ML20133D031
| ML20133D031 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| Issue date: | 07/18/1985 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML16341D347 | List: |
| References | |
| 0502D-0005K, 502D-5K, PROC-850718-01, NUDOCS 8508070205 | |
| Download: ML20133D031 (100) | |
Text
{{#Wiki_filter:_ _ _ - _ _ _ _ _ 6 e PGandt Letter No.t DCL-85-245 4,, . a 1 ENCLOSURE 1 Updates Included In This Submittal DIABLO CANTON MERGENCY PLAN MPLMENING PROCEDLRES Volume 3A Updated Tele of Contents EP M-4, Revision 9 Volume 38 Updated Table of Contents EP OR-1, Revision 5 l 1 f F h"IEESQ3 00w - l
,,o, PGandE Letter No. DCL-85-245 e j 9 ENCLOSURE 2 Location of Proprietary Information Procedure: EP M-4 -- pp. 3, 6, and 11 of 50; Data sheet ) " Post Earthquake Evaluation Summary", p.1 of 1. EP OR-1 -- Table 1, "Of fsito Emer!pncy Support orgenization Phone List," pp. '-9 of 9 0602d/0005K 1- -. mmi mmu-m
s PGandE Letter Jb.: DCL-85-245 ENCLOSURE 3 j Updates to Diablo Canyon Emergency Plan Imp 1ementing Procedures O 9 0502d/0005K
[i, PGandE Letter No.: DCL-85-245 ~ e l CURRENT IMERGENCY PLAN MPLEMENTING PROCEDURES TABLE OF CONTENTS Volume 3A 1 TITLE REV l E-0 Reactor Trip or Safety Injection 0 E-0.1 Reactor Trip Response O E-0. 2 Watural Circulation Cooldown 1 E-0,3 Natural Circulation Cooldown with Steam Vof d in Vessel 1 (with RVLIS) E-0.4 Natural Circulation Cooldown with Steam Void in Vessel 0 (Without RVLIS) E-1 Loss of Reactor or Secondary Coolant 0 E-1.1 SI Termination 0 E-1.2 Post LOCA Cooldown and Depressurization 0 E-1.3 Transfer to Cold Leg Recirculation 0 E-1.4 Transfer to Hot Leg Recirculation 0 E-2 Faulted Steam Generator Isolation 0 E-2.1 Alternate Auxiliary Feedwater Supplies O E-3 Steam Generator Tube Rupture 0 ECA-0.0 Loss of All AC Power 0 ECA-0.1 Loss of All AC Power Recovery Without SI Required 0 ECA-0.2 Loss of All AC Power Recovery with SI Required 0 ECA-0.3 Restore Vital Bus 0 ECA-1.1 Loss of Emergency Coolant Recirculation 0 ECA-1.2 LOCA 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 Response 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 Capab11ities 0 t 0502d/0005K 07/18/85 -___.._m.
j j l TABLE OF CONTENTS (Continued) FR-H.5 Response to Steam Generator Low Level 0 FR-P.1 Response to Imminent Pressurized Thermal Shock Condition 0 FR-P.2 Response to Anticipated Pressurized Thermal Shock Condition 0 FR-Z.1 Response to High Containment Pressure 0 FR-Z. 2 Response to Containment Flooding 0 FR-Z. 3 Response to High Containment Radiation Level 0 FR-I.1 Response to High Pressurizer Level 0 FR-I.2 Response to Low Pressurizer Level 0 FR-I. 3 Response to Voids in Reactor Vessel 0 R-1 Personnel Injury or Illness (Radiologically Related) 15 j and/or Overexposure R-2 Release of Airborne Radioactive Materials 5 R-3 Release of Radioactive Liquids 4 i 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 Empioyee Injury or Illness (Noneadtological) 13 M-2 Nonemployee Injury or Illness (Third Party) 11 M-3 Chlorine Release 5 M-4 Earthquake 9 M-5 Tsunami Warning 5 2 M-6 Nonradiological Fire 10 M-7 011 Spill Isolation and Clean Up Procedure 7 M-8 Containment Emergency Personnel Hatch 0 M-9 Hazardous Waste Management Contingency Plan 2 M-10 Fire Protection of Safe Shutdown Equipment, Unit 1 3 M-10 Fire Protection of Safe Shutdown Equipment, Unit 2 3 G-1 Accident Classification and Emergency Plan Activation 5 G-2 Establishment of the On-Site Emergency Organization 7 G-2 51 Emergency Organization Call List Form 69-10297 2 G-3 Notification of Off-Site Organizations 6 G-4 Personnel Accountability and Asseirbly 6 G-5 Evacuation of Nonessential Site Personnel 2 0502d/0005K 07/18/85
~ NUMBER EP M-4
- %eSW3 Pacific Gas and Electric Company REVISION 9 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1
50 i otABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE EARTHQUAKE TITLE IMPORTANT 1 TO [ ~l E f i-APPROVED PLANT MANAGER g/ DATE SAFETY 4 4 SCOPE This procedure and changes thereto require PSRC review. GENERAL Earthquakes affect the plant by producing ground motion causing plant buildings and equipnent to be stressed by induced vibration. This vibration is defined by a spectrum consisting of acceleration, frecuency and duration. The values of these parameters used in the , design of the Diablo Canyon Plant are given in Section 3.7 of the FSAR. Instrumentation at the site measures and records acceleration frecuency and duration, but only the maximum acceleration along three perpendicular axes is indicated. The seismic instrumentation which neets the requirements of Technical Specification Table 3.3-7 is described in Appendix 1. Only accelerations of greater than 0.01 g's on the containmeret base slab are recorded on the triaxial time-history accelographs. For purposes of this procedure, earthquakes are classified by the meximum acceleration indicated by the triaxial accelerometer located on the cor.tainment base slab. DCPP NUREG-0654 NUREG-0654 Maximum Earthquake Classification Action Acceleration (c's) Classification Criteria Level Unmeasured to 0.01 Micro Not detected None in plant. 0.01 to 0.1 Moderate Detected or felt Unusual event in plant 0.1 to 0.2 Strong Detected Unusual event 0.2 tc 0.6 Large Greater than Alert OBE levels Greater than 0.6 Major Greater than Site emergency SSE levels DC0036 IIX r c- -e,. --.m .--m
N -4 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 l p DATE 6/1/85 PAGE 2 0F 50 TITLE: EARTHQUAKE 4' r f 1 Unmeasured to moderate earthquakes are expected at Diablo Canyon during the life of the plant. A strerg, large or major earthquake is not expected. This is based on geological explorations and on the ? recorded seismic history of the site. This procedure is to be followed in the event that an earthquake occurs which triggers the recording instruments or is felt in plant. In the event that damage occurs, follow the appropriate Emergency Operating Procedure to mitigate the consequences of the damage first, then follow this procedure for investigation of the plant for further damage and reporting. The operator response is graduated, based on the local acceleration indicated by the Earthquake Force Monitor (EFM) up to 0.5g or on '.he SMP-1 playback if greater than 0.5g. MICR0 EARTHOUAKE (Unmeasured to 0.01g) Symotems 1. The supplerental system (SS), Terra Technology DCS-302, is triggered but the basic system (BS) Kinemetrics SMA-3, is not triggered. This means alarm input no. 1186 is in alarm and alarm input no. 1112 is not in alarm on PK 15-24 (" Seismic Instr Sys tem ). NOTt 1: If ground motion is felt "in-plant" by the operations staff, discontinue this section and go to the Moderate Eartnquake section. NSE 2: "In-plant" is insioe the double fence (Plant Protected Area). ~ Autocatic Actions None expected. Immediate Operator Actions None. l I i l 4 DC0036 2IX l l l I
I NUMBER EP M-4 1 AND g REVISION 9 OIASLO CANYQN POWER MT UNIT NO(S) DATE 6/1/85 .PAGE 3 0F 50 EARTHQUAKE TsT g Subsecuent Actions 1. Subsequent Operator Action hotify the on-call Power Production Engineer (Nuclear),(EP a. G-2 Data Processor No. 2, on call rotation personnel), the next werking day to retrieve the Supplemental System data. Document the activation of the Supplemental System with a b. Problem Report. 2. Subsequent Pcwer Prcduction Engineer Action j Have the I&C departrent retrieve the data frcm the a. Supplemental Seismic Monitoring System. ) 1) Perfom a post-event calibration of the SS tapes.
