted highly contaminated mediums separately from those that have not.]

e. Using the appropriate pipet and tip, add sufficient []

domin water to the 20 cc vial to bring the total liquid volume to 10 ml. Add 10 mis to the 1091 or 100ul aliquot.

f. Remove the diluted sample from the hot cell with []

tongs. ,

g. Cap the vial. Wipe it and seal it with tape. []

h. Screen survey the vial to verify countability []

(<,5 mR/hr contact),

i. Label and double bag the vial noting the dilution, [] )

the aliquot volume used, and the radiation level measured. Place radioactive sticker on bag.

j. Set the sample aside and inform PASS Supervisor []

sample is ready for transport to the TSC or counting room.

5. Dilution and Preparation of Off-gas for Isotopic Analysis I Perform steps below only if sample vial dose rate is >5 mR/hr.

a. Obtain a clean 14 cc gas sample vial with a []

septum installed and using a 5 ml gas tight

syringe, withdraw I cc of air from the vial and i discharge the air from the syringe.

b. Insert the syringe into the off-gas sample vial []

and remove lec. Shut the valve on the syringe before removing the vial. ,

l l

DC0294 8X

--"T"' - +- - - - - - - - --, , _ , ,

_ _ _ _ , . - , . - . _ g

N OtA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON 3

.\ DATE 8/27/85 PAGE 9 0F 12 muE. POST-ACCIDENT SAMPLING SYST:M LIQUID AND GAS SAMPLE HANDLING 4 c. Insert the syringe into the counting vial; open []

the valve on the syringe and inject the contents into the vial,

d. Survey the newly prepared vial; if the dose rate []

is >5 mR/hr, repeat Steps a. through e. above, ,

i diluting into new clean 14 cc gas sample vials until the sample vial is less than 5 mR/hr, keeping track of the number of dilutions.

e. Place a label on the counting vial repeating the []

infonnation as found on the original vial.

Calculate the new dilution factor by multiplying all dilutions together. Each dilution 15:1. Record this information on the data sheet,

f. Inquire from supervision whether the original []

sample vials should be discarded or stored for future use and perform as directed.

6. Cleaning and Securing the Hot Cell

('

a. Cleaning I

1) Disposal of Radioactive Sample Residues During these actions, the radiation levels in the sink area and airborne concentrations within the Sentry Room may become higher since the sample materials are being discharged via the sink.

! a) Turn on sink drain faucet to provide a []

slow, steady stream.

b) Open the access port on top of the hot []

cell. Remove sample caps using tongs and empty out the contents of the flasks remaining in the enclosure down the sink drain.

c) Flush out the sample flasks and wash []

off all contaminated handling tools with domin water, caustic or acid wash solutions (as appropriate), followed by a demin water rinse.

l I

DC0294 9X l

I 0iAst.o CANycN WER PLANT UNIT NO(S) 1 AND 2 R f0N

, DATE 8/27/2" PAGE 10 0F 12 TITLE. POST-ACCIDENT SAMPLING SYSTEM LIQUID AND GAS SAMPLE HANDLING d) Perform a general washdown of the hot []

cell to remove contamination. Close the access port when finished inside the hot cell.

e) Store sample flasks, vessels, etc. as []

. " dirty" materials -- not to be used again unless thoroughly cleaned and inspected.

2) Disposal or Storage of Chemicals, etc.

a) Dispose of waste chemicals, materials. []

etc. in a similar fashion as above.

b) Chemicals, reagents and other supplies []

not consumed or compromised during the sarple analyses may be stored for later use. These may be stored in the cabinet space adjacent to the sink area.

b. Securing Equipment b j Return to EP RS-15:8. !

APPENDICES

1. Checklist of Required Equipment and Supplies i

i l

l DC0294 10X

E -

otAss.o CANYON POWER l' ANT UNIT NO(S) 1 AND 2 p

, ON i

DATE 8/27/85 l PAGE 11 0F 12 l POST-ACCIDENT SAMPLING SYSTEM i Tiits. l LIQUID AND GAS SAMPLE HANDLING l

APPENDIX 1 CHECKLIST OF REQUIRED EQUIPMENT AND SUPPLIES GENERAL SAMPLE HANDLING AND MANIPULATIONS CHECK Fully operable hot cell (located in Sentry Room) U Sample shield brick (with pre-bored holes) [ ]

Long extension tongs: 14-16" in length, (2 pairs) [ ]

Domin water jug (5 gallons) [ ]

Paper towels or equivalent (1 box) [ ]

f RADIOACTIVE SAMPLE DILUTION SUPPLIES CHECK 20 ml 11guid scintillation vial w/ cap (1) [ ]

Sealing tape for 20 m1 liquid scintillation vial (1 roll) [ ]

Labels for 20 m1 liquid scintillation vial (1 box) [ ]

( Small plast.ic bags; sealable (1 dozen) [ ]

10 91 pipet w/tip [ ]

1 mi pipet w/tip [ ]

Adjustable 0-5 m1 pipet w/tip [ ]

f DC0294 11X

1 Ang 2 NUMBER EP pg.15:E DIA8tO CANYON POWER PLANT UNii No(s) REVISlon 3 DATE 8/27/85 PAGE 12 0F 12 TITLE. POST-ACCIDENT SAMPLING SYSTEM LIQUID AND GAS SAMPLE HANDLING APPENDIX 1 (Continued)

BORON SAMPLE ANALYSIS SUPPLIES CHECK 50 ml Erlenmeyer flasks w/ rubber stoppers (5 sets) [ 3 1 cm path length spectrophotometer cells w/ caps (5 sets) [ }

Dri-wipes for spectrophotometer cells (1 box) [ ] p Adjustable 0-5 al pipets w/7 tips [ ]

10 ul pipet w/4 tips [ ]

Spectrophotometer unit [ ]

Dilute nitric acid, HNO E3 3

Carminic acid solution, Stability: I week [ ]

Hydrochloric acid, hcl, concentrated [ ]

Sulfuric acid, H SO , concentrated [ ]

2 4 Standard boric acid, two of the following standards:

10 ppm, 6 ppm, 4 ppm, 2 ppm, I ppm (3 O!LUTION OF 0FF-GAS FOR ISOTOPIC ANALYSIS 14 ce gas sample vials w/ septums installed (2) [ ]

> 5 cc gas tight syringe / needle

_ [ ]

Labels for 14 ce gas vials [3 Small plastic bags; sealable [ ]

Sealing tape [ 3 E

DC0294 12X

NUMBEP EP RS-15:F 33W3 Pacific Gas and Electric Company REVISION 2 m DATE 8/5/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS p p 1 AND 2 OIA8LO CAggggg'g7 NO(S)

SENTRY POST-ACCIDENT SAMPLING SYSTEM

}. TITLE -- DATA ANALYSIS IMPORTMi W To APPROVED PLANT MANAGER g DATE DISCUSSION The purpose of this procedure is to provide a means to assemble the data generated from the various EP RB-15 sub-procedures into a concise form. Each section has a worksheet where data generated throughout the procedure is recorded. The back side records calculations and analyses results. The data sumary sheet gathers all analysis results onto one sheet.

PROCEDURE ,

1. Process data on appropriate sections of form 69-9393.

( 2. Attach all pertinent chemistry and radiochemistry data to this form.

3. Deliver the completed form to the Chemistry and Radiation Protection Supervisor for approval and disposition.

ATTACHMENTS

1. Post Accident RCS and Containment Air Sample Data Sheet. Form 69-9393

2. Specific Activity Deterinination in Reactor Coolant Analysis Data Sheet. Form 69-10548 A

DC0118 IV!

y - -- , * - - - - , - - -

69-9393 7/85 (10) Page I cf :2 TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET fEP RS-15:F)

DATA

SUMMARY

SHEET UNIT NO. 1 2

ll

l. .

PA55 PARAMETER READING COMENTS DATE INITIAL LIQUID BORON ppe diluted CONDUCTIVITY umhos/cm CHLORIDE ppm 1

00 PP" 2

pH ACTIVITY uC1/ml 0FFGAS

( HYDROGEN cc/kg ACTIVITY pCi/ml CONTAINMENT ATMOSPHERE OXYGEN 5 HYOROGEN 1 N08LE GAS ACTIVITY uCi/ml RADIO!00!NES

& PARTICULATES uC1/ml REVIEWED BY C&RP Supervisor DC0118 2VI

69-9393 7/85 (10) Page 2 of 12 -

Tf7LE: POSTACCIDENTRCSANDCONTAINMENTAfRSAMFLEDATASHEh(EPRS-15:F)

SECTION B: WORKSHEET - STRIPPED GAS LIQUID l Sample Source: Hot Legs [] Reactor Cavity Sump [] l Pzr Steam [] Equipment Drain Revr []

Pzr Liquid [] Floor Orain Revr []

RHR Pump []

VCT [] ,

Step 9.d Vacuum on RC-G-2.1 " inches of Hg" = Pv Step 11.c Sample Time Step 13.a Initial ml Final al ,

Total ml added Step 15.e Pressure on RC-G-2.1 psig = Pa

)

0C0118 3VI

69-9393 7/85 (10) Pago 3 c' 12 l

TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)

SECTION B: DATA SHEET The volume of original sample in the 14 m1 serum vial is calculated in the same manner as gases within steel sampling bombs, Procedure CAP 0-12, equation (4).

