ML20069D563

Exercise Manual

ML20069D563
Person / Time
Site:	Vogtle
Issue date:	08/04/1993
From:	GEORGIA POWER CO.
To:
References
NUDOCS 9406060042
Download: ML20069D563 (109)

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1993 NRC GRADED EXERCISE August 4,1993 SCIIEDULE OF EVENTS 1. Players Briefing Time and Date 1300 July 29,1993 Location Admin. Bldg. Auditorium 2. Controller Briefing Time and Date 0900 August 3,1993 Location EOF - Training Center Rooms 506 & 508 3. NRC Graded Exercise Date August 4,1993 4. GPC Self Critique Time and Date 1500 August 4,1993 Location EOF - Training Center Rooms 506 & 508 5. Pr liminiry Exercise Critique 0930 August 6,1993 e for Managers Admin. Bldg. Conference Room 6. NRC Exit Time TBD August 6,1993 Admin. Bldg. Conference Room O' 7. Public Critique Time TBD August 6,1993 Burke County Oflice Park GE-93 EX4002 l

l 1993 NRC GRADED EXERCISE i August 4,1993 i O CONTROLLERS l Roving Rob Dorman (B 035) Lead Exercise J. N. Roberts (B 435) Simulator: Ext. 3907/3911 Lead Simulator Perry Tucker Tom Petrak Lead Operations Gary hioore (B-478) Communications: Ext. 3911/4449 Simulator / EOF Cynthia Brady Control Room Page Operator Extra RO (unit 1) Simulator Page Operator hiichelle Gentry TSC: Ext. 4511 Lead Plant System Engineering Robert Afoye(B-133) Chemistry Ricky Bryant (B-476) HP Lewis Rouse PEO's (Ext. 3004) John Digby Greg Lee Brain Whittemore OSC: Ext. 3898 Lead Darrel Barnett (B-287) I&C Tim Ruckman (B-228) Electrical Floyd Fields (B-059) Electrical hiike Silva (B-274) hiechanical David Seckinger (B-238) hiechanical Gene Anderson hiedical O Teanna Greiner (B-193) GE 93 EX4003

1993 NRC GRADED EXERCISE August 4,1993 CONTROLLERS IIP Control Point: Ext. 4016 or 4018 HP Lead Mike Kurtzman (B-475) IIP Darlene Diaz (B-474) HP Bob Anderson (B-476) HP Art Belge (B-477) Security: Ext. 3737 PESB Tom McQuillen (B-311) Terri McCafferty (B-004) Lawrence Mayo (B-147) EOF: Ext. 4449 Lead Jim Roberts (B-435) Paul Herrmann Dose Assessment Rachelle Reddick Communict,tions Cynthia Brady Field Monitoring Teams (Lead) Russell Brown Merrill Maddox Dan Hill Gene Henry Assembly Area (Admin. Building): Terri McCafferty (B-004) O GE-93 EX4003

^) 1993 NRC GRADED EXERCISE August 4,1993 PARTICIPATING AGENCIES 1. GEORGIA POWER COMPANY A. Plant Vogtle 1. EOF 2. TSC 3. OSC 4. Simulator B. General Office Operations Center C. Emergency News Center (ENC) II. OFFSITE A. Savannah River Site - Communications only B. South Carolina EPD - Communications only C. Aiken County - Communications only D. Barnwell County - Communications only E. Allendale County - Communications only F. South Carolina Dept. of Health and Environmental Control (DHEC) - Communications only G. Georgia Emergency Management Agency (GEMA)- Partial from FEOC H. Burke County EMA - partial from EOC I. Burke County Ambulance J. Burke County Hospital GE-93 EX4004 i---

1993 NRC GRADED EXERCISE August 4,1993 OBJECTIVES The Vogtle Electric Generating Plant (VEGP) emergency preparedness exercise objectives are based on Nuclear Regulatory Commission (NRC) requirements provided in 10CFR50.47, " Emergency l Plans," and 10CFR50, Appendix E, " Emergency Planning and Preparedness for Production and Utilization Facilities." Additional guidance provided in NUREG-0654, FEMA-REP-1, Revision 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans" was utilized in developing the objectives. A. Accident Assessment and Classification 1. Demonstrate the ability to identify initiating conditions, determine emergency action levels (EAL) parameters and correctly classify the emergency throughout the exercise. 2. Demonstrate the ability to provide core damage assessments. B. Notifications O 1. Demonstrate the ability to alert, notify and mobilize site emergency response personnel. 2. Demonstrate the ability to expeditiously notify state, local and federal authorities (NRC). 3. Demonstrate the ability to warn or aavise onsite individuals of emergency conditions. C. Emereency Response 1. Demonstrate the capability to direct and control emergency operations. 2. Demonstrate the ability to transfer emergency direction from Control Room (simulator) to the Technical Support Center (TSC) and from the TSC to the Emergency Operations Facility (EOF) in a timely manner. 3. Demonstrate the ability to prepare for around the clock stafling requirements. 4. Demonstrate the ability to perform assembly and accountability in a timely manner. GE-93 EX4005

1993 NRC GRADED EXERCISE { August 4,1993 OBJECTIVES D. Emernency Response Facilities 1. Demonstrate timely activation of the TSC, Operations Support Center (OSC), and EOF. 2. Demonstrate the adequacy of equipment, security provisions, and habitability precautions for the TSC, OSC, and EOF, and Emergency News Center (ENC). 3. Demonstrate the adequacy of communications for all emergency support resources. E. Radiolonical Assessment and Control 1. Demonstrate the ability to obtain onsite radiological surveys and samples. 2. Demonstrate the ability to utilize the post accident sampling system to collect and analyze samples to determine the extent of core damage. 3. Demonstrate the ability to continuously monitor and control radiation exposure to emergency workers. 4. Demonstrate the ability to assemble and deploy field monitoring teams in a timely j fashion. 5. Demonstrate the ability to satisfactorily collect and disseminate field team data. 6. Demonstrate the ability to develop dose projections and determine appropriate protective r.ctions. i F. Medical 1. Demonstrate the ab lity to respond to and treat an injured individual. O GE-93 EX4005 =

1993 NRC GRADED EXERCISE p August 4,1993 O OBJECTIVES G. Public Information 1. Demonstrate the capability to coordinate the development and dissemination of clear, accurate and timely information to the news media. 2. Demonstrate the ability to brief the media in a clear, accurate, and timely manner. 3. Demonstrate the capability to establish and operate rumor control in a coordinated fashion. H. Recoverv 1. Demonstrate the ability to start planning for recovery by conducting an initial briefmg on recovery procedures and by the establishment of a tentative organization. 1. Evaluation 1. Demonstrate the ability to conduct a post-exercise critique to determine areas requiring improvement and corrective action. o O GE-93 EX4005 e

1993 NRC GRADED EXERCISE August 4,1993 INITIAL CONDITIONS Unit 2 is in a refueling outage. The reactor is de-fueled. + Unit 1 is in Mode 1 at MOL in Cycle 5, operating at 100% power. i The unit has been on line for 135 days. Containment mini purge is in service (release permit # 930099-G) in preparation for a + containment entry to repair the transmitter for ILT-461. .All control systems are in automatic. Key Unit 1 Parameters: Reactor Power = 100%

• RCS at NOTP RCS boron concentration = 1003 ppm (BAST = 7100 ppm)

+ Pressurizer level and Steam Generator levels at program + Core burnup = 9000 MWD /MTU + Unit i Systems / Equipment Out Of Service 0 Pressurizer level channel "461" due to a faulty transmitter. I&C preparing for containment entry to replace the transmitter. O RHR "A" train out of service (72 hour LCO bearing replacement) scheduled to return to service 1600 August 5. i Meteorological Data: Wind Direction 90 (from) + Wind Speed 2.3 mph + Temperature 80 Stability Class B + Precipitation 0"in the past 24 hours + I GE-93 EX4006 1 -n

PROCEDURE NO. REVISION PAGE NO. VEGP 10008-C 16 8 of 13 Sheet 1 of 3 n LCO STATUS SHEET SECTION I: INITIATION Applicable Modes 3,1, 3, 4,5 lo LCO Number ! 304 Tech. Spec. 3.0.4 Applicable NO (c rcle one) LCO Initiated: Date Time Tech. Spec. References 3. 5,2

3. 6, d. /; J.4. i.3 34,1.1. I, 3. 4. /. M q, j

3.9 8.J J,. 9. 6. 2 Condition Initiating LCO Action l-12o5 oo i - s c i RdA QuaP'A'TAAto M 6 ro t Lou 3rr 6E Athd G OE rM REPLACEA N E Completion REQUIRED ACTIONS USS Init/Date/ Time Wt74 00E E CC'3 Su6SV3TM idOPER A6LE, RESTORE U{E lO O ADR A6tl 5485YS TM To OPM Aste $Thre wreid 7c wouAs oc BE 14 A T GwS T' do T' Sr4Ub 64 Wira,o TH E O EXT 6tX HOtLR$ (gch 30 Hoz' sdw,fOce:J (Ji m id W6 Foccog,0 G G sx. So uRS, Document repeating actions on Figure 3. ~ Remarks t USS SS Figure 1 '03445

PROCEDURE NO. REVISION PAGE NO. VEGP 10008-C 16 9 of 13 \\ Sheet 2 of 3 LCO NUMBER' i SECTION II: RESTORATION DC, MWO, WRT Procedure, Work Being Completion USS Date Clearance Number Performed Date Init i MPLACE M cfod. L.ow dC%'6 143 0o179 CLR j IG 2_o i 3 % moc RcPtAcc.xcit< tem dooJG I9 3 COfo 0 CAU6R4rc IFI O(oiR A/d l i l i O J Continue on Page 3 of 3 if required. Continuation Sheet 3 of 3 attached? Yes [ ] No ( ] 1 Operability' Determined: Chemistry /HP Person Notified (Rad Monitors Only) Date Time Name I LCO No Longer Active: Date Time l i USS SS O Figure 1 (Cont'd.)

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~~ Georgia Power Company page 1 of 6 Vogtle Electric Generating Plant U-1 Gaseous Radioactive Waste Release Permit 930099-G Pre-Release Supplementary Data __________________._________.___~______________________________________________ PART I: PRE-RELEASP. DATA Release Point ( 25): UNIT 1 CONTAINMENT PURGE / VENT Discharge Point ( 5): UNIT ONE PLANT VENT Permit Issued: 28-apr-1993 19:06:12 Release Type: Batch r Rad Monitor: (25) 1RE2565C Rad Monitor Bckgrnd: 0.0000E+00 CPM Estim. Waste Flow: 1.8000E+04 CFM Estim. Waste Volume: 1.3932E+08 CF Estim. Release Start: 28-apr-1993 14:59:00 Estim. Release End: 03-may-1993 23:59:00 Estim. Duration: 7740.0000 MIN PART II: PRE-RELEASE CALCULATIONS Sample Entry # : 129 3as sample time: 28-apr-1993 14:59:00 Sampled by: MKJ 3as Monitor Response: 1.63E+01 CPM Total Body Dose Rate: 4.0$E-03 mrem /yr % Limit = 0.0% Skin Dose Rate: 5.93E-03 mrem /yr % Limit = 0.0% i

4ax Organ Dose Rate:

6.41E-04 mrem /yr % Limit = 0.0% iax Monitor Satpoint: 1.61E-03 uCi/cc Flag: 2.01E+05 CPM i Flags: A-Release Curies > Local Limit N-Noble Gas Dose Rate > Limit l S-Release Curies > Site Limit 0-Organ Dose Rate >' Limit i Analysis Date Measured Concen. Est. Curies foble Gases 28-apr-1993 15:16:54 1.30E-07 uCi/cc 5.13E-01 1 ? articulates 28-apr-1993 15:26:17 1.82E-12 uCi/cc 7.19E-06 ladiciodines 28-apr-1993 16:40:25 7.26E-12 uCi/cc 2.87E-05 2B FOREMAN ?ECHNICAL REVIEW:

1. ___________________________my ggggggggg

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Georgia Power Company page 2 of 6 Vogtle Electric Generating Plant U-1 ('N ) 3aseous Radioactive Waste Release Permit 930099-G 's Pre-Release Supplementary Data ISOTOPIC IDENTIFICATION - Unit 1

