ML20196K577
| ML20196K577 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/24/1999 |
| From: | Brewer J NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| References | |
| CP2804L, NUDOCS 9904020083 | |
| Download: ML20196K577 (81) | |
Text
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*NDS Document Transmittal #127639
! 3/25/99 , To: Nuclear Regulatory Commission Addressee Unique # 140 Document Control Desk ROUTINE distributon Washington, D.C. 20555 The following documents have been revised. You are currently on distribution for these documents. Verify that all documents are included in this distribution set. DOCUMENT REV COPIES l CP 2804L 1 1 l j i o\ ! I D U. I i 9904020083 990324
-A3*
PDR ADOCK 05000336 P PDR s Sign and return this form as soon as received to: Diane ONeil x2451, NDS/CDL, B433-1, Mdistone or FAX (860) 444-5711. Signature Date:
O ' ' MILLSTONE NUCLEAR POWER STATION l CHEMISTRY PROCEDURE l 1 1
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2
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Unit 2 Rx Coolant $ rid! Liquid Waste PASS [+Refi6:17]
.m ..
Approval: '
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PORC Mtg. No: N/A i Date: 3- 3 Y- f9' ( Effective Date: 3-J5-99 O Level of Use Subject Matter Expert: CONTINUOUS Jeffrey E. Brewer
p t I l lp Millstone Unit 2 lC Unit 2 Rx Coolant and Liquid Waste PASS [+Ref.6.17] TA.BLE OF CONTENTS \ 1. PURPOSE....................................................3
- 2. P RE REQ UISITES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
- 3. P R ECAUTI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 l
- 4. I N STR U CTI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 4.1 Determination of Procedure Entry Point . . . . . . . . . . . . . . . . . . . . . 11 4.7 PASS Preparation for Reactor Coolant Sampling . . . . . . . . . . . . . 12 4.3 Isolation of Reactor Coolant Samples . . . . . . . . . . . . . . . . . . . . . . . 19 4.4 Reactor Coolant Pressurized 2 ml Grab Sample Isolation . . . . . . 21 4.5 Reactor Coolant Depressurized 2 ml Grab Sample Isolation . . . . 22 4.6 Reactor Coolant In-Line Sample Isolation . . . . . . . . . . . . . . . . . . 23 4.7 Stripping of Dissolved Gases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 O
U 4.8 4.9
- Flushing PASS Prior to Reactor Coolant Sample Retrieval . . . . . 28 Reactor Coolant Sample Retrieval . . . . . . . . . . . . . . . . . . . . . . . . . . 31 l 4.10 Reactor Coolant 2 ml Grab Sample Retrieval . . . . . . . . . . . . . . . . 32 l 4.11 Reactor Coolant Liquid In-Line Sample Retrieval . . . . . . . . . . . 33 i 4.12 Reactor Coolant Gaseous In-Line Sample Retrieval . . . . . . . . . . 35 4.13 Analysis of Reactor Coolant Samples . . . . . . . . . . . . . . . . . . . . . . . 37 l l
4.14 Reactor Coolant Liquid Isotopic Analysis . . . . . . .. . . . . . . . . . . . 39 ! 4.15 Reactor Coolant Total Dissolved Gas Analysis . . . . . . . . . . . . . . . 43
'4.16 Reactor Coolant Chloride Analysis . . . . . . . . . . . . . . . . . . . . . . . . . 44 4.17 Reactor Coolant Boron Analysis . . . . .. . . . . . . . . . . . . . . . . . . . . 45 4.18 Reactor Coolant Gaseous Isotopic Analysis . . ..... ..... .. 46 l
4.19 Reactor Coolant Gas Composition Analysis . . . . . . . . . . . . . . . . . 48 l 4.20 PAS S Re st ora t io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 4.21 Liquid Waste Sampling and Analysis . . . . . . . . . . . . . . . . . -. . . . . . 54 4.22 PASS Equipme nt Inve ntory . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59
- 5. REV I EW AN D S IG N O FF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60
- 6. R E FE R EN CES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60
- 7. SUM M A RY O F CH ANGES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 m
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r-l ATTACHMENTS AND FORMS l U Attachment 1, " Unit 2 Determination of Total Dissolved Gas and Sample Quantity Worksheet" . . . . . . . . . . . . . . . . . . . 66 Attachment 2, "pH Temperature Compensation" . . . . . . . . . . . . . . . . . . 67 Attachment 3," Liquid PASS Total Dissolved Gas Worksheet" ........ 68 Attachment 4," Unit 2 Post Accident Sampli,ng Reactor Coolant Sample Dilution Data Sheet ........................ 71 Attachment 5," Unit 2 Post Accident Sampling Reactor Coolant Isotopic Worksheet" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72 Attachment 6," Unit 2 Post Accident Sampling Reactor Coolant i Gaseous Activity Worksheet ' . . . . . . . . . . . . . . . . . . . . . . . 73 i Attachment 7," Unit 2 Post Accident Sam pling' Reactor Coolant Chemical Analysis Works 3eet ...................... 74 Attachment 8," Reactor Coolant PASS Sampling Equipment Inventory" . 75 Attachment 9," Unit 2 Post Accident Sampling Liquid Waste Isotopic Works h e e t " . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76 Attachment 10, " Syringe Check" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 l p ~ Attachment 11 "pH Probe Installation" . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 V Attachment 12, " Isolation Valve Independent Verification Sheet" . . . . . 79 l I i r 1 O ' CP2804L Level of Use 9
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87of THINK JdC[ REVIEW Rev.1 Continuous ' 4 -
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- 1. ' PURPOSE
'O 1.1 Ob,jective Provide the method for sampling and analyzing Unit 2 reactor coolant and L ' liquid waste during Station Emergency Response Organization (SERO) - L activation when high radioactivity levels, due to an accident, may preclude i
' 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 L
Radiological Dose Assessment (AMRDA). Performance and implementation of this procedure satisfies the Millstone Unit 2 Technical Specification 6.18. l
.1.2 Discussion 3- This procedure provides instructions ured by the Liquid PASS Team for sampling and analysis of reactor coolant, liquid waste, or both, during post l- _S accident conditions. The analyses conducted in this procedure identify the L
presence and amounts of various radioactive isotopes and ionic impurities contained in the reactor coolant or liquid waste. The presence and amounts of certain radioactive isotopes are indicative of the type (s) and p extent of core damage that exists. The results obtained from this d procedure assist the MRDA or AMRDA in determining an estimate of Unit 2 core damage. The Unit 2 systems which can be sampled and the ,_ analyses which can be conducted through performance of this procedure ! are summarized in the following lists: l Systems Analyses l-Reactor Coolant- Liquid Isotopic Shutdown Cooling Gaseous Isotopic High Pressum Safety Injection Gaseous Composition L Low Pressure Safety Injection Total Dissolved Gas l Liquid Radwaste Chlcride Boron pH The time required to collect and analyze core coolant samples is 3 hours or less from the time the ADTS makes the decision to obtain a sample using PASS, except for chloride, which is 96 hours. Gross activity is the
, sum ofliquid and gaseous isotopic activity.
N cc In the event of a SIAS accident the following valves 2-RC-001, i 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.
Level of Use CP2804L
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p) '. This procedure is linked to the Emergency Plan, therefore the Emergency Planning Services Department wi:1 be a cross discipline reviewer for all revi"<.
- or changes to this procedure.[Ref. 6.25) 1.3 Applicability This procedure is applicable during SERO activation when in plant radioactivity levels are too high to permit reactor coolant or liquid waste sampling via the normal (conventional) method.
1.4 Frequency l 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.
- 2. PREREOUISITES 2.1 General
/ 2.1.1 SURO is activated QE drill simulation is in progress.
/ 2.1.2 MCRO or drill coordinator has been notified that a PASS sample will be taken.
/ 2.1.3 Health Physics has evaluated need for RWP.
/ 2.1.4 Nitrogen bottle with at least 500 psig is available at the ROM.
/ 2.1.5 Lab ventilation is operating.
2.1.6 Lead brick shielding has been placed at the following locations:
/ . ICP
/ .
Lab ventilation hood
/ 2.1.7 Computer radioisotopic analysis system in operation and calibrated.
/ 2.1.8 ICP has been set up for PASS sample boron analysis and calibrated or calibration has been initiated.
/ 2.1.9 Gas chromatograph has been set up for PASS sample analysis and calibrated or calibration has been initiated (NA for liquid waste sampling).
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/ 2.1.10 14cc gas vial has been stoppered and evacuated (NA for liquid
'O waste sampling)
/ 2.1.11 Proper operation of sample syringes verified using instructions in Attachment 10 (NA for liquid waste sampling).
/ 2.1.12 pH probe has been installed IAW with Attachment 11.
/ 2.L13 Health Physics has obtained a radmonitor bypass key
/ 2.1.14 PASS anti-tamper key has been obtained from Chemistry Supervisor's Office.
/ 2.1.15 Manager of Radiological Dose Assessment (MRDA) or the l Assistant Manager of Radiological Dose Assessment (AMRDA) l has requested a PASS sample to include the following:
REACTOR COOLANT Check Requested Analysis Sample Equipment Needed I O pH PASS pH probe and pH probe cable O Pressurized 2 ml grab sample 2 ml grab sample chamber i O Depressurized 2 ml grab sample 2 ml grab sample chamber O Reactor coolant liquid isotopic 250 pl" LIQUID ISOTOPIC" syringeW Q Gasisotopic 250 1" GAS ISOTOPIC" syringe and a stoppered and evacuated 14cc gas vial O Gas composition 500 pl" GAS COMP" syringe Q Total dissolved gas None O Chlorides 1 ml" CHLORIDES" syringe O Boron " LIQUID ISOTOPIC" syringe W , W S;me syringe is used for both LIOUID WASTE ; Check Reauested Analysis Sample Eauipment Needgil O Required sample aliquots for Sample bottle I discharge permit preparation l O CP2804L Level of Use . . . . THINK 'ACT REVIEW Rev.1 Continuous ' ST 'P ~ 5 of 79 I
I 2.1.16 Liquid PASS Team has completed pre-job brief as follows:
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Manager of Operational Support Center (MOSC) - 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 Q HPSI/LPSI O 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
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Manager of Radiological Dose Assessment (MRDA) or the Assistant Manager of Radiological Dose Assessment s (AMRDA) - designates one the following paths to receive PASS system effluent (NA for liquid waste sampling): l Check One O Rad waste (Equipment Drains Sump Tank) 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 c(mtrols required for implementation of this procedure l i 2.2 Documents l 2.2.1 CP 801/2801/3801Y," Routine Operation and Calibration of the Laborato ry Ion Chromatography System" 2.2.2 CP 801/2801/3801 AD, " Gas Chromatograph" 2.2.3 CP 801/2801 AJ," Inductively Coupled Argon Plasma Analysis" O V ; CP2804L Level of Use m. mW sTop . ACT- Rev.1 Continuous 60f79
1 g 2.2.4 CP 801/2801/3801 AT, " Gamma Spectroscopy Counting System l Maintenance and Operation" 2.2.5 RWP for PASS sample collection l 2.2.6 SP 2864," Liquid Waste Discharge" 2.3 Personnel 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) 2.3.4 Manager of Radiological Consequence Assessment (MRCA) 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) O 2.3.8 Liquid PASS Team consisting of at least the following personnel: At least two Chemistry Technicians At least one Health Physics Technician o l O ' CP2804L Level of Use .
