DCL-85-112, Public Version of Revised Emergency Plan Implementing Procedures,Including Table of Contents,Rev 4 to EP OR-1 Re Offsite Support & Assistance & Rev 3 to OR-2 Re Release of Info to Public & 850401 Release Memo

Public Version of Revised Emergency Plan Implementing Procedures,Including Table of Contents,Rev 4 to EP OR-1 Re Offsite Support & Assistance & Rev 3 to OR-2 Re Release of Info to Public & 850401 Release Memo

ML20113A103
Person / Time
Site:	Diablo Canyon
Issue date:	03/14/1985
From:	Shiffer J PACIFIC GAS & ELECTRIC CO.
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
CON-#285-201 DCL-85-112, OL, PROC-850314, NUDOCS 8504090478
Download: ML20113A103 (96)

Text

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. 1 I

e PGandE Lett;r No.: DCL-85-112 ENCLOSURE 1 Updates Included In This Submittal DIABLO CANYON. EMERGENCY PLAN IMPLEMENTING PROCEDURES Volume 3B Updated Table of Contents EP OR-1, Revision 4*

EP OR-2, Revision 3 EP EF-2, Revision 5*

EP EF-7, RESCINDED EP RB-15, Revision 1

EP RB-15A, revision 2 EP RB-15G, RESCINDED EP RB-15G, Revision 0**

EP RB-15H, Revision 0 EP RB-15I, Revision 0 e

f EP OR-1 and EP EF-2 were approved on February 4,1985, distributed March 4, 1985.

• • New procedure .

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i ENCLOSURE 2 I

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] Location of Privacy / Proprietary Information

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e Procedure:

EP OR-1 Table 1, Offsite Emergency Support Organization Phone List, pages 1-9.

EP OR-2 Attachment 1, Media Nott fication List, page 1.

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> ENCLOSURE 3 Updates to Diablo Canyon I .

9 Emergency P1an Imp 1ementing Procedures

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PGandE Lettsr No.: DCL-85-112 2

CURRENT EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3B L TITLE- REV OR-1 Offsite Support & Assistance 4 OR-2 Release of Information to the Public 3 EF-1 Activation and Operation of the Technical Support Center 5 EF-2 Activation and Operation of the Operational Support Center 5 i'

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 4 EF-6 Operating Procedures For EARS 9845C Controlling Stations 3 EF-6S1 Transfer of EARAUT Control 1 EF-8 EARS Operating Procedures for TSC-CC HP-1000 Station 0 RB-1 Personnel Dosimetry 1 g RB-2 Emergency Exposure Guides 1 j RB-3 Stable Iodine Thyroid Blocking 0 4

RB-4 Access to & Establishment of Controlled Areas

Under Emergency Conditions 1

RB-5 Personnel - Decontamination 2

[ RB-6 RB-7 Area & Equipment Decontamination 2

! Emergency On-Site Radiological Environmental Monitoring 3 RB-8 Emergency Off-Site Radiological Environmental Monitoring 4 i RB-9 Calculation of Release Rate & Integrated Release 3

RB-10 Protective Action Guidelines 1 RB-11. Emergency Off-Site Dose Calculations 4 i

RB-12 Mid and High Pange Plant Vent Radiation Monitors 1 RB-13 Improved In-Plant Air Sampling for Radioiodines 1 RB-14 - Core Damage Assessment Procedure 1 j RB-15 Sentry Post Accident Sampling System (SPASS)

Initial Sampling Exercise After An Accident 1-i RB-15A SPASS Initial Actions During An Emergency 2 RB-158 SPASS Reactor Coolant Sampling (Stripped-Gas and Diluted RCS) 1 3

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-]i; RB-15D SPASS Containment Air Sampling 1

-: RB-15E SPASS Gas Chromatographic liydrogen Analysis 1

SPASS RCS Liquid and Gas Sample Handling

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RB-15F SPASS Data Analysis 1 MQ '; RB-15G O RB-15H SPASS ION Chromatographic Chloride analysis 0

d3 RB-15I SPASS pH/ Conductivity / Dissolved Oxygen SPASS Sample Storage and Disposal 0 RB-16 SPASS Subsequent Sampling 0

>i RB-16A 0 4 SPASS Initial Actions During An Emergency RB-16B1 (Not Intended to Meet The 3-Hour Time Limit) 1 SMS Diluted Liquid Sampling From Reactor Coolant RB-16B2 (Not Intended to Meet The 3-Hour Time Limit) 1 SMS Undiluted Liquid Sampling From Reactor Coolant RB-16B3 (Not Intended to Meet The 3-Hour Time Limit) 1

SMS Reactor Coolant Stripped Gas Sampling RB-1684 (Not Intended to Meet The 3-Hour Time Limit)

SMS Diluted Liquid Sampling From Radwaste 1 RB-16BS (Not Intended to Meet The 3-Hour Time Limit)

SMS Undiluted Liquid Sampling From Radwaste 1

. i RB-16C (Not Containment SMS Intended toAirMeet The 3-Hour Time Limit)

Sampling 1 I .

RB-16D (Not Intended to Meet the 3-Hour Time Limit)

SMS Gas Chromatographic }iydrogen Analysis 1 i

4 RB-16E (Not Intended to Meet the 3-Hour Time Limit)

SMS Liquid and Gas Sample Handling 1 i

' RB-16F (Not Data SMS Intended to Meet The 3-Hour Time Limit)

Analysis 1

-q RB-16G (Not Intended to Meet The 3-Hour Time Limit)

SMS Ion Chromatographic Chloride Analysis 0

-} RB-16H (Not Intended to Meet The 3-Hour Time Limit)

SMS Ph/ Conductivity Dissolved Oxygen 1 b

RB-16I (Not Intended to Meet The 3-Hour Time Limit)

SMS Undiluted Containment Air Sampling 1 (NotSample Intended to Meet The 3-Hour Time Limit) s

' RB-16J SMS Storage and Disposal O

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}, m REVISION' 4

{. DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 12/26/84

• ( DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 2 l EMERGENCY PROCEDURE M LE O OFFSITE SUPPORT AND ASSISTANCE lMFO:.m., ANT l

1 APPROVED: Wb r . -446 TO PLANT MANAGFR DATE

^

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This procedure provides a functional list of non-PGandE organizations 4 which are available for emergency response support and assis,tance.

Telephone numbers are provided which are to be used for initial 4

notification of the need for emergency support. Organizations required to be notified of an emergency are addressed in the procedures referenced below or in the procedure dealing with the type of event. This procedure and changes thereto requires PSRC review.

GENERAL

(

1. Reouests for support or assistance from non-company organizations should be specific concerning the nature of the support or assistance requested, the location where needed, when it is

needed, and the phone number to use to return a call. Requests l j- may be made to mobilize support on a standby basis.

2. All initial request for support shall be approved by the Site  ;

j Emergency Coordinator or the Recovery Manager at the EOF. l

Subsequent requests shall receive the same approval if they )

j require additional resources. Requests for assistance from l i organizations supporting San Luis Obispo County also reouire  !

! County Emergency Services Director ap;:reval prior to making tha 1

' l j request.

3. Emergency response organizations are listed in Appendix 1 under 4 t he (.! N < ,- f r :13~31 titler-  !

, Radiological Emergency Protective Actions Medical Emergency Fire Emergency Health Physics / Assessment Support Plant Operation / Repair Support '

Offsite Emergency Response Support Law enforcement emergency contact means are addressed in the C appropriate security procedures.

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d EP OR-1 d NUMBER DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2

.! REVISION 4

^! DATE 12/26/84

PAGE 2 0F 2 TITLE- 0FFSITE SUPPORT AND ASSISTANCE i) n SUPPORTING PROCEDURES NPAP Cll, and its supplements, "Non-routine Notification and Reporting y to the NRC and Other Governmental Agencies"

I l] EP G-3 " Notification of Offsite Organizations" 1 ~

ATTACHMENTS

. .)

a 1. Attachment 1 - Offsite Support and Assistance Functional

Description

2. Table 1 - Offsite Emergency Support Organization Phone List.

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Page 1 of 2 j PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 I

. ATTACHMENT 1 TITLE: OFFSITE SUPPORT AND ASSISTANCE CONTACT LIST - EP OR-1 I. Radiological Emergency Protection Actions v The organizations listed in Table 1 under this heading provide support to the Sar, i

? Luis Obispo County Emergency Organization in implementing protective actions for the j general public.

i

-j All support requests from these organizations should be coordinated with San Luis

[i Obispo County. Direct requests for support would not ordinarily be required, but 1 exceptions to this may be necessary in the event of an initial notification to San Luis Obispo Ccunty reociring immediate protective actions in the low population zone j] (6 mile radius) or beyond in the affected sectors.

a II. Medical Emergency

l 1 The organizations listed in Table I under this heading provide assistance in the j transpurtation or treatment of persons injured and contaminated with radioactive j material, and/or overexposed to radiation or radioactive materials. Persons so 1 injurec' will norr.. ally be treated at French Hospital in San Luis Obispo, however, i( Saint Francis Memorial Hospital is also available shculd the need for additional nospital services arise, d III. Fire Emergency u .

j The organizations listed in Table 1 undcr this heading provide backup fire fighting

.: support to the Califcrnia Departreent of Forestry (CDF), ir the site area. Assistar.ce is coordinateo through CDF in all cases.

U IV. Health Physics / Assessment Support i

The organizations listed in Table I under this heading provide assistance in on or offsite er.onitoring, raciation protection or radiological accident assessment, y Requests for assistance are coordinated through the Emergency Radiological Advisor.

j for onsite or near site activities and with San Luis Obispo County for offsite j activity.

o

.. h e. Gge e . u h i o,,,.. c The organizations listed in Table I under this heading provide assistance in i technical assessment of plant conditions, and in maintenance / repair projects. Only 1 those organizations with defined emergency response roles are included. Assistance j from these organizations and from the resources of PGandE, other utilities ano j

vendors are available through the Corporate Emergency Response Organization.

. (

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DC0043 3VIII

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Page 2 of 2 TITLE: OFFSITE S'UPPORT AND ASSISTANCE CONTACT LIST - EP OR-1 i

)

VI. Offsite Emergency Response Support The organizations listed in Table 1 under this heading provide offsite response i support to the San Luis Obispo County Emergency Organization, or are available for support of PGandE offsite operations. These support organizations are categorized as:

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1) Transportatier,

2) Law Enforcement

3) Traffic Control

4) Public Alerting and Care I

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Page 1 of S 12/84 .

PACIFIC GAS AND ELECTRIC COMPANY .

o DEPARTNENT OF NUCLEAR PLANT OPERATIONS

( DIABLO CANYOH POWER PLANT UNIT NOS.1 AND 2 TABLE 1 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 Organization Function (s) location (s) Phone Number (s)

I. Radiological Energency Protective Actions US Coast Guard 1) Clear craft from Rescue water near DCPP Coordination Center

2) Shipboard Alameda radiological or monitoring Monterey

(

Operation i

3) Vessel decontamination i State Protective acticns in San Luis Obispc- 1 Department of- State Parks & Beaches: Headquarters Parks & hontana De Gro Pt e re sti:n A i'a State Head. Herrd.Certie i Pismo State Beach  ;

Horro Bay State Park Pismo Ranger Atascadero State Beach Station State Ingestion pathway 744 "P" St.

Department cf ' monitoring coordination Sacramento, CA .

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Public ard focd stuff  ?,

Health-Radiolog- interdiction as required.  !

feal Health

• i Secticn ,

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, I II. Medical Emergency (See precedures M-1 and R-1 also) ,, .-

s San Luis Onsite amb alance service. 358 Santa Rosa - ie . ! . , ,

1 A*belzaet Ser Let Obispe - ' . . . ',

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i Service, Inc.

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.c J' l 1 Air Arnbulance, Air Transrcrtation 701 Skyway f. Es , jf. .... '

Inc. (fixedwin or San Carlos. CA ; ,f N ,&. ,,

helicopter fror. site ' ' -

, or airport (under PGandE (L:"'" c : c.fr i i;S' N. L.'

J contract).. ' 37.( 0EM/hyi:LJ ',.

b If 'i J.Jjjy-f g. ;jfl. .

4 California Air Heatvac Hunter Ligget f.m C. x.e h( National Guard  %- M .O %$ w s

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TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued)

• i Organization Function (s) location (s) Phone Number (s') ,

San Francisco Ambulance Service in 2829 California Ambulance the San Francisco Area. Street Service San Francisco

- French Hospital Emergency Medical 1911 Johnson Ave..

Treatment San Luis Obispo Dr. Fred Mettler Consultant on VA Hospital  ;

(REMS Corp.) Radiological Injuries Albuquerque, 1 New Mexico .

- or - l 3004 La Mancha St. '

N.W. i j Albuquerque, NM 3 3 Saint Francis Emergency Medical 900 Hyde Street j Memorial Treatment San Francisco i

Hospital

Ill. Fire Emergency Cali 4rnia Prierry Site Fire Fighway 1 Departrent of Fighting Response San Luis Obispo Fui t

n. ; Ai Attad Base Paso Robles Airport I Arroyo Grande Backup fire fighting 140 Traffic Way Fire Departrent support. Arroyo Grande 1 l

h Pismo Beach Backup fire fighting Fire Department support.

1000 Bello Ave.

? , Pismo Beach 2

e San Luis Obispo Br.ckup fire fighting Garden & Pismo ,

Fire Departnee support. Streats -

• San Luis Obispo i Snuth Bey Fi-e Rackup fire fichtirc

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8. 2315 Bayview . 2/ . 1

{ Department support. Heights Drive >. '

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Morro Bay Fire Backup fire fighting 715 Harbor '

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Department support. Morro Bay . . f.

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Pag 2 3 of 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued)'*

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l I- Organization Function (s) ,Laation(s) Phone Number (s) ~

l IV. Health Physics / Assessment support Onsite I

Nuclear 1) Onsite assessment 1450 Maria Lane Regulatory 2) Coordinate federal Suite 260 Commission technical response Walnut Creek, CA 3). Develop protective Region V action Incident Response, reconsnendations. Center

4) Radiological monitoring .

Sacramento Chemical-Radiation Rancho Seco Municipal assistants and equipment. Heald, CA Utility District Control Room i

Southern Health Physics San Onofre California technicians and San Clemente, CA Ediser, equipment.

Offsite

( Cepi.. ti..em Oi l', it:dcr oi uinite San Frani.ist.o Energy monitoring and Operations assessment Office-Region 7 coordination. 7333 Broadway

2) Coordination of Oakland, CA Federal response .

(IREP Coordination). , _

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_ Nevada Operations .

Office Las Vegas, Nevada'

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Envi onmental Complete radiological Dave Duncan, Protection monitgring and Regional

-Agency assessment assistance. Radiation o Representative, .  ;

, Region IX, San j.( .- ,

Trer.:':: 4 ;f L_ . .

Wayne Bliss, b ,

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, Director of , .

Office of .

j% l'w Radiation jf^;4.;,;k' '~

. Programs, Las @,. -

-s  ;

1 Vegas Facility a

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TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) i Organization Function (s) location (s) Phone Number (s) ,

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Department of Assist in monitoring and HQ-6th Army Defense medical assistance if Presidio of San (Army) requested by the IRAP Francisco coordinator or local authorities (Nuclear l

Accident Incident Control '

l

' Teams). g Department of Assist in monitoring and Commander - Naval Defense medical assistance if Base (Navy) requested by the IRAP San Diego, CA Coordinator (Nuclear Accident Teams).

l.