Pre-Disp. : Pre-Cisp. : Pre-Disp. : Conc / Total:

Release

Estimated

Measured

Measured

Measured by Rate Curies Isotope :

uCi/cc

Conc /MPC

Conc / Total:

T uCi/sec

Released

_________________________________________________ype H-3 0: 4.04E-08 : 2.02E*01 : 2.37E-01 : 1.00E+00 : 3.43E-01 : 1.59E-01 I-131 R: 7.26E-12 : 7.26E-02 : 4.26E-05 : 1.00E+00 : 6.17E-05 : 2.87E-05 AR-41 N: 1.16E-07 : 2.90E+00 : 6.81E-01 : 8.93E-01 : 9.87E-01 : 4.58E-01 XE-133 N: 1.40E-08 : 4.66E-02 : 8.20E-02 : 1.07E-01 : 1.19E-01 : 5.52E-02 BR-82 P: 1.82E-12 : 3.04E-04 : 1.07E-05 : 1.00E+00 1.55E-05 : 7.19E-06 Totals : 1.71E-07 : 3.22E+00 : 1.45E+00 : 6.73E-01 O

__. -. _ - ~. - - Georgia Power Company page 4 of 6 Vogtle Electric Generating Plant U-1 3aseous Radioactive Waste Release Perrit 930099-G Pre-Release Supplementary Data 3eport Category

Calculated Dose Rate to Man (mrem / year) from this Release at Site Boundary.

rype of Activity

Radiciodines and Particulates Age G).oup & Pathway (s)

Child

Inhalation Controlling Sector

NE Jnit number 1

Bone

Liver

Tot-body

Thyroid

Kidne

_____________________________________________________y

Lung

GI-LLI IE : 1.37E-06 : 1.80E-04 : 1.79E-04 : 6.41E-04 : 1.81E-0

1.78E-04 : 1.78E-04

_________________________________________________________4 l l l

y 3eorgia Power company page 3 of 6 Vogtle Electric Generating Plant U-l 3aseous Radioactive Waste Release Permit 930099-G <T Pre-Release Supplementary Data _) 2eport Category

Calculated Doses at Site Boundary.

Gamma and Beta Air Doses, Tot-body and Skin

Doses and Dose Rates.

Type of Activity

Noble Gases Controlling Sector

NE Jnit number 1

Site

Tot-body

Skin Dose : Gamma Air : Beta Air

Tot-body

Skin

Boundary

Dose

mrem

mrad

mrad

Dose Rate : Dose Rate

Dist (km) : mrem

___________________________________________________________: mrem / year : mrem / year IE : 1.13E+00 : 5.96E-05 : 8.73E-05 : 6.27E-05 : 2.29E-0

4.05E-03 : 5.93E-03

_________________________________________________________5______________________ N

.._ m ~ - - - - Georgia' Power Company Vogtle Electric Generating Plant U-1 page 5 of' 6 Gaseous Radioactive Waste Release Permit 930099-G Pre-Release Supplementary Data ~ Report Category

Cumulative Dose at Site Boundary type of Activity

Noble Gases Location

NE at 1.127 km.

Unit number-1

Tot-body

Skin

Gamma Air : Beta Air

mrem

mrem

mrad

mrad This-Release

5.96E-05 : 8.73E-05 : 6.27E-05 : 2.29E-

---

....------------------------.--------...-----05 31D Prior:

To Rel

2.83E-05 : 6.69E-05 : 3.40E-05 : 1.01E-

---_..-........----. ---------.........----_...--04 31D After: telease

8.43E-05 : 1.49E-04 : 9.29E-05 :

........-_.......-----.....----........... 1.23E-04 31 Day i Limit

0.00E+00 : 0.00E+00 : 2.00E.01 :

4. .---....___-..-_.-.---.------....---..-.-..00E.01 : 1 31 Day : Limit 0.00%: 0.00%: 0.05%: .--...---_...-............--......_-_..-....._0.03%: ltr Prior: 00 Rel

3.02E-05 : 7.12E-05 : 3.62E-05

.--......_...-_-_....-_....-. _.......-_.: _1.08E-04 2tr After: telease

8.97E 05 : 1.59E-04 : 9.89E-

1.31E-04 :

.....-......-.... -_-....-_..-....___05_____. ___... 2uarterly: Limit

0.00E+00 : 0.00E+00 : 5.00E+0

.1.00E+01 :

.--------..--...----__.-..0_-..........

Quarter

aimit 0.00%: 0.004: 0.00 0.00%: tnn Prior: ?o Rel

1.29E-03 : 3.03E-03 : 1.54E-03

.-..------...--_. -_..-.. _.---.------...:.4.46E-03 .nn After: telease

1.34E-03 : 3.12E-03 : 1.60E.03 :

---

..............--..-__--.4.48E-03

.nnual .imit

0.00E+00 : 0.00E+00 : 1.00E+

2.00E+01 :

--......_---______.-..._...----__----01-.-_-. _.. _.. Annual : .imit 0.00%: 0.00%: 0.0 0.02%: .---..------------. _ __ -..---- -----_2%: N -W =rw-g- W 7 fr Y 49 -v w w - a r-m w we - wr

w w _.- c-A .-..p m..= -w - - - -. - - - ~ - - - Georgia Power Company page 6 of 6 Vogtle Electric Generating Plant U-1 f Gaseous Radioactive Waste Release Permit 930099-G ( Pre-Release Supplementary Data x Report Category Cumulative Maximum Individual Dose (mrem) for Controlling Age Group at Controlling Location Type of Activity

Radioiodines and Particulates Age Group & Pathway (s)

Child Gr_ Plane; Inhalation Location

WSW at 1.931 km.

Unit number 1

Bone

Liver

Tot-bod

---__---_-_-__-__-_______-__y

Thyroid

Kidney

Lung

GI-LLI This Release

2.10E-08: 7.43E-07: 7.40E-07:

__---_-___---_----------.--_____--------2.61E-06: 7.46E-07: 7.37E-07: 7.38E-07 31D Prior: To Re1

6.31E-07: 7.69E-05: 7.68E-05:

7.69E-05: 7.69E-05: 7.68E-0 -_.._--._-_-_._____-_--..--_--------._-9.45E-05:...... _- ....___-___........._...__5 31D After: Release

6.51E-07: 7.75E-05: 7.75E-05 7.76E-05: 7.76E-05: 7.75E-0

..._....:.9.70E-05:......_._..-__.______.. _____.--______5 31 Day Limit

3.00E-01: 3.00E-01: 3.00E-0

3.0 0E-01

3.00E-01: 3.00E-01: 3.00E-0 ______..___.__ _______ __...____._____1:___________-_..________..____... & 31 Day : Limit 0.00%: 0.03%: 0. 0.03%: 0.03%: 0.03%: -_____..____________... ________ -__03%:____-__________...__..______...-__ 2tr Prior: Co Rel

6.72E-07: 8.18E-05: 8.18E-

1.0 1E-04

8.18E-05; ._____________________________________05: a.18E-05: 8. 7E-05 g rwf 2tr After: L i telease

6.93E-07: 8.25E-05: 8.25E-

.________________________________.___05: 1.03E-04: 8.26E-05:..ouE-05: 8.25E-05 2uarterly: i Limit

7.50E+00: 7.50E+00: 7.50E+0 7.50E+00: 7.50E+00: 7.50E+00: 7.50

.______________________________________0:____________________ s Quarter: Limit 0.00%: 0.00%: 0.00 0.00%: 0.00%: 0.00%: \\nn Prior:

o Rel

8.32E-07: 9.60E-05: 9.60E-0 1.29E-04: 9.61E-05: 9.60E-05:

9. .______________________________________5:_____________________ _____________59E-05 \\nn After: telease

8.53E-07: 9.68E-05: 9.67E-0 1.32E-04: 9.68E_05: 9.67E-05: 9.67

._______________--_____________________5:____________________ innual simit

1.50E+01: 1.50E+01: 1.50E+0 1.50E+01: 1.50E+01: 1.50E+01: 1.50

.____-___----___--_______________ _____1:_________________-___.._______ . Annual : simit 0.00%: 0.00%: 0.00%: 0.00%: 0.00%: 0.00% -_-___-__--___-_____________-___-____0.00%: l l l /~N )\\N.

,_m mm... 1,._ m m._. ,,_ -,. ~. _ Georgia Powar Company No. 930099-G Vogtle Llectric Generating Plant U-1 Unit # 1 BATCH GASEOUS EFFLUENT PERMIT O I. REQUEST d X NORMAL RELEASE POINT ESTIMATED START: UNPLANNED UNIT 1 CONTAINMENT PURGE / VENT 28-apr-1993 14:59:00 RELEASE VOLUME (ESTIM.) DISCHARGE POINT ESTIMATED STOP: 1.3932E+08 CF UNIT ONE PLANT VENT 03-ma ..............................................................y-1993 23:59:00 II. SAMPLE IDENTIFICATION NUMBER COLLECTION DATE/ TIME ANALYSIS DATE/ TIME 129 28-apr-1993 14:59:00 28-a .........................................................pr-1993 15:16:54 III. RADICANALYSIS - GASEOUS T-BODY DOSE RATE < 500 CUM. AIR DOSE-GAMMA (Q) <5 CUM. ORGAN DOSE (Q) < 7.5 4.05E-03 9.89E-05 1.03E-04 SKIN DOSE RATE < 3000 CUM. AIR DOSE-GAMMA (A) < 10 CUM. ORGAN DOSE (A) < 15 5.93E-03 1.60E-03 1.32E-04 ORGAN DOSE RATE < 1500 CUM. AIR DOSE-BETA (Q) < 10 6.41E-04 1.31E-04 CUM. AIR DOSE-BETA (A) < 20 4.48E-03 IV. RADIATION MONITOR (S) NUMBER SETPOINT EFFECTIVE GAIN EXPECTED RESPONSE ACTUAL RESPONSE /^ 1RE2565C 1.61E-03 uC1/cc 7.99E-09 uCi/cc/ cpm 1.30E-07 uCi/cc uCi/cc (' 1RE12442C 3 16HNWC. A.06E-04 uCi/cc 1.60E-08 u 1.14E-08 uCi M*. W...u t#.c...d. 62. M. C1/cc/com... F.0/4yy'&1.......... / c c uCi/cc ) V. AUTHORIZATION { MAX VOLUME MAX. EFFLUENT FLOW RATE 2.7500E+06 CF 1.8000E+04 CFM i The above-named source has been sampled and analyzed and is in compliance with applicable Technical Specificat4cns. Release is authorized for the volume and flow rates specified. ( COf /lA J LAB FOREMAN jg Purge Required for (check 1) TECHNICAL REVIEW: W< rj n4 '4' B OSOS-5/UM. /][ /) _ Containment Pressure Control _ Purge Valve Survellance Tests AUTHORIZATION: _ AIARA (personnel entry) ..................................... _......pirable Air Quality (personnel entry) Res VI. RELEASE DATA TIME DATE TANX EFFLUENT OPERATOR'S PRESSURE FLOW .................+......+.......+...........+.......... RATE INITAILS ..........+.............. \\ START l l l .................+......+.......+...........+l.....................+l.............. STOP l l l XXYYYYY .............................................l.........XXXXXXXXX l

n_ --m- ~ ~ - - "- ~ ~ ~ ' " * " ~ ~ " ~ Georgia Power Company Vogtle Electric Generating Plant U-1 page 1 of 6 ) Gaseous Radioactive Waste Release Permit 930099-G J Pre. Release Supp amentary Data PART I: PRE-RELEASE DATA Release Point ( 25): UNIT 1 CONTAINMENT PURGE / VENT Discharge Point ( 5): UNIT ONE PLANT VENT Permit Issued: 28-apr-1993 19:06:12 Release Type: Batch-Rad Monitor: (25) 1RE2565C Rad Monitor Bckgrnd: 0.0000E+00 CPM Estim. Waste Flow: 1.8000E+04 CFM Estim. Waste Volume: 1.3932E+08 CF j Estim. Release Start: 28-apr-1993 14:59:00 Estim. Release End: 03-may-1993 23:59:00 # Estim. Duration: 7740.0000 MIN PART II: PRE-RELEASE CALCULATIONS Sample Entry # : 129 Gas sample time: 28-apr-1993 14:59:00 Sampled by: MKJ / Gas Monitor Response: 1.63E+01 CPM ( Total Body Dose Rate: 4.05E-03 mrem /yr t Limit = 0.0% 4 Skin Dose Rate: 5.93E-03 mrem /yr t Limit = 0.0% Max Organ Dose Rate: 6.41E-04 mrem /yr t Limit = 0.0% Max Monitor Setpoint: 1.61E-03 uCi/cc Flag: _- 2.01E+05 CPM Flags: A-Release Curies > Local Limit N. Noble Gas Dose Rate > Limit S-Release Curies > Site Limit 0-Organ Dose Rate > Limit Analysis Date Measured Est. Curies ......................................................Concen. Noble Gases 28.apr-1993 15:16:54 1.30E-07 uCi/cc ' 5.13E-01 Particulates 28-apr-1993 15:26:17 1.82E-12 uCi/cc 9' 7.19E-06 Radiciodines 28-apr-1993 16:40:25 7.26E-12 uCi/cc-"' 2.87E-05 LAB FOREMAN I TECHNICAL REVIEW: I .. )./ .....-f................................................. b ~

m --- a m u s,rc % Georgia Power Company page 2 of 6 b Vogtle Electric Generating Plant U-1 Gaseous Radioactive Waste Release Permit 930099-G Pre-P.elease Supplementary Data ISOTOPIC IDENTIFICATION - Unit 1

