ML20238E161
| ML20238E161 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/15/1987 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20238E156 | List: |
| References | |
| NUDOCS 8709140180 | |
| Download: ML20238E161 (121) | |
Text
O NORTH ANNA POWER STATION l REPORT OF EMERGENCY PREPAREDNESS EVENTS 1 RELATED TO STEAM GENERATOR TUBE RUPTURE I JULY 15, 1987 Section 1 -Narrative Summary of Unit 1 SGTR Event on July 15, 1987
, Section 2 -Chronological Overview of Key Events Section 3 -Summation of HP Monitoring Activities Section 4 -Emergency Plan Implementing Procedure (EPIP) Log Section 5 -Recovery Organization Section 6 -Key Elements of NAPS' Emergency Plan Demonstrated During SGTR Event -
I Section 7 -Use of ERCS j Section 8 -Public Affairs Response: Overview of CPNC and LMC
- "Media Comments on CERP Performance, July 15" Letter- i
-Press Releases Section 9 -W. L. Stewart Letter to Mr. A. E. Slayton, " Summary of ' Alert' 4 Emergency," dated July 15, 1987.
-Miscellaneous Correspondence from State Regarding Response to Event Section 10 -Overview of Louisa County Responsr-Section 11 -0verview of Spotsylvania Country Response Section 12 -0verview of Emergency Response Activities Section 13 -Emergency Planning: Areas for Enhancement Section 14 -Miscellaneous Logs: Plant, Emergency and Radiological Status, i
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k SECTION 1 ,
NARRATIVE
SUMMARY
OF UNIT 1 STEAM CENERATOR TUBE RUPTURE EVENT 1 ON JULY 15, 1987 I
At approximately 6:35 a.m. on July 15, 1987 North Anna Unit I was manually tripped from 100% power due to indications of a steam generator tube rupture
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in the "C" steam generator. Approximately twenty seconds later, the safety l injection system automatically initiated.
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At 6:39 a.m., a " Notification of Unusual Event" was declared after indications of the tube rupture (primary to secondary leakage exceeding one gallon per minute) in "C" Steam Generator were evaluated by control room personnel.
Initial notifications to' State and local authorities were completed by 6:51 a.m. By 6:54 a.m., the event was upgraded to an " Alert" classification at the direction of the Interim Station Emergency Manager, and in accordance with )
1 EPIP-1.01, Tab "B", Item 8. " Gross Primary to Secondary Leakage". Initial notifications to the NRC and follow-up notifications to other offsite ] I agencies that were required as a result of the upgraded classification were completed by 7:02 a.m. Following the initiation of the event, the unit was stabilized in accordance with Station Emergency Operating Procedures. In addition, Emergency Plan Implementing Procedures respective to an " Alert" gs classification were implemented to augment the onshift staff. By 7:28 a. m. ..
an accountability of all station personnel had been conducted. By 7:57 a.m.,
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the Technical Support Center and Operational Support Center were fully manned and activated. By 9:15 a.m., the Local Emergency Operations Facility was fully manned and activated.
The initial indications available to the operators were from the main steamline radiation monitors of which "A" and "B" went into alert, and "C" into high alarm at approximately 6:30 a.m. on July 15, 1987. Subsequently, pressurizer pressure and level began to decrease rapidly. Pressurizer pressure decreased (after the manual reactor trip) to approximately 1730 psig which is below the safety injection setpoint of 1765 psig. Pressurizer level decreased from its 100% power program level of approximately 65% to offscale low prior to recovery. The maximum primary to secondary leak rate has been estimated to be 550 to 650 gpm. The re-establishment of pressurizer level and isolation of the ruptured "C" steam generator'was completed under Station Emergency Operating Procedures (EP-0 and EP-3, Revision 1).-
Cooldown and depressurization of the RCS was initiated at 7:27 a.m. in accordance with Station Emergency Operating Procedure ES-3.1, Revision 1 and proceeded routinely. At 11:08 a.m., the RCS was cooled down to below 350 degrees F, and Unit I was placed in Mode 4, Hot Shutdown. At 1:33 p.m., the RCS was cooled down to less than 200 degrees F. and the unit was placed in Mode 5, Cold Shutdown. Plant conditions were stable and the emergency was terminated at 1:36 p.m., at which time termination notifications were made to the NRC and offsite agencies.
During the course of the event, effluents released from "C" Steam Generator prior to its isolation occurred through the Condenser Air Ej ector and Auxiliary Feedwater Pump Turbine exhaust. However, the release was determined to be very small. Isotopic analyses performed on samples drawn from these pathways indicated a total release of 0.33% of Technical Specification limits.
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... CHRONOLOGY.
STEAM GENERATOR TUBE RUPTURE EVENT
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.g NORTH LINA POWER STATION UNIT 1 JULY 15, 1987 i
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.) 7 .j-To support the investigation of' the Steam . Generator Tube Rupture" che z following chronology 'was reconstructed from the print outs .of the-' alarm typewriter attached.to the Control Room P-250 process computer, the Sequence of i
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. Events Recorder (Dranetz) driven by thetifachauay annunciator system,.theddata printouts extrneted from'the record kept by"c.he ERF Computer in~ the Technical u Support ' Center', . RC.and SRO~1ogs and interviews, and strip charts from Control Room recorders. '/
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Selected data was transmitted.d rom the varicus . records based won line significance of each datum as le identifief a sub-event or demonistratdd, explicitly or implicitly, a sdb-tvent in the sequence. The intent is that this s
' chronology - can ' be iscograted with other analysi5 'to determine the timelirMs, accuracy and effectiveness of the measures applied,to mitigets the accidennf.
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Once the data was transcribed, a review was perfortted . to identify the synchronism for time of the various, data scurces. The'pnir.cipal item selected for synchronism was the Automatic Pzr Lo-Lo SI. The SI action incorporates !
several actions including .feedwater isolation and normal charging isolation j that make'it readily comparable over all records. The Sequence of Events 1 j Recorder logged SI at 06:35:24:805; the P-250 logged SI at 0639..However the !
earlier Reactor Manual Trip has caused the Pi250 to alter its scan rates. The ,
P-250 Post Trip review logged SI t.t' 06:35:24 plus 1012 cycles, which equates to 06:35:40.86. The ERFC data set, collected at 06:34: 14 . records full normal charging flow and full power f nd flo5r to the steam generators, approximately 16 seconds after the reactor trip had been manually initiated. .By 06:34:21,
, the ERFC data set chaiging fluw is reduced to 82.568 gym and feed flows are ,
- about 600KLBH to 800KLBE.c By 06:34:34, all flows had reached a stable but low '
level. It appears that' SI occurred at or slightly before 06:34:14. Thi.i ;
chronology vill use 06:34: 14
( t For automatic initiation of Safety Injection, the clock cecparisons I are as follows:
RECORDER TIME L, . Sequence of Fvents Recorder (SER) 06:35:24:Bp5 i F-250 Computer 06:35:41 ' #
ERF Computer (ERFC) 06:34: 14-
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RECORDER TINI
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Sequence of. Events Recorder (SER) 06:35:04:548-P-250 Computery 06:35:24 C?.? Computer (ERFC) 06:33:56 j
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r It is concluded thk,e th4 P-250 led, the SER was.within 20 seconds of the l ;!' , P-250 and the ERFC was'about one pinute behind the P-250.
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The ehrend_legy,that follows is annotated by clock time 6ased on the P-250.
l , All the events tt e. occurred within each minute art listed in order of occurrence as'couldltest be determined.
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(1 SEQUENCE OF EMERGENCY PREPAREDNESS EVENTS July 15, 1987 0638 -EPIP-2.01, Notification of State and Local Governments, initiated.
0639 - "Notification of Unusual Event" declared.
-Unit 2 SRO assumed duties as Icterim Station Emergency Manager.
-EPIP-1.01, Emergency Manager Controlling Procedure, initiated.
-EPIP-1.02, Response to NOUE, initiated.
0645 -Security requested to dispatch officer to Control Room for access control.
0650 -EPIP-4.01, Radiological Assessment Director Controlling Procedure, initiated.
0651 -Initial offsite notification regarding "NOUE" is transmitted to State and local authorities. !
0652 -EPIP-4.02, Radiation Protection Supervisor Controlling Procedure, initiated.
0654 -Interim Station Emergency Manager upgraded event classification to
" ALERT". EPIP-1.03, Response to Alert, initiated.
-Security officer established post at Control Room.
0655 -Security is notified by Control Room to initiate EPIP-3.01, Callout, EPIP-5.03, Accountability, and EPIP-5.04, Access Control.
-Security is instructed by Control Room to have officer at roadblock to allow emergency response personnel onsite. Non-ensential personnel are to be held at roadblock, and all contractors, salesmen, and vendors arriving to the site should be turned back.
0700 -EPIP-3.01, Activation of OSC, initiated.
-Security directed to initiate EPIP-3.04, LEOF Activation.
-EPIP-4.14 Inplant Monitoring, initiated.
-EPIP-4.28, TSC/LEOF Radiation Monitoring System, initiated.
0702 -Initial " ALERT" notification messages transmitted to NRC, State and O local authorities. (EPIP-2.01 previously initiated. EPIP-2.02, Notification of NRC, initiated.)
0704 -EPIP-3.02, Activation of TSC, initiated.
0705 -EPIP-4.17, Monitoring of OSC and TSC, initiated.
0708 -Security roadblock established at Rt. 700 and station access road.
-EPIP-4.08, Initial Of f site Release Assessment , initiated.
0710 -General Office Security conducts Corporate Emergency Response Team callout.
f -EPIP-4.15, Onsite Monitoring, initiated.
0712 -Security completes LEOF activation / setup.
-EPIP-4.25, Liquid Effluent Sampling During an Emergency, initiated.
0715 -Supt. Operations and SRO On-Call arrive in Control Room.
-HP prepares to restrict access to Turbine and Auxiliary Buildings, as well as Main Steam Valve House.
-Inplant monitoring teams dispatched. Radiological check-point and dosimetry issue established at entrance of Service Building.
0718 -3rd message is transmitted to State and local authorities.
0720 -Station Manager arrives in the Control Room.
O1 -EPIP-4.03, Dose Assessment Controlling Procedure, initiated.
-EPIP-4.12, Of f site Environmental Monitoring Instructions , initiated.
0727 -EPIP-4.27, Use of Class "A" Meteorological and Dose Calculational Model, initiated. 1 f
0728 -Station accountability complete. 10 individuals missing.
-Offsite monitoring team #1 dispatched. (EPIP-4.16, Offsite Monitoring, initiated).
0730 -Assistant Station Manager arrives in Control Room and initiates transition of EPIPs and communications from Control Room to TSC.
-EPIP-4.19, Use of Radios for HP Monitoring, initiated.
0739 -Station Manager assumes Station Emergency Manager (SEM) position.
l 0745 -4th message is transmitted to State and local authorities. j
-Security is notified by HP that access to the following areas-is l restricted and that the areas are roped off:
U1 - MSVH U1 - Terry Turbine Turbine and Aux. Building.
-A radio announcement is made to all Security personnel on restricted access areas. '
-EPIP-4.06, Personnel Monitoring and Decontamination, initiated.
0747 -All missing personnel located.
0752 -EPIP-5.08, Damage Control Guideline , initiated.
l
_ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ - . _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ a
m 0753 -TSC fully manned. OSC fully manned and activated.
0757 -TSC activated.
0800 -Public Affairs inter-departmental callout conducted.
-Press release #1 is issued.
0801 -SEM and TSC Directors provide status update to facility.
0805 -Sth message is transmitted to State and local authorities.
0818 -Security is directed to allow access to Westinghouse representative.
0820 -Corporate Emergency Response Center activated.
-EPIP-2.04, Transmittal of Plant Radiological and Emergency Status, initiated.
0823 -EPIP-4.10, Determination of X/Q, initiated.
0828 -SEM, TSC Directors provide status update to f acility.
-Turbine and Auxiliary Building released from radiological controls / restricted access.
-Westinghouse representative onsite.
-6th message is transmitted to State and local authorities.
0830 -Corporate Public News Center operational.
(} -Rumor Control Area operational.
-HPN Communications established with NRC from TSC.
-Security is notified by TSC to allow Virginia Power personnel at roadblock to assemble in Warehouse #2. l
-Offsite monitoring team #2 dispatched. l l
0843 -LEOF updatos Old Dominion Electric Cooperative.
l 0845 -Security is notified by TSC to release Virginia Power personnel to !
normal work areas. All contractors are instructed to assemble in j Project Area. Contractors that do not work in Project Area are I instructed to assemble in construction parking lot. All vendors and salesmen should still be turned back at the roadblock. Any news media personnel should be directed to the Local Media Center at Mineral Fire Hall.
-Initiated callout of Security personnel to report at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, in order to allow midnight shift personnel to leave.
0846 -7th message is transmitted to State and local authorities.
0853 -EPIP-4.11, Follow-up Offsite Release Assessment, initiated.
0858 -EPIP-4.09, Source Term Assessment, initiated.
0900 -2nd press release is issued.
(O) 0905 -Security notifies Engineering and Construction that no vehicles will be allowed into Protected Area unless associated with the emergency.
0913 -8th message transmitted to State and local authorities.
0915 -LEOF activated.
(
0935 -Corporate Security arrives at LEOF.
-LEOF assumes responsibility for State and local notifications from TSC and transmits 1st message.
0937 -CERC weather forecast provided to LEOF.
0955 -Security is directed by TSC to allow OMNI contract personnel into the Protected Area.
1000 -Local Media Center fully operational.
I 1009 -2nd LEOF message to State and local authorities transmitted.
1010 -EPIP-4.18, Monitoring of LEOF, initiated.
1015 -LEOF conducts conference to begin recovery planning process, 1018 -UPI arrives at Security roadblock and is directed to the Local Media Center.
1035 -LEOF making arrangements for media tour of site in afternoon.
1040 -Received call from Jeff Lankford, NRC Region II. Notified that F.
Cantrell, B. Revsin, L. Nicholson, and S. Gagner en route to North Anna.
ETA 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />.
j 1043 -3rd LEOF message transmitted to State and local authorities.
1058 -CERC provides weather forecast update.
1100 -3rd press release is issued.
1 1102 -State Corporation Commission arrives onsite (LEOF). I 1115 -4th LEOF message to State and local authorities is transmitted.
i 1139 -CERC provides weather forecast update. I 1140 -Called Mr. Lankford with NRC and informed him that Cantrell, Revsin, and I Nicholson have a current badge at North Anna, and that access will be !
expedited.
1 1148 -Sch LEOF message transmitted to State and local authorities.
1210 -CERC provides weather forecast update.
1220 -6th LEOF message transmitted to State and local authorities.
1238 -CERC provides weather forecast update.
1241 -LEOF provides update to Old Dominion Electric Cooperative.
l 1252 -7th LEOF message is transmitted to State and local authorities.
i 1303 -NRC team arrives onsite.
V 1320 -Security notified TSC that Channel 9 news was at roadblock and stated that they were sent from Mineral Fire Hall (LMC).
1326 -8th LEOF message transmitted to State and local authorities.
1328 -Security notified Channel 9 news at roadblock, as directed by TSC, to return to the LMC and that a press conference would be held onsite later in the day.
1333 -EPIP-6.01, Re-entry / Recovery Guideline, initiated.
1335 -Emergency terminated.
1336 -Recovery meeting is scheduled in LEOF to outline organization and long-term plans (Recovery Organization is implemented).
-NRC Communications terminated.
-Emergency Response Facilities in process of deactivation.
1342 -Security notified to terminate TSC and Control Room posts.
1343 -9th and final (termination) message sent by LEOF to State and local authorities.
1345 -Mr. Nicholson (NRC) onsite. Directed to LEOF for conference.
1355 -Security instructed by LEOF to escort media from LMC to station for press conference.
i 1400 -Final press release issued.
1505 -News media onsite. -
-Security roadblock terminated.
1603 -Security post at LEOF terminated.
-Recovery meetings, outage planning proceeds into the night.
O
l 1
/ I j
SECTION 3 I i
1
\ SUMMATION OF HP MONITORING ACTIVITIES i
i i
NOTE 1: The following summary of HP monitoring activitles was compiled f' based on a review EPIP's 4.14 (Inplant Monitoring), 4.15 (Onsite
. Monitoring), 4.16 (Offsite Monitoring), 4.17 (TSC/OSC Monitoring),
and 4.18 (LEOF Monitoring). This summary does not include Count Room activities / sample analysis for liquid or ventilation samples ^
during the event, but instead is intended to provide a simple overview of general EP practices during the event.
NOTE 2: Surveys generally include dose rates, smears, and air samples. !
l i
NOTE 3: A more detailed synopsis of HP activities is presented in a separate section of the SGTR report.
TIME EVENT I 1
0705 -TSC monitoring initiated and continues throughout event.
0710 -Survey of outside areas around U-1 Terry Turbine and MSVH.
0713 -0SC monitoring initiated and continues throughout the event.
-Survey of U-1 Turbine Building, 303'.
0728 -Offsite Monitoring Team #1 dispatched to field. Monitoring continues throughout event.
0730 -Survey of Service Building. - ;
-Dose Control checkpoint established at Service Bldg. entrance.
0731 -Survey of U-1 Turbine Building, 303'.
0745 -Access to MSVH, Turbine Bldg., Aux Bldg., and Terry Turbine ,
restricted, i 1
a 0758 -Survey of Chemistry Lab / Environmental Lab.
0800 -Aux. Building Survey @ Blowdown Tanks. J 0801 -Survey of U-1 Turbine Building, 303' (CAE sample point) .
0806 -Survey of outside area, within fence, @ DP-2.
0808 -Survey of U-1 Turbine Building, 303'.
0809 -Survey of U-1 Turbine Building, 254'.
0810 -Survey of U-1 penetration, 244'. Aux. Bldg. l
-Survey of Aux. Bldg., @ Blowdown Tanks. l 0815 -Survey of U-1 Turbine Bldg., 271' and 279'
) -Offsite air sample / survey at Visitor Center for Count Room i V analysis.
0817 -Survey of U-1 Mechanical Equipment Room.
l I
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(~% 0825 -Survey of Sample Sink Room. .
0830 -Offsite Monitoring Team #2 dispatched to field. Monitoring ,
continues throughout event.
-Survey of U-1 Turbine Bldg., 303'. ,
l 0852 -Offsite air sample / survey at access road for Count Room analysis. I l
0854 -Survey of Sample / Sink Room.
0900 -Survey of U-1 Turbine Building.
-Survey of U-1 Mechanical Equipment Room.
0905 -Survey of U-l Aux. Building, 291'.
0910 -Survey of U-1 Aur.. Building, 274'.
-Offsite air sample / survey at Aspen Hills subdivision for Count Room analysis. '
l )
l 0915 -Survey of U-1 Aux. Bui'. ding, 259'. l l
0925 -Survey of U-1. Aux. Building, 244'. I 0930 -Survey of U-1 Turbine Building, 303'.
0935 -Survey of PDA and Laundry Areas.
1 g 0944 -Survey of U-1 MSVH. j
-Survey of U-1. Auxiliary Feedwater Pump Area. 4 l
l 0945 -Survey of U-1 "On-Line Chemistry Sample Cabinets."
1000 -Survey of U-1 Turbine Bldg., 303',
1 1010 -LEOF Monitoring initiated and continues throughout event. l 1
1 1030 -Survey of U-1 Turbine Bldg., 303'. 1
-Survey of U-1 Mechanical Equipment Room. )
l 1130 -Survey of U-1 Turbine Bldg., 303'. I
-Survey of U-1 Mechanical Equipment Room.
l 1156 -Survey of U-1 Quench Spray and MSVH.
1205 -Vegetation sampled at access road Southwest of plant for Count i Room analysis.
1252 -Survey of U-1 Turbine Bldg., 303'.
-Survey of U-1 Mechanical Equipment Room.
Post-Event: -Offsite Monitoring Teams return. i
-Environmental TLDs and Air Samplers changed out for analysis.
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SECTION 4 l
V EMERGENCY PI.AN IMPLEMENTING PROCEDURE (EPIP) LOG EPIP # TIME INITIATED TIME TERMINATED )
1.01 0639 1335 1.02 0639 1335 1.03 0654 1335 2.01 0638 1335 2.02 0827 1335 l 2.04 0820 1335 !
l 3.01 0655' 0755 3.02 0704 1340 3.03 0700 1335
,Cg 3.04 0708 1656 I 4.01 0650- 1335 4.02 0652 ~ 1340 i 1
4.03 0720 1340 l t
4.06 0745 0915 4.08 0708 1340 l l -l 4.09 0858 1340 4.10 0823 1340 l i
4.11 0853 1340 l l 4.12 (1) 0740 0930 l 1 4.12 (2) 0720 0730
! 4.12 (3) 0815 0830 l 1
4.14 (1) 0840 0900 I
,.- 4.14 (2) 0930 0945 :
( )
's / 4.14 (3) 1130 1159 i 4.14 (4) 0928 1008 I
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b EPIP # TIME INITIATED TIME TERMINATED a
4.14 (5) 0900 0940 4.14 (6) 0700 1403 4.14 (7) 0658 0833 4.15 0710 0820 4.16 (1) 0728 1336 4.16 (2) 0830 1400 4.17 (1) 0705 1342 ;
4.17 (2) 0713 1343 i
4.18 1010 1350 4.19 (1) 0730 1336 l 4.19 (2) 0840 1400 4.25 (1) 0712 0726 1 4.25 (2) 0727 0827 4.25 (Y) 0831 0910 I l
l 4.27 0727 1005 4.28 (1) 1030 1045 4.28 (2) 0700 0730 l
5.03 0655 0728 :
l 5.04 0655 1506 !
5.08 0752 1340 6 01 133^ 1335 (Long-term recovery i continued) l l
i NOTE: ;
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- 1) All procedures were initiated and terminated on July 15, 1987.
3 2) The copy of EPIP-2.02 which was completed at the onset of the event l 1s unaccounted for. Mr. George Marshall, the initial NRC-ENS l communicator in the Control Room, indicated in a post-event interview that the procedure was in fact completed, and that the initial report to the NRC was performed by 0702 hours0.00813 days <br />0.195 hours <br />0.00116 weeks <br />2.67111e-4 months <br />, after which continuous communications were maintained.
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SECTION 6 d .
t KEY ELEMENTS OF NORTH ANNA POWER STATION EMERGENCY PLAN DEMONSTRATED DURING SGTR EVENT O 1 O
O KEY ELEMENTS OF NORTH ANNA POWER STATION EMERGENCY PLAN DEMONSTRATED DURING SGTR EVENT 4
During the July 15,1987, "C" Steam Generator tube rupture event, most cf the key elements of the NAPS Emergency Plan were satisfactorily demonstrated.
Verification of these events having been demonstrated was achieved by reviewing logs and procedures maintained throughout the event, and by conducting interviews with emergency response personnel. The key elements that were achieved are provided below:
A. OVERALL STATION ELEMENTS
- 1. The emergency organization's ability to make proper decisions related ]
to emergency radiation exposure guidelines, and the capabilit J implement these decisions. (NUREG 0654,Section II.I., J. and K.)y to l
)
- 2. The ability to establish and maintain emergency management command and control authority, event. and maintain (NUREG 0654,Section II. continuity)of A. and B. authority throughout the
- 3. The ability to classify actual or potential emergencies in accordance with NAPS Emer Plan Implementing Procedures. (NUREG 0654,Section II. D.) gency
- 4. The ability to develop alternative systems or equipment alterations in response to accident affected plant systems or components and to formulate respective procedures to accompany these required modifications (i.e. walkdown of affected areas,. formulation of revised shutdown margin procedure, etc.). (NUREG0654,SectionII.H.andI.)
- 5. The capability to ascertain and requisition parts to perform corrective maintenance on damaged equipment, as , by establishing the Damage Control and Maintenance Support Teams.necessary(NUR 0654,Section II. H. and I.)
1
- 6. The ability to transition into the recovery mode and formulate a long-term recovery and reentry plan. (NUREG 0654,Section II. M.)
- 7. The ability to augment the on-shift emergency organ.ization to support emergency operations in a timely and effective manner. (NUREG 0654, SectionII.E.)
- 8. Effective use of Safety Parameter Display System. (NUREG 0654, SectionII.I)
- 9. Requesting offsite technical support. (NUREG 0654,Section II.C. and-E.)
- 10. Documentation and record keeping of key events. (NUREG 0654, Section :
II.N.)
- 11. Conducting mobilization of key elements of' Federal, State and local emergency plans. . (NUREG 0654,Section II.A.,B.,C.,0. and E.) )
B. OPERATIONS ELEMENTS
- 1. The ability of the Operations Staff to recognize operational symptoms indicative of degrading plant conditions. (NUREG 0654,Section II.I.)
- 2. Proficiency in evaluating parameters, properly categorizing the situation utilizing the station's emergency action level scheme, and makin the requisite emergency classification. (NUREG0654,Section II.D.
- 3. The ability to properly escalate the emergency classification. (NUREG 0654,Section II.D.)
- 4. The ability to efficiently and effectively use notification / alerting procedures and methods. (NUREG 0654,Section II.E.)
'5. The ability to provide effective communications / informational flow from the control room to supporting locations. (NUREG 0654,Section II.E. and F.)
C. SECURITY ELEMENTS The adequacy of access control and security for emergency response O 1.
facilities. (NUREG 0654,Section II.H. and J.)
- 2. The ability to perform station employee accountability. (NUREG 0654,Section II.J.)
- 3. The ability to perform call-out of station personnel. (NUREG 0654,Section II.E. and J.)
- 4. The ability to perform Security escort capabilities. (NUREG0654, SectionII.J.)
D. HEALTH PHYSICS AND CHEMISTRY ELEMENTS
- 1. The capability to perform radiological monitoring activities and assessments, and to formulate'off-site radiological dose projections.
(NUREG 0654,Section II.I., J. and K.)
- 2. The collection and analysis of water, vegetation, soil, and air samples both on-site and off-site. (NUREG 0654,Section II.K. and N.)'
- 3. The use of communications by the monitoring teams', to include sending, receiving, and understanding message content. (NUREG 0654,Section II.N.)
- 4. The response to and analysis of elevated airborne and/or liquid O. activity levels and of elevated area radiation levels.
Section II.N.)
n 5. The initiation and use of appropriate procedures for the collection, ,
(") analysis, and documentation of Environmental Monitoring samples, and for Radiological Monitoring evaluation. (NUREG 0654,Section II.N.)
