ML20106G758
| ML20106G758 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/31/1984 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16162A588 | List: |
| References | |
| PROC-841231-01, NUDOCS 8502150053 | |
| Download: ML20106G758 (175) | |
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DUKE POWER COMPANY OCONEE NUCLEAR STATION i
. EMERGENCY PLAN !
IMPLEMENTING PROCEDURES .. i N#'10KE POWER,hN l _r_ \ APPROVED: 3- D @ %, M. S. Tuckman, Station Manager Volune B l(39 Fevision 84-4 (Major Pavision) Decater, 1984
- Date Approved l Dece ber 1, 1984 Ef f ective Date D ADO O 00 t____-__ _____=_+=: = . . = . _ _ _
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n- - : - - 7 VOLUt2 B TABLE OF CONTENTS
'AP/0/B/1000/07 Procedure for Offsite Dose Calculations by Control Room Personnel or Emergency Coordinator during a Radiological Accident - (7/17/84)
PT/0/B/2000/05 Oconee Nuclear Data Transmission from TSC (09/15/82) CP/1/A/2002/04C Operating Procedure for Post Accident Liquid Sampling (PALS) System (4/24/84) CP/2/A/2002/04C Operating Procedure for Post Accident Liquid Sampling (PAIS) System (10/23/84) CP/3/A/2002/04C Operation Procedure for Post-Accident Liquid Sampling (PALS) System (10/23/84) CP/1&2/A/2002/05 Post Accident Caustic Injection into the Low Pressure Injection System (01-26-81) CP/3/A/2002/05 Post Accident Caustic Injection into the Low Pressure Injections System (01-26-81) CP/0/A/2003/02B Determination of Failed Fuel (08/30/84) CP/0/A/2004/2E Post Accident Deteenination of Boron Concentration Using Carminic Acid (07/09/82) CP/0/A/2004/3C Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter (07/09/82) CP/0/A/2005/2D Post Accident Deteenination of Gamma Isotopic Activity (07/09/82) CP/0/B/4003/01 Procedure for Environmental Surveillance Following a Large Unplanned Release of Gaseous Radioactivity (6/15/84) CP/0/B/4003/02 The Determination of Plume Direction and Sector (s) to be Monitored Following a Large Unplanned Release of Gaseous Activity (01/20/83) HP/0/B/1009/09 Procedure for Determining the Inplant Airborne Radioiodine Concentration During Accident Conditions (07/09/81) HP/0/B/1009/10 Procedure for Quantifying Gaseous Releases Through Steam Relief Valves Under Post-Accident Conditions (05/06/82) Major Revision Revision 84-4 December, 1984 ~~ __[ '
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Paga 2 l
. Table of Contents (Implementing Procedures - Continued)
HP/0/B/1009/11 Projection of Offsite Dose from the Uncon-trolled Release of Radioactive Materials , Through a Unit Vent-(6/5/84) '
- HP/0/B/1009/12 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (04/13/83)
HP/0/a/1009/14 Project Offsite Dose from Releases other than Through a Vent (6/5/84) HP/0/B/1009/15 Procedure for Sampling and Quantifying High Level Gaseous Radiciodine and Particulate Radioactivity (1/25/83) HP/0/B/1009/16 Procedure for Emergency Decontamination of Personnel and Vehicles on-site and from Off-site Remote Assembly Area (9/16/82) I HP/1/A/1009/17 Operating Procedure for Post-Accident Contain-ment Air Sampling System (5/22/84) HP/2/A/1009/17 Operating Procedure for Post-Accident Contain-mest Air Sampling System (5/22/84)
,. HP/3/A/1009/17 Operating Procedure for Post-Accident Contain-ment Air Sampling System (5/22/84)
- Chemistry Manual 5.1 Emergency Responses (4/17/84)
Compliance Manual 6.1 Emergency Response Organization (7/11/84) Health Physics Manual 11.2 Health Physics Emergency Response (8/10/84) Maintenance Directive V.D Emergency Preparedness Plan Activation (10/24/84) Performance Manual 4.5 Emergency Contingency Plan - Performance (4/13/84) i Projects Manual Emergency Response Plan (08/31/84) Station Services Station Services Emergency Plan (10/12/84) OMP 1-7 Operations Emergency Response Organization (11/1/84) 1 Major Revision Revision 84-4 December, 1984
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Form 34731 (10-81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID'No: CP/2/A/2002/04C PROCEDURE PREPARATION Change (s) _ to PROCESS RECORD Incorporated 3 (2) STATION: Oconee (3) PROCEDURE TITLE: nn.,,e<n, pen,.a,v. Snr es on.* ar,4a.ne r < a,,4 a nm=n14ne (PATsi syne m (4) PREPARED BY: b DATE: f!9 TO
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(5) REVIEWED BY: /Am IC. k_v DATE: 22IN - Cross-Disciplinary Review By: M '
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(6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY:r_ h Date: /0f2.3f8 (8) MISCELLANEOUS: Reviewed / Approved By: Date: # Reviewed / Approved By: Date: O h g a 8 s .,,q--ee , o w.ga m- - +. *- a w-
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Y j ' CP/2/A/2002/04C - Page 1 of 13 , x Checked Control Copy Date-DUKE' POWER COMPANY OCONEE NUCLEAR STATION OPERATING PROCEDURE FOR THE POST ACCIDENT LIQUID SAMPLING-(PALS) SYSTEM i
-1.0 Purpose 1
The Post Accident Liquid Sampling System (PALS) provides the capability to promptly obtain a reactor coolant system sample under a nuclear reactor i i accident condition. Sample acquisition during accident conditions will provide information to evaluate the extent of core damage which has occurred or is occurring through knowledge of reactor coolant chemistry and radiochemistry. 2.0 Limits and Precautions i 2.1 The FALS will be used to sample the' reactor coolant system under the following conditions: j 2.1.1 Post Accident. - 2.1.2 Inaccessibility of Primary Sampling' Area due to radiation
- levels. ,
2.1.3 Request from the Station Chemist or his designee ~. 2.2 UNDER ACCIDENT CONDITIONS, VALVE ALIGNMENTS SHALL NOT BE MADE.AND SAMPLES SHALL NOT BE TAKEN WITHOUT PRIOR AUTHORIZATION FROM THE TECHNICAL SUPPORT CENTER (TSC)! (Containment Isolation valves may be - closed upon ES Actuation). 2.3 UNDER ACCIDENT CONDITIONS, DO NOT ATTEMPT ANY PHASE OF SAMPLING OR ANALYIS WITHOUT HEALTH PHYSICS APPROVAL AND COVERAGE! 2.4 Radiation exposure to an individual during all phases of sampling should be limited so as not to exceed a quarterly accumulative exposure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively. All personnel will need prior authorization from TSC to knowingly exceed any exposure limit. The exposure received may require an occupational exposure penalty and/or a medical decision as to whether an individual can continue in radia-tion work. 2.4.1 If necessary to remedy a situation immediately hazardous to life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities. ~ l _a __.___= ._y r w e ,..r, e..e , 4 g,.,..ee.,,,g ..,#,_,,.. -er....r-, .,7, ,,,,- ,,v., . , . - . , , , , , - -
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Page 2 of 13 2.4.2 If necessary to save lives or prevent loss of life and/ or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will, not exceed 25 rems wholebody; 150 rems skin of-wholebody;'. - or 375 rems extremities. 2.4.3. For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin cf
' wholebody; 75 rems extremities; or 15 rems other single organ.
2.5 Portable shielding, remote handling equipment, video equipment, etc., shall be used where practical during sampling, sample preparation, and sample analysis. ' t 2.6 Chemistry personnel shall operate only those valves followed by (C) in this. procedure. If ES signal requires containment isolation during use of this procedure, Operations and Chemistry Personnel 4 should be aware of any pressure remaining in sample lines or sampling panel. , i 2.7 Working copy must be compared to control copy before use and sign off steps (Initials / Time) completed as procedure progresses. 3.0 Procedure s
'3.1 ' Preparation for Sampling 3.1.1 Valve Alignments 3.1.1.1 Notify Shift Supervisor that operation of the i
PALS is being initiated by Chemistry. Chemistry will select either Enclosure 5.5 for a RCS sample or Enclosure 5.6 for a RBNS sample, check it against the control copy, and take it to the-responsible individual in Operations (designated by the Shift Supervisor) for completion. Request Operations to complete Step 3.1 of the selected enclosure. / 3.1.1.2 The following valves are electrically controlled by the PALS Control Panel: RCS Sample: 2RC-179 (C) - Reactor Building Normal Sump Sample: 2 LWD-1026 (C) 2 LWD-1028 (C) Return Line to Reactor Building Emergency Sump (either sample): 2LP-121 (C) Demin. W;ater: 2DW-278 (C) (RCS Sample Line Flush) 2DW-280 (C) (RBNS Sample Line Flush)
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f CP/2/A/2002/04C Page 3 of 13 s 3.1.1.3 The following valves are operated manually at the Sampling Panel by Chemistry personnel. 'They must c be verified open prior to use of the panel. ,
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Initials / Time Instrument Air Supply Isolation. / 2IA-2423 Panel Instrument Air Isolation /
-(Lower right on panel)
Valve on Nitrogen Supply Bottle / (>200 psi tank pressure required;
~45 psi delivery pressure).
Panel Nitrogen Isolation / (Lower right on panel) Cooling Water Supply Isolation 2DW-282 / Demin Water Supply Isolation 2DW-281 / Panel Demin Water Isolation / , (Lower right on panel) 3.1.1.4 The following should be verified as noted (job supervisor may N/A as appropriate). ~
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2 LWD-1029 Low Point Drain (LPI Room) closed and capped 2RC-177 High Point Vent (next to ' Sampling Panel) closed and capped 2LP-110 Emergency Sump Line Drain (LPI Room) Closed - 2LP-111 Emergency Sump Line Drain Tell-tale (LPI Room) closed and capped ' 2DW-278 Remote Starter (HPI Room) "0N" 2 LWD-1028 Remote Starter (LPI Room)
"0N" 2DW-91 Reactor Building Normal Sump Line Flush (HPI Room) Closed 2RC-178 Low Point Drain (LPI Roem) closed and capped e
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-' 2DW-283 Low Point Drain (HPI Room) .
, , closed and capped 2LP-122 High Point Vent (next to Sampling Panel) closed and capped 2DW-324 Isolation Valve between UI & U2 on header (~30 ft. upstream of 2DW-281) Open 2N-262 Nitrogen Isolation: Closed 3.1.2 Health Physics Notification Contact Health Physics and ask for surveillance person prior to going to Control Panel.
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3.1,3 Additional Requirements Pick up glass syringes and sample carrier from Primary Lab, and take stop watch'and panel keys to Control' Panel. 1 / 3.1.4 Power supplies for each electrical component are listed on Enclosure 5.2. 3.2 Panel Preparation L..
- NOTE:
i If any item on panel is not clearly identified, refer to Enclosures 5.3 and 5.~4 (Control Panel Diagrams).
! 3.2.1 Turn the main selector knob on the control panel.to i
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" Reset". Place key in System Power Switch and turn clockwise. (Panel lights should come on.) Press " Reset" button.
3.2.2 Place the toggle switches for the. dilution water meter and ' dilution gas meter to "0N". 3.2.3 Place the toggle switch for the radiation monitor to "0N" and turn the scale select.to " rem /hr". If the radiation monitor is not functional, HP coverage is sufficient to operate the panel. 3.2.4 Place the thermocouple selector on TC-1. 3.2.5 Move the conductivity meter to " Measure" position. , i 3.2.6 Push in the pH meter standardize knob. 1 ' 3.2.7 Select the system to be sampled - Reactor Coolant System or Reactor Building Normal Sump - with the system selector.
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3.2.8 Open sampl& regulator valve at cooler outlet.- / _ . _ _ , ,, - . - - - - -- ~ * ~ ~ - - " " - ' ' " ' ' ' '
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f. CP/2/A/2002/04C Page 5 of 13 m 3.3 Panel Operation (Position 1) Panel Prep 3.3.1 Turn the Operation delector switch to the PANEL PREP. ,. , position. '. 3.3.2 Momentarily depress the SELECTION POWER ACTIVATE-pushbutton.
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{ 3.3.3 Depress the PURGE pushbutton for about 1 minute 10 seconds. 3.3.4 Depress the DRAIN pushbutton for about 1 minute 10 seconds. 3.4 Panel Operation (Position 2) Sample Recire 3.4.1 Request Operations. complete Steps 3.2 and 3.3 of the enclosure selected in 3.1.1.1. 3.4.2 Turn the' Operation Selector switch to the SAMPLE RECIRC. position. 3.4.3 Record the PALS or HP radiation monitor reading (background). Watch radiation monitor reading for a possible increase as sample enters the panel. 3.4.4 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. - 3.4.5 Observe that the SAMPLE INLET and SAMPLE OUTLET indicating lights are lit. Record the starting time. . i 3.4.6 Watch TC-1 closely. If it approaches 190*F, verify I ! cooling water flow, then shut off sample flow by moving selector knob off position 2. If cooling water flow is l_ 2 verified, partially close sample regulator valve and reactivate position 2. Record the temperature when TC-1 has stabilized. 3.4.7 Record pressure reading . Since sample is being returned to atmospheric. conditions, pressure will be zero or at least less than system pressure. l 3.4.8 Turn the selector knob to " Sample", position 3. 3.5 Panel Operation (Position 3) Sample 3.5.1 Turn the thermocouple selector to TC-2. 3.5.2 Momentarily depress the= SELECTION POWER-ACTIVATE pushbutton. 3.5.3 Observe that the SAMPLE INLET and SAMPLE OUTLET indicating lights are lit. e
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CP/2/A/2002/04C Page 6 of 13 3.5.4 ' Monitor the temperature gauge and when TC-2 stabilizes, record the temperature ' 3.5.5 Record the PAIS or HP radiation reading . Sub ' '. tract the initial background reading from sample radiation reading and repord . 3.5.6 Press the 1)- TC-2 Stabilize Activate button; when pressure reading stabilizes, record . 3.5.7 Press the 2) Pressure Stabilize Activate button and record . time sample flow stops . 3.5.8 Request Operations to complete Step 3.4 of the enclosure selected in 3.1.1.1. 3.6 Panel Operation (Position 4) Depressurization 3.6.1 Turn the Operation Selecto.r switch to the DEPRESSURIZATION ., position. 3.6.2 Press the " Reset" button on the gas flow totalizer to zero the readout. Preset the counter on the totalizer to 99999. 3.6.3 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. 3.6.4 ObservethattheDIWATERandSANPLEOUTLETindicating lights are lit. 3.6.5 Verify the pressure gauge on the instrument panel indicates
-15 inches of Mercury. Wait about 60 seconds.
3.6.6 Press the START button on the N2 Preset Counter and observe the PRESS /VAC gauge. When the gauge needle just begins to move press the STOP button on the Na Preset Counter. i (When the start button is pressed, system pressure should go to zero). 3.6.7 Continue to make small Na adds, by repeating 3.6.6 until the PRESS./VAC gauge reads about 0-2 inches. 3.6.8 Flip the Preset Counter POWER toggle switch to the OFF position. 3.6.9 If "5" inches is exceeded, as read from the PRESS./VAC gauge, no gas sample can be taken, because the volume of gas in the diluted gas cylinder is only known at atmospheric pressure. O , 4 e +
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CP/2/A/2002/04C Page 7 of 13 3.7 Panel Operation (Position 5) Liquid Sample 3 . 7".1 Turn the Operation Selector switch to the LIQUID SAMPLE position. , 3.7.2 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. 3.7.3 ObservethattheDIWATERandSAMPbEOUTLETindicating lights are lit. 3.7.4 Depress the LIQUID SAMPLE ACTIVATE 1) Log conductivity and hold until the conductivity meter stabilizes. -Record the specific conductivity . 3.7.5 Press both LIQUID SAMPLE ACTIVATE 1) Log conductivity and 2)-Log pH buttons and hold until pH meter stabilizes. Record pH -- 3.7.6 . Press the GAS SAMPLE 1) ACTIVATE button and hold for 1 second.
- 3.7.7 Momentarily depress the 3) DILUfED GAS SAMPLE. GRAB pushbutton.
3.8 Panel Operation-(Position 6) Liquid Sample Prep 3.8.1 Turn the Operation Selector switch to'the LIQUID SAMPLE i PREP position.
- 3.8.2 Momentarily-depress the SELECTION POWER ACTIVATE pushbutton.
3.8.3 Momentarily depress the ACTIVATE TO DESIRED mL VOLUME pushbutton and observe the SAMPLE ALIQUOT register advance one count (1.40 ml). 3.8.4 Press the " Reset" button on the dilution water flow totalizer and preset the meter for desired dilution (in 250 al increments from 250-3500 mis). Press the " Start" button and let the dilution continue ~ to completion. Record the dilution volume- . 3.8.5 Press the Activate Mix button and hold for about 15 ) seconds. 3.9 Panel Operation (Position 7) Liquid Sample i 3.9.1 Turn the Operation Selector switch to the Liquid Sample position. 3.9.2 Press the SELECTION POWER ACTIVATE button. e i
CP/2/A/2002/04C
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3.9.3 Press Activate button. Wait 45 seconds (for levels in dilution cylinder and grab sampler to equalize). 3.9.4 Momentarily depress the DILUTED SAMPLE ' GRAB pushbutton. '- - s Wait 10 seconds. 3.10 Panel Operation (Position 8) Flush-3.10.1 Turn the Operation Selector switch to the FLUSH position. 3.10.2 Pre'ss the SELECTION POWER ACTIVATE button. 3.10.3 Press the FLUSH ACTIVATE button and wait 4-5 minutes. (Observe that the first FLUSH light and the SAMPLE OUTLET indicating light are both lit.) 3.10.4 Press the FLUSH ACTIVATE button and monitor pH and conduc-tivity meters until they reach equilibrium of demineralized water (approximately 10 minutes). Observe second flush - light is lit. 3.10.5 Press the FLUSH ACTIVATE pushbutton and wait 3 minutes. (Observe the third FLUSH light is lit.) 3.10.6 Press the FLUSH ACTIVATE pushbutton and observe the COMPLETE light is lit. 3.11 Panel Operation (Position 9) Drain 3.11.1 Turn the Operation Selector switch to the DRAIN position. 3.11.2 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. Press ACTIVATE and observe that the first DRAIN light is lit. 3.11.3 Wait for about 2 minutes and again depress the ACTIVATE pushbutton and observe the second DRAIN light is lit. 3.11.4 Wait for about 2 minutes and again depress the ACTIVATE pushbutton and observe the third DRAIN light is lit. 3.11.5 Wait for about 6 minutes and again momentarily depress the ACTIVATE.pushbutton and observe the DRAIN COMPLETE light is lit. 3.12 Panel Shutdown and Decontamination 3.12.1 Turn the Sample Selector switch to the OFF position. 3.12.2 Turn the Operation Selector switch to the RESET position. 3.12.3 Momentarily depress the RESET pushbutton. e
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-s, 3.12.4 Turn.the System Power keylock to the SUMP PUMP position for J
_ about 15 minutes (or until the pump switches itself off).
, '3.12.5 Turn the System Power keylock to the SAMPLE position and record the PALS or HP Radiation Monitor meter reading .
3.12.5.1 If the radiation monitor indicates less than 3 i R/Hr_ over background,' turn the System Power keylock to the OFF position and remove the PAIS System key. 3.12.5.2 If the radiation monitor indicates greater than 3R/Hr over background, repeat 3.10 thru 3.12.5. 3.12.6 If radiation level remains greater than 3 R/hr over
' background after one repeat of Section 3.10 through 3.12.5, contact Station Chemist or his designee (personnel should move to a lower background area during this time, if one .
is available) - for permission to return to Section 3.1 and take another sample using larger dilution volume. Permission given by . 3.12.7 Request HP to survey the Post Accident Sampling Panel'and i the area around the PASP prior to sample removal to ensure the 3 R/Hr over background is not exceeded ' 3.13 Sampling ' 3.13.1 Collect 3-1.0 ml stripped gas samples at the gas grab sampler in lockable glass syringes. Place in plastic bag. 3.13.2 -Collect 3-5.0 ml liquid samples at the liquid grab sampler in lockable glass syringes. Place in plastic bag. I NOTE: Flushing of remaining sample in grab sampler is i ! desirable if radiation levels permit. Return to Position 6 and add 200 mis demin, water to - Dilution Cylinder. Continue through Position 7, cycle through Position 8 and 9 completing the. l second and third drain steps. Go to the grab l sampler and drain the liquid out (this liquid is not a sample-discard in PASP Sump or appropriate waste container in lab). 3.13.3 Request Operations to complete Steps 3.5 and 3.6 of the - enclosure selected in 3.1.1.1. 3.13.4 Place plastic bags in sample carrier and transport to Hot Lab. Place sample carrier in operating fume hood behind a lead brick shield to await analysis. O g e
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- CP/2/A/2002/04C Page 10 of 13 3.14 Sample Analysis 3.,14.1 Gas *
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3.14.1.1 Analyze one syringe of stripped gas by Chemistry . Procedure CP/0/B/2004/14A, Operation of the
' Fisher Model 25V Gas Partitioner for the Determi-nation of Hydrogen in Gas Samples. Calculate the results by the following method:
%H2 X 0 55 Kg
- 1 0 = cc/Kg H 2 Where: % H2 _is determined from CP/0/B/2004/14A 1000 cc = stripped gas bomb volume 0.155 Kg = collected sample size 1 = conversion of percent to -
100 decimal Report result cc/kg H2 3.14.1.2 Withdraw I cc of air from septum stoppered glass vial and load I cc of stripped gas into it from second syrinre. Analyze by GeLi Spectral Analysis (HP/7/B/1001/14, Procedure for Nuclear Data 6600 Sywcem Operation). Activities will be reported by Ji? for 1 cc of diluted gas sample. Calculate acclvity of dissolved gas in 1 al of reactor coola'at as follows: pCi in 1 cc x 1000 = Total activity from dissolved 155 gas in 1 al RC. GeLi Spectra Attached . 3.14.1.3 Reserve third stripped gas syringe for use as a backup, if needed. 3.14.1.4 Additional gas sample dilution may be necessary to bring amount of hydrogen or activity within range of analyses. If so, withdraw 1 cc of air from a septum stoppered glass
- rial and load I cc of-the sample to be diluted into it. Be sure to record the additional dilution information so that isotope activities may be adjusted accordingly.
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s. 3.14.2 Liquid
-3.14.2.1 Take 1 ml of l'iquid sample and dilute to 50 ml.
with Super Q water in a 60 ml poly bottle. ' Analyze by GeLi Spectral Analysis (HP/0/B/1001/14, Procedure for Nuclear Data 6600 System Operation). Activities will be reported by EP for 1 al of diluted liquid sample. Calculate activity of liquid portion of reactor coolant as followsr pci/ml = activity in diluted I al 4
- Total Dilution Volume
- Step 3.8.4 + 1.4 als.
