DCL-85-165, Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 7 to EP M-7 Re Oil Spill Isolation & Cleanup & Rev 6 to EP G-4 Re Personnel Accountability & Assembly
| ML20127D961 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/24/1985 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML16341C612 | List: |
| References | |
| DCL-85-165, PROC-850424-01, NUDOCS 8505170173 | |
| Download: ML20127D961 (257) | |
Text
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PGandE Letter No.: DCL-85-165 ENCLOSURE 1 Updates Includsd In This Submittal DIABLO CANYON EMERGENCY PLAN IMPLEMENTING PROCEDURES Volume 3A .
Updated Table of Contents EP M-7, Revision 7 EP G-4, Revision 6 Volume 3B Update Table of Contents EP EF-6, Revision 4 EP RB-3, Revision 1 EP RR-4, Revision 2 EP RB-15:A, Revision 3 EP RB-15:2, Revision 2 EP RB-15:C, Revision 2 EP RB-15:D, Revision 2 EP RB-15:E, Revision 2 EP RB-15:F, Revision 1 EP RB-15:G, Revision 1
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EP RB-15:G, Revision 1 EP RB-16: A, Revision 2 EP RB-16:B4, Revision 2 EP RB-16:B5, Revision 2 9
8505170173 850424 PDR ADOCK 05000275 F PDR 0502d/0005K .
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PGandE'L2tter No.: -DCL-85-165 .
><- - ENCLOSURE 2 L' : cation of Proprietary Information l Procecura:
EP M-7 -- pp. ? and 3 of 5-EP G-4 -- pp. 4: 5; 7i 8: 9: Surmary of.
~
. Personnel Accountability and.
Assignments, pp.1 and 2 of 2.
EP RB-15A -- pp. 3, 9 and 10 of 27
'EP RB-16A -- pp. 3, 9 and .10 of 16 EP RB-1684 -- p.1 of 7 -
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PGandE Lott:,r No.: DCL-85-165 1
i ENCLOSURE 3 l
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Updates to Dieblo Canyon ;
Percency Plan Inglementing Pr:cedures mm O
0502d/0005K .
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PGandE Lett:r No.: DCL-85-165 CURRENT CiERGENCY PLAN IMPLEMENTING PP,0CEDURES TABLE OF CCNTENTS Yolume 3A TITLE REV E-0 Reactor Trip or Safety Injection 0 E-0.1 Reactor Trip Response O E-0.2 Natural Circulation Cooldown 0 E-0.3 Natural Circulation Cooldown with Stear Void in Vessel 0 (with RVLIS)
E-0-4 Natural Circulation Cooldown with Steam Void in Vessel 0 (Without RVLIS)
E-1 Loss of Reactor or Secondary Coolant 0 E-1.1 SI Termination 0 E-1.2 Post LOCA Cooldown and Depressurization 0 E-l.3 Transfer to Cold Leg Recirculation 0 E-1.4 Transfer to Hot Leg Recirculation 0 E-2 Faul ted Steam Generator Isolation 0 E-2.1 Alternate Auxiliary Feedwater Supplies O E-3 Steam Generator Tube Rupture 0 ECA-0.0 Loss of All AC Power 0 4 ECA-0.1 Loss of All AC Power Recovery Without SI Required 0 ECA-0.2 Loss of All AC Power Recovery with SI Required 0 ECA-0.3 Restore Vital Bus 0 ECA-l.1 Loss of Emergency Coolant Recirculation 0 ECA-1.2 LOCA Outside Containment 0 ECA-2.1 Uncontrolled Depressurization of All Steam Generators 0 -
ECA-3.1 SGTR With Loss of Reactor Coolant-Subcooled Recovery Desire 0 '
ECA-3.2 SGTR with Loss of Reactor Coolant - Saturated Recovery Desired 0 ECA-3.3 SGTR Without Pressurizer Pressure Control 0
- F-0 Critical Safety Function Status Trees 0 FR-S.1 Response to Nuclear Power Generation /ATWS 0 FR-S.2 Response to Loss of Core Shutdown 0 FR-C .1 Response to Inadequate Core Cooling 0 FR-C.2 Response to Degraded Core Cooling 0 FR-C.3 Response to Saturated Core Conditions 0 FR-H.1 Response to Loss of Secondary Heat Sink 0 FR-H. 2 Pesponse to Steam Generator Overpressure 0 FR-H.3 Response to Steam Generator High Level 0 FR-H.4 Response to Loss of Normal Steam Release Capabilities 0 0502d/0005K 04/24/85
1> ...
TABLE OF CONTENTS (Continued)
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FR-H.5 Pesponse to Staan Generator Lew Level 0 FR-P.1 Pasponse to Imminent Pressurized Thermal Shcck Ccadition 0 FR-P.2 Response to Anticipa tad Pressurized Thermal Sheck Ccaditica 0 FR -Z.1 7espanse to Hich Centainmen t Pressure 0 FR -Z. 2 Response to Centainment Flooding 0 FR-2.3 Response to High Containment Radiation Level 0 FR-I.1 Response to High Pressurizer Level 0 FR-I.2 Response to Low Pressurizer Level 0 Fr-I.3 Response to Veids in Reactor Vessel 0 R -1 Personnel Injury or Illness (Radiologically Pelated) 14 and/or Overexposure R-2 Release of Airborne Radioactive Materials 5 R-3 Release of Radioactive Liquids 4 R-4 High Radiation (In Plant) 3 R-5 Radioactive Liquid Spill 3 R-6 Radiological Fire 8 R-7 Offsite Transportation Accidents 5 M-1 Employee Injury or Illness (Nonradiological) 12 M-2 Nonemployee Injury or Illness (Third Party) 10 M-3 Chlorine Release 5 M-4 Earthquake 8 M-5 Tsunani Warning 5 M-6 Nonradiological Fire 10 M-7 Oil Spill Isolation and Clean Up Procedure 7 M-8 Containment Emergency Personnel Hatch 0 M-9 Hazardous Waste Management Contingency Plan 1 M-10 Fire Protection of Safe Shutdown Equipment 3 G-1 Accident Classification and Emergency Plan Activa tion 5 G-2 Establishment of the On-Site Emergency Organization 6 G-2 S1 Dnergency Organization Call List Form 69-10297 1 G-3 Notification of Off-Site Organizations 5 G-4 Personnel Accountability and Assembly 6 i G-5 Evacuation of Nonessential Site Personnel 2 -
0 0502d/0005K 04/24/85
9GW3 Pacific Gas and Electric Company NUMBER EP M-7
- REVISION 7 4 OEnnTMENT CF NUOLEAP. PLANT CPERATIONS- ,
g c.As_o CANv0N 90wEA PLANT UNIT Nots) g 3.q,q PAGE 1 CF S 1 I i? i. t 1 AND 2 i
. . E.,EAGiriCf ?ROCEDLRE . , i e ., ~,. . ,
"'" v M, i
$U TITLE Oil SPILL ISCLATION AND CLEANUP TO
&cAOVED Y 'O '
PLANTMANAGEh DATE SCOPE This procedure outlines the steps requimd to isolate and clean up ,
small oil spills that could occur during tank truck loading and unloading or during other plant operations. It is absolutely necessary that no oil reaches Diablo Creek or the ocean from spills that might occur. This procedure and changes thereto requires PSRC review.
IMMEDIATE OPERATOR ACTION
( 1. Perform any operation which can be done rapidly to stop the spill.
- 2. Notify the Shift Foreman.
SUBSEQUENT ACTION
- 1. Notify the following Company personnel,
- a. For all occurrences:
l 1) Plant Manager.
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- 2) Plant Superintendent.
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- 3) Supervisor of Operations.
- 4) Supervisor of Chemistry and Radiation Protection,
- b. If any oil reaches the creek or the ocean:
- 1) Manager of huclear Plant Operations or his alternate.
C DC0100 IV
l NUMBER EP M-7 I OtASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 7 DATE 2/25/85 PAGE 2 0F 5 7i7,y OIL SPILL ISOLATION AND CLEANUP PROCEDURE 3 p
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l i :
' h;arvising tNelaar Ganarstion Enginaar ("trst n21 and i 2)
I Environmental Safety) or his alternate.
- 3) District Manager, Los Padres District, i
- 4) Onsite DER Marine Biologist,
- 5) PGandE Law Department.
f Mr. David J. 1111amson Company Phone '
Home Phone:
- 6) PGandE Public Information, Diablo Canyon, or San Luis Obispo Mr. Ron Weinber H e oe Pager: health Physics Freq j Ms. Missy Hobso Company Phone:
Home Phone: .
Pager: Health ysics Freq
- 2. Nctify the following non-Company agencies if any oil reaches the Creek or ocean.
- a. Federal National Response Center.
U.S. Coast Guard
' toll free) or Coast Guard ,
l San Francisco a tain of the Port ) -
Tel. -
or l Coast Guard Mont r tainofthePort)
Tel.
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OC0100 2V _.
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DiAsto CANYON power PLANT UNIT No(S) 1 AND 2 [0N DATE 2/25/85 PAGE 3 0F 5 rirts OIL SPILL ISOLATION AND CLEANUP PRCCEDURE
- b. California State Office of Emergency Services I i Sacramento (cir.g d:.n line) 1 cr e.
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- c. ' Envircr.r eW Protecticn Agency l Tel., <
l d. Californi tate Land Commission 4
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- lel.
- t. l State - Executive Officer California Regional Water Quality Centrol Board Central Ccast Region
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1;21 Laurel Lane ;
! San Luis Ooisco CA 94301 Tel. -
(Request ornia Office of Emergency Services to l notify in off-hours) j l f()TE: Ar ed of all such notifications should be kept on Fcrm
' Emergency Notification Record" or similar log. ,
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- 3. Emergency Actions for Spills During Leading and Unioading of Tank i T rucks . -l g: Operating Procedure K-8 requires that operating personnel be present during loading and unloading of tank trucks.
This individual will be responsible for taking necessary j l action should an oil spill occur during these operations.
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! a. Types of spflis that could be expected:
! 1) Transfer hose connection at truck or tank breaks loose and oil spills onto pavement.
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lC l DC0100 JV
- -_. - _-.- - . _ . - , = -
NUMBER EP M-7
- DIABLO CANYON POWE] PLANT UNIT NO(S) 1 AND 2 REVISION 7 DATE 2/25/85 PAGE 4 0F 5 r;rts CIL SPILL ISCLATION ANO CLEANUP PRCCECURE j
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- 2) Transfar hosa frcm tank truck orsaks or cracks and oil spills onto pavement.
- 3) Overfillirs of the diesel fuel oil tanks or the
- uxiliary bellar fuel oil tank, i
- 4) Oil drain from the transfer hose after being disconnected.
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- 5) A leak at the lube oil receiving connection occurs.
- b. Methods for oil spill containment and cleanup:
- 1) Sand bags and absorbents are stored near the diesel fuel cil storage tanks and the auxiliary boiler fuel oil storage tank for the purpose of diking and absorbing spilled oil.
- 2) Sand bags should be used to dike any significant oil spill which cculd flow to Diablo Creek or the ocear,.
Once the flow of oil has been stopped, absorbents should be used to clean up the oil. )
- 3) The absorbent should be used by itself only if the leak is of a small nature and a shallow film has been formed on the pavement. The absorbent can contain small spills by absorption.
- c. Action to be taken if truck is loading oil:
- 1) Shut off any transfer pump involved.
- 2) Isolate all connections to the transfer hose,
- d. Action to be taken if truck is unloading 011:
- 1) Close truck tanker drain valve.
- 2) If a leak occurs at the lube oil receiving connection.
the transfer pumps must also be shut down and the l - connection isolated from the lube oil storage tank.
- 4. Emergency Actions for Spill at Circulating Water Pump from i Bearing 011 Pot I
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DC0100 4y
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oiAsto CANYON POWE] PLANT UNIT NO(S) 1 AND 2 ((0N DATE 2/25/85
' PAGE 5 0F 5
( Tirts 0:L SPILL ISCLATION AC CLEANUP PROCEDURr I
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- 5. Emargency Actions for Major Oil Spill in an Area Snich Leeds to the Turt te Suilding Sump
- a. Periodically check the sump to verify that it is not overflowing.to the discharge side,
- b. Take samples periodically from the effluent of the oil water separator. If significant quantities of oil seem to be coming from the oil water separator, then redirect flow to the oil water separator holding tank.
- 6. Followup Reports
- a. Prepare a Nuclear Plant Problem Report (see Nuclear Plant Ad-inistrative Procedure C-12).
- b. Written notification to the Executive Officer of the RWQCE is required within 5 dcys of awareness of the ncn-compliance.
The written report will include the information required by the RWQCB Water Discharge Requirements. A copy of the report should be provided to the NRC, Region V to meet NRC reporting requirements.
- c. Any letters or reports issued outside the company should be reviewed by Mr. David Williamson of the PG&E Law Department.
REFERENCES
- 1. California Regional Water Quality control Board - Central Coast Region, Order No. 82-24, NPDES No. CA0003751, Waste Discharge Requirements for PGandE Diablo Canyon Nuclear Power Plant Units 1 and 2, San Luis Obispo County.
- 2. Diablo Canyon EPA 011 Spill Prevention Control and Countermeasure -
Plan, Rev. 2,3/25/80.
ATTACHMENT
- 1. Form 69-9221 " Emergency Notification Record"
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F-NUMBER EP G-4
= .' FGv4E Pacific Gas and Electric Company REyls10N 6 I O DEPARTMENT OF NUCLEAR PLANT OPERATCNS DATE 2/28/85 otAeto CANYON PCWER OLANT UNIT NC(S) 1.V!0 2 PAGE 1 0F 12 l
. .. ,, c E;1ERGE; ICY PROCEDURE l'
3 e b TITLE- PER30iiNEL ACCOU:iTABILITY AND A55EM5Ly 5 .'MPORThNT APPROVEo 72 d -O TO PLANT liAWcN DATE SAFET/
SCOPE This procedure describes the immediate emergency personnel assembly and accountability actions to be taken by all on-site personnel, security officers, contractors, and visitors in the event of a plant emergency. This procedure and changes thereto require PSRC review.
GENERAL In the event of an emergency situation in either Unit 1 or Unit 2, it is imperative that all personnel on-site are notified of the situation, their whereabouts identified for safety and security purposes, and that they g respond in a coordina,ted effort to the emergency.
In certain situations (e.g., if the emergency is security related),
personnel may be directed to respond in a manner other than what is stated in this procedure. In most situations, the primary notification means is the site emergency signal which alerts all personnel in the vicinity of the main plant building that an emergency exists.
- 1. The signal is produced by electronic warblers placed at numerous locations throughout the plant. It has a characteristic sound; a rapid rise in pitch followed by a slower drop. The sound cycle is repeated continuously for as long as the signal remains energized.
- 2. Flashing red lights have been provided in the containment and other plant areas where the background noise level may not pemit audible perception of the electronic warblers.
- 3. In an emergency situation, the alarm should sound for a minimum of one minute.
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DC0005 1XI ,,
OtA8LO CANYON POWER PLANT UNIT NOC 1 AND 2
$[0N .
DATE 2/28/85 PAGE 2 0F 12 TITLE PERSONNEL ACCOUNTABILITY AND ASSEMBLY i
a' j Actuation and raset of the signal shall ta as follows:
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- 1. Actuation of the plant emergency signal requires specific approval from the Shift Foreman.
- 2. The signal can be manu3lly actuated fron the operator's control console of either unit by manipulating the control switch to the ON position. Actuation can also be perfor ed from the hot shutdown panel of either unit by a control switch similar to the control console switch.
- 3. The alarm can be reset from the operator's console or the hot shutdown panel by proper operation of the control switch, or from the auxiliary relay panel EACC3 located at the 128 foot elevation on the Unit 1 equipment side.
Each site employee is assigned a designated assembly area (see Figure 1), and each aree is assigned a supervisor. The Designated Assembly Area Supervisor (DAAS) notifies the Security Shift Supervisor or General Construction Security who in turn notifies the Security Shift Supervisor, of personnel accountability. The Security Computer roll call is to be used as the primary method of accountability for personnel potentially within the plant area.
Personnel receive instructions on the assembly process as follows:
- 1. Site area personnel, visitor's and comon carriers will be logged in and out and provided with instructions at the Avila Gate guard post or plant site guard post, or the General Construction Security office.
- 2. Upon arrival and check-in at the security building, protected area visitors will receive instructions explaining what they are to do and where they are to go in the event of sounding of the Site Emergency Alarm.
INITIATING CON 0!TIONS The Shift Foreman declares that the plant is in an Alert, a Site Emergency, or a General Emergency status as defined in Emergency Procedure G-1, " Accident Classification and Emergency Plan Activation," or determines that personnel assembly and accountability is desirable, and activates the emergency signal.
DC0005 2XI
P, -
f* omaLO CANYON POWE] PLANT UNIT NO(S) 1 AND 2
$$0N DATE 2/28/85
. PAGE 3 0F 12 TiTts PERSONNEL ACCOUNTABILITY AND ASSEMBLY
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- .'ME0 DTI .%T*0.'iS
- 1. MandE c12nt persennel angaged ta critic 11 ocentiens er l
amargency recovery actions shall call tneir assignec as:3mbly Sr?Ss is $C0n 25 practical.
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l 2. Plant security personnel shall respono as follows:
- a. Those assigned to the Central Alarm Station, the Secondary i Alarm Station, the perimeter posts, and other fixed posts shall remain at their posts and await further instructions.
l b. Those on routine patrol shall continue their patrol unless otherwise instructed by the Security Shift Supervisor,
- c. All other permanent security force personnel shall call in to the Security Building for instructions, f
- 3. Plant personnel with potential imediate emergency response rolls will report to their assigned in plant assembly area Control Room, Access Control. Operational Support Center [0SC , and Technical Support Center (TSC)). Operations personne on shift
( and at the intake should call the shift foreman. All other personnel at the intake should report directly to their assembly areas. Personnel in the radiologically controlled area of the plant will initially assemble at the Radiological Access Control.
- 4. All other personnel in the protected area not involved in critical operations or emergency recovery shall proceed tn the Security Building exit and " badge out" and then proceed to their assembly area. Personnel outside the protected area will proceed directly to their assembly area.
g: It is the responsibility of each supervisor to know the general location of his subordinates at any time.
- 5. All PGandE General Construction, construction contract personnel and their visitors will evacuate the plant buildings and proceed to their assigned Assembly Areas via their assigned badge alleys.
Badges will be deposited on exit from the project.
DCC005 3XI .
1 AND 2 DIA84.0 CANYON POWE] Pt. ANT UNIT NOC h0N
- OATE 2/28/85 PAGE 4 0F 12 rira PERSONNEL ACCOUNTABILITY AND ASSEMBLY
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- 5. MancE DIR California Oe:artment of Fish anc Game eersenrei. :nd i trair vist'.:rs, will evacusts fr: tna ;! ant wf Hir:s :nt adjacent work areas and precsed i.mediataly to eneir assembly l area, the PGandE Stology Lab. 4 l
- 7. 370 visitcrs will ta ascertad to the Security 3uilding and 1 ,
i M :.".;:ac :: c a..; a ! .1 .1 a r t . .le:nn;asili;/ .vil' te :'aintair.ec by checking off those ascorted visitors against the visitor sign-in log maintained at the security office. Escorts themselves will then proceed to their own department or company assembly areas.
- 8. Visitors to General Construction and associated contractcrs will l be escorted to a visitor assembly ares and tha esecrts will then I pec eed to their own tssembly tres. Orivers will ;sek :neir vehicles and preceed on foot to tneir assigned area. I SU35ECUENT ACTIONS - UNIT 1 ONLY
- 1. The Security Shif t Supervisor will ensure that the " badge out" counter is manned for persons leaving the protected area.
- 2. The Designated Assembly Area Supervisor (DAAS) for each NPO Assembly Area will use the "8ADGE-0-MATIC" cceputer printout, :
posted on the wall of each Asserbly Area to check off the individuals pr25ent at the Asserbly Area or prepare a list of personnel present by name and badge rack number. When the head-count is complete:
a) Inside Protected Area: The OAAS for each Assembly Area insidetheprotectedarea(ControlRoom.TSC,ColdMachine Shop, and Radiological Access Control) shall inform the Security Shift.dt r normally uses the emergency conference line of the total head-count and the -
names of any incividuals not accounted for. When the
- required information has been passad on to the Security Shif t Supervisor, the OAAS should send the "BA0GE-0-MATIC
printout or list to the Security Shif t Supervisor by runner.
g ; The OAAS should maintain contact on the conference 1Ine at all times for subsequent instructions or to inform the Security Shift Supervisir of late. comers.
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OC0005 4XI
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NUMBER EP G-4
- OlASC CANYON POWED Pt. ANT UNIT NO(S) 1 AND 2 REVISION 6 i DATE 2/28/85 PAGE 5 0F 12 Tin.E. PERSONNEL ACCOUNTABILITY AND ASSEMBLY l
4 i !
6 Jf Ot.?.st:a erotac id Aral I's ic11 *.10 3 3'a i .ui" i t *de tijor .
e assambly point outside the protected area with a smaller grouo assembling at the Biolocy Lab. The Biology Lab OAAS Pail inform the Security *' Su:ervis:r (555) using confe-ence line extension f tha t:tal naad-count and L l
cha n: 2s of inditic'.als n:t 2 ::untad f: . ' e CAAS f.:e .
asen assignec classroem in tne Training Euilcin, snal!
report head-count infomation to the Training Building Comunications Coordinator (TBCC). The TBCC will relay accountab nfomation to the 555 via conference extensio d follow up by sending " Sad;e-0-Matic" lists to t S by runner. He will monitor the confe erce line and coo dinate infonati:n flow to the *AAS at each ali! ly classr :m.
NCE: Contact should be maintained en the conferee.ce line at all times for subsequent instructions or to infom the Security Shif t Supervisor of any late-comers.
- 3. The Securi_ty Shif t Supervisor ca onference lines by dialing: Inside Protected Area -
1 Outside Protected Area 4 The names of personnel unaccounted for will be detemined by the security shif t superviser by comparing the Security Computer Roll Call, or the badge racks against assembly area reports. The results will be reported to the Emergency Liaison Coordinator as soon as possible.
- 5. The Security Shift Supervisor shall notify the Emergency Liaison -
Coordinator in the TSC (or Control Room if in off nomal hours) of the site personnel accountability, complete the " Summary of Personnel Accountability and Assignments" log sheet (Form 69-10060), and forward the completed foms to,the Emergency Liaison Coordinator,
- 6. If there are 'any unaccounted for personnel, the following actions will be initiated:
- a. The Security Shif t Supervisnr will attempt to identify the last known location of the unaccounted persons from DAAS Reports and the Security Computer Roll Call, and provide this information to the Emergency Liaison Coordinator.
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0C0005 5XI -.
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otAet.O CANYON POWER PLANT UNIT NO(S)
ND 2 hh0N DATE 2/28/85 PAGE 6 0F 12 TiTtt PERSONNEL ACCOUNTABILITY AND ASSEMBLY 9
,e The Site Emrgency Ccordinator *.111 1sst3n t;preprista !
b.
( l ;se s aar.ei ta ;a r h,m a pl an t s n.P. . ' f r.11 ; f t s t un j
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} dictaces, the Emergency Radiolcgical .4 visor will provice a member of the Chemical and Radiation Protection Department far assistance. f
- c. The person le3 ding the plant search shs11 contact the Emergency Liaison Ccordinator when contact has been made i with the unaccounted for personnel.
- 7. Af ter persons assigned to other assembly areas have assembled at the Radiological Access Control, have been accounted for, and have been processed through the Contamination Control Point, the OAAS will contact the Emergency Liaison Coordinator and inform him of such. Persons assembled at Access Control may then leave the protected area via the Security Building and proceed to their designated assembly areas.
- 8. The Site Emergency Coordinator will order any necessary relocations or evacuations of assembly areas as appropriate. The CAAS of each area may relocate personnel if deemed necessary for personnel safety.
- 9. Personnel required for icrediate emergency response will be dispatched from the Operational Support Center (access control and cold machine shop asser.bly areas). Other personnel assembled may be relocated, on order of the Site Emergency Coordinator, to the Security Building ready room to await job assignment.
- 10. Personnel will be granted access to the plant only on the
} authorization of the $1te Emergency Coordinator.
- 11. Recordkeeping All records generated by the utilisation of this procedure for an exercise or emergency shall be forwarded the next working day to the Assistant Plant Manager / Support Services for review and retention. i i
- 1) Records generated from exercises will be categorized as non permanent and retained for a minimum of five years. l n
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OC0005 6XI e e
- . , otAsL9 CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/28/85
< PAGE 7 0F 12 TITLE- PERSONNEL ACCOUNTABILITY AhD ASSEMBLY
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. U .ie :r:s ganeca:4d !.o..t se:aai 4:3rg.incy 2 3n:2 ,iii ;e
' ' :stagorized as lifeti.re and placad into lifett.ra storag2 in accordance with procedure "Recuirements for Retention and 4 Ext 2nded Storage of C; era:f:n ;hua Ac:ivity Racaeus ( A; .
j E-151)."
Ass ssLY n EAs
! The first available person listed in each group below is designated as bilio f r Onnel theeach at prirary assembi DAAS to be responsible for the accounta$diai Using the conference lines, .
or rormal numbe r runner, he shall infom tTe Security Shift Su:ervisor of the sta us of his areas as s en as practicable. I
- 1. Control Roon Pha
- a. Shift Foreman--interim Site Erergency Coordinator
- b. Assistant Plant Manager / Plant Sucerintendent
- c. Operators, Control Technicians, STAS, Clerks. and others on shift
- d. Resident NRC Inspector (designated) f 2. TechnicalSupportCenteri7 hone
- a. Training Manager (E ergency Liaison Coordinator)
- b. Operator Training Instructors (Emergency Liaison Assistants)
- c. Plant Manager -long-tenn Site Emergency Coordinator
- d. Materials and Project Coordination Manager
- e. Technical Services Manager (Emergency Evaluation and Recovery Coordinator)
- f. Engineering Manager i
- g. Operations Manager (Emergency Operations Advisor) .
- h. Senior Power Production Engineer (Nuclear)--3 I i 1. Senior Power Production Engineer (Operations)
J. Regulatory Compliance Supervisor '
- k. Resident NRC Inspector (designated)
- 1. CARP Engineer (designated)
- m. Security Supervisor
- n. Chemistry and Radiation Protection Manager (Emergency RadiologicalAdvisor)
- o. Senior Instrument and Controls Supervisor
- p. Connunication Technician
- q. G.C. Resident Startup Engineer
- r. C&RP Systems Analysts (TSC EARS Operators)
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DC0005 7XI =- C
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ciAm.0 CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 6 -
DATE 2/28/85 PAGE 8 0F 12 TITLE PERSONNEL ACCOUNTABILITY AND ASSEMBLY
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- 3. Cold vachine Shop Ph:r ,
- a. Emergency Safety supervisor
- b. Maintenance Manager
- . Mainterarca En3irtars (dasignatad)
- d. Fire Marshal I a. Paintecance Fir? Brigade Cactains
- f. Maintenance Fica 3rigade i l
4 Access Control hone
- a. Senior Chemistry and Radiation Protection Engineer (designated)
- b. Ch mistry and Radiation Protection Engineers (designated)
- c. CDP F: eman (:esi;cated)
- d. Chemistry and Radiation Protection Technicians (designated)
- e. All other personnel in the controlled areas
- 5. SecurftyBuilding[ Phone
- a. Security Shif t Supervisor
- b. Security personnel not on patrol '
- c. New NPO employees not yet assigned a pernanent assembly area * )
l d. NPO visitors
- 6. TrainingSuildingRoca107{Pho l a. General Mechanical Foreman
- b. General Electrical Foreman
- c. Mechanical, Electrical, and !&C Foremen and workers l d. Work Planning personnel
- e. Warehousemen
- 7. TrainingBuildingRoom109[Pho g
- a. Operations Shift Foreman (Administrative)
- b. NPO Operators not on shift
- c. C&RP Technicians not assigned to Access Control
- d. CARP contractors I
DC0005 8XI J c 4
DIA$,0 CANYON POWER PLANT UNIT %$) 1 AND 2 ON DATE 2/28/85 PAGE 9 0F 12 TTi.s PERSONNEL ACCOUNTABILITY AND ASSEMBLY I l !
h!.Q;3miia;tc.aiti!;- ' *
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- a. Nuclear Engineers
, . 5. ? mar Pr:S ction Engi.caers .
Comouter Engineers and Soecialists i I c. '
! I d. Segulatory Conpliance '
' Generai Offica personnel e.
- f. Coast Valleys personnel
- g. NRC
- h. Occeent Control
- i. Trainers
- 9. Training Building Room 122 Phoc l
- 3. OC SL;ervis0r and [C ;es09.el
- b. CA Sucervisor and QA personnel
- c. Westinpouse
- d. Maintenance, QC, and !&C contractors
- e. College Co-op and sum er students
- 10. Training Building Room 123 Phon
- a. Office Supervisor
( D. Assistant Office Su:ervisor
- c. Perscenel Representatives
- d. Budaet Analyst
- e. EmpIoyeeCounselor
- f. Personnel and General Services Supervisor
- g. Clerical personnel and janitors
- 11. TrainingBuildingRoom222[ Phon \
- a. Assistant Plant Manager / Support Services
- b. SeniorPowerProductionEngineer(EmergencyPlanning)
- c. Interim EOF Staff
- 12. BiologyLab_iPhon
- a. DER Nuclear Section Supervisor
- b. Biology Lab staff, consultants and visitors E In off nomal working hours, the most senior supervisor present will assume the functions of the OAAS.
(
DC0005 9XI
- O it _-_ ___________ _
otAeLO C4NYON POWER PLANT UNIT NOC *
- gy DATE
- 2/28/85 PAGE 10 0F 12 TITLE PERSONNEL ACLOUNTABILITY AND ASSEMBLY I
4 PGandE GI'II .'L CONSTRUCTIC?i tto C0!:TUC G15155EMLY MEM I
! l :
Construction personnel snall be accoun:ed for oy controlli,g ene l
individual's project I.O. photo badge. Enroute to their assembly areas, ra:h employee shall deposit their I.D. bad;2 at the proper allay of entry. Each contractor will assign a staff member to report to the badge alley to assist in accounting for their personnel and for resolving any discrecancies. Figure 2 shows the assembly area locations for Unit 2 construction personnel. The assembly area supervisor will be the Senior Representative of each group on site.
I Group Area Plant Thorpe A-1 Bechtel A-1 Pullman Pcwer Products A-2 H.P. Foley and their subcontractors B PGandE General Construction Engineering Services C Quality Control Group C Mechanical Grcup C Start-Up Group C i GO Engineering Group C
! Electrical Group C Group Area I Civil Group C Administration Group C l Station Construction Crew C Line Dept./ Paint Crews C i Cal-Poly Foundation C Kaiser /Lockheed/EcoMar/ Terra C Telos C Waltek C Thermon C Towl11 Inc./Ames & Assoc. C Barnes Construction Co. E Visitors and other personnel not listed above D 4
DC0005 10X!
- n . .
0As'LO CANYON POWE] PLANT UNIT NO(S) 1 AND 2
., fSf0N 6 DATE 2/28/85
' PAGE 11 0F 12 TITLE PERSONNEL ACCOUNTABILITY AND ASSEMBLY I e i MISCELLA:EOUS i t
If an emergency occurs during the evening or on a weekend or holiday, the same areas used during workit g hours shall be utili:ed. However.
' cersonnel wno are off-site at the time of the emergency and are notified to report to the site to as:,ist in recovery operations should be instructed as to where they should report when notified. If no instructions are given, personnel reporting to the site shall proceed imediately to the Security Building Ready Room.
ATTACHMENTS
- 1. Fom No. 69-10059, Individual Accountability Sheet
- 2. Form No. 69-10060, Summary of Personnel Accountability and Assignments.
- 3. Diablo Canyon Project, Project Instruction PI-39, Rev.1
" Personnel Accountability & Site Evacuation During a Site (mergency" FIGURES
- 1. Assembly Area Locations.
( $UPPORTING PROCEDURES G-1, " Accident Classification and Emergency Plan Activation" G-5, " Evacuation of Non-essential Site Personnel" S
DC0005 11X1
NUMBER EP G-4 DIABI.O CANYON POWE7 PLANT UNIT NO(S) 1 AND 2 ' '
REVISION 6 DATE 2/28/85 PAGE 12 0F 12 TITLE: PERSONNEL ACCOUNTABILITY AND ASSEMBLY
)
I t FIGURE 1 ASSEMBLY AREA LOCATIONS (CUTSIDE PROTECTED AREA)
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I DC0005 12XI
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. 69-10059 4/82 (50) Sheet 1 of 1 I PACIFIC GAS AND ELECTRIC COMPAN, i
,. DEPARTMENT OF NUCLEAR PLANT OPERATIONS l DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 :
(~ INDIVICUAL ACCOUNTASIIITY SHEET DATE AREA ACCCUNTABILITY SUPERVISOR NAME BADGE RACK # REMARKS (NOTE ANY INJURIES) i k
t 6
DC0005 13VI!!
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Page 1 of 2
- 69-10060 10/84 (50)
DEPARTMENT OF NUCLEAR PLANT OPERATIONS
> DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 I
SUPNARY OF PE250NNEL ACCOUNTABILITY AND ASSIGNMINTS OArg f
1 SY INITIAL PERSONNEL ACCOUNTA3!LITY CONTROL In Charge Report In At Hours No. Of People Accounted For L j Yes [ ] No Missing Injured ,
I Remarks TECHNICAL In Charge Report in At Hours SUPPORT Ho. Of People Accounted For L j fes [ ] No r
Remarks
( In Charge Recort In At Hours COLO MACHINE No. Of People Accounted For L j res [ ] No
~
e Remarks In Charge Report In At Hours ACCESS
' No. Of People AccountedForLjYes[]No Missing Injured Remarks Report In At Hours BIOLOGY In Charge B -
No. Of People Accounted For L j Yes [ ] No Missing Injured Remarks l
C DC0005 14y!!!
___ _ _ - =_
69-10060 10/84 (50) Page 2 ef 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05.1 AND 2
SUMMARY
OF PERSONNEL ACCOUNTABILITY AND ASSIGNMENTS
]
F OATE INITIAL PERSON.iEL ACCOUNTABILITY u.- :q t ry .
c People fccoun ed for L j Yes [ No Injured Remarks T:AINING In Charge Report In At Hours
="ILDING No. Of People Accounted For L j Yes [ ] No ure!
Remarks
' t TION o, eepje jc'ou e For L j res [ fNo e ark i
VISITORS In Charge Report In At Hours
& No. Of People Accounted For L j Yes [ ] No CONTRACTORS Missing e
GENERAL In Charge Report In At Hours CONSTRUCTION No. Of People Accounted For L j Yes [ ] No n
a Remarks
)
DC0005 15VI!!
,. NUMBERS, pg.39 A A klVt'%kt M M A If"#% "T*
DlMwL.bA s Qt r Vnti 4 Vil I 5 T V tJ E-V a REUISION: 1 UNCONTROLLED COPY '
EXPlRATION DATE CMM
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APPROVED: '
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n constnetion uanstu nei 1.0 SCOPE 1.1 This Instruction describes the Plant Emergency Signal and the immediate action to be taken by P.G.&E. Construction and .
Service Personnel, Project Tean and Contractor Personnel (including Job Shoppers and subcontractors) and their visitors and service representatives, for an orderly evacuation of the site in response to the Emergency Signal and accountability of all personnel during such an evacuation.
(- 2.0 RESPONS B TtTTY 2.1 While construction activities remain in progress, the Field Construction Manager or his designated alternate (Contact GC Security for assigned alternate) have responsibilities and authority over the above personnel, General Construction visitors, and Security Force personnel assigned to construction activities.
In this capacity, he or his alternate will be designated as the Construction Force Assembly Coordinator with the following -
i responsibilities:
2.1.1 Communicating with the Site Emergency Coordinator to determine the conditions of any Site Emergency. This communication is normally with the Unit I Security Buil-ding through the Shift Security Supervisor.
2.1.2 Transmitting information to Contractors and other construction force related personnel.
2.1 3 Construction force assembly and personnel accountability at the site in the event of an emergency and prior to any site evacuation.
2.1.4 Evacuation of construction force personnel from the site as may be directed by the Site Emergency Coordinator in (r cooperation with the Evacuation Coordinator.
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DIABLO CANYON PROJECT NUMBER 9I-39 .
REVISION 1 Personnel Accountability & Site Evacuation DATE 2/24/84 TITLE During A site Emergency PAGE 2 OF 8 I
i i 2.1.5 frovica raquirad :.raffic conteci =cacuras. .
5 I 2,;,5 The deci:1cn te ovscuata, the type of ovacua-lon (i= mediately, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />), tha evacuatien route (North or South), the off site assembly aras, and the :sthed (by v3hicle or foot) vill be cads z by the Sits Energency Coordinator and conycyed to the i j Constructica Forca assembly C0cedicatcr. 4 2.2 heh contracter is responsible for the accountability of all their employees working at the site. An accountability program must be implenented by each Contractor to enable the Field l
Construction Manager / Construction Force Assembly Coordinator to j know how many construction personnel are on site at any given time, and their general location on the Project.
l 23 Subcontractors will be responsible for implementing their main Contractor's accountability program. Each Subcontractor will l
be responsible for the accountability of their employees.
I l
! 2.4 Rach Preiset Team Decartment Head is responsible for the '
( accountability of all their subordinates. An accountability program must be implenented to enable each supervisor to know how many of their people are on site at any given time and their general location. Each employee must be indoctrinated on his/her required response to this procedure and details of what is done in the event the Emergency Signal is activated.
f l
i l
l 30 APPLICATION _
l l 31 This Instruction applies to all construction force-related -
personnel working in all areas and elevations of the Plant Site and Project.