Pre-Disp. : Pre-Disp. : ' Pre-Disp. : Conc / Total:

Release

Estimated

Measured

Measured

Measured by Rate Curies Isotope :

uCi/cc

Conc /MPC

Conc / Total:

T uCi/sec

Released

.................................................ype / H-3 0: 4.04E-08 : 2.02E-01 : 2.37E-01 : 1.00E+00 : 3.43E-01 : 1.59E-01 I-131 R: 7.26E-12 dI 7.26E-02 : 4.26E-05 : 1.00E+00 : 6.17E-05 : 2.87E-05 AR-41 N: 1.16E-07 w' 2.90E+00 : 6.81E-01 : 8.93E-01 : 9.87E-01 : 4.58E-01 XE-133 N: 1.40E-08 a' 4.66E-02 : 8.20E-02 : 1.07E-01 : 1.19E-01 : 5.52E-02 BR-82 P: 1.82E-12 e' 3.04E-04 : 1.07E-05 : 1.00E+00 : 1.55E-0 7.19E-06 ................................................................. 5............. Totals : 1.71Er07 : 3.22E+00 : 1.45E+0 6.73E-01 ................................................................. 0............. f 1 i

~_ n sa >.x_ .,n_, ______,._4_____ _ _ Georgia Power Company page 3 of 6 Vogtle Electric Generating Plant U-1 Gaseous Radioactive Waste Release Permit 930099-G Pre-Release Supplementary Data Report Category

Calculated Doses at Site Boundary.

Gamma and Beta Air Doses, Tot-body and Skin

Doses and Dose Rates.

Type of Activity

Noble Gases Controlling Sector

NE Unit number 1

Site

Tot-body

Skin Dose : Gamma Air : Beta Air

Tot-body

Skin

Boundary

Dose

mrem

mrad

mrad

Dose Rate : Dose Rate

Dist (km) : mrem

mrem /

................................................................ year : mrem / year NE : 1.13E+00 : 5.96E-05 : 8.73E-05 : 6.27E-05 : 2.29E-05 : 4.05E-03 : 5.93E-0 ............................................................................. 3 is e O l 1 i I l l \\ l l I 1 .__._____.________,I

... ~. Georgia Power Company page 4 of 6 Vogtle Electric Generating Plant U-1 Gaseous Radioactive Waste Release Permit 930099-G Pre Release Supplementary Data Report Category

Calculated Dose Rate to Man (mrem / year) from this Release at Site Boundary.

Type of Activity

Radiciodines and Particulates Age Group & Pathway (s)

Child

Inhalation Controlling Sector

NE Unit number 1

Bone

Liver

Tot-body

Thyroid

Kidney

Lun

..............................................................g

GI-LLI NE : 1.37E-06 : 1.80E-04 : 1.79E-04 : 6.41E.04 : 1.81E-04 : 1.78E-04 : 1

........................................................................ 78E-04 J l 1 I l I 1 I 1 l 1 .. -. - - - - - -. ~ - - - ,c ---,.,.,r...

~ ame m-mcame-- e eme-r u =----=* re==,-enw mmu

==-- r-we Georgia Power Company page 5 of 6 Vogtle Electric Generating Plant U-1 (~N Gaseous Radioactive Waste Release Permit 930099-G Pre-Release Supplementary Data Report Category

Cumulative Dose at Site Boundary Type of Activity

Noble Gases Location

NE at 1.127 km.

Unit number 1

Tot-body

Skin

Gamma Air : Beta Air

mrem

mrem

mrad

mrad This Release

5.96E-05 : 8.73E-05 : 6.27E-05 : 2.29E-05 :

31D Prior: To Rel

2.83E-05 : 6.69E-05 : 3.40E-05 : 1.01E-04 :

31D After: Release

8.43E-05 : 1.49E-04 : 9.29B-05 : 1.23E-04 :

31 Day Limit

0.00E+00 : 0.00E+00 : 2.00E-01 : 4.00E-01 :

% 31 Day : Limit 0.00%: 0.00%: 0.05%: 0.03%: Qtr Prior: To Rel

3.02E-05 : 7.12E-05 : 3.62E-05 : 1.08E-04 :

3; Qtr After: Release

8.978-05 : 1.59E-04 : 9.89E-05 : 1.31E-04 :

Quarterly: Limit

0.00E+00 : 0.00E+00 : 5.00E+00 : 1.00E+01 :

) % Quarter: Limit 0.00%: 0.00%: 0.00%: 0.00%: Ann Prior: To Rel

1.29E-03 : 3.03E-03 : 1.54E-03 : 4.46E-03 :

1 Ann After: Release- : 1.14E-03 : 3.12E-03 : 1.60E-03 : 4.48E-03 1 Annual Limit

0.00E+00 : 0.00E+00 : 1.00E+01 : 2.00E+01

% Annual : i Limit 0.00%: 0.00%: 0.02%: 0.02 i l A e f* i /

- - m. w a. ,.m. u - m .- s.= w w n. n.x-,., m. _ m.a Georgia Power Company page 6-of 6 Vogtle Electric Generating Plant U-1 Gaseous Radioactive Waste Release Permit 930099-G Pre-Release Supplementary Data 4 Report Category-

Cumulative Maximum Individual Dose (mrem).for Controlling Age Group at Controlling Location Type of Activity

Radiciodines and Particulates Age Group & Pathway (s)

Child

. Gr_ Plane; Inhalation Location

WSW at 1.931 km.

Unit number 1

Bcne

Liver

Tot-body : Thyroid

Kidne

.......................................................y

Lung

GI-LLI This Release

2.10E-08: 7.43E-07: 7.40E-07: 2.61E-06: 7.46E-07: 7.37 7.38E-07

.................................................................E-07: 31D Prior: To Rel

6.31E-07: 7.69E-05: 7.68E-05: 9.45E-05: 7.69E-05: 7 7.68E-05

.............................................................. 69E-05: 31D After: Release

6.51E-07: 7.75E-05: 7.75E-05: 9.70E-05: 7.76E-05: 7 7.75E-05

.............................................................. 76E-05: 31 Day Limit

3.00E-01: 3.00E.01: 3.00E-01: 3.00E-01: 3.00E-01: 3.

3.00E.01 .............................................................. 00E-01: % 31 Day : Limit 0.00%: 0.03%: 0.03%: 0.03%: 0.03%: 0.03% ............................................................... 0.03%: Otr Prior: To Rel

6.72E-07: 8.18E-05: 8.18E-05: 1.01E-04: 8.18E-05: 8.1 8.18E-05

............................................................... 8E-05: Qtr After: Release

6.93E-07: 8.25E-05: 8.25E.05: 1.03E-04: 8.26E-05: 8.2 8.25E............................................................... 6E-05:

Quarterly: Limit

7.50E+00: 7.50E+00: 7.50E+00:'7.50E+00: 7.50E+00: 7 7.50E+00

.............................................................. 50E+00: t Quarter: Limit 0.00%: 0.00%: 0.00%: 0.00%: 0.00%: 0.00% ............................................................... 0.00%: Ann Prior: To Re1

8.32E-07: 9.60E-05: 9.60E-05: 1.29E-04: 9.61E-0 9.60E-05: 9.59E-05

.............._........................................... 5: Ann After: Release

8.53E.07: 9.68E-05: 9.67E-05: 1.32E-04: 9.68E.0 9.67E-05: 9.67E-05

......................................................... 5: Annual Limit

1.50E+01: 1.50E+01: 1.50E+01: 1.50E+01: 1.50E+

1.50E+01: 1.50E+01 ........................................................ 01: % Annual : Limit 0.00%: 0.00%: 0.00%: 0.00%: 0.00%: 0.00% ..................................................... 0.00%: b I

(~ 1993 NRC GRADED EXERCISE August 4,1993 SCENARIO ABSTRACT The initial conditions have Unit 2 defueled and in a refueling outage. Unit 1 is in Mode 1 at 100% power and has been on line for 222 days. All control systems are in automatic. Containment mini-purge is in service in preparation for a containment entry to repair pressurized level transmitter 461, which is out of service. Additionally, RHR train A is out of service due to scheduled bearing replacement. The drill scenario creates conditions for an offsite release through the sequential failure of the three fission product barriers. An event is postulated which results in fuel damage and release of fission product activity to the Reactor Coolant System (RCS). In this event, control bank D control rod H-8 drops to the full "in" position in the reactor core due to a blown stationary gripper fuse. Fuel failure occurs due to localized overheating. Various radiation sensors alarm due to the fuel failure. Mini purge damper lHV-2626B inside reactor containment fails to close when operators attempt a manual closure. An alert emergency is declared due to the breach or challenge of one of the three fission product barriers. At Alert Emergency, the ERDS in initiated, the TSC and OSC are activated, and the EOF placed on standby. Accotmtability is initiated and completed. The mechanism for control rod H-8 ruptures, resulting in a leak in the reactor vessel head. This initiates a reactor trip and SI. RHR B pump fails to start due to faulty relays and purge supply isolation damper lHV-2626B fails to automatically close on SI. A site area emergency is declared due to the breach or challenge of two of the three fission product barriers. The EOF is activated with the declaration of a site area emergency. A bomb threat is received, with an explosion subsequently occurring in the Unit 1 HVAC containment purge equipment room. Plant personnel are dispatched to investigate and report that containment purge isolation damper lHV-2627B and associated piping is breached due to an explosion. A general emergency is declared due to the breach or challenge of three fission product barriers. Protective action recommendation are made to state agencies. The release path is isolated by closing lHV-2626B, which leads to emergency tennination and recovery actions. O GE-93 1 EX4012

~ 1993 NRC GRADED EXERCISE August 4,1993 SCENARIO TIME LINE CLASS TIME EVENT 08:00 Start Drill. 08:05 Control Bank D control rod H-8, drops to the full "in" position in the reactor core (due to a blown stationary gripper fuse). Flux distribution abnormality begins due to the dropped control rod. + Control Room Operators enter Abnormal Operating Procedure 18003-C + " Rod Control System Malfunction" and reduce reactor power to less than 90%. 08:20 Fuel failure occurs due to localized overheating. Chemical Volume Control System (CVCS) letdown radiatien monitor RE- + 48000 alarms on the ERF computer and rapidly goes off-scale high. Radiation levels in the Reactor Coolant System (RCS) sample area start to increase (RE-0078). Chemistry is directed by the control room to sample the RCS. 08:22 The Gross Failed Fuel Detector alarms. 08:25 Control Room may isolate containment mini-purge HVAC. Damper 1HV-2626B inside reactor containment (IRC) fails to close. ALERT 08:35 ALERT EMERGENCY declared due to the breach or challenge of one of three fission product barriers. Unit shutdown commenced. 08:50 Emergency Response Data System to NRC activated. 09:00 TSC and OSC activated. EOF coming to standby. 09:05 Injured person call-in to control room. 09:05 Accountability complete. 09:10 EOF in standby. GE-93 1 EX4007