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- 6. The ability to assess data obtained as a result of sampling activities, and the ability co factor results into the overall assessment process. (NUREG 0654,Section II.N.)
E. EMERGENCY RESPONSE FACILITY ELEMENTS l
- 1. The ability to staff the following Emergency Response Facilities:
(NUREG 0654,Section II.B. and H.)
Control Room (CR)
Technical Support Center (TSC) l Local Emergency Operations Facility (LE0F)
Corporate Emergency Response Center (CERC) l i I l 2. Demonstrating the communications capabilities of the Control Room, i TSC, OSC, LEOF, and CERC, and the ability to maintain these l communications with Federal, State, and local governments. This l includes sending, receiving, and understanding the content of messages l involved. (NUREG 0654,Section II.E., F., and H.)
- 3. The proper utilization of the emergency response facilities and that adequate emergency response equipment exists. (NUREG 0654, Section (m) II.H.)
U F. CORPORATE ELEMENTS
- 1. Demonstrating the LE0F to be adequately staffed and communications I properly established. (NUREG 0654,Section II.H.) l
- 2. Demonstrating that the CERC can be adequately staffed and made functional (e.g., maintain communications, interface with the State Emergency Operations personnel at the CERC, provide engineering assistance, provide logistic support, and establish a Rumor Control group). (NUREG 0654,Section II.H.)
- 3. Performing the activation of the Local Media Center. (NUREG 0654,Section II.G.)
- 4. Performing the timely release and distribution of news announcements.
(NUREG 0654,Section II.G.)
i 5. Coordinating news announcements with off-site emergency response l agencies. (NUREG 0654,Section II.G.)
- 6. Conducting timely and informative media briefings. (NUREG 0654,Section II.G.)
e~ s 7. Responding to outside news inquires. (NUREG 0654,Section II.G.)
('
- 8. Establishing an effective rumor control network. (NUREG 0654,Section II.G.)
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y) The key elements of the NAPS Emergency Plan that were not fully achieved during !
the Steam Generator Tube Rupture event are provided below.
I
- 1. The ability to formulate and make protective action recommendations to protect the general public based on plant parameters and/or field monitoring information was not performed on July 15, 1987. The event was i not escalated to a Site Area Emergency and therefore no protective action l recon"nendations were made. During the practice exercise on July 14, 1987, I protective action recommendations were made to the Commonwealth of Virginia when the exercise escalated to a Site Area- Emergency and a General l Emergency. (NUREG 0654,Section II.J.) i
- 2. The initiation and use of appropriate procedures for the collection, ,
analysis, and documentation of Post Accident Sampling was not performed. !
(NUREG 0654,Section II.N.) i
- 3. The transport of an injured, contaminated individual to a medical facility I was not accomplished because there were no injuries associated with the i July 15, 1987 event. (NUREG 0654,Section II.N.) i
- 4. Response to a fire, in accordance with the requirements of the NAPS Fire Protection Program, was not accomplished because there was no fire associated M th the July 15, 1987 event. (NUREG 0654,Section II.N.)
I i n 5. Response to Local Volunteer Rescue Squads or 1.ocal Volunteer Fire j l
l g Departments was not accomplished because there was no injury or fire the July 15, 1987 event; therefore, no offsite response i
l occurring was during(NUREG 0654,Section II.N.)
requested.
]
- 6. Evacuation of nonessential personnel from the site was not performed on July 15, 1987. Incoming nonessential personnel were restricted from access to the site, and a number of vendor and craft personnel were released, but not dispatched to the remote assembly area because it was determined to be unnecessary. The ability to evacuate nonessential personnel from the site was accomplished during the practice exercise on July 14, 1987, when nonessential personnel were evacuated to the remote assembly area and ,
monitored by Health Physics. (NUREG 0654,Section II.J.)
- 7. Conducting a critique of the event on July 15, 1987 was not accomplished in a traditional manner; however, an effective critique was conducted through interviews with emergency response personnel. Additionally, a traditional j critique was performed after the practice exercise on July 14, 1987.
(NUREG 0654,Section II.N.)
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Section 7 t
I q '
h USE Of EMERGENCY RESPONSE COMPUTER SYSTEM i
1 The Emergency Response Computer System (ERCS) was used cc essively during the ]
Unit 1 Steam Generator Tube Rupture event on 07-15-87. The ERCS was used to {
determine the current status of the plant throughout the event and subsequent I cooldown to Mode 5. Real time data from the ERCS was available in the TSC, l LEOF, and CEOF. All of the screens in the TSC were continually monitored by {
Emergency Response Personnel. In particular, the Station Emergency Manager and i Emergency Operations Director continually monftered the ERCS for current plant status to better communicate with the Plant Operators. The Technical Servict.s Engineers used the ERCS to _ plot Steam Generator Pressure throughout the ,
cooldown. Also, Health Physics used the ERCS to calculate dose proj ections .
Almost all of the approximately 380 analog ~ points and 900 digital points responded accurately during the transient.
There were a few points that did not respond correctly as well as a couple of other areas for improvement with the system. These areas for improvement are discussed in detail in the l following:
Areas for improvement on the ERCS:
- 1. A few points did not respond correctif:
-There were some points that did not; update correctly due to.
calibration error, software programmius error, or incorrect field
- connections. For example, a prtasurizer, vent valve was indicated
( open. The Station Emergency Manage
- checke4'with the Control Room. I control Room indications and plant response indicated that the valve was closed. At this point the valve indication on the ERCS was taken ;
"on maintenance" to prevent the incorrect indication from causing 4 confusion later. !
- 2. There were some questions from Emergency Response Personnel on the status of data:
-There were some questions on why a particular point was "on j maintenance" or indicated in alarm. One source of confusion is a i design feature of the system. If certain values indicate instrument !
failure as a possibility, then the mid level bar is deflected full scale and colored magenta. This was to call attention to the fact that the instrument may be failed. Tiovever, in a number of cases (for example Containment Hydrogen Concentration), the actual v.21ue 'is very ,
low and is picked up by the ERCS as a failed instrument. This design feature is confusing and needs to be re-evaluated. Currently, STA's perform an Operability Check daily and place points "on maintenance" as necessary. Consequently, the STA's are very familiar with the state of the points on the ERCS. It may'bc possible to create on "ca ,
line" Operability Log on the ERCS which could be accessed by any one i using the system. This will keep other users informed :tven if the STA is not present.
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- 3. Some Alarm Setpotute are not appropriate for plant conditions:
-%! s problen has been noticed before during a previous Unit 1 )
Cooldown, GTA procedures were written to ensure that the STA's were i awpre of this problem. This problem is under investigation and alarm j limits vill be modified. This did not cause a problem during the q transient because the problem was previously identified. 1
- 4. Problam with data retrieval from Historic File:
J i
-Magnetic Tapes were recorded about every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during the transient !
l to permanently save a record of the plant parameters during cooldown. .
l These magnetic tapes are designed to be loaded back into the ERCS. ,
j The transient can then be replayed on the ERCS. It has been verified that the data on the tapes is correct; however, there are problems getting the data restored in the computer. The prograraners were able in less than a day to obtain printed data which Engineers are using to analyze the start of the transient. The problem areas with restoring j the cape to the ,romputer have been identified and a successful j i restore. tion should b6.7:complished within a short time.
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SECTION 8 O ;
PUBLIC AFFAIRS RESPONSE OVERVIEW OF CORPORATE PUBLIC NEWS CENTER AND LOCAL MEDIA No major problems were identified in the Public Affairs portion of the Corporate Emergency Response Plan during the " Alert" that was declared at 6:54 A.M. on July 15, 1987 at North Anna Power Station.
Initial callout was performed by General Office Security between 7:10 A.M.
and 7:30 A.M. The Public Affairs callout was performed between 8:00 A.M. and 8:45 A.M. Enough key personnel were at their stations to have the Corporate Public News Center, including the Rumor' Control Area, operational by 8:30 A.M., and the Local Media Center (LMC) operational by 10:00 A.M.
Interest from the media, the public and the financial community was intense. More than 45 reporters were based at the LMC in Mineral and another 20 were at OJRP at different times throughout the day. Records indicate that public information specialists in the Rumor Control area responded to almost 300 calls, including 172 form the public at large,~92 from the media and 13 from the financial community.
A number of deficiencies were evident at the LMC in Mineral, where the absence of both Security and Telecommunications personnel caused a number of problems.
Absence of Security personnel male adequate control of media represen-tatives and the fire hall itself difficult. In addition to media " roaming" around the building, m1nor incidents . occurred which included groups of j children and an elderly woman wandering through the building and a man who j appeared to be intoxicated.
l The microphones on the LMC audioconferencing system were inoperable and noise on the speaker system made it difficult for reporters to hear what was being said in the OJRP Public News Center. A telecommunications representative would have been able to correct these items. j Public Affairs is maintaining a file of all calls received in the Rumor Control area during the " Alert".
1 The next revision of the Corporate Emergency Response Plan will includ.. ,
procedures to ensure adequate security and telecommunications personnel are l present at both the North Anna and Surry Local Media Centers, q i
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MEMORANDUM To: Rodnar' Smith Richmond, Virginia From: Doug Cochya:- July 16, 1087 MEDI A COMMENTS ON CRBy__ PERFORMANCE JULY 15
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The news mtdiia present a't the' Local Media Center during the i~u,ly 15 event were ttost impressed by,the company's openness and inacperation with the medit.
n
- Almost all the media, a.T they left late in the day, came to u and expressed their appreciation for our help. Reporters for the AP, WUSA TV, WRCC TV, WRC.TV, the Washington Post and U. S.
News and World Report were particularly vocal in their appreciation. Th6 cor,sensus was that we did virtually everything possible to help them and cooperate.
Oi The entire crew from the BBC vere extremely' impressed. The
- reports.r and senior cameraman joined to say they had covered nuclear powet; accidents and operations all over the world and they felt our cooperation, openness!and general consideration were the finest they had ever seen. The cameraman added that he had been in at least two dozen nuc1sar stations worirl-wide and that North 1tma was the cleanest, n.3atest and most attractive he had ever setn.
I passed' 'o n these comments to Wayne Harrell at the time.
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Jim McLonald I
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(804) 771-6725 FOR DOGDIATE RELEASE July 15, 1967 Release No. 1 8;00 a.m.
VIRGntIA Po1GR DECLARES ALERT AT NORTH ' ANNA Virginia Power today declared an alert at its North Anna Power Station at 6:54 a.m. .
The alert was declared because the statione unit I reactor cooling system was experiencing a primary to secondary system leak in the "ca steam generator. Unit I was shut down by station personnel and is being cooled down. There appears to have been no significant release of radioactive matarial to the at=csphere. .
Virginia Pcwor has established a special phone number to provide information regarding the alert. Collect calls will ta accepted at 7J11s number. The number is (804) 771-6725.
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5 All further public statements will be issued from the Public News center at one James River Plaza, Richmond, Va. The Public News Center is located in the auditorium of One James River Plaza, corner of 8th and Cary atreets, Richmond.
Virginia Power also is setablishing a Local Media center '
at Mineral Volunteer Fire Department, Mineral, Va. However, all official company statements regarding ,the emergency will be provided at the Puislic News center in Richmond.
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'or /mmediate Release (804) 771-6725 owimmearowupr gg, FOR IMMEDIATE RELEASE July 15, 1987 Release No. 2 9:00 a.m.
AIZET STATUS CONTINUES AT NORTH ANNA POWER STATION Virginia Power reporhs that the alare status declared earlier today continues at its North Anna Power Station.
The alert, was declared because the station's unit i reactor cooling systa= was experiencing a pri=ary to secondary system leak in the "C" steam generator. Unit 1 was shut down by station personnel and is being cooled down. This shutdown was followed by an automatic initiation of the anfaty injection
, system, which injects cooling water into the reactor cooling systos. The pri=ary system leak was isolated and station shutdown continued. The unit should be in cold shutdcwn by 11:00 a.m.
A small amount of radioactive gas was released to the atmosphere through the secondary syste= air ejector. Initial indications are that the release continued for about an hour and a half and was well belcw the station's technical specification limits. No station employees were injured, and the amount of
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i t i radioactive gas released poses no threat to the health er l
safety of the-public or empicysas. l j
Virginia Power has established a special phone number to provide infor=ation regarding the alert. collect calls /ill be accepted at this number. The number is (904) 771-6725. ,
I All further public statements will be issued from the Public News Center at one James River Plaza, Rich =ond, Va. The Public News canter is located in the auditorium of Ona Jares j River Plaza, corner of ath and Cary streets, Richr.cnd.
Virginia Power also is establishing a Local Media Center at Mineral volunteer Fira Departmant, Mineral, Va. However, all official company statements regarding the amargency will be providad at the Public News Center in Richmond.
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For immediate Release O
mm Contacte (804) 771 4 725 July 15. 1987 gdd For Imr.adiate Release a
g[-
1 Release No. 3 11:20 a.m.
ALERT ST.ATUS CONTLWES AT NORTE ANNA AS C00LDOW CONTL'UES The alset status declared at North Anna Pcver Station's Unit I concinced this e.orning as the uutt headed covard cold abutdown da a routima 4 l
O. manner.
The alert was called because of a primary to secondary system leak in one of the unit's three atsam generators.
An extre=aly small release of radioactivity occurred during the incident, but it was less than two percent of the allowable limits set by the NEC and posed no threat to the safety or health of station employees or the public.
The total release, which occurred over about an hour and a half, was less than the amount of one chest x-ray and was undetectable above normal backgrcued radiation levela at the boundary of the plant.
The event at Unit 1 occurred at 6:36 a.m. and at 6:39 a.m. the levant level of emargency status, an unuousi event, was declared. The next level, an alert, was declared at 6:54 a.m.
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' Cold shut down of Unit 1 ' is expected .to be achieved. later this-afternoon. .
In addition to on-site' NRC persoenal, a team from the frRC fe expected.
to ' reach. the plant in early af ternoon. .
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Contact (804) 771-6725 i
i For immediate Release July 15, 1987 Release No. 4 2:00 p.m.
ALERT ENDED AT NORTH ANNA POWER STATION Virginia' Power officiale announced the and of the alert status at North Anna Power Station er 1:36 p.m. today.
The alert, which was Ceclared at 6:54 a.m. today, was terminated af ter Unit I was brought to a cold shutdown (cold shutdown means the prt=ary system coolant was less than 200 degrees Fahranheit). Cold shutdown had t'een project-ed to occur by about 11 a.m., but the rate of cooldern was intentionally slowed ,
1 as plant conditions quickly improved. l 1
The extree.ely s=all amount of radiation released from one of Unit l's i three oceam generators was avsn less than originally calculated.
An initial calculation of the amount of radioactive gas released indi-cated a level of less than 2 percent of tha . amount allowed by the U.S. Nuclear j Regulatory commission-an ameunt less than a chest x-ray and undetectable at the, plant's boundaries.
Such a small amount is difficult to monitor and calculate with perfect accuracy, but additional, more precise calculations shew that the level was less than I percent of the allowable limit-an amount equivelant to what would be received on a roundtrip flight across the country.
)
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O One radiation monitor on the air ejector pipe was found to be inoperative during the event. If it had been operattug, it would have detected the small amounts of radfacion that were released but the levels were sufficiently low that it would not have teolated the ralsase.
No injuries occurred, and thera was no threat to the health or safety of station employees or the public. ,
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5ECTION 9' O l July 15, 1987 1 I
Mr. Addison E. Slayton State Coordinator .;
l State Department of Emergency Services l 310 Turner Road l Richmond, Virginia 23225-6491 I
Dear Mr. Slayton:
SUtei&RY OF " ALE 2T" PMFRCENCY I NORTS AIGIA POWER STATION )
UNIT 1 "C" STEAlf GENERATOR TUBE RUPTmtE I O Enclosed is a copy of the Summary Report of the " Alert" emergency which I
j occurred at North Anna Power Station on July 15, 1987. .
Very truly yours.
W. L. Stewart Enclosure I l
cc: Mr. M. M. Cline Mr. G. O'N. Urquhart 1
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NORTH ANNA POWER STATION I
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SUMMARY
REPORT:
ALERT Initiated: July 15, 1987 at 6:54 a.m.
Terminated: July 15, 1987 at 1:36 p.m. 3 EVENT:
Unit No. 1 "C" Steam Generator Tube Rupture DESCRIPTION OF EVENT:
At approximately 6:35 a.m. on July 15, 1987, North Anna Unit 1 was manually tripped from. 100% power due to indications of a steam generator tube rupture in the "C" steam generator. Approximately twenty seconds later, the safety injection system automatically initiated due to lov Reactor Coolant System (RCS) pressure.
At 6:39 a.m., a " Notification of Unusual Event" was declared in accordance with EPIP-1.01, Tab "B", Item 7, after indications of the tube rupture
/N (primary to secondary leakage exceeding one gallon per minute) were evaluated h by control room personnel. Initial notifications to offsite authorities were completed by 6:51 a.m.
By 6:54 a.m., the event was upgraded to an " Alert" classification at the direction of the Station Emergency Manager, and in accordance with EPIP-1.01, Tab "B", Item 8, " Gross Primary to Secondary leakage". Notifications to offsite authorities that were required as a result of the escalated classification were completed by 7:02 a.m.
i Plant response to the event progressed as expected. "C" Steam Generator was j completely isolated at 6:54 a.m. All major plant equipment functioned l properly and the unit was stabilized in accordance with Station Emergency l Procedures. In addition, Emergency Plan Implementing Procedures respective to an " Alert" classification were implemented to augment the onshift emergency response staff. By 7:28 a.m., an accountability of all station personnel had ,
been conducted.
At 7:57 a.m., both the Technical Support Center and Operational Support Center were fully manned and activated. At 9:15 a.m., the Local Emergency Operations )'
Facility was fully manned and activated.
Cooldown and depressurization of the RCS was initiated in accordance with Station Emergency Procedures and proceeded routinely throughout the event. At 11:09 a.m., the RCS vas cooled down to below 350 degrees F. and Unit I was placed in Mode 4 Hot Shutdown. At 1:33 p.m., the RCS was cooled down to less than 200 degrees F. and the unit was placed in Mode 5, Cold Shutdown. Plant pJ b
conditions were stable and the emergency was terminated at 1:36 p.m., at which time termination notifications were made to offsite authorities.
During the course of the event, effluents released from "C" Steam Generator prior to its isolation occurred through the Condenser Air Ejector and m .m
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Auxiliary Feedwater Pump Turbine exhaust. However, the release was determined to be very small. Isotopic analyses performed on samples drawn from these pathways are as follows: Contribution from Condenser Air Ej ector gaseous activity was 0.44% Technical Specification limits and Iodine activity was less than detectable. Contribution from the Auxiliary Feedwater Pump Turbine was 0.175: Technical Specification limits, for a total release of 0.62% Technical Specification limits.
Unit I will remain shutdown until the problem is evaluated and corrected. No further correspondence concerning this event is anticipated.
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COMMONWEALTH of VIRGINIA A E SLAYTON JR N('lHil'!iHCll{ t ll hillCINt'llt y SClY ('CS TCWeC '
swecwmnw n- , ' va u. b a xemnrem, September 8, 1987 " " * "
oenov cmmme Mr. F. M. Cox Supervisor of Corporate Emergency Planning Virginia Power P. O. Box 26666 Richmond, Virginia 23261
Dear Francis:
RE: Steam Generator Tube Rupture Accident, North Anna Power Station (NAPS),
July 15, 1987 As you know, as a result of the referenced incident, the Departments of Emergency Services (DES), Health (Bureau of Radiological Health), and Waste Management became actively involved in this emergency and implemented their radiological emergency response plans in accordance with accepted procedures.
O Also, NAPS area local governments--Caroline, Hanover, Louisa, Orange, and Spotsylvania Counties--responded to this radiological incident by alerting direction and control officials, key service chiefs, and in two instances, activating local emergency operations centers. A DES report which outlines the various levels of response is enclosed.
For months prior to this incident, Virginia Power and this agency had planned to conduct an annual full-scale on-site exercise and a limited participa-tion (small-scale) off-site exercise on August 4, 1987. The off-site exercise was to be known by the acronym, V0PEX 1-87, and involve four State agencies (DES, Health, Virginia State Police [ VSP}, and Waste Management). VSP would be on standby to provide backup to local law enforcement units. The Exercise objectives are noted on Enclosure 2.
NAPS area local governments and the State agencies exercised and achieved V0PEX 1-87 objectives. It is generally believed that the actual event was of more value to us for training purposes than the simulated accident would have been.
We provided copies of the radiological emergency report (July 15, 1987) to the Federal Emergency Management Agency for its information. V0PEX 1-87 was not scheduled to be graded by FEMA. I hope you will provide a copy of this correspondence and enclosures to the U.S. Nuclear Regulatory Commission for its assessment of our joint capabilities to respond to a radiological emergency at the North Anna Power Station. We support Virginia Power's request for the July 15, 1987, steam generator tube rupture event to be accepted as e
satisfying the North Anna 1987 Emergency Plan Exercise requirement. j
(% Sincy > ,
/ /
eo g' Urquhart l Cl ef, Radiological Emergency J Response Planning Branch !
GOU/nas Enchauueas -
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o % 29 1 COMMONWEALTH of V1RGINIA 1
, , , tam ,
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Deparonent of Dueryncy Senicer _,gsgy
- soo m reos -
l e n. x July 15, 1987 oon, cm 3 4
M__ EMORANDLH i
To: The Hencrable vivian* E. Watts, secretary j Department of Transportation & Public Safety i FROM: A. E. Slayton, Jr. ,
SUBJECT:
Nuclear Power ion - Uni 1
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l Steam Generat a Ruptur J y 15, 1987 j Radiological Emergency -
A report on the subject accident is attached.
O additional details and reports to you on this accident as may ha I will provide V required.
I will be available at your request to discuss this incident. f i
AES/GOU/sdg j i
cc: N C1ine l M. La civita l
'Eb'e st h59 99 h B' U Db , ,,
i Department of Emergency Services ',
Emergency Response Report Subjects North Anna Pcvar_ Station - Unit 1 Steam Generatcr Tube Rupture - July 15, 1987
. Radiological Emergency
. ALERT STATUS ACHIEVED Date of Report: July 15, 1987 J The North Anna Power Station experienced a primary to secondary system leak in its unit I reactor today which was ,
declared as an Unusual Event at 6:39.a.m. The accident was I upgraded to an Alert at 6:54 a.m. when a small amount of l radioactive gas.was released to tha' atmosphere. There were no J injuries to on-site employees and no sheltering, evacuation or ]
ether protective measures were, required or taken in the local i governments near the power station. The amount of radioactive gas released posed no threat to the health or safety of the public or employees. Unit 1 began commercial operation in June 1978.
The total release, which occurred over about an hour and a half, was medically less than the amount of one chest x-ray and was undetectable above normal background radiation levels at the boundary of the plant. The power plant was brought to a complete cold shutdevn at 1 33 p.m. with all plant systems functioning properly. The Alert -(and emergency) was ' officially terminated at 1:36 p.m. State emergency response operations returned to normal O at 3:00 p.m.
Details of Response:
- 1. The Department of Emergency Services (DES) maintains 24-hour operations in the State Emergency operations conter (EOC).
The radiological emergency at the North Anna Power Station (NAPS) was handled by operations staff in its routine operations mode with limited staff augmentation by DES Plans Divisicn and Public Information personnel. All operational proceduras were implemented in accordance with approved plans.
- a. A DES Cperations Liaiscn Officer was dispatched to NAPS during the Alert Emergency phase to coordinate the passage of plant status data nd provide supplemental information to the State ECC.
- b. Operations Division notified the Department of Health, Bureau of Radiological Health (BRH) at the Unusual Event class and followed up with notifications as appropriate.
BRH deployed its Radiological Emergency Response Team (RERT) to NAPS at the Alert class. The operation and missions of the BRH are described below.
- c. The DES Director of Public Information was dispatched to Virginia Power Corporata Headquarters, One James River Plaza, at approximately 9:30 a.m. to coordinate public 1
- 2. -- - - . ._m_. -__ ,_ ___m mu-_m m _ __ _ _ _ - _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ ma
- A news releases between Virginia Power (the utility) and O off-site--state and local government--operations. He was also available to the media at this location to explain state actions with regard to response and mitigative measures. The Assistant Public Information officer was stationed in the State IOC during the amargency to respond to citizens' inquires and rumors.-
- d. DES Communications Center in the IOC is manned on a 24-hour basis. Normally the Center is staffed by a minimum of two communicators. However, on the midnight _to 8:00 a.m.. shift, only one communicator works the Center.
Unfortunatdy, the radiological emergency occurred during this period but near the end of the shift. Had this incident occurred earlier in the night,. additional duty officers would have been: required to man the radio'and telephone consoles to handle this emergency and other on-going dispatch functions.
- 2. Department of Health-Bureau of Radiological Health Radiological Health initially deployed three of its radiation safety specialists and their director to North Anna Raergency Cperations Facility (EOF) . The mobile laboratory was depicyed ,
to the Mineral Fire Station and one Radiation safety Specialist and a Radiation Advisor were sent to Virginia ECC.
Additional staff members were deployed to North Anna area.
Radiological Health also requested assistance from the Department of Waste Management. Two of their staff were deployed as field monitors and another to EOF.-
From ECC, Department of Energy at Oak Ridge was placed on ~
standby alert. Latar, it was determined that their assistance was not needed; however, an invitation was extended to use the ,
cccasion for training purposes. They declined.
)
- 3. NAPS Area Local Governments l Caroline, Hanover, Louisa, Crange and spotsylvania Counties l are within the NAPS Ten-Mile Emergency Planning Zone.
Emergency services coordinators in these jurisdictions indicated that there were no significant problems with regard to their response to the emergency. Reports of emergency were timely and the jurisdictions were prepared to implament their plans in accordance with procedures.
- 4. Federal Agencias
- a. The Nuclear Regulatory Commission (NRC), Region II (Atlanta) office was notified of the emergency at North Anna by Virginia Power. A team was readied and deployed to NAPS during mid-scrning and arrived at the pcVer station around 2:30 p.m. The NRC will prepara a.n OsO inspection report and make copies available to this agency.
- b. The Federal Emergency Management Agency (FEMA) was notified of the emergency by DES operations. FEMA did not deploy a team to the commonwealth.
- 5. Preblemi Noted:
- a. In future emergencies, the State PIO should send a Public i Information Officer,to the near-site media center in '8 accordance with the State's Plan.
