ML20092C661
| ML20092C661 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/05/1984 |
| From: | LONDON NUCLEAR |
| To: | |
| Shared Package | |
| ML20092C619 | List: |
| References | |
| NUDOCS 8406210285 | |
| Download: ML20092C661 (145) | |
Text
{{#Wiki_filter:- ATTACllMENT ^ Sections Ravision: Effsetivo Pcgs: D ts: London OP-001 -E- 5/31/84 1 of 1 Nyclear pu. PROJECT OPEi.\ TING PROCEDURE: PEACil BOTTOM DECONTAMINATION 406 a86 PEACH BOTTOM ' RECIRCULATION LINE CAN-DECON OPERATING PROCEDURES STATION SPECIAL PROCEDURE No. 694 , s s i i o ( - 8406210285 840615 PDR ADOCK 05000277 PDR P .
HCfoss title p(ossoas isF(Cityt 00f t Pact OP-001 TABLE OF - E- 5/31/84 1 of 5 CONTENTS ( PEACH BOTTOM RECIRCULATION LINES CAN-DECON OPERATING PROCEDURES SECTION PAGE 1.0 Purpose 1-1 2.0 References 1-2 3.0 Prerequisites 1-3 4.0 Precautions 1-1 5.0 Equipment and/or Tools 1-2 6.0 Operation 1 - 97 6.1 Applicability 1 6.2 Definitions 2 6.3 Receipt and Uncrating of Equipment 3 6.4 Mechanical Installation
- 4 6.5 Temporary Shielding 12 6.6 Electrical Connections 13 6.7 Preparation with Start-Up . 14 f 6.8 6.9 Pre-operational Testing Preparation of Decontamination System 18 24 6.10 Pre-operational Testing Suction Side 28 6.11 Pre-operational Testing Discharge side 30 6.12 Discharge Side Decontamination 32 6.13 Suction side Decontamination 37 6.14 Resin Slurry 42 6.15 Draining 44 6.16 Decontamination System Dismantling 45 6.17 Crating & Shipping 46 6, 18 Chemical E. Radiochemical Monitoring 74 6.19 Required Chemicals 74 s,pJ.
, 6.20 Analysis 75 6.21 Laboratory Familiarization 78 6.22 Analytical Equipment Familiarization 79 6.23 Preparation of Analytical Solutions 80 6.24 Sampling Method & Schedule 82 6.25 Analytical Procedures 82 p 6.26 Decontamination Termination Decision 91 6.27 Safety, Dose Control & Radiation Monitoring 92 r' S 6.28 d.tadiation Field Monitoring 93 6.29 Personnel Dose & Contamination Control 97
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54CTKne Tsitt af wiseoN (87tCiewt Datt pact OP-001 TABLE OF - E- 5/31/84 2 of 5 ( CONTENTS TABLE OF CONTENTS (CONTINUED) SECTION PAGE APPENDIX A - ABNORMAL OPERATIONS: 97-A 1.0 Loss .sf Temperature control 2.0 Loss of Circulating Pump
, 3.0 Loss of System Fluid 4.0 Loss of Electrical Power 5.0 Slurry Nose Failure APPENDIX B - Pipe Isolation , 97-B APPENDIX C - Special Rose Coupling Assembly Instructions 97-C APPENDIX D - As Built Flange Joint Arrangement 97-D
( Data Sheet LONDON NUCLEAR
6f Cf C4 fif LL st velson (88 tCf'vt Oatt pact OP-001 TABLE OF -E- 5/31/84 3 of 5 ( CONTENTS TABLES Table No. PAGE 6.1 valve Status: Decontamination Equipment, Static Reference State 47 6.2 Miscellaneous Decontamination Equipment Status, Static Reference State 52 6.3 Valve Status: Skid LN-4 Electric Neater, Static Reference State 53 6.4 Valve Status: Temporary Valves, Static -Reference State 54 6.4.2 RHR Return Loop 'A' Joint Arrangement ( Data Sheet $6 6.4.3 RNR Return Loop 'B' Joint Arrangement Data sheet 57 6.4.4 RHR - Suction Joint Arrangement Data Sheet 58 6.4.5 Nostle N6A Joint Arrangement i Data Sheet 59 6.4.6 Nossle N6B Joint Arrangement Data Sheet 60 6.4.7 RWCU Joint Arrangement Data Sheet 61 6.4.8 N2A-N2B Manifold and Jumper Joint Arrangement Data Sheet 62 g ,36.4.9 NlA-N1B Joint Arrangement - Data Sheet 64 LONDON NUCLEAR
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OP-001 TABLE OF -E- 5/31/84 4 of 5 k COttfENTS TABLES (Continued) l Table No* PAGE l
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6.5 Statien Installed valves, Suction Side Decontamination Status 65 6.6 station Installed valves, Discharge Side Decontamination Status 66 j 6.7 Reagent Addition Check Sheet 67 6.8 Sampling Check Sheet 68 6.9 Ra,diation Monitoring Check Sheet - 69 6.10 Operations Log Sheet 70 6.11 Chemistry Monitoring Schedule 72 6.12 Resin slurry Log 71 6.13 Final Radiation survey 73 i i s .' ' ( 4 LONDON NUCLEAR
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- 5 of 5
( CGNTENTS - I FIGURES FIGURE PAGE 3.1 Decontamination Cut Identification 1-A 6.2' Recirculation, RWCU and RHR Survey Points 97-E ! o* 6.3 Field Run Hose and Flange Joint Arrangement 97-F 6.4.1-6.4.9 - Flange Joint Arrangement 97-G
*l DRAWINGS b NUMBER TITLE PAGE 3603-A-5009-1 Flow Diagram Meater System 97-1l 3603-C-5000-1 Decontamination Equipment Flow Diagrau 97-3 3838-B-5001-1 Discharge side Decontamination 97-J 3838-B-5001-2 Discharge Side Decontamination 97-K 3838-3-5001-3 suction side Decontamination 97-L 3838-B-5001-4 Suction Side Decontamination 97-M 3838-L-2000-1 General Equipment Location 97-N s .S -
l il LON0cN NUCLEAR
3:cticna R:visi:ns Eft:ctiva , P gs: London - OP-001 -
-E- 5/31/84 1 of 1 Nuc. lear m i.,
(- PROJECT OPERATING PROCEDURES 1.0 Purpose D-24
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1.0 PURPOSE The purpose of this document is to provide a set of operat-ing procedures and guidelines f or the operation of the Decontamination System a's applied to the Peach Bottom Unit 2 Recirculation Piping System including segments of the RHR and RNCU systems. It is the intent of this procedure to outline the various steps required to decontaminate these systems. CHANGES THAT DO 'NOT CHANGE,THE INTENT OF THIS PROCEDURE MAY - BE MADE PROVIDED THAT THE CHANGES ARE DOCUMENTED ON THIS PROCEDURE AND INITIALED BY A MEMBER OF SHIFT SUPERVISION AND ONE MEMBER OF THE PORC TO SIGNIFY APPROVAL. THE PORC MEMBER APPROVAL MAY BE GRANTED BY TELEPHONE. ANY CHANGE TO THIS PROCEDURE WHICH CH ANGES ITS INTENT MUST BE REVIENED AND APPROVED BY THE PORC PRIOR TO IMPLEMENTATION. A e f
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OndOn oP-001 . -c- 5/31/s4 1 of 2 Nucleor mi., . PROJECT OPERATING PROCEDURES 2.0 References D-24
2.0 REFERENCES
M-351-19 P&ID Nuclear Boiler, Unit 2 M-361-SH1 P&ID Residual Heat' Removal System Unit 2 M-15 Equipment Location Reactor and Radwaste Building Unit 2 Plan at Elevation 135'-0" M-354-17 P&ID Reactor Water Cleanup system M-20 Equipment Location Reactor and Radwaste Building Unit 2 ( SK11084 CE, Piping Isometric of
, Recirculation sys, tem ll2D3501 GE, Manifold , ,
137C8201 GE, Pipe Cap Assembly 137C8200 GE, Plate 137CS202 GE, Decontamination Pittings 3603-C-5dOO-1 LN-1, Decontamination Equipment Plow Diagram 3603-A-5009-1 LN-4/5 Flow Diagrams
- Heater System System Diagram 3603-5-5001-1 LN-1, Decontamination. Equipment '
Equipment Installation d - Interconnections (
te t tese lette M vst@se 18'Itt'vt De f t . 64,4 + 2.0 References -E- 5/31/84 2 of 2 l 3603-A-5005-1 LN-4, Decontamination Equipment Equipment Installation Interconnections 3838-3-5000-1 Flow Diagrams Decontamination of Reactor Recirculation Pumps Suction and Discharge 3838-L-2000-1 General Equipment Location 3838-3-5001-1 Flow Diagrams: Decontamination 3438-8-5001-2 of Reactor Recirculation Fumps 3838-8-5001-3 suction and Discharge 3438-8-5001-4 112-E-3502 Decon Cuts within Drywell 796-E-401 Routing of Decon Mose Figures 4.4.1 - 6.4.9 Flange Jolat Arrangements b Figure 6.2 Field Run Mose and Flange Configuration.
