ML20203J728
| ML20203J728 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/02/1986 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20203J724 | List: |
| References | |
| PROC-860602-02, NUDOCS 8608050400 | |
| Download: ML20203J728 (103) | |
Text
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Form 34731 (3 84) (1) 10 No 0P/0/A/6200/21 DUKE POWEP COMPANY Change (s) O to PROCEDURE PROCESS RECORD 4 incorporated PREPARATION Revisiott 6 (2) STATION CATAWBA (3) PROCEDURE TITLE OPERATING PROCEDURE FOR THE POST ACCID Mf LIOUID SA!iPLIUG SYSTEMc (4) PREPARED BY . & ' 1 DATE ~2b~Ob .
(5) REVIEWED BY DATE 38~N Cross Disciplinary Review By v
Y v
(6) TEMPORARY APPROVAL (if Necessary)
By (SRO) Date By -
Date (7) APP IEY . e/ '
DATE (8) MISCELLANEOUS
(- ( //
I . Reviewed / Approved By Date Reviewed / Approved By Date COMPLETION (9) DATE(S) PERFORMED (10) PROCEDURE COMPLETION VERIFICATION O Yes C N/A Check lists and/or blanks property initialed, signed, dated or filled in N/A or N/R, as appropriate?
O Yes C N/A Listed enclosures attached?
O Yes C N/A Data sheets attached, completed, dated and signed?
O Yes C N/A Charts, graphs, etc. attached and properly dated, identified and marked?
O Yes C N/A Acceptance criteria met?
VERIFIED BY DATE (11) PROCEDURE COMPLETION APPROVED DATE (12) REMARKS e
8608050400 860716 PDR ADOCK 05000413 F PDR
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4 Form 18855 (3-80) s DUKE POWER COMPANY ,
ALARA EVALUATION CHECKLIST (1) Station CATAWBA Unit: 1 2 3 Other: shared (2) Checklist Applicable to: OP/0/A/6200/21 (3) ALARA Evaluation Check those items below which were considered applicable during the preparation and review of this document.
Flushing and draining were used to minimize source - strength and con-tamination levels prior to performing an operation.
Permanent and/or movable shielding was specified for reduction of levels.
Use of permanent or temporary local exhaust ventilation systems was used for control of airborne contamination.
Operation was designed co be completed with the least practicable time spent in the radiation field.
Appropriate tools and equipment were specified for the operation to be performed.
The operation was designed considering the minimum number of people necessary for safe job completion.
Remote handling equipment and other special tools were specified to reduce external dose.
Contamination - control techniques were specified.
The operation was designed to be conducted in creas of as low an exposure as practicable.
Additional ALARA considerations were:
ALARA Principles were not considered since the procedure did not involve work in a radiation area.
(5) Prepared by: , -u Date 'E O~ %
(6) Reviewed by: -
[ z:rs- . Date IMA -h[
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1 1
OP/0/A/6100/2. .
DUKE PoleT.R COMPANY ;
CATAWBA NUCLEAR STATION l OPERATING PROCEDURE FOR THE POST ACCIDENT LIQUID SAMPLING SYSTEMS 1.0 PURPOSE The purpose of the Post Accident Liquid Sampling System is to provide a method for promptly obtaining reactor coolant samples under a nuclear reactor accident condition.
Samples acquired during accident conditions (normal sample points are not useable due to high radiation conditions) will aid in the evaluation of information related to:
- 1) The extent of core damage which has occurred.
- 2) Types and quantities of fission products released to containment liquid.
- 3) Reactor Coolant Chemistry and Radiochemistry.
2.0 LIMITS AND PRECAUTIONS i
p 2.1 In an accident situation the decision to collect a post-accident
\, . sample will originate from the Technical Support Center. The management involved in this decision should take two factors into consideration in making this decision:
(a) Has the situation stabilized to a degree so as to minimize the risk to individuals involved in the sampling?
(b) From the present information available, has the system stabilized to a' degree that a representative sample may be obtained?
2.2 The PALS panel should only be used under the following circumstances:
(a) Caution: 1/2 EMF 48 must have' flow for readings to be valid.
The Reactor Coolant System (NC) Gross Specific Activity is expected to be or is known to be greater than 200 pCi/ml.
, This corresponds to a reading on 1/2 EMF 48 of equal to or greater than 1.64 x 105 counts per minute. (Correlation factor from BP/0/B/1000/10 is 1.22 x 10 3 (pCi/ml)/(CPM))
(b) Primary Systems Sample Sinks IA/2A and IB/2B are inaccessible due to the radiation levels ~ ~
or for other identified reasons.
- _ _ - . ~ _ . _ _ , _ _ _ - _ _ _ _ _ . , - -
OP/0/A/6200/21 Page 2 of 16 (c) The station L:hemis or his designee nas requested that the r' PALS panel be put in service.
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(d) The PALS panel is being run for sonthly operational verification, maintenance, or training purposes.
(e) When use of the normal Primary Sample systems will create a Radiation Exposure problem in the NM Lab.
2.3 The undiluted sample volume is 5.2 al (for Unit 1) and 4.4 (for Unit 2) and the final dilution volume shall be controlled between 250-3500 al.
2.4 Health Physics personnel must perform continuous radiation monitoring during sampling at the liquid sample or control panel.
During an accident situation, Health Physics personnel from the OSC must monitor all personnel entering the Auxiliary Building.
- 2.5 When handling radioactive samples, good laboratory practices are essential to prevent radioactive contamination of personnel equipment, and physical structures. Reference applicable SRWP(s)
, and RWP(s).
2.6 Individuals that have been trained on this procedure are qualified to use this procedure. Individuals shall be trained at a minimum frequency of (6) months (if indicated by testing).
2.7 Due to the nature of this procedure, a Working Copy shall be used to ensure compliance.
2.8 Do not leave the selector knob in " Grab Sample", Position 4
- longer than is required to complete all necessary steps of that
! position.
l 3.0 PANEL PREPARATION 3.1 Initial Conditions 3.1.1 In order to expedite the process, the Primary Supervisor or his designee should send two Chemistry Technicians to collect the sample.
The technicians should be chosen taking into consideration the following:
(a) Being qualified on the PALS procedure (b) Being respiratory qualified (c) Age (d) Accumulated Exposure (e) Sex (f) Physical Strength _ .
Their responsibilities are outlined below:
OP/0/A/6200/21 Page 3 of 16 Teclin'icish #1 ' - '
r (a) Completes the Initial Conditions Checklist Encionure 8.1 from OP/0/A/6200/21 at the TSC and returns the checklist to Technician #2.
(b) Informs Health Physics at the OSC that he/she will be traveling to the Hot Lab.
(c) Dresses out as necessary.
(d) Travels to the Hot Lab and prepares for the analyses.
(e) Transports samples from the NM Lab to the Hot Lab, if necessary.
(f) Analyzes the samples.
(g) Reports results by phone to the Station Chemist at the TSC and returns to the OSC.
(h) Transports the completed data sheet to Station Chemist at the TSC.
Technician #2 (a) Obtains the PAIS panel keys. (Location: Secondary Supervisor's Office Key Box or Cold Lab Key Box)
(b) Dresses out as directed by Health Physics at the OSC.
(c) Health Physics plans out a path to be taken to the NH Lab, Hot Lab, Count Room and to exit the Auxiliary Building.
(d) Travels to the NN Lab and uses the PALS to collect liquid and gas samples.
(s (e) Transports the samples to the Hot Lab.
i (f) Assists in the analysis of samples, if necessary.
l (3) Reports results by phone to the Station Chemist at the TSC and returns to the OSC.
3.1.2 (Technician #1) - Complete the Initial Conditions Checklist (Enclosure 8.1) at the TSC and return it to Technician #2 at the OSC.
3.1.3 (Technician #1) - Inform Health Physics at the OSC of your plans to travel to the Hot Lab. Inform Health Physics that travels to the outside east backside of the Auxiliary Building may be required in order to calibrate the Gas Chromatograph. Also, inform them that you may transport the sample from the NM Lab to the Hot Lab. Dress out as required by Health Physics. The Hot Lab may be locked so bring the key.
3.1.4 (Technician #1) - In the Hot Lab, prepare for the sample analyses required in Section 7.0 of OP/0/A/6200/21.
3.1.5 (Technician #2) - Obtain the PALS panel keys from the Secondary Supervisor's office Key Box or the Cold Lab key box. _ ,
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OP/0/A/6200/21 Page 4 of 16 s.t.6 (1=cnnician ez) - heport to the OSC and infons. Health 3
Physics of plans to obtain a post-accident liquid sample. !
Dress out as required by Health Physics. Health Physics !
personnel will decide the route to be taken to the PALS panel, the route to carry sample to the Hot Lab and Count '
Room, and the exit route back to the OSC. They will also address stay times (1-2 hours at the PALS Control Panel) and protective radiological dress and equipment. A Health Physics technician must be with any Chemistry personnel entering the Auxiliary Building at all times. R====her:
The buddy system is in effect.
3.1.7 (Technician #2) - Travel to the NM lab with Health Physics coverage to collect a sample using the PALS panel.
Remember to bring the required equipment listed on Enclosure 8.1, Part III.
3.2 Control Panel Preparation (Technician #2 - 543' Elev. NM Sample Room) i 3.2.1 Close the following valves: Unit 1 Unit 2 (Omit during periodic testing and training)
NC Hot Les Sepl Edr to Radiation INM29 2NH29 Monitor '
. , NC Hot Leg Sepl HX 1A Outlet INM264 2NM264 NC Hot Leg Sep1 EX 1B Outlet INM278 2NM278 ND Sep1 EX Outlet INH 265 2NM265 t
3.2.2 Obtain Operations permission to open Unit 1 Unit 2
, (or have Operations open) the ,
l following Operations valves:
1 Post Accident Liquid Sample Panel Ex Inlet IKCA8 2KCA8 l
Post Accident Liquid Sample Panel Ex Outlet IKCA10 2KCA10 .
For Unit 2, the following additional valves have to be OPENED: For A Train KC-2KCD03 and 2KCD05, For Train B l KC-2KCD04 and 2KCD06.
3.2.3 OPEN INM462 (2NM462), PASP Demerator Tank Inlet.
3.2.3.1 Fill a 50 ml Nalgene sample bottle labeled
" Dilution Water Sample" by OPENING valve l INH 456, (2NM456). When bottle .is full CLOSE IKM456, (2NM456).
3.2.3.2 En.ure liquid and gas sample bombs are attached to the PALS panel.
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OP/0/A/6200/21 Page 5 of 16
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3.2.4 Call the Control Roor and obtain the official time on the y Control Room clocks. Set the clock near the PALS panel to c., the correct time.
3.2.5 Contact the Control Room and have them open the appropriate valve (s) listed below to obtain the desired sample. Reference Enclosure 8.1, Part II(b).
(May be omitted during periodic testing)
NC Hot Les A Unit 1 Unit 2 Hot Leg Sep1 Edr Cont. Isol. INM26B 2NM26B Hot Les A Sepl Cont. Isol. INM22A 2NM22A NC Hot Les C Hot Leg Sep1 Edr Cont. Isol INM26B 2NM26B Hot Les C Sepl Cont. Isol. INM25A 2NM25A ND Pump 1A Discharte NL Pump 1A Disch Sapl Line Isol. INM39 2NH39 ND Pump IB Discharme ND Pump 1B Disch Sep1 Line Isol. INH 40 2NM40
( -) . 3.2.6 Turn the position selector knob to " RESET" position.
Place the key in the keylock power switch and turn to the right. (" Sample Position"). Press " Reset" button.
3.2.7 Place the toggle switch for the dilution water flow totalizer to "0N".
3.2.8 Place the toggle switch for the radiation monitor to "0N". Turn the scale switch to " BAT" to check the battery. The needle should travel to full scale. Turn the scale switch to "mR/ hour". The " Rem / hour" scale may be used if readings are off the scale. Always rely on Health Physics surveys to determine access to the sample l
panels.
3.2.9 Push in the pH probe " Standardize" knob.
3.2.10 Select the system to be sampled with the system selector -
RX COOLANT (refers to NC Hot Legs), RX SUMP (refers to ND Pump Discharge).
3.2.11 Verify that the pH 6.86 buffer solution has been changed within the last 30 days by referencing Enclosure 6.8 from OP/0/A/6200/11. This enclosure is located in a notebook t
in the PALS drawer.
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OP/0/A/6200/21 Page 6 of 16 0 . L . ~.2 Ocnnect the. PALS.nitrog:c :311sd:: ic tt rALS '_y
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connedti'ng thi quihk ' disconnect to the Na supply line.
s Open the cylinder valve and set the pressure regulator to 110 psig. (Always connect quick connect before OPENING the Na cylinder valve).
3.2.13 Flush (Position 6) 3.2.13.1 Turn the SELECTOR KNOB To " Flush", Position 6.
3.2.13.2 Press the " SELECTION P0hT.R-ACTIVATE" button.
3.2.13.3 Press the " FLUSH STEP" button momentarily and wait 1 minute. The first flush light should be lit. (Gas Tank).
3.2.13.4 Press the " FLUSH STEP" button momentarily and wait 2 minutes. Second flush light should be lit. (Probes).
3.2.13.5 Press the " FLUSH STEP" button momentarily and wait 2 minutes. Third flush light should be lit. (Dilution Tank).
3.2.13.6 Press the " FLUSH STEP" button momentarily and
<- wait I minute. Fourth flush light should be
( iit. (Liquid Tank).
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3.2.13.7 Press the " FLUSH STEP" button momentarily.
This terminates the flushing cycles and the "CoffPLETE" light turns on.
3.2.13.8 Turn the selector knob to " DRAIN", Position 7.
3.2.14 Drain (Position 7) .
3.2.14.1 Press the " SELECTION POWER-ACTIVATE" button.
3.2.14.2 Press the " DRAIN STEP" button momentarily and
! wait 4 minutes. The first drain light should be lit. (Dilution Tank).
3.2.14.3 Press the " DRAIN STEP" button momentarily and wait I minute. The second drain light should be lit. (Gas Line).
3.2.14.4 Press the " DRAIN STEP" button momentarily and wait 1 minute. Third flush light should be 1.4 t . (Gas Tank).
j 3.2.14.5 Press the " DRAIN STEP" button momentarily and j wait I minute. Fourth flush light should be
( lit. (Probe refill and system vent).
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OP/0/A/6200/21 Page 7 of 16 3.2.14.6 Press toe ' 0Mid 8TE*" button m"o 'sentarily.'
This cerninetes the draining cycles and the
" COMPLETE" light is illuminated.
4.0 PANEL OPERATION (Technician #2) 4.1 Initial Conditions 4.1.1 Section 3.0 is complete with the Enclosure 8.1 signed off.
4.2 Panel Prep (Position 1) 4.2.1 Turn the selector knob to the " PANEL PREP" position.
4.2.2 Press the " SELECTOR P0iv7.R - ACTIVATE" button.
4.2.3 Press the " PURGE" button, hold for 30 seconds and release.
4.2.4 Press the " DRAIN" button and hold for 30 seconds then release.
4.2.5 Press the " CALIBRATE" button and hold until the pH meter stabilizes.
f 4.2.6 Adjust the pH meter to the known pH of the standard.
l.
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4.2.7 Press the " PURGE" button, hold for 30 seconds and then release.
4.2.8 Press the " FLUSH" button and hold until the pH meter stabilizes (1 to 3 minutes) (pH of demineralized water) then release.
4.2.9 Press the " PURGE" button, hold for 30 seconds and release.
4.2.10 Press the " DRAIN" button, hold for 30 seconds and release.
j 4.2.11 Record the radiation monitor reading on Enclosure 3.2.
(Background) 4.2.12 Turn the selector knob to " SAMPLE", Position 2.
4.3 Sample (Position 2) 4.3.1 Press the " SELECTION POWER - ACTIVATE" button. Record the
- ' Time Sample Purged Started' on Enclosure 8.2. Verify a i
flow rate of 0.3-1 GPM on INMP5430 (2NMP5430) Sample Purge Flow Indicator. (For Periodic Testing, purge for ten minutes (NC), fifteen minutes (ND) before proceeding.)
Refer to Enclosure 8.7 Step 6 for proper purge times in an accident situation.
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OP/0/A/6200/21 Page 8 of 16 ,
4.3.2 If TC1 goes above Su*t., trrn tne relector knob to ' Reset."
i and press the rReset" oucton. Call the Primary Supervisor or his designee. At the completion of the purge time, record the radiation reading and TC1 temperature on Enclosure 8.2.
i
' 4.3.3 Press the " PRESSURIZE" button momentarily. When the pressure stabilizes (read on (INMP5240 (2NMP5240)) the reading on Enclosure 8.2.
4.3.4 Press the " TRAP" button momentarily. Record the time as the " Sample Trap Time" on Enclosure 8.2.
i 4.3.5 Turn the selector knob to "DEPRESSURIZATION AND GAS STRIPPING", Position 3.
4.4 Depressurization and Gas Stripping (Position 3) 4.4.1 Verify that the vacuum gauge on the control panel shows at
+
least -2512 inches mercury (INMPS190 (2NMPS190)).