- )
Make strip charts of the functional free field and trigger chanrels and others as directed by the Power Freducticn Er.,ineer (Nuclear). 3' Ir.sta t rew set of tapes in the SS recorder, at
- (
discretion of cr-call Pcwer Producticn Engineer (Nac l et.r ). 4) Ferferr. pre-esent calibration. 5) Forward the stri; charts and retoved tares te the on-call Power Production Engineer (Nuclear). l 11 the U.C. Berkeley Seisnographic Station at ~ b. ind obtain the epicenter location and magnitude of This any earthquake which could account for the SS trigger. recording is updated each weekday at 7:30 a.m. PST, and ccsers the previcus 72 hour period. TOTE: If no earthquake was recorded by the Berkeley Station, it may be desirable to contact the itute of Technology (Cal Tech) Seismic California n Center at for possible epicenter location and magnitude information. OC0036 3IX
, otASLO CANYON POWER PLANT UNIT NO(S) I # 'O 2 ) NUMBER EP M-4 l ' REVISION 9 l DATE 6/1/85 ) PAGE 4 0F 50 7,7tg EARTFQUAKE 9 r t Forward the strip charts and any information obtained from c. the Seismic Station to Civil Engineering, and request guidance as to the disposition of the SS tapes (i.e., erase and reuse, send to Terra Technology Corp., etc.). i d. } Retain the SS tapes untti directed by Civil Engineering as } to their disposition. MODERATE EARTHCt'AKE 0.Olg to 0.1g Symptoms 1. Grounc motion is felt "in-plant" (inside the double fence) by the Operaticns staff. 2. The " Seismic Instr Syster" annunciator is activated (PK 15-24). 3. The maximum acceleration on the containment base slab is indicatec to be between 0.01 ano 0.1g by the EFM. Aatcmatic Actier.s Ncne expectec. Irrediate Ocerator Actions 1. Notif, the Sr.if t Foreran (Interim Site Emergency Coordinator). 2. Male a general survey of the Centrol Rcon instrumentation, with particular attention to annunciator and computer alarms, to verify tnat no apparent plant damage has occurred. Subsecuent Actions 1. Notify the shift CARP to make preparations for entering Containment to conouct a quick fire inspection. 2. General Establish the onsite emergency organization for an Unusual a. Event as specified in EP G-2 " Establishment of the Onsite Emergency Organization." s DC0036 4IX r
NUMBER EP M-4 .s 1 AND 2 REVISION 9 c. DPBLd CANYON POWER PLANT UNIT NO(S) DATE 6/1/85 PAGE 5 0F SO s EARTHQUAKE I rarts i hetify offsite organizations as specified in EP G-3 b. " Notification of Offsite Organizations." Instruct the on-call Power Production Engineer (Nuclear) (EP G-2 Data Processor No. 2, on-call rotation personnel) to c. come onsite and retrieve seismic data. 3. Subsequent Operator Action If a unit trip has occurred, maintain the unit in HOT STANDBY (MODE 3) until the Plant Manager authorizes a return a. to power. Within two hours following an earthquake exceeding 0.02g, inspect all zones listed in Technical Specification Table b. (If the Kinemetrics SMA-3(BS) was not 3.3-11 for fires. triggered, assure the earthquake to be less than 0.02g.) If a pcrtion of the Fire Protection Systen is damaged f0TE: by the earthouake, as indicated by visual inspection ernunciaticr., it should be isolated from the cr ' lot remainder of the system (see Appendix 3 for Fire ,( Syster Iscl. Give numbers and locations). ( Comoirtc the " Post-Earthouake Level Indicator Check List," (Form 69-9249) and give it to the Shift Foreman. c. The Unit (s) will be placed in HOT STANDBY if investigatice reveals physical damage which could impair the cperatier cf d. any Seismic Class I equipment. Subsecuent Pcwer Production Engineer Action 4 Sections a, d and f are not applicable if the Basic System NOTE: has not triggered. Contact the I&C Department to retrieve the seismic data from the Kinemetrics SMA-3 basic seismic monitoring system (85). a. (See STP I-37C.) 1) Perform a pcst-event calibration of the 85 tapes. Reolace the tape cassettes in the SMA-3 and perform a 2) pre-event calibration. DC0036 SIX
otAago CANYON POWER PLANT UNIf NO(S) 1 AND 2 NUMBER EP M-4 REVISION 9 DATE 6/1/85 PAGE 6 0F SO 'rsru EARTHQUAKE j 3) Reset the EFM. 4) Play back the tapes removed from the SPA-3 on the SMP-1 and make strip charts. 5) Forward tapes and strip charts to the on-call Power } Production Engineer (Nuclear). ) b. Contact the I&C Department to retrieve additional seismic data from the supplemental seismic monitoring system. 1) Perferm a post-event calibration of the SS tapes. 2) Install a new set of tapes in the SS recorder and perform a pre-event calibration. 3) Make strip charts of the functional frea field, trigger, containment base slab and spring line channels. ) Fomard ta;es and strip charts to the on-call Pcwer Production Engineer (Nuclear). c. Cal 'he U.C. Berkeley Seisecgraphic station a ~ .nc' cbtain the epicenter 1ccation and magnitude of the earthquake. Upcn re:eiving the Basic System tapes and strip charts: d. 1) Determine if the earthquake exceeds 0.02g. If so, irrrediately notify the Shift Foreman and commence an ergineering evaluation of the fire detection instrumentation in accordance with Technical Specification 3.3.3.8, ACTION b. Tnis evaluation may include the performance of applicable systen functional tests, but must be completed within 72 hcurs folicwing the earthquake. 2) Send a copy of the record play back to the Civil Engineering Department. 3) Retain the cassette tapes for further analysis. I OCC036 SIX
NUMBER EP M-4 1 AND 2 REVISION 9 oiAsio CANYON POWER PLANT UNI' NO(S) DATE 6/1/85 PAGE 7 0F 50 EARTHQUAKE ( mm Upon receiving the Supplemental System tapes and strip e. charts: 1) Determine the maximum containment base slab acceleration of the earthquake. If the Basic System did not trigger, and the OTE: maximum: free-field acceleration from the Supplemental System is less than.01g, notify the Shift Foreman that the event may be downgraded to a Micro Earthquake. Send a copy of the strip charts and the information 2) obtained from the Berkeley Seismographic station to the Civil Engineering Department and request guidance as to the disposition of the SS tapes. Retein the SS tapes until directed by Civil Engineering 3) as to tneir disposition. f. f.ctify Il; tc contact Kinemetrics for an onsite This must be recalibratier of SMA-3 and SMP-1 equipment. pbricrmed withir. f he days following the initial event. Gather local data in accordance with Appendix 1 Post g. Earthquake Checklist. Close cut with verbel sumrary to offsite authorities fellowed by E. Occument verbe.1 e writ +c-sumary tc f:PC withir 24 hours.60-9221, " Emergency Notification R summary on Form I' the Besic System triggered, contact a Regulatory Compliance 6. Engineer to prepare a Special Report in accordance with the requiremer.ts of Technical Specification 4.3.3.3.2, anc document the notification in the Shift Foremans Log. STR0?:G EARTHOUM E (0.1 TO 0.20) Sympicr. s The maxir.um acceleration on the containment base slab is 1. indicatea tc be between 0.1g and 0.29 by the EFM. The " Seismic Instr System" main annunciator is activated (,PK 2. 15-24). The ground motion is strongly noticeable to operations personnel 3. on shift. DC0036 71X
'j ciAsLO CANYOh POWEF PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4*' i REVISION '9 DATE 6/1/85 PAGE 8 0F 50 mm EARTHQUAKE ) Automatic Actions The Unit may trip due to induced vibration or spurious relay actuation. Immediate Operator
- Actions 1.
Notify the S.hift Foreman (Interim Site Emergency Coordirator). 2. Make a general survey of the instrumentation in the Control Room with particular attention to the main annunciator and computer alarms, to verify that no readily apparent plant damage has 3 occurred. Subsecuent Actions 1. Notify the shift CARP to make preparations for entering Containment to conduct a quick fire inspection. 2. Generai Establish the onsite emergency organization for an Unusual a. Even; as specified in EP G-2 " Establishment of the Onsite 3 Emergency Organization." b. Notify offsite organizations as specified in EP G-3 " Notification of Offsite Organizations." i c. Ir.struct at lets: two Power Production Engineers (Nuclear) (EP G-2 Data Processors No. 2 and 3, on call rotation personnel) to come to the plant to assist in the post-earthquake evaluation. 3. Subsequent Operator Action If a Unit has tripped, maintain the Unit in the HOT STANDBY a. condition until the Plant Manager authorizes a return to power. \\ 0C0036 81X
NUMBER EP M-4 1 AND 2 REVISION 9 otAalo pANYgN POWER PLANT UNIT NO(S) DATE 6/1/85 PAGE 9 0F 50 EARTHQUAKE ( 7,7a b. Follow-up Investigation The follow-up investigation involves the performance of j As each check various tests and inspections of the plant. is cocpleted, the appropriate check or data sheets should be Since some forwarded to the Shift Foreman for his review. of the surveillance tests will take a considerable period to complete, the Shift Foreman has been provided with a post-earthquake evaluation summary sheet for this procedure ' (Form 69-9248) to help keep track of the progress of the investigation. 1) Complete the " Post-Earthquake Level Indicator Check List" (Form 69-9249). Return it to the Shift Foreman. Within two hours following the earthquake, inspect all 2) zones listed in Technical Specification Table 3.3-11 for fires. f0TE: If a portion of the Fire Protection System is daraged by the earthquake, as indicated by visual inspection or flow annunciation, it should be isolated from the reniainder of the. system (see Appencix 3). Complete the following " Post-Earthquake Area Inspection 3) Check Lists," checking all indicated areas for structural and equipment damage. When inspecting the various areas, pay particular attention to chipped paint at pipe restraints and hanger clamps indicating pipe movement; spauled grouting at equipment support anchors attached te walls or floors; concrete cracks, especially near equipment support anchors; damaged pipe snubbers as evidenced by leakage from hydraulic reservoirs and/or broken or bent hardware. a) Containment (outside missile shield); b) Containment (inside n.issile shiclo, if unit is shutdown); c) Auxiliary Building (main area); d) Auxiliary Building (penetration areas); DC0036 9IX
t i omal.C CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4. ' REVISION 9 DATE 6/1/85 PAGE 10 0F 50 7,7tg. EARTHQUAKE i ) e) Fuel Handling Building (main area); f) Fuel Handling Building (vent. equipment areas); t g) Turbine Building; h) Outside areas; i) Intake Structure. The areas referred to on the check lists are shown on the plant drawings included as Attachment I to this procedure, deturn the completed checklists to the Shift Foreman. 4) Complete the Post-Earthquake Surveillance Test Checklist (Form 69-9251). Forward all completed data sheets to the Shift Foreman. 5) Complete the Post-Earthquake Electrical Power Checklist (Forn69-92EE). Forward completed data sheet to the Shif t Foreman, t d' The Unit (s) will be placed in HOT STAf!DBY if investiga: ion reveals physical damage which could impair the operation of any Seismic Class I equipment. 7) Centact a Regulatory Compliance Engineer to prepare a Special Peport in acccrdance with the requirements of Technical Specification 4.3.3.3.2, and document the notification in the REMARKS section of the Post-Earthquake Evaluation Summary Sheet (Form 69-9248). 4 Subsequent Power Production Engineer Action Contact the I&C Department to retrieve seismic data from the a. Kinemetrics SMA-3 basic seismic monitoring system (85). (See STP I-37C.) 1) Perform a pcst-event calibration of the BS tapes. 2) Replace the tape cessettes in the SMA-3 and perform a pre-event calibration. 3) Reset the EFP. OC0036 10lx -ow e e n= y a wee 4
NUMSER EP M-0 1 ANO 2 REVISION 9 otA$tO CANYON POWEQ PLANT UNtf NC(S) DATE 6/1/85 PAGE II 0F 50 EARTHQUAKE 7,7 2 Play back the tapes removed from the SMA-3 on the 4) SMP-1, and make strip charts. Forward the tapes and strip charts to the on-call Pcwer 5) PrcductionEngineer(Nuclear), Contact the I&C Department to retrieve additional seismic b. data from the supplemental seismic monitoring system. Perforr. a post-event calibration of the SS tapes. 1) Play back ard make strip chart records of all channels. 2) Install a new set of tapes in the SS recorder and 3) perform a pre-event calibration. Forwarc the 55 ta;es and strip charts to the en-call 4) pcter Production Engireer (Nuclear). Ca!I tFc U.C. Berkeley Seisnegraphic station a*
- c. Mr.c cttain the epicenter location anc magnituce cf the earthcucke.
