ML20205E441
ML20205E441 | |
Person / Time | |
---|---|
Site: | Millstone ![]() |
Issue date: | 03/29/1999 |
From: | NORTHEAST NUCLEAR ENERGY CO. |
To: | |
References | |
CP-2804L, NUDOCS 9904050183 | |
Download: ML20205E441 (85) | |
Text
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- NDS Document Transmittal #128542 3/29/99 To:
Nuclear Regulatory Commission Addressee Unique # 140 ROUTINE distribution Document Control Desk Washington, D.C. 20655 The following documents have been revised. You are t rrently on distribution for these documents. Verify that all documents are included in this distribution set.
DOCUMENT REV COPlES CP 2804L 2
1 1
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050013 9904050183 990329 ~"
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PDR ADOCK 05000336
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p PDR Sign and return this form as sum as received to: Diane ONeil x2451, NDS/ COL, B433-1, Millstone or FAX (860) 444-5711.
Signature Date:
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oy MILLSTONE NUCLEAR POWER STATION CHEMISTRY PROCEDURE t
ers fj n'\\
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v s Unit 2 Rx Coolantfand(Liquid Waste PASS
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Approval:
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NP Date:
3[29 9
Effective Date:
(
0-a I eVel of Use Subject Matter Expert:
CONTINUOUS Jeffrey E. Brewer
c Millstone Unit 2 ob Unit 2 Rx Coolant and Liquid Waste PASS
[+Ref.6.17]
TABLE OF CONTENTS 1.
PURPOSE....................................................3 2.
P R E R EQ U I S ITES.............................................
4 3.
P R ECA~UTI ONS..............................................
10 4.
I N STR U CTI O NS.............................................
12 4.1 Determination of Procedure Entry Point..................... 12 4.2 PASS Preparation for Reactor Coolant Sampling.............
13 4.3 Isolation of Reactor Coolant Samples.......................
21 4.4 Reactor Coolant Pressurized 2 ml Grab Sample Isolation......
24 4.5 Reactor Coolant Depressurized 2 ml Grab Sample Isolation...
25 4.6 Reactor Coolant In-Line Sample Isolation..................
26 4.7 Stripping of Dissolved Gases..............................
28 p
4.8 Flushing PASS Prior to Reactor Coolant Sample Retrieval.....
30 d
4.9 Reactor Coolant Sample Retrieval..........................
34 4.10 Reactor Coolant 2 ml Grab Sample Retrieval................
35 4.11 Reactor Coolant Liquid In-Line Sample Retrieval...........
36 4.12 Reactor Coolant Gaseous In-Line Sample Retrieval..........
38 4.13 Analysis of Reactor Coolant Samples.......................
40 4.14 Reactor Coolant Liquid Isotopic Analysis....................
42 4.15 Reactor Coolant Total Dissolved Gas Analysis................
46 4.16 Reactor Coolant Chloride Analysis.........................
47 4.17 Reactor Coolant Boron Analysis...........................
48 4.18 Reactor Coolant Gaseous Isotopic Analysis.................
49 4.19 Reactor Coolant Gas Composition Analysis..................
51 4.20 PASS Restoration........................................
5 2 4.21 Liquid Waste Sampling and Analysis.......................
59 4.22 PASS Equipment Inventory................................
64 5.
REVIEW AND SIGNOFF.......................................
65 6.
RE FE R EN CES...............................................
65 7.
S UM MARY OF CHANGES....................................
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ATTACHMENTS AND FORMS 7s
'(v," Unit 2 Determination of Total Dissolved Gas and Sample Quantity Worksheet"...................
70, "pH Temperature Compensation"...................
71," Liquid PASS Total Dissolved Gas Worksheet"........
72
. A.tachment 4," Unit 2 Post Accident Sampli,n, g Reactor Coolant Sample Dilution Data Sheet......................
75," Unit 2 Post Accident Sampling Reactor Coolant Isotopic Worksheet"..............................
76," Unit 2 Post Accident Samplin,g Reactor Coolant Gaseous Activity Worksheet......................
77, " Unit 2 Post Accident Sam aling' Reactor Coolant Chemical Analysis WorksLieet.....................
78," Reactor Coolant PASS Sampling Equipment Inventory". 75," Unit 2 Post Accident Sampling Liquid Waste Isotopic Wo rks he e t".....................................
80 0, " Syringe Check".................................
81 p 1 "pH Probe Installation"...........................
78 O 2," Isolation Valve Independent Verification Sheet".....
79 1
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- 1. PURPOSE b
1.1 Objective l
Provide the method for sampling and analyzing Unit 2 reactor coolant and liquid waste during Station Emergency Response Organization (SERO) activation when high radioactivity lewis, due to an accident, may preclude 1
the normal (conventional) sampling method. The sampling and analysis are performed by the Liquid PASS Team as directed by the Manager of Radiological Dose Assessment (MRDA) or the Assistant Manager of Radiological Dose Assessment (AMRDA).
Per) qance and implementation of this procedure satisfies the Millstone Unit 2 Technical Specification 6.18.
1.2 Discussion This procedure provides instructions used by the Liquid PASS Team for sampling and analysis of reactor coolant, liquid waste, or both, during post accident conditions. The analyses conducted in this procedure identify the presence and amounts of various radioactive isotopes and ianic impurities contained in the reactor coolant or liquid waste. The presence and amounts of certain radioactive isotopes are indicative of the type (s) and n
extent of core damage that exists. The results obtained fram this V
procedure assist the MRDA or AMRDA in determining, an estimate of Unit 2 core damage. The Unit 2 systems which can be >ampled and the analyses which can be conducted through performance of this procedure are summarized in the following lists:
Systems Analyses Reactor Coolant LiquiiIsotopic Shutdown Cooling Gaseous Isotopic High Pressure Safety Injection Gaseous Composition Low Pressure Safety Injection Total Dissolved Gas Liquid Radwaste Chloride Boron pH The time required to collect and analyze core coolant samples is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less from the time the ADTS makes the decision to obtain a sample using PASS, except for chloride, which is 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. Gross activity is the sum ofliquid and gaseous isotopic activity.
In the event of a SIAS accident the following valves 2-RC-001, 2-RC-003 and 2-RC-045 will automatically close. If this occurs they will have to be manually over-ridden to open. This action will require SM/US direction and concurrence. These valves are over-ridden by taking them to the closed position and then to the open position.
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This procedure is linked to the Emergency Plan, therefore the Emergency C
Planning Services Department will be a cross discipline reviewer for all revisions or changes to this procedure.[Ref. 6.25]
1.3 Applicability This procedure is applicable during SERO activation when in-plant l
radioactivity levels are too high to permit reactor coolant or liquid waste sampling via the normal (conventional) method.
1.4 Frequency Performance of this procedure may be repeated periodically during SERO activation, when requested by the MRDA or AMRDA for updates or reassessments of Unit 2 reactor coolant or liquid waste PASS results.
j
- 2. PREREOUISITES 2.1 General
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2.1.1 IE drill M exercise performance, SM or US has granted permission 'a perform procedure.
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2.1.2 SERO is activated M drill simulation is in progress.
V
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2.1.3 MCRO or drill coordinator has been notified that a PASS sample will be taken.
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2.1.4 Health Physics has evaluated need for RWP.
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2.1.5 Nitrogen bottle with at least 500 psig is available at the ROM.
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2.1.6 Lab ventilation is operating.
2.1.7 Lead brick shielding has been placed at the following locations:
1 ICP
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Lab ventilation hood
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2.1.8 Computer radioisotopic analysis system in operation and calibrated.
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2.L9 ICP has been set up for PASS sample boron analysis and calibrated or calibration has been initiated.
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2.1.10 IE necessary, gas chromatograph has been set up for PASS sample l analysis and calibrated or calibration has been initiated (NA for l
liquid waste sampling).
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2.1.11 14cc gas vial has been stoppered and 100 i evacuated (NA for l
liquid waste sampling).
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2.1.12 Proper operation of sample syringes verified using instructions in 0 (NA for liquid waste sampling).
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2.1.13 pH probe has been installed IAW with Attachment 11.
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2.1.14 Radmonitor bypass key has been obtained from Operations.
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2.1.15 PASS anti-tamper key has been obtained f am Chemistry Supervisor's Office.
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2.1.16 Manager of Radiological Dose Assessment (MRDA) or the p;
Assistant Manager of Radiological Dose Assessment (AMRDA)
(,
has requested a PASS sample to include the following:
REACTOR COOLANT Check Reauested Analysis Sample Eauioment Needed Q pH PASS p'I probe and pH probe cable l
l 0 Pressurized 2 ml grab sample 2 mi grab sample chamber
)
Q Depressurized 2 ml grab sample 2 ml grab sample chamber O Reactor coolant liquid isotopic 250 1" LIQUID ISOTOPIC" syringeW O Gasisotopic 250 1" GAS ISOTOPIC" syringe and a i
stoppered and evacuated 14cc gas vial O Gas composition 500 1" GAS COMP" syringe O Total dissolved gas None 0 Chlorides 1 ml" CHLORIDES" syringe l
0 Boron
" LIQUID ISOTOPIC" syringe W V
W Same syringe is used for both LIOUID WASTE Check Requested Analysis Sample Eauioment Needed 0 Required sample aliquots for Sample bottle discharge permit preparation
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2.1.17 Sample module ventilation is in operation.
2.1.18 Anti-tamper covers have been removed from the following modules and panels:
ROM
/
Panel C103C
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Panel C103D
/
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2.1.19 2-RB-210, Degassifier Effluent Cooler Return Isolation Valve Assembly, has been verified open.
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e 2.1.20 Liquid PASS Team has completed pre-job brief as follows:
C Manager of Operational Support Center (MOSC) -
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designates, assembles, and briefs the Liquid PASS Team for implementation of this procedure Manager of Radiological Dose Assessment (MRDA) or the
/
Assistant Manager of Radiological Dose Assessment (AMRDA) - designates one the following sample points:
Check One O RCS Hot Leg O HPSI/LPSI 0 CWMT A or B O AWMT A or B If RCS hot leg sample point is designated, Manager of
/
Operational Support Center (MOSC) or designee has provided RCS system pressure.
RCS pressure:
psia Manager of Radiological Dose Assessment (MRDA) or the
/
p Assistant Manager of Radiological Dose Assessment V
(AMRDA) - designates one the following paths to receive PASS system effluent (NA for liquid waste sampling):
Check One O Rad waste (EDST) - May only receive effluent when this procedure is performed as part of a drill or exercise.
O Volume control tank Operational Support Center Assistant Radiological
/
Protection Supervisor (OSC ARPS) with the concurrence of the Manager of Radiological Consequence Assessment (MRCA) - specifies the radiological controls required for implementation of this procedure 2.2 Documents 2.2.1 CP 801/2801/3801Y," Routine Operation and Calibration of the Laboratory Ion Chromatography System" l
2.2.2 CP 801/2801/3801AD," Gas Chromatograph Operation and l
Calibration"
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r-n 2.2.3 CP 801/2801AJ," Inductively Coupled Argon Plasma Analysis" b
2.2.4 CP 801/2801/3801 AT, " Gamma Spectroscopy Counting System Maintenance and Operation" 2.2.5 RWP for PASS sample collection 2.2.6 SP 2864," Liquid Waste Discharge" 2.3 Personnel NOTE If procedure is being performed as part of a drill or exercise all personnel may not be required. Personnel required will be determined by the Emergency Planning Services Department.