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e i . 2.4 Tools and Consumables 2.4.1 1 watch (range: 0 - 24 hours) (resolution: 1 second) 2.4.2 Two,14cc gas vials with septums 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 Gamma spectroscopy calibration source 2.4.8 One,2 ml grab sample chamber
- l. 2.4.9 Two,250 I syringes 2.4.10 One,500 Isyringes 2.4.11 One,1.0 mi syringes
(/ 2.4.12 1 sample transport container 2.4.13 One,2 ml grab sample chamber transport container 2.4.14 1 grab sample transport cart 2.4.15 Syringe trangert container 2.4.16 pH probe i 2.4.17 Small tipped screwdriver 2.4.18 Tongs for inverting samples 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. 2.5.2 The ADTS shall make the decision to obtain a sample using PASS. CP2804L Level of Use .. . . . .. . .
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( l l l p 2.5.3 The Manager of Operational Support Center designates, y 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 4 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. g i 2.6 Definitions l 2.6.1 CIRCLE - to draw a circle around I 2.6.2 NOTE - To Notice or Observe with Care '
- 3. PRECAUTIONS 3.1 Do not exceed 165*F influent sampl- flow temperature to the sample O' 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. g 3.3 Do not run stripping pump dry for longer than 5 minutes because this may damage the pump.
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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 (fiquid 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 flow position when system pressure is greater than 415 psia to prevent high pressure spikes due to water hammer. 3.6 In the event of unexpected results during the course of this procedure, place the equipment in a safe or stable condition, cease performance of further steps, and contact the MRDA or AMRDA for further instructions. A G , CP2804L Level of Use -
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3.7 The maximum design pressure for the pH probe is 250 psig. Do not exceed 250 psig at pH probe. I i iVO i I O CP2804L Level of Use STOP THINK ACT REVIEW Rev.1 Continuous 10 of 79
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- 4. INSTRUCTIONS .
O J - 1 i 4.1 ~ Determination of Procedure Entry Point j {
-4.1.1 IE you have been directed to perform reactor coolant sampling and analysis, Go To Section 4.2.-
4.1.2 If you have been directed to perform liquid waste sampling and analysis, Go To Section 4.21. l - End of Section 4.1 '- i l I l l O O CP2804L l Level of Use .. - .- .-
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4.2 PASS Preparation for Reactor Coolant Sampling O 4.2.1 UNLOCK and REMOVE anti-tamper covers from the following modules and panels:
- ROM
+ PANEL C103C
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- PANEL C103D 4.2.2 At Remote Operating Module, PERFORM the following:
- a. OPEN front panel.
- 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:
ROM was energized.
- f. ENSURE " BLOWER FUSE" and "LINE FUSE" indicator lights are not lit.
- g. RESET ROM timer to zero.
4.2.3 Without transport cart and syringes, PROCEED to PANEL C72 (located outside Primary Sample Sink Roam). 4.2.4 On PANEL C72, POSITION the following valves as specified:
- a. 2-RC-003 to "CLOSE"
- b. 2-RC-002 to "CLOSE" j c. 2-LRR-61.1 to "CLOSE" j l
4.2.5 PROCEED into Primary Sample Sink Room. 4.2.6 At sample module PERFORM the following:
- a. OPEN sample module ventilation dampet CP2804L l l Level of USe ~
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- b. OPEN module door.
l V . NOTE Valves 2-S-492 (V-9) and 2-S-496 (V-14) are closed when the handle of each valve is parallel to the side of the sample chamber in a vertical position and fu ly inserted. c. ENSURE 2-S-492 (V-9) and 2-S-496 (V-14) are closed.
- d. ENSURE 2 ml grab sample chamber is installed and its quick connects are properly engaged.
4.2.7 Behind primary sample sink, OPEN 2-S-504. NOTE PASS sample purge inay be returned to the VCT or Rad Waste. MRDA or , AMRDA will designate purge return location. ' 4.2.8 At PASS valve manifold, PLACE 2-S-453 to POSITION 1. 4.2.9 E sample effluent is to be directed to Equipment Drains Sump Tank PERFORM the following:
- a. OPEN 2-S-458
- b. CLOSE 2-S-460 4.2.10 E sample effluent is to be directed to VCT PERFORM the following:
__ a. OPEN 2-S-460 ! b. CLOSE 2-S-458 4.2.11 CLOSE 2-S-2, Reactor Coolant Pre-Cooler Stop 4.2.12 OPEN 2-S-2, Reactor Coolant Pre-Cooler stop 1 turn. l ; 4.2.13 At PASS valve manifold, PERFORM one of the following:
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CP28041, Level of Use SToP !THINK ' 'ACT REVIEW Rev.1 Continuous 13 of 79 l
E RCS Hot Leg is to be sampled, POSITION 2-S-451 to ( " POSITION 1"
=
E LPSI/HPSI System is to be sampled, POSITION 2-S-452 to " POSITION 1" 4.2.14 PROCEED to reactor coolant PASS area in Unit 2 lbrbine Building. 4.2.15 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.
- c. ADJUST 2-GAN-235 (nitrogen bottle pressure regulator valve) to obtain 400 psig downstream pressure.
4.2.16 On ROM, PERFORM the following: NOTE r Monitoring af T1, T2, or T3 temperatures via the remote operating module should be selected using only the " TEMPERATURE" rotary switch. The "T1" remain depressed,pushbutton on the remote operating module shouldreg setting.
- a. ENSURE "T1" pushbutton switch is depressed.
- b. ADJUST 2-GAN-260 nitrogen pressure regulator, to obtain 80 psig as indicated on PI-1087.
l c. SET rotary temperature switch to "T1." 4.2.17 On PANEL C103C, POSITION the following valves to "CLOSE."
- a. RC-001 l b. RC-045
- c. 2 - S - 446 O CP2804L
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4.2.18 On PANEL C103D, POSITION S-448 and S-457 to "CLOSE." G ) NOTE A minimum of 15 minutes is required for remote operating module warm-up. 4.2.19 Refer To step 4.2.2.e. and ENSURE at least 15 minutes have elapsed since remote operating module was energized. 4.2.20 At the ROM, SET temperature indicator calibration setpoint to 212 F as follows:
- a. PRESS and HOLD temperature calibration button.
- b. IE readout is greater than 165 F AND "High temp" Alarm does not flash, RELEASE temperature calibration button and CONSULT with Chemistry Supervision.
{
- c. IE readout does not indicate 212 F, ADJUST the Cal Trim screw with screwdriver to obtain a readout of 212 E O
y d. RELEASE temperature calibration button. d l l h) a CP2804L Level of Use . . STOP' THINK ACT' Rev.1 REVIEW Continuous l 15 of 79 I1
[ l 79 4.2.21 On remote operating module, POSITION the following valves as l (j specified: l l l l a. 2-S-482 (V- 1) to " BYPASS" I
- b. 2-S-486 (V-2) to " GRAB" i
- 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" i 1
1
- g. '2-S-491 (V-8) to " BYPASS" i
- h. 2-S-493 (V-11) to " LIQUID" i., 2-S-494 (V-12) to " BYPASS"
- j. 2-S-495 ( v -13) to " BYPASS" (o,) k. 2-GAN-259 (V-15) to "CLOSE"
- 1. 2-S-497 (V-16) to "CLOSE"
- m. 2-S-498 (V-17) to "CLOSE"
- n. E system pressure is > 400 psig 2-S-499 ("V-18") to "LO- FLOW"
- o. E system pressure is < 400 psig 2-S-499 ("V-18") to "HIGH- FLOW"
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4.2.22 At remote operating module, FILL sample module gas loop as follows:
- a. ' POSITION the following valves as specified:
- 1) 2-S-493 (V-11) to " GAS"
- 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 ,
1
- 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." 4
- k. WAIT 30 seconds 1.
POSITION 2-S-493 (V-11) to " LIQUID" l 4.2.23 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.
i
- c. CLOSE 2-GAN-259 (V-15)
- d. WAIT at least 1 minute Level of Use .
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- e. NOTE pressure as indicated on PI-1067.
O f. IE a pressure decrease is noted following the 1 rninute wait, NOTIFY MRDA.
- g. POSITION 2-S-493 (V-11) to " GAS" 4.2.24 PERFORM the following to depressurize gas sample loop:
- a. POSITION 2-S-494 (V--12) to "INLINE"
- b. At Sample Module, OPEN 2-S-741, Gas Loop Vent
- c. WAIT at least 30 seconds
- d. CLOSE 2-S-741, Gas Loop Vent
- e. At ROM, POSITION the following valves as specified:
- 1) 2-S-489 (V-6) to "CLOSE" l
- 2) 2-S-494 (V-12) to " BYPASS" ,
- 3) 2-S-495 (V-13) to " BYPASS"
- 4) 2-S-493 (V-11) to "LIOUID" 4.2.25 At flush module, PERFORM the following:
- a. OPEN 2-S-505 to fill demineralized water flush tank.
l b. WHEN demineralized water flush tank indicates full, CLOSE l 2 - S - 505.
- c. POSITION the following valves as specified.
- 1) 2-S-506 to "OPEN" l- 2) 2-S-503 to "OPEN" l
- 3) 2-GAN-237 to " CLOSED"
- 4) 2-S-507 to " CLOSED"
- End of Section 4.2 -
Level of Use - CP2804L
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4.3 Isolation of Reactor Coolant Samples O 4.3.1 Without transport cart, syringes, and 2 ml grab sample transfer-container, PROCEED to reactor coolant PASS area in Unit 2
'Ibrbine Building.