1993 NRC GRADED EXERCISE August 4,1993 /~N U SCENARIO TIME LINE CLASS TIME EVENT 09:30 The mechanism housing for control rod H-8 ruptures, resulting in a four inch diameter leak in the reactor vessel head. Reactor Trip (if not already actuated) and Safety Injection. + RHR B pumps fails to start - trips due to faulty relays. PERMS data no longer available due to Safety Injection. Purge supply isolation damper lHV-2626B fails to close. + SITE AREA 09:45 SITE AREA EMERGENCY declared due to the breach or challenge of two of three fission product barriers. 10:15 EOF activated. O 10:45 Bomb threat called in to the main control room. (Disgruntled employee) 11:00 Explosion in the Unit 1 Heating Ventilation and Air Conditioning (HVAC) containment purge supply " equipment room" (Outside reactor containment (ORC) and located next to the north main steam valve room). Security alarm for door IC108 (room 114). + Fire alarm for fire zone 141B, local zone indicating panel (LZIP) IS48; + (rooms 114,116, and 125). Containment HVAC purge supply isolation damper lHV-2627B (ORC) QHVC light indication extinguishes. 11:01 Security dispatches oflicer to investigate door alarm. I1:01 Fire protection technician dispatched to LZIP IS48. I1:05 Security ollicer calls in to report conditions. (Steam flowing out, scattered debris, door blown ofl). O GE-93 2 EX4007

4 1993 NRC GRADED EXERCISE August 4,1993 C\\ d SCENARIO TIME LINE CLASS TIME EVENT 11:06 Fire protection tech calls in to report fire alarm investigation information. Containment HVAC purge supply isolation damper lHV-2627B and associated piping discovered breached due to bomb. GENERAL 11:15 GENERAL EMERGENCY declared due to the breach or challenge of three of three fission product barriers. Protective Action Recommendations (PAR's): Evacuate Zones A, C-5, D-5, E-5, F-5, SRS to 2 miles. Shelter the remainder of the plume EPZ. 12:00 lHV-2626B is shut, isolating the release path. 12:30 Emergency Terminated and Recovery Organization activated. 13:00 Drill Terminated. O GE-93 3 EX4007 l

1993 NRC GRADED EXERCISE AUGUST 4,1993 r~'(N) SIMULATOR SCRIPT A. SIMULATOR SETUP 1. Reset to IC #14. 2. IC Setup: a. Place containment mini purge in service per SOP 13125-1. b. Place RHR " A" handswitch,1HS 0620 in PTL. c. Fail pressurizer level channel 461 to 0%. Malf # PR03C. d. Trip channel 461 bistables. Remote Function ES27. e. Acknowledge annunciators. 3. Snap a temporary IC (Snapshot IC # ). 4. Run and catalog the following programs: a. (TOM) G.CHL1. AUG Seg 1 b. (TOM) G.CHL2.AUG Seg 1 c. (TOM) G.CHL3.AUG Seg 2 d. (TOM) G.RM. AUG Seg 10 e. (TOM) G.SISL.AUG Seg 11 5. Reset to temporary IC. 'N_. 6. Control Board Setup: a. Set control rod step counters to 228 steps on Bank D b. Ensure operator aid for.11 target @ MOL is in place on OMCB panel 'C'. c. Place hold tag on 1HS-0620 "A" RHR pump d. Ensure BAST analysis on the boron meter sample board is 7200 pprn. e. Ensure Accumulator sample analysis is updated. f. Set the ERF computer to MODE 1 7. Insert the following malfunctions: a. "RHR pump trip" (RHR pump 2), malfunction RH01B b. ' " Containment mini-purge supply isolation damper 1HV 26268 fails to close", YP:XMFB(269)=T 8. Parameters to Monitor: a. EDCLOCK b. RMCNTR2 c. RMCNTR3 d. CHFMLEAK e. SIV8801 A 9. Check / Set ERF computer and simulator clocks. GE-93 1 July 27,1993

1993 NRC GRADED EXERCISE AUGUST 4,1993 g SIMULATOR SCRIPT B. EXERCISE SETUP 1. Conduct pre-drill briefing with simulator players using message #1. C. EXERCISE 08:00 Place simulator in RUN 08:05 Insert malfunction RD131, " Dropped RCCA H-8 CBD" 08:05 + If attempts are made to close HV-26268 by pulling the fuses to solenoid, insert malfunction YP:XMFTB(266)=T. (NOTE: This will not close HV-26268 because of the override) 08:22 Insert annunciator override 464,0N, "GFFD Alarm" 09:30 Insert malfunction RD16, "RCCA H-8 ejected" 09:30 + If the operators attempt to decrease ECCS flow by throttle methods directed from EOP 19111-C, then insert remote function "HV-8801 A BIT isolation valve position" as follows: a. SET YREMFADD(17)=1.0 co 0.0 (as desired) b. SB YP:REMF(241)=T 11:00 Insert the following malfunctions to trip the mini-purge supply HVAC unit 1-1505-B7-002 M01, remove indicating lights from 1HS-26278, and create a 14" diameter breach in containment: a. YP:XMFTB(265) = T; " Explosion" b. YP:X MFTB(172) = T, and YPXSVRTY(149)= 50.0; " Containment Leak to Atmosphere" 11:25 Insert malfunction FP02 @ 10%, " Fire Protection System Acutation (Motor Driven Fire Pump)" 12:00 Remove " Containment mini-purge supply isolation damper 1HV-26268 fails to close", YP:XMFB(269) = F and remove malfunction " Containment Leak to Atmosphere" by setting YP:XMFTB(172)=F 13:00 Terminate the Drill upon the direction of the Lead Controller. 13:00 + Run and catalog the following programs: a. (SRCE) G.CHL1 Seg 1 b. (SRCE) G.CHL2 Seg1 c. (SRCE) G.CHL3 Seg 2 O d (SRCE) G.RM Seg 10 e. (SRCE) G.SISL Seg 11 GE 93 2 July 27,1993

IN-PLANT MESSAGE O TO: Control Room Operations / Maintenance Manager / TIME: 0800 General Manager FROM: All Onsite Lead Controllers THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. INITIAL CONDITIONS MESSAGE: Unit 2 is in a refueling outage. The reactor is de-fueled. Unit 1 is in Mode 1 at MOL in Cycle 5, operating at 100% power. The unit has been on line for 135 days. + Containment mini-purge is in service (release permit # 93099-G) in preparation for a + containment entry to repair the transmitter for ILT-461. All control systems are in automatic. OU Key Unit 1 Parameters: Reactor Power = 100% RCS at NOTP + RCS boron concentration = 1003 ppm (BAST = 7100 ppm) + Pressurizer level and Steam Generator levels at program Core burnup = 9000 MWD /MTU + Unit 1 Systems / Equipment Out Of Service @ Pressurizer level channel "461" due to a faulty transmitter. I&C preparing for containment entry to replace the transmitter. @ RHR "i" train out of service (72 hour LCO bearing replacement) scheduled to return to service 1600 August 5. Meteorological Data: Wind Direction 90 (from) Wind Speed 2.3 mph + Temperature 80 + Stability Class B + Precipitation 0" in the past 24 hours + ( TIIIS IS A DRILL l GE-93 1 EX4008

IN-PLANT MESSAGE l} \\- TO: PEO at Bank "D" control panel (Dropped Rod H-8) TIME: 0810 FROM: PEO Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Use attached drawings to convey appropriate conditions. O O TIIIS IS A DRILL l GE-93 2 EX4008

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IN-PLANT MESSAGE TO: I&C Technician Team (Dropped Rod H-8), TIME: 0815 (Room B71 Control Building) FROM: I&C Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Provide the following indications of a blown stationary gripper fuse. Cabinet number 2BD; Fuse "27" pop out indicator is visible. O CONTROL,LER INFORMATION: Cabinet 2BD is located in Room B-71 of the Control Building. O TIIIS IS A DRILL GE-93 3 EX4008 L

IN-PLANT MESSAGE O TO: Chemistry StafT (Primary Lab - Control Building) TIME: 0822 i FROM: Chemistty/HP Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: i Personnel EDRD's are alarming and the Area Rad Monitor (ARE-0007B) is alarming. l AV CONTROLLER INFOIDIATION: Issue only when chemistry personnel approach sample area to collect chemistry sample. ) O THIS IS A DRILL GE-93 4 EX4008

IN-PLANT MESSAGE TO: Primary Lab Personnel (Control Building) TIME: 0822 FROM: Chemistry Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: The display reading for Sample Sink Area Radiation Monitor (ARE-0007B)is 7.5E+2 mr/hr. \\ O CONTROLLER INFORMATION: Hang this message over the display window of monitor. TIIIS IS A DRILL GE-93 5 EX4008

IN-PLANT MESSAGE /~] TO: Simulator Crew TIME: 0822 FROM: Simulator Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Gross Failed Fuel Detector (GFFD) chart is reading off-scale high. Meter is off-scale high on wide & narrow range. Low (flow) alarm light is off. High alarm light is on. 6 TOS Wide Range: 1 x 10 cpm 4 TOS Narrow Range: 1 x 10 cpm O CONTROLLER INFORMATION: Issue to operator only when looking at GFFD meter. Use Attached Drawings. O TIIIS IS A DRILL GE-93 6 EX4008 I

E O O GROSS Fall FUEL DETECTOR n n ....._,0' 10 1 2 CPM g 10 1 1.5 i .5 2 0 0 POW ER NEUTRON CHANNEL OPERATION SELECTOR RANGE SELECTOR RMTE 3600 l CPM CAL OPERATE WIDE RESET NARROW - LEVEL CAL. PULSE CAL. O 2A SLO BLOW O l

O O O GROSS Fall FUEL DETECTOR n n 10 to 2 CPM 2 10 5 .s 2 o O POT \\ ER NEUTRON CH.ANNEL OPERATION SELECTOR RANGESELECTOR RMTE 3600 CPM CAL OPERATE WIDE RESET NARROW LEVEL CAL. ( II\\, g PULSE CAL. O 2A SLO BLOW O

IN-PLANT MESSAGE TO: PEO or Maintenance Team TIME: 0825+ FROM: HP Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Do not allow simulated containment entry if team is ready prior to 9:30. After 9:30 containment conditions will not allow entry. lkt s. w \\ / i dik ) f g_ w A,di@rf[g s /g e n,.y%9 . lw "O .5 l sf$f):5 5 e)%r +f yD. k ,y

6. w::( &

p>Qw: g g,_ '"Ni@ A;i s }% n/ jg: 'y p% s, y .*fff%%hh nvg g &? g gy j%q;) &] wif TIIIS IS A DRILL GE-93 7 EX4008 J

IN-PLANT MESSAGE TO: Primary Lab Chemistry Staff TIME: 0835 FROM: Chemistry /HP Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Chemistry must use PASS to obtain RCS sample. CONTROLLER INFORMATION: Issje only if Operations does not request PASS sample from Chr.mistry. O' TIIIS IS A DRILL GE-93 8 EX4008

IN-PLANT M ESSAGE r TO: Shift Superintendent TIME: 0835+ FROM: Simulator Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Declare an ALERT based on: A breach or challenge of 1 of 3 fission product barriers. / g% &o r*9 s e. i:%,)

%:(*

Ashdi 4 gy/ A Na / y l%* MO * ,A $$y c s j% " ]%g Ak 5% V f(4 spNy [thh ' g( Q vr i l hW CONTROLLER INFORMATION: Issue only on direction from Lead Controller. W \\ TIIIS IS A DRILL GE-93 9 EX4008