2.3.1 Assistant Director, Technical Support (ADTS) 2.3.2 Manager of Radiological Dose Assessment (MRDA) 2.3.3 Assistant Manager of Radiological Dose Assessment (AMRDA) gO 2.3.4 Manager of Radiological Consequence Assessment (MRCA) t 2.3.5 Manager of Operational Support Center (MOSC) 2.3.6 Operational Support Center Assistant Radiological Protection Supervisor (OSC ARPS) 2.3.7 Manager of Control Room Operations (MCRO) 2.3.8 Liquid PASS Team consisting of at least the following personnel:
At least two Chemistry Technicians At least one Health Physics Technician
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2.4 Tools and Consumables pC 2.4.1 1 watch (range: 0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (resolution: 1 second) 2.4.2 14cc gas vial with septum l
2.4.3 1 transport cart 2.4.4 Plastic bags 2.4.5 Seven,1 liter plastic bottles 2.4.6 Plastic wrap 2.4.7 One,2 ml grab sample chamber 2.4.8
%vo,250 Isyringes 2.4.9 One,500 Isyringes i
l 2.4.10 One,1.0 mi syringes i
2.4.11 1 sample transport container J
pQ 2.4.12 One,2 ml grab sample chamber transport container 2.4.13 1 grab sample transport cart 2.4.14 Syringe transport container 2.4.15 pH probe 2.4.16 Small tipped screwdriver 2.4.17 Tongs for inverting samples 2.4.18 Flat head screwdriver 2.4.19 Large channellock pliers 2.5 Responsibilities 2.5.1 Manager of Control Room Operations (MCRO) directs valve lineups from the Control Room required for Liquid PASS Team acquisition and retrieval of samples.
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1 2.5.2 The ADTS shall make the decision to obtain a sample using n
(J PASS.
i 2.5.3 The Manager of Operationa1 Support Center designates, assembles and briefs the PASS team.
2.5.4 The Manager of Radiological Consequence Assessment specifies PASS team radiological controls.
2.5.5 The Operational Support Center Assistant Radiological Protection Supervisor assigns HP technicians and briefs the PASS team on radiological conditions.
2.5.6 The Manager of Radiological Dose Assessment or the Assistant Manager of Radiological Dose Assessment specify PASS team sampling and analysis requirements.
2.6 Definitions 2.6.1 CIRCLE - to draw a circle around 2.6.2 NOTE - To Notice or Observe with Care A
2.6.3 EDST - equipment drains sump tank l
C
- 3. PRECAUTIONS 3.1 Do not exceed 165 F influent sample flow temperature to the sample module. Ifinfluent sample flow temperature exceeds 165 F, secure sample flow to prevent damage to the sample module.
3.2 Do not exceed 2500 psig system pressure because this may damage reactor coolant PASS components.
3.3 Do not run stripping pump dry for longer than 5 minutes because this may damage the pump.
3.4 Valves 2-S-492 (V-9) and 2-S-496 (V-14) in the sample module must be closed at all times except when a syringe is inserted into either sample chamber (liquid or gas) for sample retrieval. Failure to do so may discharge radioactive reactor coolant from the sample module into the Unit 2 Primary Sample Sink Room.
3.5 Valve 2-S-499 (V-18) on the remote operating module must always be in the low now position when system pressure is greater than 415 psia to prevent high pressure spikes due to water hammer.
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3.6. In the event of unexpected results during the course of this procedure, hx place the equipment in a safe or stable condition, cease performance of further steps, and contact the MRDA or AMRDA for further instructions.
3.7 The maximum design pressure for the pH probe is 250 psig. Do not exceed 250 psig at pH probe.
3.8 PASS sample effluent may be sent to radwaste (EDST) when this procedure is performed as part of a PASS drill or exercise. PASS effluent j
must be directed to the VCr for all other performances of this procedure.
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- 4. INSTRUCTIONS
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4.1 Determination of Procedure Entry Point 4.1.1 E you have been directed to perform reactor coolant sampling and analysis, Go To Section 4.2.
4.1.2 E you have been directed to perform liquid waste sampling and analysis, Go To Section 4.21.
- End of Section 4.1 -
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r 4.2 PASS Preparation for Reactor Coolant Sampling
- C' 4.2.1 At Remote Operating Module, PERFORM the following:
a.
OPEN front panel, i
b.
ENSURE 2-OAN-253 (nitrogen supply valve) is open.
c.
CLOSE front panel.
d.
On ROM panel, PRESS the " POWER ON" button to energize the ROM.
e.
NOTE current time and RECORD time:
4 ROM was energized.
f.
ENSURE " BLOWER FUSE" and "LINE FUSE" indicator lights are not lit.
1 g.
RESET ROM timer to zero.
4.2.2 Without transport cart and syringes, PROCEED to PANEL C72 (located outside Primary Sample Sink Room).
V 4.2.3 On PANEL C72, POSITION the following valves as specified:
a.
2-RC-003 to "CLOSE" b.
2-RC-002 to "CLOSE" c.
2-LRR-61.1 to "CLOSE" 4.2.4 PROCEED into Primary Sample Sink Room.
4.2.5 At sample module PERFORM the following:
a.
OPEN sample module ventilation damper.
b.
OPEN module door.
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Valves 2-S-492 (V-9) and 2-S-496 (V-14) are closed when the handle of each valve is 3arallel to the side of the sample chamber m a i
vertical position and fu ly inserted.
{
ENSURE 2-S-492 (V-9) and 2-S-496 (V-14) are c.
closed.
d.
ENSURE 2 ml grab sample chamber is installed and its quick connects are properly engaged.
e.
CLOSE module door.
4.2.6 IE sampling HPSI/LPSI, behind primary sample sink, OPEN 2 - S - 504.
NOTE PASS sampl,e purge may be returned to the VCr or Rad Waste. MRDA or AMRDA will designate purge return location.
O.
V 4.2.7 At PASS valve manifold, PLACE 2-S-453 to POSITION 1.
4.2.8 IE sample effluent is to be directed to Equipment Drains Sump Tank PERFORM the following:
a.
OPEN 2-S-458 b.
CLOSE 2-S-460 4.2.9 IE sample effluent is to be directed to VCT PERFORM the following:
a.
OPEN 2-S-460 b.
CLOSE 2-S-458 4.2.10 CLOSE 2-S-2, Reactor Coolant Pre-Cooler Stop 4.2.11 OPEN 2-S-2, Reactor Coolant Pre-Cooler stop 1 turn.
4.2.12 At PASS valve manifold, PERFORM one of the following:
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F IE RCS Hot Leg is to be sampled, POSITION 2-S-451 to
. /
" POSITION 1" l
G IE LPSI/HPSI System is to be sampled, POSITION 2-S-452 to " POSITION 1" 4.2.13 PROCEED to reactor coolant PASS area in Unit 2 Turbine Building.
4.2.14 At PASS Nitrogen Supply bottle, PERFORM the following:
a.
OPEN nitrogen bottle isolation valve.
b.
VERIFY nitrogen supply pressure is greater than or equal to 500 psig.
ADJUST 2-GAN-235 (nitrogen bottle pressure regulator c.
valve) to obtain 400 psig downstream pressure.
4 4.2.15 On ROM, PERFORM the following:
NOTE Monitorinbuld be selected using only the "TEMPERATU$E" rotary of T1, T2, or T3 temperatures via the remote rating module sh switch. The "T1" pushbutton on the remote operating module should settm,ain depressed, regardless of the " TEMPERATURE" rotary switch rem g.
a.
ENSURE "T1" pushbutton switch is depressed.
b.
ADJUST 2-GAN-260 nitrogen pressure regulator, to obtain 80 psig as indicated on PI-1087.
c.
SET rotary temperature switch to "T1."
4.2.16 On PANEL C103C, POSITION the following valves to "CLOSE."
a.
RC-001 b.
RC-045 c.
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On PANEL C103D, POSITION the following as specified:
4.2.17 w,
l S-448 to "CLOSE" l
S-457 to "CLOSE" l
=
NOTE i
A minimum of 15 minutes is required for remote operating module warm-up.
3 4.2.18 Refer To step 4.2.1.e. and ENSURE at least 15 minutes have elapsed since remote operating module was energized.
4.2.19 At the ROM, SET temperature inoicator calibration setpoint to 212 F as follows:
a.
PRESS and HOLD temperature calibration button.
b.
E readout is greater than 165 F AND "High temp" Alarm does not flash, RELEASE temperature calibration button and CONSULT with Chemistry Supervision.
c.
E readout does not indicate 212 F, ADJUST the Cal Trim screw with screwdriver to obtain a readout of 212 E d.
RELEASE temperature calibration button.
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4.2.20 On re mote operating module, POSITION the following valves as i
(ni specified:
)
a.
2-S-482 (V-1) to " BYPASS" b.
2-S-486 (V-2) to " GRAB" c.
2-S-487 (V-3) to " GRAB SAMPLE" d.
2-S-488 (V-4) to "CLOSE" e.
2-S-489 (V-6) to "CLOSE" f.
2-S-490 (V-7) to " BYPASS" g.
2-S-491 (V-8) to " BYPASS" h.
2-S-493 (V-11) to " LIQUID" i.
2-S-494 (V-12) to " BYPASS" j.
2-S-495 (V-13) to " BYPASS" k.
2-GAN-259 (V-15) to "CLOSE" 1.
2-S-497 (V-16) to "CLOSE"
- m. 2-S-498 (V-17) to "CLOSE" E system pressure is > 400 psig 2-S-499 ("V-18") to n.
"LO-FLOW" j
o.
E system pressure is < 400 psig 2-S-499 ("V-18") to "HIGH-FLOW"
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m 4.2.21 At remote operating module, FILL sample module gas loop as follows:
POSITION the following valves as specified:
a.
- 1) 2-S-493 (V-11) to "OAS"
- 2) 2-GAN-259 (V-15) to "OPEN"
- 3) 2-S-490 (V-7) to "INLINE"
- 4) 2-S-489 (V-6) to "OPEN" b.
WAIT 30 seconds c.
POSITION 2-S-494 (V-12) to "INLINE" d.
POSITION 2-S-495 (V-13) to "INLINE" e.
WAIT 30 seconds f.
POSITION 2-S-494 (V-12) to " BYPASS" g.
POSITION 2-S-491 (V-8) to "INLINE."
h.
WAIT 30 seconds i.
POSITION 2-S-490 (V-7) to " BYPASS."
j.
POSITION 2-S-491 (V-8) to " BYPASS."
k.
WAIT 30 seconds 1.
POSITION 2-S-493 (V-11) to " LIQUID" 4.2.22 PERFORM the following to leak check the gas loop:
a.
ALLOW pressure to stabilize as indicated on PI-1067.
b.
NOTE pressure as indicated on PI-1067.
c.
CLOSE 2-GAN-259 (V-15) l d.
WAIT at least 1 minute b.
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p e.
NOTE pressure as indicated on PI-1067.
f.
E a pressure decrease is noted following the 1 minute wait, NOTIFY MRDA.
g.
POSITION 2-S-489 (V-6) to "CLOSE."
l l
4.2.23 PERFORM the following to depressurize gas sample loop:
a.
POSITION 2-S-494 (V-12) to "INLINE" b.
At S ample Module, OPEN 2-S-741, Gas Loop Vent c.
WAIT at least 10 seconds l
d.
CLOSE 2-S-741, Gas Loop Vent e.
VERIFY 2-S-556, RCS Test Connection Valve, is open.
l f.
At ROM, POSITION the following valves as specified:
- 1) 2-S-494 (V-12) to " BYPASS"
- 2) 2-S-495 (V-13) to " BYPASS"
- 3) 2-S-493 (V-11) to " LIQUID" 4.2.24 At flush module, PERFORM the following:
a.
E demineralized water flush tank level indicator light does not indicate " FULL," PERFORM the following:
- 1) THROTFLE 2-S-505, PMW To Flush Tank Fill.
- 2) While filling tank, manually PUMP flush module level indicator to obtain an accurate water level.
- 3) WHEN demineralized water flush tank indicates full, CLOSE 2-S-505, PMW To Flush Tank Fill.
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b.
POSITION the following valves as specified:
.p U
- 1) 2-S-506 to "OPEN" t-
- 2) 2-S-503 to "OPEN" l
I
- 3) 2-GAN-237 to " CLOSED" l
l
- 4) 2-S-507 to " CLOSED" l
- End of Section 4.2 -
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20 of 83 l
4.3 Isolation of Reactor Coolant Samples V
4.3.1 PRESS reset button on PASS flowmeter (FI-1062) to zero the gallons indication.
4.3.2 READ totalizer and RECORD initial totalizer reading on.
4.3.3 On PANEL C103C, PERFORM one of the following:
E RCS Hot Leg is to be sampled, OPEN RC-001 and RC-045.
E HPSI/LPSI System is to be sampled, OPEN 2-S-446.
=
4.3.4 On Remote Operating Module, PERFORM the following:
a.
