IR 05000409/1982002
| ML20041E592 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/26/1982 |
| From: | Axelson W, Madison A, Pagliaro J, Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20041E585 | List: |
| References | |
| 50-409-82-02, 50-409-82-2, NUDOCS 8203110124 | |
| Download: ML20041E592 (17) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION III
Report No. 50-409/82-02(DEPOS)
Docket No. 50-409 License No. DPR-45 Licensee: Dairyland Power Coo;.orative 2615 East Avenue - South La Crosse, WI 54601 i
Facility Name:
Lacrosse Boiling Water Reactor Inspection At:
LACBWR Site, Genoa, WI Inspectior. Conducted: F ruar 10, 1982 l'lf LAhU
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Inspectors:
A. Pa liar
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t M. Madison /
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Approved By:
W. L. hx s n, Chief 1 1S g 2.
Emergen xPreparednes Section
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C. J. Pape fello, Chief Emergency Preparedness and Program Support Branch Inspection Summary Inspection on February 10, 1982 (Report No. 50-409/82-02(DEPOS))
Areas Inspecten:
Routine announced inspection of the Lacrosse Boiling Water Reactor emergency exercise involving observation of key functions of the Emergency Operations Facility and the Technical Support Center during the exercise. The inspection involved 12 inspector-hours onsite by two NRC inspectors.
Results: No items of noncompliance or deviations were identified. Adequate functioning of the Emergency Operations Facility and the Technical Support Center was demonstrated.
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L B203110124 820226 PDR ADOCK 05000409 G
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DETAILS
1.
Persons Contacted NRC Observers and Areas Observed J. A. Pagliaro, Emergency Planning Analyst, Emergency Preparedness Section, Region III, Emergency Operations Facility (EOF)
A. Madison, Resident Inspector at Monticello, Technical Support Center (TSC)
Dairyland Power Cooperative
- J. W. Taylor, Assistant General Manager - Power, (DPC)
- R. Brimer, Electrial Engineer, (LACBWR)
- L. Goodman, Operations Engineer, (LACBWR)
- T.A.
Steele, Director, Environmental Affairs (LACBWR)
- Eric Hennen, Environmental Engineer, (DPC)
- Paul Shafer, Emergency Plan Coordinator, (LACBWR)
R. Shimshak, Plant Manager, (LACBWR)
O. Boyd, Operations Supervisor, (LACBWR)
B. Zibung, Radiation Protection Coordinator (LACBWR)
H. Polsean, Shift Supervisor, (LACBWR)
H. Towsley, Shift Technical Advisor, (LACBWR)
P. Crandall, Communicator, (LACBWR)
M. Holmes, Health Physicist, (LACBWR)
D. Rybarek, Drill Captain / Observer (LACBWR)
- Denotes those present at exit interview.
2.
General An exercise of the licensee's Radiological Emergency Response Plan limited to the functions of the Emergency Operations Facility (EOF)
and Technical Support Center was conducted on February 10, 1982.
The exercise tested the licensee's response to a loss of coolant accident and an offsite release of radioactivity. Attachment 1 describes the scenario. The licensee conducted the exercise to demonstrate he could perform the following functions in a timely manner.
1.
Establish and maintain communication with the local governmental agency with the lead responsibility in emergency response sufficient to ensure that both parties are aware of each others activities and recommendations.
2.
Establish and maintian communication with the Joint Public Information Center sufficient to provide the Dairyland Public Information Of ficer with timely information and to review press releases before they are issued.
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3.
Establish and maintain communications with the plant sufficient
to ensure that the Emergency Control Director can control the overall direction of the emergency response.
4.
Perform accurately and timely offsite dose assessment.
5.
Maintain records of the above activities.
Participation of offsite governmental agencies was limited to communi-cations.
3.
General Observations a.