V14 = V lume f original sample in the 14 al serum vial, al Y

b

= V lume f expansion vessel (EV-1) = 300 ml V = Volume of lines from EV-1 to RC-Y-15 = 60 mi 9

P, = P7 = Pressure after expansion I 1

= psig+14.7[ 30 in He 1

= inches of Hg i /6 14.7 psfa j P, = Pressure evacuated system = inches of Hg V, = Volume of the gas aliquot transferred by diluter value (RC-0V-2)

= 0.024 ml y = (Vs )IYb )(Pf-Py )(V9) [p ,p )

, (Vb+Yg (Pf )(Vg+V3) (Pf )

(

The volume of the original sample in the 14 mi serum vial, V14, is to be used in the radionuclide analysis programs.

Transfer results from counting printout to specific Activity Determination in Reactor Coolant Analysis Data Sheet prior to Data Sunenary Sheet.

DC0118 4VI

69-9393 7/85 (10) Page 4 of 12 -

TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)

SECTION C: WORKSHEET - CONTAINMENT AIR SAMPLING DATE ANALYST Step 2.e Containment temperature = ( *F+460)x5/9= *K=Tc Containment pressure = psig + 14.7 = psia Step 3.c Sample Pressure: containment air pressure CASP-PI-1109 psig Sample Time Step 3.e TNT 196 = *C + 273 =

K = T, SECTION C: DATA SHEET - CONTAINMENT AIR ISOTOPIC ANALYSIS Sampling Technician N Containment Noble Gas Fractional Yield = Tg/(43,400 x T,) = Y NG Noble Gas Activity = uCi/cc Counted 8y

! Containment Air Iodine and Particulates Fractional Yield = Tg /T, = Y gp Iodine and Particulate Activity = uCi/cc Counted 8y Where: Y gp and Y NG are fractional yields entered into the analysis program.

OC0118 SVI

69-9393 7/85 (10) Page 5 cf 12 TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)

SECTION 0: OFFGAS ANALYSIS BY G.C. DATE ANALYST'S INITIALS

4. Sample Analysis-

j. Off gas sample pressure RC-G-2.1 psig + 14.7 = psia

n. Peak Height Average - Hydrogen (trace peak height avg um baseline um) + attenuation /100 peak height SP = mm Peak height-CP = Peak height-SP x (Calibration Pressure: recorded on cal, graph)

(at calibration (from trace pressure at sample (Sample Pressure) pressure Peak height-CP = mm x ( psia)= un

( psia) ,

H = cc/kg H2 in offgas (from c$libration curve)

(

4 DC0118 6VI

0 69-9393 7/85 (10) Page 6 of 12 .

TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP R8-15:F)

SECTION 0:

WORKSHEET G.C. - ANALYSIS (CONT'0) DATE -

4 Sample Analysis (Continued) ANALYST'S INITIALS CA

n. Peak Height Average - Hydrogen (trace peak height avg a baseline m ) + attenuation /100 peau height SP = mm Peak height-CP = Peak height-SP x (Calibration Pmssure-)

(at calibration (from trace) (containment Pressure) * (ca(Tshl femp) pressure)

Peak height-CP = mm x psia 'K psia *K H = 1H 2in CA (fromc$librationcurve)

Peak Height Average - Oxygen (trace peak height avg a baseline m)+ attenuation /100 peak height SP = m

]

Peak height-CP = Peak height-SP x CCalibration Pressure? x (Ts)

(atcalibration (from trace) i, containment PressureJ (cal Temp) pressure)

Peak height-CP = mm x psia) ( *K) esia) ( *K) 10 = 5 in CA (fromcaIibrationcurve)

DC0118 7VI

69-9393 7/85 (10) Page 7 of 12 TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F) l SECTION E: WORKSHEET - RCS LIQUID SAMPLE HANDLING

2.a. R0-2 ambient background - hot cell mR/hr !

teletector

e. Teletector sample plus background mR/hr i

f. net reading sample mR/hr 3.a. Volume RCS pipetted for isotopic analysis 5 ml F

1 al 100 ut 10 u t ll

4. Soron Analysis i

Standard Sample .

! ppm opm 1 2

, absorbance Calculated l

. ppm 8 in !

sample l s . ,

SECTION E: DATA SHEET i

i total m1 water added to sample = dilution !

factor i sample size (UI=0.023ml) or (U!!=0.027ml) l

> Boron Analyses ,

i

! [8]inRCS =[8]insamplexdilutionfactor Sample 1 [8]inRCS = x = ppm Baron

Sample 2 [8]inRCS = x = ppm Boron isotopic Analysis ;

=

Fractional Yield = 1 = 1 allution factor ;

l

! 0C0118 8VI

69-9393 7/85 (10) Page 8 o' 12 TITLE: POST ACCfDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-10 F)

J SECTION E: RCS GAS SAMPLE HANDLING

~

5. Use only if off gas sample vial dose rate 3 mR/hr 2

Oflutions: 1 15:1 2 225:1 F' 3 3375:1

4 50,625:1 5 76,000:1 l[

Final Oilution = :1 SECTION G: WORKSHEET - ION CHROMAT0 GRAPHIC CHLORIDE ANALYSES

3. Sample Analysis (trace peak height - baseline ) x attenuation /100 peak height = mm ppm Chloride SECTION N: WORKSHEET - pH/CONOUCTIVITY/ DISSOLVED OXYGEN

! 2. Sample Analysis I-conductivity of sample stream from CMP umho i

temperature of sample stream from CMP 'C oxygen concentration reading open 0 2

ppb 0 2

pH reading temperature 'C i

4 OC0118 9VI

~

PACfFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERAf!ONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AN0 2 TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)

SECTION A: WORKSHEET - INITIAL ACTIONS DATE REMOTE CONTAINMENT HYOROGEN MONITORS CEL-82 CEL-83 Time switched from 0FF to STAN08Y (N/A if in STAN08Y prior to this step)

Scaleused(Step 10) 10% [] []

20% [] []

Meter Reading - % (Step 10)

Time (Step 10)

Analyst's Initials

(

, DC0118 10VI i

.I a 69-9'393' 7/85 (10) ,

page 11 of 1; TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)

?

SECTION D: WORKSHEET - G.C. ANALYSIS (CONT'0)

3. Null Verification c.11) (trace peak height avg -

baseline ) x attenuation /100 peak height = oxygen concentration

.- Less than 10% oxygen value calculated Yes, proceed No, proceed but contact C&RP Supervisor

(

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3 9 s q

f k J w

DC0118 12VI

NUMBER EP RB-15:G

.T_. 35143 Pacific Gas and Electric Company REv!SION 2 DEPARTMENT OF NUCGAA Pt. ANT OPERATIONS Y kRG E OP N IYG PN CkDURE SENTRY POST-ACCIDENT SAMPLING SYSTEM mm. --ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS MPORTANT APPROVED f0' b b gp DATE PLANTMANAG@

1 DISCUSSION l

The purpose of this procedure is to detail the steps required to measure chloride concentrations of reactor coolant. Included are steps to complete flushing of both the LSP reactor coolant module and CAP lines. This procedure requires operator actions at the LSP, CAP, and CMP.

I PREREQUISITES

1. The Ion Chromatograph (I.C.) was turned on according to Procedure EP RB-15:A and has warmed up for 30 minutes.

( 2. CAP, CMP, and LSP systems lined up as detailed in Procedure EP ,

RB-15:A. I

3. Verify that the following annunciator windows are off on the PCP:

a. REACTOR COOLANT SAMPLE COOLING WATER LOW FLOW

b. REACTOR COOLANT SAMP'.E COOLING WATER LOW PRESS !

c. REACTOR COOLANT SAMPLE COOLING WATER HIGH TEMP i

d. REACTOR C0OLANT PURGE HIGH TEMP .

(

e. REACTOR C00LANT SAMPLE HIGH TEMP f

f. LIQUID SAMPLE PANEL HIGH PLENUM PRESS

g. CHEM ANALYSIS PANEL HIGH PLENUM PRESS

4. The following equipment should be available:

a ,. Meter-long reach rod DC0209 lIX

- - - --e,--,-.---- ,----m-w ,-, ,-., m.,---- --,-. ,,~,w -

,-y.,,- -,- --

DiAsLO CANYON POWEQ PLANT UNIT NO(S) 1 AND 2

[Vh0N DATE 6/25/85 PAGE 2 0F 8 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

--ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS PRECAUTIONS

1. This sampling involves processing of water that may be highly radioactive. Precautions should be taken to prevent skin contact i or ingestion.

2. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush periods, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose area.

3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.

4. For the Ion Chromatograph (I.C.):

a. The calibration curve should oe checked once every 4 samples by analyzing a chloride standard,

b. Calibration should be checked when first using a new eluent.

c. Regeneration is required about once every 6-8 hours of continuous operation. Refer to the troubleshooting and surveillance and maintenance procedure. )

d. During continuous operation, the separator column must be cleaned on a daily basis or every other regeneration by pumping eluent through the column for a minimum of 10 minutes, followed by a 20 minute domineralized water rinse.

. This may be coincident with regeneration of the suppressor column. Refer to the troubleshooting and surveillance and maintenance procedure CAP G-3.

PROCEDURE l 1. Instrument Calibration

a. Set the 0FFSET range switch to left. []

b. Set MODE to LIN. []

l c. Adjust the COARSE vernier switch to zero the meter.

It may be necessary to adjust the FINE pot to zero the meter. []

DC0209 21X i

o:Ast.O CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 fSf0N

- DATE 6/25/85 PAGE 3 0F 8 TiTt.E. SENTRY POST-ACCIDENT SAMPLING SYSTEM

--ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS

d. Operate the system until the baseline is stabilized with the umho FULL SCALE switch in the 1 position adjusting the FINE pot as necessary to zero the meter. []

2. Chloride Standard Check

a. If Standard Check has been perfonned within the []

last week proceed to step 3.

b. Close or check closed CAP-V-15. []

c. Verify CAP-CAL-3 is at least half full.