4.4.2 Press the " SELECTION POWER-ACTIVATE" button. Wait at least 60 seconds and then verify the Incoming Sample Pressure gauge reads less than 400 psig pressure (INMP5240 (2NMP5240)).
i ,
4 ( 4.4.3 Press the " GAS STRIPPING START" button somentarily beneath the flow totalizer and monitor the vacuum gauge. Press the " GAS STRIPPING STOP" button momentarily when the vacuum gauge needle reads + 15 i 1 inch mercury (for Unit 1), +10 j i 1 inch mercury (For Unit 2). If i 1 inch is not achieved, a new stripped gas sample will need to be taken f (i.e.) start from Section 4.3.
- 4.4.4 Turn the selector knob to ." GRAB SAMPLE", Position 4.
1 4.3 Grab Sample (Position 4) j< 4.5.1 Press the " SELECTION POWER-ACTIVATE" button.
, 4.5.2 Press the " GRAB ML" button momentarily. Wait I minute.
1 4.5.3 Set the dilution water FLOW TOTALIZER to 02500 (for testing).
In an accident situation, refer to the Station Chemist's Reccamended dilution factor, Enclosure 8.1, Part IV.
Press the " RESET" button on the flow totalizer. Press the
" START" button and let the dilution continue to completion.
l Record the flow totalizer setting on Enclosure 8.2.
! 4.5.4 Press the " MIXING" button and hold for 10 seconds.
4 4.5.5 Press the " GRAB SAMPLE-pH" button, momentarily. Allow the
! ( -. seter to stabilize.
4.5.6 Record the pH reading on Enclosure 8.2.
i i
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- OP/0/A/6200/21 Pase 9 of 16 4.5.7 Press the "CAS SAMPLE - TRAP OPEN" bntron wwnt.-rily. .
f Wait 10 seconds.
4.5.8 Press the " GAS SAMPLE - TRAP CLOSE" button momentarily.
4.5.9 Turn the selector knob to position 5 " LIQUID SAMPIZ".
4.6 Liquid Sample (Position 5) 4.6.1 Press the " SELECTION POWER-ACTIVATE" button.
4.6.2 Hold the " LIQUID SAMPLE-TRAP OPEN" button for 1013 seconds.
4.6.3 Immedistely af ter 1013 seconds, press the " LIQUID SAMPLE-TRAP CLOSE" button momentarily.
4.6.4 Turn the selector knob to " FLUSH", Position 6.
4 4.7 Flush (Position 6) 4.7.1 Press the " SELECTION POWER-ACTIVATE" button.
i 4.7.2 Press the " FLUSH STEP" button momentarily and wait 1
! minute. The first' flush light should be lit.
1 ,
(Gas Tank)
,f. 4.7.3 Press the " FLUSH STEP" button momentarily and wait for
\
2 minutes. Second flush light should be lit. (Probes) 4.7.4 Press the " FLUSH STEP" button momentarily and wait 4 minutes. Third flush light should be lit. (Dilution Tank).
4.7.5 Press the " FLUSH STEP" button momentarily and wait 1 minute. Fourth flush light should be lit. (Liquid Tank).
4.7.6 Press the " FLUSH STEP" button momentarily. This
! terminates the flushing cycles and the " COMPLETE" light j
turns on.
4.7.7 Turn the selector knob to " DRAIN", Position 7.
l 4.8 Drain (Position 7) 4.8.1 Press the " SELECTION POWER-ACTIVATE" button.
4.8.2 Press the " DRAIN STEP" button momentarily and wait 4 minutes. First drain light should be lit. (Dilution Tank) 4.8.3 Press the " DRAIN STEP" button momentarily and wait for 1 minute. The second drain light should be lit. (Cas Line) f 4.8.4 Press the " DRAIN STEP" button momentarily and wait 1 l
(' minute. The third drain light should be lit. (Gas Tank).
.,__-........_--._.,,.,l._ _ . . _ ._______ _ ~ -. _.__..~..._ _ ._ _ _ _ _ . _ - - , _ . - - _
OP/0/A/6200/21 Page 10 of 16 4.9.5 Press the " DRAIN STEF" custon somentsrily and wait I f minute. The fourth drain light should be lit. (Probe -
refill and system vent). .
4.8.6 Press the " DRAIN STEP" button momentarily. This terminates the draining cycles and the " COMPLETE" light is illuminated.
4.9 Reset 4.9.1 Turn the selector knob to " RESET" and press the " RESET" button.
4.9.2 Contact the Control Room and have them close the valves opened in Sections 3.2.2 and 3.2.5. (May be omitted during Periodic Testing.)
4.9.3 If the "PLHP SUMP" light is lit, it indicates the sump has water in it. Turn the SYSTEM POWER EEY to the left to operate the sump pump. The " PUMP ON" light will light and remain on until the pump has stopped.
4.9.4 After the " PUMP COMPLETE" light turns on, indicating that the pump has stopped, turn the SYSTEM POWER EEY to the right to re-energize the PALS.
[ i 4.9.5 Record the radiation level on Enclosure 8.2. If the field at the panel is greater than 3 Rem /hr. (3000 mR/hr.), go to Section 5.0.
l 4.9.6 If this is the last sample to be collected this trip, I
proceed to Section 4.10, Sample Panel Shutdown. If other samples are to be collected this trip proceed to Section 6.0, Sample Retrieval.
4.10 Sample Panel Shutdown 4.10.1 Turn the SYSTEM POWER EEY to the vertical off position and turn the position selector knob to " RESET".
4.10.2 Place the panel keys in a plastic bag with Enclosure 8.1 (NC or ND Loop data). (Omit during periodic testing.)
4.10.3 Turn the toggle switch for the flow totalizer to "0IT".
4.10.4 Turn the toggle switch for the radiation monitor to "0FF".
i j 4.10.5 Pull out the pH probe standardize knob.
l 4.10.6 Close nitrogen cylinder valve and disconnect the quick
! disconnect.
4.10.7 Turn System Selector Knob to off.
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OP/0/A/6200/21 Page 11 of 16 4 4.10.8- Eeter 00000 on slow totalizer.
t 4.10.9 Proceed to Section 6.0, Sample Retrieva).
5.0 DECONTAMINATION 5.1 Repeat the panel Flush, Drain and Reset Modes: Section 4.6.4 through 4.9.3.
5.2 If the level is less than 3 Rem / hour, turn the SYSTEM POWER KEY to the vertical position and continue with Section 4.9.6. If however, the radiation level remains greater than 3 Rem / hour, contact the Station Chemist at the TSC for his recommendations.
6.0 SAMPLE RETRIEVAL 6.1 Initial Conditions 6.1.1 A gas and degassed liquid sample are in the gas and liquid samplers.
6.1.2 Health Physics personnel are providing continuous monitoring of the area.
6.2 Sampling 6.2.1 1
( Fill out remaining information on gas and liquid sample labels.
6.2.2 The " Sample Trap Time" and " Dilution Factor" may be found on Enclosure 8.2.
6.2.3 Take the completed labels and place each one on a plastic bag. Place another plastic bag inside of each of the two labeled plastic bags. These will be used later for double bagging the samples.
CAITIION: Do not approach the samplers on the sample panel until a Health Physics Technician has surveyed the area. Do not relay solely on the PAI,S panel's radiation monitor (INMMT5350/
2NMT5350) as indication of the radiation in the area. (0mit during periodic testing).
6.2.4 Approach the samplers located on the sides of the sample panel. If possible, have the Health Physics Technician take on contact readings on each sample vessel. (Omit during periodic testing). Record these readings on labels on sample bags.
6.2.5 Detach the quick-disconnects on each sample vessel. Place the samplers in the labeled plastic bags. Seal tightly.
OP/0/A/6200/22 Page 12 of 16 6.2.6 Place the s.sples 'in'the sample carrier.
6.2.7 Close INM462 (2NM462).
6.2.8 After returning to the outer roos, record the "On Contact" liquid and gas radiation readings on Enclosure 8.2. (Omit during periodic testing).
6.2.9 If this is the last sample to be collected this trip, take the samples to the Hot Lab in the sample carrier and place in an operating fuse hood behind a lead brick shield to await analysis. However, if another sample is to be collected, call Technician #1 at the Hot Lab and have him come down and transport the samples and the completed portion of Enclosure 8.2 up to the lab. Then proceed with Section 6.2.10 to begin the collection of a second sample.
One of the sample hoods in the Hot Lab should be designated specifically for sample storage. Lead bricks should line the front of the sample hood so that samples
{ may be placed behind them.
1 6.2.10 In order to begin the process of collecting a second s sample perform Steps 3.2.5 and 3.2.10.
I 6.2.11 Attach new liquid and gas samplers on the side of the PALS
( panel. New samplers are located in the PALS drawer.
6.2.12 Begin at Step 4.2, Panel Prep. and repeat the procedure for the new sample, j 7.0 SAMPLE ANALYSIS 7.1 Initial Conditions (Technician #1) i 7.1.1 A f ame hood in the Hot Lab is prepared to accept a port-accident sample: (1) the ventilation fan is on and (2) Lead bricks line the front of the panel. ;
7.1.2 Two 5cc lockable sample syringes have been verified workable and evacuated.
7.1.3 A 5cc vial has been evacuated and placed in the fume hood.
I 7.1.4 A clean 50 ml nalgene sample bottle has been placed in the sample hood.
7.1.5 Reagents to run CP/0/A/8100/16 have been prepared and standards have been run.
l l
OP/0/A/6200/21 1 Page 13 of 16 k
7.1.6 The Gas thrometegrarh has been started up and standardized y per CP/0/A/6100/46, Chemistry Procedure for the g Determination of Stripped Gas by G. C.
7.2 Stripped Gas Samples CALTIION: Perform all actions involving the transfer, preparation, or analysis of the gas sample under the fuse hood.
7.2.1 Insert a lockable 5cc syringe into the gas sampler and withdraw Ice of sample. While still under the fume hood, inject the sample into an evacuated Sec vial.
7.2.2 Double bag the vial. Seal tightly. Prepare a label for the bag as follows:
" Liquid Sample Name Initials Date Sample Trap Time Sample Factor "
The " Gas Sample Name" and " Sample Trap Time" may be obtained from the gas sampler label. Calculate the actual sample volume as follows:
, Unit 1: Sample Volume = 110 ml x 1 al = 0.42 al k 260 ml Where: 110 ml = liquid tank volume (including tubing) 260 ml = gas tank volume (including tubing)
I al = sample volume injected into vial Unit 2: Sample Volume = 105 ml x 1 al = 0.37 al 286 al Where: 105 al = liquid tank volume (including tubing) 286 al = gas tank volume (including tubing) 1 al = sample volume injected into vial Complete the Sample Requisition form using the sample volume calculated above to fill in the " Sample Volume" blank on the form. This will allow Health Physics to adjust isotopic activities from diluted samples to reflect reactor coolant activity.
7.2.3 Using a sample carrier, transport the sample to the Health Physics Count Room, or elsewhere for gamma spectral analysis.
1
.o
\,.
1 a-----,--- - , ,----,--.-,,--,.n,,,.___, , _ , , _ , , . . , _ . , _ - , , . . _ - - . _ . . , . . . , . , , _ , - . _ , _ _ . _ , _ . . _ ,
OP/0/A/6200/21
. . . . Pag = 14 of 16
...; . . e a o - . . , .
7.2.4 Insert a lockable Sec sfrin oe into the gas rampler and withdraw 5c3 of sample. Lock cae syringe.
7.2.5 Analyze the 5cc sample of stripped gas per CP/0/B/8100/45, 7.3 Liquid Sample CAUTION: Perform all actions involving the transfer, preparation, or analysis of the liquid sample in the fume hood.
7.3.1 Take 10 cc of liquid sample and prepare for analysis per CP/0/A/8200/04, Chemistry Procedure for the Determination of Gamma Isotopic Activity. Dilute 10 cc to 100 cc with Super-Q water in a 125 m1 wide mouth Nalgene bottle.
Report the actual sample volume being counted on the sample requisition form under " Sample Volume" and submit to Health Physics so that the appropriate adjustment of isotopic activities occurs.
Unit 1
" Sample Volume" (ml) DF Flow Totalizer Setting 0.206 48.4 02500 0.104 , 96.7 05000
, 0.058 172.3 09000
, 0.014 673.5 35000 s .. .
Unit 2
" Sample Volume" (ml) DF Flow Totalizer Settins 0.172 58.2 02500 0.086 115.0 05000 0.048 207.0 09000 0.012 808.2 35000 Double bag the vial. Seal tightly. Prepare a label for the bag as follows:
" LIQUID SAMPLE NAME INITIALS DATE SAMPLE TRAF TIME SAMPLE VOLUME The " LIQUID SAMPLE NAME" and " SAMPLE TRAP TIME" can be i obtained from the liquid sampler label. The " SAMPLE VOLUME" is obtained from the chart in this step.
t I
a 4
--- . - -,y,y ,--r _ . . . ._,,, . _ . - - , _ - _ . , .m. . . - - - - - _ . _ _ . . - . , . _..,__-.__,r..
.---.-.y _m- - - . . ,,,._.-,--,-_-.--f- __-.--r-
OP/0/A/6200/21
,, Page 15 of 16 7.5.4 4' axe 50 mA of 'aigaid sample' 46d' nnilyzi' Tb'r 'ooruo per ,
CP/0/Af8100/16.
Then, multiply the ppe BORON MEASURED, i.e. the value ~
obtained per CP/0/A/8100/16 by the Dilution Factor to obtain the ppe Boron in the Resctor Coolant.
ppa BORON IN THE REACTOR COOLANT =
ppa BORON MEASURED X DILUTION FACTOR Record the " Boron Concentration" on Enclosure 8.2.
7.3.3 Subtract the radiation field (background), #1 - Enclosure 8.2, from sample activity found at purge time completion
(#3) and record on Enclosure 8.2. This is the radiation due to the sample.
7.3.4 Chloride Analysis CAUTION: Perform all actions which involve the transfer of the liquid sample to another container under the fuse hood.
7.3.4.1 Contact the Station Chemist at the TSC (#2531).
7 j;, Ask him to contact the General Office personnel L
(at the Crisis Management Center during an accident situation). Inform them that a post-accident liquid sample is to be transported to the Applied Science Center for chloride analysis on the ion-chromatograph.
They should contact A. M. Desk for workload clearance. Also, ask the Station Chemist to t fill out a Chemical Sciences, Analysis Request Form, Enclosure 8.9 for the sample.
7.3.4.2 A hard copy of the gamma spectrum and tritium data as well as the sample volume should be transferred to the Applied Science Center Radiation Protection Officer (Charmaine Bonus) or her designee. A telecopy can be sent to the Applied Science Center (CHEMPLOT can also be used).
7.3.4.3 Transfer 20 al 15 al of sample from the liquid sample to a 50 mi nalgene bottle.
7.3.4.4 Double bag the bottle. Seal tightly. Label the bag as follows
~ ~
r " LIQUID SAMPLE NAME l
( ~ INITIA13 DATE SAMPLE TRAP TIME DILUTION FACTOR "
l l
5
OP/0/A/6200/21 Page 16 of 16
'4ae ' bah /Li TnAF TIE anu ' 01LuT20l= 1 A( IteA !
f can b .htained from the liquid Enclosure 8.2.
,,, Place the bag in a shielded container for transport.
7.3.4.5 Once the sample shipment has been authorized by the Radiation Protection Officer, the sample shipment should be sent to the Physical Sciences Building in care of the Radiation Protection Officer. The dilution water sample obtained in Step 3.2.3 should also be sent for analysis at this time.
7.3.4.6 When the sample results are obtained record the results on Enclosure 8.2. .
7.4 If the dilution proves inadequate for any of the above procedures
- f contact the Station Chemist or his designee.
7.5 Report all results in the Primary Chemistry Legal Log. In an accident situation results should be relayed by phone to the Station Chemist at the TSC as soon as possible. Phone number, 2531.
7.6 Clean the liquid and gas samplers under the fume hood: Remove and replace the septum in the gas sampler. Flush the liquid sampler with Super Q water.
k 7.7 With Enclosure 8.2 in a plastic bag, exit the Auxiliary Building.
Check out through the Operation's Support Center.
7.8 Transport Enclosure 8.2 to the Station Chemist at the TSC.
i 8.0 ENCLOSURES 8.1 Initial Conditions Checklist 8.2 PALS Data Sheet
- 8.3 Valve Alignment (Unit 1) i
! 8.4 Valve Alignment (Unit 2) 8.5 PAIS Control Panel Layout 8.6 Valve Sequence Table 8.7 General Information 8.8 Operation's Supply - Valve Alignment 8.9 Chemical Sciences Analysis Request Form , ,
k- -
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,_._,,.,.,_n..,_,_. ,n _,, . - - - . ,_, . - _ _ - . - , = - - - - - . . - , - - .
{
Page 1 of 4
. "**2
~ '*
ENCLOSURE 8.1
- OP/ 0/ A/6200/21 INITIAL CONDITIONS CKeCKLIST Date: J /
PART I. (Verifying the System's Ability to Function) Initial /Date
- 1. Verify that the Post Accident Liquid Sampling System /
Periodic Test, PT/1/A/4208/08 (PT/2/A/4208/08) is current prior to sampling. (Periodic Test Program -
Computer Printout)
? PART II. (Interfacing Groups) Initial /Date
- 3. Contact Operations (complete at TSC).