POSITION 2-S-486 (V-2) to " BYPASS."
NOTE A reactor coolant flow path to the sample module is now established.
Oy b.
READ sample module radiation level on "RMSII" radiation meter and RECORD reading on Attachment 1.
c.
E sample flow is not at least 0.25 gpm, CONSULT with MRDA or AMRDA for instructions.
i l
Av y g,,. 4 W v q r/x A
Ce2804L A
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Level of Use pg pq p?{7TisirvT Rev.2 Continuous p%
21 of 83 1
I OV C AUTIO N Influent sample temperatures exceeding 165 F can damage the sample module. The "HIGH-TEMP" "T1" mdicator light on the remote operating module flashes when i(nfluen)t sample temperature exceeds 165 E d.
E HIGH-TEMP (T1) indicator light flashes, PERFORM the following:
- 1) E sampling RCS Hot Leg PERFORM the following:
CLOSE 2-RC-001 4
CLOSE 2-RC-045
- 2) E Sampling HPSI/LPSI System, CLOSE 2-S-446.
- 3) NOTIFY MRDA or AMRDA and REQUEST further instructions.
OD 4.3.5 E sampling RCS Hot Leg, PURGE 15 gallons 4.3.6 E sampling HPSI/LPSI, PURGE 5 gallons 4.3.7 PERFORM the following actions as applicable:
E acquisition of pressurized 2 ml grab sample is directed by MRDA or AMRDA, Refer To Section 4.4 and ISOLATE pressurized 2 ml grab sample via remote operating module.
i E acquisition of depressurized 2 ml grab sample is directed by MRDA or AMRDA, Refer ib Section 4.5 and ISOLATE depressurized 2 ml grab sample via remote operating module.
E acquisition of liquid in-line sample OR gaseous in-line sample is directed by MRDA or AMRDA, Refer To Section 4.6 and ISOLATE in-line sample via remote operating module.
4.3.8 On PANEL C103C, PERFORM one of the following:
TA A.
N AdTA
-.'_ REM 5FT
_/t Ce2804t Level of Use
/P%TOEF*iiij{%
/#%
/P%
22 of 83 j
7 Rev. 2 gontinuous
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l
I
(~y E RCS Hot Leg was sampled, CLOSE 2-RC-001 and V
2-RC-045.
E HPSI/LFSI System was sampled, CLOSE 2-S-446.
4.3.9 Go To Section 4.7.
- End of Section 4.3 -
i i
0 w
STOP',. '.3 ' T.k._'# " REVIEW 1.__
CP?SO4L 1,
' Level of Use T
THINK ACT Rev.2 gontinuous jpg jjegg
)pg g,'
23 of 83
j i
4.4 Reactor Coolant Pressurized 2 ml Grab Sample Isolation n
ALARA This Section should only be performed when directed by MRDA or AMRDA.
4.4.1 POSITION 2-S-482 (V-1) to " GRAB" 4.4.2 POSITION 2-S-486 (V-2) to " GRAB" 4.4.3 ALLOW approximately 60 seconds for flow to stabilize.
NOTE A pressurized sample is now trapped (isolated) in the 2 mi shielded grab sample chamber.
4.4.4 POSITION 2-S-487 (V-3) to " NORMAL AND FLUSH."
O 4.4.5 POSITION 2-S-482 (V-1) to " BYPASS."
b NOTE Flow rate should drop to zero when "2-S-486" ("V-2") is positioned to
" BYPASS."
4.4.6 POSITION 2-S-486 (V-2) to " BYPASS."
4.4.7 RECORD the following information on Attachment 1:
System sampled Grab Sample isolation date Grab Sample isolation time 4.4.8 Go To Step 4.3.7.
l l
- End of Section 4.4 -
l (O c 28 4L Level of Use
,,. 5. g7 7
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2 Continuous j;%
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peg p%
24 of 83
l 4.5 Reactor Coolant Depressurized 2 ml Grab Sample Isolation p
, Q ALARA This Section should only be performed when directed by MRDA or AMRDA.
1 4.5.1 POSITION 2-S-482 (V-1) to "ORAB" 4.5.2 POSITION 2-S-486 (V-2) to " GRAB" 4.5.3 ALLOW approximately 60 seconds for flow to stabilize.
4.5.4 POSITION 2-S-482 (V-1) to " BYPASS" 4.5.5 POSITION 2-S-487 (V-3) to " NORMAL AND FLUSH."
NOTE A depressurized sample is now trapped (isolated) in the 2 mi shielded grab sample chamber.
%)
4.5.6 RECORD the following information on Attachment 1:
System sampled Grab sample isolation date Grab sample isolation time 1
I 4.5.7 Go To Step 4.3.7.
l
- End of Section 4.5 -
' (3
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4.6 Reactor Coolant In-Line Sample Isolation l
G ALARA This Section should only be performed when directed by MRDA or AMRDA.
i 4.6.1 SET rotary temperature switch to "T2."
4.6.2 POSITION the following valves as specified:
a.
2-S-482 (V-1) to " BYPASS."
b.
2-S-486 (V-2) to " GRAB."
c.
2-S-498 (V-17) to "OPEN."
d.
2-S-487 (V-16) to "OPEN."
e.
2-S-488 (V-4) to "OPEN."
O()
4.6.3 IE flow is not at least 0.25 gpm, CONSULT with MRDA or AMRDA for guidance.
4.6.4 WAIT at least 1 minute.
4.6.5 WHEN pH reading has stabilized, RECORD the following on :
pH reading pH temperature (T2) 4.6.6 POSITION the following valves as specified:
a.
2-S-487 (V-6) to OPEN.
l b.
2-S-498 (V-17) to "CLOSE'.
c.
2-S-497 (V-16) to "CLOSE" l
l 4.6.7 Refer To Attachment 2 and DETERMINE correction factor for l
measured temperature.
tO V
CP2804L Level of Use yg 7,
7 g
Continuous p%
p%
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26 0f 83
i
,o 4.6.8 ADD correction factor to pH value and RECORD sum on V.
4.6.9 POSITION 2-S-490 (V-7) to "INLINE"
)
4.6.10 POSITION 2-S-491 (V-8) to "INLINE."
4.6.11 WAIT at least 15 seconds 4.6.12 POSITION 2-S-491 (V-8) to " BYPASS."
4.6.13 START stripping pump 4.6.14 WAIT 15 seconds 4.6.15 STOP stripping pump 4.6.16 POSITION 2-S-489 (V-6) to "CLOSE."
4.6.17 POSITION 2-S-488 (V-4) to "CLOSE."
NOTE U
A pressurized saYle of known volume is now isolated within the boundaries of 2-488 (V-4),2-S-489 (V-6), and 2-S-493 (V-11).
4.6.18 RECORD the following information on Attachment 1:
System sampled In-line sample isolation date In-line sample isolation time 4.6.19 READ totalizer and RECORD final totalizer reading on.
4.6.20 Go To Step 4.3.7.
l
- End of Section 4,6 -
G V
Level of Use
);
f A
~f CP2804L gontinuous N5T$ii' 'iH,iNR TNCV, "REViEV7 Rev.2 j;rg yg p.,q ppN 27 of 83
r l
4.7 Stripping of Dissolved Gases C
l 4.7.1 SET rotary temperature switch to "T3."
4.7.2 RECORD the following on Attachment 1:
Initial gas loop temperature (T3)
Initial gas loop pressure reading from PI-1067.
4.7.3 POSITION 2-S -493 (V-11) to " GAS" to allow liquid loop and sample chamber to depressurize.
4.7.4 NOTE the following:
Gas Loop Pressure Gas Loop Temperature (T-3) 4.7.5 POSITION the following valves as specified:
i 4.7.6 2-S-493 (V-11) to " LIQUID".
f 4.7.7 2-S-491 (V-8) to " BYPASS" v
4.7.8 2-S-490 (V-7) to " BYPASS."
4.7.9 START stripping pump.
4.7.10 WHEN 1 minute has elapsed, STOP stripping pump.
4.7.11 POSITION 2-S-493 (V-11) to " GAS".
4.7.12 WHEN Gas Loop Pressure reading (P-2) from PI-1067 stabilizes, NOTE pressure:
4.7.13 POSITION 2-S-493 (V-11) to " LIQUID".
4.7.14 POSITION 2-S-491 (V-8) and 2-S-490 (V-7) to "INLINE" 4.7.15 START stripping pump 4.7.16 WHEN 1 minute has elapsed, STOP stripping pump.
l 4.7.17 POSITION 2-S-493 (V-11) to " GAS".
mfV A
Level of Use A
A A 7 *FIEVIEVT cP2804t T Y F ' THIN F TACT Rev. 2 S
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28 or 83
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l 4.7.18 WHEN Gas Loop Pressure reading (P-2) from PI-1067 gQ stabilizes, NOTE pressure:
4.7.19 IE a pressure increase was noted between steps 4.7.12 and 4.7.18, Go To step 4.7.6.
4.7.20 POSITION 2-S-493 (V-11) to " LIQUID".
4.7.21 POSITION 2-S-490 (V-7) to " BYPASS."
4.7.22 START stripping purap.
4.7.23 POSITION the following valves as specified:
a.
2-S-491 (V-8) to " BYPASS."
b.
2-S-494 (V-12) to " BYPASS."
c.
2-S-495 (V-13) to " BYPASS."
d.
2-S-493 (V-11) to " GAS."
4.7.24 WAIT 1 minute O
4.7.25 POSITION 2-S-494 (V-12) to "INLINE" 4.7.26 POSITION 2-S-495 (V-413) to "INLINE."
4.7.27 WHEN 1 minute has elapsed, STOP stripping pump.
4.7.28 RECORD the following on Attachment 1:
Final Gas Loop Temperature (T3).
Final Gas loop pressure reading from PI-1067.
4.7.29 Go To Section 4.8.
- End of Section 4.7 -
l l
l l O f
Level of Use f
4
)7 VEVIE9T CP2804L T5TdE# '*i'HINF NAdT Rev. 2 Continuous jyg jp4k M
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29 of 83
F l
4.8 Flushing PASS Prior to Reactor Coolant Samples Retrieval
!n 4.8.1 On Remote Operating Module, POSITION the following valves are positioned as specified:
a.
2-S-482 (V-1) to " BYPASS" b.
2-S-486 (V-2) to " GRAB" c.
2-S-487 (V-3) to " NORMAL AND FLUSH" d.
2-S-488 (V-4) to "CLOSE" e.
2-S-489 (V-6) to "CLOSE" f.
2-S-490 (V-7) to " BYPASS" g.
2-S-491 (V-8) to " BYPASS" h.
2-S-493 (V--11) to " LIQUID" i.
2-S-494 (V-12) to " BYPASS" O
j.
2-S-495 (V-13) to " BYPASS" v
k.
2-GAN-259 (V-15) to "CLOSE" 1.
2-S-497 (V-16) to "CLOSE"
- m. 2-S-498 (V-17) to "CLOSE" 4.8.2 On PANEL C103D, PERFORM one of the following:
E RCS Hot Leg was sampled, OPEN "S-449."
E HPSI/LPSI System was sampled, OPEN "S-448."
(h.
Level of Use A
A A
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CP2804t Continuous
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- 7...
pC NOTE Opening "2-S-497" ("V-16") and "2-S-498" ("V-17") allows flow past the pH probe in the sample module.
l 4.8.3 At ROM, POSITION the following:
a.
2-S-498 (V-17) to "OPEN" b.
2-S-497 (V-16) to "OPEN" c.
2-S-488 (V-4) to "OPEN" d.
2-S-499 (V-18) to "HI-FLOW."
NOTE A flow should be evident on remote o when Flush Pump P-155 is running. perating module " FLOWMETER" 4
O 4.8.4 On Panel C103D, POSITION " FLUSH PUMP P-155" to "ON."
V 4.8.5 START the stripping pump NOTE The following flush times may vary according to the activity of the samples required.
4.8.6 WAIT 2 minutes.
4.8.7 CYCLE 2-S-488 (V-4) with its final position being open.
l NOTE Radiation level in sample module should decrease markedly as sample is flushed from sample module piping.