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s:cticn Revisiens ggftiv3 Pe938 l OP.001 -E- 5/31/84 1 of 3 ' ( Nuclear nu.. : PROJECT OPERATING 3.0 Prerequisites PROCEDURES D-24 3.0 PREREQUISITES
- 1) The preparation of plant interface locations !
(valved out/ tagged, drained / vented, blanked / adapted, unplugged etc.) with appro-priate blocking permits (as required by LN drawing 3838-8-5001-1). SSV
- 2) suf ficient concrete shield blocks available
- to construct temporary shielding as per LN Drawing 3603-5-5001-1. (Drawing specifies a l
concrete shielding thickness of 2 ft.) {.- PEco const.
- 3) Appropriate piping isolated by C8&I. ,
(see Appendix 5). l GE
- 4) 20,000 Gallons condensate transf er available to fill system.
asy
- 5) Orains available to accept slystem volume at end of decontamination. Total system volume will be drained to the torus or radweste.
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- L M CT ON TITLE PE vtSCN (FFECrivE Dait PaGE 3.0 Prerequisites -E- 5/31/84 % of 3
- 6) Preoperational testing and inspection of LN equipment before shipping to Peach Bottom LNEC
- 7) Radiation work permits available l GE
- 8) EP coverage needed for all decon operations.
- 9) All chemicals listed in Section 6.19 are available t
LN
- 10) All chemical analysis equipment outlined in i Section 6.20 are available .
LN ! ( 11) Check meter batteries and calibration I l LN t
- 12) Remove insulation around recirculation line isolation valves (M0-43A, 43B, 53A, 53B)
GE i
- 13) Preparations made to adequately support all
[ temporary lines and hose, and protect all - hose outside drywell from traffic. See Section 6.4, Figures 6.4.1 through ( 6.4.9 ( , l U GE/LN l . l
- l LONDON NUCLEAR .
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SE Cics 1:1LE mE v@ON EFFECtavt Datt Pace ( 3.0 Prerequisites -E- 5/31/84 3 of 3
- 14) Verify installation of plastic over drywell openings to torus.
UE/LN
- 15) Verify that no more than 50% of the insulation on piping and equipment has been .
removed. ! t GE/LN
- 16) Recirculation auction and recirculation discharge valves are to be closed but not back seated.
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p Unit 2 Operator E 1 . (. P O LONDON NUCLEAF,
l Section: Revision: Effective- Page: Date: London OP-ool -E- s/31/84 1 or 1 : ( Nuclear nue: PROJECT OPERATING 4.0 Precautions D-24 l PROCEDURES > li 4.0 PRECAUTIONS ' i
- 1) During equipment installation, all'possible hard-ware connections are to be installed prior to dry-well entry.
- 2) During performance of all phases of l decontamination project work, the control room extension 4223o 'r 4423 shall be notified of any significant leakage from plant systems or i decontamination equipment. '
- 3) 't:o <M \c4cku:A re.t.Xt., eA V(5 I
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, Section: Revision: fe tive Page:
1._Ondon OP-001 -E- 5/31/84 1 of 2 , Nuclear m 1.: PROJECT OPERATING ~ PROCEDURES 5.0 Equipment and/or Tools [ D-24 ! 5.0 EQUIPMENT AND/OR TOOLS 5.1 LN decontamination equipment consisting of:
- 1) one ion exchange skid
- 2) one auxiliary equipment skid (pump skid)
- 3) two supplementary heating skids !
5.2 Supplementary equipment and miscellaneous supplies quantities:
- 1) 40 cu. ft. of IRN-77 and 40 cu. ft. of IRN-78 !
- 2) 4 stainless steel corrosion coupons i
- 3) 70 kg of LND-101A
- 4) 10 gallons of 35% solution of hydrazine in water.
- 5) 5 gallons Rodine 31A '
- 6) miscellaneous installation tools and equipment
- 7) two fabricated spool pieces for Recirculation system decontamination connections
- 8) 10 - 2" ball valves, 16 - 3" ball valves i
- 9) 2" hose and fittings, total length of 350 ft
- 10) 3" hose and fittings, total length 900 ft '
- 11) 1-1/2" hose and fittings, total length of 200 ft,
- 12) 1" hose and fittings, total length of 150 ft !
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-E- 5/31/84 2 of 2 Tools .
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- 13) 2- 3" 1500 crosses t
- 14) spray shields and collection pans for each flanged joint in the flow path. Catch pans to be set l
beneath the 43 and 53 isolation valves. (CB & I supplied. t
- 15) hydrostatic test pump i I
- 16) ra An overhead crane (or forklift truck) with a 6 ton t '. ng . If a forklift truck is used, the required ,
fo' length is 8-1/2'. t
- 17) Eberline E-530N equipped with a HP220A tungsten shielded detector (supplied and calibrated by LN) 18 ) One Gamma meter having a range of 0 to 1000 R/hr (supplied by Station.) '
t
- 19) Two Gamma meters having a range of 0 to 2 R/hr (sup-(- plied by Station).
- 20) Station approved plastic sheeting to cover torus ,
vents. (PECo supplied). t 1 e 5 9 LONDON NUCLEAR
i Section: Revision: Effective Page: - Date: London OP-001 -E- 5/31/84 t 1 of 97 Nuclear ( m 1.: ! PROJECT OPERATING , PROCEDURES 6.0 Procedures n-?d r i 6.0 PROCEDURES 6.1 Applicability ! The decontamination effort, for Peach Bottom Unit 42 ! Recirculation System, is a one time application prior to re-placing the piping in this system and segments of piping in associated systems. ~ The decontamination system i s based on the "all cut l scenerio" which eliminates any process fluid from entering the vessel. Prior to cutting the various segments of pipe, it out is assumed all preliminary preparations have been carried ! as outlined in the Peach Bottom Unit 2 Recirculation
- Piping Decontamination Activity Schedule, latest revision.
The procedure, therefore, is based on receiving the recirc-ulation system in a drained depressurized state with all the { appropriate adapters on the cut pipe ends. , The procedure outlines the. tasks required to setup the decon- ; tamination flow path, to ope' rate and monitor the decontamina- i tion equipment and process and to dismantle the temporary .j connections and components used during this effort. i
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i ucio ma nvso enecnet oave cc I ( 6.0 Procedures - E- 5/31/84 2 of 97 l 6.2 DEFINITIONS , The following terminology is frequently used in the text of ! the procedure: Decontamination Connection !