(a) If this is an accident situation, the containment /
abould have been isolated by an ST signal. Verify that the signal has been cleared.
Initial /Date CAUTION: Warn Operations not to open any sample lines until Chemistry has realigned valves in the NM lab. Opening containment isolation sample valves too early could increase radiation levels in the NM lab.
( (b) Request permission to open the desired valves out /
of the list below. Place a check beside the sample l point (s) to be used.
NC Hot Les A Unit 1 Unit 2 Check Rot I43 Sep1 Edr Coat Isol INH 26B 2NH26B
- Hot Les Sep1 A Coat Isol INM22A 2NM22A
! NC Hot Les C i Hot Les Sepl Edr Cont Isol INM26B 2NM26B Hot Les C Sepl Coat Isol INM25A 2NM25A ND Pump 1A Discharme Unit 1 Unit 2 i
- ND Psep 1A Disch Sep1 Line Isol INM39 2NM39 ND Psep 1B Discharge Unit 1 Unit 2
- ND Psep 1B Disch Sep1 Line Isol INH 40 2NH40
- Verify with Operations that the respective A or B Train is in service.
J
_ . Initial / Time
, (c) Verify with Operations that a 1EC Essential Supply /
Header is in operation for Unit 1 Sampling. For Unit 2, verify with Operations that a 2KC Essential Supply Header is in operation for Unit 2 Sampling.
Page 2 of 4 INCLUSUll 6.1 OP/0/A/62OO/21 ,
I * 'IWITIAL' CONDITIONS CHECKLIST Date: / /
Initial / Time (d) Request permission to open or to have an operator open the following Operations valves in order to provide cooling water flow to the panel. These valves are locked closed. The keys should be obtained prior to proceedina to the panel.
/
Unit 1 Unit 2 Post Accident Liquid Sample Panel Ex Inlet IECA8 2KCA8 Post Accident Liquid Sample Panel Ex outlet IKCA10 2KCA10 For Unit 2, the following additional valves have to be OPENED: A Train KC-2KCD03 and 2KCD05, B Train KC-2KC-D04 and 2KCD06.
(e) Verify Power Panel Boards 1XXPA and 1KKPB are /
energized for Unit I sampling. 2KXPA and 2KKPB for Unit 2 sampling.
- 2. Contact Radwaste Chemistry (Complete at TSC). Initial /Date Notify Radwaste Chemistry that the PALS panel will be /
operated. Waste liquid from the panel is pumped to
., WEIT Sump "A". (For Unit 1 sampling). For Unit 2 sampling the waste liquid is pumped to WEIT Sump "B".
- 3. Contact Health Physics (Complete at TSC). Initial /Date t
(a) Request Health Physic's Coverage for obtaining a /
post-accident liquid sample.
Initial /Date (b) Verify Health Physic's ability to count a sample /
in the Count Room or elsewhere.
1 PART III. (Required Equipment) Check
- 1. Technician #2 should have the following items before departing to the NM lab:
(a) The PALS panel keys (A set of keys are located in the Secondary Supervisor's office and the Cold Lab)
(b) A Working Copy of OP/0/A/6200/21 with Enclosure 8.1 completed. . .
(c) A High Radiation Area Key for the NM Lab.
(d) A Shielded Sample Carrier
l Page 3 of 4 :
E::CLG5LX A.1
.PidiAiec00,2.
e INITIAL collD"TICH CZCALIST Date: / /
Check
-(e) Plastic bags left on Cold Side (f) Black ball point pen (g) A 50 ml Walgene Sample bottle labeled
" Dilution Water Sample" (h) Fill out two labels as follows:
Label one: " Liquid Sample Name Initials ;
Date
- Sample Trap Time
- Dilution Factor Label the second: " Gas Sample Name Initial's
- Sample Trap Time
- The " Sample Trap Time" and " Dilution Factor" will be entered after the samples have been obtained. This information will be on Enclosure 8.2.
PART IV Recommended Dilution Volume (From Station Chemist at TSC)
Unit 1 Dilution Factor ' Flow Totalizer Settina Check One 48.4 02500 96.7 05000 172.3 09000 573.5 35000 6
1 Pc32 4 of 4 ERCLOSJRE 8.1 i.'5 S 'OP/0/A/0200/21 INITIAL CONDITION CHECKLIST Date: / /
Unit 2 l Dilution Factor Flow Totalizer Settina Check One I
58.2 02500 115.0 05000
~ - ~
207.0 09000 808.2 35000 Station Chemist Initial /Date
/
4 v l
i l
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l Pcat 1 of 4 ENCLOSURI C.2 Oi /s /,./6 0v,21 f
PALS DATA SHEET s.
(Circle One)
NC Loop A - C Data (Page I of II)
Initial /Date
/
PART I. (Complete at Control Panel) TIME
- 1. Radiation Field (Background) mR/hr __
- 2. Time sample purge started.
- 3. Radiation field (sample purge time completion) mR/hr
- 4. TC1 temperature (stabilized with Sample Flowing) *C
- 5. Radiation due to sample, (#3) - (#1) (Complete after mR/hr Sample Collection)
- 6. Pressure at isolation psig
- 7. Sample Trap Time
- 8. Flow totalizer setting
- 9. pH of sample
- 10. Radiation reading (From 4.9.5) mR/hr
- 11. Radiation reading on contact with samplers.
(Omit during Periodic Testing.) Gas mR/hr Liquid mR/hr i
l l
.- _ - - = __ _ - - _ _ . _ - - _ - _ _
Page 2 of 4
,' ' ' l - ~
, ENCLOSURE 8.2 CP/ 3/.1/t 2C 3/.1 PAIS DATA SHEET (Circle One)
NC Loop A - C Data (Page II of II)
Initial /Date
/
PART II. (Complete at Hot Lab) yin
- 1. Hydrogen Concentration ec/kg H
- 2. Boron Concentration ppa B
- 3. Dilution Factor Reference Enclosure 8.7, number 7 ;
~
- 4. Chloride Concentration ppb C1
- 5. Gamma Spectral Analysis (Gas) (Attach H.P. Data Sheet)
- 6. Gamma Spectral Analysis (Liquid) (Attach H.P. Data Sheet)
In as accident situation, the results from this data sheet should be g ) forwarded to the Station Chemist at the Technical Support Center as soon
- as possible. TSC phone number - 2531.
Initial /Date
/
1 l
V.
l
Page 3 of 4 1
. ENCLOSURE 8.2 1)P/0/A/6200/21 l
/ PALS DATA SEET
~ (Circle One)
ND Loop A - B Data (Page I of II)
Initial /Date
/
PART I. (Complete at Control Panel) TIE
- 1. Radiation Field (Background) mR/hr
- 2. Time sample purge started.
- 3. Radiation field (sample purge time completion) mR/hr
- 4. TC1 temperature (stabilized with Sample Flowing) 'C
- 5. Radiation due to sample, (#3) - (#1) (Complete after mR/hr Sample Collection)
- 6. Pressure at isolation psig i
- 7. Sample Trap Time
- 8. Flow totalizer setting
- 9. pH of sample
- 10. Radiation reading (From 4.9.5) mR/hr l 11. Radiation reading on contact with samplers.
(Omit during Periodic Testing.) Gas mR/hr Liquid. mR/hr me e op
,--,.-_.-..--e,, _ - . . , , - . , ,. r- n,vn~,-n---v-----~,---.e--- -
--mw -m----n ~w--,wm~-v--,---w-~-'-'- '- ' *-"" ' * ' '
t Page 4 of 4
.3CLOSUrtE 8 2 OP/v/a/6290/.1
,- PALS DATA SHEET ,
i i (Circle One)
ND Loop A - B Data (Page II of II)
Initial /Date
/
PART II. (Complete at Hot Lab) TIME
- 3. Dilution Factor Reference Enclosure 8.7, number 7
- 4. Chloride Concentration ppb C1"
- 5. Gaauna Spectral Analysis (Gas) (Attach H.P. Data Sheet)
- 6. Gamma Spectral Analysis (Liquid) , (Attach H.P. Data Sheet)
In an accident situation, the results from this data sheet should be forwarded to the Station Chemis the Technical Support Center as soon
{ as possible. TSC phone number ,
1 Initial /Date
/
m
uuss. ruer.n w . a..e Farm 18768 (R8 81) '
CATAVBA NUCLEAR STATION ENC 145UPI. 8.3
~
CP/C/1/6:00.?21 (Unit 1) val.I. Ael N!.l.h~l I/v:CI..N
'
- VE NO' VALVE NAME POSITl0N INITIAL
~
As-543 E -5d 1NH342 PASP Domin Supply Flow bter Influent Rs. 238 710t0TTIJ D AB-543 EE-5d 1NH343 PASP Dealm. Supply Isol to rep 1 Edr Rs. 238 OPEN AB-543 EE-5d INM351 PASP Air Eductor Isolation Tros VI Ra. 238 OPEN AB-543 EE-5d 1NM298 Nitro 8en Supply to PASP , Rs. 238 OPEN AB-543 EE-5d 1NH393 PASP Effluent to WEIT Sump A Isol '\ Rs. 238 OPEN ,
~
AB-543 EE-5d INH 321 PASP Liquid Tank Effluent to WEIT , Rs. 238 TIDt0!TLI D AB-543 EE-5d 1NH334 PASP Calibration Tank Vent to Aux Blds Exhattst Rs. 238 CIDSED AB-543 EE-50 1Nii328 PASP Sample Line Nitrogen Supply Isolation Rs. 238 OPEN p : AB-543 EE-5L
.NH452 PASP Dilation Tank Sample Rm. 238 CIDSED AB-543 EE-5L 1NH449 PASP Calibration Tank Drain Rs. 238 CIDSED AB-543 EE-50 1ECC99 Sample Cooler Outlet Valve -
Rs. 238 OPEN AB-54.3 E-5d .
INH 456 PASP Demerator Tank Sample Rs. 238 CLOSED l
l AB-543 Er-5d ,
1NH453 PASP Liquid Tank Sample Rm. 238 CLOSED AB-543 EE-5d 1NH448 PASP Nitrogen Inlet to Liquid Tank Rs. 238 OPEN
~
AB-543 EE-5L INM462 PASP Demerator Tank Inlet Rs. 238 CLOSED AB-543 EE-5d.
1NH427 PASP Na Vent Valve Rs 238 CLOSED e
. . - , - , _ _ _ _ _ _ , , . - - . - , . , , . , . , , _ , _ , . - - _ - . , , . . - _ _ _ , . _ . _ _ .--,.-.mm.r,,..- - . . - - - - _ , - _ _ _ - , .
DUKE POWER COMPANY Form 18768 (R8 81) CA*IAWBA NUCLEAR STATION ENCLOSURE 8.4 OPio/A/,62,00/21 (Unit 2)
'*ALVE
. ALIGNMENT LOCA110N
- b.
- VC NC*
VALVE NAME POSITION INITIAt.
AB-543 EE-61 2NM342 PASP Demin Supply Flow Meter Influent Rm. 248 Om 61 2NM343 PASP Demin. Supply Isol to Sapl Hdr AB-543 EE-61 Rm. 248 OPEN 2NM351 PASP Air Eductor Isolation From VI AB-543 EE-61 Rm. 248 OPEN 1
AB-543 EE-61 2NM298 Nitrogen Supply to PASP OPS Rm. 248 AB-543 EE-61 2NM393 PASP Effluent to WEFT Sump A Isol @U Rm. 248 2NM321 PASP Liquid Tank Effluent to WEFT AB-543 EE-61 THROTTLEE Rm. 248 AB 3 2NM334 PASP Calibration T'ank Vent to Aux Bldg Exhaust 28 MSm
~ N 28 PASP Sample Line Nitrogen Supply Isolation AB-543 EE-61 Rm. 248 2NM452 PASP Dilution Tank Sample AB 43 EE-61 2NM449 PASP Calibration Tank Drain AB 43 EE-61 AB 3 2KCC99 Sample Cooler Outlet Valve 24 OPEN AB-543 EE-61 2NM456 PASP Demerator Tank Sample 8 Rm. 248 2NM453 PASP Liquid Tank Sample AB-543 EE-61 CESE Ex. 248
~
AB-543 EE-61 2NM448 PASP Nitrogen Inlet to Liquid Tank Rs. 248 OPE AB-543 EE-61 2NM462 PASP Demerator Tank Inlet 8 Rm. 248 ._
2NH427 PASP N2 Vent Valve 2 CLOSED -
- - , - .---->,-,--,_...------a,,--ana- - - , - - , - - - , - . . - - - - , , - , . , , - , , , . , , , , - - ---,----,---m-.., , e- - . ,g. - , , , , - . , - -
ENCLOSURE 8.5 Page 1 of 2 P-Lc CONTROI. DAhTi. LAYOITT t v/s.jp 16100i21 i
DRAIN OTT RESET PANEL P3.EP_ _
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i Page 1 of 3
. ENCLOSURE 8.6
. OP!0/A/6200/21 VALVES SEQUENCE TABLE I '
Pushbotton t
Fu=ction Activation Valves 1.0 Panel Prep 1hh313, lhM312, lh3315 1NMSV0311, lhh311, lht310, 1NM314, 1NMSV3201 1.1 Calibrate H INM333, lhh332 1.2 Purge H INM330, 1NM336 INM307, 1NM305 1.3 Flush . H 1ht331, INM338, INM307, INM309 1.4 Drain H INM338, INM307, 1NM305 2.0 Sample Trap 1KCA9, INM294, lh3324 1NM319, INM313, INM312 1NMSV0311, 153314 2.1 Pressurize 'M 1hM319 l
2.2 Trap M INM324 3.0 Depressurization 1NM317, 1NM315 3.1 Gas Stripping Start M INM325, 1NM327 3.2 Gas Stripping Stop M INM325, 1NM327 4.0 Grab Sample INM339, 1NM346 l
4.1 Grab al M INM318, 1NM325, 1NM329, i
i INMSV0336 4.2 D.M. Flow Meter Start M INM341, 1NM346 l 4.3 D.M. Flow Meter Stop M INM341, INM346 4.4 Eixing H INM340 4.5 pH M INMSV0336 4.6 Trap Open M IN53'5,INM312, 1
- 1NMSV0311, lh3324, 1hH319, INM345, INM322 l
% e Page 2 of 3
, ENCLOSURE 8.6 op/0/A,6200/21 VAIFEF SF.00ENt:E TABIE
/
Pushbotton Function Activation Valves
- 4.7 Trap Close M 1hM315, lhh312 1h3SV0311 5.0 Liquid Sample lhh324, 1NM319 1NM345, lht322, 1NM348 1h3SV0350, 1NM346 5.1 Trap Open H INM319, 1NM346, INM309 -
INM304, lhh376 5.2 Trap Close H INMSV0350 6.0 Flush 6.1 Gas Tank M INM316, INH 312, 1NM308, INM309 6.2 Probes M INM331, 1NM338, 1NM307, INH 309
(
6.3 Dilute tank M INM347, 1NM301, INM309 6.4 Liquid Tank M INM331, INM329, INM325 1NM319, INM322 7.0 Drain 7.1 Dilute Tank
- M INM376, 1NM348, 1NM304, 1NM305 7.2 Gas Line M INM323, 1NM315, 1NM312 INM308, INH 305 7.3 Gas Tank M ,
1NM323, INM315, INM317, 1NM325, INM329, 1NM338, 1NM307, INM305 7.4 Probe Refill & M 1h3331, 1NM338, lhM307 System Vent 1hM309, INM312, INM313 1NM346, 1NM348, 1NM315 1NMSV3200
( .
1 .
a .
Pcas 3 of 3 ENCLOSURE 8.6
'2 c' ' C7* OP/0/A/6200/21
- ' VALVES SEQUENC1.'rAELE LEGEND
]
M- Momentarily depressing the button initiates the function, l N- The function will operate as long as the pushbutton is depressed.
_N- Indicates that the valve is de-energized when the pushbutton is depressed.
- - he same valve sequence is used for Unit 2 PALS; therefore, the valves will simply be labeled with a 2 prefix.
t t
e e
gum ee
, r , - -
Pago 1 of 2 LNCll.:5UAE 8.7
'uP/t/A/620J/21
/ ' GENERAL INFORMATION v
- 1. PALS Panel Location: Unit 1 - (Room 238, Col. FF-55, AB-543)
Unit 2 - (Room 248, Col. FF-59, AB-543)
See Page 2 of this enclosure for a general arrangement drawing.
- 2. Telephone Number at Control Panel - Ext. 2109 (Unit 1), Ext. 2209 (Unit 2)
- 3. Breaker Information:
Unit 1 Fdr. Breaker Comp / Breaker Description Location 1EXPA #3 Post Accident Sampling AB 554' Sample Pump and Sol. Vivs. RM 350 CC-57 1EXPB #34 Post Accident Liquid AB 554' Sampling Control Panel RM 350 CC-56 Unit 2 Fdr. Breaker Comp / Breaker Description Location
. 2KIPA #3 Post Accident Sample AB 554' Pump and Sol. Vivs. RM 340 CC-57 2EXPB #34 Post Accident Liquid AB 554' Sampling Control Panel RM 340 CC-58
- 4. Area Radiation Monitor: 1 EMF-2 is located in Room 238.