Procedures This exercise was conducted in accordance with 10 CFR 50, Appendix E requirements using the LACBWR Emergency Plan, and the Emergency Plan Procedures (EPPs) used by the plant and the TSC and EOF.
b.
Coordination The response of the licensee's organization was acceptable.
If the event had been real the actions of the licensee would have been sufficient to permit the State and local authorities to take appropriate protective actions. The operation of the licensee's Emergency Operations Facility has been improved and is acceptable.
c.
Observers The licensee had a observer / drill captain in the control room.
There were two NRC observers, one in the EOF and the other in the TSC and control room, d.
Critique The licensee held a critique immediately following the exercise on February 10, 1982. NRC and the licensee discussed the results of the exercise in the exit interview.
4.
Specific Deficiencies Noted Problems identified by the NRC involved noncompletion of the licensee's Emergency Response Facilities in accordance with NUREG-0696, e.g.,
Control Room, Technical Support Center, Emergency Operations Facility
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and Operational Support Centers. These are previously noted open items f
and are due to be in place by October 1, 1982.
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5.
Specific Observations
a.
Control Room and Technical Support Center The inspector observed operations in the technical support center (TSC) and a simulated control room (CR). There were some communi-3, cations problems and some confusion concerning whether the Emer-gency Operations Facility (EOF) was on standby or activated very early in the exercise. However, the problems were quickly re-solved and subsequent communication flow was good. Several good recommendations were offered by the TSC. Their use of speaker-phones on the three-way communications link (TSC, CR, EOF) and the speaker-phones inability to receive while transmitting did impede the smooth flow of information. The licensee informed the inspector that they are in the process of obtaining headset-phones for the TSC which will solve this problem.
The overall performance in the TSC and simulated control room were considered acceptable.
b.
Emergency Operations Facility (EOF)
The EOF is located in the DPC Headquarters Building in Lacrosse, Wisconsin. The inspector noted that there were in place organi-zation charts for the TSC and EOF, the various communications forms (copies attached to this report), maps of the reactor site and environs, plant layout drawings, a situation board, specified locations for the various communicators, the ENS and HPN tele-phones, six telephones with headsets for the principal personnel and copies of the Safety Analysis Report. Also, available for dose assessment was a computer programmed to perform dispersion and dose estimates.
At 1147 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.364335e-4 months <br /> Assistant General Manager (who becomes the Emergency Control Director (ECD) when the EOF is fully activated) announccd an Alert situation had been declared and at 1152 he briefed the occupants of the E0F of the plant status causing the alert status to be declared. At about 1206 hours0.014 days <br />0.335 hours <br />0.00199 weeks <br />4.58883e-4 months <br /> onsite emergency was declared based on increasing containment activity and pressure. At 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br /> the EOF was fully operational, and the Assistant General Manager took responsibility as the ECD. All personnel responsibic
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for emergency functions in the EOF had arrived to assume their
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responsibilities at 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br />. The EOF was activated in approxi-
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mately 50 minutes after initiation of the scenario. A General Emergency status was declared at about 1233 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.691565e-4 months <br /> based on core i
spray failure. At 1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br /> the core spray was established and at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> the hypothetical leak of radioactive material was secured. By 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br /> the emergency status was reduced (on a conservativa time frame) from Site Emergency to Alert status, thus terminating the exercise for the EOF. The control of the recovery and reentry phase was passed on to the TSC and control l
room.
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During the course of the exercise it was noted by the inspector
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that the communications, command and control, and use of technical judgement was effective and efficient. Dispersion and dose calcu-j lations were performed in a timely manner and results were accurate.
I The permanent EOF was not completed at the time of the exercise.
The due date for completion, as per NUREG-0696 is October 1, 1982.
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Some of the visual aids for dose projections, trend analysis were
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not in place. However, the licensee indicated these would be in place with completion of the EOF.
The overall performance in the EOF is considered acceptable and satisfies the concerns outlined in the Confirmation of Action Letter dated October 28, 1981, and listed in Paragraph 2 of this
report.