(CAP G-3, directs filling). []

d. Align CAP-V-5 to CHLORIDE CALIB. SOL'N, []

e. Open CAP-V-15. []

f. Turn on the L&N recorder. []

. g. After 1 minute, place the LOAD / INJECT switch at the CMP to INJECT and mark the recorder trace with

( date, time, injection point, analyst's initials, sample type, and conductivity meter setting. []

h. After 1 minute, place the LOAD / INJECT switch in LOAD position. []

E: The Cl~ peak will elute about 5 min. after injection.

1. Close CAP-V-15. []

i

j. Align CAP-V-5 Counterclockwise to CLOSED. []

k. Align CAP-V-29 to vent (6 o' clock) []

1. After the Cl* peak has eluted, wait 5 minutes then shut off the L&N recorder. []

f DC0209 3IX l

g -

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

DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:G REV!SION 2 DATE 6/25/85 PAGE 4 0F 8 TiTts. SENTRY POST-ACCIDENT SAMPLING SYSTEM

--ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS

m. Align CAP-V-5 to RCS sample (9 o' clock). []

n. Determine the peak height:

Peak height 2.(Trace Peak Height - Baseline) x Attenuation 100 Peak Height = nn Corresponding ppm Cl from CAL. Curve opm(A)

o. Compare the Cl standard peak with the calibration curve.

For the same umho setting, the values should be within 210%.

(A) - 1.0 x 100 = % Difference (B) 1.0 Is(6)within210%? (YES/NO)

3. Sample Analysis f

a. At the CMP, activate the L&N recorder. []

b. Place the I.C. LOAD / INJECT switch in the INJECT [] )

position and mark the inject position on the chart paper.

c. On the chart paper, record the date/ time, sample []

source used, umho setting, and analyst's initials.

d. After approximately 1 minute from sample injection, []

place the LOAD / INJECT switch in the LOAD position.

[The chloride peak will appear approximately 5 minutes l

after injection at the same retention time observed forthestandard.]

e. Examine the i.&N recorder. If the chloride peak []

goes off-scale, repeat steps 3.b. to 3.d. using a larger umho setting (i.e. 3 umho). p

f. Turn CAP-V-5 to the DEMIN WATER position. []

g. Flush with demin water for 2 minutes. []

h. After the Cl" peak has eluted, wait 5 minutes I then turn off the L&N recorder. []

DC0209 41X '

"*'t e

DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N DATE 6/25/85 PAGE 5 0F 8 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

--10N CHROMAT0 GRAPHIC CHLORIDE ANALYSIS

i. Determine the peak height Peak height = (Trace peak height - baseline) x Attenuation 100 l Peak height = m i

J. Detennine the ppm chloride from the calibration curve and record on the data sheet (EP RB-15:F).

k. If pH/ conductivity /D0 are to be analyzed proceed []

to EP RB-15:H.

4. Flushing

a. At the PCP, perfann the following:

1) Close the remote plant and source isolation []

valves.

2) Open the remote flush isolation valve. []

( b. At the LSP, close RC-V-1.X. []

c. At the CAP, align CAP-V-5 and CAP-V-6 to LIQUID []

SAMPLE.

d. At the LSP, open RC-V-4 []

e. Open RC-VREL-2 until RC-FI-2 indicates maximum flow. [] l Flush with domin water for 3 minutes.

f. Close RC-V-7. []

g. Open RC-V-3. []

h. Adjust RC-VREL-1 until RC-FI-1 indicates maximum [] l flow. Flush with domin water for 1 minute. I

1. Close RC-V-3. []

j. Open RC-V-1.X and flush with demin water for 5 minutes. []

k. Close RC-V-1.X. []

DC0209 5IX

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NLGBER EP RS-15:G REVIS!ON 2 DATE 6/25/85 PAGE 6 0F 8 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM

--ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS

1. Open RC-V-7. []

m. Adjust RC-VREL-2 until RC-FI-2 indicates maximum []

flow. Flush with demin water for 3 minutes.

n. At the CMP, cycle the LOAD / INJECT switch at least 3 times. Return it to the LOAD position. []

o. At the CAP, align CAP-V-5 to CLOSED. []

p. Tui n CAP-V-6 to OXYGEN CALIB SOLUTION. []

q. Close CAP-V-11. []

r. Terminate flushing by closing the following valves:

RC-V-7 RC-V-2 RC-V-4 RC-VREL-1 ' ',

RC-VREL-2 ..

s. Align RC-V-22 to WASTE. []

t. At the PCP, close the remote flush isolation valve. [] -

u. Call the control room and have operations close the containment isolation valves opened earlier. []

5. Flushing the Separator and Suppressor Columns f If the I.C. is not needed for further sampling in an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

! period then the following steps should be performed before system shutdown can be started,

a. Perform the following I.C. valve alignments to wash the fodine and other :ations from the suppressor

, column:

1

1) Check that the conductivity meter made switch is set to ZERO. []

l-l

~

1 l

DC0209 6IX ,

otAato CANYON POWEM PLANT UNIT NO(S) 1 AND 2 vh0N

.. DATE 6/25/85 PAGE 7 0F 8 m LE. SENTRY POST-ACCIDENT SAMPLING SYSTEM

--ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS

2) In the eluent / pump enclosure of the CAP, check the following:

a) Check the levels of eluent, water, and regenerants are at least half full. []

b) Check that the I.C. pumps and vent if air is visible in the sightglass or tubing. [ *]

c) Check that the pump stroke settings are set at 40% for both pumps. []

3) At the CMP, check the following:

a) Check that the regeneration time thumbwheels are set at 15 min for REG and 45 min for RIN. []

b) Align the following air toggle switches to the indicated positions:

SWITCH POSITION

(; Eg/ Water Eg []

E DOWN []

2 SEP-1,'SEP-2 SEP-1 []

SUP-1/RGN-2 SUP-2/RGN-1 []

INJECT / LOAD LOAD []

4) Depress regeneration START button and the []

suppressor column will automatically be regenerated.

5) Flush the separator column for 20 min. After 20 []

min., turn the E3 switch to DOWN and rinse the separator coTumn with demin. water for 10 min.

6. System Shutdown

a. After completion of column regeneration, perform the following:

1) Turn I.C. POWER switch to 0FF. []

DC0209 71X i

i I

l DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fPRB-15:G DATE 6/25/85 PAGE 8 0F 8 T TLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

--ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS

2) Turn AIR switch to 0FF. []

3) Turn GAUGE switch to 0FF. []

4) Turn ELUENT pump switch to 0FF. []

5) Turn conductivity meter MODE switch to ZERO. []

b. If pH/ conductivity /00 are to be done, proceed []

to section H.

c. If finished with all CMP / CAP analyses, turn CMP []

power at front of panel to 0FF and turn off two switches at back of G.C. unit.

8. Data Analysis Proceed to EP R8-15:F for data analysis. []

, 9. If finished with all sampling / analysis go to 15:8 []

Final Flushing.

REFERENCES Sentry Equipment Corp. High Radiation Sampling System Operating and Maintenance Manual.

l l

DC0209 81X ,

l l

l

h NUMBER EP RB-15:H 7 G v4 3 Pacific Gas and Electric Company REVISION 2 oEPARTMENT OF NUCLEAR PLANT OPERATIONS ,

1 AND 2 PAGE 1 0F 9 DIABLO CANYON POWER PLANT UNIT NO(S)

EMERGENCY OPERATING PROCEDURE SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE -- PH/ CONDUCTIVITY / DISSOLVED OXYGEN gp ,,.

APPROVEo Y- SAFETY DATE PLANTMANAG3' DISCUSSION The purpose of this procedure is to detail the steps required to measure pH, conductivity, and dissolved oxygen concentrations of reactor coolant. Included are steps to complete flushing of both the LSP reactor coolant module an CAP lines. This procedure requires operator actions at the LSP, CAP, and CMP.

PREREQUISITES

! 1. Monitors are turned on according to procedure EP RB-15:A: ,

a. and have warmed up for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if oxygen analyzer has not been calibrated within 1 week;

b. or, have warmed up for 30 minutes if oxygen analyzer does not need calibration.

2. CAP, CMP, and LSP systems lined up as detailed in procedure EP RB-15:A.

3. Verify that the following annunciator windows are off on the PCP:

a. REACTOR COOLANT SAMPLE COOLING WATER LOW FLOW

b. REACTOR COOLANT SAMPLE COOLING WATER LOW PRESS

c. REACTOR COOLANT SAMPLE COOLING WATER HIGH TEMP

d. REACTOR COOLANT PURGE HIGH TEMP'

e. REACTOR COOLANT SAMPLE HIGH TEMP

f. LIQUID SAMPLE PANEL HIGH PLENUM PRESS

g. CHEM ANALYSIS PANEL HIGH PLENUM PRESS i

DC0416 IVII ,

NUMBER EP RB-15:H 1 AND 2 OIA8LO CANYON POWER PLANT UNIT NO(S) REV1SION 2 DATE 6/25/85 PAGE 2 0F 9 TITm' SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN

4. The following equipment must be available:

a. Meter-long reach rod

b. Small screwdriver

5. The conductivity meter should have been calibrated within the last 3 months.

PRECAUTIONS

1. This sampling involves processing of water that will be highly radioactive. Precautions thould be taken to prevent skin contact or ingestion.

2. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush periods, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose area.

3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises. J PROCEDURE

1. Monitor Calibration

a. pH Calibration If pH meter has been calibrated within the last week, proceed to Step 1.b., Dissolved Oxygen analyses.