2EHF-2 is located in Roars 248.
- 5. Station Chemist phone number at TSC - 2531.
- 6. Sample Line Purge Volumes Unit 1 NC Icop A to PALS - 22.5 gallons (45 minute purge @ .5 GPM)
NC Icop C to PALS - 19.5 gallons (39 minute purge @ .5 GPM)
ND Loop A to PALS - 25.0 gallons (50 minute purge @ .5 GPM)
ND Icop B to PALS - 32.5 gallons (65 minute purge @ .5 GPM)
Unit 2 NC Loop A to PALS - 21.5 gallons (43 minute purge @ .5 GPM) !
\ -
NC Icop C to PALS - 19.2 gallons (38 minute purge @ .5 GPM) j ND Icop A to PALS - 9.6 gallons (20 minute purge @ .5 GPM)
~
ND Icop B to PALS - 12.6 gallons (25 minute purge @ .5 GPM)
Pag? 2 of 2 ENCLOSURE 3.7 Or/tfrivinC/a1
( GENERAL IhTOEMION - -
- 7. Dilution Factors Unit 1/ Unit 2 Flow Totalizer Setting Dilution Factor Dilution Water Added (al) 02500/02500 48.4/58.2 250.0/250.0 05000/05000 96.7/115.0 500.0/500.0 09000/09000 172.3/207.4 900.0/900.0 35000/35000 673.5/ sos.2 3500.0/3500.0 h.
1 4
9 m -e
(.
- . l DUKE POWER COMPANY Pass 1 of 2
. Form 18768 m8-81) CATAWBA NUCLEAR STATION ENCLOSURE 8.8
'OP/0/A/6200/21 OPERATION'$ SUPPLY VALVES - VALVE ALIGhrQ.h!
.VE NO. * -
VALVE NAME
, "0 lTION ~ lhlTIAL Unit 1 PALS Supply Valves AB-553 GG-56 IVI230 Root Isol. Rm. 200 OPEN AB-543 EE-53 IVI86 Aux. Bldg. 343 Elev. VI Supply Rm. 217 OPEN 4 AB-543 FF-So 1YM436 Post Accident Unit 1 Sample Isol. Rs. 238 OPEN AB-543 FF-So 1YM256 YM Header Isol Rs. 238 OPEN 1KCA8 Post Accident Liquid Sample Panel Ex Inlet AB-546 EE-So LOCKED Rs. 238 CICSED 1KCA10 Post Accident Liquid Sample Panel Ex Outlet AB-546 EE-So LOCKED Ra. 238 CLOSED
(_, Unit 2 PALS Supply Valves h
2VI402 Liquid Sample Panel Supply Isol. AB-543 OPEN 2VI230 Unit 2 Aux. Bldg. Rcot Isol. AB-543 OPEN 2VI86 Aux Bldg 543 Elev. VI Supply AB-543 OPEN
.i 1YM437 Post Accident Unit 2 Sample Isol. AB-543 FF-64) OPEN Rm. 248 1YM140 YM Header. Isolation AB-543 FF-5 F OPEN Rs. 200 2KCA8 Post Accident Liquid Sample Panel Hx Inlet AB, 543, LOCKED EE-FF, 60-6 L CLOSED 2KCA10 Post Accident Liquid Sample Panel Ex Outlet AB, 543 LOCKED EE-FF, 60-6 L CLOSED NOTE: The valves listed above all belong to Operations. Contact Operations if a valve is -
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found in an incorrect position.
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DUKE POWER COMPANY Page 2 of 2 Foim 18768 (R8 81) CATAWBA NUCLEAR STATION l ENCLOSURE 8.8 OP/0/A/6200/2.1 - '
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Form 34731 (3 84) (1) lD No. HP/0/B/1009/09 DUKE POWER COMPANY Change (s) O to PROCEDURE PROCESS RECORD 3 g,,co,por,t e PREPARATION (2) STATION Catawba (3) PROCEDURE TITLE Guidelines for Accident and Emergency Response (4) PREPARED BY - - A DATE
/I~ N (5) REVIEWED BY ~ / OATE de
' ~
Cross-Disciplinary Review By (l N/R 8_ & A ' J e (6) TEMPORARY APPROVAL (if Necessary) ,
By (SRO) Date By ^ Date (7) APPROVED BY U DATE /7 (8) MISCELLANEOUS n /
V.
Reviewed / Approved BV Date Reviewed / Approved By Date COMPLETION (9) DATE(S) PERFORMED (10) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate?
O Yes O N/A Listed enclosures attached?
Oyes O N/A Data sheets attached, completed, dated and signed?
Oyes O N/A Charts, graphs, etc. attached and properly dated, identified and marked?
l O Yes O N/A Acceptance criteria met?
VERIFIED BY DATE (11) PROCEDURE COMPLETION APPROVED DATE (12) REMARKS i
HP/0/B/1009/09
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION GUIDELINES FOR ACCIDENT AND EMERGENCY RESPONSE 1.0 PURPOSE 1.1 To provide guidance for notification / activation of the Health Physics Organization in the event of an emergency situation.
1.2 To assure proper assignment of responsibility.
1.3 To give general guidance for initial response of the Health Physics organization.
1.4 To give general guidance for continuing response of the Health l Physics organization.
2.0 REFERENCES
2.1 HP/0/B/1001/12, Technical Specifications Gaseous Waste Sampling and Analysis.
2.2 HP/0/B/1009/04, Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Station.
2.3 HP/0/B/1009/05, Personnel / Vehicle Monitoring for Emergency Conditions.
2.4 HP/0/B/1009/06, Alternative Method for Determining Dose Rate Within the Reactor Building.
2.5 HP/0/B/1009/07, In-plant Particulate and Iodine Monitoring Under Accident Conditions.
2.6 HP/0/B/1009/08, Contamination Control During Transportation of Contaminated Injured Individuals.
2.7 HP/0/B/1009/10 Body Burden Analysis Following Suspected Uptakes of Mixed Fission or Activation Products.
2.8 HP/0/B/1009/12, Quantifying Gaseous Release through Steam Relief Valves Under Post-Accident Conditions.
2.9 HP/0/B/1009/13, Off-Site Dose Projection - Uncontrolled Release of Radioactive Material through the Unit Vent.
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2.10 HP/0/B/1009/14, Health Physics Actions Following an Uncontrolled Release of Liquid Radioactive Material.
2.11 HP/0/B/1009/15, Offsite Dose Projections - Uncontrolled Release of Gaseous Radioactive Material other than through the Unit Vent.
s HP/0/B/1009/09 Page 2 of 4 2.12 HP/0/B/1009/16, Distribution of Potassium Iodide Tablets in the Event of <t Radioiodine Release.
2.13 HP/0/B/1009/17, Post Accident Containment Air Sampling System.
2.14 HP/0/B/1009/19, Emergency Radio System Operations,. Maintenance, and Communications.
2.15 HP/0/B/1009/21, Abnormal Unit Vent Samp1'ing.
2.16 RP/0/A/5000/11, Protective Action Recommendations Without the OAC.
2.17 RP/0/B/5000/12, Control of Assessment and Repair Teams.
2.18 Catawba Nuclear Station Emergency Plan. ,
2.19 System Health Physics Manual.
2.20 Catawba Nuclear Station, Station Directive 2.8.1, Reporting Requirements.
2.21 Catawba Nuclear Station, Station Directive 3.8.4, Onsite Emergency Organization.
3.0 LIMITS AND PRECAUTIONS i
3.1 This procedure shall only be initiated at the direction of Health j Physics Supervision.
3.2 This procedure may be initiated in part or whole, depending on the type and severity of emergency.
3.3 This procedure provides general guidance for initial response. Any particular situation may require actions not addressed in this procedure.
3.4 For incidents occurring during backshifts, Health Physics shift personnel shall be responsible for on-site response only until directed otherwise by the Station Health Physicist.
4.0 PROCEDURE 4.1 Upon notification of an emergency condition, the Station Health Physicist shall activate the Health Physics organization by notifying one or all of the following:
4.1.1 Surveillance and Control Coordinator.
4.1.2 Support Functions Coordinator.
4.1.3 Staff Coordinator.
4.1.4 Shift Technician (To advise, if during back shift).
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HP/0/B/1009/09 Page 3 of 4 4.2 Individual coordinators will notify alternates and supervisors to <
be under their direction during the emergency, and will make arrangements through the supervisors for the notification of non-exempt personnel.
4.3 If the emergency is classified above the Notification of Unusual Event category, the Station Health Physicist shall proceed to the Technical Support Center (TSC), and coordinate the overall Health Physics response. Enclosures 5.2 and 5.3 provide general guidelines for response.
4.4 When notified to respond to an emergency, the Surveillance and Control Coordinator shall assume alternate responsibility for the Station Health Physicist, and shall activate the S&C Coordinator identified in Reference 2.18 who will act according to Enclosures 5.4 and 5.5.
r 4.5 When notified to respond to an emergency, the Support Functions Coordinator shall assume alternate responsibility for the Station Health Physicist and shall activate the Support Functions Cocrdinator identified in Reference 2.18 who will act according to Enclosures 5.6 and 5.7.
4.6 Vhen notified to respond to an emergency, the Staff Coordinator shall act according to Enclosures 5.8 and 5.9.
4.7 When notified to' respond to an emergency, the Field Monitoring Coordinator shall act according to Enclosures 5.10 and 5.11.
4.8 When notified to respond to an emergency, the Operation Support Center (OSC) Supervisor shall act according to Enclosures 5.12 and 5.13.
5.0 ENCLOSURES 5.1 Guidelines For Planned Emergency Exposures 5.2 Station Health Physicist - Initial Response 5.3 Station Health Physicist - Continuing Response 5.4 Surveillance and Control Coordinator - Initial Response 5.5 Surveillance and Control Coordinator - Continuing Response 5.6 Support Functions Coordinator - Initial Response 4
5.7 Support Functions Coordinator - Continuing Response 5.8 Staff (Data Analysis) Coordinator - Initial Response i 5.9 Staff (Data Analysis) Coordinator - Continuing Response l
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HP/0/B/1009/09 Page 4 of 4 5.10 Field Monitoring Coordinator - Initial Response
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5.11 Field Monitoring Coordinator - Continuing Response 5.12 OSC Health Physics Supervisor - Initial Response 5.13 OSC Health Physics Supervisor - Continuing Response ~ -
5.14 Reserve Personnel / Personnel Monitoring Leader Response 5.15 OSC Response Personnel Dose Record Form 5.16 Procurement of Helicopters for Aerial Environmental Surveillance v
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Page 1 of 2 HP/0/B/1009/09 -
ENCLOSURE 5.1 GUIDELINES FOR PLANNED EMERGENCY EXPOSURES 5.1.1 Obtain the verbal or written approval of the Emergency Coordinator to exceed planned maximum limits.
5.1.2 If it is necessary to remedy a situation immediately hazardous to life and property, an individual (Duke Power p.ersonnel, or Outside Services) may receive exposure up to:
Skin of the Whole Body 30 rems (125 rem)*
or Thyroid Extremities 75 rems v
- Doses up to this limit may be authorized by the Recovery Manager.
5.1.3 If it is necessary to save lives or prevent loss of lives and/or extensive damage to croperty, an individual may volunteer to receive exposure up to:
Skin of the Whole Body 150 rems or Thyroid
( Extremities 375 rems
- Doses up to this limit may be authorized by the Recovery Manager, Station Manager or Emergency Coordinator. For application of these exposures, extensive damage to property should be considered to result in loss of life or the inability to control or mitigate the accident with the assurance that life can be protected.
5.1.4 If possible, the individual (s) should be selected by the following criteria:
2 5.1.4.1 Personnel should be volunteers or professional rescue personnel.
5.1.4.2 Personnel should be broadly familiar with the potential consequences of such exposure.
5.1.4.3 Women capable of reproduction should not take part in these actions.
5.1.4.4 All factors being equal, volunteers above the age of 45 should be selected.
5.1.5 Exposure shall be maintained ALARA.
4 5.1.6 Internal exposure should be minimized by the use of the best available respiratory protection, and contamination should be controlled by the use of available protective clothing.
5.1.7 All exposures (permissible, planned maximum, planned emergency and acciden-tal) shall require documentation and an occupational dose penalty if necessary.
Page 2 of 2 HP/0/B/1009/09 ENCLOSURE 5.1 GUIDELINES FOR PLANNED EMERGENCY EXPOSURES 5.1.8 Exposures *above the guidelines of Section 5.1.3 should be authorized by the Recovery Manager, Station Manager or Emergency Coordinator and will require a medical decision as to whether the individual may continue in radiological work and should be limited to once in a lifetime. -
5.1.9 Reports of planned emergency exposures shall be reported as per Catawba Nuclear Station Directive 2.8.1 (Reporting Requirements).
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Page 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.2 STATION HEALTH PHYSICIST
. INITIAL RESPONSE 5.2.1 Assemble supporting materials and take to TSC.
5.2.2 The Station Health Physicist shall as necessary: ,
5.2.2.1 Establish the exposure limit for blanket dose extension, for Exposure Class 1 to a maximum of 1000 mrem /qtr; for Exposure Class 3 to a maximum of 2500 mrem; for Exposure Class 2 personnel (pregnant females) they shall not be extended above their 500 mRam limit, and should be reassigned to work locations in the Administration Building until radiation' levels are evaluated.
5.2.2.2 Govern planned emergency exposures by Enclosure 5.1 (Guidelines For Planned Emergency Exposures).
5.2.2.3 Coordinate the overall Health Physics response.
5.2.2.4 Recommend protective action on-site for assembled personnel and those with work duties.
f 5.2.2.5 Recommend off-site protective action to the Emergency t
Coordinator until the CMC (Crisis Management Center) is activated.
5.2.2.6 Initiate, as necessary, HP/0/B/1009/16, Distribution of Potassium Iodide Tablets in the Event of a Radiciodine Release.
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Page 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.3 STATION HEALTH PHYSICIST CONTINUING RESPONSE 5.3.1 Interface with the CMC when it is activated.
5.3.2 Coordinate Health Physics shift rotation and aul,entation of personnel and equipment. --
5.3.3 Should evacuation be required; coordinate the identification of "Non-Essential" personnel with other TSC groups.
5.3.3.1 All females should be given first consideration *due to limited use in a radiological exposure situation.
5.3.3.2 Sufficient personnel should be retained to support need for backup personnel.
5.3.4 Direct trending of available information to support Health Physics TSC response.
5.3.5 When CMC is in place, continue Protective Action assessment and recommendations as a confirming response.
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Page 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.4 SURVEILLANCE AND CONTROL COORDINATOR
. INITIAL RESPONSE 5.4.1 Assemble supporting materials and take to TSC.
5.4.2 Establish radiological access controls for the Station and Control '
Room.
5.4.2.1 Initiate, as necessary, HP/0/B/1009/07, In-Plant Particulate and Iodine Monitoring Under Accident
, Conditions.
5.4.2.2 Initiate, as necessary, HP/0/B/1009/08, Contamination Control During Transportation of Contaminated Injured Individuals.
5.4.2.3 Initiate discussions by need for Buddy System for radiological conditions.
5.4.3 If the emergency is classified above the Notification of Unusual Event category:
5.4.3.1 Send the following personnel as necessary to the Operations Support Center (OSC):
5.4.3.1.1 One Supervisor to coordinate Health Physics support and communicate with the TSC and shall act according to Enclosures 5.12 and 3.13.
5.4.3.1.2 One Technician to provide job coverage (sampling, operation, maintenance, etc.).
5.4.3.1.3 Two Technicians to monitor and report plant radiological status.
5.4.3.1.4 Two Technicians to provide fire / medical emergency / rescue team / damage control coverage.
5.4.3.2 Direct sufficient personnel to the Administra-tion Building, DRC office, as staging area.
5.4.3.3 Identify a Supervisor or Lead Technician as Reserve Personnel / Personnel Monitoring Leader and he/she shall act according to Enclosure 5.14.
5.4.3.4 Proceed to the TSC and coordinate Surveillance and Control response, with emphasis upon OSC activities.
5.4.3.5 Request TSC Security staff to provide locations of officers remaining on post. Evaluate exposure potential for these officers and recommend protective actions as necessary.
Page 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.5 SURVEILLANCE AND CONTROL COORDINATOR
. CONTINUING RESPONSE 5.5.1 The S&C Coordinator shall, as necessary:
5.5.1.1 Initiate through RP/PM Leader HP/0/B/1009/05, Personnel / Vehicle Monitoring for Emergency'donditions, when a site assembly occurs due_ to radiological conditions.
5.5.1.2 Initiate, as necessary, HP/0/B/1009/17, Post Accident Containment Air Sampling System.
5.5.2 Provide direction and support to the OSC Health Physics Supervisor:
5.5.2.1 Coordinate in plant and on-site monitoring in support of TSC needs.
5.5.2.2 Keep OSC Supervisor appraised of TSC events and activities that may require OSC response (planned maintenance, operation, sampling).