Uper. receiving the 6asic Syster tapes and play back records c. the FEE cr. call sr.ccid: Serc a cc;j o' thc play ba:k recercs to Civil l ', Engineering. ReWr the cassette tapes fer further at alysis. 2) Uper receiving the Supplemertal Systen, tapes and strip e. charts the PPE on call should: Send a ccpy of the strip charts and the information 1) obtained from the Berkeley Seismcgraphic station tc Civil Engineerir.g and recuest guicance as to the disposition of the SS tapes. Retain the SS tapes until directed by Civil Engineerinn 2) as to their dispcsition. Notify I5C to contact Kinemetrics for an ersiteThis must be f. recalibration of SMA-5 and SMP-1 equipnent. performed within five davs fcilowing tre initial event. 0C0036 11IX
m. DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP M-4 ' REVISION 9 DATE 6/1/85 PAGE 12 0F 50 7,7 g EARTHOUAXE Gather local data in accordance with Appendix 1 Post g. Earthquake Checklist. h. Comence an engineering evaluation of the fire detectic, instrumentation in accordance with Technical Specification 3.3.3.8, ACTION b. This evaluation may include the performance of applicable system functional tests, but.nust be completed within 72 hours follcwing the earthquake. 5. a written summary to NRC within 24 hours.Close out with v sumary on Form 69-9221. Document verbal LAPGE EARTHQUAKE (between 0.24 and 0.6g) _Symo toms 1. The " Seismic Instr System" main annunciator is activated (PK 15-24). 2. The maxirur acceleratier indicated by the Earthouake Force Penitor or the SMP-1 tape playback strip chart is greater than 0.29 but less than 0.6 g's. 3. .Seisnic reacter trip (PK 04-15). _AbtC*:2 tic ACt icr.5 1. The Unit ray trip due to induced vibration. 2. Seisnic Reacter trip at greater than er equal to 0.35g. Imnediate Operator Actions 1. Notify the Shif t Foreman (Interim Site Energency Coordinator). 2. Make a general survey of the instrumentation in the control room, with particular attention to the main annunciator and computer alarms, to verify that ne readily apparent plant damage has occurred. 3. Begin appropriate action to place the unit (s) into HOT STANDBY on a controlled basis. \\ DC0036 121X )
NUMBER 1 AND 2 REVISION 9 OLABLO CANYON POWER PLANT UNIT NO(S) DATE 6/1/85 PAGE 13 0F 50 Et,RTHQUAKE i ' Tn LE Subseauent Actions Notify the shif t CARP to make preparations for entering Containment to conduct a quick inspection for fires. 1. 2. General Sound the Emergency Signal. a. b. Declare an ALERT. Establish the onsite emergency organization as specified in EP G-2 " Establishment of the Onsite Emergency Organization." c. Notify offsite personnel and agencies as specified in EP G-3 d. " Notification of Offsite Organizations." 10CFR100 rec,uires the unit be placed in a shutdown condition Plant shutdown te 3. foT10 wine earthquakes in excess of the OBE. COLD SHUTDOWN should commence at the direction of the Site Emcrgency Coc,rdinator. 4 Subsequent Operatcr Action. .( Perforr., the same procedure as for e STRONG earthquake (0.1 c. to 0.29). Subse:;uset Pcwer Production Engineer Actions 5. Perform the same procedure as for a STRONG earthquake (0.1 a. to 0.29). Close out with verbal sumary to offsite authorities followed by Document verbal 6. a written sumary to NRC within 24 hours. summary on Fom 69-9221. MAJOR EAFTHOUAKE (GREATER THAN 0.6g's) Symptoms The " Seismic Instr System" main annunciator is activated (PK 1. 15-24). The maximum acceleration indicated by the earthquake force 2. monitor is pegged at 50ig. CC0036 13IX
OlA8LO CANYON POWER PLANT UNIT NO(S)2 AND 2 f0N ^ DATE 6/1/85 PAGE 14 0F 50 M LE. EARTHQUAKE l ) 3. The maximum acceleration on the SMP-1 playback strip chart is greater than 0.6 g's. 4 Seismic reactor trip (PK 04-15). 1 Automatic Actions Seismic reactor trip. Immediate Operator Actions 1. Check reactor (s) trippeo and unit (s) in HOT STANDBY. trip reactor (s) manually. If not, 2. Notify the Shift Foreman (Interim Site Emergency Coordinator). 3. Make a general survey of the instrumentation in the control room, 9;ith particular attenticr to the main annunciator and computer alarms, to verify that no readily apparent plant damage has occurred. Subsectent Actiens 1. Nctify shif t CARP to make preparatier.s for ente [ing Containment to conduct a cuick irspection for fires. 2. Ger.e ral a. Scun: site eracrgency sigr.al. b. Declare a SITE ENZRGENCY. Establish the onsite emergency organization as specified in c. EP G-2 " Establishment of the Onsite Emergency Organization." d. Notify offsite personnel and agencies as specified in EP G-3 " Notification of Offsite Organizations." 3. 10CFP.100 requires the unit be placed in'a shutdown condition following earthouaker in excess of the OBE. Plant shutdown to COLD SHUT 00Wh should corrrence at the direction of the Site Emergency Coordinator. 4 DC0036 141X
NUMBER EP M-4 'J 1 AND 2 REVISION 9 DIAfiLO CbNYO,N POWER PLANT UNIT NO(S) DATE 6/1/85 PAGE 15 0F 50 EARTHQUAKE (' DTLE 4. Subsecuent Operator Actions Perfom the same procedure as for a STRONG earthquake (0.1 a. to 0.29). Subsequent Power Production Engineer Actions 5. Perform the same procedure as for a STRONG earthquake (0.1 a. to 0.2g). Close out with verbal summary to offsite tuthorities followed by Document verbal 6. a written summary to NRC within 24 hours. surr..ary on Fom 69-9221. REFERENCES 10 CFR 100, Appendix A, Section VI (a) (3). 1. AEC Reguiatcry Guide 1.12. "Instrun.entation for Earthquakes." 2. Stancare h1L.!, " Earthquake Instrur.cntation Criteria for 3. ANS: Nuclear Pcwer Plant." i{ 4 Ciablo Canjct. FSAR, Section 3.7. 443296, " Seismic Instrumentation." S. PGandE Drawing Nc. 452417. " Diagram of Connections, Seismic 6. PGandE Drawir.g Ao. Ir.strur entatier System." "Seisrr.ic Instrumentation System," PGanoE Record Dwg. File No. ?. 683697. NUREG-0610. " Draft Emergency Action Level Guidelines for kuclear 8. Power Plants," September 1979. A'TACuf'ENTS Fcrrc. 65-92E1, "Emergencj hotificaticn Record", 3/62. 1. Form 69-9248, " Post-Eartnquake Evaluation Sumary", 9/84 2. Form 69-9249, " Post-Earthquake Level Indicator Check Lists", 9/84 3. (10 pages). DC0036 15D \\
DIASLO CANYON POWER PLANT UNIT NO(S) I SNO 2 t ON DATE 6/1/85 PAGE 16 0F 50 rirts. EARTHQUAKE a 4 Fom 69-9250, " Post-Earthquake Area Inspection Check Lists", 4/84 (10 pages). 5. Fom 69-9251, " Post-Earthquake Surveillance Check List", 4/84 6. Fom 69-9252, " Post-Earthquake Electrical Power Check List"* 9/84. 7 Fom 69-10291, " Data Sheets for Peak Shock Recorders S/N 701, 710, 728", 9/84 8. Fom 69-9283, " Data Sheet for Engcahl Peak Acceleration Recorder", 9/84 1 = e= f I i DC0036 16IX l 4
NUMBER EP M-4 olIBLO CANYON POWER PLANT UNIT NO(S)I ANO 2 REVISION 9 OATE 6/1/85 PAGE 17 0F 50 EARTHQUAKE 7gg I APPENDIX 1 SEISMIC lhSTRL'FENTATION DESCRIPTION AND POST EARTHQUAKE CHECKLIST DESCRIPTION 1. Ger.cral There are three types of seismic sensors:
- 1) Engdahl peak shock records; 2) Engcahl peak acceleration recorders, and 3)
Kinemetrics triaxial accelerometers. The different sensors are provided at plant locations as shown on PGandE drawing 443296, 443043, and 443044 MEAS. NO. OF DWG. INSTRUMENTS Af:0 SENSOP LOCATIO!!S RANGE INSTR. DESIG. 1. Tria>:ial Response-Spectrum Reccrders (Engdehl)
- a. Coi.tair.:.ent Ease Slat, El. 69,180:
1.6-90g 1 6 2-25.4 Hz \\./ 2. Triaxie! Feak Acceicg aphs (Engdahl)
- a. Containtcet Base Slab. El. 89, 180*
22g 1 3b
- b. Ter l! nit 1 Containrent, El. 303.5,
- 59 1
3a 22?*
- c. Intake near ASW Pump 1-2 Say, El. 2
=2g 1 3f
- d. Turbine Building, El. 85, Machine
- 2g 1
3e Shop
- e. Auxiliary Building, El. 140, Hot 29 1
3k Shop
- f. Auxiliary Euilding, El. 14C, near
- 29 1
Sn Control Room Door 3. Triaxial Tirre-History Accelographs (Kinenetrics)
- a. Unit 1 Containeert Base Slab, El.
19 1 lb 89, 180' DC0036 17IX
NUMBER EP M-4 1 AND 2 i DIABLO CANYON POWER PLANT UNIT NO(S) REVISION 9' DATE 6/1/85-PAGE 18 0F 50 EARTHQUAKE TITLE i MEAS. NO. OF DWG. INSTRUMENTS AND SENSOR LOCATIONS RANGE INSTR. DESIG. i
- b. Top Unit 1 Containment El. 303.5, 2g 1
la + 225'
- c. Auxiliary Building, El. 64
- 1g 1
1p 2. Triaxial Response - Spectrum Recorde s (Engdahl) Each of these units contains twelve spring steel reeds of different lengths and weights. A diamond-tipped stylus is attached to the free end of each reed. A flat plate is mounted adjacent to each stylus such that in the event of an earthquake, the vibrating stylus inscribes a permanent record of its deflection on the plate. Since each reed has a different resonant frequency, this arrangement provides the earthquake acceleration (as measured by reed displacement) at twelve different frequencies. There are actLally three individual shock recorder units on the conteinment base slab with ene unit oriented along the three 3 perpendicular (x, y, z) axes. 3. Triaxial Peak Acceleregraphs or Peak Acceleration Recorder (Engdahl PAR's) The accelerograph records by scribing a line on the surface of a record plate. Three reccrd plates are included in each unit, oriented along the three perpendicular axes. The lines are inscribed by a contact diamond stylus, one for each axis. The peak acceleration is treasured as the maximum deflection from the zero baseline. 4 Triaxial Time - History Acceleregraphs (Kinemetrics) Each triaxial accelerometer unit centains three accelerometers oriented along the three perpendicular axes. Each accelerometer is a damped spring-mass device which is fed to a trechanica'-electrical transducer. The signals from the accelerometers are fed to one or both of two units (see Figure 1). The first is a SMA-3 magnetic tape cassette recording system. This system has a starter unit which automatically starts the cassettes at a present level (0.01 when the acceleration drops below this level (g) and shuts it off the unit is then ready fcr a succeeding earthquake). The tapes can be played back on a SMP-1 playback which is rack mounted with the SMA-3 unit. This provides a strip chart record of the acceleration. g DC0036 181X A
NUMBER EP M-4 1 AND 2 REVISION 9 DIABLO CANYON POWER PLANT UNIT NO(S) DATE 6/1/85 1 19 0F 50 PAGE 4 EARTHQUAKE 7ga. The base slab accelerometer output also goes to an earthquake force monitor unit (EFM-1), which simply contains three The indicators (one each axis) which read out in percent of g. indicator pointer is held at its maximum reading until reset, so peak acceleration can be determined. t DC0036 19?X
DIABLO CANYON POWE? PLANT UNIT NO(S) IM2 NUMBER EP M-4'* REVISION '9 DATE 6/1/85 PAGE 20 0F 50 7,7 a EARTHQUAKE APPENDIX 1 (Continued) _ POST-EARTHQUAKE CHECK _fqTE: Spare cassettes and plates are stored in the chart room adjacent to the control room. 1. Replace the cassettes in the SMA-3 recording system following the retrieval instructions on page 9 of Record No. 683697-15. Insure Play back the cassettes and reccrd the peak accele the SMA-3 is a higher class instrument than EFM-1, base Since by the SMA-3 f f this readit.g is greater than the EFM strip charts with the other records of the quake. Keep the Send the cassettes to the Supervising huclear Generation Engineer in the Department of Nuclear Plant Operations with instructions to pass on to the Civil Engineering Department. If the ir.dicateo acceleration on the EFM is 0.5 g's, determine the actual peak acceleration from unit containment base slab as follows: \\ Play back the tapes on position #1 of the play back recorder 6 gain selector switch, t. Find the highest peak (either positise or negative) for the highest acceleration. c. Convert te c's. The scaling on this range is :1.0g full scale when the playback recorder gain selector switch is on pcsition el. full scale; for switch position #4, 20.25The scaling for switch po 9's full scale; for switch position r10, 0.1 g's full scale, To convert to g's for recordings made from the accelograph c. atop Unit I containment, scaling wculd be as follows: playback recorder gain selector switch position #1 - 22.0 g full scale; selector switch position 62 - :1.0g full scale; switch position *4 - - :0.2 g full scale. 0.5 g full scale; switch positten AIO 2. If the maximum acceleration indicated by the earthquake force monitor is greater than 0.1g, replace the recording plates in the Engdahl peak shock recorders (PSR's) and peak acceleration recorders (FAP's). I 0C0036 20!X
REVISION 9 DIABLO CANYON POWE'l PLANT UNIT NO(S) DATE 6/1/85 PAGE 21 0F 50 EARTHQUAKE 7m APPENDIX 1 (Continued) Measure to the nearest hundredth of an inch the length of the scribe marks (naximum distance of the scratched record from the 3. zero line) on each plate from the peak shock recorder using the Record the length of the scribe on magnifying scale provided.the appropriate attached data sheet noting the Convert the scribe length in inches number and the reed number. to the equivalent static acceleration by multiplying by the Record this value on the data sheet. acceleration sensitivity. Forward one copy of the data sheet, as well as the ' plates, to the Department of Nuclear Plant Operations for transmittal to the Civil Engineering Department. Retain each original copy for the plant records. When removing or inst 6111ng PAR record plates, use the following 4. procedure, Recove the recoro access plugs from the PAR housing. a. Re.: 6 cr irstall the PAR record plates. L. It is inportant not to move the scribe arms of the ( CAUTION: PAR in the measurement axis direction whileThis removing or installing PAR record plates. will avoid false indications on the record plates. Fc' the se-ici numbers of all PAR record plates and Re: corresperding PAR location following removal on the data c. sheet. Record the time and date of removal on the PAR record plates d. and data sheet. Measure, to the nearest thousandth of an inch, the length of the scribe rark (maximur distance of the scratched record from the 6. zero line) on each record plate from the PAR"s using the Record the length of the scribe on magnifying scale provided.the appropriate ettached data sheet notino t Convert the scribe length, in record plate serial numbers. inches, to the equivalent static acceleration by multiplying by Record this value on the acceleration sensitivity of the PAR. Forward one copy of the data she the data sheet. the PAR record plates, to the Department of Nuclear Plar.t Operctions, Supervising f uclear Generation Engineer, for Retain the transmittal to the Civil Engineering Department. original copy for the plart records. DC0036 211X
l 01AsLO CANYON POWER PLANT UNI? NO(S) 1 AND 2 E M-4.' DATE 6/1/85 ints EARTHQUAKE PAGE 22 0F 50 The nominal acceleration sensitivities for Engdahl PAR's model number PAR 400-1 (29) g/ inch, respectively.*and PAR 400-2 (5g) are 10 g/ inch and 25
- Based on a nominal full scale deflection of 0.200 inches.