1) Make sure the pH buffer tanks are over half []

full with pH 7 and pH 4 or 10 buffers at the CAP.

[To fill, vent tank pressure, remove pipe cap on top of sight glass and fill with appropriate buffer. Be sure to install pipe cap and then repressurize tank.]

2) Align CAP-V-6 to pH CALIB SOLUTION. []

1 DC0416 2VII

NUMBER EP RB-15:F 1 AND 2 otAsto CANYON POWER PLANT UNIT NO(S) REVISION 2 ,

DATE 6/25/85 l PAGE 3 0F 9 i N SENTRY POST-ACCIDENT SAMPLING SYSTEM I

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN l

3) Adjust CAP-V-26 until sufficient flow is []

indicated by red flow indicator light.

Flow for 2 minutes. During this time cycle CAP-V-7 between Rexnord and Orbisphere Oxygen l l Analyzer position. ;

4) Turn CAP-V-6 counterclockwise to 0XYGEN []

CALIS. SOLUTION to terminate flow, then ;

align CAP-V-27 to vent position. 1 1

5) Observe and record the temperature of the buffer solution as indicated on the CMP.

Temp. 'C

[ Correct the buffer pH value for the '

[]

recorded temp. from the pH Temperature Correction Table (Appendix 1).]

6) Adjust the pH monitor R-3 until the meter indicates the temperature corrected pH value. []

I- 7) Observe the pH monitor reading for 2 minutes and adjust if drift exceeds !0.1 pH units.

pH

8) Align CAP-V-6 to DEMIN WATER and flush for 2 []

minutes. Cycle V-7 between Orbisphere to Rexnord l to flush D0 deadleg.

9) Align CAP-V-30 to pH calibration tank CAL-2. []

10) Align CAP-V-28 to the nitrogen supply line. []

11) Align CAP-V-6 to the pH CALIB SOLUTION. []

12) Open CAP-V-16 until the red flow indicator is lit. Flow for 2 minutes. Cycle CAP-V-7 between Rexnord and Orbisphere Oxygen Analyzer. []

13) Turn CAP-V-6 counterclockwise to the OXYGEN CALIB SOLUTION to tenninate flow. [ ].

l l

DC0416 3VII l

l

1 AND 2 IU ER EP RB-15:H 0A8LO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 6/25/85 PAGE 4 0F 9 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN

14) Align CAP-V-28 to vent position. []

15) Observe and record the temperature of the buffer solution as indicated on the CMP.

Temp. "C

[ Correct the buffer pH value for the []

recorded temp. from the pH Temperature Correction Table (Appendix 1).]

16) After the meter reading has stabilized, record the reading and compare to the temperature corrected pH value. The reading should be within 0.5 pH units of the temperature corrected value, pH

17) Align CAP-V-6 to DEMIN WATER and flush for 2 []

minutes. During this time cycle V-7 from Orbisphere to Rexnord.

l .

b. Dissolved Oxygen Analyzer Calibration

1) Rexnord a) Adjust mechanical zero with power []

switch behind meter face of unit to 0FF.

b) With power switch ON, and function []

selector switch on ZERO, adjust ZERO ADJ.

to get zero reading on the instrument.

c) Turn function selection switcii to 20 mg/1. []

2) Orbisphere Turn knob on Orbisphere from "off" to "02 "'

3) Align V-7 to Rexnord or Orbisphere depending []

on directions given by supervision.

If calibration has been performed within 1 week skip remaining portions of this step.

DC0416 4VII

NUMBER EP RB-15:H 2 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 6/25/85 PAGE 5 0F 9 N SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN

4) Open CAP-V-9. []

5) Align CAP-V-6 to OXYGEN CALIB SOLUTION. []

6) Close CAP-V-17 until the red flow indicator is lit. []

7) Purge for 15 minutes then read and record the temperature of the water in CAL-4 at the CMP.

Temp. *C

8) Determine the dissolved oxygen concentration from the Solubility of Ox Water table (Appendix 2)and ygen in Air record theSaturated value.

ppm dissolved oxygen a) Rexnord b While flowing, adjust the CAL ADJ to []

indicate the dissolved oxygen concentration in ppm previously recorded in Step 1.b.9).

(This may involve changing the scale switch position).

b) Orbisphere While flowing push " cal" kneb and adjust as above. []

10) Turn the oxygen calibration pump to 0FF. []

11) Close CAP-V-9. []

12) Align CAP-V-6 to LIQUID SAMPLE. (9 o' clock) []

2. Sample Analysis I

a. Flow for 5 minutes or until meter reading []

stabilizes. Cycle CAP-V-7 between Orbisphere and Rexnord.

DC0416 SVII ~ .

NUMBER EP RB-15:H 1 AND 2 DIABLO CANYON POWER PLANT UNIT NCMS) REVISION 2 DATE 6/25/85 PAGE 6 0F 9 7gg~ SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN

b. Observe and record conductivity meter reading and temperature of the sample stream from the CMP.

Cond. umho Temp. 'C c.

1) Rexnord:

Observe the Rexnord dissolved oxygen meter []

reading and turn to a lower scale position as the meter reading decreases. Purge 15 minutes.

2) Orbisphere Read display noting whether ppb or ppm is indicated. ppm l?

ppb 1. .

d. Read the 02 concentration. ppm 0 2

e. Turn CAP-V-6 counterclockwise to OXYGEN CALIB []

)

. SOLUTION to terminate sample flow and permit pH reading to stabilize.

f. Observe the pH meter for 1 minute to ensure the reading has stabilized. Record the pH reading.

pH Temp. *C

g. If I.C. analyses is to be perfonned proceed to []

EP RB-15:G.

3. Sample Calculations. I

a. Correct the recorded sample pH for temperature []

from the pH Temperature Correction Table (Appendix 1).

b. Transfer all data to data sheets EP RB-15:F. []

F DC0416 6VII

NUMBER EP RB-15:H ,

DIABLO OANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 2 DATE 6/25/85 PAGE 8 0F 9 7gtg. SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN APPENDIX 1 pH TEMPERATURE CORRECTION TA8LES SAMPLE pH TEMPERATURE CORRECTION TABLE TEMP *C CORR TEMP'C CORR 16 .31 31 +.20 17 .27 32 +.24 18 .24 33 +.26 19 .20 34 +.29 l 20 .16 35 +.32 21 .13 36 +.36 22 .10 37 +.40 23 .07 38 +.43 24 .03 39 +.46 25 .00 40 +.50 26 +.04 41 +.53 ,

27 +.07 42 +.56 28 +.10 43 +.59 29 +.14 44 +.63 ('

30 +.17 45 +.66 L BUFFER pH TEMPERATURE CORRECTION TABLE RED GREEN 8LUE TEMP pH4 pH7 pH10 10*C 4.00 7.06 10.18 15'C -- -- 10.12 ,

20*C 4.00 7.02 10.06 25'C 4.00 7.00 10.01 30*C 4.01 6.99 9.97 35'C -- -- 9.93 40*C 4.03 6.98 9.89 l 45'C -- -- 9.86 l 50*C 4.06 6.97 9.83 60*C 4.09 6.98 --

70'C 4.12 6.99 --

l 80*C 4.16 7.00 --

90*C 4.19 7.02 --

95'C 4.21 ,

7.03 --

i i *TAKEN FROM LABELS ON BECKMAN BUFFERS I

l DC0416 8VII l 1

1 AND 2 NUMBER EP RB-15:H DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 6/25/85 PAGE 7 0F 9 7,7tg SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN

4. CMP Shutdown

a. pH Monitor - Turn switches S-3 and 5-1 to []

the OFF position,

b. Conductivity Monitor - Turn function select []

switch to ZERO position.

p

c. Orbisphere - return knob to "off" position. [] l S. Continue with flushing using EP RB-15:G, Step 5. F REFERENCES

1. Sentry Equipment Corp. High Radiation Sampling System Operating and Maintenance Manual.

APPENDICES

1. pH Temperature Correction Table g 2. Solubility of Oxygen in Air Saturated Water F

DC0416 7VII y ----. - . - p --, . , - . , , . - - - - - - , ,y --

g--- ,-------,--,---w,-.,r--- i

NUMBER EP RS-15:H DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 2 DATE 6/25/85 l o

PAGE 9 0F 9 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN APPENDIX 2 SOLUBILITY OF OXYGEN IN AIR SATURATED WATER (For Oxygen in Air at 1 atm.)

TEMP PPM TEMP PPM

'C DISSOLVED 'C DISSOLVED OXYGEN OXYGEN 16 9.9 31 7.5 l 1

17 9.7 32 7.4 18 9.5 33 7.3 19 9.3 34 7.2 20 9.2 35 7.1 21 9.0 36 7.0 k 22 8.8 37 6.8 23 8.7 38 6.7 24 8.5 39 6.6 25 8.4 40 6.5 26 8.2 41 6.4 27 8.1 42 6.3 28 7.9 43 6.2 29 7.8 44 6.1 30 7.7 5 6.0 DC0416 9VII

l RUMBER EP RB-15:I '

4 .-

?G5743 Pacific Gas and Electric Company REVISION l DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 3 DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE SENTRY POST-ACCIDENT SAMPLING SYSTEM

.8 TITLE. -- SAMPLE STORAGE AND DISPOSAL W IMPORTANT

~ '

APPROVED.

DATE SAFETY PLANT MANAGER g)

DISCUSSION The purpose of this procedure is to provide a means for disposal of stripped-gas samples and storage of RCS Ifquid samples.

PRECAUTIONS

1. Same as EP RB-15:A.

PREREQUISITES

1. PGandE Post Accident Sampling Shipping Packaging.

( 2. Gas bottle Griptong. -

i

3. 14 ce gas sample bottle.