4.0 PROCEDURE 4.1 EM'RCENCI sir E 4.1.1 Identification 41.1.1 'Ibe Sinnal is produced by electronic warblers i
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., DIABLO CANYON PROJECT NUMBER pl.39 REVISION i Personnel Accountability & Site Evacuation DATE 2/24/84 TITLE During A Site E=ergency PAGE 3 CF 8
( : I
$ placed at numerous 1ccations throu;nout the ple, , j n h a . :hrsetori: tie neund '< ien 12 a rapid pine ,
in pitch folicwed by a slower drop. De sound cycle is repeated continuously for 13 long 9s the signal rc:ains one.si:ed.
'l 4.1.1. 2 M M * -- "3 have been providad in the l
Contain=ent and other high noise reas since the background noise level would not permit audible perception of the electronic warblers.
4.1.1 3 under an emergency situation the alara should sound for a minimum of one minute.
4.1.2 Testing The Emergency Signal will be actuated for test purposes every Friday at 12:10 p.m. for a period of approximately ten (10) seconds.
4.2 RESPONSE 4.2.1 Preinet Team Personnel. Construction Contractors and
( Subcontractors, and other construction force related nersonnel will evacuate from the plant buildings and adjacent work areas, exit through their M spective assigned badge alleys and proceed insediately to their assigned assembly areas, in response to the Energency Signsl. Assigned alleys are those entrances where the site photo badge is kept for each category of worker. A listing of all ostegories of personnel governed by this Instruction, and assigned assembly areas is found in Appendix A ( Attachment 6.1). A map showing the location of assembly areas is shown on Appendix B ( Attachment 6.2).
Routes to be taken to assembly areas is shown on Appendix C (Attachment 6 3).
4.2.2 111 Unf t I eenstruction nernean=1 will exit through the plant security buildings leaving their Unit I badges but not their site photo I.D. badges. Employees will proceed to their assigned badge alley leaving their site photo I.D. badge, and then to their assigned assembly area. All personnel vill be accounted for by issuance and control of the individual site photo I.D. badges. Each contractor will assign a staff member to report to the badge alley to assist in the accounting of their personnel and resolu-tion of any discrepancies.
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DIABLO CANYON PROJECT NUMBER pl.39 . .
REVISION t DATE 2/24/84 TITLE Personnel Accountability & Site Evacuation PAGE 4 OF 8 I Durtne A Site Emercanev
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Iscertad visitors will res;cnd to the signal snd will .
i proceed along with their escorts tc their specifiad l visitor assembly area. Accountability of visitors will 1
, be maintained by checking off those esecreed visiters at the assembly areas against the visitor sign-in-log main-tained at the security office. Escorts themselves will proceed to their assigned assembly areas af ter escorting their visitors to the visitor assembly area.
4.2.4 Unascerted Visitors. Ralescersons. Vender & Manuf acturers' Reeresentatives. Local Deliveries The above persons will also report to their assigned assembly area. Upon arrival and check in at the Project, these persons will be provided with a map and written instruc-tions explaining what they are to do and where they are to go in the event of a site evacuation (refer to Appen-dix D, Attachment 6.4). Accountability will be main-tained by checking off unescorted visitors at the assembly areas against the visitor sign-in-log maintained at the )
security office. Persons with vehicles will leave them parked and proceed on foot to their designated asse=bly areas.
4.2 5 c= on Carriens Common carriers will be handled in the same manner as unescorted visitors with the exception that they will be logged in and out and provided with a map and instructions at the plantaite guard post rather than the security office.
Drivers will leave their vehicles and proceed on foot to ,
their designated assembly area.
4.2.6 c==n Personnel. Meehanie services. communientions Personnel and Others working in the switch yards, clarifier, camp & back project areas will report directly to their appropriate assembly area. Vehicles carrying persons from these outlying areas may be driven to the upper lot road area, via the camp road, and parked.
These persons will check in at the upper lot guard station upon arrival. The number of vehicles used to move persons from outlying areas to the assembly areas should be kept at a minimum.
I
DIABLO CANYON PROJECT NUMBER PI-39
,}~ ,
REVISION 1 Personnel Accountability & Site Evacuation O 2/2'/0' TITLE Luring a Site Emergency PAGE 5 OF s t 1 i '
- l i
3 I II.2.7 Lim Cr rr? (ef*-Sit? f' c. ud "t e-- i s t i "o
- Brined S Diibio em v c: Crews working on sita er en tcwer line work Zast of the .sita 4ho gal. ad accass :o : heir verk througn tne site) vill check in sod report their j persennel and verk locatic: to the u;;3r let read suard station daily. These crews will stay in the area of their work.
4.2.8 P N ka' ten G.C. Security Guards In as auch as possible G.C. Pinkerton Security personnel will remain at their posts. Mobile & Building Foot Patrols and the Sergeant, will report to the Sergeant's/
Captain's Trailer which will serve as the G.C. Security command post. The G.C. Security Office will i==ediately, upon the initiation of the signal, contact the G.C.
Force Captain and relay information to the Shift Security Supervisor on the specific location of the guards remainir4 on post to determine the necessity of immediate evacuation of these posts. Guards on post to be included in the evacuation will be notified by radio and ordered to their Sergeant's Trailer for reassignment. Parking lot guards
' ( - remaining on post will limit access to personal vehicles until instructions for orderly evacuation are received.
The Security Guard Captain is responsible for the accountability of all guards assigned to construction activities and will report directly to the Field Construc-truction Manager or his designate.
4.2.9 Instructions On Energencv: Upon arrival at assigned assembly areas, all personnel will receive further ,
instructions on the nature of the emergency. As soon as l
possible after the signal sounding, an accurate tally .
l must be available to the Field Construction Manager or his designated alternate indicating missing personnel and their last known location on the Project.
43 PERSONNEL ACCOUNTABILITY 4 31 General All personnel will be accounted for by the issuance and control of the individual's Project photo I.D. badge.
I.D. badges will be issued and controlled at one of the l following designated Project " Points of gntry":
4 31.1 Administration Buildina Guard Station: General l (, ,
Construction Project Team (All employees associated o
, _ _ - - ~ - _ _ . , . _ _ _ _ _ . _ . _ , , - _ . .
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DIABLO CANYON PROJECT NUMBER PI-39 *
- REVISION 1 DATE 2/24/84 Pusonnel Accountability & Site Evacuation TITLE ny em A m. E-.rme,, p GE
. < 5 ch :epts. of ..eninistration, nsetrical, 1 i
thchanieri, Civtt, Startu?, Instr":?nt ni:n, !
C2cercl Grvices, Quality Control, Cc:=unications,
- Cc-site Engineering, Project Control), Pullnan (Magnaflux), Solect H.P. Foley, assigr.ed job sho
.cerscenel (Pace Eng. , Cods III, Cataract, 'Jaltak, ?
l Wisco, Innova, Etc.), y.rystal Kitan personnel.
4 3 1.2 Lower tot Baden A11.v cates: Alleys #1 thru #9 and #11 thru #14 assigned to personnel of H.P.
Foley Co. , Pullman Power Products Co. , Plant
' thorpe, Bechtel G.P.M.A.
4.3 1.3 lamgGt Badme 111ev Ste #10: Assigned to mis-cellaneous PTGC and Contractor personnel.
4 3 1.4 Uneer Lot Read Station: P.G.&E. camp / warehouse personnel, Hechanic Services group.
4.3 1 5 Plantsite Gyard Station: (Lower Lot Entrance)
Assigned management of: H.P. Foley, Pullman Power, Plant Thorpe, Lundeen, Barnes Construction, and select amployees of S.L.O. Garbage Co., Able Main- ,
tenance, Western Santitation, Santa Maria Vending, )
Coperheat, P.T.&T. Co. , Bechtel G-bec, Zerox, IBM, R.P. Richards, S & M Sprinkler, Bisco, Santa Cruz Research Group.
4.4 Badge Control 4.4.1 At the beginning of a shift personnel will pick up their photo badges at the appropriate Guard Station where they ~
normally enter the Project. Immediately after shift change each of the guards at the controlling entry ,
stations will determine the status of the employees covered by their posts.
4.4.2 On normal work days, the day shift guards will fill out a form listing the employees NOT ON SITE, by name & badge number, swing shift guards will do likewise for their shift. On other than normal work days, (holidays, weekends, other than normal work hours) guards will fill out a form listing the employees CN SITE, by name & badge number. These listings will be kept current at all times during the shifts by additions or deletions of those entering or leaving the Project, and will be supplied to the Field Construction Manager or his designate when requirec .
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DIABLO CANYON PROJECT NUMBER PI-39 v "
REVISION 1 Personnel Accountability & Site Evacuation DATE 2/24/84 1 i
i lTLE Durinz A Site E=ergency PAGE 7 0F a i j
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i l.4 3 23r0cnr.31 LJaVing thd Jit3 Vill badge QuC 4nd 3.10,< in 40 4 j
the Guard Post where they nor: ally enter the Project, l i except personnel (such is Station Constructics, Line i l Depc. , and Contractor read scrh creve) 13avin6 *"* **
- a j in Cc:pacy Vehicles for off site work vho will leave '
l 1 their badses with the guards at the plant:ita antrance to l tne icwer packin6 lot, and retrieve them from there upon their return.
4.5 evneuntion 4.5.1 Any evacuation cf the Diablo Canyon Site will begin fra the EMERnFMCY AERFMBLY ARPAM as shown in the Diablo Canyon Power Plant Emergency Procedure G-4 " Personnel Accountability and Assembly". All personnel covered by this procedure are instructed to proceed to these areas on foot upon activation of the Emergency Signal and to wait there for further instructions.
4.5.2 The Construction Force Assembly Coordinator will implement the Site Emergency Coordinator's evacuation
(- decision and see that various groups are accounted for -
and released sequentiklly and in an orderly manner so that traffic congestion is minimized and traffic flows smoothly away from the site.
4.5 3 G.C. security personnel will assist by directing traffic out of the lots and controlling key intersections during the evacuation as directed by the Evacuation Coordinator.
4.5.4 All evacuations whether by vehicle or on foot, will be led by security personnel. Accompanying each assembly .
area group will be a person who will be in charge of personnel accountability and release at the off site assembly areas. Security personnel will be radio i
equipped and in contact with the Evacuation Coordinator l
and the Site Emergency Coordinator.
4.5.5 Once off the site, the evacuation will be led to the off site assembly area by a Sheriff's vehicle (if available).
One of the lead guards will transfer to the vehicle with his portable radio and ride to the off site assembly area in the Sheriff's vehicle so that continuous communications are maintained.
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DIABLO CANYON PROJECT NUMBER Pl-39 - -
REVISION 1 DATE 2/24/84 IIIb Personnel Accountability & Site Evacuation Durine A Site Emereency PAGE 8 OF 8 i
}
} t.5.6 In tha met of 2n mcuation on feet, Inarda er ?.9.u. l 4 Mr?mrel with r? dies rd fir:t ?.11 hi : rill 5:
intarsparae: at appropriace in;erval.s in che group to maintain cc:::=unication and provide first aid, if f nocassary.
l
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5.0 REFERENCES
i 5.1 Depart =ent of Nuclear Plant Operations E=ergency Precedure G-4 l " Personnel Accountability and Assembly".
i 5.2 Department of Nuclear Plant Operations Emergency Procedure G-5.
! " Evacuation of Nonessential Site Personnel".
6.0 ATTACHMENTS
6.1 Appendix-A
List of Assigned Assembly Areas
)
6.2 . Appendix-B: Location Map of Assembly Areas
6.3 Appendix-C
Maps of Routes to Assembly Areas
6.4 Appendix-D
Visitor Information on Site Emergencies P9 3
I I
i l
- ..- .. . .. . . ASSIGNID ASSEMBLY AREAS "A" AREA
_A_l 7
Sechtel (G-Bec) -
-Flantherpe
_A_2 Pullman Power Freducts and their subcentractors "S" ARIA H. P. Foley and their subcontractors "C" AREA "C" AREA P4TJ General Construction Contractors General Services (PT-GC) Waltek Quality Control Group (PT-GC) Cataract Mechanical Group (PT-GC) Innova Startup Group (PT-GC) Wisco OnSite Engineering Group (OPEG) Code-3 Instrumentation Group (PT-GC) Pace Electrical Group ((PT-GC) Bisco Civil Group (PT-GC) Krystal Klean'
( Civil-Hydro Group (PT-GC) G. O. Personnel Ad=inistration Grcup (PT-GC) assigned to project Station Construction /Line Dept.
"D" AREA _"D" AREA
~ Construction Force Assembly Visitors (Escorted and Unesecrted)
Coordinator Common Carriers PT-GC Management Vendors and Service Companies FT-PC Management -
~
"E" ARIA Barnes Construction Co.
PAGE 1 0F 1 DATE 1-20-84
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UPPER PARKING :
AREA RANGE f GUARD SHACK N} % e __
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AREAS FOR CONTRACTOR PERSOtafJEL 1 PAGE I of 2 REY.O I/2_Of'04 i i
m APP' NDIX C -
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UPPER PARKING LOT -
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ARROWS INDICATE ROUTE TO ASSEMBLY AREAS FOR P.T.G.C.( ALL Gf(OUPS 's.O.P.E.G.,
CONTRACT PERSONNEL ( JOB SHOP PERSONNEL ) WORKING WITil PROJf CT TEAM AND ALL OTHERS ASSIGNED TO AREA "C" PAGE 2 eL2 REV.O I/2Of(f
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3 v's??*.? m ee' m cN V01cese to Disolo Canyon -
A.s a visitor to this site, there are several rules and procedures which you should be tware of. Ihey have been designed for ve n**tv and must be strictly cenplied with.
- 1. If you have been issued a hard hat, wear it in all hard hat areas.
- 2. The visitor badge issued to you is to be worn in plain view at all times. (In certain areas on the site you may be asked to surrender this badge; however, you will be provided with another badge in exchange.)
- 3. Persons cleared to enter the operating areas of the plant will be provided with additional instructions governing their actions while in these locations, prior to entry.
Emerrencias
( .Should a situation arise which requires the evacuation of this site, the Plant Emergency Signal will be activated. The Signal is produced by electronic varblers placed at tunerous locations throughout the plant. It has a characteristic sound which is a rapid rise in pitch followed by a slower drop. The sound cycle is repeated continuously for as
! 1:ng as r.he signal remains energized.
Flashing red lights have been provided in the Containment since the background noise level l would not permit audible perception of the electronic warblers.
L -
Under an emergency situation the alarm should sound for a miniaua of one minute, i
i ,
The Energency Signal will be actuated for test purposes every Friday at 12:10 p.m. for a period of approximately ten (10) seconds.
Should the Signal be activated during your visit other than at the test time, proceed on foot to the area merked 'D' on the map provided you and wait for further instructions.
nnescorted visitors. If uncertain as to the location of Assembly Area 'D' ask any Security Officer.
Escorted Visitors will be taken to Assembly Area 'D' by their escort.
( PAGE 1 Oy 2 REv. 4 1/20/84 1
CAREHOUSE -
SHOCTING RANGE g h.%
g BATCH MNT g ROAD SWITCHYARD ACCES /
2%e\, @ * / L M LANT sECun Ty A ENLARGED a r. o c .. AREA DISCHAR #C
44 1 PACIFIC OCEAN INTAK$
COVE gp'TGN 9 SHOOTING \C RANGE C p; I
go A**
I i WAREHOUSE u- a ~l , , .
UPPER "~ _
PARKING C A2 LOT 0 ,
ooo m e So%
LOT A A!j pgggG to SG .
? 1 _
p4Ge 1 Rev.4 care l'72 d~/e4 j . . .. . _.
PGandE Letter No.: DCL-85-165 CURRENT S4ERGENCY PLAN UtPLEMENTING PRCCEDL'RES TABLE CF CONTENTS Volume 38 TITLE ,
REV OR-1 Offsite Support & Assistance 4
'0R-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 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 4 EF-651 Transfer of EARAUT Control 1
. EF-8 EARS Operating Procedures for TSC-CC HP-1000 Station 0 RB-1 Personnel Dosimetry 1 RB-2 Emergency Exposure Guides 1 RB-3 Stable Iodine Thyroid Blocking ..
1 RB-4 Access to a Establishment of Controlled Areas Under Emergency Conditions 2 RB-5 Personnel Cecontamination 2 RB-6 Area & Equipment Decontamination 2 RB-7 Emergency On-Site Radiological Environmental Monitoring 3 RB-8 Emergency Off-Site Radiological Environmental Monitoring 4 RB-9 Calculation of Release Rate & Integrated Release 3 RB-10 Protective Action Guidelines 1 RB-ll Emergency Off-Site Dose Calculations 4 RB-12 Mid and $gh Range Plant Vent _ Radiation Monitors 1 RB-13 Improved In-Plant Air Sampling for Radiof odines 1 PB-14 Core Damage Assessment Procedure 1 ,
RB-15 Sentry Post Accident Sampiing System (SPASS)
-Initial . Sampling Fxercise After An Accident 1 RB-15A SPASS Initial Actions During An Emergency 3 RB-158 SPASS Reactor Coolant Sampling (Stripped-Gas and Diluted RCS) 2 0502d/0005K- 04/24/85 r 5
TITLE REY RB-15C SPASS Containment Air Sampling. 2 RB-150 SPASS Gas Chromatographic Hydrogen Analysis 2 RB-LEE SPASS RCS Liquid and Gas Sample Handling ?
RS-ISF SPASS Cata Analysis 1 ES-ISG SPAS 3 ICN Chroma tograchic Chicrida analysis 1 R3 -l SH SPASS pH/Ccnductivity/Ci35cived Cxygen 1 i.-15I J,2AS5 Saa:le Stcrage and 01sposal 0 33-16 SPASS Subsequent Sampling 0 RS-16A SPASS Initial Actions During An Emergency
(!bt Intended to b'eet The 3-Heur Time Limit) 2 P3-1681 SPA 55 Diluted Liquid Sampling Frem Reactor Coolant (Not Intanded to t'eet The 3-Hour Time Limit) 1 R8-1682 SPASS Undiluted Liquid Sampling Frca Reactor Coolant (Not Intended to Meet The 3-Hour Time Limit) 1 RB-1683 SPXTS Reactor Coolant Stripped Gas Sampling (Not Intended to Meet The 3-Hour Time Limit) 1 RB-1684 SPIIS Diluted Liquid Sampling From Radwaste (Not Intended to Meet The 3-Hour Time Limit) 2 RB-1685 SPXYS undiluted Liquid Sampling From Radwaste (Not Intended to Meet The 3-Hour Time Limit) 2 RB-16C SPXTS Containment Air Sampling (htt Intended to Meet the 3-Hour Time Limit) 1 RB-16D SPITS Gas Chromatographic Hydrogen Analysis (Not Intended to Meet the 3-Heur Time Limit) 1 RB-16E SPXTS Liquid and Gas Sample Handling (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16F SPXTS Data Analysis (Not Intended to Meet The 3-Hour Time Limit) 0 RB-16G SPAYS Ion Chromatographic Chloride Analysis (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16H SPXTS Ph/ Conductivity Dissolved Oxygen (Not Intended to Meet The 3-Hour Time Limit) 1 RB-161 SPXTS Undiluted Containment Air Sampling (Not Intended to Meet the 3-Hour Time Limit) 0 RB-16J SPXTS Sample Storage and Disposal (Not Intended to Meet The 3-Hour Time Limit) 0 O
G s
0502d/0005K 04/24/85 h
5
. NUMBER EP EF-6
-m Pacific Gas and Electric Company REVISION 4 e c W .i.
', 1 0F 63 PAGE <
1m:
j fl[
[Q;[,CEPARTMENT emne c-eesa ..u usa nce OF NUCLEAR PLANT EMERGENCY PROCEDU:E o m ATING ;;ccrou u S rcr. EA:s 93: C t l g;.
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T 6 TbA-, 44 f5' To i CATE SA,T_:Ty P!.AhiMANAGEg ,
SCOPE This procedure provides startup instructions and operating flow diagrams for any HP-9845C station capable of functioning as a controlling station for the Emergency Assessment and Response System (EARS). These EARS stations includethe Control Room (CR) Technical Support Center (TSC), and Emergency Operations Facility (EOF).
In addition a discussion of the terminology used, and a brief overview of sone of the support sof tware and data file contents and structu e used in the EARS is included.
Startup and operating instructions for the EARS TSC HP-1000F computer are contained in procedure EP EF-8.
( This procedure ard changes thereto requires PSRC review.
CONTENTS 2
DISCUSSION . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2 PROCEDURE ............................
- 1. EARS Hardware at Controlling Stations .. . .....2 ,
- 2. Start-up. Procedures .................3 3
- 3. Shut-down Procedures . . . . . . . . . . . . . . . . . .
3 4 Power Failure .....................
- 5. EARS Software and Flow Diagrams ............A 4
- a. STATUS ......................
- b. EARAUT (Controller) . . . . . . . . . . . . . . . . 9
- c. EARAUT (Non-Controller) . . . . . . . . . . . . . 2)
- d. EARMAff .....................29 DC0009 IIV
otA8L@ CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 10/22/84 PAGE 2 0F 63 OPERATING PROCEDURES FOR EARS 9845C CONTROLLING STATIONS
- 2. EMCC / EAR rce . . . . . . . . . . . . . . . . . . 39
- 6. Ter-s Cem on To EARAUT and EARMAN ..........55
- 7. EARS Support Software for HP-9845C . . . . . . . . . . 59
- 8. Re fe re n c e s . . . . . . . . . . . . . . . . . . . . . . 51 APPENDIX A: (EARS Hardware) . . . . . . . . . . . . . . . 62 APPENDIX B: Loading HP-9845C Internal Printer Paper . . . 63 i
DISCUSSION The purpose of the EARS is to assist the Company Emergency Response Organization and offsite authorities in quantifying offsite radiological consequences should radioactive isotopes be released during an accident at the DCPP. The system gathers data on meteorological parameters, onsite and offsite real time radiation monitor readings. It perfoms dispersion computations, disse .f rates information and displays data to various onsite and offsite stations.
These stations include the CR, the TSC, the EOF, the Corporate Incident Response Center (CIRC), and the State Office of Emergency Services (OES) stations. )
The CR, TSC, and EOF are all capable of being the controlling station; although only one can be the controller at any one time. Any station that is not functioning as the controller can receive calculational results from the EARAUT (EARS automatic) program via comunication links. If the links are disrupted. EARS can function by means of the manual EARS program (EARMAN), using data obtained via voice communication with the controlling station operator.
This procedure provides the necessary infonnation for CR, TSC, and EOF operators to start up the EARS computer hardware and run the three -
primary EARS programs (STATUS, EARAUT, EARPAN) on the HP-9845C desktop computer at the respective station.
The structures and contents of all EARS data files at the CR, TSC, and EOF EARS stations is given in Ref. 1.
l l
l 1 DC0009 2IV 1
L
DIAAl.O CANYON POWE2 PLANT UNIT NO(S) 1 AND 2 ON '
DATE 10/22/84 PAGE 3 0F 63 OPERATING PROCEDURES FOR EARS
.l', ' , , . 9845C CONTRCLLING STATIONS .
t
- FRCCEDURE
- 1. EA:S H3rdware at Centro 11ine Statiens All HP hardware at the CR, TSC and EOF is c:vered by a service maintenance agreement with Hewlett-Packard, Inc. (see Ap;:endix A for a complete list of hardware). In case of any hardwsee failure, contact the System Manager of the EARS and explain the problem to him. If the System Manager or his alternate cannot be contacted, the EARS operator may call Hewlett-Packard service
[800]821-2446 directly during business hours (8 a.m. to 5 p.m.,
Monday thru Friday).
- 2. Start-Up Procedures .
The following start-up procedures assume that all power to the computer hardware is off when the EARS operator arrives at an EARS station.
- a. Set the power strip switch on. All of the equipment at each station is connected to one power strip which is located on th? back of the desk console, except at the TSC-CC where it
( is attached to the console underneath the HP-9845C. This should turn everything on if the station was left in proper order, with*all cf the individual component switches set to the "0N" or "1" position. Check to see that all of the switches on all of the components are set to "0N" or "1" at this point.
- b. Check to see that the 7906 disc drive RUN/STOP switch is set to "RUN". After about one minute the front panel of the 7906 should display ' DRIVE READY'.
- c. Check to see that the HP-9845C computer power switch (on the The CRT should right beep side of theacomputer)(is and begin self-test set to "1"." MEMORY TEST IN PROGRES message should appear on the CRT). When the self-test is completed, the "9845 READY FOR USE" message and a flashing cursor will appear on the CRT indicating the computer is .
ready for use,
- d. Af ter the entire system at this station is turned on, check the paper reserve in the HP-9845C internal printer.
Instructions on how to load a new roll of themal paper into the HP-9845C internal printer is given in Appendix B.
~~
DC0009 3IV
1 NUMBER EP EF-6 DIASL9 CANYON POWED PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/22/84 PAGE 4 0F 63 OPERATING PROCEDURES FOR EARS
. A. 9345C CONTROLL!hG STATIONS
(
i !
i :
- 3. Shu:-Down Procedures
- a. ? lace the 7905 disc drive RUN/STOP switch to the STOP cosition, and wait for the '000R UNLOCXID' light to ap; ear on the front panel of the disc.
- b. Turn the power strip switch to off position. This should turn off all of the equipment.
- 4. Power Failure Should the power to the system be lost during operation, the system must be shut-down as described in section 3 before power is restored.
Any data in the computer memory is erased by power failure.
- 5. EARS Software and Flow Diagrams There are three primary EARS programs stored on the HP-7906 disc drive (select code: C:12): 1) " STATUS: fur non-emergency (or idle) mode operations; 2) "EARAUT" automatic EARS program; and
- 3) "EARMAN" - manual EARS program for emergency mode operations.
There are two basic modes in which the EARAUT program can be operated: CONTROL and NON-CONTROL. Only the CR and the TSC EARS stations at DCPP, and the EOF EARS station at the Sheriff's Office in San Luis Obispo can be operated in the CONTROL mode.
Only one station can serve as the controller at any one time.
Data is transmitted to al' NON-CONTROL stations in fixed data strings containing infomation about the accident, instrument readings, calculated dose results, and messages.
Once the EARS station is activated, the operator should start running the STATUS program. If the emergency mode of EARS has l already been established at another controlling station. EARAUT i
! program will automatically be loaded from the disc and be run on the HP-9845C.
The flow diagrams following each program description are intended to give an EARS operator a general overview of the operator logic flow for each of the main EARS programs. The numbers in the flow diagrams reference other " KEY SETS" within the same program, whereas the letters reference specific entry points within the same or other programs. -
l l
t DC0009 4!V
l
. , l DIABLd CANYON POWE"2 PLANT UNIT NO(S I AND 2 ON DATE 10/22/84
- PAGE 5 0F 63 OPERATING PROCEDURES FOR EARS g #, , $845C CONTROLLING STATICNS
- a. STATL'S Wher EARS is not c;:vatad in the emergency moda, this
- progran allows all HP-9645C stations to log onto the system for data polling purposes. As long as this station stays
'loggec on' to the system, it can be ' scheduled' automatically to go into emergency mode by a CONTROL station when an emergency is declared.
When ' logged on', this program allows the operator to poll the HP-1000 at the TSC for meteorology (HET), plant radiationmonitors(RMS),orpressurizedionchambers(PIC) data. It also allows the operator to determine the system network status, such as which stations are currently logged on the systen, and when they are logged on or off. In addition, the site and area maps can be displayed and
' dumped' to the thermal printer on the HP-9845C.
Once logged on, the operator of one of the CONTROL stations can initiate the energency mode of EARS by pressing the key under the CRT labeled ' START EARAUT'. This will load EARAUT
( and thereby begin the actual assessment of the emergency.
- 1) After the computer system at this station is up and running STATUS can be loaded and run by entering the following commands from the HP-9845C keyboard, a) Typein'SCRATCPA', press [ EXECUTE].
b) Typein'SCRATCHC', press [ EXECUTE).
~
c) Type 'LOAu " STATUS: c",10'andpress[ EXECUTE] .
key.
- 2) The following three pages are flow diagrams for STATUS.
(
DC0009 5!V
NUMBER EP EF-6 AND 2 REVISION 4 otAato CANYON POWEQ PLAN 1 UNIT N0(S)
DATE 10/22/84 PAGE 6 0F 63 OPERATItiG PROCEDURES FOR EARS
- I 3 SS45C CONTRCLLIfiG STAT:0NS
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DC0009 61V
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NUMBER EP EF-6 1 AND 2 . ,. P: VISION 4 DIA8LO CANYON POWE2 FLANT UNIT NO(S) f: ATE 10/22/84 PAGE 7 0F 63 OPERATING PROCEDURES FOR EARS t
c W 95'E: CONTRC;LIG 57.*T!C.';5 1
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11 OC0009 7!V e
NUMBER EP EP-6 oiAsto CAP. von PcwE3 PLANT UNIT NO(S) iAND2 REVISION 4 DATE 10/22/84 PAGE 8 0F 63 OPERATING PROCEDURES FOR EARS TITLE 9945C CONTROLLING STATIONS t
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DIASL9 CANYON POWO PLANT UN'T NO(S) 1 AND 2 f0N DATE 10/22/84 PAGE 9 0F 63 OPERATING 000CEDURES FOR EARS
}W j
SS45C CCNTROLLING STATIONS e i 4 i t
- b. EARAUT PR03 RAM (Contro113r)
The EARS autcmatic (2ARAUT) controllar ;r:ge:m c:nsi:t: of two subprograms: EARADC (Central processing progran for Control 11rc statiens), and EARrde (Release rate calculation subprogram), in addition to the EARAUT main entry program.
These subprograms are loaded in and out of the HP-9845C as needed.
EARAUT can be loaded and run as the CONTROLLING station either by pressing the ' START EARAUT' softkey in the STATUS program, or by manually loading the program from disc and running it. Should you lead EARAUT with the intentions of becoming the CONTROLLER, but someone else has already assumed that function from another station, you will automatically be logged on as NON-CONTROLLER when running the program.
- 1. Af ter the computer system at this station has been started up EARAUT can be loaded and run by entering the following comands from the HP-9845C keyboard,
- a. Typein'SCRATCHA', press (EXECUTE),
- b. Typein'SCRATCHC', press (EXECUTE).
- c. Type ' LOAD "EARAUT: c", 10' and press the
[ EXECUTE] key.
- 2. The following nine pages are flow diagrams for controlling EARAUT.
(
DC0009 91V
r i
- NUMBER EP E'F-6 '.
ciAsto CANYON POWE3 PLANT UNIT NO(S) 1 AND*2 REVISION 4 DATE 10/22/84 PAGE 10 0F 63 00ERATING PROCEDURES FOR EARS I'I'I ,
9945C CONTR0Lt.ING STATIONS
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- NUMBER EP EF-6 DIA8LO CANYON POWEQ PLANT UNIT NO(S) 1 AND 2 REVISION 4
~
DATE 10/22/84 PAGE 11 0F 63 OPERATING PROCEDUD.ES FOR EARS
( ET'I 9345C C Z TF.0'.LIN3 33710A5 l
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CONT AOL E ARAUT FIRST UPD ATE l
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DC0009 111V
NUMBER EP EF-6 otAB o CANv0N POWEQ PLANT UNIT NO(S) kAND2 REVISION 4 DATE 10/22/84 PAGE 12 0F 63 OPERATING PROCEDUPES FOR EARS 7'T'E 9545C CONTROLLING STATIONS t
1 OONTROL IA AAUT ?!1CJEOTICH 32FORS FIAST UFCATE lata.'
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NUMBER EP EF-6 i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REV1510N 4 's l DATE 10/22/84 PAGE 13 . 0F 63 OPERATItiG PROCEDURES FOR EARS l t LE' 9545: CD.NTROL!.ING STATI0h5
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NUMBER EP EF-6 .
DIA81.0 CANYON POWE3 PLANT UNIT NOISI 'I AND 2 REVISION 4 4
DATE 10/22/84
', PAGE 14 0F 63 OPERATING PROCEDURES FOR EARS MLE i 9845C CONTROLLING STATIONS 3 ,
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NUMBER EP EF-6 DIABLO CANYON POWEO PLANT UNIT NO(S) I AND 2 REY 2510N 4 DATE 10/22/84 PAGE 15 0F 63 l OPERATING PROCEDURES FOR EARS l 93'3C CCNTROLLING STATIONS i 4
'f 2 l 3 t
CONTROL 2ARAUT NEXT UPDAT2
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DC0009 151V
NUMBER EP F-6 otABLO CANYON POWER PLANT UNIT NO(S) 1 AND'2 REVISI JN 4 DATE 10/22/84
- PAGE 16 0F 63 OPERATING PROCEDURES FOR EARS '
TITLE 9345C CONTE 0!.!.!NG STATIONS I
1 CONTROL EARAUT NEXT PRO 2CTON 6
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DC0009 161V l -
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NUMBER EP EF-6 1 AND 2 REVISION 4 oiAsiO CANYON POWER PLANT UNIT NO(S) 10/22/84 DATE PAGE 17 0F 63 0:ERATING ?'O'EDUEES FOR EARS TIT'- E 9~: E CONTROLt.ING STAT 10NS 8 l
1 i i CONTROL EARAUT XEY 3ET #3 I
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DC0009 171V
~
NUMBER EP (F-6 DIABLO CANYON POWE3 PLANT UNIT NO(S)
- 1 AND 2 REV1SION 4 DATE 10/22/84 PAGE 18 0F 63 OPERATING PROCEDURES FOR EARS TITLE 3 9845C CONTROLLING STATIONS I 1 OONTact,iluuTx2Y air v4 .
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- l. I DC0009 181V -.
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NUMBER EP EF-6
' AND 2 OtABLO CANYON POWED PLANT UNIT NO(S) * - REVISION 4 DATE 10/22/84 PAGE 19 0F 63
. OPERATING PROCEDURES FOR EARS
/ T'T LE 9945C CONTROLLING STATIONS
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1I DC0009 191V _,
NUMBER EP EF-6 -
'l AND*2 REVISION 4 DIA8LO CANYON POWER PLANT UNIT NO(S)
DATE 10/22/84 PAGE 20 0F 63 OPERATING PROCEDURES FOR EARS ,
I' M 9845C CONTROLLING STATIONS l t
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CONTAOL E AR AUT KEY SET *S i
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9345C CCNT2CLLING STATIONS l .
l c. EARA'S NOMAM (Non-conteo;;ec)
The EARS autem tic (EA:AUT) nen-controllar program consists e
of cne subprogram: SAR CC (Cantrai processing program for I Ncn-Controlling stations), in addition to the EARAUT main entry program. These subprograms are leaded in and cut of the HP-9845C as needed.
The function of EARAUT as a non-controller is to receive periodic updates of plume release parameters, and observe the resulting plume displays, as based on input from a EARS CONTROL station.
EARAUT (Non-controller) can be run in either one of two ways. The user can load the STATUS program and wait for one of the ' CONTROL' stations to log on as the ' CONTROLLER', or the user can load the EARAUT program and specify a non-controlling mode, provided the controlling station is logged on.
- 1. After the computer system at this station has been started up EARAUT can be loaded and run independently
- of the ' STATUS' program by entering the following commands from the HP-9845C keyboard,
- a. Typein'SCRATCHA', press [ EXECUTE].
- b. Typein'SCRATCHC', press [ EXECUTE].
- c. Type in ' LOAD "EARAUT: c", 10' and press the
- [ EXECUTE] key. -
l 2. The following SEVEN pages are flow diagrams for ,
non-controlling EARAUT.
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DC0009 21IV
NUMBER EP EF'-6 OIA8LO CANYON POWEp PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/22/84 PAGE 22 0F 63 OPERATING PROCEDURES FOR EARS TITLE 9845C CONTROLLING STATIONS 4
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NUMBER EP EF-6 DIASL9 C LNYON WE3 PLANT UNIT NO(S) ' I ANY 2 REVISION 4 ,
DATE 10/22/84 PAGE 24 0F 63 OPERATING PROCED'JRES FOR EARS T6TLE 9S'50 CONTROLLING STATIONS
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NUMBER EP EF-6 1 AND 2 REVISION *4 otASLO CANYON PO'.siA PL. ANT UNIT NO(S)
DATE 10/22/84 PAGE 25 0F 63 OPERATING PROCEDURES FOR EARS
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PAGE 27 0F 63 !
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DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f0N DATE 10/22/84 PAGE 29 0F 63 0??RATIG FRCCED'.'RES 700 ! ADS i
W 98s5C CONTROLLING STATIONS
- d. EARPAN PROGRAMS The EARS ibnual (EAR"aN) program is the manual version of
' the EARS programs. All of its fun:tions are performed at the individual HP-3345C stations independant of the operation of the other stations and the HP-1000 at the TSC.
Any data input such as MET data or release rate data is manually entered free the keyboard. In addition no data is transmitted to or from a station that is operating EARPAN.
EARMAN consists of two separate subprograms: EARMDC (Core subprogram), and EARRDC (Release rate definition subprogram), in addition to the initial entry program EARMAN.
In the event of a hardware failure of the HP-1000 at the TSC and/or the loss of communications between various HP-9845C EARS stations and the HP-1000, EARMAN program can be initiated. Essential data can be obtained by telephone communication via PGandE or PT&T lines with EARS operators at the other ' CONTROLLING STATIONS' (CR, TSC, or EOF).
- 1. To load and run the EARMAN program type in the following commands from the keyboard,
- a. Type in ' SCRATCH A', press [ EXECUTE].