- b. A DES operated high-speed.telecopier is needed in the EOF f to provide timely transmission of pla.nt status reports and j other hard copy transmissions to the state Eoc. This unit ;
should be purchased and made available to the DES 1 operations Liaison.
- c. Two communications officers should be available in the 200 communications Center on all shifts.
The foregoing is a general description of the state's response to i the Steam Generator Tube Rupture accident which occurred on NAPS !
unit i reactor. There was a very small release of radioactive gas to the environment but was of no threat to health or safety of persens on- or off-site.
Additional details will be provided as may be required in g subsequent reports. !
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1 APPENDIX 3 I
VOPEX 1-87 EXERCISE OBJECTIVES In addition to the previously stated purposes of VOPEX l-87, the Exercise will have as its objectives, the testing and' evaluation l of the following elements of the plans:
- 1. Demonstrate the ability to. activate the Emergency Operations Facility (EOF) and State and local (simulated) EOCs in_a ;
timely manner. j
- 2. Demonstrate the adequacy of communication systems among and within emergency response organizations and between all designated facilities and field activities. 1
- 3. Demonstrate the adequacy of accident assessment- abilities of the State. '
i I 4. Demonstrate the ability to provide _ advance coordination of information released (simulated) to the general public.
- 5. Demonstrate that internal message and information flow (collection, consolidation and dissemination) in the EOF /EOCs j ensures coordination with all affected agency representatives. .{
- 6. Demonstrate the ability of the EOF /EOC to direct- field ' teams 'l to perform plume monitoring and sampling.
- 7. Demonstrate the ability of the EOF to transmit data and protective action recommendations to the State EOC.
- 8. Demonstrate that response organizations can alert and notify emergency response personnel in a timely fashion.
- 9. Demonstrate the existence and adequacy. of appropriate 1'
emergency facilities and equipment to support the emergency-response.
The objectives and the primary focus for this exercise will center on communications and coordination of State and local response-activities.
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~ COMMONWEALTH of V1RGJNIA s= = coo,= = e<
oenarimcnr 4 emersency sen* es _ga:tsem2ees >
l
% n. x July 15, 1987 o,p, cane w ,
1 MEMORANDUM i
TO: The Honorabis Vivian E. Watts, Secretary }
Department of Transportation & Public Safety j FROM: A. E. Slayton, Jr. ,
SUILTECT: Nuclear Power ion - Uni 1
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l Steam Generat e Ruptur J y 15, 1987 -!
Radiological Emergency j A report on the subject accident is attached. I will provide
[
additional details and reports to you on this accident as may ha required.
I will be available at your request to discuss this incident.
AES/GOU/sdg ec: M. Cline M. La civita i
1 0 -
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f Department of Emergency Services Emergency Response Report O subject: North Anna Power Station - Unit 1 Steam Generator Tube Rupture - July 15, 1987 Radiological Emergency 1
. ALERT STATUS ACHIEVED Date of Report: July 15, 1987 i
The North Anna Power Station experienced a primary to l secondary system leak in its unit I reactor today which was i declared as an Unusual Event at 6:39 a.m. The accident was ,
upgraded to an Alert at 6:54 a.m. when a .small amount of !
radioactive gas was released to the atmosphere. There were no injuries to on-site employees and no sheltering, evacuation or other protective measures were required or takan in the local governments near the power station. The amount of radioactive gas released posed no threat to the health or safety of the public or employees. Unit 1 began commercial operation in June 1978.
The total release, which occurred over about an hour and a half, was medically 1ssa than the amount of one chest x-ray and ;
was undetectable above normal background radiation levels at the -
boundary of the plant. The power plant was brought to a complete cold shutdown at 1:33 p.m. with all plant systems functioning properly. The Alert (and emergency was officially terminated at 1:36 p.m. State emergency response) operations returned to normal at 3:00 p.m. ,
L Details of Response:
- 1. The Department of Emergency Services (DES) maintains 24-hour operations in the State Emergency Operations center (EOC) .
The radiological emergency at the North Anna Power Station (NAPS) was handled by Operations staff in its routine operations mode with limited staff augmentation by DES Plans l Division and Public Information personnel. All operational 1 procedures were implemented in accordance with approved plans. !
q
- a. A DES Operations Liaisen Officer was dispatched to NAPS i
during the Alert Emergency phase to coordinate the passage of plant status data and provide supplemental information to the State ECC.
l
- b. Operations Division notified the Department of Hesith, Bureau of Radiological Health (BRH) at the Unusual Event class and followed up with notifications as appropriate.
BRH deployed its Radiological Emergency Response Team (RERT) to NAPS at the Alert class. The operation and missions of the BRH are described below.
- c. The DES Director of public Information was dispatched to Virginia power Corporate Headquarters, One James River Plaza, at approximately 9:30 a.m. to coordinate public
news releases between Virginia Power (the utility) and' off-site--state and local government--operations. He was
/7 also,available'to the media at this location to explain
() state actions with regard to response and mitigative measures. The Assistant Public Information officer was stationed in the State IOC during the emergency to respond to citizens' inquires and rumors.
- d. DES Communications Center-in the EOC is manned on a 24-hour basis. Normally the Contar is staffed by a minimum of two communicators. However, on the midnight to 8:00 a.m. shift, cnly one communicator works the_ Center.
Unfortunately, the radiological emergency occurred during this period but near the end of the shift. . Mad this incident occurred earlier in the night, additional duty officers would have been required to man the radio and telephone consoles to handle this emergency and other on-going dispatch functions.
- 2. Department of Health-Bureau of Radiological Health Radiological Health initially deployed three of its radiation safety specialists and their director to North Anna Raergency operations Facility (EOF) . The mobile laboratory was deployed to the Mineral Fire Station and one Radiation Safety Specialist and a Radiation Advisor were sent to Virginia ECC.
Additional staff members were deployed to North Anna area.
O Radiological Health also requested assistance frca the Department of Waste Management. Two of their staff were deployed as field monitors and another to EOF.
From EOC, Department of Energy at Oak Ridge was placed on standby alert. Iater, it was dotarmined that their assistance was not needed; however, an invitation was extended to use the occasion for training purposes. They declined.
- 3. NAPS Area Local Governments Caroline, Hanover, Louisa, Crange and Spotsylvania Counties are within the NAPS Ten-Mile Emergency Planning Zene.
Emergency Services Coordinators in these jurisdictions indicated that there were no significant problems with regard to their response to the emergency. Reports of emergency were timely and the jurisdictions were prepared to implement their plans in accordance with procedures.
- 4. Federal Agencies
- a. The Nuclear Regulatory Ccamission (NRC), Region II (Atlanta) office was notified of the emergency at North Anna by Virginia Power. A team was readied and deployed to NAPS during mid-morning and arrived at the pcVer station around 2 30 p.m. The NRC will prepare an inspection report and make copies available to this 1.O agency.
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- b. The Federal Emergency Management Agency (FIMA) was notified of the emergency by DES Operations. FEMA did not {
deploy a team to the commonwealth.
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- 5. Probler.s.Noteds ]
1
- a. In future emergencies, the State PIO should send a Public d Information Officer.to the near-site media center in I accordance with the State's Plan, j
- b. A DES operated high-speed telecopier is needed in the EOF to provide timely transmission of plant status reports and other hard copy transmissions to the State IOC. This unit should be purchased and made available to the DES operations Liaison.
- c. Two communications officers should be available in the Eoc coz:munications Center on all shifts.
The foregoing is a general description of the state's response to the Steam Generator Tube Rupture accident which occurred on NAPS 1 unit i reactor. There was a very small release of radioactive gas to the environment but was of no threat to health or safety of persons on- or off-site.
)
Additional details will be provided as may be required in
(~ subsequent reports.
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SECTION 10 OVERVIEW OF LOUISA COUNTY RESPONSE NOTE: This infomation was collected through an interview with Mrs. Tiny Manrique, Deputy Emergency Services Coordinator for Louisa County, and contains excerpts of logs maintained by both the Sheriff's Office and County EOC during the July 15, 1987 SGTR event at North Anna.
- 1. OVERVIEW OF SHERIFF'S OFFICE LOG:
TIME EVENT _
0640 -Received initial report of emergency.
0653 -Confirmed emergency via NAPS communicator.
0718 -Completed notification of County emergency response personnel. ;
-Received emergency message, j 0805 -Received emergency message; communications now from TSC. '
0823 -Received emergency message.
0835 -Off1ce of Emergency Services opened.
0909 -Received message that today's siren test is cancelled.
0913 -Received emergency message.
0935 -Understand LEOF activated.
O 1009 1043
-Received emergency message (also being taken in EOC).
-Received emergency message.
1103 -Received emergency message.
1148 -Received emergency message.
1217 -Received emergency message.
1235 -Received emergency message.
1326 -Received emergency message.
1336 -Received emergency message, " Alert" terminated.
1344 -Termination of EOC.
- 2. OVERVIEW OF EOC LOG I
TIME EVENT 0830 -County EOC activated. !
0905 -Briefing with State EOC. Highway Department personnel standing by with barricades.
0910 -Siren test cancelled !
0913 -Received emergency message. !
0914 -Delegate Earl Dickenson called. Some people in area are i evacuating themselves.
0935 -Received emergency message.
1009 -Received emergency message. j 1017 -Sheriff's department notified that Channel 6 reported information about a " cloud hanging" in area.
. . , , - - - ......... . . ~ . . . . ._.. . .. . . . .
's 1018 -County Administrator telephoned State for news verification.
1025 -Richmond returned call. Provided information from first and second press release.
1043 -Received emergency message. .
1045 -Radiological officer arrived at EOC and was briefed.
1050 -Dispatched monitoring team around Rt. 700 and 652.
1054 -County Administrator telephoned State PIO of call form Fluvanna County saying that Channel 8 reported an evacuation of 15 mile j radius of plant. . , l 1115 -Received emergency message. )
1148 -Received emergency message, l 1220 -Received emergency messagc. !
1231 -Radiological Officer reports only background readings to EOC. )
1252 -Received emergency message. ]
1326 -Received emergency message. j 1336 -Received emergency message, " Alert" terminated. j 1345 -EOC deactivated. ]
- 3. Comments from Deputy Emergency Services Coordinator:
The Deputy Emergency Services Coordinator for Louisa County indicated that she could not think of any deficiencies (on the part of Virginia Power) that occurred during the event. She felt that communications from I
,m North Anna were adequate and that the EOC was kept well informed of the
( event. Furthermore, she stated that, for the most part, utility and
[
b county response was excellent-.
A minor problem existed at the onset of the event. A new dispatcher was present in the office who was unfamiliar with response procedures; ,
however, this was quickly rectified.
A review of the EOC log, though, indicated that portions of the media's coverage of the event should be investigated further (i.e. report of a 15 mile radius evacuation).
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l SECTION 11 r 4 OVERVIEW OF SPorSTLVANIA COUNTY RESPONS'E l
1 NOTE: This information was collected through an interview with j Mr. Harry Lewis, Emergency Services Coordinator for Spotsylvania l County.
Initial notification of the emergency at North Anna was received by the Public Safety Dispatcher. (Sheriff's Office) at 0649. hours. By 9746 hours0.113 days <br />2.707 hours <br />0.0161 weeks <br />0.00371 months <br />, all 4 l key emergency response' personnel were notified to standby for possible )
implementation of the Spotsylvania County Radiological Emergency Response- I Plan. Only four individuals were unavailable (see attached). I Local media representatives were contacted at approximatively 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> j and given information for release to citizens residing in the area. Mr. Lewis- 1 I
pointed out that in his opinion, the media did a good job of accurately reporting events to the public. In other words, the media reported statements that he had provided to them for release "almost verbatim".
The Emergency Operations Center was partially manned during the " Alert".
The Evacuation Assembly Center could have been operational in approximately !
two (2) hours from initial notification of incoming evacuees, had it been I necessary.
O. The termination message was received from North Anna at 1343. hours and all county participants were not'ified to " stand down'? by -1430 hours. It should be j noted that Mr. Lewis found notifications from North Anna were satisfactory I (including content and frequency), and even ventured to say that both Spotsylvania County's and Virginia, Power's response to this event were far superior to exercises that he had participated in over the past few years.
One item of concern to Mr. Lewis was a lack'of mobile communications equipment. There was no way for him to maintain contact with the dispatcher while in route to the EOC from his home. He has already addressed this issue through a letter to the State Department of Emergency Services.
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( ) i SPOTSYLVANIA COUNTY CALLOUT
/ JULY 15, 1987 SGTR EVENT ,
I
- 1. Sheriff Waddy '
- 2. R. McDaniel
- 3. J.dinston I
- 4. R. Chenault
- 5. H. Lewis
- 6. N. Brooks '
- 7. T. Osterheld
- 8. D. Boggs '
- 9. A. Landers 'j l
- 10. M. Arritt
- 11. State Police l
\
- 12. L. Branner {
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- 13. Dr. Mundy I 4
- 14. Mrs. Leslie
- 15. C. Cousins
- 16. S. Ennis l
17 W. Compton l
- 18. K. Payne j l
19 W. Sacra
- 20. D. Moody *
- 21. J.
- 22. F. Hans (lete message)
- 23. L. Lemoine (left message) 24 D. Kurtch (left message) v s
s . . . . .,. - - . . ~ . . . . - . - ~ + ,. . .
-._-___-_________m. __________-_.-__-____.____
SECTION 12 i a ,
pVERVIEW0FEMERGENCYRESPONSEACTIVITIES I
Staffing ud Responsibility (NUREG 0654,Section II.A. and B.) I Specific assignments to the e.mergency organization were made in accordance I with the Station Emergency Plan and were adequate to respond to the event. l Timely activation, staffing, and operation of Emergency Response Facilities was I accomplished. ,
Emergency Response Support and Resources (NUREG 0654,Section II.C.)
Support resour'esc (i.e. Westinghouse, OMNI, MODCOMP, etc) were requested and effectively used during the event. State resources that participated at 1 I
the LEOF were cadequately accommodated. In general response agencies i demonstrated their ability to augment the Station response.
Emergency Classification (NUREG 0654,Section II.D.)
I'he emergency classification and action level scheme, as provided in the Emergency Plan and Implementing Procedures, was adequate for the classification of the event. Emergency Plan Implementating Procedures adequately provided for
(],
initial and continuing assessment and response actions during the emergency.
NotificationMethodsandProcedures (NUREG 0654,Section II.E. and F.)
Procedures established for notification of Federal, State and local response organizations and emergency personnel were promptly and effectively implemented. Content of initial and followup messages was adequate and consistent with the requirements of the Emergency Plan. Furthermore, provisions in place to alert Virginia Power's augmented emergency response organization were executed and found to be effective.
l Notification of NRC was initiated at 0702 hours0.00813 days <br />0.195 hours <br />0.00116 weeks <br />2.67111e-4 months <br /> and continuously maintained to termination of the event.
State / local notifications were accomplisited as follows:
l MESSAGE # TIME l 1 0651 2 0702 '
3 0718 4 0745 5 0805 6 0828 7 0846 n)
(
8 9
0913 0935 10 1009 11 1043
12 1115
.O 13 14 1148 1220 15 1252-16 1326 17 1343 Station call-out was initiated at 0655 hours0.00758 days <br />0.182 hours <br />0.00108 weeks <br />2.492275e-4 months <br />.
Corporate call-out was initiated at 0710 hours0.00822 days <br />0.197 hours <br />0.00117 weeks <br />2.70155e-4 months <br />.
Station accountability was initiated at 0655 hours0.00758 days <br />0.182 hours <br />0.00108 weeks <br />2.492275e-4 months <br /> and completed at 0728 hours0.00843 days <br />0.202 hours <br />0.0012 weeks <br />2.77004e-4 months <br />.
Emergency Communications (NUREG 0654,Section II.F.)
Communications between emergency facilities, principal response organizations and emergency personnel were promptly established and continuously maintained throughout the event. Necessary equipment and procedures were in place in order to provide adequate communications. No significant equipment malfunctions occurred. However, there were some problems with the audioconferencing and speaker systems at the Local Media Center. This was not prohibitive during the event, and corrective action has been initiated.
Media and Public Information (NUREG 0654,Section II.G.).
Information concerning the emergency was made available to the media' for dissemination to the public. Four press releases were issued during the event (at0800,0900, 1100, and 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> respectively). In addition, press briefings were conducted at the Corporate Public News Center (CPNC) and Local Media Center (LMC) throughout the day. The above facilities were activated at 0830 and 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, respectively.
Following termination of the event, the media was brought from the LMC to the station for an indepth briefing and plant tour.
Emergency Facilities and Equipment (NUREG0654,SectionII.H.)
Emergency facilities were activated and promptly staffed during the event, and the facilities were adequately equipped to support the response effort.
The activation times for the Emergency Response facilities are provided below.
Technical Support Center - 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br /> Operational Support Center - 0753 hours0.00872 days <br />0.209 hours <br />0.00125 weeks <br />2.865165e-4 months <br /> Local Emergency Operations Facility - 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> Corporate Emergency Response Center - 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br /> Corporate Public News Center 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> Local Media Center - 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> It should be noted that the Technical Support Center (TSC) was fully manned prior to 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br />. However, the Station Emergency Manager did not relocate from the Control Room to the TSC until 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br />, and therefore, the TSC was.
not " officially" activated until that time.
f Accident A M sment (NUREG 0654,Section II.I. and K.)
(
Methods, systemse a5d equipment for assessing and monitoring actual 'onsite consequences of the event were adequate. Assessment and response activities included both an engfreering assessment of plant status and an assessment of radiological hazards. .Inplant:. onsite and offsite monitoring teams were promptly dispatched and effecti vely used throughzt the event.
Recovery Planning (NUREG 0654,Section II.M.)
Prior to *mnination of the event, a Recovery Organization was formulated.
This team wa,. tasked with developing sperific , plans and procadures for recovery. The iecovery Organization was established under the directiqn ,of the Vice President - Nuclear Operstions Department. 'The organization created a
" command ' wnter" in the LE0F, established a long-term interface arrangement with the NRC and State, and formulated the following support structure:
- 1. Maintenance and Repair Team
- 2. Technical Evaluation Team >
- 3. Nuclear Safe (v and Licensing Team
- 4. Industry Interface Tcam
] i
- 5. Health Physics Taam The recovery organization was implemented upon termination of the event.
Summary The July 15, 19F/ SGTR event demonstrated that emergency response personnel within the Virginia Power organization are capable of sati';factorily responding to an emergency of this nature. Furthermore, the NRC and emergency organizations within the State of Virginia demonstrated thm capability to respond to requests for essistance during such an cm rgency. In conclusion, the North. Anna Power Station and those emergency resiensk agancies that support it effectively mitigated the transient ' event ar.d adeq'uately protected the health and safety of the public.
I i
1
, 4
SECTION 13 U(~N EMERGENCY PLANNING
{
CORRECTIVE ACTIONS AND AREAS FOR ENHANCEMENT l t
Exercises of the Emergency Plan, by their very nature, provide only a limited view of the effectiveness of planned responses to events. This is )
because necessary simulation often masks real response. Although the a circumstances of the SGTR event on July 15, 1987 were unfortunate, it provided i a unique opportunity to see how the North Anna Emergency Plan (NAEP) works '
under actual conditions. This report discusses elements of the Plan's execution that require corrective action or enhancement.
- 1. Technical Support Center Radiation Monitor i l
The Eberline radiation monitor in the Technical Support Center was not activated in a timely manner due to equipment deficiencies and personnel being unfamiliar with the monitor, 1 d
- a. The equipment deficiencies (i.e. alarm setpoints were improper and 4
channel 7 does not check / source) will be corrected. i
- b. Health physics personnel who may be assigned responsibility for activating the motitor in the Technical Support Center will be trained to activate the monitor.
1 .m I l 2. Health Physics Network Telephone V
i Communication of health physics information to NRC using the HPN j j
telephone in the Technical Support Center was delayed due to health physics personnel urdamilicrity with their duties and the fact that ;
the telephone was being used by the NRC for communication of plant I status information. Health Physics personnel will be trained in the proper use of the HPN phone. !
- 3. Emergency Meteorological and Dose Assessment Model The health physics personnel in the Technical Support Center were unable to utilize the Emergency Meteorological and Dose Assessment ;
Model on the Emergency Response Facility Computer System due to i unfamiliarity with the computer system and model. Dose assessments j were performed by manual means in accordance with the Emergency Plan l Implementing Procedures. The training program for health physics personnel on the use of the computer system and model will be reviewed and updated to address this problem, and personnel will be trained in the use of the model.
- 4. Event Chronology Reconstruction Notes taken by log keepers were sketchy in some cases, making it difficult to reconstruct events and decisions. The problem of keeping p logs during the emergency will be evaluated and enhancements d recommended.
1
)
- 5. Emergency Response Computer System f~^
( The Emergency Response Computer System performed very well during the event. The system was used by each of the response facilities to assess the changing conditions of the unit and helped to minimize the j manual transfer of information between locations. Some deficiencies ;
in the system were noted including a few data points that did not !
correspond to actual conditions and some inappropriate alarm !
setpoints. Further, it was recognized during the event that use of the system could be improved by dedicating personnel in each facility to operate the system and facilitate data retrieval from the system. l 1
- a. Provisions for dedicated personnel to operate the system in the LEOF and CERC will be incorporated into the appropriate emergency response procedures, and the personnel will be provided specialized training on the system and their role in the emergency response organization.
- b. The deficiencies noted in the system will be corrected.
- 6. Health Physics Assessment of Release Paths )
During the initial phases of the event prior to activation of the Technical Support Center, the Health Physics personnel in the Control i Room experienced difficulties in identifying radiological release paths and reading meteorological panel instruments. This necessitated )
assignment of an unlicensed control room operator to assist in
\ obtaining the required meteorological information and some additional interaction with the Operations staff to identify release paths.
a.
Training of the Health Physics Shift Supervisors on the possible release paths and the meteorological and radiation monitoring instrumentation in the control room will be evaluated and upgraded as deemed necessary.
t
- b. Emergency Plan Implementing Procedure 4.01 will be reviewed and possibly revised to include additional guidance on release paths and system alignments.
i
- 7. Emergency Response Facility Status Boards !
Differences between the ERF status boards and radiological and '
emergency status sheets contained in the Emergency Plan Implementing Procedures were noted during the event. The status boards will be updated as necessary.
- 8. Communication between Operations and Health Physics Departments The initial contacts with the Health Physics personnel to request i samples, and following the Safety Injection actuation to direct' entry into the EPIPs, were given quickly and without explanation due to the rapidity of events occurring. This led to a misunderstanding of conditions and delayed responses by the Health Physics personnel. In Q order to prevent recurrence of this situation, the Operator Training Program will be amended to include participation by the Health Physics l Shift Supervisors during simulator training. The simulated initiation i
of the Emergency Plan and the communications between Operations and
, Health Physics will be stressed during this training.
- 9. Public Affairs
- a. At the Local Media Center, absence of Security personnel made adequate control of media representatives difficult. Also, microphones on the autoconferencing system were inoperable and noise on the speaker system made it difficult for reporters to hear messages transmitted from the CPNC. A Telecommunications representative would have been able to correct these problems.
Therefore, the next revision of the Corporate Emergency Response Plan will include provisions for Security and Telecommunications personnel at the Local Media Center. Also, completion of the new Multi-functional Media Center should resolve this problem.
- b. Channel 8 news apparently reported that a 15-mile radius area around the plant was being evacuated. This should be investigated further, and cons!.deration should be given..'to closely monitor network broticacts for the purpose of quickly identifying and correcting misinformation.
- 10. Security
- a. During callout, it was determined .that three (3) telephone numbers were incorrect on the Emergency Personnel Notification List. Obtaining the correct numbers added some time to the
( callout process. The correct telephone numbers have been obtained and the notification list is in the process of being revised.
- b. EPIP-3.01 should be revised to more accurately reflect callout using the Emergency Personnel Notification List. Some position titles have changed and this should be reflected in the EPIP. It should be noted thet this did not significantly hinder the callout procese.
o !
i
)
i SECTION 14 t v
a ;
l i
l I
i MISCELLANEOUS LOGS: (ATTACHED) I l
PLANT STATUS j EMERGENCT STATUS RADIOLOGICAL STATUS l
i J
l i
l l
1 I
l j
06 6 PLANT STATUS, NORTH ' ANNA POWER STATION gy;7 REACTOR POWER O %
PRIMARY SYSTEM REACTOR COOLANT SYS, TEM (T = Temperature)- HOTTEST TH907 F HOTTEST TC T F LOOP"! AT C) F LOOP *2 AT. A
~
F LOOP '3 AT- C F PPESSURE ~~) 1 ( PSIG ' PRESSURIZER LEVEL T3 %
REACTOR C00LAN PUMP PRT LEVEL 1] %
A: A. R 00C g, A, R. OC C: A. 00C COREPARAMETEd CORE EXIT THERMOCOUPLE Nkb F MARGIN TO SATURATION Ch A - T F Ch B - O F SOURCE RANGE COUNTS N 31 - l.60 N 32 - /IN '
INTERMEDIATE RANGf AMPS N 35 -
h 4 N0' N 36 - 8gd RVLIS HO/d I h) me kaNA %
CONTAINMENT 9L N TEMP. % oF
_ PRESS. , PSIA SUMP LEVEL */-
CONT. ISOLATION PHASE I. II. III: ~
HYDROGEN O %
SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
AUX. FEEDWATER AUX. FEED FLOW O (GPM) CN-TK-!/2 LEVELh Y %
, 3A: A. h 00C 38: Q R. 00C FW-P-2 % R. 00C ENGINEERED SAFEGbRDS - RWST N % SIFLOW .
(GPM)
HHSI Ash R. 00C 8:@ R. 00C Ci ~ A.d 00C OSRS A: ( A.)R. 00C gg($ R. 00C LHSI A:M R. 00C 8: Q R. 00C ISRS As fd R, 00C BO) R. 00C OS Ar]'D R. 00C B:64, R, 00C _R__.00C RS-P-3A:
RS-P-3B: @((Q R. 00C RS-TK-!: 95( %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY)
H:@ DIESEL, DEAD, BACKFEED DEAD, BACKFEED EMERG CY DIESEL GENERATOR (EDG)
Jh DIESEL.
H: OP, VAI , OOC J: OP, ,00C RESER STATION SERVICE A: / DEAD B DEAD C: /0EAD ,
HIGH RANGE EFFLUENT RAD MONITORS VENT VENT AE 190CE55 rE-Ft- Co C.