PROCEDURE

1. Disposal of Reactor Coolant Stripped-Gas Samples

a. At the LSP

1) Close or check closed valves RC-V-1.1 through RC-V-1.5 [] -

2) Verify that RC-G-4 indicates approximately 100 psig Ar. []

b. At the PCP

1) Close or check closed FCV-9351A, FCV-9351-B

FCV-9350A, FCV-9350-B FCV-9353A ll l 0C0118 1VII

l l

l otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EP RB-15:I DATE 9/24/85 1 PAGE 2 0F 3 SENTRY POST-ACCIDENT SAMPLING SYSTEM I'7 1

-- SAMPLE STORAGE AND DISPOSAL FCV-692, FCV-693, FCV-694 FCV-1412. FCV-1413

FCV-1416, FCV-1417 FCV-1418 FCV-1419, FCV-1420 ',

c. Align the following valves, as described:

RC-V-10 closed)

RC-V-15 closed)

RC-V-14 closed)

RC-V-11 CLOSED)

RC-V-13 closed)

RC-V-12(closed)

RC-DV-2 (9 o' clock) l'

d. Bottle Evacuation

1) With the griptong, install the diluted gas sample bottle on the front panel needle. []

2) Open RC-V-13. []

3) Open RC-V-12 and evacuate until RC-G-2.2 .

indicates a minimum vacuum of 22 inches )

of mercury. []

4) Turn RC-DV-2 to the 6 o' clock position and continue the evacuation until a minimum vacuum of 22 inches of mercury is indicated on RC-G-2.2. []

5) Close in order RC-V-13 and RC-V-12. []

6) Open RC-V-14 and allow the bottle to pressurize to approximately 1 psig as indicated on RC-G-2.2. []

7) Close RC-V-14. []

8) Open RC-V-13 and RC-V-12 and evacuate until RC-G-2.2 indicates a minimum vacuum of 22 inches of mercury. []

DC0118 2VII i

DIA8LO CANYON POWER CLANT UNIT NO(S) 1 AND 2 R ON

.- DATE 9/24/85 PAGE 3 0F 3 SENTRY POST-ACCIDENT SAMPLING SYSTEM 787 1

-- SAMPLE STORAGE AND DISPOSAL 1

l

9) Close in order RC-V-13 and RC-V-12. [] l

10) Open RC-V-14 and allow the bottle to pressurize to approximately 1 psig as indicated on RC-G-2.2. []

11) Close RC-V-14. []

12) Repeat steps 8 through 11 three times to remove all radioactive gases. []

e. Bottle Disposal

1) Remove the griptong from the panel. []

2) Perform a radioactive survey of the bottle and dispose accordingly. []

2. Access and Removal of Diluted RCS Liquid Sample Bottle Refer to RCP-RW-10 for removal of bottle from cart / cask and preparation for transport.

(-

DC0118 3VII

O NUMBER EP RB-15:J P G5143 Pacific Gas and Electric Company REVISION O DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 7 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY OPERATING PROCEDURE SENTRY POST-ACCIDENT SAMPLING SYSTEM --

TITLE. UNDILUTED LIQUID SAMPLING FROM REACTOR COOLANT IMPORTANT APPROVED- YS SAFETY PLANTMANAGg DATE DISCUSSION The purpose of this procedure is to detail the steps required to obtain an undiluted liquid sample during accident conditions and complete module flushing.

PREREQUISITES

1. System was initially lined up as described in procedure EP RB-15:A.

C 2. Verify that the following annunciator windows are off on the PCP:

a. REACTOR COOLANT SAMPLE COOLING WATER LOW FLOW t

b. REACTOR COOLANT SAMPLE COOLING WATER LOW PRESS

c. REACTOR COOLANT SAMPLE COOLING WATER HIGH TEMP

d. REACTOR COOLANT PURGE HIGH TEMP

e. REACTOR COOLANT SAMPLE HIGH TEMP

f. LIQUID SAMPLE PANEL HIGH PLENUM PRESS

3. The following equipment must be available and operational:

a. Meter-leng reach rod l b. Needle flu 3h tool with damin water in a sample bottle and a new septum

c. Sample cart / cask with the 15 mi lift rod assembly l

l l

DC0109 11 1

DIABLO CANYON POWER Pt. ANT UNIT NO(S)

NUMBER EP RB-15:J 1 AND 2 REVISION 0 DATE 6/25/85 PAGE 2 0F 7 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM --

UNDILUTED LIQUID SAMPLING FROM REACTOR COOLANT

d. A prelabeled 15 m1 sample bottle with a new septum

1) The label should have the sample source, date, estimated time of sample, and the initials of the person taking the sample. (From this point estimate 19 minutes.)

PRECAUTIONS

1. This sampling involves processing of water that will be highly radioactive. Precautions should be taken to prevent skin contact or ingestion.

2. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush periods it may not be necessary to stand near the panels and consideration should be given to moving to a low dose rate area.

3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.

T PROCEDt'PE g

1. Turn on the switch to light the undiluted bottle fill []

station.

2. Place the bottle on the cart / cask assembly cavity piston. []

a. Turn the direction valve for the hydraulic piston []

in the down position and Icwer the bottle into the cask cavity.

b. Close and open the cask to verify that the cover is []

working properly,

c. Position the cart / cask under the undiluted reactor []

coolant fill station needles and set the brake,

d. Turn the direction valve for the hydraulic piston []

in the up position and raise the bottle onto the needles.

DC0109 21

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R S ON DATE 6/25/85 PAGE 3 0F 7 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM --

UNDILUTED LIQUID SAMPLING FROM REACTOR COOLANT

3. Reactor Coolant Sample Line Purge

a. Open RC-V-8.1. []

b. Determine which sample source isolation valves will have to be opened from the list below:

SAMPLE SOURCE CONTAINMENT ISOLATION VALVES Hot Legs Loops 1 and 4 FCV-9356A and FCV-9356B Pressurizer Steam Space FCV-9354A and FCV-9354B Pressurizer Liquid Space FCV-9355A and FCV-9355B RHR Pumps Discharge N/A Volume Control Tank N/A

c. Call the Control Room and have operations block []

open the appropriate containment isolation valves,

d. Open the corresponding remote plant isolation valve []

(RPIV) and remote source isolation valve (RSIV) at the PCP (see Appendix 1 for proper valve).

(

e. Close remote flush isolation valve (RFIV). []

NOTE 1: The sample source valves are labeled RC-V-1.1 through RC-V-1.5. Throughout this procedure, the form RC-V-1.X will be used to indicate the source valve to be operated. The sample source used for sampling will have been given at a briefing by the Site Chem and Rad Protection Coordinator.

F0TE 2: Upon implementation of the next step, sample will be flowing into the back of the LSP. The meter-long reach rod should be used to operate V-1.X (see Appendix 1 for proper valve).

g. Open RC-V-3. []

h. Slowly open RC-VREL-1 until RC-FI-1 indicates []

100% flow or 1900 cc/ min. Purge for 9 minutes.

1. Slowly close RC-VREL-1 until RC-FI-1 indicates []

36% or 700 cc/ min. Continue the purge for 1 minute.

J. Close RC-V-3. []

DC0109 31

'i OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fSON DATE 6/25/85 PAGE 4 0F 7 -

TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM --

UNDILUTED LIQUID SAMPLING FROM REACTOR COOLANT

4. Sampling

a. Open RC-V-7 and RCV-2. []

b. Slowly open RC-VREL-2 until RC-FI-2 indicates 100% flow or100 cc/ min. Purge for 3 minutes.

()

c. Turn RC-V-19 to SAMPLE. []

CAUTION: Do not exceed 20 psig on RC-G-3.

d. Adjust RC-VREL-2 until RC-G-3 indicates 20 psig or []

RC-F.I-2 ndicates 100% flow or 200 cc/ min. Purge for 2 minutes.

e. Close RC-V-7 []

f. Let RC-G-3 return to O psig and wait 30 seconds to []

allow the bottle to depressurize.

g. Turn RC-V-19 to BYPASS. [] I

h. Close RC-V-1.X. []

1. Call the control room and have operations close the []

containment isolation valves opened earlier.

5. Sample Cart / Cask Removal

a. Turn the direction valve for the cart / cask hydraulic []

piston to the down position and slowly lower the bottle into the cask,

b. Close the cask. Release brake and remove the []

i cart / cask from the sample station and away from the LSP.

c. Install and secure the auxiliary shield. []

d. Install and secure the needle flush tool onto the []

undiluted reactor coolant fill station needles.

0C0109 41 2

NUMBER EP RB-15:J DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0

~

DATE 6/25/85 PAGE 5 0F 7 TITLE: SENTRY POST-ACCIDENT SAMPLING SYSTEM --

UNDILUTED LIQUID SAMPLING FROM REACTOR COOLANT

6. Initial Flushing

a. At the PCP, perform the following:

1) Close the remote source isolation valve. []

2) Close the remote plant isolation valve. []

3) Open the remote flush isolation valve (see []

Appendix 1 for proper valve),

b. Open RC-V-7 and RC-V-4. []

c. Adjust RC-VREL-2 until RC-FI-2 indicates 100% flow.

Flush with demin water for 3 minutes. []

d. Close RC-V-7. []

e. Open RC-V-3. []

f. Adjust RC-VREL-1 until RC-FI-1 indicates 80-90% []

(, flow. Flush with demin water for 1 minute.

g. Close RC-V-3. []

h. Open RC-V-1.X and flush with demin water for 5 []

minutes.

i. Close RC-V-1.X. []

7. Final Flushing l

a. Open RC-V-8.1 and RC-V-8.2. []

b. Adjust RC-VREL-2 until RC-FI-2 indicates 100% flow. []

Flush with demin water for 1 minute.