4.3.2 PRESS reset button on PASS flowmeter (FI-1062) to zero the gallons indication. 4.3.3 READ totalizer and RECORD initial totalizer reading on Attachment 1. 4.3.4 On PANEL C103C, PERFORM one of the following: I 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. 4.3.5 0,n Remote Operating Module, PERFORM the following:
- a. POSITION 2-S-486 (V-2) to " BYPASS." l l - .
NOTE , A reactor coolant flow path to the sample module is now established. 1 , 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.
C AUTIO N r Influent sample temperatures exceedin module. The "HIGH-TEMP"("T1")g 165light mdicator F can damage on the remote the sample operating module flashes when influent sample temperature exceeds 165*E
- d. E HIGH-TEMP (TI) indicator light flashes, PERFORM the following:
g CP2804L Level of Use . .. STOP THINK ACT REVIEW' Rev.I Continuous 19 0f 79 l-
i c-
- 1) E sampling RCS Hot Leg PERFORM the following:
U)' '
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CLOSE 2-RC-001 i CLOSE 2-RC--045
- 2) E Sampling HPSI/LPSI System, CLOSE 2-S-446.
- 3) NOTIFY MRDA or AMRDA and REQUEST further instructions.
4.3.6 WHEN 5 gallons have been purged, 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. E acquisition of depressurized 2 ml grab sample is directed
, by MRDA or AMRDA, Refer To Section 4.5 and ISOLATE depressurized 2 ml grab sample via remote operating module.
E acquisition of liquid in-line sample QR gaseous in-line sample is directed by MRDA or AMRDA, Refer To l (--) Section 4.6 and ISOLATE in-line sample via remote operating module. 4.3.7 On PANEL C103C, PERFORM one of the following: l l
- E RCS Hot Leg was sampled, CLOSE 2-RC-001 nnd l
2- RC-045.
=
E HPSI/LPSI System was sampled, CLOSE 2-S-446. l l l 4.3.8 Go To Section 4.7. 1 j - End of Section 4.3 - l l ( )
' s' CP2804L Level of Use .
STOP THINK ' ACT REVIEW Rev.I Continuous 20 of 79 f
4.4 Reactor Coolant Pressurized 2 ml Grab Sample Isolation ALARA This Section should only be performed when directed by MRDA or AMRDA. 4.4.1 POSITION 2-S-482 (V-1) to "ORAB" 4.4.2 POSITION 2-S-486 (V-2) to " GRAB" 4.4.3 ALLOW approximately 60 seconds for flow to stabilize. 1 NOTE A pressurized sample is now trapped (isolated) in the 2 ml shielded grab sample chamber. 4.4.4 POSITION 2-S-487 (V-3) to " NORMAL AND FLUSH." 4.4.5 POSITION 2-S-482 (V-1) to " BYPASS." NOTE l 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 l l . Grab Sample isolation date Grab Sample isolation time 1 I i
- End of Section 4.4 -
O CP2804L Level of Use _ . STOP" ' THINK ' ACT REVIEW ~ Rev.1 Continuous 21 of 79 u
1 4.5 Reactor Coolant Depressurized 2 ml Grah Sample Isolation l ALARA This Section should only be performed when directed by MRDA or AMRDA. 1 4.5.1 l POSITION 2-S-482 (V-1) to " GRAB" 4 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" , l 4.5.5 POSITION 2-S-487 (V-3) to " NORMAL AND FLUSH." NOTE A de ressurized sample is now trapped (isolated) in the 2 ml shielded grab l samp e chamber. ; 4.5.6 RECORD the following information on Attachment 1: System sampled Grab sample isolation date
. Grab sample isolation time
- End of Section 4.5 -
O CP2804L Level of Use STOP' THiNK ' 4ACT' " REVIEW Rev.1 Continuous ' 22 0f 79
- 1 4.6 Reactor Coolant In-Line Sample Isolation Q)
ALARA j This Section should only be performed when directed by MRDA or AMRDA. 4.6.1 - SET rotary temperature switch to "T2." l 4.6.2 POSITION the following valves as specified:
- a. 2-S-482 (V-1) to " GRAB"
- b. 2-S-486 (V-2) to " BYPASS"
- c. 2-S-498 (V-17) to "OPEN"
- d. 2-S-487 (V-16) to "OPEN"
- e. 2-S-488 (V-4) to "OPEN" 4.6.3 WAIT at least 2 minutes 4.6.4 WHEN pH reading has stabilized, RECORD the following on Attachment 1:
pH reading > pH temperature (T2) l 4.6.5 POSITION the following valves as specified:
- a. 2-S-497 (V-16) to "CLOSE"
- b. 2-S-498 (V- 17) to "CLOSE'.
_ c. 2-S-487 (V-6) to OPEN.
- j. 4.6.6 IE flow is not at least 0.25 gpm, CONSULT with MRDA or AMRDA for guidance.
l th CP2804L Level of Use ....s- , . THIN [. . 'ACT REVIEW Rev.! l Continuous STY ' 23 cf 79 l 1 I
(h NOTE Steps 4.6.8 and 4.6.9 may be performed concurently with the 2 minute wait specified in step 4.6.7. 4.6.7 WAIT at least 2 minutes 4.6.8 Refer To Attachment 2 and DETERMINE correction factor for measured temperature. 4.6.9 ADD correction factor to pH value and RECORD sum on Attachment 1. , l 4.6.10 POSITION 2-S-490 (V-7) to "INLINE" 4.6.11 POSITION 2-S-491 (V-8) to "INLINE." 4.6.12 WAIT at least 15 seconds 4.6.13 POSITION 2-S-491 (V-8) to " BYPASS."
'"'^"'"""'"'""""
C1J J 4.6.15 WAIT 15 seconds j I 4.6.16 STOP stripping pump i 4.6.17 POSITION 2-S-489 (V-6) to "CLOSE." 4.6.18 ' ALLOW sample flow to drop to zero. 1 4.6.19 POSITION 2-S-488 (V-4) to "CLOSE." NOTE A pressurized sample of known volume is now isolated within the boundaries of 2-S-488 (V-4),2-S-489 (V-6), and 2-S-493 (V-11). i 4.6.20 RECORD the following information on Attachment 1: l
- System sampled '
i In-line sample isolation date CP2804L Level of Use . ST P' .THINK 'ACT REVIEW Rev.1 i Continuous ' 24 of 79 L
In-line sample isolation time O
~ 4.6.21 READ totalizer and RECORD final totalizer reading on l Attachment 1.
4.6.22 Go To Section 4.7
- End of Section 4.6 -
I i O l 1 l i L i i ! l i 1
)
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/ ... ,
25 of 79
- t. I
4.7 Stripping of Dissolved Gases 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: 4.7.6 2-S-493 (V-11) to "LIOUID". 4.7.7 2-S-491 (V-8) to " BYPASS" 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 WAIT until Gas Loop Pressure reading (P-2) from PI-1067 stabilizes. 4.7.13 POSITION 2-S-493 (V-11) to "LIOUID". 4.7.14 POSITION 2-S-491 (V-8) and 2-S-490 (V-7) to "INLINE" 4.7.15 START stripping pump I l 4.7.16 WHEN 1 minute has elapsed, STOP stripping pump. 4.7.17 POSITION 2-S-493 (V-11) to " GAS"
.O) u.
CP2804L
- Level of Use ACT REVIEW Rev.1 Continuous MOf M7K
- 26 of 79
! l ! I
y. 4.7.18 WAIT until Gas Loop Pressure reading (P-2) from PI-1067 stabilizes. 4.7.19 IE a pressure increase was noted in step 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." l 4.7.22 START stripping pump. l 4.7.23 POSITION the following valves as specified:
- a. 2-S-491 (V-8) to " BYPASS."
i b. 2-S-494 (V-12) to " BYPASS." l
- c. 2-S-495 (V-13) to " BYPASS."
d, 2-S-493 (V-11) to " GAS." 4.7.24 WAIT 1 minute t 4.7.25 POSITION 2-S-494 (V-12) to "INLINE" 4.7.26 POSITION 2-S-495 (V-13) 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 -
O CP2804L Level of USe - - - STOP THINK ACT REVIEW Rev.1 Continuous 27 of 79
r i ( l
\ .p 4.8 Flushing PASS Prior to Reactor Coolant Samples Retrieval (
4.8.1 On Remote Operating Module, POSITION the following valves are positioned as specified: l i a. 2-S-482 (V-1) to " BYPASS"
- b. 2-S-486 (V-2) to "ORAB"
- c. 2-S-487 (V-3) to " NORMAL AND FLUSH" l
- d. 2-S-488 (V-4) to "CLOSE"
- e. 2-S-489 (V-6) to "CLOSE"
- f. 2-S-490 (V-7) to " BYPASS" I
- 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" !
4.8.2 On PANEL C103D, PERFORM one of the following: E RCS Hot Leg was sampled, OPEN "2-S-449." i E HPSI/LPSI System was sampled, OPEN "2-S-448." i i NOTE l Opening "2-S-497" ("V-16") and "2-S-498" ("V-17") allows flow past the pH probe in the sample module. 4.8.3 At ROM, POSITION the following: O
. (V Level of Use CP2804L
._. ~ . .
i gOntinuous 'STO . THINK ~.. 'ACT' REVIEW Rev.1 28 of 79
l p a. 2-S-498 (V-17) to "OPEN" t
- 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
- hen Flush Pump P-155 is running. perating module " FLOWMETER" 4.8.4 On Panel C103D, POSITION " FLUSH PUMP P-155" to "ON."
4.8.5 START the stripping pump
, NOTE I
The following flush' times may vary according to the activity of the samples required. [
- a. CONTINUE flushing for 2. minutes and PERFORM the following:
CYCLE 2-S-488 (V-4) several times to ensure all i liquid is flushed from under valve seat. NOTE Radiation levelin sample module should decrease markedly as sample is i flushed from sample module piping. MONITOR flow and radiation levels to assess flush effectiveness.