9 i s h DC0036 221X
NUMBER EP M-4 DiMLQ CANYON POWE3 PLANT UNIT NO(S) 1 AND 2 REVISION 9 DATE 6/1/85 / PAGE 23 0F 50 TITLE EARTHQUAKE ( APPENDIX 1 (Continued) \\ anstarczaron rzazzza / TE-u24 urn Acerr-em nnurns Acm nnwr:It ( M ail 0GET DCMI) (BAKE SLA3) (AnrTTIArY EUILDIEC) ( m \\/ \\/ \\/ \\/ SMA-3 ECORDINC ETSTEM (CONTICL BOOM) ~ FIGURE 1 B'.0:r: DI AGRA. Cr KINEF.ETRICS ACCELEROMETER Uh!TS DC0036 22 Vill
==..= =._.- DIA8LO CANYON POWEF PLANT UNIT NO(S) 1 AhD 2 NUMBER EP M-4. ' I REVISION 9 DATE 6/1/85 PAGE 24 0F 50 i EARTHOUAKE y,7tg l 1 APPENDIX 2 SUFFLEMENTAL SEISMIC SYSTEM (Terra Technology 0C5-302) locations of Detectors Table A2-1 Recorder Max. Elev. CHANNEL ORIENTATION No, g Unit Location (Ft.) 1 2 3 1-1 1 1 Containment NW. 89 Vert. 120 30 1-2 1 1 Containment NE. 89 Vert. 240 150 1-3 2 1 Containment NNW. 140 Vert. 180 90 1-4 2 1 Centainment SSE. 140 Vert. 0 270 2-1 1 1 Containment Base S. 89 Vert. 0 270 0-E 3 1 Containment NE. 231 Vert. 60 330 (spring 11ne) 2-3 3 1 Certainment S.. 231 Vert. 180 90 (springline) 2-4 1 1 Centainment Cntr. 91 Vert. i 1 Ccrtainment S. 140 90 16G 3-1 2 1 Centainment W. 140 180 90 3-2 3 1 Centainrent hW. 231 Vert. 300 210 (springline) 3-3 1 1 Auxiliary 81dg. 9.7-U 100 Vert. 0 270 3-4 1 1 Auxiliary Bldg.18-H 100 Vert. 270 180 4-1 1 1 Auxiliary Bldg.18-U 100 Vert. 90 0 4-2 1 2 Turbine B1dg. 35-D* 85 vert. 180 90 4-0 1 2 Containment N. 89 Vert. 90 1 Turbine Bldg. 1-0 140 0 4-4 1 2 Containment SE. 89 Vert. 210 1 1 Turbinc Bldg. 1-0 140 270 DC0036 24!X
e I ANO 2 ON Olh8LO CANYON POWER PLANT UNIT NO(S) DATE 6/1/85 .PAGE 25 0F 50 EARTHQUAKE t TITLE l APPENDIX 2 (continued) f a SUPPLEMENTAL SEISMIC SYSTEM (Terra Technology DCS-302) locations of Detectors f Table A2-1 h u i Recorder Max Elev. CHANNEL ORIENTATION ho. g Unit Location (Ft.) 1 2 3 f' ( E-1 1 2 Containment SW. 89 Vert. 330 E-2 1 1 Turrir.c Bldg.1-0 65 Vert. 0 270 f.(' 5-3 1 FF Pew Water Reservoir Grnd. Vert. 0 270 54 1 FF Meteorclegical Tower Grnd. Vert. 90 0 C-1 1 FF G.C. l!arehouse Grnd. Vert. 180 90 ' NOTE: Channel Orientation is azimutns from plant north (which is 23' counter-cicckwise frce the north). i DCCC36 251X
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DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON 9' DATE 6/1/85 PAGE 26 0F 50 7,7tg EARTHQUAKE l j / 4 APPENDIX 3 POST EARTHQUAKE FIRE SYSTEM ISOLATION VALVES j (Reference P&ID's 102018 and 108018 & OVID 106718) Operating Valve P&ID OVID OVID ID l No. SHT No SHT No Coord System / Area
- I FP-0-20 3
3 32-B Pkg. Bir. 0-1 & 0-2 Rm. Fire Sys. } Isolation (Isol.) FP-0-19A 3 3 32-8 Pkg. Bir. 0-1 Samp. Cooler Isol. FP-0-304 3 3 36-8 Fire Pp. 0-1 Mini Recirc 1st Off FP-0-305 3 1 35-B Fire Pp. 0-1 Mini Recirc 2nd Off FP-0-302 3 3 36-C Fire Pp. 0-2 Mini Recirc 1st Off l FF-0-303 3 3 35-C Fire Pp. 0-2 flini Recirc 2nd Off FP-1-4:: 4 4 40-B Unit 1 Turbine Building (T/B) N. 3 Sprinkler Heater Isol. FP-1-50 4 4 44-8 Unit 1 T/B So. Spr. Header Isol. FP-2-E? 4 4 46-8 Unit 2 T/B N. Spr. Header Isol. FP-2-66 4 4 49-8 Unit 2 T/B So. Spr. Header Isol. FF-1-44 4 4 40-8 Unit 1 T/B Loop Dividing Valve FP-1-49 4 4 44-8 Unit 1 T/B Loop Dividing Valve FP-1-332 5 6 61-E Aux. Bldg. Units 1 and 2 - 100' Elev/ Unit 1 FH Bldg - 100' Elev/ Aux. FW Pp. 1-1 Spr. Sys. Isol. FP-1-335 5 6 61-D Unit 1 Area GE/GW Elev.115' Spr. Sys. Isol. FP-1-338 5 6 62-D Unit 1 Area GE/GW Elev. 100' Spr. Sys. Isol. s DC0036 26IX
~~ EP M-6 ~' NUMBER 1 AND 2 REVISION 9 e DIABLQ CANYON POWER PLANT UNIT NO(S) DATE 6/1/85 PAGE 27 0F 50 EARTHQUAKE '( y,7a POST EARTHQUAKE FIRE SYSTEM ISOLATION VALVES (Re'erence P&ID's 102018 and 108018 & OVID 106718) (Page 2) Operating Valve P&ID OVID OVID ID Nc. SHT No SHT No Coord System / Area FP-1-341 5 6 63-C Unit 1 Aux. Bldg. Fan Rm & Cont. Rm. HVAC Equip. Rm. Spr. l Sys. Isol. Unit 1 Aux. Bldg. Serv. Wtr. Isol. FP-1-30 5 6 61-C (from Hose Reel Header) Unit 1 Aux. Bldg. Serv. Wtr.1501. FP-1-32 5 6 60-C (from Aux. Bldg. Fire Loop) Chemical Lab. Rm. Spr. Sys. Isol. i FF-1-37 5 6 62-5 FP-1-34C E 6 61-B Unit 1 Charging, CCW Pps. Spr. Sys. Isol. FP-2-352 5 6 67-E Unit 2 FH Bldg. 100' Elev. Spr. Sys. Isol. FF-2-8CC f:/P 6 67-E Aux. FW Pp. 2-1 Spr. Sys. Isol. Unit 2 Area GE/GW Elev. 100' Spr. Sys. FP-2-861 N/S* 6 65-C Isol. FP-2-30 5 6 66-D Unit 2 Area GE/GW Elev.115' Spr. Sys. Isol. FP-2-359 5 6 68-0 Security Diesel Spr. Sys. Isol. Unit 2 Serv. Wtr. Isol. from Fire Line FP-2-857 5 6 66-C Elev. 140' (1st Off) l FP-2-32 5 6 66-C Unit 2 Aux. Bldg. Serv. Wtr. Isol. (from Unit 2 Aux. Bldg. Fire Loop) j Unit 2 Charging, CCW Pps. Spr. Sys. FP-2-349 5 6 67-B 1s01.
- Not Shown.