4.8.8 MONITOR flow and radiation levels to assess flush effectiveness.
A A
A 3
CP2804L Level of Use v fop 7 TfMINF TACT 7 TEViiW Rev. 2 s
gOntinUOUS jpg sq p
M 31 of 83
I
.,o 4.8.9 POSITION the following valves as specified:
(v a.
2-S -489 (V-6) to "OPEN"
)
b.
2-S-497 (V-16) to "CLOSE" l
c.
2-S-498 (V-17) to "CLOSE" 4.8.10 WAIT 1 minute.
4.8.11 CYCLE 2-S-489 (V-6) several times with its final position being open.
1 4.8.12 POSITION 2-S-493 (V-11) to " GAS."
4.8.13 WAIT 1 minute.
l 4.8.14 STOP stripping pump.
4.8.15 POSITION the following valves as specified:
a.
2-S-489 (V-6) to "CLOSE" b.
2-S-486 (V-2) to " BYPASS" c.
2-S-488 (V-4) to "CLOSE" 4.8.16 WAIT 1 minute.
4.8.17 POSITION 2-S-482 (V-1) to " GRAB" 4.8.18 POSITION 2-S-486 (V-2) to " GRAB" 4.8.19 FLUSH for 60 ceconds 4.8.20 PERFORM the following on PANEL C103D:
a.
POSITION " FLUSH PUMP P-155" to "OFE" b.
PERFORM one of the following:
IE RCS Hot Leg was sampled, CLOSE "S-449."
l IE HPSI/LPSI System was sampled, CLOSE "S-448."
3 1 (0
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i
-n 4,8.21 Go To Section 4.9 ks
- End of Section 4.8 -
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4.9. Reactor Coolant Sample Retrieval l Chem Tech l
4.9.1 OBTAIN the following items and PROCEED to sample module in Primary Sample Sink Room:
PASS transport cart Prepared syringes
__l HP iecn l" 4.9.2 PERFORM a rapid radiation survey of sample module area to ensure radiation level is less than level specified in radiological controls.
l Chem Tech l
4.9.3 E radiation level is greater than or equal to level specified in radiological controls, Refer To Section 4.8 and PERFORM PASS flush.
4.9.4 PERFORM the following actions as applicable:
E acquisition of pressurized 2 mi grab sample or depressurized 2 ml grab sample is directed by MRDA or AMRDA, Refer To Section 4.10 and RETRIEVE 2 ml grab sample from sample module.
Oy E acquisition of liquid in-line sample is directed by MRDA or AMRDA, Refer To Section 4.11 and RETRIEVE liquid in-line sample from sample module.
E acquisition of gaseous in-line sample is directed by MRDA or AMRDA, Refer To Section 4.12 and RETRIEVE gaseous in-line sample from sample module.
4.9.5 RETURN to chemistry lab with transport cart and samples.
4.9.6 Go To Section 4.13.
- End of Section 4.9 -
(3
,egTg7 x9.A A.
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3af83
L p 4.10 Reactor Coolant 2 ml Grab Sample Retrieval kJ ALARA This Section should only be performed when directed by MRDA or AMRDA.
4.10.1 PROCEED to Primary Sample Sink Room 4.10.2 OPEN module door.
4.10.3 GRAB unlatching knob and PULL slide tray outside of sample module.
4.10.4 DISCONNECT flexible hoses from grab sample valve operator.
4.10.5 LIFT 2 ml grab sample chamber from slide tray and PLACE in transport contam, er.
4.10.6 PLACE lid on transport container.
f]
4.10.7 PLACE spare 2 mi sample chamber on slide tray.
v 4.10.8 ENSURE 2 ml grab sample chamber is located so that quick connect collars are properly positioned in yoke and 2 mi grab sample chamber is pressed firmly down onto slide tray.
4.10.9 CONNECT flexible hoses to grab sample chamber air operator.
4.10.10 ENSURE blue quick connects on grab sample chamber air operator are mated.
4.10.11 PUSH slide tray, with 2 ml grab sample chamber, back into sample module until liquid quick connects latch.
4.10.12 Go To step 4.9.4.
4.10.13 IE no further samples are to be obtained, CLOSE module door.
l
- End of Section 4.10 -
l
\\
O N
Level of Use ygT P7 'T F % V 'W EF R v.2 Continuous pq pq pg pg 3g of g3
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4.11 Reactor Coolant Liquid In-Line Sample Retrieval C-ALARA This Section should only be performed when directed by MRDA or AMRDA.
4.11.1 PROCEED to Primary Sample Sink Room 4.11.2 OPEN sample module door.
4.11.3 INSERT "LIQU'D ISOTOPIC" syringe gently into brass needle guide until syringe needle is bottomed.
l 4.11.4 OPEN 2-S-G2 (V-9) by gently pulling valve handle out to its stop.
4.11.5 COMPLETE insertion of " LIQUID ISOTOPIC" syringe needle into brass needle guide until syringe needle nut mates into needle guide slot.
ALARA 1.
Do not unscrew syringe nosecap more than 2 turns. Excessive turns will disengage nosecap and needle from syringe.
2.
Steps 4.11.6 through 4.11.9 should be performed rapidly to minimize exposure.
4.11.6 WITHDRAW approximately 100 pl liquid sample.
4.11.7 UNSCREW syringe body 2 turns counterclockwise to lock sample syringe.
4.11.8 WITHDRAW " LIQUID ISOTOPIC" syringe carefully and CLOSE 2-S-492 (V-9) as syringe is removed.
4.11.9 PLFE " LIQUID ISOTOPIC" syringe in transport container.
4.11.10 INSERT " CHLORIDES" syringe gently into brass needle guide until syringe needle is bottomed.
4.11.11 OPEN 2-S-492 (V-9) by gently pulling valve handle out to its
(
)
stop.
'5IOP ')THI$F N[ACIT "5EVIEW k
/3 CP2804L Level of Use i
Rev.2 gOntinUOUS
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36 of 83
l l
gm 4.11.12 COMPLETE insertion of" CHLORIDES" syringe needle into G
brass needle guide until syringe needle nut mates into needle guide slot.
ALARA 1.
Do not unscrew syringe nosecap more than 2 turns. Excessive turns will disengage nosecap and needle from syringe.
2.
Steps 4.11.13 through 4.11.16 should be performed rapidly to minimize exposure.
l l
4.11.13 WITHDRAW approximately 1.0 mi liquid sample 4.11.14 UNSCREW sviinge body 2 turns counterclockwise to lock sample syrmge.
4.11.15 WITHDRAW " CHLORIDES" syringe carefully and CLOSE 2-S-492 (V-9) as syringe is removed.
4.11.16 PLACE " CHLORIDES" syringe in transport container.
i A
4.11.17 Go To step 4.9.4.
C 4.11.18 IE no further samples are to be obtained, CLOSE cample module door.
- End of Section 4.11 -
(^g i
iJ Level of Use A
A A
A CP2804L Continuous
'@rF NAiNiP NAcf7 Tdviiw Rev.2 peg M
h M
37 0f 83
(m.
4.12 Reactor Coolant Gaseous In-Line Sample Retrieval LJ ALARA This Section should only be performed when directed by MRDA or AMRDA.
4.12.1 PROCEED to Primary Sample Sink Room 4.12.2 OPEN sample module door.
4.12.3 INSERT " GAS ISOTOPIC" syringe gently into brass needle guide until syringe needle is bottomed.
4.12.4 OPEN 2-S-496 (V-14) by gently pulling valve handle out to its stop.
4.12.5 COMPLETE insertion of " GAS ISOTOPIC" syringe needle into brass needle guide until syringe needle nut mates into brass needle guide slot.
ALARA 1.
Do not unscrew syringe nosecap more than 2 turns. Excessive turns will disengage nosecap and needle from syringe.
2.
Steps 4.12.6 through 4.12.12 should be performed rapidly to minimize exposure.
4.12.6 WITHDRAW approximately 100 1 gas sample.
4.12.7 UNSCREW syringe body 2 turns counterclockwise to lock sample syringe.
4.12.8 WITHDRAW " GAS ISOTOPIC" syringe carefully and CLOSE 2-S-496 (V-14) as syringe is removed.
4.12.9 RECORD volume of gas sample transferred to syringe (V ) on t.
4.12.10 INSERT needle into stoppered 14cc gas vial.
4.12.11 UNLOCK syringe and INJECT gas contents into stoppered 14cc
(]
gas vial.
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38 of 83
(m 4.12.12 PLACE " GAS ISOTOPIC" syringe and 14cc gas vial in transport y
container.
4.12.13 IE gas composition sample is required, PERFORM the following:
a.
INSERT " GAS COMP" syringe gently into brass needle guide until syringe needle is bottomed.
b.
OPEN 2-S-496 (V-14) by gently pulling valve handle out to its stop.
c.
COMPLETE insertion of" GAS COMP" syringe needle into brass needle guide until syringe needle nut mates into brass needle guide slot.
ALARA 1.
Do not unscrew syringe nosecap more than 2 turns. Excessive turns will disengage nosecap and needle from syringe.
2.
Steps 4.12.13d. through 4.12.13g. should be performed rapidly to mimmize exposure.
p
(,j d.
JHDRAW approximately 500 1 gas sample e.
UNSCREW syringe body 2 turns counterclockwise to lock sample syringe.
f.
WITHDRAW " GAS COMP" syringe carefully and CLOSE 2-S-496 (V-14) as syringe is removed.
g.
PLACE " GAS COMP" syringe in transport container.
4.12.14 Go To step 4.9.4.
4.12.15 IE no further samples are to be obtained, CLOSE sample module door.
- End of Section 4.12 -
CS C 28 Level of Use 7
7, g
,2 Continuous pg pg pg 7%
39 of 83
4.13 Analysis of Reactor Coolant Samples C
l Chem Tech l
4.13.1 E retrieved, PLACE -2 mi shielded grab sample and transport container in properly shielded location for future off-site transport.
l HP Tech l
4.13.2 E liquid in-line samples OR gaseous in-line samples were retrieved, DETERMINE handling requirements as follows:
a.
OPEN transport container cover and MEASURE contact dose rate.
b.
E dose rate is greater than or equal to 1 R/hr, NOTIFY OSC ARPS and REQUESTinstructions for handling.
E dose rate is less than 1 R/hr, DIRECT Chemistry c.
Technicians to handle samples as normal radioactive samples and to minimize radiation exposure when performing required analyses.
NOTE o
Analys,is outlined in the following Sections may be performed concurrently y
as equipment and personnel permit.-
l Chem Tech l
4.13.3 Refer To the following sections as applicable and PERFORM analysis:
Section 4.14, " Reactor Coolant Liquid Isotopic Analysis" Section 4.15," Reactor Coolant Total Dissolved Gas Analysis" Section 4.16," Reactor Coolant Chloride Analysis"
=
Section 4.17," Reactor Coolant Baron Analysis" Section 4.18," Reactor Coolant Gaseous Isotopic Analysis" Section 4.19," Reactor Coolant Gas Composition Analysis" 4.13.4 WHEN analysis are complete, REPORT results to MRDA or AMRDA.
4.13.5 COMPLETE applicable Attachments.
AU b
h f
JA CP2804L Level of Use gontinuous N 5t6 V Thl F N AC Y ' T E iE W Rev.2
/F%
9%
/%
p'%
40 of 83
.p 4.13.6 E copies of results are requested, FAX or SEND copies of the
.Q applicable Attachments or isotopic printouts to requesting individuals:
4.13.7 FORWARD original and copy of completed attachments and gamma spectrometer printouts to Chemistry Supervision.
ALARA High-level (greater than or equ radioactive waste samples cannot be disposed of m, al to 100 mrem /hr) hot sink.
the chemistry lab 4.13.8 E any diluted sample bottles measuring greater than or equal to 100 mR/hr on contact were prepared in step 4.14.5, PERFORM the following:
a.
REQUEST OSC ARPS to provide storage instructions for sample bottles, b.
STORE sample bottles as directed by OSC ARPS.
- End of Section 4.13 -
1 Level of Use A
A A
A I
CP2804L i
Continuous T5 tov 'TTUWF NACF"REViff Rev. 2 p%
p%
p%
p%
41 of 83
4.14 Reactor Coolant Liquid Isotopic Analysis
- V l Chem Tech l
- 4.14.1 PREPARE 20 ml " ISOTOPIC ORIGINAI" sample bottle as follows:
a.