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6.
Exit Interview
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The inspectors held an exit interview at the conclusion of the exercise with representatives listed in Paragraph 1 of this report. Observations and concerns resulting from the exercise given in Paragraph 4 of this report were discussed with the licensee.
7.
Licensee Actions on Previously Identified Items Related to Emergency Preparedness i
The following previously identified items are considered closed.
Planning Standard 50.47(b)(5) (Notification Methods and Procedures)
Deficiency 409/81-13-06 The licensee has not demonstrated that administrative and physical means have been established for alerting and providing prompt in-
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structions to the public within the plume exposure pathway EPZ.
The licensee will be responsible for ensuring prompt alerting and notification of the public in accordance with the Commission's
regulations.
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Resolution The licensee has operationally tested the administrative and physical means established for alerting and providing prompt instructions to the public within the plume exposure pathway EPZ by January 29, 1982.
This system meets the requirements as specified in 10 CFR 50 Appendix E, Section D.
This item is considered closed.
Planning Standard 50.47(b)(7) (Public Education and Information)
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Deficiency 409/81-13-10 Distribution of the Public Information Brochure to inform the resident and transient population of the plume exposure EPZ of what to do in the i
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event of an emergency had not been accomplished.
There were no provi-
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sions for annual update and dissemination of the brochure.
The Public Information Brochures has been distributed to the resident and made available to the transient population in the plume exposure EPZ. Provisions have been made by the licensee for annual update and dissemination of the brochure. This item is considered closed.
Attachments:
1.
Exercise Scenario 2.
Communications forms
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NRC OBSERVEi EMERGENCY OPERATIONS FACILITY REDRILL FEBRyARY 10, 1987 DRILL CAPTAIN AND OBSERVER:
DRILL OBSERVER:
SIMULATED CONTROL ROOM /TSC D. RYBARIK E0F R. BRIMER
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(Cards)
NRC OBSERVER:
NRC OBSERVER:
MR. A. MADISON DR. C. PAPIERELLO (Cards)
(Monticello, R. I.)
MR. J. PAGLIARO The Emergency Drill Scenario begins.
The Reactor is operating normally at 40 MWe (85% power) and power is going to the DPC grid.
The reactor pressure is 1240 psig, the temperature is 560*F.
'ihe SPING 4 stack effluent monitor is reading 3.0 x 10-5 pCi/cc (low range noble gas) and the Tracer Lab stack gas monitor is reading 1,800 cpm.
The containment building Tracer Lab immedicate particulate air monitor is reading 2,000 cpm and the gaseous monitor is reading 4,000 cpm.
All area radiation monitors in the plant are on-scale and normal.
Meteorological Data:
Stack WD 200
. Surface WD 190 Dif f. T 1.0 F
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Stack WS 4.4 mph Surface WS 4.0 mph
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11:30 AM A complete loss of AC Power has occurred.
Reactor scrams, all rods insert to full.
Reactor pressure rises to 1380 psig.
Forced circulation pumps shutdown.
Reactor Feed Pump trips. Emergency diesel-generators f ail to start.
Multiple annunciators alarm simultaneously shutdown condenser does not come in.
11:32 AM Shift Supervisor (acting ECD) declares an ALERT, based on loss of offsite l
power and all onsite AC power. Follow EPP-2 and Operations Manual, Volume 3, Section 3.3.2.
Following EPP-2 activate the TSC.
(Make sure you place all La Crosse Office EOF Personnel on standby status per EPP-2).
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11:40 AM Offsite AC Power is restored.
Control Room Annunciator C10-1 (Reactor Narrow Range Pressure Alarm),
Annunciator C7-1 (Tracer Lab Containment Building Gas Monitor High Alarm).
Annunciator C11-1 (CB Dampers closed), Annunciator Cl-2 (Reactor Water Level Low) + D2-2 (Reactor Water Level Low) all alarm simultaneously, a.