(

c. Turn RC-V-19 to SAMPLE. []

CAUTION: Do not exceed 20 psig on RC-G-3.

f l

l l

i l DC0109 5I t

NUMBER EP RB-15:J -

DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISf0N O DATE 6/25/85 PAGE 6 0F 7 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM --

UNDILUTED LIQUID SAMPLING FROM REACTOR COOLANT

d. Adjust RC-VREL-2 until RC-G-3 indicates 20 psig or []

RC-FI-2 indicates 100% flow. Flush with demin water for 2 minutes.

e. Close RC-V-2. []

f. Let RC-G-3 return to O psig and wait 30 seconds to []

allow bottle to depressurize.

g. Turn RC-V-19 to BYPASS. []

h. Terminate flushing by closing the following valves:

~'

RC-V-8.2

RC-V-8.1

', RC-V-4

RC-VREL-1

RC-VREL-2 .J

8. Turn off the undiluted fill station light. []

9. At the PCP, close the remote flush isolation valve. [] )

10. Remove the needle flush tool and survey the bottle for []

disposal.

11. Perform a radiation and contamination survey on the []

cart / cask assembly. Handle the sample according to procedure EP RB-15:I.

12. Refer to Proceoure RCP RW-10 for Radwaste shipment. []

REFERENCES

1. Sentry Equipment Corp. High Radiation Sampling System Operating ;

and Maintenance Manual. ;

l APPENDICES l

1. Valves for Obtaining Samples from Reactor Coolant. l l

m g

DC0109 6I -

-'_ _-_, w __ _.-----w. _--y, ,.- , ,-- , , , , _ , , . ._ ,,

NUMBER EP RB-15:J DIA8LO CANYON POWE00 DLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 6/25/85 PAGE 7 0F 7 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM --

UNDILUTED LIQUID SAMPLING FROM REACTOR COOLANT APPENDIX 1 LSP SAMPLE REMOTE PLANT REMOTE SOURCE REMOTE FLUSH SOURCE ISOLATION VALVE ISOLATION VALVE ISOLATION VALVE VALVE SAMPLE SOURCE (RPIV) (RSIV) (RFIV) (SSV)

RC Hot Leg 1 FCV-9351 A FCV-692 FCV-1416 RC-V-1.1 RC Hot Leg 4 FCV-9351 B FCV-692 FCV-1416 RC-V-1.1 PZR Liquid FCV-9350 B FCV-693 FCV-1417 RC-V-1.2 PZR Steam FCV-9350 A FCV-694 FCV-1418 RC-V-1.3 RHR Pump 1-1 Discharge FCV-9353 A FCV-1413 FCV-1419 RC-Y-1.4 RHR Pump 1-2 Discharge FCV-9353 8 FCV-1413 FCV-1419 RC-V-1.4 VCT Liquid FCV-137 FCV-1412 FCV-1420 RC-V-1.5 f

P DC0109 71

NUMBER EP RB-;5:K

_y

,y #I4 T '

Pacific Gas and Electric Company REVISION O DEPARTMENT O'F NUCLEAR PLANT OPERATONS PAGE I 0F 7 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2

/ EMERGENCY OPERATING PROCEDURE SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE . -- DILUTED LIQUID SAMPLING FROM RADWASTE

/ IMPORTANT APPROVED yM -

E TO PLANTMANAGEJ)

DATE SAFETY s

DISCUSSION The purpose of this procedure is to detail the steps required to obtain a diluted liquid sample from the radwaste module during accident conditions and complete module flushing.

Sample sources addrcssed are Reactor Cavity Sump, Equipment Drain Receiver, Floor Drain Receiver and RHR Pump Room sump.

The containment isolation valves FCV-696 and FCV-697 are controlled

,from the Containment Isolation Yalve Panel in the Sentry Room only.

These switches require a key to operate. A copy of the key is located

't in the Sentry Room. These valves are to be opened only during an

t. emergency or for testing.

4 PREREQUISITES

1. System was ir.itially lined up as described in procedure EP'RB-15:A.

2., Verify that the following annunciator windows are g on the PCP:

a. RADWASTE SAMPLE COOLING WATER LOW FLOW

b. RADWASTE SAMPLE COOLING WATER LOW PRESS

c. RADWASTE SAMPLE COOLING WATER HIGH TEMP

d. RADWASTE HIGH TEMP

e. LIQUID SAMPLE PANEL HIGH PLENUM PRESS

3. The following equipment must be available and operational:

a. Meter-long reach rod s

DC0294 III 4

l

NUMBER EP RS-15:K DIASLO CANYON POWER PLANT UNIT WS) 1 AND 2 REVISION O DATE 6/25/85 PAGE 2 Cf 7 rira' SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- DILUTED LIQUID SAMPLING FROM RA0 WASTE

b. Hand operated vacuum pump

c. Sample cart / cask with 60 mi lift rod assembly

d. A prelabeled 60 mi sample bottle with a new septum

1) The label should have the sample source, date, estimated time of sample, and the initials of the person taking the sample (from this point estimate 21 minutes).

PRECAUTIONS,

1. This sampling involves processing of water that will be highly radioactive. Precaution should be taken to prevent skin contact or ingestion.

2. Time in a radiation field should be limited to that necessary to' perfom the required operations. During purge and flush periods, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose rate area.

3. A dose rate instrument should be on and periodic monitoring is j suggested during purge and sampling exercises. -

PROCEDURE

1. Verify RW-DV-1 is turned to BYPAS3. Fill reservoir []

t RW-R-1 with demin water,

a. Open RW-Y-10 and RW-V-9. []

b. Adjust reservoir RW-R-1 until the water level []

in graduated cylinder RW-C-1 is at least 100 ml.

c. Close RW-V-9 and RW-V-10. []

2. Align RW-V-8 to the 9 o' clock position. []

Align RW-V-4 to the SAMPLE position. []

DC0294 2II l

l DIA8LO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 R S ON

.- DATE 6/25/85 l PAGE 3 0F 7 )

7,7 g SENTRY POST-ACCIDENT SAMPLING SYSTEM j

-- DILUTED LIQUID SAMPLING FROM RADWASTE

3. Sample Purging Reactor Cavity Sump:

Coordinate with Operations to turn on the reactor cavity sump pumps, then open containment isolation valves FCV S00 and 501 for one rainute and then close. Open valves FCV 696 and 697.

Containment isolation valves FCV 696 and 697 are key operated valve switches controlled in the Sentry Room at the POST LOCA CNT ISOLATION PANEL.

Equipment Drain Receiver or Floor Drain Receiver:

Coordinate with Operations to have EDR or FDR placed on recirculation for Post Loca Sampling. ,

RHR Room Sump:

Verify with control room that RHR room high level is indicated.

Coordinate with Operations to transfer the entire contents of a FDR to another holding tank or overboard. Manually pump down RHR room sump to the empty FDR and place FDR on recirc for Post Loca Sampling.

(

a. Open the corresponding remote plant isolation []

valve (RPIV), remote source isolation valve (RSIV),

at the PCP (see Appendix 1 for proper valve),

b. Close the remote flush isolation valve at the PCP. []

g: The sample source valves are labeled RW-V-2.1 thru RW-V-2.3. Throughout this procedure, the form RW-V-2.X will be used to indicate the source valve to be operated. The sample source used for sampling will have been given at the briefing by the Site Chem and Rad Protection Coordinator.

c. Slowly open Sample source valve RW-V-2.X (see []

Appendix 1 for proper valve) until RW-FI-1 indicates 100% flow or 200 cc/ min. Purge to waste for 7 minutes.

d. While sample is purging continue with cart / cask preparation.

DC0294 3II

1 AND 2 NUMSER EP RS-15:K DIA8LO CANYON POWER Pt. ANT UNIT NO(S) REVISION 0 DATE 6/25/85 PAGE 4 0F 7

SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- DILUTED LIQUID SAMPLING FROM RADWASTE

4. Insert the needle of the hand operated vacuum pump []

into the septum of the prelabeled 60 mi sample bottle:

a. Evacuate to the maximum vacuum achievable with []

the pump. The vacuum must be at least 15" of Hg.

b. Keep the pump connected to the bottle for 1 minute []

to assure that the bottle retains the vacuum. .

5. Turn on the switch to light the diluted bottle fill []

station.

6. Remove the bottle from the vacuum pump and place []

the bottle on the cart / cask assembly cavity piston,

a. Turn the direction valve for the hydraulic piston []

to tha down position and lower the bottle into the cask cavity.

b. Close and open the cask to verify that the cover []

is wor'ing properly.

c. Position the cart / cask under the diluted radwaste []

fill station needle and set the brake.

~

d. Turn the direction valve for the hydraulic []

piston to the up position do not raise the bottle onto the needle.

7. Sampling - when line has purged for 7 minutes

a. Turn RW-V-8 to BYPASS. []

b. Close RW-V-2.X. []

c. Close FCV-696 and FCV-697 if opened earlier []

and notify the control room when closed.

8. Initial Flushing

a. At the PCP. close the remote source isolation []

valve if applicable.