TARE 20 mi sample bottle.
i b.
ADD 10 ml DI water to sample bottle, c.
RECORD DI water mass on Attachment 7.
i d.
TARE 20 ml sample bottle with water.
ALARA Steps 4.14.1 e. through k. should be performed rapidly to minimize exposure.
I e.
REMOVE " LIQUID ISOTOPIC" syringe from syringe transfer container.
A f.
UNLOCK syringe and INJECT contents of" LIQUID l
b ISOTOPIC" syringe into sample bottle.
g.
RECORD 100 I sample mass on the following: (M d d
h.
CIRCLE " Isotopic Original" on Attachment 4.
i.
PLACE empty " LIQUID ISOTOPIC" syringe in plastic bag and SEAL bag.
j.
PLACE sealed plastic bag in properly shielded location for future disposal.
k.
Using tongs, INVERT sample bottle several times to mix.
1.
WRAP " ISOTOPIC ORIGINAI" bottle in plastic wrap.
l l HP Tech l
- 4.14.2 MEASURE contact dose rate of" ISOTOPIC ORIGINAI" (n
bottle.
T5 7 T A
- YA6T ht CP2804L A
A Level of Use THINI(
7 TEVIE%T Rev.2 gontinuous ja jjg pjg jp$
. 2 of 83
i l
O l Chem Tech l: 4.14.3 E contact dose rate of sample bottle is greater than or equal to Q
25 mR/hr, Go To step 4.14.5.
4.14.4 E contact dose rate of " ISOTOPIC ORIGINAL" bottle is less than 25 mR/hr, Go To step 4.14.6.
4.14.5 DILUTE sample using 1:1000 (solute: solvent) dilution factor as follows: [+Ref. 6.18]
TRANSFER 1.0 ml from bottle containing sample (solute a.
bottle) into 1 liter bottle filled with DI water (solvent bottle) and CAP bottle.
b.
PLACE solute bottle in plastic bag and SEAL bag.
c.
STORE solute bottle in shielded location.
d.
Using tongs, INVERT solvent bottle several times to mix.
LABEL solvent liter bottle either "15t, "2nd, "3rd, u4th,"5th,
]
e.
"6th, or "7th DILUTION," as applicable, for the 1:1000 dilution being performed.
(7 f.
CIRCLE either "1st, "2nd, "3rd, a4th, "5th, "6th, or 7th a
V Dilution"in Sample Dilution column on Attachment 4, as applicable, for the 1:1000 dilution being performed.
l HP Tech l
g.
MEASURE contact dose rate of solvent liter bottle.
l Chem Tech l
h.
E contact dose rate of solvent liter bottle is less than 25 mR/hr, Go Tb step 4.14.6.
i.
E contact dose rate of solvent liter bottle is greater than or equal to 25 mR/hr, Go To step 4.14.5 a..
4.14.6 DETERMINE reactor coolant liquid isotopic activity as follows:
a.
PLACE 2.5 cm shelf in detector to be used for reactor coolant liquid isotopic analysis.
l C
yh y
s, mk.L d
C Level of Use R.2 l
Continuous pq pg 43 0f 83 l
n b.
Using the following information, Refer To l
CP 801/2801/3801 AT, " Gamma Spectroscopy Counting System Maintenance and Operation," and ANALYZE t
sample:
]
Closed cave Applicable geometry for sample container and shelf being used Five minute count time j
General library Sample mass corresponding to the last circled sample dilution on Attachment 4 in gms Inline sample date and time as recorded on Attachment 1 c.
IE dead time is greater than or equal to 20%, PERFORM the following:
- 1) ABORTcount.
- 2) Go To step 4.14.5.
p
- d.. STORE sample bottle in shielded location.
J e.
DETERMINE background as follows:
- 1) Using the following information, Refer ib CP 801/2801/3801 AT, " Gamma Spectroscopy Counting System Maintenance and Operation," and PERFORM background count on detector that was used for reactor coolant liquid isotopic analysis.
Closed cave
=
Applicable geometry for shelf that was used a
Five minute count time General library Sample mass corresponding to the last circled sample
=
dilution on Attachment 4
- 2) RECORD allidentified isotopes and their associated background activity levels in pCi/gm on Attachment 5.
' 13 V
Level of Use
[
f f
J CP2804L TsTbF '_TH E ac r "mdEW Rev.2 Continuous M
pg M
M 44 of 83
f.
Refer To Attachment 5 and CALCULATE reactor coolant s
liquid isotopic activity as follows:
- 1) Refer To reactor coolant liquid isotopic printout and RECORD all identified isotopes and their associated activitylevelsin Ci/gm.
- 2) For each isotope listed, SUBTRACT background activity and RECORD asisotope activityin Ci/gm.
- 3) ADD isotope activities and RECORD as total isotope activityin Ci/gm.
4.14.7 Go To step 4.13.3 and COMPLETE any remaining analysis, j
- End of Section 4.14 -
G G
l i
I AV Level of Use g
g
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CP2804L TtoF 'TAINF *p~j y bisF s
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pg 45 of 83
4.15 Reactor Coolant Total Dissolved Gas Analysis 4.15.1 Refer To one of the following and CALCULATE total dissolved gas:
Computer program 4.15.2 RECORD total dissolved gas in cc/kg on Attachment 1.
4.15.3 Go To step 4.13.3 and COMPLETE any remaining analysis.
- End of Section 4.15 -
/
. Q'
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n 4.16 Reactor Coolant Chloride Analysis I
N) 4.16.1 REMOVE " CHLORIDES" syringe from syringe transfer container.
4.16.2 INJECT contents of" CHLORIDES" syringe into small test tube J
]
4.16.3 Refer To CP 801/2801/3801Y," Routine Operation and Calibration of the Laboratory Ion Chromatography Systems," and ANALYZE sample for chlorides.
r 4.16.4 PLACE empty " CHLORIDES" syringe in plastic bag and SEAL bag.
1 4.16.5 PLACE sealed plastic bag in properly shielded location for future I
disposal.
4.16.6 RECORD chloride concentration in ppm on Attachment 7.
4.16.7 Go To step 4.13.3 and COMPLETE any remaining analysis.
p.,
- End of Section 4.16 -
i i
l l
i Level of Use b
i C 8
,9gr y gg 7,
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Continuous pq pg jfg fyg 47 0f 83 l
m 4.17 Reactor Coolant Boron Analysis 4.17.1 WHEN sample bottle labeled " ISOTOPIC ORIGINAI" is no longer needed for isotopic analysis, Refer 7b CP 801/2801 AJ,
" Inductively Coupled Argon Plasma Analysis" and ANALYZE sample bottle for boron.
4.17.2 PLACE " ISOTOPIC ORIGINAI" sample bottle in plastic bag and SEAL bag.
4.17.3 PLACE sealed plastic bag in properly shielded location for future disposal.
4.17.4 Refer To Attachment 7 and CALCULATE boron concentration in ppm.
4.17.5 Go To step 4.13.3 and COMPLETE any remaining analysis.
- End of Section 4.17 -
O(d C'
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Level of Use N$
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Rev.2 7
go jpg %g 'pg Continuous 43 0r g3
n 4.18 Reactor Coolant Gaseous Isotopic Analysis 4.18.1 WRAP stoppered 14cc vial in plastic wrap.
4.18.2 PLACE sample on 2.5 cm shelf.
4.18.3 DETERMINE gas isotopic activity as follows:
a.
Using the following information, Refer To CP 801/2801/3801 AT, " Gamma Spectroscopy Counting System Maintenance and Operation," and ANALYZE sample:
Open cave Applicable geometry for shelf being used Five minute count time Generallibrary
=
Sample in-line isolation date and time as recorded on j
Sample quantity as calculated on Attachment 1 O(j b.
IE dead time is greater than or equal to 20%, PERFORM the following:
- 1) ABORTcount.
NOTE There are 3 shelves available for this count. They are the 2.5 cm, the 10 cm and the 30 cm shelves.
- 2) REPLACE shelf with next higher shelf.
- 3) Go To step 4.18.3.a.
c.
PLACE empty " GAS ISOTOPIC" syringe and 14cc vial in labeled plastic bag and SEAL bag.
d.
PLACE sealed plastic bag in source locker for future disposal.
O. g, dNA I m)EVIEW
- ) TOP CP2804L L
Level of Use L
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R Rev. 2 S
gOntinUOUS a
jyak
@ of 83
n e.
DETERMINE background as follows:
(
- 1) Using the following information, Refer To CP 801/2801/3801 AT, " Gamma Spectroscopy Counting System Maintenance and Operation," and PERFORM background count on detector that was used for gas isotopic analysis.
Open cave Applicable geometry for shelf that was used Five minute count time Generallibrary Sample quantity as calculated on line 14 of
- 2) RECORD all identified isotopes and their associated background activity levels in Ci/gm on Attachment 6.
f.
Refer To Attachment 6 and CALCULATE gas activity as follows:
- 1) Refer To gas isotopic printout and RECORD all identified isotopes and their associated activity levels in Ci/gm.
- 2) For each isotope listed, SUBTRACT background activity from printout activity and RECORD as isotope activity in pCi/gm.
l
- 3) ADD isotope activities and RECORD as " Total Gaseous Activity."
4.13.4 Go To step 4.13.3 and COMPLETE any remaining analysis.
- End of Section 4.18 -
(
Level of Use A
A f
A CP2804L W Mir Tevin Rev.2 7sP "M%
9%
p%
50 0f 83 Continuous p%
I i
g s.
4.19 Reactor Coolant Gas Composition Analysis (s
4.19.1 REMOVE " GAS COMP" syringe from transport container.
{
l 4.19.2 Refer To CP 801/2801/3801 AD, " Gas Chromatograph," and PERFORM the following analyses on sample:
i l
Hydrogen analysis Oxygen analysis 4.19.3 PLACE empty " GAS COMP" syringe in plastic bag and seal bag.
4.19.4 STORE sealed plastic bag in properly shielded location for future disposal.
4.19.5 RECORD results of gas composition analysis on bottom of.
4.19.6 Go lb step 4.13.3 and COMPLETE any remaining analysis.
- End of Section 4.19 -
(m.
\\v i
LJ Level of Use dL d1 A
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i 4.20 PASS Restoration 1
J NOTE Performance of this section prepares the reactor coolant PASS and sample chambers for the next sampImg by removing (flushing) existing i
l contamination from samphng pipmg and equipment.
4.20.1 PROCEED to PASS sampling area in Unit 2 Thrbine Building.
4.20.2 IE demineralized water flush tank level indicator light doer :.
indicate " FULL," PERFORM the following:
a.
THROTTLE 2-S-505, PMW To Flush Thnk FiE.
]
b.
While filling tank, manually PUMP flush module level indicator to obtain an accurate water level.
c.
WHEN demineralized water flush tank indicates full, CLOSE 2-S-505, PMW To Flush Tank Fill.
4.20.3 On Remote Operating Module, POSITION the following valves g
as speciried:
a.
2-S-482 (V-1) to " BYPASS" b.
2-S-486 (V-2) to " GRAB" c.
2-S-487 (V--3) to " GRAB SAMPLE" d.
2-S-488 (V-i) to "CLOSE" e.
2-S-489 (V-6) to "CLOSE" f.
2-S-490 (V-7) to "INLINE" g.
2-S-491 (V-8) to " BYPASS" h.
2-S-493 (V-11) to " GAS" l
i.
2-S-494 (V-12) to " BYPASS" l
j.
2-S-495 (V-13) to " BYPASS" O
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2-GAN-259 (V-15) to "CLOSE" 1.
2-S-497 (V-16) to "CLOSE"
- m. 2-S-498 (V-17) to "CLOSE" n.
2-S-499 (V-18) to "HI-FLOW" i
4.20.4 On PANEL C103D, PERFORM the following:
a.
PERFORM one of the following:
E RCS Hot Leg was sampled, OPEN "2-S-449."
E HPSI/LPSI System was sampled, OPEN "2-S-448."
4.20.5 POSITION the following valves as specified:
a.