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GeLi Spectra Attached . 3.14.2.2 Take 5 ml of liquid sample and analyze for boron by CP/0/A/2004/02E, Post Accident Determination , of Boron Concentration Using Carminic Acid. Correct results.for dilution as follows: ppm BRCS = ppe measured x
- Total Dilution Volume
- Step 3.8.4 + 1.4 mis-Boron Concentration
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i ppm. 3.14.2.3 Take 5 mls of liquid sample and analyze for chloride by CP/0/A/2004/03C, Post Accident ,
! Determination of Chloride by Specific Ion
, Electrode Using Beckman 4500 Meter. Correct
)
results for dilution as in 3.14.2.2. NOTE: Chloride analysis only to be done in an , accident situation. i Chloride Concentration ppe. 3.14.2.4 Report results of liquid sample analyses in Primary Chemistry Data Log. 3.14.2.5 Reserve third liquid syringe for use as a backup, if needed. L 3.14.2.6 Additional liquid sample dilution may be neces-l sary to bring amount of activity within range. If so, withdraw I ml of sample from 60 ml poly bottle (from Section 3.14.2.1) and dilute to 50 ml with Super Q for analysis. Be sure to record the additional dilution information so that isot, ope activities may be adjusted accord-ingly - ' 4-,,u.m,iwww-,m.,,, - ~a . e w =v- eyw,w gq.,gy,gew m,goa q w e, as s ,+,, - w e ,w w c,,-o-, ge-,-,% ,, , +- ,ge,.-,-e,ew ,eg,--w -~e-,.-,---r*=t-w--N r P W w--r '-
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CP/2/A/2002/04C Page 12 of 13 3.14.2.7 Route completed procedure to Operational Support Center. Accepted By: ' 3.15 Waste Disposal 1 3.15.1 Determine by detailed planning meeting the exact course of action to be taken. Under no condition will liquid or solid wastes be disposed of without prior specific HP directions. , 3.15 .2 Designate a sealable carboy as the " Post Accident Lab i Waste" container. This container must be shielded and used
'as an interim liquid. waste disposal container for all liquid analytical waste.
3.15.3 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protec-
- tive covering to prevent the spread of airborne activity.
4.0 References 4.1 NUREG-0737, Section II.B.3 4.2 DPC System Health' Physics Manual
- 1 4.3 Radiological Health Handbook, U.S. Dept. of HEW (1970).
4.4 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev. 1 (1972). 4.5 Post Accident Liquid Sampling System Manual, Steam Production Depart-ment, OM-267A-28 (1981) 4.6 MNS Operating Procedure OP/0/A/6200/48 1 4 4.7 DPC Alara Manual (1980) 4.8 ONS Emergency Plan 4.9 0FS Chemistry Manual Section 5.1 5.0 Enclosures 5.1 Post Accident Authorization for Operation of PAIS j 5.2 U2 PALS Power Supplies 5.3 PALS Control Panel Diagram - Left 5.4- PALS Control Panel Diagram - Right
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' Page 13 og 13 , 5.5 Operations Checklist for Reactor Coolant System Valve Lineups to Post Accident Liquid Sampling System 5.6 Operations Checklist for Reactor Building Normal Sump Valve Lineups '- -
to Post Accident Liquid Sampling System. 4 i . e e 4 4 I l i G S l i l I 9
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ENCLOSURE 5.1
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CP/2/A/2002/04C ' i-
~POSTACCIDENTAUTkORIZATIONFOROPERATIONOFPALS t : Technician / Time o < l. ' Verbal / written direction for sampling the Reactor
! ' Coolant System (RCS) has been received from the Technical Support Center (TSC). / j . Person Authorizing Sampling
- 2. The specific post-accident analysis requested by TSC: /
Savole to be taken: RCS 0. RBNS O-
/ .
Boron ., ' Chloride - Isotopic Analysis for j Iodines 4 a Cesiums
's Noble Gases
.Non-Volatile Fission Products
- Other (Specify)
- 3 3. Determine by detailed planning meeting the exact course j
of action and data required. / I 4. Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the expo- { sure to personnel while sampling. / i
; 5. Have HP ' determine the required respiratory e ipment
' and protective clothing to prevent or-minimize internal exposure in any Planned Emergency situation. Use high i range and/or extremity dosimetry if required. /
- 6. Request HP to designate a route from PALS to the lab.
/
Sample route designated: 4
- ~ 7. Evaluate the use of portable shielding, remote handling i ._.
equipment, video equipment, etc., to minimize the expo- . sure to personnel in the lab for the required analyses. /' f ^
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CP/2/A/2002/04C PALS Control Panel Diagram-Lefe . ORAIN OFF RESET PANE L PR EP. d @ nai ** Ooo Oc- @ $&$0 com w.3 na w, FLUSH 9 1
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CP/2/A/2002/04C ENCLOSURE 5.5 OPERATIONS CHECKLIST FOR REACTOR COOLANT SYSTEM VALVE LINEUPS TO POS ACCIDENT LIQUID SAMPLING SYSTEM 1.0 Purpose This enclosure gives the valve lineups needed for Chemistry Personnel to sample the Reactor Coolant System (RCS). Locations of valves are given to facilitate li,neups. 2.0 Limits and Precautions
- 2.1 RIA-54 should be in service and monitored during the course of operation of the PALS.
2.2 Demineralized water header must be in service and have at least 60 psi pressure (per Station Directive 3.1.15).
, 3.0 Procedure ~/
Verification Date Date Init./ Time Init./ Time 3.1 Ensure the following breakers are closed: 3.1.1 IL2 Bkr. #37 Sampling / Control Panels Power Supply (located next to U2 sampling panel) 3.1.2 MCCIXL Bkr. for 2DW-278 (RCS sample line flush) and 21WD-1028 (RENS i Sample Line) 3.1.3 Remove white tag from breaker #9
' on 2KVIB (placed per OP/2/A/1102/01 l
i Enclosure 4.1, Section 2.8), and close breaker. NOTE: Both 2RC-162 and 2RC-164 l are powered from this breaker. l 3.1.4 Remove white tag from breaker #4 on 2KVIA (pl* aced per OP/2/A/1102/01 - Enclosure 4.1, Section 2.8) for 2RC-165, and close breaker.
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e-Pags 2 of 5 . ENCLOSURE 5.5 CP/2/A/2002/04C i Verification Date Date. Init./ Time Init./ Time. 3.2 To obtain'a reactor coolant sample, the-valves listed in this section shouldebe aligned as follows: 3.2.1 2RC-84 Inside reactor building
- refer to Fill and Vent Procedure (OP/2/A/1103/02) to verify OPEN status.
1- 3.2.2 2RC-174/2RC-176 (Test Connections) j and 2RC-175 (High Point Vent) ., inside reactor building - refer to Fill and Vent Pro-cedure (OP/2/A/ 1103/02) to verify
- CLOSED Status, s_. 3.2.3' Open 2RC-162 inside reactor building-operated from control room.
3.2.4 Open 2RC-163 inside r'eactor building-operated
. from control room.
NOTE: The following initial conditions must be " observed. 3.2.5 If containment integrity is i required, then Steps 3.2.6 and -. ' 3.2.7 must be completed. 3.2.6 Designate a responsible person in i
' the Control Room to immediately 3
close the isolation valves (2RC-164 l and 2RC-165) if an ES actuation 3 occurs. I 1 3.2.7 Record that containment isolation i . valves 2RC-164 and 2RC-165 are open in OP/0/A/1102/20 (Shift Turnover).
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s~- Page 3 of 5 s ENCLOSURE 5.5 CP/2/A/2002/04C
~
. Verification Date Date Init./ Time Init./ Time 3.2.8 Open 2RC-164 in Unit 2 LPI Room-operated from Control Room.
3.2.9 Open 2RC-165 in Unit 2 LPI Room-
-operated from Control Room.
CAUTION: If ES actuation occurs, immediately close isola-tion valves for containment ., isolation. 3.3 To allow recirculation of sample, align 2LP-65, return line valve to the RB Emergency Sump: - NOTE: The following initial conditions must be observed. 3.3.1 If Containment integrity is ~ required, then Steps 3.3.2 and 3.3.3 must be completed. 3.3.2 Station a responsible person in the vicinity of 2LP-65 to immediately close 2LP-65 if ES Actuation occurs. This person must be in constant communication with the Control Room the entire time 2LP-65 is open. 3.3.3 Record that the valve is open in OP/0/A/1102/20 (Shift Turnover). 3.3.4 Open 2LP-65 manual valve (located in Unit 2 LPI Room) to be operated by reach rod from LPI/HPI Hatch Room 118, 119 (on west wall directly behind 2LP-22). s
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.. s Paga 4 cf 5 . ~ ENCLOSURE 5.5 CP/2/A/2002/04C
- Verification Date Date Init./ Time Init./ Time 3.4 Chemistry will inform Operations when they have obtained the RCS sample in the panel and th-t following valves should then be realigned as follows:
3.4.1 CLOSE 2RC-165 in Unit 2 LPI Room-operated from Control Room. 3.4.2 CLOSE 2RC-164 in Unit 2 LPI Room-operated from Control Room. NOTE: Remove the containment isolation valves (2RC-164 and 2RC-165) from OP/0/A/ 1102/20 (Shift Turnover). 3.4.3 CLOSE 2RC-163 inside Reactor Building-operated from Control Room. 3.4.4 CLOSE 2RC-162 inside Reactor Buildins-operated from Control Room. 3.5 Chemistry will inform Operations when entire sampling sequence has been completed. 3.5.1 CLOSE 2LP-65 Manual valve (located in LPI Room) operated by reach rod from LPI/HPI Hatch Room 118, 119 (on west wall directly behind 2LP-22). NOTE: This will regain contain-ment integrity. Remove the containment isolation valve per OP/0/A/1102/20 (Shift Turnover).
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ENCLOSURE 5.5 CP/2/A/2002/04C Verification Date Date Init./ Time Init./ Time 3.5.2 Ensure the following breakers are ' open: -- 3.5.2.1 khite tag open breaker #9 on 2KVIB. NOTE: Both 2RC-162 and 2RC-164 are powered from this breaker. 3.5.2.2 White tag open breaker #4 on 2KVIA for 2RC-165. 3.6 Return completed enclosure to Chemistry
. personnel operating PALS.
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, CP/2/A/2002/04C ENCLOSURE 5.6 -
OPERATIONS CHECKLIST FOR REACTOR BUILDING NORMAL SUMP VALVE LINEUPS TO POST' ACCIDENT
-SAMPLING SYSTEM 1.0 Purpose This' enclosure gives the valve-lineups needed for Chemistry Personnel to sample the Reactor Building Normal Sump (RBNS). Locations of valves are given to facilitate lineups.
. 2.0 Limits and Precautions 2.1 RIA-54 should be in service and monitored during the course of-operation of the PALS.
1 2.2 Demineralized water header must be in service and have at least 60 psi pressure (per Station Directive 3.1.15). 3.0 Procedure Verification Date Date Init./ Time ' 'Init./ Time 3.1 Ensure the following breakers are closed: 3.1.1 112 Bkr. #37 Sampling / Control Panels Power S'typly (located next to U2 sampFA= pa.tel) 3.1.2 McC2r h . A t RB Normal Sump Samp'e .s.y 4rer Supply. 3.1.3 MCC1XL Bkr. for 2DW-278 (RCS Sample line flush) and 2 LWD-1028 (RENS Sample Line). 3.2 To obtain a reactor building normal sump sample, the following valves should be aligned as indicated: 3.2.1 White tag open breaker on RB Normal Sump Pump 2A. White Tag No. (Located *on MCC2XL). - e maa
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_ . _ _ . - -. - . - . . - - . -- -- - - ~ ~ ~ ~ ~~ ' * . Page 2 of 4 ENCLOSURE 5.6 CP/2/A/2002/04C Verification
- Date Date Init./ Time Init./ Time 3.2.2 White tag open breaker on RB Normal Sump Pump 23. White Tag No.
(Located on MCC-2XN) 3.2.3 CLOSE 2 LWD-30 RB Normal Sump Pump 2A Suction. Operated by reach rod on east wall of valve gallery room in LPI/HPI Hatch Room 118, 119. 3.2.4 _CLOSE 2 LWD-33 RB Normal Sump Pump 2B Suction. Operated by reach rod on east wall of. valve gallery room in LPI/HPI Hatch Room 118,'119, 3.2.5 OPEN 2 LWD-1 Reactor building ' normal sump line. This is an ES valve operated from the Control Room. 3.2.6 OPEN 2 LWD-2 Reactor building nor-mal sump line. This is an ES valve oper-ated from the Control Room. i 3.3 To allow recirculation of sample, align 2LP-65, return line valve to the RB Emergency Sump: NOTE: The following initial conditions must be observed: 3.3.1 If containment Integrity is required, then Steps 3.3.2 and 3.3.3 must be completed . 3.3.2 Station a responsible person in the vicinity of 2LP-65 to immediate-ly close 2LP-65 if ES Actuation occurs. This person must be in constant communication with the Control R'oom the entire time - 2LP-65 is open. e e w t 'e -s -qu..-* wnn ~.e-. ----.ae-e,- - - - ~ - - - " , - - - - ~ - - -
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Pega 3 of 4 ENCLOSURE 5.6 CP/2/A/2002/04C .
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Verification Date Date Init./ Time Init./ Time 3.3.3 Record that the valve is open in OP/0/A/1102/20 (Shift Turnover). 3.3.4 OPEN 2LP-65 Ma'nual valve (lo-cated in Unit 2 LPI Room) to be operated by reach rod from LPI/HP1 - Hatch Room 118, 119 (on west wall directly behind . 2LP-22). 3.4 Chemistry will inform Operations when they have obtained the reactor building normal sump sample in the panel, and the following valves should then be realigned as follows: 3.4.1 CLOSE 2 LWD-2 Reactor building ' normal sump line. This is an ES valve operated , from the Control Room. , 3.4.2 CLOSE 2 LWD-1 Reactor building normal I sump line. This is an ES valve operated from the Control Room. , 3.4.3 OPEN 2 LWD-33 RB Normal Sump Pump (2WD-2B) Suction. Operated by. reach rod on east wall of I valve gallery room in LPI/HPI Hatch Room 118, 119. 3.4.4 OPEN 2 LWD-30 RB Normal Sump Pump , (2WD-2A) Suction. i Operated by reach rod on east wall of , valve. gallery room in LPI/HPI Hatch Room 118, 119. 1
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Page 4 of 4 ENCLOSUPI 5.6 CP/2/A/2002/04C Verification Date Date Init./ Time Init./ Time 3.4.5 Remove white tag from breaker on RB Normal Sump Pump 2B. Wite Tag No. 3.4.6 Remove tag from breaker on RB Normal Sump Pump 2A. Wite Tag No. 3.5 Chemistry will-inform Operations when entire sampling sequence has been completed. + 3.5.1 CLOSE 2LP-65 Manual valve (located in LPI Room) operated by reach rod from LPI/RPI Hatch Room 118, 119 (on west wall directly behind 2LP-22). NOTE:
.j This will regain contain-ment integrity. Remove the containment isolation valve from OP/0/A/1102/20 (Shift Turnover).
3.6 Return completed enclosure to Chemistry Personnel operating PAIS. ama. h r I l
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CONTROL COFL . _ . - , - Form 34731 (10-81) *[ (Formerly SPD 100211 - ('y- @d'jiP\ I k V N ._ r . DUKE POWER COMPANY (1) ID No: CP/3/A/2002/04C PROCEDURE PREPARATION Change (s) - to PROCESS RECORD 2 Incorporated (2) STATION: ocnn..- (3) . PROCEDURE TITLE: oneracine Pvne.ai,v. fnv che pn.* Arrfa.n* r < n,,4 a . Samoline (PALS) Svetem (4) PREPARED BY: h M // DATE: 2[9!M(/. (5) REVIEWED BY: bt , 7 DATE: 2v/f/ - r~ u ' ' Cross-Disciplinary Review By: - _ N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY:t Date: /O 3fkN (8) MISCELLANEOUS: ' Reviewed / Approved By: Date: Reviewed / Approved By: Date: T 0 O e e
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e CP/3/A/2002/04C , Page 1 of 12 4 , 1 DUKE POWER COMPANY d OCONEE NUCLEAR STATION
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OPERATING PROCEDURE FOR THE POST ACCIDENT LIQUID SAMPLING (PALS) SYSTEM
-1.0 Purpose - ~
) The Post Accident Liquid Sampling System (PALS) provides the capability to
- promptly obtain a reactor coolant system sample under a nuclear reactor accident condition. Sample acquisition during accident conditions will provide information to evaluate the extent.of core damage which has ~
occurred or is occurring through kn'owledge of reactor coolant chemistry and radiochemistry. - 4 2.0 Limits and Precautions j . 2.1 T
'he PALS will be used to sample the reactor coolant' system under the-following conditions:
2.1.1 Post Accident. 2.1.2 Inaccessibility of Primary Sampling Area due to radiation ~ ~ i levels. ~ ' _/ 2.1.3 Request from the Station Chemist or his designee. ' 2.2 UNDER ACCIDENT CONDITIONS, VALVE ALIGNMENTS SHALL NOT BE MADE AND SAMPLES SHALL NOT BE TAKEN WITHOUT PRIOR AUTHORIZATION FROM THE TECHNICAL SUPPORT CENTER (TSC)! (Containment Isolation' valves may be closed upon ES Actuation). 't ! 2.3 UNDER ACCIDENT CONDITIONS, DO NOT ATTEMPT ANY PHASF. OF SAMPLING OR
~
ANALYSIS WITHOUT HEALTH PHYSICS APPROVAL AND COVERAGE!
- 2.4 Radiation exposure to an individual during all phases of sampling 4
should be limited so as not to exceed a quarterly accumulative exposure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively. All personnel will need prior authoriz: tion from TSC to knowingly exceed any expo wre limit. The exposure received may require an occupational exposure penalty and/or
' a medical decision as to whether an individual can continue in radia-tion work.
1 2.4.1 If necessary to remedy a situation immediately hazardous'to
' life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.
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Page 2 of 12
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' 2.4.2 'If necessary to save lives or prevent loss of life and/ or
- extensive damage to property (voluntary basis only),'the Planned Emergency Exposure for Duke Power Personnel will -
not exceed 25. rems wholebody; 150 rems skin of wholebody; '. - or 375 rems extremities. ~ 2.4.3 For Outside Services Personnel the Planned- Emergency Exposure will not exceed 5 rems whoLebody; 30 rems skin of
- wholebody; 75 rems extremities; or 15 rems other single
_ . . . _ organ. _ j .
. 2.5 Portable shielding,. remote' handling equipment, video equipment,'etc.,
i shall be used where practical during sampling, sample preparation, J and sample analysis. , 2.6 Chemistry personnel shall operate only those valves followed by (C) in this procedure. If ES signal requires containment isolation during use of this procedure, Operations and Chemistry personnel I should be aware of any pressure remaining in sample lines or - sampling panel. . 2.7 Working copy must be compared to control copy before use and sign-off steps (Initials / Time) completed as procedure progresses. 3.0 Procedure
- 3.1 Preparation for Sampling -
3.1.1 Valve Alignments 3.1.1.1 Notify Shif t Supervisor that operation of the -
- PALS is being initiated by Chemistry., Chemistry.
will select either Enclosure 5.5 for a RCS sample or Enclosure 5.6 for a RBNS sample, check ' it against the Control Copy, and take it to the
. responsible individual in Operations (designated i
by the Shift Supervisor) for completion. ~ Request Operations to complete Step 3.1 of the selected enclosure. .
~
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3.1.1.2 The following valves are~ electrically controlled by the PALS Control Panel:
. . . _ . 2 .: u .u_... J.. '
_ :. s.v. a. RCS Sample: 3RC-179 (C) i
- . Reactor Building Normal Sump Sample
- 3 LWD-1026 (C) 3 LWD-1028 (C)
Return Line to Reactor Building Emergency Sump (either sample): 3LP-121 (C) + i Demin. Water: 3DW-278 (C) (RCS Sample Line Flush) 3DW-280 (C) (RENS Sample'Line Flush) .
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CP/3/A/2002/04C
, Page 3 of 12 4 . ~ 3.1.1.3 The following valves are operated manually at -
the Sampling Panel by-Chemistry personnel. They - must be verified open prior to use of _ the , panel. - - Initials / Time Instrument Air Supply Isolation 3IA-2423 / Panel Instrument Air Isolation (Lower right on pahel) / Valve on Nitrogen Supply Bottle (> 200 psi tank pressure required,
- 45 psi delivery pressure) /
Panel Nitrogen Isolation-(Lower right on panel) '/ '. Cooling Water Supply Isolation
- 3DW-282 '
/
g Demin Water Supply Isolation 3DW-281
/
Panel Demin Water Isolation (Lower right on panel) , __/ 3.1.1.4 The following should be verified as noted prior to periodic testing (Job Supervisor may N/A as appropriate):
- 3DW-283 Low Point Drain (HPI Room) Closed ll and Capped
- i 3 LWD-1029 Low Point Drain (LPI Room)
Closed and Capped 3RC-177 High Point Vent (next to Sampling Panel) Closed and Capped i 3LP-122 High Point Vent (next to Sampling ! Panel) Closed and Capped i
- 3LP-110 Emergency Sump Line B Drain (LPI Room) Closed 3LP-111 Emergency Sump Line B Drain Tell-Tale (LPI Room) Closed and Capped 3DW-91 Reactor Building Flush Line
,(HPI Room) Closed 3DW-278 Remote Starter (HPI Room) ' ON" l
i .
CP/3/A/2002/04C Page 4 of 12
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3 LWD-1028 Remote Starter (LPI-Room)
"0N" 3N-262 Nitrogen Isolation: Closed - -
3.1.2 Health Physics Notification Contact Health Physics and ask for surveillance ; person prior to going to Control Panel.
/
3.1.3 Additional Requirements r Pick up glass syringes and sample carrier from-Primary Lab, and take stop watch and panel keys ! to Control Panel. 3.1.4 Power supplies for each electrical component are listed on Enclosure 5.2. 3.2 Panel Preparation . NOTE: If any item on panel is not clearly identified, refer to Enclosures 5.3 and 5.4 (Control Panel Diagrams). 3.2.1 Turn the main selector knob on the control' panel to
" Reset". Place key in System Power Swit'h c and turn clockwise. (Panel lights should come on.) Press " Reset" button.