DC0036 271X
I DIASLO CANYON POWER PLANT UNIT NO(S)I ANO 2 NUMBER EP M-4 i REVISION.9 } DATE 6/2/S5 PAGE 28 0F 50 TITLE. EARTHQUAKE i i i POST EARTHQUAKE FIRE SYSTEM ISOLATION VALVES (Reference P&ID's 102018 and 108018 & OVID 106718) (Page 3) Operating Valve P&ID OVID OVID 10 } No. _SHT No SHT No .Coord Systern/ Area FP-1-177 7 8 88-A Unit 1 Containment (Cont.) Fire Water Sys. Manual Isol, a FF-1-193 7 8 85-D Unit 1 RCP 1-1 Spr. Sys. Isol. i FP-1-203 7 8 83-D Unit 1 RCP 1-2 Spr. Sys. Isol. FP-1-189 7 8 82-C Unit 1 RCP 1-3 Spr. Sys. Isol. FP-1-184 7 8 84-B Unit 1 RCP 1-4 Spr. Sys. Isol. FP-1-181-A 7 8 85-B Vent Line #1 1501. off Unit 1 Cont. Fire Water Header FP-1-197 7 8 84-0 Vent Line #3 Isol. cff Unit 1 Cont. Fire Water Header FP-1-188-A 7 8 83-B Vent Line #2 Isol. off Unit 1 Cont. Fire Water Header FP-2-864 7 8A 81A-B i Unit 2 Cont. Fire Water Sys. Manual I ~ Isoi. FP-2-891 7 8A 84A-D Unit 2 RCP 2-1 Spr. Sys. Isol. FP-2-883 7 8A 86A-D Unit 2 RCP 2-2 Spr. Sys. Isol. FP-2-880 7 8A 87A-C Unit 2 RCP 2-3 Spr. Sys. Isol. FP-2-874 7 8A 85A-B Unit 2 RCP 2 a Spr. Sys. Isc1. FP-2-870 7 BA 84A-B Vent Line #1 Isol. off Unit 2 Cont. Fire Water Header FP-2-877 7 8A 86A-B Vent Line #2 Isol off Unit 2 Cont. Fire Water Header FP-2-887 7 8A 85A-D Vent Line #3 Isol. off Unit 2 Cont. I Fire Water Header DC0036 28IX ves - .-..,_m.--. ........ _.-_m ~_-,.-..__m..,,.....
NUMBER EP M-4 1 AND 2 REVISION 9 otAhtQ CANYON POWER PLANT UNIT NO(S) DATE 6/1/85 PAGE 29 0F 50 EARTHQUAKE 7,7 g POST EARTHOUAKE FIRE SYSTEM ISOLATION VALVES (Reference P&ID's 102018 and 108018 & OVID 106718) (Page 4) Operating Valve P&ID OVID DVID 10 No. SHT No SHT No Coord_ System / Area FP-1-24 5 6 60-E Temp Unit 2 Isol. FF-2-27 5 6 66-E Temp Unit 2 Isol. FP-2-26 5 6 63-C Temp Unit 2 Isol. FP-2-345 7 6 67-E Temp Unit 2 Isol. Tc be removec f rcrr list when Unit 2 goes on-line. I DC0036 291X ~
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v Page 1 of 1 R 61-9248 9/84 (10) DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABI,0 CANYON POWER PLANT UNITS 1 AND 2 DATA SHEET: POST-EARTHOUAKE EVALUATION SUPEARY EP M-4 i 1. DATE/ TIME OF QUAXE / 2. POWER LEVELS: UNIT 1
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PEAK ACCELERATION (FROM EFM-1 or SMA-3) NORTH SOUTH G: EAST WEST G: VERTICAL G TIME / INITIALS 4 CHECK LISTS / Seisnic Instrument Precedure 6. / b. Level Ir.dicatoa Check List / Surveillar.ce Test Check List c. / d. Electrical Power Check List / t. Area Ins;tctier Cne:,, List RIMA:r$: ( Magnitude 5. Ept eer,te r: JctrieFA. a'ty the ear *.hquake fro. U.C. Berkeley Seismographic Statice. - i Reviewed by: Pcwer Productice Engineer Date/ fire / DC0036 50!!
O 2 69 9249 9/84 (10) Page 1 of 3 DEPARTMENT OF NUCLEAR PLANT OPERATION 5 DIABLO CANYON POWER PLANT UNITS 1 AND 2 DATA $NEET: POST-EARTHOUAKE LEVEL INDICATOR CHECK LIST. EP M-4 j UNIT DATE INSTRUCTIONS: Check the indicators twice, at about 15 minutes to one hour apart. Inform the Shift Foreman of any reading outside of its normal range, or which I changes by more than expected in the interval. UNIT 1 LEVEL / TIME Vertical Board 1 Reading 1 Reading 2 I L1-139 CCW Surge Tank 1-1A / / LI-140 CCW Surge Tank 1-1E / / LI-931 Spray Additive Tank / / L!-94C Containtert Recirc Sump / / LI-941 Containn.ent Recire Sueo / / Vertical Board 2 LI-920 Refueling Water Storage Tank (5.T.) / / L1-921 Fefueling Water S.T. / / t( : LI-922 Refueling Water 5.T. / / L1-112 Volur+ Control Tank / / L*-149 Primary Watee Storage Tant / / 'ic-tdet? Per e ? L1-14E Ccr.dersete St:ragt Ta".L 1-1 / / LI-147 Transfer Tank 0 1 / / L1-144RawWaterRes.01A(West) / / L1-145RawWaterRes.018(East) / / LI-146 Fire Water 5.T. / / SEEE!! Aus, f1de. Control Panel LI-140 Monitor Tank 1-1 / / LI-181 Monitor Tank 1 2 / / i L1-148 RCOT 1-1 / / LI-60 Containment Structure Sump 1-1 / / LI 61 Containment Structre $ ump 1 2 / / LI-62 Reactor Cavity Sump Unit 1 / / g L!-229 Weste Conc. Holding Tank 01 / / DC0036 51!!
69-9249 9/84 (10) Page 2 of 3,, l DATA SHEET: POST-EANTHOUAKE LEVEL INDfCATOR CHECK LTST, EP. M-4 [ UNIT 1 LEVEL / TIME ) Aux. Bldg. Control Panel (Cont'd) Reading 1 Reading 2 LI-170 Liquid Holdup Tank 1-1 / / LI-168 Liquid Holdup Tank 1-2 / / LI-167 Liquid Holdup Tank 0-1 / / LI-168 Liquid Holdup Tank 2-1 / / LI-170 Liquid Holdup Tank 2-2 / / LI-165 Concentrate Holding Tank / / LI-158 Equip.DrainReceiver(Rec.)0-1 / / LI-160 Equip. Drain Rec. 0-2 / / l LI-162 Flocr Drair. Rec. 0-1 / / i LI-164 Floor Drain Rec. 0-2 / / LI-1E0 Monitor Tank 2-1 / / LI-181 Monitor Tank 2-2 / / LI-1EF RCDT 2-1 / / LI-60 Cor.tainmer.: Structure Sump 2-1 / / LI-61 Contair..er.: Structure Sump 2-2 / / LI-62 Reactor Cavity Sump, Unit 2 / / Ut:IT 2 Vertical Board 1 LI-139 CCW Surge Tank 2-1A / / L:-140 CCW Surge Tank 2-1E / / LI-931 Spray Additive Tank / / LI-940 Containmer.: Recirc Sump / / LI-941 Containment Recirc Sump / / Vertical Board 2 LI-920 Refueling Water Storage Tank / / LI-921 Refueling Water Storage Tank / / LI-922 Refueling Water Storage Tank / / LI-112 Volume Control Tank / / LI-149 Primary Water Storage Tank / / b. DC0036 52!1
,6'9-9249' 9/84 (10) Page 3 of 3 l DATdSHEET: POST-EARTHOUAKE LEVEL INDICATOR CHECK LIST, EP N-4 i UNIT 2 LEVEL / TIME Vertical Board 3 . Reading 1 Reading 2 LI-148 Condensate Storage Tank 2-1 / / LI-144 Raw Water Res. 01A (West) / / LI-145 Raw Water Res. 015 (East) / / Data Taken By: I REMARKS: Reviewed Ey: Snif-Fore::.y : Date/ Time / f f l k i DC0036 5311 I [
69-9250 4/84 (10) Page 1 of 10 DEPARTMENT OF NUCLEAR PLANT OPERAT10NS DIABLO CANYON POWER PLANT UNITS 1 AND 2 ( DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST CONTAINMENT (OUTSIDE MISSILE SHIELD), EP M-4 UNIT 1 CHECKED BY TIME /DATE AREA - 6' (ELEV. 140' & ABOVE) INCLUDING DOME & LINER, SPkAY HCRS. & PIPING, ETC. / AREA - 17 (ELEV. 117') / AREA - 30 (ELEV. 91') / L'N:T 2 CHECKED BY TIME /DATE AREA - 9 (ELEV. 140' & ASOVE) INCLUDIkG DOME & LIhEk, SFRA) HDR5. 6 FIPING, ETC. / AREA - 25 (ELEr. 117') / A7.Er. - 4.- (E.E'. 51') / REIG H.5 : Reviewed Ey: ~~ Sr.if t Forema-Time /Date /
- Area designations refer to Attachment I to Emergency Procedure M-4.
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-. s.-. l. 69-9250 4/64 (10) Page 2 of 10 4 j DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST CONTAINMENT (INSIDE MISSILE SHIELD). EP h-4 i t I NOTE: TO BE COMPLETED ONLY IF Uh1T IS SHUT DOWN. 1 UNIT 1 CHECKED BY TIME /DATE AREA - 16* (ELEV. 117') / 4 i AREA - 29 (ELEV. 91') / AREA - 44 (5ELOW ELEV. 91') / UNIT 2 CHECKED BY TIME /DATE AREA - 24 (ELEY. 117') / AREA - 29 (ELEV. 91') / AREA - 51 (ELEV. 91') / REMARi.d: Re. i e r.t: !!) : Sniit foremar. Time /Date / a
- Area designations refer to Attachment I to Emergency Procedure M-4 1!
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59,-9250' 4/84 (10) Page 3 of 10 DATA
- SHEET: POST-EARTHOUAKE AREA. INSPECTION CHECK LIST AUXILIARY BUILDING (MAIN AREA), EP M-4 i
TIME /DATE UNITS 1 & 2 CHECKED BY / AREA - IU* (ELEV. 140') AREA - 10A (R00F AREA & EQUIP. ABOVE ELEV 140') / / AREA - 13 (ELEY. 115' & 126') / AREA - 15 (ELEV. 115') / AREA - 20 (ELEY. 127') / AREA - 21 (ELEY. 115') / AREA - 22 (ELEV. 115') / AREA - 32 (ELEv. 10G') / AREA - 33 (ELEY. 100') / AREA - 34 (ELEV. 100') / AREA - 35 (ELEV. 100') / AREA - 45 (ELEV. E5') / AREA - 46 (ELEV. EE', / ARE* 47 (ELEY. E5') / AREA - 4E (ELEV. BE') / AREA - $2 (ELEV. 73') / AREA - 53 (ELEV. L ') / ~ AREA - 5 (ELEl. 60' & 64') / APE 5 - SE (E'.EV. 60' & EI') / AREA - SE (ELEl. 60' & 64') / AREA - 57 (ELEv. 64') REMARKS: Reviewed By: Shift Foreman Time /Date / l
- Area desigr.ations refer to Attachmer.t I to Emergency Procedure M-4.