" Decontamination connection" is a spool piece fabricated to (
mate with LN.3"-1500 flanged hose fitting and the 4"-9006 ex- ! tended flanges located at the suction of both A and B recirc- I ulation pumps. These connections are used as tie-in locations for the decontamination equipment. ; Suction Side Decontamination I r
" Suction side decontamination" is the portion of the recirc-ulation piping system which consists of the piping from the ,
closed recirculation pump discharge valve, through the pump [ and pump suction isolation valve through the recirculation i piping up to the safe ends through the 3" hose. connected to : the safe end on the suction line of the other loop. Two seg- ! f ments of additional piping, (RHR supply and RWCU suction),- are included in this flow path as well (refer to Drawing 3838-5001-3 and 3838-B-5001-4). Discharge Side Decontamination L
" Discharge side decontamination" is the portion of the re- l circulation piping system which consists of the piping from l the closed recirculation pump suction valves, through the :
pump and pump discharge piping, header and the risers ; through the temporary decon manifold header to the risers, header and discharge piping of the other loop. Two segments ! of additional piping, (RHR return loop A and RHR return loop : B), are included in this flow path as well (refer to Drawing ! 3838-B-5001-1 and 3838-B-5001-2).
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Decontamination System ' This terminology refers to all piping, valves, components ! etc. that will be in contact with the CAN-DECON reagent, therefore the decontamination system consists of the recirc- l ulation discharge and suction, RHR return, RHR supply and , RRCU lines and the decontamination equipment as well. ; 6.3 Receipt and Uncratinq of LN Equipment i i a) Inspect exterior of all shipping crates for possible dam-age. Verify arrival of all containers. . LNEC , b) Inspect all paperwork pertaining to shipment including: ,
- 1) health physics surveys k.
- 2) invoice - if any damage is apparent at this time or if crates were not tarped during shipment, ensure it }
is noted on invoice before acceptance. Have driver D, l sign and, if possible, photograph apparent damage. Notify LN offices immediately. i LNEC c) Lif t equipment from truck with overhead crane or fork- ' [ lift truck. LNEC' ! l l d) If necessary, temporarily store equipment, accompanying hoses and fittings indoors, if possible, leaving a min-g.. imum of 2'-0" on all sides for uncrating. i i
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6.0 Procedures -E- 5/31/84 4 of 97 e) HP coverage required. Uncrate skids by removing all lag bolts from top section. Lift top off and out of way. (Check sides of top marked for proper alignment during re-assembly.) LNEC HP f) Depending on equipment availability and overhead clear-ance, skids can either be lifted out of crate through
* , top (must use lifting lugs, located on top of pump skid and on bottom of IX skid), or can remove sides by removing lag bolts on corners and bottom (mark all joints before removing to insure proper realignment dur-ing re-assembly).
LNEC g) Lift skids off bottom of crates. Lower wheels on skids f by tightening nuts on wheel channels located on corners of skids and roll into place as per 3838-L-2000-1. LNEC h) Receipt inspection. LNEC/GEQA 6.4 Mechanical Installation and Interconnections THIS SECTION DEFINES THE FIELD RUN PIPE, HOSE SUPPORT AND JOINT CONNECTION ARRANGEMENT FOR THE TEMPORARY DECONTAMINATION FLOW PATE. SEE THE FOLLOWING REFERENCES AND INSTRUCTIONS REQUIRED TO COMPLETE STEPS 6.4 a) THROUGH 6.4 v). CONTINUOUS HP COVERAGE IS REQUIRED.
- 1) Drawings 3603-B-5001-1 and 3603-A-5005-1 .
LONDON NUCLEAR I
I ucr.o virta at m.o enecieve cave e ce 6.0 Procedures - E-(, 5/31/84 5 of 97 (
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- 2) Figure 6.3 Routing of Decon Hose. \
- 3) Figure 6.4.1, Flange Joint General Arrangement.
3
- 4) Figure 6.4.2, RER Return - Loop 'A' Joint !
Arrangement !'
- 5) Figure 6.4.3, RER Return - Loop 'B' Joint -
Arrangement ; I
- 6) b Figure 6.4.4, RER Suction Joint Arrangement.
- 7) Figure 6.4.5, Nozzle N6A Joint Arrangement !
- 8) Figure 6.4.6, Nozzle N6B Joint Arrangement l 9)
Figure 6.4.7, RWCU Joint Arrangement
- 10) Figure 6.4.8, N2A - N2B Manifold and Jumper Joint Arrangement. !
i
- 11) Figure 6.4.9, NlA, N1B Joint Arrangement.
- 12) Figure 6.4.10, Flange Joint Bolt-Up Data Sheet. .
ALL HOSE IS FIELD RUN, HOSE CLAMP / RESTRAINTS SHALL BE ! UTILIEED TO BEAR THE UNSUPPORTED LOAD OF WATER FILLED HOSE, l THE CLAMPS / RESTRAINTS SHALL BE SECURED TO AVAILABLE l RAILINGS, GRATES,. STEEL BEAMS OR NON-VITAL PIPE. i t HOSE PROTECTORS SHALL BE INSTALLED AT LOCATIONS WHERE CONTINUOUS NECESSARY. PERSONNEL ACCESS OVER INSTALLED HOSE IS LIMITED ACCESS LOCATIONS WILL NOT BE COVERED WITE HOSE PROTECTORS. HOSE WILL BE RUN HORIZONTIALLY WHERE POSSIBLE, TO PERMIT LAYING FLANGED JOINTS ON THE DECK. LEAK ; COLLECTION- PANS WILL BE INSTALLED UNDER FLANGED JOINTS WHERE I POSSIBLE. SPLASH SHIELDS WILL BE PLACED OVER EACH FLANGED HOSE CONNECTION JOINT. LEAK COLLECTION PANS WILL BE PLACED UNDER THE 43A/B AND 53A/B MO VALVES. , r .' *
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I SECT C*e TITLE RE vtSCs4 EFFECTevt DATE PAGE ( 6.0 Procedures - E- 5/31/84 6 of 97 HOSE CRADLES WILL BE INSTALLED AT LOCATIONS WHERE HOSE MUST RUN OVER SHARP EDGES. i A FLANGE JOINT BOLT-UP DATA SHEET WILL BE COMPLETED FOR ALL FLANGE CONNECTIONS AND NOTED ON THE FLANGE JOINT ARRANGEMENT ! DATA SHEET, TABLES 6.4.2 - 6.4.9. DATA SHEETS SHALL BE ! ATTACHED TO THIS PROCEDURE AS APPENDIX D. SHOULD IT BECOME NECESSARY TO FIELD ASSEMBLE A HOSE TO f NIPPLE CONNECTION. SEE APPENDIX C, SPECIAL ASSEMBLY ! INSTRUCTIONS. a) CB&I - interconnect pump skid, ion exchange skid and l heating skid using 2" and 3" hoses, and install isola-tion valves at the ends of the hose between heater skid and pump skid. t LNEC/GEQA b) CB&I - Bolt one 3" cross-tee fitting together and connect to decontamination equipment suction. LNEC/GEQA l c) CB&I - connect 3" suction hose to decontamination equipment and run to decontamination connection at ! recirculation pump "B" suction. 1
. CB&I -
install 3" isolating valve at each end of i hose prior to connection LNEC/GEQA CB&I - make final connection between hose and decon-tamination connection GE-QA/LNEC !
's.
' LN - SUPPLY 3"-1500 RF X 4"-900# T/G REDUCER.