%h MAHr~5Trt"T A 3 *.N 0 " c R " 8 9uot ce * -C ~2.7 o e' r.e w REMARKS '~l ~\ F M @30 LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRG - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Avetleble. R = Running. 00C = Out of Commission)
TDFEMERGY.OGN NAPS /:1 2-8-85
- ~. ., .. . . - . . .
D PLANT STATUS NORTH ANNA POWER -STATION - UNIT I O- REACTOR POWER'-
O- %)
PRIMARY SYSTEM -
REACTOR COOLANT SYSTEM (T ': Temperature) - HOTTEST TH 5N F HOTTEST TC 39 L F -
LOOPal AT o F LOOP "2 AT O F LOOP E3 AT O F l PRESSURE r, 4 7 PSIG PRESSURIZER LEVEL so , %
PRT LEVEL ~~~
'? / %
.l REACTOR COOLANT PUMP A:. A. (% 00C B: [% R,- 00C C: R. 00C !
CORE PARAMETERS CORE EXIT THERMOCOUPLE. '4 I 7.. o -
F MARGIN TO SATURATION Ch A - 9 (, F Ch 8 - % $' F' SOURCE RANGE COUNTS N 31 - N 32 -
INTERMEDIATE RANGE AMPS N 35 - N 36 -
RVLIS %
CONTAINMENT 9L TEMP. M oF PRESS. 9,$ PSIA SUMP LEVEL Y ., %
CONT. ISOLATION PHASE I. II III: HYDROGEN % .
SECONDARY SYSTEM STEAM GENERATOR (LEVEL)
A dV %B 3L % C N %
AUX. FEE 0 WATER ' AUX.' FEED FLOW (GPM) CN-TK-1/2 LEVEL Ff/9 S%
3A: A. t 00C 38: h R. 00C FW-P-2 h R.
OOC 1 ENGINEERED SAFECNROS - RWST
- A, R.~ 00C - B: $ R, 00C N % SIFLOW n ._
' (GPM) .
HHS! C: A,@ 0OC OSRS A: CM R. 00C BQD R. 00C_
'LHSI : A, R. 00C B: [A_) R. 00C ISR$ A: A - R. 00C 8: h R. 00C OS _A R. 00C B: W R. 00C RS-P-3A: Ch R. - 00C RS-P-3B: W R. 00C
~
ELECTRICAL DISTRIBUTION RS-TK-1: 9% %
EM RGENCY BUS (SUPPLY)
H RSS DIESEL, DEAD, BACKFEED J RSS DIESEL, DEAD, BACKFEED EMERG OIESEL GENERATOR (EDG)
H: OP. ,00C ,00C J: OP RESER STATION SERVICE A / DEAD B: (DEAD C /0EAD I HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT i MAIN STEAM A B- C REMARKS i
O LEGENO: HHS1 - HIGH HEAD S.I.
OSRS - OUTSIDE RECIRC. SPRAY ISRS - INSIDE RECIRC.' SPRAY I OS - OUENCH SPRAY RSS '- RESERVE STATION SERVICE (A = Avetleble, R = Runntng. 00C ' : Out of Commission)
TDFEMERGY.DGN NAPS /11 '2*B-85
. . . - , . - - . . . -, ....;.1 -
)
gOf0 PLANT STATUS p NORTH ANNA POWER STATION UNIT /~
%)
REACTOR POWER O '%
PRIMARY SYSTEM REACTOR COOLANT SYSTEM . (T = Temperature) - HOTTEST TH M9 F HOTTEST -TC'.PI, F' LOOP"1 oT c5 F LOOP "2 AT n F LOOP '3 AT~ O F PRESSURE (, y ~) & PSIG PRESSURIZER LEVEL 3f 6 % d PRT LEVEL % .
REACTOR C00LAN P A A. 'R) UMP 00C g R. 00C C: h R.- 00C ]
CORE PARAMETERS CORE EXIT THERMOCOUPLE F j MARGIN TO SATURATION Ch A - F 'Ch'B - F SOURCE RANGE COUNTS N 31 - N 32 - '
I INTERMEDIATE RANGE AMPS N 35 - N 36 -
1 RVLIS % 1 CONTAINMENT 97. v TEMP. oF PRESS. 9. 7 PSIA SUMP LEVEL J %
3 CONT. ISOLATION PHASE I. II. III: HYDROGEN %
SECONDARY SYSTEM I STEAM GENERATOR (LEVEL)
A 3 (.o %B 43 % C 5% f %
AUX. FEEDWATER AUX. FEED FLOW (GPM) CN-TK-1/2 LEVEL %
G- 3A: A. M v
00C 38: @ R. 00C FW-P-2.' h ~
R. '00C ENGINEERED SAFEGUARDS - RWST 9 '[ ' % SI FLOW O' (GPM) -
HHSI A: A. R. 00C B: A. R. 00C C: A R. 00C OSRS A: A. R. 00C g, A, R. 00C LHSI 'A: A. R. 00C B: A. R. 00C ISRS A: A. R, 00C 8: A. R. 00C '
OS A:. A. R. 00C B: A. R. 00C RS-P-3A AR, 00C RS-P-3B: A. h , 00C RS-TK-1: %-
ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY) '
H:RSS. DIESEL. DEAD, BACKFEED J:RSS, DIESEL. DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EOG)
H: OP, AVAIL. 00C J: OP, AVAIL,00C j RESERVE STATION SERVICE i
As HOT /0EAD 8: HOT / DEAD C HOT / DEA,0 HIGH RANGE EFFLUENT RAD MONITORS VENT VENT PROCESS VENT MAIN STEAM A' B C REMARKS l
LEGENO: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. - ISRS - INSIDE . RECIRC. SPRAY OS - OUENCH SPRAY RSS - RESERVE STATION SERVICE (A = Available.' R = Running. 00C = Out of Commission)
. TOFEMERGY.OGN NAPS /11 2 8-E5 '
_m_m.___- _ - _ _ _ . _ _ _ _ _ _ _- -. -
- -ee<
. . . . . ,- .-.-. . . ~ . . ,
q0 0 l O PLANT STATUS ;
NORTH ANNA POWER STATION UNIT I l>
REACTOR POWER o %
PRIMARY SYSTEM J REACTOR COOLANT SYSTEM (T = Temperature) - HOTTEST TH F HOTTEST TC F LOOP"I oT F Loop og 37 F LOOP "3 AT F l PRESSURE % !
PSIG PRESSURIZER LEVEL _
PRT LEVEL '7/ %-
REACTOR COOLANT PUMP A A. R, 00C g: A. R. 00C ~ C: A. ' R. 00C CORE PARAMETERS
-#F CORE EXIT THERMOCOUPLE 796 MARGIN TO SATURATION Ch A - lo (, F Ch B.- 10 t p SOURCE RANGE COUNTS N 31 - (O 3 N 32 - 10 7 INTERMEDIATE RANGE AMPS N 35 - l V to " N'36 - 6w 16 ' "
RVLIS 4O %
CONTAINMENT o TEMP, F PRESS. PSIA %
SUMP. LEVEL l CONT. ISOLATION PHASE I,II. III: HYDROGEN % .
SECONDARY SYSTEM ;
STEAM GENERATOR (LEVEL)
A 34, % IM % B 44% I f8c* % C fl 7o ' lo 26* %
AUX. FEEDWATER AUX. FEED FLOW (GPM) CN-TK-I/2 LEVEL T,*4TS %
3A: A. R. 00C 38: A. R.- 00C FW-P-2 A. R, 00C ENGINEERED SAFEGUARDS - RWST % S' FLOW (GPM)
HHSI A: A. R. 00C B: A. R. 00C C: A. R. 00C LSRS A: A. . R. 00C 8: A. R. 00C t LHSI A: A. R. 00C B: A. R. 00C ISRS A: A. R. 00C .B: A. R. 00C OS A: A. R. 00C B: A. R. 00C RS-P-3A: A. R. 00C 'I RS-P-38: A. R. 00C RS-TK-1: %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (SUPPLY)
H: RSS, DIESEL, DEAD. BACKFEED J:RSS. DIESEL, DEAD, BACKFEED EMERGENCY DIESEL GENERATOR (EDG)
H: OP, AVAIL,00C J: OP, AVAIL,00C RESERVE STATION SERVICE A: HOT / DEAD B: HOT /OEAD C: HOT / DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENT *Ol'4.l6' I PROCESS VENT .0f x 10" MAIN STEAM A .tw f0" B . st, x lo
- C K / /o* !
REMARKS S/[ A 2 e y to A 'h T.T
- Lo # c M. T x I e 3 j
("" LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY
\ LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY '
OS - QUENCH SPRAY RSS .- RESERVE STATION SERVICE ' ,
(A = Avetleble, R = Running, 00C = Out of Commission) '
TDFEMERGY.0GN NAPS /l] 2-0-85
,..4.. . . , . -_. - . _ . . . , , - . . _ . , . - . - . - . - - - +-- . - - , - - - - , + - . -
PLANT STATUS '
l 07-15-1987 GO9:29:45:
NORTH ANNA POWER STATION ' I PRIMARY SYSTEM UNIT :1 O) t REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 380 *F HOT TC 382 *Fl LOOP #1 dT O *F LOOP #2 dT O F LOOP #3 dT O *F ;
PRESSURE 665 PSIG PRESSURIZER LEVEL 20 %
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission)
AR BA CA CORE PARAMETERS I CORE EXIT THERMOCOUPLE 404 *F MARGIN TO SATURATION ChA 106 *F chb 101 *F SOURCE RANGE COUNTS N31 1.OE3 N32 1.OE3 INTERMEDIATE RANGE AMPS N35 9.OE-11 N36 6.OE-11 RVLIS 40 %
CONTAINMENT j TEMP. 92 *F PRESS. 9.75 PSIA SUMP LEVEL 3 % 1 CONT. ISOLATION PHASE I, II, or III HYDROGEN %
I SECONDARY SYSTEM l l
STEAM GENERATOR LEVEL A 38 % B 40 % C 64 % i AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 %,
(A = Available, R = Running, OOC = Out of Commission) 3As R 3B: A FW-P-2: A j
.i ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
(]/
/
HHSI As A LHSI As A B: A B: A C: R OSRS As ISRS As A
A B: A B: A QS A A B: A RS-P-3A A B: A l RS-TK-1: 99 %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 Ja 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or DOC)
H AVL J: AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C: H HIGH RANGE EFFLUENT RAD MONITORS I VENT VENT A=.02 B=.01 PROCESS VENT .02 MAIN STEAM A .11 MR/HR B .02 MR/HR C .15 MR/HR REMARKS i
/~N LEGEND: HHSI - HIGH HEAD S.I. OSRS - CUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH SPRAY RSS - RESERVE STATION SERVICE!
' ~ ~ ~ ~ ~ -- -
-_______________"--~ - ~ ~~
PLANT STATUS 07-10-1937 GO9:56:45q NORTH ANNA POWER STATION PRIMARY SYSTEM UNIT : I k" REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 377 *F HOT TC 375 *F LOOPW1 dT O 'F LOOP #2 dT O *F LOOP #3 dT O 'F PRESSURE 530 PSIG PRESSURIZER LEVEL 51.8 %
REACTOR COOLAtJT PUMP (A = Available, R= Running, OOC = Qut of commission)
AR BA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 406 *F MARGIN TO SATURATION ChA 30 *F chb 74 *F ,
SOURCE RANGE COUNTS N31 9.5E2 N32 9.5E2 INTERMEDIATE RANGE AMPS N35 8.OE-11 N36 5.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 90 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 40 % B 46 % C 57 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 %)
(A = Available, R = Running, OOC = Out of Commission) l 3As R 3B A FW-A-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM .
I (A = Available, R = Running, OOC = Out of Commission) g HHSI As A LHSI As A B: A B: A C R OSRS As A B: A ISRS As A B: A I QS As A B A RS-P-3As A B: A j RS-TK-1: 99 % !
ELECTRICAL DISTRIBUTION i EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 Jr 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or OOC)
H AVL Jr AVL l
RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=. 02 B=.01 PROCESS VENT .02 MAIN STEAM A .15 MR/HR B .03 MR/HR C .15 MR/HR REMARKS SECURED COOLDOWN. "C"S/G DD 2.5E3 "A"S/G BD 3.5E2 "B"S/G BD 9.5E2
^
LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - GUENCH SPRAY RSS - RESERVE STATION SERVICE
~ ~ ~ ~ ~~~" " " - " " - ~ ~~ ' " ' ' -"~ ~~~ ~~
~
)
PLANT STATUS 07-15-1937 910:10:58" NORTH ANNA POWER STATI i
PRIMARY SYSTEM UNIT REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 379 *F HOT TC 377 *F LOOP #1 dT O 'F LOOP #2 dT O *F LOOP #3 dT O *F ,
PRESSURE 482 PSIG PRESSURIZER LEVEL 69.8 %
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission) l AR BA CA i
CORE PARAMETERS 5 CORE EXIT THERMOCOUPLE 394 *F f MARGIN TO SATURATION ChA 77 'F chb 72 *F SOURCE RANGE COUNTS N31 9.5E2 N32 9.5E2 INTERMEDIATE RANGE AMPS N35 7.OE-11 N36 4.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, I I, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 38 % B 50 % C 46 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 %!
(A = Available, R= Running, OOC = Out of Commission) 3As R 3B: A FW-P-2: A t l
ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM
(
('
(A = Available, R= Running, OOC = Out of Commission)
HHSI As A B: A C R OSRS As A B: A CHSI As A B: A ISRS As A B: A QS As A B: A RS-P-3As A B: A RS-TK-1: 99 %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 J 1 l
EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or OOC)
H AVL J AVL j I
RESERVE STATION SERVICE (H = HOT, D = DEAD) !
A: H B H C H {
l HIGH RANGE EFFLUENT RAD MONITORS l '
VENT VENT A=.01 B=.02 l PROCESS VENT .02 l 1
i MAIN STEAM A .09 MR/HR B .02 MR/HR C .09 MR/HR i
REMARKS SECURED COOLDOWN. "C"S/G BD 2.5E3 "A"S/G BD 3.5E2 "B"S/G BD 9.5E2 i
l
]
O LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY l OS - OUENCH SPRAY RSS -
RESERVE STATION SERVICE I
~
PLANT STATUS -
07-15-1937 010:18:32:
NORTH ANNA POWER STATION s g PRIMARY SYSTEM UNIT :
REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 379 *F HOT TC 377 *F LOOP #1 dT O 'F LOOP #2 dT O *F LOOP #3 dT O 'F PRESSURE 482 PSIG PRESSURIZER LEVEL 69.8 %
REACTOR COOLANT PUMP (A = AvailAble, R = Running, OOC = Out of commission)
AR BA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 394 *F MARGIN TO SATURATION ChA 77 *F chb 72 *F SOURCE RANGE COUNTS N31 9.5E2 N32 9.5E2 INTERMEDIATE RANGE AMPS N35 7.OE-11 N36 4.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 38 % B 50 % C 46 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 %
(A = Available, R = Running, OOC = Out of Commission) 3As R 3B: A FW-P-2: A 1 ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Qut of Commission) t HHSI As A B: A C: R OSRS As A B: A U
LHSI As A B: A ISRS As A B: A l QS As A B: A RS-P-3As A B: A RS-TK-1: 99 %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs l
1 J 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or DOC) l H: AVL J: AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C: H !
HIGH RANGE EFFLUENT RAD MONITORS !
VENT VENT A=.01 B=.02 j
PROCESS VENT .02 !
l MAIN STEAM A .09 MR/HR B .02 MR/HR C .09 MR/HR !
REMARKS SECURED COOLDOWN. "C"S/G BD 2.5E3 "A"S/G BD 3.5E2 "B"S/G BD 9.5E2 '
n U LEGEND: HHSI - HIGH' HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY !
QS - QUENCH SPRAY RSS - RESERVE STATION SERVICE I l
~
~. .. .-..
PLANT STATUS #E 07-15-1937 @10:23:42 NORTH ANNA POWER STATION l PRIMARY SYSTEM UNIT :
?
REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 380 *F HOT TC 376 *F LOOP #1 dT 0 *F LOOP #2 dT 0 *F LOOP #3 dT 0 *F PRESSURE 465 PSIG PRESSURIZER LEVEL 75.0 %
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Qut of commission)
AR BA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 394 'F MARGIN TO SATURATION ChA 77 *F chb 72 *F SOURCE RANGE COUNTS N31 9.5E2 N32 9.5E2 INTERMEDIATE. RANGE AMPS N35 7.0E-11 N36 4.0E-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 40 % B 46 % C 40 % ]
AUX. FEEDWATER AUX. FEED FLOW 0 GPM 1-CN-TK-1 LEVEL 95 %l (A = Available, R = Running, DOC = Qut of Commission) i 3As R 3B A FW-P-2: A j ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Availacle, R = Running, OOC = Out of Commission)
O HHSI As A LHSI As A GS As A B: A B: A B: A C R OSRS As A ISRS A A RS-P-3As A B: A Ba'A B: A RS-TK-1: 99 %
' ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4= BACKFEED)
Hs 1 Ja 1 EMERGENCY DIESEL GENERATOR (EDG) ( O P, AVL, or COC)
H: AVL J AVL RESERVE STATION SERVICE (H = HOT,- D = DEAD)
As H B H C: H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02
- PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .09 MR/HR >
REMARKS C/D ON C S/G IN PROGRESS BY FILLING AND BACKFILL TO RCS
\
\ \
N .
iEGEND: HHSI - HIGH HEAD S.I. OShS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH SPRAY RSS -
RESERVE STATION SERVICE
~
a l PLANT STATUS 07-15-1937 010:36:0 NORTH ANNA POWER STATION PRIMARY SYSTEM UNIT si REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 380 *F HOT TC 377 *R LOOP #1 dT O *F LOOP #2 dT O *F LOOP #3 dT O *F j PRESSURE 438 PSIG PRESSURIZER LEVEL 61.5 %
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission) ;
AR BA CA ]
CORE PARAMETERS CORE EXIT THERMOCOUPLE 391 *F f MARGIN TO SATURATION ChA 71 *F chb 62 *F SOURCE RANGE COUNTS N31 9.5E2 N32 9.5E2 INTERMEDIATE RANGE AMPS N35 7.OE-11 N36 4.OE-11 {
RVLIS 40 % j i
CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 40 % B 47 % C 41 % 1 AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 d (A = Available, R = Running, OOC = Out of Commission) 3As R 3B: A FW-P-2: A- 3 ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM I O (A a Available, R = Running, OOC = Out of Commission) =
HHSI A A B: A C: R OSRS As A B: A l LHSI As A B A ISRS As A B: A GS As A B: A RS-P-3As A B: A l RS-TK-1 99 %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 J 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or DOC)
.H AVL J: AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H Be H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 i
MAIN STEAM A .09 MR/HR. B .02 MR/HR C .09 MR/HR REMARKS TAVE 376 RHR HOLD ON '
i LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY GS - GUENCH SPRAY RSS -
RESERVE STATION SERVICd O
_______._______[
_ O*'?
- * ' ' * * ' * * " ' ' ' ""***'******#"* """" ' ~ ^ - ' ^ ^ ^ ' ^ - ^ ^ ^ - ^ ^ ' -
PLANT STATUS 07-15-1937 @10:50:04 NORTH ANNA POWER STATIO'N PRIMARY SYSTEM UNIT 21 REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 378 *F HOT TC 376 *F
[~
LOOP #1 dT 0 *F LOOP #2 dT 0 *F LOOP #3 dT 0 *F PRESSURE 399 PSIG PRESSURIZER LEVEL 63.0 %
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission)
AR DA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 391 *F MARGIN TO SATURATION ChA 64 *F chb 60 *F-SOURCE RANGE COUNTS N31 8.0E2 N32 8.0E2 INTERMEDIATE RANGE AMPS N35 7.0E-11 N36 4.0E-11 RVLIS 40 % j CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 % ;
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 41 % B 46 % C 35 %
AUX. FEEDWATER AUX. FEED FLOW 0 GPM 1-CN-TK-1 LEVEL 95 %)
(A = Available, R = Running, OOC = Out of Commission) l 3As R 3B A FW-P-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW.SEC GPM (A = Available, R = Running, OOC = Out of Commission) l HHSI As A B: A C R OSRS As A B: A !
O LHSI As A OS As A B: A.
B: A ISRS As A RS-P-3As A RS-TK-1: 99 B: A B
A
~ ' ~ '
ELECTRICAL DISTRIBUTION EMERGENCY BUS (i = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED) l Hs 1 Ja 1 .
EMERGENCY DIESEL GENCRATOR (EDG) (OP, AVL, or OOC.) )
H AVL J: AVL .)
l RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C: H HIGH RANGE EFFLUENT RAD MONITORS ,
1 VENT VENT A=.01 B=.02 :
I PROCESS VENT .02 .
MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR REMARKS TAVE 377
'\/
) LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SARAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY' .
OS - QUENCH SPRAY RSS -
RESERVE STATION SERVIC@
...a
. . . . _. . .u . a. ,
PLANT STATUS 07-15-1937 011:04:12 NORTH ANNA POWER STATION {
PRIMARY SYSTEM UNIT 31.
O REACTOR COOLANT SYSTEM (T= Temperature)
LOOP #1 dT O PRESSURE 399
- F
. *F
- F REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out.of commission)
AR BA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 391 *F MARGIN TO SATURATION ChA 64 *F chb 60 '*F SOURCE RANGE COUNTS N31 8.OE2 N32 8.OE2 INTERMEDIATE RANGE AMPS N35 7.OE-11 N36 4.OE-11 RVLIS 40 %
CONTAINMENT
. TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL'4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 41 % B 46 % C 35 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 %
(A = Available, R = Running, DOC = Out of Commission) 3As R 3B A FW-P-2 'A ENGINEERED SAFEGUARDS - RWST 97 %- SI FLOW SEC -GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI As A B: A C: R OSRS As A B1 A LHSI As A B: A ISRS As'A B: A h(/ QS As A B: A RS-P-3As A B: A
_ _. RS-TK-1: 99 ~%
ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 =-DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 J 1 EMERGENCY DIESEL GENERATOR (EDG) ( O P, AVL, or DOC)
H AVL J: AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR REMARKS TAVE 377 O LEGEND: HHSI - HIGH HEAD S.I.
LHSI - LOW HEAD S.I.
QS - GUENCH SPRAY OSRS - OUTSIDE RECIRC. SPRAY ~
ISRS - INSIDE RECIRC. SPRAY RSS - RESERVE-STATION SERVICE
. . . _ . . . . . . . . - - . ~ . - . . _ . . . . . . . . . _ . . . . . . . _ - . . ... ..~.......f...L
PLANT STATUS C 07-15-1987 G11:07:02 NORTH ANNA POWER STATION PRIMARY SYSTEM UNIT 31 I i
s o REACTOR COOLANT GYSTEM (T= Temperature) HOT TH 363 *F HOT TC 357 *F!
( L.vv. - -
encoovnw 375 0 *F ro1G LOOP #2 dT O *F PRESSURIZER LEVEL 58.0 LOOP #3 dT O
- F l REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission)
AR BA CA J
CORE PARAM'ITERS '
CORE' EX J'r THERMOCOUPLE 390 *F MARGIN TO SATURATION ChA 62 *F chb 58 *F SOURCE RANGE COUNTS N31 8.OE2 N32 8.0E2 INTERMEDIATE RANGE AMPS N35 7.OE-11 N36 4.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 42 % B 46 % C 30 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 %i (A = Available, R = Running, OOC = Out of Commission) 3As R 3B: A FW-P-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI As A B: A C R OSRS As A B: A (N LHSI As R B: A ISRS A A B: A (j OS. As A B: A RS-A-3As A B: A RS-TK-1: 99 % <
ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4= BACKFEED)
Hs 1 J: 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or OOC)
H AVL J AVL i RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B: H C: H HIGH RANGE EFFLUENT RAD MONITORS l
VENT VENT A=.01 B=.02 !
l1 PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR i
REMARKS TAVE 360 $
1 1
I
+
LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY y LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY j
j OS -- QUENCH SPRAY RSS - RESERVE STATION SERVICEI l
i i
1 n
PLANT STATUS- 07-15-1937 011:23:46 NORTH ANNA POWER STATION fb 1 PRIMARY SYSTEM UNIT s'
[
(,j REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 348 LOOP #1 dT o *F LOOP #2 dT O *F
- k
- F PRESSURE 390 PSIG PRESSURIZER LEVEL 25.0 %
' REACTOR COOLANT PUMP (A = Available, R = Running, DOC = Qut of commission) j AR BA CA j CORE PARAMETERS CORE EXIT THERMOCOUPLE 390 *F MARGIN TO SATURATION'ChA 62 *F chb 58 *F J
SOURCE RANGE COUNTS N31 8.0E2 N32 8.0E2 INTERMEDIATE RANGE AMPS N35 7.0E-11 N36 4.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN % {
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 41 % B 50 % C 34 % 1 AUX. FEEDWATER AUX. FEED FLOW 0 GPM 1-CN-TK-1 LEVEL 95 %
(A = Available, R = Running, OOC = Out of Commission) 3As R 3B A FW-A-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI A A B: A C: R OSRS As A B: A LHSI As A B: A ISRS As A B: A O- QS A: A B: A RS-A-3As RS-TK-1:
A 99 B: A i
ELECTRICAL DISTRIBUTION EMERGENCY BUS (i = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACMFEED)
Hs 1 Ja 1 EMERGENCY DIESEL GENERATOR (EDG) ( O P, AVL, or DOC) l H AVL , J AVL {
RESERVE STATION SERVICE (H = HOT, D = DEAD)
A H B: H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 l
MAIN STEAM A .09 MR/H B .02 MR/HR C .07 MR/HR I
REMARKS TAVE 360 I 1 O LEGEND: HHSI - HIGH HEAD S.I.
LHSI - LOW HEAD S.I.