3.2.2 Place the toggle switches for the dilution water meter and dilution gas meter to "0N". 3.2.3 ~ Place the toggle switch for the radiation monitor to "0N" and turn the scale select to "mr/hr". If the radiation monitor is not functional, HP coverage is sufficient to operate the panel. 3.2.4 Place the thermocouple selector to TC-1. 3.2.5 Move the conductivity meter to." Measure" position. 3.2.6 Push in the pH meter standardize knob. 3.2.7 Select the system to be sampled - Reactor Coolant System or Reactor Building Normal Sump - with the system selector. 3.2.8 Open sample regulator valve at cooler outlet. / 3.3 Panel Operation (Position 1) Panel Prep 3.3.1 Turn the Operation Selector switch to the PANEL PREP. position. 3.3.2 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. 0
~ '
CP/3/A/2002/04C Page 5 of 12
- 3. 3.3 ' Depress the PURGE pushbutton for about 1 minute 10 seconds.
3.3.4 Depress the DRAIN pushbutton for about I minute 10 second,s.
~. .
3.4 Panel Operation (Position 2) Sample Recire , 3.4.1 Request Operations complete Steps 3.2 and 3.3 of the enclosure selected in 3.1.1.1. 3.4.2 Turn the' Operation Selector switch to the SAMPLE RECIRC. position. 3.4.3 Record the PALS or HP radiation monitor reading (background). Watch radiation monitor reading for-a por.sible increase as sample enters the panel. 2 3.4.4 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. 3.4.5 - Observe that the SAMPLE INLET and SAMPLE OUTLET indicating ];
' lights are lit. Record .the starting time .
3.4.6 Watch TC-1 closely. If it approaches 190*F, verify cooling water flow, then shut off flow by moving selector 4 knob off-position 2. If cooling water flow is verified, 4 partially close sample regulator valve and reactivate position 2. Record the temperature when TC-1 has - stabilized. 3.4.7 Record pressure reading . Since sample is being returned to atmospheric conditions, pressure will be zero or at least less than system pressure. , 3.4.8 Turn the selector knob to " Sample", position 3. 3.5 Panel Operation (Position 3) Sample 3.5.1 Turn the thermocouple selector to TC-2. 3.5.2 Momentarily depress the SELECTION POWER ACTIVATE' pushbutton. 3.5.3 Observe that the SAMPLE INLET and SAMPLE OUTIIT indicating lights are lit.
~
3.5.4 Monitor the temperature gauge and when TC-2 stabilizes, record the temperature . 3.5.5 Record the PAIS radiation reading , t Subtract the initial background reading from sample radia-tion reading and record .
- 3.5.6 Press the 1) TC-2 Stabilize Activate button; when pressure reading stabilizes, record . -
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CP/3/A/2002/04C Page 6 of 12 p
/
3.5. 7 ' Press t. 2) Pressure Stabilize Activate button and record time sample flow stops . 3.5.8 ' Request Operations to complete Step 3.4 of the enclosure '.' - selected in 3.1.1.1. ' 3.6 Panel Operation (Position 4) Depressurization 3.6.1 Turn the Operation Selector switch to the DEPRESSURIZATION position. 3.6.2 Press the " Reset" button on the gas flow totalizer to zero the readout. Preset the counter on the totalizer to 99999. 3.6.3- Momentarily depress the SELECTION POWER ACTIVATE pushbutton. 3.6.4 Observe that the DI WATER and SAMPLE OUTLET indicating lights are lit. , 3.6.5 Verify the pressure gauge on the instrument panel indicates
-25 inches of Mercury. Wait about 60 seconds.
3.6.6 Press the START button on the N2 Preset Counter and observe the PRESS /VAC gauge. When the gauge needle just begins to
' move, press the STOP button on the N2 Preset Counter.
(When the start button is pressed, system pressure should'- go to zero). 3.6.7 Continue to make small Na adds, by repeating 3.6.6 until the PRESS./VAC gauge reads about 0-2 inches. 3.6.8 Flip the Preset Counter POWER toggle switch to the OFF position. 3.6.9 If "5" inches is exceeded, as read from the PRESS./VAC gauge,~no gas sample can be taken, because the volume of gas in the diluted gas cylinder is only known at atmospheric pressure. 3.7 Panel Operation (Position 5) Liquid Sample 3.7.1 Turn the Operation Selector switch to the LIQUID SAMPLE position.
. I 3.7.2 Momentarily depress the SELECTION POWER ACTIVATE pushbutton.
3.7.3 Observe that the DI WATER and SAMPLE OUTLET indicating lights are lit. 3.7.4 Depress the LIQUID SAMPLE ACTIVATE 1) Log conductivity and hold until the conductivity meter stabilizes. Record the specific conductivity . - l l i 1 l l 1 i
'~ ~
- . . - l' - - _ , _ __ - - . l
i __ . - .. . - - . - - - - - - - - - - - - - . - \ CP/3/A/2002/04C l
. Page 7 of 12 3.7.5 Press both LIQUID SAMPLE ACTIVATE 1) Log conductivity and <
- 2) Log pH buttons, and hold until pH meter stabilizes.
Record pH . 3.7.6 Press the GAS SAMPLE 1) ACTIVATE button and hold for 1 secohd. 3.7.7 Momentarily depress the 3) DILUTED GAS SAMPLE GRAB pushbutton. 3.8 Panel Operation (Position 6) Liquid Sample Prep 3.8.1 Turn the Operation Selector switch to the LIQUID SAMPLE PREP position. 3.8.2 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. - 3.8.3 Momentarily depress the ACTIVATE TO DESIRED mL VOLUME
- pushbutton and observe the SAMPLE ALIQUOT register advance one count (.635 ml).
3.8.4 Press the " Reset" button on the dilution water flow totalizer and preset the meter for desit<tf dilution (in 250 ml increments from 250-3500 mls) . Press the " Start" button and let the dilution continue to completion. Record.the dilution volume . 3.8.5 Press the Activate Mix button and hold for about 15
, seconds.
3.9 Panel Operation (Position 7) Liquid Sample . . 3.9.1 Turn the Operation Selector switch to the Liquid Sample position. ' 3.9.2 Press the SELECTION POWER ACTIVATE button. 3.9.3 Press Activate button. Wait 45 seconds (for levels in , dilution cylinder and grab sampler to equalize). 3.9.4 - Momentarily depress the DILUTED SAMPLE GRAB pushbutton. Wait 10 seconds.
, 3.10 Panel Operation (Position 8) Flush 3.10.1 Turn the Operation Selector switch to the FLUSH position.
j 3.10.2 Press the SELECTION POWER ACTIVATE button. i 3.10.3 Press the FLUSH ACTIVATE button and wait 4-5 minutes. (Observe that the first FLUSH light and the SAMPLE OUTLET indicating light are both lit.)
,. , .. . . , ,~--*-,--,,.,--?-&,erve.-*w-,.=.***v:4 w tm ee. ese e,-=. e w r n - e eyr m. 4 - , - . -- - ~e e - - ~ - - -
" ^ ~ '
. = - - .
. 1 H
CP/3/A/2002/04C Page.8 of 12
. f' %. l 1 / -
3.10.4 Press the. FLUSH ACTIVATE button-and monitor pH and conduc-tivity meters until they. reach equilibrium of demineralized water (approximately 10 minutes). Observe second flush '{ light is lit. . '. ' - 3.10.5 Press the FLUSH ACTIVATE pushbutton and wait 3 minutes. (Observe the third FLUSH light is lit.) 3.10.6 Press the' FLUSH ACTIVATE pushbutton and observe the
- COMPLETE light is lit.
i 3.11 Panel Operation (Position 9) Drain i , 3.11.1 Turn the Operation Selector switch to the DRAIN position. 3.11.2. Momentarily depress the SELECTION POWER ACTIVATE pushbutton. Press ACTIVATE and observe that the first
- DRAIN light is lit.
( 3.11.3 Wait for about 2 minutes and again depress the ACTIVATE - pushbutton and observe the second DRAIN light is lit.- 3.11.4 Wait for about 2 minutes and again depress the ACTIVATE ( pushbutton and observe the third DRAIN light is lit. 1. 3.11.5 Wait for about 6 minutes and again momentarily depress the ACTIVATE pushbutton and observe the DRAIN COMPLETE light is lit. 3.12 Panel Shutdown and Decontamination 3.12.1 Turn the Sample Selector switch to the OFF position. 3.12.2 Turn the Operation Selector switch to the RESET position. 3.12.3 Momentarily depress the RESET pushbutton. 2 1 3.12.4 Turn the System Power keylock to the SUMP PUMP position for about 15 minutes (or until the pump switches itself off). 3.12.5 Turn the System Power keylock to the SAMPLE position and ' record the PALS or HP Radiation Monitor meter reading s
!' 3.12.5.1 If the radiation monitor indicates less than 3 3
' R/Hr over background, turn the System Power keylock to the OFF position and remove the PALS System key. ! 3.12.5.2 If the radiation monitor indicates greater than 3R/He over background, repeat 3.10 thru 3.12.5. l k a
- - . - - - ~ ~ - - - - - - - - , ~ , - - - .- ,..,--[-*
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CP/3/A/2002/04C Page 9 of 12 3.12.6 If radiation level remains greater than 3 R/hr over background after one repeat of Section 3.10 through 3.12.5, contact Station Chemi'st or his designee (personnel'should, move to a lower background area during this time, if one " - is available) for permission to return to Section 3.1 and take another sample using larger dilution volume. Permission given by . 3.12.7 Request HP to survey the Post Accident Sampling Panel and the area around the PASP prior to sample removal to ensure the 3 R/Hr over background is not exceeded. 3.13 Sampling
- 3.13.1 Collect 3-1.0 m1 stripped gas samples at the gas grab 1.
sampler in lockable glass syringes. Place in plastic bag.
. 3.13.2 Collect 3-5.0 ml liquid samples at the liquid grab sampler in lockable glass syringes. Place in plastic bag. .
Flushing of remaining sample in grab sampler is desirable if radiation levels permit. Return to Position 6 and add 200 mis demin. water to Dilution Cylinder. Continue through Position 7, cycle through Position 8 and 9 completing the second and third drain steps. Go to the grab sampler and drain the liquid out (this liquid is - not a sample-discard in PASP Sump or appropriate waste container in lab). 3.13.3 Request Operations to c'omplete Steps 3.5 and 3.6 of the enclosure selected in 3.1.1.1. 3.13.4 Place plastic bags in sample carrier and transport to Hot Lab. Place sample carrier in operating fume hood behind a y lead brick shield to await analysis. , 3.14 Sample Analysis 3.14.1 Gas 3.14.1.1 Analyze one syringe of stripped gas by Chemistry Procedure CP/0/B/2004/14A, Operation of the Fisher Model 25V Gas Partitioner for the Determi-nation of Hydrogen in Gas Samples. Calculate the results by the following method:
%H2 X o gg 4
100 CC/ 8 2 e 9
=*~-
e j .
, , . , . .--~ s,m- --~v.-+n---.w,~,," - , , < , - - , , - , -- ~ - - - ,r-. --
,---r ,,----,+n.r
. . - _ - - . ._ . _ _ ~ .
-v+
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, .A-
~
CP/3/A/2002/04C-
- Page 10.of 12 fM Where: %H 2 is determined'from CP/0/B/2004/14A 1000 cc = stripped gas bomb volume ,
, 0.155 Kg = collected sample size 1 = conversion of percent to-100 decimal Report result cc/Kg H2 3.14.1.2 Withdraw 1-cc of - from septum stoppered glass 4
i vial and load 1 et stripped gas into it from second syringe. Analyze by GeLi Spectral Analysis (HP/0/B/1001/14, Procedure for Nuclear Data 6600 System Operation). Activities will be l reported by HP for 1 cc of diluted gas sample. Calculate activity of dissolved gas in 1 ml of reactor coolant as follows: -
- I pCi in 1 cc x 1000 = Total activity from dissolved 155 gas in 1 ml RC.
t Ge Li Spectra Attached- . 3.14.1.3 Reserve third stripped gas syringe for use as a backup, if needed. 4 3.14.1.4 Additional gas sample dilution may be necessary to bring amount of hydrogen or activity within range of analyses. If so, withdraw I cc of air
' from a septum stoppered glass vial and load 1 cc of the sample.to be diluted into it. Be sure to r record the additional dilution information so I ' that isotope activities may 'be adjusted accordingly.
3.14.2 Liquid ' 3.14.2.1 Take 1 al of liquid sample and dilute to 50 21 with Super Q water in a 60 ml poly bottle. Analyze by GeLi Spectral Analysis (HP/0/B/1001/14, Procedure for Nuclear Data 6600 , System Operation). Activities will be reported by MP for 1 ml of diluted liquid sample. Calculate activity of liquid portion of reactor coolant as follows: pei/ml = activity in diluted I ml x
- Total Dilution Volume
- Step 3.8.4 + .635 mis
- GeLi Spe'ctra Attached ..
i t s
--- , n, w---,+, ,w-m--c-, -e-- ., .n~ .- .---- - - . , , = , - - . , . . . , - ,- ,- .--,----r--- . e $N ' , L, ~
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CP/3/A/2002/04C Page 11 of 12
-3.14.2.2 Take 5 ml of liquid sample and analyze for . boro ~n by CP/0/A/2004/02E, Post Accident Determination of Boron Concentration Using Carminic Acid. ,
Correct results for dilution as follows: - - ppm BRCS ppm measured x
'f"3
- Step 3.8.4 + .635 mis Baron Concentration opm.
3.14.2.3 Take 5 mis of liquid sample and analyze for chloride by CP/0/A/2004/03C, Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter. Correct
. results for dilution as in 3.14.2.2.
Chloride concentration opm. . 3.14.2.4 -Report results of liquid sample analyses in-Primary Chemistry Data Log. 3.14.2.5 Reserve third liquid syringe for use as a backup, . if needed. 3.14.2.6 Additional' liquid sample dilution may be neces-sary to bring amount of activity within range. ' If so, withdraw I ml of sample from 60 ml poly bottle (from Section 3.14.2.1) and dilute to 50 ml with Super Q for analysis. Be sure to record the additional dilution information so that isotope activities may be adjusted accord-ingly. 3.14.2.7 Route completed procedure to Operational Support Center. Accepted by: 3.15 Waste Disposal 3.15 .1 Determine by detailed planning meeting the exact course of action to be taken. Under no condition will liquid or solid wastes be disposed of without prior specific HP directions. 3.15.2 Designate a sealable carboy as the " Post Accident Lab Waste" container. This container must be shielded and used as an interim liquid waste disposal container for all liquid analytical waste. 3.15.3 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protec-tive covering to prevent the spread of airborne activity. D
. , + - - _ _ _ . _ - . _ _ . _ . . _
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CP/3/A/2002/04C Page 12 of 1.2 fN i 4.0 -References
~
4.1' NUREG-0737, Sect' ion II.B.3
~
- l. 4.2 DPC System Health Physics Manual 4.3 Radiological Health Handbook, U.S. Dept.. of HEW (1970).
i. 4.4 Radiation Safety Technician Training Course, H.J. Hoe, ANL-7291 Rev. 1 (1972). , . , 4.5 Post Accident Liquid Sampling System Nanual, Steam Production Depart-ment, ON-267A-28 (1981) 4.6 HNS Operating Procedure OP/0/A/6200/48
. 4.7 DPC Alara Manual (1980) -
1 l 4.8 ONS Emergency Plan * 'l 4.9 ONS Chemistry Manual Section 5.1 i j 5.0 Enclosures e 5.1 Post Accident Authorization for Operation of PALS 1 1 s 5.2 U3 PALS Power Supplies
;, 5.3 PALS Control Panel Diagram - Left '
J
),
5.4 PALS Control Panel Diagram - Right , 3
' 5.5 Operations checklist for Reactor Coolant System Valve Lineups to Post Accident Liquid Sampling System i
j 5.6 Operations checklist for Reactor Building Normal Sump Valve Lineups - j to Post Accident Liquid Sampling System , 4 i 5 . t . 4 I -
. _ , . . . , 5 ., m.b. .r_, . , _ . , . - ,mm.,.._,, - . , . - - . ._,,,,,,y-. ._. .,_. ... _, ,_ , _ . , . . . , . _ ,._-.m _. r___,-mr, - . - - -
_. _ _ . _ _ _ _._._..______..__.._______._.u .,
. ENCLOSURE 5.1 CP/3/A/2002/04C ,
~
POST ACCIDENT AUTHORIZATION FOR OPERATION OF PAIS
. Technician / Time
- 1. Verbal / written direction for sampling the Reactor Coolant System (RCS) has been received from the Technical Support Center (TSC). / .
' Person Authorizing Sampling
- 2. The specific post-accident analysis requested by TSC: /
Sample to be taken: RCS O RBNS O / Boron Chloride Isotopic Analysis for Iodines Cesiums s Noble Gases ,- Non-Volatile Fission Products Other (Specify) ' -
- 3. Determine by detailed planning meeting the exact course of action and data required. /
- 4. Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the expo-sure to personnel while sampling. /
- 5. Have HP determine the required respiratory equipment and protective clothing to prevent or minimize internal exposure in any Planned Emergency situation. Use high range and/or extremity dosimetry if required. /
- 6. , Request EP to designate a route from PALS to the lab. /
Sample route designated:
- 7. Evaluate the use of portable shielding, remote handling equipments video equipment, etc., to minimize the expo-sure to personnel in the, lab for the required analyses. /
~ , e
_ _ _ . . _ _ . i.T
- - .P ga 1 cf 1 ENCLOSURE 5.2 ,
CP/3/A/2002/04C
- Unit 3 PALS Power Supplies f
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_ . _ . _ . _ _ _ _ _ . . . . i. .. - Enclosure 5.3 CP/3 /A/2002/04C PALS Control Panel Diaeram-tefe , i CRAIN OFF RESET PANE L PREP. lA te e c. to I) h Adivde OOO he= ' h c41:wi. QQhQ b.. nush w n
' s, FLUSH 9 1
- SAMPLE REClRC.
8)hPidkda Qc, m ,u.rc-1 h f M tV M OOO a 2 7 3 SAMPLE Ped *4 (5 saw t)@LIQUlO 441 SAMPLE Tc15%A17.cs,Adl 4gy f 6 4 '5"'" "MU" 1)@Dilehd S***Ph 5 MI'd* J' LIOUID SAMPLE PREP. DEPRESSURIZATION ICUtoSAMPL (64.5 ddAafh a ms . g a ut y PI) (%.stt 4t Cawdtr SS hW" g) g Act,*,.ic, 6 h*n.2 ASSAMPLE kN st votome se, gend:44. c) h ,C. A d o-2." DNaa01 w b 2)nq Stq" e- -~ * 'o. E Bo.J. use al w.W. n - t. 45+vt. u. htar ED @ h 4 A @ h cAAA.c.4. 2 sr @Dw ase. qsQ Occxase. 3%dtwe n. %b- 10 sac. a 53 @dca Co SYSTEM POV'E R I' @ SE L E CTIC T. POV.E R O O O Svaap QAdIMC F1 2. l Kr.ylor.k l t SEE DRAWING NO. LO401800 FOR PANEL DETAIL l l
. i s
Enclosure 5.4 yw CP/3/A/2002/04C
.. . PALS Control Panel Diagram-Right
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Page 1 of 5
, Checked Control Copy Date
~CP/3/A/2002/04C ENCLOSURE 5.5 OPERATIONS CHECKLIST FOR REACTOR COOLANT SYSTEM VALVE LINEUPS TO POST ACCIDENT LIQUID SAMPLING SYSTEM 1.0 Purpose This enclosure gives the valve lineups needed for Chemistry personnel to sample the Reactor Coolant System (RCS). Location of valves are given to facilitate lineup. a
, 2.0 Limits and Precautions 2.1 3RIA-54 should be in service and monitored during the course of
- operation of the PALS.
2.2 Demineralized water header must.be in service and have at least , 60 psi pressure (per Sta. Dir. 3.1.15). - 3.0 Procedure Verification Date Date Init./ Time Init./ Time 3.1 Ensure the following breakers are closed: 3.1.1 3KTH1 Bkr. #8 Sampling / Control
- Panels Power Supply (located next to U3 sampling panel) /
3.1.2 MCC3XL Bkr. for 3DW-278 (RCS sample line flush) and 3 LWD-1028 (RBNS Sample Line) / 3.1.3 Ensure breakers located on KVIB.C l.
~
(#8) are closed (Power supply to 3RC-162, 3RC-163). / 3.2 To obtain a reactor coolant sample, the valves listed in this section should be aligned as follows: 3.2.1 3RC-84 ,Inside reactor building
- refer to Fill and Vent -
Procedure (OP/3/A/1103/02) to verify OPEN status. /
Page 2 of 5 ENCLOSURE 5.5 CP/3/A/2002/04C
~ .
. . Verification Date Date Init./ Time Init./ Time 3.2.2 3RC-174/3RC-176(Test Connections)
,- and 3RC-175 (High Point Vent) -
, Inside reactor building -- refer to -
1~' Fill and Vent Procedure (OP/3/A/1103/02) to verify CLOSED statua. / 3.2.3 OPEN 3RC-162 Inside reactor building- ' operated from control room. / / l 3.2.4 OPEN 3RC-163 Inside reactor building-operated from control room. / / - NOTE: The following initial conditions must be
, observed.
3.2.5 If containment integrity is required,' then Steps 3.2.6 and 3.2.7 must be completed. 3.2.6 Station a responsible person in the vicinity of 3RC-164 and 3RC-165 to immediately close them if ES actua- ~ tion occurs. This person must be in constant communication with the Con-trol Room the entire time 3RC-164 and } 3RC-165 are open. ' 3.2.7 Record that containment isolation valves 3RC-164 and 3RC-165 are open in OP/0/A/1102/20 (Shift Turnover). i i 3.2.8 OPEN 3RC-164 Manual Valve (located in U3 LPI Room) to be operated by reach rod i from U3 LPI/RPI Hatch
- Room 158, 159 (on west
- wall next to spiral staircase). / /
t
- e i
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. . - . . . - . --- - ~ *- - '--
Page 3 of 5 ' ENCLOSURE 5.5 CP/3/A/2002/04C - {) .
~
. . i Verification Date Date
- Init./ Time Init./ Time.
3.2.9 OPEN 3RC-165. . Manual Valve (located
- i. in U3 LPI Room) to be '
operated by reach rod-from U3 LPI/IPI Hatch
- Room 158, 159 (on west vall next to spiral staircase). , / /
CAUTION: ' If ES actuation occurs, . Lamediately close isolation valves for containment' isolation . 3 j 3.3 To allow recirculation of sample, align 3LP-65, , 1 return line valve to the RB Emergency Sump: t ', NOTE: The following initial conditions ' must be observed. l 3.3.1 If containment integrity is required, j then Steps 3.3.2 and 3.3.3 aust be , completed. l 3.3.2 Station a responsible person in the ! vicinity of 3LP-65 to immediately } close 3LP-65 if ES Actuation occurs. This person must be in constant ,. : [ communication with the Control Roon j the entire time 3LP-65 is open. i 3.3.3 Record that the valve is open in
- l OP/0/A/1102/20 (Shift Turnover).