( . LONDON NUCLEAR l
SECteOes fifLE f(wissoes (Ff fCfiYt Daf t PAGE 6.0 Procedures - E- 5/31/84 7 of 97 i I 1 d) CB&I - connect 3" hose to decontamination equipment ! suction and run to RHR return Loop 'B' connection. i (Tie-in point upstream of valve A0-10-46B). ; LNEC/GEQA
. CB&I -
install 3" isolating valve at each end of i hose prior to connection i i ' LNEC/GEQA j CB&I loop "B"
- make final connection between hose and RHR connection
. GEQA/LNEC ,
CONNECTION PREPARED WITH 3", 150f FLANGE e) CB&I - connect 3" hose to decontamination equipment suc-p - tion and run to RHR return loop "A" connection. (Tie-in 1 g, point is upstream of valve AO-10-46A.) i LNEC/GEQA s
. CB&I -
install 3" isolating valve at each end of ! hose prior to connection j LNEC/GEQA l CB&I - make final connection between hose and RHR l loop "A" connection GEQA/LNEC j CONNECTION PREPARED WITH 3", 1500 FLANGE f f) CB&I - connect 3" discharge hose to decontamination ; t equipment at auxiliary electric heater skid inlet. ! LNEC/GEQA { g) CB&I - bolt one 3" - cross-te'e fitting to auxiliary electric heater outlet. . ( LNEC/GEQA f LONDON N'JCLEAR
e SECicN IllL E p(VI$@N (FF(CIlvt Oaf f pact
-(- 6.0 Procedures -E- 5/31/84 8 of 97 h) CB&I - connect 3" hose at auxiliary electric heater out-let and run to decontamination connection at recirc-ulation pump "A" suction.
LNEC/GE0A
- 1) CB&I - install 3" isolating valve at each end of hose prior to connection LNEC/GEQA
- 2) CB&I - make final connection between 3" hose and de-contamination connection GEQA/LNEC LN TO SUPPLY 3"-1500 RF X 4"-900# T/G REDUCER.
( i) CB&I - connect 3" hose to decontamination equipment dis-charge and run to RHR supply connection. (Tie-in point is downstream of valve MO-18.) LNEC/GEQA
. CB&I -
install 3" isolating valve at each end of hose prior to connection LNEC/GEQA CB&I - make final connection between hose and RHR supply connection GEQA/LNEC CONNECTION PREPARED WITH 3",150 # FLANGE j) CB&I - connect 3" hose to decontamination equipment dis-g, charge and run to RWCU connection. LNEC/GEQA
. CB&I -
install 3" isolating valve at each end of hose prior to connection. l ( LNEC/GEQA LoN00N NUCLEAR ,
S(CiaCpe TaTLE REtns:DN EFFECTst#E D3VE CAGE ( 6.0 Procedures -E- 5/31/84 9 of 9'? CB&I - make final connection between hose and RWCU connection GEQA/LNEC CONNECTION PREPARED WITH 3 " , 150 0 FLANGE k) SP - supply and locate lead shield blankets on inter-connecting hoses, so as to minimize radiation exposure in the immediate vicinity of the pump and ion exchange skids. STATION MAINTENANCE & HP
- 1) CBEI - run and connect 3" hose f rom recirculation suc-tion loop"A" connection to recirculation suction loop"B" connection. (See Drawing 3838-B-5000-1.)
GEQA/LNEC CONNECTIONS PREPARED WITH 3", 150# FLANGES
. CB&I - install 3" isolating valve at each end of hose prior to connection LNEC/GEQA l
m) CB&I - run 2" hose f rom all 5 riser connections on loop "B" and connect to manifold. GE-QA/LNEC
. CB&I - install 2" isolating valve on riser end of hose prior to connection GE-QA/LNEC s y.. . CB&I - install manifold as per Drawing ll2D3501
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SECTIO's fiftf AEvlsoe (FFECTWC OATE F&CE ( 6.0 Procedures -E- 5/31/84 10 of 97 n) CB&I - run 2" hose from all 5 riser connections on loop "A" and connect to manifold. GE-QA/LNEC
. CB&I - to install 2" isolating valve on riser end of hose prior to connection LNEC/GEQA
. CB&I - install manifold as per Drawing ll2D3501. ,
GE-QA/LNEC o) CB&I - run 3" hose from loop "A" manifold connection to loop "B" 3" connection, and connect. - GE-QA/LNEC
. CB&I - install 2" isolating valves at each end of ! hose prior to connection LNEC/GEQA p) CB&I - connect 1-1/2" hose to decontamination equipment and run to, Station service water supply.
LNEC/GEQA
. CB&I. - make final connection between-- service-water supply connection and hose GE-QA/LNEC
. CBEI - install tell-tale drain line between service water supply and decontamination equipment, complete with isolation valve.
q) CB&I - connect 1-1/2" hose and run to Station Rad waste g ,. (local floor drain). LNEC/GEQA , E i LONDON NUCLEAA I i w,--- m--,- ,- --- r y y y. -- - ,- , ,.,..m.,-v---,,-_,,--- . , , , - - , --
- - - , , , , , , - - , . , , , - - - - - - - - , , - - - . - - , - , .,w --,
SECisON fiftt AE viaiON EFFECityt DATE paGE 6.0 Procedures 5/31/84
-E- 11 of 97 CB&I - make final connection between cooling water return connection and hose GE-QA/LNEC r) CB&I - connect 1" hose from decontamination pump skid and run to Station floor drain.
GE-QA/LNEC CB&I - verify drain is unplugged SP s) CB&I - connect 1" hose from electric heater skid and run to Station floor drain. l l LNEC/GEQA CB&I - verify drain is unplugged GE-QA/LNEC t) CB&I - connect 1" hose from ion exchange skid and run to Station floor drain. LNEC/GEQA CB&I - verify drain is unplugged GE-QA/LNEC u) CB&I - connect 1-1/2" hose to line CDl-1/2" located on ion exchange skid and run to Station condensate transfer t ! supply. l A d cSrM C CB&I - install tell-tale drain line between F ul m ! g,fy wM,er supply and decontamination equipment complete l l with isolation valve I d' ' 1" CONDENSATE SUPPLY LINE LOCATED ON PUMP SKID (LN-1) WILL NOT BE USED. l
- j LNEC/GEQA 1
l LONDON NUCLEAR
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e SECisON TITLE pteissON (FFECIltE DATE Ccct * ( 6.0 Procedures -E- 5/31/84 12 of 97 CB&I - make final connection between hose and conden-sate transfer supply or demin water GE-QA/LNEC v) CB&I - connect 1-1/2" slurry hose and run to liner. LNEC/GEQA l CB&I - make final connection between hose and liner. GE-QA/LNEC
. CBEI - supply 1-1/2" - 150 f RF x 4"-150 0 RF reducer w) CB&I - connect Nitrogen cylinder c/w regulator (adjust-able within the range 10-100 psig) to decontamination equipment.