- b. Type in ' SCRATCH C', press [ EXECUTE].
- c. Type in ' LOAD "EARMAN: c" 10' and press [ EXECUTE].
- 2. The following nine pages are flow diagrams for EARMAN.
DC0009 291V
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DATE 10/22/84 PAGE 30 0F 63 0FERATING PROCEDURES FOR EARS
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NUMBER EP EF-6
- 2 AND 2 ggyggggy 4 DIABLO CANYON POWE3 PLANT UNIT NO(S)
DATE 10/22/84 PAGE 31 0F 63
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NUMBER ED EF-6 1 AND 2 REVISION 4 OIABLO CANYO4 POWEA PLANT UNIT NO(Si DATE 10/22/84 PAGE 33 0F 63 i , 0 EetTPn PROCEDURES F00 (ARS 33450 CONTR0'.'.;M $717:0t4 l *'8 g i
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NUMBER EP EF-6 ofAs0 CANYON POWE] PWT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/22/84 PAGE 34 0F 63 OPERATING PROCEDURES FOR EARS W 95450 CONTROLLING STATIONS 4
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NUMBER EP EF-6 otAsLO CANYON POWE] M f UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/22/84 F 63 OPERATING PROCEDURES FOR EARS
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NUMBER EP EF-6 otAsLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2
- REVISION 4 DATE 10/22/84 PAGE 29 0F 63 CPE?:'IM1 ee00!CUeES F0e EteS W 9245C CCNT,10LL!hG STATIONS 1
- e. EA 20C/EARede F20GDAM5 The release rate definitier ;r:gran EA1000/!2 Red: i s ifnked
< by the Core program EARICC/EARADO. Thirteen different release c;tions are available in these prog *a.-s. Tna logic fcr each option is outlined in the following fourteen pa;Ls of flow diagrams. . .
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NUMBER EP EF-6
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DATE 10/22/64
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OPERATING PROCEDURES FOR EARS ,
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NUMBER EP EF-6 otAsLO CANYON POWEQ PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/22/84 PAGE 43 0F 63 ODEDATING Po.0CEDUDES F0D EARS lN 95450 CONTR0'. LING STATIONS 1 4
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NtMBER EP EF-6 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/22/84 PAGE 44 0F 63 OPERATING PROCEDURES FOR EARS 7#'E 95:5C CONTROLLIM STATIC %
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- - - NUMBER EP EF-6 DIABLO CANYON POWER PLANT UNIT NO(S; 1 AND 2 REVISION 4 DATE 10/22/84 PAGE 45 0F 63
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I NUMGER EP EF-6 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/22/84 PAGE 46 0F 63 l
00ERATING PROCEDURES FOR EARS s W 9345C CONTROLLING STATIONS j
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DC0009 461V
. . NUMBER EP EF-6 1 AND 2 REV1SION 4
. DIA8'.O CANYON POWER PLANT UNIT NO(S) 10/22/84 DATE PAGE 47 0F 63
- 0:ERCIN3 FFOCED'JRES FOR EARS
' W 96:5C CONTROLLING STATIONS
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DC0009 471V
OtA8LO CANYON POWER PL. ANT UNIT NO(S) 1AN62 f5ON
- DATE 10/22/84 PAGE 48 0F 63 OPERATING PROCEDURES FOR EARS I T'I 9545C CONTROLLING STATION 3 )
i .
$ i i
LCS3 CF CCCLANT ACClCENT OPTION 5 d
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100% G AF 100% CO P E NOBLE GASES:
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DISF RELEASE RATE TAB LE d
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DC0009 4EIV
=-__-_-
NUMBER EP EF-6 DIABLO CANYON POWEn PLANT UNIT NO(S) 1 AND 2 REVISION 4
- DATE 10/22/84 PAGE 49 0F 63 OPEFATING ??CCED'.' PES FOR E:ps
- I ' -- 95'5: CONTROLLIN3 STATIONS f 1 i
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. . 1 NUMBER EP EF-6 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 1
~ DATE 10/22/84 PAGE 50 0F 63 OPERATING PROCEDURES FOR EARS s
.'". . " . 9845C C0tiTROLLItiG STATI0?is
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CONT AOL ADO EJECTION ACCIDENT I
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DCOC09 50!Y
. NtMBER EP EF-6 DiAsLO CANYON POWER MT UNIT NO(S) I kND 2 REVISION 4
. DATE 10/22/84 PAGE 51 0F 63 ODECATING PROCEDURES FOR EARS l
9 85C CONTROLLING STATIONS
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- DC0009 511V
~ NUMBER EP EF-6 DIA8;.0 CANYON POWER PLANT UNIT NO(S)
AND 2 REVISION 4 DATE 10/22/84 PAGE 52 0F 63 OPERATING PROCEDURES FOR EARS T IW 9845C CONTROLLitlG STATIONS 4'
1 8
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L
- NUMBER EP EF-6 1 AND 2 REVISION 4 DIABLO CANYON POWER PLANT UNIT NO(S) 10/22/84 DATE PAGE 53 0F 63 OPED3 TING DROCEDVDES FOR EAP.S "d 9545C CONTROLLItG STATIONS
- i '
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DC0009 53!V
NUMBER EP EF-6 1 AND 2 REVISION 4 DIABLO CANYON POWER PLANT UNIT NO(S)
DATE 10/22/84 PAGE 54 0F 63 OPERATING PROCEDURES F00 EARS
- 'E 38450 CONTROLLING STATIONS
)
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DC0009 541V I:
-,s .
_=
~
NUMBER EP EF-6 DIA8LO CANYON POWER PLANT UNIT NO(S) . 1 AND 2 REVISION 4 DATE 10/22/84
. PAGE 55 0F 63
( OPERATING PROCEDURES FOR EARS
,[' 9845C CCNTRCLLING STATIONS l
t t j s t
- 6. Tems Comon to EARAUT and_EfRMAN Meteo-oiocic?1 Cata Inout Meta:rciogical data from the primary and the backuo MET tc*. vers l are sent to the HP-1000 computer at the TSC. Both STATUS and i EARAUT programs can ' poll' the HP-1000 for MET data (averaged, previous or current), including wind direction, wind speed, lapse rate, precipitation, and mixing height (provided the data link between this station and the TSC exists).
During a drill run, MET data is read from the HP-1000 drill database.
If EARMAN program is run, the operator has to enter all MET data manually.
Release Estimate The DCPP Emergency Procedure RB-9 (Ref. 2) is the technical basis for the EARS release rate calculations. The radionuclide k distribution and release rate are determined in the EARS subprograms EARrde or EARRDC, using one or more of the following techniques:
- a. Plant vent monitors and vent flow indication.
- b. Containment area monitors and derived release ratr based on containment leak rate, etc.
- c. Isotopic analyses of selected plant containers and systems -
performed prior to the accident. ^
L Steam line monitors and stean flow rate meters.
d.
l G
l i
I DC0009 55IV
1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S) [S$0N DATE 10/22/84 PAGE 56 0F 63 CPERATING PROCEDURES FOR EARS
) 7:TLE 9845C CONTROLLING STATIONS ,
i
- e. Final Safety Analysis Report (FSAR)(Ref. 3) accicent scenarios:
-Steam Generator Tube Rupture Accident
-Loss of Coolant Accident (LOCA)
-Fuel Handling Accident
-Control Rod Ejection Accident
--Locked Pump Rotor Accident
-Loss of Offsite Power Accident
-Steam Line Break Accident
-Volume Control Tank Rupture Accident
-Waste Gas Decey Tank Rupture Accident
-Liquid Holdup Tank Rupture Accident When using the FSAR cases, the operator must exercise judgement as to whether the ' expected case' or the ' design basis' estimates are appropriate to adequately describe the accident. The DCPP Emergency Procedure RB-11 (Ref. 4) indicates that unless actual l' release data is available, the operator should initially choose '
the ' design basis' (more conservative) values in determining ,
initial accident classification. )
- f. If none of the FSAR r.ccident types is appropriate, the
' Manually Specified Release Rate' or ' Tank or Building Inventory' permits manual entry of radionuclide release data, either by isotope or as total noble gases and iodines.
P.A.G. Table The Protective Action Guide (PAG) criteria used in the EARS programs are from Table 5.1 of Reference 5. They apply to the ,
total dose (or dose comitment) up to the time of interest. The criteria are:
\
l a. No action needed if Whole Body dose <0.5 rem
- and thyroid l_
dose = 0.5 rem and Whole Body <5 rem, or Thyroid >=5 rem and Thyroid <25 rem.
- c. Evacuatien recommended if Whole Body >=5 Rem or Thyroid >=
25 rem.
i
- 0.5 ren is the PAG criteria set by the State of California. }
l _.
DC0009 561V
~
- ~
NUMBER *EP EF-6 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 4 DATE 10/22/84
. FAGE 57 0F 63 g
^lN CPERATING PROCEDURES FCR EARS SS"5C CONTROLLING STATI0h5 I
1 i
! I f
Projections and Ucdates It is possible to run up to five class A ' dose projections' before the first update and between any two subsequent updates, and forty segmented Gaussian modeled, near 'real-time' dose updates. A ' projection' is a straight line Gaussian modeled dispersion and dose calculation which does NOT deposit activities but does take into account previously accumulated doses from updates. An ' update' is a complete set of segmented Caussian modeled dispersion and dose calculations which disperses and deposits activities alon'g the travelling direction.
In EARMAN operation, at the end of either projection or update calculations, a set of output tables is automatically printed.
Edoe Dose Rate The edge dose rate is the plume exposure rate at the edge of the plune as displayed for the dose type (thyroid or immersion) selected. This is displayed on the right-side of the CRT graphics area. If the edge dose rate value chosen is greater than the plume center dose rate, *
(' message " Edge dose rate > Centerline dose rate" is displayed. When a new edge dose rate is chosen, a plume with this new dose rate will be drawn. This is to prevent confusion regarding the parameters selected and the particular plume displayed.
The edge dose rate is always in mrem /hr. The default value in the EARS is 0.1 mrsm/hr. It can be changed by pressing the EDGE DOSE TYPE / RATE soft key and entering a new edge dose rate.
Dose Type .
Two different dose types can be selected: thyroid or imersion.
Whenever a new dose type is selected and a previous plume is already displayed, the new plume will be redrawn for the new dose type.
l I
Radius and Plume Center l'
The value displayed as '+ Radius' on the right-side of the CRT graphics area is the minimum distance in meters from the plume segment center (denoted by a small white cross on the graphics) to the edge of the plume for a given edge dose rate. This marker is used to indicate the l
' centers' of the plume segments, starting from the earliest (generally the outermost segment) to the latest segment (generally the innermost L(
!i _. .
DC0009 57IV I
OMT-LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 10/22/84 PAGE 58 0F 63 OPERATING PROCEDURES FOR EARS s
,, T ,-,
9345C CO:iTROLLING STATIONS )
i !
L- i or closest to the site). The pitma :antar-line cc:a rate is indicatad in mrem /hr under the '+ Center Dose Rate' label en the right-side of the CRT graphics area.
Each time the STEP CENTER soft key is pressed, the white cross will move to the next plume segment center and the corresponding center-line dose rate and radius will change accordingly, cycling frcm the earliest segment to the latest.
Sector Element The cumulative deposition data are listed for each of 96 ' sector elements'.
A sector element is an area bounded by a division of the compass into 16 sectors (from number 1 centered on North to number 16 on NNW) with radial distances as 800 meters to 2 miles, 2 to 5 miles, 5 to 10 miles, 10 to 15 miles, and 15 to 20 miles.
Cumulative Deposition The cumulative deposition listed as Ci/m**2 of 'Cs-137 equivalents' is '
I the quantity of Cs-137 which would yield a direct radiation exposure rate from ground plane deposition equal to the decay-corrected sum of all deposition which has occurred for that period. Due to uncertainties involved in calculating both wet and dry deposition, this information is meant just to provide guidance to field survey teams as to where deposition is likely to have occurred. The values listed have relatively large uncertainties and should be used together with accurate field survey data in detennining appropriate protective actions. _
Output Tables -
The EARS output is listed in tabular forms as:
Table 1 (EARMAN) or Table 1A (EARAUT or STATUS) - MET data (wind speed, wind direction, sigma theta, lapse rate, precipitation, stability classes, and mix height); -
Table IB (EARAUT or STATUS) - PIC data; Table IC (EARAUT or STATUS) - RMS data;
}
DC0009 58IV
DIABLO CANYON POWER PLANT UNIT NO(S) 1AND 2 RE ON DATE 10/22/84 PAGE 59 0F 63 OPERATING PROCEDURES FOR EARS W '
92A C CONTROLLING STATIONS .
Table 2 - Release rate data in Ci/sec; Table 3 - Emergency status data (amergency class, projection or update duratien, incident and release start times, accicent type anc any l message);
Table 4 (EARMAN) - Plume segment radial intercept (RI) points dose rates and endpoints (EP) dose rates and doses eata; A RI point is the
- intersection of a plume segment centerline with one of the radial rings: 800 m, 2, 5, 10, 15 or 20 miles.
Table 4A (EARAUT) - Plume segment radial intercept (RI) points dose rates data; Table 48 (EARMAN or EARAUT) - Plume segment centerline endpoint (EP) dose rates data; Table 5 (EARMAf,' or EARAUT) - Dese rates, doses and P. A.G.'s at specific locations; Table 6 (EARMAN or EARAUT) - Deposition data by sector elements.
{ .
Table 7 (EARMAN) - Dose equivalent I-131 and Cs-137 rehose rates, total noble gas release rate and averaged energy released per disintegration.
- 7. EARS Support Software The function of the EARS support programs is to initialize, edit or review the EARS data files. These programs include EAREDT, EARSED, EARSDP, EARKSP, EARKDC and EARDOC, and are all stored on the HP-7906 disc drive at the stations. These programs are not normally used during emergency conditions.
EAREDT - Data File Edit Program The EAREDT program is used to setup, edit, or print the fixed data files used by the EARS for system parameters, isotope -
specific parameters, FSAR release rate data, site boundary
(
locations, fixed PIC locations, RMS parameters, etc. This program can also duplicate from one msus to another all of the data files used by the EARS.
The data files accessed by this program are ERDSYS, ERNRMS, ERRTXY, ERDISO, ERBNDY, ERPLOC, ERNMAP, ERDMET, ERNSTN, ERDGRD, ERSTDC, ERSRCE, ERMONI and ERELOC.
DC0009 59IV
DiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 S ON DATE 10/22/84 PAGE 60 0F 63
, "'8 OPERATlHG PROCECURES FCR EARS 9845C CONTROLLING STATIONS "
t
)
l i i EARSED - Data Strino File Edit Procram The EARSED program allows the operator to access the data base to print, edit or initialize the projecticn and update string data stored on ERDSTA and EADSTR, respectively. Rather than decoding the strings, this program edits or prints the ASCII characters of the string for each of the parameters. EARSED can also purge old data on ERDSTA or ERDSTR.
EARSDP - Calculational Parameters Plot Program The EARSDP program allows the operator to print the imersion dose correction factors and to plot sigma y, sigma z and plume depletion curves used in the EARS calculations. Data files accessed by this program are ERDSIG, ERDDEP and ERDIMR.
EARKSP - Soft Key Functions Defining Program The EARKSP program is used to create and edit the soft key labels used in EARAUT, EARMAN, and STATUS programs. Labels for the soft keys are stored in a string array that is read from a data file on the program mass sotrage media (7906 disc cartridge). .
)
Data files EARSKY, EARACK, and EARKEY are used in program; STATUS, EARAUT, EARMAN, respectively.
EARKDC - Graphics Documentation Program The EARKDC program is a documentation program used to describe the CRT screen layout and sof t key functions of the EARMAN, -
EARAUT and STATUS programs.
EARDOC - File Documentation Program
(
l The EARDOC is a documentation program that lists all types of data files in the HP-9845C software. For each data file or type of data file, the file name, size, contents and general purpose l can be listed. .
l
[
l DC0009 60lV
- e o OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fSON DATE 10/22/84
- PAGE 61 0F 63 C?EEATING PFOCEDURES FOR EAES 7#'I 9845C CONTROLLING STATIONS f
- 8. REFERENCES
- 1. " EARS User's Operating Manual for CIRC S:stic ", Rev. 3, 3 July, 1954 t
- 2. PGandE: "DCPP Emergency Procedure RS Determination of Release Rates", Rev. 1, 1983.
- 3. PGandE: "DCPP Final Safety Analysis Report", Chapter 15..
- 5. EPA: " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents"; EPA-520/1-75-001, 1975.
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l
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DC0009 611V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON l DATE 10/22/84 l PAGE 62 0F 63 s j 7#'E OPERATING FROCEDURES FOR EARS 9345C CCNTROLLING STATIONS
) '
i 1
APPENDIX A EARS HARDWARE The EARS cceputer hardware at CR, TSC, and EOF EARS stations includes:
MODEL DESCRIPTION FUNCTION HP-9845C Desktop Computer w/ graphics EARS graphics computer ROM, I/O ROMS, Mass storage at this station ROM, Assembly execution ROM HP-7906MR Disc Drive Mass storage unit HP-98041A Disc Interface Interface the 9845C with the 7906 HP-13037C Disc Controller Controis 7906 operation HP-98036A Serial Interface Interface the 9845C with the modem to the I (select code 5 at TSC & CR)
DC0009 621V
1 AND 2 ON DIABLO CANYON POWER PLANT UNIT NO(S)
DATE 10/22/84 PAGE 63 0F 63 CPERATING PROCEDURES FOR EARS
- i W 9545C CONTROLLING STATIONS a,
4 APPENDIX B LOADING HP-93:5C IHTERNAL PRI'iTING FA~ER 1
To perform Printer paper is loaded by using the following procecure.
the following steps, the computer must be switched "0N".
- 1. Lift or remove the access cover on the top of the printer by The pushing down on the raised surface at the rear of the door.
door can be removed by lifting up and pulling it toward you. It is reinstalled by placing it on the hinge pins and pushing until it snaps into place.
- 2. Remove and discard the paper core of any previous roll. If the remaining roll is small and a new roll is to be used, remove the old roll by:
- a. Unrolling and lif ting it upwards until the roll is above the printer, then,
~~
It b. Holding the rol1 firmly and pulling it upward and forward; the paper guide will tear the paper off.
- 3. If any paper rer.ains in the printer mechanism, remove it by pressing the PAPER ADVANCE key until the paper stops moving.
4 Remove the first layer of paper from a new roll. Be sure the paper has a cleanly torn or cut edge, as paper with a ragged edge may not load properly. The corners can be folded back to form a _
point for easier loading.
- 5. Insert the new roll such that the free e6d is positioned as shown. Press the PAPER ADVANCE key until paper appears at the front of the printer, then close the access door.
(
e e DC0009 631V
NUMBER EP RB-3
, 9SW3 Pacific Gas and Electric Company REVISION 1 dan 2/2e/85 cammna c nuctsu r w ensur.e .s mE 1 0F :
1 c: 2 j
' ]%j IM cas.:: wyes :xsn =tm u c ses rumi:7 n:x::n i
m;s STABLE 100!NE THYROID BLOCKIb g~ IMPORTANT '
gooovso ??. S 74- A L!/46 To ,i SAFETY PLRT MAf!A3Egl CATE SCOPE This procedure addresses administration of Potassium Iodide (KI) under emergency conditions for emergency personnel. Action levels, recuired authorizatinr, method of distribution and record-keeping are described. This procedure and changes thereto require PSRC review.
ICTI0f. LEVELS
(' thyroid is likely to be received by an individucl.
NOTE: Refer to figure 1 of this procedure to determine thyroid dose as a function of the airborne I-131 concentration.
I
- 2. If possible, prior to undertakivig an emergency response operation where high levels of radio-iodine are suspected, or no current air analysis is available.
f0TE: In all cases where airborne contamination is anticipated, ~
personnel should be fitted with pressure / demand Self Contained Breathing Apparatus (SCBA) as a minimum. .
PROCEDURE
- 1. The)iteEmergencyCoordinator,actingonadvicefromthe Emergency Radiological Advisor shall designate, for on-site personnel, when and who shall receive KI. ,
ETE: Personnel with sensitivity to Iodine may develop adverse symptoms resulting from ingestion of KI tablets. An allergy to shellfish may indicate Iodine sensitivity.
Personnel with a history of Iodine sensitivity may be permitted to take KI tablets only after being verbally warned of the possible effects and having initialed the distribution record, so indicating. (See the Patient
(-'
Package Insert, Attachment 2).
DC0017 IIII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/28/85 '
PAGE 2 0F 4 1
STABLE ICDINE THYROID SLOCKING I) t i
The Emergency Liason Coordinator will infonn all on-site personnel located in the Control Rocm Operational Support Center (OSC), Security Building. and all other personnel in their designated assembly areas.
- 2. The Recovery Manager, acting on advice from the Radiological Emergency Recovery Manager shall designate, for off-site personnel, when and who shall receive KI. These tablets are available in Kits 1, 2 and 3 located in the Mobile Emergency Monitoring Laboratory (MEML) garage. These kits may be obtained by the designated monitoring teams from the PGandE San Luis Obispo Service Center.
- 3. The Emergency Radiological Advisor, or Radiological Emergency Recover Manager, or their designee shall:
- a. Notify all affected monitoring teams of the decision for personnel potertially exposed to high-level airborne contamination to use the precaution of KI.
- b. Inform each affected supervisor to be responsible for J disseminating the directive and appropriate warning and ensuring that all proper preventive precautions have been observed.
- c. Advise supervisors to obtain bottle (s) of 130 mg KI tablets from the TSC, First Aid Room cabinet or Emergency Kits as appropriate and dispense one (1) tablet to each individual I that has emergency team assignments and could enter a high-level airborne radiofodine environment. _
NOTE 1: Once taken and the I-131 concentration is verified
' or the calculated dose determined, the tablets should be administered for ten (10) days post-exposure. Dosage is one tablet, once a day.
l Individuals suspected of inhalation of airborne contaminants should receive thyroid counts on a regular basis throughout the KI treatment period to -
i verify effectiveness of treatment and to estimate i dose comitment.
l t0TE 2: If possible, K! should be administered
' approximately one to one-half hour before exposure for maximum blockage. Final uptake is halved if KI is administered within 3-4 hours after exposure.
l
' Little benefit is gained with KI administration ,
10-12 hours after exposure. )
DC0017 21V
OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 [fSf0N DATE 2/28/85
( PAGE 3 0F 4 STABLE IODINE THYFOID 3'.C: KING 37 4
- d. Insure that records are maintained for those people wno were administered the XI t3blets. Use Form No. 69-9395, Recore cf Potassium !ctice Distri:ution, or other leg. Eacn person I i
rust initial next to his (her) name to indicate that he (sne) has been warned about possible side effects.
- e. Inform the Materials Department if available, or the l Corporate Materials Coordinator at the General Office , that the K! tablets were used 50 that adequate supplies are maintained.
FIGURES
- 1. Thyroid Dose Due to Inhalation of I-131 ATTACHMENTS
- 2. Patient Package Insert for THYRO-BLOCK, Wallace Laboratories,
(. !ssue 10/79.
S e
DC0017 31V
__ - - _.- _ _ . - - - - . ._. ._- . - - _ - = . . - _ - . . . .
NWBER EP RB-3 .
1 AND 2 REVISION 1 onto CANYON POWER PLANT UNIT NO(S)
DATE 2/28/85 PAGE 4 0F 4 STABLE IODINE THYROID SLOCXING J f
m FIGURE 1 THYROID DCSE DUE TO INHALATION OF I-131 1
2 1 x 10 6 1
-m i M ' I Ill i J JP 30 dayy/ f[ ,,
/ 7 days / ,
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/ ['/ 1'hr. Esposure Time 10 _- _
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1 10-9 10-8 lo-T lo-6 to-5 Atrhorne I-131 Concentratton (yct/cc) s OC0017 4II
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h Page 1 of 1 PACTF1C GAS AND ELECTRfC COMPANV
. DEPARTMENT OF NUCLEAR PLANT OPERAT10NS
, DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 ,,
? y I
?
-\ '
ATTACWENT ?
9 e ....., e . e. .,. en..a S a' NOw acTAsmuu Icemt -teus Cer .ain fo- no of io6ne ceip your thyroid ?h.c woranz. Mest reop.e teet ur m.ar t.uy :M . rom imis. .ut mu wt cr
, i n.sh. The thpond can "stort ' or hcic cruy a etr mn a=oant of l' THYRO BLOCK" l icone.
In s radatioc emereency. raEcactive isime may be rekssed e 90TASSiUM 10300 t.be air. Th;s maursaj =ay be b.- .athed or swahamed It say
- i (pronounce
- co+TAShum EYEeoyes enter the thyroid gland and dams:e it. The da=.sre *ould pro-
[ 'i (scre .sies u hably not show itae!1 for years Chudren are most hkely to ha$e l tab.ETS aa: SOWTiCS U S *
- thyroid da= age.
. If you take potassium iodade, it wiD fiD.up your thyroid gised.
f This reduces the chance that harmful raicacuve icir.e si:
estar the thyroid gland.
TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC ,
- RELEASED INTO THE Alk. POTASSIUM ,10DIDE LA who know they an allergic to iodide. You may take potassium FORM OF IODINL CAN HELP PROTECT YOL. iodide even if you are tahmg medicines for a thyroid problem ifor asample, a thyroid hormone or antithyroid drugt. Pregnant and IF YOU ARE TOLD TO TAKE THIS MEDICINE.TAKE IT nursing women and babies and children may also take thas drug
? ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE L MAY inn HOW AND WHEN TO TAKE POTASSIUM IODIDE OFTEN.
CREASE MORE THE RISKWILL OFNOT SIDEHELP YOU AND,OT EFFECTS. DO A TAKE i Potassium lodide should be taken as soon as possible aber THIS DRf/G IF YOU KNOH YOU ARE ALLERGlC TO public health of ficials tell you. You should take one dose every 24 JODIDI (SEE SIDE ETFECTS BELOM.I bours. More will not help you because the thyroid can " hold" on-ly limitad amounts of iodme. Larger doses willincrease the risk of side effects You will probably be told not to take the drug for more than 10 days. ;
INDICATIONS SIDE EFFECTS iYROID BLOCKING IN A RADIATION EMERGENCY
~
(- JNLL Usually, side effects of potassium iodide happen when people take higher doses for a long tune. You should be careful not to take more than the recommended dose or take it for longer than DIRECTIONS FOR USE you are told Side effects are unlikely because of the low dose and Uce orJy as dincted by State or local pubhc health authorities in the short time you will be takmg the drug.
g that event of a radaauon ernergency. Possible side effects include skin rashes, swelling of the sehvary s DOSE glands. and " iodism" tmstallic taste. burning mouth and throat.
l Tablets ADULTS AND CHILDREN 1 YEAR OT sore teeth and gums, symptoms of a head cold. and someumes stomach upset and daarrheal.
AGE OR OLDER: One (1 tablet once a 4
day. Crush for smaU children. A few people have an allergic reaction with more serious symp-BABIES UNDER 1 YEAR OF AGE; toms.These could be fever and joint pams, or sweihng of parts of 3 One half (1!2) tablet once a day. Crush the face and body and at times severe shortness of breath requir-E fi"' ing imme&ste medical attanuon. -
D Sclusion- ADULTS AND CHILDREN 1 YEAR OT AGE OR OLDER; Add 6 drops to one- Taking io6de may rarely cause overectivity of the thpoid i half glass ofliquid and drmk each day. gland, underactivity of the thyroad gland, or enlargement of the '
' thyroid sland (goiter).
BABIES UNDER 1 YEAR OF AGE:
Add 3 drops to a small amount of hquid -
WHAT TO DO IF SIDE EFFECTS OCCUR For alldosage forms: T e fo lhdays unless daracted otherm H & & docu an sem or H yn W en he nactsn.
stop taking potassium iodide. Then, s! possible, cad a doctor or L
by State or local public health authorities. pubbe health authority for metrucuons.
Ston et controued room temperature between IS' and 30*C(59' to 86'F). Keep container tightly closed and protect from bght. HOW SUPPLIED .
Do not use the solution if it appears brownish m the nozzle of the THYRO.BLOCKW TABLETS (Potassium lo&de. U.Sf.s bot-0 ties of 14 tabiets (NDC 0037 0472 20.1 Each white, rmnd, scored bottle.
tablet contams 130 mg potassium io6de.
WARNING T).YRO BLOCKS SOLUTION IPotassium lo6de Solution.
Potassium iodide should nor be used by people energie to iodid' S.P.30 ml11 fl. cz.) light. resistant. measured drop 6spensmg Keep out of the reach of children. In case of overdose or allergic units INDC 0037 4257 25. Each drop contains 21 mg potauaurn rescuon contact a physician or the public health authority. iodid i DESCRIPTION WALLACE LABORATORIES -
l
~ Each TH RO BLOCKW TABLET contains 130 mg of n,,,,, ,,
- potasaium iodide. , CAR 7ER.WALLACL INC
- Each drop of THYRO BLOCKW SOLUTION contams 21 mg of Cranoury, he. Jersey 08512 potanium io&de.
Cw 107915-1079 issue 10/79 e
DC0017 61!!
l .
NUMBER EP RB-4
%G55G
.f Pacific Gas and Electric Company REVISION 2 DATE 2/11/85
$ DEPARTMENT OF NUCLEAR PLANT OPERATICNS - -
njy g'l Y- C CrABLO CANYON CCWEA PLANT UNIT NC(S) 1 AND 2 j Na -
j 9 EMERGEiiCY PROCE00RE l
1 M 'd ACCES5 TO AND ESTABLISHMENT OF CONTROLLED
' i M')"
TITL2 AREA 3 'Jh0ER iME?GE.' ICY CCNDITIOM
!MPORTANE AppnCvgo. T f Yh . Y TO PLANTMANAGE5d DATE SAFE 4y i SCOPE This procedure provides criteria for expanding the boundaries of the Radiological Centrols Area or establishing a new Controlled Area if I the need arises under emergency conditions. The administrative controls which are employed to control access to areas for radiation protection purposes under emergency conditions are addressed. This procecure also cescribes the methods to be employed for the subsequent returr of such areas to normal access and use. This procedure and changes there require PSRC approval.
. GENERAL The normal permanent Radiological Controls Area of the plant incluces the containment buildings, the fuel handling buildings, the outside tankage areas containing radioactive liquids, the solid radwaste storage area, most of the auxiliary building, and the calibration facility in the Unit 2 turbine building.
Radiological monitoring during and after an unplanned release may indicate the need to establish Temporary Controls Areas. In adaition.
emergency conditions may necessitate the establishment of Temporary '
Radiation Areas, Temporary Radioactive Materials Areas, Temporary High Radiation Areas Temporary Airborne Radioactivity Areas and Loose Contamination Areas.
PROCEDURE
- 1. Acministrative Control
- a. Authorization
- 1) All entries into a controlled area affected by the emergency shall be made under the provision of a valid SWP.
DC0432 11
DIA8LO CANYON POWER PLANT UNIT NO(S)
NUMBER EP RB-4 1 AND 2 REVISION 21 DATE 2/11/85 PAGE 2 0F 6 7gge ACCESS TO AND ESTA3LISHMENT OF CONTROLLED ARIAS UNDER EMERGENCY CONDITIONS i s I
NOTE: C&RP personnel should perform the evaluation recuired for issuance of an SWP, hcwever a clearance request is not required when an emergency has been declared.
If the situation requires immediate action, the SWP portior, of form 69-9158 and the SWP form 69-9300 may be completed following the entry, however, the C&RP approval for entry and authorization of The Emergency Radiological Advisor (or Site Emergency Coordinator) shall be obtained verbally.
- 2) The Emergency Operations Advisor and the Emergency Evaluations and Recovery Coordinator will provide the Site Emergency Coordinator with an evaluation of conditions affecting access to Controlled Areas. I
- 3) The Emergency Radiological Advisor will be notified of all requests to enter the Radiological Controls Area to l insure implementation of appropriate methods to minimize personnel exposure. ,
)
- 4) The Chemical and Radiation Protection Coordinator located at the Access Control is responsible for implementation of appropriate radiation protection methods.
- 5) All entries and exits from the Radiological Controls l Areas shall be recorded by the Chemical and Radiation Protection Coordinator or Operational Support Center i -
Supervisor. I
- 6) Information needed for a Special Work Permit (SWP) will use the forms provided in RCP G-1 " Radiation Work Permits."
- b. Exposure Control
- 1) All entrances and exits to the Radiological Controls 'l Areas shall be through Access Control with the following exceptions:
a) If Access Control cannot be used, new entry and egress points will be established.
WW DC0432 2II
- NUMBER EP RB-4 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 21 DATE 2/11/85 PAGE 3 0F 6
' n- c ACCESS TO AND ESTABLISHMENT OF CCNTROLLED AREAS UNDER EMERGENCY CONDITIONS l l b) Under emergency conditions and if approved by the Site Emergency Coordinator, the Radiological I Controls Area entry point locatec at the eest sida of the Control Roc = may be usec. ,
- 2) Individuals shall not enter any area where dose rates are unknown or beyond the range of instruments and l dosimetry provided. l
.i
- 4) Protective clothing and/or respirators should be used as appropriate. In all cases where airborne radioactivity is anticipated, personnel shall be fitted with full face respirators as a minimum. Refer to procedure RCP G-3, " Personnel Internal Exposure
(
Control.."
- 6) Administrative methods used during normal operations to minimize personnel exposure (such as ALARA measures) >
should remain in force to the extent consistent with emergency recovery efforts. l _
- 7) If personnel exposures are projected to be greater than ,
established exposure limits in RCS-1 " External l Radiation Dose Control," an Emergency Exposure Permit shall be completed per EP RB-2, " Emergency Exposure Guides."
- 2. Criteria and method (s) used to establish expanded Radiological l.
Controls Areas under emergency conditions.
m e DC0432 311
' ~
DIABLO' CANYON POWER Pt WT UNr* NO(S) 1 AND 2 DATE h RB-4 2/11/85 PAGE 4 0F 6
.m ACCESS TO AND ESTABLISHMENT OF CONTROLLED ADEAS UNDER EMERGENCY CONDITIONS i *
- b. Establish a new control area entry and exit point if existing entry and exit points cennot be used,
- c. Remove any personal food supplies fr:m affected area and/or !
prcnibit their consumpticn.
- d. Isolate water supply to drinking fountains in effected '
areas, and/or othemise prohibit consumption. t
- e. Continue to monitor radiological conditions during the emergency for indication of possible change of status to posted Controlled Area boundaries.
3 '. Criteri ';r permitting return of areas to nomal use,
- a. Verify that the emergency has been terminated and plant l conditions have been returned to a controlled status.
- b. If the drinking water supply (i.e., reservoir and surrounding watershed), could be potentially contaminated, botticd water will be supplied until analysis of the water can determine that it is safe for consumption. )
. Pemanent fi.ttures (i.e. , drinking fountains, equipment, and buildings), vill have to be surveyed to identify surfaces that have tr, be decontaninated.
- d. The necd for immediate access across contaminated areas within the RCA boundary will have to be evaluated. If time does not permit initial decontamination, lay plastic sheets (s) over pathways to access points to prevent further -
spread of contamination. ,
- e. Follow decontamination methods described in EP RB-6, " Area and Equipment Decontamination" or appropriate Radiation Control Standards and Procedures,
- f. After decontamination work is complete verify by performing final radiation and contamination survey as per RCP G-7
" Radiation and Contamination Surveys" and G-8 " Sampling and Measurement of Airborne Radioactivity." If results are below Radiological Controls Area limits return the l controlled area boundary to its original status.
N
}
DC0432 4II
otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 RB-4
. , . DATE 2/11/85 PAGE 5 0F 6 i y' "
, ACCESS TO AND ESTABLISHMENT OF CONTROLLED AREAS UNDER EMERGENCY CONDITIONS t
- g. If uncontrolled area limits are exceeded, do one or more of l the following:
- 1) Continue decontamination prccedure.
- 2) Cover contaminated area with clean surface (i.e.,
plastic sheets, paper boards, etc.).
- 3) Fix loose contamination using strippable paint.
- 4) Remove contaminated material to radioactive control a rea.
- 5) If contamination is isolated, barricade off local area. i
- 6) If none of the above prove sufficient, establish a permanent Radiological Controls Area to include the new I affected 6rea as soon as is practical under emergency recovery efforts.
STANDARDS
{ Radiation Control Standard 1, " External Radiation Dose Control" Radiation Control Standard 4, " Control of Access" Radiation Control Standard 6, ' Control of Radioactive Materials" l SUPPORTING PROCEDURES Radiation Control Procedurb G-1, " Radiation Work Pemits" ~
l Radiation Control Procedure G-2, " Personnel External Exposure Dosimetry and Control" l
l Radiation Control Procedure G-3, " Personnel Internal Exposure Control" Radiation Control Procedure G-5, " Control of Access for Radiation .
Protection Purposes" Radiation Control Procedure G-7, " Radiation and Contamination Surveys"
': Radiation Control Procedure G-8, " Sampling and Measurement of Airborne Radioactivity"
~~
DC0432 SII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON 2 DATE 2/11/85 PAGE 6 0F 6 ACCESS TO AND ESTABLISMMENT OF CONTROLLEO AREAS l N' UNDER EMERGENCY CONDITIONS
+
t -
i t I t Emergency Procedure RB-1, " Personnel Dosimetry" l 1
Emergency Procedure RS-2, " Emergency Exposure Guides' 3 Energency Procadure RS-3, " Stable Iodine Thyroid Slocking" Emergency Procedure RB-5, " Personnel Decontamination" Emergency Procedure RB-6, " Area and Equipment Decontamination"
)
O b
DC0432 61
--.--,--m-------- - -- y _ --. . %-. w. +,e-e - m e m-
NUMBER EP RB-25:A
.T_. G W3 Pacific Gas and Electric. Company REVISION 3 DATE 3/26/85 CECA ATMENT CF NUCLEAR PLANT C:E A ATIONS ;
~ TAaLC CANYON 20'AE:1 PLANT UN!T NC(3) 1D2 I [!M EMERGENCv CFE;ATI?;G PRCCEDURE I I
[ T:TLE T;'0,Y FC T :::::E:;T SA",.::.B3 SYSTE?