I l 3.3.4 OPEN 3LP-65 Nanual valve (located l in Unit 3 LPI Room) , to be operated by reach [. rod from LPI/HPI Hatch !' Room 158,159 (on west
, wall directly behind '
3LP-22). / / 3.4 Chemistry will inform Operations when they have obtained the RCS sample in the panel and the following valves should then be realigned as ' follows: , e 0
.n, ~ ,.,.- , w,.- ~ . , . - - + - - -- -r . . - - , . ,w--,, , , , , . - .-----..-.,-------..,-,,,,,.,n,-, n - - , .
r --n. -- ..,
r- .. a. "..< - .-- c: _._ . - - - . , --- _ _ - - - - . . Page 4 of 5. ! ,A:< ENCLOSURE 5.5 i CP/3/A/2002/04C l- N ,, Verification ! Date Date-Init./ Time' Init./ Time 3.4.1 CLOSE 3RC-165 Manual Valve (located in U3 LPI Roon) to be operated by reach rod from LPI/HPI Hatch Room 158, 159 (on west wall next to spiral stair-case). / / 3.4.2 CLOSE 3RC-164 Manual Valve'(located in U3 LPI Room) to be
-operated by reach rod from LPI/HPI Hatch Room 158, 159 (on west wall-next to spiral stair-case). / /
NOTE: Remove the ~
, containment d isolation valves -
(3RC-164 and-3RC-165) from OP/0/A/1102/20 (Shift Turnover). 3.4.3 CLOSE 3RC-163 Inside Reactor Building-operated from Control Room. / / 3.4.4 CLOSE 3RC-162 Inside Reactor Building-
- operated from Control Room. / /
3.5 Chemistry will inform Operations when entire sampling sequence has been completed. 3.5.1 CLOSE 3LP-65 Manual valve (located
- in LPI Room) operated by reach rod from LPI/
HPI Hatch Room 158, 159 * (on west wall directly-behind 3LP-22). / / 3.5.2 This will regain containment intes-rity. Remove the containment isola-tion valve from OP/0/A/1102/20 (Shift Turnove r)*. *
/ .
.m ._ J__ ;
. -~. .. _ . - _.
4 Page 5 of 5 ENCLOSURE 5.5 CP/3/A/2002/04C Verification 4 Date Date 1 Init./ Time Init./ Time j 3.6 Return completed enclosure to Chemistry per-sonnel operating PALS. ~ ~ ~
/
4 4 1 e L t 4 t I e I 4'
./
i 1 i - 6
- 1 i
1 I l I i f 8 i l l o S _ . , . _ ~ _ . ._. _ _ . _ . ._ __._ _.. .._._, _ __, _ ___.__.,- ,.. _. , .,_... .. ..-_ _, _ _ _ _ _.. _ , _ ._.,_- ..- . _. .. _ _ ...._ _._..
. .. - - - . -- -~- -
_ Page 1 of 4 r. Checked Control Copy Date CP/3/A/2002/04C
. ENCLOSURE 5.6 ,
OPERATIONS CHECKLIST FOR REACTOR BUILDING NORMAL SUMP VALVE LINEUPS TO POST ACCIDENT SAMPLING SYSTEM 1.0 Purpose This enclosure gives the valve lineups needed for Chemistry personnel to . sample the Reacto'r Building Normal Sump (RENS). Locations of valves are given to facilitate lineups. 2.0 Limits and Precautions 2.1 3RIA-54 should be in service and monitored during the course of operation of the PALS. i 2.2 Demineralized water header must be in service and have at least 60
, psi pressure (per Sta. Dir. 3.1.15).
3.0 Procedure Verification Date ,. Date Init./ Time Init./ Time 3.1 Ensure the following breakers are closed: 3.1.1 3KTH1 Bkr. 48 Sampling / Control Panels ' Power Supply (located next to U3 Sampling Panel) / 3.1.2 MCC3XL Bkr. #9C RB Normal Sump Sample Pump Power Supply. / 3.1.3 MCC3XL Bkr. for 3DW-278 (RCS Sample
- Line Flush) and 3 LWD-1028 (RBNS Sample Line). /
3.2 To obtain a reactor building normal sump sample, the following valves should be aligned as indicated: 3.2.1 White tag open breaker on RB Normal Sump Pump,3A White Tag No. (Located on MCC3XL). / - I l l io ,,, , .. .+, +--%+==-,*,4 -- -* ~ ~ ~ ~ ~ * * * ' * - * ' " ' " * " ' ^ " " ' ' ' ' *
- e
_ 1_ _._. _ .- - - - - - - - Page 2 of 4 ENCLOSURE 5.6 CP/3/A/2002/04C ,
~. -
i Verification-Date Date Init./ Time Init./ Time 3.2.2 White tag open breaker on RB Normal Sump Pump 3B White Tag No. (Located on MCC-3XN) / 3.2.3 CLOSE 3 LWD-30 RB Normal Sump Pump (3A) Suction. Opera-ted by reach rod on east wall of valve gallery at bottom of spiral staircase. / 3.2.4 CLOSE 3 LWD-33 RB Normal Sump Pump (3B) Suction. Opera-ted.by reach rod on east wall of valve gallery directly at bottom of spiral t staircase. /- 3.2.5 J OPEN 3 LWD-1 Reactor building normal sump line. This is an ES valve 'l operated from the Control Room. / / 3.2.6 OPEN 3 LWD-2 Reactor building normal sump line. This is an ES valve operated from the Control Room. / / 3.3 To allow recirculation of sample, align 3LP-65, return line valve to the RB Emergency Sump: NOTE: The following initial conditions must be ' observed: 3.3.1 If containment Integrity is required, then Steps 3.3.2 and 3.3.3 must be completed. 3.3.2 Station a responsible person in the vicinity of 3LP-65 to immediately close 3LP-65 if ES Actuation occurs. This person must be in constant com-munication with the Control Room the - entire time 3LP-65 is open. i , e l , - - , - .-
Page 3 of 4
N ENCLOSURE 5.6 CP/3/A/2002/04C
' s, ..
Verification Date Date Init./ Time Init./ Time 3.3.3 Record that the valve is open in OP/0/A/1102/20 (Shift Turnover).. ,__
- 3. 3.*4 OPEN 3LP-65 Manual valve (located' in Unit 3 LPI Room) to be operated by reach rod from LPI/
KPI Hatch Room 158, 159 (on west wall directly behind 3LP-22). / / . 3.4 Chemistry will inform Operations when they have obtained the reactor building dormal sump sample in the panel, and the following valves should then be realigned as follows: 3.4.1 CLOSE 3 LWD-2 Reactor building. normal sump line.
, This is an ES valve operated from the Control Room. / /
3.4.2 CLOSE 3 LWD-1 Reactor building , normal sump line. This is an ES valve operated from the Control Room. / / . 3.4.3 OPEN 3 LWD-33 RB Normal Sump Pump (3B) Suction. Operated by reach rod on east wall of valve gallery directly at bottom of spiral staircase. / 3.4.4 OPEN 3 LWD-30 RB Normal Sump Pump (3A) Suction. Operated by reach rod on east wall of valve gallery : directly at bottom of ' spiral staircase. / 3.4.5 Remove white tag from breaker on RB
- Normal Sump Pump 3B. White {
Tag No. ~
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,, Page 4 of 4 ENCLOSURE 5.6 e
CP/3/A/2002/04C , .
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Verification Date Date Init./ Time Init./ Time 3.4.6 Remove white tag from breaker on RB Normal Sump Pump 3A. White-Tag No. / 3.5 Chemistry will inform Operations when entire sampling sequence has been completed. 1-3.5.1 CLOSE 3LP-65 Manual valve (located in LPI Room) operated. by reach rod from LPI/ HPI Hatch Room 158, 159 . (on west wall directly behind 3LP-22). / / NOTE: This will regain containment integrity. Remove the containment isolation valve from OP/0/A/1102/20 (Shift Turnover) .
,j 3.6 Return completed enclosure to Chemistry Personnel operating PALS. /
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,m _ i g 'JII k Oconee Nuclear Station-Maintenance Directive V.D Approval: _ Y, haut, OriginalDake: 4-24-84 Revised Date: fo /; Y/7 DUKE POWER COMPANY OCONEE NUCI. EAR STATION '
EMERGENCY PREPAREDNESS PIAN ACTIVATION 1.0 Purpose The purpose of this directive is to provide instructions on how to activate the Maintenance Response Organization in case of a site emergency. 2.0 Responsibility Responsibilities of Maintenance Group personnel are described in the body of this directive. 3.0 Implementation . i This directive explains the duties of various Maintenance Group personnel whenever the Emergency Plan is activated. 3.1 Normal Working Hours (0800 - 1630) 3.1.1 Superintendent of Maint'enance will:
- a. Be contacted by Station Manager and advised of the emergency situation.
- b. Contact the following personnel:
- 1) Planning and Scheduling Engineer or Maintenance Services Engineer (backup)
- 2) I&E Engineer
- 3) Mechanical Maintenance Engineer
- 4) Transmission Oconee Support Engineer (See Attachment #4)
- c. Report to the Technical Support Center (T.S.C.) with a copy of the " Safety Related Systems, Structures and Components" Manual.
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- d. Determine if the Operational Support Center (0.S.C.) s has been established and reports information to the Station Manager.
i.
- .e. De,termine additional' manpower needs once the situation
- has been evaluated and contacts the appropriate personnel (e.g.,'T.S.C. communicator, etc.) (See Attachment #2). ~
4 3.1.2 Planning and Schedulina Enaineer when contacted will: a) Raport to the Operational Support Center. b) -Receive turnover from the IEE Supervisor on shift. . c) Report 0.S.C. status to the Operations Shift Supervisor 4 and Superintendent of Maintenance.
. d) Maintain control of the 0.S.C. and respond with
- ' craft support to requests of the Operations Shift Supervisor and/or T.S.C. (see Attachment #3).
e) Contact 0.S.C. Communicator and have him/her report to the 0.S.C. (Maintenance Duty Engineer). 3.1.3 I&E Enaineer when contacted will: - - 1 a) Report to the 0.5.C. if requested. - b) Keep the Superintendent of Maintenance up-to-date as to the activities of the I&E Section.
, ,3.1.4 Mechanical Maintenance Enaineer when contacted will:
a) Report to the 0.S.C. if requested. b) Keep the Supt. of Maintenance up-to-date as to the activities of the Mech. Maint. Section. 3.1.5 Transmission Department Oconee Support Entineer when contacted will , a) Report to OSC if requested. ' b) When directed to report to OSC, contact appropriate personnel in substation maintenance and have them ~ report to OSC. (See Attachment #4) c) Keep the Superintendent of Maintenance up-to-date as l to the activities of the Transmission Department. 3.1.6 Maintenance Shift (12 hsur) Personnel
- a. I&E Shift Crew Supervisor - Reports with crew to the .=
OSC (Unit 3 I&E Shop) at Site Assembly Alarm. I&E Shift ~' Supervisor reports accountability to appropriate I&E e** b
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3-Coordinator. I&E Supervisor contacts Operations Shift Supervisor to make him aware when the OSC is established. (I&E, MM, Chemistry, HP) determine from the Operations Shift Supervisor the emergency situation and respond as directed by the Operations Shift Supervisor. Serves as OSC Coordinator until relieved. Sets up communication equipment.
- b. Mechanical Maintenance Shift Crew Supervisor - Reports with crew to the OSC (Unit 3 I&E Shop)'at the Site Assembly Alarm. Mechanical Mainterance Supervisor reports accountability to appropriate MM Coordinator.
Follows instructions for response from the OSC Coordinator.
- c. Materials Shift Personnel - Reports to Supply Issue Window at Site Assembly Alarm. Stands by Phone 1256 for further instructions. Reports accountability to Materials Supervisor.
3.1.7 Maintenance Duty Engineer When Contacted by OSC Coordinator Will:
- a. Report to 0.S.C. as 0.S.C. Communicator
'" b. Check out communication equipment in the 0.S.C. to verify it is installed properly and operational.
- 3.2 Backshift, Hol'iday, Weekends -
3.2.1 Superintendent of Maintenance
- a. Receives information concerning emergency through contact with Station Manager (alternate).
- b. Reports to the Technical Support Center with a copy of the Safety-Related Systems & Components Manual.
- c. Determines if the Operational Support Center has been established and reports information to Station Manager.
- d. Determines additional manpower needs once the eme,r,gency situation has been evaluated. (e.g., Maintenance TSC Communicator).
3.2.2 Maintenance Group Duty Engineer will be contacted by Globe Security to activate the Maintenance Emergency Response Organization. The Duty Engineer will: a) Contact Planning and Scheduling Engineer and advise him to report to the 0.S.C. f . b) Contact the I&E Engineer and advise him to report to the 0.S.C. , c) Contact the Mech. Maint. Engineer and advise him to report to the O.S.C.
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1 d) Contact the him/her T.S.C.to to report Maintenance the T.S.C. ' Communicator and advise ' k e) Contact Transmission Department Oconee Support Engineer and advise him to report to the 0.S.C. f) Report to the 0.S.C. to serve as 0.S.C. Maintenance Communf.:sto r. Attachment il shows the primary and alternates for the above (a through d) positions and their home phone numbers. If alterna us are used for positions described in a thru c, the duty engineer will advise the person contacted which position he will be filling. 3.2.3 The Maintenance Services Engineer', I&E Engineer, Mech. Maint. Engineer, and Transmission Department Oconee Support Engineer's duties are the same as described in Section 3.1 for normal duty hours. 3.2.4 Maintenance Shift Personnel
- a. I&E Shift Crew Supervisor - Reports with crew to the OSC (Unit 3 IE Shop) at Site Assembly Alarm. I&E Shift Supervisor reports accountability to Security Shift -
Lieutenant. I&E Shift Supervisor contacts Operations Shift Supervisor to make him aware when the OSC is established (I&E, MM, Chemistry, HP) . Determine from , , , , the Operations Shift Supervisor the emergency situation and respond as directed by Operations Shift Supervisor. Serve as OSC Coordinator until relieved.
- b. MM Shift Crew Supervisor - Reports with crew to the OSC (Unit 3 I&E Shop) at Site Assembly Alarm. Reports accountability to Security Shift Iieutenant. Follows instructions for response from the OSC Coordinator.
- c. Materials Shift Personnel - Reports to Supply Issue Window at Site Assembly Alarm. Calls Mechanical Maintenance Shift Supervisor at Extension 1113 and reports accountability. (Keep calling until phone
' is answered). Stands by Phone 1256 for further instructions. 4.0 Attachments Attachment #1 MagntgagnegDg Egggoggggft incitx!ed in outside Attachment #2 Technical Support Center Checklist Attachment #3 OSC Coordinator Checklist Attachment #4 Tra:uimission Depart:nent and Substaticn Division Contact LiF* (Not incitx!ed in cutside distribtuicn-Confidential Infon E Attachlent #5a TSC Diagram (Not distributed-Confidential Infor::ation) - Attachment #5b OSC Diagram (Not distributed-cenfidential Informaticn) I i.
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Maintenance Directive V.D
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( . ATTACHMENT 2 TECHNICAL SUPPORT CENTER i ECKLIST
- 1. Superintendent of Maintenance in TSC with phone operable
- 2. Maintenance TSC Communicator available (See Attachment #1)
- 3. OSC Coordinator in place in the OSC with maintenance crews available
- 4. Manpower needs being evaluated (i.e., Number of Maintenance people on site Site Assembly still taking place or have they been returned to work?
If still at Site Assembly, what are the activity levels at the Assembly areas? ,, Evacuation process (which crews are releasea first with information when they are to return, etc.)?
- 5. Determine alternate methods of communication should probsens occur with telephones.
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% I Maintenance Directive V.D
-s ATTACHMENT 3 '
OSC COORDINATOR CHECKLIST Planning and Scheduling Engineer shall d t
- 1. e ermine:
Phones are operable in the OSC
- 2. .
Intra station system operable - 3. Chem'istry, HP, Safety) Emergency Response radios av groups (I&E, MM, 4 Supervisors in place 1.r each sectionpresented re 5.
'6. OSC Communicator is available ce Duty(Maintenan Engineer)
Establish Liaison with Operations 7. Appropriate information update process
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. STATION SERVICES PROCEDURE # t ORIGINAL DATE 10/07/83 ' APPROVAI, v Nbd-N t . REVISED DATE jn /ia /6
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DuEE e0w.R COMnNT lisFORNAT,0N ONLY OCONEE NUCI. EAR STATION STATION SERVICES EMERGENCY PLAN-4 } 1.0 Purpose To describe responsibilities of the Station Services Group during a Station Emergency to include: - Accountability of all site people and the Establishment of the TSC 2.0 Procedure i 2.1 Administrative Duty Personnel Emergency Response Notifications- . When notified of Emergency Condition: 2.1.1 Notify Superintendent of Station Services A) John McIntosh or i 4 B) Don Austin 2.1.2 Notify one person to make remaining calls: A) Mike Roach or i B) Buea DeNard or C) Penny Goebel or D) Joan Sanders , -2.1.3 Remaining Calls: ! A) Station 4rvices (TSC) Communication: (Option of Superintendent or Designee) a) Bill Stengel or b) Stan Scott I . . l
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a 2-i B) Training and Safety Coordinator: a) Jerry Itin or
, b) Dixie Kelly ,
C) Station Services Clerical Support a) Teresa Stewart b) Draama Bridges D) Administrative Coordinator: a) Mike Roach or b) Buea DeNard E) Contract Services Coordinatcr: . a) Tom McQuarrie b) Scott Bryant F) Switchboard Relief if necessary - Duty Person or Superintendent would identify..whether this is ' s necessary at this point. , a) Penny Goebel or b) Joan Sanders , 2.2 Accountability of all Station Services site personnel shall be made within 20 minutes to Dreana Bridges, Adm. Coordinator Clerk,- Ext. 1796. This total will then be called in to the Station Services Superintendent, in the TSC. Station Services Superintendent will report total Station Services personnel accounted for to Security Shift Lieutenant. 2.3 Establishment of TSC. 2.3.1 Upon arrival to site, check with switchboard operator to determine if a representative has been notified from each group identified as the emergency response organization (reference Enclosure 1). If a group cannot be notified, assist the switchboard operator with alternative contacts and verify the Shift Supervisor is aware'of response group (s) not notified. -
- 4. 4_- - - --
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t ,- u.. 2.3.2 Prior to entering protected area: Pick up Emergency Response Notebook, and Administrative
. Policy Manual from John McIntosh's office (in blue cabinet)
, and take to TSC.
Verify.that Security has dispatched officer (s) to TSC and .
=-
OSC to control access, and all phones have been switched. If this has not been accomplished, request Security support. 2.3.3 . Upon entering protected area:
- Locate roll-around cart in I&E office on Turbine floor (or elsewhere) and take to TSC cabinet in Control Room to 2
provide storage and distribution capability. 2.3.4 Upon arrival ~at TSC, unlock TSC-storage cabinet at back of I & 2 Control Room. (Key located in Emergency Plan Manual.) Remove copier and telecopier and set up in Computer Room l (Unit'l & 2) or verify they are already in use. Verify that portable radio with ear set-has been delivered to TSC by Safety Dept. for monitoring purposes. Remove materials and supplies .from storage cabinet and place on roll-around cart for.use in TSC. Set up TSC logbook and record names of' people in TSC (may request Security assistance). Ensure people properly use sign in and sign out log. j Place Pickens and Oconee Emergency Plan on roll around cart
- or verify they are in use elsewhere.
Place General Arrangement Drawings and Site Drawing on-table (for list of drawing.and table locations, see PT/0/B/ l. 2000/04). I Place Fire Plan on roll aronoj cart or verify it is in use elsewhere. .. 4
- Place paper, pads, pencils, Jens, and notebooks on roll-
, around cart or verify their availability elsewhere. Place Crisis Telephone Directory on roll-around cart _or verify its use elsewhere. l I l _,-.- . :r_ . : . . - ~ ~-- - ' ; - ~. .- - ~~ ~~ ~
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t Place Data Displays (stored in TSC cabinet) for information updates in TSC and OSC or verify their set-up (and verify they will be updated by Integrated Scheduling,'in the TSC only). ' 2.3.5 Verify existence of the following or remind others of the requirement. Verify the radio has been set up by the Environmental Section. Verify the TSC cart is available (located in SS office) and normally put into use by Coleman Jennings, Offsite Communicator) with the following materials: Emergency Plan and Implementing Procedure Crisis Management Plrn Message Forms Authentication Procedures
-Verify availability of Technical Specification (normally in SS Office).
Verify availability of FSAR (normally in SS Office). , Verify availability of Station Directives (normally in i Control Room or SS Office). Verify availability of Plant Operations Drawings (in Control' Room). Verify availability of Safety related structures, systems and components, description (provided by Joe Davis). i Verify availability of various I&E Drawings-(located in Shop). Verify availability of Emergency Procedures -(provided by Norman Pope) Verify the VAX system is on line and operable. ! Model A System (HP) __m s _p- s- *v*
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___.I. __ _. _ _ _ . . . _ _ - _ _ _ . - - . 1 ~ ' lT l' i I ~ -- Verify the OSC is established and operational.
' Personnel in place.
i Supplies /first aid kits available. Survey instruments available. Dosimetry available. Intercom Systems operable. Radios operable and available. f r a I
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Page 1 of 2 s~~ [ Reviewedby/kL.$w*;'il Approved by 3 % he de. Date 11/1/h&#
. Revision # Original OCONEE NUCIIAR, STATION OPERATIONS MANAGEMENT PROCEDURE 1-7
?.lF0iiM Ail 0 N O EMERGENCY RESPONSE ORGANIZATION 1.0 Purpose The purpose of this OMP is to:
- 1) Identify the Emergency Response participants and their responsibilities.
2.0 References NUREG 0654 Emergency Plan 3.0 Responsibilities 3.1 The Superintendent of Operations shall: A) Participate as a member of the' Technical Support Center B) Oversee Operations activities' C) Monitor the emergency situation D) Make recommendations for stabilization and recovery of the emergency situation E) Relieve the Shift Supervisor as Emergency Coordinator in the i event the Station Manager is unavailable. 3.2 The Duty Engineer shall: A) Participate as a member of the Operational Support Center B) Act as Superintendent of Operations should he be unavailable C) Relieve the Shif t Supervisor as Emergency Coordinator in the event that none of the following can be contacted: Station Manager, Superintendent of Operations, Superintendent of Technical Services or Superintendent of Maintenance.