LNEC/GEQA x) LN install corrosion coupons.' LNEC/GEQA y) LN load ion exchange resins as per Section 6.7.2. This is initial loading. 6.5 Temporary Shielding a) CBEI - construct temporary shielding (dense concrete blocks) around the ion exchange skid as detailed on LN Drawing 3603-B-5001-1. MAINTENANCE /GEQA s .' - : 4 ( LONDON NUCLEAR r I I
SECT C* Tiitt p(UtsCN (FFECimEDATE pcG(
- 6.0 Procedtres -E- 5/31/84/ 13 of 97 :
b) CB&I - lay lead blankets on temporary hose lines, locat-ed near pump skid. t MAINTENANCE /GEQA SHIELD WALL MAY BE CONSTRUCTED DURING EQUIPMENT SETUP. i
~ verify concrete shielding blocks are installed as designated and that no cracks are present. '
LNEC/HP 6.6 E?ectrical Connections a) PECo El Construction - install a 480 Volt, 300 Amp, 3 phase power to LN pump skid (see LN Drawing 3603-B-5001-1). PECo El Const./GEQA i ( b) PECo El Construction - supply 480 Volt, 400 Amp, 3 phase power to electric heater skid (see LN Drawing 3603-A-5005-1). ! r PECo El Constr./GEQA I
SUMMARY
- 6.3 - 6.6 I
Final Verification of Completion of Equipment f Installation. [ LNEC/GEQA O. . i i 5 LONDON RUCLEAR I
MCYoe ISTLE m(vtse0N (FFECTevt DATE FLGE
- 6.0 Procedures -E- 5/31/84 14 of 97 I
k l 6.7 Preparation for Startup 6.7.1 Decontamination System Verification a) Verify that Decontamination equipment is isolated from Recirculation Piping System by closing the fol-lowing valves (if open): CUl-V1 Hose Isolation - Process End CU3-V4 Hose Isolation - Process End V1 RHR Return "A" Isolation - Skid End V2 RHR Return "B" Isolation - Skid End V5 RHR Supply Isolation - Skid End V6 RWCU Isolation - Skid End LNEC/GEQA b) verify that decontamination equipment is connected to Station services and process systems as described in Sections 6.4 to 6.6 of this procedure. f LNEC/GEQA c) verify that following Station services are available:
- 1) condensate transfer available to line CD-301
- 2) service water available to line CW-301
- 3) power available to the auxiliary equipment and sup-plementary heater skids LNEC/GEQA s
e LONDON NUCLEAR
SECTION TITLE mt v@C*e EFF1CTivt DATE PAGE 6.0 Procedures -E- 5/31/84 15 of 97 d) Verify that corrosion coupons are installed in CU-103. LNEC/GEQA e) Verify that the status of the decontamination valves and equipment is as per Tables 6.1, 6.2 and 6.3 (see LN Drawing 3603-C-5000-1) with the exceptions given in 6.7.1(a). If not, correct positions LNEC/GEQA 6.7.2 Addition of Ion Exchange Resin Add ion exchange resin to each ion exchange column as follows. Equipment designations are for column CU-201. Equivalent designations for columns CU-202 and CU-203 are shown in brackets respectively. a) Open CVl-V1 (CVl-V2/V3 ) to relieve any pressure in the l(f j vessel. b) Close CU4-V1 (CU4-v2/V3) and CUS-V1 (CUS-V2/V3) c) Remove access flange. d) Fill CU-201 approximately one third full of condensate or demin by opening CDl-V4 and adjusting CDl-V1 (CDl-V2/V3). e) Fill CU-201 (CU-202/203) with resin as indicated below: 3 6.5 ft IRg-77 (strong acid cation) and 0.5 ft IRN-78 (strong base anion) on top of the IRN-77 MAINTAI4i NATER LEVEL AT OR ABOVE THAT OF THE RESIN DURING ADDITION.
- g.
- THIS SECTION IS USED FOR ALL RESIN LOADING INCLUDING THE INITIAL FILL DESCRIBED IN. SECTION 6.4 (Y) .
( LONDON NUCLEAR
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SECT Os TITLE sigytsos EFFECTsYE Daf t pcGE , 6.0 Procedures - E- 5/31/84 16 of 97 k f) Once addition of resin is complete, raise water level to top of flange, reinstall access flange and fill column with water by opening CDl-V1 (CDl-V2/V3). g) When water appears at vent pot CV-206, close CDl-V1 (CDl-V2/V3 ) , CVl-V1 (CVl-V2/V3) and CDl-V4. h) Lock RSl-V6 shut to avoid any inadvertent manipulation during the decontamination. LNEC/GEQA Ion exchange resin loaded. 6.7.3 Initial Filling and Venting (BP Bold Point) a) The decontamination equipment is initially filled while the equipment remains isolated from the recirc-ulation system. Prior to filling all the components on decontamination equipment are placed on line by opening or verifying open the following valves: CU2-V6 Main Cooler Inlet CU6-V1 Reverse Flow Isolation CU7-V1 Reverse Flow Isolation CD2-V2 Surge Tank Isolation CSI-V1 Before Sample Isolation CSI-V2 Before Sample Isolation CS3-V1 After IX Sample Isolation CS3-V2 After IX Sample Isolation CI2-V1 Chemical Injection Inlet Isolation CI3-V1 Chemical Injection Outlet Isolation CU'.-v9 Purification Flow Control CUS-V8 Purification Flow Control CU4-V3 IX CU-203 Inlet . CUS-V3 IX CU-203 Outlet CU4-V2 IX CU-202 Inlet CUS-V2 IX CU-202 Outlet CU4-V1 IX CU-201 Inlet CUS-V1 IX CU-201 Outlet r .% LNEC/GEQA ( LoNOON NUCLsAR,
SECf*04 tifLE ag wesson (FFEClivE Daft pacq ! 6.0 Procedures 5/31/84 , -E- 17 of 97 ( b) Open, or verify open, CDl-V4 and CDl-V6 while surge tank sight glass indication is monitored. Once the ' water level rises to the low water level mark on the tank, throttle back on CDl-V4. l At this point, all components on LN equipment are vent- I ed individually as follows: l c) Open CV5-V1 to vent chemical injection vessel CI-101, , when flow is ve.cified to SG-101, close CVS-V1. ' d) Open CV4-V1 to vent main cooler CU-104 outlet line, , once flow is veri *iied to SG-101, close CV4-V1. ' e) Open CV3-V1 to vent heater CU-105, once flow is verified to SG-101, close CV3-V1. f) Open CS4-V1 to vent sample lines, once flow to sample sink is verified, close CS4-V1. (
- g) Open CVl-V1, to vent ion exchange column CU-201, when <
flow is verified through SG-202, close CVl-V1. h) Open CVl-V2 to vent ion exchange column CU-202, when ' flow is verified through SG-202, close CVl-V2.
- 1) Open CVl-V3 to vent ion exchange column CU-203, when flow is verified through SG-202, close CVl-V3.
i i
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t i LONDON NUCLEAR 1
5(CTeow Taftt set v4 SON 888(Cisvt Daft PAGE 6.0 Procedures -E- 5/31/84 18 of 97 ( j) Open CV10-V1 to vent electric heater skid (Skid 4) pro-cess line, when flow is verified through SG-401, close CV10-V1. k) Close CDl-V4'and CDl-V6. Isolate condensate supply (station side).