IN-PLANT MESSAGE TO: Shift Superintendent / Control Room TIME: 0835+ Plant Page Conununicator FROM: Simulator / Control Room Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: 1. Make this announcement after you receive call from Simulator Plant Page Communicator. a. " ATTENTION ALL PERSONNEL - TIIIS IS A DRILL - AN ALERT HAS BEEN DECLARED FOR UNIT I DUE TO FUEL DAMAGE. b. EMERGENCY RESPONSE PERSONNEL REPORT TO YOL R EMERGENCY RESPONSE FACILITY. O c. " PERSONNEL WORKING (ON/IN) CALL CONTROL ROOM AT EXTENSION AND CONTINUE WORK" 1 d, ALL OTIIER PERSONNEL EXIT TIIE PROTECTED AREA AND REPORT TO THE ADMINISTRATION BUILDING. TIIIS IS A DRILL. II. Sound the alarm for an Alert - Warble Tone (15 seconds). III. Repeat the announcement from Step I. CONTROLLER INFORMATION: ~ Note that assembly and accountability will actually be performed. Use this if ALERT is declared due to fission product barrier breach / challenge. TIIIS IS A DRILL l GE-93 10 EX4008 1 )

w-IN-PLANT MESSAGE TO: Emergency Director TIME: 0840+ FROM: Lead Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Use this script for EARLY DISMISSAL announcement: TIIIS IS A DRILL " ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL. THE EMERGENCY DIRECTOR HAS DIRECTED A SIMULATED EARLY DISMISSAL. TAKE NO EARLY DISMISSAL ACTION BECAUSE THIS IS A DRILL." (Repeat announcement) i i CONTROLLER INFORMATION: Early Dismissal can be ordered any time afler declaration of Alert Emergency. Give this message to the ED if and when he decides Early Dismissal is appropriate. TIIIS IS A DRILL l GE-93 11 EX4008

IN-PLANT MESSAGE TO: Shift Superintendent / Control Room TIME: 0845+ Plant Page Communicator FROM: Simulator / Control Room Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: j I. Make this announcement after you receive call from Simulator Plant Page Communicator. j a. " ATTENTION ALL PERSONNEL-TIIIS IS A DRILL-AN ALERT HAS BEEN DECLARED FOR UNIT 1 DUE TO FUEL DAMAGE. b. EMERGENCY RESPONSE PERSONNEL REPORT TO YOUR EMERGENCY RESPONSE FACILITY. c. " PERSONNEL WORKING (ON/IN) CALL CONTROL ROOM AT EXTENSION AND CONTINUE WORK" d. ALL OTIIER PERSONNEL EXIT THE PROTECTED AREA AND REPORT TO THE ADMINISTRATION BUILDING. TIIIS IS A DRILL. II. Sound the alarm for an Alert - Warble Tone (15 seconds). III. Repeat the announcement from Step I. CONTROLLER INFORMATION: Second announcement during accountability. TIIIS IS A DRILL l GE-93 12 EX4008

IN-PLANT MESSAGE TO: Shift Superintendent / Control Room TIME: 0855+ Plant Page Communicator FROM: Simulator / Control Room Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: 1. Make this announcement afler you receive call from Simulator Plant Page Communicator, a. " ATTENTION ALL PERSONNEL-TIIIS IS A DRILL-AN ALERT HAS BEEN DECLARED FOR UNIT 1 DUE TO FUEL DAMAGE. b. EMERGENCY RESPONSE PERSONNEL REPORT TO YOUR EMERGENCY RESPONSE FACILITY. c. " PERSONNEL WORKING (ON/IN) CALL CONTROL ROOM AT EXTENSION AND CONTINUE WORK" d. ALL OTHER PERSONNEL EXIT THE PROTECTED AREA AND REPORT TO THE ADMINISTRATION BUILDING. Tills IS A DRILL. II. Sound the alarm for an Alert. Warble Tone (15 seconds). III. Repeat the announcement from Step I. CONTROLLER INFORMATION: Third announcement during accountability. TIIIS IS A DRILL l GE-93 13 EX4008

IN-PLANT MESSAGE TO: OSC Repair Team (A-Train RHR Pump) TIME: 0900+ FROM: OSC Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: The new lower motor bearing was damaged during installation. The replacement should arrive by federal express today at 1600 hours. O CONTROLLER INFORMATION: This message should be issued to the team that was working on "A" train RHR pump motor replacement. O TIIIS IS A DRILL GE-93 14 EX4008

IN-PLANT MESSAGF, TO: Simulator (Extension 4369) TIME: 0905 FROM: Injured Individual (Medical Emergency Lead Controller) TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: "(This is a drill). I need help in the Administration Building Auditorium. has fallen and is complaining of chest pains. (This is a drill)" O = CONTROLLER INFORMATION: The injured individuals co-worker should telephone the above report into the Simulator (Extension 4369). Do not transmit any additional information. O' TIIIS IS A DRILL GE-93 15 EX4008

IN-PLANT MESSAGE h TO: Shift Superintendent TIME: 0906+ FROM: Simulator / Control Room Controller THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Page 911 for first responders. A$ Ad _/"', $' 4 $hp * +% WQv::m& n ?*4 y k V , N{%h y# A%/ At.94P 4 <t / d*3h 2' h M ckk? *g w [ *Nky d a by g h %%d? A, 7 f( Mh h -h a + Sk ff y;p { dM ' ' a) *9; [ 3j' ~%e' a )o %,w. THIS IS A DRILL GE-93 16 EX4008

IN-PLANT MESSAGE TO: Control Room Page (Controller) TIME: 0910 FROM: TSC Lead Controller TIIIS IS A DRILL DO NOT Initiate actions affecting normal plant operations. MESSAGE: "All personnel who assembled in the Administration Building as part of the assembly / accountability return to your work stations" O 1 l 1 CONTROLLER INFORMATION: Issue after assembly and accountability have been completed and not later than I hour afler the start of assembly and l accountability (declaration of Alert). ( l N TIIIS IS A DRILL GE-93 17 EX4008

IN-PLANT MESSAGE ob TO: Medical Emergency Response Team TIME: 0915+ FROM: Medical Emergency Lead Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Upon arriving at the Admin. Building Auditorium you observe a man lying on the floor. He is conscious and agitated. M EDICAI, SYM PTO51S: Conscious and complaining of chest pain, shortness of breath. Skin is pale and clammy. Patient clutching his chest. Patient has taken two nitroglycerin with no relief. CONTROLLER INFORMATION: Simulator / Control Room telephone 4369 TIIIS IS A DRILL GE-93 18 EX4008

IN-PLANT MESSAGE O TO: Medical Emergency Response Team TIME: 0915& FROM: Observation (Medical Ernergency Lead Controller) TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. Pulse Illood Respirations Notes (beats er min Pressure ( ier minute)

]Wf:.z:.ra when found 80 100/60 shallow Labored breathing, chest pains 15 mins later 84 106/60 shallow Irregular respirations, shortness of breath l 30 mins later l

84 100/60 shallow l same: l CONTROLLER INFORMATION: First responders should reassure the patient and keep patient calm. Other expected actions by the first responders are taking vital signs and packaging patient for transport. V TIIIS IS A DRILL l GE-93 19 EX4008

IN-PLANT MESSAGE O TO: TSC Manager TIME: 0915+ FROM: TSC Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Ambulance should simulate transport ofinjured person to Burke County Hospital. O l CONTROLLER INFORM ATION: Hand to TSC Manager only in the event he is unsure where ambulance should go. Ambulance will not actually arrive at the plant site nor transport patient to hospital. O TIIIS IS A DRILL l GE.93 20 EX4008

IN-PLANT MESSAGE TO: HP Supervisor in TSC TIME: 0930 FROM: TSC Controller FIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: PERMS data no longer available on PERMS CRT. O CONTROLLER INFORMATION: Hang message over face of PERMS CRT. O' TIIIS IS A DRILL GE-93 21 EX4008

IN-PLANT MESSAGE TO: HP Supervisor /HP Control Point TIME: 0930 FROM: HP Control Point Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: PERMS data no longer available on PERMS CRT. O CONTROLLER INFORMATION: Hang message over face of PERMS CRT. d O l TIIIS IS A DRILL GE-93 22 EX4003

IN-PLANT MESSAGE TO: PEO responder TIME: 0940+ ("B" Train RIIR - Rm A-50 Control Building) FROM: PEO Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Describe scene to OSC repair team player. GREEN LIGHT ON RED LIGHT OFF If upper cubicle door is opened the red light resistor is charred. CONTROLLER INFORMATION: Do not give upper cubicle information unless PEO opens door. TIIIS IS A DRILL i i GE-93 23 EX4008

IN-PLANT MESSAGE TO: OSC Repair Team TIME: 0940+ ("B" Train RHR - Rm A-50 Control Building) FROM: OSC Controller TIIIS IS A DRILL I DO NOT initiate actions affecting normal plant operations. MESSAGE: Describe scene to OSC Repair Team player. GREEN LIGHT ON RED LIGHT OFF h' upper cubicle door is opened the red light resistor is charred. b P CONTROLLER INFORMATION: Repair personnel could simulate pulling a resistor from any other equipment with a red indicating light which is not operating (example "A" Train RHR). TIIIS IS A DRILL l GE-93 24 EX4008

IN-PLANT MESSAGE TO: Shift Superintendent TIME: 0945+ FROM: Simulator Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Declare a SITE AREA EMERGENCY based on: A breach or challenge of 2 of 3 fission product barriers. .d dsk ,;~ g# x Ab i . %ilb) f~NSS g t N A 17 ja:, u e ,eg >et *}? ao .N ? ns. S? [ bh Gj /L %p l ~ N Uh W j\\ %, ah' / 9 %q*uss f 'isF ,f*kw+? ? a-k) %9 O TIIIS IS A DRILL GE-93 25 EX4008

IN-PLANT MESSAGE TO: Shift Superintendent / Control Room TIME: 0945+ Plant Page Communicator FROM: Simulator / Control Room Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: 1. Make this announcement afler you receive call from Simulator Plant Page Communicator. a. " ATTENTION ALL PERSONNEL - TIIIS IS A DRILL - A SITE AREA EMERGENCY HAS BEEN DECLARED FOR UNIT 1 DUE TO A LARGE BREAK LOCA INSIDE CONTAINMENT / LOSS OF SECOND FISSION PRODUCT BARRIER." b. EMERGENCY RESPONSE PERSONNEL CONTINUE TO WORK ON SIMULATED EMERGENCY DUTIES." O II. Sound the alarm for a Site Area Emergency - Pulse Tone (15 seconds). III. Repeat the announcement from Step I. l CONTROLLER INFORMATION: Use this if a Site Area Emergency is declared due to product barriers breach / challenge. O TIIIS IS A DRILL i GE-93 26 EX4008 l

IN-PLANT MESSAGE TO: Sirnulator Control Room (Ext. 4369) TIME: 1045 FROM: Disgruntled Employee (Controller) TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: "TIIIS IS A DRILL. TIIIS IS A DRILL. I have placed a bomb in the protected area and it will go ofrat about 1100 this morning and you can't do a thing about it. I'll teach you people not to treat me the way you do. TIIIS IS A DRILL." CONTROLLER INFORM ATION: Read this message and give No additional information. TIIIS IS A DRILL GE-93 27 EX4008

IN-PLANT MESSAGE TO: Simulated Control Room TIME: 1100 FROM: TSC/OSC CONTROLLERS TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Make announcement to ALL players "You havejust now heard a loud thump. Tills IS A DRILL" O r \\ TIIIS IS A DRILL GE-93 28 EX4008 i l

IN-PLANT MESSAGE TO: Control Room Fire Technician TIME: 1100 FROM: Simulator Controller TIIIS IS A DRILL DO NOT initiate actions alTecting normal plant operations. MESSAGE: The Fire Computer has reported: Fire Alarm Zone 141B Fire Alarm LZIP IS48 O O TIIIS IS A DRILL GE-93 29 EX4008

IN-PLANT MESSAGE (J 10: Simnia,e, cent,ei Reem oge, ate,s rim e, iioo that respond to Seismic Panel FROM: Simulator Controller TIIIS IS A DRILI, DO NOT initiate actions affecting normal plant operations. MESSAGE: The " EVENT INDICATOR" located at SM-3 Control Rack of Seismic Control Panel (ANCQSIP) is "ON" and alarming. (white flag is showing) O CONTROLLER INFORMATION: Issue only afler simulator personnel arrive at SMA-3 control rack of the seismic control panel. OV TIIIS IS A DRILL l GE-93 30 EX4008