-- IN:TIAL ACTIOllS DURI!iG A!! EMERGE;CY APPAOVED - ^ @
pL A'4T MA*iAGER j DATE PURPOSE The purpose of ttis procedure is to define some of the actions taken when a decision is made by the Site Emergency Coordinator to obtain a post accident sample using the Post Accident Sample System (PASS).
This procedure guides, with consideration of plant emergency radiation hazards, the Sentry team to access and make operable the Sentry room.
It also guides the team to withdraw from the Sentry room upon sample acquisition. This procedure and changes thereto requires PSRC approval.
DISCUSSION
, This procedure ensures sample recovery with a minimum risk to personnel in a limited time frame.
The movable shield in the 85' penetration area will usually block that access route. Therefore ingress and egress may be required across the
, RCA boundary. Performance of this procedure may require the transfer -
of radioactive samples to non-RCA's. For these reasons this procedure involves exemptions from certain routine RCA access requirements. '
Personnel implementing this procedure should be covered by an SWP during an accident, drill, or drill-like training. Routine use of the I
Sentry roon is covered by the C&RP routine sampling RWP.
Particularly hazardous or unexpected conditions may occur in post accident situations. Direction by appropriate supervision rnay augment or supercede portions of this procedure because every possibility cannot be anticipated.
b d G DC0109 IX
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 V ON 3 DATE 3/26/85 PACE 2 0F 27 Tiits SES.TRY POST-ACCIDEtF SAFPLING SYSTEM i -- INITIAL ACTICNS DURING AN EMERGENCY I l'
+ i I
PREREQUISITES AND PRECAUTIONS
- 1. The Site Emergency Coordinator should pre-plan post-accident sampling with the Emergency Radiological Advisor anc the Site Chemical and Radiation Protection Ccorcinator prior to ordering a plant entry (i.e., prior to deciding to collect a post-accident sample) when unusually hazardous radiation or contamination levels are known or suspected to exist.
- 2. A sufficient number of properly qualified personnel to complete the task should bE available prior to making the post accident sample decision. This might include:
- a. Two people on the Sentry team; one of whom is a qualified C&RP Technician and the other an Unescorted Radiation Worker,
- b. A sample transporter qualified as a C&RP Technician,
- c. A count room qualified person in the TSC lab.
. 3. The Work Permit will specify protective equipment. Unless conditions warrant less stringent requirements, it is suggested that full PC's, SCBA's and accident dosimetry be worn.
4 The Sentry team will make a post-accident entry to the plant only when directed by supervision and when possessing a high range portable survey meter to permit surveying into areas of unknown radiological conditions.
- 5. The Sentry team should be informed of plant status as it pertains to significant hazards, both radiological and non-radiological, ,
along access routes.
- 6. Exposure hazards, both airborne and direct radiation, in the Sentry room should be monitored remotely for pre-entry status and locally for tracking while sampling.
- a. Use the Eberline Control Terminal (s) in either Access Control or the cold machine shop to remotely address the SPING air monitor in the Sentry room, which can be read locally.
DC0109 2X m.. -
l l
' - l DiA8tO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:A REVISION 3 DATE 3/26/85 PAGE 3 0F 27 rirts SENTRY POST-ACCIDENT SAMPLING SYSTE?i I
-- I?:.' I A.' ACTI C.',5 CUR I.'iG A.*i E.'u.w... t .
I i i .
- b. Area radiation trenitor RE-48, in the Sentry rocr car. be read in the Control 2o0., or 1cca'iy.
I
- 7. Cerrurications are vital curing a cleat e ergency. Ent y ten l r.st be aole to cer unicate witn tne Cente:1 Rocm and a;;re;:riate supe rv i s ion.
S. CiR? 7echni:fars have tr ecuired for ac:ess to arc?s anc ecui; ent re's'ad ** *n's --:6hre ard have securitj key
- ards te enter d:: !f the Sentry tea-t c:et rot
- csscis e't*er c' t ese : er 'a "a racacie aste keys e' .
c . ij o!.$i '
o thi *e r' ey Osbinet in tr ~
- 9. Me c:ntainrert isolatice valves FCV-696, 697, 698, 699 ar.d 7C0 a e ccatre eled f ror; t.ae C;ntainr:er.t Isolation Valve Parel in the 3 entry Re:r cr,1y. These switches require a key te operate. Keys are located in the Sentry room.
- C. It is i:;c-tant to ccr.dct :eraticns in an ex;editicus rae.rer
- provice ti. ely vitil plant status infer ation.
- 11. Any infcrmation dissericated at briefing or any information recorded or Sentry Status Scard may allow changes in procedure to reflect a current, trar.sient ccndition of the system.
PROCEDURE 1
l
- 1. Access te Sentry Rooe Area The Diatic Canycn Shielding Review indicates that the felicwing .
routes n.ight minimize exposures,
- a. Vic Turbine Building at 8S' Elevation DC0109 3x
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N DATE 3/26/85 FAGE 4 0F 27 T.T. s SENTRY POST-ACCIDENT !*FPLItiG SYSTE.'t
-- !!.!'! AL ACTIONS 08.' RIM N: E."EPGENCY l'
- 1) Unit I I
Starting at the Cold Machine Shop croceed into the hailway to door 7125C, proceec nor:n to accr *122 and exit building. From here turn south and enter door
=192 to the Motor Repair Shop.
FIGURE la l -- - - _- U- -
J ~
. u.
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=
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7 j { (32 )O O ame G 0C0109 4X J
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:A
, REVISION 3 DATE 3/26/85 PAGE 5 0F 27 Tirts set.TRY FOST-ACCIDENT SA!GLING SYSTEtt
-- it.ITIAL ACTl0f,5 DURING AN EMEF.GENCY t 1
I
- 2) Unit II Starting at the Cold Machine Shop proceed into the hallway to door #140, proceed scuth to door #122 and exit building. From here turn north and erter *192 to the Motor Repair Shop. ,
FIGURE lb
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otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ,
U~
DATE 3/26/85 PAGE 6 0F 27 T:TLE SENTRY FOST-ACCIDDiT SAMPLIhG SYSTEM
-- INITIAL ACTIONS OLRING AN EMERGENCY 8 l
- b. Around Turbine Building at 85' Elevation
- 1) Unit I Starting at the Cold Machine Shop proceed west to the outside via door #129, turn right and continue north around the Unit 1 Turbine Building looping around the transformers at the north end of the plant. Continue south to door #192 between containment and the Turbine Building. Enter the Motor Repair Shop via door #192.
FIGURE 2a 4 <-- -
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.-------.-----..J DC0109 6X
e o DIA810 CANYON POWER PLANT UNIT NO(S) 1 AND 2
, ON DATE 3/26/85 PAGE 7 0F 27 TITLE SENTRY FOST-ACCIDENT SAMPLING SYSTEM 4
-- INITIAL ACTIONS DUP!NG Att EMERGENCY l l 1
i s
- 2) Unit II Starting ~ at the Cold Machine Snop proceed to the outside via door A129, turn left and centinue scuth around the Unit II Turbine Building looping around the transformers at the south end of the plant. Continue north to door 4192 between containment and the Turbine Building. Enter the Motor Repair Shop via door #192.
FIGURE 2b
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{Q k ,,,,: . . . . . . . . . /
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o OO OO Oo o o O , ,n ~ ' '*
~~. tr,- -.OO o . 'l'. ' .. -
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'.~..................._..................,.r DC0109 7X
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N DATE 3/26/85 PAGE 8 0F 27 TsTLE SENTRY POST-ACCICEl.I SAMPlihG SYSTEM
-- INITIAL ACTIONS DURING AN EMERGENCY l
- c. Other Access Routes The Figure la or Ib pathway is preferred. Mcwever an ar.:ess route other than those above may be suggested by actual post accicent conditions (e.g., fire, high energy lire break, etc.) The final route selected should be directed by appropriate supervisory personnel.
- 2. Initial Set-up of Sentry Room Equipment
- a. Gas Supply Cylinders Check The gas supply cylinders for Sentry Room equipment are located along the east wall of the Motor Repair Shop.
Proceed to the gas storage rack and verify the following:
- 1) The cylinder valves are fully open for all three cylinders.
- 2) The manifold valves are fully open for all three cylinders.
- 3) The argon regulator shows tank pressura of approximately 1000 psig and the regulator is set to 100 psig.
f0TE: 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 10% H span gas cylinders should have at least 100 psig and 60th regulators should be set at .
10 psig.
- b. Emergency Ventilation System Line-up. (Optional: If proper ventilation is lined up proceed to step 2.c., Steel Shield DoorClosure.)
i li _. .
DC0109 8X t
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 E00 EP RB-15:A REVISI0f 3 .
DATE 3/26/85 PAGE 9 0F 27 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- ::::T:AL ACTIC.'.S DUP.:tiG Ati EMERGE? ICY i n
i 8
i
- 1) Climb the Icdder to the ss to enter the !
ventilation ra-- -
I w
l f0TE: Minin'ze the tire that the ve.9t r:cm doces are !
open.
21 Proceed to breaker panel PPHRS, 52-12J-35 and check all breaker: O f. .
- 2) Proceed to the motor controllers for fans and hea*ers
- 3:ee . : , e<* of t*e :-eave ca-ei a-c cusr :'
I ;? an: RESE~ cusn u:::r en ea:n crc.
21 E"ER LEAC (IS-150'. is the pre # erred systen.
=i 0:er its su:cly and exhaust dar;ers and the succly are exFaust ver.: darpers (a total of 4 car;ers) and close all other dampers, t' Push the START pushbuttcos on the meter ccatec':ers for the EMER LEAD su;cly f an, extaust f a'., and heater 29A, in tnat crder.
- 5) EMER RE00N (IS-;51) is to be used as a backup if EMER LEAL is inoperable, a) Oper, its supply and exhaust darpers and the supply and exhaust vent dampers and clcse all other dampers.
~
b) Push the START pushbutton on the motor controllers for the EMER RE0ut, supply fan, exhaust fan ar.d -
hecter 29B, in that order.
- 6) Return to the Motcr Repair Shop.
l 1
DC0109 SX l 1
k.h
. o DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S ON DATE 3/26/85 PAGE 10 0F 27 Tirts SENTRY PCST-ACCIDENT SAMPLING SYSTEM
-- INITIAL ACTIONS OURING AN EMERGENCY I :
t
- c. Stael Shield Door Closure. (Optional. If the shield dear is closed proceed to step 2.d., P.adiological Assessment.)
- 1) Pr0ceed through d0cr !!92-Af south of the Unit ! Mot:r Ra; air Sh:p, cr c::r *192-A n:rth of ths L'r.it !! Ma::r <
Repair Shep, and visually check the shield dcor's wincr.
cable. If the marked portien of the cable indicates the shield is closed return to the Motor Repair Shop and proceed with step d., Radiological Assessment below.
2' C:s#!!e the w'ccn untii tre a r'r ed --:ics :< the c r's 1
/ 's t o ;y tr.c::stes tr.e sn ie* : c or is ;;:sec.
- 3) Return to tne Mo:ce Repair Shcp.
- d. Radic!cgical Assessrent of Sentry Recm
'" all
- 1) Enter tge Sentry room via the RCA or *197 ard the watertight docr ~
2' Perform a gereral area radiation survey a) Note high levels such as might exist at the auxiliary building end of the rcom due to ECCS piping.
b) Note icw level areas for sample screen surveying later.
- 3) Note the reading of RE-48 on the Process Control Panel (PCP). Recheck it intemittently.
- 4) Monitor airborne radioactivity using the SPING. If airborne levels permit the respirator, if worn, may be removed at this time. It should be done anytime there is a potential for airborne contamination to be introduced into the room,
- e. Proceed to the Ventilation Control Panel.
- 1) Check the alarrrs.
a) Press TEST and note the red alarm indicators flash while the audible alarm sounds.
OC0109 10X
DiAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N..
DATE 3/26/85 PAGE 11 0F 27 l
TITLE SENTRY-POST-ACCIDENT S*MPLING SYSTEM
-- INITIAL ACTION 5 DURING AN EMERGENCY b) Press SILENCE to stop the audible alarm.
, c) Press ACK and note the flashing alarm indicators i
glow steadily.
d) Press RESET and note the red alarm indicators go out.
- 2) If the NORMAL VENT switch is on, turn it off.
- 3) If the EMER LEAD ventilation system is desired and is not operating depress in order the SUPPLY, EXHALST, and HEATER pushbuttons.
- 4) Observe the appropriate indicating lights for proper operation of the desired ventilation line-up.
- 5) If necessa ry, return to step 2.b. , Emergency Ventilation Line-up.
- f. Containment Atr.icsphere Sarple Line Heating
- 1) Proceed to the CCP and position the FUNCTION SELECT from 0FF to SF1-3/GGD.
- 2) Observe the following:
c) The POWER ON indicator lights.
b) The flow monitor 20*; and 100% flow lights turn -
on for approximately 25 seconds. ,
- 3) Press the PILOT LIGHT TEST pushbutton and note which lights are not functional.
d) Turn the HEAT TRACE PCKER SWITCH to the ON position.
- 5) Place the temperature select switches for EHT 196 and EFT 197 to the down position marked 260'.
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DC0109 IIX
DiAsto CANYON POWEA PLANT UNIT NO(S) 1 AND 2 Sf0N DATE 3/26/85 PAGE 12 0F 27 MLE SENTRY PCST-ACC! CENT SAMFL!t.G SYSTEP
-- INITIAL ACTION 3 CUFING AN E"EFGENCY ,
t i
1
- g. Rear Panel Access Rolling Shield Cicsure.
If the panel roiling shield is closed prcceed to step 3.,
Electrical Line-up.
- 1) Perforn this valve line-up check in the rear of the shielded panels:
CAP-V-13 CLOSED (above the G.C.) []
CAP-V-31 OPEN (adjacent to the G.C.) []
CAP-V-32 OPEN (adjacent to the G.C.) []
CASP-V-1 OPEN (overhead on cont. atmos.
supply line) []
CASP-V-2 OPEN (lower part of CASP) []
CASP-V-3 OPEN (mid part of CASP) []
- 2) Get the come-a-long from the cabinet and attach one end to the pad eye on the east wall and the other to the pad eye on the door.
- 3) Operate the ceme-a-long until the rciling shield is biccking the dcorway.
- 2. Electrical Line-up
~
Proceed to the breaker panel PYNM, located next to the Vent !
Control Panel, and check positions of breakers as follows: .
BKR #1 -
ON [] BXR #2 - ON []
BKR #3 -
ON [] BKR #4 - ON []
BKR #5 -
ON [] BKR #6 -
ON [] l BKR #7 -
ON [] BKR 88 -
ON []
BKR #9 - ON [] BKR #10 - ON [] l BKP #11 - ON [] BKR #12 -
ON []
MAIN BKR - ON []
i 9 . - .
j DC0109 12X i
l DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND,2 ON
' DATE 3/26/85 PAGE 13 0F 27 M LE SENTRY POST-ACCIDENT SAMFLING SYSTEM
, -- It;!TIAL ACTICNS DURING A'i EMERGETiCY 6 l 4 The Containment Atmosphere Hydrogen Analyzers If hydrogen in centain: rent air is to be analyzed by G.C. proceed to step 5. CMP / CAP power up.
The two redundant analyzer systems' remote panels are between the PCP and the CMP. 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 STAND 2Y. []
POTE: If the power switch is 0FF, then turn it to STANDBY and give the system six hours to werm up. If beth systems have not been in STANDBY for at least six hours, or are otherwise inoperable, use the gas chromatograph, step 5, below. Record the time of switching from 0FF to STANDBY .
- 2) Solencid operated sample lire containment isolation valve switches CLOSED. (FCV-235,236,237, 238,239,240) []
- 3) Oxygen gas tank connected and isolation valve closed. (Tank should be changed at 100 psig.) [] _
- b. H2 AnalyzerSystem(s) Operation. ,
- 1) Turn the three sample line switches.
to the OPEN position. Observe the position indicating lights. [][]
- 2) Open the oxygen tank isolation valve and adiust regulator to 27 2 2 psig. [][]
- 3) Turn the n'ain power switch from STANDBY to ANALYZE. [][]
- 4) Push the REMOTE SELECTOR pushbutton to gain control at this panel and reset COMMON ALARM, if necessary. [][]
- 5) Turn the dual range switch to the 0-10" range. [][]
DC0109 13X
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N DATE 3/26/85 PAGE 14 0F 27 Tirts- SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- INITIAL ACTIONS CUR!NG AN EMERGENCY CEL: 82 83
- 6) Adjust the ZERO and SPAN potentiometers until they agree with their respective values indicated on calibration stickers located under each potentiometer. [][]
- 7) Turn the function selector switch to SAMPLE. [][]
TIME (82) (83)
- 8) If both CEL 82 and 83 are to be used, repeat steps 4.b.1) to 7) for the second system wh,ile waiting for the first syster to stabilize, which takes approximately 6 minutes. [][]
- 9) Proceed with step 6., Initial Valve Line Up, while waiting for stabilization. When 6 minutes have-elapsed since switching to SAMPLE, continue with step 10) below. [][]
- 10) Record the analyzer meter reading, the time read, and the scale used. [][]
MeterReading(%)
Time -
Scale Used WTE: 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 if the analyzer (s) are to remain in ANALYZE or be returned to STANDBY. [][]
OTE: Advise the Control Room of the reagent gas depletion and the limited lifetime of the sample 1 pumps, which are located in the i 100' El. penetration area. ;
l
)
1 DC0109 14X
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
[VfSf0N DATE 3/26/85 PAGE 15 0F 27 TiiLE SE'.TRY POST-ACCIDENT SAMPLING SYSTEM
-- INITIAL ACT10t,5 DU^U.G At; EMEFGENCY CEL: 82 83
- c. Standby
- 1) Turn the function selector to ZERO and purge the analyzer for 6 minutes. [][]
- 2) Turn the main power switch to STANDBY. [][]
- 3) Cicse the reagent tank isolation valve. [][]
- 4) Turr. the three sample line isolation valve switches to the CLOSED position. [][]
- 5) Push Comron Alarm to Reset [][]
- 5. CMP /CAF Power Up/ Gas Chromatograph Startup
- a. At tr.e CAP aligt. V-6 and V-5 to DEMIN WATER. []
- b. Oper. V-8, V-11 and V-2. []
- c. Check the threr green root valve handles next to the CAF ccwn in the vertical position to allow Argcr, and the Sp!r gases to the CAP. .
[]
- d. Open or check open CAP-V-10 and adjust instrument air pressure to 80 2 psig. []
- e. Open or check open CAP-V-14 and adjust argon pressure to 25 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.
4} Check that the TCD at the back of the panel is 1; ]J turned Ct.,
- g. On the G.C. front panel
- 1) Select atteruation factor of 250 (25 x 10).
Place all function switches in the 0FF (out) position. []
DC0109 15X
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N3 DATE 3/26/85 PAGE 16 0F 27 TsTLE SEtiTRY FOST-ACCIDENT SAMPLIfiG SYSTEM
-- It. T!AL ACTIONS CURING AN EMERGENCY
- 2) Depress MAN and CLEAR switches. []
- 3) Enter "C0" initiating G.C. warmup.
Time on
- 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 sample.
- 2) Locate wrenches, labels, and bags. []
- b. Valve HCV-21, which is located next to the []
chemical sink, should be positioned to the TO CONTAINMENT position, except during Training or Drill when it should be positioned to the POST LOCA COLL TAhk position.
- c. Sample cooler water valve should be turned until indicator shows OPEN []
- d. At the CASP []
- 1) Install a loaded filter asser.bly into the containment air dilution system. []
~
The tubing end 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 quick-disconnects. []
b) OPEN the INLET and OUTLET valves and CLOSE the BYPASS valve on the engaged cart / cask. []
c) Connect PI-1109 (an MSIS pressure monitor) to the engaged cart / cask. Plug it in and turn the selector switch to the proper cart / cask.
Cart / Cask []
DC0109 16X
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N 3 DATE 3/26/85 PAGE 17 0F 27 7:TLE SEliTRY POST-ACCIDENT SAMPLING SYSTEM
-- Di!TIAL ACTI0t45 00RihG Ari E.uERGENCY t
- 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. []
- 6) Align CASP-DV-1 to CASP-SF-5 position. []
- 7) Install a new septum on CASP-SF-5. []
- c. At the CCP:
- 1) Adjust Np pressure' regulator to 100 psig as
~
fr.dicatet on CCP-Gl. []
t0TE: This pressure will drop to 80 psig when the eductor is on and Low N2PRESS alarm will sound.
- 2) All 11 of the CCP 3 position valve switches should be CLOSED:
AV-1 [] St-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 SAMPLE FLASK window which glows steady.
b) Rclease the TEST button and verify that the ISOLATE SAMPLE FLASK window goes off. []
OC0109 17X
T s
- OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N 3 DATE 3/26/85 PAGE 18 0F 27 TITLE SENTFY POST-ACCIDENT SAMFLIriG SYSTEM
-- ItilTIAL ACTIONS CURitiG AN DIERGEliCY 9
c) Push the ACX button and verify:
(1) the alarm is silenced. []
(2) the 3 upper windows glow steady. []
d) Push the RESET button and verify that all windows are off. []
- f. At the POST LOCA CNT ISOLATION PANEL all five key []
operated valve switches should be CLOSED.
- g. At the CAP, valves should be positioned as follows:
CAP-V-12 (open) []
Adjust nitrogon regulator until nitrogen pressure gauge is 60 t 2 psig. []
CAP-V-7 (REXNORD OXYGEN ANAL) [] l CAP-V-6 (open) []
CAP-V-6 (DEMIN WATER) [] l CAP-V-5 (CLOSED) []
CAP-V-2 (open) []
CAP-V-1 (open) []
CAP-V-29 (12 o' clock) Tcp of CAL TANKS []
CAP-V-20 (12 o' clock) Top of CAL TANKS [] ~
CAP-V-27 (12 o' clock) Top of CAL TANKS [] ~
CAF-V-15 (closed) Bottom of CAL TAfWS []
CAP-V-16 (closed) Bottom of CAL TANKS []
CAP-V-26 (closed) Bottom of CAL TANKS []
CAP-V-30 (9 o' clock) CAL TANK 1/2 Selector []
CAP-V-25 (closed) Bottom of CAL TANKS []
CAP-V-20 (closed) Bottom of CAL TANKS []
CAP-V-19 (closed) Bottom cf CAL TANKS []
CAP-V-11 (open) []
CAP-V-24 (closed) []
CAP-V-17 (closed) []
CAP-V-9 (closed) []
CAP-V-18 (closed) [] , ,
DC0109 18X
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2
' {0N DATE 3/26/85 PAGE 19 0F 27 m ts 5 ENTRY POST-ACCIDENT SAMPLING SYSTEM
-- INITI"L ACTIONS CL:lil.G AN EMERGEhCY
- h. At the Denin Module of the LSP, valves should be positiered as follows:
DM-V-1.1 (clcsed) []
DM-V-1.2 (closed) [3 DM-V-1.3 (closed) []
DM-V-3 (closed) [3 DM-VREL-1.1 (closed) []
DM-VREL-1.2 (closed) []
DM-VREL-1.3 (closed) []
- i. At the Open Grab Sanple panel of the LSP, valves should be positioned as follows:
Rkl-V-6 (closed) [3 DM-V-2.1 (closed) [3 DM-V-7.2(closed) [3 DM-V-2.3 (closed) [] l RC-V-17 (closed) [3 RC-V-6.1 (closed) [3 RC-V-6.2 (closed) [3 RC-V-5.1 (closed) [3 RC-V-5.2 (closed) [3
~
- j. At the PC Module of the LSP, valves should be positioned as follows:
RC-V-12 (12 o' clock) []
RC-V-15 (CLOSED) []
RC-V-14 (closed) []
RC-V-13 (9 o' clock) [3 RC-V-10 (9 o' clock) []
PC-V-11 (CLOSED) []
RC-DV-2 (9 o' clock) [3 PC-VREL-1 (closed) []
DC0109 19X
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ff0N DATE 3/26/85 PAGE 20 0F 27 mLE SENTRY POST-ACCIDENT SAPDLIfiG SYSTEM
-- Ih!TIAL ACI!Of.S OURING Af; EMERGEttCY RC-VREL-2 (closed) []
RC-V-3 (clcsed) []
RC-V-7 (9 o'cicck) []
RC-V-2 (closed) []
RC-V-1.1 (closed) []
RC-V-1.2 (closed) []
RC-V-1.3 (closed) []
RC-V-1.4 (closed) []
RC-V-1.5 (closed) []
RC-V-4 (closed) []
RC-V-8.1 (closed) []
RC-V-8.2 (closed) []
RC-V-16 (closed) []
RC-V-9 ,( CLOSED) [']
RC-V-18 (6 o' clock) []
RC-V-19 (BYPASS) []
. RC-V-20 (closed) []
RC-V-21 (closed) []
RC-DV-1 (BYPASS) []
RC-V-22 (TOWASTE) [] ,
- k. At the RV Module of the LSP, valves should be
- positioned as follows:
RW-V-9 (closed) []
RW-V-10 (closed) []
RW-DV-1 (BYPASS) []
RW-V-8 (BYPASS) []
RW-Y-7 (BYPASS) []
RW-V-5 (6 o' clock) []
RW-V-4 (closed) []
RW-V-3 (closed) []
DC0109 20X
r- .
. . 7 DIA8LO CANYON POWED P NT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:A
.. REVISION 3 3/26/85 DATE PAGE 21 0F 27 TITLE SENTRY FOS 7-ACCIDENT SAMPLIhG SYC*EM
-- INITI AL ' ACTIONS CLRING AN EMERGE.',CY RW-V-1.1 thrcugh RW-V-1.10 (12 o' clock) []
RW-V-2.1 thrcugh RW-2.10 (6 o'cic:k) []
- 1. At the PP0 CESS CONTRCL PANEL (PCP)
FOTE: Notify the Control Room when any valve alignments are charged.
- 1) Positien or- check the position of the following switches for valves:
FCV-9351A (CLOSE) []
FCV-93518 (CLOSE) [3 FCV-9350B (CLOSE) []
FCV-9350A (CLOSE) []
FCV-9553A (CLOSE) []
FCV-9353B (CLOSE) []
During Drill or Training the above valves shoulc be left in REMOTE.
FCV-692 (CLOSE) []
FCV-693 (CLOSE) []
FCV-694 (CLOSE) r]
FCV-1413 (CLOSE) [ -
FCV-1416 (CLOSE) []
FCV-1417 (CLOSE) []
FCV-1418 (CLOSE) []
FCV-1419 (CLOSE) []
FCV-1417 (CLOSE) []
FCV-Id10 (CLOSE) []
FCV-1411 (CLOSE) []
FCV-1414 (CLOSE) []
FCV-1415 (CLOSE) []
FCV-1420 (CLOSE) [')
DC0109 21X
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 (V ON DATE 3/26/85 I PAGE 22 0F 27 TITLE SENTRY POST-ACCIDEfiT SAMPLING SYSTEM
-- Ifl!TI AL ACTIC';S C'J0:NG M EMERGENCY
)
FCV-1421 (CLOSE) []
FCV-14:2 (CLOSE) []
FCV-1422 (CLOSE) []
FCV-1424 (CLOSE) []
FCV-1425 (CLOSE) []
FCV-624 (CLOSE) []
FCV-1426 (POST LOCA SAMPLING) - During Drill []
or Training this valve should be left in the RE 11/12 position.
+
- 2) Position switches for POST LOCA COLLECTION TANK TRANSFER PUMPS I and 2 to the STOP position. []
- 3) At the PCP a) Push the TEST button and verify:
(1) the alarm sounds []
(2) all labeled windows flash []
b) Push the ACK buttor, and verify:
(1) the alarm is silenced []
(2) all labeled windows glow steady [] _.
c) Push the RESET button and verity that all windows are off. []
- 7. Monitor Startup a'nd 02 Calibration Tank Recirculation (CAP)
- a. Dissolved 02 Calibration Tank Recirculation
- 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.
If water must be added to the tank, check closed CAP-V-12, open CAP-V-11 and CAP-V-24 and fill the tank. Close CAP-V-24. []
- 3) Open fully CAP-V-17. []
m $
DC0109 22X
DIABL9 CANYON POWEQ PLANT UNIT NO(S) 1 AND 2
[jSy0N DATE 3/26/85 j PAGE 23 CF 27 TITL5 SENTRY FCST-ACCICENT SAMPLING SYSTEM
-- INITI.2L ACTIONS CURING AN EMERGENCY 4 s .
-i
- 4) Turn the 0, CALIB. SYSTEM pump to ON position.
Indicator iichts for the pump should light on i both the CAP and CMP. [] I
- 5) Fecirculate the water for at least I heur. []
Time on
- 6) Continue to recirculate until the actual calibration is performed. []
- b. pH Monitor (CMP) h I) Place internal S-1 toggle switch to ON (up) position.
[]
- 2) Switch 5-3 to the OFF position. []
- 3) With a small screwdriver, adjust R-3 standardize control for full downward and upward deflection and then reset to a reading of 7.0. []
- 4) Switch S-3 to the ON position. []
- 5) Close door. []
- c. Conductivity Monitor (CMP) h
- 1) Observe that the meter reading is on zero when the selector switch is on ZERO. [] .
- 2) Turn the selector switch to CHECK. The meter indicator should move to CHECK on the reter scale. []
NOTE: If it does not move to CHECK, consult the Site Emergency Coordinator for directions.
- 3) Switch the selector switch to MEASURE. The monitor is now ready for operation. []
- 4) Energize for 30 minutes.
Time on DC0109 23X a.
__m_ .. _ _ _ _ . _ _ _ _ _ _
F 0Asto CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:A REVISION 3 DATE 3/26/85 PAGE 24 0F 27 TITLE SENTRY POST-ACCICENT SA." FLING SYSTEM
-- INITIAL ACTI0h5 00RihG AN EFE?GENCY
If the YSI is not to be used proceed to step e., Rexnord Analy:er.
- 1) If calibration has been performed within ene []
week, proceed to step e.
- 2) Turn POWER switch to ON. []
- 3) Turn 02FILTER to 0FF. []
- 4) Turn 0 2 RANGE to 0-20 ppm. []
- 5) Turn PEN INPUT to ZERO. []
- 6) Turn CHART SPEED to RAPID. []
- 7) Adjust the PEN ZERO control until the pen traces a line on the 0-20 chart scale at 0. []
- 8) Turr CHART SPEED to 10. []
- 9) Turn PEN INPUT to -Op . []
- 10) Energize for 30 minutes.
Time on
- e. Rexnord Analyzer l
Implement this section only if Rexnord Analyzer is to be -
used.
- 1) Adjust mechanical zero with power switch to []
unit OFF.
1 l
i i
! DC0109 24X
DIABLO CANYON POWEQ PLANT UNIT NO(S) 1 AND 2 N EP RB-15:A DATE 3/26/85 PAGE 25 0F 27 TaL2 SENTRr FOST-ACCIDET;T SAMPLIhG SYSTEM
-- INIT!;L ACT CNS DL'R:!;G AN EMERCEhCY
- 2) With power switch ON, and function selector []
switch on ZERO, adjust ZER0 ADv'. to gat zero reccing on the ir.strument.
- 3) Turn function selection switch to 20 mg/1. []
- f. Ion Chromatograph Startup FOTE: Proceed with this section only if chloride analyses is to be done at this time.
- 1) Note the level of chloride calibration []
standard (2000 ppm B as boric acid and 1 ppm chloride) in CAL-3. %
- 2) Verify that air bubbles are not visible in []
the sight glass or in tygon capillary tubing.
NOTE: If air bubbles are present, check the pumps for prime and vent; venting is required when eluent containers are filled. Refer to Procedure CAP G-3.
- 3) Verify that the following reagents are available:
EI/E2 Eluent: 2.0 g Na0H/2.4 M Na 2003 []
IN Sulfuric Acid (H2SO4 ) []
Deionized Water Rinse []
- 4) If any of the reagents listed in step 3 is not [] -
available or has not been prepared within the last 30 days, refer to Appendix 1 for details of reagent preparation.
- 5) At the CMP place the POWER and AIR switches []
to ON position.
DC0109 25X
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 Sf0N DATE 3/26/85 PAGE 25 0F 27 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEP
) -- INITIAL ACTIONS DURING AN EMERGENCY
- i
- 6) Place LOAD / INJECT switch in the LOAD position. []
- 7) Place the E-2 switch in the UP position. []
- 8) Place the SEPARATOR switch in the SEP-1 position. [ ]
- 9) Place the SUPPRESSOR switch in the SUP-1/RGN-2 []
position.
- 10) At the CAP set MODE switch to ZERO and verify []
needle points to 0.
NOTE: If.not at ZERO, adjust to ZERO with the screw below the meter face.
- 11) Set MODE switch to CAL and verify needle []
swings full scale.
f0TE: If adjustment is necessary, adjust using the screw at the top of the circuit board (the one labeledMETER).
- 12) Set MODE switch to zero. []
- 13) Set the uMHO FULL SCALE switch to 30. []
- 14) Check if eluent pump setting is 40 percent. []
- 15) At the CMP turn the eluent pump switch to []
ON position. -
- 16) Turn GAUGE switch to ON position. If reading []
on ELUENT PUMP DISCHARGE PRESSURE is very l .
l low, check capillary lines for air (CAP G-3).
- 17) Allow system to warm up and stabilize for
- 30 minutes.
l Time on
- 8. Sampling may now conmence using specific sampling procedures.
l APPENDICES
- l. 1. Reagent Preparation
^
DC0109 26X
OtA8LO CANYON POWER PLANT UNIT NO(S) ,1 AND 2
, ON DATE 3/26/85 )
PAGE 27 0F 27 :
TITLE SEi;TRY POST-ACCIDENT SAMPLItiG SYSTEM
-- II.ITIAL ACTIC .5 CURI?;G At; EMERGENCY !
APPENDIX 1 REAGENT PREPARATI0h N]TE: Reagents rust be made using demin water with a conductance of less than 1 tmho.
- 1. E1/E2 Eluent - 2rM NaOH/2.4m?i Na 2 CO3 Add 0.329 Na0H and 1.00g Na 7 CO, (anhydrous) to 4.0 liters of derineralized water, dissolve End mix.
- 2. lti Hg 50 4 Add with stirring 120 ml of concentrated sulfuric acid to a liters of denin water and cool. Trarsfer the solution of a 4 liter collapsible container, remove excess air, and label ccr.tainer with initials and date. Cennect it to the line REGEN SYSTEM-1. Open the container valve and vent pump inlet lir.es.
- 3. Demineralized Water Rinse Fill a four (4) liter collapsible container with demin water.
Remove excess air from the bottle and label. Connect it to the water line in the reagent storage facility. Open the container valve and vent pump inlet lines.
- 4. Chloride Standard
~
Add 2m1 of 1000 ppm chloride standard and 22.9 d 0.1g H3 80, to twe separate 2 liter volumetric flasks. Dilute each flask to'the .
mark, with demin water. The cal tank holds 3.5 liters.
l i
- DC0109 27X
+
NUMBER EP RB-15:8 PG943 Pacific Gas and Electric Company REVISION 2
[O!) ceca TMENT OF NUcLEAA PLANT OPERATIONS
~
c PAGE 1 0F 12 I
- !!',i. ciAno cxuos PowEn PLANT ut.
- 7 NOcs) 1 A~. - ,, 4 h..,;, EMERGENCV PRCCE0!;RE j
, p3, 3E:,TRY P037-AC:i;Et,T SA;su r.G s e siEM OE;crea i lg ;;;;s COOLANT SAMPL NG (STRIPPED-GAS AND DILUTED RCS)
AoonovEO N0 O' 3/6 WE j PLANT MANAGER g ' DATE l
DISCUSSION The purpose of this procedure is to detail the steps requtred to sample liquid and to strip gas frem the reactor coolant. This procedure will further detail the steps required to prepare a sample for H., analysis. This procedure requires operations at the LSP, CAP, and CMP panels. A complete flush of the modules will be done after the sample has been processed and system will be returned to initial lineup status.
PREREOUISITES .
- 1. System was initially lined up as described in Procedure EP RS-15:A.
- 2. Verify that the following annunciator windows are off on the PCP:
- a. REACTOR COOLANT SAMPLE COOLING WATER LOW FLOW
- b. REACTOR COOLANT SAMPLE COOLING WATER LOW PRESS
- c. REACTOR COOLANT SAMPLE COOLING WATER HIGH TEMP
, d. REACTOR COOLANT PURGE HIGH TEMP
- e. REACTOR COOLANT SAMPLE WATER HIGH TEMP
- f. LIQUID SAMPLE PANEL HIGH PLENUM PRESS
- g. CHEM ANALYSIS PANEL HIGH PLENUM PRESS
- 3. The followir.g equipment must be available and operational:
- a. Meter-lorg reach rod
- b. Hand operated vacuum pump DC0124 IVI
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
.- f0N DATE 3/21/85 PAGE 2 0F 13 m tE. SENTRY POST-ACCIDEtiT SAMPLIfiG SYSTEM REACTOR CCCLA';T SA"PLIfiG (STRIPPED-GAS AND DILUTED RCS)
- c. Gas bottle griptcng
- d. Sample cart / cask
- e. A pre-labeled 60 mi sample bottle with a new septum and 14 cc gas sample bottle f0TE: The labels should have the sample source, date, estinated time of the sample, and the initials of the person taking the sample. (From this point estima'.e 20 minutes.)