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-==. _.:. Page 4 of l'0 l 69-9250 4/84 (10) - t DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST AUXILIARY BUILDING (PENETRATION AREAS), EP M-4 UNIT 1 CHECKED BY, TIME /DATE AREA - 7 (ELEY. 140') / .j AREA - 16 (ELEV. 115') / AREA - 28 (ELEV. 100') / AREA - 43 (ELEV. 85') / UNIT 2 CHECKED BY TIME /DATE AREA - 8 (ELEY. 140') / AREA - 25 (ELEV. 115') / AREA - 36 (ELEV. 100') / AREt. - 49 (ELE'i. 65') / REERhS: + 4 DC0056 57:1 .,--a.- -,-__c -_y y.-. w ' - - +, - -
A9.-9255 4/64 (10) Page 5 of 10 .' DATkSHEET: POST-EARTHQUAKE AREA INSPECTI0h CHECK LIST FUEL, HANDLING BUILDING (MAIN AREA), EP M-4 ( UNIT 1 CHECKED BY TIME /DATE AREA -2 (ELEV. 140') / AREA - 3 (ELEV. 140') HOT SHOP AREA / AREA - 12 (ELEV. 115' & 126') / AREA - 27 (ELEV. 100') / UNIT 2 CHECKED BY TIME /DATE AREA - 4 (ELEY. 140') / ' ~ AREA - 14 (ELEV. 11E' 6 126') / AF.EA - 36 (ELEY. 100') / REMARi;5 : l(. DC0036-58II \\
Page 6'of 10,' i 69-9350 4/84 (10) DATA SHEET: POST-EARTHOUAKE AREA INSPECTION CHECK LIST FUEL HANDLING BU (VENT EQUIPMENT AREAS), EP M-4 1 4 UNIT 1 CHECKED BY TIME /DATE / i AREA - 1 (ELEV. 140') ,i / j AREA - 11 (ELEV. 115') 1 / ' AREA - 26 (ELEV. 100') / AREA-42(ELEV.85') UNIT 2 CHECKED BY TIME /DATE / AEEA - 5 (ELEV. 140') / APEA - 15 (ELEV. 115') / AREA - 37 (ELEV. 100') / AREA - 5L (E.E.. LE') T - EEKnRt.5 : l l- \\ DC0036 5911
69-9250 4/84 (10) Page 7 of 10 DATA SHEET: POST-EARTHOUAKE AREA INSPECTION CHECK LIST UNIT 1 TURBINE BUILDING, EP M-4 ~ ~ l UhlT 1 CHECKED BY TIME /DATE AREA - 58 (ELEV. 140') / AREA - 60 (ELEV. 107' & 119') / AREA - 61 (ELEV. 119' & 125') / AREA - 62 (ELEV. 119' & 123') / AREA - 65 (ELEV. 107') / AREA - 66 (ELEV. 104' & 108') / AREA - 67 (MACH. SHOP OVERHEAD) / AREA - 31 (ELEV. 109') Mh; STM. LINE PLTFM. / AREA - 70 (ELEV. SE' & BELOW) / AREA - 71 (ELEY. 8E') / AREA - 72 (ELEV. 85' & EELOW) / AREA - 73 (ELEV. SE' & BEL 0h) / AREA - 74 (ELEV. EL') / l REMARKS: _t DC0036 60!! ~ e = = - - ..%.p w e....,~,. -r-y .g
{ 69-9250 4/84 (10) Page 8 of 10 DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST UNIT 2 TURBINE BUILDING, EP h-4 .i UNIT 2 CHECKED BY TIME /DATE [ { AREA - 59 (ELEV. 140') / AREA - 63 (ELEV. 119' & 125') / ll AREA - 64 (ELEY. 107' & 119') / 1 AREA - 68 (ELEV. 104' & 108') / AREA - 41 (ELEV. 109') Mte. STM. LINE PLATFM. / AREA - 69 (ELEY. 107') / AREA - 75 (ELEY. 85' & BELOW) / 1 AREA - 76 (ELEV. 85' & BELOW)' / AREA - 77 (ELEV. 85' & EELOW) / AREA - 76 (ELE'. 85') / q REMARid: O i-I L n L DC0036 6111
69.-9250 4/64 (10) Page 9 of 10 ~ DATA SHEET: POST-EARTHQUAKE ARE4 INSPECTION CdECK LIST OUTSIDE AREAS, EP M-4 ( CHECKED BY TIME /DATE AREA - 79 (UNIT 1 F.H. BLDG. EXTERIOR, STOR. TKS, STOR. AREAS, ETC.) / AREA - 80 (UNIT 2 F.H. BLDG. EXTERIOR, STOR. TKS, STOR. AREAS, ETC.) / AREA - El (UNIT 1 BLDG. EXTERIORS, MN, AUX. & STUP. XFMR. BKS. & STRUCTURES, ETC.) / AREA - 82 (UNIT 2 BLDG. EXTERIORS, MN, & AUX. XFMR. BKS. & STRUCTURES, ETC.) / AREA - 63 (UNITS 1 & 2 DISCP. STRUCTURE) / AREA - 84 (230 KV SWYD. & LINES) / AREA - 85 (RAi KTR. STOR. PONDS) / AFEA - 6t. (50E K'.' SWYL. & LINES) / REMARKS: (. i DC0036 62II O
i 69-9250 4/84 (10) Page 10 o,f.10 DATA SHEET: POST-EARTHQUAKE AREA INSPECTION CHECK LIST INTAKE STRUCTURE, i EP M-4 CHECKED BY TIME /DATE AREA - 87 (ELEV. 17.5') / AREA - 88 (ELEV. -2') / AREA - 89 (AUX. SALT WATER PUMP COMPARTMENTS / & VENT. SHAFTS) / AREA - 90 (PIPE & DISCHARGE VALVE GALLERIES) / / ^ REMARKS: 9 m e t DC0036 6311
I -9251 4/84 (10) Page 1 of 1 S DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNITS 1 AND 2 DATA SHEET: POST-EARTHQUAKE SURVEILLANCE TEST CHECK LIST, EP M-4 i, UNIT DATE INSTRUCTIONS: Check the data sheet when the time test is completed and the initials of the person performing the test. TIME / INITIALS A. Instrument Surveillance Tests 1. I-1 Channel Check (shift and daily / portionsonly) a. Shift Data Sheet / b. Daily Data Sheet / 2. I-29 Emergency Signals and Communications / Syster Functional Test B. Reactor and Au>iliaries 1. R-1A, Excrcising Full Length Control Rods / 2. E-IO, Reac!ce Coolant Syster Leskage / Evaluatior.. C. Miscellaneous and Integrated Tests k. 1. M-16E Operatier cf Slave Relays K6U4A / and K604E (Safety Injection). 2. M-16C Operation of Slave Relay K606A / (Safety Ir.jection). 5. M-I6D Operation of Slave Relay K6086 / (Safety Injection). 4. M-16E Operation of Slave Relay K633A / and K609A (Safety Injection ana Auxiliary FW Pump Start). 5. h-16F Operation of Slave Relay K6338 / ano K609B (Safety Injection and Auxiliary FW'PumpStart). 6. M-16I Operatior, of Slave Relays K606A / and K606B (Phase A Containment Isolation). REMARKS: i Reviewed By: Shift Foreman Time /Date / DC0036 64II g, g-,- -m, y y w--, --.-w, w w-- --ze-
69-9252' 9/84 (10) Paje 1 of 1 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT.OF hUCLEAR PLANT OPERATI0h5 DIABLO CAhYON POWER PLANT UNIT NOS. 1 AND 2 ,( DATA SHEET: POST-EARTHQUAKE ELECTRICAL POWER CHECK LIST, EP M-4 DATE: INSTRUCTIONS: Insure that the lines indicated are functioning properly. Insure 4 that the batteries are undamaged and that the chargers continue to supply the load. Start all diesels and bring them to rated voltage. i -A. 500 KV System TIME / INITIALS j 1. Midway #2 line / 2. Midway #3 line / 3. Gates line / 4. Tie line tc Unit 1 / 5. Tie line te Unit 2 / 4 6. 500 KV Switchyard / E. 230 KV Syster 1. Morrc Bay-Diatic line / ~ 2. Morre Bay-Mesa line / l 3. Tie lire to startup bank 1-1 / i {~ 4 Tie line to startup bank 2-1 / 5. 23C KV Switchyard / C. Statier Eatteries 2 Chargers 1. Bat ery 1-1 / 2. St-tery 1-2 / 3. Battery 1-3 / ~ 4. Battery 2-1 / 5. Battery 2-2 / 6. Battery 2-3 / D. Diesel Generators 1. Generater 1-1 / 2. Generator 1-2 / 3. Generator 1-3 / 4. Generator 2-1 / 5. Generator 2-2 / REMARKS: Reviewed By: Shift Foreman Time /Date / DC0036 65II -ee, ,-.n- -,.,e
69-10291 9/S4 (10) Page 1 of 3 PAC 8FIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DfABLO CANYON POWER PLANT UNfT NOS. 1 AND 2 TITLE: CALIBRATION AND TEST DATA SHEET. EP M-4 TM - PEAK SHOCK RECORDER PSR1200 - H (NORTH / SOUTH) RECORDER S/N 701 CALIBRATION DATE 5/3/84 _ INITIALS RECORD PLATES S/N SURFACE EQUIVALENT ACCELERATION STATIC REED FREQUENCY SENSITIVITY DISPLACEMENT ACCELERATION nub'BER (Hertz) (g/ inch) (inches) (g) 1 1.96 0.351 2 2.56 0.550 3 3.23 0.810 4 3.97 1.19 5 5.18 2.23 6 6.3d 3.24 7 8.10 5.08 e 10.2 7.63 9 12.7 11.6 10 16.1 19.2 11 20.2 27.8 12 25.6 45.5 Darpinc: 2' viscous carrirg (C of 25) TESTER TEST DATE I TEST LOCATION PREPAFED BY TEST NUMBER DATE _
- Values based on Kinemetrics Calibration Test Report and Certification for DCPP Seismi Ins trumenta tier..