IN-PLANT MESSAGE TO: SAS/CAS Operators TIME: 1100 FROM: Security Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Door IC108 has an Alarm. O O TIIIS IS A DRILL l GE-93 31 EX4008

IN-PLANT MESSAGE TO: Simulator Shift Superintendent TIME: 1100 1 FROM: Simulator Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: ALL Seismic Equipment is working properly. O CONTROLLER INFORM ATION: Issue ifI&C is requested to inspect seismic equipment. TIIIS IS A DRILL l GE-93 32 EX4008

IN-PLANT NIESSAGE TO: Security Officers at Unit 1 HVAC Containment TIME: 1105+ Purge Supply Equipment Room FROM: Security Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Upon arriving at the scene you observe that there is steam filling the room from a broken pipe. (Rooms 114, 116, 125). The door has been torn from its hinges and there is NO fire or smoke present, only steam. Tills IS A DRILL l GE-93 33 EX4008

IN-PLANT MESSAGE 4 TO: Fire Protection Tech /PEO TIME: 1110+ FROM: Security Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: The door to rooms 114,116, and 125 has been torn from its hinges. The HVAC outside air intake louvers have also been blown out and are damaged. The containment HVAC piping before and up to HV-2627B is flared withjagged edges and is open to the environment and steam is coming out the pipe. There are blast marks around the room. O CONTROLLER INFORMATION: If personnel go into containment HVAC equipment room they will be contaminated. O TIIIS IS A DRILL GE-93 34 EX4008

IN-PLANT MESSAGE OV TO: OSC Repair Teams TIME: 1110+ FROM: OSC Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: After completing inspection of Rooms 114,116, and 125 you observed the following: Panel INB1702N door is open with charring inside. TV-12432C equipment bldg. HVAC outside air intake louvers are blown out. Some sections of the expand -o-flash around the outside of room is blown away. The containment IIVAC piping coming out of PEN 83 up to valve HV-2627B is blown away. The 'v end of the containment side of pipe is flared with jagged edges. CONTROLLER INFORMATION: These team members should be decontaminated upon exit of rooms if not properly dressed out. TilIS IS A DRILL GE-93 35 EX4008

IN-PLANT MESSAGE TO: Shift Superintendent TIME: 1123+ FROM: Simulator Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Upgrade to GENERAL EMERGENCY based on: A breach or chakenge of 3 of 3 fission product barriers. f dd em gik '$' $[ [ j y e s d% ?

']@h/

.k, 7 / ?q$)l ,.s: a lif% # J <.sy ' jd/ / Aff; $g p , q:,, s. Ff"M;- <n:i

g

)$,- h A e p / F f y,l*. if y 9 .i k h -% f* g ^ OO TIIIS IS A DRILL GE 93 36 EX4008

IN-PLANT MESSAGE }O d TO: Shift Superintendent / Control Room TIME: 1123+ / Plant Page Communicator FROM: Simulator / Control Room Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: I. Make this announcement after you receive call from Simulator Plant Page Communicator. a. " ATTENTION ALL PERSONNEL - TIIIS IS A DRILL - A GENERAL EMERGENCY HAS BEEN DECLARED FOR UNIT I DUE TO A BREACH OR CHALLENGE OF 3 OF 3 FISSION PRODUCT BARRIERS." b. EMERGENCY RESPONSE PERSONNEL CONTINUE TO WORK ON SIMULATED EMERGENCY DUTIES." O II. Sound the alarm for a General Emergency - Yelp Tone (15 seconds). 111. Repeat the announcement from Step I. O Tills IS A DRILL GE-93 37 EX4008 1

IN-PLANT MESSAGE O TO: Control Room Fire Technician TIME: 1125+ FROM: Simulator Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: The fire computer has reported: Electric fire Pump is running. O 1 TIIIS IS A DRILL GE-93 38 EX4008

IN-PLANT MESSAGE O To: eso'osc reems Time: >>23 FROM: Operations /OSC Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Post Indicating Valve 1-2301-U4-391 (fire water to unit I turbine building) is leaking water at the point where the valve enters the ground. (approximately 25 gallons per minute). O O rnis is A Dain I GE-93 39 EX4008

IN-PLANT MESSAGE l' TO: Health Physics Decon Team TIME: 1130+ FROM: Health Physics Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Initial Conenmination Survey Data: Overall body - 50k cpm Face - Chin - 30k cpm Decontamination Survev Data: O After ist decontamination efforts: \\ Overall body - 10k cpm Face - 5k cpm After 2nd decontamination efforts: Overall body 2k cpm Face - <100 cpm Afler 3rd decontamination efforts: Overall body <100 cpm CONTROLLER INFORMATION: These contamination levels are for all personnel that initially enter Rooms 114,116 and 125 of the control building. O TIIIS IS A DRILL GE-93 40 EX4008

i IN-PLANT MF.,SSAGE TO: Emergency Director, TSC Manager, OSC Manager TIME: 1215+ FROM: EOF Controller, TSC Lead Controller, OSC Lead Controller TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: P Time is advanced 48 hours. Plant conditions have stabilized. A RCS leak still exists but the core is covered and decay heat is being removed with RHR in hot leg recirc mode. Both trains of RHR are operational. Plant Temperatures is 112 F. The release of radioactivity from containment has stopped. Containment is full of radioactive gas. RE-002/003 read 100 mrem /hr. Make plans to enter Recovery and establish an Initial Recovery Organization. O TIIIS IS A DRILL l GE-93 41 EX4008

IN-PLANT MESSAGE TO: All Players TIME: 1300+ FROM: All Controllers TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: DRILL TERNIINATED All Players please complete critique forms and panicipate in critique process. O CONTROLLER INFORMATION: Issue only after approval of Lead Exercise Controller. i TIIIS IS A DRILL GE-93 42 EX4008

IN-PLANT MESSAGE TO: All Participants TIME: 1300+ FROM: Control Room Plant Page Communicator TIIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: 1. Make this announcement after you receive call from Simulator Plant Page Communicator. "NITENTION ALL PERSONNEL " ALL DRILL ACTIVITIES ARE TERMINATED. ALL DRILL ACTIVITIES ARE TERMINATED" O) CONTROLLER INFORMATION: Simulated Control Room telephone 4369 or 4370. TIIIS IS A DRILL GE-93 43 EX4008

PORT NAME i'QA CHECK I PAGE : -1 .EPORT DATE : OV-Ag-1993 03 :08 :26.25 VOGTLE ELECTRIC GENERATING PLANT RADIOCHEMISTRY ANALYSIS SYSTEM NID QUALITY CONTROL REPORT TITLE, Unit 1 RCS HOT LEG - LOOP 3 DEGASSED LIQ. i SAMPLE #

2650-93 SAMPLE GEOMETRY

SCIN_SO SAMPLE TYPE

DEGASSED LIQ SAMPLE QUANTITY

8.00000E+00 COUNT TIME

09-Ag3-1993 02:44:08.00 REACTOR UNIT #

1 SAMPLE TIME oy-A*g-1993 01:05:00.00 OPERATOR NAME

AROBERSON PEAK ENERGY DECAY CORR ISOTOPE ENERGY DIFF (KEV)

UCI/ML COMMENTS F-18 511.00 -0.14 1.022E-01

• Peak FWHM Suspect NA-24 1368.53

-0.15 3.347E-03 Nuclide QA Results OK CL-38 1642.42 0.25 8.852E-04

• Count Rate Error >50%

CR-51 320.08 -0.27 2.438E-02 Nuclide QA Results OK MN-54 834.83 -0.05 1.189E-02 Nuclide QA Results OK MN-56 1810.69 -0.28 1.186E-03 Nuclide QA Results OK CD-57 122.06 0.02 2.565E-04 Nuclide QA Results OK CO-58 810.76 -0.05 8.562E-02 Nuclide QA Results OK FE-59 1099.22 -0.11 3.775E-03 Nuclide QA Results OK CO-60 1332.47 -0.09 5.775E-03 Nuclide QA Results OK O NB-95 765.79 -0.07 4.730E-03 Nuclide QA-Results OK ZR-95 756.72 -0.07 3.045E-03 Nuclide QA Results OK NB-97 657.90 -0.36 1.198E-03 Nuclide QA R'esults OK ZR-97 743.36 -0.12 3.844E-04 Nuclide QA Results OK SN-113 391.69 -0.26 3.968E-04 Nuclide QA Results OK-I-133 529.87 -0.32 3.436E-04 Nuclide QA Results OK CS-134 795.85 -0.07 1.080E-03 Nuclide QA Results OK I-134 847.03 0.14 5.350E-03 Nuclide QA Results OK I-135 1260.41 -0.03 8.149E-04 Nuclide QA Results OK XE-135 249.79 -0.41 7.680E-05

• Peak FWHM Suspect
• Count Rate Error >30%

CS-137 661.65 -0.11 1.263E-03 Nuclide QA Results OK CE-144 133.20 -0.37 1.814E-03 ~ Peak FWHM Suspect W-187 479.53 -0.21 5.167E-04

• Count Rate Error >30%

AVG ENERGY DIFF = -b$k4 6b3Ebk=TOTALGAMMAACTIVITY 2 Dose Equivalent Iodine-131 - 1.060E-04 133.57 kev Peak was used in identifying 2 isotopes 846.89 kev Peak was used in identifying 2 isotopes 1038.70 kev Peak was used in identifying 2 isotopes UNIDENTIFIED PEAKS O ENERGY NET AREA FWHM CTS /SEC ERROR -61.10 612. 0.88 5.097E-01 45.84 172.23 795. 1.84 6.622E-01 34.64 -~

' REPdRT NAME

QA CHECK PAGE : 1 REPORT DATE : 04-4g9-1993 01:41:51.94 VOGTLE ELECTRIC GENERATING PLANT

(-] RADIOCHEMISTRY ANALYSIS SYSTEM V NID QUALITY CONTROL REPORT TITLE : Unit 1 RCS HOT LEG - LOOP 3 - DISSOLVED GAS SAMPLE #

2648-93 SAMPLE GEOMETRY

14 GAS _SO SAMPLE TYPE

DISSOLVED GAS SAMPLE QUANTITY

2.00000E+00

op -Jug 1993 01: 05 : 00.00 COUNT TIME 1993 01:23:16.00 REACTOR UNIT #

1 gu - Ag&. OPERATOR NAME

AROBERSON SAMPLE TIME

( PEAK ENERGY DECAY CORR ISOTOPE ENERGY DIFF (KEV) UCI/CC COMMENTS _AR-41 1293.64 0.09 1.550E-02 Nuclide QA Results OK KR-85M 131.10 v.v1 1.A9As-u4 Nuclide QA Results OK KR-87 402.58 0.26 2.883E-04

• Count Rate Error >30%

XE-135 249.79 -0.17 5.153E-04 Nuclide QA Results OK XE-135M 526.56 -0.13 4.855E-04 Nuclide QA Results OK XE-138 434.49 -0.17 1.856E-03

• Count Rate Error >30%

AVG ENERGY DIFF = -0.02 1.876E TOTAL GAMMA ACTIVITY UNIDENTIFIED PEAKS ENERGY NET AREA FWHM CTS /SEC ERROR 196.40 297. 1.52 2.966E-01 25.41 462.25 77. 1.77 7.727E-02 39.08 511.06 26825. 2.37 2.683E+01 0.70 810.93 39. 1.28 3.911E-02 51.15 889.67 28. 1.39 2.827E-02 50.58 1436.24 23. 2.08 2.283E-02 39.18 Total Unidentifed Peaks = 6 % Unident'ified Peaks = 42.86 REVIEWED BY : L L DATE : ? g i APPROVED BY : 'e d v7 60-DATE : h~ O7 O

O REPORT NAME: QA CllECK REPORT DATE: 4-AUG.-1993 10.20:57 i i VOGTLE ELECTRIC GENERATING PLANT RADIOCllEMISTRY ANALYSIS SYSTEM NID QUALITY REPORT TITLE: UNIT # 1 PASS SAMPLE #. 2649 93 S AMPLE TYPE: LIQUID OPERATOR: MARVIN MUDDLE PEAK LLCAY CORR l ISOTOPE ENERGY UC1/CC Kr-85 m 151.18 2.28E0 Kr-87 402.58 2.42 E+ 1 Kr-88 196 32 1.60E+2 Xc-131 n 164.01 1.31 E+ 1 Xc-133 81.00 2.3 E+ 2 Xc-133m 233 14 8.5 E + 1 ) 1-131 364.48 9.6E + 1 d 1-132 667.69 1.4E+2 I-133 529.87 1.4E+2 1-135 1280.4