C10-1 readout indicates 1200 psig reactor pressure.
b.
The Tracer Lab Containment Building Gas Monitor readout indicates 300,000 cpm which corresponds about 1.0 x 10-4 pCi/cc noble gas activity inside containment.
c.
Two CB area radiation monitors alarm and indicate 100mR/hr, d.
Cl-2 readout indicates -16 inches on reactor water level.
e.
ECCS pumps IA/IB are running.
f.
Neither Condensate Pumps or Reactor Feed Pumps can be restarted.
11:45 AM (a) D2-2 readout indicates -13 inches on reactor water level and decreasing slowly, (b) C10-1 readout indicates 1000 psig reactor pressure and decreasing 11:50 AM All CB ARM's alarm and indicate between 750mR/hr and 1 R/hr.
The Tracer Lab CB Gas Monitor and Particulate Monitors peg out at 1 x 106 cpm.
SPING 4 trend alarmr on Channel 5 indica'.e increase in noble gas release to the stack.
The reading o1 the SPING-4 reaches 3 x 10-3 pCi/cc.
The Tracer Lab stack immediate particulate monitor pegs out at 1 x 105 c pm.
The T. L. stack gas monitor increase from 2 x 10 cpm (1.0 x 10-3 pCi/cc) to 8 x 104 cpm (4.0 x 10-3 pCi/cc).
Both stack blowers (70,000 cfm or 3.3 x 107 cc/sec) are operational.
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17:00 Noon
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Control Room Annunciator C4-4 Alarms (CB Pressure High) Containment Building Pressure reaches 5 psig and appears to be increasing slowly.
Reactor pressure at 800 psig.
SPING-4 stack gas monitor (Channel 5) alert alarms and has an indicated reading of 5 x 10-2 pCi/cc, (Channel 7) reads 1.8 x 103 Beq/cc.
Reactor water level indicator at -25 inches and slowly decreasing.
STA reviewing EPP-1 determines that a site area emergengy should be declared.
12:05 PM Shift Supervisor declares SITE AREA EMERGENCY.
Follow EPP-2 and:
DO NOT BLAST PLANT SIREN (SIMULATE).
DO NOT EVACUATE PERSONNEL TO G-1 (SIMULATE).
NOTIFY NRC, for this practice drill.
CALL VERNON COUNTY SHERIFF.
(Following EPP-2, activate E0F (La Crosse Office).
When personnel reach EOF they establish communications with the plant personnel.
The ECD role will be assumed by corporate management person.)
DO NOT ACTIVATE THE JPIC, but notify R. Marose at 8-380.
12:25 PM Reactor water level indication is at -30 inches and slowly decreasing.
Control Roon Annunciator El-1 (Reactor Aux. Device Trip) alarms.
ECCS Pumps I A and IB trip due to electrical motor shorts.
Control Room Annunciator D-6-3 (ECCS Pumps 1 A/1B running) clears.
Control Room Annunciator E/A-1 (EmergG " Core Spray Flow Low) alarms.
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Reactor Pressure:
650 psig 12:28 PM HPCS Pump cannot be restarted, MDS Valves won't open.
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12:35 PM
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General Emergency is declared based on loss of core cooling with fuel cladding degradation imminent.
12:40 PM
Tracer Lab Stack Gas Monitor pegs out at 1 x 10 cpm.
All ARM's peg out at 10 R/hr. High Range Containment Building Radiation Monitor reads 2.5 x In3 R/hr.
Estimated containment building atmosphere noble gas activity is 20 uCi/cc.
Meteorological data:
Stack WD 180 Surface WD 153 Di f f T
+1.5'F
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Stack WS 3.0 mph Surface WS 3.0 mph
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SPING 4 high alarms on Channel 5 at full scale (10-1 uC1/cc) and alert alarms
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on Channel 7, 2.81 x 10 Beq-Mev/cc (0.76 u Ci/cc).