- 4. The gas chromatograph must be in a standby mode with a valid calibration.
Assign one LSP operator to EP RB-15:D to prepare the G.C.
PRECAUTIONS
- 1. See EP RB-15:A for details.
- 2. This sampling invcives processing of water that will be highly radicactive. Precautions should be taken to prevent skin' contact or ingestion.
- 3. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush period, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose area.
~
- 4. A dose rate instrument should be on and periodic monitoring is suggestec during purge and sampling exercises. .
- 5. The LSP operator must verify that the gas chromatograph is ready to receive a gas sample before opening valve RC-V-15. Valve RC-V-15 must be closed after filling all G.C. sample loops and prior to performing diluted gas sampling and final flushing operations.
! CC0124 2VI
~
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:B REVISION 2 DATE 3/21/85 PAGE 3 0F 13 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM REACTCR CCOLANT SAMPLING (STRIFFED-GAS A:.0 DILUTED RCS) .
PROCEDURE
- 1. Verify RC-DV-1 is turned to BYPASS. Fill reservoir []
RC-R-1 with demin water:
- a. Open RC-V-20 and RC-V-21. []
- b. Adjust reservoir RC-R-1 until the water level in graduated cylinder RC-C-1 is over 100 mis. []
- c. Close RC-V-21 and RC-V-20. []
- 2. Verify that the following valves are closed:
RC-Y-1.1 thrcugh 1.5 []
RC-V-4 []
- 3. Insert the neecle of the hand operated vacuum pump into the septum of the prelabeled 60 m1 sample bottle: []
- a. Evacuate to the maximum vacuum achievable with the hand pump. The vacuum must be at least 15" of Hg. []
- b. Keep the pump connected to the bottle for 3 rinutes to assure that the bottle retains the vacuum. []
- 4. Turn on the switch to light the diluted bottle fill station. []
- 5. Remove the bottle from the vacuum pump and place -
bottle on the cart / cask assembly cavity piston. []
- a. Turn the direction valve for the hydraulic piston to the down position and lower the bottle into the cask cavity. []
- b. Close and open the cask to verify that the cover is working properly. []
- c. Position the cart / cask under the diluted reactor coolant fill station needle and set the brake. []
DC0124 3VI
=
1 1
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 S Ofi DATE 3/21/85 i PAGE 4 0F 13 ;
TITLE SEtiTRY POST-ACCICENT sat <PLING SYSTEM REACTOR l C01A:;T SAMPLIllG (STRIPPED-GAS AliD DILUTE: R 5) ;
i
- d. Turn the direction valve for the hydraulic piston to the uo position and raise the bottle onto the needle. []
- 6. At the PCP verify that the sample cooler water ficw, temperature, and pressure annunciator lights are off. []
- 7. Open the following valves:
RC-V-9 []
RC-V-8.2 [j RC-V-10 []
- 8. Drying Expansion Vessel CAllTION: Adhere to directions for clockwise and counterclockwise movement of valves,
- a. Turn RC-V-11 clockwise to 3 o' clock position. []
- b. Pull open RC-VREL-2. When there is a sharp increase in pressure indicated on RC-G-3, release RC-VREL-2. []
- c. Adjust RC-VREL-2 until RC-G-3 indicates approximately 20 psig. Dry RC-EV-1 with argon for 1 minute. []
~
- d. Turn RC-V-11 counterclockwise to the 9 o'cicek position to permit RC-EV-1 to vent, then close RC-V-9. []
- 9. Gas Extraction and Line Evacuation
- a. Install the prelabeled, diluted gas sample bottle on the front panel needle. []
- b. Open RC-V-13 and then open RC-V-12 and evacuate until RC-G-2.1 and RC-G-2.2 indicate a minimum of 22" of Hg. []
- c. Turn RC-DV-2 to the 6 o' clock position and continue the evacuation until RC-G-2.2 indicates l the same reading as RC-G-2.1 or a minimum of
! 22" of Hg. []
- DC0124 4VI
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:B REVISION 2 DATE 3/21/85 PAGE 5 0F 13 TITLE . SENTRY POST-ACCIDENT SAMPLING SYSTEM REACTOR COOLANT SAMFLING (STRIP 3ED-GAS AND DILUTED RCS) 4 l
i
- d. Close in order:
RC-V-13 RC-V-10 I3 I'
RC-V-12 lb Wait for a minimum 2 minutes to Verify vacuum is holding. []
Record the vacuum on RC-G-2,1 " of Hg. []
- e. Turn RC-V-11 clockwise to the CLOSED position. []
- f. Turn RC-DV-2 to the 9 o' clock position. []
- g. Open RC-V-74 and verify the pressure on RC-G-2.2 is approximately 1 psig. []
- h. Close RC-VREL-2. []
- 10. 'Re?ctor Coolant Sanple Line Purge
- a. Open RC-V-8.1. []
- b. Determine which sample source isolation valves will have to be opened from the list below:
SAMPLE SOURCE CONTAINMENT ISOLATION VALVES Hot Legs Loops 1 and 4 FCV-9356A and FCV-9356B -
Pressurizer Steam Space FCV-9354A and FCV-93546 Pressurizer Liquid Space FCV-9355A and FCV-93552 RHR Pumps Discharge N/A Volume Control Tank N/A l
- c. Call the Control Room and have operations block []
open the apprepriate containment isolation valves.
l
- d. Open the corresponding remote plant isolation []
valve (RPIV) and remote source isolation valve (RSIV) at the PCP (see Appendix 1 for proper valve).
- e. Close the remote flush isolation valve (RFIV). []
DC0124 SVI
- - ,n-
NUFBER EP RB-15:B 1 AND 2 OIABLO' CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 3/21/85 PAGE 6 0F 13 7,7tg SENTRY POST-ACCIDENT SA : FLING SYSTEM REACTOR CCOLANT SA"PLING (STRIPPED-GAS AND DILUTED RC5,!
i NOTE 1: The sample scurce valves are labeled RC-V-1.1 through RC-V-1.5. Throughout this procedure, the forn 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.
NOTE 2: Upon implementation of the next step, sample will be flowing into the back of the LSP. The meter-long reach rod should be used to operate valves and a dose rate survey should be done to monitor radiation levels.
- f. Open the sample source valve RC-V-1.X (see Appendix 1 for p*oper valve). []
- g. Open RC-V-3. []
- h. Slowly open RC-VREL-1 until RC-FI-1 indicates 100% flow or 1900 cc/ min. Purge for 9 minutes.
. []
- i. Slowly close RC-VREL-1 until RC-FI-1 indicates 36% or 700 cc/ min. Continue the purge for 1 minute. []
- j. Close RC-V-3. [].
- 11. Reactor Coolant Sampling
- a. Align RC-V-22 to CHEM PANEL. []
~
- b. At CAP align'V-6 and V-5 to LIQUID SAMPLE. []
- c. Open RC-V-2. []
- d. Adjust RC-VREL-2 until RC-FI-2 indicates 100%
flow or 200 cc/ min. Purge for 3 minutes. []
- e. Close RC-V-8.2 and record time . []
- f. Close RC-V-8.1 []
- g. Open RC-V-7 and continue purge to CAP. []
- h. Turn RC-DV-1 to SAMPLE. []
mm G DC0124 6VI 8
e
OtABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE '3/21/85 PAGE 7 0F 13 T6T - E?iTRY POST-ACCIDEiii SMPLING SYSTEM REACTOR
, CCOLANT SAMFLING (STRIPPEO-GAS A?iD CILUTED RC3) ,
i
- 12. CAP Analyses
- 3. One cperator car. new analy:e pH/ Conductivity /00
! according to EP RS-15:H Step 3. Sample Analyses. Subsequently chloride can be determined according to EP RB-15:G.
- b. Ore operator can continue with the liquid sampling procedure.
- 13. Liquid Sample Dilution
- a. Read initial ml on buret . []
- b. Crack open RC-V-21, and add 23 mis of water from the graduated cylinder RC-C-1 to the sample bottle, then close RC-V-21. []
Read final ml .
Determine total ml added .
- c. Turn the RC-DV-1 to BYPASS. []
- d. Place the direction valve for the hydraulic piston in the down position and lower the sample into the cask. []
- e. Close the cask. []
- 14. Sample Cask / Cart Removal
- a. Release brake and remove the cart / cask from the sample station and place in temporary hold area. []
- b. Perform a radiation and contamination survey on the cart / cask assembly. []
- c. Turn off the diluted fill station light. []
m $
4 DC0124 7VI a -
'1 e
1 AND 2 fiUMBER EP RB-15:B DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 3/21/85 PAGE 8 0F 13 m t'e SENTRY FOST-ACCIDENT SAMPLING SYSTEM REACTOR CCCLANT SA"FLIliG (STRIFFED-3AS A.;D DILUTED RC3) ,
)
< l 2
- 15. Gas Stripping Operaticr.
- a. Open RC-V-9, wait approximately 5 secer.cs, and close RC-V-9. []
- b. Open RC-V-16. []
- c. Snap open RC-V-9 and wait for 1 minute. []
- d. Close RC-V-16 and then.close RC-V-9. []
- e. Turn RC-V-11 counterclockwise to the 9 o' clock []
position. The pressure reaaing is normally between 5 and 10 psig. Record the reading en RC-G-2.1.
RC-G-2.1 psig
- 16. Diluted Gas Sampling
- a. Turn RC-DV-2 to the 6 o' clock position and wait until the pressure on RC-G-2,2 returns to 1 psig. []
- b. Turn RC-DV-2 to the 9 o' clock position. []
- c. Close RC-V-14. []
h
- d. Remove the griptong containing the diluted gas []
sample and store. Inform PASS Supervisor that the diluted offgas sample is available for transfer, ,
WTE 1: The sample is now ready for analysis in the Gas Chromatograph.
l WTE 2: The G.C. operator should be at Step 4.f. of EP RB-15:D.
i It DC0124 8VI
I AND 2 NUMBER EP RB-15:8 DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 3/21/85 PAGE 9 0F 13
."' g'e SEiTRY PCST-ACCIDENT SAMPLING SYSTEM REACTOR CCCLANT SA"PLING (STRIPPEC-GAS ANO DILUTED RCS) <
l
- 17. Stop here and analyze the sample according to EP RB-15:D. []
Direct the G.C. operator to align RC-V-15 to "LS? to GAS CHRCMAT".
- 15. Do not proceed to tne next step until the offgas sample is complete.
- 19. Call the control room and have operations close []
the containment isolation valves openad earlier if needed.
- 20. Final Flushing
- a. Verify RC-V-15 is in the CLOSED position. []
- b. Turn RC-V-11 cour.terclockwise to the 6 o' clock position. []
- c. Open the following valves:
RC-V-9 ;
RC-V-7 '
RC-V-8.1
- d. Adjust RC-VREL-2 until RC-FI-2 indicates 100%
ficw or 200 cc/ min. Flush with demin water for 1 minute. []
- e. Open RC-V-8.2. []
~
- f. Close RC-V-9 and RC-V-7. []
A
- g. Adjust RC-VREL-2 until RC-FI-2 indicates 100%
flow or 200 cc/ min. Flush with demin water for 3 minutes. []
- h. Close RC-V-8.1. []
1 DC0124 9VI
NUMBER EP RB-15:B 1 AND 2 otAaLO CANYON POWER PLANT UNIT NO(S) REVISION 2
. DATE 3/21/85 PAGE 10 0F 13 7,7 t'e SEtiTRY POST-ACCIDEtiT SAMPLItiG SYSTEM REACTOR CCCLAt4T SA"7 lit,G (STRIPPED-GAS AtQ DILUTED RCS) ; ;
! i f
- i. Turn RC-V-11 counterclockwise to tne 3 o' clock position. []
- j. Open RC-V-9. []
- k. Full open RC-VREL-2. []
- 1) When there is a sharp increase in pressure indicated on RC-G-3, release RC-VREL-2. []
- 2) Adjust RC-VREL-2 until RC-G-3 indicates 20 psig. []
- 3) Flush with argon for 3 minutes. []
- 1. Close RC-V-9. []
- m. Open RC-V-10. []
- n. Turn RC-V-11 counterclockwise to the 9 o' clock position and allow RC-EV-1 to vent. []
- o. Close RC-V-10. []
- p. Turn RC-V-11 clockwise to CLOSED. []
~
, q. Open RC-V-8.1. []
- r. Adjust RC-VREL-2 until RC-FI-2 indicates 100% flow or 200 cc/ min. [] _
Flush with demin water for 1 minute. [] .
- s. Close RC-V-2. []
- t. Open RC-V-1.X and flush with demin water for 5 minutes. []
- u. Close RC-V-1.X. []
m e DC0124 10VI
0Asto ANYON PCWER PLANT UNIT NO(S) 1 AND 2
. h0N DATE 3/21/85 PAGE 11 0F 13 TIT d SENTRY POST-ACCIDENT SAMPLING SYSTEM REACTOR CCCLANT SAGLING (STRIPPED-GAS AND DILUTED RCS) 1 1
- v. Terminate flushing by closing the following valves. []
RC-V-8.1 []
RC-V-8.2 i7 RC-VREL-1 '1 RC-VREL-2 '
RC-V-4 ll ))
- 21. At the PCP, close the remote flush isolation valve. [~ ]
- 22. Close sample cooler water. []
- 23. Turn off any fill station lights. []
- 24. Turn off emergency ventilatien. []
- 25. Serple transfer. []
- a. Transfer the diluted off-gas sample to the TSC. []
- 26. Precess the data according to Procedure EP RB-16:F. []
- 27. Check with OSC for any changes in conditions then exit []
Post Loca Room with the same precautions as access.
- 28. .When exiting through Motor Repair Shop close the []
bottle Isolation Valves for the Sentry gas supplies. -
- 29. If this procedure has been used for a drill or training -
the following steps should also be included:
- a. Reopen LSP shield door by attaching come-a-long []
and strap to other end and open.
- b. Release brake on wench next to motor repair shop. []
- c. Take ccme-a-long and strap te penetraticn shield []
door, attach to door and eye ball in floor and open door. Return come-a-long to Sentry Room.
- d. Restock Emergency Locker on 85' Elevation with []
any clothing, dosimetry or respirator /facemasks used during the drill.
DC0124 11VI w
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:B REVISION 2 DATE 3/21/85 PAGE 12 0F 13 TITL5 SENTRY FOST-ACCIDENT SAM? LING SYSTEM REACTOR CCOLANT SAMPLING (STRIPPED-GAS AND DILUTED RCS) g i 4 I t
- e. Return keys to Rad Foreman's office. []
REFERENCES
- 1. Sentry Equipment Corp. High Radiation Sampling System Operating and Maintenance Manual.
APPENDICES
- 1. Valves for Obtaining Samples from Reactor Coolant.
i l
i
(
l DC0124 12VI l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
. Sf0N 1 DATE 3/21/85 PAGE 13 Oc 13 TITLE SENTRY POST-ACCICENT SAMPLING SYSTEM REACTOR j COOLANT SAFPLING (STRIPPED-GAS ANC DILUTED ROS) l APPENDIX 1 1 VALVES FOR 0 STAINING SAMPLES FROM REACTOR COOLANT l REMOTE PLANT REMOTE SOURCE REMOVE FLUSH LSP SAMPLE SAMPLE ISOLATI0t. VALVE ISOLATION VALVE ISOLATION VALVE SOURCE VALVE l SOURCE (RPIV) (RSIV) (RFIV) (SSV)
RC Hot Leg 1 FCV-9351 A FCV-692 FCV-1416 RC-V-1.1 RC Hot Leg a FCV-9351 B FCV-692 FCV-1416 RC-V-1.1 PZo Liquic FCV-9350 B FCV-693 FCV-1417 RC-V-1.2 PZR Steam FCV-9350 A FCV-694 FCV-1418 RC-V-1.3 RHF. Pump 1-1 Discharge FCV-9353 A FCV-1413 FCV-1419 RC-V-1.4 RHP Pump 1-2 Discharge FCV-9353 S FCV-1413 FCV-1419 RC-V-1.4
. VCT Liquid N/A FCV-1412 FCV-1420 RC-V-1.5 e
{
DC0124 13VI
~
NUMBER EP RB-15:C 7 G5#3 Pacific Gas and Electric Company REVISION 2 b CEPAmivENT ce Nuct. EAR PLLNT CPERATICNS I S
[ ciasto CANYON ocwEn ptanT UN:T nets) 1 AND 2 l
(,-!' i t EMERGENCY PROCEDL!RE 1 St41 SENT Y DO"T-*.CCIDE' 7 Sav:Lp;.*, Sy3TEv '
I Ey ! TiTus CC';TA!NME:.T AIP. SA;' FLING APPROVED - " E 5 PLANT MANAGER j DATE DISCUSSION The purpose of this procedure is to detail the steps required to make ccntainment air available for gas chromatography and to dilute a containtrent air sample for isotopic analysis of noble gases, particulates, and radionuclides. This procedure will also detail the steps for a complete system flush and return to the initial valve line up.
After purging containment air through the G.C. and loading the diluter valve, this procedure will direct sampling personnel to EP RB-15:D, for gas analysis and to procedure EP RB-15:E, for preparation of the diluted containment air sample for isotopic analysis.
The containment isolation valves FCV-698, FCV-699 and FCV-700 are controlled from the Containment Isolation Valve Panel in the Sentry Room only. These switches require redundant keys to operate. Copies of the keys are located in the Control Room and in the Sentry Room.
PRERE0VISITES
- 1. System was initially lined up as described in procedure EP RB-15:A.
- 2. Verify that the following annunciator windows are off on the PCP:
- a. LIQUID SAMPLE PANEL HIGH PLENUM PRESS
- b. CHEMICAL Af1ALYSIS PANEL HIGH PLENUM PRESS
- c. CONTAINMENT AIR SAMPLE PANEL HIGH PLENUM PRESS DC0124 IVI
, . l 01Asto CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:C l
.- REVISION 2 DATE 2/25/85 PAGE 2 0F 8 TITLE SENTRY POST-ACCIDENT SMPLING SYSTEM l
CONTAIN. met.T AIR SAMPLif,G
- 3. The following equipment must be available and operational:
- a. Meter-long reach rod
- b. A gas tight 5cc locking syringe
- c. A 14cc gas vial with a new septum installed
- d. Bags, tape, and labels
- e. Four channel MSIS Pressure Monitor (CASP-PI-1109)
- f. Two crescent wrenches
- g. Spare filter assemblies
- 4. Prior to initiating this analyses procedure the G.C. must be prepared according to EP RB-15:D, and needed Calibration Verifications must be completed.
PRECAUTIONS ,
- 1. This sampling involves processing of containment air that may be highly radicactive. Precautions should be taken to prevent releases to the sampling environment.
- 2. Time in a radiation field should be limited to that necessary to perform the 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 rate area. -
~
- 3. A dose rate instrument r.hould be on and periodic monitoring is suggested during purge and sampling exercises.
PROCEDURE
- 1. Sample Flask Evacuation NOTE: Ensure that a loaded filter assembly is installed.
- a. Close outlet valve of the engaged cart / cask. []
- b. Verify that any unused CASP ports located at []
the base of the CASP have been capped.
mm e i DC0124 2VI
otAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fPRB-15:C DATE 2/25/85 PAGE 3 0F 8 TITLE - SENTRY POST-ACCICENT SAMPLING SYSTEM l CONTAINMENT AIR SAICLI!,G I l
l
- c. At the CCP, place the switch for CCP-AV-1 to OPEN. []
.OTE: This allows containment pressure to be me % ored on CASP-PI-1109.
- d. Chsnge the positions of the following valves:
CAliP-DV-1 to Containment Supply []
CASP-V-16 to CASP-SF-5 []
- e. Centact the Control Roon and request permission to open FCV-700, the sample return containment isolation valve. In succeeding steps FCV-698 and 699 and will be operated also.
Inquire whether the Control Room wants to be notified every time each valve is operated or only when sampling is conpleted and containment isolation valves are closed. Also ebtain and record containment terperature and pressure from the Control P.oem.
- F psi 9
- f. Evacuate CASP-SF-5 by opening the following valves:
FCV-700 (key operated - keys located in top []
drawer by sink)
CASP-V-17 [] _.
CCP-AV-2 []
CCP-SV-10 []
- g. When CASP-SF-5 pressure is as low as apparently []
achievable as indicated on CASP-PI-1116, align CASP-V-16 to CASP-DV-1. If vacuum is not held, replace the filter assembly or septum and repeat Steps c. through f.
- 2. Sample Purge
- a. Open containment isolation valves FCV-699 and []
FCV-698 at the Containment Isolation Valve Panel and notify the Control Room, if requested.
DC0124 3VI E.
- DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 fSf0N DATE 2/25/85 PAGE 4 0F 8 TITLE SENTRY POST-ACC10ENT SAM? LING SYSTEM j CO.'. TAI WENT A 7 Sui; LING .
! I
- b. Containment air is new being purged through []
the sample canel back to containment. Purge fcr 5 minutes.
- c. At the CCP, close CCP-SV-10 and record containment air pressure as indicated on CASP-PI-1109 and sample time.
CASP-PI-1109 psig l Sample Time b
- d. Record the temperature indicated on THT 196.
C
- e. The G.C. should be ready to accept a sample at point EP RS-15:D Section 4.F.
- f. Continue with Sample Analyses using EP RB-15:D.
- 3. Sample Dilution
- a. Align CASP-DV-1 to CASP-SF-5. N7 will flush []
the sample aliquot into CASP-SF-5 througn the removable filter assembly.
- b. When the pressure in CASP-SF-5 as indicated on []
CASP-PI-1116 is 14.70 psia, or as high as achievable, whichever is first, close CASP-V-17.
4 Initial Flushing
- a. If the G.C. was used for containment H analysis then perform the following steps, othemise2 skip to Step b.
- 1) At the LSP, align RC-V-15 to CASP TO GAS []
CHRCMAT position.
- 2) At the G.C. control panel, enter "13" to []
start argon flush of sample line back to CASP. Flush for 2 minutes.
- 3) Terminate argen flush by entering "14" at []
the G.C. control panel.
- 4) At the LSP, align RC-V-15 to CLOSED position. []
DC0124 4VI
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
, ON-2/25/85 DATE PAGE 5 0F 8 TITLE SDiTRY POST-ACCIDENT SAMPLING SYSTEM CCNTAID'ET.T AIR SAMPLING s
- b. Align CASP-V-16 to CASP-SF-5. []
- c. Open CCP-SV-10 and flush removable filter assembly []
for 1 minute,
- d. Close containment isolation valve FCV-699. []
- e. Open CCP SV-5. []
- f. Change the positions of the following valves:
Align CASP-DV-1 to Containment Supply []
Align CASP-V-16 to CASP-DV-1 []
- g. At the CCP, close CCP-AV-2 and CCP-SV-5.
- h. Open containment isolation valve FCV-699 and []
flush line with nitrogen for 2 minutes. Notify the Control Room that this valve was cpened, if requested to earlier. ,
- i. Close CCP-SV-10 and CCP-AV-1. []
- 5. Sample Handling
- a. Survey the removable filter assembly and CASP-SF-5 []
to determine contact dose rates.
NOTE: Under worst case conditions, the contact dose rate of -
the filter, using a teletector, will be about 165 mR/hr. The contact dose rate at centerline of '
CASP-SF-5 will be about 44 mR/hr.
- b. Position the exhaust duct as close as possible to []
the removable filter assembly,
- c. Using the crescent wrenches, disconnect the []
filter assembly from the system, then separate the assembly into two halves and place the two halves in a bag, seal, and survey.
- 1) Place a prewritten label on the bag. The []
label should have the name of the sample, dose rate, time, containment air pressure, and the initials of the sampler.
--4 DC0124 SVI
OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/25/85 PAGE 6 0F 8 TITLE. SENTRY POST-ACCIDEtiT SAMPL!NG SYSTEM j C0tiTAlt; met.T AIR SAMFi.ItiG
- 2) Store the sample to minimize exposure frem []
it.
- 3) Inform PASS Supervisor that CA sanple is []
ready for transport. l t-
- d. Install a new filter assembly into the system []
making sure the connections are tight,
- e. Partially evacuate a septum sealed 14cc gas vial []
t'y withdrawing 2cc from it using a syringe.
- f. Flush a 5 ml gas tight syringe by inserting its []
needle into the septum of CASP-SF-5, withdrawing Icc and injecting it a5ain.
- g. Using the flushed syringe withdraw a 2cc sample []
aliquot from CASP-SF-5.
- h. Inject the syringe contents into the evacuated []
14cc gas vial,
- i. Place the gas vial into a bag, seal and survey it. []
- j. Place a prewritten label on the bag. The label []
shall have the name of the sample, dass rate, time, cont, air pressure, volume of 1 ml and the initials of the sampler.
- k. Store the sample to minimize exposure from it. [] -
- 6. Final Flushing -
- a. Align CASP-V-16 to CASP-SF-5. []
- b. Open the following valves:
CCP-AV-2 []
CCP-SV-10 .
[]
CASP-V-17 []
- c. Evacuate CASP-SF-5 until vacuum is as low as []
achievable as indicated on CASP-PI-1116
- d. Close CCP-AV-2 and allow 2N to fill CASP-SF-5. []
DC0124 6VI
O!A8LO CANYON POWER PLANT UNIT NO(S) I'AND 2
, h0N DATE 2/25/85 PAGE 7 0F 8 m LE SENTRY POST-ACCIDE!!T SAMFLING SYSTEM i CC:; TAI.'iMENT AIR SA:'FLIfiG I
d
- e. Repeat Steps 6.b. through d. above once more. [] l
- f. Close CCP-SV-10. []
- g. Open the CUTLET valve en the engaged cart / cask. []
- h. Open CCP-SV-10. []
- i. Open CCP-SV-1.2 and allow2 N to flush the line []
for 2 minutes.
- 7. Terminate flushing by closing the following valves:
CCP-SV-10 []
CCP-SV-1.2 []
F
- 8. Change the positicns of the following valves:
CASP-V-16 to CA.SP-DV-1 []
CASP-DV-1 to CASP-SF-5 []
- 9. Turn 0FF and disconnect the CASP-PI-1109, MSIS []
Pressure Monitor connected to the cart / cask.
- 10. At the Containment Isolation Valve Panel CLOSE the following valves and notify the Control Room that they are closed:
FCV-698 [] _
FCV-699 [] -
FCV-700 []
- 11. At the CCP turn the FUNCTION SELECT switch to 0FF []
and deenergize the heat tracing.
the power switch to 0FF.
- 13. Process the data according to procedure EP RB-15:F. []
- DC0124 7VI I
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:C REVISION 2 DATE 2/25/85 PAGE 8 CF 8 TiTts SENTRY POST-ACCIDENT SAMPLING SYSTEM CONTA:NMENT AIR SAP? LING REFERENCES
- 1. NUREG 0737
- 2. Diablo Canyen Shielding Review.
A B
1 DC0124 8VI
- - - - 9- - - -
NUMBER EP RB-15:D p(27y42 Pacific Gas and Electric Company REVISION 2
,- DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 2/25/85
^
- CIABLO C ANYON POWEA PL ANT UN;T NO(S) 1 AND 2 j EMERGENCY CFERATII.C PROCEDURE i q[.y; jg SEliT?.Y FCST-ACCIDENT SAMPLING SYSTEP i s..a. 7;rcE -- SA5 Ch;0MATOG4 W IC AriALYSIS 't
.y AopagvEO % [$ h d--.
PLANT MANAGER l 3/
DATE
((
j 4 -
DISCUSSION The purpose of this procedure is to detail the steps required to determine the dissolved hydrogen concentration in reactor coolant, the percent hydrogen concentration and oxygen concentration in containment air by gas chromatography. This procedure will detail gas analysis from RC-V-15 on the LSP to the Gas Chromatograph. The sample gas for analysis should be prepared according to any of the following procedures:
EP RB-15:D EP RE-15:C PRE;ECUISITES
- 1. The Gas Chromatograph (G.C.) should be in the ON or STANDBY condition for a minimum of 30 minutes before sample analysis.
F
- 2. Carrier gas (Ar) should be available with cylinder outlet pressure 1000 psig.
PRECAUTIONS
- 1. Mor.itoring with a dose rate instrument should be done during the transfer of sample to the G.C.
If the carrier gas cylinder errpties while the G.C. is in use, the thermal conductivity detector (TCD) protection device will turn off the current to the TCD.
DC0109 1VIII
DIABLO CANYON POWER PLANT U'N IT NO(S) 1 AND 2 '
, f[0N DATE 2/25/85
- PAGE 2 0F 10 TITLE . SENTRY FCST-ACCIDENT SAMPLING SYSTEMS
-- GAS CHRCMATOGRAPhlC ANALYSIS PROCEDURE
- 1. Analysis Program I
- a. Release all pushbuttons and depress the CLEAR []
button.
- b. Check that the following program is in memory []
by entering the two digit STEP number and verify that the TIME and CODE numbers are as shown below. Do this for each STEP. If the memory is correct, proceed to Step 2. Platen Stabilization.
i/ STEP TIME CODE
' I
+
01 00:01 03 02 00:02 25
, 03 00:10 01 04 03:00 00 i
- c. If the program is not correct, enter the program as follows:
- 1) Depress ENTER and CLEAR []
- 2) Enter the above program into memory, by []
entering the two digit pairs in the sequence r shown above, for one line.
I L f0TE: If an entry error is made, depress CLEAR to L blank display and re-enter the entire line. _
f
- 3) Release ENTER, depress CLEAR and repeat []
Step 1.b. ,
- 4) Repeat Steps 1) through 3) for remainder []
of lines as necessary.
, d. If technician deems it necessary to change programing times to accomodate peaks, they may be varied with identification on: trace as./ to actual program used.
- 2. Platen Stabilization
- a. Depress MAN and CLEAR []
\
m -
j ;0C0109 2VIII I
^
m E
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h0N 2 DATE 2/25/85 PACE 3 0F 10 TITLE SEi;TRY PCSI-ACCIDENT SAMPLING SYSTEMS !
-- GAS CHRCMATC5EAFh:C ANALYSIS l I
- b. Check to see if the G.C. has stabilized by doing the following:
- 1) Select attenuation factor of 250 (25 x 10) []
- 2) Enter "01" and then "35" to display set []
point of platen temp and record for a minimun of 30 seconds.
- 3) Enter "45" to display actual platen temperature []
and record for a minimum of 30 seconds.
POTE: Stabilization is complete when platen set-point and actual temperature are within 1/2 grid marking of each other as indicated on the G.C.
l chart recorder only.
- 4) Er.ter "00" and mark chart recorder on the []
G.C. with date. time, and initials.
I
- 3. Calibration Verification If G.C. Calibration Verifications have been done within the last 7 days, proceed to Step 4. Sample Analyses,
- a. Hydrogen Verification - only verification needed when analyzing offgas
- 1) Select loop No. 1. []
- 2) Enter "23" to evacuate the G.C. until the []
red HI VACUUM light is on. -
a) Cycle loop selector through loops 2, []
3, and 4, pausing at each loop and evacuating until the HI YACUUM iight is on.
b) Cycle a minimum of 3 times through []
loops 1, 2, 3, and 4, pausing at each loop.
c) Select loop No. 1. []
- 3) Enter "24" to terminate evacuation of the []
G.C.
DC0109 3VIII l l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EF RB-15:D hf.gg DATE 2/25/85 PAGE 4 0F 10 T!TLE SENTRY POST-ACCIDENT SAMPLliG SYSTEMS ;
-- GAS CHROMAT0 GRAPHIC ANALYSIS 1 t
i
- 4) Select attenuation factor of 500 (5 x 100) []
for the 10% H, source or 5 (5 x 10) for the 2000 ppm H s6urce.
2
- 3) Depress CAL-1 switch for 10% H 7 source, or []
CAL-2 switch for 2000 ppm H sburce, and 2
wait 10 seconds after amber LOW VACUUM light is cn. Cycle through loops three times.
- 6) Release CAL-1 or CAL-2 switch and wait 10 []
seconds.
- 7) Start the L&N recorder. []
- 8) Depress AUTO switch to on (in) and press []
CLEAR. Wait until the G.C. display clock has timed to a minimum of 3 minutes. During this time interval, identify the L&N recorder trace with the date/ time, gas used, loop number, attenuation factor and operator initials.
- 9) Release AUT0 switch to off (out) position. []
Press CLEAR and enter "00".
- 10) Repeat Steps 8) and 9) for subsequent loops. []
- 11) Stop the L&N recorder. []
- 12) Calculate the hydrogen peak height as follows: -
peak height = (Trace peak heicht - baseline) x attenuation '
100 peak height =
- 13) Compare the peak height calculated against []
the value shown on the concentration versus peak height curve for the same attenuation factor and calibration gas. The values should be within 2 10 percent of each other,
- b. Oxygen Verification i 1) Ensure that a loaded filter assembly is []
installed.
DC0109 4VIII I
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/25/85 PAGE 5 CF 10 TITLE SENTR'r POST-ACC10E?;T SAMPLING SYSTEMS
-- GAS CHRCMATCGRAPHIC Ai,A'. YSIS s
3 1-
- 2) Change the positions of the following valves:
CASF-DV-1 to Containment Supply []
CASP-V-16 to CASP-SF-5 []
- 3) Contact the Control Room and request []
permission to open FCV-700, the sample return containment isolation valve.
- 4) Evacuate CASP-SF-5 by opening the following valves:
FCV-700 (key operated) []
CASP-V-17 []
CCP-AV-2 []
CCP-SV-10 []
5). Evacuate CASP-SF-5 until pressure is as []
low as apparently achievable as indicated on CASP-PI-1116.
- 6) Remove fitting and septum from the end of []
. SF-5 to allow ambient air to purge through sampic panel and into containment. Purge for 2 minutes.
- 7) Close CCP-SV-10 and FCV-700 and replace [] ,
septum and fitting on SF-5.
- 8) Depress SAMP switch and verify red sample []
light is on.
- 9) Select loop No. 1. []
- 10) Enter "23" to evacuate the G.C. until the []
read HI VACUUM light is on.
a) Cycle loop selector through loops 2, 3, []
and 4, pausing at each loop and evacuating until the HI VACUUM light is on.
b) Cycle a minimum of 3 times through []
loops 1, 2, 3, and 4, pausing at each loop.
?
DC0109 EVIII
1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/25/85 PAGE 6 0F 10 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEMS
-- GAS CHRO'4A70 GRAPHIC At?ALYSIS l
c) Select loop No. 1. []
- 11) Enter "24" to terminate evacuation. []
- 12) Select attenuaticn factor of 100 (1 x 100). []
- 13) Align RC-V-15 to CASP to GAS CHROMAT.
- 14) Cycle loop selector through loops 1, 2, 3, []
and 4, pausing at each loop. Cycle 3 times.
a) Select loop No. 1. []
- 15) Align RC-V-15 to the CLOSED position and []
release SAMP switch.
- 16) Start the L&N recorder, wait 5 seconds. []
- 17) Depress AUTC to on (in) pcsition and press []
CLEAR.
a) Wait until the G.C. display clock has []
timed to a minimum of 3 minutes.
During this time interval identify the recorder trace with sample name, date/ time, loop number, attenuation factor and operator initials.
- 18) Release AUTO switch to off (out) position. []
Press CLEAR and enter "00".
- 19) Stop the L&N recorder. []
- 20) Calculate the net peak height and detemine []
l the oxygen concentration from the appropriate calibration curve.
peak height = m
- 21) Record the net peak height on the recorder []
trace. Repeat the analysis and select the next loop and appropriate attenuation factor (5 x 1, 25 x 1,1 x 100, or 5 x 100).
Repeat Steps 16 through 21 for loop 2, 3 and 4.
I DC0109 6VIII b
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/25/85
. PAGE 7 0F 10 m LE SENTRY POST-ACCIDENT SAMPLING SYSTEMS
-- GAS CH9CMATOGRAPHIC ANALYSIS 4 I
h
- c. Null Verificaticn
- 1) Derress SAMP switch and enter "23" to evacuate []
the G.C. until the red HI VACUUM light is cr.
- 2) Cycle through each loop and evacuate until []
the red HI VACUUM light is on.
- 3) Enter "13" to initiate argon purge. []
- 4) Cycle loop selector through loops 1, 2, 3, []
and 4, pausing at each loop. Cycle 3 times.
Select loop No. 1.
- 5) Enter "14" to terminate the purgt. []
- 6) Enter "24" to terminate the evacuation. []
- 7) Enter "00". []
Depress AUTO tc on (in) position and press
~
- 8) [] ~~
CLEAR.
a) Wait until the G.C. display clock has []
timed to a minimum of 3 minutes. During this time interval identify the recorder trace with sample time name, date/ time, loop number, attenuation factor and operator initials.
^
- 9) Release AUTO switch to off (out) position. []
Press CLEAR and enter "00". .
- 10) Repeat the analysis and select the next []
loop and appropriate attenuation factor !
(5 x 1,1 x 100, or 5 x 100). Repeat Steps
- 8) through 10) for loop No. 2.
- 11) If greater than 10% of sampled air oxygen []
concentration is recorded on trace, the system is not thorou Repeat Steps 1) through 10)ghly purged.
one time.
1
- 12) If greater than 10f. of sampled air oxygen is []
still present contact C&RP supervision while continuing with analyses. l I
1
.1 DCC109 7VIII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/25/85 pAGE 8 0F 10 TITLE SENTRY FOST-ACCIDENT SAMPLING SYSTEMS
-- GAS CHROPATOGPAPHIC ANALYSfr 13)- Release SAMP switch to off position. []
- 14) Stcp the L&N recorder. []
- 4. Sample Analysis
- a. Depress SAMP switch and verify red sample light []
is on.