- 1) supply cooling water to main cooler (CU-104 ) and sam-ple cooler (CS-101) by opening CW2-V1 and CW3-V1. -
When condensate appears on sample cooler coil, then . cooling water flow is verified. Close valves CW2-V1 . and CW3-V1. Isolate cooling water supply (station ! side) and open tell-tale to drain. . Decontamination equipment filled / vented l LNEC/GE-QA l l 6.8 Pre-Operational Testino of Decontamination Equipment (( Carry out a series of tests on the decontamination equipment prior to system startup. These are as follows: i 6.8.1 Beater Circuit Test a) Energize the power supplies to heater CU-105 by switch-ing circuit breaker switches to ON. b) Select individual heater control panel switches to , OE. Verify heaters will not energize in the no flow condition . , c) Turn off or verify off all heater switches. Heater circuit test complete. LNEC/GE-QA ( LoN00N NUCLEAR
SE CisON Tsitt ga ve5eOm (88tCfivt Daf t pgG, . 6.0 Procedures - E- 5/31/84 19 of 97 I 6.8.2 Decontamination Equipment Leak Test (HP Hold Point) MONITOR HYDRO PRESSURE CONSTANTLY, USING CALIBRATED GAUGE ON PUMP SKID TO PROTECT AGAINST OVER-PRESSURIZATION Hydro test the decontamination equipment to 225 psig by the following method (HP PRESENT FOR LEAK TEST). , a) Install hydrostatic test pump to line HT2-1/2" skid. Open valve HT2-V1. b) Isolate all pressure gauges by closing valves CUl-VS, CU3-VS, CU 2-V10, CU 2-Vil, CIl-v3, CU10-VS, Cull-V4 CUl-V6. c) Use the hydrostatic test pump to increase system pres-sure to 130 psig. At this point, the relief valves RVl-V1, RVl-V2, RVl-V3 and RV10-V1 are individually I checked to ensure each valve relieves. d) If required, reset the relief valves until they re-f lieve at the desired pressur.e of 130 psig. Upon satis-factory operation, each relief valve is removed or plugged for the duration of the system leak test. el Increase system pressure to 225 psig in steps as indi-cated on pressure indicator located on hydrostatic test pump. f) Hold pressure at 225 psig (+ 23 psig) for a minimum of 30 minutes. g) Check all exposed joints for leaks. h) Af ter the system is checked for leaks and the neces-sary adjustments are completed, decrease the system pressure to 125 psig by opening CV2-V1, close HT2-V1, and disconnect the hydrostatic test pump. ALLOWABLE TOLERANCE DURING BYDROSTATIC TEST IS 104 s s- OVER 30 MINUTE INTERVAL. p@Vu . ( % LONDON NUCLEAR l
l MCiaom 111LE alw4cN 888tCf 8vt Daf t paGE , 6.0 Procedures - E- 5/31/84 20 of 97 1 i) Secure demineralized water or condensate flow j) Open valves CUl-VS, CU 3-VS , CU2-V10, CO2-V11, CIl-V3, CU10-V5 and Cull-V4 CUl-V6. System leak test complete. NEC/GE-QA 6.8 3 Eigh/ Low Pressure Switch Check No. 1 m) With the equipment pressure at 125 psig as per Section 6.8.2, the control switch for circulating pump CU-102 is selected to ON. Verify CU-102 will not energize in the high pressure condition. Return pump switch to OFF position. b) Open CV2-V1 to lower pressure (PI-101) to 20 psig, l then close CV2-V1. , c) Select CU-102 control switch to ON. Verify CU-102 will not energize in the low pressure condition. d) Lower pressure to atmospheric and reinstall relief valves RVl-V1, RVl-V2 and RVl-V3 and remove plug f rom RV10-V1. Pressuro switch test complete. LNEC/GE-QA ( LON00N NUCLEAR
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64Ct e titti naviseose tECtivt Catt pact [ l 4 6.0 Procedures - E- 5/31/84 21 of 97 ; i i 6.8.4 Circulating Pump _(CU-102) Test , l This test is performed with the decontamination equipment , isolated from the recirculation system. l a) op. n, or check' open the following valves: , 4 CUl-V3 Skid Inlet Isolation { CUl-V4 Circulation Pump Suction l CU2-V9 Heater Inlet Isolation : CU3-VI Heater Outlet Isolation CU6-V1 Reverse Flow Isolation l
- CD2-V2 Surge Tank Isolation -
b) Close or check closed the following valves: , f CU1-V2 Hose Isolation Skid End i CU10-V1 Hose Isolation 4 CUS-V8 - Purification Flow Control , Circulacion Pump Discharge CU2-V3 CU4-V4 IX Cleanup, Inlet Isolation , 4
- CU5-V4 IX Cleanup outlet Isolation A CU3-V2 Skid Outlet Isolation V1 RHR Return "A" Imolation V2 RHR Return "B" Isolation CU2-V2 Circulatjon Pump Bypass [
^
c) Adjust pressure in decontamination equipment to 35 psig by opening ST1-V1, and ST1-V2 until PI-101 indi- ' i cates required pressure. . l l ] d) Adjust valve CU2-V8 to one . turn open. e) Push start button for circulaClon pump CU-102. ' I f) Slowly open valve CU2-V8. . t i g) Adjust flow in pump skid loop to 250 GPM + 50 GPM by ' opening valves CU2-V8 and CU2-V2. Monitor flow on - indicator FI-101.
'Y' Pump Test Complete LN/GE-QA I
( d
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LoNooN NUCLEAR i-
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e MCfiO*e 91144 mg vessoas (88tCtevt Oaf t eact 6.0 Procedures -E- 5/31/84 22 of 97 ( 6.8.5 Bigh/ Low' Pressure Switch Check - No. 2 Recheck the pressure switches during pump open flow test to ensure the circulation pump CU-102 will shutdown on in-creasing and decr' easing pressure conditions. a) Increasing Pressure
- 1) Place nitrogen cylinder on line and slowly increase system pressure to 100 psig + 5 psig (high pressure setpoint TIS psig I 5 psig) as indicated on PI-102 by opening vaTve ST1-V1 and ST1-V2. Continue to increase pressure until circulation pump CU-102 stops on high pressure trip. .Close ST1-vl and ST1-V2.
Adjustments to setpoint must be made at this time and the procedure repeated as necessary.
- 2) Depressurine system to jj,psig 1 5 psig as indicated on PI-101 by open;,ng valve CV2-V1.
- 3) Restart circulating pump CU-102 by opening
( CU2-V2 and throttling CU2-V8 to 1 turn open. Start pump and throttle flow to 250 150 GPM as indicated on FI-101. b) Decreasing Pressure
- 1) While circulation pump CU-102 is running, lower system pressure below setpoint (30 psig i 4 psig) by opening valve Cv2-V1. Continue to decrease pressure until CU-102 stops on low pressure trip. Close CV2-V1. Adjustments to setpoint must be made at the time, and if so, repeat check. .
- 2) on completion of check, place the nitrogen cylin-der on line by opening valve ST1-V1 and ST1-V2 to increase system pressure to 45 psig i 10 psig.
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SECTCN ti1LE AEvi$eOM EFFECTIVE Dalt paGE e 6.0 Procedures -E- 5/31/84 23 of 97 i (s + t
- 3) Restart circulating pump CU-102 by opening valve I CU2-V2 and throttling valve CU2-V.8 to 1 turn l open. Start pump and throttle flow to 250 GPM l
+ 50 GPM as indicated on FI-101.