i DC003E 6811
69-10291 9/84 (10) Page 2'of 3,. TITLE: CALIBRATION AND TEST DATA SHEET, EP M-4 TM PEAK SHOCK RECORDER / PSR1200 - H (East / West) RECORDER S/N 710 CALIBRATION DATE 5/3/84 INITIALS RECORD PLATES S/N SURFACE EQUIVALENT ACCELERATION STATIC REED FREQUENCY SENSITIVITY DISPLACEMENT ACCELERATION NUMBER (Hertz) (g/ inch) (inches) (g) 1 1.92 0.343 2 2.50 0.537 3 3.13 0.823 4 3.97 1.17 5 5.20 2.20 6 6.40 3.22 7 7.9e 4.94 8 10.1 11.7 9 12.7 12.2 10 16.1 19.4 11 20.3 30.8 12 25.4 45.5 Dam. ping: l's viscous darping (Q of 25) TEST DATE ~~ TESTER PREFARED BY TEST LOCATION DATE TEST NUMBER 4 DC0036 69II
~ ~~ 69-10291 5/64 (10) Page 3 of 3 TfTLE: CALIBRATf0N AND TEST DATA SHEET, EP M-4 i TM PEAK SHOCK RECORDER 2 i PSR1200 - V (VERT.) RECORDER S/h 728 CALIBRATION DATE 5/3/84 INITIALS RECORD PLATES S/N SURFACE EQUIVALEhT ACCELERATION STATIC REED FREQUENCY SENSITIVITY DISPLACEMENT ACCELERATION NUMBER (Hertz) (g/ inch) (inches) (g) 1 1.92 0.315 2 2.49 0.493 3 3.23 0.816 4 3.53 1.10 5 5.15 2.06 6 6.43 3.13 7 8.06 4.9E 8 10.2 7.55 9 12.7 12.5 10 16.1 16.2 11 20.2 26.6 Ic e5.* 4.- Dac;ir.;: i:. siscous damping (Q of 25) TESTER TEST DATE TEST LOCATION PREPARED BY TEST hUMSER DATE DC0036 70I1
69-9283 9/84 (10) Page 1 of 2 PACIFIC GAS AND ELECTRIC COMPANY i DEPARTMENT OF NUCLEAR PLANT OPERATIONS l l DIABLO CANYON POWER PLANT UNIT N05. 1 AND 2 TITLE: CALIBRATION At:D TEST DATA SHEET - PEAK ACCELERATION RECORDER, EP M-4 j DATE TIME PAR 400-1 RECORDER S/N 669 RECORD PLATE S/N CAL. DATE 10/1/81 LOCATION: CONTAINMENT BASE SLAB UNIT 1. EL. 39', 180' ACCELERAT10fi DISPLACEMENT ACCELERATION PERFORMED BY SENSOR SENSITIVITY g/in g/ mn. Inches mm (g) L 16.3 0.640 T 16.1 0.635 l V 15.4 0.60C DATE TIME PAR 400-2,_ RECORDER S/N 654 RECORD PLATE S/f. CAL. DATE 10/1/81 LOCA!!Of;: TOP OF l't.:1 1 CONTAlf;MEr.T. EL. 303.5', 225* ACCELEiJ.710h 015PLACEMEhi ACCELERATION PERFORMED BY SEf:fG:. SENSITIY!TY ( g!)n g/ cv Inches m-(g) L 32.5 1.2E T 30.1 1.18 V 32.3
- .27 DATE TIME PAR 400-1 RECORDER S/N 673 RECORD PLATE S/N CAL. DATE 10/1/61 LOCATION:
INTAKE NEAR ASW PUMP 1-2 BAY, EL. 2' ACCELERATION DISPLACEMENT ACCELERATIOfi PERFORMED BY SENSOP SENSITIVITY g/1n g/mm Inches mm (q) L 13.1 0.515 T 15.4 0.606 V 13.8 0.543 DC0036 66!! .___1____
69-9283 9/64 (10) Page 2 o'f 2,. TITLE: CALIBRATTON'AND TEST DATA SHEET - PEAK ACCELERATIQN RECORDER, EP M-4 DATE TIME PAR 400-1 RECORDER S/N 672 + RECORD PLATE S/fi CAL. DATE 10/1/81~ LOCATION: TURBINE BUILDING, MACHINE SHOP EL. 85' ACCELERATIOh D15PLACEMEhi ACCELERATION PERFORMED BY SENSOR SENSITIVITY g/in g/rrrn Incnes mm (g) L 16.2 0.635 T 15.6 0.615 V 14.2 0.558 DATE TIME PAR 400-1 RECORDER S/N 682 RECORD PLATE S/t. CAL. DATE 10/1/81 1 LOCATIC.: AUXILIAhY SUILDING, HOT SHOP EL. 140' ACCELERATION 015PLACEMEhT ACCELERATIOh PERFORMED BY SEUS0R SENSITIVITY a/ir. g/ar I r.cne s no (g) L 15.3 0.601 T 15.4 0.60E i V 12.7 0.500 CATE TIME PAR 400-1 RECORDER S/N EE3 RECORD PLATE S/h CAL. DATE 10/1/81 LOCATION: AUXILIARY BUILDING NEAR CONTROL ROOM 000R, EL. 140' ACCELERATION DISPLACEMENT ACCELERATION PERFORMED BY SENSOR SENSITIVITY g/in g/rm-Incnes nr (g) j L 16.2 0.635 T 16.0 0.630 V 14.3 0.562 l-DC0036 67II
PGandE Letter No.: DCL-85-245 CURRENT EMERGENCY PLAN ~ IMPLEMENTING PROCEDURES TABLE OF CONTENTS ( Yolume 3B TITLE REY OR-1 Offsite Support & Assistance 5 OR-2 Release of Information to the Public 3 EF-1 Activation and Operation of the Technical Support Center 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 6 EF-6 Operating Procedures For EARS 9845C Controlling Stations 4 EF-6S1 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 & Establishment of Controlled Areas 1 j thder Emergency Conditions 2 RB-5 Personnel Decontamination 2 RB-6 Area & Equipment Decontamination 2 j RB-7 Emergency On-Site Radiological Environmental Monitoring 4 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-11 Emergency Off-Site Dose Calculations 4 l RB-12 Mid and High Range Plant Vent Radiation Monitors 1 RB-13 Improved In-Plant Air Sampling for Radioiodines 1 RB-14 Core Damage Assessment Procedure 2 RB-15 Sentry Post Accident Samp1ing System (SPASS) Initial Sampling Exercise After An Accident 1 RB-15A SPASS Initial Actions During An Emergency 3 i~ RB-15B SPASS Reactor Coolant Sampling (Stripped-Gas and Diluted RCS) 2 I 0502d/0005K 07/18/85 2 .-,..w. -.,_.----__---,..,-_.~-_,.,,,---__.__,.-,m_,__,,y --._._,__,,c
i TITLE REV RB-15C SPASS Containment Air Sampling 2 RB-15D SPASS Gas Chromatographic Hydrogen Analysis 2 RB-15E SPASS RCS Liquid and Gas Sample Handling 2 RB-15F SPASS Data Analysis 1 RB-15G SPASS Ion Chromatographic Chloride Analysis 1 RB-15H SPASS pH/ Conductivity / Dissolved Oxygen 1 RB-15I SPASS Sampie Storage and Disposal 0 RB-16 SPASS Subsequent Sampling 0 RB-16A SPASS Initial Actions During An Dnergency (Not Intended to Meet The 3-Hour Time Limit) 2 RB-1681 57X!iS Diluted Liquid Sampling From Reactor Coolant (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16B2 S7X!IS Undiluted Liquid Sampling From Reactor Coolant (Not Intended to Meet The 3-Hour Time Limit) 1 S7XlIS Reactor Coolant Stripped Gas Sampling) R3-16B3 (Not Intended to Meet The 3-Hour Time Limit 1 RB-16B4 SPXTS Diluted Liquid Sampling From Ra&aste (Not Intended to Meet The 3-Hour Time Limit) 2 RB-16B S S7XTS Undiluted Liquid Sampling From Ra&aste (Not Intended to Meet The 3-Hour Time Limit) 2 RB-16C SPXTS Containment Air Sampling (Not Intended to Meet the 3-Hour Time Limit) 1 RB-16D SPXTS Gas Chromatographic Hydrogen Analysis (Not Intended to Meet the 3-Hour Time Limit) 1 RB-16E SPX53 Liquid and Gas Sample Handling (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16F SPX5S Data Analysis (Not Intended to Meet The 3-Hour Time Limit) 0 RB-16G SPXKS Ion Chromatographic Ch1oride Analysis (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16H SPX!IS Ph/ Conductivity Dissolved Oxygen (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16I SPXIIS Undiluted Containment Air Sampling (Not Intended to Meet The 3-Hour Time Limit) 0 RB-16J SPX!IS Sample Storage and Disposal (Not Intended to Meet The 3-Hour Time Limit) 0 2-07/18/85 0502d/0005K += c 3 w-p
4 NUMBER EP OR-1 3D W Pacific Gas and Electric Company REVISION 5 f DEPARTMENT OF NUCLEAR PLANT OPERATIONS PAGE 1 0F 2 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 EMERGENCY PROCEDURE l TITLE: OFFSITE SUPPORT AND ASSISTANCE W IMFORTAN 7E / LA~ ' 7 3 TO APPROVED: PLANTMANAGERj DATE SAFETY ~ SCOPE This procedure provides a functional list of non-PGandE organizations which are available for emergency response support and assistance. Telephone numbers are provided which are to be used for initial notification of the need for emergency support. Organizations required to be notified of an emergency are addressed in the procedures referenced below or in the procedure dealing with the type of event. This procedure and changes thereto requires PSRC review. GENERAL 1. Requests for support or assistance from non-company organizations should be specific concerning the nature of the support or assistance requested, the location where needed, when it is needed, and the phone number to use to return a call. Requests may be made to mobilize support on a standby basis. ~ 2. All initial request for support shall be approved by the Site Emergency Coordinator or the Recovery Manager at the EOF. Subsequent requests shall receive the same approval if they require additional resources. Requests for assistance from organizations supporting San Luis Obispo County also require County Emergency Services Director approval prior to making the request. 3. Emergency response organizations are listed in Appendix 1 under the following functional titles: Radiological Emergency Protective Actions Medical Emergency Fire Emergency Health Physics / Assessment Support Plant Operation / Repair Support Offsite Emergency Response Support Law enforcement emergency contact means are addressed in the appropriate security procedures. DC0043 IXI + -
.= .. =. ~ l'. otA8LO CANYON POWER PLANT UNIT %S) 1 AND 2 NUMBER EP OR-1 REVISION 5 DATE 5/15/85 ~ PAGE 2 0F '2 TITLE OFFSITE SUPPORT AND ASSISTANCE SUPPORTING PROCEDURES NPAP Cll, and its supplements, "Non-routine Notification and Reporting to the NRC and Other Governmental Agencies" j EP G-3 " Notification of Offsite Organizations" ATTACHMENTS I:
- 1. - Offsite Support and Assistance Functional Description 2.
Table 1 - Offsite Emergency Support Organization Phone List. l o-I l l-L h I l DC0043 2XI 1-. L u,
i J 12/84 Page 1 of 2 . PACIFIC GAS AND ELECTRIC COMPANY, DEPARTMENT OF NUCLEAR PLANT OPERATIONS ( DIABLO CANYON POWER PLANT UNIT NOS. 1 AND 2 ,f % ATTACHMENT 1 TITLE: OFFSITE SUPPORT AND ASSISTANCE CONTACT LIST - EP OR-1 I. Radiological Emergency Protection Actions The organizations listed in Table 1 under this heading provide support to the San Luis Obispo County Emergency Organization in implementing protective actions for the general public. All support requests from these organizations should be coordinated with San Luis Obispo County. Direct requests for support would not ordinarily be required, but exceptions to this may be necessary in the event of an initial notification to San Luis Obispo County requiring inmediate protective actions in the low population zone (6 mile radius) or beyond in the affected sectors. II. Medical Emergency i The organizations listed in Table 1 under this heading provide assistance in the l transportation or treatment of persons injured and contaminated with radioactive material, and/or overexposed to radiation or radioactive materials. Persons so injured will normally be treated at French Hospital in San Luis Obispo, however, (- Saint Francis Memorial Hospital is also available should the need for additional hospital services arise. j III. Fire Emergency The organizations listed in Table 1 under this heading provide backup fire fighting support to the California Department of Forestry (C0F), in the site ares. Assistance is coordinated through CDF in all cases. i - IV. Health Physics / Assessment Support j The organizations listed in Table 1 under this heading provide assistance in on or offsite monitoring, radiation protection or radiological accident assessment. Requests for assistance are coordinated through the Emergency Radiological Advisor for onsite or near site activities and with San Luis Obispo County for offsite activity. V. Plant Operation / Repair Support The organizations Ifsted in Table 1 under this heading provide assistance in technical assessment of plant conditions, and in maintenance / repair projects. Only those organizations with defined emergency response roles are included. Assistance from these organizations and from the resources of PGandE, other utilities and vendors are available through the Corporate Emergency Response Organization. I l 4 f DC0043 3VIII ~ _- .__m. m-y -.r-- w v- ,.-p9,,.r-., .---w y. ,,w--.-, v m. --.--ww-., --.---,w
..._.,..m._ 1 4 Page 2 of,2 .i TITLE: OFFSITE SUPPORT AND ASSISTANCE CONTACT LIST - EP OR-1
- i r
VI. Offsite Emergency Response Support ] The organizations listed in Table 1 under this heading provide offsite response support to the San Luis Obispo County Emergency Organization, or are available for support of PGandE offsite operations. These support organizations are categorized as: 1) Transportation 2) Law Enforcement 3) Traffic Control
- i 4)
Public Alerting and Care a 1 i ..] p-- DC0043 4VIII i
- - ~.. -.