National Weather reports, WSFO-Redwood  !

Weather forecasts and special l Service advice from Wr.ther City ,

(fl02.A) Service Forecasting  ;

Offices (WSF0)-normally WSFO-Los coordinated through Angeles i M tc. r!,v y porc e--e t f-CIRC.

i State Office Assessment support to Emergency of Emergency local agencies. Response Center; . .

Sacramer,to, CA

~

Services State Depertment Ingestion pathwry 744 "P" Street i ,

a of Public~ monitoring coordinatior. Sacramento. CA i" c ' ,

Health-Radiolog- and food stuff 11 MM'- - '

ical Health ' interdiction as required. ~ .. ,-M . QF ' [: 2 Bureau ,

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i San Luis Obispo Coordinate county County Gov't.

MM : '94 cd . ? ?f.j%;,'[7 County of emergercy response Center gF Emergency activities and emergency San Luis Obispo ;g', ' 9,g 9 i Services planning. gg*.p,gy).4 u - . m:

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,s San Luis Obispo Direct offsite moni- d M

+ County Environmental tnring and assessment activities of San Luis 2191 Johnson San Luis Obispo dlQ.

Q~bW%l:%g+Vf Ave.t.[$f-[}

Obispn County. - )

. Health

? 5574 Capistrano )"dh iM . M,'d}"}m

" " y I Ave. Atascadero  ?

0CC045- 8VII

Pag? 5 cf 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATIbN PHONE LIST - EP OR-1 (continued)" ,

I *! Organization Function (s) location (s) Phone Number (s) i V. Plant Operation / Repair Support i

l Westinghouse Technical, onsite or Monroeville (Notifyas Electric Company materials assistance or Nuclear Center Indicated Below) -

reactor systems or components.

NOTIFY ONLY IF TECHNICAL, ONSITE OR MATERIALS ASSISTANCE ON REACTOR SYSTEMS IS NEEDEDPROVIDEPLANTEMERGENCYNUMBER[~ 3FORREPLY. NOTIFY ONE l WESTINGHOUSE CONTACT ONLY USING THE BROW LIST IN THE ORDER SHOWN. )

TITLE NAME OFFICE /HOME/HOME HOT LINE

1. SITE SERV!CES MANAGER R0ff BL'CHHOLZ NOTE: UNLESS OTHERWISE TiiUTCATED ALL THE BELOW NUMBERS ARE IN AREA CODE 412. i

2. OPERATING PLAl;T GIL KUBANSEK RESIDUAL MA'.' AGE -

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( AS L ALIlf.l.n's L - Unbc LAnreiLL ,

9 2nd ALTERNATE JIM REA '

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3. SERVICE RESP 0f;SE MANAGER TOM HITLO

~

.lst ALTERNATE 808 STOKES 2nd ALTERNATE JOE LEBLENG

. 4 EMERGENCY RESPONSE T0ft APDERSON P! RECTOR ,

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5. EMERGENCY RESP 0!iSE RON LEHR g

DEPUTY DIRECTOR  !

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F C.  : .:. : * -

COMMUNICATIONS - -

Q-NOTE: - Unless indicated otherwise, all phone numbers are area code 412. Where an area code other thari 412 is shown, it applies to the office, home, and HHL' numbers.

i DCC043 9VII

. 1 Page 6 of 9 ,

TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued)

Organization Function (s) location (s) Phone Number (s)

Institute of 1) Locating emergency Emergency i Nuclear Power manpower and Response Center Operations equipment Atlanta, Georgia

2) Operational analysis-

3) Information dissemination

4) Organization of i experts for advice i Rogers Helicopter on standby Rogers Helicopter, Helicopter under PGandE contract Clovis, CA  :

sound system and i lightino. '.

i ji i

i Rottr-Aics, Inc. Helicopter (s), as Rotor-Aids, Inc.

available, unoer PGancE 0xnard, CA CCrtract.

ni i s ric . .scs .ci he i s tupici g h , , ea ant. Jose g

available under PGenciE -

contract. Medivac i ca pa t. il i ty.

Conder Helicopter (s),as Condor -

Helicopters availabic, under PGandE Helicopters and . .

contract. At least 1 Aviation Inc.

- light duty helicopter Oxnard Airport available at all times. Ventura, CA or -

Mr. Gary 0' Conner  !  ;

Air Act';1aa:c, '- ' '

Fivec' eing er helicepter Mr. Steve Smith L ~. . . 7 ," , ' ' ' '

International air ambulance service 795 Skyway San -

~

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California Fixed wing and heli- Air Attach Base l .,,' '

w Departcen. of ccpter for cct:. .y/ Pasc Rchics is ,'._U~'-

Forestry state support, as Airport bw -

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ava il at,l e.

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Ifage 7 cf 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued)-*

I Organfration -Function (s) Location (s) Phone Number (s)

VI. Offsite Emeroencv Response Support ,

Transportation

... ~ ,

l California 1) Fixed wing or San Francisco Area ~ .

Highway Patrol helicopter for 455 8th Street 7

transportation of San Francisco I essential personnel.

2) Escort of priority vehicles, i State San Luis Obispo Area S.L.O. H.Q.

Parks and Recreation Hearst Castle  :

Department ,

Ken Huddlescon  !

Emergency Coordinator 24 Hour  !

( Dispa tcr.er _ . . _ _ _ l Pisrrn Beach (PangerStation)

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Page 8 of 9 .

( TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) i J. Oroanization Function (s) location (s) Phone Nunber(s) -

..! Law Enforcement

..\

i San Luis Obispo 1) Lt.w enforcement in Dispatch office 1 County Sheriff county areas not County ,

V under city PD's. Operational j 2) Primary response Facility 1

agency under SLO Highway 1 t County emergency San Luis Obispo 1 plan.

I j Arroyo Grande Law enforcerent in 200 N. Halcyon 1 Police Arroyo Grande. Rd.

! Department Arroyo Grande -

i , .P -

Atascadero Law enforcement in Administration -

Police Atascadero. Building '

! Department Lewis Ave.

Atascadero i

fiorro Bay latz enforce t-t in 850 Morro Bay Police Morrn Bay. Boulevard l i Geni u..cni i;orro Say g Pismo Beach Law enforcenent in Pismo 1000 Bello Ave. f Police Beach. Pismo Beach , l Department j

~

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San Luis Obispo Law enforcement in Sar. 575 Santa Rosa  ;

_ Police Luis Obispo. San Luis Obispo { l Department i q

Monterey County Law enforcement in Salinas '

I Sheriff f:crterey Ccunty.  :

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Sente Barb?rr Law enforcement in Scnta Sante Barbera j - 1, _

County Sheriff Barbara County. L- ', .

Traffic Control (City police, fire and public work also support) l r, - - ,

California 1) Primary traffic 675 Calif. Blvd. ? ~q Highway Patrol cortrol support to San Luis Obispo ? a ,.

SLO County. . i

. % .. I i 2) Fixed wing or CoastalDiv.H.Q.:Jj.n.O  ;

1122 Laurel Lane _jE h 6 helicopter traffic I surveillance. San Luis Obispo  ;

i 0C0043 12VII

Page 9 ef 9 TITLE: OFF3ITE EMERGENCY SUPPORT ORGAN'IZATION PHONE LIST - EP OR-1 (continued)~*

l( Oroanization Function (s) location (s) Phone Number (s)  ;.

. Public Alerting and Care 1 i'

American Nuclear Emergency assistance 270 Farmington Insurers (AtI) funding of the public for Ave.

i emergency response Farmington, Conn .

I ~

expenses from an j .

7 extraordinary nuclear j i occurance. Assistance is -

! coordinated through CIRC, i Corporate Liaison Coordinator.

! American Red Primary operator of care 1216 Morro

? Cross and feeding facilities San Luis Obispo in support of SLO County.  ;

Emergency Primary stations for KVEC 8

Broadcas t providing emergency 820 Walnut Stations public information in San Luis Obispo support of SLO County.

KSLY 2895 S. Higuera

-( Sar. Luis CLisp; KATY 1146 Monterey San Luis Obispo . _ , _ .

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NUMBER EP OR-2

[^ }Gv43 Pacific Gas and Electric Company REVISION 3

' A DATE 1/23i85

, DEPARTMENT OF NUCLEAR PLANT OPERATIONS I( ciAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 3 EMERGENCY OPERATING PROCEDURE TITLE. RELEASE OF INFORMATION TO THE PUBLIC APPROVED Y S i PLANTMANAGg DATE ,

l i IMPORTANT

! TO  !

l SAFETY

! SCOPE This procedure describes the requirements for releasing infomation to i the public concerning an Alert, Site Area, or General Emergency

} experienced at the Diablo Canyon Power Plant, t

This procedure and changes thereto require PSRC review. l l

GEhERAL

1. Any information released to the news media during an emergency

( situatior, at the Diabio Canyon Fower Fiant must be accurate ano informative. For this reason, all nfficial PGandE news relettes will be issued after being reviewed for technical accuracy and approved by the Recovery Manager, or in his absence, the Site Emergency Coordinator.

?. Normal news releases which do not involve an Alert, Site ANa, or l General Emergency situation shall be made in accordance with Administrative Procedure A-9, "Public Announcements Involving Nuclear Plant Operations."

3. When possible, the appror.riate federal, state and local agencies involved in the response, shall be informed of the content of all

PGandE official releases before they are made.

4 The Public Information Recovery Manager (PIRM) or interim PIRM shcold cccperate in the preparation of all news reletses oriainating from federal, state or local agencies involved in the l emergency.

l l

(

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DC0003 IV _

E

. DiAaLO CANYON PcMNER PLANT UNIT NCHS) 1.AND 2 S ON j DATE 1/23/85 j PAGE 2 0F 3

$ m LE. RELEASE OF INFORMATION TO THE PUBLIC

5. Any news media personnel who arrive at the plant site shall be denied access unless their presence is specifically approved by the Site Emergency Coordinator, the Recovery Manager and the Public Information Recovery Manager. Security force personnel shall direct the news media to the Media Briefing Center.

I INITIATING CONDITIONS ,

The Shift Foreman declares that the plant is in an Alert, Site Area, or General Energency condition as defined in Emergency Procedure G-1,

, " Accident Classification and Emergency Plan Activation" and initiates the actions described in Emergency Procedure G-2 " Establishment of the Onsite Emergency Organization."

IMMEDIATE ACTIONS

1. Uper. activation of the emergency plan, the Advisor to the County

' Emergency Organization (ACE 0) and his staff will activate the Emergency Operations Facility (EOF) in accordance with Emergency Procedure EF-3, " Activation of the Emergency Operations Facility."

SUBSEOUENT ACTIOMS t

) 1. The Site Emergency Coordinator shall be responsible for approving

?

all Company releases to the news media until arrival of the 1 kecovery Manager at the EGF. The Recovery Manager will assume responsibility for approving all releases to the news media after arrival at the EOF.

I 2. All releases should be provided to the San Luis Obispo County Public Information Officer, if available, prior to release!

]

1

.j 3. If the Site Emergency Coordinator or the Recovery Manager dh ects-9 that the news media are to be contacted, the interim PIRM may

notify the news media listed on Attachment 1, " Media Notification List," or other bonafide media contacts, and may read the appropriate prepareo message from Attachment 1, "Prepareo Messages for News Media," or prepare a special release.

4. Once news briefings have been authorized, the PIRM, interim PIPf or the Technical Assistant to the PIRM (TAPIRM) shall:

a. Notify the Public Information Officer of the San Luis Obispo County Emergency Organization of the news release and its content, and coordinate a joint release, if possible.

4 4

j DC0003 2V e

)' DiASLO CANYON POWER PLANT UNIT NO(5) 1 AND 2 .

ON DATE 1/23/85 PAGE 3 0F 3

( TTts: RELEASE OF'INFORMATION TO THE PUBLIC

b. Notify the news media listed on Attachment 1, " Media Notification List" or other bonafide media contacts that a

} statement is forthcoming and infom them that the Cuesta College Auditorium " Media Center" will be opened.

c. Request the Media Center Manager, or their alternate, to

! proceed to the Media Briefing Center, open it, and prepare for the meeting with the media.

d. The PIRM or interim PIRM assisted by the TAPIRM will prepare news releases originated by PGandE. The TAPIRM will primarily assure tne accuracy of the technical content of

, the release.

SUPPORTING PROCEDURES AP A-9, "Public Announcements Involving Nuclear Operations" EP G-1, " Accident Classification and Emergency Plan Activation" EP G-2, "Establishmee.c of the Onsite Emergency Organization"

>(~ EP EF-3. "Activatian of the Emergency Operations Facility" l

Corporate Emergency Response Plan Inplementing Procedure 3.2, "Public Relations" l ATTACHMCIATS

1. Media Notification List

2. Prepared Messages for News Media

(

DC0003 3V 4

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PACIFIC GAS AND ELECTRIC Page 1 of I

. OEPARTMENT OF' NUCLEAR PLANT OPERATIONS i DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 4

o-ATTACHMENT 1 l i MEDIA NOTIFICATION LIST i

i Radio and Television Stations l KVEC Radio-E.B.S Input Days .

I (SanLuisObispo) .\

KSBY Television (San Luis Obispo) {'

j KC0Y Television (Santa Maria) l KEYT Television (Santa Barbara) l, KSLY Radio-E.B.S Input Nights

(San Luis Obispo) (Also KUNA-FM)

KATY Radio-E.B.S. Backup (San Luis Obispo) l KCBX-FM Radio (Sar Luis Obispo) '

! K202-FM Radio (San Luis Obispo) h KBAI. Radio (Morro Bay) l KPRL Radic (Pasn Rct.les)

, (Aisc KPRA CH) l KKAL Racio (Arroyo Grande)

. AlQu nadio th gAtaschoero) i s

Newspapers I

r Daily Press (Paso Robles)

(Bi-Weekly) a

- Santa Maria Times l

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g Telegram-Tribune .

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, -Santa Barbara News Press t i s.

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- Page 1 of 5 P PACIFIC 4AS AND ELECTRIC I. DEPARTMENT OF NUCLEAR PLANT OPERATIONS f, DIABI A CANYON POWER PLANT UNIT NOS.1 AND 2

' ATTACHMENT 2 i PREPARED M N NEWS MEDIA DRAFT NEWS RELEASE

} Date and Time (24-hour clock) l Pacific Gas and Electric Company notified count

Nuclear Regulatory Comnission (NRC) officials at (time) y, state and (day or date) of an (emergency classification) at its Diablo Canyon Nuclear Power Plant Unit near San Luis Obispo, California.

As required by the NRC, an (emergency classification) is declared for (emergency classification definitior)

The (emeroency classification) was declared because (describe events: use as many paragraphs as necessary)

PGandE said the plant is (continuina to operate), (being operated atreducedpower)(shutdown)(beingshutdown}.

The Citblo Canycr. riant is sete 220 miles south of Sar. Francisen 1 and 200 miles north of Los Angeles.