5.5.2.3 Coordinate with OSC and TSC groups to ensure adequate pre-planning occurs to limit radiation exposures.
5.5.2.4 Obtain additional emergency kit items and supplies to support.0SC if needed.
5.5.3 Monitor dose rate in TSC. Initiate discussion with Station Health Physicist regarding the need to evacuate the TSC should dose rate exceed 5 mR/hr and be expected to continue.
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Page 1 of 2 KP/0/B/1009/09 ENCLOSURE 5.6
- SUPPORT FUNCTIONS COORDINATOR
- INITIAL RESPONSE -
5.6.1 Assemble supporting materials and take to TSC. .
5.6.2 Evaluate the need to establish an alternate location Eor sample analysis.
5.6.3 Establish a count room sample priority list if emergency radiological sampling is in progress or is going to begin.
5.6.4 Initiate, as necessary, KP/0/B/1009/10, Body Burden Analysis Following Suspected Uptakes of Mixed Fission or Activation Products.
5.6.5 If the emergency is classified above the Notification of Unusual i Event category:
l 5.6.5.1 Establish alternate dosimetry issue peints for personnel L
and high range dosimetry, as necessary.
5.6.5.2 Issue blanket dose extensions for OSC personnel, to the
. limit established by the Station Health Physicist.
5.6.5.3 Provide representatives from Dosimetry and Records Control in the OSC to:
5.6.5.3.1 Record the following information on the OSC Response Personnel Dose Record Form (Enclosure 5.15) as emergency response personnel enter the OSC.
5.6.5.3.1.1 Name
! Health Physics Badge Number 5.6.5.3.1.2 5.6.5.3.1.3 Social Security Number 5.6.5.3.1.4 Exposure Class i
5.6.5.3.1.5 Birthdate 5.6.5.3.1.6 Age 5.6.5.3.1.7 Work Group 5.6.5.3.1.8 Quarterly and yearly dose to date j 5.6.5.3.1.9 Permissible lifetime dose to date f
5.6.5.3.1.10 Total lifetime dose to date l NOTE: This may be obtained at the first available opportunity.
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i Page 2 of 2 RP/0/B/1009/09 ENCLOSURE 5.6 SUPPORT FUNCTIONS COORDINATOR INITIAL RESPONSE 5.6.5.3.2 As personnel leave the OSC to enter a radiation field, dosimeters shall.be checked for rezeroing and the following information recorded on the OSC Response Personnel Dose Record Form (Enclosure 5.15):
5.6.5.3.2.1 Data and Time Out 5.6.5.3.2.2 Dosimeter Reading Out 5.6.5.3.3 As personnel return to the OSC from entering a
. radiation field, dosimeters shall be checked for rezeroing and the following information recorded on the OSC Response Personnel Dose Record Form (Enclosure 5.15):
5.6.5.3.3.1 Date and Time In 5.6.5.3.3.2 Dosimeter Reading In i
5.6.5.3.3.3 Retotal of quarterly dose 5.6.5.4 Proceed to the TSC and coordinate Support Function Response.
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Page 1 of 1 HP/0/B/1009/09
- ENCLOSURZ S.7 SUPPORT FUNCTIONS COORDINATOR
. CORTINUING RESPONSE 5.7.1 Ensure collection and retention of collected samples is adequate to reconstruct data following the emergency.
5.7.2 Acquire additional anti-contamination clothing, dosi' metry, respiratory or monitoring equipment from:
Existing Station Stock CMC Admin and Logistics Groups 5.7.3 Direct implementation of HP/0/B/1001/12, Technical Specifications Gaseous Waste Sampling and Analysis and/or HP/0/B/1009/21, Abnormal Unit Vent Sampling as necessary to collect containment and unit vent samples.
All sampling will be coordinated with OSC Health Physics personnel to determine habitability and RWP requirements.
5.7.4 Retrieve radiation instrumentation from Instrument Issue area and stage in DRC office.
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'3 Page 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.8 STAFF (DATA ANALYSIS) COORDINATOR INITIAL RESPONSE 5.8.1 Assemble supporting materials and take to TSC.
5.8.1.1 Review any assessments made using RP/0/A/5000/11, Protective Action Recommendations Without the OAC.
5.8.2 Initiate the following procedures as necessary.
5.8.2.1 HP/0/B/1009/13, Off-Site Dose Projection - Uncontrolled Release of Radioactive Material through the Unit Vent.
5.8.2.2 HP/0/B/1009/14, Health Physics Actions Following an Uncontrolled Release of Liquid Radioactive Material.
5.8.2.3 KP/0/B/1009/15, Offsite Dose Projections - Uncontrolled Release of Ganeous Radioactive Material other than through the Unit Vent.
5.8.3 Assume the duties of the Data Analysis Coordinator if the emergency is classified above the Notification of Unusual Event Category and:
5.8.3.1 Proceed to the TSC.
5.8.3.2 Initiate activation of the Field Monitoring Organization by notifying the Field Monitoring Coordinator to respond according to Enclosure 5.10 and 5.11.
5.8.3.3 Initiate the following procedures as necessary:
1 5.8.3.3.1 HP/0/B/1009/06, Alternative Method for Determining Dese Rate Within the Reactor
- Building.
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! 5.8.3.3.2 HP/0/B/1009/12, Quantifying Gaseous Release
, through Steam Relief Valves Under Post-Accident Conditions.
i 5.8.3.4 Provide special evaluation in areas such as shielding, off-site consquences of a containment loss or steam l
generator tube rupture, BBA, etc.
Page l'of 1 HP/0/B/1009/09 ENCLOSURE 5.9 STAFF (DATA ANALYSIS) COORDINATOR
. CONTINUING RESPONSE I
5.9.1 Evaluate the need to recalculate dose projections based upon:
5.9.1.1 Known changes in meteorological status (wind speed, wind _
direction, AT, precipitation).
5.9.1.2 Known changes in EMF readings.
5.9.1.3 Projected change in meteorological conditions.
S.9.2 Evaluate total effect of dose projections when making multiple releases (containment, vent releases, etc.).
5.9.3 Evaluate total effect of dose projections when releases are expected to continue for longer than two hours, or to otherwise be effected by extended evacuation times.
5.9.4 When the CMC is established, all dose projections and recommendations will be coordinated with the CMC Off-Site Radiological Support Section to assure consistency.
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Page 1 of 2 HP/0/B/1009/09
, ENCLOSURE 5.10 ,
FIELD MONITORING COORDINATOR INITIAL RESPONSE 5.10.1 Assemble supporting materials to take to TSC.
5.10.2 Initial Response
, . 5.10.2.l~ Activate the field monitoring organization by:
i 5.10.2.1.1 Notifying the TSC Radio Operator to report to the TSC and initiate HP/0/B/1009/19, Emergency Radio System Operations, Maintenance, and Communications.
5.10.2.1.2 Selecting eleven (11) Catawba Nuclear Station Field Monitoring Team (FMT) r members to be organized as follows:
Team Call Sign Number of Members Transportation Alpha 2 Land Vehicle Bravo 2 Land Vehicle Charlie 2 Land Vehicle Delta 2 Land Vehicle Echo 1 Helicopter Foxtrot 2 (Onsite Team) 5.10.2.1.3 Instruct Flfr's to complete checkout steps y from HP/0/B/1009/04, Environmental Moni-toring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Station.
NOTE: Team Foxtrot is exempt from this step.
5.10.2.2 Proceed to the TSC.
5.10.2.3 Obtain plant radiological status and evaluate the potential or existence of an off-site release of radioactive material (liquid or gaseous).
5.10.2.4 Obtain meteorological information and determine initial sample direction.
5.10.2.5 Determine the need for aerial environmental surveillance based on plant radiological status and meteorological information.
5.10.2.5.1 If immediately needed, obtain helicopter support per Enclosure 5.16, Procurement of Helicopters for Aerial Environmental Surveillance.
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Page 2 of 2 HP/0/B/1009/09 ENCLOSURE 5.10 FIELD MONITORING COORDINATOR INITIAL RESPONSE 5.10.2.5.2 If the possibility exists for future need, put helicopter support on standby per Enclosure 5.16.
5.10.2.6 Determine plume location (width) based on stability class j (establish estimated plume location on 10 mile radius map).
5.10.2.7 Dispatch on-site monitoring team, foxtrot, up to the exclusion area boundary fence at the estimated plume location.
v 5.10.2.8 Dispatch Alpha Team to the 0.5 mile radius to traverse the plume at it's estimated arc.
5.10.3 Based on stability class, wind direction, wind speed, and the time since release (time since trip), dispatch B, C, and D teams as follows:
5.10.3.1 Dispatch Bravo Team to criss-cross the left side of the plume.
5.10.3.2 Dispatch Charlie Team to criss-cross the right side of the plume.
5.10.3.3 Dispatch Delta Team to a point at the centerline of the plume. .
5.10.3.4 Instruct FMT's to take, as needed, special samples per HP/0/B/1009/04.
Page 1 of 1 KP/0/B/1009/09 ENCLOSURE 5.11 FIELD MONITORING COORDINATOR CONTINUING RESPONSE 5.11.1 Continuing Response 5.11.1.1 Maintain the 10 mile radius map by:
5.11.1.1.1 Posting current FMT locations.
5.11.1.1.2 Posting latest instrument survey results for each monitoring location.
5.11.1.1.3 Confirm and illustrate the approximate plume shape and location based on the accumulated field data. .
5.11.1.2 Continue field monitoring strategies by:
5.11.1.2.1 Reviewing plant radiological status, field data and meteorological information approximately every 15 minutes for changes which might affect field monitoring strategies.
5.11.1.2.2 Advise FMT's on public protective actions and conditions they should be aware of
(' while in the area.
5.11.1.3 Advise the Data Analysis Coordinator of field monitoring results.
5.11.1.4 Maintain an organized file of all sample results/ data generated from FMT activities.
5.11.1.5 Maintain FMT equipment and supplies including protective clothing, liquid nitrogen, etc.; and schedule shift coverage.
5.11.2 CMC Turnover 5.11.2.1 Once CMC is established, coordinate turnover of FMT's to
, CMC control.
I 5.11.2.2 Turnover of TSC FMT's to CMC Control shall occur at the intersection of SC 274 and SC 49. Should plume location interfere, alternate turnover location may be established.
5.11.2.3 Once CMC has assumed control of FMT's, notify the Data Analysis Coordinator and dissolve TSC field monitoring organization.
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Page 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.12 OSC HEALTH PHYSICS SUPERVISOR
. INITIAL RESPONSE l 5.12.1 Assemble supporting materials and take to OSC. l 5.12.2 Contact OSC Operation Supervisor and coordinate HealthI Physics support for OSC activities. Assist in implementation of RP/0/B/5000/12, Control of Assessment and Repair Teams.
5.12.3 Provide immediate job coverage as necessary. Give due consideration to the fact that plant conditions may be unstable and radiological conditions unknown.
5.12.4 Provide immediate Health Physics coverage as necessary to support
. Fire Brigade, damage control, medical emergency,and other emergency activities.
5.12.5 Direct technicians to obtain preliminary radiological information available in Control Room.
5.12.5.1 Emphasis should be placed upon determining the areas of the plcat experiencing increasing radiation levels.
5.12.6 Based upon initial Control Room indications, direct technicians to monitor and report radiological status which will support OSC activities.
5.12.7 Establish control over all OSC personnel radiation exposure and limit to blanket dose extension levels.
5.12.7.1 All activities which cause these levels to be approached or exceeded, require pre planning and coordination with TSC S&C Coordinator.
5.12.8 Direct assignment of additional dosimetry to provide adequate monitoring for the conditions expected.
5.12.9 Direct the use of protective clothing to Itsit the spread of contamination consistent with the conditions expected.
5.12.10 Obtain additional instrumentation to support OSC activities l
(Teletector, neutron instrument alpha instrument, friskers), if
- necessary.
- 5.12.11 Require each exit from OSC to Auxiliary Building be preceeded by a l briefing on task to be done and radiological conditions expected when applicable.
5.12.12 Coordinate Health Physics activities for assessment and repair teams in accordance with RP/0/B/5000/12.
5.12.13 Post blanket dose extension values.
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Page 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.13 OSC HEALTH PHYSICS SUPERVISOR CONTINUING RESPONSE 5.13.1 Maintain ro.ttine contact with TSC S&C Coordinator to provide update on OSC activities and to receive plant status reports, 5.13.2 Obtain thru Support Functions Coordinator, additional dosimetry / protective clothing / emergency kit items necessary to support OSC activ!. ties.
5.13.3 Coordinate OSC activities requiring pre-planning.
5.13.3.1 Emphasis shotid be placed upon:
DosimetryWhole Body & Extremities)
Protective C,lothing Route to and from task Respiratory equipment Need for Buddy system because of safety hazard (radiological and non-radiclogical)
Establishing dese limits and/or dose rate considerations for high exposure jobs on unknown situations Communications equipment Additional monitoring instrumentation 5.13.4 Monitor dose rate La OSC. Should General Area reach 5 mR/hr.,
initiate discussion with S&C Coordinator on the need to evacuate the OSC, should dose rate be expected to continue.
5.13.5 All RE-ENTRY efforts should consider the special problems that may exist:
High gamma fields Increased Beta fields High Contamination levels .
High airborne rad levels 1
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Page 1 of 1 RP/0/B/1009/09 ENCLOSURE 5.14 RESERVE PERSONNEL / PERSONNEL MONITORING I.EADER RESPONSE 5.14.1 Assemble all Health Physics personnel not initially required for emergency response. Non-essential personnel should be evaluated for use in the emergency.
5.14.2 Identify personnel and/or personnel monitoring teams. for the following locations.
5.14.2.1 Field Monitoring 5.14.2.2 All on-site assembly areas are identified in Station Directive 3.0.7.
5.14.2.3 PAP Area.
5.14.2.4 Construction Personnel Exit Area (Brass Gate).
5.14.2.5 Evacuation Facility (Alpha or Bravo). Two monitoring teams if both locations are used.
5.14.3 Initiate, as necessary, HP/0/B/1009/05, Personnel / Vehicle Monitoring for Emergency Conditions.
5.14.4 Initiate random monitoring of vehicles located in the upper and lower parking lots starting with vehicles nearest the affected unit. The monitoring team identified in Step 5.14.2.4 should be used for this purpose.
5.14.5 Coordinate with the TSC Surveillance and Control Coordinator on relocating personnel monitoring teams if background radiation renders normal monitoring locations unfit.
5.14.6 Supervise Health Physics efforts at the Evacuation Facility (s) as per Reference 2.2.
5.14.7 Provide direction to reserve Health Physics personnel:
5.14.7.1 Direct and control personnel in the staging area (DRC office in the Adminiss.ation Building).
5.14.7.2 Coordinate with Surveillance and Control Coordinator to provide additional manpower, as necessary.
5.14.7.3 Coordinate with Support Functions Coordinator to provide additional manpower, as necessary.
5.14.7.4 Direct activities of Field Monitoring Teams if relieved by CMC personnel.
5.14.7.5 Begin scheduling activities for Health Physics personnel.
5.14.7.6 Support OSC Supervisor with major activities as required.
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Page 1 of 1 HP/0/9/1009/09 .
ENCLOSURE 5.15 OSC RESPONSE PERSONNEL DOSE RECCRD FORM Name: HP Badge No.: .-
Social Security No.: Exposure Class:
Birthdate: Age: Work Group:
t
- Quarterly Dose to Date: ares
- Yearly Dese to Date: ares Permissible Lifetime Dose to Date: arem Total Lifetime Dose to Date: arem I Out Date/ Time Dosimeter Reading
- Quarterly Dose Total Comments In Out (mrem) In (area)
- Current Quarter Dose mrom Plus Today's Dosimeter Dose mrem.
- Current Yearly Dose arem Plus Today's Desimeter Dose mrem.
i J.
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Page 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.16 PROCUREMENT OF HELICOPTERS FOR AERIAL ENVIRONMENTAL SURVEILLANCE Inland Airways, Myrtle Beach, S.C. , is under contract to Duke Power Company to furnish one helicopter upon request and an additional helicopter within six hours following notification. Once a helicopter is requested, there is a maximum elapsed time of three hours for the helicopter to arrive at Catawba Nuclear Station or other dispatched locations.
Helicopter service is limited to daylight hours and adequate flying weather.
The helicopters will hold three people, the pilot and two passengers. To perform surveys, instrumentation may limit the passenger space.
To obtain helicopter (s) for emergency service contact:
Office Home NOTE: These contacts are in Duke Power Company Transmission Dept.,
Line Division.