DC0294 4II l

' NUMBER Ep ps ,5:x otAsLO CANYON POWEQ PLANT UNIT NO(S) 1 AND 2 REVI510N 0 DATE 6/25/85 FAGE 5 0F 7 7,7g ~ SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- DILUTED LIQUID SAMPLING FROM RADWASTE ,

b. Slowly open RW-V-3 until RW-FI-1 indicates 30% []

flow or 60 cc/ min. Flush with demin water for 2 minutes,

c. Slowly open RW-V-2.X until RW-FI-1 indicates 30% []

flow or 60 cc/ min. Flush with domin water for 3 minutes.

d. Close RW-V-2.X and RW-V-3. []

e. At the PCP, open the remote flush isolation valve []

(see Appendix 1 for proper valve). Flush with demin water for 6 minutes.

f. Close the remote flush isolation valve at the PCP. []

9. Sample Dilution ',

a. Raise sample bottle in LSP cart / cask up, onto needle. []

b. Turn RW-DV-1 to SAMPLE. []

c. Read initial al on buret .

t Crack open RW-V-9 and add 23 mis of water from the buret to the sample bottle, then close RW-V-9.

Read final el Record the volume added, als

c. Turn RW-DV-1 to BYPASS. []

d. P Ace the direction valve for the hydraulic []

piston in the down position and slowly lower the bottle into the cask.

e. Close the cask. []

10. Sample Cask / Cart Removal

- a. Release the brake and remove the cart / cask from []

l the sample station.

~

l DC0294 SII l

l l

-,,w w wy-, ,,.w-- - - -w-- ----- -- - - - - ---m---,,+w,----rww --y-yv -+w, ,-g - - w

NUPSER EP RS-;5:K DIA8LO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION O DATE 6/25/85 PAGE 6 0F 7 TITu~ SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- DILUTED LIQUID SAMPLING FROM RADWASTE ,

b. Perforin a radiation and contamination survey on []

the cart / cask assembly and transfer the sample according to the appropriate EP RB-16 Subprocedure.

c. Turn off the diluted fill station light. []

11. If sample is to be analyzed at CAP:

a. Turn RW-V-4 to CHEM PANEL. []

b. Proceed to EP RB-15:H for pH/ conductivity /D0 []

Analysis and EP R8-15:6 for I.C. Analyses.

c. After analyses return to this section.

12. Final Flushing

a. Turn RW-V-8 to the 9 o' clock position. []

b. Slowly open RW-V-3 until RW-FI-1 indicates 100% []

flow or 200 cc/ min. Flush with domin water for 2 minutes.

c. Turn RW-V-8 to BYPASS. []

d. Terminate flushing by closing RW-V-3. []

13. Close Sample Cooler Water. []

14. Using procedure EP RB-15:E, aliquot and analyze the []

diluted liquid sample for boron and specific activity.

15. Process the data according to EP RB-15:F. []

REFERENCES

1. Sentry Equipment Corp. High Radiation Sampling System Operating I

and Maintenance Manual.

APPENDICES

1. Valves for Obtaining Samples from Radwaste.

1 OCO294 611 l

l l

NUMBER EP RB-15:K 1 AND 2 0iAsLO CANYON POWER PLANT UNIT NO(S) REVISION 0 l

DATE 6/25/85 PAGE 7 0F 7 SENTRY POST-ACCIDENT SAMPLING SYSTEM I'I#

-- DILUTED LIQUID SAMPLING FROM RADWASTE APPENDIX 1 l VALVES FOR OBTAINING SAMPLES FROM RADWASTE CONTAINMENT REMOTE SOURCE REMOTE FLUSH LSP SAMPLE SAMPLE ISOLATION ISOLATION ISOLATION SOURCE SOURCE VALVES VALVE VALVE VALVE Rx Cavity Sump FCV-696 Not FCV-1423 RW-V-2.1 FCV-697 Applicable Floor Drn Reevr Not FCV-1415 FCV-1425 RW-V-2.2 Applicable Equip Drn Reevr Not FCV-1414 FCV-1424 RW-V-2.3 Applicable

(

l i

e DC0294 7II -

l O

NUMBER EP RE .5:L

-~.

,,#14 3 Pacific Gas and Electric Company REVISION O DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 7 OtA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY OPERATING PROCEDURE SENTRY POST-ACCIDENT SAMPLING SYSTEM g TITLE. -- UNDILUTED LIQUID SAMPLING FROM RADWASTE IMPORTANT APPROVED T- Y 10M46 SAFETY PLANT MANAG{dV DATE DISCUSSION The purpose of the procedure is to detail the steps required to obtain an undiluted radwaste liquid sample during accident conditions and '

complete module flushing. Sample sources addressed are Reactor Cavity Sump. Equipment Drain Receiver, Floor Drain Receiver and RHR Pump Room Sump.

PREREQUISITES

1. System was initially lined up as described in procedure EP R8-15:A.

2. Verify that the following annunciator windows are d on the PCP:

a. RADWASTE SAMPLE COOLING WATER LOW FLOW

b. RADWASTE SAMPLE COOLING WATER LOW PRESS

c. RADWASTE SAMPLE COOLING WATER HIGH TEMP

d. RADWASTE HIGH TEMP

e. LIQUID SAMPLE PANEL HIGH PLENUM PRESS

3. The following equipment must be available and operaticnal:

a. Meter-long reach rod

b. Needle flush tool with demin water in a 15 m1 sample bottle and a new septum.

c. Sample cart / cask with the 15 ml lift rod assembly.

j DC0294 111

_ . _ - . - _ _ - _+ _ . _ - . - _ _ - . . _ , _ _ _ _ _ - . - . _ _ - - . . . . . _ -

i 1

DIA8LO CANYON POWEQ PLANT UNIT NO(G 1 AND 2

{0N DATE 6/25/85 PAGE 2 0F 7 SENTRY POST-ACCIDENT SAMPLING SYSTEM N

-- UNDILUTED LIQUID SAMPLING FROM RADWASTE

d. A prelabeled 15 al bottle sample source, date, estimated time of sample, and the initials of the person taking the sample (from this point estimate 16 minutes).

PRECAUTIONS ,

1. This sampling involves processing of water that will be highly radioactive. Precautions should be taken to prevent skin contact

, or ingestion.

2. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush periods, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose rate area.

3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.

PROCEDURE

1. Turn on the switch to light the undiluted fill station. []

2. Place the bottle on the cart / cask assembly cavity []

piston. ;

a. Turn .ne direction valve for the hydraulic []

piston in the down position and lower the bottle into the cask cavity,

b. Close and open the cask to verify that the []

cover is working properly,

c. Position the cart / cask under the undiluted []

radweste fill stations needles and set the brake.

d. Turn the direction valve for the hydraulic piston []

to the up position and raise the bottle onto the needles.

DC0294 2II i

DiAsto CANYON POWER Pt. ANT UNIT NO($) NUMBER EP PB-15:L 1 AND 2 RE/ISION O DATE 6/25/85 PAGE 3 0F 7 yi7g~ SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED LIQUID SAMPLING FROM RADWASTE

3. Sample purging Reactor Cavity Sump:

Coordinate with Operations to turn on the reactor cavity sump pumps, then open containment isolation valves FCV 500 .

and 501 for one minute. Close isolation valves FCV 500 and 501 and open valves FCV 696 and 697. Containment isolation valves FCV 696 and 697 are key operated valve switches controlled in the Sentry Room at the POST LOCA CNT ISOLATION PANEL.

Equipment Drain Receiver or Floor Orain Receiver:

Coordinate with Operations to have EDR or FDR placed on recirculation for Post Loca Sampling.,

RHR Room Sump:

Verify with control room that RHR room high level is indicated. Coordinate with Operations to transfer the entire contents of FDR to another holding tank or overboard.

Manually pump down RHR room sump to FDR and place FDR on g

recirc for Post Loca Sampling.

a. Align RW-V-4 to the SAMPLE position. []

b. Open the corresponding remote plant isolation []

valve (RP!V), remote source isolation valve (RSIV), the PCP (see Appendix 1 for proper valve),

c. Close the remote flush isolation valve at the PCP []

(see Appendix 1 for proper valve).

g: The sample source valves are labeled RW-V-2.1 thru RW-V-2.3. Throughout this procedure, the form RW-V-2.X will be used to indicate the source valve o be operated. The sample source used for sampling will have been given at the briefing by the site Chem l

and Rad Protection Coordinator.

I

d. Slowly open the sample source valve RW-V-2.X []

(see Appendix 1 for proper valve) until RW-FI-1 indicates 100% flow or 200 cc/ min. Purge to waste for 7 minutes.

DC0294 311

4 OIA8LC CANYON POWER PLANT UNIT NO(S) 1 AND 2 E F8-151 f DATE 6/25/85 PAGE 4 0F 7 7,7g' SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED LIQUID SAMPLING FROM RADWASTE

4. Sampling

a. Adjust RW-V-2.X until RW-G-1 indicates 20 psig or []

less.

CAUTIW: Do not exceed 20 psig on RW-G-lin these steps,

b. Turn RW-V-7 to SAMPLE. []

c. Adjust RW-V-2.X until RW-G-1 indicates 20 psig []

or RW-FI-1 indicates 40% flow or 80 cc/ min.

Purge for 1 minute.

d. Close RW-V-2.X. []

e. Let RW-G-1 return to O psig and wait 30 seconds []

to allow bottle to depressurize.

f. Turn RW-V-7 to BYPASS. []

g. Close FCV-696 and FCV-697 if opened earlier []

and notify control room when closed. ;

5. Sample Cart / Cask Removal

a. Turn the direction valve for the cart / cask []

hydraulic piston to the down position and slowly lower the bottle into the cask.

b. Close the cask. Release the brake and remove the []

cart / cask from the sampling station and away from the LSP.

c. Install and secure the auxiliary shielci, []

d. Install and secure the needle flush tool []

centaining a 15 mi sample bottle onto the undiluted radwaste fill station needles.