- b. Select loop No. 1. []
- c. Enter "23" to evacuate the G.C. until the red []
HI VACUUM light is on.
- 1) Cycle loop selector through loops 2, 3, and []
4, pausing at each loop and evacuating until the HI VACUUM light is on.
- 2) Cycle a minimum of 3 times through loops 1, []
2, 3, and 4, pausing at each icop.
- 3) Select loop No. 1. []
- d. Enter "24" to terminate evacuation. []
- e. Select attenuation factor of 500 (5 x 100). []
NOTE: Before proceeding consult with the LSP operator to assure that a gas sample is available at'RC-V-15.
- f. When the appropriate gas sample is available at RC-V-15 align RC-V-15 to one of the following positions: -
- 1) LSP TO GAS CHROMAT. for reactor coolant []
off-gas sample.
- 2) CASP TO GAS CHROMAT. for containment air []
sample. .
- g. Cycle loop selector through loops 1, 2, 3, and []
4, pausing at each loop. Cycle 3 times.
- 1) Select loop No. 1. []
I DC0109 8 Vill
i DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/25/85 I PAGE 9 0F 10 TirtE SENTRY FCST-ACCIDENT SAMPLING SYSTEME 3 -- GAS CHRCMATOGRAFHIC ANA.YSIS i
4 i
- h. Release SAMP switch and align RC-V-15 to the []
CLOSED pcsition.
N3TE: If the analysis applies to centainter.t air, proceed to Step "j".
- i. Record the pressure on RC-G-2.1 on the data sheet, EP RS-15:F.
Reading: psig NOTE 1: The pressure is normally between 5 and 10 psig. l NCTE 2: Notify the main LSP operator when RC-V-15 is closed.
J. Stcrt the L&h recorder, wait 5 seconds. []
- k. Depress AUTO to on (ini positicn and press CLEAR. []
- 1) Wait until the G.C. display clock has []
timed tc a minimum of 3 minutes. During this tire interval identify the recorder trace with sample name, date/tima, loop number, attenuation factor and operator initials.
- 1. Release AUTO switch to off (out) position. []
Press CLEAR and enter "00".
- m. Stop the LEN recorder. [] _
- n. Calculate the net peak height end determine the [] -
hydrogen concentration from the appropriate calibration curve.
peak height = nm
- o. Record the net peak height on the recorder trace. []
Repeat the analysis and select the next loop and appropriate attenuation factor (5 x 1, 25 x 1, 1 x 100, or 5 x 100). Repeat Steps J. through o.
for loop No. 2 and any subsequent loops as needed.
Run one loop on same attenuation as oxygen calibration.
mG DC0109 9VIII e
i oiAsto CANYON POWER PLANT UNil NO(S) 1 AND 2
. Sf0N 2 DATE 2/25/85 FACE 10 0F 10 m ts SENTRY POST-ACCIDENT SAMPLING SYSTEMS
-- GAS CHRCMAT0 GRAPHIC AMLYSIS
- p. Purge the G.C. residual gas as follows:
- 1) Depress SAMP and enter "23" and evacuate []
the G.C. until the red HI VACUUM light is on.
- 2) Cycle through each locp and evacuate until []
the red HI VACUUM light is on.
- 3) Enter "13" to initiate argon purge. []
- 4) . Cycle loop selector through loops 1, 2, 3, []
anc 4, pausing at each loop. Cycle 3 times.
- 5) Enter "14" to terminate the purge. []
- 6) Enter "24" to terminate the evacuation. []
- 7) Enter "00". []
- 8) Release SAMP switch to off position. []
- q. After final use of G.C.
- 1) Shutdown the instrument by turning off the []
power to the TCD.
- 2) Secure the gas supplies for the G.C.
a) CLOSE the 3 rcot valves next to the CAP. []
b) CLOSE CAP-V-10. []
c) CLOSE CAP-V-14. []
- r. Return to the referencing procedure.
NOTE: For stripped-gas, this is EP RB-15:B, Step 15.f.
For Containment Air, this is EP RB-15:C, Step 3.
- s. Record the net peak height from Step n. on the appropriate data sheet and attach traces used.
REFERENCES
- 1. Sentry Equipment Corp. High Radiation Sampling System Operating ,
anc Maintenance Manual.
e DC0109 10VIII
NUMBER EP RB-15:E EC)GW3 Pacific Gas and Electric Company REVISION 2 DEDARTVENT Or NUCLEAR DLANT OPER ATIONS ,
b1 tM OIABLO C ANYCN POWEA PUNT UNIT NOIS)
EMEPGE.NCY PROCEDURI 1 AND 2 i ,
1 i Pd SE.TRY N PCST ACCIDENT S M Liv 3 SYSTV i' l
7,7;s RCS L 0U:0 AND GAS SAMLI HAN LING n ,aO,eo X 0 7Ab- 3!MK '
)
PLANT MANAGER ! DATE SCOPE This procedure provides guidance for safely handling post accident liquid samples obtained from the Reactor Coolant System (RCS) using the SENTRY PASS. The diluted liquid sample from the RCS is aliquetted. The aliquot may be used for boron or for y-assay.
Further dilutions for y-assay are done in the hot cell. Likewise, steps for preparation of diluted containment air samples for counting are also detailed. This procedure and changes thereto require PSRC review.
DISCUSSION Based on worst-case post accident assumptions regarding sample radioactivity content, special precautions may be required for handling RCS and containment air sample acquired using the Sentry PASS. Sample aliquots are transferred by precision pipets to a dilution vial for radiological counting or an appropriate reaction flask for chemical analysis. These flasks may be kept inside the hot cell throughout the procedure to minimize personnel exposures and also to contain the airborne radioactivity generated within the hot cell area. Control of airborne activity is accomplished by use of an overhead ventilation duct which creates a slightly negative pressure inside the enclosure. After all sample manipulations are completed, the radioactive waste solutions may be flushed down the Sentry Room sink via the receiver funnel drain valve and, if necessary, the inside surfaces of the hot cell may be sprayed down to reduce the contamination levels within the sample handling area.
PREREOUISITES AND PRECAUTIONS
- 1. Personnel assigned to conduct this procedure should be familiar with the considerations of handling highly radioactive liquid and gas samples and shall be experienced with the analytical chemistry techniques employed in this procedure. Also, any individual performing this procedure should be capable of:
l DC0294 IVII
.w.-
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EP RB-15:E
, g DATE 3/21/85 PAGE 2 0F 12 l TtTLE SET;TRY POST-ACCIDENT SA'GLING SYSTEM RCS LIQUID
- AND GAS SAMPLE HANDLING l l 1
- a. -Making does rate measurements with portable survey instruments,
- b. Assessing response and basic trends of continuous air monitoring equipment.
- c. Taking actions based on items 1.a and 1.b.
- 2. Unless conditions are known to warrant less stringent precautions, complete protective clothing and accident dosimetry (including high range and extremity dosimeters) will be required.
Lapel air samplers are also recommended. Full respiratory protection equipment (SCBA) may also be necessary.
- 3. To minimize time spent in hot sample handling, ensure availability of the required equipment for performing applicable portions of this procedure. This includes sample vessels, pipets, handling tools, reagents, etc. A comprehensive listing of these supplies is provided in a check list format in Appendix 1 to this procedure to facilitate the review.
- 4. Wheri the liquid sample is handled, there is a possibility that local radiation levels and airborne radioactivity could increase.
Since the sample is to be contained within the hot cell, the increases should not be too high; however, as precautionary measure, all individuals within the Sentiy Room should have functioning respirators. Monitorin i survey instruments (for dose rates)g should be performed usingand any availab (for airborne) for early identification of potential problems.
- 5. This procedure is designed to permit all sample handling to be
- performed by the use of tongs or other remote handling devices.
Unless the samples are surveyed and known not to present a significant source of exposure to the fingers, hands or other extremities, no sample manipulations involving direct hand l- contact should be attempted.
l l
DC0294 2VII l
t- _
I DIABLO CANYON POWER PL. ANT UNIT NO(S) 1 AND 2' Sf0N 2 DATE 3/21/85 PAGE 3 0F 12 m LE SENTRY PCST-ACCICENT SA?GLING SYSTEM RCS LICUID AND G"45 SAMPLE HAtCLI" PROCEDURE
- 1. Preparation of Sample Enclosure and Sink Area inis section covers the preliminary steps required before performing actual liquid sample manipulations. It is important that all required handling equipment and reagents to be employed are available prior to handling the liquid sample in order to minimize time spent working around hot samples within the hot cell.
- a. Initial Survey of Sample Enclosure and Sink Area
- 1) Perform a radiation survey of the hot cell area to verify that no highly radioactive sample material remains inside or around the enclosure from a previous use. If an indication of radioactive sample materiels is found, these materials should be promptly disposed of as set forth below under " Clean-Up" in Section 6 of this procedure.
- 2) Visually inspect the inside of the hot cell for unwanted material and for cleanliness. If material remains, remove and store or discard,it, whichever is appropriate.
- b. Acquisition of Required Supplies Assemble the necessary supplies, equipment, etc. to perform the required steps. A listing of these supplies is _
presented in Appendix 1 to this procedure for the following preparation and analysis categories. .
- 1) General Equipment Requirements (Sections '1 , 2, and 6)
- 2) Dilution of Liquid Sample for Radiological Counting (Section3)
- 3) Chemical Analysis for Boron Levels (Sectien 4)
- 4) Dilution of Off-gas for Isotopic Analysis (Section 5)
- 5) Containment Air Fractionation Supplies
- c. Preparation of Hot Cell Area for Use
- 1) Open the access door to the hot cell.
1 DC0294 3VII J .
DIABLO CANYON POWER PLANT UNIT NO(S) 1 ANO 2 NUMBER E'> RB-15:E REVISION 2 DATE 3/21/85 PAGE 4 0F 12 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM RCS LIQUID Ali0 GAS SAMPLE HMDLING l
F
- 2) Carefully position shielded sample holder brick for use in conjunction with pipet operations.
- 3) If a liquid sample for radiological analysis is te be diluted pursuant to Section 3 of this procedure, install an uncapped, clean 20 cc liquid scintillation vial into its appropriate sample port within the sample holder brick. Leave the cap and sealing tape outside the hot cell for later use.
- 4) If a Boron analysis is to be performed (pursuant to Section 4), install two 50 ml Erlenmeyer flasks into their appropriate sample ports within the sample holder brick, leave rubber stopper caps (one for each 50 mi flask) outside the hot cell for later use.
- 5) If a Boron analysis is to be performed, install two clean, uncapped, prewiped I cm path length photocell into the appropriate sample port within the sample holder brick. Keep the cap plugs available outside the hot cell for later use. - ,
NOTE: Be careful not to scratch the transmission surfaces nor to depesit extraneous material (e.g. - powder or lint) especially from gloves.
- 6) Check that a R0-7-BM probe, or appropriate range probe, is installed in the mount above the receiving funnel.
The probe should be 5 inches above the base of the hot cell. The attached cable should run through the vent -
chimney and fit in the slot provided for it. Connect
- I the cable to the R0-7 and turn the detector on.
- 7) Verify air flow ( a piece of paper is suggested) into the elephant trunk vent shroud.
l
- 8) Connect ventilation shroud to the chimney on top of cover switch.
- 9) prepare remaining equipment, materials, reagents, etc.
required for the planned sample manipulations and analyses.
- 10) Turn on the spectrophotometer and allow it to warm up.
Absorbance should be read 45 to 60 minutes after carminic acid is added. Note the time .
DC0294 4VII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/21/85 PAGE 5 0F 12 Tirts set,TRY FOST-ACCIDENT SAMPLING SYSTEM RCS LICUID APG GAS SA5'PLE HANDLING f
4 i
- 2. Obtaining a Liquid Sample from the cart / cask
- a. Place an RO-2A over the het cell ar.d determine the ambient l background response of the R0-2A. Note the reading and then remove the RC-2A.
R0-2A Reading: mR/hr (ambient background)
- b. Move the cart / cask to the sink area and set the brake.
- c. Uncover the sample vial by rolling the radiation shield away from the sample cavity.
- 1) Transfer the bottle containing the diluted reactor coolant to the hot cell and remove the lid.
- 2) Close the cask and move it away.
- 3) Close tbc access door to the hot cell.
- d. Measure the radiation level with the R0-7 and record the reading.
mR/hr (ambient background plus sample)
=
- e. Calculate the net sample reading by subtacting the value of step 2.c. from the value of step 2.e.
mR/hr (step 2.e.)
mR/hr (step 2.c.)
mR/hr (net sample reading)
- 3. Dilution and Preparation of Liquid Sample for Radioassay This step involves selection and dilution of a sample aliquot to obtain a counting geometry of 10 mis liquid in a 20 mi vial. The sample volume is based on the exposure rate recorc'ed in Step 2.f.
l DC0294 SVII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/21/85 PAGE 6 0F 12 mLs SENTRY F0ST-ACCIDENT SA? FLING SYSTEM RC5 LICUID ATO GAS SA'GLE HAN0 Lit,'G
- a. Select the appropriate pipet tip size and pipet volume as follcws:
Picet A: rox. Ster 2.::. Reading Check 5 ml < 1.6 mR/hr [ 1*
I ml > 1.6 mR/hr but <'16 mR/hr I
100 ul > 16 mR/hr but < 160 mR/hr I*
10 ul > 160 mR/hr [ l
- b. Open the access door on top of shielded sample enclosure.
- c. Using the pipet volume setting chosen in Step 3.a. above, obtain this volume of RCS liquid sample from the sample bottle, keeping hands as far away as possible from tne " hot" sample liquid.
- d. Slowly discharge the aliquot into the empty 20 cc liquid scintillation vial previously placed within the shield brick. Discard the pipet tip.
NOTE: Dispose of materials that have contacted highly contaminated mediums separately from those that have not.
- e. Using the appropriate pipette and tip, add sufficient demin water to the 20 cc vial to bring the total liquid volume to 10 ml. Add 10 mis to the 10u1 or 100u1 aliquot.
- f. Remove the diluted sample from the hot cell with tongs.
- g. Cap the vial. Wipe it and seal it with tape. '
- h. Screen survey the vial to verify countability (< 5 mR/hr contact).
- i. Label and bag the vial noting the dilution, the aliquot volume used, and the radiation level measured.
- k. If a chemical analysis for Boron is to be performed, proceed below to Section 4. If no chemical analysis is to be i
performed, proceed below to Section 6 to clean up and secure the hot cell for later use.
DC0294 6VII l-
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h(h0N DATE 3/21/85 PACE 7 0F 12 TCL5 SENTRY FOST-ACCIDENT SA"PLIris SYSTEM RCS LICUID
.ifi ; GAS SA'TLE HA'C' INS i
1
modified to permit the aoplication to highly radioactive samples.
Sample manipulations are performed primarily within the hot cell.
F
- a. Pipet 2 mi each of the 2 and 10 ppm boron. standard solution ;
into a 50 ml Erlenmeyer flask. Pipet 2 ml of demin water into a second 50 ml Erlenmeyer flask. (Both these flasks should be outside the hot cell.)
- b. Open the access door on top of the hot cell.
NOTE: Open hot cell access lid whenever something is added to a flask. Close it immediately afterwards,
- d. Pipet 10 ul of concentrated hcl to each flask stopper and swirl. Alicw flasks to cool (s 2 minutes).
- e. Add 10.0 ml of concentrated H7504 into each flask, stopper and swirl. Allow flasks to cool room temperature (s 15 minutes).
- f. Add 10.0 ml of carminic acid solution into each flask.
- g. Stopper again and, using tongs, swirl to mix well. _
b DC0294 7VII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/21/85 PAGE 8 0F 12 TITLs SENTRY FOST-ACCIDENT SAMPLII;G S'/5 TEM PCS LIQUID g
ATC GAS SAMPLE MAN LING q
> I i
- h. Being careful to avoid direct hand contact with the cuvettes, between approximately 40 and 55 minutes after the carninic adc, transfer solutions to clean, prewiped 1 cm cuvettes and carefully cap them. This may be accomolished using a 5 ml pipet set for 4 ml, and, in the case of the
" hot" sarrple the capping and cuvette transfer must be performed using tongs.
- i. Set the spectrophotometer to a wavelength of 585 nm and adjust the blank for 0% absorbance.
J. Read the baron standard to verify agreement with calibration graph within !5%. If this agreement is not obtained continue the analysis but inform supervision immediately.
- k. Read the absorbance of the sample (s). Record results and return the samples to the hot cell.
(Absorbance RCS)
Calibration. Graph (Standard Curve) ppm Boron RCS (diluted) = ppm Record this on the data sheet in EP RB-15:F.
- 1. Notify the PASS Supervisor of results of sample analysis.
- m. Turn the spectrophotometer off and proceed to Section 5 below.
- 5. Dilution and Preparation of Off-gas for Isotopic Analysis .
- M)TE: Perform rteps below only if sample vial dose rate is >5 l mR/hr.
- a. Obtain a clean 14 cc gas semple vial with a septum installed and using a 5 ml gas tight syringe, withdraw I cc of air
! from the vial and discharge the air from the syringe.
- b. Insert the syringe into the off-gas sample vial and remove Icc. Shut the valve on the syringe before removing the vial.
DC0294 8VII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
. ON DATE 3/21/85 PAGE 9 0F 12 mtz set,TRY FCST-ACCIDENT SAf<PLING SYSTEM RCS LICl)l0
- AND GAS SA"?LE HA! CLING 1 f i ;
e
- c. Insert the syringe into the counting vial; open the valve on the syringe and inject the contents into the vial.
- d. Survey the newly prepared vial; if the dose rate is >5 cR/hr, repeat steps a. through e. abcve, diluting into new clean 14 cc gas sample vials until the sample vial is less than 5 mR/hr, keeping track of the number of dilutions.
- e. Place a label on the counting vial repeating the information as found on the original vial. Calculate the new dilution factor by multiplying all dilutions together. Each dilution 15:1. Record this infonnation on the data sheet.
- f. Inquire fron supervision whether the original sample vials should be discarded or stored for future use and perform as directed.
- 6. Cleaning and Securing the Hot Cell
- a. Cleaning
- 1) Disposal of Radioactive Sample Residues During these actions, the radiation levels in the sink area and airborne concentrations within the Sentry Room may become higher since the sample materials are being discharged via the sink.
a) Turn on sink drain faucet to provide a slow, steady stream, -
b b) Open the access port on top of the hot cell. -
Remove sample caps using tongs and, using the remote handling device, empty out the contents of the flasks remaining in the enclosure down the sink drain, p
c) Flush out the sample flasks and wash off all contaminated handling tools with demin water, caustic or acid wash solutions (as appropriate),
followed by a demin water rinse, d) Perform a general washdown of the hot cell to remove contamination. Close the access port when finished inside the hot cell.
DC0294 9VII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/21/85 PAGE 10 CF *2 TirtE SENTRY FOST-ACCIDENT SAMPLING SYSTEM RCS LIQtJID i Af.D CAS SAMPLE HA!iDLItiG i i e) Store sample flasks, vessels, etc. as " dirty" materials -- not to be used acain unless thoroughly cleaned and inspected.
- 2) Disposal or Storage of Chemicals, etc.
a) Dispose of waste chemicals, materials, etc. in a similar fashion as above for the radioactive vessels. (0f course the precautions regarding radioactivity should not apply).
b) Chemicals, reagents and other supplies not consumed or compromised during the sample analyses may be stored for later use. These may be stored in the cabinet space adjacent to the sink area,
- b. Securing Equipment
- 1) Valves a) Verify that the sink water flow is secured off.
l
- 2) Ventilation If the hot cell and all survey / access parts are !
secured, the ventilation flow via the overhead duct may be turned off, provided there is no other requirement for this system.
- 3) When ready to do so, transfer samples to the TSC or -
counting roon for counting.
l
- 4) Turn all ventilation OFF when leaving the Sentry Room unless the Sentry Room will be used in the near future.
- 5) When exiting through the Motor Repair Shop, note the pressures of the gas supply bottles.
psig Argon i Cal Gas 1 psig Cal Gas 2 psig
- 6) Close the bottle isolation valves for the Sentry supply l
gasses.
ese .
DC0294 10VII L
&E DIABLO CANYON POWER PLANT UNIT NO(S) 1 AfiD 2 ((g [
DATE 3/21/85 6 PAGE 11 OT 12 T Tus set;TRY POST-ACCIDEt;T SAMPLItiG SYSTEM RCS LICUID Af!D GAS SAYPLE HA!CLIT'G i >
APPEtiDIX 1 CHECKLIST OF REQUIRED EQUI?ME117 At;D SUFPLIES j b
GEtiERAL SAMFLE hat;DLItiG A!iD MAf;IPULATI0t;S (Sections 1, 2, and 6) CHECK Fully operable hot cell (located in Sentry Room) [ ]
Sample shield brick (with pre-bored holes) [ ]
Long extension tongs: 14-16" in length, (2 pairs) [ ]
R0-7 w/RO-7-BM probe and 5' cable [ ]
Acid cleaning soluticn (1 gallon) [ ]
Caustic clear.irg solution (1 gallor:) [ ]
Demin water jug (5 gallons) [ ]
Suction bulb [ ]
Rubber hose (5' long with trigger spray nozzle and tap hook-up) [ ]
30 ml beakers (3) [ ]
Paper towels or equivalent (1 box) [ ]
Alcohol (1 liter) [ ]
RADIOACTIVE SAMPLE DILL' TION SUPPLIES (SECTI0fi 3) CHECK 20 ml liquid scintillation vial w/ cap (1) [ ]
Sealing tape for 20 ml liquid scintillation vial (1 roll) [ ]
Labels for 20 mi liquid scintillation vial (1 box) [ ]
Small plastic bags; sealable (1 dozen) [ ]
10 91 pipet w/tip [ ]
1 mi pipet w/tip [ ]
Adjustable 0-5 ml pipet w/tip [ ]
Shielded syringe (calibrated for 5 cc volume) [ ]
Spare syringe cylinder [ ]
M 6 DC0294 11VII
DIA8LO CANYON POWEFi PLANT UNIT NO(S) 1 AND 2 ON DATE 3/21/85 PAGE 12 0F 12 T;TLE SENTRY POST-ACCIDENT SAMPLING SYSTEM RCS LIQUID AhD GAS SA"PLE HANDLINS g
APPENDIX 1 (Continued)
BORON SAMPLE ANALYSIS SUPPLIES (SECTION 4) CHECK 50 ml Erlenmeyer flasks w/ rubber stoppers (4 sets) [ ]
1 cm path length spectrophotometer cells w/ caps (3 sets) [ ]
Dri-wipes for spectrophotometer cells (1 box) [ ]
Rinse / soak bath for 1 cm path length spectrophotometer cells [ ]
100 m1 volumetric flask [ ]
Adjustable 0-5 mi pipets w/ tips [ ]
10 ul pipet w/ tips (3) [ ]
Spectrophotometer unit [ ]
Dilute nitric acid, HNO E3 3
Carminic acid solution, Stability: I week (30 ml/ analysis) [ ]
Hydrochloric acid, HC1, concentrated (30 ml/ analysis) [ ]
Sulfuric acid, H SO2 4, concentrated (30 ml/ analysis) [ ]
Standard boric acid, two of the following standards: 10 ppm, 6 ppm, [ ]
4 ppm, 2 ppm, 1 ppm DILUTION OF 0FF-GAS FOR ISOTOPIC ANALYSIS (SECTION 5) 14 cc gas sample vials w/ septums installed (2) [ ]
5 cc gas tight syringe / needle [ ]
Labels for 14 cc gas vials [ ]
Small plastic bags; sealable [ ]
Sealing tape [ ]
CONTAINMENT AIR FRACTIONATION SUPPLIES Spare U-tube filter assembly [ ]
I Reagents must be stored in boron free containers; use plastic 4
DC0294 12VII
.,:. NUMBER EP RB-15:F
._- @cw.md Pac.fic i Gas and Elecin.c Company REVISION 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 3/22/85 pmt . s.--
C' OIA3LC CANYON PCWER PLANT UNIT NCis) 1A;D2 rout 1 O r- 1 l
4 L ,, }
l bi EVERGE:CY PROCECLH !
tj '
7 E SE::T POST-A ::'I?iT SA:L:: 5 SYSTI:1
-- DATA ANALYSIS APCACVED
-p
- n. M
,o M' N.
/-
I J/M., /
t -
l l
PLANT MANAGE 9 ,.' OATE 1 i
DISCUSSION The purpose of this procedure is to provide a means to assemble the data generated fron the various EP RB-15 sub-procedures into a concise form. Each section has a worksheet where data generated throughout the procedure is recorded. The back side records calculations and analyses results. The data summary sheet gathers all analysis results onto one sheet.
PROCEDURE
- 1. Process data on appropriate sections of fonn 69-9393.
- 2. Attach all pertinent chemistry and radiochemistry data to this form.
- 3. Deliver the cortpleted form to the Cheristry and Radiation Protection Supervisor for approval and disposition.
i ee O DC0118 1111
. ]
69-9393 .3/85 (10) .
Page 1 of 14 PACIFIC GAS AND ELECTRIC COMPANY
' DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: -FOST .50CIDENT PCS A?:0 CONTAINMENT A!o SAMPLE D*TA SHEET (EP PE-15:F) ,
SECTICt! A: WOR'.5-EET - li;!TIAL ACTIONS DATE REMOTE CC'.Til:iME!.T HYDROGEN K:.! TORE CEL-02 CEL-E3 Tire switched fror GFF to STANDEY
'(N/A if in STANDEY orior te this step)
Scals used (Step IC: 10'. [] []
20'. [] []
Meter Reedi g '- (Step IC)
Tir.e ' (Ster 10)
Ariclyst's Initials t
l t
i 30C0118 "!!!
I . ..
, 69-9393 3/85 (10) Page 2 of 14 TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
SECTION E: 'n'09.f.SMEET - STP.!DPED G AS . AND DILUTED DCS DATE A'. Ac V ST San:le Scarce: het Legs []
P:r Stear. []
F:r Liquid []
RHE Pur.r [']
VCT []
Step 9.d Vacuur on RC-G-2.1 of Hg Step 11.c Sam.ple Tine Ster 13.e Initial el Final ml it.tal c.i added Ster 15.3 Pressure on RC-G-2.1 psig SECTI:{ E: RCS GAS SAMPLE HA"DLIf;G
- 5. Use only if sample vial dose rat' mR/hr Dilutiens: 1 15:1 [
2 225:1 '
3 3375:1 '
4 50,625:1 5 76,000:1 ') -
Fir.al Dilution = :1 1
4 p -.
K 0C0115 3111
...m m
Page 3 of 14 69-9393 3/85 (10)
TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
SECTION B: DATA SHEET ine sclu e of c-igirtl car;'e r the la rl serum vial is calculated i
ir tha 12 e r:nre' a: ;asal . : s:c al tar;'irg t:-::, ? 0:eev e Ca
' 0-12, cccatice fa' V., = Volure of origiral sample in the 14 mi serum vial, el V =-Volure cf expansion vessel (EV-1) = 30: r1 3
V g
= Vclure cf lir.es fror EV-1 to RCV-15 = 60 r1 P.a
= Pf = Pressure after expansion 1 1 f f
= , psig - 14.7 30 in Hg = inches of Hg i
/ ( iM 7 psi )
F, = Fressure evacuated system = inche,s of'hg V
- Volute of the gas aliquet transferred by diluter value (DV-2) 3
0.0;; r1 i,g
(Ys )(Vb )(Ff -Pv-i(Vg-i (V*Vh/Ef)(\g-V e 3)
- The velur.e cf the origiral sample in the 14 mi serum vial, V74, is to be used in the racicrutlide ar. clysis programs.
Trar.sfer results fror. cour. ting printout to specific Activity Determination in Reactor Coolant Analysis Data Sheet prior to Data Summary Sheet.
h i
i 0C0118 4111
Page4of15 69-9393 3/85 (10)
TITLE: POST ACCIDENT RCS AND C0t!TAINMENT AIR SAMPLE DATA SHEET (EP RC-15:F)
DATE SECT:Of' C: tiO .r. SHEET - C !:TA!!:"E!: AIR SAMDLit:S A:,ALYST Step 1.e Contaitree; terperature = ( 'F +;E0) x 5/9 = 'X T c
Con:rinren: pressure = psis Step 2.c-
. Sample Pressure: cor.tainment air pressure CASP-PI-1109 psig Sar.ple Tina Stec 2.d TH ;96 = 'C + 273 = *K=T s 0
I t DC0116 5111
l 69-9393 3/85 (10) Page 5 of 14 TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
SECT:C' C: 017A SHEET - CC';TA!'ME'i! AIF. ISC70F!C ANALYSIS 3a. :ii r.9 Te:. 1::tr C:rtain ert t;cbie Gas Fractioral Yield = T C/(43,4;C x T s )'= Y, -
e.J 4- N:ble Gas Activity = uCi/cc Counted By Containn'er.t Air lodir e er.c Particuletes Fracticr.r.1 Yield Tc l s' IF Icdine ar.d Fr.rticulate Activity = uCi/cc Counted By
'r.r e re : Y,,P ort Y,7 are frecticeal yields entered inte the analysis prograr..
m 9
d O DC0118 6Ill
Page 6 of 14' 69-9393 3/65 (10)
TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
DATE SECTIO!!: D: VCDK5uEET - G.C. ANALYSIS A' Ev57
- 3. Calibra t ion '.'eri ficatico .
- 3. bycr ger - sear ce calt:ra ien gn : Cai 1-;01 []
Cai 2-0.2' []
- 12) LcoD I
.(trate peak height - baseline ) x attenuation /100 peak height = .
hydrogen concentration
- 1. cop 2 i (trace peal height - baseline ) x attenuation /100 s
peak height = hydrogen concentration Lot p 2 (trace peak height - baseline ) x attenuation /100 peak height = hydrogen concentration _
Loop 4
{ ra t peak height - baseline ) x attenuation /100 perf height = hydrogen concentration i b. Oxygen
- 20) Loop 1 (trace peak height - baseline ) x attenuation /100 _
peak height = hydrogen concentration Loop 2 (trace peak height - baseltne ) x attenuation /100 peak height = hydrogen concentration Loop 3
- baseline ) x attenuation /100 (trace peak height peak height = hydrogen coceentration Loop 4 ,
- baseline ) x atteruation /100 (trace peak height
~*
peak height = hydrogen concentration -
DC0116 ?!!!
69-9393 3/85 ;(10) Page 7 of 14
= .f TITLE: POST ACCIDEllT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
SECT 10t! D: WO MSHEET - G.C. Af;ALYSIS (C0!iT'D)
- 3. .%11 tieri fi:stier
- ;35d1192 Mtorunica /"^
10 (;rica ceM.!.:i;F: }
peak height = oxygen concentration I
Less than 10'. value calculated Ste; 20) Yes 5 t:0 4 Sample Ar.alysis l
- i. Off gas scrple pressure RC-G-2.1 psig
- n. Loop I (trace peak height - baseline ) x attenuation /100 peak height =
Hydroger. [. ]
0xygen []
Locp 2 (trac + teak height - baseline ) x attenuation /100 peak height =
Hydregen []
0xygen [] ,
Loop 3 (trace peak height - baseline ) x attenuation /100 peak height =
Hydrogen []
0xygen []
Loop 4 (trace peak height - baseline ) x attenuation /100 i
peak height =
Hydrogen []
0xygen [] _. .
DC0118 8III
- ~>
h- - -- - . .
-'1
.f Page 8 of 14 9393 3/85 (10)
TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F) l
[
1 SECT:09 D: CATA 5WEET - HY3RCSEN CONCENTP.ATICN SY G.C.
DATE
[
MA'_ y S? 'S IN!?! A' 5 Peak height-CP = Peek height-5: x (Calibratier. Pressure: recorded en cai, en:C (fror trace) (Sa,piing Pres sure;-
(at calibratier pressure) for CA: from EP RB:C = psig + 14.7 = psia
- Sanpling Pressure
- for offgas: from EP RB:D = psig + 14.7 = psia Lecp :
Feak height-CP = mx( psia) = m
( psia)
- h. .
= *H (fror cafibration curve)
Lecp :
Peat height-Ce = r: x ( _
_ psia) = r.
( psia) i H, = iH (f roc cafibration curve)'
Loo;- : ,
Peak height-CP = mx( psia) = mr
( psia) iH = iH 2 (fromcakibratier. curve)
Loop :
Peak height-CP = mx( psia) = r
( psia) tH - = iH (fromcafibrationcurve) -.
J DC0116 9111
69-3393 3/85 (10) Page 9 of 14 TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
SECT C?. D: DATA SHEET - CXVGEN CONCENTPATIO" SY G.C.
DATE A'u'_v5T'S IN:~II'_5
-Peak height-CP = Fea'. height-S? x (Calibration Fressure: recceded cr. ct! :-a:n}
(at calibratier (fror trace) (5arpiing Pressure).
pressure)
- Sampling Pressure - for CA: from EP RB:C = psig + 14.7 = psia Loop :
Peal Feig*.t-CP = nr. x ( psia) = mr.
( psia)
=
0 ,
(frerca$ibraticr. curve;
' Loop _,
Peak heigt.-CP = nx ( psia) = mm
( psia)
=
'O 'e (fror ca$ibratior. curve)
Loop :
Peak height-CP = mx( psia) = mm
~
( psia) i0 = %
(fromcafibrationcurve)
Loop :
Peak height-CP = mm x ( psia) = mm
( psia)
=
i0 %
(freeca$ibrationcurve) r s DC0118 10111
Page 10 of 14 69-9393 3/85 (20)
TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET-(EP RB-15:F)
SECT!Ct. E: WORKSHEET - RCS LICL' 0 SAMPLE HANDLING ANALYST E.a. RC-ZA a.ciect'backgr ;nd - hat cell r:f r,r
- e. 30-7 sa.m ple plus bactground mR/hr
- f. net reading sarple mR/hr 3.a. Volume RCS pipetted for isotopic analysis 5 mi )
1 ml '
100 ut '
10 ut
- d. Eoren Ar.alysis Standard Sarole Opm ope 1 2 absorbance Calculated pp- B DC011f. 11111
f Page 11 of 14 69-9393 3/85 (10)
TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
SECT!0!; E: OATA SPEET to:ai r' water acacc tc sanpie = :ilatier factor -
sample size 0.024 mi Ecren Analyses
[B] in RCS = [5] in sarple x dilutien factor Sample 1 = x = ppm Soron
[E] ir. RCS Sample 2 = x = ppm Boron
[E] in RC5 Isetopic Analysis
Fracticral Yield = 1 1 dilutitn factor Volure Sar.ple Pipetted.
6 m e LC0118 12111 J w
Pag 2 12 of 14 69-9393 3/85 (10)
TITLE: POST ACCIDEUT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
SECTION G: W0oKSPEET - 10!! CucouATOGDAPHIC CHLORIDE ANALYSES ANALYST
- 2. Chicrice Stan:acc Cnece
- m. (trace peak height - baseline ) x~attenuaticn /100 peak height Ch!cride concentration '( A)
- n. (A)-1.0 x 100 % Difference (B) 1.0 Is B less than 10:.? YES - Proceed NC - Proceed, but contact C&RF Superviser 4 Sample Analysis
- i. (trace peak height - baseline ) x attenuation /100 peak height = mc
.ppe Ct.ioride 1
I 4
DC0118 13III
( --.
69-9393 3/85 (10) Page 13 of 14 TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET (EP RB-15:F)
' DATr' SE T!CR F: '4C:M59EET - p4/CCN;UCT!V!TY/CISSOLVED OXYGEN ANALYST
- 1. - thritcr Cali:raticr
- a. ;'r Calibratic-5)a) pF: te perature 0# buffer solution *C
- 7) pH 7 buffer value from Lable
- 15) terperature of buffer solutien *C
- 16) pH 4 buffer value reading
- b. Dissolved Oxygen Analyzer Calibration
- 5) terperature water *C
- 6) Sclubility oxygen ppm from table
- 3. Sarple Ar.alysis
- e. oxyger concentratier reading ppn 0 2
- f. pH reading temperature 'C -
O e
- e
- OC011E 14III
Page 14 of 14
- 69-9393 3/85 (10)
TITLE: POST ACCIDENT RCS AND CONTAINMENT AIR SAMPLE DATA SHEET s DATA
SUMMARY
SHEET r;
......a 3
4 L J PASS COMMENTS DATE I"IT:AL READ:NG PARAMETER SORON . ppn RCS LIQUID diluted a CONDUCTIVITY umhos/cm.
CHLORIDE ppm D0 PP*
2 pH
- ACTIVITY uCi/ml ~
HYDROGEN cc/ka OFFGAS ACTIVITY pCi/ml CONTAINMENT OXYGEN %
ATMOSPHERE _
HYDROGEN NOBLE GAS ACTIVITY uCi/ml RADIOI0 DINES
& PARTICULATES vCi/mi 4
REVIE'AED BY C&U Supervisor .
i J
l DC0118 ~ 15111
69-10548 11/83 (100)
Page 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT 0,F NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 TITLE: SPECIFIC ACTIVITY DETERMINATION IN REACTOR COOLANT ANALYSIS DATA SHEET l role location: Perferred by:
Sa :le C:lle::icn Cate/ Time: /
h-3: .Ci/mi Sr/Y-90: .c4 Se-53: uCi/mi Gasecus Activity Results Sa ;1e Analysis Ca e/ Time: /
./uclid2 Activity Concentration Nuclide Activity Concentrati0n
- uCi/ml : uCi/n
- LCi/ml : .Ci/c
- LCi/ml : .Ci/m
- uCi/ml : ;Ci/m
- uCi/ml : uti/r Degassed Liquid Activity Results Sample Analysis Date/ Time: /
Nuclide Activity Concentration Nuclide Activity Concentration
- uCi/ml : uCi/
- uCi/ml : uti/
- uCi/ml : uCi/-
- uCi/ml : uCi/-
. : uCi/ml : uCi/:
- uC1/ml : uCi/:
- uCi/ml : .Ci /r
- uti/ml : uCi/r
- uti/ml : uti/r -
- CCi/ml : CCi/r .