1i i The !E.4 billier plant's tre nuclear. units tonather can generate 1

> about 2.2 million kilowatts of electric power.

1 PGandE, one of the nation's largest utilities, provides gas and i elec.ric se vice tc 20 nillion Northern Californians. I j' 7##

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'.) DRAFT NEWS BULLETIN - CLOSE OUT EVENT i

,f Pacific Gas and Electric Company, in agreement with Federal State and a County officials, rescinded the energency status declaration for Diablo 1 Canyon Nuclear Power Plant at (time) on (date) .

s 1

The 2.2 million kilowatt Nuclear Power Plant near San Luis Obispo, 4

California, is (operatino normally, at safe shutdown).

Complete details will be given to the news media hs they become j available.

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! , -NEWS RELEASE GUIDELINES I. Obtain details of the emergency from the Site Emergency Coordinator or Recovery Manager. Consult with Technical Advisor.

!!. Include:

A. Time and date of news release.

B. Time of notification of County and State officials.

C. Principal actions being taken at the plant.

D. Assistance being given by County or State.

E. Radioactivity release.

I. Wind direction

2. Dose estimates: site, offsite.

3. Deployment of PGandE radiological monitoring teams.

F. Injuries.

1. How many.

2. What kind.

. G. Number of workers on site when emergency declared.

, III. Work in important general information (plant location, generr. ting l carecity, construction ecsts, etc.) where appropriate.

It. Attributt til infornation to either Pacific Gas and Electric Compar.y i or designated coreany spokespersons.

A. When nating PGandE crployees, identify then by corporate title and explain their emergency duties and title.

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!{ ATTACHMENT 2 (Continued)

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1 EMERGENCY CLASSIFICATION DEFINITIONS U

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UNUSUAL EVENT:

1 U As required by the NRC, an " Unusual Event" is declared for an d other-than-normal plant condition not requiring an emergency response for the county, state or general public.

']a 3 ALERT:

-l As required by the NRC, an " Alert" is declared for an actual or 2

potential degradation of plant safety systems. Any release of j radioactivity would be small and undetectable beyond a one-half mile radius T of the plant.

U

] SITE AREA EMERGENCY:

As required by the NRC, a " Site Area Emergency" is declared for actual or potential failure of major plant functions needed to protect the public.

Any release of radicactivity may affect areas around a one-half mile radius of the plant.

GENERAL EMERGENCY:

As required by the !!RC, a " General Emergency" is declared for actual q' or imminent releases of radioactivity which may require protection actions by the. general public.

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. GENERAL INFORMATION B '.

! The Diablo Canyon Nuclear Power Plant occupies 735 acres of coastal i property about 12 miles southwest of San Luis Obispo ce California's

central coast.

l The Diablo Canyon Nuclear Power Plant is situated on the California i coast about midway between San Francisco and Los Angeles.

l l The Atomic Energy Comission licensed construction of Diablo Canyon 8

Unit 1 in April 1968 and Unit 2 in December, 1970. The two power plants l l have been ir. operation since (date and date) respectively.

I I

4 The Diablo Canyon plant uses a Westinghouse pressurized water reactor.

During normal operation, the water in the reactor is under about 2,200 pounds per square inch pressure, which prevents the water from boiling even thouah it is heated to above 600 degrees Farenh'it.

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t NUMBER EP EF-2 8o TGV43 Pacific Gas and Electric Company REVISION 5

i . A DATE 1/14/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS l . l. I i 1 AND 2 PAGE 1 0F 6 DIA8LO CANYON POWER PLANT UNIT NO(S)

EMERGENCY PROCEDURE ACTIVATION AND OPERATION OF THE TITLE. OPERATIONAL SUPP0RT CENTER O .

APPROVED PLANT MANAGER g DATE i

j SCOPE i This procedure describes the actions taken in the event it becomes necessary to activate the Operational Support Center.

) This procedure ard changes thereto require PSRC review.

?

GENERAL The Operational Support Center (OSC) provides a place separate from j the control room and Technical Support Center where designated suoport j( personnel assemble and await specific assignment during an emergency.

4 The OSC is designated as the Chenistry and Radiation Protection access

! control entry hallway, locker room and break room located on the plant l 85' olevation entrance to the auxiliary building, and adjacent 1 radiological access control and cold machine shop areas. These areas 3 contain a variety of emergency support equipment which is imediately available for emergency use. It is equipped with dedicated tie line telephone extensions to the control room and TSC and also has a CBX j 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 emeroency signal.

K

2. Provider a ine" inn fnr the staging of trained manpower for assignment to relief and special emergency positions on an as-needed basis to facilitate the following functions

- emergency maintenance, repair and damage control L

- fire fighting, search and rescue and first aid h

- emergency sampling of plant fluids '

L a location for storage of selected emergency response j{ equipment j - provide facilities for personnel decontamination DC0026 IIX l

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I AND 2 NUMBER EP EF-2 3 REVISION 5 1

DATE 1/14/85 l PAGE 2 0F 6 '

I TITLE. ACTIVATION AND OPERATION OF THE OPERATIONAL SUPPORT CENTER 1

3. Provides an assembly point for reserve ifcensed and non-licensed plant operators who may respond as directed to emergency mitigation efforts.

L Initiating Conditions il i The Shift Foreman declares that the plant is in an Alert, Site Area j Emergency, or General Emergency status as defined in Emergency 1 Procedure G-1, "Acc1 dent Classf fication and Emergency Plant i

Activation", or determines that activation of onsite emergency centers is warranted and sounds the Site Emergency Signal or orders call out i of plant staff personnel in accordance with Emergency Procedure G-2 1

" Establishment o' the Onsite Emergency Organization".

1 Immediate Actions - Normal Hours 1

1. When the site emergency signal is sounded, all personnel not

engaged in critical operations or emergency recovery actions will i report to their assigned assembly locations in accordance with 4 Emergency Procedure G-4 " Personnel Accountability and Assembly."

1 Personnel desionated fn* innediate emargency response will rencet 3 to the Operational Support Center. This includes the Operational i Support Center Supervisor, the Site Chemistry and Padiation l Protection Coordinator, the Emergency Safety Supervisor support c staffs and the ifaintenance Fire Brigade.

Irrediate Actions - Of' Normal Hours

1. OSC personnel required for emergency response will be notified in accordance with Energency Procedure G-2, " Establishment of the Onsite Emergency Orgarization."

?. 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 tn report to the OSC may proceed directly to the GSC and be immediateiy available 'or fire fighting, energency

] mafrtanance, search and rescue or rarfiological monitoring, es i appropriate.

i

! 4 Personnel notiffec', but not given a snaci#fe emergency response

} location should initially report to the security building lunch t room (ready room) for further instructions.

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DWWA CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 NUMBER EP EF-2 REVISION 5

• DATE' 1/14/85

[ PAGE 3 0F 6 l ji l Tms: ACTIVATION AND OPERATION OF THE i OPERATIONAL SUPPORT CENTER Subsequent Actions

1. The Emergency Liaison Coordinator assigned to the TSC will

, dispatch a liaison assistant to the security building ready room l as soon as man power pemits. 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.1 tc remain on stand-by at the security building

, ready room or report to the OSC.

s 3. The OSC Supervisor reports to the Emergency Maintenance l Coordinator. In an emergency, the Emergency Maintenance Coordinctor responds to requests from the control room

! (initially) or the Technical Support Center (TSCI for repairs, l ascertains manpower needs, and makes assignments to maintenance groups as needed. To support him in this role, an OSC Supervisor lI f

1s dalegeted tha mermih414ty for assuring teams responding to emergency plant conditions are properly equipped and prepared.

} Tne OSC Supervisor maintains comunications with the control room .

g and TSC. He will brief response teams on plant status and other

plant evolutions in progress that might affect them. He assures i they receiva briefings from Chemistry and Radiation Protection

! (C&RP) on job requirements and radiation protection provisions for the feb. He will provide teans with redios for back-up communications and insure telephone comunications are established so tear:s can be infomed nf significant changes in

plant conditions (such as changes in emergency classification or i 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 recomendea safetv marsures enti status of response terms in the plent. In performing these duties he will comunicate with the site C&RP coordinator, the cr:crgency mt.intenance coordir.ator, the emerger.cy operations coordinator and the emergency liaison coordinator as needed to exchange information and be aware of plant conditions.

l This relationship is shown in figure 1.

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DWRO CANYON POWER PL. ANT UNIT NWS) ' 1 AND 2 ON I DATE 1/14/85 PACE 4 0F 6 ,

TITLE: ACTIVATION AND OPERATION OF THE

)- OPERATIONAL SUPPORT CENTER

Record Keeping i o

] All records generated by the utilization of the OSC for an exercise or emergency shall be forwarded the next working day to the Assistant J

Plant Manager / Support Services for review and retention, o

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

2. Records generated from actual emergency events will be j, categorized as lifetime and placed into lifetime storage in y

accordance with procedure AP E-1 SI, " Requirements for Retention i

and Extended Storage of Operation Phase Activity Records."

i j OSC Eauipment Description

-t j 1. Comunications The OSC has the capability to comunicate with the control room, TSC, appropriate response teams and other plant extension via

.l telephone. It is eoutpped with extensions of a dedicated 1 telephone tie line to the control room and TSC and also has a CBA

' telephone extension with emergency facility priority access to telephone circuits, as well as nonnal in-plant telephone capability.

Both the Access Control Area and General Maintenance Foreman b 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.

9 1 The telephona is the primary means of comunicating with maintenance teams dispatched into the plant. During emergency response situations, maintenance teams will carry radios to -

l> provide back-up communications. Radios are available to the OSC

'- and have OPS /SEC/HP frequency capability. These radios are maintaines at access control. This ensures the racios are

charged and immediately available for use. Operations and the 1 fire br.gade also have radios which can be utilized.

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. piAaLO CANYON POMR PLANT UNIT NO(S) I AND 2 ON DATE 1/14/85 PAGE 5 0F 6

( Trns: ACTIVATION AND OPERATION OF THE OPERATIONAL SUPPORT CENTER

2. Status Boards An OSC status board is maintained whenever the OSC is activated and operational. It provides information on plant emergency status, radiological conditions, work assignments, team member names, team locations, radio call signs and phone extensions as appropria te. The OSC status board is in addition to those routinely used by C&RP.

C. Reference Materials A current controlled ccpy 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 4

from the foremen office area of the cold n.achine shop. A set of Emergency Procedures is located in the office at access control.

Plant layout drawings may be " marked-up" on the window glas ;

using felt markers to identify tean locations and to brief on the most expeditious, lowest rediation level, and safest routes to a respcnse locaticr..

( L. Radiation Nonitoring Equipment C&RP will provide radiation monitoring equipment to teams and individct.ls as appropriate.

/

E. Protective Clothing Protective clothing is immediately available at access control.

HSA's (self contained breathing apparatus) are also available.

Fire brigade members are equipped with protective clothing specifically designed for fire fighting activities.

F. First Aid Medical Supplies First aid medical supplies are located at the access control first aid room.

G. Occontamination Access control provides showers, soaps, shampoos, towels, wasto disposal, extra clothing, friskers and technical expertise in the event personnel become contaminated while in the plant.

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,i J osasLO CANYON POWER PUWT UNIT NO(S)

• 1 AND 2 NUMBER EP EF-2 j REVISION 5

DATE 1/14/85 j.j PAGE 6 0F 6 ij Tm2

ACTIVATION AND OPERATION OF THE l- OPERATIONAL SUPPORT CENTER d

L L.

] H. Sampling Equipment

['.

[ Routine air and liquid sampling equipment is available at access control. Equipment for emergency sampling of the reactor coolant system and containment atmosphere is located in a marked cabinet I

in the hallway between access control and cold machines shop.

I.

Maintenance Equipment j Maintenance eouipment is located in the cold machine shop adjacent to the OSC. A large inventory of tools, parts and heavy lj equipment is located there. The cold machine shop has the q capability to fabricate some parts which may not be readily d available. -

J fj J. Fire Fighting Equipment A

H Fire fighting equipment for the fire brigades is stored at the

!!, north end of the Unit 1 turbine building on the 85' elevation, if the auxiliary building stairwell landing approximately 90'

elevatinn, and the control operator readyroen. A plant fire truck and two hose line trailers are located within the protected

, area ready for use. A fire brigade status board is located in L the cold machine shop.

Attachment

] '

OSC organization chart Supporting Prncedures A. EP G-1, Accident Classification and Emergency Plan Activation

i. B. EP G-2, Establishment of the Onsite Emergency Organization L C. EP G-4, Persunnel Accountability and Assembly i

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SITE EMERGENCY COORDINATOR .

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, LIAISON MAINTENANCE OPERATIONS EVALUATIONS i COORDINATOR COORDINATOR COORDINATOR & RECOVERY l- (TSC) (OSC) (CONTROL ROOM) COORDINATOR (TSC)

! I I i L._._._._._._ _. - . _ . _ . q . _ . - . _' SHIFT FORMAN ]

I l l I SECURITY l OPERATIONS ADVISOR ,

I&C ELEC/ MECH (TSC)

OSC MAINTENANCE MAINTENANCE RESERVE FIRE BRIGADE ADVISOR ADVISOR SUPERVISOR OPERATORS LEADER -

l (TSC) (TSC) (OSC) EMERGENCY l [

g RAD ADVISOR

. (TSC)

{ B DE I I  ! '

I&C ELECTRICAL MECHANICAL  ! l COORDINATOR COORDINATOR COORDINATOR l.

h SITE CHEM (ISC SHOP) (050) (OSC) l 8 RADIATION l '

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NUMBER EP RB-15 e, 7GrW3 Pacific Gas and Electric Company REVISION 1 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 4 j

,; DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 i EMERGENCY OPERATING PROCEDURE ,

SENTRY POST ACCIDENT SAMPLING SYSTEM TITLE INITIAL SAMPLING EXERCISE AFTER AN ACCIDENT  ;

g APPROVED YS PLANT MANAGER f) DATE i SCOPE

. i 4

Nureg 0737 requires samples to be taken and analyzed within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the decision is made to take a sample. This procedure is designed to ensure safe and reliable methods to meet this requirement.

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

1. ForRC(ReactorCoolant) Samples:

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

1) Gas Chromatograph Analysis

2) Diluted stripped gas samples for isotopic analysis

b. Diluted RC samples:

l 1) Boron analysis

2) Isotopic Analysis

c. In-Line analyses:

L 1) Ion chromatographic analyses for chloride

2) pH/ conductivity / dissolved oxygen L 2. For CA (Containment Air) Samples:

l

_ a. Diluted CA samples for isotopic analysis ,,

j b. Gas Chromatograph Analysis

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

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NUMBER EP RB-15 osaaLO CANYON POWER PLANT UNIT NCKS) 1 AND 2 REVISION 1 I' - DATE 1/22/85 l PAGE 2 0F 4 mLE: SENTRY POST ACCIDENT SAMPLING

'! SYSTEM INITIAL SAMPLING EXERCISE AFTER AN ACCIDIENT i

samples for the initial sample exercise following an accident and s

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.

1 This procedure and the procedure listed below, and changes thereto, require PSRC review.

PROCEDURE

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

EP RB-15:A -- Sentry Lab Access / Egress and Initial Actions During an Emergency ,

t This procedure details necessary steps for accessing and egressing the lab, Gas

- Chromatograph startup, initial system lineup, and

' annunciator testing prior to the first sample i exercise during an accident.