2-S-489 (V-6) to "OPEN" b.
2-S-498 (V-17) to "OPEN" c.
2-S-497 (V-16) to "OPEN"
[s\\
d.
2-S-488 (V-4) to "OPEN" 4.20.6 POSITION " FLUSH PUMP P-155" to "ON."
l NOTE j
A flo,w should be evident on " FLOWMETER"when stripping pump is runmng.
4.20. /
START stripping pump 4.20.8 WAIT at least 3 minutes 4.20.9 POSITION 2-S-493 (V-11) to " LIQUID."
l 4.20.10 POSITION 2-S-491 (V-8) to "INLINE."
j 4.20.11 STOP stripping pump 4.20.12 WAIT at least 3 minutes d
h
[
l4 CP2804L Level of Use T5TOF 'YkiWF NAbV 'ii. 'iV7 Rev.2 EVl gOntinUOUS 4
9 83
n 4.20.13 POSITION the following valves as specified:
a.
2-S-490 (V-7) to " BYPASS" b.
2-S-491 (V-8) to " BYPASS" c.
2-S-486 (V-2) to " BYPASS" 4.20.14 Walt"least 30 seconds 4.20.15 POSITION the following valves as specified:
a.
2-S-488 (V-4) to "CLOSE" b.
2-S-498 (V-17) to "CLOSE" c.
2-S-497 (V-16) to "CLOSE" d.
2-S-489 (V-6) to "CLOSE" e.
2-S-482 (V-1) to " GRAB" f.
2-S-486 (V-2) to " GRAB" G7 D
4.20.16 FLUSH for at least 3 minutes 4.20.17 POSITION 2-S-487 (V-3) to " NORMAL AND FLUSH."
1 4.20.18 On Panel C103D, POSITION " FLUSH PUMP P-155" to "OFE" 4.20.19 On flush module, CLOSE "2-S-506".
4.20.20 On PANEL C103D, PERFORM one of the following:
IE RCS Hot Leg was sampled, CLOSE "2-S-449."
IE HPSI/LPSI System was sampled, CLOSE "2-S-448."
4.20.21 PERFORM nitrogen flush of gas loop as follows:
a.
POSITION 2-S-486 (V-2) to "ORAB."
b.
OPEN 2-S-489 (V-6).
p
\\
Level of Use A
A A,7 T5VIEF A
CP2804L TSToV *i~HlNF NEAdT Rev.2 Continuous pg p%
p%
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54 0f 83
F
\\
c.
POSITION the following valves as indicated:
73
('"
2-S-493 (V-11) to " GAS"
=
2-S-494 (V-12) to "INLINE" 1
2-S-495 (V-13) to "INLINE" d.
VERIFY 2-GAN-260 is approximately 80 psig.
e.
OPEN 2-GAN-259 (V-15).
f.
START stripping pump.
g.
WAIT at least 1 minute.
4 h.
POSITION valves as follows:
2-S-494 (V-12) to " BYPASS" 2-S-495 (V-13) to " BYPASS" i.
WAIT at least 1 minute.
O' L
j.
POSITION valves as follows:
2-S-495 (V-13) to "INLINE" 2-S-490 (V-7) to " BYPASS" k.
STOP stripping pump.
1.
WAIT 30 seconds.
- m. CLOSE 2-GAN-259 (V-15).
n.
CLOSE 2-S-489 (V-6).
o.
POSITION 2-S-493 (V-11) to "LIOUID."
4.20.22 On Remote Operating Module, PERFORM the following:
a.
POSITION the following valves as specified:
- 1) 2-S-482 (V-1) to " BYPASS"
,.d,* yd_7 hi_
CP2804L Level of Use
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- 2) 2-S-486 (V-2) to " GRAB"
-V
- 3) 2-S-487 (V-3) to " GRAB SAMPLE"
- 4) 2-S-488 (V-4) to "CLOSE"
- 5) 2-S-489 (V-6) to "CLOSE"
- 6) 2-S-490 (V-7) to " BYPASS"
- 7) 2-S-491 (V-8) to " BYPASS"
- 8) 2-S-493 (V-11) to " LIQUID"
- 9) 2-S-494 (V-12) to " BYPASS"
- 10) 2-S-495 (V-13) to " BYPASS"
- 11) 2-GAN-259 (V-15) to "CLOSE"
- 12) 2-S-497 (V-16) to "CLOSE" g
- 13) 2-S-498 (V-17) to "CLOSE"
- 14) 2-S-499 (V-18) to "LO-FLOW" b.
BACK OFF 2-GAN-260 (V-19) (nitrogen pressure regulator) completely.
4.20.23 BACK OFF 2-GAN-235, Nitrogen Supply Regulator.
l 4.20.24 At nitrogen bottle, CLOSE nitrogen bottle isolation valve.
4.20.25 DE-ENERGIZE Remote Operating Module.
4.20.26 REPLACE and LOCK anti-tamper covers on the following modules and panels:
Remote Operating Module
" PANEL C103C" a
" PANEL C103D" f)
U Level of Use j
[ 7 N AC F M {EvT j
CP2804L TSToF % K Rev. 2 gontinuous g%
p%
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56 of 83
i
,m, 4.20.27 E demineralized water flush tank levelindicator light does not b
indicate " FULL," PERFORM the following:
a.
THROTTLE 2-S-505, PMW To Flush Tank Fill.
b.
While filling tank, manually PUMP flush module level indicator to obtain an accurate water level.
i c.
WHEN demineralized water flush tank indicates full, CLOSE 2-S-505, PMW To Flush Tank Fill.
4.20.28 PROCEED to sample module in Primary Sample Sink Room.
4.20.19 PLACE 2-S-453 in "POS 2."
4.20.30 PLACE 2-S-451 in "POS 2."
l i
4.20.31 E open, CLOSE "2-S-460."
4.20.32 CLOSE 2-S-556, RCS Test Connection.
l' 4.20.33 Behind primary sample sink, CLOSE 2-S-504.
o ALARA pH probe may be extremely radioactive. Proper radiological controls and surveys should be adhered to in order to prevent over-exposure or contamination of adjacent equipment or personel.
4.20.34 REMOVE pH probe (AE 1068) and o-ring from sample chamber.
i 4.20.35 E pH probe protective cover absorbant material is not damp, FILL pH probe protective cover with a few drops of KCL.
4.20.36 INSTALL pH probe protective cover onto pH probe.
4.20.37 INSTALL FME cover on AE 1068 sample chamber.
4.20.38 STORE pH probe in a vertical position such that the KCL remains on the pH probe sensor.
1 oV
.,f,,g[,,.07 Th(i&T f
A CP2804L Level of Use Rev. 2 i
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F 1
l p 4.20.39 REQUEST second chemistry technician to independently verify v
the position of the following valves:
l a.
2-RC-001 "CLOSE."
1 b.
2-RC-002 "CLOSE."
c.
2-RC-003 "OPEN."
l d.
2-RC-045 "OPEN."
e.
2-LRR-61.1 "CLOSE."
4.20.40 DOCUMENTindependent verification on Attachment 12,
" Isolation Valves Independent Verification Sheet."
4.20.41 RETURN to chemistry lab.
4.20.42 NOTIFY MCRO that reactor coolant PASS sampling has been completed.
- End of Section 4.20 -
rm O
1 i
l l
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f l
l fx Uquid PASS 4.21 Liquid Waste Sampling and Analysis Team ALARA This Section should only be performed when directed by MRDA or AMRDA.
4.21.1 ENSURE lead brick shield in Chemistry Lab Primary Sample Hood Area is intact.
4.21.2 PERFORM one of the following:
E CWMT is to be sampled, CONSULT MCRO to ensure CV. \\1T bas been recirculated at least 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> with mixer or at least 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> with pump.
E AWMT is to be sampled, CONSULT MCRO to ENSURE AWMT has been recirculated at least 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> with mixer or at least 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> with pump.
4.21.3 PROCEED to left side of primary sample sink in Primary Sample
,fq Sink Room.
U 4.21.4 E CWMT is to be sampled, ESTABLISH sample flow from CWMT as follows:
a.
ENSURE "2-S-262" (rack shutoff valve) is open.
b.
OPEN "2-S-111" (sample isolation valve).
c.
E sampling A CWMT, REQUEST operations close "2-LRR-124.1 A."
d.
E sampling B CWMT, REQUEST operations close "2-LRR-124.1B."
l HP Tech.
l e.
MONITOR radiation dose rate as sample flow is established to ensure personnel radiation exposure remains less than level specified in radiological controls.
/~'s A
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9%
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l f
ALARA Sample flow rate and flush time may require adjustment as radiation levels increase. MRDA or AMRDA shall specify the required adjustments.
l Chem Tech.
l f.
THROTFLE 2-S-111 to obtain sample flow rate of approximately 500 ml/ min and FLUSH for 20 minutes.
g.
RETURN to Chemistry Lab.
4.21.5 E AWMT is to be sampled, ESTABLISH sangle flow from AWMT as follows:
a.
ENSURE 2-S-126 (Rack Shutoff valve) is open.
b.
OPEN 2-S-128 (sample isolation valve).
c.
REQUEST Operations to close "2-LRA-55.1".
d.
MONITOR radiation dose rate as sample flow is established to ensure personnel radiation exposure remains less than p
level specified in radiological controls.
V ALARA O
Sample flow rate and flush time may require adjustment as radiation levels increase. MRDA or AMRDA shall specify the required adjustments.
e.
THROTTLE 2-S-128 to obtain sample flow rate of approximately 500 ml/ min and FLUSH for 20 minutes.
f.
RETURN to Chemistry Lab.
4.21.6 WHEN required flush period is completed, RETURN ta primary sample sink.
l HP Tech.
f 4.21.7 MONITOR dose rates l Chem Tech.
l' 4.21.8 E dose rates preclude obtaining required discharge samples, PERFORM the following:
a.
NOTIFY MRDA r,(3 Level of Use A
A A
A Ce2804t 75TdFF *T'HINK* NAC7 TEYlE97 Rev. 2 gOntinUOUS pq)
Ak
/PS 60 of 83
n
( [3 b.
REQUEST guidance on sample volumes.
v OBTAIN sample equipment required to collect adequate c.
sample for analyses.
4.21.9 Refer To SP 2864 and OBTAIN required sample aliquots for l
discharge permit preparation.
1 l
4.21.10 E AWMT was sampled AND sampling is complete, PERFORM l
i the following:
NOTIFY Operations that "2-LRA-55.1" may be opened a.
b.
CLOSE "2-S-128" Sample Isolation Valve.
4.21.11 E CWMT was sampled MJ2 sampling is complete, PERFORM the following:
i a.
E A CWMT was sampled, NOTIFY Operations that "2-LRR-124.1 A may be opened.
b.
E B CWMT was sampled, NOTIFY Operations that "2-LRR-124.1B may be opened.
4.21.12 CLOSE 2-S-111 Sample Isolation Valve.
/.2L13 Refer To CP 801/2801/3801 AT, " Gamma Spectroscopy Counting Sytm Maintenance and Operation," and PERFORM liquid waste activity analysis as follows:
l a.
PERFORM a 5 minute, closed cave, background count on the detector to be used for liquid isotopic analysis.
b.
RECORD required isotopes and their associated background activitylevels on Attachment 9.
c.
SAVE gamma spectrometer printout for future reference.
j d.
PIACE bagged sample liter bottle on detector in gamma spectrometer and PERFORM a 5 minute, closed cave count using the following information:
Sample date and time as recorded on Attachment 9.
Sample volume corresponding to the last circled sample dilution on Attachment 4.
V(3
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CP2804L L
Levelof Use
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IE dead time is less than 20%, Go To step 4.21.14.
e.
l f.
IE dead time is greater than or equal to 20%, PERFORM the following:
- 1) OPEN cave and REMOVE sample liter bottle.
- 2) TRANSFER 1.0 ml of sample from sample liter bottle (the solute liter bottle) into another 1 liter plastic bottle l
filled with demineralized water (the solvent liter bottle).
- 3) RECORD new sample volume on Attachment 4, as applicable, for the 1000:1 dilution being performed.
- 4) PACKAGE solvent liter bottle (diluted sample liter bottle)in a plastic bag and SEAL bag.