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OMP 1-7 ' Page 2 of 2
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.( 3.3 The-Shif t Supervisor shall:
A) Serve as Emergency Coordinator until relieved by the Station Manager or his designee. B)- Oversee Control-Room activities on the affected unit. C) Respond to the emergency situation in accordance with Emergency . Procedures, the Emergency Plan and Emergency Plan Implementing Procedures. O O J I s 9 0 9 1 e w
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DUKE POWER COMPANY ~
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OCONEE NUCLEAR STATION
, .. EMERGENCY PLAN
, IMPLEMENTING PROCEDURES 7
1 i l DUKE POWER , Y . / APPROVED: LLC iM.M M. S. Tuck:: tan, Station Manager Date pp oved or sien) l Deceber 1, 1984 Ef f ective Date s 7,._- , - . _ . , . - . , . - . - ~'~,.?"
, . . _ '~'~~l' ___ 'T_'_,.
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VOLUME C TABLE OF CONTENTS Emergency Telephone Numbers - (Rev. 84-4, 9/30/84) RP/0/B/1000/01 Emergency Classification - (11/29/84)
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RP/0/B/1000/02 Notification of Unusual Event - (11/29/84) RP/0/B/1000/03 Alert - (11/29/84) RP/0/B/1000/04 Site Area Emergency - (11/29/84) RP/0/B/1000/05. General Emergency - (11/29/84)
, RP/0/B/1000/06 Protective Action Recommedations - (11/29/84)
RP/0/B/1000/09 Procedure for Site Assembly (11/29/84) RP/0/B/1000/10 Procedure for Emergency Evacuation of Station Personnel - (6/1/84) RP/0/B/1000/11 Dose Extention (11/29/84)
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f f e i i i h v-Major Revision Revision 84-4 December, 1984 r- -. -
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i k DfERGENCY TEIIPHONE NLHBERS
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This enclosure provides a listing of telephone numbers for various personnel . and agencies that may have a part in dealing with an emergency situation or providing other assistance as needed at Oconee Nuclear Station.
+.
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Rev. 84-4 9/30/84
., _ - - . _ . . .... .- ,, _ ~ -
=
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I EMERGENCY TELEPHONE NUMBERS This directory provides a listing of telephone numbers for various personnel' and agencies that may have a part in dealing with an emergency situation or providing other , assistance as needed at Oconee Nuclear Station. TABLE OF CONTENTS NOTIFICATION OF AGENCIES, CRISIS MANAGEMENT TEAM. . . . . . . . . . . . 1- 5 EMERGENCY FACILITY LOCATIONS. . . . . . . . . . . . ; . . . . . . . . . 6 OCONEE TELEPHONE ACCESS CODES . . . . . . . . . . . . . . . . . . . . . 7 TECHNICAL SUPPORT CENTER. . . . . . . . . . . . . . . . . . . . . . . . 8 OPERATIONAL SUPPORT CENTER. . . . . . . . . . . . . . . . . . . . . . . 9 OFFSITE DOSE ASSESSMENT . . . . . . . . . . . . . . . . . . . . . . . . 8 EMERGENCY COUNT-ROOM. . . . . . . . . . . . . . . . . . . . . . . . . . 8 CRISIS MANAGEMENT CENTER . . . . . . . . . . . . . . . . . . . . . . . 11 - 13 GENERAL OFFICE SUPPORT CENTER , . . . . . . . . . . . . . . . . . . . . 12 BACKUP CRISIS MANAGEMENT CENTER - (Liberty) . . . . . . . . . . . . . . 13 CRISIS NEWS CENTER. . . . . . . . . . . . . . . . . . . . . . . . . . . 14 NUCLEAR REGULATORY COMMISSION . . . . . . . . . . . . . . . . . . . . 5 DUEE EMERGENCY RADIO , . . . . . . . . . . . . . . . . . . . . . . . . 16 EMERGENCY NUMBERS - Pickens County . . . . . . . . . . . . . . . . . . 17 EMERGENCY NUMBERS - Oconee County . . . . . . . . . . . . . . . . . . . 18 Rev. 84-4 9/30/84 s y ye s w-==,E --e- % ---t g e a,y y g as y . -, - t.= 9 . #- ,e+ r =
3 i DUKE POWER COMPANY OCONEE NUCLEAR STATION NL*J1ER CODE FOR IDENTIFYING PERSONNEL / ACTIVITIES TO BE NOTIFIED CODE
- 1. NUCLEAR REGULATCRY COMMISSION by Red Phone within one hour.
- 2. UNIT COORDINATOR /0PERATIONS DUlT ENGINEER who will notify: ,
A. Superintendent of Operations. J. N. Pope, Offir:e ................. Home ............. . . . . B. Station Manager / Emergency Coordinator (or alternate as listed in number 8) M. S. Tuckman, Office . ............... Home . .............;.. { C. Nuclear Production Duty Engineer who will notify:
- 1. Corporate Communications
- 2. Crisis Management Organization
- 3. SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL (Warning Point State of South Carolina)
Bureau of Radiological Health (0800 ,1700). .. ..... . . Answering Service after hours, weekends, holidays. .. . . .
- State Emergency Operations Center, Columbia, S.C. . .
- Forward Emergency Operations Center, Clemson, S. C. .
Alternate Number . . . .
- NOTE: These numbers are to be used once the State
~
has established their Emergency Operations. Rev. 84-4 9/30/84
E. ? , p -- - p . I e E N ? 4. COUNTY N G CY PREPAREDNESS AGENCIES Oconee County Emergency Preparedness . .... ... : Alternach Number - 24 hour, Page. , , Alternata Number - 24 hour, Pager I Pickens County Emergency Preparedness. .... ...... Alternate Number - (0830-1700) [ Alternate Number - 24 hour, Page E L a
- 5. COUNTY SHERIFF'S DEPARTMENTS .
3llf. r 3.-- L 1 "A Oconee County (24 hours) . . . . . . . . . . . . . . . . . { Alternate Number . . ....
~~"7 *
.- l
[ Pickens County (24 hours) . . . . . . . . . . . . . . . . . Alternate Number . ..... . Alternate Number . . . E ... - e . - Alternate Number . ..... . ' 6. MEDICAT. ASSISTANCE s Oconee Memorial Hospital Ambulance Service . . . r . r E Oconee Memorial Hospital Switchboard / Supervisor or Nursing,.
- .s h Additional Medical assistance may be provided through the '
- following institutions:
,. . s Pickens County Ambulance Service . .............
- g e Cannon Memorial Hospital / Supervisor 'of Nursing . . . . . . . ~ ' p e Easley Baptist Hospital / Supervisor of Nursing . . . . . . . . U u
- 7. FIRE ASSISTANCE '
! Oconee County Rural Fire Protection Association . ...... .. Woods or Forest Fire (Oconee County, Oakvay Tower) . . . . . . .. { Woods or Forest Fire (Pickens' County, Woodall Mt. Tower) . . . - I s b l ' E p. b - b Rev. 84-4 9/30/84 B ll~f [a n :- p -- - . - - - - .
1 i l l 3-N .
- 8. EMERGENCY COORDINATOR AND ALTERNATES (TSC Activation)
(If the first person cannot be reached, go to the next person down the list until one person is contacted) Station Manager _ M. S. Tuckman, Office . . . . ............ l Home . . . . . ....'........ Superintendent of Technical Services T. S. Barr, Office . . . . . ............ Home . . . . . . ............ j Superintendent of Maintenance J. M. Davis, Office . . . . . ...."........
; Home . . . . . . ............
1 Superintendent of Operations j J. N. Pope, Office . . . . . ............ Home . . . . . . ............ l l Operations Duty Engineer . . . . . ............ 1 I i l il i l Rev. 84-4 9/30/84 D 4 v,---,w--,-- ---na-,w
l I x,
, s
- 9. WATER DEPARTMENTS l
Should releases of radioactive effluent into Lake Keowee or Lake Hartwell potentially effect municipal water intakes or exceed technical specifi-
; cations. Contact the appropriate authorities as indicated below:
Lake Keovee l Seneca, H. J. Balding, Office . . . . . .. . . . . . } Home . . . .... . . . . . . i Lake Hartwell l, City of Clemson Mayor of Clemson, Office . . . . ....... . .. i Home . . . . . .. ..... . . . (If the mayor cannot be reached, call one of the following
- Clemson Administrator's Office . .. .... . . . .
l Home . . .. . . . . . . .. , Clemson Filter Plant (0700-1700) .. . . . . . . . . i j Clemson University . l President's Office . . . . . . . . . . . . . . . . . Home .. . . . . . . .. . . . . . . . . Security - Police (24 hours) . . . .. . . . . . . . (If the President cannot be reached, call) i Clemson University Physical Plant (0800-1630) . . . . j Anderson Water Vorks (24 Hr. Number) . .. ..... . . . l AGENCIES THAT MAY RESPOND TO AN EMERGENCY AT THE OCONEE NUCT. EAR STATION l l { 10. LAW ENFORCEMENT (24-hour numbers) S. C. Highway Patrol (Greenville, S.C.) . . . . . . . . . S. C. Enforcement Division (Columbia, S.C.) . . . . . . . FBI (Columbia, S.C.) . . . . . . . . . . . . . . . . . . t - l l i i Rev. 84-4 9/30/84 l l J"""** q . ., s - i l l_ _ _ , . .
, , , ,, , ,i,__._- - - - - - - .' ' '
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- 11. BCMB DISPOSAL.
Explosives Ordinance Disposal Detachment Control (24-hour) (Fort Jackson, Columbia, $.C.)
- 12. RADIATION AND CONTAMINATION (Depart =ent of Energy)
S' ACTS, Department of Energy (Oak Ridge, Tennessee) (24 hr. number - after 1700 ask for Beeper number) . DOE Emergency Radiological Monitoring Team (Aiken, S.C.)
- 13. INGESTI'ON PATHVAT Warning Point - State of North Carolina .
.(24 hour).
(N.C. Highway Patrol) (Primary Contact) N.C. Division of Emergency Management (0800-1700) (Alternate Contact) Warning Point - State of Georgia .(24 hour). (Georgia Emergency Preparedness Agency) (Primary Contact) Geo g g a tg ent of Natural Resources . . (24 hour) 14 NUCLEAR REGULATORY COMMISSION NRC Operations Center (via Bethesda Central Office) NRC Operations Center (via Silver Spring Central Office) US NRC, Region II US NRC, Region II (Operations Center) . .- US NRC, Oconee Resident Inspectors Jack Bryant (Home) Kent Sasser (Heme) Larry King (Home)
- 15. BUS TRANSPORTATION Anderson Retail Office (24 hour number)
(Contact John Holland, Jerry Whitfield)
- 16. NATIONAL VEATHER SERVICE - METEOROLOGICAL BACK-UP SOURCE Greenville-Spartanburg Weather Service (24 hour)
Rev. 84-4 9/30/84
i 6-i N i
- 17. FEDERAL AERONAUTICS AGENCY PRIVATE AIRCRAFT Flight Standards District Office . . . .(0800-1700). . . .
Flight Service Station (After hours, weekends, holidays) . j MILITARY AIRCRAFT
! Air Station Mgr. (Shaw AF Base) . ............
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{ 1 7m k i I OCONEE NUCLEAR STATION CRISIS COMMUNICATIONS DIRECTORY The crisis directoryTis intended for use should the Oconee Emergency Plan require implementation. Both station and corporate level telephone numbers are provided. The station's emergency organization will operate from the Technical Support Center near the Units 1 and 2 Control Room. . The corporate emergency organization will operate from the Crisis Management Center located in the Visitors Center and Oconee Training Center.
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EMERGENCY FACILITY LOCATIONS Technical Support Center - Control Rooms 1 and 2 Operational Support Center - Centrol Room 3 Crisis Management Center - Oconee Training Center Alternate Location: Liberty Retail Office Crisis News Center - Keowee-Toxaway Visitors Center Alternate Location: Liberty Retail Office Rev. 84-4 9/30/84 l
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. ; l OCONEE NUCLEAR STATION' .
TELEPHONE DIRECTORY Seneca Lines l i (803) I i Easley Lines (803) i Anderson Line (803) Six Mile Line
- (803)
Dial Code Charlotte General Office)
- (Micro-Wave) l (Catawba) l 1
(McGuire) i trendant (To access Bell Line) Seneca l Easley 1 Anderson Six Mile d Rev. 84-4 9/30/84 i v m -- -.---. . , . - - r.n,J---, e-- - - - - - - - , - - - - - - + - , - - - - - - - - - - - , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
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OCONEE NUCLEAR STATION
- CRISIS PHONE DIRECTORY TECHNICAL SUPPORT CE. VIER t Telephone Number i
m, l Outside Station POSITION /NAME Line Number EMERGENCY C00RDINATION 1 Emergency Coordinator . . . . . . . . . . . . . . . Offsite Communicator . . . . . . . . . . . . .
- Superintendent of Operations ... . .......
Superintendent of Technical Services ....... i l Data Transmissions Coordinator . ....... Data Release (Unit 1 & 2). . . . ....... i i (Unit 3). . ... ........ - j Chemistry . .. ... . .... ....... 4 i Compliance . .. ... . .. ... ,,. . . . . i Station Health Physicist ...... ..... 1 1 Superintendent of Integrated Scheduling . ..... Superintendent of Station Services ........ 1 ] Clerical Support . .. . ... . ....... i l NRC Resident Inspector . . . ... . ....... , O_FT. SITE DOSE ASSESSMENT t l Dose Assessment Coordinator ......... l Data Line (HP) Model A . ........... 1 - l Field Monitoring Coordinator . . ....... i Emergency Count Room . . .. .. ...... 1 l l s MAJOR REVISION Rev. 84-4 9/30/S4
in Telephone Number Outside Station Line Numbe r CONTROL ROOM Unit 1 . . . . Unit 2 , Unit 3 . . , Shif t Supervisor (Unit 1 & 2) (Unit 3) . . . l OPERATIONAL SUpFORT CI.NTER (Support group consists of Health Physics, Chemistry, Maintenance, Safety Operations group) - Operatiocal Support Center Coordinator Mechanical Maintenance Engineer Mechanical Maintenance Supervisor - - I & E Engineer . I & E supervisor Health Physics Support . . Lose Control , S & C Coordinator Support Function Coordinator. Chemistry Support . - Medical Jupport ' OSC Communicator Operations Liason Unit 93 Operations Offices ' Nuclear Equipment Operators (Unit 1 & 2 Emergencies) Nuclear Equipment Operators (Unit 3 Emergencies) Rev. 84-4 9/30/84
OCO?.TE NUCLEAR STATION CRIJIS PHONE DIRECTORY CRISIS :MNAGEMENT CENTER i PRIVATE ONS POSITION /NAME LINE SWITCHBOARD RECOVERY MANAGER State of S.C. (FEOC Line) (Duke Line) SCHEDULING / PLANNING TECHNICAL SERVICES SUPPORT S.C. Bureau of Radiological Health (Duke Line) (FEOC Line) 0FFSITE RADIOLOGICAL CCORDINATOR NUCLEAR ENGINEERING SERVICES DESIGN AND CONSTRUCTION SUPPORT. ADMINISTRATION AND LOGISTICS Y DATA COORDINATION z TELECOPIER QVISORY SUPPORT NUCLEAR REGULATORY COMMISSION BABCOCK & WILCOX (NSSS SUPPLIER) " Rev. 84-4 9/30/84
OCONEE NUCLEAR STATION CRISIS PHONE DIRECTORY GENERAL OFFICE SUF?0RT CENTER CORPORATI HEADQUARTERS (Contact with the Governor) A. C. Thies W. H. Owen # WACHOVIA CENTER RECOVERY MANAGER (Room 1010) (Speaker Phone) (Dedicated line to State Director) NRC SCHEDULING / PLANNING (Room 1010) TECHNICAL SERVICES SUPPORT (Room 2390) 0FFSITE RADIOLOGICAL COORDINATOR (Room 1222) NUCLEAR ENGINEERING SERVICES STAFF (Room 1704) i' ADMINISTRATION AND LOGISTICS (Room 0925) NUCLEAR REGULATORY COMMISSION (Room 1488) ELECTRIC CENTER DESIGN AND CONSTRUCTION SUPPORT (Room 32, 3rd Floor) CHARLOTTE SUPPLY BUILDING J CRISIS NEWS GROUP - DUKE (3rd Floor)
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Rev. 84-4 9/30/84 f
l' , i . 13 -
\ t S.C. PUBLIC INFORMATION OITICERS (Room 215) l l
l 1 i I NRC NEWS STAIT (Room 215) l l FEMA PUBLIC INFORMATION OETICES (Room 215). i
*Dedicate d line to State Center ;
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l l i Rev. 84-4 9/30/84 I
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- OCONEE NUCLEAR STATION .
, CRISIS PHONE DIRECTORY ,i . . BACKUP CRISIS MANAGEMENT CENTER LIBERTY RETAIL OFTICE, LIBERTY, S.C. AREA CODE - 803 f Telephone Number RECOVERY MANAGER SCHEDULING / PLANNING PUBLIC INFORMATION OFFICERS
- State of South Carolina i Oconee County *
{ Pickens County ] DESIGN AND CONSTRUCTION I NUCLEAR ENGINEERING SERVICES OFFSITE RADIOLOGICAL C00RDINATOR ADMINISTRATION AND LOGISTICS i I ' TECHNICAL SERVICES SUPPORT i' GOVERNMENT AGENCIES
- NRC State of South Carolina
] ' Oconee County Pickens County ll
- NOTE: Call any one of the numbers listed to reach the desired representative.
l I . l l l Rev. 84-4 9/30/84
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OCONEE NUCLEAR STATION l CRISIS PHONE DIRECTORY CRISIS NEWS CENTER , KE0kT.E-T0XAWAY VISITORS' CENTER 1, Private CNS Position /Name Line Switchboard CRISIS NEWS DIRECTOR ) Mary Cartwright i l, i i COMMERCIAL NEWS MEDIA (Active Numbers) ] For drill purposes only i i COMMERCIAL NEWS MEDIA (Inactive Numbers) Activated only during an
; actual emergency l
l i NRC/ STATE / COUNTY PUBLIC l INFORMATION OFFICERS (PI0'S) NRC Oconee County Pickens County
' State of S.C. (FECO Line)
(Duke Line)
- Note: NRC, Oconee County or Pickens County may be reached on any one of these phones.
- Rev. 84-4 9/30/84
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CCONEE NUCLEAR STATION EMERGENCY RADIO The call letters identify the Emergency Radio frequency. The following is a listing of ra to locations, unit call letters, and identifiers. Use identifiers to begin a transmission and the call letters to close out the radio transmission. (For example: Oconee Nuclear Stat on Control Room to Pickens County Law Enforcement Center. Close out wi f.) i ONS Base Station Remotes Location Unit Call Letters Identifier
- 1. Unit 1&2 Control Roca Oconee Control Rfym
- 2. Crisis Management Center Oconee CMC
- 3. Technical Support Center Oconee TSC
)
Coded Squelch Radios
~
( Location Encode Unit Call Letters Identifier
- 4. .Pickens LEC Pickens LEC
, Pickens EOC Pickens ECC Pickens EPD Pickens EPD
- 5. Oconee LEC Oconee LEC
- 6. State FEOC - (Clemson) State FECC ALL ABOVE RADIOS MAY BE ' ACTIVATED BY, ENCODING NO Field Monitoring Teams Location Unit Call Letters Identifier
- 8. Field Monitor coordinator Leader *
- 9. Field Monitor Team Alpha
- 10. Field Monitor, Team Bravo
- 11. Field Monitor Team Charlie
- 12. Field Monitor Team Delta
- 13. Field Monitor Team Echo
- 14. Field Monitor Team Foxtrot TO COMMUNICATE BET %T.EN BASE STATION REMOTES (1, 2, 3), THE INTERCOM MUST BE USED: The following procedure must be used:
- 1. Push INTERCOM button and hold ~
- 2. Push MIKE button and hold '
- 3. Send message (example, CMC to TSC)
- 4. Release both buttons to receive a response.
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Rev. 84-4 9/30/84 e
l , . . _ . ._ ._ . . _ . ~ _ . _ , _ _ . - ._ _ . ._. ___ 1 . l
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2 17 - l .i- % EMERGENCY OPERATION CLNTER - 1 f Pickens County I Primary Number
- EXECUTIVE GRotJP*
{ Emergency Preparedness
! County Administrator County Council i Legal Officer I OPERATIONS CROUP
- Law Enforcement i
Rescue Squad
. LT Fire Service Medical Service Health Service Dept. of Public Works ASSESSMLYr*
Transportation Emergency Welfare Service Shelter Service 4 _. Red Cross Public Information l RADEF Mental Health - Damage Assessment Supply and Procurement I , ALTERNATE NtJMBER (to any group) I l ( PUBLIC INFORMATION OFFICER ) l ', CRISIS NEWS CLVTER-ONS* State of South Carolina Oconee County Pickens County NRC , CRISIS NEWS CENTER LIBERTY RETAIL OFFICE * '- State of South Carolina Oconee County - Pickens County NRC
,
- Call any one.of the listed numbers to reach group desired.
ss Rev. 84-4 9/30/84 89 _ , - - - - - , . , . _ . . ___ _ . , ___.. _., - . . _ _ _ , , _ , _ _ , . , . _ _ _ . _ _ , , . , _ , . . . , . . . _ . , _ . . _ ,. ,,__.,_..-.,,,.n,, , , , ,-,
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i - t ,. l , EMERGENCY OPERATION CENTER Oconee County l Primary Number (24-hour) ..... . . ........ f
- OPERATIONS
- i i i l
l Fire Protection ................. l Police . ..................... 1 Public Roads . .................. Emergency Medical Services . . . . ........ Rescue Squads .................. l ASSESSMENT
- l Emergency Welfare Services . . . . . .......
I I l Radiological Defense . .... . . ........ i . l Damage Assessment ..........'...... , 9
, EXECITTIVE GROUP *
[ { Superviser/ Chairman County Council . . . . . . . . EOC Director . .................. Financial Officer ................ FNF Representative . . .... . . ........ i j PUBLIC INFORMATION OFFICER , I CRISIS NEWS CENTER-ONS l State of South Carolina Oconee County l Pickens County i , EC . l CRISIS NEWS CENTER LIBERTY RETAIE OFFICE , , State of South Carolina ; Oconee County { , Pickens County ! l NBC '
\
l
- Call any one of the listed numbers to reach group desired. l
_ - ) 1 Rev. 84-4 9/30/84 pd 11
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Form SPD-1002-1
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IhiJ II ' '*~l ' DUKE PCb'EK COMPANY (1) ID No: RP/0/B/1000/01 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: OCONEE (3) PROCEDURE TITLE: CLASSIFICATION OF EMERGENCY
/"N (4) PREPARED BY: -/ sfprtd; DATE: // 7/
(5) , REVIEED BY. cf [ DATE: ///'/ 8'/ Cross-Disciplinary Review By: L We v 'k-N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Ddte: (7) APPROVED BY: ,M b h Date: llf11/ PC/ (8) MISCELLANEOUS: Reviewed /t.7,w. J By: -stf 7_ Dato: //If/#ss-u y < s Reviewed / Approved By: Date: l
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m J-RP/0/B/1000/01 DUKE POWER COMPANY OCONEE NUCLEAR STATION - . CLASSIFICATION OF EMERGENCY 1.0 Symptoms 1.1 Notification of Unusual Event 1.1.1 Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. 1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs. 4 1.2 Alert
, 1.2.1 Events are in progress or have occurred which involve an
~ actual or potential substantial degradation of the level of safety of the plant.