05 - QUENCH SPRAY OSRS - OUTSIDE RECIRC. SPRAY ISRS - INSIDE RECIRC. SPRAY:
RSS -
RESERVE STATION SERVIC@
- - -.. .,_ . .. .. .. ,, , _4 m
PLANT STATUS )l 07-15-1987 011:32:39-NORTH ANNA POWER STATION l
PRIMARY SYSTEM UNIT :
/O REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 348 *F HOT TC 346 *Fl h LOOP #1 dT O PRESSURE 390
- F REACTOR COOLANT PUMP (A = Available, R = Running, DOC = Out of commission) I AR BA CA j CORE PARAMETERS CORE EXIT THERMOCOUPLE 390 *F l MARGIN TO SATURATION ChA 62 'F chb 58 *F '
SOURCE RANGE COUNTS N31 8.OE2 N32 8.OE2 INTERMEDIATE RANGE AMPS N35 7.OE-11 N36 4.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 41 % B 50 % C 34 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 %i (A = Available, R = Running, OOC = Out of Commission) 3As R 3D: A FW-A-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI As A B: A C: R OSRS As A B: A
[] LHSI As A B: A ISRS As A B: A Q OS A A B: A RS-P-3As RS-TK-1:
A 99 B: A ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 Ja 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or OOC)
H AVL J AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A= 01 B=.02 !
PROCESS VENT .02
]
MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR j l
REMARMS TAVE 3tc {
l
(' LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY l
(' LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY I QS - QUENCH SPRAY RSS -
RESERVE STATION SERVICE' 4
..._......)
1
PLANT STATUS NORTH' ANNA POWER STATION 07-15-1937011:37f PRIMARY SYSTEM UNIT :
REACTOR COOLANT SYSTEM (T= Temperature) m LOOP #1 dT O HOT TH 340 *F HOT TC 338
'F LOOP #2 dT'O
( PRESSURE 365 *F LOOP #3 dT O 'M PSIG REACTOR COOLANT PUMP PRESSURIZER LEVEL 27.0 %
AR (A BA = Available, R = Running, OCC = Out of commission)
CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 390 *F MARGIN TO SATURATION ChA 87 SOURCE RANGE COUNTS N31 8.OE2-
- F chb 87 *F N32 8.OE2 INTERMEDIATE RANGE AMPS N35 7.OE-11 N36 4.OE-11 RVLIS 40 q
{
CONTAINMENT I TEMP. 92 *F PRESS. 10.5 l PSIA- SUMP LEVEL 4 CONT. ISOLATION PHASE I, II, or III %
HYDROGEN %
SECONDARY SYSTEM i
I STEAM GENERATOR LEVEL i A 42 % B 48 % C 38 i
AUX. FEEDWATER '%
AUX. FEED FLOW O GPM ]
(A 3A: = Available, R = Running, OOC = Qut of Commission) 1-CN-TK-1 LEVEL 95 6 R 3B A FW-P-Es A i 1
-ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC !
GPM (A =HHSI Available, As A R = Running, OOC = Out of Commission) {
Bs A C R j LHSI As A Ba' A 'OSRS A A B: A QS As A ISRS As A O ELECTRICAL DISTRIBUTION B: A RS-P-3As A RS-TK-1: 99 B: A B: A EMERGENCY BUS Hs 1 (1Ja= RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED) 1 EMERGENCY H AVL DIESEL GENERATOR (EDG) (OP, AVL, or OOC)
J AVL RESERVE STATION SERVICE (H = HOT, A H Be H D = DEAD)
C H HIGH RANGE EFFLUENT RAD MONITORS l
VENT VENT A=.01 B=.02 PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR REMARKS TAVE 360 LEGEND: HHSI - HIGH HEAD S.I.
LHSI - LOW HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY i
OS - OUENCH SPRAY ISRS - INSIDE RECIRC. SPRAY
%d RSS
- RESERVE STATION SERVICE ,
, _ . . . . . . . . . . . . . . . . . .. . . , . . . . . . . . _ . . __......,,_,q 4
']
PLANT STATUS 07-15-19*,7 (F11 s 37: 3k NORTH ANNA POWER STATION PRIMARY SYSTEM UNIT :
REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 340 *F HOT TC 338 'F O LOOP #1 dT 0 PRESSURE 365
- F LOOP #3 dT 0
- F
. REACTOR COOLANT PUMP (A = Available, R= Running, OOC = Out of commission)
AR BA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 390 *F MARGIN TO SATURATION ChA 87 *F chb 87 'F SOURCE RANGE COUNTS N31 8.0E2 N32 8.0E2 INTERMEDIATE RANGE AMPS N35 7.0E-11 N36 4.OE-11 ]'
RVLIS 40 %
CONTAINMENT TEMP. 92 'F PRESS. 10.5 PSIA SUMP LEVEL 4 % ,
CONT. ISOLATION PHASE I, II, or III HYDROGEN % l SECONDARY SYSTEM STEAM GENERATOR LEVEL l
A 42 % B 48 % C 38 %
AUX. FEEDWATER AUX. FEED FLOW 0 GPM 1-CN-TK-1 LEVEL 95 %'
(A = Available, R = Running, OOC = Qut of Commission) 3As R 3B: A FW-A-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI As A B: A C: R OSRS As A B: A LHSI A A B: A ISRS As A B: A O' OS As A B: A RS-P-3As RS-TK-1:
A 99 B: A ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 J 1 l
EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or DOC)
H AVL J AVL RESERVE STATION SERVICE (H = HOT, D = DEAD) j A H B H C H i HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 MAIN STEAM A.0 MR/HR B .02 MR/HR C .07 MR/HR REMARKS TAVE 360 i
LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY O
, LHSI - LOW HEAD S.I.
QS - QUENCH SPRAY ISRS - INSIDE RECIRC. SPRAY-RSS -
RESERVE STATION SERVICE!
. , . . _ ,-, , , . - _ . . . . - . . . . . . . - - . . . . . . . . , , - - - . . . - - - . ~ ~ . .-
'l
PLANT STATUS 07-15-1937 01 N
NORTH ANNA POWEA STATION PRIMARY SYSTEM N REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 340 *F HOT TC 338 *F
["'}
( ,f LOOP #1 dT O *F LOOP #2 dT O *F LOOP #3 dT O *F PRESSURE 365 PSIG PRESSURIZER LEVEL 27.0 %
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission)
AR BA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 290 *F MARGIN TO SATURATION ChA 87 *F chb B7 *F SOURCE RANGE COUNTS N31 8.OE2 N32 8.OE2 INTERMEDIATE RANGE AMPS N35 7.OE-11 N36 4.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.5 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 42 % B 48 % C 38 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL 95 %
(A = Available, R= Running, DOC = Out of Commission) 3A: R 3B A FW-P-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Qut of Commission)
HHSI As A B: A C R OSRS A A B: A LHSI A A B: A ISRS A A B: A
[~)'s
( QS As A B: A RS-A-34: A RS-TK-1: 99 B: A ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BECKFEED)
Hs 1 J: 1 EMERGENCY DIESEL GENERATOR (EDG) ( O P, AVL, or DOC)
H: AVL J: AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B: H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR I
REMARKS TAVE 360
's I
, LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY
( LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH SPRAY RSS -
RESERVE STATION SERVICE 1
=
l J
PLANT STATUS 07-15-1937 011:56:4T NORTH ANNA POWER STATION !{ .
PRIMARY SYSTEM UNIT si
- F O REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 331 LOOP #1 dT 0 PRESSURE 342 PSIG
- F LOOP #2 dT 0 PRESSURIZER LEVEL 23.0
- F
- F.
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Qut of commission)'
AR BA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 350 *F MARGIN TO SATURATION ChA 90 *F chb 85 *F SOURCE RANGE COUNTS N31 6.0E2 N32 6.0E2 INTERMEDIATE RANGE AMPS N35 4.0E-11 N36 3.0E-11 RVLIS 40 %
CONTAINMENT TEMP. 92 #F PRESS. 10.8 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 42 % B 42 % C 41 %
AUX. FEEDWATER AUX. FEED FLOW 0 GPM 1-CN-TK-1 LEVEL 95 -q (A = Available, R = Running, OOC = Out of Commission) 3As R 3B A FW-P-2: A ENGINEERED SAFE 3UARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI A A B: A C: R OSRS A A B: A O LHSI As A GS As A B: A B: A ISRS As A RS-P-3As A RS-TK-1: 99 B: A B: A ELECTRICAL DISTRIBUTION -
EMERGENCY BUS (i = RSS, 2 = DIESEL, 3 = DEAD, 4= BACKFEED)
Hs 1 J: 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or DOC)
H AVL J: AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C H l 1
HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR REMARKS TAVE 360 i
O LEGEND: HHSI - HIGH HEAD S.I.
LHSI - LOW HEAD S.I.
GS - QUENCH SPRAY OSRS - OUTSIDE RECIRC. SPRAY ISRS - INSIDE RECIRC. SPRAY-RSS - RESERVESTATIONSERV i
l
.i l
l
_ _ -__ _ _ _ -_----------_-_-- - __ __ _---_____J
PLANT STATUS 07.15-1907 G11:59:17 NORTH ANNA POWER STATION "
- Q.s PRIMARY SYSTEM N
'7'/ UNIT si
/O REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 331 *F HOT TC 329 *F
'( ) LOOP #1 dT O *F LOOP #2 dT O #F LOOP #3 dT O 'F i PRESSURE 342 PSIG PRESSURIZER LEVEL 23.0 %
REACTOR COOLANT PUMP (A = Available, R= Running, OOC = Out of commission)
AR BA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE .350 *F MARGIN TO SATURATION ChA 90 *F chb 85 *F i SOURCE RANGE COUNTS N31 6.OE2 N32 6.OE2 i INTERMEDIATE RANGE AMPS N35 4.OE-11 N36 3.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.8 PSIA SUMP LEVEL 4 %-
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 42 % B 42 % C 41 % I AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TM-1 LEVEL 95 %I (A = Available, R = Running, OOC = Out of Commission) 3A: R 3B A FW-A-2: A ;
ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI As A B A C R OSRS A A B: A LHSI A A. B: A. ISRS As A B: A O)
( QS As A B: A RS-P-3As A RS-TM-1: 99 B: A ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
H 1 J 1 s
EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or DOC) l H AVL J: AVL j RESERVE STATION SERVICE (H = HOT, D = DEAD) i A H B H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 j i
PROCESS VENT .02 l
MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR I s !
I REMARKS TAVE 360 ;
) i l
l LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY j
[~})
\ LHSI - LOW HEAD S.I.
QS - QUENCH SPRAY ISRS - INSIDE RECIRC. SPRAY RSS - RESERVE STATION SERVICE l
l t
_ _ _ - - - - - _ _ _ _ _ - 1
1 PLANT STATUS 07-15-1907 012:17:241 NORTH ANNA POWER STATION j PRIMARY SYSTEM UNIT 21
/ \ REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 331 *F HOT . 'rc 32i1
- F)
(_,/ LOOP #1 dT O *F LOOP #2 dT O *F LCOP#3 dT C *F PRESSURE 342 PSIG PRESSURIZER LEVEL 23.0 %
REACTOR COOLANT PUMA (A = Available. R= Running, OOC = Out of commission)
AR EA CA CORE PARAMETERS CORE EXIT THERMOCOUPLE 350 *F .
MARGIN TO SATURATION ChA 90 *F chb 85 *F '
SOURCE RANGE COUNTS N31 6.OE2 N32 6.OE2 INTERMEDIATE RANGE AMPS N35 4.OE-11 N36 3.OE-11 RVLIS , 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.8 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
l l SECONDARY SYSTEM l
STEAM GENERATOR LEVEL A 42 % B 42 % C 41 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-ON-TK-1 LEVEL 95 %
(A = Available, R = Running, OOC = Out of Commission) ,
3A R 3B: A FW-P-24 A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Sunning, OOC = Qut of Commission) .l HHSI As A B: A C: R OSRS As A B: A
/ LHSI As A B: A ISRS A A B: A
\ f OS As A B: A RS-P-3As A B: A
! RS-TK-1 99 %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED) ;
H 1 J 1 l
l EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or DOC) l H AVL J AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
A H Be H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 l MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR REMARKS TAVE 360 l
, / #\ LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY l LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - QUENCH EPRAY RSS - RESERVE STATION SERVICEi
. - . . . . . . ~ . . . .. . . _ . . . . . . . . . . - .. .
- w -
PLANT STATUS 07-15-1937 912:23:29 NORTH ANNA POWER STATION PRI) Y SYSTEM UNIT *1 REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 305 *F O LOOP #1 dT O PRESSURE 340
'F
- F REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission)
AR BA CA
/
' CORE PARAMETERS a CORE EXIT THERMOCOUPLE 350 #F MARGIN TO SATURATION ChA 90 *F chb 85 *F SOURCE RANGE COUNTU N31 6.OE2 N32 6.OE2 INTERMEDIATE RANGE AMPO N35.4.OE-11 N36 3.OE-11 RVLIS 40 %
CONTAINMENT I "
}
TEMP. 92 *F PRESS. 10,8 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I II, or III HYDROGEN %
( SECONDARY SYSTEM STEAM GENERATOR LEVEL A 40 % 3 44 % C 50 %
j AUX. FEEDWATER OUL FEED'Fl.OW O GPM 1-CN-TK-1 LEVEL 95_ %-
(A = Available, R = Running, OOC = Out of Commtssion) 3As R '3D: I A FW-P-2: A h
ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI As A B: A Cs R OSRS As A B: A
/ LHSI As A Bi A ISRS As A B: A QS As A B: A RS-P-3As A B: A l
, RS-TK-1: 99 %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (i = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 J 1 EMERGENCY DIESEL GENERATOR (EDG) ( O P, AVL, or OOC)
H AVL Ja AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B: H C: H 4 HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B= 02 l PROCESS VENT ,02 l
MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR I
REMARKS RHR IN SERVICE AT 1215 BECURED RCP'8 CB 1793 AT 1120 DEPRESS RCS l
[ LEGEND: HHSI - HIGN HEMD S.I. OSRS - OUTSIDE RECIRC. SPRAY LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY OS - QUENCH SPRAY RSS -
RESERVE STATION SERVICE <
e
- 2.1._ _. . _.. . . . . _ _ _. . . _
, ..._.._. . ,.4 i
1 E_._______________________.______________
. . . . . . ~ .. . . ,
l / l PLANT STATUIl 07-15-1907 012:31 d '
NORTH ANNA POWER STATION -
fY PRIMARY SYSTEM UNIT si i ("~ REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 305 *
.F HOT TC 304' *h
\ LOOP #1 dT 0 #F LDOP#2 dT 0 *F LOOP #3 dT 0 *F l PRESSURE 340 PSIG PRESSURIZER LEVEL 21.0 %
l REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission) l AR BA CA ,
CORE PARAMETERS CORE EXIT THERMOCOUPLE 350 *F MARGIN TO SATURATION ChA 90 *F chb 85 *F SOURCE RANGE COUNTS N31 6.OE2 N32 6.OE2 INTERMEDIATE RANGE AMPS N35 4.0E-11 N36 3.0E-11 RVLIS 40 %
~
CONTAINMENT i TEMP. 92 *F PRESS. 10.8 PSIA SUMP LEVEL 4 % l CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 40 % B 44 % C 50 %
AUX. FEEDWATER AUX. FEED FLOW 0 GPM 1-CN-TK-1 LEVEL 95 0 (A = Available, R= Running, OOC = Out of Commission) 3A: R 3B A FW-P-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Qut of Commission)
HHSI As A B: A C R OSRS As A B: A LHSI As A B: A ISRS As A B: A Of QS As A B: A RS-P-3As RS-TK-1:
A 99 B
A-ELECTRICAL DISTRIBUTION
. EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 Jo 1 EMERGENCY DIESEL GENERATOR (EDG) ( O P, AVL, or OOC)
H AVL J AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
A H Be H C: H HIGH RANGE EFFLUENT RAD MONITORS i
VENT VENT A=.01 B=.02 j PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR i
REMARKS RHR IN SERVICE AT 1215 SECURED RCP' S CB 1793 AT 1120 DEPRESS RCS LEGEND: HHSI - HIGH HEAD S.I.
O LHSI - LOW HEAD S.I.
GS - QUENCH SPRAY OSRS - OUTSIDE RECIRC. SPRAY' ISRS - INSIDE RECIRC. SPRAY RSS -
RESERVE STATION SERVICE'
_m
_ __ .~ -
+
l PLAN 1 STATUS 07-10-1937 012:51:59)
,, NORTH ANM4 POWER STAT [ON PRIMARY SYSTuM bl UNIT si i s
[(,/ REACTOR COOLANT SYSTEM F* Temperature)
LOOP #2 dT O HOT TH 287 *F HOT TC 271 LOOP #3 dT O
- F
(A a Ava.i l a b le, R= Running, OOC = Out of commission)
REACTOR COOLANT PUMP AA BO CA ,
1 CORE PARAMETERS CORE EXIT THERMOCOUPLE 350 *F j MARGIN TO SATURATION ChA 90 *F ChD 85 *F SOURCE RANGE COUNTS N31 6.OE2 N32 6.OE2 INTERMEDIATE RANGE AMPS N35 4.OE-11 f,35 3.OE-11 RV .!S 40 %
CONTAINMENT l TEMP. 92 *F PRESS. 10.8 PSIA SYlp LEVEL 4 3 i l .
CONT. ISOLATION PHASE I, II, or III HYDROCIIN l % l SECONDARY SYSTEM ~
l STEAM GENERATOR LEVEL i A 42 % B 42 % C 50 %
AUX. FEEDWATER AUX. FCED FLOW O GDM 1-CN-TK-1 LEVEL 95 %I (A = Available, R = Ru6ning, OOC = Cut of Commission) l 3A A 3Bs A FW-4-2: A ENGINEERED SAFEGUARDS - RWST 97 % GI FLOW SEC GPM (A = Available, R = Running, OOC = Qut of Commission) l HHSI As A Es-A C: R OSRS As A B: A
/ LHBI As A B: A ISRS As A B: A
( 'CS As A B: A RS-P-3As A D: A RS-TK-1: 99 %
l ELECTRICAL DISTRIBUTION I l
EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEF k 4 = BACKFEED) l Hs 1 J 1 l
EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or OOC) l H AVL '
J: AVL r?EGERVE STATION SERVICE (H s' HOT, D = DEAD)
A: H B H CM HIGH RANGE EFFLUENT RAD MONITORS I VENT VENT Ao 01 B=.02 i
~
PRCOESS VENT . Ori -
j MPIfJ STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR REMARKS RHR IN SERVICE AT 1215 SECURED RCP' S CB 1793 AT 1120 DEPRESS RCS TAVG 275 42 DEGREE F/HR C/D RATE LEGENDS HNS.: - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY j LHSI - LOW HEAD S.I. ISRS - INSIDE'FCCIRC. SPRAY QS - QUENCH FPRAY RSS - RESERVE STATION SERVICE:
6 n o s wa< _ e ww <er ep ', rue -
- see. - n w,es s ==me e.= e eee we see
- & arh oe e. .s .mm
) *
(
)-
PLANT STATUS 07-15-1987 353:05
. NORTH ANNA POWER STATION 72 UNIT *1 PRIMARY SYSTEM .
i ,
f\
REACTOR COOLANT SYSTEM (T= Temperature)
LOOP #1 dT 0 *F. LOOP #2 dT 0 HOT TH 268
- F
- F PRESSURE 263 PSIG . PRESSURIZER LEVEL 56 %
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission)
Af BA CA CORE PAR 4 METERS CORE EXIT THERMOCOUPLE 350 *F ' i MARGIN TO SATURATION ChA 90 *F chb 85 *F SOURCE RANGE COUNTS N31 6.0E2- N32 6.0E2 INTERMEDIATE RANGE AMPS N35 4.0E-11 N36 3.0E-11 )
RVLIS 40 %.
CONTAINMENT j TEMP. 92 *F PRESS. 10.8- PSIA SUMP LEVEL 4 % i CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 48 % B 44 % C 44 %
AUX. FEEDWATER AUX. FEED FLOW 0 GPM 1-CN-TK-1 LEVEL 95 %l
. (A = Available, R = Running, OOC = Out of Commission) j 3As A 3B A FW-A-2: A !
ENGINEERED SAFEGUARDS - RWST 97' % SI FLOW SEC GPM (A = Available, R = Running, OOC = Out of Commission)
HHSI As A B: A C R OSRS As A B: A
,O LHSI As A OS As A B A B: A ISRS As RS-P-3As A
A B: A B: A
]
RS-TK-1: 99 %
ELECTRICAL DISTRIBUTION _
EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 Ja 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL,.or COC)
H AVL J AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C H l HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR v .07 MR/HR REMARKS RHR IN SERVICE AT 1215 SECURED RCP' S CB 1793 AT 1120 j EEPRESS RCS TAVG 275 42 DEGREE F/HR C/D RATE
~
'^ OSRS - OUTSIDE RECIRC. SPRAY j LEGEND: HHSI - HIGH HEAD S.I.
LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY
- QUENCH SPRAY RSS - RESERVE STATION SERVICS QS
. . . . . . . ~ . - . . ..
. ~ ... -. ,. .. - - - . - - .
. _ _ - - _ _ - - . _ . _ = _ - - _ _
l
} l PLANT STATUS 2. '07-15-1987 913:02:32 NORTH ANNA POWER STATION -
PRIMARY SYSTEM UNIT 1 O REACTOR COOLANT SYSTEM LOOP #1 dT O PRESSURE 251 (T= Temperature)
- F PSIG-LOOP #2 dT O HOT TH 253 _
PRESSURIZER LEVEL 57
- F
. L'E
- F REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Qut of commission) i AA BA CA 1 CORE PARAMETERS CORE EXIT THERMOCOUPLE 350 *F MARGIN TC .:niURATION ChA 90 *F chb 85 *F~ ,
SOURCE RANGE COUNTS N31 6.OE2 N32 6.OE2 l INTERMEDIATE RANGE AMPS N35 4.OE-11 N36 3.OE-11 RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.8 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM GENERATOR LEVEL A 40 % B 45 % C 36 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TM-1 LEVEL 95 %'
(A = Available, R = Running, COC = Out of Commission) 3As A 3B: A FW-A-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC.= Out of Commission)
HHSI As A B: A C: R OSRS As A B: A O LHSI As A QS As A B: A B: A
~
ISRS A A RS-P-3As A RS-TK-1: 99 8: A B: A ELECTRICAL DISTRIBUTION EMERGENCY BUS (1 = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED)
Hs 1 J 1 EMERGENCY DIESEL GENERATOR (EDG) (OP, AVL, or COC)
H AVL J AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
As H B H C H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR
)
REMARKS RHR IN SERVICE AT 1215 SECURED RCP' S CB 1793 AT 1120 DEPRESS RCS TAVG 275 42 DEGREE F/HR C/D RATE
)
O LEGEND: HHSI - HIGH HEAD S.I.
LHSI - LOW HEAD S.I.
GS - GUENCH SARAY OSRS - OUTSIDE RECIRC. SPRAY .l ISRS - INSIDE RECIRC. SARAY RSS -
RESERVE STATION SERVICEj l
1
- - . . - . - ~ . ~ . - . - . . . - . . . . . _ . . . - . . . . . . . . .
. . . . . . ~ . . . . - ....
PLANT STATUS 07-15-1987 013:23J34:
NOttTH ANNA POWER STATION N N
{f PRIMARY SYSTEM UNJJ REACTOR COOLANT SYSTEM (T= Temperature) HOT TH 224 *F HOT TC 218 *F LOOP #1 dT O *F LOOP #2 dT O *F LOOP #3 dT O *F PRESSURE 251 PSIG PRESSURIZER LEVEL 39 % ,
REACTOR COOLANT PUMP (A = Available, R = Running, OOC = Out of commission) {
AA BA C" A i
CORE PARAMETERS CORE EXIT THERMOCOUPLE 225 *F MARGIN TO SATURATION ChA 90 *F chb 85 *F ;
SOURCE RANGE COUNTS N31 '. OE2' N32 6.OE2 {
INTERMEDIATE RANGE AMPS N35 4.OE-11 N36 3.OE-11 l RVLIS 40 %
CONTAINMENT TEMP. 92 *F PRESS. 10.8 PSIA SUMP LEVEL 4 %
CONT. ISOLATION PHASE I, II, or III HYDROGEN %
SECONDARY SYSTEM STEAM G'ENERATOR LEVEL A 47 % B 44 % C 38 %
AUX. FEEDWATER AUX. FEED FLOW O GPM 1-CN-TK-1 LEVEL'95- %
(A = Available, R = Running,-OOC = Out of Commission) 3As A 3B: A FW-P-2: A ENGINEERED SAFEGUARDS - RWST 97 % SI FLOW SEC GPM (A = Available, R = Running, OOC = Qut of Commission)
, HHSI As A B: A C: R OSRS As A B: A
( LHSI As A B: A ISRS As A B: A ;
j GS As A B: A RS-P-3As A B: A RS-TK-1: 99 %
ELECTRICAL DISTRIBUTION EMERGENCY BUS (i = RSS, 2 = DIESEL, 3 = DEAD, 4 = BACKFEED) 1 Hs 1 J 1 EMERGENCY DIESEL GENERATGR (EDG). ( O P, AVL, or OOC)
H AVL J AVL RESERVE STATION SERVICE (H = HOT, D = DEAD)
At H B H C: H HIGH RANGE EFFLUENT RAD MONITORS VENT VENT A=.01 B=.02 <
PROCESS VENT .02 MAIN STEAM A .09 MR/HR B .02 MR/HR C .07 MR/HR REMARKS VCT LEVEL 42% CHS RATE 25GPM LETDOWN 95GPM
\
Ms LEGEND: HHSI - HIGH HEAD S.I. OSRS - OUTSIDE RECIRC. SPRAY ;
l LHSI - LOW HEAD S.I. ISRS - INSIDE RECIRC. SPRAY QS - GUENCH SPRAY RSS -
RESERVE STATION SERVICEi
. .. , -w . m. ~e. e -
~w . a - . ~ . . e - w. . ~ -
. . . ~ ' . i ..' ' ' ' .i 1 1
No.9Fssy220 -
i A TTACHMENTTITLE REVIS10N NUMBER '
07 hh
'EPIP-2.01 REPORT OF EMERGSNCY TO STATE AND LOCAL GOVERNMENTS ;
MGE A ATTACHMENT 1
1 of 1 i 1
MI58 ACE:
This te Virginia Power North Anna Control teos C TSC O L Or. standby for a roll-cell f atto..d I j by se emergency message. Use e port of Emergency fore to copy this message. (conduct a ;
roll-call and check the bosee se each party amovere.) !
iam Couery rginia State 10C ease County petsylvania County mover County rotine County The emergency maassage is se followes
/
Itse 1.' amargency clases E notification of Unusual Event Q Alert Deelsted at d 6~3 9 os 7/6/@
', Site Area Emergency (16 nr. time)
General Emergency Beersency terminated (if checked. go to item 9)
Itas 2. Asetetance ra questeds Epone. C (no.) rire Unite from f" (no.) Police Unite free (ao.) Reecae Unite free l (Ot.ber)
Ites 3. Emergency response estione underveys Bone tation amargency personnel called is Station monitoring teses dispeeched offeite (Otbar) anw47?vs eTM64/ #4bof/%%.