- 5) Go To step 4.21.13.d.
4.21.14 Refer To SP 2864," Liquid Waste Discharge," and PERFORM required NPDES analyses.
4.21.15 Refer To Attachment 9 and DETERMINE total waste activity as follows:
l a.
SUBTRACT background activity level from printout activity level to obtain isotope activity level for each isotope.
b.
ADD isotope activity level for each isotope to obtain total isotope activity.
4.21.16 Refer To SP 2864," Liquid Waste Discharge," and PERFORM manual calculation for discharge permit.
4.21.17 COPY the following documents 2 times:
Completed attachments Gamma spectrometer printouts IE originated, completed liquid discharge permit
-O Level of Use A
A
/i A
CP2804L gOntinUOUS NETF '~THisF MEXF YEVIEF Rev. 2 pg f%
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62 of 83
i
,c 4.21.18 SEND originals of the following documents to MRDA or (y)
AMRDA:
Completed attachments
\\
Gamma spectrometer printouts 1
IE originated, completed liquid discharge permit 4.21.19 FILE copies of the following documents:
Completed attachments Gamma spectrometer printouts IE originated, completed liquid discharge permit 4.21.20 PLACE bagged sample liter bottle (s) in properly shielded location for future disposal.
- End of Section 4.21 -
.0 ig Level of Use ll k
d
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l 1
4.22 PASS Lquipment Inventory s,
4.22.1 Cuarterly and after each PASS sample, PERFORM inventory of l
all equipment required to perform containment PASS sampling.
l 4.22.2 COMPLETE Attachment 8," Reactor Coolant Sampling Inventory."
4.22.3 FORWARD Attachment 8 to Chemistry Supervision
- End of Section 4.22 -
I 3
(G I
l i
(s ~%)
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- 5. REVIEW AND SIGNOFF g
i t V
5.1 Indicate (check) Subsections of this procedure which were performed:
j Q 4.1 04.2 04.3 04.4 04.5 04.6 O 4.7 04.8 04.9 0 4.10 0 4.11 0 4.12 l
O 4.13 0 4.14 0 4.15 0 4.16 0 4.17 0 4.18 0 4.19 O 4.20 0 4.21 0 4.22 I
l 5.2 If procedure was terminated prior to completion, specify cause:
i I
5.3 This procedure was performed by the following personnel:
Job supervisor (MRDA):
b)
V Print Name Signature Initials l
Liquid PASS Team personnel:
i Print Name Signature Initials Print Name Signature Initials Print Name Signature Initials
?
Print Name Signature Initials 5.4 This p:..cedure was reviewed by Chemistry Supervision:
Print Name Signature Initials
- 6. REFERENCES 6.1
" Final Safety Analysis Report Unit 2," Appendix 12A Level Of Use k
.lt A
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gOntinUOUS ps j
pgk 65 of 83 L
l
f I
fm 6.2 " Millstone Nuclear Power Station Emergency Plan" 6.3 RAB Accident and Shielding File #608.002 l
6.4 NUREG-0654," Criteria for Preparation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 6.5 NUREG-0737," Clarification of TMI Action Plan Requirements, l
Supplement 1, Requirements for Emergency Response Capability" l
6.6 " Instructions Model 8500 Gas Chromatograph:" Perkin-Elmer, October 1987 l
6.7 " Technical Manual for De-ionized Water Flushing Module:" General Dynamics Corporation; Electric Boat Division, Reactor Plant Seivices, November 1981 l
l 6.8 " Technical Manual for Reactor Coolant Post-Accident Sample System:"
l General Dynamics Corporation; Electric Boat Division, Reactor Plant Services, May 1982 l
a 6.9 "VAX/VMS Spectroscopy Applications Package User's Manual 07-0196,"
I April 1982 j
(3 j
V 6.10 SP 2864," Liquid Waste Discharge" l
6.11 CP 801/2801/3801 AT," Gamma Spectroscopy Counting System Maintenance and Operation" j
l 6.12 CP 801/2801/3801AD," Gas Chromatograph Operation and Calibration" t
6.13 CP 2801X," Routine Operation, Calibration and Maintenance of the
]
DX-120 and DX-500 Laboratory Ion Chromatography Systems" 6.14 CP 807/2807/3807AA," Boron Analysis" 6.15 Chemistry Memorandum CHEM-93-1212; from J. P. Kangley to l
J. Broussard, dated January 18th 1993 6.16 CP 801/2801/3801AJ," Inductively Coupled Argon Plasma Analysis" 6.17 NRC, Docket Number 50-245. 50-336. Combined Inspection 50 - 245/80 - 18,50 -336/80 -20. December 171980, Page 12
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6.18 NRC, Commitment Record # RCR-10781. Docketed Correspondence Q
Dated 11/17/87. Combined Inspection 50-245/87-24,50-336/87-21, l
l 50-423/87-19.
6.19 USNRC Reg Guide 1.97, Rev. 3 May 1983," Instrumentation for Light Water Coolant Nuclear Power Plants to Assess Plant and Environs Condition During and Following an Accident 6.20 CR M3-97-3450," Calculation Used in Liquid PASS E Plan Procedure Appears In Error" 6.21 CR M2-97-2509," PASS Operation and Configuration Differ in FSAR, Reg Guide 1.97 and EPOP" 6.22 CR M2-97-2797," PASS Equipment and Supplies are not Inventoried IAW Regulatory and Site requirements" 6.23 CR M2-97-2905," Audit of PASS Determined that Existing Program Requirements may not Ensure TS 6.18 Compliance" 6.24 CR M1-97-0641,"EPOP Procedures References Call for Performing Chloride Analysis"
{V3 s25 Memo 98-067, From Max Keyes to Tom Blount, PASS Procedure Meeting Minutes 6.26 Millstone Nuclear Power Station, Unit 2, Technical Specification 6.18, August 28,1992.
6.27 MPNS-2 FSAR, Section 9.6," Post Accident Sampling System" 6.28 EPRI NP-3513,"Postaccident Liquid Sampling Systems," Final Report, May 1984 6.29 INFO Post Accident Sampling Preparedness CY 707 INPO 91-019 6.30 Technical Paper," Temperature - Another Wild Card in pH Control,"
submitted by TBI-Bailey, February 14,1995.
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CP280L Level of Use i
Continuous Rev.2 pg p%
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- 7.
SUMMARY
OF CHANGES V
7.1 Added prerequisite for SM or US to grant permission to perform this procedure during E-plan drill or exercise.
1 7.2 Changed GC prerequisite to be performed only if necessary.
i 7.3 Added requirement to evacuate 100 1 from 14.4 cc gas vial.
l 7.4 Changed prerequisite for obtaining radmonitor bypass key to obtain key from Operations.
7.5 Added prerequisite to verify sample module ventilation is in operation.
7.6. Moved steps to remove anti-tamper covers to prerequisites.
7.7 Added prerequisite to verify 2-RB-210 is open.
7.8 Added restriction on directing PASS system effluent to the EDST to prerequisites and precautions.
7.9 Changed number of gas vials required from two to one.
O:
7.10 Added flat head screwdriver and large channel lock pliers to tools and D
consumables.
7.11 Added EDST to definitions.
7.12 Added "1E sampling HPSI/LPSI" to step opening 2-S-504.
7.13 Changed wait time for gas loop depressurization from 30 seconds to 10 seconds.
7.14 Added step to verify 2-S-556 open after leak checking gas loop.
7.15 Changed steps to fill demineralized water flush tank to mimic steps in SP 2849.
7.16 Increased purge volume to 15 gallons to ensure 3 volume flush is performed.
7.17 Added step at end of each sample isolation Section return to step directing all sample collection.
7.18 Moved step requesting assistance from MRDA or AMRDA if sample flow
,O is not at least 0.25 gpm to earlier in Section for isolating in-line sample.
V Level of Use k
3 Td.W CP2804L T
. gontinuous 8 TOV %NF EVIE Rev.2 jpq jjs%
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7.19 Changed 2 minute wait to 1 minute prior to observing pH reading.
y 7.20 Rearranged sequence of steps isolating pH probe.
1 7.21 Added lines for recording measured pressures during stripping of gases.
7.22 Added requirement to ensure final position of 2-S-488 and 2-S-489 are open when flushing prior to sample retrieval.
I 7.23 T vorded steps for retrieving in-line samples to incorporated lessons leamed duiing performance of procedure.
7.24 Added note indicating that sample analysis may be performed concurrently when personnel and equipment are available.
7.25 Added note indicating that there are three shelves that can be used for counting gas sample.
7.26 Incorporated lessons learned during performance of procedure into restoration section.
7.27 Added steps to purge gas loop with nitrogen during restoration.
O 7.28 Added steps to remove pH probe when sampling is completed.
V 7.29 Incorporated lessons learned during performance of procedure into syringe check and pH probe installation attachments..
1 I
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.A CP2804L TsioV 7HINF
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E 1
l Unit 2 Determination of Total Dissolved Gas and Sample Quantity Worksheet (Sheet l of 2)
Grab Sample Worksheet Completed by:
System Sampled:
Print Name Isolation Date:
Isolation Time:
Signature:
In-line Sample System Sampled:
Isolation Date:
Isolation Time:
DATA 1.
Initial Totalizer Reading Gals 2.
Radiation Meter Reading:
rem /hr 3.
Uncorr.:cted Coolant pH 4.
pH Temperature Reading F
5.
Corrected (77 F) Coolant pH 6.
Final Totalizer Meter Reading Gals 7.
Initial Gas Loop Temperature F
p 8.
Initial Gas Loop Pressure psig 9.
Final Gas Loop Temperature F
- 10. Final Gas Loop Pressure psig
- 11. Volume of Gas Transferred to the Syringe cc CALCULATIONS
- 12. Total Dissolved Gas from computer or Attachment 3: TDG cc/Kg
- 13. Calculate the syringe sample quantity as follows:
V = 6.40 Ms am t
V+5 t
Where V = Volume of Gas Sample in Syringe in ml.
t l
Reviewed by:
Date:
Print Name Signature (D
i Level of Use 4
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A_
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pH Temperature Compensation (Page 1 of 1)
Temperature pH
(*F) 5 6
7 8
9 60
- 0.05
- 0.03 0
- 0.03
- 0.05 62
- 0.04
- 0.02 0
- 0.02
- 0.04 64
- 0.03
- 0.02 0
- 0.02
- 0.03 66
- 0.03
- 0.02 0
- 0.02
- 0.03 68
- 0.02
- 0.01 0
- 0.01
- 0.02 70
- 0.01
- 0.01 0
- 0.01
- 0.01 72
- 0.01
- 0.01 0
- 0.01
- 0.01 74 0.00 0.00 0
0.00 0.00 76 0.01 0.00 0
0.00 0.01 78 0.01 0.01 0
0.01 0.01 80 0.02 0.01 0
0.01 0.02 82 0.03 0.01 0
0.01 0.03 84 0.03 0.02 0
0.02 0.03 86 0.04 0.02 0
0.02 0.04
/~'%
88 0.05 0.02 0
0.02 0.05 V
i 90 0.05 0.03 0
0.03 0.05 1
92 0.06 0.03 0
0.03 0.06 94 0.07 0.03 0
0.03 0.07 96 0.08 0.04 0
0.04 0.08 98 0.08 0.04 0
0.04 0.08 j
100 0.09 0.04 0
0.04 0.09 102 0.10 0.05 0
0.05 0.10 104 0.10 0.05 0
0.05 0.10 106 0.11 0.06 0
0.06 0.11 108 0.12 0.06 0
0.06 0.12 110 0.12 0.06 0
0.06 0.12 112 0.13 0.07 0
0.07 0.13 114 0.14 0.07 0
0.07 0.14 116 0.14 0.07 0
0.07 0.14 118 0.15 0.08 0
0.08 0.15 120 0.16 0.08 0
0.08 C ',6 O
Level Of Use 3
k d,/ '#_EVIEW d
CP2804L gOntinUOUS STOEF *ihIN f 'EACT R
Rev. 2 T
j j'
71 of 83
)
Liquid PASS Total Dissolved Gas Worksheet f-S (Page 1 of 3)
IV NOTE When performing the following calculation carry significant digits throughout calculation to infinity. Ensure that the "N" term is carried out to a minimum of 3 significant digits. This is absolutely necessary in order to ensure the accuracy of this equation j
Injtial Data:
A - Initial Gas Loop Pressure (psig)
B - Absolute Gas Loop Pressure (psia)
A C,, ' f, J.5 p 1 ; & g ?- y B
+
14.7
=
C - Initial Gas Loop Temperature ( F) D - Absolute Gas Loop Temperature ( R)
C
-n ry g
D
+
460
=
Equilibrium Data:
Q E - Final Gas Loop Pressure (psig)
F - Absolute Gas Loop Pressure (psia)
E i:
~ " O.,, ; ',
,y F
+
14.7
=
G - Final Gas L,oop Temperature ( F)
H - Absolute Gas Loop Temperature ( R)
G
, Bea H
+
460
=
I - Henry's Constant for Nitrogen at Equilibrium (psia / mole Fraction)
[(H*0.9893)-406.46]*10000 H
'w-
% di%fe "2 n; 2
I X
0.9893 406.46 i X 10000
=
J - Partial Pressure of Nitrogen at Equilibrium (psia) - J1 (Numerator Term)
B
- H *I*0.195
- 18.015 *454 B
M H
I O'
"1 U
. ;g ~ R %
J1 X
X X
0.195 X 18.015 X 454
=
A A
,J8 CP2804L Level of Use n,,, e n,K n
'STOP THIN
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i l
Atttchment 3 Liquid PASS Total Dissolved Gas Worksheet p
(Page 2 of 3)
(
v J - Partitel Pressure of Nitrogen at Equilibrium (psla) - J2 (Denominator Term)
[(!