1.2.2 Any releases are expected to be limited to small fractions
.of the EPA Protection Action Guideline exposure levels.
1.3 Site Area Emergency i 1.3.1 Events are in process or have occurred which involve actual or likely major failures of plant functions l needed for protection of the public. 1.3.2 Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary, i 1.4 General Emergency 1.4.1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. 1.4.2 Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. . 2.0 Immediate Actions 2.1 Compare actual plant conditions to the Emergency Action Level (s)* listed in Enclosure 4.1 then declare the appropriate Emergency Class as indicated. l
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RP/0/B/1000/01
-. Page 2 of 2 2.2 Initiate the Emergency Response Procedure (RP) applicable to the Emergency Class as follows:
- Notification of Unusual Event RP/0/B/1000/02 Alert RP/0/B/1000/03 Site Area Emergency RP/0/B/1000/04 General Emergency RP/0/B/1000/05 3.0 Subsequent Actions 3.1 To escalate, de-escalate or close out the Emergency, consult the procedure indicated by the action level.
4.0 Enclosures i.
, 4.1 Emcrgency Action Level (s) for Emergency Classes '
Event No. Pare (s) 4.1.1 Primary Coolant Leak 3&4 4.1.2 Fuel Damage 5 4.1.3 Steam System Failure 6 4.1.4 High Radiation / Radiological Effluents 7 4.1.5 Loss of Shutdown Function 8
, 4.1.6 Loss of Power -
9 4.1.7 Fires and Security Actions
. 10 4.1.8 Loss of Alarms and/or Communications 11 4.1.9 Spent Fuel Damage 12 l 4.1.10 Natural Disasters and Other Hazards 13, .
4.1.11 Other Abnormal Plant Conditions 14 & 15 l 4 i # 9 - -a ,.
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. IIF/e/p/lege/el
! ENCI.OStfRE 4.1.4 4
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IIIGif itADIATIOff/IRADIOlA)CICAL EFFLUENTS tfWttst84L EMET
! , alt.RT SITE AREA EMEREESICT GEmERAL ESERGENCY i.. 3. RAtl0LOCICAL EFFLIENT TS 1910173 EXCEF9FD 8. RICII RAelATicIl LEVEL OII RICE I. ACCIDENTAL MIJASE OF GASES AT
{~ __. ._ - AIDSURNE CONTAltlIIATICII: TIIE SITE 300supART WIDF.R HETEOR- 3. ACCIMNTAL MlfASE INInta ACTUAL IIEft.htPLOGICAL CCII-j
*WOTE: TS ler 0113 geerese release e Step Imereese by a facter of OlmCICAL CelsDITIcWS ERISTIIIs AT Shored 3-h it System TM TIME or MLEASE. DITICIIS AT SITE ROHIISAAT:
' ! 8000 tiere mermal setpolet of - RIR 37. &#, 35, 31, 48. St. 33. e RfA 45/44 In valle eiere sede
- RfA 45/ 4 la valid elese l CASE 00f5 EIPLWENT mede
- 3. IIADI0t.OCICAL EFFLNEIFTS ERCEE98015 AIIB
- BlA-ES la valid etere mode for le fl8IES TS
=
AND more then I heer AIID - - - - - - -- 84S20115 EFFLUENTS
- Ceecees efflecet oserie resette
- Sample resette eith rette-
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We for 30 elestes,
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- Release rate retrolettene seleS AIIs OR 'L vent searle **alyelo and fles
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! rate date are le cerces of TS Ilotto per NF/9/p/1009/IS.
- 99 e Release rate relculottene "l oolse vent semple emelyele and . * $40 mit/IIr WO for 2 mimetes
- 1. IIADIAffoil IIVEL IN RS WITII 'I t LIQUID EffLilENT flee rete date are la encoes et 2. RADIATICII LEVEL lh CONTAIIIMENT WITIt LEAR RATE Artvot1tIATE FOR ?
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Page 12 . e
- 1 Ilr/0/B/1000/01 ENCE,05UllE 4.1.9 - ,
SPENT FUEL, DAMAGE tutMAL EVTNT AIERT . SliE AREA EE RCENCY GE.ataAL EMracENCY I. (UEL DAMACE ACCIDENT WITN 1. IIAJolt imMAGE TO SPENT FUEL: MLEASE OF RA010ACTitITT 70s -
*NetEt DAMAGE MECNANISM IS e Centelament - RIA-4 WICW ALA8WI e Spent Feel Feel - BIA-43 AllRT e Large object demagee feel g t
AI.Asul e Water less below feel level j .I.N.
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i I WIA 2,3,4,49 NIGN Alers with geoeese eseple reselte indicet-i ing effette dose congereble to e SAE #2 RALS (Enc. 4.3.4) k e reel-me dll a Smildlag k , ; 1 RIA-6 NICII Alere le Spent feel ' I Feel E RIA 48 Nical Ateem with geneese '
! semyle resulte ledicating effette 1 i dose conceveble t. sAE el sAts, (sec. 4.1.4) 'I - ?
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. . INITIAL NOTIFICATION PEUJIREN!NFS CONSULT DCRGENCY 'IMFFIIONE DIRECIORY Notify 1,2,3,4 -
Notify 1,2,3,4 - e t
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iT-.I;IjJ.3 bi/ e a WdR Qtj2 .oy . i :s:.d T, l1ii'Viialn j iV3 ; i. .; g [ r ~w vun - 1 For:n SPD-!CO2-1 - i DUKE PCh*ER COMPANY PROCEDURE PREPARATION (1) ID No: RP/0/3/1000/02 i Change (s) 0 to PROCESS RECORD 0 Incorporated (2)' STATION: OCONEE (3) PROCEDURE TITLE: NOTIFICATION OF UNUSUAL EVENTS (4) PREPARED BY / .. DATE: ///f//V (5) REVII'ED BY: MA - . DATE: //!//re/ Cross-nisciplinary Review By: L r-1: N/R: v (6) TEMPORARY APPROVAL (IT NELESSART): - By: (SRO) Date: By: Date: (7) APPROVED BT: ) I h Dato: Il } 3 i } 74 (8) MISCELLANECUS: 1 Reviewed / m n ni By: -&>"" wy M Date: ///s,/#4 Reviewed / Approved By: Date: R ) i I
, - - ~,. ,. . - . . . . . , - . , , . , -. ._
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.( N RP/0/B/1000/02 DUEE POWER COMPANY -
~
. OCONEE NUCLEAR STATION NOTIFICATION OF UNUSUAL EVENTS 1.0 SYMPTOMS 1.1 Conditions exist where events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant.
2.0 IMMEDIATE ACTIONS ~ 2.1 Actions are not required to be followed in any particular sequence.
- 2.2 The Shift Supervisor / Emergency Coordinator shall
Date i Initial / Time f a 2.2.1 Appoint On-Shift Communicator (s). l 2.2.2 Appoint person to maintain logs. 2.2.3 Augmeht support as needed. 2.3 The On-Shift Communicator (s) shall: NOTE: i WARNING MESSAGE FORMS ARE IN THE IMPLEMENTING PROCEDURES CART. EMERGENCY COORDINATOR MUST APPROVI CONTENTS OF WARNING MESSAGE PRIOR TO RELEASE OFFSIT 4 2.3.1 Complete Part I (Initial Notification) of the Warning Message fo m . Have available the authentication procedure. .
- 2.3.1.1 Use Part I & II of the Warning Message forin as l applicable. Mark all spaces "N/A" when infomation
- is not applicable. Mark "Later" when information a is not currently available, 2.3.2 Notify the Counties / State of South Carolina within 15 minutes a
of the declaration of emergency. Use the Emergency Telephone Directory. 2.3.3
! Notify the NRC within 1 hour of the declaration of emergency.
- Open Ifne to the NRC may be required.
2.3.4
- Contact the Unit Operating / Duty Engineer. Operations Engineer shall use infomation from Enclosure 4.1 to complete his i notification requirements, d
a i
- . _ e . . , . . _ _ . . . _ . _ _ - . ,__ _ .- _._ _, ,.- _, ,- ._
m - - ---~ - ~ " - - ' - - - ~ ~ ~
~T 4
RP/0/B/1000/02 Date < Initial / Time - i . 3.0 SUBSEQUENT ACTIONS '.', 3.1 If the UNdSUAL EVENT situation lasts longer than 1 hour, up-date Counties / State of South Carolina agencies each hour. i OR 1If there is any significant change in the situation OR i As agreed upon with individual agencies until the emergency is closed out. 3.2 Assess the emergency situation: ) - Remain in an UN SUAL EVENT OR Escalate to a more severe class i OR 1 Terminate the emergency. i 3.3 Close out the UNUSUAL EVENT. i 3.3.1 On-shift commimientor(s) will give a verbal summary closing out the emergency to the Counties / State of South Carolina agencies and the NRC. 3.3.2 Shift Supervisor shall complete the UNUSUAL EVENT - l
- procedure and forward the procedure with all copies l of the Warning Message form'to the ONS Emergency Preparedness Coordinator. .
3.3.3 The Emergency Preparedness Coordinator shall be respon-sible for the Completed Procedure Process Record of Emergency Plan implementing procedures initiated by the Control Room. 3.3.4 The Emergency Preparedness Coordinator shall prepare a written summary for the Station Manager's signature. This summary will be forwarded to the offsite authorities (County and' State) within 24 hours of the time closecut was determined by the Emergency Coordinator. , 4.0 ENCI.OSURES 4.1 Emergency Information 4 e i
~. _
m , . - _ . . . . _ _ _ . _ _ _ _ .
RP/0/B/1000/02 Enclosure 4.1
.' DUKE POWER COMPANY OCONEE NUCLEAR STATION-EMERGENCY INFORMATION Date/ Time
- 1. This is -
at Oconee Nuclear Station. (Name and Title)
- 2. This is is not a driu. An Unusual Event -
Alert Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit # . (Time)
- 3. Initiating condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status).
- 4. C6 erective measures being taken: *
, 5. There have have not been any injuries to plant personnel.
- 6. Release of radio ~ activity: is taking place .
is not taking place
- 7. Notifications made: NRC Yes State Yes Counties Yes
_No _ No _No
- 8. Crisis Management Team response required:
Unusual Event - Notify Corp. Communications and Company Management. Alert - Bring Cdsis Management Team to stand-by. -
- Site Area Emergency - Activate the Crisis Management Team.
General Emergency - Activate the Crisis Management Team.
- 9. I can be reached at for follow-up information.
,10.
(Telephone Number) Additional Comments: _ 4 . i
- 11. Superintendent of Operations' Date Time Station Manager Date Time N.P. Duty Engin Date Time
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,7 7 r'n n Form SPD-1002-1 0 - I* -
DUKE POWER COMPANY (1) ID No: RP/0/B/1000/03 PROCEDURE PREPARATION. Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: nt nnn (3) PROCEDURE TITLE: ALERT (4) PREPARED BY (( DATE: //[f/fY (5) REVIEWED BY: /- m > w - DATE: // #//' Cross-Disciplitary Review By e -- -- N/R: v (6) TEMPORARY APPROVAL (IF NECESSARY): - By: (SRO) Date: By: Date: (7) APPROVED BY: d $Y Date:
!! fii (8) MISCELLANEOUS:
Reviewed! M - --d By: fpM I
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Date: //4,/A vy / r Reviewed / Approved By: Date: I p..- O
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. .j OCONEE NUCLEAR STATION ALERT 1.0 SYMPTOMS .
1.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. 2.0 IMMEDIATE ACTIONS 2.1 Actions are not required to be followed in any particular sequenc$. 2.2 The Shift Supervisor / Emergency Coordinator shall:
- Date Initial / Time 2.2.1 Appoint On-Shift Communicator (s).
2.2.2 Appoint person to maintain logs. . 2.2.3 Initiate a Site Assembly in accordance with RP/0/B/1000/09 to set up the Tech *=1 Support Center. 2.2.4 Dispatch onsite monitoring teams to assess radiation and contamination. 2.3 The On-Shift Communicator (s) shall: NOTE: WARNING MESSAGE FORMS ARE IN THE IMPLEMENTING PROCEDURES CART. EMERGENCY COORDINATOR MUST APPROE CONTENTS OFFSITE. RELEASED OF WARNING MESSAGE PRIOR TO INFORMATION BEIN 2.3.1 Complete Part I (Initial Notification) of the Warning Message form. Have available the authentication procedure. 2.3.1.1 Use Part I & II of the Warning Message form as applicable. Mark all spaces "N/A" when information is "Not applicable." Mark "Later" when information is not currently available. 2.3.2 Notify the Counties / State of South Carolina within 15 minutes of the declaration of emergency. Use the Emergency Telephone Directory. u ..- *--- - ~ -~ ...
, _ ,_ _ _ . _ . , _ _ _ _ . . . . - - - -- - -- --- - - - -~ - -
4 RP/0/B/1000/03 ! Date Initial / Time ' 2.3.3 Notify the NRC within 1 hour of the declaration of the [ l 1
, emergency. Open line to the NRC may be required.
2.3.4 Contact the Unit Operating / Duty Engineer. Infomation l
' ~ from Enclosure 4.1 shall be used by the Operations Engineer to complete his notification requirements.
2.3.5 Contact Security Shift Lieutenant. (Enclosure 4.2 provides response actions of Security.) 2.3.5.1 Code Red (0800-1630 Weekdays Monday through Friday) 2.3.5.2 Code Blue (After hours, holidays, weekends) 3.0 SUBSEQUINT ACTIONS NOTE: CONTROL ROOM OR TECHNICAL SUPPORT CENTER 3.1 If the ALERT lasts longer than 1 hour, update Counties / State , of South Carolina agencies each hour , _O R y ,( If there is any significant change in the situation-
, QR As agreed upon with individual agencies until the emergency is closed out.
3.2 Technical Support Center Operational. (See Enclosure 4.3) 3.3 urisis Management Center Operational. 3.4 Assess the emergency situation: Remain in an ALERT OR i Escalate to a more severe class 9a Reduce the emergency classification QR_ Terminate the eme" 9 _--e, ' -. --a .- ,, . # -
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RP/0/B/1000/03 f', Date Initial / Time - 3.5 The Offsite Communicator (s) in the Technical Support Center will give '. a verbal summary to reduce or clos,e out the emergency to the Counties / State of South Carolina agencies and the NRC. 3.5.1 The Emergency Preparedness Coordinator shall prepare a written summary for the Station Manager's signature. This summary will be forwarded to the offsite authorities within.8 hours of the de-escalation or closeout by the Emergency Coordinator. 3.6 The Emergency Preparedness Coordinator shall be responsible for completing all Completed Procedure Process Records of Emergency Plan implementing procedures initiated by the Control Room and/or Technical Support Center during the emergency. 4.0 ENCLOSURES 4.1 Emergency Infonnation 4.2 Globe Security Response 4.3 Technical Support Center Turnover Sheet e J
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RP/0/B/1000/03 l Enclosure 4.1 1 DUKE POWER COMPANY ' OCONEE NUCLEAR STATION ' EMERGENCY INFORMATION j
,1 Date/ Time .
i
- 1. This is .
at Oconee Nuclear Station. , , (Name and Title) 1
- 2. This is
- is not a drill. An Unusual Event Alert Site Area Emergency General Emergency was declared by the Emergency Codrdinator at on Unit # .
(Time)
- 3. Initiating condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status).
- 4. Corrective measures being taken: *
- 5. There have have not been any injuries to plant personnel.
- 6. Release of radioactivity: is taking place is not taking place
- 7. Notifications made: NRC Yes State Yes
~
Counties Yes _No No No
- 8. Crisis Management Team response required:
Unusual Event - Notify Corp. Communications and Company Management. Alert - Bring Crisis Management Team to stand-by. Site Area Emergency - Activate the Crisis Management Teain. General Emergency - Activate the Crisis Management Team.
- 9. I can be reached at for follow-up information.
(Telephone Number)
- 10. Additional Comments: _
- 11. Superintendent of Operations Date Time l Station Manager Date Time N.P. Duty Engineer Date Time y ,.
5
. . . _ = . . _ _. -_ - --
RP/0/B/1000/03 Enclosure 4.2 DUKE POWER COMPANY OCONEE NUCLEAR STATION .
^ '
GLOBE SECURITY RESPONSE Date/ Time . AT On-Shift Communicator Telephone Number To: AT 1309 Secunty Shift Lieutenant Telephone Number Give the following information:
- 1. This is is not a drill. The Technical Support Center is being activated for an emergency relating to Unit # .
n a 2. Provide Code Red Response: (0800 - 1630 Weekdays Monday through Friday) Access and Control to all three Control Rooms. Station Personnel Accountability Patrol station for Site Assembly and secure the gates.
. Switch telephones to TSC and OSC.
t
- Implement Globe Procedure 81-0100-0-06 i
Provide Manpower for MERT Team Provide Code Blue Response: (After hours, weekends, holidays) Recall Duty Personnel per Duty Roster Switch telephones to TSC and OCS Unlock doors to TSC and OSC Patrol station for Site Assembly and secure the gates Access and Control to all three Control Rooms Station Personnel Accountability Implement Globe Procedure 81-0100-0-06 Provide Manpower for MERT Team S O
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6- RP/0/B/1000/03 Enclosure 4.3 m DUKE POWER COMPANY OCONEE NUCLEAR STATION - TECHNICAL SUPPORT CENTER TURNOVER SHEET '
- 1. Personnel arriving in the Technical Support Center shall relieve "
Operations personnel of peripheral duties ordinarily assigned to
. their section. These persons will be provided direction from the Emergency Coordinator / Shift SuperWsor until he is relieved of accident management responsibilities by the Station Manager /
alternate once the Technical Support Center is operational. Date Initial / Time FACE TO FACE WRITTEN TURNOVER IS REQUIRED NAME-Station Manager Health Physics Dose Assessment Performance . Compliance
- 2. Technical Support Center Operational
- 3. Station Manager shall assume the following accident management responsibilities: ,
Provide for continuous staffing of the Technical Support Center and Operational Support Center Maintain station accountability and dose control Implement approval process for release of information Provide update of emergency status to plant personnel Provide protective action recommendations to County / State authorities Make available news release to TSC and OSC Maintain contact with Crisis Management Center Direct and initiate measures to control and mitigate the emergency a O =
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W9 4';we ' ~ " " Form SPD-1002-1 - h- ' DUKE POWER CCMPANY (1) ID No: U/0/B/1000/04 PROCEDURE PREPARATION Change (s) 0 to PROCESS RECORD- 0 Incorporated . (2) STATION: OCONEE (3) PROCEDURE TITLE: SITE AREA EMERGENCY _ (4) PREPARED BY d(( axwje .DATE: ///f[# (5) REVIEWED BY: h, Jefb DATE: //!/ I Cros N isciplinary Review By L M N/R: u (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: b b b. - Date: I L } 2. g l Q Q (8) MISCELLANECUS: , Reviewed /A;;;::23 By: gr ^f $ pa g e : ,,h],y, Wr
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Reviewed / Approved By: Date: A e
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- RP/0/B/1000/04 DUKE POWER COMPANY .
OCONEE NUCLEAR STATION '
- SITE AREA EMERGENCY 1.0 . SYMPTOMS 1.1 Events are in process or have occurred which involve 'a n actual or likely of the major failure of plant functions needed for protection public.
2.0 IMMEDIATE ACTIONS 2.1 Actions are not required to be followed in any particular sequence. 2.2 The Shift Supervisor / Emergency Coordinator shall: NOTE: PROTECTIVE ACTION RECOMMENDATIONS ARE THE RESPONSIBILITY MAY NOT BE DELEGATED. OF THE EMERGENCY COORDINAT Date Initial / Time " 2.2.1 Recommend within 15 minutes of declaration of SITE AR ~ EMERGENCY to Counties / State of South Carolina that Alerting Sirens be sounded and that the EBS be activated to inform the public of a potential for later protective actions. 2.2.2 Appoint On-shift communicator (s). 2.2.3 Appoint person to maintain logs. 2.2.4 Initiate a Site Assembly in accordance with RP/0/B/1000/09 to set up the Technical Support Center. 2.2.5 Dispatch onsite monitoring teams to assess radiation and contammation. 2.3 The On-Shift Communicator (s) shall: NOTE: WARNING MESSAGE PROCEDURES CART. FORMS ARE IN THE IMPLEMEN CONTENTS OF WARNING MESSAGES BEING RELEASED OFFSITE. m e e s -me s-
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- - - - - - - - - - ^ - " ~
RP/0/B/1000/04 Date Initial / Time . 2.3.1 . Complete Part I (Initial Notification) of the Warning ..
^
- Message form. Have available the authentication procedure.
Emergency Coordinator must make the initial notification since protective recommendations are required. 2.3.1.1 Use Part I & II of the Warning Message form as applicable. Mark all spaces "N/A" when information-is not applicable. Mark "Later" when information is not currently available. 2.3.2 Notify the NRC within I hour of the declaration of the emergency. Open line to the NRC may be required. 2.3.3 Contact unit Operating / Duty Engineer. Information from Enclosure 4.1 shall be used by the Operations Engineer to complete his notification requirements. 2.3.4 Contact Security Shift Lieutenant to respond. (Enclosure 4.2 provides response actions of Security.) 2.3.4.1 Code Red (0800-1630 Weekdays Monday through Friday) 2.3.4.2 Code Blue (After hours, wee'kends, holidays) - 3.0 SUBSEQUENT ACTIONS t NOTE: CONTROL ROOM OR TECHNICAL SUPPORT CENTER 3.1 Update Counties / State of South Carolina agencies each half hour QR_ If there is any significant change in the' situation 9.R_ Asclosed is agreedout.upon with individual agencies until the emergency 3.2 Follow-up Protective Action Recommendations to offsite authorities. Use RP/0/B/1000/06 for determination of protective action recom-mendations. 3.2.1 Offsite dose calculations will be made by Operations or i the Health Physics Center depending on which group is available. This information will be used by the Emergency State of SouthtoCarolina. Coordinator make recommendations to the Counties / l
._ .._,. _. _l__ . _ _ . - . . - - -- - - - - - - - --
3- RP/0/B/1000/04 m
't Date Initial / Time '
3.3 Consider evacuation of non-essential personnel per RP/0/B/1000/10. h '. ! 3.4 Technfr=1 Support Center Operational. (See Enclosure 4.3.) 3.5 Crisis Management Center Operational. 3.6 Assess the emergency situation: Remain in a SITE AREA EMERGENCY EE Escalate to a more severe class Of i Reduce the emergency classification SE Terminate the emergency classification. 3.7 The Recovery Manager at the Crisis Management Center shall recommend
,j close out'or reduction of the emergency classification by phone or by briefing to offsite authorities at the Crisis Management Center. The Recovery Manager shall provide a written summary to
' offsite closeout. authorities within 8 hours of the class reduction or 3.8 The Emergency Preparedness Coordinator shall be responsible for completing all Completed Procedure Process Records of Emergency Plan implementing procedures initiated by the Control Room and/or Technical Support Center. I 4.0 ENCLOSURES j 4.1 Emergency Infor1 nation i 4.2 Globe Security Response 4.3 Technical Support Center Turnover Sheet l pe
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RP/0/B/1000/04 Enclosure 4.1 c DITRE POWER COMPANY OCONEE NUCLEAR STATION EMERGENCY INFORMATION
- 1. I'his is at Oconee Nuclear Station. .