- b. POSITION the following valves as specified:
( 1) 2-S-489 (V-6) to "OPEN"
- 2) 2-S-497 (V-16) to "CLOSE"
{J CP2804L Level of Use 3 STOP THINK 'ACT' ' REVIEW Rev.1 Continuous :@ M 29 of 79 L m
i l ,. l l
- 3) 2-S-498 (V-17) to "CLOSE" O c. CONTINUE flushing for another 2 minutes and CYCLE i'
2-S- 489 (V-6) several times. i l
\
b
- d. POSITION 2-S-493 (V-11) to " GAS." )
L e. WAIT 2 minutes
- f. STOP stripping pump
- g. POSITION the following valves as specified:
1
- 1) 2-S-489 (V-6) to "CLOSE" I
- 2) 2-S-486 (V-2) to " BYPASS"
- 3) 2-S-488 (V-4) to "CLOSE" h, WAIT at least 60 seconds i
- i. POSITION 2-S-482 (V-1) to " GRAB" l
( ) j. POSITION 2-S-486 (V-2) to "ORAB" 4 4.8.6 FLUSH for 60 seconds 4.8.7 PERFORM the following on PANEL C103D: i
- a. POSITION " FLUSH PUMP P-155" to "OFE" l
- b. PERFORM one of the following:
- =
E RCS Hot Leg was sampled, CLOSE "2-S-449." (. j E HPSI/LPSI System was sampled, CLOSE "2-S-448." l 4.8.8 Go To Section 4.9
- End of Section 4.8 -
C\ U ! Level of Use '
-.J CP2804L
. _ . . . . . . . . .~ . .
SIT THINK ACT REVIEW _. Rev.I ! Continuous r9 .
, 30 of 79 L
y i 4.9 - Reactor Coolant Sample Retrieval - f [ Chem Tech l 4.9.1 OBTAIN the following items and PROCEED to sample module l in Primary Sample Sink Room: PASS transport cart j l Prepared syringes l HP Tech 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 l E radiation level is greater than or equal to level specified in l Chem Tech l' 4.9.3 l radiological controls, Refer To Section 4.8 and PERFORM PASS I flush. l 4.9.4 PERFORM the following actions as applicable:
, E acquisition of pressurized 2 ml grab sample or ,
depressurized 2 ml grab sample is directed by MRDA or 1 AMRDA, Refer To Section 4.10 and RETRIEVE 2 ml grab sample from sample module. 1. E acquisition ofliquid in-line sample is directed by MRDA or AMRDA, Refer Tb 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. l 4.9.6 Go To Section 4.13.
- - End of Section 4.9 - l l '
L I i , i Y i
-{N G
CP2804L Level of Use STOP' THINK 'ACT' REVIEW Rev.1 Continuous * '
, 31 of 79
r I 4.10 Reactor Coolant 2 ml Grab Sample Retrieval ALARA This Secion should only be performed when directed by MRDA or i AMRDA. a 4.10.1 PROCEED to Primary Sample Sink Room 4.10.2 OPEN module door. l 4.10.3 GRAB unlaiching inob and PULL slide tray outside of sample module. 4.10.4 DISCONNECT flexible hoses from grab sample valve operator. 4.10.5 LIFI 2 m! grab sample chamber from slide tray and PLACE in transport container. 4.10.6 PLACE lid on transport container. 70 4.10.7 PLACE spare 2 mi sample chamber on slide tray. l
.V 4.10.8 ENSURE 2 mi grab sample chamber is located so that quick connect collars are properly positioned in yoke and 2 ml 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 3 mple module untilliquid quick connects latch. 4.10.12 CLOSE module door. l
- End of Section 4.10 - l l
l O. I ' L) , l Level of Use CP2804L STOP.- THINK _-. ..'ACT * . . -REVIEW Rev.1 Continuous g - ; . 32 of 79
.-q 4.11 Reactor Coolant Liquid In-Line Sample Retrieval L)
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 lower access door. 4.11.3 INSERT " LIQUID ISOTOPIC" syringe gently into brass needle l guide until syringe needle bottoms on septum. 4.11.4 OPEN 2-S-492 (V-9) by gently pulling valve handle out to its stop. ___ 4.11.5 COMPLETE insertion of" LIQUID ISOTOPIC" syringe needle idto brass needle guide until syringe needle nut mates into need guide slot. I (m) ALARA i
- 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 100 1 liquid sample, then LOCK sample in
" LIQUID ISOTOPIC" syringe by unscrewing syringe nosecap l 2 turns.
4.11.7 WITHDRAW " LIQUID ISOTOPIC" syringe carefully from l needle guide. 4.11.8 CLOSE 2-S-492 (V-9) by gently pushing valve handle in to its
- stop (handia. is parallel to chamber).
4.11.9 PLACE " LIQUID ISOTOPIC" syringe in transport container. 4.11.10 INSERT " CHLORIDES" syringe gently into brass needle guide until syringe needle bottoms on septum. ( \ L) CP2804L
- Level of Use -.
STOP' THINK ACT REVIEW Rev.1 Continuous - 33 of 79 L
I l 4.11.11 OPEN 2-S-492 (V-9) by gently pulling valve handle out to its (n ) stop. 4.11.12 COMPLETE insertion of" CHLORIDES" syringe needle into brass needle guide until syringe needle nut mates into needle l guide slot. l 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.
4.11.13 WITHDRAW 1.0 ml liquid sample, then LOCK sample in
" CHLORIDES" syringe by unscrewing syringe nosecap 2 turns.
4.11.14 WITHDRAW " CHLORIDES" syringe carefully from needle gnide.
~4.11.15 CLOSE 2-S-492 (V-9) by gently pushing valve handle in to its stop (handle is parallel to chamber).
4.11.16 PLACE " CHLORIDES" syringe in transport container. 4.11.17 CLOSE sample module lower access door.
- End of Section 4.11 -
V,O CP2804L Level of Use - STOP- THINK ACT REVIEW Rev.1 CONTINUOUS 34 of 79
i
,q , 4.12 Reactor Coolant Gaseous In-Line Sample Retrieval i V ALARA This Section should only be performed when directed by MRDA >r i AMRDA.
4.12.1 PROCEED to Primary Sample Sink Room 4.12.2 OPEN sample module upper access door. 4.12.3 INSERT " GAS ISOTOPIC" syringe gently into brass needle guide until syringe needle bottoms on septum. i 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 bfass needle guide until syringe needle nut mates into brass needle guide slot. I
/
(_/ 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. I 4.12.6 WITHDRAW 100 1 gas sample, then LOCK sample in " GAS ISOTOPIC" syringe by unscrewing syringe nosecap 2 turns. 4.12.7 WITHDRAW " GAS ISOTOPIC" syringe carefully from brass needle guide. 4.12.8 CLOSE 2-S-496 (V-14) by gently pushing valve handle in to its stop. 4.12.9 RECORD volume of gas sample transferred to syringe (Vi ) on , Attachment 1. l I 4.12.10 INSERT needle into stoppered 14cc gas vial.
,a fU Level of Use .
CP2804L l
.mM
-STOP , ACT RE m Rev.1 Continuous 35 of 79
I l 4.12.11 UNLOCK syringe and INJECT gas contents into stoppered 14cc l gas vial. 4.12.12 PLACE " GAS ISOTOPIC" syringe and 14cc gas vial in transport container. 4.12.13 INSERT" GAS COMP" syringe gently into brass needle guide l until syringe needle bottoms on septum. 4.12.14 OPEN 2-S-496 (V-14) by gently pulling valve handle out to its stop. 4.12.15 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 ne-edle from syringe.
- 2. Steps 4.12.16 through 4.12.19 should be performed rapidly to minimize exposure.
O V 4.12.16 WITHDRAW 500 1 gas sample, then LOCK sample in " GAS COMP" syringe by unscrewing syringe nosecap 2 turns. 4.12.17 WITHDRAW " GAS COMP" syringe carefully imm brass needle guide. 4.12.18 CLOSE 2-S-496 (V-14) by gently pushing valve handle in to its l stop. ; l 4.12.19 PLACE " GAS COMP" syringe in transport container. 4.12.20 CLOSE sample module door. 1
- End of Section 4.12 -
I U,m l CP2804L Level of Use ST P THINK ACT REVIEW Rev.1 Continuous 36 of 79
f
, 4.13 Analysis of Reactor Coolant Samples I l 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 I transport. l
- l HP Tech l 4.13.2 E liquid in-line samples OE gaseous in-line samples were l 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 REQUEST instructions for handling.
- c. E dose rate is less than 1 R/hr, DIRECT Chemistry
'Iechnicians to handle samples as normal radioactive samples and to minimize radiation exposure when performing required analyses.
l Chem Tech l: 4.13.3 R'efer To the following sections as applicable and PERFORM analysis: p
- Section 4.14," Reactor Coolant Liquid Isotopic Analysis" V
Section'4.15," Reactor Coolant Total Dissolved Gas Analysis" Section 4.16," Reactor Coolant Chloride Analysis" Section 4.17," Reactor Coolant Boron Analysis" Section 4.18," Reactor Coolant Gaseous Isotopic Analysis" ; Section 4.19," Reactor Coolant Gas Composition Analysis" 4.13.4 E copics of results are requested, FAX or SEND copies of the l applicable Attachments or isotopic printouts to requesting l individuals: 4.13.5 FORWARD original and copy of completed attachments and gamma spectrometer printouts to Chemistry Supervision. L O Level of Use _ CP2804L
.ST P ' THINK ' ~AUT ~ REVIEVi Rev.1 Continuous . "i 37 0f 79
r: O W Attai y l High-level radioactive waste j samples cann(greater ot be disposed of thanm the orchemistry egual to lab100 mrem /hr) hot sink. l 4.13.6 IE 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: l
- 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 -
'O 1 i i i LO CP2804L Level of Use .
?,
ST P' . . .THINK ' ACT REVIEW Rev.1 Continuous ' 38 of 79
l l q 4.14 Reactor Coolant Liquid Isotopic Analysis V i ' l Chem Tech l 4.14.1 PREPARE 20 ml" ISOTOPIC ORIGINAI" sample bottle as follows: ! a. TARE 20 mi sample bottle.
- b. ADD 10 ml DI water to sample bottle.
- c. WEIGH sample bottle and RECORD DI water mass on l Attachment 7.
- d. TARE 20 mi sample bottle with water.
ALARA Steps 4.14.1 e. through k. should be performed rapidly to minimize l-exposure. L
- e. REMOVE " LIQUID ISOTOPIC" syringe from syringe transfer container.
- f. INJECT contents of " LIQUID ISOTOPIC" syringe into l sample bottle.