Ites 4 Evacuation of easite personnels $5e U fee, tvecuated to
( Itse S. Progneste of situations C1mproving IJtable. ,
i Osoeemains O(Other) !
Itse 6. es of radioactive materist NOT occurred and is NOT projected Q!epresentlyoccurrieb.
U te prsjected to occur.
Seeoccurredandlanowtepneced Item 7. Wind directica Le from the 8/h 3 Vind speed is Ib MPR.
Itse s. naearket T( w () - I / Fos 4 M e. NC Tu *) G [ G4 f.
q$FS1y llI$C161/
Itse 9. This to $6 M N (nese) O.4/f M / Met 9 G44WI (position)
Plasse scheowledge receipt of this message (Conduct roll-call and check bosse) isa County rainia State 20C ange County 3 8 potty 1vania County never County rotine County This to Virginia Power porth Annabstrol toonCTSCC1. EOF out at ties kd os 7 /W l (26 br. time) (date)
~~"~~scrrt: TRE FOLIDVIEC INF0gMATION IS FOR $2 Aft USE ONLT. TRAMfMIT TO STATE EDC ST THE "EING-DOWN" TELEPHONE CIRCUIT.
1 Item 10. Areas affected ares some. I 5ectore and tomes itse 11. Recommended off-site protective acticass pose. ;
Sheltertag La sectore and tones j Evacuation is sectors and Zones Q(Other) {
thia is Virginia Power Berth Annahontrol toonCT3CCLt0F out et time ' OGTI os 7 /6 /N
!,j i
(24 hr. tLee) (sate)
( i i
e i t
I
."***"Ir"-r P** es 44u.e. p am +e , un- E o no r . . . , , , , , , .,,,,g, , , , , , _ _
' - 1 J
No.9188y330 )
1 i
ATTACHMENT TITLE REVIS10N l>
NUMBER 07 EPIP-2.01
(' ATTACHMENT REPORT OF RADIOLOGICAL CONDITIONS TO THE STATE.
PAGE 2
1 of 1
-j NOT!s INFCinATION 05 THIS FORM I$ FotM $ TATE U$t CNLY JefD WILL lt *1M5M:**ED TO
This to sorth anne Power Stattee M Centrol teen C TSC C LECT C C10F.
I have a report of radiotesitel tenditiona. Une a teeeet of tadteleuteel Condittene fers to sety this message.
Please Lafers me uten your are ready to espy. (Freteed when taformed).
"Itse 1. Type of release te Airborne. rolessed at elevottee of ft. ,
Watetterne ]
Y I8erfas "Itas la. Phfsiss1 fers of release is pill.
ses8 C liquids Csolidt Cunknevn. /
- 1tes Lb. Chemical fern of release is teert asete gases: C radioidiese s. Cuaunews. ,
Speettically _
f
- ! en 1. setease C hessa et . Cieestimatedtobestaet .
(26 ar. stas) (26 ar. tame)
"Itas 3. Release derettee Cves bro. Cteestimatedtobe hre.- 1 I
hrs. j
- 1 ten 4. Time between reacter ehetdows sad beginaia6 el release wee Q U set appiacatio." l
- h tem 3. vied directies is it e $ . etad eyeed Le N Mrs.
8tability 41ase La _
4 *1:en 6. T rature to M *F. recipitaties fe,ru is Duone C Rain C81eet -
Seev C(Quws)
D "Itse 7. The todiae/Neele Cao latie le .
Useasem.' ,
1
" Item 8. Preieeted total release earnivalent Curies of t-L31 to Curtes. 1 BUnanown."
- 1tes 9. Protected total roleses etsiveleet Curies of Ze-L33 to- Q Curtu.
U Goemon."
"tten 10. astual Whole lady done tete at the Site Seeadery is Q et/hr U Ueaeews.-
" Item Lt. feetasted Whole lady dose rates are O mA/hr et Site Soundary.
et/hr et 1 milee, m&/hr at 3 miles, et/hr et LO milee J
- 1tes it. _Preiseted total integrated Whole ledy do.e to C .a et site neuedary.
.a at t muee.
es et 5 miles.
as et 10 s11ee. ;
- ttom 13. Prefected total integrated Thyroid does is C at et lite lovedary, mA at 2 miles. ,
mA et 5 miles. ,
eA et 10 miles.
I
- tten 14. Actual eurf ase radionettre teaceminattee is C Orit/100cm is tese .
Q Unseown."
"Ite's 13. $setfse seeditiene are se fellowes (Cive brief status and cause of eastgesey):
4
- ttie la WOW / P) Pit C04 % _ est at stae AIO em @ !6 ID ma= * (le nr.stae) (use)
[D i
(poettises I
.L .
- -- ~ . ~ . , . . . . . . .._ , .
.*h'4'*W'"4 8F h weggem, .,, ,
"M
I see, treersee MUltBER ATTACHNINTTITLE REVIsl0M EFIP-2.01 ~ 07
$ REPORT OF ENERGENCY TO STATE AND IDCAL GOVE300ENTS ATTACHNENT MGE 1 1 of I WERSAGts This to firstata Power Berth A Centrol Seen C TSC C 1,30F. StameSpy for a re11 call fellesed by en meegemey unseeds. Use e Sapert of Smergency form to espy this message. (Caedset a toli-call and check the besse se eneh party mesetw)
County irgiata State EDC Canary W Spoterivania Commty Wemessor County cere11me County the emergency = ===?= is as fellesas
^
Ita 1. amargemey slaaes Estificatise of Sumenal Beast g 4
) Alert Sealered et- ee 7 /b /g I Site Aree heersency (24 hr. time)
, General Guergemey .
, ,, Emergemey tevedseted (if checked so to item 9)
Iten 2. Assistence regnested: hBhee. (ee.) Fire Daite from (no.) Police Saite itus -
T5tEr>(es.) Saeems caite free l i
stem 3. amersoney respamme estiene enderusy:
Bees O station emergeoey perse .ast called to Stasian assitoring teams &Lapecched offeite @(Other)AD64#BT'06 MWry AGO4M Itas 4 Eveeusties of smelte peresumals @ge U Tee. Essenated to
, Isen 5. ProSuseste of siteetien: C!apearing DStable.
! qasementes O(oth=r)
Item 6. Se noms of redisassive antarials ' .
See ust esserved sad Le Hof projected Is preemely esserries. I Ene escarred and is mee tasminated le projasted to esaur.
Its 7. Wind direettee is from the / t Wind speed is 'lY tra.
Item S. Seanthes YG ~T!)R2 90hIWS$ !
tt a 9. This te b NNM (name)
/ @fN
- CUtlM (posities)
Please = h tedge receipt of this amenage (Caenset rell-tall'eshi cheek bases).
/
QNetes Cemety State MC 'enge Comesy hfSpetsy19amie Cemety Resever Cemety retine Commty This Le fissinia Fuent Berth trol SeemOTSCO lme est at ties CD/ em 7 /T /D I (24 hr. tian) (date)
Et TEE PR.imt!NB IEFOMATION IS FOL STATE 058 QEt,T. flaaENIT TO STATE SDC pf TEE
- R2B M GMW" TEL2FBtWE CIRCrtT.
item 10. Areas affected are Daems.
f U5eetere end temme I
Item 11. "- ' off-vite protective actieses l
'emme. ~. !
Sheltertag is Saetere and 3eese l Bonametten te Seetore and teens i O(Other) ,,,
1%e te firstate reser sorth AsseOCentrol SeesOTScO1aor e.t et ti.e OOR. a. o rf 6/ M (24 hr. tian) , dese)
( $. i 1
l 1
l q
,w..- e .. w * . wvme w . - ....w .. w. .. -.m' t , .. .--..p.
a .?
___i___ -___l___
nn.oresysse '
ATTAChletENT MTLE REVWON
, MUuMR 07.
IFIF-2.01 .
l REPORT OF DERGENCY TO STATE AND LOCAL GOVER20ENTS nel ATTAcxuanT 1 of 1 1
i l
'88" 888 .f nas is 'trstata $==e arrth As 3 Co sret seen C tsC C t.nor. staaer for a ren-mu feu. sed I l by an emergeme' ansanon. Use a Esport of Smargemey form to tory this aseemse. (Candmet a .I reu-eall amt cheek the hamme ao seek ty assuore.)
Jse das Comney rgtata State RIC County Sfeasylvania Caumney Beesver Couunty C CaroLiam County i th. o.orse.,y - s. .e f.umi tt i. n reemey 21ame r sattna.tsa. .f - s e=c iAlset Declared at O en )/ Nb/ i 1
, $tte Ares guergamey (24 hr. ties) {
m Gameral horsency 'J
. ! hergemey teresanted (if sheekad. se to ttem 9)
. it. .. . 1.t _ . v ted, s. ( .> ,,re m te fr (ae.) Police Outta free l Mr)(ae.) naamme Omite from amersamer response ast1sas endereurs I team 3.
Q stattaa enseguesy persec.nel ea1 w is 8sene Statias meestaring teams dispatched effeite y (Other) 4 M 44 'WMDV M%Me*I O, >
Itas 4 heenatias of aseita persammelt Lto . - ted to 1
3 ttan S. Pregammaa of attentimes Qtaprertag $ table. j l
U soreentag Q(Other) _ _ _ _
Itan 6. Belanas of sudsmaattve anterials Quas per ensurved and la UDT projastad Q1spresentlyeesorrias.
Uans seenrred and to see teaminated UIs projected to assar.
Itan 7. Utad tirostiam is free the Wind speed is Irs.
team S. Samothes S AUC1 l$ lllU &U$ r Ib M (D0ld4)b WWVY j 1
0%?Pssa917%
Itmo 9. S ia is N T77 C(ffhGt(($
/ k/db*k. @Mht s (name) (posttima)
Planse ashassledge teemige of this mammage (Camdmet reUacall and theek besse) l /
1.smiss Caumsy Tiagtais State MIC QQrangeCaumty I Lousia County County W CaroLine Casesy l
this to Tt state fuser Berth J - rel Bomm O TSCCtm F est at time 8716 (24 hr. taas) .
am 7 #T N (dete) ll 3 EUft: TER PGLLautBB 115ceeArts 18 PUE STA25 558 GET. vnassarrT 10 Sta2E EBC SY TER ~
-l i
=n mr.m"
sostare and Samme item 11. ' ' eff-site protective estismes ases.
I Shattertag ta Sectors and Esame ,i Bresmatian la Seeters and Seems O(Other)
This is firsinia reser serth MCentret seenOTerr"h any t et time O'7 / 8 7 f /5 ffp O
e.
( p hr. time) (este) I4i I
k l
I
ne.ersetsso REMBOW
( MuntstR A17ACMetMT MTLE 07
'EFIP-2.01 REPORT OF EMEEGENCY TO STATE AND LOCAL GOVERNMENTS MGE ATTACMaffMT 1-1 of 1 2 8485:
This to firstala Feuer Berth M Centrol toen C TSC C LEDF. Samey for a roll-eall fo11ased h by an emergency essenge. Use a tapoM of Imargumey fore to espy this ====ta. (Camenet a rail-eali and sheek the hemme es aesh ausmere.)
causry yinginia state soc orange Councy spetsylvania cammty temsvar Coney -
reline Comney the emergemey messasse is se follaues stan 1. Basegamey elases estifiaattaa of 9mmmmal heat M #"
Alare Deelared at Uhhil J '1 em 7 / 6 / & r)
Site Area austgemey (24 kr. tism)
General Smergemey
, amargemey termtmated (if *h-ahd. so to item 9)
Itan 2. Assistance requested @ gees. (mm.) Fire Dmite from (ao.) Police Omite free Er)(ee.) Osesse Omite free Itma 3. Omar Osse.gemey response estians ederesy Qstatia. amore.ney peree.t.at tatled ta i
QStattaa ammitorias tease dispetshed effette E](Other)m6 eMW vtT&n66
' Item 4. Sweemeties of emaita paremamels Jie Tee Breamsted to
~
Item 5. Pregassis of stamnatie:ss Q!apreetas OStable.
l U soreentag Q(0thes) ttem 6. Satanas of re a==*two estarials
@ Bas Upt senarred W is EUT projected Q1spreenulyenumrries.
Uano esserved and is aos termianted . U1a -projected to mesar.
Itan 7. Viad direccian is fuen the t Wind opend La b 19 5.
Item 8. tammetas @M HMM M ABW Ml00 EMd 4WfSN Item 9. This ta W CWL#llT.9 (name)
/ PA4PQ (QMM (poettian)
Flames ashnestadge reemipt of this amenage (Camdmet roll-eall and, cheek bsues) laatse Commay State EDC ange County USpotsylventa County U bemover Csumey U Caretime Ceemsy this is firginia pesar Berth AmmmECsetrol Beh set et ties (2e he, time)9; 7b/ l (dese)
- gs TEE 745, taw 1381Ercener10518 FOR State EBE ONLY. TRABSMIT TO STatt 3DC BT TER
- 1.335-8015" TEJPECNE CIE SIT.
Itan 10. Areas affneted ares Qases.
U Seetera and 1sene I
tten 11. ieummedad effacite protestive settamos 6 'Emma.
4 mattering ta sectore and Sense treamation ta sosters and Sense Q(Othat) m #_
thia' ta virginia Peeer sorth AndCastrel mesmOTsCO.aor est et taas se 7 / 5 /#7 g
- (24gtgg) (dese) 4 4 4 9
,, m.mm a = yi , e ,e ==ise, - w .e< .,-ee*,e -.,e, .m.= e. e. .g, .. u -ee... + ._.+--ye,e,q
,*e.Wrestese P _ _ _
ATTACHNENT MTLE REVIGl0N
, MUNSER 07-IFIP-2.01 REPORT OF DERGENCY TO STATE AND LOCAL GOVERNMENTS PAGE ATTACHNENT .
1 1 of 1
.i?
MRESAGE:
This to firstate Feuer perth AnnaC Centrol team TSC C L307. Stasey for e roll-eall fellseed 'l by as amergency assesse. Use a tapert of tenrgency form to copy this eseesse. (Ceedmet e roll-call and cheek the bases se each party enseers.)
[ta=8==Comty .
rainia State 3DC % e Camary w Spotsylvanie County Eemover County w Caro 11me Commty The emergency messense is se feilenes item 1. Inorgemey alases I" antif teeties of Dumenal seems I I Alert Declared et ONO en )/ /87 1,, Site Area tusrgemey (24 br. time)
General amargemey 1,..Emergemey tenutanced (if h W . go to Itan 9)
Item 2. Aseistence requestada 05een. (es.) Fire Unite from (me.) Police cates iree S r)(me.) Seeses Omite free Item 3. Smergemey reopease actions enderemys Been Ostette. amores.ey perse. =et called ta Stetten semiterias comme dispeeched effette C (Other)
- Iten 4. Bosemattee of emette perasemais Qas UYes Speemsted to Isen S. Prespeeis of situst'tems I layrerieg stable.
I normoning (Other)
Item 6. Release of ra amattuu materials Q1epresentlyseemeries.
85ae Rae59f escurred seemered and and is meeteterminated NOT projected Ute projected to esar.
~
ltem 7. Wied direction is from the a Wind speed is WB.
Item 8. Remarte N w; t PA--
M In.* M d h . '
,d S-e- & " 1TC.
Itas 9. This te dAL 1 / U N. C6HA, G (mensg (penities)
Please schmouledge receipt of this e (Condmet roll-call and besse)
Camary Tirgiese State B C enge County wSpotsylvente County ammeser Caumer Carotias Camacy this te virgiate teemt north AnneCCentrol - - 9=r out at time D@C[ en 7 / 6/87 l (2e he tama) (date) ga TER FIE.LatrtES INFOMATIM IS PUE STATE USS MT. TRAS$ NIT TO STATE EDC ST TEE "325G-40W" TEEFWout .
Item 23. Areas affected eres Game.
Sectors sad seems
~
Itan 11. Seep off.eita protective e tienes es.a.
shattering in Seeters and Isees tweemeties in Sestare and temas Q(Other)
This te Virginia Poset sortt AmmaOContrei nes 0Ts&r set et ties JF e. > /ic /gi (24 tr. tian) (deae) !
,,-e.an. e e e
. . _ - _ _ _ _ _ . _ _ - _ _ _ _ _ _ . . - _ _ _ . _ - - - . E '
1 No.97sg7220 I j
7 l 4
\_) A TTACHMENT TITLE REVISION NUMBER EPIP-2.01 07 REPORT OF EMERGENCY TO STATE AND LOCAL GOVERNMENTS j ATTACHMENT NGE i 1 Of I f
\
1 K235AG11
- his is firginia Power North Amaa O C.. trol noom Tsc O tror. Staa4>y for . roti-call f otlowed I by an emergency message. One a Report sf Emergency fem to copy this message. (Conduct a {
q roll-call and check the bones as each party answers.) j 1as Covery rginia State E0C e Ceuacy Spotsylvania County sever County reline County The emerseecy esassage is se fo11swet ites 1. taargency clasas otifiution of Deusual twent c,
. Alars , Declared at b3b os 7 / / I/u7 "3TTE Area taargency (24 hr. time)
Gemaral taergency Emergeary terminated (if checked. go to Item 9) l Itas 2. Aastetance requested (ae.) fire Osits free l (es.) Police Units from I (no.) tascue Units free i l(Otaar)
Itas 3. taargemey suspeese actions underway F C 5tatica emergency perso-nel called is
$$tation nomitoring teams dispeccbed offsh C (Other)
'm g item 4 tvacuacian of omsten per la I
- s, tvecusted to tes 5. Prognosis of situations CImproving able.
OIhrteeming Q(other)
Itse 6. Salmana af - ' * " r 4_- - "*4a1*
~
j QRaeNOToccurvedandisNOTproje#ct u,reraarra n.e armor. 8lapresentlyescurring.
w.
- z. ,,.3eoed to cour.
Item 7. Wind direction is from the t Utad speed La / MPE.
trea 8. Ammarket M 6P'k 6 !
A1 a >>em- waan ndure Z) sce nz y ir m bzuwaiikd (
ttee 9. This le f .2979/l. 7)Vm '
qIsas) (poettions Please schnowledge receipt of this maeemse (Conduct roll-call cM check boxes) i l
ias County Wgista State E0C ffge County j
,3potaytvaaLa County er County rotine County '
Thia is Virginia Fevst north AnnaCCastrui LEDF ost at time [ $ O 3 (26 nr. time) m '(date>
"7 //N [ lj i i
!Lt*?t
~ TtX FULLoimIG INyctMAT10515 FCt STATI USE OWLY. TI.AE3MIT TO STATE 20C ST THE '
- 1DC-DOWR" TI:2FRoirs CISCIT.
Ites 19. Areas affected aret home.
U $ectore and Isaan Itse 11. e w ed off-site protective actions: i A Rome.
, .shatterias La Sectors sad tones j
.tveematies la sectors and Zonan O(other)
This is Tirginia reser sorth AnasCControl A CCL20F out et time b' os 7 dO7 (26 hr. taae) (dates !
I 1
(O) 1 mz n ytu& ,
i
- ~
-m -n ow - ~*c~-w o~~ oo w = * ~ * ' - ~ ~ " o ow ' ' ' ~ ~ ~ ~ - I
1
. . . .~.s. .-
No.97sg7320 m
(% REVISION
.NUNDER A TTACHMENT TITLE EPIP-2.01 07-REPORT OF DERGENCY TO STATE AND LOCAL GOVERNMENTS ATTACHMENT PAGE 1
1 of 1 nEssacts f This to firginia temet porth &ameC Centrol Reen T5C C 1.20F. Standby for a roll call fellemed l by se emergency massage. See e Report of tamtgency fore se copy this message. (Caeduct a roll-esil chest the beses se each ty amenere.) ,_
ies Comary rginia State EOC sage Comary '
speteylvania County Remover County Carollas Comacy The emergency mannesse is as felleues Itan 1. amargemey slaae Jetifiaation of Unnemal Event Alert . Declared at Ob3 O em 7 / /*) /
Site Ares Emergency (24 hr. tims)
General Emergency Eastassey t ruinated (if checked. se to ttem 9)
Itas 2. Asetatance requestads Neme. (es.) Fire Daite from (es.) Pelica Unita from (no.) Rosene Unite free M e)
{ tem 3 Emergemey reopease actione underway C Station emergency persee.nel called La tatise usatsering teams dispeeched effeite C(Other)
Its 4 Eveausties of emette peroommets re O Tee. Sve- to itse '3. Progmesia of situottens roving Statie.
U Beressias C(Othat) ,
~
Itan 4. Selease af radiesc't19e esterialt 80T scourred and La NOT Frejected to presently osestries.
occurred and te new terminated In projected to occur.
It s 7. Wind directies is from the ' t Utad speed is / NFE. l tsaa 8. Asmarket fbn/*H9 % /h>1/bekkCs > A/O' N d O .f*C W AMAMJ . PAY.4*@At sofM L Ak A#.rt tLLfAiut,d l* W o * '
ttaa 9. Thie La f Ofit1AALMs W o w " $%
<oempv a ipfestsee) 3 Flease ashmouladge rossipe of this masse n (Coedmet tell-call and c ~ bones) ime County taia State IOC - County poterivasta Couary er Consty rettee County. ,
This is Tirgiate Peuer perth eneaCCentrol TSCC1,IDF set et ties /WY w (26 ar. ti->
~7 U S S '/ '
aate> - l ;.
\ 3: TEE FULL 0trtNI INTOEMATIOR t$ FOR STATE USE OtlLT. TEANSMIT TO STATE EOC ST TEE-
- tINO-00WW" TELEFWout CIRCUtt.
l l
Item 19. Areas affected dres .
Sectors and tease 1 i
ttes Lt. ef f=eite protective setienes !
uses. - J Shelterias is Sectare med temoe ;
tressettee ta Sectors and toene j Q(Other) , '
ThielavirgiataFeerworthAnneCControl F est et stasOkb_ on '7<4t/f M7 (26 nr. st=> ate > li
(
coc. M .
4
'l
__ _.__=_1 .m m- -+ m - - - - - - - -. -- 4 ~ ~ - - - , . -- . ___---
I J
. . . .._ s No.9?ssy220 r
NUMBER ATTACHMENT TITLE REWSl0N EPIP-2.01 07 REPORT OF EMERGENCY TO STATE AND LOCAL GOVERNMENTS A TTACHMENT PA GE 1 1 of 1 i
i d
nssSAGEs ThislefirstataPowerSorthAssaCControltao. O tE0r. standhy for a roll-esil folto..d Ii by se emergency message. Use a Report of Emergency form to copy this massage. (Conduct a roll-call check the boxes as each rey answere.)
tee County rgiata State 10C ange Couary l Spotsylvania County mover Covery Caroline County l
The emergency massesse is se followes j Itsa 1. Emergemey claeas tificattoe of Deuaual Evesc OGSY
,f y %
l f[lert A Declared at % w - ou 7 /d/k] '
Site Area Eastgency 24 ar. time)
General Emergency Emergency terminated (if checked. go to Item t)
Itas 2. Assistance requested (no.) Fire Unite free
{ (ea.) Pelice Unite from (oo.) Rascoe Unite free
! Nr) team 3. test eary roepense actione undorueys C . Cstecto. o.orgemey perse,a.1 called ta tazios assitoring teens dispatched offeito C (Other)
Item 4 Evacustias of osoite persomme12 se Tea, tweetseted to Itse 5. Prognosta of situations Improving C$ table.
Beressing C(Other)
Item 4. Relasse of radiesetive materials C)sh h0T securred Isad is NOT projected C1spresostlyoccurring.
Maae occurred and is ese terminated Ola projected to accur.
Itse 7 Wind directice is from the t Viad speed is 0 MPt.
4 ltea 8. tamartas OVM hnx.n wha M, =taa.a , MA st &c . j .
aYH sm/A s A LA_ J.LMk> Qd" "
h / *2 Y Vo $ M*"'-
t em 9. Tkia is __ &m ifAvuA & h j $8MWUV t o.p > o gesu->
Plasse ac ledge receipt of this assesse (Conduct roll-call and check beses) ina County taia State ROC se County 8peteylvania Couerv Reaever County WCaroline Comary This is tirginia Power Berth ha# Control CCLICF out at time d h/3 on 7 UI h7 l (24 hr. time) teate)
Es THE POLLOWDIC INFORMATION !$ FOR STATE USS ONLT. TRAESMIT TO SyATE E0C ST TER "U NC-00 4" TELEFilous CIRCUIT.
Item 10. Areas affected ares one.
Sectore med Zones Itas 11. E ed off-site protective actiones 3heltering ta lectors and Zones 8tvecuation in Sectors and Zoeaa Q (Other) ,
This is firginia Power North AsamCCentrol CCL10FoutattimeO9/b on 7 //f/N ,
(26 br. siae) (dates I i
O !
h m..... . . _ , . , _ . . _ . . _ , . _ , _ . . . . _ . _ _ _ _ - _ . - _
NUMBER ATTACHMENT TITLE ( / REylSION an acHMENI REPORT OF EMERGENCY TO -
STATE AND LOC'.L GOVERNMENTS NE I [
MESSAGE: (l #
'This as North Anne Power Stetson O Control Room OTSC KLEOF 0 CEOF.
Standby form for e roll-enll followed by en emergency message. Use o Report of Emergency to copyLouise [thisCounty messege.' (Conduct a roEOC Virginia State 1-cell and check -
range County the bones as seoh d Spotsylvanie County Of6nover County - Caroline County
'The emergency message as es follows:
' Item 1. Emergency Class O Nottf acetton of Unusual Event te Aree Emergency O General Emergency Declared et S
' "#*'on I dbh 'd*
O Emergency terminated (if checked. go to Item 9)
- ltem 2. Assistence requeste,d: None. O. (no.) Fire Units from .
O (no. ' Police Units from .
i O (no.) Rescue Units from .
O (Other) l
' Item 3. Emergency response actions underway O Hone.
Station emergency personnel celled in.
Station monitoring teams dispatched ofI site.[O (Other) l
' Item 4. Evnouetion of on-site personnel: No. !