High/ Low Pressure Switch Check - No. 2 Complete ; LNEC/GE-QA 6.8.6 Flow Check Through Ion Exchange Columns a) Check valve CU4-V13 is closed and open valves CU4-V4 !' and CUS-V4. Monitor flow indicator PI-202. i b) Adjust flow in ion exchange skid to approximately 40 : GPM on FI-202 by adjusting valve CU2-V8. Enter on log i sheet as per table 6.10. 4 c) Check flow in each ion exchange column by: ! ( 1) closing valves CU4-Vl/V2 and monitoring flow indi-cator FI-202 to check flow through ion exchange column CU-203. Record FI-202 reading
- 2) open valve CD4-V2 and close valve CU4-V3. Monitor FI-202 to check flow through ion exchange column CU-202. Record and compare with previous flow ,
through CU-203. 3) open valve CU4-V1 and close valve CU4-V2. Monitor FI-202 to check flow through ion exchange column CU-201. Compare with previous flows through i j CU-203 and CU-202. THE FLOWS THROUGH EACH COLUMN SHALL AGREE ; WITHIN 5 GPM. IF THIS IS NOT THE CASE, RE-PEAT THE TEST TO LOCATE AND RECTIFY THE l PROBLEM. i
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+
, LNEC/GE-QA i
I i LONDON NUCLEAR l
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i < ? SECie0N TsYtt RE va580N (FFECTevE DaTE pact 9.0 Procedures -E- 5/31/84 24 of 97 ! ( l I d) Upon completion, open valves CU4-Vl/v2/V3 and leave !i the ion exchange columns valved in. i Ion exchange column flow check complete. l LNEC/GE-QA ! 6.8.7 Heater Control Checks l
- l
~
a) Check high temperature cutoff switch is set to 285oF b) Turn CU-105 heater switches on. , c) Check indication lights are on. l l
. d) Check operation of high temperature cutoff switch by [
adjusting temperature cutoff below indicated ! temperature. , i e). Repeat sets (a) through (d) for heater CU-401. -l t f) Restore set points to normal condition (285 F). f (' Both heater control checks complete. l l LNEC/GE-QA i r 6.9 Preparation of the Recirculation Decontamination System l Both the suction and discharge sides of the recirculation : decontamination system are filled, vented and tested for i leaks simultaneously. All further tests and decontamina- ! tion will be carried out separately. i PERIODIC WALK-DOWN OF THE SYSTEM SHALL BE INITIATED WHEN ; THE HOSES AND SYSTEM ARE PRESSURIZED. THE INTEGRITY OF , i FILLED PRESSURIZED HOSE, HOSE (FLANGE AND NIPPLE) ' l CONNECTIONS AND COMPONENT JOINTS SHALL BE VERIFIED. , i WALK-DOWN SHALL BE CONDUCTED ON THE HOUR AND HALF HOUR BY TWO ASSIGNED PERSONNEL. ALL OBSERVATIONS SHALL BE s RECORDED IN A LOG MAINTAINED BY THE DECONTAMINATION ; SUPERVISOR. THE CONTROL ROOM X 4223 or X 4423 SHALL BE . NOTIFIED OF ANY SIGNIFICANT LEAKAGE FROM PLANT SYSTEMS OR l EQUIPMENT. iI
. i LONDON NUCLEAR s
. . _ . s . . _ - . . . - . _ __..__._,,-_m...-._,_,.,m.__, ___
$(Cisom tiTL( af viS*0N (IF(CTIVE DAI( PAG (
(. 6.0 Procedures - E- 5/31/84 25 of 97 ; 6.9.1 Decontamination System Valve Status r a) Align Recirculation RHR and RWCU system valve as follows: l Valve l Designation Description Position MO-53A Recirculation Pump "A" Open Discharge Isolation , MO-53B Recirculation Pump "B" Open Discharge Isolation MO-43A Recirculation Pump "A" Open f Suction Isolation MO-43B Recirculation Pump "B" Open Suction Isolation MO-66A Ring Header "A" Bypass Open MO-66B Ring Header "B" Bypass Open l MO-65A Ring Header "A" Crosstie Open MO-65B Ring Header "B" Crosstie Open POS-81A RHR Return "A" Open POS-81B RER Return "B" Open ! AO-46A RHR Return "A" Check Open i AO-46B RHR Return "B" Check Open , i l M012-15 RWCU Suction Isolation Open i r MAN 12-46 RWCU Suction Open , MO-10-18 RHR Supply Open ;
.. MAN 10-88 RHR Supply Open l MO-12-18 RWCU Supply Open 163A RHR Return 'A' Check By-Pass Open 163B RHR Return 'B' Check By-Pass Open LNDC/GE-QA/ UNIT 2 OP.
l LONDON NUCLEAR
'f
SECTsON T11LE REUsscN EFFECieUE DATE CcGE ,i 6.0 Procedures -E- 5/31/84 26 of 97 ! l b) Check open, or open, all temporary valves V1 through ' V26 as per Table 6.4 ' LNDC/GE-QA 6.9.2 Filling and Venting (HP Hold Point) a) Open/ check open the following valves: l CUl-V1 Hose Isolation Process End CUl-V2 Rose Isolation Skid End i CU10-V1 Hose Isolation j CU2-V3 Circulation Pump Discharge Isolation : CU3-V4 Hose Isolation Process End l CU3-V1 Heater Outlet Isolation , CU3-V2 Skid Outlet Isolation ' CU2-V8- --Main Cooler Bypass l CU2-V9 Heater Inlet Isolation CU10-V2 Hose Isolation _ ! p CU3-V3 Hose Isolation Skid End i i CU6-V1 Reverse Flow Isolation ! CU7-V1 Reverse Flow Isolation CU4-V4 IX Cleanup Isolation CU4-V14 Hose CU-301 Isolation ! CU4-V15 Hose CU-301 Isolation i Vll Recirculation Loop "A" Suction Vent } V12 Recirculation Loop "B" Suction Vent ! . V27 RWCU. Vent ! E i s .% *
- 1 I
i t i L i ' LONDON NUCLEAR i I 1
- - - - . - - . , , , . --.,,,,--n-- w,,-,.,- . . , , - - . ...,-,,..------,-,,.--m, ~--,..,--,-_,,-,_,-n.-,w, - - - , ---,----,,p.,---,
i i i SECTaow isttt agvasaQN (FFECTivE DATE pact , i 6.0 Procedures - E- 5/31/84 27 of 97 , i:
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b) Check and record reading on TM-201, totalizing flow i meter. ' c) Open CDl-V4 and adjust CDl-V6 open to obtain a reason- ! able fill rate on TM-201 (using condensate water : supply). d) Check decontamination system temporary connections in-side and outside drywell for leakage. : e) When system water inventory approaches 9200 gallons, l as indicated on TM-201, throttle back on CDl-V6 and ! monitor drains from temporary vent valves Vll, V12, and v27. il ; f) Close Vll, V12, and v27 as water appears in its i i respective drain line. g) Flow is reverified through ion exchange columns by I opening CV1-V1 (CVl-v2/V3). When flow is verified l through SG-201, CVl-V1 (CVl-V2/V3) is closed. ! h) Close CD4-V1 and CDl-V6 when system is full of water.
' \
j System is filled and vented. ! l LNEC/GE-QA r i 6.9.3 System Leak Test (HP Hold Point) I a) Place the nitrogen cylinder on line by opening ST1-V1 i and ST1-V2 and the Nitrogen gas cover pressure is grad- ) ually increased to 125 psig on pressure indicator i PI-101. Close ST1-V1. ; b) Hold pressure at 125 psig (+ 5 psig) for a minimum of 30 minutes. c) Check all exposed joints for leaks, and complete the necessary adjustments, crack open CV2-V1 and reduce ; W- the pressure to approximately 35 psig. Close CV2-V1. i n o Y l LONDON NdCLEAR
i stcica vitts atws.o= EFFtctwt oaf E pscs ; , 6.0 Procedures -E- 5/31/84 28 of 97 ! I 1 d) If leaks are detected in system, repair per GE ' recommendation, and MRF's for station equipment. e) If leaks are detected in the LN decontamination equip- { ment and/or temporary connections, then corrective ac- l tion shall be taken as deemed necessary. System leak test completed. f LNDC/GE-QA ; 6.10 Preoperational Testing - Suction Side 6.10.1 Pre-decontamination Radiation Survey $ t a) Perform initial radiation survey of recirculation sys- l tem as detailed in Section 6.27. . LN/GEQA/HP 6.10.2 Valve Status i a) Position valves in accordance with Tables 6.1 through 6.5 for initial valve status to commence ; preoperational testing on the suction side, j Table 6.2, 6.2, 6.3 and 6.4 LNDC/GE-QA/ Table 6.5 I Unit 2 operator , ! b) Close the following valves: V1 RHR Return "A" Isolation - Skid End . V2 RHR Return "B" Isolation - Skid End ' V5 RHR Supply Isolation - Skid End i V6 RWCU Isolation - Skid End l CU2-V2 Circulation Pump Bypass l g, CU4-V4 IX Cleanup Inlet , LNDC/GE-QA l l r ( LONDON NUCLEAR t l 1
t MCTCN IITLE RE w@ON EFFECTevt DatE PAGE , 6.0 Procedures - E- 5/31/84 29 of 97 ( i t 6.10.3 Flow Test at Operating Conditions - i a) Notify Unit 2 Operator to secure drywell coolers ! during heat-up and decon. [ LN-GEQA ; b) Throttle CU2-V8 to 1 turn open. c) Start circulating pump CU-102 and throttle flow to approximately 250 + 50 GPM by opening CU2-V8 and adjusting CU2-V2 to a cracked open position. d) Once flow is established in the recirculation suction lines, then valve in RHR and RWCU lines by i opening valves V5 and V6. Check all temporary connections inside and outside drywell for leakage. e) vent decontamination system as necessary. f) Check flow through RHR supply line by closing valves l CU3-V3 and V6. Monitor FI-101. l ( g) 'Chec k flow through RWCU line by opening V6 and l closing V5. Monitor FI-101. i h) On completion of satisfactory flow through the recirculation suction, RWCU and RHR supply lines open ! valves CU3-v3 and V5 and commence heatup. ' i) Select hgater CU-105 to auto to commence heatup to 250 F i 5 F. j) Select auxiliary electric heater CU-401 to" auto". k) As temperature is heating up, bleed-off system to i maintain a system pressure of 40 psig i 5 psig as in-
- dicated on PI-101. This is accomplished by opening l valves CD2-V2'and RD2-V4 as necessary. ,
l -
, 1) Monitor system, once temperature is reached, hold for l
's . at least 30 minutes. Check all temporary connections l j
inside and reaches 200ougside F and adrywell g a i for n 'a leaks,,Fwhen t 250 + tgmperature
~
5 F. Take i corrective action to repair leaks. l l o l
- LoNOoM NUCLEAR j; t
HCTom TITLE ftEvtscN EFFECTIVE DATE PAGE 6.0 Procedures - E- 5/31/84 30 of 97 l i Record i n Operations Log Sheet, Table 6.10. t Temporary hand-held temperature read-out devices will be used to monitor temperatures around the circuit. !