EP RB-15:B -- Reactor Coolant Sampling This procedure details the steps required for sampling any one of 5 different sample sources and obtaining a stripped gas sample and making available for gas chromatographic analysis.

EP RB-15:C -- Containment Air Sampling This procedure details the steps required to make containment air available for gas chromatographic analysis and to dilute containment air for isotopic analysis.

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. 1 DiAeLO CANYON POWER PLANT UNIT NCHS) 1 AND 2 ON- l

,.., DATE 1/22/85 iI i

PAGE 3 0F 4 TIT

• SENTRY POST ACCIDENT SAMPLING l SYSTEM INITIAL SAMPLING EXERCISE AFTER AN ACCIDIENT l

EP RB-15:0 -- Gas Chromatographic Hydrogen Analysis ~

! This procedure details the steps required (1) to i i check the instrument calibration prior to sample I 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-Y-I5 before using this procedure.

l EP RB-15:E -- Post-Accident RCS Liquid and Gas Sample Handling This procedure details the steps required to l prepare (1) a diluted liquid sample for boron analysis, (2) a diluted off-gas sample for l 1sotopic analysis (3) a diluted liquid sample for i isotopic analysis, and (4) a diluted containment air sample for isotopic analysis.

t EP RB-15:F -- Data Analysis i

This procedure provides a standard format to record data obtained in the EP RB-15 procedures.

EP RB-15:G -- Ion Chromatographic Chloride Analysis This procedure details the steps required to measure the chloride concentrations from the sample sources available at the Reactor Coolant module of 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 reactor coolant sample.

EP RB-15:! .- Eample Storage and Disposal This procedure provides a means for dispo' sal of stripped gas samples and storage of RCS liquid samples.

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' PAGE 4 0F 4

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m a SENTRY POST ACCIDENT SAMPLING SYSTEM INITIAL SAMPLING EXERCISE AFTER AN ACCIDIENT

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l REFERENCES

1 Sentry High Radiation Sampling System Operations and Maintenance Manual

2. EP RB-16

3. Nureg 0737 f

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i. NUMBER EP RB-15:A FGw'3 Pacific Gas and Electric Company REv!SION 2.

DEPARTMENT OF NUCLEAR PLANT OPERATIONS I DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 N 1 0F 27 j EMERGENCY OPERATING PROCEDURE  :

lI SENTRY POST-ACCIDENT SAMPLING SYSTEM l g TITLE. -- INITIAL ACTIONS DURING AN EMERGENCY APPROVED

! PLANTMANAGEE) DATE y PURp0SE 8

The purpcse of this procedure is to define some of the actions taken

' when a decision is made by the Site Emergency Coordinator to obtair, a post accident sample using the Post Accident Sample System (PASS).

This procedure guides, with consideration of plant emergency radiation hazards, the Sentry team tu access and make operable the Sentry room.

I It also guides the team to withdraw from the Sentry room upon sample j acouisitiori. This procedure and changes thereto requires PSRC approval.

, DISCUSSION l

! This proccdure ensurcs sample recovery with a minimum risk to j personnel in e limited time frame.

i i The movable shield in the 85' penetration area will usually block that i access route. Therefore ingress and egress may be required across the i RCA boundary. Performance of this procedure may require the transfer i

)

of radioactive samples to non-RCA's. For these reasons this procedure I

involves exemptions from certain routine RCA access requirements.

I Perscr.nel implementing this procedure should be covered by an SWP during an accident, drill, or drill-like training. Routine use of the Sentry rcom is cuvered by the C&RP routine sampling RWP.

Particularly hazardous or unexpected conditions may occur in post accident situations. Direction by appropriate superviticr. may augr.xnt or supercede portions of this procedure because every possib.ility

, cannot be anticipated.

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PAGE 2 0F 27 d TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM j -- INITIAL ACTIONS DURING AN EMERGENCY 1

PREREQUISITES AND PRECAUTIONS j 1. The Site Emergency Coordinator should pre-plan post-accident a sampling with the Emergency Radiological Advisor and the Site i Chemical and Radiation Protection Coordinator prior to ordering a R 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.

1. i. A sufficient number of properly qualified personnel to complete a the task should be available prior to making the post accident sample decision. This might include:

g a. Two people on the Sentry team; one of whom is a qualified r C&RP Technician and the other an Unescorted Radiation l Worker.

1 i b. A sample transporter qualified as a C&RP Technician.

I j c. A count room qualified person in the TSC lab.

> 3. The Work Permit will specify protective equipment. Unless

• i conditions warrant less stringent requirements, it is suggested 4 that full PC's, SCBA's and accident dosimetry be worn.

I 4. The Sentry team will make a post-accident entry to the plant only

]( when directed by supervision and when possessing a high range s portable survey noter to pennit surveying into areas of unknown a radiological conditions.

q li 5. The Sentry team should be informed of plant status as it pertains 1 to significant hazaros, both radiological and non-radiological, y along access routes.

4 Li 6. Exposure hazards, both airbdrne 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 Acoess Control or the cold machine shop to remotely address the SPING air monitor in the Sentry room, which can be read locally.

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DIA81.0 CANYON POWER Pt. ANT UNIT %$) 1 AND 2 NUMBER EP RB-15:A REVISION 2 DATE 1/4/85

.* PAGE 3 0F 27 i TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- Ih!TIAL ACTIONS DURING AN EMERGENCY a

[ b. Area radiation monitor RE-48, in the Sentry room, can be read in the Control Room or locally.

7. Communications are vital during a plant emergency. Entry teams must be able to communicate with the Control Room and appropriate supervision.

8. C&RP Technicians have the AC4 N key required for access to areas and equipmer.t related to this procedure and have security key

caros to enter door #116 or #197. If the Sentry team does not 2

pcssess either of these then take the applicable master keys located in the lock box in the R.P. office. The key to the 85' l elev. post-accident equipment locker is number 37, located in the key cabinet in the R.P. office.

9. The containment isolation valves FCV-69C, 697, 698, 699 and 700 are centrollec from the Containment Isolation Valve Panel in the Sentry Room only. These switches require a key to operate. Keys

are located in the Sentry room.

1 j 10. It is important to conduct operations in an expediticus manner te provide tir.Ely vital plant status information.

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 i

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DIABLO CANYON POWER PLANT UNIT NO(S)

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PAGE 4 0F 27

't j TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM l

1 -- INITIAL ACTIONS DURING AN EMERGENCY 1  ;

I

% l (j 1) Unit I l 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 i

1. 192 to the Motor Repair Shop.

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-- INITIAL ACTIONS DURING All EMERGENCY i

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[ 2) Unit II t

! Starting at the Cold Machine Shop proceed into the I hallway to door #140, proceed south to door #122 and exit building. From here turn north and enter #192 to ,

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TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

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-- INITIAL ACTIONS DURING AN EMERGENCY l

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l b. Around Turbine Building at 85' Elevation a

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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 transformers at the north end of the plant. Continue

.i south to door #192 between containment and the Turbine Suilding. Enter the Motor Repair Shop via door #192.

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{j .- INITIAL ACTIONS DURING AN EMERGENCY A

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j Starting at the Cold Machine Shop proceed to the -

outside via door #129, turn left and continue south d around the Unit II Turbine Building looping around the

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_j north to door #192 between containment and the Turbine Building. Enter the Motor Repair Shop via door #192.

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) PAGE 8 0F 27 TITLE: SENTRY POST-ACCIDENT SAMPLING SYSTEM

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INITIAL ACTIONS DURING AN EMERGENCY

. i.

c. Other Access Routes I The Figure la or Ib pathway is preferred. However an access l route other than those above may be suggested by actual post accident conditions (e.g., fire, high energy line break, etc.). The final route selected should be directed by appropriate supervisory personnel.

._ i 2. Initial Set-up of Sentry Room Equipment a

"! a. Gas Supply Cylinders Check d

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 the following:

1 1) The cylinder valves are fully open for all three

] cy lir.de rs.

it Li 2) The manifold valves are fully open for all three l; cylinders.

L:

S) The argon regulator shows tank pressure of approximately 1000 psig and the regulator is set to 100 i psig.

NOTE: 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 10t H atleast100psigandd.spangascylindersshouldhave oth regulators should be set at j 10 psig.

b. Emergency Ventilation System Line-up. (Optional. If proper ventilation is lined up proceed to step 2.c., Steel Shield

] Door Closure).

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TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM i

-- INITIAL ACTIONS DURING AN EMERGENCY

1) Climb the ladder to the cat walk and cross to enter the ventilation room. (AC4 N key required).

NOTE: Minimize the time that the vent room doors are open.

2) Proceed to breaker panel PPHRS, 52-12J-35 and check all breakers ON.

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

4) EMER LEAD (15-150) is the preferred system.

c) 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 ST*RT pushbuttons on the motcr 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) Oper. its supply cnd exhaust dampers and the supply and exhaust vent dampers and cicse all other dampers, b) Push the START pushbutton on the motor controllers for the EMER REDUN supply fan, exhaust fan and heater 293, in that order.

6) Return to the Motor Repair Shop.

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TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM .

-- INITIAL ACTIONS DURING AN EMERGENCY

c. Steel Shield Door Closure. (0ptional. If the shield door is closed proceed to step 2.d., Radiological Assessment.)

1) Proceed through door #192-Af south of the Unit I Motor Repair Shop, or door #192-A north of the Unit II Motor i Repair Shop, and visually check the shield door's winch

'i 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 j below.

2) Operate the winch until the marked portion of the cable visibly indicates the shield door is closed.

3) Return to the Motor Repair Shop.

d. Radiological Assessment of Sentry Room i

1) Enter tge Sentry room via the RCA boundary (door #116 or #197 and the watertight door. (Key at RP key box) j 2) Perform a general area radiation survey a) Note high levels such as might exist at the i auxiliary buildim end of the room due to ECCS

' piping.

j b) Note low level areas for sample screen surveying

- later, a

3) Note the reading of RE-48 on the Process Control Panel (PCP). Recheck it intermittently.

4) Monitor airborne radioactivity using the SPING. If j

airborne levels permit 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 intc the rool.;.

]

i

} e. Proceed to the Ventilation Control Panel.

1) Check the alarns.

a) Press TEST and note the red alarm indicators flash while the audible alarm sounds.

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DIASLO CANYON POWER PLANT UNIT %S) NUMBER EP RB-15:A 1 AND 2 REVISION 2

' DATE 1/4/85 PAGE 11 0F 27 i TITLE- SENTRY POST-ACCIDENT SAMPLING SYSTEM l -- INITIAL ACTIONS DURING AN EMERGEhCY l

i b) Press SILENCE to stop the audible alarm.

c) Press ACK and note the flashing alarm indicators

glow steadily.

d) Press RESET and note tha red alarm indicators go out, i

i

2) If the NORMAL VENT switch is on, turn it off.

! 3) If the EMER LEAD ventilation system is desired ar.d is

. not operating depress in order the SUPPLY, EXHAUST, and HEATER pushbuttons.

4) Observe the appropriate indicating lights for proper operation of the desired ventilation line-up.

j 5) If necessary, return to step 2.b. , Emergency j Ventilation Line-up.

f. Containment Atmosphere Sample Line Heating

1) Proceed to the CCP ar.d position the FUNCTION SELECT

. from 0FF to SF1-3/GGD.

l

) 1) Observe the following:

a) The POWER ON indicator lights, b) The flow monitor 205 and 100% flow lights turn on for approximately 25 seconds.

t. 3) Press the PILOT LIGHT TEST pushbutton and note which lights are not functional.

. 4) Turn the HEAT TRACE POWER SWITCH to the ON l position.

~

5) Place the temperature select switches for EHT 196 and EHT 197 to the down position marked 260 .

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. DATE 1/4/85 PAGE 12 0F 27 j TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM j -- INITIAL ACTIONS DURING AN EMERGENCY j

q

? g. Rear Panel Access Rolling Shield Closure.

4 If the panel rolling shield is closed proceed to step 3.,

i Electrical Line-up.

4 i'i 1) Perform this valve line-up check in the rear of the j shielded panels:

l4 i CAP-V-13 CLOSED (above the GC) []

CAP-V-31 OPEN (adjacent to the GC) []

d d CAP-V-32 OPEN (adjacent to the GC) []

l CASP-V-1 OPEN (overhead on cont. atmos.

li supplyline) []

li a

j CASP-V-2 OPEN (lower part of CASP) []

) CASP-V-3 CPEN (mid part of CASP) []

1

] 2) Get tne come-a-long from the cabinet and attach one ena te the pad eye on the east wcil and the other to the

]j pad eye on the door.

3) Operate the come-a-long until the rolling shield is blocking the doorway.

]

3. Electrical Line-up H Proceed to the breaker panel PYNMIi, located next to the Vent Control Panel, and check positions of breakers as follows:

BKR #1 -

ON [] BKR #2 -

ON []

,f BKR #3 -

ON [] BKR #4 -

ON []

BKR #5 -

0FF [] BKR #6 -

ON []

BKR #7 -

ON [] BKR #8 -

ON [] .

i BKR #9 -

ON [] BKR #10 - ON [~]'

I BKR til - 0FF [] BKR #12 - ON []

i MAIN BKR - ON []

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I-DIAKO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h EP RB-15:A l DATE 1/4/85

.s PAGE 13 0F 27 j TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM l -- INITIAL ACTIONS DURING AN EMERGENCY

4. The Containment Atmosphere Hydrogen Analyzers The two redundant analyzer systems' remote panels are between the PCP and the CHP. Beneath each panel are the switches for controlling the three sample line containment isolation valves.

The reagent gas tank (oxygen) is against the auxiliary building

! wall of the Sentry Room.

. a. Initial Conditions of an Analyzer System

1) Main power switch at remote' panel in STANDBY. []

j NOTt: If the power switch is 0FF, then turn it to STANDBY and give the system six hours to warm up. If both systems have not been in STANDBY for at least six hours, or are otherwise inoperable, use the gas chromatograph, step 5, below. Recora the time of switching from 0FF to STANDBY .

i 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 closed. (Tank should be changed 6t 100 psig) []

b. H2 Analyzer System (s) Operation.

CEL: 82 83

1) Turn the three sample line switches to the OPEN position. Observe the position indicating lights. [][]

j Open the oxygen tank isolation valve 2) and adjust regulator to 27 2 psig. [][]

' 3) Turn the main power switch from STANDBY to A!;ALYZE. [][]

4) Push the REMOTE SELECTOR pushbutton to gain control at this panel and reset COMMON ALARM, if necessary. [][]

L

5) Turn the dual range switch i

to the 0-10% range. [][]

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DIA8LO C LNYON PQWER PLANT UNIT NO(S) 1 AND 2 h0N u DATE 1/4/85 j PAGE 14 0F 27

?

TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

[ -- INITIAL ACTIONS DURING AN EMERGENCY I CEL: 82 83

( 6) Adjust the ZERO and SPAN potentiometers until they agree with their respective values in.dicatedon calibration stickers located under each potentiometer. [][]

7) Turn the function selector switch to SAMPLE. [][]

TIME (82) (83)

[ 8) If both CEL 82 and 83 are to be used, repeat steps 4.b.1) to 7) for the second systen while waiting for the first system to stabilize, which takes approximately j 6 minutes. [][]

J l 9) Proceed with step 6., Initial Valve Line Up, R while waiting for stabilization. When 6 minutes have elapsed since switching to L

CAMPLE, continue with step 10) below. [][]

.i

10) Record the analy:er meter reading, the time '

read, and the scale used. [][]

] MeterReading(',)

[t Time

!j Scalc Used 1

L NOTE: If the meter reads greater than 9%, the 0-20%

scale should be used.

11) Inform the Control Room of which scale and CEL is used and ask the Control Room l if the analyzer (s) are to remain in ANALYZE or be returned to STANDBY. [][]

NOTE: Advise the Control Room of the reagent gas depletion and the .

i limited lifetime of the sample -

4 pumps, which are located in the I 100' El. penetration area.

a

12) If directed to leave the analyzer (s) in 1 ANALYZE proceed with step 5, CMP / CAP Power Up. . . [][]

)

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btASLO CANYON POWER PLANT UNIT NCHS) 1 AND 2 h0N DATE 1/4/85

.' PAGE 15 0F 27

!( TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS DURING AN EMERGENCY l

CEL: 82 83 l c. Standby l 1) Turn the function selector to ZER0 and f

purge the analyzer for 6 minutes. [][] l

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. [][]

5) Push Coninon Alarm to Reset [][]

5. CMP / CAP Power Up/ Gas Chromatograph Startup

( a. At the CAP align V-6 and V-5 to DEMIN WATER.

l q t. Oper. V-8 and V-2.

x -

j . .~c . Check the three green root valve handles next to

, the CAP down in the vertical position to allow j Argon and the Span gases to the CAP. []

$ d. Open or check open CAP-V-10 and adjust

instrument air pressure to 8012 psig. []

e. Open or check open CAP-V-14 and adjust argon pressure to 40 : 1 psig. []

f. At the CMP, turn the POWER switch to ON. []

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. On the G.C. front panel .

1) Select attenuation factor of 250 (25 x 10).

Place all function switches in the OFF (out) position. []

i Depress MAN and CLEAR switches. []

2) 1

3) Enter "00" initiating G.C. warmup. Time on

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a DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:A REVISION 2

, DATE 1/4/85 )

PAGE 16 0F 27

, TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS DURING AN EMERGENCY Y

6. Initial Valve Lineup

a. Unlock the cabinet door and the drawer lock bar under the counter, if locked.

1) Locate a loaded filter assembly for the containment air j sample.

1 j 2) Locate wrenches, labels, and bags.

b. Valve HCV-21, which is located next to the chemical sink, ll should be positioned to the TO CONTAINMENT position. []

c. Sample cooler wate valve should be turned until indicator shows OPEN []

d. At the CASP []

1) Install a loaded filter assembly into the containment air dilution system. []

The tubing enc with the blue dab of paint on it should

[

be on the bottom. Tighten but do not damage the

- fittings. Retighten if leakage is noted later.

2) CASP cart / cask connection for pressure indication.

a) Engage and lock a cart / cask on its D quick-disconnects. []

R b) OPEN the INLET and OUTLET valves and CLOSE the BYPASS valve on the engaged cart / cask. []

c) Connect PI-1109 (an MBIS pressure monitor) to the engaged cart / cask. Plug it.in and turn the selector switch to the proper cart / cask.

Cart / Cask []

3) Check that PI-1116 is plugged in and turn it on. []

4) Close or check closed CASP-V-17. []

5) Align CASP-V-16 to the CASP-DV-1 position. []

I 6) Align CASP-DV-1 to CASP-SF-5 position. []

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61ABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-IS:A REVISION 2 DATE 1/4/85 PAGE 17 0F 27 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM t'

-- INITIAL ACTIONS DURING Ah EMERGENCY

7) Install a new septum on CASP-SF-5. []

e. At the CCP:

, 1) Adjust N7 pressure regulator to 100 psig as indicated j on CCP-GI. []

4

NOTE

This pressure will drop to 80 psig when the eductor is on and Low N2 PRESS alam 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 and hold the TEST button and verify:

(1) the alarm sounds. []

(2) all labeled windows flash except ISOLATE SAMPLEFLASKwindowwhichglowssteady.[]

b) Release the TEST button and verify that the

~~

ISOLATE SAMPLE FLASL window goes off. []

c) Push the ACK button and verify:

(1) the alam is silenced. []

(

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-i REVISION 2 d.

DATE 1/4/85 PAGE 18 0F 27

, TITLE: SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS DURING AN EMERGENCY (2) the 3 upper windows glow steady. []

n

] d) Push the RESET button and verify that all windows are off. []

q O f. At the POST LOCA CNT ISOLATION PANEL all five key operated valve switches should be CLOSED.

}

ji g. At the CAP, valves should be positioned as follows:

CAP-V-12(open) []

g Adjust nitrogen regulator until nitrogen li pressure gauge is 60 2 psig. []

CAP-V-7 (YSIOXYGENANAL.) []

] CAP-V-C (open) []

CAP-V-6 (0XYGEN CALIB. SOL'N) []

i! CAP-V-5 (CLOSED) []

CAF-V-2 (open) []

j CAF-V-1 (open) []

(j CAP-V-29 (12 o' clock) Top of CAL TANKS []

CAP-V-28 (12 o' clock) Top of CAL TANKS []

3 CAP-V-27(12o' clock) Top of CAL TANKS []

j CAP-V-15(closed) Bottom of CAL TANKS []

] CAP-V-16 (closed) Bottom of CAL TANKS []

lj CAP-V-26 (closed) Bottom of CAL TANKS []

fj CAP-V-30 (9 o' clock) CAL TANK 1/2 Selector []

j CAP-V-25(closed) Bottom of CAL TANKS []

j CAP-V-20(closed) Bottom of CAL TANKS []

] CAP-V-19(closed) Bottom of CAL TANKS ,, [ ]

CAP-V-11 (open) []

O it CAP-V-24 (closed) []

] CAP-V-17 (closed) []

l CAP-V-9 (closed) []

CAP-V-18(closed) []

i DC0109 18IX

• • NUMBER EP RB-15:A

'DIA8LO CANYON POWED PLANT UNIT NO(S) 1 AND 2 REVISION 2 DATE 1/4/85

.. PAGE 19 0F 27

,  ; TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTI0ldS DURING AN EMERGENCY

h. 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) []

DM-VREL-1.1 (closed) []

DM-VREL-1.2 (closed) []

DM-VREL-1.3 (closed) []

i. At the Open Grab Sample panel of the LSP, valves shouic be positioned as follows:

RK-V-6 (closed) []

[A-V-2.1 (closed) []

, DM-V-2.2 (closeo) []

MC-V-2.3 (closed) []

RC-V-17 (closed) []

RC-V-6.1 (closed) []

RC-V-6.2 (closed) []

RC-V-5.1 (closed) []

RC-V-5.2 (closed) []

j. At the RC Module of the LSP, valves should be l positioned as follows:  !

RC-V-12 (12o' clock) [j RC-V-15 (CLCSED) []

RC-V-14 (closed) ,,

[] j RC-V-13 (9 o' clock) []

RC-V-10 (9 o' clock) []

RC-V-11 (CLOSED) []

RC-DV-2 (9 o' clock) []

RC-VREL-1 (closed) []

DC0109 191X -

- . 3 +

- . .. . . . ,x u;:n +:.. ;;- . . .: . :

DIAst.O CANYON , POWER PLANT UNIT NO(S) 1 AND 2 Sf0N DATE 1/4/85 PAGE 20 0F 27 h TITLE: SENTRY POST-ACCIDENT SAMPLING SYSTEN

-- INITIAL ACTIONS DURING AN ENEPGENCY RC-VREL-2 (closed) []

RC-V-3 (closed) []

l RC-V-7 (9o' clock) []

] RC-V-2 (closed) []

., RC-V-1.1 (closed) []

j RC-V-1.2 (closed) []

d RC-V-1.3 (closed) []

g RC-V-1.4 (closea) []

[ RC-V-1.5 (closed) []

RC-V-4 (closed) []

RC-V-8.1 (closed) []

RC-V-8.2 (closed)

[]

RC-V-16 (closed) []

Ll RC-V-9 (CLOSED) []

RC-V-18 (6 o' clock) []

! RC-V-19 (BYPASS) []

M RC-V-20 (closed) []

RC-V-21 (closed) []

RC-DV-1 (BYPASS) [. ]

RC-V-22 (TOWASTE) [] l

k. At the RW Module of the LSP, valves should be positioned as follows:

RW-V-9 (closed) []

RW-V-10 (closed) []

RW-DV-1 (BYPASS) ,

[]

RU-V-8 (BYPASS) , []

RW-V-7 (BYPASS) []

RW-V-5 (6o' clock) []

RW-V-4 (closed) []

RW-V-3 (closed) []

T DC0109 20IX

, , 7. :

a - - . . _ . .-

DIA81.0 CANYON POWER PLANT UNIT NO(S) 1 AND 2 hff0N DATE 1/4/85

PAGE 21 0F 27

!J TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS DURING AN EMERGENCY l

b I

h RW-V-1.1 through RW-V-1.10 (12 o' clock) []

RW-V-2.1 through RW-2.10 (6 o' clock) []

i 1. At the PROCESS CONTROL PANEL (PCP)  !

NOTE: Notify the Control Room when any valve alignments are changed.

[ 1) Position or check the position of the following switches for valves:

! FCV-9351A (CLOSE) []

FCV-93518 (CLOSE) []

l FCV-93500(CLOSE) []

FCV-9350A(CLOSE) []

FCV-9353A(CLOSE) []

FCV-9353B (CLOSE) []

. FCV-6Ei (CLOSE) []

FCV-693 (CLOSE) []

FCV-654 (CLOSE) []

FCV-1413 (CLOSE) {]

i FCV-1416 (CLOSE) []

FCV-1417 (CLOSE) []

FCV-1416 (CLOSE) []

FCV-1419 (CLOSE) []

] FCV-1412 (CLOSE) []

h FCV-1410 (CLOSE) []

i' FCV-1411 (CLOSE) []

[ FCV-1414 (CLOSE) ,,

[]

FCV-1415 (CLOSE) []

FCV-1420 (CLOSE) []

FCV-1421 (CLOSE) []

l FCV-1422 (CLOSE) []

FCV-1423 (CLOSE) []

[ FCV-1424 (CLOSE) []

1 DC0109 211X ~

- - t

52Z--

. . _ .3 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 1

Sf0N DATE 1/4/85 PAGE 22 0F 27 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM q -- INITIAL ACTIONS DURING AN EMERGENCY j FCV-1425 (CLOSE) []

FCV-624 (CLOSE) []

)1 FCV-1428 (POST LOCA SAMPLING) []

d 2) Position switches for POST LOCA COLLECTION TANK h TRANSFER PUMPS I and 2 to the STOP position. []

3) At the PCP 1

i a) Push the TEST button and verify:

I;

j (1) the alarm sounds []

i (2) all labeled windows flash []

b) Push the ACK button and verify:

(1) the alarm is silenced []

(2) all labeled windows glow steaoy []

.! c) Push the RESET button and verify that j all windows are off. []

I b

q 7. Monitor Startup and 02 Calibration Tank Recirculation (CAP) a

a. Dissolved 02 Calibration Tank Recirculation 1

i

1) If calibration has been performed 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.

a If water must be added to the tank, check closed L

CAP-V-18, open CAP-V-11 and CAP-V-24 and fill the tar.k. Close CAi-V-24. ,

[]

'~

3) Open fully CAP-V-17. []

}

4) Turn the O CALIB. SYSTEM pump to ON position.

! Indicator $1ghts for the pump should light on -

both the CAP and CMP. []

)

l-l DC0109 221X -

- ..~..... - -

e )

DIA8LO CANYON POWER PUWT UNIT NCHS) 1 AND 2 ff0N l DATE D4/85 (

PAGE 23 0F 27 TITLE: SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONE DURING AN EMERGENCY I

5) Recirculate the water for at least I hour. []

Time on

6) Continue to recirculate until the actual calibration is performed. []

b. pHMonitor(CMP) .

1) Make sure the pH buffer tanks are over half full with pH7 and pH4 or 10 buffers at the CAP. []

NOTE: 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) If calibratior. has been performed within one week proceed to Step c, conductivity monitor.

3) Place internal S-1 toggle switch to ON (up) position. []

4) Switch 5-3 to the OFF position. []

5) With a small screwdriver, adjust R-3 standardize

' ccr.trel for full downward and upward deflection and ther. reset to a reading of 7.0. []

6) Switch S-3 to the ON position. []

7) Close door. []

c. Conductivity Monitor (CMP)

1) If calibration has been performed within one week, ,

proceed to step d. '

l .

2) Observe that the meter reading is on zero when the selector switch is on ZERO. []

l l

l l

OC0109 23IX l

l DIA8LO CANYON POWER PLANT UNIT NO(S) NUMBER EP RB-15:A 1 AND 2 REVISION 2 )

_ DATE 1/4/85 l

PAGE 24 0F 27

.j TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM

j -- INITIAL ACTIONS DURING AN EMERGENCY 4

3

3) Turn the selector switch to CHECK. The meter

~. indicator should move to CHECK on the meter il scale. []

j NOTE: If it does not move to CHECK, consult the 4

Site Emergency Coordinator for directions.

4) Switch the selector switch to MEASURE. The .

g monitor is now ready for operation. []

) 5) Energize for 30 minutes.

] Time on l} d. YS1DissolvedOxygenAnalyzer(CMP) 3

~

If the YSI is not to be used proceed to e. Rexnord Analyzer.

1) If calibration has been performed within one j week, proceed to step e.

2) Turn POWER switch to ON. i

[]

3) Turn 02FILTER to 0FF. []

4) Turn 0 RANGE to 0-20 ppm. []

2 j 5) Turn PEN INPUT to ZERO. []

a 6) Turn CHART SPEED to RAPID. []

O

!; 7) Adjust the PEN ZERO control until the pen traces a line on the 0-20 chart scale at O. []

8) Turn CHART SPEED to 10. []

9) Turn PEN INPUT to -02 ' E3 4

10) Energize for 30 minutes. ~

[ Time on P

', e. Rexnord Analyzer j Implement this section only if Rexnord Analyzer is to be j used.

LI j 1) Adjust mechanical zero with power switch 0FF. g d

DC0109 24IX .

1 *

!* DIA8LO CANYON POWE3 PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:A

) REVISION 2

! DATE 1/4/85

., PAGE 25 0F 27 i TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- INITIAL ACTIONS DURING AN EMERGENCY 1 2) With power switch ON, and functino selector switch on ZERO, adjust ZERO ADJ. to get zero reading on the instrument.

3) Turn function selection switch to 20 mg/1.

f. Ion' Chromatograph Startup NOTE: Proceed with this section only if chloride analyses is to be done at this time.

8

1) Verify that the level of chloride calibration standard (2000 ppra B as boric acid and 1 ppm chloride) is at least half full in CAL-3. []

! 2)

Verifyor glass that air bubbles in tygen aretubing.

capillary not visible in the sig[ht]

NOTE: If air bubbles are present, check the pumps for prime and vent; venting is required when eluent centainers are filled. Refer to Procedure l CAP 6-3.