- g. WEIGH sample bottle and RECORD 100 1 sample mass on the following:
Attachment 4 (Md d
=
Attachment 7
- 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.
l HP Tech - l 4.14.2 MEASURE contact dose rate of " ISOTOPIC ORIGINAL"
, bottle.
a CP2804L Level of Use .. ~
..STOP' THINK ACT. REVIEW Rev.1 Continuous l /
- s 39 of 79 I
L i
l n g
._ _l Chem Tech l 4.14.3_ E contact dose rate of sample bottle is greater than or equal to 25 mR/hr, Go To step 4.14.5.
4.14.4 E contact dose rate of " ISOTOPIC ORIGINAI" 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]
- a. TRANSFER 1.0 mi from bottle containing sample (solute 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.
e.' LABEL solvent liter bottle either "1St, "2nd, "3rd, a4th, "5th, a
"6th, or 7th DILUTION," as applicable, for the 1:1000 dilution being performed.
(' _._ f. CIRCLE either "151, "2nd, "3rd, a4th, "5th, "6th, or "7th 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 i mR/hr, Go To rap 4.14.6. i l i. E contact dose rate of solvent liter bottle is greater than or l equal to 25 mR/hr, Go To step 4.14.5 a.. l l 4.14.6 DETERMINE reactor coolant liquid isotopic activity as follows: l
- a. PLACE sample bottle in plastic bag and SEAL bag. l
- b. PLACE 2.5 cm shelf in detector to be used for reactor coolant liquid isotopic analysis.
Level of Use CP2804L
. STOP " THINK ~ ACT ' REVIEW' Rev.1 i Continuous 40 of 79 z
I
- c. Using the following information, Refer To f
CP 801/2801/3801 AT, " Gamma Spectroscopy Counting l System Maintenance and Operation," and ANALYZE sample: Closed cave Applicable geometry for sample container and shelf being used a Five minute count time Generallibrary l Sample mass corresponding to the last circled sample dilution on Attachment 4 Inline sample date and time as recorded on Attachment I
- d. IE dead time is greater than or equal to 20%, PERFORM the following:
, 1) ABORTcount.
- 2) Go To step 4.14.5.
( e. STORE sample bottle in shielded location.
- f. DETERMINE background as follows:
- 1) Using the fc,llowing information, Refer To CP 801/2801/3801 AT, " Gamma Spectroscopy Counting System Maintenance and Operation," and PERFORM background count en detector that was used for reactor coolant liquid isotopic analysis.
- Closed cave Applicable geometry for shelf that was used ,
Five minute count time a General library Sample mass corresponding to the last circled sample dilution on Attachment 4
- 2) RECORD all identified isotopes and their associated
- background activity levels in pCi/gm on Attachment 5.
fO i Level of Use ^ CP2804L
.-STOP ~ .THINK ACT?- REVIEW Rev.1 Continuous
.- i 41 of 79 l
(! ! g. Refer To Attachment 5 and CALCULATE reactor coolant
~v.(.s) liquid isotopic activity as follows:
- 1) Refer To reactor coolant liquid isotopic printout and RECORD all identified isotopes and their associated activity levels in pCilgm.
I
- 2) For each isotope listed, SU13 TRACT background activity and RECORD as isotope activity in Ci/gm.
- 3) ADD isotope activities and RECORD as total isotope activity in pCi/gm.
4.14.7 REPORT results to MRDA or AMRDA. 4.14.8 Go To step 4.13.3 and COMPLETE any remaining analysis. l
- End of Section 4.14 -
U, l n LJ CP2804L Levelof Use - . . . . , . .. . STOP- THINK' "ACT' REVIEW. Rev.1 Continuous < . 42 0f 79
l 4.15 Reactor Coolant Total Dissolved Gas Analysis 4.15.1 Refer To one of the following and CALCULATE total dissolved gas: Computer program
=
Attachment 3 4.15.2 RECORD total dissolved gas in cc/kg on Attachment 1. 4.15.3 REPORT results of total dissolved gas analysis to MRDA or AMRDA. 4.15.4 Go To step 4.13.3 and COMPLETE any remaining analysis. l l
- End of Section 4.15 - l l
O LJ i i l CP2804L Level of Use . . . . . . . . .. .. sT P' Th!NK ' ..AT . .. REVIEW Rev.1 Continuous " r 43 of 79
4.16 Reactor Coolant Chloride Analysis V 4.16.1 REMOVE " CHLORIDES" syringe from syringe transfer container. 4.16.2 INJECT contents of" CHLORIDES" syringe into small test tube located in lead brick at IC. 4.16.3 Refer To CP 801/2801/3801Y," Routine Operation and Calibration of the Laboratory Ion Chromatography Systems," and ANALYZE sample for chlorides. 4.16.4 PLACE empty " CHLORIDES" syringe in plastic bag and SEAL bag. 4.16.5 PLACE sealed plastic bag in properly shielded location for future disposal. 4.16.6 RECORD chloride concentration in ppm on Attachment 7. 4.16.7. R'EPORT results to MRDA or AMRDA. 4.16.8 Go To step 4.13.3 and COMPLETE any remaining analysis. l
- End of Section 4.16 -
l l L lO Level of Use ,b
's M AcT ' REVIEW' CP2804L Rev.1 l Continuous 1( m ,
e '"' 44 of 79 i i ,
ri-4.17 Reactor Coolani Boron Analysis
- O
- l. 4.17.1 WHEN sample bottle labeled " ISOTOPIC ORIGINAI" is no
- longer needed for isotopic analysis, Refer To CP 801/2801 AJ, l " Inductively Coupled Argon Plasma Analysis" and ANALYZE
- sample bottle for boron.
4.17.2 PLACE " ISOTOPIC ORIGINAL" 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 REPORT results to MRDA or AMRDA. 4.17.6 Go To step 4.13.3 and COMPLETE any remaining analysis. l
- End of Section 4.17 -
1 l I i fh U CP2804L Level of Use .
. STOP" .THINK ACT REVIEW - Rev.1 Continuous , ..' '
45 of 79 a
! i i
- l. 4.18 Reactor Coolant Gaseous Isotopic Analysis
\ uJ 4.18.1 WRAP stoppered 14cc vial in plastic wrap. 1 l
)
4.18.2 DETERMINE gas isotopic activity as follows: l l a. Using the following information, Refer To CP 801/2801/3801AT," Gamma Spectroscopy Counting System Maintenance and Operation," and ANALYZE ' sample:
- Open cave I Applicable geometry for shelf being used l i
=
Five minute count time Generallibrary l !
=
Sample isolation date and time as recorded on Attachment 1 a = Sample quantity as calculated on Attachment 1
- b. IE dead time is greater than or equal to 20%, PERFORM the following:
~)
- 1) ABORTcount.
- 2) REPLACE shelf with next higher shelf.
- 3) Go To step 4.18.2a.
- c. PLACE empty " GAS ISOTOPIC" syringe and 14cc vial in labeled plastic bag and SEAL bag.
- d. PLACE scaled plastic bag in source locker for future disposa!.
i l I e Level of Use - CP2804L ' I
'STbP TphK ~ 'ACp REVIEW Rev.1 gontinuous -
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I l I DETERMINE background as follows: O G e. ! 1) Using the following information, Refer To l CP 801/2801/3801 AT, " Gamma Spcctroscopy Counting ] i System Maintenance and Operation," and PERFORM l background count on detector that was used for gas {' i isotopic analysis. l Open cave Applicable geometry for shelf that was used l Five minute count time j l General library l Sample quantity as calculated on line 14 of Attachment 1
- 2) RECORD allidentified isotopes and their associated background activity levels in pCi/gm on Attachment 6.
f., Refer To Attachn ent 6 and CALCULATE gas activity as follows:
- 1) Refer To gas isotopic printout and RECORD all identified isotopes and their associated activity levels in pCi/gm.
- 2) For each isotope listed, SUBTRACT background activity from printout activity and RECORD as isotope activity in pCi.'gm. '
- 3) ADD isotope activities and RECORD as "1btal Gaseous Activity."
4.18.3 REPORT total gaseous activity to MRDA or AMRDA. 4.18.4 Go lb step 4.13.3 and COMPLETE any remaining analysis. l 1
- End of Section 4.18 -
l I .O CP2804L Level of Use .
' STdP' THINK 'ACT' REVIEW Rev.1 Continuous +
~
4 47 0f 79 ' l
4.19 Reactor Coolant Gas Composition Analysis 4.19.1 REMOVE " GAS COMP" syringe from transport container. 4.19.2 Refer To CP 801/2801/3801AD, " Gas Chromatograph," and PERFORM the following analyses on sample: l
- Hydrogen analysis 1.
Oxygen analysis 4.19.3 PLACE empty " GAS COMP" syringe in a labeled plastic bag and sealbag. 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 Attachment 6. 4.19.6 C$o To step 4.13.3 and COMPLETE any remaining analysis. l p - End of Section 4.19 - k.) l I l l l O
.LJ L. CP2804L i . Level of Use _ . . . .
THINK' ACT ' REVIEW Rev.1 Continuous SIOP'
- Lit 48 of 79
.=
c: o 4.20 PASS Restoration k i l NOTE Performance of this section prepares the reactor coolant PASS and sample chambers for the next sampim. contamination from samphng pipmg and eqm(pment.g by removing flushing 4.20.1 PROCEED to PASS sampling area in Unit 2 Turbine Building. j 4.20.2 On Remote Operating Module, VERIFY the following valves are positioned as specified:
- a. 2-S-482 (V-1) to " BYPASS"
- b. 2-S-486 (V-2) to "ORAB"
- c. 2-S-487 (V-3) to " GRAB SAMPLE"
- d. 2-S-488 (V-4) to "CLOSE" g e. 2-S-489 (V-6) to "CLOSE" V f. 2-S-490 (V-7) to "INLINE"
- g. 2-S-491 (V-8) to " BYPASS"
- h. 2-S-493 (V-11) to " GAS"
- i. 2-S-494 (V- 12) to "IN-LINE"
- 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"
- n. 2-S-499 (V-18) to "HI-FLOW"
[ ; i C CP2804L i Level of Use . .. ,. . . STOP' . THINK' .ACT REVIEW Rev.1 Continuous 4 ( 49 of 79
i
'4.20.3 On PANEL C103D, PERFORM the following:
' V i i
- a. PERFORM one of the following:
l
- IE RCS Hot Leg was sampled, OPEN "2-S-449."