SPING Channel 3 (I-131)
reaches 370 uCi per 10 minutes (approximately equal to 5.29 x 10 # uCi/cc)
discharges from the stack. Both stack blowers are operational at 70,000 cfm (3.3 x 107 cc/sec). TSC calculates estimated off-site dose.
H 8 S Supervisor dispatches appropriate HP Technician with emergency radiological monitoring equipment to offsite locations downwind as per EPP-8.
12:45 PM Operators try to restart ECCS pumps but they will not start.
Primary coolant pressure is about 500 psig.
Reactor water level drops rapidly to +10 inches on the wide range.
12:50 PM Manual Depressurization Valves are opened and Alternate Core Spray System flow commences.
1:00 PM SPING-4 Channel 7 at 5.55 x 104 Beg /cc (1.5 uCi Channel 3 (I-131) is at 400pCiper10 minutes (approximately1.6x10fcc).
pCi/cc).
Both stack blowers operational.
Meteorological data:
Stack WD 200 Surface WS 170 Di f f T
+2.0 F
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Stack WS 4.0 mph Surface WD 5.0 mph
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1:10 PM
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Operator discovers that the shutdown condenser vent to off-gas valve is opened.
He turns control switch to close and the valve indication remains opened. ARM steam tunnel is reading 2500 mR/hr.
1:20 PM HP Technician determines dose rate is 20 R/hr in tunnel.
Shut down condenser vent to offgas isolation valve in tunnel is closed.
1:25 PM SPING-4 Channel 5 Noble Gas activity on scale at 1 x 10-2 pCi/cc. Channel 7 Noble Gas activity is at 3.7 x In2 Beq/cc.
Channel 3 (I-131) is at 0.4 pCi per 10 minutes (3.6 x 10-6 pC1/cc).
Meteorological data:
Stack WD 300 Surface WD =
27 0 Di f f. T = +2.0'F
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15.0 mph Surface WS =
5.0 mph Stack WS
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1:30 PM Wide range reactor water level is 50 in. CB level is 330 in. CB pressure is 28 psig.
1:35 PM SPING-4 Channel 5 Noble Gas activity is 6 x 10 4 p Ci/cc, and Channel 3 (I-131)
is at 0.0025 u Ci per 10 minutes (10 x 10-8 pCi/cc).
The Tracer Lab Stack Gas d
Monitor is back on scale at 3 x 10 cpm.
1:40 PM ECD determines that the energency has de-escalated to an ALERT status.
Of f-site HP Technicians continue to survey, take air samples, vegetation samples, etc.
1:45 PM The HP Technician Team is recalled.
1:50 PM ECD will deactivate E0F and terminate drill.
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DAIRYLAND POWER COOPERATIVE
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EMERGENCY OPERATIONS FACILITY / TECHNICAL SUPPORT CENTER REACTOR OPERATIONS PARAMETERS COMMUNICATIONS DATE:
MESSAGE #
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T!ME:
INITIALS:
____________..... __._____. _______._______.._________________________________
CONTROL ROOM OSC - 2 (Genoa 1)
_____..______.____________________ ____________________..__________ __________
FROM:
EOF T0:
TSC CONTROL ROOM OSC - 2 (Genoa 1)
___________________..______ ___________________________________________...____
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MESSAGE:
1.
Reactor Water Level in. (Safety Channels 1, 2, 3)
(Wide Range)
2.
Reactor Pressure psig.
3.
Reactor Temperature
'F.
4.
Containment Building Isolated:
YES NO 5.
Emergency Systems in Operation:
a.
Shutdown Condenser YES N0 b.
ECCS YES N0
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ACS YES N0 d.
lA Diesel / Generator YES N0 e.
1B Diesel / Generator YES N0 f.
HPSW YES NO g.
ESWSS YES N0 6.