3) Verify that the following reagents are available.

! E1/E2 Eluent: 2.0 mM Na0H/2.4 mM Na2003 E3 Iff Sulfuric Acid (H2SO4 ) []

Deionized Water Rinse []

, 4) If any of the reagents listed in ctep 3 is not  !

available or has not been prepared within the last 30 days, refer to Appendix 1 for details of reagent preparation. []

5) Place the POWER and AIR switches to DN position. []

6) Place LOAD / INJECT switch in the LOAD position. ' []

i 4

7) Place the E-2 switch in the UP position. [] l b 1 j 8) PlacetheSEPARATORswitchintheSEP-1 position.[] '

J j

(

1 L

DC0109 2SIX I N.

• • 9

1 L;

l' DIA81.0 CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:A REVISION 2 3 DATE 1/4/85 lj PAGE 26 0F 27 TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM i

\ -- INITIAL ACTIONS DURING AN EMERGENCY l h l l

b

9) Place the SUPPRESSOR switch in the SUP-1/RGN-2 l h position. []

NOTE: The following are performed at the conductivity meter on the CAP:

J 10) Set MODE switch to ZERO and verify needle points 10 0. []

1 POTE: If not at ZERO, adjust to ZERO with the screw j below the meter face.

11) Set MODE switch to CAL and verify needlo swings full scale. []

l NOTE: If adjustment is necessary, adjust usin

, screw at the top of the circuit board (gthe the one labeled METER).

i 12) Set tiODE switch to zero. []

13) Set the pMHO FULL SCALE switch to 30. []

.1 ij 14) Check if eluent pump setting is 40 percent. []

l i

j 15) Turn the eluent pump switch to ON position. []

16) Turn GAUGE switch to GN position. If reading

, is very low, check capillary lines for

,, air (CAP G-3). []

1 1 17) Allow system to warm up and stabilize for j

c; 30 minutes.

j Time on W

ll 8. Sampling may now commence using specific sampling procedures.

APPENDICES -

L'

1. Reagent Preparatiun 1

}

}

} DC0109 261X 1

4

{*

i

. F

)* istABLO CANYON PCRWA PLANT UNIT NO(S) 1 AND 2 hSf0N j DATE 1/4/85

, . o. g PAGE 27 0F 27 j i j TITLE: SENTRY POST-ACCIDENT SAMPLING SYSTEM i -- INITIAL ACTIONS DURING AN EMERGENCY J .'

i APPENDIX 1 y

c REAGENT PREPARATION I NOTE: Reagents must be made using demin water with a conductance of less than I umho. l

1. E1/E2 Eluent - 2mM NaOH/2.4mM Na2003 Add 0.32g Na0H and 1.00g Na CO (anhydrous) to 4.0 liters of demineralized water,dissolhe$ndmix.

2. 1 N_ Hg SO4 Add with stirring 120 ml of concentrated sulfuric acid to 4 liters of demin water and cool. Transfer the solution of a 4

liter collapsable container, remove excess air, and label container with ir.itials and date. Connect it to the line REGEN SYSTEl:-1. Open the cor.tainer valve and vent pump inlet lines.

l l 3. Demineralized Water Rinse Fill a four (4) liter collapsable container with demin water.

Rer.ove 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 1 0.19 H 3 80 3 to two separate 2 liter volumetric flasks. Dilute each flask to the mark, with demin water. The cal tank holds 3.S liters.

l l

l I

DC0109 271X ,

) r% %

NUMBER EP RB-15:G

} G S?J 3 Pacific Gas and Electric Company REVISION 0 1

DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 AGE 1 0F 11 EMEPGCNCY OPERATING PROCEDUP.E SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE.

g --ION CHROMATOGP.APHIC CHLORIDE ANALYSIS APPROVED *

1. i PLANT MANAGER g DATE DISCUSSION The purpose cf this procedure is to detail the steps required to neasure 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.

PREREQUISITES

1. The Ion thromatograph (IC) was turned on according to Procedure EP RD-15:A and has warmed up for 30 :.inutes.

2. CAP, CMP, E.nd LSP systems lined U as detailed in Procedure EP RB-IS:A.

3. Verify t>t'. the fcilowing annunciator windcws are off on the PCP:

a. REACTOR COOLANT SAMPLE COOLING WATER LOW FLOW

b. REACTOR COOLANT SAMPLE COOLING WATER LOW PRESS

c. PEACTOR CCXANT SAMPLE C0 CLING WATER HIGH TEMP i

d. REACTOR COOLANT PURGE HIGH TEMP l

e. REACTOR COOLANT SAMPLE HIGH TEMP

f. LIQUID SAMPLE PANEL HIGH PLENUM PRESS , ,

g. CHEM ANALYSIS PANEL HIGH PLENUM PRESS

4. The fellowing equipment should be available:  !

a. Meter-long reach rod

(

l l

DC0209 IVI -

l

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. w . ;.u. ~ . . .....,,e, c.; . .: .. a.w::a.nn:.=,:.m: - , , -

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DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON 1 DATE 1/21/85 1 PAGE 2 0F 11 1 SENTRY POST-ACCIDENT SAMPLING SYSTEM j

m LE: --ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS 1

I]

j PRECAUTIONS 11

/ 1. This sampling involves processing of water that may be highly l radioactive. Precautions should be taken to prevent skin contact or ingestion.

[j 3

j

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 y suggested during purge and sampling exercises.

Ti

.J 4 For the Ion Chromatograph (IC):

)

i l a. The calibration curve should be checked once every 4 samples I by analyzing a chloride standard.

.; b. Calibertion should be checked when first using a new eluent.

l c. Regeneration is required about once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of .

l, continuous operation. Refer to the troubleshooting and L surveillance and maintenance procedure.

l During continuous operation, the separator colunn must be d.

cleaned on a deily basis or every other regeneratinn by n

pumping eluent through the column for a minimum of 10 j

minutes, followed by a 20 minute demineralized water rinse.

7 This may be coincident with regeneration of the suppressor

l. colunn. Refer to the troubleshonting and surveillance and maintenance procedure CAP G-3.

PROCEDURE .

1. Instrument Calibration g: If analysis is required from a second sacple source, then nonitor calibration is not needed again. Proceed to step

2. LSP and CAP Purging.

a. If calibration has been performed within the last week proceed to step 2.

]

l II 1

)

is

DC0209 2VI

,Y"l W ?Y */ I O?e *

"'[ Y & 'S ' W .n- '~*~* l~~ R*' * *

.- NUMBER EP RB-15:G DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION O I l

DATE 1/21/85 j v PAGE 3 0F 11 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE.

f --ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS i

l b. Set the OFFSET range switch to left. []

i, c. Set MODE to LIN. []

l d. Adjust the COARSE vernier switch to zero the meter.

- It may be necessary to adjust the FINE pot to zero the meter. []

l e. 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 I

( a. C1cse or check closed CAP-V-15. []

b. Verify CAP-CAL-3 is at least half full.

(CAP G-3, directs fillire). []

c. Align CAP-V-5 to CHLORIDE CALIB. SOL'N. []

d. Open CAP-V-15. []

, e. Turn on the L&N recorder. []

f. 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, I sample type, and conductivity meter setting. []

! g. After I minute, place the LOAD / INJECT switch in j LOAD position. []

! NOTE: The Cl peak will elute about 5 min, after injection.

f f h. Close CAP-V-15. []

l ~~

j 1. Align CAP-V-5 Counterclockwise to CLOSED. []

I

j. Align CAP-V-29 to vent (6 o' clock) []

k. After the Cl peak has eluted, wait 5 minutes then shut off the L&N recorder. []

i DC0200 3VI .

~ ~

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. z;we .w; a. -~. .v. ~ . .. :. . > a. :m u a- u u r:77 a t. m . m .> x i

3 1 ,

1 N'JMBER EP RB-15:G DIABLO CANYON NWER PLANT UNIT NO(S) 1 AND 2 i REVISION 0

. DATE 1/21/85 PAGE 4 0F 11 1 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE. --ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS d

a

1. Align CAP-V-5 to RCS sample (9 o' clock). []

]

3 in . Determine the peak height:

q j Peak height = (Trace Peak Height - Baseline) x Attentuation 100

} Peak Height = mm (i

j  ;

Corresponding ppm Cl from CAL. Curve ppm (A) j n. Compare the Cl standard peak with the calibration curve.

For the same umho setting, the values should be within 210%.

]

}

{3 (A) - 1.0 x 100 = Difference 3) 1.0 j Is (B) within :10%? (YES/NO)

3. LSP and CAP Purging et If LSF has been previously purged during Reactor Coolant

.y Liquid /offgas sampling then proceed to step j.

=

]i a. Determine which sanple source isolation valves will have to be opened from the list below:

?q SAMPLE SOURCE CONTAINMENT ISOLATION VALVES ll Hot Legs Loops 1 ard 4 FCV-9356A and FCV-9356B j Pressurizer Steam Space FCV-9354A and FCV-9354B

]~ Pressurizer Liquid Space FCV-9355A and FCV-9355B PHR Pumps Discharge N/A ll . Volume Control Tank N/A l*

b. Call the Control Roor and have operations block open the

!+ appropriate containment isolation valves.

c. Open the corresponding remote plant isolation valve (RP!V) and remote source isolation valve (RSIV) at the PCP (see attachment I for proper valve).

A a

li d

8 1

?

l-

? DC0209 4VI -

, y. g 7, 7 ,

.m . 77 _ . ,, , . ., ,.quy;.7g..m.;g.m,7...

7 .. .

1 AND 2 l~' DIABLO CANYON POWER PLANT UNIT NO(S)

DATE ON 1/21/85 i

i'* .. PAGE 5 0F 11 SENTRY POST-ACCIDENT SAMPLING SYSTEM M LE. --ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS

]

i

d. Close remote flush isolation valve (RFIV). []

M: The sample source valves are labeled i RC-V-1.1 through RC-V-1.5. Throughout I -

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.

-K)TE: upon implementation of the next step, sample will be flowing into the back of the LSP. The I meter-long reach rod should be used to operate l valves and a dose rate survey should be done to monitor radiation levels.

e. Open the sample source valve RC-V-1.X (see Attachernt 1 for proper valve). []

f. Open RC-V-3. []

g. Slowly open RC-VREL-1 ur.til RC-FI-1 indicates 100*; flow or 1900 cc/rin Purge for 9 minutes. []

h. Slowly close RC-VREL-1 until RC-FI-1 indicates j 365 or 700 cc/ min. Continue the purge for 1 minute, []

i. Close RC-V-3. []

j. Open the following valves:

RC-V-7 RC-V-2 l[

k. Position RC-V-22 to the TO CHEM PANEL position. []

I

1. Adjust RC-VREL-2 until RC-FI-2 indicates 100% full flow or 200 cc/nin. l

[]

l 5

m. Verify that the red FULL FLOW lights are lit for the i ION CHROMAT loop at the CMP and CAP panels. Adjust

! RC-VREL-2 if necessary to obtain proper flow rate. [] ,

1 l

n. Continue the purge for 5 minutes. []

l l

DC0209 SVI .

' ( W![ QM l _ _

L', ,.

w. .. , . = :-- w, . . . . .. us i.ac.unGswa ,~ c a . .a umknnnExh

+

' e o NUMBER EP RB-15:G DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 REVISION O DATE 1/21/85  !

m PAGE 6 0F 11 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE:

--!ON CHROMAT0 GRAPHIC CHLORIDE ANALYSIS J

f 4. Sample Analysis

a. At the CMP, activate the L8N recorder. []

? .

b. Place the IC LOAD / INJECT switch in the INJECT position 3 and mark the inject position on the chart paper. []

c. On the chart paper, record the date/ time, sample

?j source used, umho setting, chart speed, and

]j ' analyst's initials. []

I*

d. After approximately 1 minute from sample injection,

, place the LOAD / INJECT switch in the LOAD position. []

M

The chloride peak will appear approximately 5 minutes after injection at the same retention 1 time observed for the standard.

] e. Turn CAP-V-5 to the DEMIN WATER position. []

f. Flush with demin water for 2 minutes. []

g. Examine the L&D recorder. If the chloride peak goes off-scale, a reanalysis must be completed using a larger umho setting (3 umho) and following j

3 the steps below, otherwise skip to step "h". []

]- 1) Select appropriate attenuation. []

[ 2) Align CAP-V-5 to LIQUID SAMPLE. []

1 j 3) Continue the purge for 1 minute. []

H H 4) Place LOAD / INJECT switch in the INJECT position 1 and mark the inject position on the chart paper. []

5) On the chart paper, record the date/ time, sample

? source used, umho setting, chart speed, and I;

i; analyst's initials. .. *- [ ]

p 6) After approximately 1 minute, place the j LOAD / INJECT switch in the LOAD position. []

lI , E: The chloride peak will appear at approximately J 5 minutes after injection.

lia L

DC0209 6VI f

, n .,.,.g.,.,. ., .

1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S)

[0N DATE 1/21/85

- . PAGE 7 0F 11 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE

--ION CHROMAT0 GRAPHIC CFLORIDE ANALYSIS 4

7) Turn CAP-V-5 to the DEMIN WATER position. []

- 8) Flush with demin water for 2 minutes. []

9) Exanine the L&N recorder for the chloride p'eak. []

l0TE: If the chloride peak is off scale, change the umho setting and repeat step g. until the chloride peak is on scale.

1

h. After the Cl perk has eluted, wait 5 minutes then turn off the L&N recorder. []

i. Detemine the peak height Peak height = (Trace peak height - baseline) x attentuation 100 i Peak height = mm j j. Detemire the ppm chloride from the calibration curve

and record on the data sheet (EP RC-15:F).