IE HPSI/LPSI System was sampled, OPEN "2-S-448."
- b. POSITION " FLUSH PUMP P-155" to "ON."
4.20.4 On Remote Operating Module, PERFORM the following:
\
- a. POSITION the following valves as specified:
i
- 1) 2-S-489 (V-6) to "OPEN"
- 2) 2-S-498 (V-17) to "OPEN"
- 3) 2-S-497 (V-16) to "OPEN"
- 4) 2-S-488 (V-4) to "OPEN"
- 5) 2-S-495 (V-13) to "IN-LINE" O
NOTE A flo,w should be evident on " FLOWMETER" when stripping pump is runnmg. E
- b. START stripping pump
- c. WAIT at least 3 minutes
- d. POSITION 2-S-494 (V-12) to " BYPASS"
- e. POSITION 2-S-495 (V-13) to " BYPASS"
- f. WAIT 30 seconds
- g. POSITION 2-S-491 (V-8) to "INLINE" i h. STOP stripping pump ,
1
- i. POSITION 2-S-494 (V-12) to "lN-LINE."
]
Level of Use ; CP2804L i ST P" ~ ' THIN'K ' 'ACT' REVIEv/ Rev.1 l Continuous
- 50 of 79 l
r:
- j. WAIT at least 3 minutes
' d,o
- k. POSITION the following valves as specified:
- 1) 2-S-490 (V-7) to " BYPASS"
- 2) 2-S-491 (V-8) to " BYPASS"
- 3) 2-S-486 (V-2) to " BYPASS"
- 1. WAIT at least 30 seconds
- m. POSITION the following valves as specified:
- 1) 2-S-488 (V-4) to "CLOSE"
- 2) 2-S-489 (V-6) to "CLOSE"
- 3) 2-S-497 (V-16) to "CLOSE"
- 4) 2-S-498 (V-17) to "CLOSE"
- 5) 2-S-482 (V-1) to " GRAB" 1
- 6) 2-S-486 (V-2) to " GRAB"
- n. FLUSH for at least 3 minutes
- o. POSITION 2-S-487 (V-3) to " NORMAL AND FLUSH."
4.20.5 On Panel C103D, POSITION " FLUSH PUMP P-1.<5" to "OFE" 4.20.6 On flush module, CLOSE "2- S-506". l 4.20.7 On PANEL C103D, PERFORM one of the following: E RCS Hot Leg was sampled, CLOSE "2-S-449." E HPSI/LPSI System was sampled, CLOSE "2-S -448." 4.20.8 On Remote Operating Module, PERFORM the following:
- a. POSITION the following valves as specified. )
O CP2.804L Level of Use . l STOP THINK ~ =ACT' REVIEW Rev.1 j CONTINUOUS " 51 of 79
r l
- 1) .2-S-482 (V-1) to " BYPASS" O 2) 2-S-486 (V-2) to " GRAB"
- 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 "LIOUID"
- 9) 2-S-494 (V-12) to " BYPASS"
- 10) 2-S-495 (V-13) to " BYPASS"
- 11) 2-GAN-259 (V-15) to "CLOSE" g 12) 2-S-497 (V-16) to "CLOSE" U
- 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.
4.20.9 At nitrogen bottle, CLOSE nitrogen bottle isolation valve. 4.20.10 DE-ENERGIZE Remote Operating Module. 4.20.11 REPLACE and LOCK anti-tamper covers on the following modules and panels: ; Remote Operating Module
" PANEL C103C"
* " PANEL C103D" 4.20.12 PROCEED to sample module in Primary Sample Sink Room.
O V Levelof Use - CP2804L _ SToP' THINK ~ACT REVIE / Rev.1 l Continuous M
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52 of 79 l e.
r l l l 4.20.13 PLACE 2-S-453 in "POS 2." 4.20.14 IE open, CLOSE "2-S-460." 4.20.15 Behind primary sample sink, CLOSE 2-S-504. 4.20.16 REQUEST second chemistry technician to independently verify the position of the following valves: I a. 2-RC-001 "CLOSE"
- b. 2-RC-002 "CLOSE"
- c. 2-RC-003 "OPEN" l d. 2-RC-045 "OPEN"
- e. 2-LRR-61.1 "CLOSE" 4.20.17 DOCUMENTindependent verification on Attachment 12,
" Isolation Valves Independent Verification Sheet" 4.20.18 RETURN to chemistry lab.
)
4.20.19 NOTIFY MCRO that reactor coolant PASS sampling has been completed. l l - End of Section 4.20 - l l L l i I 1 i
-V0 '
Level of Use o, . CP2804L
' gontinUOUS STOP THINK !ACT' REVIEW Rev.1 53 of 79
r p Liquid PASS ' 4.21 Liquid Waste Sampling and Analysis g Team ALARA l 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 CWMT has been recirculated at least 2.0 hours with mixer or at least 7.7 hours with pump. E AWMT is to be sampled, CONSULT MCRO to ENSURE AWMT has been recirculated at least 0.5 hours with mixer or at least 4.0 hours with pump. 4.21.3 PROCEED to left side of primary sample sink in Primary Sample Sink Room. v 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). j
- c. E sampling A CWMT, REQUEST operations close !
"2-LRR- 124.1 A." 4
- d. E sampling B CWMT, REQUEST operations close "2- LR R- 124.1 B."
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.
O. V l CP2804L Level of Use . . - . STOP ~- THINK- 'ACT REVIEW Rev.1 Continuous - ' " 54 of 79
i t 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. THROTTLE 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 sample 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
/~'; level specified in radiological controls.
V ALARA 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 to primary sample sink.
] HP Tech. l 4.21.7 MONITOR dose rates l Chem Tech. l 4.21.8 E dose rates preclude obtaining required discharge samples,
, PERFORM the following: l a. NOTIFY MRDA lIV CP2804L Level of Use .
..STOP THINK ACT REVIEW Rev.1 Continuous 55 of 79 I
)
p
- b. REQUEST guidance on sample volumes.
I c. OBTAIN sample equipment required to collect adequate l sample for analyses. I i 4.21.9 Refer To SP 2864 and OBTAIN required sample aliquots for discharge permit preparation. l
-4.21.10 E AWMT was sampled AND sampling is complete, PERFORM the following:
- a. NOTIFY Operations that "2-LRA-55.1" may be opened
- b. CLOSE "2-S-128" Sample Isolation Valve.
4.21.11 E CWMT was sampled AND sampling is complete, PERFORM the following:
- a. E A CWMT was sampled, NOTIFY Operations that
, "2-LRR-124.1A may be opened.
- b. E B CWMT was sampled, NOTIFY Operations that "2-LRR-124.1B may be opened.
O 4.21.12 CLOSE 2-S-111 Sample Isolation Valve. 4.21.13 Refer To CP 801/2801/3801AT," Gamma Spectroscopy Counting System Maintenance and Operation," and PERFORM liquid waste activity analysis as follows:
- 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.
- d. PLACE bagged sample liter bottle on detector in gamma spectrometer and PERFORM a 5 minute, closed cave count using the following information:
Sample date and timc aa record.J on Attachment 9. Sample volume corresponding to the last circled sample dilution on Attachment 4. CP2SO4L Le'iel of Use .. .
...STOP'_ THINK . ACT -. REVIEW Rev.1 Continuous '
56 of 79
- e. IE dead time is less than 20%, Go To step 4.21.14.
O f. IE dead time is greater than or equal to 20%, PERFORM the following:
- 1) OPEN cave and REMOVE sampl:: liter bottle.
- 2) TRANSFER 1.0 ml of sample from sample liter bottle (the solute liter bottle) into another 1 liter plastic bottle filled with demineralized water (the solvent liter bottle).
- 3) RECORD new sample volume on Attachment 4, as l applicable, for the 1000:1 dilution being performed.
l l 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 R,efer 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:
- 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 i
~N l ~ (G Level of Use CP2804L STOP' THINK 7ACT', REVIEW Rev.1 Continuous * ^*
57 of 79 i
l 4.21.18 SEND originals of the following documents to MRDA or l AMRDA: Completed attachments Gamma spectrometer printouts E originated, completed liquid discharge permit
- 4.21.19 FILE copies of the following documents:
Completed attachments j 1 Gamma spectrometer printouts E 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 -
O i O CP2804L Level of Use . . ST P" THINK ACT REVIEW Rev.1 Continuo S ' 58 of 79 L
! l 4.22 PASS Equipment Inventory I i 4.22.1 Quarterly and after each PASS sample, PERFORM inventory of all equipment required to perform containment PASS sampling.
,. 4.22.2 COMPLETE Attachment 8," Reactor Coolant Sampling Inventory."
4.22.3 FORWARD Attachment 8 to Chemistry Supervision
- End of Section 4.22 -
l Q l l l O CP2804L Level of Use .,,_,.. .. . . , .. . .. STpf THINK 'ACT ,' REVIEW Rev.1
. Continuous ""
' ~
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l l q 5. REVIEW AND SIGNOFF b 5.1 Indicate (check) Subsections of this procedure which were performed: O 4.1 04.2 'O 4.3 ,]4.4 04.5 0 4.6 04.7 O 4.8 Q 4.9 0 4.10 0 4.11 0 4.12 0 4.13 0 4.14 0 4.15 0 4.16 0 4.17 0 4.18 O 4 19 0 4.20 0 4.21 0 4.22 5.2 If p^ocedure was terminated prior to completion, specify cause: 5.3 This procedure was performed by the following personnel: Job supervisor (MRDA): O Print Name Signature Initials Liquid PASS Team personnel: Print Name Signature Initials Print Narae Signature Initials Print Name Signature Initials Print Name Signature Initials 5.4 This procedure was reviewed by Chemistry Supervision: Print Name Signature Initials
- 6. REFERENCES 6.1 "Fmal Safety Analysis Report Unit 2," Appendix 12A CP2804L Level of Use . h.