(Name and Title)
- 2. This is is not a driH. An Unusual Event Alert Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit # .
(Tim.e)
- 3. Initiating condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status) .
- 4. Corrective measures being taken:
- 5. There have have not been any injuries to plant personnel.
- 6. Release of radioactivity: is talong place is not taking place '
- 7. Notifications made: NRC Yes .S tate Yes Counties Yes No _No No
- 8. Crisis Management Team response required:
Unusual Event - Notify Corp. Communications and Company Management. Alert - Bring Crisis Management Team to stand-by. Site Area Emergency - Activate the Crisis Management Tear:r. General Emergency - Activate the Crisis Management Team.
- 9. I can bs' reached at for follow-up information.
(Telephone Number)
'10. Additional Comments:
! 11. Superintendent of Operations Date Time Station Manager Date Time
~
N.P. Duty Engin Date Time e e
r,
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-S- RP/0/B/1000/04 Enclosure 4.2 i
1 DUKE POWER COMPANY
.~
OCONEE NUCLEAR STATION - GLOBE SECURITY RESPONSE . Date/ Time AT On-Shift Communicator Telephone Number TO: AT l Secunty Shift Lieutenant one er Give the following information:
- 1. This is 's i not ~~ a drill. The Technical Support Center is being activated for an emergency relating to Unit # .
2. Provide Code -Red Response: (0800 - 1630 Weekdays Monday through Friday) Access and Control to all three Control Rooms. Station Personnel Accountability Patrol station for Site Assembly and secure the gates. Switch telephones to TSC and OSC. Implement Globe Procedure 81-0100-0-06 Provide Manpower for MERT Team Provide Code Blue Response: (After hours, weekends, holidays) Recall Duty Personnel per Duty Roster Switch telephones to TSC and OCS Unlock doors to TSC and OSC Patrol station for Site Assembly and secure the gates Access ard Control to all three Control Rooms Station Personnel Accountability Implement Globe Procedure 81-0100-0-06 Provide Manpower for MERT Team I O
_ , . _ _ _ ~_ - - - --- --
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- 6.- RP/0/B/1000/04 Enclosure 4.3 DUKE POWER COMPANY .
OCONEE NUCLEAR STATION TECHNICAL SUPPORT CENTER TURNOVER SHEET
- 1. Personnel arriving in the Technical Support Center shall relieve Operations personnel of peripheral duties ordinarily assigned to their section. These persons will be provided direction from the Emergency Coordinator / Shift Supervisor until he is relieved of accident management responsibilities by the Station Manager /
alternate once the Technical Support Center is operational. Date Initial / Time FACE TO FACE WRITTEN TURNOVER IS REQUIRED NAME Station Manager . Health Physics Dose Assessment Performance Compliance
- 2. Technical Support Center Operational .
- 3. Station Manager shall assume the following accident management responsibilities:
Provide for continuous staffing of the Technical Support Center and Operational Support Center Maintain station accountability and dose control
- Implement approval process for release of information Provide update of emergency status to plant personnel Provide protective action recommendations to County / State authorities
! Make available news release to TSC and OSC i Maintain contact with Crisis Management Center Direct and initiate measures to control and mitigate the emergency h l
J . _ _ _ . .-.. . ~ . . . .--~.r..~ n,.-_. . ..-, NFORMATION O For:n SPD-1002-1 = h VJ U -
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DUKE POWER COMPANY (1) ID No: RP/0/B/1000/05 PROCEDURE PREPARATION Change (s) n ,t o PROCESS RECORD n Incorporated - (2) STATION: ocnww (3) PROCEDURE TITLE:__ GENERAL E4ERGENCT n . (4) PREPARED BY: w DATE: // / / (5) REVIEWED BY: Def f DATE: // /M '/ . Cross-Disciplinary Review By: R b- r'_d U N/R: (6) TEMPORARY APPROVAL (17 NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: ( h Data: 18 M l 24 (8) MISCELLANEOUS: 1 Reiteved/k;::::: By: 9720 Date: 1)/94 /1 4 ' . wy // Reviewed / Approved By: Date: < m O wwe- O e
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O RP/0/B/1000/05
~
DUEE POWER COMPANY -
- ~
OCONEE NUCLEAR STATION ~ GENERAL EMERGENCY 1.0 SYMPTOMS - 1.1 Events are in process or have occurred which involve an actual or 2mminent substantial core degradation or melting with potential for loss of containment integrity. 2.0 IMMEDIATE ACTIONS - - 2.1 Actions are not required to be followed in any particular sequence. l 2.2 The Shift Supervisor / Emergency Coordinator shall-
- i NOTE: PROTECTIVE ACTION RECOMMENDATIONS ARE THE SOLE RESPONSIBILITY OF THE EMERGENCY COORDINATOR AND MAY NOT BE DELEGATED.
Date
/ Initial / Time
[ .- .. 2.2.1 Time of day - 1000 to 1559 l Within 15 minutes, of a declaration of a GENERAL EMERGENCY, recommend to County / State authorities that all residents in the 2 mile radius and 5 mile downwind in a 90* sector go indoors, close all windows and doors, turn off ventilation equipment and monitor EBS for in-formation. NOTE: IDENTIFY the areas in the 90* Sector 2.2.2 Time of day - 1600 to 1000 t Within 15 minutes of a declaration of a GENERAL EMERGENCY, recommend to County / State authorities that
' all residents out to 5 miles should go indoors, close all windows and doors, turn off ventilation equipment and monitor EBS for information.
2.2.3 Appoint on-shift communicator (s). 2.2.4 Appoint person to maintain logs. 2.2.5 Initiate a Site Assembly in'accordance with RP/0/B/1000/09 to set up Technical Support Center. a.
# .- - - - - - .4-- . . - . ---..-4... . . . - . - - - - -
RP/0/B/1000/05
~
. Date .
' Initial / Time -
2.2.6 ' Dispatch onsite monitoring teams to. assess radiation and '. . contamination. . 2.3 The On-Shift Communicator (s) shall: NOTE: WARNING MESSAGE FbRMS ARE IN THE IMPLEMENTING PROCEDURES CART. EMERGENCY COORDINATOR MUST APPROVE CONTENTS OF ALL WARNING MESSAGES. PRIOR TO RELEASE OFFSITE. 2.3.1. Complete Part I (Initial Notification) of the warning Message form. Have available the authentication procedure. Emergency Coordinator must make the initial notification since protective recommendations are required. 2.3.1.1 Use Part I and II of the Warning Message fonn as applicable. Mark all spaces "N/A" when informa-tion is not applicable and mark "later" when . information is not currently available.
- 2.3.2 Notify the NRC within 1 hour of the declaration of the emergency. Open line to the NRC may be required.
1 2.3.3 Contact Unit Operating / Duty Engineer. Information from
- s..
Enclosure 4.1 shall be us'e d by the Operations Engineer to complete his notification requirements. 2.3 4 Contact Security Shift Lieutenant to respond. (See Enclosure 4.2). i 2.3.4.1 Code Red - (0800-1630 Weekdays Monday through Friday.) 2.3.4.2 Code Blue - (After hours, weekends, holidays.) 3.0 SUBSEQUENT ACTIONS NOTE: CONTROL ROOM OR TECHNICAL SUPPORT CENTER l 4 3.1 Update County / State agencies each half hour { OR If there is any significant change in the situation _O_R_ ' As agreed up,on with individual agencies until the emergency is closed out. . s l l
., -,- .- . - . , . - , . - ~ .,, -,.--w-_+-e.~,m,.,y s . - - . ~ .,
. RP/0/B/1000/05 Date '
Initial / Time - 3.2 Follow-up Protective Action Recommendations to offsite agencies. -. I Use RP/0/B/1000/06 for determination.of protective action recommendations required. 3.2.1 Offsite dose calculations will be made by Operations or Health Physics Center personnel depending on which group is available. This information will-be used by the Emergency Coordinator to make recommendations to the Counties / State of South Carolina. 3.3 Evacuate non-essential personnel per RP/0/B/1000/10. 4 3.4 Dispatch Offsite Monitoring Teams to monitor radiation and contammation. J 3.5 Technical Support Center Operational. (See Enclosure 4.3). . 3.6 Crisis Management Center Operational. 4 3.7 Assess the emergency condition: Remain in the GENERAL EMERGENCY 4 OR
- Reduce the emergency classification i
9.R, , Tarminate the emergency classification. : 3.8 The Recovery Manager at the Crisis Management Center shall close out or recommend reduction of the emergency classification by phone or by briefing to offsite authorities at the Crisis Manage-ment Center. The Recovery Management shall provide a written summary to offsite authorities within 8 hours of the class reduction or closecut. 3.9 The Emergency Preparedness Coordinator shall be responsible for completing all Completed Procedure Process Records of Emergency Plan implementing procedures initiated by the Control Room and/or Technical Support Center during the emergency. 4.0 ENCLOSURES 3 4.1 Emergency Information 4.2 Globe Security Response 4.3 Technical Support Center Turnover Sheet Y f K' ~~L -,V.. ^ * * " ' ". '**"^*?~*'
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RP/0/B/1000/OS
' Enclosure 4.1 DUKE POWER COMPANY OCONEE NUCLEAR STATION EMERGENCY INFORMATION -
~
- 1. This is .
at Oconee Nuclear Station. (Name and Title) -
'2. This is is not a drill. An Unusual Event Alert Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit # .
(Time)
- 3. Initiating condition:
(Give as close to the emergency plan description . as possible status). together with station parameters used to determine emergency
- 4. Corrective measures being taken:
- 5. ,There have have not been any injuries to plant personnel.
- 6. Re' lease of radioactivity:
'~
is taking place is not taking place
- 7. Notifications made: NRC Yes
, State Yes Counties Yes No No -
No
- 8. Crisis Management Team response required:
Unusual Event - Notify Corp. Communications and Company Management. Alert - Bring Crisis Management Teah to stand-by. . . Site Area Emergency - Activate the Crisis Management Team. General Emergency - Activate the Crisis Management Team.
- 9. I can be reached at for follow-up information.
(Telephone Number)
- 10. Additional Comments:
- 11. Superintendent of Operations Date Time Station Manager Date Time N.P. Duty Engineer Date Time I .
RP/0/B/1000/OS Enclosure 4.2
' DUKE POWER COMPANY OCONEE NUCLEAR STATION Ipa 7/Inic". GLOBE SECURITY RESPONSE AT On-Shift Communicator Telephone Number TO: AT Security Shift Lieutenant Telephone Number Give the following information:
- 1. This is is not a drill. The Technical Support Center is being activated for an emergency relating to Unit #
2. Provide Code Red Resconse: (0800 - 1630 Weekdays Monday through Friday) , Access and Control to all three Control Rooms. Station' Personnel Accountability Patrol station for Site Assembly and secure the gates. Switch t,elephones to TSC and OSC. Implement Globe Procedure 81-0100-0-06 Provide Manpower for MERT Team Provide Code Blue Resconse: (After hours, weekends, holidays)
.,. a3-Dutz Personnel per Duty Roster Switch telephones to TSC and OCS U,nlock doors to TSC and OSC Patrol station for Site Assembly and secure the gates Access and Control to all three Control Rooms Station Personnel Accountability Implement Globe Procedure 81-0100-0-06 Provide Manpower for MERT Team ~
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1 RP/0/B/1000/05 Enclosure 4.3 DUKE POWER COMPANY OCONEE NUCLEAR STATION TECHNICAL SUPPORT CENTER TURNOVER SHEET
- 1. Personnel arriving in the Technical Support Center.shall relieve Operations personnel of peripheral duties ordinarily assigned to their section. These persons will be provided direction from the Emergency Coordinator / Shift Supervisor until he is relieved of accident management responsibilities by the Station Manager /
alternate once the Technical Support Center is operational. Date Inital/ Time FACE TO FACE WRITTEN TURNOVER IS REQUIRED NAME Station Manager Health Physics Dose Assessmerit ' Perfomance Compliance
- 2. Technical Support Center Operational
- 3. Station Manager shall assume the following accident management responsibilities:
Provide for continuous staffing of the Technical Support Center and Operational Support Center Maintain station accountability and dose control Implement approval process for release of infomation Provide update of emergency status to plant personnel Provide protective action recommendations to County / State authorities Make available news release to TSC and OSC Maintain contact with Crisis Management Center Direct and initiate measures to control and mitigate the emergency , O
. 7, ._..- . , . _ _
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! ,..,* 1 ; " : ~~ : " i ' I 'j, b,,W d'rdJ;u;g h g'g f t Form SPD-1002-1 '
-1 DUKE POWER COMPANY (1) ID No: Rp/o/3/1000/06 PROCEDURE PREPARATION Change (s) 0 to PROCESS RECORD 0 Incorporated (2) STATION: OCCNEE (3) PROCEDURE TITLE: PROTECTIVE ACTION RECO. W ATIONS A . .
(4) PREPARED BY:- _L 3 DATE: // / # (S) REVII'ED BY: ( DATE: // Y Cross-Disciplinary Review By: b$M V N/R: (6) TDiPORARY APPROVAL (IF NECESSARY):" By: , (SRO) Date: By: ' Date: AQm (/ APPROVED BY: Date: 11 . Ml7y (8) MISCELLANEOUS: Reviewed /';;rr--d By: 77 PI Date: <//NMif#-
- vy s Reviewed / Approved By:
Date: i l
RP/0/B/1000/6 . I '. DUKE POWER COMPANY - OCONEE NUCLEAR STATION PROTECTIVE ACTION RECOMMENDATIONS 1.0 SYMPTOMS - 1.1 Radioactive releases (or potential for release) that produce projected doses in excess of the limits in Enclosure 4.2 requires protective action recommendations.
- 2.0 IMMEDIATE ACTIONS 2.1 Refer to- Enclosure 4.1 to determine ,the protective action recommendations.
J 2.2 Request actual doce projections and re-evaluate recommendations to counties and state using offsite monitorint measurements (if available), current meteorology, and core / reactor coolant system / containment status.
, 3.0 SUBSEQUENT ACTIONS
- NOTE:
COUNTY AND/OR STATE EMERGENCY OPERATIONS CENTER FACILITIES MAY OR MAY NOT BE ESTABLISHED AND THE GENERAL OFFICE EMERGENCY RESPONSE ORGANIZATION HAS NOT BEEN ACTIVATED. 3.1 Contact Oconee County and Pickens County Emergency Preparedness agencies to update them on the revised recommendations. Notify the State of South Carolina warning point of the recommended I action. 4.0 ENCLOSURES I 4.1 Protective Action Guide Flowchart I I 4.2 Protective Action Guide O
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. SURE 4.1 PROTE ON GUIDE CHART
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4 5 l DUKE POWER COMPANY - RP/0/B/1000/06 ' OCONEE NUCLEAR STATION Enclosure 4.2 ' PROTECTIVE ACTION CUIDES , !
, Projected Dose (Rem) to the Population Recommended Actions (a) Comments 4 Whole Body <1 1 No protective action required. '
Previously recommended 11
- State may issue an advisory to seek shelter and await Thyroid <5 further instructions or to voluntarily evacuate. protecti've actions may Honitor environmental radiation levels. ' be' reconsidered or terminated.
I Whole Body I to <5 Seek shelter and wait further instructions. consider evacuation particularly for children and l 3 Thyroid 5 to <25 pregnant women. 8 Monitor environmental radiation levels. Control access. '
] Whole Body 5 and above Conduct mandatory evacuation of populations in the j predetermined area. '
Seeking shelter would be ! Thyroid 25 and above an alternative if
- Monitor environmental radiation levels and 4d just area evacuation were not , ,i
[ for mandatory evacuation based on these levels. immediately possible. t Control access. '} l Projected Dose (Rem) to Emergency Team Workers !" . VOLUNTARY BASIS - , ; (P.LANNED EMERGENCY EXPOSURE BEYOND 10 CFR 20 LIMITS) Whole Body 5-25* Control exposure of emergency. team members to these "- Skin of whole body 30-125* levels except for lifesaving missions. {' Thyroid 125* (Appropriate - ' Extremities controls for emergency workers, include time ; 75 limitations, respirators, and stable iodine.) ! Respirators and stable I' lodine should be used . Whole body 25-75* Control exposure of emergency team members performing where effective for Thyroid 150* lifesaving missions to this level. (Control of time emeagency team workers. . Skin of whole body 150* of exposure will be most effective.) Extremities 375 (a) These actions must take are recommended existing conditions intofor planning purposes. Protective action decisions at the time of the incident consideratica.
- NOTE:
! Dose up to this limit must be authorized by the Emergency Coordinator.
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- DUKE P0k'ER CCMPANY (1) ID,No: RP/0/3/1000/09 PROCEDURE PREPARATION Change (s) 0 to PROCESS RECORD 0 Incorporated (2) STATION: OCONEE .
(3) PROCEDURE TITLE: PROCEDURE FOR SITE ASSEMBLY
. A (4) PREPARED BY: A _*: DATE: // # /
(5) REVIEWED BY. m [_ DATE: ///P[ Cross-Disciplinary Review By: b d+- ,ek N/R: U (6) TDfPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVEDBY:hb m Date: 1i 13 3N (8) MISCELLANEQUS: Reviewed / Approved By I /juc6MDate: A6 ./ / Reviewed / P-~-M By: -:ps'y F-I vy Date:s wh///4 s e 8
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OC,0 NEE NUCLEAR STATION PROCEDURE FOR SITE ASSEMBLY 1.0 SYMPTOMS 4 1.1 A test of response time and procedures employed in completing an accounting of onsite. personnel. 1.2 A station incident occurs and: 1 1.2.1 The Technical Support Center is required to be established. . 1.2.2 Portions of the protected area may require evacuation or a station evacuation may be required. , 2.0 IMMEDIATE ACTIONS
,, 2.1 Action Plan for Shift Supervisor. (Enclosure 4.1)
, 2.2 Action Plan for Security Shift' Lieutenant (Enclosure 4.2)
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2.3' Personnel Assembly Signak (warble sound) is made over the Public Address System from Control Room 1&2. 2.4 Announcement is made over the Public Address System. (See Enclosure 4.3) 4 2.5 t The alarm and announcements shall be continued for a duration long enough to ensure all onsite personnel are aware of the Site Assembly and are responding. (At least 6 alarms and announcements over a 15 min. period). . 3.0 SUBSEQUENT ACTIONS 3.1 Action Plan for Onsite Personnel (Enclosure 4.4) - 3.2 When personnel accountability has been completed following a Site Assembly, one of the following will occur. 3.2.1 If the requirement fcr an assembly no longer exists, a request to return to nomal duties will be given by the Emergency Coordinator. 3.2.2 Plant conditions may require evacuation of the station. Consult procedure RP/0/3/1000/10. t
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., "o 2- RP/0/B/1000/09 4.0 ENCLOSURES #
4.1 - Action' Plan Emergency Coordinator .
- 4.2 Action Plan for Security Shift Lieutenant '
4.3 Public Address Innouncement 4.4 Action Plan for Onsite Personnel
. 4.5 Site Assembly Locations 4
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ENCLOSURE 4.1 DUKE POWER COMPANY OCONEE NUCLEAR STATION . , ACTION PLAN FOR EMERGENCY COORDINATOR (SHIFT SUPERVISOR AND/OR STATION MANAGER) 4.1.1 Alert Security Shift Lieutenant that a Site Assembly will be initiated. 4.1.2 Direct necessary actions to account for any missing personnel. 4.1.2.1 MERT Team will be utilized for this purpose. 4.1.3 Examine'the radiation / contamination levels established in RP/0/B/1000/10 to determine the classes of personnel that may need to be evacuated. 4.1.'4 If the requirements for an assembly no longer exist, return the station, to normal duties. Y e C i O e svee g eve -,we--e y+e w = .*g- e w e e r e .w , ,, e w w g -+w.3 .ee n - e-p- .- --w - -
? 4- RP/0/B/1000/09 ENCLOSURE 4.2 l DUKE POWER COMPANY < OCONEE NUCLEAR STATION . - ACTION PLAN FOR SECURITY SHIFT LIEUTENANT 4.2.1 Contact Visitors Center, Keowee Hydro and Technical Training Center to make them aware of Site Assembly. 4.2.2 Initiate a' patrol of the general station areas within station boundaries, both inside and outside of the restricted area, to assure that personnel in remote and noise restrictive areas are aware of the Site Assembly requirement. 3 4.2.3 Restrict traffic in and out of the station gates during l Site. Assembly. . NOTE: SHOULD SITE ASSEMBLY BE INITIATED DURING HIGH TRAFFIC INGRESS AND EGRESS, TRAFFIC FLOW WILL NOT BE RESTRICTED. 4.2.4. Receive Accountability reports from all groups. Use Enclosure 4.5 as an aid. 4.2.5. Report total accountability to the Emergency Coordinator within 30 minutes of the time the assembly was initiated. Report the name(s) of any missing person (s). 4.2.6 Coordinate a search and rescue effort if directed by 'the Emergency Coordinator. 4.2.6.1 Utilize the MERT Team for this purpose. 4.2.7 Contact Visitors Centor, Keowee Hydro and Technical Trainmg Center to make them aware of Site Assembly completio.n. 4.2.8 Coordinate evacuation if so instructed by Emergency Coordinator. O i......,.-.i,,-- ...,i
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RP/0/B/1000/09 . ENCLOSURE 4.3 l
- DUKE POWER COMPANY OCONEE NUCLEAR STATION - -l ANNOUNCEMENT "THIS IS A SITE ASSEMBLY. THIS IS A SITE ASSEMBLY."