Containment Building Pressure psig Temperature
'F.
7.
High Range C. B. Rad. Monitors (A)
R/hr (B)
R/hr Fuel Clad Degradation Indication:
HRCB Rad Monitor Fuel Degradation 101 - 10 R/hr 0%
103 - 10 R/hr 1%
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104 - 10 R/hr
= 10%
105 - 10 R/hr
=100%
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Other significant Reactor Operations Parameters.
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9.
Current Emergency Classification Status:
Unusual Event Site Area Emergency Alert General Emergency Originators Name Received By
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DAIRYLAND POWER COOPERATIVE
EMERGENCY OPERATIONS FACILITY / TECHNICAL SUPPCRT CENTER
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INEANT RADIOLOGICAL PARAMETERS COMMUNICATIONS
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MESSAGE #
DATE:
,
TIME:
INITIALS:
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CONTROL ROOM OSC 2 (Genoa 1)
Other
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CONTROL ROOM OSC - 2 (Genoa 1)
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Other
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MESSAGE:
4 mR/hr)
mR/hr ave.
mR/hr max #
1.
Low Range ARM's (0-10 2.
ARM 7 (0-105 mR/hr)
mR/hr 5 mR/hr)
mR/hr 3.
ARM 8 (0 10 8 R/hr) A R/hr B
R/hr 4.
H.R.C.3. A.R.M. (0_10 5.
mR/hr G-3 mR/hr Stack Blower Flow Rate:
6.
STACK AIR MONITOR O cc/sec 1.65 x 10 cc/sec 3.3 x 107 cc/sec
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A.
SPING.4 18 Part pCi 3. 1-131 pCi 5. LR Noble Gas pCi/cc 7. MR Noble Gas seq /cc 2. a Part pCi 9. HR Noble Gas seq /cc B.
TRACER LAB 1. Immed. Part cpm 2. Delay Part cpm 3. Noble Gas cpm 7.
Meteorological Information: Type of Release None Ground Elevated WS mph 0 m
aT (100 10m)
F WD
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8.
Containment Building Air Monitor A.
SPING-3 16 Part pCi 3. 1-131 pCi 5. LR Noble Gas pCi/cc 7. MR Noble Gas seq /cc 2. a Part pC i B.
TRACER LAB 1. Immed. Part cpm 2. Delay Part cpm 3. Noble Gas cpm 9.
Tunnel Mon.
cpm 10. Forced Circulation Pump Cub. Monitor cpm.
11. Liquid Waste Monitor cpm.
12. Additional Portable Radiological Surveys;
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13. Current Emergency Classification:
Unusual Event Site Area Emergency Alert General Emergency Originator Received By
TABLE 6 Page 50
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DAIRYLAND POWER COOPERATIVE EPP-2 R
EMERGENCY OPERATIONS FACILITY Issue 4 j
k[]) ATE:
INFIELD RADIOLOGICAL ASSESSMENT TEAMS ASSESSMENT PKRAME TERS RADIO COMMUNICATIONS
D MESSAGE #
TIME:
INI TI ALS:
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T0/FROM:
Field RAP Team 1 FROM/TO:
EOF (Circle Field RAP Team 2 (Circle Field Rap Team 1 One)
Field RAP Team 3 One)
Field Rap Team 2 EOF Field Rap Team 3 Other Other
...._____________...__.______ ______ _________...__________.. _____.. ________.-_____ _____________.
i e MESaAGE:
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Location Sector xu - o
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Distance f rom LACBWR m1.
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L o%% m 3-5 %.
m 'u 4-2.
Direct Immersion Dose Equivalent Rates mR/hr mR ad/hr mNO a E-L u
eum eoaeo 3.
Ground direct radiation readings:
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L Lw E9 m CLC'.Y_C_9._____...__pm
- como C
Cpm oC
__________________.-_______--_-...-.____-...____..__.. ___-..________________
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4.