2. l E+2 Cs-134 795 85 1.15 E-2 Tc-132 230.0 1.17E-1 Ha-140 537.0 1.90E-1 Pr-144 695.1 1.5 E-1 TOTAL GAMMA ACTIVITY 1.10E+3 uCi/cc REVIEWED BY:

APPROVED BY:

O. A REPORT NAME: QA CHECK REPORT DATE: 4-AUG.-1993 10:30:37 VOGTLE ELECTRIC GENERATING PLANT RADIOCHEMISTRY ANALYSIS SYSTEM NID QUALITY REPORT TITLE: UNIT # 1 PASS SAMPLE #: 2650-93 S AMPLE TYPE: CONTAINMENT ATMOSPHERE OPERATOR: MARVIN MUDDLE PEAK DECAY CORR ISOTOPE ENERGY UCI/CC Kr-85m 151.18 3.09E-4 Kr-87 402.58 8.80E-6 Kr-88 196.32 5 89E-5 Xc-131m 164.01 4.72 E-6 Xc-133 81.00 8.40E-5 Xc-1.3 3 m 233.14 3.09E-5 g 1 131 364.48 3.49E-5 V l-132 667.69 5 16E-5 1-133 529.87 5 01E-5 1-135 1280.4 7.6-E-5 TOTAL GAMMA ACTIVITY 7.08E-4 uCi/cc REVIEWED BY: APPROVED BY: ((

1993 NRC GRADED EXERCISE August 4,1993 O IN-etixT ue SuRvEv DxTi TABLE FHB A-1 TIME 0930 FOX AMBIENT RADIATION LEVELS mR/hr AREA A-1 150 150 A-2 5 5 A-3 2.5 2.5 A-4 As Read As Read 0d

• NOTE:

200 mR/hr VALUE IS AT TIIREE FT WITH LID OFF OF SAMPLE TRANSPORT PIG AS PASS PANEL. CONTACT DOSE ON SIDE OF SAMPLE TRANSPORT PIG IS 20 mR/hr. There is a reading of 2R/hr on contact. AIRBORNE RADIOACTIVITY LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCISE" LOOSE SURFACE CONTAMINATION LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCISE" O GE-93 1 EX4010

m I e t V H.$ k 1 g4 cc n.- u b.yu uh i 3, y- = g g N e v um (. \\B i I e a o E $ _~ 0 f u ed 3 e E. D a t t. O $ @W M z 4 JN Evi U un g n i GE-93 2 EX4010 t

1993 NRC GRADED EXERCISE August 4,1993 O ix-eLANT ursuavEvoiTi TIME 0800 0931 1001 1031 1101 1201 0930 1000 1030 1100 1200 FOX AMBIENT RADIATION LEVEL POINT OF RELEASE mR/hr AREA Al AS READ 150 150 150 1,500 150 A2 AS READ 20 20 20 1000 20 A3 AS READ 5 5 5 700 5 A4 AS READ 150 150 150 750 150 A5 AS READ 20 20 20 750 20 A6 AS READ 150 150 150 2000 150 A7 AS READ 150 150 150 150 150 A8 AS READ AS READ AS READ AS READ 10 AS READ A9 AS READ ASFEAD AS READ AS READ 200 AS READ A10 AS READ AS READ AS READ AS READ 350 AS READ All AS READ AS READ AS READ AS READ 200 AS READ A12 AS, READ AS READ AS READ AS READ 40 AS READ O GE-93 3 EX4010

1993 NRC GRADED EXERCISE August 4,1993 O iN-etAsr ire SURvEv uAri AIRBORNE RADIOACTIVITY LEVELS NOTE LEVELS "AS READ" UNTIL 1100 HOURS Il00-FOX ISOTOPE ACTIVITY pCi/cc Kr-85m 3.09E-3 Kr-87 8.8 E-5 Kr-88 5.89E-4 Xe-131m 4.72E-4 Xe-133 8.4 E-4 Xe-133m 3.lE-4 1-131 4.59E-7 1-132 5.16E-7 I-133 5.01 E-8 1-135 7.6E-6 Co-58 6.2 E-8 Cs-134 3.lE-7 Cs 137 4.7E-8 O GE 93 4 EX4010

1993 NRC GRADED EXERCISE August 4,1993 O is-e'^xT ><e suavev oATA LOOSE SURFACE CONTAMINATION LEVELS NOTE LEVELS "AS READ" UNTIL 1100 HOURS 1100 - FOX AREA Rooms 114,116,125 200 MRAD /hr smearable O A10 5 MRAD /hr smearable A9 & Al1 AS READ A8 & A12 AS READ l O GE-93 5 EX4010

i = ] N 1 N NoATH MSN l 3 x CTE/m v'A \\ VC l .Ec T?oom 1 ir.d l l l iz2 l 7 s 14 n-v a @a x 114 \\ w m. OD J P_ _- \\ O a ~~ e

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1993 NRC GRADED EXERCISE August 4,1993 .O in-eLANT ur SuavEv oxTA LEVEL "A" UNIT 1 0930 TIME 0800 FOX AMBIENT RADIATION LEVELS mR/hr AREA A-1 AS READ 100 A-2 AS READ 5 0 AIRBORNE RADIOACTIVITY LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCISE" LOOSE SURFACE CONTAMINATION LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCISE" O q GE-93 7 EX4010

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1993 NRC GRADED EXERCISE August 4,1993 O IN-PLANT HP SURVEY DATA LEVEL "B" UNIT 1 0930 TIME 0800 FOX AMBIENT RADI ATION LEVELS mR/hr AREA A-1 AS READ 150 A-2 AS READ 10 O AIRBORNE RADIOACTIVITY LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCo3" LOOSE SURFACE CONTAMINATION LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCISE" i G E-93 9 EX4010

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1993 NRC GRADED EXERCISE August 4,1993 O iN-etANT iie SURver DATA LEVEL, "C" UNIT 1 0930 TIME 0800 FOX AMBIENT RADIATION LEVELS mR/hr AREA A-1 ' AS READ 175 A-2 AS READ 10 O AIRBORNE RADIOACTIVITY LEVELS GENERAL AREAS "AS READ FOR Tile DURATION OF THE EXERCISE" LOOSE SURFACE CONTAMINATION LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCISE" O GE-93 11 EX4010

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i 1993 NRC GRADED EXERCISE August 4,1993 O in-r'AxT ue Suavev o^TA LEVEL "D" UNIT 1 0930 TIME 0800 FOX AMBIENT RADIATION LEVELS mR/hr AREA A-1 AS READ 175 A-2 AS READ 10 O AIRBORNE RADIOACTIVITY LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCISE" LOOSE SURFACE CONTAMINATION LEVELS GENERAL AREAS "AS READ FOR THE DURATION OF THE EXERCISE" O GE-93 13 EX4010

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O O O 1993 NRC GRADED EXERCISE August 4,1993 RADIATION MONITORS (STEAM GENERATORS) pCi/cm3 RANGE ALERT ALARM NORMAL 0800 FOX RE-019 ' STM GEN SAMPLE LIQ : 17.2 E 1.4 E-2 : 9.0E-6, -3.0E-5t 9.0E-N ' 1.8E RE-021 STM GEN BLOWDOWN LIQ 7.IE-9 7.IE-3 9.0E-6 1.8E-5 0.0E0 9.5E-7 RE-13120 2 STEM GEN 1 MAIN STM LINER '3.6E 1.1E+3 : 2.0E-1; -3.03-1? 1.0E-1 ; 7.2 E-2 RE-13121 STEM GEN 2 MAIN STM LINE 3.6E-3 1.lE+3 2.0E-1 3.0E-1 1.0E-1 7.4 E-2 RE 13122 t STEM GEN 3 MAIN STM IJNET L3.6E-31 11.2+3 ~2.0E-13 -3.03-l e 1.0E-I r 9.5E-2t RE-13119 STEM GEN 4 MAIN STM LINE 3.6E-3 1.IE+3 2.0E-l 3.03-1 1.0E-1 8.7E-2 RE-12839C CNDSR AIR EJCTRISTM (L)? 1.2E-8 3.5E-3 : 6.3E# 7.9E-4 : 8.0E-8 L 4.5E-7 i RE-12839D CNDSR AIR EJCTR/STM (M) 1.4E-4 4.2E+1 1.0E0 3.0E0 8.0E-8 0.0 RE-12839E L CNDSR AIR EJCTR/STM (H)i-3.2E-1 1.9E+4 F 5.0E+2 5.0E+2 4 8.0E-80 0.0 ? RANGE ALERT ALARM NORMAL 0800 0820 0821 0820 0821 FOX l RE-48000 l CVCS LETDOWN l 2.0E-4 4.0E+1 l 8.0E0

1. lE+1 4.0E0 4.0E0 TOS ITOS l RCS NC-NO CHANGE TOS - TOP OF SCALE RADIATION MONITORS (AREA) mR/hr RANGE ALERT ALARM NORMAL 0800 0820 0822 0930 0820 0822 0930 FOX RE.0013 CONTROUROOMr-

~ 1.2E-2 r - 1.2E+3 ~ 11.0E-l> 2.5E-I E 15.0E-26 5.0E-2n 6NCt J NC.?: " NCI RE-007B SAMPLING ROOM 7.5E-3 7.5E+2 2.0E+ 1 4.0E+1 6.0E0 6.0E0 7.5E+2 1.0E+ 1 NC RE-408

FUEL HANDLING BLDG" 9.7E-3

• 9.7E+2 s 1.0EfU

- 2.5E0 2 8.0E-2r 2.3E-11 ' 2.3E-1 ' LNCd 2NCa NC - NO CHANGE GE-93 1 EX4011

O O O 1993 NRC GRADED EXERCISE August 4,1993 RADIATION MONITORS (CONTAINMENT) RANGE ALERT ALARM NORMAL SOX 0930 1000 1100 1200 Ci/cm3 0930 1000 1100 1200 FOX 3E-2565A CNMT VENT EFFL PART-' 2.1 E-11 ~ 4 2E-6 c 2.4 E-7 : 3.0E-7s 0.0E0 1.9 E-10 :- NC-iNC-NC: NC-RE-256M1 CNMT VENT EFFL IODINE I.7E-11 3.4E-6 1.0E-7 1.3E-7 0.0E0 2.9E-I I NC NC NC NC RE-2565C - CNMT VENT EFFL GAS::' 5.6E-8 1.1E-2 : L9E-4 ' 2.4 E-41 2.0E-7:" 2.E-7: ENC"

NCJ

'NCF rNC: RE-2562A CNMT ATM PART 9.lE-Il 1.8E-5 2.lE-8 2.6E-8 2.0E-9 2.0E-9 NC NC NC NC RE-2562C CNMT ATM CAS-6.2 E-8 s 'L2E-2 : 8.8E4 ' 9.7E-6 < 4.0E-60 7.sE-71 LNC- <NC5

NC:

'NC-mR/hr RE-002 CNMT BLDG LOW RANGE 4 1.0E ' 1.0E+3 : 1.0E+2 9 7.6E+2 " 1.3E+ 1 :: 1.3E+1 ; .TOS -

TOSi TOS*

TOSF RE-003 CMNT BLDG LOW RANGE 1.0E-2 1.0E+3 1.0E+2 7.6E+2 1.3E+1 1.3E+1 TOS TOS TOS TOS RE-004 - CNMT BLDG ACCESS HATCH 1.7E-2 / ' 1.7E+3 -- 1.0E+13 ? l.5E+1 ' 2.0E-1 ':: 2.0E + (TOS) TOS! TOS4 -TOS RE-005 CNMT BLDG HIGH RANGE 1.0E+3 1.6E+ 11 3.0E+3 1.0E+5 5.0E+I 5.0E+ 1 3.1 E+6 3.8E+6 4.5E+6 2.0E+6 RE-006 CNMT BLDG HIGH RANGE 1.0E+3 - 1.8E+11 - 3.0E+3 ? 1.0E45 4:- 5.0E+1i 5.0E+1/ r2.9EMi 3.3E+61 '4.0E+65 2.1E+67 RE-011 CNMT BLDG INCORE INSTR I.0E-1 1.0E+4 5.0E+1 1.0E+2 5.0E0 5.0E+0 TOS TOS TOS TOS TOS - TOP OF SCALE i GE-93 2 EX4011