O es.Eveevoted to .'
'! tem S. Prognosis of situotsons Impr oving. O Stable.
O orsening. O (Other) .'
' Item G. Release of radioactive meteriel:
(V} O Hos NOT occurred and as NOT projected.
{ '
O le presently occurring.
Has occurred and is now terminated. O la projected to occur.'
'! tem 7. Wind direction as-from the M Wind speed is f.b MPH.'
' Item B. Description of Events 0
- I- MN A A a d__e_ -rN_ _ d, e s -
A, N b_e_d_ _. A i W
gy a ru 1y A*T~y >- 9/ m- R~b l
\_ F*. QT~'. .' f
'i tem 9. This is , ( >Jw_
NS ynow&pg.7 i
% l in i ipo.i u.n>
l
'Please acknojul dge roceipt of this mes,sege.'
s Louise County (Conduct CT virginie State EOC roll cell and check boxes)
& Orange County YSpotsylvenne County t}Ionover County [Coroline County
'This is North Ane,o Po e St.gtson out et timMN on .<,,, /f.s.,/M.' O Control Room O TSC K LEOF 0 CEOF u4 +. u > (e NOTE:
THE FOLLOWINO
' RING-DOWN' TELEPHofE INFORMATION CIRCUlT. IS FOR STATE USE ONLY. TRANSMIT TO STATE
- lt.m is. Aree. arrect.d ere:O None.
Sectors and Zones d
bN='
I d, .
'I tem !!. Recommended of f site protective actions: \
$None.
O Sheltering in Sectors and Zones O Evocuatim in Sectors and Zones
- O (Other) .
g
- This is North Anne Power Stetson O Control Room O TSC O LEOF 0 CEOF
\] out at time u . ~. u ,on __,.w...i /__., / , .'
t0FleC.MOvJXin senPS/3 s.S-ss
. , . . _ . . . . . . _ . . . a. _-
No.97887220 J NUMBER ATTACHMENT TITLE REvlSION REPORT.OF EMERGENCY TO AM E HMENT NE STATE ANO LOCAL GOVERNMENTS MESSAGE:
'Thas as North Anne Power Stetson O Control Room OTSC 5 LEOF 0 CEOF.
Standby for a roll cell followed by en emergency message. Use 'e Report of Emergency form to copy this message.' (Conduc e roll-cell and check the> boxes as each party answers.)
M Louise County Virginie State EOC Orange County Spotsylvanie County Hanover County - Q Carolane County
'The emergency message as as follows:
' Item 1. Emergency Class: Notification of Unusual Event O Sa Area Emergency Declared et on 1 " /" 'b' ' b .' (
0 General Emergency O Emergency terminated (if checked. go to Item' 9)
' Item 2. Assistence requested:MNone. O (noJ Fire Units from .
O - (no.) Police Units from .
O (no.) Rescue Units from .
O (Other) .' )
' Item 3. Emergency response actions underway:
O None. kStation emergency personriel celled in.
MStation monitoring teams dispatched of f-site. O (Other) .
- ! tem 4. Evecuation of on site personnels.M No.
O Yes. Evacuated to .'
- ! tem 5. Prognosis of situettons klmproving. O Stable.
0 Worsening. O (Other) *
( ' Item 6. Release of radioactive metersel O Has NOT occurred and is NOT projected. O !s presently occurring.
,dkHee occurred and is now teemanated. O Is pro jected to occur.' _ __. {
' Item 7. Wind direction is from the _ : Wind speed as MPH.'
- ! tem 8. Description of Events 0^# !' "4 b !
' Item 9. This is NWMVM / bI .
1 in. > <, . . s,.e> i
'Please acknowledge receipt of this message.' (Conduct roll cell efd check boxes) 1 N Louise County Virginae State EOC 3 Orange County l M Spotaglvente County Henover County \ Caroline County
- This is North Anne Power Station O Control Room OTSC kLEOF 0 CEOF l f) out et time+./M <2 u >on 2 /fT/4.* <e s.> );
NOTE: THE FOLLOWING INFORMATION IS FOR STATE USE ONLY. TRANSMIT TO STATE EOC BY THE
' RING-DOWN' TELEPHONE CIRCUIT.
I
- ! tem 10. Areas ef fected ere:O None. -
3 MSectors and Zones d- "
' Item 11. Recommended off-site protectsve actions:
M None.
O Sheltering an Sectors and Zones .
j
,j O Evacuetion in Sectors and Zones .'
O (Other) *
( 'This is North Anna Power Station O Control Room O TSC O LEOF O CEOF '
out et time on /__/ _,.' +
<24 +.u > io.s. ;
TDFE4RGT.DGN emPS/2 6-6 85.
- l
. . . . _ . . . _ , _ . _ . . _ , . - . _ , . . . .~.
_.r. .m._ _.m
No.97887220 l l
/ NUMBER ATTACHMENT TITLE REvlSION m A REPORT OF EMERGENCY TO (u,) d ,
"""""EN' STATE AND LOCAL GOVERNMENTS NE l
MESSAGE:
'This as North Anne Power Station O Control Roo~m OTSC LEOF 0 CEOF.
Standby for a roll cell followed bg en emergency nessage. Use e Report of Emergency form to copy this message.' (CF '.uct a roll-cell and check the boxes es each party enswers.) ]
k Louise Count Virginia State EOC M Orange County i g Spotsylver a County Hanover County jl( Caroline County
'The emergency messege is es follows: !
' Item 1. Emergency Cless: O Nottf acetion of Unusual Event W I*'*
O Site Aree Emergency Declared et C6fh on ~7
_ _/$~p._c
/ .. b l
(24 +. u..) ion.
0 General Emergency ;
O Emergency terminated (if checked. go to Item 9) )
' Item 2. Assistence requested: k None. C (no.) Fire Units from .
O (no.) Police Units from .
l 0 (no.) Rescue Units from . !
O (Other) - .'
]
' Item 3. Emergency response actions underway:
O None. MStetton emergency personnel celled in.
MStetton monitoring teams dispetched of f site. O (Other) .'
i
- Item 4. Evecuation of on site perssonnels dE'No.
O Yes.Evocuated to .' j
/" *! te m 5. Prognosis of situations ,II(Improving. O Steble.
( ]j v
O Worsening. O (Other) .'
' Item G. Release of radioactive meteriel 4 O Hos NOT occurred and is NOT projected. O Is presently occurring.
Han occurred and is now ter mina ted. O Is projected to occur.'
'I tem 7. Wind diree'.non is from the : Wind speed 2s O HPH.'
l
' Item 8. Description of Event C ** M b E' 3 C C
- N 'O M O ^ O ^84 d !
'I tem 9. This is /f // A E/ desm EyG A f [ C. ,.
in . ipoiuom
'Pleese acknowledge receipt of this message.' (Conduct roll-cell and check boxes) f1Lousse County ,)!1 Virginie State EOC DK Orenge County jg Spotsylvenne County @ enover County A Caroline County
'This is North Anne Power Stetson O Control Room OTSC O LEOF 0 CEOF r
out et time / ON on 2. d/D.*
(24 +. um.) (oat.)
' NOTE: THE FOLLOWING INFORMATION IS FOR STATE USE ONLY. TRANIMIT TO STATE EOC BY THE
- RING-DOWN' TELEPHONE CIRCUIT.
' Item 10. Areas ef fected are:O None. /
.,hr Sectors and Zones /
j //9 .'
' Item 11. Recommended of f-site protective ections:
l N None.
O Sheltering an Sectors end Zones *
\' O Evocuetson in Sectors end Zones O (0 + er) .
(/ 'This as North Anne Power Station O Control Room O TSC' O LEOF 0 f.70F l out et time on /_ /_ .*
(24 +. um.i to.s.>
73f f %.1CV.DGN MP$/2 0585
.. c.~. . -- -. . ....~..... ---c._ . . .
1 No.97887220 NUMBER ATTACHMENT TITLE REVISION g g AT W ENT REPORT OF EMERGENCY TO NE STATE AND LOCAL GOVERNMENTS 4
ff MESSAGE:
'This is North Anne Power Station O Control Room O TSC kLEOF 0 CEOF.
Stendby for a roll-cell followed by en emergency message. Use e Report of Emergency form to copy this message.' ("onduct a roll cell and check the boxJs es each party answers.)
M Louise County Virginae State EOC M Grange County g Spotsylvense County p$Henover County k Caroline County
'The emergency message is as follows:
' Item 1. Emergency Class: O Notification of Unusual Event Aree Emergency Declered et on 7 *[ *#/
b .*
O General Emergency ,
O Emergency terminated (if checked. go to item 9) j
' Item 2. Assistence requested:kNone. Q (no.) Fire Units from .
O (no.) Polie. Units from .
O (no.) Rescue Units from .
O (Other) .'
'! tem 3. Emergency response actions underway:
O None. gSteuon emergency personnel celled in.
- ]
KStaticn monitoring teams dispatched of f site. O (Other) .
]
'I tem 4. Evocuetion nf on site personnel:k No.
O Yes.Eveeueted to .
O ' Item 5. Prognosis of situatons kimproving. O Stable.
O Worsening. O (Other) .'
' Item 6. Release of radioecuve meerials
- O Has NOT occurred and is 00T projected. O Is presently occurring.
MHes occurred and as now tofminated. O Is projected to occur.'
' Item 7. Wind direction is from the M : Wind speed is /d MPH.'
i
' Item 8. Desertption of Events 044 U# 7* b*d b d 'd IA ^h0 4
' Item 9. This as dMM OE A / 6C ,. ]
inom. (pon uen>
j
- Please acknowledge receipt of this message.' (Conduct roll cell and check boxes) '
4 Louise County hf Virginie State EOC A Orange County gSpotsylvenne County $ Henover County g Caroline County
'This is North Ann Power Steuon O Control Room O TSC M LEOF 0 CEOF 7
out et time T uon cv ~. .> 2./ w.< f /82.*
t NOTE: THE FOLLOWING INFORMATION IS FOR STATE USE ONLY. TRANSMIT TO STATE EOC BY THE l
' RING-DOWN* TELEPHONE CIRCulT. '
'I tem 10. Arees ef f ected are:O None.
)l(Sectors and Zones
\ /'f .
-)
' Item 11. Recommended of f site protecuve actions:
Mone.
O Sheltering in Sectors and Zones .'
O Evacuation in Sectors and Zones .'
f' j
\
O (Other) .'
( 'Thas is North Anne Power Stat 6n O Control Room OTSC O LEOF 0 CEOF out at t2me a s ~. ua.>
on
/,/
<a. .>
TF MROVEN W S/2 A+85
____E.___7._.u._ ._ l Mi N P- -- *? %D?D
- N ' *
- 'T**W
-- - *M"** 9 *""N""O*W" "'N*#" - # " ' " " " " * " ~ " " "
~
p No.97887220 NUMBER ATTACHMENT TITLE REv!SION REPORT OF EMERGENCY TO
{ ArTAcHMENT STATE AND LOCAL GOVERNMENTS NE
.pt*'*
- MESSAGE:
'This as North Anne Power Stetson O Control Room OTSC 'kLEOF 0 CEOF.
Standby for a roll-cell followed by on emergency message. Use a Report of Emergency form to copy thss message.' (Conduct e roll-cell end check the boxes as each party enswers.)
Louise County M Virginio State EOC j( Orange County
@bSpotsylvonne County .M(Henover County g Caroline County
'The emergency message se es follows:
' Item 1. Emergency Class: O Notification of Unusual Event i
,2( Alert O Site Aree Emergency Declared at on 7 /d/N.*
O General Emergency O Emergency teemanated hf checked. go to Item 9)
' Item 2. Assistence requestedt kNone. O (no.) Fire Units from .
O (no.) Police Units from .
O (no.) Rescue Units from .
O (Otherl .'
' Item 3. Emergency response actions underway: 1 O None. )![' Station emergency personnel celled in.
% Station monitoring teams dispatched of f-site. O (Other) .'
' Item 4. Evecuetion of on-site personnel:kNo.
O Yes.Eveeueted to .' )
' Item 5. Prognosis of situottons klmproving. O Steble.
O Worsening. O (Other) .'
' Item 6. Release of redsoect.sve meternel O Hos NOT occurred and is NOT proa ected. O Is presently occurring.
es occurred and is now terminated. O la proJ*ct*d to occur.'
' Item 7. Wind direction is from the : Wind speed as MPH.'
.ltem 8. Description of Event C'o M f Out la Ceedde4u A) Noadj kssM A f ~
l
- ! tem 9. This as 6', / E o ro.ms vec A.,
f 4 car Ce - m um.a,u 4 a ,.
(n > ipo..u en
'Please acknowledge receipt of this message.' (Conduct roll cell end check boxes)
M Louise County M Virginia State EOC k Drenge County g Spotsylvanie County Menover County g Caroline County i
'This as North Anne Power Stetson O Control Room O TSC .ll(LEOF 0 CEOF 7 out at timecz4M+.@ on .2 /.l.[/.'!C.'
u..) <a.s.>
NOTE: THE FOLLOWING INFORMATION IS FOR STATE USE ONLY. TRANSMIT TO STATE EOC BY THE
' RING-DOWN' TELEPHONE CIRCUlT.
' Item 10. Areas ef f ected ere:O None.
!'g JR' Sectors and Zones .
j
'I tem 11. Recommended of f-site protective actionst kNone. !
O Sheltering in Sectors and Zones .
O Evocuetion in Sectors and Zones .
I O (Other) .'
' 'This is North Anne Power Stetson O Control Room OTSC O LEOF 0 CEOF out at time on / / _.* i a4 w. um. re.s.> '
son w .cco. evs s-s as
- - ~-- ~ - - - - - L-- ' - - ' - - ----
1 1
1 No.97887220 I
.t NUMBER g/ ATTACHMENT TITLE REVISION Y REPORT OF EMERGENCY TO O AMAMMENT sk STATE AND LOCAL GOVERNMENTS PAGE MESSAGE:
'This is North Anne Power Stetson O Control Room OTSC M LEOF 0 CEOF.
Standby for a roll-cell followed by en emergency message. Use a Report of Emergency form to copy thas message.' (Conduct a roll cell and check the boxes es each party answers.)
W Lousse County M Virginie State EOC )( Orange County MSpotsylvenne County KHenover County g Caroline County I
'The emergency message as es follows: I
' Item 1. Emergency Class: O Notaf acetion of Unusual Event S:t Aree Emergency Declared et i24 nr. u..>
on 2<e.s. / I/U .'
O Generel Emergency O Emergency terminated (if checked. go to Item 9)
' Item 2. Assistence requested: kNone. O (no.) Fire Units from .
O (no.) Police Units from .
O (no.) Rescue Units from .
O (Other) .' ;
' Item 3. Emergency response actions underway:
O None. htetson emergency personnel celled in.
KStetton monitoring teams d2spatched off site. O (Other) .'
' Item d. Evecuation of on sit, personnels,3(No.
O Yes. Evecuated to .' )
}
- Item 5. Prognosis of situetton: M(Improving. O Steble.
"/ O Worsening. O (Other) .'
' Item 6. Release of radioactive meterials Hee NOT occurred and as NOT projected. O Is presently occurring. l Has occurred and as now terminated. O !s projected to occur.'
' Item 7. Wind direction is from the : Wand speed as MPH.
' Item 8. Description of Events bd OG 70 C C
- 2 b '3 d M I
' Item 9. This is #
MN8A -
/
b"" 'd4 CCh /M 8 / .
m ., -
'Please acknowledge receipt of this message.' (Conduct roll cell and check boxes)
Qt'.Virginie State EOC p(Orange County g%Spotsylvente Louise County County gHenoverCounty O Caroline County
'This is North A Po e Station O Control Room O TSC kLEOF 0 CEOF out et tiene M on.2.//[/ M .'
c24 Hr. u ) toes.:
I NOTE: THE FOLLOWING INFORMATION IS FOR STATE USE ONLY. TRANSMIT TO STATE EOC BY THE
' RING-DOWN' TELEPHONE CIRCUIT. ,
.it.m 1. Ar.as of f ect.d ere,0 Non..
pfSectorsandZones g g j j ,9 .
' Item !!. Recommended of f site protective actions:
K None, O Sheltering in Sectors and Zones .
l 0 Evacuation in Sectors ed Zones * '
C O (Other) -
'This is North Anne Power Station O Control Room OTSC D LEOF 0 CEOF out at time (24 ne,u on i
/ / .'
to.s.
forEWRCV.DCat NAPS /2 6-S*85 an e Am .m aame n s M am M.m m e eM . A .--m A_.__ .__---naen sma. h ._wmm.-4.. n.rt_mM _mm_. _mmm _-__.a
]
No. cl7887220 NUMBER ATTACHMENT TITLE REvls10N
/"
\
AMACHMENT .N */ REPORT OF EMERGENCY TO STATE AND LOCAL GOVERNMENTS
'NE s
MESSAGE:
'This as North Anna Power Stetson O Control Room O TSC k LEOF 0 CEOF. :j Standby for a roll-cell followed by en emergency message. Use e Report of Emergency form to copy this message.' (Conduct a roll-cell and check .the boxes as each party answers.)
M Louise County )l( Vargante State EOC R Orange County y Spotsylvenne County M Hanover County K Caroline County
'The emergency message is as follows:
' Item 1. Emergency Class: O Notification of Unusual Event Aree Emergency Declared et on 2 /I,_I/ E .'
O General Emergency '2'**"**' '
O Emerg ney terminated (if checked. go to item 9)
' Item 2. Assistence requested:MNone. O (noJ Fire Units from . 1 O (no.) Police Units from .
O (no.) Rescue Units from .
O (Other) .'
- ! tem 3. Emergency response actions underwegi O None. M Stat 2on emergency personnel celled in.
XStetson monitoring teams dispatched off site. O (Other) .'
'I tem 4. Evacuation of on sate personnels)(No.
O Yes.Evecuated to .
' Item 5. Prognosis of situation: Mlmproving. O Stable.
O Wcesening. O (Other) .'
' Item 6. Release of redsocctive metersels l 0 Has NOT occurred and is NOT projected. O Is presently occurring.
Has occurred and is now terminated. O In proJ*cted to occur.'
' Item 7. Wind direction is from the I Wand speed so [ MPH.' .
' Item 8. Description of Event: Ce ^* E D C* bd 4!
- Item 9. This as b' / MEW 1 / b4 0 *M /" V .
in .) -
<p . uon)
'Please acknowledge receipt of this message.' (Conduct roll-cell and check boxes)
ALouise County MVirginia State EOC M Orange County K Spotsylvenne County pt'HonoverCounty k Caroline County ,
'This as North Anna Power Station O Control Room O TSC A LEOF 0 CEOF time /*W on _2. //,O._ f_,'2.' l
[l out et (24 +. um.) ice s.i NOTE: THE FOLLOWING INFORMATION IS FOR STATE USE ONLY. TRANSMIT TO STATE EOC BY THE
-i
- RING-DOWN' TELEPHONE CIRCUIT.
'i t.m ie. Ar.es af fected ere O None.
.gSectorsandzon.s ggj j g j'</g .-
' Item 11. Recommended of f site protective octaons:
\ y Non..
t O Sheltering in Sectors and Zones -_ = .'
O Evacuation in Sectors and Zones
) .
.- 0 (Other) .
'Thts is North Anna Power Station O Control Roost O TSC O LEOF 0 CEOF cut at time on ,,,,,, / ,,,, /.,__ .'
(24 *. t ) (d.t.)
TDFE4RC1.DGN NAr$/2 6*6-Os
_ _ > _ .x__.a e ___.-_1.au 3 M aw o w wmmm.s s. . . _ -_ _ _ _ ..
No.97887220 NUMBER g ATTACHMENT TITLE REVISION l 8 REPORT OF EMERGENCY TO
.( AMACHMENT STATE AND LOCAL' GOVERNMENTS NE MESSAGE: ;
'This as North Anne Power Stetson O Control Room O TSC M(LEOF 0 CEOF. j Standby for a roll-cell followed by en emergency nessage. Use a Report of Emergency '
form to copy this message.' (Conduct a roll-cell and check the boxes as each party answers.)
A Louise County Virginia State EOC p Orange County pt;Spotsylvense County Hanover County g Caroline County
'The emergency messege is as follows:
'ltem 1. Emergency Class: O Nottf acetson of Unusual Event Area Emergency O General Emergency Declared at (2 4 +. u..> on.2/Y,/E.'
en.
O Emergency terminated -(if checked. go to item 9)
- ! tem 2. Assistence requested: kNone. O (no.) Fire Units from .
O (no.) Polsee Units from .
O (no.) Rescue Units from .
O (Other) .' j l
i
' Item 3. Emergency response actions underway:
O None. Station emergency personnel called in.
gtetson monitoring teams dispatched of f-site. O (Other) .'
l ' Item 4. Evecuetion of on site personnels)(No.
l 0 Yes.Eveeueted to .' '
i ' Item 5. Prognosis of satuottons klmproving. O Stable.
l Q O Worsening. O (Other) .'
l
- ltem 6. Release of radioactive meterial:
O Has NOT occurred and is NOT projected. O is presently occurring.
MHee occurred and as now terminated, O la proJ*eted . to occur.'
' Item 7. Wind direction is from the : Wand speed is MPH.'
' Item 8. Description of Eventa #5** N Ad M*#mAk Cd1S 'I # ' CW D 0) b EN:f i /I d1A,5c, b d&
' Item 9. This as O' OIMEM / S*D Md .'
in > V <po.i u on>
'Please acknowledge receipt of this message.' (Conduct coll cell and check boxes)
M Louise County arginio State EOC A Orange County KSpotsylvenne County Hanover County g Caroline County
'This is North Ann P e Stetson O Control Room 0 CEOF out et time OTSCkLEOF 24 . b ,on .,2e/f.,.,/d .'
h0TE:THE FOLLOWING INFORMATION IS FOR STATE USE ONLY. TRANSMIT TO STATE EOC BY THE
' RING-DOWN' TELEPHONE CIRCUlT.
t
'I tem 10. Areen ef f ected are:O None.
ASectorsandZones , j ,
' Item !! Recommended of f-site protectave actions:
MNone.
O Sheltering in Sectors and Zones .
t O Evecuation in Sectors and Zones j
.' )
) 0 (Other) *
\ {
\ 'This is North Anne Power Station O Control Room OTSC O LEOF 0 CEOF )
3 out et time on _,_ / ,_ /.__, .'
124 Mr. hm.1 I (d g.: 4 TDFE48tGY.DGse NAPS /2 6-s 86
i No.97887220 i NUMBER ATTACHMENT TITLE REVISION
,n
/\ REPORT OF EMERGENCY TO Q
ATTACHMENT p PA E STATE AND LOCAL GOVERNMENTS l MESSAGE:
'This is North Anne Power Stetson O Control Room OTSC kLEOF G CEOF.
Standby for a roll-cell followed by en emergency message. Use e Report of Emergency form to copy this message.' (Conduct a roll-cell and check the boxes as each party answers.)
Louise County M Virginia State EOC k Orange County Spotsylvenne County (Hanover County Coroline County
'The emergency message is es follows:
' Item 1. Emergency Class: O Notaf acetion of Unusual Event O St Area Emergency Oeclered at O on /
/b.'
O General Emergency I MEmergency terminated 4f checked, go to Item 9) )
i
- ! tem 2. Assistence requested: O None. O (no.) Fire Units from .
j O (no.) Police Units from .
l C (no.) Rescue Units from . i O (Other) .' l i
- Item 3. Emergency response ections underweg 1 O None. O Station emergency personnel celled in. l O Station monitoring teems dispatched of r site. O (Other) .' i j ' Item 4. Evacuation of on site personnel: O No.
l 0 Yes.Evocuated to _ .
{O A-
' Item 5. Prognosis of situation: O Improving.
0 Worsening.
O Stable.
O (Other) .'
I
]
' Item 6. Release of radioactive metersel: '
O Hos NOT occurred and is NOT projected. O Is presently occurring.
O Has occurred and is now terminated. O In proJ*e ted to occur.'
l
' Item 7. Wind direction is from the : Wind speed as MPH.*
' Item 8. Description of Events O M i b' M /*'
l
' Item 9. This as -
/ b + b * .
)
% in .) iposiuon>
'Please acknowledge receipt of this message.' (Conduct roll-cell and check boxes)
Louise County Virginie State EOC M0renge County Spotsylvense County Hanover County Caroline County N \
$'This is North Anne P wer Station O Control Roorn O TSC )(LEOF 0 CEOF
- I out et time a4 O
~. 3 u >on .Z. /I)[Z .*
io.
NOTE: THE FOLLOWING INFORMATION IS FOR STATE USE ONLY. TRANSMIT TO STATE EOC BY THE
' RING-DOWN' TELEPHONE CIRCUIT.
l ' Item 10. Areas ef fected eresp None. l l 0 Sectors and Zones .' l l
l
- Item 11. Recommended of f site protective actions:
l ,G None.
l .
O Sheltering in Sectors end Zones .
l O Evacuation in Sectors and Zones
- l (S) 4 y
O (Other)
/
N 'This is North Anne Power Station O Control Room O TSC D LEOF O CEOF i out et time on l
/ /._ /
l c4 +. u > co.s.
'0 fen (RGv.DGN
- SAPS /2 6-5 85
.e. . .. . . J-_. - . . ~ - _ . s .
^
RADIOLOGICAL STATUS O Bened on .f r. site 3,.e,. es.d on aediciogioni monitoring s,s m d.te TIME T, REND
- i. rv ,e or reises. is airborn.. ,eieased et eie.etion of -
( t. et#
C Waterborne O Surface Spall.
le. Physseel form of release is O gens O laquada O solads O unkno.n.
Ib. Chemical form of release se O inert noble gases: O radionodines: O unkno.n.
Specific ally
- 2. Reloos. O began at dbO e24 ar, u >
0 ia estamete to began et asu.u ,
- 3. Release duration .es f' b , hours.
O as estameted to be hours. p 4 Tim. bet. n reactor shutd..n and beginning or e.i.e.. .es N A hours O not opplicable.
- 5. Wind direction from MO wind speed se O M PH. Stobility class is .
- 6. Temperature is b Y oF. Precipitetson form is one O R.in O Sleet O Sno.
O (Other) .
- 7. The ladine/ Noble Gas Retao is U O Unkno.n.
- 8. Projected total release equivalent Curses of 1-131 is M Curies.
{ O Unkno.n.
V _ a.
( 9. Projected total release equsvalent Curses of Xe-133 is O Curies.