Permanent Environment 61 Air Sampler Charcoal Cartridge changed to Ag-Zeolite YES NO Filter Paper Changed YES NO a.
nR/hr s mR/hr 6 b.
Flow rate cfm.
c.
Total Flow cf.
d.
Filter gross beta counts cpm.
e.
Cartridge gross beta counts cpm.
_________--______----______________....__ _________-__-__-.--___-..-_.----___________-__-______...--
.o o d ou f.
Nal(TI) or Germanium MCA analysis results
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-um me Total spa pCi/cc, Isotopes:
eam-oo o
a a o a,-
N Evw (
X o r- *- e* >
e-oO e m M
- c-c tw v 4-r4 3 e c o s 4-er
_?_T'.?_?_?T_f--_---__.._______..__._____._______________-_____-___-__.__-.______-.___--_____---___
5.
Portable Radeco - DC Air Sample Taken YES NO CHARC0AL AgZeolite a.
Flow rate Ipm b.
Total sample time min.
c.
Total sample flow 1pm x mi n. x 103
=
cc d.
Filter gross beta counts cpm e.
Cartridge gross beta counts cpm
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______-_.__.______._-___________________...___-_______--____-_-____
. *%
f.
Nal(TI) or Germanium MCA analysis results:
c 13# l's e 8,*
Total spa pCi/cc, Isotopes:
E v 4_ ed N
m X L Or-
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e-o (J m W M
'e-m%
L) 4. eA B C C C) N 4-i o'
%
cC >w 4 3 Q >* W
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6.
Vegetation Sample Taken YES NO 7.
Surface Soil Sample Taken YES N0 8.
Surface Water Sample Taken YES NO 9.
Milk Sample Taken YES NO 10. Weather Conditions El l. Other significant itTms:
Originators Name Received By
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TABLE 4 Page 48 DAIRYLAND POWER COOPERATIVE EPP-2 D
EMERGENCY OPERATIONS FACILITY / TECHNICAL SUPPORT CENTER Issue 4 REACTOR OPERATIONS PARAME TERS
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COMMUNICA TI ONS DATE:
MESSAGE #
TIME:
INI TI ALS:
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..............................................................................
(Circle CONTROL ROOM (Circle TSC One)
OSC. 2 (Genoa 1)
One)
CONTROL ROOM EOF OSC. 2 (Genoa 1)
..............................................................................
MESSAGE:
1.
Reactor Water Level in. (Safety Channels 1, 2, 3)
(Wide Range)
2.
Reactor Pressure psig.
3.
Reactor Temperature F.
4.
Containment Building Isolated:
YES N0 5.
Emergency Systems in Operation:
a.
Shutdown Condenser YES N0 b.
ECCS YES N0 c.
ACS YES N0 d.
lA Diesel / Generator YES NO e.
IB Diesel / Generator YES N0 f.
HPSW YES C
ESWSS YES N0 t
!
6.
Containment Building Pressure psig Temperature
'F.
7.
High Range C. B. Rad. Monitors (A)
R/hr (B)
R/hr Fuel Clad Degradation Indication:
HRCB Rad Monitor Fuel Degradation
103. 10 R/hr 0%
10 R/hr 1%
=
104. 10 R/hr
= 10%
,
10b. 10 R/hr
=100%
8.
Other significant Reactor Operations Parameters.
!
,.
)
9.
Current Emergency Classification Status:
,
Unusual Event Site Area Fmergency i
Alert General Emergency
i Originators Name Received By
,
. - - - _ - -
_
-_
<
",
TABLE 5 page 49
'
R~
^'RYLAN P WER C00 PERATIVE Epp 2 A
EMERGENCY OPERATIONS FACIL I TY/ TECHNICAL SUPPORT CENTER Issue 4 INPLANT RADIOLOGICAL PAPAMETERS O
COMMUNICA TIONS
- '
>
DATE:
MESSAGE #
TIME:
INI TI ALS:
__...__.....________..__..... _________...
__ ________
___ ______________
(Circle CONTROL ROOM (Circle TSC One)
0SC - 2 (Genoa 1)
One)
CONTROL ROOM E0F OSC. 2 (Genoa 1)
OTHER OTHER
__________..._____..__....__...._________________...__.....____......._____.
MESSAGE:
1.