O O O 1993 NRC GRADED EXERCISE August 4,1993 RADIATION MONITORS (GASEOUS) pCikm3 RANGE ALERT ALARM NORMAL 0800 FOX RE-013 - WASTE GAS PROC SYS - 1.9E-1 ? 3.7E+3 4

2.4 E+2 r 2.4 E+3 6.0E-11 BAD 2 RE-12442A PLANT VENT PART 6.5E-11 1.3 E-5 1.5 E-6 1.9E-6 7.0E-10 4.6E-10 RE-124428 PLANT VENT IODINE i t.7E-11 E

'3.4E4 i 6.7E-71 8.4E-7 : 1.SE-11; RE-12442C PLANT VEN'F GAS

2. lE-7 4.lE-2 2.5E-4 3.lE-4 1.2E-7 5.8E-7 RE-12444C PLANTVENT GAS :

1.5E-7 ^ 9.2E-3 ? 2.5E-4 ::: 3.1E 1.2E-7 c-2.4 E-7 ? RE-12444D PLANT VENT GAS 1.4 E-4 4.2E+1 1.0E0 3.0E0 0.0E0 0.0E0 RE-12444E PLANT VENT CAS t 3.2E i t.9E+4 9: '5.0E+2 L 5.0E+2 T 0.0E0: 0.0E09 ARE-014 - WASTE GAS PROC EFFL ? 3.7E-2 4 3.7E+3 e - 1.1E0 :H 1.4E0 4 < 1.0E-1 2.0E-2; RE-039A WASTE GAS DECAY TK EFFL 2.7E-8 5.4E-3 1.0E-5 1.0E-4 6.0E-8 1.8E-7 RE-039B : . WASTE CAS DECAY TK ::- - 1.8E.81

3.6E-3T

1.0E-5f

1.0E-4)

1.0E-72 2.9E-8 }

CMPSR VENT 4 RE-AUCT FUEL IIAND BLDG EFFL GAS 2.5E-9 2.5E-3 4.0E-7 6.0E-7 4.4E-8 4.8E-8 RE-024A" ' SELECTIVE CUBICLE PART1 i1.3E-11; ~ 1.3 E-5'1 2.0E-8 2 3.0E-8? fl.0E0 o BAD? RE4124B SELECTIVE CUBICLE GAS 5.9E-8 5.9E-2 1.9E-5 2.8E-5 0.0E0 BAD RE-12116 h CR AIR INTAKE GAS s 4.NE-9 ? '4.8E-3 s: 7.2E-7 5 1.0E4

• 6.0EG!:

0.0E01 RE-12117 CR AIR INTAKE GAS 4.8E-9 4.8E-3 8.0E-7 1.2E-6 0.0E0 0.0E0 NC - NO CHANGE TOS - TOP OF SCALE SOX - START OF EXERCISE FOX - FINISil OF EXERCISE GE-93 3 EX4011

1993 NRC GRADED EXERCISE August 4,1993 O WEATIIER FORECAST TO: EOF Dose Assessment Staff TIME: 1015+ FROM: EOF Controllers TLIIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Bush Field Weather Report (forecast) No rain forecasted. Temperatures ranging from middle 80's to middle 90's. I Partly cloudy. Winds from southeast up to 5 miles per hour. ~ l O coxraouen1xvoa"^Tios: e<ev>ae cerece,' emiv >r i xers reseeet <ere<m t'ee. n GE-93 1 EX4009 l

7 O O O 1993 NRC GRADED EXERCISE August 4,1993 METEOROLOGICAL DATA (15 Minute Ave) 0800 0815 0830 0845 0900 0915 0930 0945 1000 l PRI MET TWR 10M Wind Speed - mph 2.5 5.2 6.1 3.4 3.7 5.1 4.2 3.7 4.2 l PRI MET TWR 10M Wind Dir. 90 . 81 85 96 76 91 70 78 90 l PRI MET TWR 10M Ambient Temp - Deg. F 80* 81* 81* 82* 82* 84* 85* 85* 85* l PRI METTWR 10M DEW PT Temp 74* 75 75 74 75* 75* 76" 76* 76* l PRI MET TWR IUM Sigms Theta 22.0 20.6 21.2 19.3 17.5 16.9 19.0 20.1 20.8 l PRI MET TWR 60M Wind Speed - mph 3.0 4.2 5.I 3.6 3.5 4.2 3.3 5.I 3.9 l PRI MET TWR 60M Wind Dir. I10 101 105 116 64 67 79 70 80 l PRI MET TWR 60M Precipitation .4 .4 .4 .4 .4 .4 .4 .4 .4 PRI MET TWR 60-10M Delta Temp - Deg F -1.6 -1.7 -1.6 -1.6 -1.4 -1.4 -I.5 -1.6 -1.6 bi h.hh ~ ~ k SEC MET TWR 10M Wind Speed - mph BAD l SEC MET TWR 10M Wind Dir. - Deg. BAD l SEC METTWR Ambient Temp-Deg F BAD SEC MET TWR 10M Sigma Theta BAD Stability Class B B B B C C B B B ll L GE-93 2 EX4009 t a m..m m2 e -r u. "N

O O 1993 NRC GRADED EXERCISE August 4,1993 METEOROLOGICAL DATA (15 Minute Ave) l 1015 1930 1945 1100 1115 1130 1145 1200 1215 l PRI MET TWR 10M Wind Speed - mph 3.5 3.0 4.1 4.3 3.1 2.9 3.4 3.6 3.3 l PRI MET TWR 10M Wind Dir. 80 85 95 90 100 130 125 135 90 l PRI MET TWR 10M Ambient Temp - Deg. F 86* 86* 86* 86* 87* 87* 87* 88* 88* l PRI METTWR 10M DEW PTTemp 76 76 76* 76* 76* 76* 76* 76* 76* l PRI MET TWR 10M Sigma Theta 16.4 17.0 20.1 21 19.1 19.1 19.0 16.9 17.0 l PRI MET TWR 60M Wind Speed - mph 3.0 2.7 3.I 4.2 4.0 3.5 4.2 4.5 4.0 l PRI MET TWR 60M Wind Dir. 100 105 95 75 110 120 135 130 110 l PRI MET TWR 60M Precipitation .4 .4 .4 .4 .4 .4 .4 .4 .4 PRI MET TWR 60-10M Delta Temp - Deg F -1.4 - 1.5 -1.6 -l.6 -1.6 -1.6 -1.6 -1.4 -1.4 hk kkhI)hIbhNNhjk N Ihh SEC MET TWR 10M Wind Speed - mph BAD l SEC MET TWR 10M Wind Dir. - Deg. BAD l SEC MET TWR Ambient Temp - Deg F BAD l t SEC MET TWR 10M Sigma Theta BAD I $ hkh f [ bk kk: h

NNbb Y

fk ~ j Stability Cisss - C C B B B B B C C l GE-93 3 EX4009

i s g ~s y N. (> l 1993 NRC GRADED EXERCISE August 4,1993 METEOROLOGICAL DATA (15 Minute Ave) 1230 1245 1300 1315 l PRI MET TWR 10M Wind Speed - mph 5.1 4.2 3.9 4.0 l PRI MET TWR 10M Wind Dir. 79 80 92 90 PRI M ET TWR 10M Ambient Temp - Den. F 88 88 89* 89* l PRI MET TWR 10M DEW PT Temp 75 75 76# 76 l PRI MET TWR 10M Sigma Theta 18.3 18.4 18 18 l PRI MET TWR 60M Wind Speed - mph 4.6 5.0 4.9 5.1 l PRI MET TWR 60M Wind Dir. 90 100 101 100 l PRI MET TWR 60M Precipitation .4 .4 .4 .4 l PRI M ET TWR 60-10M Delta Temp - Deg F -1.6 -1.6 -1.6 -1.6 teennemanatiff!!aguairmaster48 21Mastamesflammanener ""*= = ~ = l SEC MET TWR 10M Wind Speed - mph BAD l SEC MET TWR 10M Wind Dir. - Deg. BAD l SEC MET TWR Ambient Temp-Deg F BAD SEC MET TWR 10M Sigma Theta BAD 4 ~ K ;kI(j khh}hh bk kI.k!!h Stability Class B B B B GE-93 4 EX4009

i O O O DOWNWIND PLUME DATA WHOLE BODY DATA ALONG PLUME CENTERLINE General Area Count Rate - cpm l (Whole Body Dose Rate - mrem /hr) DOWNWIND DISTANCE (Miles) 0.6 1 '2 3 4 5 6 7 8 9 10 ETA 1110 1117 1134 1151 1208 1226 1243 1300 1317 1334 1351 cpm 340,000 340,000 23,800 17,000 6,800 13,600 10,200 10,200 6,800 3,400 3,400 i mrem /hr 100 100 7 5 2 4 3 3 2 1 1 ETA 1125 1132 1149 1206 1224 1241 1258 1315 1332 1349 cpm 408,000 374,000 34,000 17,000 10,200 10,200 10,200 13,600 6,800 3,400 mR m/hr 120 110 10 5 3 3 3 4 2 1 ETA 1140 1147 1204 1221 1239 1256 1313 1330 1347 l cpm 340,000 408,000 27,200 20,400 6,800 6,800 10,200 6,800 3,400 mrem /hr 100 120 8 6 2 2 3 2 1 ETA 1155 1204 1221 1238 1255 1312 1329 1346 1403 cpm 374,000 374,000 34,000 17,000 10,200 10,200 6,800 6,800 3,400 I mrem /hr 110 110 10 5 3 3 2 2 1 l ll ETA 1210 1227 1234 1251 1308 1325 1342 1359 1416 cpm 306,000 340,000 30,600 20,400 10,200 6,800 10,200 6,800 3,400 mrem /hr 90 100 9 6 3 2 3 2 1 ETA 1225 1242 1259 1316 1333 1350 1406 cpm 0 0 0 0 0 0 0 mrem /hr 0 0 0 0 0 0 0 NOTES: background reading For " closed window" readings use the above values. Use table values for map areas shaded BLUE. For "open window" readings use 3.00 times the Use 0.10 times table values for map areas shaded YELLOW. table values. Use 0.01 times table values for map areas shaded GREEN. Use 3,400 cpm /imR to determine epm's. ( Use the sample readings for waist and 2-inch readings. l

O O O DOWNWIND PLUME DATA PARTICULATE & SILVER ZEOLITE DATA ALONG PLUME CENTERLINE DOWNWIND DISTANCE (Miles) 0.6 1 2 3 4 5 6 7 8 9 10 ETA 1110 1117 1134 1151 1208 1226 1243 1300 1317 1334 1351 pad. 0 0 0 0 0 0 0 0 0 0 0 AgZ nepm 950 100 , 50 30 10 35 30 20 10 5 5 ETA 1125 1132 1149 1206 1224 1241 1258 1315 1332 1349 pad. 0 0 0 0 0 0 0 0 0 0 AgZ ncpm 1045 980 95 30 20 20 20 35 10 5 ETA 1140 1147 1204 1221 1239 1256 1313 1330 1347 pad. 0 0 0 0 0 0 0 0 0 AgZ ncpm 950 1045 63 40 10 10 20 10 5 ETA 1155 1204 1221 1238 1255 1312 1329 1346 1403 pad 0 0 0 0 0 0 0 0 0 AgZ ncpm 980 980 95 30 29 20 10 10 5 ETA 1210 1227 1234 1251 1308 1325 1342 1359 1416 pad. 0 0 0 0 0 0 0 0 0 AgZ nepm 825 940 84 40 20 10 20 10 5 ETA 1225 1242 1259 1316 1333 1350 1406 part. 0 0 0 0 0 0 0 AgZ ncpm 0 0 0 0 0 0 0 NOTES: Use 0.10 times table values for map areas shaded YELLOW. Use 0.01 times table values for map areas shaded GREEN.

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