STOP' THINK
~
ACT REVIEW Rev.1 Continuous *
/ 60 of 79
{ L l i 6.2 " Millstone Nuclear Power Station Emergency Plan" 6.3 RAB Accident and Shielding File #608.002 6.4l NUREG-0654," Criteria for Preparation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" i. l 6.5 N'UREG-0737," Clarification of TMI Action Plan Requirements, l = Supplement 1, Requirements for Emergency Response Capability" 1
- 6.6
" Instructions Model 8500 Gas Chromatograph:" Perkin-Elmer, October 1987 6.7 " Technical Manual for De-Ionize <'. Water Flushing Module:" General Dynamics Corporation; Electric Loat Division, Reactor Plant Services, November 1981
' 6.8 " Technical Manual for Reactor Coolant Post-Accident Sample System:"
General Dynamics Corporation; Electric Boat Division, Reactor Plant Services, May 1982 6.9 "VAX/VMS Spectroscopy Applications Package User's Manual 07-0196," i April 1982 V . 6.10 SP 2864," Liquid Waste Discharge" 6.11 CP 801/2801/3801AT," Gamma Spectroscopy Counting System Maintenance and Operation" 6.12 CP 801/2801/3801AD," Gas Chromatograph" 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 J. Broussard, dated January 18th 1993 6.16 CP 801/2801/3801 AJ," 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 O CP2804L Level of Use ..
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~
S1OP' THINK i ACT REVIEW Rev.1 Continuous g ,2 i ' 61 of 79
r 6.18 NRC, Commitment Record # RCR-10781. Docketed Correspondance O Dated 11/17/87. Combined Inspection 50-245/87-24,50-336/87-21, 50 -423/87 - 19. 6.19 USNRC Reg Guide 1.97, Rev. 3 May 1983," Instrumentation fer Light Water Coolant Nuclear Power Plants to Assess Plant and Environs Conditior. During and Following an Accid at 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" , p 6.25 Memo 98-067, From Max Keyes to Tom Blount, PASS Procedure V 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 Samp!.ing Systems," Final Report, May 1984 6.29 INPO Post Accident Sampling Preparedness CY 707 INPO 91-01') 6.30 Technical Paper," Temperature - Another Wild Card in pH Control," submitted by TBI-Bailey, February 14,1995. l l Level of Use .. - CP2804L SToP' THINK ' l'ACT REVIEW Rev.1 Continuous ' 4 62 of 79 l l
p 7.
SUMMARY
OF CHANGES 7.1 Modified paragraph in discussion Section describing 3 hour time limit for collecting and analyzing PASS samples. 7.2 Deleted paragraph in discussion Section describing gas chromatograph and IC set-up upon SERO activation. Made set-up of allinstruments a prerequisites that can be performed upon SERO activation. 7.3 Added numerous prerequisites including set-up and calibration of required instruments. 7.4 Deleted prerequisite for ADEOF to request performance of this procedure. The ADTS makes the decision to collect a sample using the PASS system. This is reflected in the Section 2.5, " Responsibilities." 7.5 Dcleted prerequisite for MRCA or OSC ARPS to assess exposure to personnel is within NU or Fedeial limits. The PASS sampling procedure has been evaluated and determined to result in exposures below the allowed limits during a worst case accident. 7.6 Deleted option in prerequisites for alternate sample volume. The volumes used have been evaluated and determined to result in exposures (] L.j' below the allowed limits during a worst case accident. 7.7 Deleted option in prerequisites for MRDA or the AMRDA to select boron and chloride analysis method based on radiological conditions, complexity of sample matrix, or both. The methods used have been evaluated and determined to result in exposures below the allowed limits during a worst case accident. 7.8 Moved steps to preform syringe check to Attachment 10," Syringe Check." Made syringe check a prerequisite to be completed using Attachment 10. 7.9 Added CP 801/2801/3801Y," Routine Operation and Calibration of the Laboratory lon Chromatography System," and "RWP for PASS sample collection" to Section 2.2," Documents." Deleted CP 2801X," Routine Operation, Calibration and Maintenance of the DX-120 and DX-500 Laboratory Ion Chromt.tography Systems," from Section 2.2. 7.10 Added pH probe to Section 2.4," Tools and Consumables." l 7.11 Deleted definitions for personnel and defined them in Section 2.3, l
" Personnel."
p 7.12 Added precaution for maximum design pressure of pH probe. V CP2804L Level of Use STOP THINK ACT REVIEW Rev.I Continuous 63 of 79 l
I l g 7.13 Deleted Sections 4.2," Determination of Sampling and Analysis !
\'"' Requirements,' and 4.3," Chemistry Lab Preparation for Reactor Coolant Sampling and Analysis." Moved required actions to Section 2.1,
" Prerequisites."
7.14 Changed from " lower access door" to " module door" when retrieving 2 ml grab sample chambe3i n Section 4.10," Reactor Coolant 2 ml Grab Sample Retrieval." 1 7.15 Changed syringe label from " ISOTOPIC" to " LIQUID ISOTOPIC." 7.16 Added steps to Section 4.6," Reactor Coolant In-Line Sample Isolation," to temperature compensate pH reading using Attachment 2. 7.17 Changed Section 4.7," Reactor Coolant Total Dissohed Gas Measurement.," to match same steps in SP 2849. 7.18 Added ALARA warning to minimize handling of syringe samples. 7.19 Moved collection of" GAS ISOTOPIC" sample to before " GAS COMP" { sample. Withdrawing the " GAS ISOTOPIC" sample after the " GAS COMP" sample invalidates part of the basis for calculating the syringe 1 sample quantity. ! O V 7.20 Moved injection of " GAS ISOTOPIC" syringe into 14cc gas vial from i Section 4.18, " Reactor Coolant Garcous Isotopic Analysis," to Section 4.12," Reactor Coolant Ga:.cous In-Line Sample Retrieval." 7.21 Deleted Section 4.15," Preparation of Reactor Coolant Samples 4or ! Analysis." Put required steps in Sections 4.13, " Analysis of Reactor ! Coolant Samples," and 4.14," Reactor Coolant Lignid Isotopic Analysis." 7.22 Added step for HP to determine handling requirements for syringe samples brought to lab. 7.23 Added " contact" or "on contact" to steps obtaining dose readings of samples. 7.24 Changed steps in Section 4.13," Analysis of Reactor Coolant Samples," to allow any sample to be preformed in any order. Also added step at end of each sample section to return to this section and complete any remaining analysis. 7.25 Changed " Isotopic Original" volume from 1.0 liter to 10 ml to reduce dilution factor from 1:10,000 to 1:100. This allows boron analysis to be p performed on the " Isotopic Original" bottle. I GA CP2804L Level of Use STOP THINK ACT' REVIEW Rev.1 Continuous 64 of 79
f i em 7.26 Moved steps directing disposition ofisotopic printouts and attachments ( ,) from Sections 4.14," Reactor Coolant Liquid Isotopic Analysis," and 4.18, l
" Reactor Coolant Gaseous Isotopic Analysis," to Section 4.13, " Analysis of Reactor Coolant Samples." Inserted "1E requested" at beginning of step i to send copies to MRDA or AMRDA. l 7.27 Moved isotopic background counts to after sample counts. This allows any contamination left on a counting shelf to be subtracted as background.
)
7.28 Changed Section 4.16," Reactor Coolam Chloride Analysis," to inccrporate the use of a shielded test tube and to direct the storage of the empty " CHLORIDES" syringe. 7.29 Changed Section 4.17," Reactor Coolant Boron Analysis," to analyze the I
" ISOTOPIC ORIGINAI" bottle prepared in Sec+ ion 4.14, " Reactor Coolant Liquid Isotopic Analysis."
7.30 Condensed steps in Section 4.18," Reactor Coolant Gaseous Isotopic Analysis," directing actions when dead time is greater than 20%. 7.31 Deleted shelf ratio calculation and associated Attachment. A calibration efficiency curve has been prepared for each shelf that can be used with the 14cc vial.
,~
U 7.32 Rewrote TDG formula and revised syringe sample quantity in response to CR M3-97-3450. Added option to determine TDG using computer program or Attachment 3," Liquid PASS Total Dissolved Gas Worksheet." 7.33 Deleted liquid waste from Attachment 4," Unit 2 Post Accident Sampling Reactor Coolant Sample Dilution Data Sheet." Changed sample volume determination to sample mass determination based on measured mass of 100 pl syringe sample and number of 1:1000 dilutions performed. I i o
%s CP2804L Level of Use ST P THINK ACT REVIEW Rev.1 ,
Continuous 65 of 79 l
c Attachment 1 Unit 2 Determination of Total Dissolved Gas and Sample Quantity Worksheet l (Sheet 1 of 2) Grab Sample Worksheet Completed by: System Sampled: . Print Name Isolation Datc: Isolation Time: Signature: Jn-line Sample System Samplet Isolation Date: Isolation Time: DATA
- 1. Initial Totalizer Reading Gals
- 2. Radiation Meter Reading: rem /hr
- 3. Uncorrected 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
- 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 l
- 13. Calculate the syringe sample quantity as follows:
V i= 6.40 Ms gm V+5 i Where V t= Volume of Gas Sample in Syringe in ml. Reviewed by: Date: Print Name Signature
/^'\
I.J CP2804L Level of Use . . STOP' THINK ACT REVIEW Rev.1 Continuous 66 of 79
e 1 Attrchment 2 pH Temperature Compensation (Page1of1) Temperature Pli ( 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 ; i 68 - 0.02 - 0.01 0 - 0.01 - 0.02 1 70 - 0.01 - 0.01 0 - 0.01 - 0.01 1 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 i 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 b'O 90 0.05 0.03 0 0.03 0.05 92 0.06 0.03 0 0.03 0.06 94 0.07 0.03 0 0.03 0.07 I 96 0.08 0.04 0 0.04 0.08 i 98 0.08 0.04 0 0.04 0.08 100 0.09 0.04 0 0.04 0.09 l 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 J _ 120 0.16 0.08 0 0.08 0.16 Io Level of Use . _.STOP THINK~ "ACT CP2804L Rev.1 REVl5W' Continuous ' 67 0f 79
I l Attcchment 3 Liquid PASS Total Dissolved Gas Worksheet p (Page 1 of 3) l U i NOTE l When performing the fo!!owing calculation cany 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 Initial Data: A - Initial Gas Loop Pressure (psig) B - Absolute Gas Loop Pressure (psia) A E g;MM$Ni@ h5?g?j R B
+ 14.7 =
C - Initial Gas Loop Temperature ( F) D - Absolute Gas Loop Temperature ( R) C yf: Wpc 4"R;% ?M Q D
+ 460 =
Eauilibrium Data: h (V E - Final Gas Loop Pressure (psig) F - Absolute Gas Loop Pressure (psia) E ; ' " n % gp ,lg'JP
- F
+ 14.7 =
G - Final Gas Loop Temperature ( F) H - Absolute Gas Loop Temperature ( R) G *
'hi' '. , H
+ 460 =
I - Henry's Constant for Nitrogen at Equilibrium (psia / mole Fraction) [(H*0.9893)-406.46]*10000 H I X 0.9893 - 406.46 X 10000 = J - Partial Pressure of Nitrogen at Equilibrium (psia) - Ji (Numerator Term) l B
- H 'I*0.195
- 18.015 *454 B H I .Il
( . X X X 0.195,X 18.015 X 454 = F CP2804L Level of Use
. STOP" THINK ACT REVIEW Rev.1 Continuous 68 of 79
m i Attrchment 3 l Liquid PASS Total Dissolved Gas Worksheet (Page 2 of 3) ( I J - Partial Pressure of Nitrogen at Equilibrium (psia) - J2 (Denominator Term) [(I
- 0.195
- 18.015 *454) + (H
- 250
- 10.73
- 28.317)]
- D a - Left Hand Side of Denominator Term I Pf RAMf%: $ ~ Snf# M ;"9 N# R a X 0.195 X 18.015 X 454 =
b - Right Hand Side of Denominator Term H $4 QiO % @ .;fgy39 Ris @% y $ b X 250 X 10.73 X 28.317 = Completed Denominator Term a y b $ D y J2
+ X =
Completed J Term J1 l> , J2 M J
+ =
1 K - Vapor Pressure of Water at Equilibrium (psia) [(-9496.5*/H)INVfn]*21790834
@gg@# y H INVfnt MS;^M". 9], K
- 9496.5 + X 21790834 =
L - Partial Pressure of Hydrogen at Equilibrium (psia) F-J -K F J - K 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 fn key. In any case should you have any questions, contact Supervision for guidance. CP2804L Level of USe . . . . ..