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~ s Form 34731 (3-84) 1) ID No:RP/0/B/5000/13 Change (s) 4 to 5_,,, Incorporated Retype 9 2 DUKE Pok7R COMPANY PROCEDURE PRCCISS RECORD PREPARATION (2) STATION: CATAWBA (3) PROCEDURE TITI.E: NRC REPORTING REQUIREMENTS (4) PREPARED BY: Mike Bo1ch DATE: .Tn w ci . 1oA6 (5) REVIIVED BY: . Idh k ,h M DATE: /o/.8/k b Cross-DisciplinaryReviewBy:h t'-r-Af MI/ f'#.4/R:
l l (/ 0 l (6) IIMPORARY APPROVAL (II NECESSARY):
By: (SRO) Date:
By: A ,1 Date:
(7) APPROVED BY: . Date: I //
l} { */
(8) !!ISCILI.A. ECUS:
Y t/
Reviewed / Approved By: Date:
s Reviewed / Approved By: Date:
COMPI.ETION (9) DATE(S) PERIORMID:
(10) PROCEDURI COMPLETION VERITICATION:
YIS N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate?
YES N/A Listed enclosures attached?
YES N/A Data sheets attached, completed, dated and signed?
YES N/A- Charts, graphs, etc. attached and properly dated, identified and marked?
YES N/A Acceptance ersteria met?
VERITIED BY: CATE:
(11) PROCEDURI COMPLETION APPROVID: DATE:
- ~
(12) REMARKS:
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RP/0/B/5000/13 DUKE POWER COMPANY CATAWBA NUCLEAR STATION NRC NOTIFICATION REQUIREMENTS 1.0 SYMPTOMS 1.1 Plant conditions requiring NRC notification in accordance with:
10 CFR50.72,10 CFR20.205,10 CFR20.403, and 10 CFR73.71.
1.1.1 Immediate,1 Hour and 4 Hour Notifications.
1.1.2 24 Hour Notifications for Operating License Condition Deviations.
1.2 See Enclosure 4.1 f'o r determination of appropriate notification requirement.
--- 2.0 IMMEDIATE ACTIONS - ' ~
2.1 Complete one of the following enclosures:
2.1.1 Enclosure 4.2 " Checklist for Significant Event Notification"
(
2.1.2 Enclosure 4.3 " Report of Serious Physical Security Events" When reporting from Section 4.1.2.7 of Enclosure 4.1 2.2 Notify the NRC Operations Center by the following means:
2.2.1 Pri. - Emergency Notification System Phone 9I 2.2.2 Alt. 202-951-0550 or 301-427-4056 or 301-427-4259
. 2.3 Notify the NRC Region ll Office at 404-331-4503 of any event listed in Section 4.1.1.5 of Enclosure 4.1.
NOTE: No Enclosure for reporting to Region ll from Section 4.1.1.5 of Enclosure 4.1 3.0 SUBSEQUENT ACTIONS 3.1 Provide follow-up notification as described below:
3.1.1 Emergency Classes 3.1.1.1 Any further degradation in level of safety of the plant including those that require declaration of any Emergency Class, if such a declaration has not been previously made.
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r RP/0/B/5J.i:U/13 Page 2 of 2 3.1.1.2 Any change in the Emergency Class 3.1.1.3 Termination of the Emergency 3.1.2 Results of ensuing eva!uations or assessments of plant conditions 3.1.3 Effectiveness of response or protective measures taken 3.1.4 Information related to plant behavior that is not understood 3.2 Mair.tain an "Open", continuous, communications channel with the NRC Operations Center, upon request by the NRC.
3.3 Notify the following individual:
3.3.1 Compliance Engineer Primary Alternate Duty Compliance Engineer (See current Station Home:
Duty List) 3.3.2 If neither the Compliance Engineer nor the Duty Compliance Engineer can be reached then call directly to the:
NRC Resident inspector Primary - Unit 1 Primary - Unit 2 Alternate - Unit 2 Alternate - Unit 1 3.4 Upon completion of this procedure, attach a completed Procedure Process Record Form and forward to the Compliance Engineer for review prior to submission to Master File.
4.0 ENCLOSURES l
4.1 Events Requiring NRC Notification 4.2 Checklist for Serious Event Notification 4.3 Report of Serious Physical Security Events
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RP/0/B/5CC0/13 Evenw Requiring NRC Notification Enclosure 4.1 Page 1 of 6 4.1.1 Events Requiring "lMMEDI ATE NOTIFICATIONS":
Immediately after notification to states and counties and not later than one hour after the time the Emergency Class was declared.
4.1.1.1 The declaration of any of the Emergency Classes specified in the Catawba Emergency Plan 4.1.1.2 Any change from one Emergency Class to another 4.1.1.3 Termination of the Emergency
! 4.1.1.4 For any incident involving . byproduct, source or special nuclear material which may have caused or t
3 threatens to cause the following:
4.1.1.4.1 Individual Exposure 3 25 Rem Whole Body or
> 150 Rem Skin of Whole Body OC l > 375 Rem Extremities
. 4.1.1.4.2 Release of radioactive material in concentration which if averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period would exceed 5,000 times the applicable concentration of the limits specified in 10 CFR 20, Appendix B, Table ll.
4.1.1.4.3 Loss of one working week or more of the operation of any unit.
4.1.1.4.4 Damage to property in excess of $200,000.
4.1.1.5 Notification to NRC Reginal Office, Region ll, j Atlanta, GA. (see Step 2.3). Receipt of a package of radioactive materials with:
4.1.1.5.1 >0.01 uCi/100cm2 loose radioactive inatorial on the external surface or I
'5
RP/0/B/5000/13 Eve.. .s Requiring NRC Notification Enclosures 4.1 Page 2 of 6 4.1.1.5.2 >200 MR/hr. on external surface or 4.1.1.5.3 >10 MR/hr. at three (3) feet frem the external surface 4.1.2 Events Requiring "ONE HOUR REPORTS":
As soon as practical and within one hour of the occurrence.
4.1.2.1 The initiation of any nuclear plant shutdown required by Technical Specifications (i.e.
Safety Limit Violation). See notes:
NOTE: 1. The Initiation of a Shutdown is defined as, "A reduction in Power required by an action statement of Tech. Specs of any unplanned trip (automatic or manual) to Mode 3."
- 2. A Shutdown is defined (for reporting requirements) as, " Mode 3 and below".
4.1.2.2 Any deviation from a plant License Condition or Technical Specification authorized in 10CFR50.54(x) .
(Licensee may take reasonable action that departs from a license condition or a technical specification in an emergency when this action is immediately needed to protect the health and safety of the public and no action consistent 1
with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent.)
4.1.2.3 Any event or condition during operation that results in the condition of the plant, including the principle safety barriers, being seriously degraded, or results in the plant being:
4.1.2.3.1 in an unanalyzed condition that significantly compromises islant safety.
4.1.2.3.2 in a condition that is outside the
, design basis of the plant.
4.1.2.3.3 in a condition not covered by the i
plant's operating and emergency procedu res.
~
, 4.1.2.4 Any event that results or shoulci have resulted i in Emergency Core Cooling System ,(ECCS) discharge into the reactor coolant system as a 1
result of a valid signal.
i
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RP/0/B/5000/13 Events Requiring NRC Notification Enclosure 4.1 Page 3 of 6 4.1.2.5 Any event that results in a major loss of emergency assessment capability, offsite response capability, or communications capability (e.g.,
significant portion of control room indication, Emergency Notification System or Offsite Notification System).
Note: A loss of 25% of the Prompt Alerting Siren System for Catawba Nuclear Station is reportable when 19 or more sirens are reported inoperable for > 4 hou rs.
4.1.2.6 Any natural phenomenon or other external condition or any event that poses an actual threat to the safety of the plant or significantly hampers site personnel in the performance of duties necessary for the safe operation of the plant, including fires, toxic gas releases or radioactive releases.
4.1.2.7 Safeguard events as determined by security personnel and Station Management.
4.1.2.7.1 A trace investigation of a lost or unaccounted for shipment pursuant to 10 CFR 73.27.
4.1.2.7.2 An attempt (actual or suspected) to commit a theft or unlawful diversion of Special Nuclear Material.
4.1.2.7.3 Any event which significantly threatens or lessens the effectiveness of the physical security system:
NOTE: Reports of Safeguards Events should be made by Catawba Security Procedure # M,
" Reporting of Safeguards Events" .
Security Supervision will provide all information to the Operation's Shift Supervisor for NRC notification.
RP/0/B/5000/13 Evenu Requiring NRC Notification Enclosure 4.1 Page 4 of 6 4.1.3 Events Requiring "FOUR HOUR REPORTS" -
As soon as practical and within four hours of the occurrence.
4.1.3.1 Any event found while the reactor (s) is/are shutdown, that had it been found while the reactor (s) was/were in operation would have resulted in the plant, including its principle safety barriers, being seriously degraded or being in an unanalyzed condition that signifi-cantly compromises plant safety.
4.1.3.2 Any event or condition that results in manual or automatic activation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS).
(However, activation of an ESF including the RPS, that results from and is part of the preplanned sequence during testing or reactor operation need not be reported).
4.1.3.3 Any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are
. needed to:
i 4.1.3.3.1 Shutdown the reactor and maintain it in a safe shutdown condition.
4.1.3.3.2 Remove residual heat.
4.1.3.3.3 Control the release of radioactive material.
4.1.3.3.4 Mitigate the consequences of an
- accident.
4.1.3.4 Any airborne radioactive release that exceeds 2 times the applicable
- concentrations of the limits specified in i
10CFR20, Appendix B, Table il in i
unrestricted areas when averaged over a time period of one hour.
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RP/0/B/5000/13 Events Requiring NRC Notification Enclosure 4.1 Page 5 of _6__
4.1.3.5 Any liquid effluent release that exceeds 2 times the limiting combined MPC (See 10CFR20, Appendix B, Note 1.) at the point of entry into the receiving water (unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour. (Immediate Notifications made under this requirement also satisfy the require-ments of 10CFR20.403, Paragraph (a)(2) and (b)(2)). (See 4.1.1.4.2).
4.1.3.6 Any event requiring the transpcrt of a radioactively contaminated person to an offsite medical facility for treatment.
4.1.3.7 Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a News Release is planned or Notification to Other Government Agencies has been or will be made. Such an event may include an onsite fatality or inadventent release of radioactively contaminated materials.
4.1.4 Events Requiring "24 Hour Reports" 4.1.4.1 Operating License Conditions Deviations Requiring "24 Hr. Notifications":
4.1.4.1.1 Refer to Operating License 4.1.4.2 Security Events:
NOTE: Reports of Safeguards Events should be made by Catawba Security Procedure
- 106, 0 " Reporting of Safeguards Events".
Security Supervision will provide all information to the Operation's Shift Supervisor for NRC notification.
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RP/0/B/5000/13 Evenu Requiring NRC Notification Enclosure 4.1 Page 6 of 6 4.1.5 Follow-up Notifications .
4.1.5.1 During the course of the event, report:
4.1.5.1.1 Any further degradation in the level of safety of the plant or other worsening plant conditions, including those that require the declaration of any of the Emergency Classes, if such a dolcaration has not been previously made or Any change in the Emergency Class or Termination of the Emergency.
4.1.5.1.2 The results of ensuing evaluations or assessments of plant conditions 4.1.5.1.3 The effectiveness of response or protective measures taken.
4.1.5.1.4 Information related to plant-behavior that is not understood.
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RP/0/B/50CO/13 ENCLOSURE 4.2 PAG E .1, OF 4 CHECKLIST FOR SIGNIFICANT EVENT NOTIFICATION .
Complete the applicable portions of this enclosure and transmit to the NRC Operations Center as required by Enclosure 4.1.
State the following to the NRC Operations Center:
"THIS NOTIFICATION IS MADE IN ACCORDANCE WITH 10CFR50.72. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION IN NRC REGION ll MAKING THE NOTIFICATION."
- 1. a. My Name is: My title is:
My Location is: Catawba Nuclear Station,, Concerning Unit (1/2/Both)
I can be called-back at
- b. "Your Name Please"
- 2. Time of Notification Date of Notification 1
- 3. Event Classification
- Check appropriate box (s).
- a. -Emergency Plan Declaration -Other immediate Notification O- Notification of Unusual Event O- Alert O- Site Area Emergency O- General Emergency -
- b. -A "ONE-HOUR" Notification
- c. -A "FOUR-HOUR" Notification
- d. -A "24-HOUR" Notification i
- 4. Event
Description:
l Category Initiation Signal
. Reactor Trip ESF Actuation ECCS Actuation Safety injection Flow Other LCO Action Statement System Component
~ ~
Cause: Mechanical Electrical Personnel Error Procedural Inadequacy Other i
f i
- _ , _ . . . _ _ _ _ _ . _ _ _ _ _ _ _ . , _ _ . _ . . _ _ _ . , _ _ . . . ____:..____n___________ _
1 RP/0/B/5000/13 ENCLOSURE 4.2 !
PAGE 2 OF 4 i Event Time EDT/ Event Date .
Mo./ Day I Event
Description:
i l
- 5. Plant Status:
- a. Power prior to event:
- b. Power at time of report:
- c. Did all systems function as required?, (If no, Yes/No explain below.
- d. Anything " unusual" g not understood? (If yes, Yes/No explain below) .
- e. Corrective Actions:
I
- f. Mode of Operation till correction
- g. Estimate of time to restart
- 6. Outside agencies or personnel notified:
State: N.C. & S.C.
'Cou nty: York, Gaston & Mecklenburg NRC Resident , , -
(Yes) (No) (will be)
Other: Press Release:
(Yes/No)
- 7. Radiological Release: (if yes, complete this Yes/No paragraph)
- a. Release: Liquid Gaseous Planned Unplanned
- b. Location /Sou rce:
- I j
RP/0/B/5000/13 ENCLOSURE 4.2 )
PAGE 3 OF 4 !
- c. Release Rate:
- d. Duration of Release:
- e. Estimated Total Activity:
- f. Estimated Total lodine:
- g. Grab Sample:
- h. Monitor Reading:
- 1. Tech Spec Limit:
J. Personnel Exposed or Contaminated: ,
- k. Areas Evacuated:
- 1. Plant HP Backup Requested:
- m. Additional Information:
- 8. Additional Information on NC System Leaks or'S/G Tube Leaks:
- a. Sudden or Long Term Development:
- b. Start Date & Time:
- c. Leak Rate:
- d. Leak Volume:
- e. Tech Spec Limit
- f. Primary Coolant Activity:
- g. Secondary Coolant Activity:
- h. Radiation Monitor Readings:
- 1. Condenser
- 3. S/G Blowdown
RP/0/B/5000/13 ENCLOSURE 4.2 !
PAGE 4 OF 4 I
- 1. Safety Related Equipment Not Operational:
J. Special Actions Taken (if any):
,l
- i l
l l
l l
. _ , . . . - . _ _ ~ . _ . , , _ _ , _ . . - . _ . _ _ _ _ _, . _ _ _ _ _ _ _ _ _ . _ . . . . _ _ . . _ _ . . . _ , . . _ . _ . - _ _ _ . . _ _
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RP/0/B/5000/13 ENCLOSURE 4.3 PAGE 1 OF 1 REPORT OF SERIOUS PHYSICAL SECURITY EVENTS- .
DATE/ TIME OF NOTIFICATION NRC PERSON NOTIFIED State the following to the NRC Operations Center:
~ "THIS NOTIFICATION IS MADE IN ACCORDANCE WITH - - -
10C FR73.71. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION IN NRC REGION 11 MAKING THE NOTIFICATION."
My Name is: My title is:
I can be reached at .
"Your Name Please" .
- 1. *DATE OF OCCURRENCE: 3.* POWER LEVEL OF UNITS:
- 2.
- TIME OF OCCURRENCE: Unit 1 Unit 2 i'
- lf date and time of occurrence are not known, indicate the date and time of discovery.
- 4. DESCRIPTION OF EVENT:
- 5. SECURITY RESPONSE / COMPENSATORY MEASURES ESTABLISHED: -
- 6. LLEA (Local Law Enforcement Agency) NOTIFIED 7 YES NO (if Yes, name organization and telephone number)
- 7. CONSEQUENCES AT PLANT:
Description of Equipment Systems Affected
m
= ..
l Form 34731 (3 84) (1) !D No. HP/0/B/ LOO 9/1 DUKE POWER COMPANY Change (s) O to PROC 3 DURE PROCESS RECORD n incorporated PREPARATION (2) STATION CATAWBA (3)' PROCEDURE TITLE OFFSITE DOSE PROJECTIONS (4) PREPARED BY hI -" DATE IM (5) REVIEWED BY h DATE Cross Disciplinary Review By N/R V
(6) TEMPORARY APPROVAL (If No,cessary)
By (SRO) Date By ^
- Date (7) APPROVED BY DATE !
V
( //
(8) MISCELLANEOUS Reviewed / Approved By Date k
Reviewed / Approved By Date COMPLETION (9) DATE(S) PERFORMED (10) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate' i
O Yes O N/A Listed enclosures attached?
O Yes O N/A Data sheets attached, completed, dated and signed?
i Oyes O N/A Charts, graphs, etc. attached and properly dated, identified and marked?
O Yes O N/A Acceptance criteria met?
VERIFIED BY DATE i (11) PROCEDURE COMPLETION APPROVED DATE l
(12) REMARKS I
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HP/0/B/1009/18 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
- OFFSITE DOSE PROJECTIONS 1.0 Purcose To describe a method for projecting dose commitment from a noble gas and/or iodine release, through the containment, the unit vent and/or the steam relief valves, during an emergency.