. : uCi/ml : uti/r
- uti/ml : uCi/r
- uCi/ml : uCi/r
- uCi/ml : uti/r
- uCi/ml : .Ci/r
. Combined Activity = total of all above analysis = . Ci/r I = _____ MeV/ dis Determined on 100/E= uCi/ml Is combined activity greater than 100/1 limit? [] YES []NO
' answer is yes, Shift Foreman notified DATE/ TIME / By
.RP Supervisor (name) notified DATE/ Time / By NPPR initiated DATE/ TIME By Reviewed by DATE/ TIME C&RP Supervisor
-w ,r , , - wy,,c ,,-,,_,,,-._,.,,.m._ ,-w. , , , ,y,,,.,,--e,w , , , , , , ,,y.-y,-,.,-,-- ,,,.,,--,y-.__,. y -- - - - - - e-.,w+--- ---m,-9,
NUMBER EP RB-15:G
.T_. G v43 Pacific Gas and Electric Company REVISION 1 o
DATE 3/26/85 ce ' op N W l h!f cineto cANvcN POWE4 plant UNIT NO'S) 1 AIO 2 1 'pgi EMEDGENCY CPERA~ING PROCEDURE i I
~
.t'; > 1 SENTRY PAST ACCIDENT Sa'r::ly!G Svg- u 2 TITLE --ION CHRG",ATC3^.APHIC CHLCRIDE ANALY5I5 I APPROVED b ' M bli <
PLANT MANAGER ) DATE 1 d
DISCUSSION The purpose of this procedure is to detail the steps required to measure chloride concentrations of reactor coolant. Included are steps to complete flushing of both the LSP reactor coolant module and CAP lines. This procedure requires operator actions at the LSP, CAP, and CMP.
PREREQUISITES
- 3. Verify that the following annunciator windows are off on the PCP:
- a. REACTOR COOLANT SAMPLE COOLING WATER LOW FLOW
- b. REACTOR COOLANT SAMPLE COOLING WATER LOW PRESS
- c. REACTOR COOLANT SAMPLE COOLING WATER HIGH TEMP
- d. REACTOR COOLANT PURGE HIGH TEMP
- e. REACTOR COOLANT SAMPLE HIGH TEMP
- f. LIQUID SAMPLE PANEL HIGH PLENUM PRESS
- g. CHEM ANALYSIS PANEL HIGH PLENUM PRESS 4 The following equipmer.t should be available:
- a. Meter-long reach rod j DC0209 IVII
DAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 f0N DATE 3/26/85 PAGE 2 0F 11 mLE SENTRY POST-ACCIDENT SAMPLING SYSTEM
--IC:; CHRO:ATOGRAPHIC CHLCREE ANALYSIS g
PRECAUTIONS
- 1. This sampling involves processing of water that may be highly radioactive. Precautions should be taken to prevent skin centact I or ingestion.
- 2. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush periods, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose area.
- 3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.
- 4. For the Ion Chromatograph (IC):
- a. The calibration curve should be checked once every 4 samples by analyzing a chloride standard.
- b. Calibration should be checked when first using a new eluent,
- c. Regeneration is required about once every 6-8 hours of l continuous operation. Refer to the troubleshooting and surveillance and maintenance procedure,
- d. During continuous operation, the separator column must be cleaned on a daily basis or every other regeneration by pumping eluent through the column for a minimum of 10 minutes, followed by a 20 minute demineralized water rinse.
This may be coincident with regeneration of the suppressor ~'
column. Refer to the troubleshooting and surveillance and maintenance procedure CAP G-3. .
PROCEDURE
- 1. Instrument Calibration b
- a. Set the OFFSET range switch to left. []
- b. Set MODE to LIN. []
- c. Adjust the C0 ARSE ve nier switch to zero the meter.
It may be necessary to adjust the FINE pot to zero the meter. []
i OCO209 2VII
R EP RB-15:G DIABLO CANYON POWE'1 PLANT UNIT NO(S) 1 AND 2 DATE 3/26/85 PAGE 3 0F 11 TITLE SENTaY POST-ACCIDEfC SAM LIfiG SYSTEM l
--ICl; CHECM.ATCGRAPHIC CHLCEIDE Al.ALYSIS j i 4
- d. Operate the system until the baseline is stabilized with the umno FULL SCALE switch in the 1 position adjusting tne FINE pot as necessary to :ere the meter. []
- 2. Chloride Standard Check
- a. If Standard Check has been performed within the []
last week proceed to step 3.
- b. Close or check closed CAP-V-15. []
- c. Verify CAP-CAL-3 is at least half full.
(CAP G-3, directs filling). []
- d. Align CAP-V-5 to CHLORIDE CALIB. SOL'N. []
- e. Open CAP-V-IS. []
- f. Turn on the L&N recorder. []
- g. After 1 minute, place the LOAD / INJECT switch at the CMP to INJECT and mark the recorder trace with date, time, injection point, analyst's initials, sample type, and conductivity meter setting. []
- h. After 1 minute, place the LOAD / INJECT switch in LOAD position. []
NOTE: The C1 peak will elute about 5 min. after injection.
- i. Close CAP-V-15. []
- j. Align CAP-V-5 Counterclockwise to CLOSED. []
- k. Align CAP-V-29 to vent (6 o' clock) []
- 1. After the Cl peak has eluted, wait 5 minutes then shut off the L&N recorder. []
-e f
DC0209 3VII
DIABLO CANYON POWER PLANT UNIT NO(S) . 1 AND 2
[f[0N DATE 3/26/85 PAGE 4 0F 11 TITLE SENTRY POST-ACCIDENT SAM.: LING SYSTEM
--ION CHROMATOGRA: HIC CHLORIDE ANALYSic '
. I
- m. Align CAP-V-5 to RCS sample (9 o' clock). []
- n. Deternine the peak height:
Peak height = (Trace Peak Heicht - Baseline) x Attenuation
, 100 Peak Height = mm Corresponding ppm Cl from CAL. Curve ppm (A)
- o. Compare the Cl~ standard peak with the calibration curve.
For the same umho setting, the values should be within 10%.
(A) - 1.0 x 100 = Difference (B) 1.0 Is (B) within 210%? (YES/N0)
- 3. LSP and CAP Purging If LSP has been previously purged during Reactor Coolant Liquid /offgas sampling then proceed to step c. l
- a. Determine which sample vurce isolation valves will have to be opened from the list below
SAMPLE SOURCE CONTAINMENT ISOLATION VALVES Hot Legs Loops 1 and 4 FCV-9356A and FCV-9356B Pressurizer Steam Space FCV-9354A and FCV-93548 l Pressurizer Liquid Space FCV-9355A and FCV-93558 '
RHR Pumps Discharge N/A Volume Control Tank N/A
- b. Call the Control Room and have operations block open the l
appropriate containment isolation valves.
L c. Open the corresponding remote plant isolation valve (RPIV) and remote source isolation valve (RSIV) at the PCP (see Appendix 1 for proper valve).
hi I: .
L DC0209 4VII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/26/85 PAGE 5 0F 11 mts SENTRY POST-ACCIDENT SAMPLING SYSTEM
--!CN CHROMAT0 GRAPHIC CHLORIDE A.'iALYSIS i f
i
- d. Close remote flush isolation valve (RFIV). []
FOTE 1: The sample source valves are labeled RC-V-1.1 through RC-V-1.5. Throughout this procedure, the form RC-V-1.X will be used to indicate the source valve to be operated. The sample source used for sampling will have been given at a briefing by the Site Chem and Rad Protection Coordinator.
NOTE 2: upon implementation of the next step, sample will be flowing into the back of the LSP. -The meter-long reach rod should be used to operate valves and a dose rate survey should be done to monitor radiation levels,
- e. Open the sample source valve RC-V-1.X (see Appendix 1 for proper valve). []
- f. Open RC-V-3. []
- g. If LSP has been previously purged proceed to step h. [] l Slowly open RC-VREL-1 until RC-F1-1 indicates 1001 flow or 1900 cc/ min. Purge for 9 minutes.
- h. Slowly close RC-VREL-1 until RC-FI-1 indicates 36% 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 []
- k. Position RC-V-22 to the TO CHEM PANEL position. []
- 1. Adjust RC-VREL-2 until RC-FI-2 indicates 100% full flow or 200 cc/ min. []
- m. Verify that the red FULL FLOW lights are lit for the ION CHROMAT loop at the ChP and CAP panels. Adjust RC-VREL-2 if necessary to obtain proper flow rate. []
- n. Continue the purge for 5 minutes. []
mO DC0209 SVII
1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S)
[fh0N DATE 3/26/85 PAGE 5 0F 11 m LE. SENTRY PCST-ACCIDENT SAMPLING SYSTEM
--ICN CHECMAT0 GRAPHIC CHLCRIDE ANALYSIS
- 4. Sample Analysis
- a. At the CMP, activate the L&N recorder. []
- b. Place the IC LOAD / INJECT switch in the INJECT position and mark the inject position on the chart paper. []
- c. On the chart paper, record the date/ time, sample source used, p ing, chart speed, and analyst's initials. []
. d. After approximately I minute from sample injection, place the LOAD / INJECT switch in the LOAD position. []
WTE: The chloride peak will appear approximately 5 minutes after injection at the same retention 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&N reccrder. If the chloride peak gces off-scale, a reanalvtis must be completed using a larger umho set , i3 umho) and following the steps below, otherwise skip to step "h". ~[]
- 1) Select appropriate attenuation. []
- 2) Align CAP-V-5 to LIQUID SAMPLE. [] _
- 3) Continue the purge for 1 minute. [] .
- 2) Place LOAD / INJECT switch in the INJECT position 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 analyst's initials. []
- 6) After approximately 1 minute, place the LOAD / INJECT switch in the LOAD position. []
POTE: The chloride peak will appear at approximately 5 minutes after injection, i
}
DC0209 6VII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
[fh0N DATE 3/26/85 PACE 7 0F 11 mts SE.NTRY POST-4:CIDENT SAMPLING SYSTEM
--ION CHROMA 73 GRAPH C CHLORIDE ANALYS:S t
- 7) Turn CAP-V-5 to the OEMIN WATER position. []
S) Flush with demin water for 2 minutes. []
- 9) Examine tne L6:s recorder for the cnioride peak. []
NOTE: If the chloride peak is off scale, change the umbo setting and repeat step g. until the chloride peak is on scale.
- h. After the C1' peak has eluted, wait 5 mirutes then turn off the L&N recorder. []
ppm Cl-
- k. If pH/ conductivity /00 are to be analyzed proceed []
to EP RB-15:H.
- 5. Flushing
- a. At the PCP, perform the following:
- 1) Close the remote plant and source isolation .
valves. (See Appendix 1). []
- 2) Open the remote flush isolation valve (see Appenoix I for proper valve). []
- b. At the LSP, close RC-V-1.X. []
- c. At the CAP, align CAP-V-5 to LIQUID SAMPLE. []
- d. At the LSP, open RC-V-4. []
- e. Open RC-VREL-2 until RC-FI-2 indicates 100% of full flow or 200 cc/ min. Flush with demin water for 3 minutes. []
0C0209 7VII 2
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2
[hf0N DATE 3/26/85 PAGE 8 0F 11 m LE SENTRY POST-ACCIDENT SAPPLIt:G SYSTEM
--ICli CHRCt%T0 GRAPH!C CHLCR!DE AtiALYSIS ;
, i
- f. Close RC-V-7. []
- g. Open RC-V-3. []
- h. Acjust RC-VREL-1 until RC-FI-I indicates 100% of full ficw or 1900 cc/ min. Flush with demin water for 1 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 RC-V-7. []
- m. Adjust RC-VREL-2 until RC-FI-2 indicates 100% of a full flow or 200 cc/ min. Flush with demin water for 3 minutes. []
- n. At the CMP, cycle the LOAD / INJECT switch at least 3 times. Return it to the LOAD position. []
- o. At the CAP, align CAP-V-5 to CLOSED. []
- p. 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 flushing by closing the following valves:
l RC-V-7 ',',
RC-V-2 ,,
! RC-V-4 ,,
l RC-VREL-1 ,,
RC-VREL-2 .
- t. Align RC-V-22 to WASTE. []
- u. At the PCP, close the remote flush isolation valve. []
(Appendix 1)
- v. Call the control room and have operations close the I containment isolation valves opened earlier. []
DC0209 8VII
1 AND 2 DIABLO CANYON POWER PLANT UNIT NO(S)
[h EP RB-15:3 DATE 3/26/85 g PAGE 9 0F 11 Tirts SENTRY FCST-ACCIDENT SAMPLING SYSTEM
--IC.N CHROMATCGP.APHIC CHL0EIDE ANALYSIS I
- 6. Flushing the Separator and Suppressor Columns
- If the IC is net needec for further sampling in an 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> j period then the following steps should be perfor~ed before system shutdcwn can be started.
NOTE: Direction from the Site Emergency Coordinator may preclude this section, if radiological conditions warrant.
- 1) Check that the conductivity meter mode switch is set to ZERO. []
- 2) In the eluer.t/ pump enclosure of the CAP, check the following:
a) Check the levels of elvent, water, and regenerants are at least half full. []
b) Check that the I.C. pumps and vent if air is visible in the sightglass or tubing. []
c) Check that the pump stroke settings are set at 40'; for both pumps. []
- 3) At the CMP, check the following: ,
a) Check that the regeneration time ,
thumbwheels are set at 15 min fer REG and 45 min for RIN. []
b) Align the following air toggle switches to the indicated positions:
SWITCH POSITION E3 / Water E ;)
E DbWN
SkP-1/SEP-2 SEP-1
SUP-1/RGN-2 SUP-2/RGN-1 l INJECT /LGAD LOAD l)
DC0209 9VII
1 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NJMBER EP RB-15:G REVISION 1 DATE 3/26/85 PAGE 10 0F 11 TITLE SENTRY F0ST-ACCIDENT SAMPLING SYSTEM
--IC's CHRCMAT0 GRAPHIC CHLORIDE ANALYSIS 3
- 4) Depress regeneration START button and the suppressor column will autcratically be
. regerera ted. []
- 5) Flush the separator column for 20 min. Af ter 20 nin., turn the E, switch to DOWN and rinse the separator column with demin. water for 10 min. []
- 7. System Shutdown
- 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 ELUEhT pump switch to 0FF. []
- 5) Turn conductivity reter MODE switch to ZERO. []
- b. If pH/ conductivity /00 a*re to be done, proceed []
to section H.
- 8. Data Analysis
- a. Proceed to EP RB-15:F for data analysis. []
- 9. If finished with all sampling / analysis go to 15:H []
Step 6, system shutdown.
l REFERENCES l
Sentry Equipment Corp. High Radiation Sampling System Operating and
! Maintenance Manual.
APPENDIX
- 1. Valves for Obtaining Samples from Reactor Coolant i
DC0209 10VII i
clASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 HUMBER EP RB-15:G
' REVISION 1 DATE 3/26/85 PAGE 11 0F 11 TITLE SENTRY FOST-ACCIDENT SAMPLING SYSTEM i
--!CN CHRCMAT0 GRAPHIC CHLORIDE ANALYSIS 4
APPENDIX 1 VALVES FCR OBTA!NING SAMPLES FRCM REACTCR COCLANT LSP SAMPLE REMOTE PLANT 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 PC-V-1.1 RC Hot Leg 4 FCV-9351 B FCV-692 FCV-1416 RC-V-1.1 PZR Liquid FCV-9350 B FCV-693 FCV-1417 RC-V-1.2 PZR Stear FCV-9350 A FC'.-694 FCV-1418 RC-V-1.3 RHR Pump 1-1 Discharge FCV-9353 A FCV-1413 FCV-1419 RC-V-1.4 RHP. 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 Sump FCV-697 Floor Drn Reevr N/A FCV-1415 FCV-1425 RW-V-2,2 -
Equip Drn -
Reevr N/A FCV-1414 FCV-1424 RW-V-2.3 i
DC0209 11VII
NUMBER EP RB-15:H 3Gw3 Pacific Gas and Electric Company REVISION 1 j DEPARTMENT OF NUCLEAR PLANT OPERATICNS
$ c AaLO CANYON PCWE A PLANT UNIT NO(S) i AND E Nb E!'ERSDCY CPERATD3 PROCECURE t SET.TRY PCST-ACCIDDT SA"PLING SYSTEM l I h;::il 2 ..
-w
] nTea -- Ph/CO:Q:CT;.';Ti/DI550LVE5 usiGEN 1
W l
AFDCOVED T- " 3 W[ {
PLANT mat 1AGER j DATE j g
DISCUSSION The purpose of this procedure is to detail the steps required to
. measure pH, conductivity, and dissolved oxygen concentrations of reactor coolant. Included are steps to complete flushing of both the LSP reactor coolant module an CAP lines. This procedure requires operator, actions at the LSP, CAP, and CMP.
PREREQUISITES
- 1. Monitors are turned on according to procedure EP RB-15:A:
- a. and have warrned up for I hour if oxygen analyzer has not beer calibrated within I week;
- b. or, have warmed up for 30 minutes if oxygen analyzer does not need calibration.
- 3. Verify that the following annunciator windows are off on the PCP:
- a. REACTOR COOLANT SAMPLE COOLING WATER LOW FLOW
- b. REACTOR COOLANT SAMPLE COOLING WATER LOW PRESS
- c. REACTOR COOLANT SAMPLE COOLING WATER HIGH TEMP
- d. REACTOR COOLANT PURGE HIGH TEMP
! e. REACTOR COOLANT SAMPLE HIGH TEMP
- f. LIQUID SAMPLE PANEL HIGH PLENUM PRESS
! g. CHEM ANALYSIS PANEL HIGH PLENUM PRESS l
l DC0416 IIII
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 3/26/85 PAGE 2 0F 12 TITLE SENTRY P05T-ACC:0E.97 SAMPLING SYSTEM
-- PH/CONDUCTIV!TY/ DISSOLVED OXYGEN 4
- i
- 4. The folicwing equipment must be available:
- a. Heter-long reach rod
- b. Small screwdriver
- 5. The conductivity meter should have been calibrated within the last 3 months.
PRECAUTIONS
- 1. This sampling involves processing of water that will be highly radioactive. Precautions should be taken to prevent skin contact or ingestion. ,
- 2. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush periods, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose area.
- 3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.
PROCEDURE
- 1. Monitor Calibration If the cap Monitors have been calibrated within the last 7 days proceed to step 2, LSP and CAP Purging.
E
- a. pH Calibration -
- 1) Make sure the pH buffer tanks are over half []
full with pH 7 and pH 4 or 10 buffers at the CAP.
f0TE: To fill, vent tank pressure, remove pipe cap or.
top of sight glass and fill with appropriate buffer. Be sure to install pipe cap and then repressurize tank.
I 2) Align CAP-V-6 to pH CALIB SOLUTION []
- 3) Adjust CAP-V-26 until sufficient flow is []
l indicated by red flow indicator light.
Flow for 2 minutes. Cycle CAP-V-7 to Rexrord and then back to the YSI 0xygen Analyzer. I l
i DC0416 2ill k
l 1
4
/ DIABLO CANYON POWER PLANT UNIT NOIS) 1 AND 2 MSG EP RB-1 M
REVISION 1 DATE 3/26/85
. PAGE 3 0F 12 m LE SENTRY FOST-ACCIDEi;T SAMPLING SYSTEM
-- PH/CO'C' CTIVITY/DISSCLVED OXY 3EN 8
- 4) Turn CAP-V-6 counterclockwise to 0XYGEN []
CALIB. SCLUTION to terminate flow, then align CAP-V-27 to vent position.
i -
- 5) Observe and record the tenperature of the buffer solution as indicated on the CMP.
Temp. *C a) Correct the buffer pH value for the []
recorded temp. from the pH Temperature Correction Table (Appendix 1),
f) 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 WATER and flush for 2 []
minutes. Cycle V-7 from YSI to Rexnord to flush D0 deadleg.
9} Align CAP-V-30 to pH calibration tank CAL-2. []
- 10) Align CAP-V-28 to the nitrogen supply line. []
- 11) Align CAP-V-6 to the pH CALIB SOLUTION. [] ,
- 12) Open CAP-V-16 until the red flow indicator ,
is lit. Flow for 2 minutes. Cycle CAP-V-7 to Rexnord and then back to YSI 0xygen Analyzer. []
- 13) Turn CAP-V-6 counterclockwise to the OXYGEN CALIB SOLUTION to terminate flow. []
- 14) Align CAP-V-28 te 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 []
recorded temp. from the pH Temperature Correction Table (Appendix 1).
DC0416 3III
I NUMBER EP RB-15:H DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 DATE 3/26/85 PAGE 4 0F 12 m, ~ , SENTRY POST-ACCIDENT SAPF'_ING SYSTEM
-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN i
4
- 16) After tne meter reading nas stabilized, record the reading and ccmpare to the temperature corrected pH value. Tne reading should be within 20.5 pH units of )
the temperature corrected value.
pH
- 17) Align CAP-V-6 to DEMIN WATER and flush for 2 []
minutes. Cycle V-7 from YSI to Rexnord.
- 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 -
1 is lit. []
- 5) Purge for 5 minutes (YSI) or 15 minutes (Rexnord) then read and record the temperature of the water in CAL-4 at the CMP.
, Tenp. *C l -
- 6) Determine the dissolved oxygen concentration from the Solubility of 0xygen in Air Saturated -
Water table (Appendix 2) and record the value.
ppm dissolved oxygen
- 7) Adjustment a) YSI:
While flowing, adjust the 07 calibration []
knob until the pen traces to tne dissolved oxygen concentration in ppm recorded in step 6),
i DC0416 4III
t 1 AND 2 NUMBER EP RB-15:H DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 1 DATE '3/26/85 PAGE 5 0F 12 7;7g' SENTR't. POST-ACCIDENT SAMPLING SYSTEM
-- PF/ CONDUCTIVITY / DIS 5CL'!ED OXYGEN l.
b) Rexnord:
'n'hile fic'aing, adjust the CAL ADJ to []
indicate the dissolvea oxygen concentration in ppm previously recorced 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) Align CAP-V-6 to LIQUID SAMPLE. (9 o' clock) []
- 2. LSP and CAP Purging If LSP has been previously purged during Reactor Coolant.
Liquid /cffgas sampling then prcceed to step c.
l
- a. Determine which sample scurce isolation valves will have to be opened from the list below:
SAMPLE SOURCE CONTAINMENT ISOLATION VALVES Hot Legs Loops I and 4 FCV-9356A and FCV-9356B Pressurizer Steam Space FCV-9354A and FCV-93548 Pressurizer Liquid Space FCV-9355A and FCV-9355B RHR Pumps Discharge N/A Volume Control Tank N/A
- b. Call the Control Room and have' operations block
~
[ .1 open the appropriate containment isolation valves. .
- c. Open the corresponding remote plant isolation []
valve (RPIV), remote source isolation valve (RSIV), .at the PCP (see Appenoix 1 for proper valve).
W G DC0416 5111
NUMBER EP RB-15:H DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1
, DATE 3/26/85 PAGE 6 0F I2 7;; g SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- PH/CONOUCTIVITY/ DISSOLVED OXYGEN i 1
- d. Close remote flush isolation valve (RFIV). []
BOTE 1: The sample source valves are labeled RC-V-1.1 through RC-V-1.5. Throughout this procedure, the form RC-V-1.X will be used to indicate the scurce 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.
FOTE 2: Upon implementation of the next step, sample will be flowing into the back of the LSP. The meter-long reach rod should be used to operate valves and a dose rate survey should be dor.e to monitor radiation levels,
- e. Open the sample source valve RC-V-1.X (see []
Appendix 1 for proper valve).
- f. Open RC-V-3. []
- g. If LSP has been previously purged proceed to step h. []
Sicwly open RC-VREL-1 until RC-FI-1 indicates 100% flow or 1900 cc/ min. Purge for 9 minutes.
- h. Slcwly close RC-VREL 1 until RC-FI-1 indicates []
36% or 700 cc/ min. Continue the purge for 1 minute.
- i. Close RC-V-3. []
- j. Open the following valves:
^
RC-V-7 ,]
l RC-V-2 J .
- k. Position RC-V-22 to the TO CHEM PANEL position. []
- 1. Adjust RC-VREl-2 until RC-FI-2 indicates 100% or []
200 cc/ min.
- m. Verify that the red FULL FLOW lights are lit for []
l the pH, 0 ,7 and COND loop at the CMP and CAP panels.
Adjust RC:VREL-2 if necessary to obtain proper flow rate.
- n. At the CMP, turn YSI CHART SPEED to RAPID and []
l verify PEN INPUT is set to -02*
I l
DC0416 6III i
O DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EP RB-15:H DATE 3/26/85 PAGE 7 CF 12 Tirts SENTRY FCST-ACCIDEtiT SAMPLING SYSTEM
-- PH/CONCL'CTIVITY/CISSCLV20 CXYGEN j 4
d
- 3. Sa.Tple Analysis
- a. Flow for 5 minutes'or until meter reading []
stabilizes. Cycle CAP-V-7 to YSI for 30 seconds and back to Rexnord.
- b. Observe and record conductivity meter reading and temperature.of the sample stream from the CMP.
Cond. umho Temp. *C
- c. 1) YSI:
Turn YSI CHART SPEED to 1 and mark the []
chart paper with the date/ time, 0 2 range, sample source, sample temperature, and operator's initials.
- 2) Rexnord:
Observe the Rexnord dissolved oxygen meter []
reading and t'irn to a lower scale position as the meter reading decreases. Purge 15 minutes,
- d. Read the 02 concentration. ppm 0 2
- e. Turn CAP-V-6 counterclockwise to 0XYGEN CALIB []
SOLUTION to terminate sample flow and permit pH reading to stabilize.
- f. Observe the pH meter for 1 minute to ensure the reading has stabilized. Record the pH reading.
, pH Temp. 'C
- g. If I.C. analyrcs is to be perfomed proceed to []
EP RS-15:G.
- 4. Flushing
- a. At the PCP, perform the following:
- 1) Close the remote source isolation valve. []
. DC0416 7III
/# -
NUMBER EP RB-15:H DIABLO CANYON POWER PLANT UNIT NO(S) , 1 AND 2 REVIS10N 1
. DATE 3/26/85 PAGE 8 0F 12 m gg SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN i
- 2) Open tne remote flush isolation valve (see Appendix 3 for proper valve). []
- b. At the LSP, close RC-V-1.X. [;
- c. At the-CAP, align CAP-V-6 to LIOUID SAMPLE.
(9 o' clock) []
- d. At the LSP, open RC-V-4 []
- e. Open RC-VREL-2 until RC-FI-2 indicates 100% flow or "[]
200 cc/ min. Flush with demin water for 1 minute.
- f. Close RC-V-7. , []
- g. Open RC-V-3. []
- h. Adjust RC-VREL-1 until RC-FI-1 indicates 100'. []
flow or 1900 cc/ min. Flush with demin water for 1 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 RC-V-7. []
i
- m. Adjust RC-VREL-2 until RC-FI-2 indicates 100%
flow or 200 cc/ min. Flush with demin water for 3 minutes. []
! n. At the CAP, align CAP-V-6 to 0XYGEN CALIB SOLUTION. []
- o. Terminate flushing by closing the following valves:
RC-V-7 ,[
RC-V-2 ,,,
RC-V 4 ,, 1 l
RC-VREL-1 ,,
RC-VREL-2
- p. Align RC-V-22 to WASTE. []
l )
DC0416 81II
45.
1 AND 2 NUMBER EP RB-15:H oiAsto CANYON POWER PLANT UNIT NO(S) REVISION 1 DATE 3/26/85 f PAGE 9 0Fs 12 7g g- SENTRY FCST-ACCIDENT SA"PLING SYSTEM
-- PH/ CONDUCTIVITY /D:5SDLVED OXYGEN
- i 4
- q. At the PCF, cicse the remote flush isolation []
valve. ,
- r. Call the cortrol room and nave operation: close []
the containnent isolation valves openec earlier.
+
- 5. Sanple Calculations,
- a. Correct the recorded sample pH for temperature []
f rom the pH~ Temperature Correction Table (Appendix 1).
- b. Transfer all data to data sheets EP F,B-I5:F. []
- c. If further analyses / sampling is to be done []
proceed to appropriate procedure.
/
- 6. System Shutdown
- a. CMP Shutdown
- 1) pH Monitor - Turn switches 5-3 and S-1 to []
the OFF position.
4
' 2) Conductivity Monitor - Turn function
- select []
1 switch to ZERO position, t
g 3) YSI Monitor - Turn YSI POWER switch to 0FF []
position.
5
POWER OFF and turn gas supplies off by lifting to horizontal position green root valves next to CAP.
/
REFERENCES
- 1. Sentry Equipment Corp. High Radiation Sampling System Operating
}
l Y and Maintenance Manual.
y APPENDICES
- 1. pH Tenperature Correction Table
- 2. Solubility of Oxygen in Air Saturated Water
- 3. Valves for Obtaining Samples from Reactor Coolant i
DC0416 9111 b '* . _ _ _ _ _ _ _ _ _ . _ _
f , .
NUMBER EP RB-15:H CIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REV1SION 1 DATE 3/26/85 PAGE 10 0F 12 m ,"e SEtiTRY POST-ACCIDE!:T SAMPLItiG SYSTE?1
-- PH/ CONDUCTIVITY / DISSOLVED OXYGEN s
t APPENDIX 1 pH TEMPERATURE CCRRECTION TAELES SAMPLE oH TEMPEPATURE CORRECTION TABLE
' TEMP *C CORR TEMP'C CORR 16 .31 31 +.20 17 .27 32 +.24 18 .24 33 +.26 19 .20 34 +.29 20 .16 35 +.32 21 .13 36 +.36 s 22 .10 37 +.40 23 .07 38 +.43 24 .03 39 +.46 25 .00 40 +.50 26 +.04 -
41 +.53 27 +.07 42 +.56 28 +.10 43 + 59 29 +.14 44 +.63
- 30 + 17 45 +.66 BUFFER pH TEMPERATURE CORRECTION TABLE RED GREEN BLUE TEMP pH4 pH7 pH10 10'C 4.00 7.06 10.18 15'C -- --
10.12 -
20*C 4.00 7.02 10.06 25*C 4.00 7.00 10.01 30*C 4.01 6.99 9.97 35'C -- --
9.93 40*C 4.03 6.98 9.89 45'C -- -- 9.86 50*C 4.06 6.97 9.83 60*C 4.09 6.98 --
70*C 4.12 6.99 --
80'C 4.16 7.00 --
90*C 4.19 7.02 --
95'C 4.21 7.03 --
- TAKEN FROM LABELS ON BECKMAN BUFFERS y
~~
DC0416 10111
- - _ _ _ _ _ _ _ - .-. __ __. . _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ a
1 l
NUMBER EP RB-15:li j OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 1 1 DATE 3/26/85 :
- PAGE 11 0F 12 7gtg SE'iTPY FCST-ACCIDENT SAMPLIt
- C SY3 TEM
-- Ph/CGlC CTIVITY/ DISSOLVED OXYGEN k i l l
APPENDIX 2 SCLUSILITY CF 07YGEN IN AIR SATURATEC WATER (For Oxygen in Air at 1 atm.)
TEMP PPM TEMP PPM C DISSOLVED *C DISSOLVED OXYGEN OXYGEN r
16 9.9 31 7.5 1 17 9.7 32 7.4 18 9.5 33 7.3 19 9.3 34 7.2 20 9.2 35 7.1 21 9.0 36 7.0 22 8.8 37 6.8 73 8.7 38 6.7 24 8.5 39 6.6 25 8.4 40 6.5 26 8.2 41 6.4 27 8.1 42 6.3 28 7.9 43 6.2 29 7.8 44 6.1 30 7.7 5 6.0 l
DC0416 11111
,- n -, n --
NUMBER EP RB-15:H 1 AND 2 oiAsto CANYON POWER PLANT UNIT NO(S) REVISION 1 DATE 3/26/85 PAGE 12 0F 12 m'E .
SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- FH/C0 CUCTIVITY/DISSCLVED OXYGEN APPEtiDI A 3 VALVES FOR CSTAINIt;G SAMPLES FROM REACTOR C00LANT LSP SAMPLE RE"0TE PLANT RE"0TE SCURCE REMOTE FLL'SH SOURCE ISOLATION VALVE ISCLATION VALVE ISOLATION VALVE V AL VE 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 B FCV-693 FCV-1417 RC-V-1.2 P2R Steam 9350 A FCV-694 FCV-1418 RC-V-1.3 RHR Pump 1-1 Discharge 9353 A FCV-1413 FCV-1419 RC-V-1.4 RHR Pump 1-2 Discharge 9353 B FCV-1413 FCV-1419 RC-V-1.4 VCT Liquid N/A FCV-1412 FCV-1420 RC-V-1.5 Rx Cavity Sump FCV-696 N/A FCV-1423 RW-V-2.1 FCV-697 Floor Drn Reevr N/A FCV-1415 FCV-1425 RW-V-2.2
.Equipm Drr. Reevr N/A FCV-1414 FCV-1424 RW-V-2.3 1
I I
i l
l
~~
- DC0416 12111
mm . NUMBER EP RB-16:A
.f W14 3 Pacific Gas and Electric (ompany REVISION 2
)n oEPARTMENT OF NUCLEAR PLANT OPERATIONS 4
iq cuscc CANYON POWEQ OLANT UNIT NC($; 1 AlC 2 * * #n - d, _
bl
- tu f-P EAGENCY OPBATING PROCEPURE SEPTFi POST-ACCICENT SAMPLING SYSTEM l
i
}
ut Tm E -- IN: TI E ACTIerd DuF,;t;C AN EPERGE ;Cy '
- ,/
-p o M / -
Aspacysc A. b /-WW" leM//O
/
j PLANT MANAGER f;- DATE 4
PURPOSE The purpose of this procedure is to defirie some of the actions taken when a decision is made by the Site Emergency Coordinator to cbtain a post accicent sample using the Post Accident Saniple System (PASS).
This procedure guides, with consideration of plant emergency radiaticr.
hazarcs, the Sentry tearn to access and make operable the Sentry room.
It also guides the team to withdraw from the Sentry room upon sample acquisition. This procedure is a guideline to emergency conditions.
Actual syster usage will be described in CAP G-4 for liquid sampling or G-5 for off gas. This procedure and changes thereto requires PSRC approval.
DISCUSSION This procedure ensures sample recovery with a minimum risk to personnel in a limited time frame.
The movable shield in the 85' penetration area will usually block that access route. Therefore ingress and egress may be required across the RCA boundary. Performance of this procedure may require the transfer of radioactive samples to ncn-RCA's. For these reascns this procedure involves exemptions from certain routine RCA access requirements.
Personnel implementing this procedure should be covered by an SWP during an accident, drill, or drill-like training. Routine use of the Sentry room is covered by the C&RP routine sampling RWP.
Particularly hazardous or unexpected conditions may occur in post accident situations. Direction by appropriate supervision may augment or supercece portions of this procedure because every possibility cannot be anticipated.
DC0128 IIX
r DIABLO CANYON POWER PLANT UNIT NO(S) NUMBER EP RB-16:A 1 AND 2 REVISION 2 1/21/85 DATE PAGE 2 0F 16 SENTRY POST-ACCIDENT SAMPLING SYSTEM TITLE -- INITIAL ACTIONS DURING AN EMERGENCY i
1 I t 1 PREREQUISITES AND FRECAUTIOh5
- 1. The Site Emergency Coordinator should pre r'an post-accident ;
sampling with the Emergency Radiolcgica' .evisor and the Site Chemical and Radiation Protection Coordinator prior to ordering a t plant entry (i.e., prior to deciding to collect a post-accident sample) when unusually hazardous radiation or contamination levels are known or suspected to exist.
- 2. A sufficient number of properly qualified personnel to complete the task should be av611able prior to making the post accident sample decision. This might include:
- a. Two people on the Sentry team; one of whom is a qualified C&RP Technician and the other an Unescorted Radiation Worker.
- u. A sample transporter qualified as a C&RP Technician.
- c. A count room qualified person in the TSC lab.
- 3. The Work Permit will specify protective equipment. Unless conditions warrant less stringent requirements, it is suggested that full PC's, SCBA's and accident dosimetry be worn. -
4 The Sentry team will make a post-accident entry to the plant only when directed by supervision and when possessing a high range portable survey meter to permit surveying into areas of unknown radiological conditions.
- 5. The Sentry team should be informed of plant status as it pertains -
to significant hazards, both radiological and non-radiological, along access routes. ,
- 6. Exposure hazards, both airborne and direct radiation, in the Sentry room should be monitored remotely for pre-entry status and locally for tracking while sampling.
- a. Use the Eberline Control Terminal (s) in either Access Control or the cold machine shop to remotely address the SPING air monitor in the Sentry room, which can be read locally.
i DC0128 21X
oiAaLO CANYON POWEA PLANT UNIT NO(S) NUMBER EP RB-16: A 1 AND 2 REVISION 2 DATE 1/21/85
- PAGE 3 0F 16 SEriTRY POST-ACCIDEfiT SAMPLING SYSTEM 787LE -- Iti'IllL ACTICiss DURItiG Afi EMERGEliCY .