0 Unknown.
- 10. Aewel whole Body dose rete et the Site Boundary se mR/hr.
O Unknown.
I
- 11. Estimated Whole Body dose rates are O A/ w (
mR/hr et Site Bounderv. %
I mR/hr et 2 miles.
- / mR/he et 5 miles.
\f/ mR/hr et le miles.
OUnkken.
- 12. Projected total integrated Whole Booy dose is c A/M mR et Sat. Boundary.
. .t 3 m .
Ii ma et s ,,ge,,
W mR et 10 miles.
O 9mkiwi.n. !
- 13. Projected total integrated Thyroid dose is O mA et Site Boundary.
, .e I mR .* 2 mi,...
/ mR et 5 miles.
-'I mR et 10 miles.
O Unknown.
gg h *N bb OPM/100cm2 in g,n, $
- 14. Actual surf ace radioactive contaminetton is O O Unkno.n.
g' '
- 15. Steven conditions are es folio.si 1
(A*H h$ ^'!' bhbO A A&
- 4. th D C ZS_ e l /e ZA YO 7~S Ge i QA Originel Recovery Manager Pinks Reanologice! Assessment Coordinator Yello.s State forEMEstGY.DGNne' 6-4 87 l
___.__.________.__.__._24.-1.w.wa In -
- L ^ " - - ^ ~ ^ ~ ^ " ^ "
~
g W8 09//
RADIOLOGICAL STATUS g
a 8.s.d on orr. site sor...,e e.ed on me dicl.gieel monitoring syst.m de'*
TIME L TREND-
- i. 1 e o, e.l..s. se. 4 b _ e. ,el.es.d e,el..e _ o, o .,.,,o-o O Surf ace Spill.
.og.
l e.
Physical form of release as O gets Q liquidi' O solads O unknown.
- a. Ch.m..ei roem or reiease is o in.rt nooie , eses, a radio.odiees, Spe iriceit , =
i o - eo.n. !'
- 2. Release D began et O
- a. . uw .
Q is estameted to began et .
44 nr. sp.o*
- 3. Release duretaon as l' ___ hours.
O is estameted to be hours.
4 r I Time bet =*en roector shutdown and beginning of release mes 6J /' A hours 1
(
O not applicable.
- 5. Wind direction from . Wind speed as A MPH. Stability class is '- b .
- 6. Temperature :- N
- F. Precipitation form is ne a Rain O Sleet O Sno.
7 The lodine / Noble Gas Retaa is Er [ .
O Unknowm --a-in.
- 8. Projected totai release equa.elent Curies of I-131 is F bN0 Curies. OY/O V O Unkno-o. .
,co,.c.d _1 r.l..s. e,u..el.nt C.i.. o, ..!>> is An e 2.c. i.e O Unknown
. oew # tL.
- 18. Actual Whole Body dose rete et the Site Boundary is O M mR/hr.
O Unknown. %
- 11. Estameted Whole Body dose rates are l
mR/hr et Sate Boundary. .fI y >
I/ .-mR/hr et 2 miles.
_mR/hr et 5 miles.
Y __ mR/hr et 18 miles.
O Unknown.
- 12. Projected total integrated Whole Body dose ism MM i mR et Site Boundary.
mR et 2 miles. %
I
'V mA et 5 mies.
._ mR et le miles.
O UnEno.n.
- 13. Proa eted total integrated Throid dose .is M __ mR et Site sounde,y .
. t , m, .s. _
I' mR et 5 miles.
mR et 10 miles.
O Unkno.n.
- 14. Actual surface radioacts.e contamination is PM/100cm2 in y,ne . ,
O Unknown. .
IS Station condittons are as follows:
- i. 2.9 % CSr kw xn ,
A/w L~rd ori,insi, Reco.org eneo.c Pinks Radiological Assess.eent Coordinator Yello =i S tate TOFEMERG f.DCN/74 6 4*87 9
___ _ _ _ _ _ . - - - - - - - - - - - ^ ' ^ ^ "
j
,f.-
h i
RADIOLOGICAL STATUS k !
a s. d en otr..te ..v. a se.ed on Radiologie=1 monitoring svitem da'* /
1 TIME - TREND
- . Top. or e.l...e i. W Airborn.. c.1.e..d .t .i. .uon or _31"L rs. 0(rW a w.terborn. q o surr.e. ss,ill. ,
!a. Phvoical form of role.se se % gees a laquad: O solada C unkne.n. {
lb. I Ch.mical form of' release se % aneet noble gases: O radionodiness - O unkno n.
Specifically
- 2. Release )L6egen et W .
124 fir, tsanes D is e.timated to begin at .
1
.W 4
- 3. R.i..
dur.uon Je. /3 ho-c i. ..umeted to 6. hour..
4 Tmo b.t..en.. to shutdo.n end b.ginn.n,or e.ie . . / O q hour. -
O not applicable.
dS3f- t i- ,.re.t,_ <com a .wi~.p..di. e.o - . .. . t. . l e.e . o . i
- 6. Temperature as eF. Precipitation form asMNone O Rain C Sle.t C Sno. f O 10thee) . l
- 7. 1 The todane/Nobl. Ces Retao se O .
a unkno.a. --->= j t
- 8. Projected total release equa.alent Curie.~of 1 1318. O N C -i.e.
N
' V e.
O unknown.. I j
R. pro,..t.d t.i ,eie . e ui..ient C,,e. or x.133 is #6 32 C-2.cu,,e, O Unknown.
i } ,__,, i1
- 19. Actual Whole Body dose rete et th. Site Boundary t. d M ,,._mR/hr.
Q Unkno.n.
,,. e.umeimi..o,d...c....r. / w mR . e,s .. .o ~.: i I-mR/he et 2 miles.
_mR/hr et 5 mil.s.
.. tL_
Y
_ mR/hr et le miles.
O unkno.n.
- 12. Projected total antegrated Whol. Body do.e to mR et $ste Boundary.
mR .t 2 m .
mA .t 5 miles, mR es 18 male O Unkno n.
- 13. _Peojoeted .
total integrated Thread done i. g. h mu R at Site Boundary.
mR .t 2 mii...
mR et 5 mil.a.
mR .t 18 miles.
O unkno.n.
,.. .,, .c.do..u... t. min.t.oni. a % ,, m.,e2_.
0 Unkno.n.
t4-
- 15. Steuen condiuono are as follo. 6
%2 ~
- n 7'r/ i.,
Originals Reco..ev Maneg.e P nks Radiological Ass.ese.nt Coordinator i
Yello.,$t.te f0FEMEstCT,0GN/76 6. a.8 7 l
l l
l
- _f" ii ar t
-/W1
(-
o ..s.d - o,f...t. ..
RADIOLOGICAL STATUS o a...d oe a.d oio >..i mon to in . s-m d.t.
\
,. , . .f ..,.. ,. ,A,, b-.. . .,....d risc Tatso > <
>1. ,
O W.t.rborn.
. t .] ... t,- .( f,.
een d O sef.e. all. %
l., Physic.1 form of e.l.. a.
i
.se Q Inqunds O solac O unknows 1 lb. Ch.mic.l form of c.l..o. na snert nobl. g ..s (
Spectfic elly C r.dioiodiness C unknown.
j
- 2. R.1.... ' /b.9.n et -- #MO 1 as
- w . .
0 is .stam.t.d to b.gan .t -
') 3
- 3. R.I..s. dw.uon F..s-~l> I hov O is .s tam.t.d to I,. hour..
4 Tim. bwtw n c..etor shutdown .nd b.g:nning of e.l.... .a 0 - $
- hours [4
, Q not .pplacobi..
- 5. Vand dir.ction from . Wnad op..d 1. -
mph. Stabilatw cle.* is Mb
- s. ,.m . t.. ,. 4 y .r. e...,,,t. .n f.n ,. du.n.
l O R.s.m __-
0 Sie.t O Sao.
v c coth.,)-
7.
rh. rodin./>.obl. c.. R.t.io .. [ -_ M O .
4 {
O unwno n. ,
I V -> l
- 8. ero, ud tot.ir i.. i
...i.etcu,... ori.iali. d'S e @ c ,...
9 C Urknown.. ih _ {
i I eo,.ci.dtos.i,.i.........i.ntco..%1..iaaydal2E-2c,,. i V I O;Vr*nowri. f h ,_,
- 10. Ac tu.) Whol. Body do.. c.t. .t th. Sat. 84 vnd.cy i.
NEk mR/tv .
C Unkno.n. , -l l 11. Estam.t.d whol. Body dos. c.tes .c.
d #M__ mR/he .t Sat. Bound.cy.
mR/hr .s 2 milan. s!
mR/hr .t if ml.ra mR/hr .t 19 twie.s.
O Urenown.
- 12. Pen.!.et.d total int ge.t.d whol. Body dos. is _ )(#'>t l"#
__ oft a s Site Bound.ry.
R .s 2 mal.s 14 .t 5 mal.s.
mA .s10 mil.s.
O Unkno.m
- 13. Proa.et.d tot.] ant.gr.t.d Thyroid do ao i N mR,A.h.tbx So.nd.ev. m.t...
mR .t5 ed. ;
_ _ mR .t 18 miles. '
'i. I C Unknown
,.. n .,. ,,.....d....t.......
,. A m o n , a ,n 2-. i i
fl_
.-.t,-
/,
O Unkno.n. .
- 15. St.tson con i tions .r. .s folloosi c
- hnWe T 1 OS$
~~
Origin.1: R.co.ecy Man.g., L _, s-~N Pi nks R.diologic.l Ass.sse.nt Coordinato,
- x Y.llows St.t.
v f 0FEME %f.DCN/7. 6-d
- 8 7 b
. j
,, , e.... k
- _ , ,
, -.,___..,. .-- . - ~ --
, _ _ _ , _ _ _ _ _ _ - . - - - - ^ ^ ^ ^ ' ^ ' '
. 1 4
. m..
RADIOLOGICAL STATUS Uttk' j
k e.e.d on err-site surveve D Based on Radiological monitoring ovetem d*'*
p .
TIME TREND
- 1. Type of reises. se % Aarborne. r ire.ed et elevation of 87 f t. IIM
) t D Waterborn.
O Surface Spill.
l e. Phv.ie.1 form of .l e. is ,3( ges, a ji.edi a solie is. ch.m .el roem or ,eiese. is A in.rt nobi. ..e.
a urano.n.
a r adio.od.n... o or*no.n.
.#M sp.cificelle . . .
' {
- 2. Release M began et. O b 3 0 .
,' ga ein v.
O is sett ested to bs gan et -.
- 3. Reloose dwegaon M es
- hose.
' D se estimated to be hows. -
4 1,m. n ...o,.c .,e- be.. .-g .,r.ie.a. ..e Z a _ h..e -
er i
..-.r.._ , rom a . . - e. d .e s - , e..).t. .).se .e o. f j m T _. t.. .. a o ,. ,r....._on
<.rm ..oon. O Rain O $ lees O Sno.
O (Other) .
- 7. A Th. lodine / Noble Cao Retao se
.. " ===a>
l o ura no-o.
- 8. Projected total release oosivelent Curses of I-131 is C<ies. i O Unkno.as
- a. er.;..t.d iot.1 c.iees. .R..vei.et c. ries or x..i32 .e d 3m C., em otW-
{
0 Ur*no o. i I __.
la. aetool whol. soe v dos. ret. .t th. sit. sounaarv is [#, O L 0 Ur*n mR/hr. /008 h- 4
- 11. Estameted Whole Body done rates se s $ O* 0Ee A
' mR/hr et sie Boundary. ,
mR/hr et 2 males. t Y %
I 1 mR/hr et $ mal.a.
mR/hr et 18 males.
O Urano.m.
- 12. Projected towel integrated Whole Body does se mR et Site Boundary.
I ---
- mR et 2 milee.
I- mR et 5 miles.
' W mA et 18 males.
C urino.m. .
i
- 13. Projoeted total int.greted Thy old dos. is
_ mR et Site Boundary. .
mR .s 2 m.,.e. - e.
h mR et 5 miles.
O mR et 18 m:1.o.
O Ur*no n.
- 14. Actual safece radioactive con + aminationin Zone I se lND$~OPM/190cm .
S' V %
y 0 Unkno.rs
- 15. Steuen cond taone are se folls as d_b% A='A/ od
)
Originali Recovery Meneger Pires Redsologicel Assessmenf g f fisorcinetor
!t Yello e State forEMERGY. DON /7e 6-4 87
.i' L
g f.
, , ,.. e n - n", h '~' * *" "*' . . _ . _ . . . _ _ . _ . ,-=- -
'} - :. .. _ __
g6 I
( RADIOLOGICAL STATUS O B...d .e R.dtolo9sc.I monitoring 0 B. sed .n .f f- it. .ur..v. .v.1** d.
TM Tp0
- 1. Tup. or e.l.. i. dirborn.. r.1....d .t .1... tion or 127 r t. /0.30 a w. wroorn.
O surf.c. 5p:11.
l Phy.acol f orm of e.l.. a. I/,e.,t
..: no 01 rausds
- i. ......
C .olids D unkno.n. M is. ch.mi..i rorm or r.i.... .. a r od,0. d.n.., o unkno.n.
g so.ca...u.
- 2. R.i.... o ,.,_ .t a .. t.m.t om
,o ..,,n .t j
- 3. R.I.. dwr.taon ET . /
- D.n* hour.. __
D i .. tam.t.d to b. hour..
4 Tim. b.t. a r..ctor .hutoo.n .no e.g.nning or r.l. . . / O hour.
o not .ppi.e.e!..
S. Wind dar.ction from . Wind .p..d i. _
/ MPH. Stobality cl... a. -- . /O F
- 6. T.mper t.. i. b
- F. Precipit.tnen form a. N on. /@
C R.in O $1..t O Sno.
O (Oth.r) .
a 7 Th. todin./Nobl. C R. tao n. bIW . .08 -t*
a unkno.n.
p
.r.- . t., r .> . ... ... . . .n t c. . .. o, l . ,,, . . < woc ...
D Unkno.n.
"l _
tJ
~
,. .ro,.c t.d ,ot., r.:. . ..... .nt c.i.. o, .... , i. om.1 c... tL.
O Unkno.n.
- 10. Actu.1 Whole Body do e.t. .t tt,. Sat. Bound.ry s. AOb mR/hr. 10 %
O Unkno.n.
,,. <.t m. . d . .>. .o do.. c.t.. . . so.oz mR .t ,,,. .o_d. , '
ti_
mR~ ., , mai...
mR/hr .t 5 mil...
mR/hr .t 19 mile O Unkno.n.
- 12. Prea.es.d tos.1 int.g-.t.d Whol. Body do i. [M mR .t S:t. B.und.ev.
. me .t mii...
le mR .s 5 male f mR .t 18 mil...
O Unka..n.
- 13. Peny.et.d tot.1 int.gr.ted Throad do i.
MN, mRme.t.,,$st. mii.
Bound.ry.
I' mA .t 5 mile..
W mA .t 18 mile D Unknown.
- 14. Aeto.1.urf.c. c.dio.e ta.. contemen. tion i. _ DPM/190cmI in Zon. . ,
C Unkno.n.
- 15. St.taan condition. .r. .. f.11os se h "__ ' Y OD Origin.11 R. cow.ey M.n.g.e Pi nks R.: $ologic.1 A.....m.nt Coordan. tor V.llo.:St.t.
?!MME str a f.DGNM4 6-4-87
......y_. . .
w-r- __ _
- T
- c ~,
s .
i
. L,. -
RADIOLOGICAL STATUS j N d en Str..ite oor. .
o see.d on abete,xvi .=torino . .et.m e*"
3 i. T,oe a 2e,e. <e ed., borne., ele.,
TIME TREND O wer.14eborne d et el..eu.I IT br JAL.
O Selece tent $ ^
te. ' Phyncel ferm ' .
releeen <a (f *e, l D laquad D 4 1sds 1 lb. Chemical form or centsee se Speca ric ell gr43 7s noble geoess C rsh uisciness O unknown.
O unknown.
MM
, w- /- I l
l.es. - et .
ug _.
I
- D .
- . e,%eatuL, to begin at 4
- s. n,. u.,w. .
/
- 3. n.i. , e ,euen d' e.'._ 4 k_ hour
, 4 s
- - me.eu.s.tedtob._ .._
ho-o.
4 tim. b.t. n ..eter e.,utuo.a and 6.g nning ir e,ne e g.
c ..J ., . >a,.
~'
O not @plame'
- 5. Wind direcuan fe'ea N Wed speed as-- . MPH. $t g e; sty o'd e- .
- s. Temperet ,e se T i* F. Precipitetson fore: se O None .i ,
O Rain jb , i D Sleet ~
s 1
/
O Snow <
O tot > er) - \ "' '
- 7. . - . .
The ladin,/ Noble Gese Retae se dj O IN nowrw .-,
.f I etr. '
B. Preyvited total release oca.wel.ns Curica of I-131 is t. .
- O unkne.n.
_ Cases.
\J ,
,. m . y otelr.l.ee. . _ .l.ns C.e,.e o,
,[ .. m as o a s 4 c...
Q ,', "** M_ t
- 10. _Actuel Whole Body dose rete et me $ste Boundary ss#
O mA/hr.
, C known. / % j j(
- 11. Eeumeted whole Boog oose rates are h"'l dI.'Imn et
_._.._ mR~ e , Site Bounderw. m,i.e.
,__mR/hr et 5 miles.
anR/hr et 19 milee.
Q 1)nkneure.
12 Prometed total integrated Whole B.4
. I 9 uses at O mR es mR .t .$ste me,.Boundary. -a
-1 mR et 5 miles,
_ mA et 10 milee.
/ ; Q tMnown.
13 pge,,,te,d total intoyoted 7turoid dose se 0 M mR et Site Boundary.
_. mA ; et 2 ast.es.
~ ._ e4 e3 4 miles. ,
~ .. _ mR et .9 railee. '
- 3 Jnkno*% t' f
] 3.s. t.ei .,<e.e s red,oe.u.. ..ntemineuen is o .__ oPmmem in z.. -- b
.15. Steuen condicone ore as follo...
n .no.n. .
i I_ i
- 8. N O .
_ _ _ _ w
,s-Original Recow.ru Manager _ - -
Pi nks Radiological Assessment Ce6rdaneto-f i.
Yellow State i h' (
- s. TDFEMERCV.DGNne 6 4 87 2 5 .
/ .Y g :6 y'
3
- a. y .( ,
,,....~--a-~~'"
Y
~'~ _,, . . . -. * - " * ' * "-
s _ _ . _ - . _. _______.____w
O. I
\./
O. RADIOLOGICAL STATUS
~
[s.enofrentee,. eve a e d oa namelosieel monitorias evet.m a*'*
TIME TREND
,. . . . , . . , . . . . s .rb n.... ... .t .,... _ ., m u - j o Wesorbore.
O Surface Spill. 1 t e. Phyencel form of roleseo se [ pes Q 1: quad O solida D vnknowm NN Ib. Chemical form of release no Finers noble gemeen O radionodiness D unknown. (
Specifice!!y I - - - -
1
- 2. Release D began at .
o so .eum.t.d - b. gin et .
- 3. Relenae dsouon duae I' hours O no enumeted u be hours '
4 Time beteeen remator shutdown and beginning of release =*e [ hows O not applicable.
- 5. Wind direction from N . Wind speed so HPH. Stebality close is . /A//
- s. Temp.reture se N o F. Precipatetson fores is None /18!
O Rain O Sleet O Snow C (Otheel ,
n
- 7. The lodine / Noble Coe Re+.ie is . OM "
---en.
O Ureno m I
- 8. Projected t.otal release ecuivalent Curses of I-131 to NN Curnom W V_
o unkno.n.
C') ,. Pro,..t.d t. ! r.1.o.. .,_el.nt C.I.e of ,e.,2, se Me-, C,s.
D Unknown.
a H __ '
I
- 19. Actuel whole Body does rete et the Site Boundary no / O 'O D mR/hr. /
Unknown it.fsum.t - e eo ,do.. c.t. .r. a M mR,-etSat..ound.e,. '
t Lo. -
mR/hr et 2 miles, mR/hr et 5 miles.
mR/hr et 19 milem O Unknown.
- 12. Projected total integreted Whole Body done is [ N mR et Site Boundary. ---> l
., , mii.e.
i mR et 5 milee. '
mA et 19 miles C Unknown.
- 13. Projected total integrated Thyroid dos. is F 2#dd mA et Site Boundary. - - >
- n t , mi, ...
mR et 5 miles, mR et 19 mitee. ,
C Unknowm j
- 14. Actuel eurf ace radiometive contaminetton is dd N DPM/190cm2 in Zone .
O Unknown. I is. sieuon .on uona are en rono.es ld6 m &,e lr42 oerD '
O.fo2 % 7~5 (/2!lb) s orig,eal Reco.or, sene ee 74-me.sy e-2. ci 7 3i
\
Pinki Radiological Aeoessment Coordinator /,75 5 -t 70 W Yellows Steto TDFEMERGY.QGh/7e 6-4-87 )
i l
m eeses. t.e+yople.* , e Amp-Wehm+99s*mse m esper4y age =* D94.P.**W'D. * * = *ww . * * - ' g meme
l
.- . .)
1 y -
4A e l A RA010 LOGICAL STATUS Ig s
ene,f... .w. . o 8..ed . d.elo,,.ei monit.cin. ... _ d.t. {
O- 1. > e of ..e>ee eO Waterborne.- e.rboerelesedteleauoof>27 f t.
1 1:se 1,esa O Surface Spill.
le. Phyencel fwm of releen. 4e oss Q laounds O solad O unknown.
Ib. Chemical form or release in W ineet noole gases: O radiciodinew Specifically Q unknown.
- 2. .lelsese Ybeganat fA ,
a i. e.um. sed to be,in .s - .
- 3. Release duretion se -- /'
__ hows. j o .o e.um.ted to b. hows. __
4 rime bet.een ,.e tn. .hutdo.n and b.,,nnin, of ,.ies.e ee v O hou, .
O not applicable.
jd L Winv. direction from # . Wind speed se MPH. Stabalsty cleos to -
- 6. Temperatwo se -
[2I D __e F. Precapatataon form seMNone 'l O Rain ../ N[
O Sleet O Sno.
O tother)
- 7.
- The lodine / Noble Gas Metae as WM d W
0 Unknown. 0 V
- 8. Projected total roleseo emovelent Curses of !.131 se NW O unknr,=n.
__ Curnee. ~
08N V 9
Projected total celease equi.elent Curses of xe-133 is d E N" E .
3 Curses. #2 IIe 4l l 0 Unknown. t %
- 10. Aewel Whole Body does rete et the Sste BoundarydeseOM y n..~
.mR/hr. f300 ff
,,...um.t., ~ . .o ,do.. ..te. .r. a . .t ,_ _ der. ,m R~ .s 2 m:1.
mR/hr et 5 miles.
tL.
_. mR/hr et 10 miles.
O Unknown.
- 12. Projected total integrated Whole Body dose as [- 2d
_mR et Site Boundary, f mR et 2 mil.. .
__ mR et 5 miles.
mR et 18 miles.
O unkno.n.
- 13. Projected total integrated Thiroad done is W _mR et $ste Boundary.
mR et 2 mine NO _
_. mR et 5 miles, mR et 10 males.
O Unknown.
- 14. Actual surf ace redseecuve contaminetton as k OPM/100cm 3 an Zone -
O unknown. .
/M ,,,. !
1% Steuen conditions are es follower j I
LWF T& k$ 0$1"'O O , C,2 4 i
i "T".S Originals Reco ery Meneger l i l P nk: Pedsological Assessment Coordinetoe Yellows Sta to TDFCMERGY.0GN/7e 6-8 87 l
.__ . . . - , . . _ . . . . . . . . _ . . _ _ . . . . . ._.._w I
_ m)
. 1 1
L41 RADIOt.0GICAL STATUS ed. don.ff.eitesor.oy.
O 1. T e o, releeso .e a e ed on Red.eiogieel monitoring ovetem dose .
s borne.r.l.a.e
._b n.
et ele.e - of ~~
TIME o-TREND 0 Suriece Sp 1 le. Phymeal form of celease in Q headt O nohdi D unknown.
Ib. Chemecel form er celeone is nort noble genes: O radiciodinese O unknown.
Specifically
- 2. R.i..se - Men .t No
- a. ,. . . . !
O is estimated to begin et .
- 3. Release dsesion de /I . hows.
O is estimeted to be -- hows.
- 4. Time between eseotoe shutdown and beginning of reloose wee O M not opphcable.
_. how e hb
- 5. Wind direction (com - . Wind speed i, MPH. Stebalaty cleos is .
- s. T-ot,e is 7f or. Preon,itet. n rorm se /~.n.
Q Rain Dif O Sleet Q Sno.
O tother) .
7.
th. todinen bi. ca. R.us i. / Estd a o unkno.n.
Od'N " - m. ,
l
- 8. Projeoted total release owevelent Curies of !*l31 se [-
o una -
Cur ses.
ON V e.
ro,..t.~.el ,.l.ee. .. .el.nt C. .. o, ..133 se ue- < C.,e tL O Unknown.
- 10. Actual Whole Body done rate et the Site Boundary se [ N Ok
~
O nown.
mR/hr. 8 00 %
- n. ceume- whoi. ... dos. v.m e,e /6ud '
i R,, e, S,,e oo,de,,.
mRoo. et 2 miies.
eoo i 4 _,,
l mR/hr et 5 miles.
mR/hr et 19 miles.
O Unknown.
- 12. Projected total integrated Whole Body does se [NM
.__ mR es $nte Boundary. I50 .-e.
mR et 2 miles.
- mR et 5 milee.
mR et 18 miles.
O Vnknown.
- 13. _ Pro;eeted total intoyoted Throid does se EM ._ mR es $ste Boundary.
mR et 2 mil., 11 N %
mR et 5 miles.
. mR et le miles.
Q Unknown.
{
- 14. Actual surface redsoective contamination so I I M D Unknown.
._0PM/100cm2 in gon, , f3h ,,,,,,,,
- 15. Steuon conditione are es follo se )
qw rw4 stro an /, o rs Originah Recoveev Meneger 1 Pinks Radiological Assenement Coced4netor Yellows Stoto
- )
) TorEMERi,Y.0GNne 6-4 67
, ._.,4 "-*--a _ . . . , , , . . . . .
. _ . , l
_ _ _ _ - _ _ - - _ _ _ _ - _ _ _ - - - - - - - - - - - - - ..