2.0 References 2.1 HP/0/B/1000/10, Determination of Radiation Monitor Setpoints 2.2 HP/0/B/1009/06, Alternative Method For Determining Dose Rate Within The Reactor Building 2.3 HP/0/B/1009/14, Health Physics Actions Following an Uncontrolled Release of Liquid Radioactive Material 2.4 HP/1/B/1009/17, Unit 1 Post-Accident Containment Air Sampling System t
2.5 HP/0/B/1009/21, Abnormal Unit Vent Sampling
~
2.6 CNS Technical Specification 3.6.1.2 2.7 Offsite Dose Calculation Manual (ODCM) 2.8 Regulatory Guide 1.4, " Assumptions Used For Evaluating The Potential Radiological Consequences of a Loss of Coolant Accident For Pressurized Water Reactors" 2.9 Regulatory Guide 1.109, " Calculations of Annual Doses to Man From Routine Releases of Reactor Effluents For The Purpose of Evaluat-ing Compliance With 10 CFR Part 50, Appendix I" 2.10 NuReg-0396, EPA 520/1-78-016. " Planning Basis For The Development of State and Local Government Radiological Emergency Response Plans In Support of Light Water Nuclear Power Plants" 2.11 NuReg-0654, FEMA-REP-1,Rev.1, " Criteria For Preparation And Evaluation of Radiological Emergency Response Plans And Perparedness in Support of Nuclear Power Plants" 2.12 Letter from F.G. Hudson, September 30, 1985, re: Release Rate Information for McGuire and Catawba Nuclear Station (File:
CN-134.10) 2.13 Catawba Nuclear Station Class A Computer Model Validation (File NUC-0306)
.- , , , , . . .-.m.-- , _ . . , -_ , , , . , _ _ . _ _ - . , , , . . . - - -
HP/0/B/1009/18 Page 2 3.0 Limits and Precautions 3.1 This procedure is an alternative method of dose assessment to the Catawba Class A Atmospheric Dispersion Model computer code.
3.2 This procedure applies to releases made from Catawba Nuclear Station only. Many of the values contained in this procedure are site specific.
3.3 It is assumed that the whole body dose from an iodine release is very small compared to the thyroid dosel therefore, iodine whole body dose is not considered here.
3.4 This procedure considers all releases to be ground level releas-es.
4.0 Procedure 4.1 Meteorology Assessment 4.1.1 Acquire the following information and record on the Meteorology and Dose Assessment Worksheet(Enclosure 5.1):
4.1.1.1 Lower tower wind speed (WS) in miles per hour.
4.1.1.1.1 Use upper tower wind speed if lower tower wind speed is not available.
4.1.1.2 Upper tower wind direction in degrees from North (North = 0 ).
4.1.1.2.1 Use lower tower wind direction if upper tower wind direction is not available.
4.1.1.2.2 If the wind speed or wind direction can not be obtained from plant sys-tems, obtain them from the National Weather Service (phone 704-399-5631).
If the NWS information is unavailable, then obtain data from McGuire Nuclear Station Control Room (73 or 78, then 875, then ext 4262, or 4263, or 4264).
4.1.1.3 Temperature gradient (L1T) in degrees centigrade.
4.1.1.4 Using Enclosure 5.2, record the stability class based on 41,T.
4.1.1.4.1 Use stablity class G if the tempera-ture gradient is unknown.
4.1.1.5 If necessary, use forecasted meteorological data for calculating doses due to changing meteorolog-
HP/0/B/1009/18 Page 3 e
ical conditions.
4 4.1.2 Determgne the atmospheric dispersion paramters, X/Q (sec/m ), for .5, 2, 5 and 10 miles (record on Enclosure
- 5.1)
I 4.1.2.1 Using 41T, determine the two hour relative concentration value(CH) fr m Enclosure 5.2.
4.1.2.2 Convert the C * "**
- H X/Q = H
. WS ,
i 4.1.3 Using Enclosure 5.3, circle on Enclosure 5.1 the protective action zones (PAZ), based upon wind speed and wind direction.
4.2 Source Term Assessment - Steam Relief Valve (Enclosure 5.4) 4.2.1 Determine the Sub-Ncble Gas Release Rates, SQ ***
NG by the,following methods
( 4.2.1.1 For Unit 1-EMF 26. EMF 27, EMF 28 and EMF 29 or for Unit 2-EMF 10, EMF 11. EMF 12, EMF 13:
SQ NG
= R/hr X 1 X LBM X CF Ci VOPEN lbm R/hr t
where R/hr = EMF 26, EMF 27, EMF 20, EMF 29 or EMF 10, EMF 11, EMF 12, EMF 13 reading i
VOPEN = time the valve is open in seconds LBM = lbm released for the time the l
valve was open i CF = the correction factor per Enclo-
{
sure 5.5.
4.2.2 Determine the Noble Gas Release Rate. QNG **"
O = +
NG M 26) + SONG (EMF 27) + SONG (EMF 28) l SG (EMF 29) 4.2.3 Determine the Iodine release rate, O g(Ci/sec):
O g =O rat NG wheres
- Irat = ratio of 1131eqv./Xe133eqv. from Enclosure 5.6.
4.2.4 '"d n Enclosure 5.1.
- Record QNG GI 4.3 Source Term Assessment - Containment (Enclosure 5.7) l l
- - - . - - - , ,- --.,,..n- , ,- , _ - . - ,-,n,, , . - . - ~ , , . - -. ,._,.,,,,, ,, w , ,,,,--,--,---n.- ,,,.m. ---n,
HP/0/B/1009/19 Page 4 4.3.1 Determine the Noble Gas Concentration Factor, CNG(Ci hr),
by one of the following methods: sec ml 4.3.1.1 If EMF 39(L) d 1E7 cpm, C
NG = CPM X CF Ci.hr sec ml cpm where CPM = EMF 39(L) reading CF = the correction factor per Enclosure 5.8.
4.3.1.2 If EMF 39(L) is offscale and EMF 39(H) > 100 cpm, C
NG
= CPM X CF Ci hr see ml cpm where:
CPM = EMF 39(H) reading CF = the correction factor per Enclosure 5.9.
4.3.1.3 If EMF 39(H) is offscale, base on ENF53A or EMF 53B:
NG = R/hr X CF Ci he C
sec ml R/hr where R/hr = EMF 53 reading CF = the correction factor per Enclosure 5.10.
4.3.1.4 Based on FACS samples C * ""
- NG sec uCi where Conc = the Xe-133 equivalent sample data (uCi/ml) from Reference 2.4.
4.3.2 Determine the Iodine Concentration Factor, Cg(C1 hr), by one of the following methods: see ml 4.3.2.1 Based on 1131eqv./Xe133eqv. ration C g =C rat NG where Irat = ratio of 1131eqv./Xe133eqv. from Enclosure 5.6.
4.3.2.2 Based on EMF 40:
C g= /\ CPM X 9.82E-20 Ci he min Limin sec ml cpm
- e HP/0/B/1009/18 Page 5 where:
41 CPM = reading from EMF 40 41,mi n = the time interval for EMF 40 ob-servation(normally 15 minut S
- )
9.82E-20 = 4.OE-5 uCi/ cpm X .25 min /ft (inverse o5 EMF flow rate) X 3.53E-5 ft /mi X 1Ci/1E6uCi X 1hr/3600sec.
4.OE-5 = correlation factor for EMF 40 from Reference 2.1.
4.3.2.3 Based on PACS sample:
C g = Conc X 2.78E-10 Ci he sec uCi where Conc = I-131 equivalent sample data (uC1/ml) from Reference 2.4.
4.3.3 Determine the containment building Leak Rate, LR(ml/hr),
by one of the following methods 4.3.3.1 Based on containment pressures LR = RLR (from Enclosure 5.11) 4.3.3.2 Based on an opening in containment:
LR = OIC (from Enclosura 5.12) 4.3.3.3 Based on design leak rate: ,
4 LR = 2.449E6 (Reference 2.13) 4.3.4 Determine the Noble Gas Release Rate, Q #C'8 NG QNG " NG 4.3.5 Determine the Iodine Release Rate, Q g(C1/sec):
O g =C g X LR 4.3.6 Record Q NG and Q g on Enclosure 5.1.
4.4 Source Term Assessment - Unit Vent (Enclosure 5.13) 4.4.1 Determine the Noble Gas Concentration Factor, CNG(
by one of the following methods:
- I"$'
sec ft 4.4.1.1 If EMF 36(L) < 1E7 cpm, CNG " sec ft "3 epm l
I
HP/0/B/1009/18 Page 6 where CPM = EMF 36(L) reading CF .= the correction factor per Enclosure 5.14.
4.4.1.2 If EMF 36(L) is offscale and EMF 36(H) > 100 cpm, CNG " *I"3 sec ft cpm where:
CPM = EMF 36(H) reading CF = the correction factor per Enclosure 5.15.
4.4.1.3 If EMF 36(H) is offscale, based on EMF 54:
C = R/hr X CF Ci min g NG see ft R/hr where:
R/hr = EMF 54 reading CF = the correction factor per Enclosure 5.16.
- 4.4.1.4 Based on unit vent sample
I l C = nc X . 2E-4 Ci min m1 NG 3 l see ft uCi where Conc = the Xe-133 equivalent sample data (uCi/ml) from Reference 2.5.
i 4.4.2 Determine tne Iodine Concentration Factor, Cg(Ci ming,by l one of the following methods: sec ft i
! 4.4.2.1 Based on I131eqv./Xe133eqv. ration C y =C "*
NG where Irat = ratio of I131eqv./Xe133eqv. from Enclosure 5.6.
4.4.2.2 Based on EMF 37:
C = /\ CPM X 1.11E-13 Ci min _ min Llmin sec ft" cpm where:
L1 CPM = reading from EMF 37 Limin = the time interval for EMF 37 ob-servation(normally 15 minutes 3 1.11E-13 = 4.OE-5 uCi/ cpm X .1667 min /ft (inverse of EMF flow rate) X 1Ci/1E6uCi X 1 min /60sec.
HP/0/B/1009/18 Page 7 4.OE-5 = correlation factor for EMF 37 from Reference 2.1.
4.4.2.3 Based on unit vent sample:
C = Conc X 4.72E-4 Ci min _ml sec ft" uCi where Conc = I-131 equivalent sample data (uCi/ml) from Reference 2.5.
4.4.3 Determine the Noble Gas Release Rate. Q NG "
Opg =C "
NG where CFM = unit vent flow rate in cubic feet per min (cfm) 4.4.4 Determine the Iodine Release Rate, Qg(Ci/sec):
O g =C g X CFM 4.4.5 Record O NG and Qg on Enclosure 5.1.
4.5 Dose Assessment (Enclosure 5.1) 4.5.1 Determine the total Noble Gas and ladine Release Rates (TQ NG and TQg) from all releases.
4.5.2 Determine the Projected Whole Body Dose Rate, DRwb (rem /hr), due to noble gases for .5, 2, 5 and 10 miles:
DRwb = TO NG X/Q .6 rem m hr Ci where:
33.6 is the adult whole body dose 5 "v'r'i a factor from Reference 2.9 in rem m hr Ci 4.5.3 Determine the Projected Whole Body Dose, Dwb(rem), due to noble gasas for .5, 2, 5 and 10 mi1=ss Dwb = DRwb X 2 hr where:
dose is integrated over 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period 4.5.4 Determine the Projected Thyroid Dose Rate, DRct(rem /hr),
due to iodine for .5, 2, 5 and 10 miles:
DRet = TO X X/Q X 2.26E6 rem m I
hr Ci
l HP/0/B/1009/18 Page 8 '
where:
2.26E6 is the child thyroid dose egnversion factor from Reference 2.9 in rem m hr Ci 4.5.5 Determine the Projected Thyroid Dose, Det(rem), due to iodine for .5, 2, 5 and 10 miles:
Det = DRet X 2 he where:
dose is integrated over 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period 4.6 Protective Action Recommendations (on Enclosure 5.17):
1 4.6.1 Record the next sequential report number.
i
! 4.6.2 Circle the PA2s and the actions for the current and pre-vious protective action recommendations.
4.6.3 If the projected dose in a PAZ is < 1 rem whole body or < 5 rem thyroid, then recommend no protective action (action A).
k 4.6.4 If the projected dose in a PAZ is 1 - 5 rem whole body or 5 - 25 rem thyroid, then recommend evacuate d
children and pregnant women and shelter others(action B).
4.6.6 If the projected dose in a PAZ is > 5 rem whole body or > 25 rem thyroid, then recommend evacuate everyone (action C).
4.6.7 If the dose rate at the site boundary is >= 5.OE-4 rem /hr whole body, then recommend an Alert.
. 4.6.8 If the dose rate at the site boundary is >= .05 rem /hr whole body or >= .25 rem /hr thyroid, then recommend a Site Area Emergency if readings last 30 minutes.
4.6.9 If the dose rate at the site boundary is >= .5 rem /hr whole body or >= 2.5 rem /hr thyroid, then recommend a Site Area Emergency if readings last 2 minutes.
4.6.10 If the dose rate at the site boundary is >= 1 rem /hr whole body or >= 5 rem /hr thyroid, then recommend a General Emergency.