1 I
. i 4
- b. Area radiation monitor RE-48, in the Ser,try room, can be esad in the Centrol Re:c. cr ic: ally.
- 7. Ccrzunications are vital during a ciant emergency. Entry tears ;
- s be acie :s c:municate w1:n t e : Ort-01 R;;m. anc 3;; :;riate supervision.
E. C&RP Technicians have th Rey required fcr access to areas and ecuictent related to this procedure ana have security key car:s tc enter c;cr =116 cr s197. If the Sentry team does not acssess either of *-=ea **=n take the acolicacle master keys
' :i e: :- tc ~-a <eg . /+25' l eiev m u<..ent ecas; rent ocser :. ocatec :r tre 1 4
- 9. Trc certainmert isolaticr. valves FCV-696, 697, 698, 699 and 700 are centrolled fr r the C y tainment Isciatien valve Parel in the
$ e r.try R30a. c r.1 - '>ces e '*-ba- require a key to operate. Keys are locateu
- 10. It is imaortar:.t to corduct c:eraticrs in ar ex eciticus manrer to pr:< ice tir.:ely sital plart status information.
RG ECURE
- 1. Access to Sentry Rocm Area The Diablo Canyon Shielding Review indicates that the follcwing routes might minimize exposures.
- a. Via Turbine Building at 85' Elevation 9
DC0128 31X
OIIBLO CANYON POWER PLANT UNIT NO(S)1 AND 2 NUMBER EP RB-16:A REVISION 2 OATE 1/21/85 SENTRY POST-ACCIDENT SAMPLING SYSTEM PAGE 4 0F 16 TITLE -- INITIAL ACTI0f.5 DURifiG AN EMERGENCY i i
- 1) Unit 1 l Starting at the Cold Machir.e Sh:p proceed into the hallway to door =125C, proceed north to door #122 ard exit building. Fr r- here turn south ar.d er.ter decr
- 192 to the Motor Repair Shop.
FIGURE la m . lb- - '
.- / -
__ Y,1 i ,,,
......,m *
'm ygl r -a
~
- i. 0100
'i> J :
y .
s, r;ni,
-....-...,,,s.. _t 0 00 DD i
__ fl
-- ~~- -
u -
1 1
O O .,,
i 117 131
=
=10]EJDJJ - -
00 OO DO D'.Oq- C ca Cca E ts '
o
, r.
I i
DC0128 4IX i
k .
1 OlABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP R8-16:A REVISION 2 DATE 1/21/85 SENTRY POST-ACCIDENT S W !.It?G SYSTE" 0F 1E Tiit.E .- INITIA'. ACTIONS DURIf;G AN EMERGENC) i !*
- l'
- 2) Unit II Starting at the Cold Mecnine Shop proceed into the 8 hailway to door *140, proceed south to decr -122 and exit building. From here turn nortn and enter =192 to the Motor Repair Shop.
FIGURE lb t
i I
^
If .. 2
.. : \. '
TIsi='l- r ', '"'m>l-......s, wu p d ""',;,,2 LLj 1
t T
_1 .
c.... ....
I ta ' :
a - T; L__;. O -
-r -
g 1,,.
r r- ,
, p_.7_..,)
O 00 $ o o 00 00 00 O ;n' , n
va __ ._
m .
1 m 4 DC0128 SIX c - - - , - - -
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AhD 2 NUMBER EP RB-16:A REVISION 2 DATE 1/21/85 SENTRY POST-ACCIDEf!T SAM?'.ItiG SYSTEM PAGE 6 0F 16 TITLE -- If;!TIAL ACTIO'iS DURItiG At; EMERGENCY i
?
- b. Arcund Turbine Building at 85' Elevation
- 1) Unit I Starting at the Cold Machine Shcp proceed west to tne outside via door #129, turn right and continue north around the Unit 1 Turbine Building looping arcund the transformers at the north end of the plant. Continue south to door #192 between containment and the Turbine Building. Enter the Motor Repair Shop via door #192.
FIGURE 2a
_ _s 4
.[ :-
. Y .
i 's s n.
. J . . . .
i
~...--- m 'ms j
', r r 0100
l -' i cpJm y
I
- i l 1,SCl l
' . O 000 0 0 0 ' '
l l l
, fl ,
u l
i i O o o=
., I;; ,,,
j 7.__
- . moot , ,
w I r 0 0,
1c d'E Q
. c O
?<i,
I ......................--. ........J l
l me e DC0128 6IX
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:A REVISION 2 DATE 1/21/85 SE.* TRY FCET ACCIDE:,7 SA FLING SYSTEM EM 7 UF IS TITus em 1r,ITIj,L ACTIONS DURIfiS AT EidERGEhCY !
- 2) Unit II Starting at the Cold Machine Shop ;;rt:2ed to the cutside via 3::.r :1:9, turn 'ef t and c:rtinue scutn arounc the Unit II Turbine Building looping around the transformers at the south end of the plant. Continue north te door *192 between containment and the Turbine Building. Enter the Motor Repair Shop via door a192.
FIGURE 2b
$ s ,
.. . . m o see-ee~..e e m
. es m
_y g- e' e
m> ,,,,{ . e e . e . . . . / ..,,
[,5;f " l '#
L- '
Le
- LLJ , Y1,
<: r :
6 i
oo i i 1 Q . ',,,, ! -
! ta - %1-,:!
O
- - gi"i O u
, , , .. . . . ... =a l .. ..e .
5 e l
. r r- :
pts e .
, .mee_j, ,a
'., O 00 00 Oo go , gO O ;", ' " ", ,' ,
~.
+
.- m- -e .i .. ,
's ,
g y
g M. ed
~. .eeeeoeseeeoeeeeee .
eeeeemeeeeeeeoeeeeemes# ,
\-
f DC0128 71X l
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h ON DATE 1/21/85 SEtiTRY POST-ACCIDENT SAMPLING SYSTEM PAGE 8 0F 16 TITLE -- INITIAL ACTIONS DURING AN EMERGENCY I
i i
- c. Other Access Rcutes The Figure la or Ib pa*hway is preferred. However an access l route other than those above may be suggested by actual post accident conditions (e.g., fire, hign energy line break, e tc. ) . The final route selected should be directed by appropriate supervisory personnel.
- 2. Initial Set-up of Sentry Room Equipment
- 6. Gas Supply Cylinders Check The gas supply cylinders for Sentry Room equipment are located along the east wall of the tiotor Repair Shop.
Proceed to the gas storage rack and verify the following:
- 1) The cylinder valves are fully open for all three cylinders.
- 2) The manifold valves are fully open for all three cylinders.
- 3) The argon regulator shows tank pressure of approximately 1000 psig and the regulator is set to 100 psig.
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, span gas cylinders should have at least 100 psig and both regulators should be set at .
10 psig.
- b. Emergency Ventilation System Line-up. (Optional. If proper ventilation is lined up proceed to step 2.c., Steel Shield DoorClosure).
I i
e G DC0128 EIX
DiAsLo CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RS-16:A REVISION 2 DATE 1/21/85 SENTRY POST-ACCIDENT SAM 0 LING SYSTEM PAGE 9 0F 16 TITLE -- It.ITIAL ACTIONS DURING AN EMERGENCY ;.
i I
i
- 1) Climb the ladder t
- cross to enter the ventilati:n c::n. -
1 i
- NOTE: Pinfrf:e the tire tha*. the v?qt r :r c:ces a-s !
c;er.
- 3) Proceed to the coter controllers for fans ard heaters lccated to the left of the breaker :arel and pusn the I ~C : in: EIE' :.f-t.::; :r 23:- : e.
a) EFE: lea 0 (IS-150) is the pre' erred systen.
a) Open its supply and exhaust dam ers and the su:p!y and exhaust vent dar;ers (a total of 4 dampers) ar.c cicse all other dampers, b) Push the START pushbuttons en the motor ccrtrollers for t*e EVER LEAD su:cly fan, exhaust fan, nr.c teater 29A, in that ceder.
5; EMEC REDUN (IS-151) is to be used as a backup if EMER LEAD is inoperable.
a) Open its supply and exhaust dampers and the supply and exhaust vent dampers and close all other dacpers.
b) Push the START pushbutton en the motor centrollers for the EMER REDUN supply fan, exhaust fan and heater 295, in that order.
- 6) Return to the Motor Repair Shop.
- c. Steel Shield Door Closure. (Optional, if the shield door is closed proceed to step 2.d., Radiological Assessment.)
h DC0128 91X
DIABLO CANYON POWER PLANT UNIT NOIS) 1 AND 2 Ih' h fP R8-16:A l DATE 1/21/85 SENTRY POST-ACCIDENT SAMPLING SYSTEFt PAGE 10 0F 16 TITLE -- It.ITIAL ACTIONS DURING AN EMERGENCY -
t 4
t i I
- 1) Proceedthroughdocrr192-j soutn of the Unit I Motor Repair Shop or doce elm-A nceth of the Unit 11 Mctor t Recair Sh:p. ar.d sisually check the snield d: r's wir.ch cable. If the marked portion of the cable indicates '
the snield is closed return to tne P:, tor Re;6tr in::,
and proceed with step d., Radiological Assessment '
below.
- 2) Operate tre wincn until tne marked portion of the cable visibly indicates the shield dccr is cicsed.
- . :eten :: 9e *:::- Re;3i- Ir::.
- d. Radiolegical Assessment of Sentry Rocm
- 1) Enter the Sentry roem via the ne or v116 r
=197) and the watertight decr .
- 2) Perfom a general area radiation survey a) Note high levels such as might exist at the availiar;r building end cf the room due to ECOS c y,ing.
b) Note low level areas for sample screen surveying later, i
- 3) Note the reading of RE-48 on the Process Control Panel (PCP). Recheck it intemittently.
- 4) Monitor airborne radioactivity using the SPING. If airborne levels permit the respirator, if worn, may be removed at this time. It should be denned anyttnie there is a potential for airborne contamination to be introduced into the room,
- e. Proceed to the Ventilation Control Panel.
- 1) Check the alarms, a) press TEST and note the red alarm Indicators flash while the audible alarm sounds.
e OC0128 10!X
DIA8LO CANYON POWED PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:A REVISION 2 DATE 1/21/85 SENTRY POST-ACCIDENT SAMPLING SYSTEM PAGE 11 0F 16 TITLE -- II.ITIAL ACTIONS DUR: fog AN EMERGENCY
+ I i i k
b) Press SILENCE to stop the audible alarm, cf Press ACK and note the fiasning alarm indicators glow steacily.
d) Press RESET and note the red alarm indicators go out.
- 2) If the NORl'AL VENT switch is on, turn it off.
- 3) If the EMER LEAD ventilation system is desired and is not operating depress in order the SUPPLY, EXHAUST, and HEATER pushbuttons. ,
- 4) Observe the appropriate indicating lights for proper operation of the desired ventilation line-up.
- 5) If necessary, return to step 2.b., Emergency Ventilation Line-up,
- f. Containment Atmosphere Sample Line Heating
- 1) Proceed to the CCP and pcsition the FUNCTION SELECT from 0FF to SF1-3/GGD.
- 2) Observe the following: -
a) The POWER ON indicator lights.
b) The flow monitor 20t and 100'; flow lights turn cn for approximately 25 seconds.
- 3) Press the PILOT LIGHT TEST pushbutton and note which lights are not functional.
- 4) Turn the HEAT TRACE POWER SWITCH to the ON position.
DC0128 111X
E NUMBER EP RB-16:A 0AsL@ CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 2
- DATE 1/21/85 SENTRY POST-ACCIDENT SAMPLING SYSTEM PAGE 12 0F 16 TITLE -- INIT!AL ACTICT:S DURING A!; EMERCENCY
- 5) Place the temperature select switches for EHT 1% ar.d EHT 197 to the down position marked 260'.
9 Rear Panel Access Rolling Shield Closure.
If the panel rciling shield is closed proceed to step 3.,
Electrical Line-up.
- 1) Perform this valve line-up check in the rear of the shielded panels:
CAP-V-13 CLOSED (above the GC) []
CAP-V-31 OPEN (adjacent to the GC) []
CAP-V-32 OPEN (adjacent to the GC) []
CASP-V-1 OPEN (overhead on cont. atmos.
supply line) []
CASP-V-2 OPEN (lower part of CASP) []
CASP-V-3 OPEN (mid part of CASP) []
- 2) Get the come-a-long from the cabinet and attach one end to the pad eye on the east wall and the other to the pad eye on the door.
- 3) Operate the come-a-long until the rolling shield is blocking the doorway.
- 3. Electrical Line-up ,
Proceed to the breaker panel PYNM , located next to the Vent Control Panel, and check
- positions of breakers as follows:
BKR #1 - ON [] BKR #2 - ON []
BKR #3 - ON [] BKR #4 - ON []
BKR #5 - ON [] BKR #6 - ON [] l BKR e7 - 04 [] BKR #8 - ON []
BKR #9 - ON [] BKR #10 - ON []
BKR #11 - ON [] BKR #12 - ON [] l MAIN B64 - ON []
i DC0128 12IX
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 1/21/85 SENTRY POST-ACCIDENT S WPLING SYSTEM PAGE 13 0F 16 TtTL2 -- INITIAL ACTIONS DJIfiG AN EMERGENCY I
The reagent gas tank (oxygen) is against the auxiliary building wall of the Sentry Room.
- a. . Initial Conditions of an Analyzer System
- 1) Mein power switch at remote panel in STANDBY. []
. NOTE: If the power switch is 0FF, then turn it to STANDBY ard give the system six hours to warm up. If both systems have not been in STAhD6Y for at least six hours, or are otherwise inoperable, use the gas chromatograph, step 5, below. Record the time of switching from 0FF to STANC8Y .
- 2) Solenoid operited sample line containment isolation valve switches CLOSED. (FCV-235,236,237, 238,239,240) []
- 3) Oxygen gas tank connected and isolation valve closed. (Tank should be changed at 100 psig) []
- b. H,'
Analyzer System (s) Operation.
CEL: 82 83 i) Turn the three sample lir.e switches to the OPEN position. Observe the -
position indicating lights. [] []
- 2) Open the oxygen tank isolation valve ano adjust regulator to 27 2 2 psig. [] []
- 3) Turn the main power switch from STANDSY to ANALYZE. [] []
- 4) Push the REMOTE SELECTOR pushbutton to gain control at this panel and reset COMMON ALARM, if necessary. [] []
- 5) Turn the dual range switch to the 0-10% range. [] []
. DC0128 131X u
DIABLO CANYON POWEl PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:A REVISION 2 DATE 1/21/85 SENTRY POST-ACCIDENT SAMPLING SYSTEM PAGE 14 0F 16 TITLE -- IN!TIAL ACTIONS DURING Ali EMEEGENCY i
CEL: 82 63 E) Adjust the ZERO and SPAN potentiometers until trey agree witn tnetr respective values indicated on calibration stickers located under ea:5 potentlemeter. [] []
- 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 6 minutes. [] []
- 9) Proceed with step 6., Initial Valve Line Up, while waiting for stabilization. When 6 minutes have elapsed since switching to SAMPLE, continue with step 10) below. [] []
- 10) Record the analyzer ceter reading, the time read, and the scale used. [] []
Meter Reading (%)
Time Scale Used NOTE: If the meter reads greater than 9t, the 0-20'4 scale should be used. .
- 11) Inform the Control Room of which scale '
and CEL is used and ask the Control Rocm 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 limited lifetime of the sample pumps, which are located in the 100' El. penetration area.
Power Up... [] []
DC0128 14IX t
EP RB-16:A OIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2
[
DATE N
1/21/85 set.TRY POST-ACCIDENT SAMPLING SYSTEM PAGE 15 0F 16
-- IhITIAL ACTICMS DLEING AN EMEP.GEhCy l Tats l i !
CEL: 82 83
- c. Standby
- 1) Turn the function selector to ZEPO and purge the analyzer fcr 6 minutes. [] []
- 2) Turn the main power switch 'to STANDBY. [] []
- 3) Close the reagent tank isolation valve. [] []
- 4) Turn the three sample line isolation valve switches to the CLOSED position. [] []
- 5) Push Common Alarm to Reset [] []
REFERENCES
- 1. Sentry Equipment Corp. High Radiation Sampling Systems Operations and haintenance Mar.ual.
APPENDICES
- 1. Reasent Preparation 5
- O DC0128 151X
DIABLS CANYON POWER PLANT UNIT NO(S) 1 AND 2 h ON
. DATE 1/21/85 SENTRY POST-ACCIDENT SAMPLING SYSTEM PAGE 16 0F 16 TITLE -- I i:TI AL ACTI0l:S OURI :G Afi EMERGENCY i
i ATTACHMENT 1 REAGE?iT FREPARATI0h NOTE: Reagents must nave a shelf life of 30 days. Reagents must be made using demin water with a conductance of less than 1 umho.
- 1. E1/E2 Eluent - 2mM ha0H/2.4mM Na2003 Add 0.329 haOH and 1.00g Na,CO (anhydrous) to 4.0 liters of demineralized water, dissolvt an,d mix.
- 2. 1p_ H2 S0 4 Add with stirring 120 ml of concentrated sulfuric acid to 4 liters of demin water and cool. Transfer the solution of a 4 If ter collapsable container, remove excess air, and label container with initials and date. Connect it to the line REGEN SYSTEM-1. Open the container valve and vent pump inlet lines.
- 3. Demineralized Water Rinse Fill a four (4) liter collapsable container with demin water.
Remove excess air from the bottle and label. Connect it to the water line in the reagent storage facility. Open the container valve and vent pump inlet lines.
separate 2 liter volumetric flasks. Dilute each flask tothe
- mark, with demin water. The cal tank holds 3.5 liters.
5
~*
0C0128 16IX
s .
NUMBER EP RB-16:B4 3GW3 Pacific Gas and Electric Company REVISION 2 IA1 DATE 3/7/85 .
CEDAATMENT OF NUCLE AR PLANT OPERATIONS
! 1 j: l-l. i 1 Afl0 e- PAGE 1 0F '7 OIABLO CANYON POWE A DLANT UNIT NOf Si ,
J ,
I y& EMERGENCY CPERAT!!iG PROCECL'?E 1 i
i r;l SEtr a POST.:CC;CEt:T Sw::,p.S Sv5 Ev i 7,Tsg -- 0;'_UTEC LIOL':0 3A::FL:.G FRC:; RA0WA57E I
[.'d.
9 n r i i a n na,ga h- (*. ' ~/ , b & -2?lN f P'.at.T MANAGER g 9 ATE j CIS'USS:0'.
Tre :2-::sc :f : is ;r::e:.re is :: :e:ri :-e 5:e:s re;uirec to cbtain a diluted licuid sample fror the radaste module during accf dent conditt:ns and ccmclete mcdule flushing.
Sarpie scurces addressed are Reactor Cavity Sump Equi; rent Orain Rc:eiver, Fi:;r Crain Re:eiver and RHR Fum Room surp.
The certaicreet isciatien valves FCV-696 and FCV-697 are controlled fr:r the Certainrent isolation Valve Panel in tha aatrv R0cm only.
.:. . ,.e.-res re .<ra 3 , y c-2r3..
ineseh3'Sesire5$tec;eneconi,,wringan
~
erer;eccy er rar :esting.
P3E;E0"ISITES
- 1. Systen was initially lined up as described in procedure EP RE-16:A.
- 2. Vert fy that the following annunciator windows are off on the PCP:
- b. RA0 WASTE SAMPLE COOL! fig WATER LOW PRESS
- c. RADWASTE SAMPLE COOLING WATER HIGH TEMP
- d. RA? WASTE HIGH TEMP
- e. LIGul0 SAMPLE PAfiEL HIGH PLENUM PRESS l
- 3. The fc11cwing equipment must be available and operational:
- a. Meter-long reach rod l
DC0294 IV t
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-15:84 REVISION 2 -
DATE 3/7/85 PAGE 2 0F 7 TITLE SEtiTRY POST-ACCIDEtlT SAMPLING SYSTEM
- -- 0
- LUTED LIQUID SAMPL!NG F.RCM UOWASTE ,
- b. Hand operated vacuum pump
- c. Sample cart / cask with 60 mi lift rod asser.cly
- d. A prelabeled 50 mi sample bottle with a new septum
- 1) The label shculd have the sample source, date, estimated time of sample, and the initials of the person taking the sample (from this point estimate 21 minutes).
PRECAUTIONS
- 1. This sampling involves processing of water that will be highly radicactive. Precaution shculd be taken to prevent skin contact or ingestion.
- 2. Time in a radiation field should be limited to that necessary to perform the required operations. During purge and flush periods, it may not be necessary to stand near the panels and consideration should be given to moving to a low dose rate area.
- 3. A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.
PROCEDURE
- 1. Verify RW-DV-1 is turned to BYPASS. Fill reservoir []
RW-R-1 with demin water,
- a. Open RW-V-10 and RW-V-9. []
- b. Adjust reservoir RW.R-1 until the water level in graduated cylinder RW-C-1 is at least 100 ml. []
- c. Close RW-V-9 and RW-V-10. []
- 2. Insert the needle of the hand operated vacuum pump []
into the septum of the prelabeled 60 m1 sample bottle:
- a. Evacuate to the maximum vacuum achievable with []
the pump. The vacuum must be at least IS" of Hg.
- b. Keep the pump connected to the bottle for 1 minute []
to assure that the bottle retains the vacuum, i
DC0294 2V
, f
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:84 REVISION 2 DATE 3/7/85 PAGE 3 0F 7 LTLE SEriTRY FCST-ACCIDEt;T SWLING SYSTEM
. f -- CILUTED '.!OUID SAM ....; ravM RAC;;AST~
1 I I .'
- 3. Turn on tne switen to light the diluted bottle fill []
station.
- 4. Remove the bottle frcm the vacuum pump and place []
the bottle on the cart / cask assembly cavity piston.
- a. Turn the direction valve for the~ hydraulic piston []
to one down position and lower the bottle into the cask cavity.
- b. Close and open the cask to verify that the cover []
is working properly,
- c. Position the cart / cask under the diluted radwaste []
fill station needle and set the brake,
- d. Turn the direction valve for the hydraulic []
piston to the up position and raise the bottle onto the needle.
- 5. Alien RW-V-8 to the 9 o'c1cck position. []
Align RW-V-4 to the SAMPLE position. []
- 6. Sample Purging Reactor Cavity Sump:
Coordinate with Operations to turn on the reactor cavity sump pumps, then open containment isolation valves FCV 500 and 501 for one minute and then close. Open valves FCV 696 and 697.
Containment isolation valves FCV 696 and 697 are key operated valve switches controlled in the Sentry Room at the POST LOCA CNT ISOLATION PANEL. .
Equipment Drain Receiver or Floor Drain Receiver:
Coordinate with Operations to have EDR or FDR placed on recirculation for Post Loca Sampling.
RHR Room Sump:
Verify with control room that RHR room high level is indicated.
Coordinate with Operations to transfer the entire contents of a FOR to another holding tank or overboard. Manually pump down RHR room sump to the empty FOR and place FOR on recirc for Post Loca Sampling.
DC0294 3V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP R8-16:84 REVISION 2 DATE 3/7/85 PAGE 4 0F 7 t
ME SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- CILUTED LIQUID S*MPLING FROM RACMSTE ,
- a. Open the corresponding remote plant isolation []
valve (RPIV), reccte source isolation valve (RSIV),
at the PCP (see Apper. dix 1 for proper valve),
- b. Close the remote flush isolation valve at the PCP. []
NOTE: The sample source valves are labeled RW-V-2.1 thru RW-V-2.3. Throughout this procedure, the form RW-V-2.X will be used to indicate the source valve to be operated. The sample source used for sampling will have been given at the briefing by the Site Chem and Rad Protection Coordinator,
- c. Slowly open Sample source v'alve RW-V-2.X (see []
Appendix 1 for proper valve) until RW-FI-1 indicates 100% flow or 200 cc/ min. Purge to waste for 7 minutes.
- 7. Sampling a ._. Turn RW-V-8 to BYPASS. []
- b. ' lose C RW-V-2.X. []
- c. Close FCV-696 and FCV-697 if opened earlier []
and notify the control room when closed.
- 8. Initial Flushing
- a. At the PCP, close the remote source isolation []
valve if applicable,
- b. Slowly open RW-V-3 until RW-FI-1 indicates 30% []
flow or 60 cc/ min. Flush with demin water for 2 minutes. }.
- c. Slowly open RW-V-2.X until RW-FI-1 indicates 30% []
flow or 60 cc/ min. Flush with demin water for .
3 minutes.
- d. Close RW-V-2.X and RW-V-3. [] l
- e. At the PCP, open the remote flush isolation valve []
(see Appendix 1 for proper valve). Flush with demi,n water for 6 minutes.
s .
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:84 REVISION 2 DATE 3/7/85 PAGE 5 Or 7 TITLE SET.TRY POST-ACCICEt.T SAMPLit,G SYSTEM
- -- DRUTED LIQUID SAMPLING FROM RA0 WASTE i
- 9. Sample Dilution
- a. Turn RW-DV-1 to SAMPLE. []
- b. At RW-C-1, read initial ml .
Crack open RW-V-9 and add 23 mis of water from RW-C-1 to the sample bottle, then close RW-V-9.
Read final ml Record the volume added. mis
- c. Turn RW-DV-1 to BYPASS. []
- d. Place the directicn valve for the hydraulic []
piston in the down position and slowly lower the bottle into the cask.
- e. Close the cask. []
- 10. Sample Cask /Ca.-t Removal
- a. Release the brake and remove the cart / cask from []
the sample station.
- b. Perform a radiation and contamination survey on []
the cart / cask assembly and transfer the sample according to the appropriate EP RB-16 Subprocedure.
- 11. Turn off the diluted fill station light. []
- 12. If sample is to be analyzed at CAP:
- a. Turn RW-V-4 to CHEM PANEL. []
- b. Proceed to EP RB-16 Section G for I.C. Analysis []
and/or Section H for pH/ conductivity /DO.
- c. After analyses return to this section.
- 13. Final Flushing
- a. Turn RW-V-8 to the 9 o' clock position. []
DC0294 SV
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-86:B4 REVISION 2 DATE 3/7/85 PAGE 6 0F 7 TITLE SENTRY FOST-ACCIDENT SAPPLING SYSTEM DILUTED LIQUID SAMPLING FROM RA0 WASTE i !
i i
- b. Slowly open RW-V-3 until RW-FI-1 indicates 100% []
ficw or 200 cc/ min. Flush with demin water for 2 minutes.
i
- c. Turn RW-V-8 to SYPASS. []
- d. Terminate flushing by closing the following valves:
RW-V-3 []
- 14. Close Sarple Cooler Water. []
diluted liquid sample for boron and specific activity.
- 16. Process the deta according to EP RB-16:F. []
REFERENCES
- 1. Sentry Equipment Corp. High Radiaticn Sampling System Operating and Maintenance Manual.
~
APPENDICES
- 1. Valves for Obtaining Samples from Radwaste.
I i
~*
DC0294 6V
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:84 REVISION 2 DATE 3/7/85
. PAGE 7 0F 7 mLE SEP.TRY POST-ACCIDO;T SAs9L!r;G SYSTEt>
-- O! LUTE 0 L:CU:0 SAl;FtIN3 FRC. EADWASTE l l I :
APPEtiDIX 1 l VALVE 3 FOR 057AINItiG SA?9LES FRCM RA WASTE CONTAINMErdi REMOTE SOURCE REMOTE FLUSH LSP SAMPLE SAMPLE ISOLATIO!. ISOLATI0t1 ISOLATION SOURCE SOURCE VALVES VALVE VALVE VALVE Rx Caity Su:r,7 FCV-696 Not FCV-1423 RW-V-2.1 FCV-697 Applicable Floor Drn Reevr Not FCV-1415- FCV-1425 RW-V-2.2 Applicable Eouip Drn Reevr Not FCV-1414 FCV-1424 RW-V-2.3 Applicable 9
4 O DC0294 7V
NUMBER EP RB-16:B5 PGW3 Pacific Gas and Electric Company REVISION 2 D canamENT cr nuct.zaa staNT cosnArious
,[ 1 AN E I C I 021.c cAwcn Pcw2a pun! UNtr Ncis; i oii EMER3Et.a C.:ERATING PRacEcu:E f h] :'7' ?OST *::::E';T : APPL.*N3 c/ITZ" j g i,rtz -- UaDILLIED LIQUID SAff9 LING FRC5' RADWASTE appnoveo T. /N N'#~g' FLANT MA'MGER 3/ho/?3 DATE j
DISCUSSION The purpose of the procedure is to detail the steps required to obtain ar undiluted radwaste liquid sample during accident conditions and complete module flushing. Sample sources addressed are Reactor Cavity Sump. Equipment Orain Receiver, Floor Orain Receiver and RHR Pump Room Sump.
PREREQUISITES
- 1. Syster: was initially lined up as described in procedure EP RB-16:A.
- 2. Verify that the following annunciator windows are off on the PCP:
- a. RADWASTE SAMPLE COOLING WATER LOW FLOW
- b. RADWASTE SAMPLE COOLING WATER LOW PRESS
- c. RADWASTE SAMPLE COOLING WATER HIGH TEMP
- d. RADWASTE HIGH TEMP
- e. LIQUID SAMPLE PANEL HIGH PLENUM PPESS
- 3. The following equiement must be available and operational:
- a. Meter-long reach rod
- b. Needle flush tool with demin water in a 15 mi sample bcttle and a new septum,
- c. ~5 ample cart / cask with the 15 mi lift rod assembly.
- d. A prelabeled 15 m1 sample source, date, estimated time of sample, and the initials of the person taking the sample (from this point estimate 16 minutes).
OCO294 IV!
o -
OtABLO CANYON POWED PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:85 REVISION 2 DATE 3/7/85 7,7tg PAGE 2 0F 7 SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- UNDILUTED LIOUID SAMPLING FRCM RADWASTE I '
-)
i FRICAUTIONS I 1.
This radioactive. sampling involves processing of water that will be highly or ingestion. Precsutiens shoulo be taken to prevent skin contact \
i 2.
Time in a radiation field should be limited to that necessary to perform the required operations.
it.may not be necessary to stand near the panels and"oring purge and flush perio consideration should be given to moving to a low dose rate area. {
3.
A dose rate instrument should be on and periodic monitoring is suggested during purge and sampling exercises.
PROCEDURE 1.
Turn on the switch to light the undiluted fill station. [] !
2.
Place the bottle on the cart / cask assembly cavity piston, []
- a. Turn the direction valve for the hydraulic piston in'the down. position and lower the bottle []
into the cask cavity,
- b. Close and open the cask to verify that the cover is working properly. []
c.
Position the cart / cask under the undfluted []
radwaste fill stations needles and set the brake.
- d. Turn the direction valve for the hydraulic piston to the up position and raise the bottle onto the [] '
needles.
- 3. Sample purging Reactor Cavity Sump:
Coordinate with Operations to turn on the reactor cavity sump pumps, then open containment isolation valves FCV 500 and 501 for one minute. Close isolation valves FCV 500 and 501 and open valves FCV 696 and 697. Containment isolation valves FCV 696 and 697 are key operated valve switches controlled in the Sentry Room at the POST LOCA CNT ISOLATION PANEL.
I DC0294 2VI '*
DIABLO CANYON POWEb PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:85 REVISION 2 DATE '3/7/85
- PAGE 3 0F 7 ;
" SENTRY POST-ACCIDENT SA"9 LING SYSTE'-t
-- UNDILUTED LIQUID SAYFLING FRO.'t RADXASTE I
Ecuioment Drain Receiver or Floor Drain Receiver:
Coordinate with 0;erations to have EOR or FOR placed en recirculaticr. for Post Loca Samoling.
RHR Roc:- Sump:
Verify with control room that RHR room high level is indicated. Coordinate with Operations to transfer the entire contents of FDR to another holding tank or overboard.
Manually pump down RHR room sunp to FDR and place FDR on recirc for Post Loca Sampling.
- a. Aliga RW-V-4 to the SAMPLE position. []
- b. Open the corresponding remote plant isolation []
valve (RPIV), remote source isolation valve (RSIV), the PCP (see Appendix 1 for proper valve),
- c. Close the remote flush isolaticn valve at the PCP []
(see Appendix 1 for proper valve).
t0TE: The sample source valves are labeled RW-V-2.1 thru RW-V-2.3. Throughcut this procedure, the form RW-V-2.X will be used to indicate the source valve to be cperated. The sample source used for sampling will have been given at the briefing by the site Chem and Rad Protection Coordinator.
- d. Slowly open the sample source valve RW-V-2.X []
(see Appendix 1 for proper valve) until RW-FI-1
~
indicates 100t flow or 200 cc/ min. Purge to ,
waste for 7 minutes.
- 4. Sampling
- a. Adjust RW-V-2.X until RW-G-1 indicates 20 psig or less. []
cal 1710N: Do not exceed 20 psig on RW-G-lin these steps.
- b. Turn RW-V-7 to SAMPLE. []
DC0294 3VI
F
. DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:B5 REVISION 2 DATE 3/7/85 TITLE SENTRY POST-ACCIDENT SAMPLING SYSTEM PAGE 4 0F 7-
-- UCILUTED LIQ"ID SAMPLING FROM RADWASTE l _..
c.
Ajjust P.W-V-2.X until RW-G-1 indicates 20 psig []
or RW-FI-I Purge for 1 indicates minute, 40% ficw or 80 cc/nin.
- d. Close'RW-V-2.X.
[]
- e. Let RW-G-1 return to O psig and wait 30 seconds to allow bottle to depressurize. []
f.
Turn RW-V-7 to BYPASS.
[]
- g. Close FCV-696 and FCV-697 if opened earlier and notify control room when closed. []
- 5. Sample Cart / Cask Removal a.
Turn the direction valve for the cart cask []
hydraulic piston to the down position and slowly lower the bottle into the cask.
b.
Close the cask. Release the brake and remove the []
cart / cask from the sampling station and away from the LSP.
- c. Install and secure the auxiliary shield. []
- d. Install and secure the needle flush tool containing a 15 mi sample bottle onto the []
undiluted radwaste fill station needles.
- 6. Initial flushing -
- a. At the PCP, close the sample source isolation '
valve. (See Appendix 1) []
{
- b. Slowly open RW-V-3 until RW-FI-1 indicates 307 flow or 60 cc/ min. Flush with demin water for [] l 3 minutes.
[
- c. Slowly open RW-V-2.X until RW-FI-1 indicates 307, flow or 60 cc/ min. Flush with demin water for []
3 minutes.
- d. Close RW-V-2.X and RW-V-3. []
I DC0294 4VI --
- mo
v e DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:B5 REVISION 2 DATE 3/7/85
. PAGE 5 0F 7 mg SE';TRY POST-ACCIDE':' SA"? LING SYSTEM
-- UNDILUTED LICUID SAM?LIti3 FRCM RA0 WASTE l
i I 3
- e. At the PCP, cpen the remote flush isolation []
valve (see Ac:endix 1 for orcrer valve). Flush with denin water for 6 minutes.
- f. Close :ne remote flush isolatien valve at the [] l PCP.
- 7. If sample is to be analyzed at CAP:
- a. Turn RW-V-4 to CHEM PANEL. []
and/or Section H for pH/ conductivity /00.
- c. Af ter analyses return to this section. []
- 6. Final Flushing
- a. Turn PW-V-7 to SAMPLE []
CAUTION: D> not exceed 20 psig on RW-G-1 in this step.
- b. Slowly cren RW-V-3 until RW-G-1 indicates 20 []
psig or RW-FI-1 indicates 301 flow or 60 cc/ min.
Purge fcr 2 minutes.
- c. Close RW-V-3 and let RW-G-1 return to O psig. []
Wait 30 seconds to allow the bottle to .
depressurize.
- d. Turn RW-V-7 to BYPASS. []
- 9. Turn off the undiluted fill station light. []
- 10. Remove the needle flush tool and survey bottle for []
disposal.
- 11. Perform a radiation and contanination survey on the []
cart / cask assembly and move the sample according to the appropriate EP RE-16 Subprocedure.
- 12. Close Sample Cooler Water. []
diluted liquid sample for boron and specific activity.
m 9 DC0294 SVI
o OtA8LO CANYON POWEQ PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-26:B5 REVISION 2 DATE 3/7/85 PAGE 6 0F 7 7,7t,
~
SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- UNDILUTED LIQUID SA?GLING FRCM RAD'a'ASTE 1
- 14. Process tne data according to EP RS-16:F.
REFERENCES
- 1. Sentry Equipment Corp. High Radiaticn Sampling System Operating and Maintenance Manual.
APPENDICES
- 1. Valves for Obtaining Samples from Radwaste.
2%
9 l
l-1 t
DC0294 6VI O m-
DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-16:B5 REVISION 2 DATE 3/7/85 PAGE 7 0F 7 m tg SENTRY POST-ACCIDENT SAMPLING SYSTEM
-- UNDILUTED LICUID SAMPLINS FROM RADWASTE I
. I t '
APPEt; DIX I VALVES FOR 05TA!fiING SAMPLES FROM RADWASTE C0fiTAINMENT REMOTE SOURCE REMOTE FLUSH LSP SAMPLE SAMPLE ISOLATION ISOLATION ISOLATION SOURCE SOURCE VALVES VALVE VALVE VALVE Rx Cavity Sump FCV-696 Not FCV-1423 RW-V-2,1 FCV-697 Applicable Floor Drn Reevr tiot FCV-1415 FCV-1425 RW-V-2.2 Applicable Equip Drr. Reeve flot FCV-1414 FCV-1424 RW-V-2.3 Applicable 0
W
~~
DC0294 7VI
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