ALL VISITORS ARE TO REPORT TO THE RECEPTIONIST LOBBY. ALL PERMANENTLY BADGED PERSONNEL SHALL REPORT TO THE " AREA DESIGNATED ON THE BACK Or YOUR SECURITY BADGE. ALL OTHER PERSONNEL NOT PRESENTLY WEARING SECURITY BADGES SHALL REPORT TO YOUR SUPERVISOR. NOTE: IF ANY PARTICULAR AREA OF THE PLANT IS FOUND TO BE RADIOLOGICALLY UNSAFE DURING AN EMERGENCY, AND A SITE ASSEMBLY IS HELD, WARNINGS SHOULD BE SOUNDED THROUGH THE TO USE.PUBLIC ADDRESS SYSTEM ADVISING THE " SAFE" CORRIDORS 9 1 O
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. RP/0/B/1000/09 ENCLOSURE 4.4 DUKE POWER COMPANY - ,
OCONEE NUCLEAR STATION. ' I '.
' ACTION ' PLAN FOR ONSITE PERSONNEL IN RESP'ONDING TO A SITE ASSEMBLY ALAR 4.4.1 Each person (except those noted in '4.4.3) shall assemble with their
' supervisor. EACH REPORTING SUPERVISOR IS TO REPORT LOCATION,
' NAME, TELEPHONE NUMBER, NUMBER OF PEOPLE ASSEMBLED, AND THE NAME(S) OF ANY UNACCOUNTED PERSON (S). Assembly points for personnel onsite at Oconee Nuclear Station are identified in Enclosure 4.5. Additionally, these locations are on the back of the security badge for those personnel inside security.
NOTE: . TOTAL ACCOUNTABILITY SHALL BE MADE WITHIN 30 MINUTES. SUPERVISOR SHOULD REPORT THEIR ACCOUNTABILITY WITHIN
- 8 TO 10 MINUTES. SUPERINTENDENTS SHALL HAVE A TOTAL NUMBER FOR THEIR GROUP AND THE NAMES OF ANY PERSONS 1
NOT ACCOUNTED FOR WITHIN 20 MINUTES. 4.4.2 0800-1630 (Monday-Friday normal working hours) Each supervisor shall be responsible for accounting for all personnel re-porting to him. Station Superintendents and the Supervisors of various organizations working at Oconee (SSD, Transmissions, QA,' Visitors Center
- Keowee-Hydro, SMS, and B&W) shall make an accountability report to the -
SECURITY SHIFT LIEUTENANT for their areas of accountability. When reports from all areas are received, the Emergency Coordinator will be notified that all persons have been accounted for. After hours, weekends. holidays Each supervisor shall be responsible for accounting for all personnel reporting to him. Supervisors shall report accountability to the SECURITY SHIFT LIEUTENANT. When reports from all areas are received, the Emergency Coordinator will be notified that all persons have been accounted for by their supervisor. , 4.4.3 Persons working'in Radiation Control Areas in protective clothing i should leave their work areas and go to the appropriate change room. ! In the change room, they should contact the appropriate persons as I designated by 4.4.2 for personnel accountability reporting. Judgement should be used concerning the advisability of changing clothes and reportag to normal assembly areas. NOTE: IN CASC OF A REACTOR BUILDING EVACUATION ALARM, THE REPO2 TING REQUIREMENTS IN 4.4.3 ABOVE APPLY. I l l e y,w-.w,-ww.--,.,--e:- . , r#+. ,3-> - - _ - - , - - -- e -
RP/0/B/1000/09
'i ENCLOSURE 4.S e
DUKE POWER COMPANY
' OCONEE NUCLEAR STATION ,
, SITE ASSEMBLY LOCATIONS -
DUKE OCONEE NUCLEAR STATION PERSONNEL Section Assembly Point Manager's Group: Station Manager / Superintendents: Respective Offices l and Assigned Clerks . Station Services: Administrative Services Administrative Offices Training / Safety Training Office Contract Services Contract Services' Offices Maintenance: I&E Engineers I&E~ Engineers' Offices I&E Shifts A,B,C,D,E (On-Duty) Operational Supporc Center I&E Supervisors & Technicians i L - I&E Shops Turbine Building - Mech. Maintenance Shifts A,B,C,D,E Operational Support Center (On-Duty) Mechanical Maintenance Supervisors
& Technicians -
Maintenance Shop Mechanical Maintenance Engineers Mechanical Maintenance Engineers' Offices Planning & Scheduling Planning & Scheduling Offices Materials Materials Offices Maintenance Mgt. Support Maintenance Mgt. Support Offices Operations: All
- Control Rooms / Operating Engineers' Offices Integrated Scheduling: All Integrated Scheduling Offices O
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RP/0/B/1000/09 ' ENCLOSURE 4.S i
~, Technical Services:
Projects' Projects Offices Performance (All) . . Performance Engineer's Office - , Health Physics: Projects and Training Station Health Physicist's Office Support Functions Station Health Physicist's Office Surveillance and Control ~ Station Health Physicist's Office HP Shift Personnel (A,B,C,D,E) Operational Support Center (On-Duty) Chemistry: Staff Chemists Station Chemist's Office Radwaste Radwaste Coordinator's Office
- Power Chemistry Station Chemist's Office Chemistry Shift Personnel '
Operational Support Center (On-Duty A,B ,C,D,E) Environmental Chemistry Environmental Offices Radwaste Startup Team Radwaste Startup Office Compliance Compliance Engineer's Office Quality Assurance: All - Quality Assurance Offices Training Services: All Personnel at Training Center Oconee Training Center Oconee Safety Review Group: All Compliance Office DUKE NON-OCONEE NUCLEAR STATION PERSONNEL (Permanently Badged Personnel) Section Assembly Point Station Services: Administration Offices Operations: Operating Engineers' Offices Chemistry: Station Chemist's Office Health Physics: Station Health Physicist's Office SMS: SMS Offices Station Support Division: SSD' Offices Keowee: Keowee Hydro Station Visitors' Center: Visitor Center Office Quality Assurance: QA. Offices i
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.. ENCLOSURE 4.5
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- DUKE NON-OCONEE NUCLEAR STATION PERSONNEL ,
Section Assembly Point -- Design Engineering- : '. Projects Office Maintenance: Service Building Mezzanine (I&E, Mechanical Maintenance,
. or. Planning & Scheduling Offices)
Sub. Station Maintenance Sub. Station Maintenance Offices NON-DUKE OCONEE NUCLEAR STATION PERSONNEL K-Mac: Those Inside Security Canteen South End, Turbine Building Those Outside Security Admmistration Bldg. Canteen Babcock & Wilcox: All Resident Engineer's Office Globe Security: Personnel Access Portal Health Physics Vendors Station Health Physicist's
- Office Chem-Nuclear:
Radwaste Coordinator's Office
- NRC: All Compliance Office Wometco: All Administration Building Canteen VISITORS Inside Security with Escort i Outside Security Receptionist Lobby Receptionist Lobby OTHER PERSONNEL OUTSIDE PROTECTED AREA All personnel not identified above will report to the Receptionist Lobby.
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(6) TEMPORARY APPROVAL (IF NECESSARY):
, By: (SRO) Date:
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DUKE POWER COMPANY - OCONEE NUCLEAR STATION PROCEDURE FOR EMERGENCY EVACUATION OF STATION -PERSONNEL The purpose of this procedure is to set guidelines for dealing with an emergency evacuation should it become necessary for non-essential personnel ' to be evacuated during a radiological emergency. . Station Evacuation is activated only after personnel have been assembled through a Site Assembly. 1.0 SYMPTOMS Category 1 (Enclosure 4.1) 1)' External Radiation Level > 2 mrems in any one hour -
- 2) Airborne Radioactivity > 1 x mpe for an unrestricted area (10CFR20, Appendix B, Table II)
G Category 2 and 3 (Enclosure 4.1) l '. 1) External Radiation level > 2.5. mrem /hr 100 mrems/ week, or
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- 2) Airborne Radioactivity > equivalent amount inhaled for 40 hours /
week for 13 weeks at 1 mpc (10CFR20, Section 20.103 and Appendix B, Table 1) ' 2.0 LMMEDIATE ACTION 2.1 When it is determined that the emergency situation requires station evacuation, the Emergency Coordinator shall: , Date/ Initial Name 2.1.1 Determine evacuation route using meteorological information available and local area maps. 2.1.2 Determine offsite assembly location. Health Physics Surveillance and Control personnel should obtain the 4 keys to the appropriate school from Security. Keys are located in the Security-Controlled D e Box in the Unit #3 Shif t Supervisor's office. 2.1.3 Determine re-entry routes to be used for entry into
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the station.
' 2.1.4 Work with available group representatives; make a determination of station support staff required to safely operate the station and deal with an emergency.
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'i Date/ Initial Name 2.1.5 Prepare. instructions to be relayed to onsite personnel. ,
2.1.6 Direct Health Physics personnel to implement emergency surveillance and decontamination plans for personnel and vehicle evacuation. 2.1.7 Provide evacuation instructions' to supervisors onsite for distribution to station personnel. 2.1.8 Direct Station Security to patrol the station general areas to assure evacuation instructions are carried out. 3.0 SUBSEQUENT ACTION
, 3.1 Station Security will set up the evacuation exit points from the station.
3.2 The Appropriate County EOC will be made aware that the station is being evacuated so that law enforcement escort can be provided. Officers will be required to properly secure the school area so that processing may be carried out in an orderly manner. Supervisory
' personnel evacuated to the remote area will assist in maintaining order and control.
3.3 Health Physics will monitor and decontaminate personnel and vehicles in accordance with HP/0/B/1009/16, both onsite and offsite. 3.4 If personal vehicles cannot be used for evacuation, the Superintendent of Station Services shall arrange for bu i transportation through the Anderson Retail Office. See Emergency Telephone Directory located in TSC Emergency Procedures Cart. 3.5 Once transportation has been determined / secured, evacuation will take place. 4.0 ENCLOSURES 4.1 Categories of Personnel ' l 4.2 Emergency Evacuation Routes 9 9 t t* - v - ,- ys%.m- , ,,,y- * - - . = - ,- + - -
Z RP/0/B/1000/10 Enclosure 4.1 DUKE POWER COMPANY , OCONEE NUCLEAR STATION CATEGORIES OF PERSONNEL 4 i. CATEGORY I All members of the general public and 'other persons 'who are not . subject to occupational radiation exposure at Oconee Nuclear Station:
' Visitors - Wometco "A" Workers Keowee Hydro CATEGORY 2 -
d ' Various groups of personnel who are subject to occupational radiation exposure at the station and are considered non-essential to the operation of the station-during a classified emergency situation. SMS Chem-Nuclear SSD . :
' Vendors (Other than HP) i QA Duke Personnel (Other than ONS)
B&W - All others (not listed in 3 below)'
- Design Engineering Oconee Training Center .
s. CATEGORY 3 l 2 Personnel identified as the Emergency Response Organization. Operations Globe Security i Health Physics Resident B&W Engineer. Health Physics Vendors Station Services Compliance Maintenance i ? NRC Resident Inspector Chemistry ' K-Mac Performance Transmissions Visitor's Center Projects I e } k i a 0 nn r-- 4 >.. r, n.. , ,.c.-., . - . , , - , . ,,,,e4 - ,w., , , , , . _.n.. g . ., , . -,_.e.
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DUKE POWER COMPANY (1) ID No: RP/0/3/1000/11 PROCEDURE PREPARATION Change (s) O ts PROCESS RECORD 0 Incorporated (2) STATION: OCONEE . (3) PROCEDURE TITLE: PLANNED EMERGENCY EXPOSURE A (4) PREPARED BY:, h DATE: // / / (5) REVIEWED BY: [ DATE: // 9 8F Cross-Disciplinary Review By: b$ N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: l By: 'Date: (7) APPROVED BY: Date: ll 19 l b (8) MISCELLANEOUS: " Revtewed/ Approved By: !,1 u w Date: //- 2 /-T Y Reviewed / Approved By: Ef Date: r ///f,y/dPA
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. OCONEE NUCLEAR STATION
' PLANNED EMERGENCY EXPOSURE 1.0. SYMPTOMS .
1.1 Situation which is immediately hazardous to life and property ' ~ 1.2 Situation where it is necessary to save lihes or prevent loss of lives . . . . . 1.2.1 Action (s). required to strictly save lives. 1.2.2 Actions required to prevent loss of equipment which would
" provide mitigation of and/or recovery from the accident.
2.0 IMMEDIATE ACTIONS 2.1 Select individuals by the following conditions: 7 2.1.1 Personnel should be voluntee$s.
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2.1.2 Personnel should be broadly familiar with the potential
>t consequences of such exposure.
2.1.3 Women capable of reproduction should not take part in these actions. 2.1.4 All factors being equal, select volunteers above the age of 45 and those who normally encounter little exposure, t 2.2 Obtain the verbal or written approval of the Emergency Coordinator to extend dose limits for planned emergency exposures. Complete ' either Enclosure 4.1 or Enclosure 4.2 depending on the symptoms. 2.3 Exposure should be maintained ALARA. 3.0 SUBSEQUENT ACTIONS 3.1 Exposures above 10CFR20 limits may require an occupational penalty. 3.2 Exposures within the guidelines of Enclosure 4.2 may require a medical decision as to whether the individual may continue in i radiological work and should be limited to a once in a lifetime dose. '.. 3.3 Planned emergency doses shall be recorded, estimated il necessary, and included in the individ'ual's exposure history record. k
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- 2-3.4 Reports of planned emergency exposure shall be reported as per Oconee Nuclear Station reporting requirements. '
4.0 ENCLOSURES
- i 4.1 Exposures Hazardous to Life and Property 4.2 Exposures Necessary to Save Lives or Prevent Loss of Lives e
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Enclostire 4.2 , RP/0/B/1000/11 EXPOSURES HAZARDOUS TO SAVE LIVES OR PREVENT LOSS OF LIVES i I. Request for Planned Enier Exposu re _ _ _ __ ___..__ _ __ ___ _ _ __.--______gency II Approval for Planned Emer .------___-__---..__----.
...._---__ ------_--_.-______..-_ . ..__...-_----...._--_------...gency Expos u re j
TO: Station llealth Physicist Date: _ Request No.:
. FROM:
(Operational Support Center) Permission is hereby granted for the individual (s) listed below to exceed the guidelineis set forth in the System Planned voluntary maximum exposures are required to ifealth Physics Manual but within the guidelines of the remedy the following situation where it is necessary Crisis Management Plan
- as statect on this form. .
to save lives or loss of lives. (NOTE: Those actions , necessary to directly save lives and equipment that if APPROVAL REQUIRED BY: ' i lost would prevent mitigation of and/or recovery from the accident) NOTIFIED: Emergency Coordinator ;
- t Recovery Manager i
, i ! Date: Time: ! Date: ! Time: ! Phone Call In Person ! l Whole Body Phone Call Skin of Whole Body or Thyroid ISO25rems - 75**Rems
- Extremities '
375 rems , CDose to this limit must be approved by Emergency Coordinator .; l H.P. . Dsdge Name !, Number Age Work Group Signature Dose > Receive'd .
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RP/0/B/1000/11 Enclosure 4.1
- f EXPOSURES IIAZARDOUS TO LIFE AND PROPERTY
- 1. Request for Planned Emergency Exposure i
--------------------------------------------------------------------- Approval for Planned Emergency Expos u re II.
TO: Station IIealth Physicist Date: Request No.: ( 4 FHOM: (Operational Support Center) Permission is hereby granted for the individual (s) listed ' below to exceed the guidelines set forth*in the System Planned voluntary maximum exposures are required to llealth Physics Manual but within the guidelines of the
' remedy the following situation immediately hazardous Crisis Management Plan
- as stated on this form. '
to life and property: '
- APPROVAL REQUIRBD BY:
i NOTIFIED:
. Emergency Coordinator .
Recovery Manager Date: Time: Date: Time: , Phone Call ___In Person Whole Body 5 - 25* Ikus Phone Call " Skin of Whole Body or Thyroid 30 -125* Iksns Extremities 'l5 rems t, i CDose to this limit must be approved by Emergency Coordinator. ! II . P. B dge Name Age
- Dose Number Work Group Signature Received ,
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DUKE POWER COMPANY
- p. o. sox use OCONEE NUCLEAR STATION SENECA.S.C.29678 esa s! !
December 14, 1984 INTRASTATION LETTER OCONEE NUCLEAR STATION s TO: - 6// CONTROL COPY NO.
SUBJECT:
OCONEE NUCLEAR STATION Emergency Implementing Procedures Manual Revision No. 84-4 Please make Oconee Nuclearthe following Station changes Emergency to the Volume B, Implementing Procedures Manual Plan: , REMOVE ESgT '
- 1. Title Page, Rev. 84-3
- 2. 1.- Title Page, Rev. 84-4 Table of Contents, (1-3) 2. Table of contents, (1-2)
- 3.
- Emergency Telephone Numbers 3. #
(Tab & Proc.) 4
*RP/0/B/1000/01
- 5. *RP/0/B/1000/02 (Tab & Proc.)
(Tab & Proc.) 4. #
- 6. 5. #
*RP/0/B/1000/03 (Tab & Proc.)
- 7. *RP/0/B/1000/04 (Tab & Proc.) 6. #
- 8. 7. #
9.
*RP/0/B/1000/05 (Tab & Proc.) 8. #
*RP/0/B/1000/06 (Tab & Proc.) 9. #
- 10. AP/0/B/1000/07 (Tab Only)
- 11. AP/0/B/1000/08 (Tab & Proc.) 10. AP/0/B/1000/07 (New Tab) 11.
12. 13.
*RP/0/B/1000/09 (Tab & Proc.) 12. #
- 14. *-- *RP/0/B/1000/10 (Tab & Proc.) 13. #
14
- 15. PT/0/B/2000/04 (Tab & Proc.) 15. #RP/0/B/1000/11 - see Volume C which has been deleted
- 16. CP/1/A/2002/04A (Tab & Proc.) 16.
which has been deleted
- 17. CP/2/A/2002/04A (Tab & Proc.) 17, which has been deleted 18.
CP/3/A/2002/04A (Tab & Proc.) 18. which has been deleted ,
- 19. CP/1/A/2002/04B .(Tab & Proc.) 19. -
~~
which has been deleted i. J 20. CP/2/A/2002/04B (Tab & Proc.) 20. . l ll 3 which has been deleted
<o a l0! 21. CP/3/A/2002/04B (Tab & Proc.) 21.
' which has been deleted -
g t a
/ :
- 22. CP/1/A/2002/04C (Tab only) 22.
- 23. CP/2/A/2002/04C (Tab & Proc.) CP/1/A/2002/04C (New Tab)
E$ ! 23.
- 24. CP/2/A/2002/04C (Tab & Proc.)
lO '! 25. CP/3/A/2002/04C (Tab & Proc.) CP/'.&2/A/2002/05 (Tab only) 24. CP/3/A/2002/04C (Tab & Proc.)
- 26. CP/3/A/2002/05 (Tab only) 25. CP/1&2/2002/05 (New Tab) t l 27. 26. CP/3/A/2002/05 (New Tab)
CI'. CP/0/B/2003/02 (Tab & Proc.) 27. --- which has been deleted
- 23. - - -
- 29. 28.
CP/0/B/2004/02E (Tab only) CP/0/B/2003/023 (New Tab)
- 30. 29.
CP/0/P/2004/03C (Tab Only) CP/0/B/2004/02E (New Tab)
- 31. 30. CP/0/B/2004/03C (New Tab)
CP/0/B/2005/02D (Tab only)
- 32. CP/0/B/4003/01 (Tab only) 31. CP/0/B/2005/02D (New Tab)
- 33. 32. CP/0/B/4003/01 (New Tab)
CP/0/A/4003/02 (Tab Only)
- 33. CP/0/B/4003/02 (New Tab)
" ~ , . a- .
Prga 2 of 2. J. T. McIntosh's, letter dated .
- 34. HP/0/B/1009/09 (Tab only)
~
12/1 /84 8' 34 ,
- 35. HP/0/B/1009/10 (Tab only) 35. HP/0/B/1009/09 (New Tab) !~
- 36. HP/0/B/1009/11 (Tab only) -36 HP/0/B/1009/10 (New Tab)
- 37. HP/0/B/1009/12 (Tab Only)
- 38. 37. HP/0/B/1009/11 (New Tab) !
HP/0/3/1009/13 (Tab & Proc.) 38. -HP/0/B/1009/12 (New Tab) ! which has been deleted '
- 39. HP/0/3/1009/14_ (Tab only)
, 40. HP/0/3/1009/15 (Tab Only) 39. HP/0/B/1009/14 (New Tab)
- 41. HP/0/3/1009/16 (Tab only) 40. HP/0/B/1009/15 (New Tab)
- 42. HP/1/A/1009/17 (Tab Only) 41. HP/0/3/1009/16 (New Tab)
- 43. HP/2/A/1009/17 (Tab only) 42. HP/1/A/1009/17 (New Tab)
- 44. HP/3/A/1009/17.(Tab Only) 43. HP/2/A/1009/17 (New Tab)
- 45. IP/0/3/1601/13 (Tab & Proc.) 44. HP/3/A/1009/17 (New Tab
- 45. -
which has been deleted
- 46. -
- 47. -
- 46. Chemistry Manual 5.1(New Tab) before Prc
- 47. Compliance Manual 6.1 (New Tab) lefore
- 48. - Proc. --
48, Health Physics Manual 11.2 (New Tab) before Proc. 11.1 49.
- 50. Maintenance Directive V.D & Tab 49.
- 51. -
- 50. Maintenance Directive V.D & Tab
- 51. Performance Man. 4.5 (New Tab) before Prc Project Services Manual 6.1 (New Tab)
- 52. before proc.
- 53. -Seption Services' Procedure 52.
- 53. Station Services (Tab & Proc.)
OMP 1-7 (Tab & Proc.) which is new NOTE:
*These are being deleted from VOLUME B.
#These will be issued in VOLUE C.
Also for your find attached update and upkeep. an additional VOLUME C of the Emergency Impl ementing Procedures that you have received VOLUME C below. Acknowledge that revision has been ma 1984. Return it to Document Control by December 21 g T. McIntosh Superintendent i Station Services ' ,
.r .
/1ss Attachments & VOLUME C CCONEE NUCLEAR STATION 4 DIERGENCY IMPLEMENTING PROCEDURES MANUAL Revision No. 84-4 (December,1984)
CONTROL COPY NO. . S b i SIGNATURE L6 CATION DATE p, ..e -
, _ . - . _ - . y
an mar,, UNITED STATES
! o,t. NUCLEAR REGULATORY COMMISSION
,I wAssiNovow, p. c. 20sss f
% 5 (
,#a February 11, 198,5 I
i I 50-269/270/287 Oconee i MEMORANDUM FOR: Chief, Document Management Branch, TIDC I FROM: Director, Division of Rules and Records, ADM ;.
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be m3de publicl available.
/
. M. Felton, Director ivision of Rules and Recor Office of Administration k
Attachment:
As stated I T l
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