] upm C1'

5. Flushing 4

a. At the PCP, perfom the following:

1) Close the remote plant and source isolation valves.(see Attachment 1). []

2) Open the remote flush isolation valve (see Attachment 1 for proper valve). []

b. At the LSP, close RC-V-1.X. []

c. At the CAP, align CAF-V-5 to LIQUID SAMPLC. []

d. At the LSP, oper. RC-V-4 []

e. Open RC-VREL-2 until RC-FI-2 indicates 100% of

.i full flow or 200 cc/ min. Flush with demin water for 3 minutes. []

f. Close RC-V-7. []

g. Open RC-V-3. []

I DC0209 7VI ff?f] ST[. , -

. z . . s.z .ra u .. . . :=; . , = . . v; s.savuw;::an u 1 AND 2 I DIABLO CANYON POWER PLANT U 41T NO(L)

R ON l DATE 1/21/85 PAGE 8 0F 11 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE:

--ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS r

, h. Adjust RC-VREL-1 until RC-FI-1 indicates 100% of

( full flow or 1900 cc/ min. Flush with denin water for 1 minute. []

i 1. Close RC-V-3. []

i j. Open RC-V-1.X and flush with demin water for j 5 minutes. []

) k. Close RC-V-1.X. []

1. Open RC-V-7. []

m. Adjust P.C-VREL-2 until RC-FI-2 indicates 100% of

) full flow or 200 cc/ min. Flush with demin water 4 for 3 ninutes. []

}

n. At the CMP, cycle the LOAD / INJECT switch at least 1 times. Return it to the LOAD position. []

.) o. At the CAP, align CAP-V-5 to CLOSED. []

s

p. Turn CAP-V-6 to LIQUID SAMPLE (9 o' clock) and flush with demin water for 2 minutes. []

q. Turn CAP-V-6 to 0XYGEN CALIB SOLUTION. []

r. Close CAP-V-11. []

s. Terminate flushirg by closing the following valves:

J RC-V-7 '

L RC-V-2 ' '

N RC-V-4 j

9 RC-VP.EL-1 '

RC-VREL-2 .

j t. Align RC-V-22 to W/.FTE. []

] u. At the PCP, close the remote flush isolation valve: []

(Attachment 1)

-4 j

v. Call the control room and have operations close the containment isolation valves opened earlier. []

l p

9 DC0209 8V1 '

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f' DuBLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 1/21/85 PAGE 9 0F 11 j* TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM i --ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS I

. 6. Flushing the Separator and Suppressor Columns

> If the IC is not needed for further sampling in an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period then the following steps should be performed before f system shutdown can be started.

i a. Perform the following IC valve alignments to wash the iodine and other cations frem the suppressor column:

OTE: Direction fron the Site Emergency Coordinatnr may preclude this section, if radiological conditions warrant.

f

1) Check that the conductivity meter mode switch

is set to ZERO. []

[ 2) In the eluent / pump enclosure of the CAP, check i the following:

I 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 f set at 40!, for both pumps. []

j 3) At the CMP, check the following:

a) Check that the regeneration time ,

l thumbwheels are set at 15 min for REG l and 45 min for RIN. []  !

l b) Align the following air toggle switches to '

the indicated positions:

SWITCH POSITION ..

Ey / Water E g []

E DOWN g []

SEP-1/SEP-2 SEP-1 []

SUP-1/RGN-2 SUP-2/RGN-1 []

INJECT / LOAD LOAD []

DC0209 9VI -

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l 1 .

DIA8LO CANYM POWER PLANT UNIT NO(S) 1 AND 2 h0N DATE 1/21/85 PAGE 10 0F 11

'l SENTRY POST-ACCIDENT SAMPLING SYSTEM j TITLE.

--ION CHROMAT0 GRAPHIC CHLORIDE ANALYSIS A

.] 4) Depress regeneration START button and the j suppressor column will automatically be

?i, regenerated. []

d j 5) Flush the separator column for 20 min. After 20

" min., turn the E switch 3

to DOWN and rinse the separator coTumn with demin. water for 10 min. []

k y 7. Systen Shutdown 1

a. After completion of column regeneration, perform the following:

! 1) Turn IC POWER switch to 0FF. []

2) Turn AIR switch to 0FF. []

3) Turn GAUGE switch to 0FF. []

4; Turn ELUENT pump switch to 0FF. []

11 Turn conductivity meter MODE switch to ZERO.

K) []

b. If pH/ conductivity /00 are to be done, proceed to section H.

c. If finished with all CMP ar.alyses, turn CMP power off. []

1 8. Data Anclysis il i r. Proceed to EP RB-15:F for data analysis

i j 9. If finished with all sampling / analysis go to 15

H l Step 6, system shutdown.

REFERENCES

l 1 Sentry Equipnent Corp. High Radiation Sampling System Operating and Maintenance Manual.

APPENDIX Valves for Obtaining Samples from Reactor Coolant

)

l l

i DC0209 10VI .

lI 1

DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 R ON DATE 1/21/85

.' PAGE 11 0F 11 i SENTRY POST-ACCIDENT SAMPLI?lG SYSTEM

, TITLE

--!ON CHROMAT0 GRAPHIC CHLORIDE ANALYSIS l

l l EP RB-15:G f VALVES FOR OBTAINING SAMPLES FROM REACTOR COOLANT i

l I

APPENDIX 1 i

LSP SAMPLE REtiOTE PLAT:T REMOTE SOURCE REMOVE 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 Hnt Leg 4 FCV-9351 B FCV-692 FCV-1416 RC-V-1.1 i PZR Liquid FCV-9350 B FCV-693 FCV-1417 RC-V-1.2 h

! PZP Stean FCV-9350 A FCV-694 FCV-1418 RC-V-1.3 I

RHR Pump 1-1 l Discharge FCV-9353 A FCV-1413 FCV-1419 RC-V-1.4 f

l RHR Pump 1-2

! Discharge FCV-9353 8 FCV-1413 FCV-1419 RC-V-1.4 VCT Liquid N/A FCV-1412 FCV-1420 RC-V-1.5 Rx Cavity FCV-696 N/A FCV-1423 RW-V-2.1 l Sump FCV-697 Floor Orn Reevr N/A FCV-1415 FCV-1425 RW-V-2.2 Equip Drn Reevr N/A FCV-1414 FCV-1424 RW-V-2.3

(

DC0209 11VI -

. NUMBER EP RB-15:H GW3 Pacific Gas and Electric Company REVISION O

~

DEPARTMENT OF NUCLEAR PLANT OPERATIONS I 1 12 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

. EMERGENCY OPERATING PROCEDURE SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE -- PH/ CONDUCTIVITY / DISSOLVED OXYGEN l ^

APPROVED

^i b PLANTMANAGg) DATE l

'. DISCUSSI0rl i 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 4 LSP reactor coolant module an CAP lines. This procedure requires operator actions at the LSP, CAP, and CMP.

/

~

PRERE00! SITES i 1. Monitors are turned on according te procedure EP RB-15:A:

1 t a. and have warmed up for I hour if oxygen analyzer has not 2 '

been calibrated within 1 week;

b. or, have warmed up for 30 rinutes if oxygen analyzer does not need calibration.

4

2. CAP, CitP, and LSP syttems lined up as detailec' in procedure EP PD-15:A.

! 3. Verify that the ic110 wing annunciator windows are off on the PCP:

e. REACTOR C00LAt:T SAMPLE COOLING WATER LOW FLOl:

b. REACTOR COOLANT SAftPLE COOLING WATER LOW PRESS

c. REACTOR C00LAl:T SAMPLE COOLING WATER HIGH TEMP

d. REACTOR COOLANT PLIRGE HIGH TEMP

e. REACTOR COOLANT SAMPLE HIGH TEMP ,,

f. LIQL'ID SAMPLE pat:EL HIGH PLEl:UM PRESS

g. CHEM ANALYSIS PAliEL HIGH PLENUM PRESS

(

r DC0416 11 ,

-. . ... a.: . wu.wana;; . - . . . . . - 2.:.ua l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 V ON DATE 1/21/85

, PAGE 2 0F 12 SENTRY POST-ACCIDENT SAMPLING SYSTEM M LE 4 -- PH/ CONDUCTIVITY / DISSOLVED OXYGEN 1

li 3

j 4. The following equipment must be available:

i j a. Meter-long reach rod y

a b. Small screwdriver i

5. The conductivity meter should have been calibrated within the last 3 months.

1 i PRECAUTIONS i

'! 1. This sanpling involves processing of water that will be highly 1 radioactive. Precautions should be taken to prevent skin contact or ingestien.

2. Time in a radiation field should be limited to that necessary to perform the reouired 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 suggestec during purge and sampling exercises.

PROCEDUP.E

1. Menitor Calibration f0TE: If analysis is required from a second sample source, then moritor calibration is not needed again. Proceed to step p 2. LSP and CAP Purging i

p a. pH Calibration 1 1) Align CAP-V-6 to pH CALIB SOLUTION []

?'

l

2) Adjust CAP-V-26 until sufficient flow is

j. indicated by red flow indicator light.

j Flow for ' rinutes. Cycle CAP-V-7 to Rexnard

} and then back to the YSI 0xygen Analyzer. [3 a

l' 3) Turn CAP-V-6 counterclockwise to OXYGEN CALIB. SOLUTION to terminate flow. []

4) Align CAP-V-27 to vent position. []

\

1-DC0416 21 ,

.-- .c

l* DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 I

R ON DATE 1/21/85

~

. PAGE 3 0F 12 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE-

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN

5) Observe and record the temperature of the buffer solution as indicated on the CMP.

Temp. 'C I

] a) Correct the buffer pH value for the recorded temp. from the pH Temperature

! Correction Table (Appendix 1). []

i j 6) Adjust the pH monitor R-3 until the meter indicates the temperature corrected pH value. []

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 WATEP. and flush for 2 minutes. Cycle V-7 from YSI to Rexnord to flush 00 deadleg. []

9) Align CAP-V-30 to pH calibration tank CAL-2. []

10; Align CAP-V-26 tc. the nitrogen supply line. []

11) Align CAF-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 to Rexnard and then back to YSI 0xygen Analyzer. []

13) Turn CAP-V-6 counterclockwise to the 0XYGEN CALIB SOLUTION to terminate flov. [-]

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 a) Correct the buffer pH value for the reco'rded temp. from the pH Temperature Correction Table (Appendix 1). []

i l

(

DC0416 31 .

l

\ 1

.1 . s.. .. . 1 - % M::.uc.n,1, a.2

~

NUMBER EP RB-15:H DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 0 DATE 1/21/85 PAGE 4 0F 12 4

SENTRY POST-ACCIDENT SAMPLING SYSTEM l TITLE. -- PH/ CONDUCTIVITY / DISSOLVED OXYGEN 1

': 16) After the meter reading has stabilized, record the j reading and compare to the temperature corrected pH

.! value. The reading should be within 0.5 pH units of j the temperature corrected value.

.j pH

J lj 17) Align CAP-V-6 to DEMIN WATER and flush for 2 j minutes. Cycle V-7 from YSI to Rexnord. []

u lj b. Dissolved Oxygen Analyzer Calibration l NOTE: If calibration has been performed within 1 week proceed to step 2. LSP and CAP Purging.

b 1) Align V-7 to YSI or Rexnord depending on directions given by supervision.

2) Open CAP-V-9. []

3) Align CAP-V-6 to 0XYGEN CALIB SOLUTION. []

4) Close CAP-V-17 until the red flow indicator is lit. []

l

5) Purge for 5 minutes (YSI) or 15 minutes (Rexnord) then read and record the temperature of the water in CAL-4 at the CitP.

l l Temp. 'C

6) Determine the dissolved oxygen concentration from the Solubility of Oxygen in Air Saturated Water table (Appendix 2) and recurd the value, ppm dissolved oxygen

7) Adjustment a) YSI:

j' While flowing, adjust the Op calibration knob l until the pen traces to the dissolved oxygen ccncentration in ppm recorded in step 6). []

9 DC0416 41 .

mw c ,

l DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 1/21/25 PAGE 5 0F 12 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE- -- PH/ CONDUCTIVITY / DISSOLVED OXYGEN b) Rexnord:

While flowing, adjust the CAL ADJ to indicate the dissolved oxygen concentration in ppm previously recorded in step 1.b.6).

(This may involve changing the scale switch position). []

8) Turn the oxygen calibration pump to 0FF. []

9) Close CAP-V-9. []

10) Aligr CAP-V-6 to LIQUID SAMPLE. (9 o' clock) []

2. LSP and CAP Purging If LSP has been previously purged during Reactor Coolant Liquid /offges sampling ther proceed to step j.

c. Deterrine which sample source isolation valves will have to be opened from the list below:

SAMDLE SOFDCE CONTAINMErlT ISCLATION 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

b. Cell the Control Room and have operations block open the appropriate containment isolation valves.

c. Open the corresponding remote plant isolation valve (RPIV),

remote source isolation valve (RSIV), at the PCP (see Appendix 1 for proper velve).

d. Close remote flush isolation valve (RFIV). ,[]

10T_E: 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.

(

DC0416 51

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S ON DATE 1/21/85

!- PAGE 6 0F 12 i SENTRY POST-ACCIDENT SAMPLING SYSTEM

.{ TITLE.

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN u

'I WTE: Upon implementation of the next step, sample will be flowing into the back of the LSP. The ri,eter-long reach rod should be used to operate j valves and a dose rate survey should be done 2

6 to monitor radiation levels.

l e. Open the sample source valve RC-V-1.X (see Appendix 1 for proper valve). []

1 f. Open RC-V-3. []

d

] g. Slowly open RC-VREL-1 until RC-FI-1 indicates 1 100!; flow or 1900 cc/ min. Purge for 9 minutes. []

l:

a h. Slowly close RC-VREL 1 until RC-FI-1 indicates 36% or 700 cc/ min. Continue the purge for 1 minute. []

1 l Close RC-V-3.

i. []

j. Open the following valves:

) 0.C-V-7 ']

1 RC-V-2 ]

k. Positior: RC-V-22 to the TO CHEM PANEL pnsition. []

1. Adjust RC-VREL-2 until RC-FI-2 indicates 100% or 200 cc/ min. []

L m. Verify that the red FULL FLOW lights are lit for 1 the pH, 0 , and CONC loop at the CMP and CAP panels.

2 ll Adjust RC-VREL-2 if necessary to obtain proper j flow rate. []

n. At the CMP, turn YSI CHAPT SPEED to RAPID and verify PEN INPUT is set to -02* b3

3. Sample Analysis a a. Flow for 5 minutes or until meter reading stabiltres.'

4 Cycle CAP-V-7 to Rexnord for 30 seconds and back i to YSI 0xygen Analyzer. []

a

,d

'i n

DC0416 61 -

P -

, , . - --- -~, . ~ ~ s ,- --c s _

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 OH DATE 1/21/85 PAGE 7 0F 12

, SENTRY POST-ACCIDENT SAMPLING SYSTEM m LE

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN

b. Observe and record conductivity meter reading and temperature of the sample stream from the CMP.

t Cond. umho Temp. 'C

c. Turn CAP-V-6 counterclockwise to OXYGEN CALIB i SOLUTION to terminate sample flow and permit pH reading to stabilize. []

d. 1) YSI:

Turn YSI CHART SPEED to I and mark the i

chart paper with the date/ time, 0 7 range, sample source, sample temperature,' and operator's initials. []

2) Rexncrd:

Observe the Rexnord dissolved oxygen meter

, reading and turn to a lower scale position as the meter reading decreases. Purge 15 minutes.

[j,

e. Read the 03 concentration. ppm 0 2

f. Observe the p!{ noter for 1 minute to ensure the reading has stabilized. Record the pH reading, ph Temp. 'C i 4 Flushing

. a. At the PCP, perform the following:

1) Close the remote source isolation valve. []

C) Open t!.e remote flush isolation valve (see Appendix 3 for preper valve). ..

[]

b. At the LSP, close RC-V-1.X. []

c. At the CAP, align CAP-V-6 to LIQUID SAMPLE.

(9 o' clock) []

d. At the LSP, open RC-V-4. []

i DC0416 7I

~

.. a . c. _

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Vl SON 0 l 1 DATE 1/21/85 l t PAGE 8 0F 12 0 SENTRY POST-ACCIDENT SAMPLING SYSTEM a

m LE.