e S/85 Page 1 of 9 PACIFIC GAS AND ELECTRIC CCMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 4 TABLE 1 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 Organization Function (s) location (s) Phone Number (s) I. Radiological Emergency Protective Actions US Coast Guard
- 1) Clear craft from Marine water near DCPP Safety Office
- 2) Shipboard San Francisco radiological or monitoring Monterey Operation
- 3) Vessel decontamination State Protective actions in San Luis Obispo Department of State Parks & Beaches:
Headquarters Parks & Montana De Oro Recreation Avila State Beach Hearst Castle ( Pismo State Beach (. Morro Bay State Park Pismo Ranger l Atascadero State Beach Station l Pismo Dunes l Station State Ingestion pathway 744 "P" St. Department of monitoring coordination Sacramento, CA Public and food stuff l Health-Radiolog-interdiction as required. ical Health Section II. Medical Emergency (See procedures M-1 and R-1 also) San Luis Onsite ambulance service. 358 Santa Rosa Ambulance San Luis Obispo Service, Inc. Air Ambulance, Air Transportation 701 Skyway Inc. (fixed wing or San Carlos, CA helicopter) frem site or airport (under PGandE contract). California Air Medivac Hunter Ligget National Guard OC0043 SX
Page 2 of 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) / Organization Function (s) location (s) Phone Number (s) San Francisco Ambulance Service in 2829 California Artulance the San Francisco Area. Street l Service San Francisco French Hospital Erergency Medical 1911 Johnson Ave. Treatment San Luis Obispo Dr. Fred Mettler Consultant on VA Hospital (REMS Corp.) Radiological Injuries Albuque rque, New Mexico . or = 3004 La Mancha St N.W. Albuquerque, NM Saint Francis Erergency Medical 900 Hyde Street Mem eial Treat.m nt San Francisco Hospital III. Fire Em rgency California Priracy Site Fire Highway 1 Decartment of Fighting Response San Luis Obispo Forestry Air Attack Base Paso Rebles Airport Arroyo Grande Backup fire fighting 140 Traffic Way Fire Department support. Arroyo Grande ~ Pisco Beach Backup fire fighting 1000 Bello Ave. Fire Department support. Pismo 3each San Luis Obispo Sackup fire fighting Garden & Pismo Fire Departrent support. S treets l San Luis Obispo South Bay Fire Backup fire fighting 2315 Bayview Department support. Heights Drive Los Osos Morro Bay Fire Backup fire fighting 715 Harbor Departmen t support. Morro Bay A OC0043 6X
Page 3 of 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) 4 ~ Orcanization Function (s) location (s) Phone Number (s) IV. Health Physics / Assessment Succort Onsite Nuclear
- 1) Onsite assessment 1450 Maria Lane Regulatory
- 2) Coordinate federal Suite 260 Cenni ssion technical response Walnut Creek, CA Region V
- 3) Develop protective action Incident Response reccanendations.
Center
- 4) Radiological monitoring Sacramento Chemical-Radiation Rancho Seco Municipal assistants and equipment. Heald, CA Utility District Control Rocm l
Southern Health Physics San Onofre California tecnnicians and San Clemente, CA Edison equi; ment, i f' Portland Chemistry and/or Portland, Oregon . ( General Electric Radiation Protection V.P. Nuclear Gen. l Technicians and Mgr., Tech. l Equipment. Funct. I t Trojan Plant General Manager dashington Health Physicist and WNP-2, Hanford, 3ubite Pcwer Health Physics / Chemistry Wash. Emerg. Supply System Technicians and equipment Coordinator or i Security Control I Arizona Pubite Radiological Engineer or Shift Supv. Service Supervising Radiation or Physicist, Chemist or Supervising Chemist, Rad. Prot. Offic Radiation Protection Tech, Chemistry Techs, OC0043 7X
Page 4 of 9 TITLE: OFFSITE EMEMENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) Organization Function (s) location (s) Phone Number (s) Department of
- 1) Federal offsite San Francisco Energy monitoring and Operations assessment Office-Region 7 coordination.
7333 Broacway
- 2) Coordination of Oakland, CA Federal response (IREP Coordination).
Nevada Operations not in service Office Las Vegas, Nevada Environmental Ccmolete radiological Dave Duncan, Protection monitoring and Regional Agency assessment assistance. Radiation Representative, Region IX, San Francisco Wayne 81fss, Director of l Office of Radiation l Prcgrams, Las Vegas Facility ) Department of Assist in monitoring and HQ-6th Army l Defense medical assistance if Presidio of San (Army) requested by the IRAP Francisco ccordinator or local authorities (Nuclear Accident Incident Control I Teams), Department of Assist in monitoring and Cocinander - Naval De fense medical assistance if Base (Navy) requested by the AP San Diego, CA Coordinator ( M H r Accident T;th. National Weather rex rts, WSFO-Redwood Wea ther forecasts and special Service advice from Weather City (NCAA) Service Forecasting Of fices (WSFO)-normally WSFO-Los coordinated through Angeles Meterology personnel in CIRC. I OC0043 8X l
Pagg S of 9 l TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) I Organization Function (s) location (s) Phone Number (s) State Office Assessment support to Emergency of Emergency local agencies. Response Center Se rvices Sacramento, CA State Department Ingestion pathway 744 "P" Street of Public monitoring coordination Sacramento, CA Health-Radiolog-and food stuff ical Health interdiction as required. Sureau San Luis Obispo Coordinate county County Gov't. County of emergency response Center Emergency activities and emergency Sar. Luis Obispo Services planning. San Luis Obispo Direct offsite moni-2191 Johnson Ave. County toring and assessment San Luis Obispo Envircreental activities of San Luis Healtn 'Obispo County. k. SS74 Capistrano Ave. Atascadero V. Plant Oceration/Recair Succort Westinghouse Technical, onsite or Monroeville (Notify as Electric Ccmpany materials assistance or Nuclear Center Indicated Belcw) reactor systems or compcnents. NOTIFY ONLY IF TECHNICAL, ONSITE OR MATERIALS ASSISTANCE ON REACTOR SYSTEMS IS NEEDE] PROVICE PLANT EMERGENCY NL'MBER [805-595-733S] FOR REPLY. NOTIFY ONE WESTINGHOUSE CONTACT ONLY USING THE SELCW LIST IN THE ORDER SHCWN. TITLE NAME OFFICE /HCME/HCME HOT LINE Unless indicated otherwise, all phone numbers are area code [41([ heme, Where NOTE: i an area code other than[412]is shewn, it applies to the office, and HHL numbers. 1. SITE SERVICES RCN SUCHHOLZ MANAGER 2. OPERATING PLANT GIL XUSANSEX RESIOUAL MANAGER IST ALTERNATE JOHN GALLIX 2ND ALTERNATI JOHN MISK0 l DC0043 9X g.
Pago 6 of 9 TITLE: OFFSITE ENERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) TITLE NANE OFFICE /HCME/HOME HOT LINE 3. SERVICE RESPONSE TCM MITLO MANAGER IST ALTERNATE 808 ST0XES 2ND ALTERNATE JOE LEBLENG 4 EMERGENCY RESPCNSE TCM ANCERSON l 0! RECTOR 5. EMERGENCY RESPCNSE RON LEHR l CEPUTY 0! RECTOR 6. EMERGENCY NEWS MIXE MANGAN CCMMUNICATIONS L-Or;anization Function (s) location (s) Phone Number (s) Institute of
- 1) Lccating emergency E.mergency l
Nuclear Pcwer marpcwer and Response Center Operatiens equipment Atlanta, Georgia
- 2) Ocerational analysis 3)
Informa tion l dissemination
- 4) Organization of experts for advice Rcgers Helicopter en standby Rogers Helicopter Helicopter under PGancE contract Clovis, CA scund system and lighting.
Rory Regers (hece - or - Robin Rogers Rotor-Aids, Inc. Helicopter (s), as Rotor-Aids, Inc. available, under PGandE 0xnard, CA contract. Aris Helicopter Helicopter (s),as San Jose available under PGancE centract. Medivac capability. DC0043 10X i
9 O ~ l Pago 7 of 9 1 TITLE: OFFSITE ENERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (continued) Organization Function (s) location (s) Phone Number (s) Condor Helicopter (s),as Condor Helicopters available, under PGandE Helicopters and contract. At least 1 Aviation Inc. light duty helicopter Oxnard Airport available at all times. Ventura, CA of Mr. Gary O' Conner Chief Pilot l Air Ambulance, Fixed wing or helicopter Mr. Steve Smith International air ambulance service 795 Skyway San under PGandE contract. Carlos, CA Cali fornia Fixed wing and he11-Air Attack Base ) l Cepartment of copter for ccunty/ P3so Rcbles Forestry state supcort, as Airport available. VI. Offsite Emer;eccy Desconse Succort Transoortation California
- 1) Fixed wing or San Francisco Are Highway Patrol helicopter for 455 Sth Street transportation of San Francisco essential personnel.
- 2) Es<: ort of priority vehicles.
State San Luis Obispo Area S.L.O. H.Q. l Parks and Recreation Hearst Castle Cepa rtment Ken Huddlescon Emergency l Coordinator 24 Hour Dispatcher Pismo Beach g (Ranger Station) OC0043 11X ' = = ....m. s-e ~ q
4 E Page 8 of 9 TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATION PHONE LIST - EP OR-1 (c Orcanization Function (s) location (s) Phone Nurber(s) Law Enforcement San Luis Obispo 1) Law enforcement in Dispatch office l I ) County Sheriff county areas not County i under city PO's. Operational 2) Primary response Facility agency under SLO Highway 1 County emergency San Luis Obispo plan. Arroyo Grande Law enforcement in 200 N. Halcyon j Police Arroyo Grande. Rd. i Cep a r: ment Arroyo Grande Atascadero law enforcement in Administratien Police A:ascadero. Building ) Lewis Ave. Cesart ent Ata scadero Morro Say Law enforcement in 850 Morro Bay Police Morro Bay. Soulevard Cepartment Morro Say Pismo Beach Law enforcement in Pismo 1000 Bello Ave. Police Beach. Pismo Beach Department San Luis Obispo Law enforcement in San 575 Santa Rosa l Police Luis Obispo. San Luis Obispo Ce:artment Monterey County Law enforcement in Salinas Sheriff Monterey County. Santa Barbara Law enforcement in Santa Santa Barbara County Sheriff Barbara County. Traf fic Control (City police, fire and public work also support) California
- 1) Primary traffic 675 Calif. 31vd.
Highway Patrol control support to San Luis Obispo SLO County. 4
- 2) Fixed wing or Coastal Oiv. H.Q.
helicopter traffic 1122 Laurel Lane n su rvei llance. San Luis Obispo 4 OC0043 12X
l O 4 .ar Paga 9 of g e TITLE: OFFSITE EMERGENCY SUPPORT ORGANIZATTOY PHO Organization Function (s ) location (s) ~ Phone Number (s) Public Alerting and Car-American Nuclear Emergency assistance 270 Farmington l Insurers (ANI) funding of the public for Ave. emergency response Farmington, Conn. expenses from an extraordinary nuclear occurance. Assistance is coordinated through CIRC, Corporate Liaison Coordinator. American Red Primary operator of care 1216 Morro Cross and feeding facilities San Luis Obispo in support of SLO County. t Emergency Primary stations for KVEC i Broadcas t providing emergency 820 Walnut j Stations public information in San Luis Obispo l support of SLO County. XSLY ( 2895 S. Higuera San Luis Obispo KATY \\ 1146 Monterey San Luis Obispo -i 1 i 'W"J
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