.STOP' THINK 'ACT REVIEW Rev.1 Continuous W "4 69 of 79 l
Attachment 3 L Liquid PASS Total Dissolved Gas Worksheet 1 )
.p (Page 3 of 3) !
t i V \ l M - Henry's Constant for Hydrogen at Equilibrium (psla/ mole fraction) [(H*0.3081)-64]*1000 H E <!l:g4;p9 '
@a hj 3P%g;;e - e. M 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 Hand Term a - left hand side ; L 3 Wi T M @ pDQk & p@ # a X 250 + ,
+ 18.015 + 454 =
b - right hand side
$t %n? g jy W;yg(
L H $$j ggl4 s, b X 0.195 + + 10.73 + 28.317 = Completed Left Hand Term i a b . N1
+ =
N2 - Right Hand Term (10.73*492*28.317*1000)/(14.7*0.25) 7 , N2 ; 10.73 X 492 X 28.317 X 1000 + -14.7 + 0.25 = 40677543.87 l l Completed N Term N1 N2 . N X 40677543.87 = l lf
- (
CP2804L Level of Use .- .
"NK 'AT* REVIEW Rev.1 Continuous ST F; j- dr' o 3 ,
70 of 79
r Attachment 4 l Unit 2 Post Accident Sampling Reactor Coolant l Sample Dilution Data Sheet q) (Sheet 1 of 1)
- Sample Werksheet Completed by
l 'Iype: Print Name System Sampled: Isolation Date: Signature: Isolation Time: ! NOTE Circle the appropriate sample bottle dilution corresponding to the dilution (s required during performance of step. The semple mass is determine)d by multiplying the 100 pl sample mass Mai) by the applica correction for the sample dilution that is being cou(nted, i Degas Liquid Sample Sample Dilution ' Mass (em) Isotopic Original Mdl = gm O O 1st Dilution Mdt
- 1.0E-01 =
- 1.0E-01 = gm 2nd Dilution Mdl a 1.0E-04 =
- 1.0E-04 = gm 3rd Dilution Mdl = 1.0E-07 =
- 1.0E-07 = gm 4th Dilution Mal
- 1.0E-10 = = 1.0E-10 = gm 5th Dilution Mdi
- 1.0E-13 =
- 1.0E-13 = gm 6th Dilution Mai = 1.0E-16 = = 1.0E- 16 = gm 7th Dilution Mai = 1.0E-19 =
- 1.0E-19 = gm Reviewed by: Date:
Print Name Signature O CP2804L Level of Use . . . . . sTOP' THINK .ACT' REVIEW Rev.1 Continuous , 73 ,779 t
r Attachment 5 Unit 2 Post Accident Sampling Reactor Coolant Isotopic Worksheet (Sheet 1 of 1) Sample Worksheet Completed by: Location: Print Name Isolation Date: Isolation Time: Signature: Printout Activity - Background = lsotope Activity Isotope Printout Activity Background Isotope Activity (2-place accuracy) (2 place accuracy) ( Ci/gm) ( Cilgm) ( Ci/gm) o O 1 i 2 1 NOTE: Total Isotope Activity = Totalisotope Activity (2 place accuracy)( Ci/gm) summation of allisotope activities. l Reviewed by: Date: Print Name Signature O CP2804L Level of Use . ST P THINK AC7 REVIEW Rev.1 Continuous 72 of 79
Attachment 6 Unit 2 Post Accident Sampling o Reactor Coolant Gaseous Activity Worksheet C (Sheet 1 of 1) Samole Worksheet Completed by: Location: Print Name 3 Isolation Date: j Isolation Time: Sigaature: Printout Activity - Bacnground = Isotope Activity Isotope Printout Activity Background Isotope Activity (2-place accuracy) (2 place accuracy) ( Ci/gm) ( Ci/gm) ( Ci/gm) G' l NOTE: Total Gaseous Activity = Total Gaseous Activit > ( -P ace l accuracy) ( Cilgm) summation of allisotope activities. Gas Composition Analysis
% Hydrogen: % Oxygen:
Reviewed by: Date: g Print Name - Signature Level of Use --~ CP2804L
- ST P- . THINK ACT REVIEW Rev.1 Continuous - '
73 0f 79 I L
r Attachment 7 Unit 2 Post Accident Sampling p Reactor Coolant Chemical Analysis Worksheet V (Sheet 1 of 1) Sample Worksheet Completed by: Location: Print Name Isolation Date: Isolation Time: Signature: Boron Data: Boron Weinht Data: DI Water Mass: grams l 100 pl Sample Mass: grams 1 Boron Correction Factor: DI water mass + 100 pl Sample Mass l Correction Factor = 100 1 Sample Mass , gm + gm Correction Factor = = I 0 gm Boron (ppm) = Analysis results in ppm Correction Factor Boron (ppm) = ppm . = ppm Coolant chloride concentration: ppm Coolant pH (Attachment 1) Additional Analysis Concentration l l Reviewed by: Date: 1 Print Name Signature Level of Use CP2804L ST P' THINK ACT REVIEW Rev.1 Continuous + 74 of ?9
Attachment 8 Reactor Coolant PASS Sampling Equipment Inventory (Sheet 1 of 1)
%J Equipment Name Required On Hand Ordered 250 I syringe with sideport needle 2 500 I syringe with sideport needle 1 1.0 mi syringe with sideport needle 1 Syringe transport container 1 Liquid radwaste sample vial 4 Dansport container for sample vials 1 0.1 cc sample loop for gas chromatograph 1 2 mlgrab sample chamber 2*
Ransport cask for grab sample chamber 1 Transport cart 1 CaroPac PA1 Guard (10-32) column 2 Anion micromembrane suppressor 1 250 misainple loop 1
- 1 installed in PASS reactor coolant sample cabinet.
Reason for Inventory:(circle one) Quarterly After Use j Remarks: Date: Signature: 0 l l l I l i t' l ( CP2804L l Level of Use . ' STOP THINK ACT REVIEW ' Rev,1 i Continuous l 75 of 79 L :
Attcchment 9 I Unit 2 Post Accident Sampling Liquid Waste Isotopic Worksheet I (Sheet 1 of 1) O' Samph Worksheet Completed by: . Tank: Print Name Date: Time: Signature: l Printout Activity - Background = lsotope Activity Isotope Printout Activity Background Isotope Activity (2-place accuracy.) (2 place accuracy) ( Ci/gm) ( Ci/gm) ( Ci/gm) i
,3 O
NOTE: Total Isotope Activity = Totalisotope Activit (2 place accuracy) iCUgm) summation of all isotope activities. l l ! Reviewed by: Date: ! Print Name Signature i O V CP2804L Level of Use STOP THINK ~ 'ACT REVIEW Rev.1 Continuous 76 of 79 1 b .. _
y i L Attachment 10 l Syringe Check
., (Sheet 1 of1)
V i
- 1. ENSURE syringe is open (needle screwed against syringe body).
- 2. DRAW air into syringe.
1
- 3. PLACE needle in a beaker of water.
~ 4. PRESS plunger and ENSURE air exits syringe.
- 5. REMOVE needic from beaker.
- 6. DRAW air into syringe.
l 7. UNSCREW nosecap 2 turns.
- 8. PLACE needle in beaker of water.
- 9. , PRESS plunger and ENSURE no air exits syringe.
- 10. REMOVE needle from water and SCREW syringe nosecap against syringe body.
1 O l Qi 11. PRESS plunger. I i l l l l i 1 ! I l= i l l CP2804L
~
Level of Use l - .. Slop ' THINK ' "ACT1 REVIEW Rev.1 Continuous <1 , - 77 of 79 L -
e Attachm:nt 11 l pH Probe Installation (Sheet 1 of 1
- 1. OPEN module door.
- 2. REMOVE protective cover from pH probe sensor.
- 3. REMOVE FME cover from pH probe (AE 1068) sample chamber.
- 4. INSTALL pH probe (AE 1068) and 0-ring into sample chamber.
- 5. CLOSE module door.
!O iV l . I f l l l l l l i O CP2804L t Level of Use Cr.. ,uous STOP THINK
~
ACT' REVIEW Rev.1 78 @
1 l 1 Attachment 12 Isolation Valve Independent Verification Sheet A (Sheet 1 of 1) V Valve Required Position Independently Verified Independently Verified By: Sign Name l By: Sign Name 1 2-RC-001 CLOSED 2-RC-002 CLOSED 2-RC-003 OPEN 2-RC-045 OPEN 2-LRR-61.1 CLOSED (~)) 1 1 l be gj Level of Use . . . CP2804L )
.ST P" THINK ACT REVIEW Rev.1 Continuous 79 of 79 i
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