-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN

e. Open RC-VREL-2 until RC-FI-2 indicates 100% flow or j 200 cc/ min. Flush with demin water for 1 minute. []

f. Close RC-V-7. []

g. Open PC-V-3 []

k; t h. Adjust RC-VREL-1 until RC-FI-1 indicates 100%

. flow or 1900 cc/ min. Flush with demin water for 1 g minute. []

i. Close RC-V-3. []

j. Open RC-V-1.X and flush with demin water for 5 minutes. []

k. Close RC-V-1.X. []

$ 1. Open PC-V-7. []

6 y m. Adjust RC-VREL-2 until RC-FI-2 indicates 100%

h ficw cr 200 cc/r.in. Flush with dea.in water for 3 minutes. []

) n. At the CAP, elign CAP-V-6 to OXYGEN CALIB 3 SOLUTION. []

9

o. Termirate flushing by closing the following valves:

'1 i RC-V-7 '1

?

{ RC-V-2 RC-/-4

'I l RC-VFEL-1 1 RC-VREL-2 [)

i i

p. Align RC-V-22 to WASTE. []

i q. At the PCP, close the remote flush isolation velve. []

~

r. Call the control room and have operations close tire containment isolation valves opened earlier. []

. 5. Sample Calculations.

j a. Correct the recorded sample pH for temperature from the pH a Temperature Correction Table (Appendix 1). []

.! I

b. Transfer all data to data sheets EP RB-15:F.

j DC0416 81 N +-

1 AND 2 NUMBER EP RB-15:H DIA8LO CANYCN POWE3 PLANT UNIT NO(S)

• REVISION O DATE '1/21/85

' PAGE 9 0F 12 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE -- PH/ CONDUCTIVITY / DISSOLVED OXYGEN 4

c. If further analyses / sampling is to be done proceed to appropriate

procedure, f 6. System Shutdown i

~

a. CMP Shutdown l 1) pH Monitor - Turn switches S-3 and S-1 to the OFF

position.

[]

2) Conductivity Monitor - Turn function select switch to ZERO position. []

~

3) YSI Monitor - Turn YSI POWER switch to 0FF position.

[]

b. Turn gas supplies off by lifting to horizontal position green rcot valves next to CAP.

c. If finished with all CMP analysis, turn CMP POWER OFF.

d. At the CCP, turn Functicr Select switch to 0FF.

e. Turn off Ernergency Ventilation.

f. When exiting through the Motor Repeir Shop close the bottle isolation valves for the Sentry ges supplies.

REFERENCES

1. Sentry Ecuipr,ent Corp. High Ri:diation Sanpling Systen Operating and Maintenance Manual.

APPENDICES

1. pH Temperature Correction Table

2. Solubility of Oxyger it. Air Saturated Water

3. Valves for Obtaining Samples from Reactor Coolant 4

DC0416 91

i I AUD 2 NUMBER EP RB-15:H -

OlASLO CANYON POWER PLANT UNIT NO(S) REVISION 0 DATE 1/21/85

~; PAGE 10 0F 12 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE: -- PH/ CONDUCTIVITY / DISSOLVED OXYGEN t

l v

i EP RB-15:H I

i APPENDIX 1 i.

e pH TEl1PER8.TURE CORRECTION TABLES SAMPLE pH TEMPERATURE CORRECTION TABLE TEMP *C CORR TEMP *C CORR 16 .31 31 +.20 17 .27 32 +.24 18 .24 33 +.26 9 19 .20 34 +.29 I

26 .16 35 +.32 h 21 .13 36 +.36 q 22 10 37 +.40 23 .07 38 +.43 24 .03 39 + 46

, 25 .00 40 +.50 3 26 +.0a 41 +.53 l 27 +.07 42 +.56

. 28 +.10 43 +.59 29 +.14 44 +.63 30 +.17 45 +.66 I

BUFFER pH TEMPERATURE CORPECTION TABLE 3

j RED GREEN CLt'E

TEMP pH4 pH7 pH10 1

] 10*C 4.00 7.06 10.18 1 15'C -- --

10.12 1 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 45'C -- --

9.86 50*C 4.06 6.97 9.83

/ 60'C 4.09 6.98 --

4 70*C 4.12 6.99 --

80*C 4.16 7.00 --

. 90*C 4.19 7.02 --

95'C 4.21 7.03 --

3

• TAKEN FR0!i LABELS ON BECKMAN BUFFERS DC0416 101 -

i I..,,.-. ,, '-

p ,

.. .n.. -

. . \

E

!!

• 1 AND 2 DIASI.O CANYON POWER PLANT UNIT NO(S) p l3ON f' DATE 1/21/85 PAGE- 11 0F 12 l SENTRY POST-ACCIDENT SAMPLING SYSTEM i e Ti m .

-- PH/C0fCUCTIVITY/ DISSOLVED OXYGEN 1

EP RB-15:H SOLUBILITY OF OXYGEN IN AIR SATURATED WATER (For Oxygen in Air at I atm.)

APPENDIX 2 e

TEMP PPM TEMP PPM

• C DISSOLVED 'C DISSOLVED

, OXYGEN OXYGEll 16 9.9 31 7.5 17 9.7 32 7.4 l

18 9.5 33 7.3

! 19 9.3 34 7.2 l! 20 9.2 35 7.1 21 9.0 36 7.0 22 8.8 37 6.8 23 8.7 38 6.7 j 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' l 30 7.7 5 6.0 h

h(

DC0416 111 t

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) -

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON j DATE 1/21/85 1

- PAGE 12 0F 12 1 SENTRY POST-ACCIDENT SAMPLING SYSTEM

] TITLE: .. PH/ CONDUCTIVITY / DISSOLVED OXYGEN b

I EP RB-15:H j VALVES FOR OBTAINING SAMPLES l APPENDIX 3 J

l

's 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 9351 A FCV-692 FCV-1416 RC-V-1.1 RC Hot Leg 4 9351 B FCV-692 FCV-1416 RC-V-1.1 PZR Liquid 9350 8 FCV-693 FCV-1417 RC-V-1.2 PZP Steam 9350 A FCV-694 FCV-1418 RC-V-1.3 RHP. Pump 1-1 I

.a Discharge 9353 A FCV-1413 FCV-1419 RC-V-1.4 RHR Pump 1-2 3 Discharge 9353 B FCV-1413 FCV-1419 RC-V-1.4 VCT Liquid it/A FCV-1412 FCV-1420 RC-V-I.5 j Rx Cavity Sump FCV-696 N/A FCV-1423 RW-V-2.1 i FCV-697 Floor Drn Reevr N/A FCV-1415 FCV-1425 RW-V-2.2

]

Equipm Den Reevr N/A FCV-1414 FCV-1424 RL'-V- 2 . 3

l j .

1 h n 2

DC0416 121 ,

~ ;;mmy v:n .. __

. . . _ ._,c_ _ _

j q l.' .

NUMBER EP R8-15:I i

l-

. FGY.4E Pacific Gas and Electric Company REyISloN 0 1

m DATE 1/22/85 DEPARTMENT OF NUCLEAR PLANT OPERATIONS

, p

DIA8LO CANYON POWER PLANT UNIT NO(S) I ANO 2 I EMERGENCY PROCEDURE TITLE. SENTRY POST-ACCIDENT SAMPLING SYSTEM S -- SAMPLE STORAGE AND DISPOSAL 8

APPROVED Y$ # i bb PLANTMANAGERg DATE i l

. DISCUSSION The purpose of this procedure is to provide a means for disposal of stripped-gas samples and storage of RCS liquid samples.

PRECAUTIONS

1. Same as EP RS-15:A.

j PREREQUISITES

1. PGandE Post Accident Sampling Packaging, Type A.

2. Gas bottle Griptong.

3. 14 cc gas sample bottle.

PROCEDURE

1. Disposal of Reactor Coolant Stripped-Gas Samples

a. At the LSP I) Close or check closed valves.

RC-V-1.1 through RC-V-1.5 []

I 2) Verify that RC.-G-4 indicates approximately l

100 psig Ar. []

i l- b. At the PCP l ,

1) Close or check closed FCV-9351A, FCV-9351-B

l FCV-9350A, FCV-9350-8 FCV-9353A j)

[ f DC0118 IIV

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• 4 e

.w a . .w ua =a, . . .m s ;yw..>i. ua.w:p . ::.. . . =

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

$h0N DATE 1/22/85 j PAGE 2 0F 4' '

7' M ;

SENTRY POST-ACCIDENT SAMPLING SYSTEM

j -- SAMPLE STORAGE AND DISPOSAL

.i m-N M FCV-692 FCV-693, FCV-694 [;

FCV-1412, FCV-1413 ,,

+

FCV-1416, FCV-1417, FCV-1418 9 FCV-1419, FCV-1420 ,' )

J j c. Align the following valves:

1 RC-V-10 (closed) l]

RC-V-15 closed) i,j RC-V-14 closed) ,

i q RC-V-11 (CLOSED) i,J 3 RC-V-13 (closed) ,,

1 RC-V-12 (closed) '.

4 RC-DV-2 (9 o' clock) ]

q d. Bottle Evacuation 1 1) With the griptong, insta11 the diluted gas sample

, bottle on the front panel needle. []

i j 2) Open RC-V-13. []

d 3) Open RC-V-12 and evacuate until RC-G-2.2 indicates a j

minimum vacuum of 22 inches mercury. []

] 4) Turn RC-DV-2 to the 6 o' clock position and continue the t evacuation until a minimum vacuum of 22 inches of j mercury is indicated on RC-G-2.2 []

a

] 5) Close in order RC-V-13 and RC-V-12. []

i

i 6) Open RC-V-14 and allow the bottle to pressurize to approximately 1 psig as indicated on RC-G-2.2. []

ll b

] 7) Close RC-V-14. []

i i 8) Open RC-V-13 and RC-V-12 and evacuate until RC.G-2.2 indicates a minimum vacuum of 22 inches mercury. []

j

9) Close in order RC-V-13 and RC-V-12. []

li 1

(

t dDC0118 21V

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

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

.. . ,. w . . ..z . . . . :. ~ = ..  :. .w a.uwmuw - . . -

muew re-OIsaaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON

' DATE 1/22/85 I - PAGE' 3 0F 4 lA

• SENTRY POST-ACCIDENT SAMPLING SYSTEM

-- SAMPLE STORAGE AND DISPOSAL l

i t 10) Open RC-V-14 and allow the bottle to pressurize to approximately 1 psig as indicated on RC-G-2.2. []

j 11) Close RC-V-14. []

r i 12) Repeat steps 8 through 11 three times to remove all radioactit a gases. []

e. Bottle Disposal f

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

a. Open the Sentry cart / cask. []

b. Align the internal portion of the Post Accident i

. Packaging (PASP) over the Sentry cart / cask cavity. []

c. Withdraw the tungsten shield at the base of the transfer cask. []

. d. Slowly lower the sample bottle access mechanism until the l

latch grasps the sample bottle. []

,[ e. Slowly raise the sample bottle into the cavity of the l

transfer cask. []

f. Close the tungsten shield at the base of the transfer cask. []

g. With two persons (one at each arm of the transfer cask),

carefully move the bottle to the storage location. []

h. Place the transfer cask on the sample bottle storage

, platform. -

[]

i. Withdraw the tungsten shield at the base of the transfer cask. []

l L

i(

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l -

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l1 q o -

~g ij c-h 1 AND 2 NUMBER EP RB-15:I DiasLO CANYON POWER PLANT UNIT NO(S) t REVISI0ft 0 DATE 1/22/85 PAGE 4 0F 4' SENTRY POST-ACCIDENT SAMPLING SYSTEM <

~

N -- SAMPLE STORAGE AND DISPOSAL

• 1 4

j. Slowly , lower the sample bottle to the platform and continus

. the downward movement until the sample bottle is

} released. []

1 y'

k. Raise the bottle access mechanism and close the tungsten

., shield. []

t

)

4 i.

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o Il

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i C PV PACIFIC OAS AND E LE C T RIC C O M PANY I'

n statt sincer. san ra4NetSCO, CAltFORNI A 94106 TELEPHONE (415) 78: 4211 p.gg ,

March 14,1985 i

PGandE Letter No.: DCL-85-112

, Mr. John B. liartin, Regional Administrator i U. S. Nuclear Regulatory Comission, Region V 1450 Maria Lane, Suite 210

! Walnut Creek, CA 94596-5368 Re: Docket No. 50-275, OL-DPR-80 1

Docket No. 50-323 Diablo Canyon Units 1 and 2 Emergency Plan Implementing Procedure Updates

Dear Mr. Martin:

i In accordance with Section V, " Implementing Procedures," of 10 CFR 50, Appendix E, PGandE is submitting one copy of the updates to the detailed Implementing Procedures (Enclosure 3) for the Diablo Canyon Power Plant Units 1 and 2 Emergency Plan. These updates are listed in Enclosure 1. Concurrently ,

two copies of each update are being submitted to the Document Control Desk.

Some of the updates contain privacy / proprietary information. This

[ privacy / proprietary information has been bracketed in accordance with NRC Generic Letter 81-27 and is identified in Enclosure 2.

i Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.

i Sincerely, W. A. Raymond

[ for J. D. Shiffer

[ Enclosures cc: R. T. Dodds R. Fish Document Control Desk (2)

Service List cc w/o Enc 3: G. W. Knighton i

g'od t { '}-

I

.l J

ag *q* -* 1 ***"'?-

9  %

• ea e- f, e , y ,q

pa airug'o

• g UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION f ,I WASHINGTON, D. C. 20555 April 1, 1985 50-275/323 Diablo Canyon i

MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Division of Rules and Records, ADM

SUBJECT:

REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be made publici available.

4

/ ')

. M. Felton, Director ivisionofofAdministration Office Rules and Record 'f/d

Attachment:

As stated l

l 1

o e

- , . . . .-,.- . - . - - = --

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR 8995500eas DOC.DATE: 85/03/14 NOTARIZED: No DOCKET s FACIL 50-275 Diablo Canyon Nuclear Power- Plant, Unit 1, Pacific.Ga 05000275 50-323 Diablo Canyon Nuclear Power Plant, Unit 2', Pacific Ga

• 05000323 AUTH.NAME AUTHOR AFFILIATION , .

SHIFFER,J.D. Rochester Gas & Electric Corp.

CECIP.NAME RECIP!ENT AFFILIATION

~

MARTIN,J.B. Region 5, Office of Director

SUBJECT:

Central Files version of revised emergency pla,n implementing procedures, including table of contents,Rev 4 to EP ORat ce

., offslte supp'rto & assistance.& Rev 3 to EP OR-2 re release

of info to ouo11c.W/850314 Itr. i

" DISTRIBUTION CODE: X0050 . COPIES RECEIVED LTR , ENCL . SIZES._jh ____

TITLE

Emero Plan.(CF Avail) i NOTES J Hanchett icy PDR Documents. 05000275

OL309/22/81

J Hanchett 1cy PDR Documents. 05000323 RECIPIENT COPIES RECIPIENT COPIES ID CODE /NAME- LTTR ENCL ID CODE /NAME LTTR ENCL' NRR LB3 BC 1- 0 SCHIERLING, H =ggjf 1 1 INTERNAL ADM/DRR $$le 1 1 IE/DEPER/EPS f2 2

~EP /IRB JV7 1 1 NRR/DSI/AES 2., 1 1 NRR/DSI/RAB REG FILES 1 0

/ 1 1 NOTES: 1 1 l

I l

l l

l l

TOTAL NUMBER Oe c0 PIES REQUIRED: LTTR 10 ENCL 8 1

..