- 5.0 Enclosures 5.1 Sample of Meteorology, Source Term and Dose Assessment Worksheet 5.2 Two-hour Relative Concentration Factors (CH' 5.3 Protective Action Zones Determination 5.4 Sample of Source Term Assessment - Steam Relief Valves 5.5 EMF 26, EMF 27, EMF 28, EMF 29 or EMF 10, EMF 11, EMF 12, EMF 13 Noble Gas
HP/0/B/1009/18 Page 9 Correction Factor 5.6 1131eqv./Xe133eqv. Ratio 5.7 Sample of Source Term Assessment - Containment 5.8 EMF 39(L) Noble Gas Correction Factor 5.9 EMF 39(H) Noble Gas Correction Factor 5.10 EMF 53 Noble Gas Correction Factor 5.11 Containment Leakage Rate versus Pressure 5.12 Containment Leakage Rate versus Pressure and Size Opening 5.13 Sample of Source Term Assessment - Unit Vent 5.14 EMF 36(L) Noble Gas Correction Factor 5.15 EMF 36(H) Noble Gas Correction Factor 5.16 EMF 54 Noble Gas Correction Factor 5.17 Sample of Recommended Protective Action Report J
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 ,
Enclosure 5.1 Meteorology, Source Term and Dose Assessment Unit Report #
Raactor Trip / Projection based on data on /
(date/ time) (date/ time)
Prepared By:
_________________________________________________________==-----__________
M2teorology Assessment Wind Speed mph Wind Direction __ degrees from North Temperature Gradient (/1,T) C Stability Class A B-C D E F G Mile X/Q(sec/m ) CH(mph-sec/m ) Mile X/Q(sec/m ) CH(mph-sec/m )
.5 2 X/Q = CJd 4 5 WS 7 10 8 v Miles .5 1 2 4 5 7 8 PA2 AO B1 El AlC1D1F1 B2 A2 C2 D2 E2 F2 F3 A3 -
Total Source Term Assessment Steam Relief Containment Unit Vent Total (Ci/sec)
Encl. 5.4 Encl. 5.7 Encl. 5.13 Ci/sec + C1/sec + Ci/sec = = TQ NG Ci/sec + Ci/sec + Ci/sec = = TQ g Dose Assessment Adult whole body Child thyroid 4
DRwb = TO X X/Q X 33.6 DRet = TQ X X/Q X 2.26E6 Dwb = DRUS X 2 Det = DRdt X .2 Distance Dose Rate 2hr Dose Distance Dose Rate Ehr Dose mile rem /hr rem mile rem /hr rem
.5 .5 2 2 5 5 10 10 1 1 4 4 7 7 8 8 Field Data Adult whole body Child thyroid Location Dose Rate Ehr Dose Location Dose Rate Ehr Dose rem /hr rem - rem /hr rem b) Emergency Drill
--,e-----w -
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-,e ,, , , , w-- ,,---g ,----,r w - e- ---rwn---y,-v%, , - - , , w % . w- -m-----w---w-,-yr
DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 '
Enclosure 5.2 Two-hour Relative Concentration Factors (CH' Temperature Stability Distance (miles)
Gradient ( C) Class .5 2 5 10 41J < .6 A 1.4E-5 5.9E-7 2.5E-7 1.5E-7
.6 1 fly < .5 B-C 1.5E-4 1.3E-5 2.7E-6 7.8E-7
.5 i 41T < .2 D 3.8E-4 4.9E-5 1.2E-5 4.3E-6
.2 1 417 <+.4 E 6.9E-4 9.6E-5 2.5E-5 9.7E-6
+.4 1 fly <+1.2 F 1.1E-3 2.OE-4 6.3E-5 3.OE-5 ~
+1.2 1 41J G 1.8E-3 4.3E-4 1.7E-4 7.3E-5
- units are moh see m
---,---_------------------------------------------------------------------- ~
Tcmperature Stability Distance (miles)
Gradient ( C) Class 1 3 4 6 7 t
__-----------------------_--____---------_-== __-_---_--------__--------
41T'< .6 A 1.2E-6 4.1E-7 3.2E-7 2.OE-7 1.9E-7
.6 i LlT < .5 B-C 4.5E-5 6.3E-6 3.9E-6 1.9E-6 1.4E-6
.5 1 417 < .2 D 1.4E-4 2.7E-5 1.7E-5 9.2E-6 7.3E-6
.2 i 41T <+.4 E 2.5E-4 5.5E-5 3.5E-5 2.OE-5 1.6E-5
+% i 41T <+1.2 F 5.1E-4 1.2E-4 8.2E-5 5.1E-5 4.3E-5 i 2< /\T G 1.1E-3 2.7E-4 2.OE-4 1.3E-4 1.2E-4 Tsmperature Stability Distance (miles)
Gradient ( C) Class 8 9 LlT < .6 A 1.8E-7 1.6E-7 r .6 i LlT < .5 B-C 1.1E-6 8.3E-7 l
.5 1 41J < .2 D 6.OE-6 5.OE-6
.2 i 41T <+.4 E 1.3E-5 1.1E-5
+.4 i 41T <+1.2 F 3.8E-5 3.3E-5
+1.2 1 417 G 8.6E-5 7.8E-5
@ e
-- - . + y- . - --.- , - _ _ , . - - - + - - -,-.- m ww_.-.,y.y_,,,-7,-+-m. -.._..-.__.e y ---.6 -_.-9,,.. . - _ . e a- - - w g m e
- s DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.3 Protective Action Zones Determination
. Wind Direction Wind Soeed decrees from North PAZ any 0 - 360 AO 1 5 mph O - 360 A1,B1,C1.D1,E1,F1
> 5 mph O.1 - 22 C1,D1 22.1 - 73 C1 D1.El 73.1 - 100 C1,D1.E1,F1 108.1 - 120 D1.E1.F1 120.1 - 159 E1 F1 159.1 - 207 E1,F1,Al 207.1 - 247 F1,A1,81
~ ~ ~ --
247.1 - 265 A1,B1 265.1 - 298 A1,B1,C1 298.1 - 330 B1,C1 338.1 - 360 B1,C1,D1 any 0.1 - 27 C2,D2 27.1 - 69 C2 D2,E2 69.1 - 95 D2,E2,F2 95.1 - 132 D2,E2,F2,F3 i
132.1 - 144 E2,F2,F3 144.1 - 160 E2,F2,F3,A2 160.1 - 201 F2,F3,A2 201.1 - 229 F2,F3,A2 B2 229.1 - 249 F3,A2,B2 249.1 - 259 A2,92 A3 259.1 - 290 A2,B2 A3,C2 290.1 - 304 B2,A3,C2 304.1 - 331 B2.C2 331.1 - 360 B2,C2,D2 l
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 '
Enclosure 5.4 Source Term Assessment - Steam Relief Valves Report * ,
Racctor Trip / Projection baseo on data on /
(date/ time) (date/ time)
Calculations based on Melted Core LOCA NOBLE GAS boced on EMF 26 or EMF 10 SO =
CL = R/hr X 1 X lbm X Ci NG sec sec lbm R/hr
+ Encl. 5.5 boced on EMF 27 or EMF 11 SO =
Q1 = R/hr X 1 X lbm X Ci NG Ibm R/hr see see
+ Encl. 5.5 boced on EMF 28 or EMF 12 SO El " ' R/hr X 1 X lbm X Ci NG " see see Ibm R/hr '
+ Encl. 5.5 boced on EMF 29 or EMF 13 F"'.= QL = R/hr X 1 X lbm X Ci see see Ibm R/hr
+ Encl. 5.5 From all Steam Relief valves O **C NG "
IODINE From all Steam Relief valves Qg = eqv. el eqv. ra nc .6)
Ci/sec(ONG) 1
> 0 = Ci/sec 7
Emergency Drill Prepared by:
f
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,w----r y . . _ _ ---
--m.m.y-.-- , ---,--m, . . - ,w ,,--,,y--, .,w y--w, -e_m_---,,--e-yr-----v- . _ _ _ -
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.5 EMF 26, EMF 27, EMF 28, EMF 29 or EMF 10, EMF 11, EMF 12, EMF 13 Noble Gas Correction Factor Time Since Trip (hrs) Correction Factor based on Melted Core 10 3.622 12 3.971 14 4.041 _
2.8 4.029 124 3.332 148 2.647 1100 2.438 1250 2.438 1500 2.438 1720 2.438
- units in Ci lbm R/hr -
- Enclosure 5.5 is th5 c rr*1ati n fact r per Reference 2.13 X 2.83E4 mig X .41 ft X ft 1bm 1E6 m1 41 = specific gravity of steam per Reference 2.13
- 6 6
DUKF POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/10 ,
Enclosure 5.6
- I131eqv./Xe133eqv. Ratio Time Since Trip (hrs) Ratio based on LOCA Ratio based on Melted Core 10 2.74E-3 2.24E-3 1,2 3.42E-3 9.66E-3 1,4 3.82E-3 1.59E-2 le k.34E-3 2.85E-2 124 ,
4.79E-3 7.52E-2 140 4.84E-3 1.11E-1 1100 5.06E-3 1.33E-1 1250 6.55E-3 1.80E-1 1500 1.02E-2 2.90E-1 1720 1.44E-2 4.33E-1
- Enclosure 5.6 is from Reference 2.13
(
DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.7 Source Term Asssssment - Containment Report #
Reactor Trip / Projection based on data on /
(date/ time) (date/ time)
Calculations based on Melted Core LOCA Containment pressure esig LR = ml/hr LR based on Realistic Leak Rate 1" 2" 4" 6" 8" 12" 18" 34" diameter opening (circle one) Personnel Hatch opening Equipment Hatch opening Design Leak Rate (2.449E6)
NOBLE GAS C = Ci hr = cpm X C i h r. --
based on NG sec m1 sec m1 cpm EMF 39(L)
(Encl. 5.8)
C = Ci hr = cpm X Ci he --
based on NG sec m1 sec ml cpm EMF 39(H) i (Encl. 5.9)
C = Ci hr = R/hr X Ci hr -- based on NG see ml R/hr EMF 53 j sec m1 (Encl. 5.10)
C = Ci hr = uCi/mi X 2.78E-10 Ci hr -- based on NG sec uCi PACS sample see m1 i
Q * " #"
NG NG IODINE Cy = Ci hr =
Ci hr(CNG' '9"*# * '9"*
see m1 see m1 ratio (Encl. 5.6) i Cg = Ci hr = Llepm X 9.82E-20 Ci hr min --
based on sec ml 41 min sec m1 epm EMF 40 l C = Ci hr = uC1/mi X 2.78E-10 Ci he -- based on I
l sec m1 sec uCi PACS sample
! O g =C y X LR = Ci/sec I
I Emergency Drill Prepared by:
l 1
4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/8/1009/18 .
Enclosure 5.8 EMF 39(L) Noble Gas Correction Factor l Time Since Trip (hrs) Correction Factor Correction Factor based on LOCA based on Melted Core 10 6.394E-18 6.672E-17 12 6.394E-18 4.448E-17 14 6.394E-18 3.058E-17 18 6.394E-18 2.113E-17 124 6.394E-18 1.112E-17 148 6.394E-18 1.056E-17 a
1100 6.394E-18 1.390E-17 1250 6.394E-18 1.446E-17 1500 6.394E-18 9.730E-18 1720 6.394E-18 6.394E-18
- units in Ci he sec mi epm
- Enclosure 5.8 gs the correlation factor per Reference 2.13 X i
he X m
, 3600 see 1E6 ml 6
Y l
l y - . - - - - - -- p,w- - - - - - - , - -
DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 .
Enclosure 5.9 EMF 39(H) Noble Gas Correction Factor Time Since Trip (hrs) Correction Factor Correction Factor based on LOCA based on Melted Core 1,0 5.56E-14 1.429E-13 1,2 5.56E-14 1.OO3E-13 1,4 5.56E-14 1.232E-13 18 5.56E-14 1.195E-13 124 5.56E-14 7.339E-14 148 5.56E-14 6.060E-14
>100 5.56E-14 5.699E-14 l 1250 5.56E-14 5.588E-14 <
4 1500 5.56E-14 5.560E-14 1720 5.56E-14 5.560E-14
- units in Ci he see ml cpm
- Enclosure 5.9 gs the correlation factor per Reference 2.13 X hr X m 3600 see 1E6 ml m
y-a- .--e v.- - - - - y gre-----yr- --i--pr. - v-m -
I DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.10 l EMF 53 Noble Gas Correction Factor Time Since Trip (hrs) Correction Factor Correction Factor based on LOCA based on Melted Core 1,0 3.781E-10 1.190E-9 12 3.114E-10 5.894E-10 14 2.780E-10 4.726E-10 18 2.446E-10 3.392E-10 124 2.335E-10 1.890E-10 148 2.335E-10 1.668E-10 1100 2.335E-10 1.612E-10 1250 2.335E-10 1.557E-10 1500 2.335E-10 1.251E-10 1720 2.335E-10 1.056E-10
- units in Ci he sec ml R/hr --
- Enclosure 5.10 1s the correlation factor per Reference 2.13 X hr X ,3 3600 sec 1E6 ml l
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l DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.11 Containment Leakage Rate Versus Pressure PSIG ml/hr 10 2.3OOE5 12 4.536E5 14 8.316E5 18 1.397E6 110 1.591E6 111 1.663E6 112 1.714E6 113 1.764E6 114 1.800E6 115 1.836E6
- Enclosure 5.11 js the realistic leakage rate (m /sec) per Reference 2.12 X 1E6 ml/m X 3600 sec/hr.
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION -
HP/0/B/1009/18 Enclosure 5.12 Containment Leakage Rate Versus Pressure and Size Opening For 1" opening .
PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 2.209EO >5.0 3.908E8 >12.5 5.862E8
>2.50 2.889E8 >7.5 4.588E8 >15.0 6.287E8
>3.75 3.483E8 >10.0 5.268E8 For 2" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 8.496EG >5.0 1.512E9 >12.5 2.243E9
>2.50 1.121E9 >7.5 1.784E9 >15.0 2.464E9
>3.75 1.342E9 >10.0 2.022E9 For 4" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 3.144E9 >5.0 5.692E9 >12.5 8.496E9
>2.50 4.248E9 >7.5 6.797E9 >15.0 9.176E9
>3.75 5.098E9 >10.0 7.731E9 For 6" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 7.137E9 >5.0 1.291E10 >12.5 1.937E10
>2.50 9.516E9 >7.5 1.529E10 >15.0 2.124E10
>3.75 1.138E10 >10.0 1.716E10 8" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 1.257E10 >5.0 2.243E10 >12.5 3.381E10
>2.50 1.640E10 >7.5 2.634E10 >15.0 3.568E10
>3.75 1.971E10 >10.0 3.042E10 For 12" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 2.719E10 >5.0 5.012E10 >12.5 7.476E10
>2.50 3.738E10 >7.5 5.947E10 >15.0 8.156E10
>3.75 4.452E10 >10.0 6.712E10 For 18" opening PSIG ml/hr DSIG ml/hr PSIG ml/hr
>1.25 5.522E10 15.0 1.OO3E11 >12.5 1.529E11
>2.50 7.476E10 >7.5 1.189E11 >15.0 1.665E11
>3.75 8.836E10 >10.0 1.351E11 For 34" opening i
PSIG ml/hr PSIG ml/hr PSIG ml/hr 1
>1.25 1.869E11 >5.0 3.398E11 >12.5 5.132E11
>2.50 2.583E11 >7.5 4.078E11 >15.0 5.607E11
>3.75 3.093E11 >10.0 4.588E11 For Personnel Hatch opening PSIG ml/hr P3IG ml/hr PSIG ml/hr
>1.25 2.379E12 >5.0 4.690E12 >12.5 6.967E12
>2.50 3.398E12 >7.5 5.573E12 >15.0 7.646E12
>3.75 4.111E12 >10.0 6.372E12 For Equipment Hatch opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 1.121E13 >5.0 2.022E13 >12.5 3.059E13
>2.50 1.478E13 >7.5 2.379E13 >15.0 3.398E13
>3.75 1.767E13 >10.0 2.719E13
- Enclosure 5.12 is the containment leakage for an gpening size in standard cubic feet per min (scfm) X 2.83E4 ml/ft X 60 min /hr.
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION .
HP/0/B/1009/19 Enclosure 5.13 Source Term Assessment - Unit Vent Report #
Racetor Trip / Projecti.on based on data on /
(date/ time) (date/ time)
Calculations based 3 n Melted Core LOCA CFM = ft / min NOBLE GAS I = cpm X Ci min -- based on C
NG " * "3 sec ft sec ft cpm 3
EMF 36(L)
(Encl. 5.14) e cpm Ci min -- based on C
NG " I *I"3 sec ft
= X see ft cpm 3 EMF 36(H)
(Encl. 5.15T
= R/hr X Ci min ~~
C NG " * "3 sec ft sec ft R/hr 3
EMF 54 t (Encl. 5.16)
C = Ci min = uCi/ml X 4.72E-4 Ci min _ml --
based on
--- U sec ft _
see ft" uCi UV sample G yg = C yg X CFM = C1/sec IODINE Cg = Ci min 3" * "b NG' '9"*# * '9"*
sec ft sec ft ratio (Encl. 5.6)
C = Ci min = /\ cpm X 1.11E-13 Ci min _ min --
based on see ft 25 min sec ft" cpm EMF 37 C = Ci min = uCi/ml X 4.72E-4 Ci min _ml --
based on I
sec ft see ft" uCi UV sample Og = C X CFM = Ci/sec 7
Emergency Drill Prepared by:
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a DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.14 EMF 36(L) Noble Gas Correction Factor Time Since Trip (hrs) Correction Factor Correction Factor based on LOCA based on Melted Core 10 1.086E-11 1.133E-10 12 1.086E-11 7.552E-11
_ 14 _
1.086E-11 5.192E-11 2,8 1.086E-11 3.587E-11 124 1.086E-11 1.888E-11 148 1.086E-11 1.794E-11 1100 1.086E-11 2.360E-11 1250 1.086E-11 2.454E-11 1500 1.086E-11 1.652E-11 1720 1.086E-11 1.086E-11
- units in Ci min sec ft cpm
- Enclosure 5.14 is the c Srelati n fact r per Reference 2.13 X
[ 2.83E4 eigX min X ft 60 see 1E6 ml
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_ . _ - - . ._ __ - . _ . . ~ . _ , - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . , _ _ . _ _ . _ _ _ _ _ _ _ . _ _ . _ _ - _ . _ _ _ _ . _ . _ _ _ _
l 0 J DUKE POWER COMPANY' CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.15 EMF 36(H) Noble Gas Correction Factor Time Since Trip (hrs) Correction Factor Correction Factor' based on LOCA based on Melted Core 10 9.44E-8 2.426E-7 12 9.44E-8 1.704E-7 14 9.44E-9 2.091E-7 18 9.44E-8 2.030E-7 124 9.44E-9 1.246E-7 148 9.44E-8 1.029E-7 1100 9.44E-8 9.676E-9 1,250 9.44E-8 9.487E-8 1500 9.44E-8 9.440E-9 1720 9.44E-8 9.440E-8
- units in Ci min 3 sec ft cpm
- Enclosure 5.15 is the cogrelation factor per Reference 2.13 X 2.83E4 migX min X ft 60 sec 1E6 ml
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION -
'HP/0/B/1009/18 Enclosure 5.16 EMF 54 Noble Gas Correction Factor Time Since Trip (hrs) Corrsction Factor Correction Factor based on LOCA based on Melted Core 10 2.358E-4 1.887E-3 12 2.358E-4 1.179E-3 14 2.358E-4 9.905E-4 18 2.358E-4 6.367E 4 124 2.358E-4 2.931E-4 148 . 2.358E-4 2.405E-4 1100 2.358E-4 2.358E-4 1250 2.358E-4 2.358E-4 1500 2.358E-4 2.358E-4 1728 2.358E-4 2.358E-4
- units in Ci min sec ft R/hr
'
- Enclosure 5.16 is the c Srelati n fact r per Reference 2.13 X
', min X 2.83E4 ml3X ft 60 see 1E6 ml i
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/13 Enclosure 5.17 Recommended Protective Action Report To Station Health Physicist Report #
The recommended protective actions for the public are:
Current Previous
.PAZ Actions Actions AO A B C A B C ,
B1 El A B C A B C Al C1 D1 F1 A B C A B C B2 A B C A B C A2 C2 D2 E2 F2 A B C A B C F3 A B C '
A B C A3 A B C A B C A - monitor environmental radiation levels. No specific actions.
B - seek shelteri consider evacuation, especially for children and pregnant women. Monitor environmental radiation levels. Control access.
( C - evacuatel seek shelter if immediate evacuation is not possible.
s Monitor environmental radiation levels. Control access.
- - based on field data.
Emergency Classification Recommend Alert Recommend Site Area Emergency if readings last 30 minutes Recommend Site Area Emergency if readings last 2 minutes Recommend General Emergency Comments:
/
Data Analysis Coordinator Date/ Time Emergency Det11 l
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