6. Initial flushing

a. At the PCP, close the sample source isolation []

valve. (See Appendix 1) l DC0294 4II

N DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 p g hPRb-15:L DATE 6/25/85 PAGE 5 0F 7 7,7g' SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED LIQUID SAMPLING FROM RADWASTE

b. Slowly open RW-V-3 until RW-FI-1 indicates 30% []

flow or 60 cc/ min. Flush with demin water for 3 minutes.

c. Slowly open RW-V-2.X until RW-FI-1 indicates 30% []

flow or 60 cc/ min. Flush with domin water for 3 minutes.

d. Close RW-V-2.X and RW-V-3. []

e. At the PCP, open the remote flush isolation []

valve (see Appendix 1 for proper valve). Flush with domin water for 6 minutes,

f. Close the remote flush isolation valve at the []

PCP.

7. If sample is to be analyzed at CAP:

a. Turn RW-V-4 to CHEM PANEL. []

b. Proceed to EP R8-15:H for pH/ conductivity /00 and EP RB-15:G for I.C. analyses. []

\

c. After analyses return to this section. []

8. Final Flushing

a. Turn RW-V-7 to SAMPLE []

CAllTIGi: Do not exceed 20 psig on RW-G-1 in this step.

b. Slowly open RW-V-3 until RW-G-1 indicates 20 []

psig or RW-FI-1 indicates 30% flow or 60 cc/ min.

Purge for 2 minutes.

c. Close RW-V-3 and let RW-G-1 return to O psig. []

Wait 30 seconds to allow the bottle to depressurize.

d. Turn RW-V-7 to BYPASS. []

. DC0294 511

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

,.-,- = - _-

DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NL t P RB-15:L DATE 6/25/85 PAGE 5 0F 7 7m' SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED LIQUID SAMPLING FROM RADWASTE

9. Turn off the undiluted fill station light. []

10. Remove the needle flush tool and survey bottle for []

disposal.

11. Perfom a radiation and contamination survey on the []

cart / cask assembly and move the sample according to the appropriate EP RB-16 Subprocedure.

12. Close Sample Cooler Water. []

13. Using Pr3cedure EP RB-15:E, aliquot and analyze the []

diluted liquid sample for boron and specific activity.

14. Process the data according to EP R8-15:F. .

REFERENCES

1. Sentry Equipment Corp. High Radiation Sampling System Operating and Maintenance Manual.

APPENDICES

1. Valves for Obtaining Samples from Radwaste.

i i

r l

! DC0294 611 l

l f

,- ~

- - - - - - , - - , - - . - , - , . - - - , . . _,,,,,.m ., , ,,. ,..-,---_,_w_--.. _ .- - - ,-- .n - - - - . _ - - - - - - - - - - - - - - - _

or :

DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 N '4 E P RS-15:L p

DATE 6/25/85 PAGE 7 0F 7 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM i

-- UNDILUTED LIQUID SAMPLING FROM RADWASTE APPENDIX 1 VALVES FOR OBTAINING SAMPLES FROM RADWASTE CONTAINMENT REMOTE SOURCE REMOTE FLUSH LSP SAMPLE SAMPLE ISOLATION ISOLATION ISOLATION SOURCE SOURCE VALVE VALVE VALVE VALVE Rx Cavity Sump FCV-696 Not FCV-1423 RW-V-2.1 FCV-697 Applicable Floor Orn Reevr Not FCV-1415 FCV-1425 RW-V-2.2 Applicable Equip Drn Reevr Not FCV-1414 FCV-1424 RW-V-2.3 Applicable r

DC0294 7!!

O NUMBER EP RB-15:M yGsG Pacific Gas and Electric Company REVISION 0 DEPARTMENT OF NUCLEAR PLANT OPERATIONS GE 1 F 5

[ DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY OPERATING PROCEDURE l

l- TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED CONTAINMENT AIR SAMPLING M p g g ,7 W TO APPROVED Y$ .

fp @-Q SAFETY PLANTMANAGERM DATE DISCUSSION The purpose of this procedure is to detail the steps required to obtain an undiluted containment air sample in a cart / cask assembly for gross isotopic analysis.

Complete system flushing will be done at the completion of sampling and the valve line up will be returned to the initial line up.

PREREOUISITES I 1. System was initially lined up as described in procedure EP RB-15:A.

2. Verify that the following annunciator window is off on the PCP and CCP.

a. CONTAINMENT AIR SAMPLE PANEL HIGH PLENUM PRESS

3. The following equipment must be available and operational:

a. Meter-long reach rod

b. 4 Channel MBIS Pressure Monitor (CASP-PI-1109)

PRECAUTIONS

1. This sampling involves processing of containment air that will be highly radioactive. Precautions should be taken to prevent releases to the sampling environment.

2. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush periods, it may not te necessary to stand near the panels and consideration should be given to moving to a low dose rete area.

i

3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.

DC0128 III l

NUMBER EP RB-15:M -

DIABLO CANYON POWER PLANT (JNtT NO(S) 1 AND 2 REVISION 0 DATE 6/25/85 PAGE 2 0F 5 7,7g ~

SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED CONTAINMENT AIR SAMPLING PROLiDURE

1. Automatic Undiluted Sampling of Containment Air Into The Cart / Cask

a. Ensure that a cart / cask is engaged and locked []

on the quick disconnects in the SAMPLE 1 location and the BYPASS valve is closed and the INLET and OUTLET valves are open.

1) Connect the Pressure Monitor unit to the []

cart / cask being used.

2) Plug the AC power cord into the outlet near []

the CASP and turn on the Pressure Monitor to the cell number corresponding to the cart / cask being used.

b. Place the following valve switches on the CCP in the AUTO position:

CCP-AV-1 F' CCP-SV-1.2

CCP-SV-5 '

CCP-AV-2 ,,

CCP-SV-10 .

c. Ensure that CASP-V-17 is closed. []

d. Ensure that the following valves are in the position indicated:

CASP-V-16 to CASP-DV-1 CASP-DV-1 to CASP-SF-5 Il

e. At the CASP, verify that the green INACTIVE Light []

is on. If not, push the RESET button directly below the ACTIVE /IN/CTIVE lights.

f. At the CCP, press the SYSTEM RESET pushbutton. []

DC0128 2II

DIA8LO CANYON POWER PLANT UNIT NO(S)

E P RB-15:M 1 AND 2 N[3 DATE 6/25/85 PAGE 3 0F 5 TIT u SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED CONTAINMENT AIR SAMPLING

g. At the Containment Isolation Valve Panel open the following valves:

FCV-698

FCV-699

FCV-700

h. Press the EXERCISE START pushbutton. []

NJTE: The system will automatically sample containment air through the following sequential operations:

2 minute presample backflush 3 minute sample capture 15 second equilibrate flask pressure 3 minute residual gas removal 15 second post sample backflush 15 second post sample backflush

1. When the ISOLATION SAMcLE FLASX alann sounds, proceed to the CCP and perform the following:

I

1) Press the EXERCISE STOP pushbutton and verify []

the red light in the knob is lit.

a) Note containment pressure as indicated on CASP-PI-1109 and record it on the printer paper at the CCP along with the initials of the person taking the sample.

2) Using the meter-long reach rod, close the []

INLET and OUTLET valves and open the BYPASS valve on the cart / cask.

3) At the CCP, release the EXERCISE STOP []

pushbutton and press the EXERCISE START pushbutton and verify that the SAMPLE LINE FLASK FLUSH timer is on.

K)TE: If the above steps 1) - 3) ere not done within 3 minutes, the program sequencer will reset to home position and the sample flask must be manually flushed as detailed in step k.

DC0128 3II

.c n : -

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:M REVISION O DATE 6/25/85 PAGE 4 0F 5 7,7a~ SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED CGNTAINMENT AIR SAMPLING

j. Observe that the SF EXERCISE COMPLETE light is []

lit for SF-1. If indicator is lit proceed to step 1.

k. Manual Sample Flask Line Flushing MHE: This section is to be done only if the SF EXERCISE COMPLETE light is not on.

1) Using the meter-long reach rod, close the []

INLET and OUTLET valves and open the BYPASS valve on the cart / cask.

a) Note containment pressure as indicated on []

CASP-PI-1109 and record it on the printer paper at the CCP along with the initials of the person taking the sample.

2) At the CCP, turn all valve switches to the []

> CLOSED position.

3) Turn the following valve switches to the OPEN position: l CCP-SV-10 l CCP-SV-1.2 CCP-AV-1

'll 1, .

4) Flush the sample flask line for 3 minutes. []

5) Close the following valves:

CCP-SV-1,2 l'

CCP-AV-1 i CCP-SV-10 '[

1. Sample Cart / Cask Removal

1) Turn off Pressure Monitor and disconnect from []

l cart / cask.

2) Unlock the quick disconnects from SF-1, []

remove the cart / cask assembly and place it in a temporary hold area.

I l DC0128 4II l l l l J

?

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ' S ON DATE 6/25/85 PAGE 5 0F 5 TITw" SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- UNDILUTED CONTAINMENT AIR SAMPLING

3) Detach the paper with the cart / cask information []

from the printer on the CCP an attach it to the cart / cask.

?OTE: Perform a radiation / contamination survey on cart / cask assembly.

4) Install a backup cart / cask assembly. []

5) Push the RESET button at the CASP to change []

the sampling flask indicator light from ACTIVE to INACTIVE status.

6) At the CCP, check closed or close all valve []

switches.

m. At the containment isolation valve panel, close the following valves: 4 FCV-698 .

( FCV-699 FCV-700

'l 'l t .

\

DC0128 5!!

ML20137X193

Text

6.1 Appendiz-A

6.4 Appendiz-D

Description:

SUMMARY

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