- 0.195
- 18.015
- 454) + (H
- 250
- 10.73
- 28.317)]
- D a
Left Hand Side of Denominator Term I
,' o7 &$
97 :, '%
a MP a
1 X
0.195 X
18.015 X
454
=
b - Right Hand Side of Denominator Term H
7 n 0%;
dWM #,
b X
250 X
10.73 X
28.317
=
Completed Denominator Term a
q b
D a
J2 o
+
X
=
Completed J Term J1 J2 m
J
+
=
()
K - Vapor Pressure of Water at Equilibrium (psia)
[(-9496.5*/H)INVfn]*21790834
% g,.
- ig H
INVfni
%g AT K
- 9496.5,4-l X
21790834
=
L - Partial Pressure of Hydrogen at Equilibrium (psia)
F-J-K F
+
J
- 1 K
h L
=
Note 1: This step means that the inverse natural log will be taken of the result of -9496.5 + H.
On some calculators this can be performed by pressing the INV key followed by the fn key. On others this will be done by pressing the 2nd key followed by the En key. In any case should you have any questions, contact Supervision for guidance.
(oh 75To F TfSIN F T./4 CP2804L
-d k
Level of Use AC 7 M EVl5Y7 Rev.2 gOntinUOUS y.
7
/M 73 of 83 Liquid PASS Total Dissolved Gas Worksheet
!n (Page 3 0f 3) b M - Henry's Constant for Hydrogen at Equilibrium (psia / mole fraction)
((H*0.3081)-64]*1000 H
& a
, Ft u f6.
g M
l
' X 0.3081 64 X
10000
=
l N = TDG @ STP (cc/kg)
([(*250)/(M*18.015*454)]+[ L*0.195)/(H'10.73*28.317)])*[(10.73*492*28.317*1000/(14.7*0.25)]
N1 - Left Handl r a - left hand side L
e M
We,
,1 a
X 250
+
+
18.015
+
454
=
b - right hand side p.
L H
b j
a X 0.k95
+
+
10.73
+
28.317
=
Completed Left Hand Term a
b N1
+
=
N2 - Right Hand Term (10.73*492*28.317*1000)/(14.7*0.25) ff~y
';gy cg ' ', i T E
gjgs a N2 10.73 X
492 X
28.317 X
1000
+
14.7
+
0.25 40677543.87
=
Completed N Term N1 N2 N
X 40677543.87
=
(3 G/
A A
Ce2804L
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STOP
'THINK 9AC{
REVIEW Rev. 2 gOnlinUOUS pg jpg p;g jpg.
74 of 83
I Unit 2 Post Accident Sampling Reactor Coolant Sample Dilution Data Sheet (Sheet 1 of1)
Samole Worksheet Completed by:
Type:
Print Name System Sampled:
Isolation Date:
Signature:
Isolation Time:
NOTE i
Circle the appropriate sample bottle dilution corresponding to the dilution (s)d by multiplying the 100 pl sample mass Mal) by the applicable required during performance of step. The sample mass is determine correction for the sample dilution that is being cou(nted.
Degas Liquid Sample Sample Dilution Mass (um)
Isotopic Original Mdl =
gm O
'V 15t Dilution Mdl
- 1.0E-01 =
- 1.0E-01 =
gm 2nd Dilutic:-
Mdl
- 1.0E-04 =
- 1.0E-04 =
gm 3rd Dilution Mdl 1.0E-07 =
- 1.0E-07 =
gm 4th Dilution Mdl 1.0E-10 =
- 1.0E-10 =
gm 5th Dilution Mdl 1.0E-13 =
- 1.0E-13 =
gm 6th Dilution Mdl
- 1.0E-16 =
- 1.0E-16 =
gm 7th Dilution Mai
- 1.0E-19 =
- 1.0E-19 =
gm i
Reviewed by:
Date:
Print Name Signature
'0 l
1
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A Level of Use A
Ce2804L TiroF 'Fs'is7 TAdiT"REVIE T Rev. 2 Continuous pjg jpg jp%
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75 of 83
f Unit 2 Post Accident Sampling Reactor Coolant Isotopic Worksheet (Sheet 1 of 1)
(3 V
Sample Worksheet Completed by:
Location:
Print Name Isolation Date:
Isolation Time:
Signature:
l Printout Activity
Background
=
1sotope Activity Isotope Printout Activity
Background
Isotope Activity (2-place accuracy)
(2-place accuracy)
( Ci/gm)
( Ci/gm)
( Ci/gm) l l
1 pd l
l l
l i
NOTE: TotalIsotope Activity =
TotalIsotope Activity
( -place accuracy)( Ci/gm) summation of allisotope activities.
Reviewed by:
l Print Name Date:
Signature i
s
! d b
hs.
A A
ce2804t l
Level of Use
'IT6F N$1NF NIC7'5EVi@VT Rev.2 I
gonlinuous jj,4 jpg jg 76 of 83 i-
(
Attachmcnt 6 Unit 2 Post Accident Sampling n
Reactor Coolant Gaseous Activity Worksheet
()
(Sheet 1 of 1)
Sample Worksheet Completed by:
1 Location:
Print Name Isolation Date:
{
Isolation Time:
Signature:
Printout Activity
Background
=
Isotope Activity Isotope Printout Activity
Background
Isotope Activity (2-place accuracy)
(2-place accuracy)
( Ci/gm)
( Ci/gm)
( Ci/gm) 4 l
i g(
l i
NOTE: Total Gaseous Activity =
Total Gaseous Activit (2-place accuracy)( Ci/gm)
. summation of allisotope activities.
Gas Composition Analysis
% Hydrogen:
% Oxygen:
Reviewed by:
Date:
C')
Print Name Signature U/
A Ce2804o A
A
- 5; tov 't" HINE" 'YACV "5IEW597 Level of Use Rev.2 gontinuous jpg pq4
/F%
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77 of 83
1 i
Attrchment 7 Unit 2 Post Accident Sampling
'g Reactor Coolant Chemical Analysis Worksheet y
(Sheet 1 of 1)
Samole Worksheet Completed by:
Location:
' Print Name Isolation Date:
l Isolation Time:
Signature:
Boron Data:
Boron Weight Data:
DI Water Mass:
grams 100 pl Sample Mass:
grams Boron Correction Factor:
Correction Factor =
100 1 Sample Mass 1
gm +
gm Correction Factor =
1
=
(3 k
V gm Boron (ppm) = Analysis results in ppm. Correction Factor Boron (ppm) =
ppm e ppm
=
Coolant chloride concentration:
ppm Coolant pH (Attachment 1)
Additional Analysis Concentration I
Reviewed by:
Date:
Print Name Signature r i b
C 2804L Level of Use yf 7 7,qg7 g
g Continuous pg p.%
M p'%
78 0r83
i Reactor Coolant PASS Samnling Equipment Inventory I
(Sheet 1 of 1) l 0 I 'v l
Equipment Name Required On Hand Ordered 250 i syringe with sideport needle 2
500 I syring. with sideport needle 1
1.0 mi syringe with sideport needle 1
Syringe transport container 1
I Liquid radwaste sample vial 4
Transport container for sample vials 1
0.1 cc sample loop for gas chromatograph 1
2 ml grab sample chamber 2'
Transport cask for grab sample chamber 1
Transport cart 1
CaroPac PA1 Guard (10-32) column 2
Anion micromembrane suppressor 1
250 ml sample loop 1
- 1 installed in PASS reactor coolant sample cabinet.
~
Reason for Inventory:(circle one)
Quarterly After Use O
Remarks:
a f\\J' I
Date:
Signature:
i l
l l
i 1
OV vgY F 'iHINT %[CP 'iiEViv7 ib A
a 4
CP2804L Level of Use Rev 2 ontinuous jpN
/Mk
/Wk
/Wk 79 of 83
Unit 2 Post Accident Sampling Liquid Waste Isotopic Worksheet l
(Sheet 1 of 1)
(U Sample Worksheet Completed by:
Tank:
Print Name
)
Date:
Time:
Signature:
Printout Activity
Background
lsotope Activity
=
3 Isotope Printout Activity
Background
Isotope Activity (2-place accuracy)
(2 place accuracy)
( Ci/gm)
(pCi/gm)
( Ci/gm) l D.
U NOTE: Total Isotope Activity =
TotalIsotope Activit (2 place amuracy) CUgm) summatiou,f allisotope activities.
Reviewed by:
Date:
Print Name Signature l n
- .3 " *ibNk' "fAk TEViisT k
g CP2804L Level of Use STdP Rev.2 gOntinUOus jpg jpg
/p
/M 80 of 83
Att chment 10 Syringe Checic
,, s (Sheet 1 of 1) tQ/
- 1. CHECK each of the prepared syringes for proper operation as follows:
1.1 ENSURE syringe is open (syringe nosecap screwed against syringe body).
i 1.2 DRAW air into syringe.
1.3 l' LACE needle in a beaker of water.
1.4 FRESS plunger and ENSURE air exits syringe.
1.5 REMOVE needle from beaker.
1.6 DRAW air into syringe.
1.7 UNSCREW syringe nosecap 2 turns.
l 1.8 PLACE needle in beaker of water.
l 1.9 PRESS plunger and ENSURE no air exits syringe.
p 1.10 REMOVE needle from water and SCREW syringe nosecap against
'yj syringe body.
1.11 PRESS plunger.
(J)
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81 of 83
e Attr.chment 11 pH Probe Installation (Sheet 1 of1
' V
- 1. OPEN module door.
- 2. REMOVE FME cover from pH probe (AE 1068) sample chamber.
- 3. REMOVE protective cover from pH probe sensor.
- 4. INSTALL pH probe (AE 1068) and 0-ring into sample chamber.
- 5. INSTALL electrical connector onto pH probe.
l
- 6. CLOSE module door.
I
(~')
%.J l
l p
l
'J
,],g,g7,%
Te/g g
CP2804L Level of Use viiW Rev. 2 Continuous pg pg p%
82 0f 83 2
Isolation Valve Independent Verification Sheet
,g (Sheet 1 of 1)
?
l V
1 Valve Required Position Indepenc~ently Verified Independently Verified By: Sign Name By: Print Name 2-RC-001 CLOSED 1
2-RC-002 CLOSED
]
2-RC-003 OPEN 2-RC-045 OPEN
~
2-LRR-61.1 CLOSED nN]
oN)
A J
Level of Use b
/t Ce2804L Continuous
- 5TOF 'tklNS# *TAdiI'5EvisW Rev.2 pq p%
9%
P4(
83 0f 83
__