Low Range ARM's (010 mR/hr)
mR/hr ave.
mR/hr max #
2.
ARM 7 (0 105 mR/hr)
mR/hr 3.
ARM 8 (0 105 mR/hr)
mR/hr 4.
H.R.C.B.A.R.M. (0 108 R/hr) A R/hr B
_ R/hr 5.
mR/hr G-3 mR/hr
, _ _ _ _ _ _ _ _ _ _ _... _ _ _.... _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.... _ _...... _ _ _ _.
6.
STACK AIR MONITOR Stack Blower Flow Rate:
-
0 cc/sec 1.65 x 107 cc/sec 3.3 x 107 cc/sec
~
A.
SPING-4
_
ogs 1. s Part pCi 3. I-131 pCi 5. LR Noble Gas pCi/cc u gg 2. a Part pCi 7. MR Noble Gas pCi/cc g,m 9. HR Noble Gas pCi/cc s.t e
'
6 pCi/Ci)
gg.
(To obtain source term in Ci/sec mutiply the pCi/cc x cc/sec + 10 y
B.
TRACER LAB
~3e 1. Immed. Part cpm 2. Delay Part cpm 3. Noble Gas cpm 8.* $
g 3 g-7.
Meteorological Information:
Type of Release None Ground Elevated g3 WS mph 0 m
t2T (100-10m)
a: u -
WD
@
m o_________.._______________________
...___..______________________....__________......__...__ ______
8.
Containment Building Air Monitor A.
SPING-3 1. s Part pCi 3. 1-131 pCi 5. LR Noble Gas pCi/cc 2. a Part pCi 7. MR Noble Gas pCi/cc B.
TRACER LAB 1. Immed. Part cpm 2. Delay Part cpm 3. Noble Gas cpm 9.
Tunnel Mon.
cpm 10. Forced Circulation Pump Cub. Monitor cpm.
11. Liquid Waste Monitor _
cpm.
12. Additional Portable Radiological Surveys; 13. Current Emergency Classification:
Unusual Event Site Area Emergency Alert General Emergency 07%ismcc R@ceived By/
f TABLE 3 Page 47 DAIRYLAND POWER COOPERATIVE EPP-2 EMERGENCY OPERATIONS FACILITY Issue 4
!)h EMERGENCY CONTROL DIRECTOR /0FFSI TE AGENCY
-
.
>
EMERGENCY OPERATIONS CENTERS COMMUNICA TIONS DATE:
TIME:
INI TI ALS:
MESSAGE #*
_............................______................__..__.........._......_____
T0/FROM: (Circle One)
FROM/TO: (Circle One)
US NRC (Region III)
E0F (Emergency Control Director US NRC R.A.P.
US NRC (Bethesda)
EOF (Radiological Assessment Director)
Vernon Co. E0C (Viroqua)
State of WI E0C (Tomah)
State of WI E0C (Madison)
State of WI R.A.P.
Houston County E0C (Caledonia)
State of MN E0C (Rochester)
State of MN E0C (St. Paul)
State of MN R.A.P.
JPIC FEMA Other
.._________.........__....... __.._......................_.......__.....___...__
MESSAGE:
)
_
i
{
Originators Name Received By l
- 1. Use Rad # if originated by Rad Commissioner.
.
l 2. Use Opd # if originated by RAD Reviewed
{
Opd Communicator.
,
3. Use Secretary's initial #
'
if originated by secretary.
ECD Reviewed A Approved
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_
.
.
-.
-.
.
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