?
l LNDCfGLQA LNDCfGEQA (200 F) (250 F) m) On completion of satisfactory operation, select , heaters CU-105 agd CU-401 to OFF. Allow temperature ; , to drop below 200 F. n) On completion of test, select CU-102 to OFF. LNDC/GE-QA ! 6.11 Preoperational Testing - Discharge Side : 6.11.1 Valve Status i a) Position valves as per Tables 6.1, 6.2, 6.3, 6.4, and l 6.6 to commence preoperational testing on the ; tli sch arge s i de. 4
-( l Table 6.1, 6.2, 6.3 and 6.4 LNDC/GE-QA Table 6.6 -
Unit 2 Operator b) Close the following valves: , V1- RHR Return "A" Isolation - Skid'End V2 RHR Return "B" Isolation - Skid End i V5 RHR Supply Isolation - Skid End l V6 RWCU Pump Bypass ~ CU2-V2 Circulation Pump Bypass CU4-V4 IX Cleanup Inlet ; LNDC/GE-QA 6.11(2..-Flow Test at Operating Conditions a) Throttle CU2-V8 to 1 turn open'. b) Start circulating pump CU-102 and throttle flow to ap- ; proximately 250 GPM + 50 GPM on flow indicator l FI-101 by opening CO2-VI and adjusting CU2-V2, to a ; cracked open position. ( ,
. LONDON NUCLEAR
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SECT sO*e TsfLE RE v$0N EFFECilvt DATE PAGE ,. 6.0 Procedures -E- 5/31/84 31 of 97 ( c) Vent decontamination system as necessary, d) Once flow is established in the recirculation dis-charge lines, then valve in RHR return lines by open-ing valves V1 and V2. Check all temporary connections inside and outside drywell for leakage. e) Monitor flow indicator FI-101 and continue venting as required. f) Flow through RHR return "B" line is checked by closing valves CUl-v2 and V1. Monitor FI-101. g) Flow through RHR return "A" line is checked by opening V1 and closing V2. Monitor FI-101. h) On completion of satisf actory operation, open CUl-V2 and V2 and commence heatup.
- 1) Selget hgater CU-105, to auto to commence heatup to 250 F i 5 F.
( j) Select auxiliary electric heater CU-401 to auto. k) As temperature is heating up, system shall be bled-off to maintain a system pressure of 40 psig as indicated on PI-101. This is accomplished by opening valves CD2-V2 and RD2-V4 as necessary.
- 1) Monitor system, once temperature is reached, hold for at least 30 minutes. Check all temporary connections inside and200 reaches ougside F anddrywell againfor atleaks,,Fwhen 250 + tgmperature 5 F. Take corrective action to fix leaks. Record in Operations Log Sheet, Table 6.10. Temporary, hand-held temperature read-out devices will be used to monitor temperatures.
m) On completion of satisfactogy operation, maintain system temperature at 250 F i 5 F. O' Flow test at operating conditions completed. LNDCfGEQA LNDCfGEQA (200 F) (250 F) { LONDON NUCLEAR
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- 6.0 Procedures -E- 5/31/84 32 of 97 l
( [ I i ! 6.12 Discharge Side Decontamination ' f The following subsections detail the procedure used for [ performing the decontamination of the discharge side of f 1 the recirculation piping and RHR return lines. To ! decontaminate ef fectively, the discharge side is divided ! into two separate flow paths. Refer to LN Drawings ; 3838-B-5001-1, Flow Path #1 and 3838-B-5001-2, Flow Path t
#2. Piping and components on Flow Path 41 will be decon-l taminated first, then Flow Path 92. ;
6.12.1 Valve Status + Align the decontamination system valves to incorporate ! the flow path designated in Flow Path fl, Refer to LN ) Drawing 3838-B-5001-1. l i a) Position valves as per Tables 6.1, 6.3, 6.4 and 6.6. ! L Table 6.1, 6.3 and 6.4 ! LNDC/GEQA Table 6.6 r Unit 2 Operator : b) Close the following valves: - V1 RHR Return "A" Isolation Skid End ! V2 RHR Return "B" Isolation - Skid End V5 RHR Supply Isolation - Skid End ' V6 RWCU Isolation - Skid End i LNDC/GEQA l c) Throttle the following valves: l MO-65A - Ring Header "A" Crosstie ! Unit 2 Operator j l
's. Riser valves: V13, V14, V15, V16, V17, V18, Vl9, V20, !
V21, V22 as necessary, to vary decon flows, if needed ' to accelerate decon in one or more risers. ; ( LNDC/GEQA ( 1 l LONDON NUCLEAR l 1 l .
i sccion TiTLt atvision (fF(CYswEDAf( PAGE 6.0 Procedures -E- 5/31/84 33 of 97 ( I i I 6.12.2 Hydrazine Injection f i
-Add sufficient hydrazine (35% solution of hydrazine in ;
water) to the decontamination system via chemical injec- l
'tlon vessel CI-101 to obtain a concentration of 100 ppb l oxygen.
Add hydrazine according to the following steps: a) Open CV5-V1 and monitor pressure indicator PI-103 un- : til vessel pressure reads O psig. , b) Open RD2-V6 until level in vessel as indicated on CI-101 sight glass reaches 1/2 level, + 10 inches, then close RD2-V6 and CV5-V1. [ c) Open CIl-V1 and add 8 litres of 35% hyd'razine to l CI-102. , d) Once hydrazine has been injected, close CIl-V1 and i open CI3-V1 then CI2-V1. l e) Keep CI-101 on line for a minimum of 5 minutes, to en-( - sure hydrazine has been injected. I f) Close CI2-V1 and C13-V1. f g) Perform sampling to establish the dissolved oxygen con- ! centration (as per Section 6.24 of this procedure), i and steps (a) through (f) are repeated as necessary to lower the dissolved oxygen levels below 100 ppb. , KEEP HYDRAZINE IN A TIGHT SEALED CONTAINER WHILE NOT IN USE. SAFETY GLASSES OR FACE SHIELD AND j RUBBER GLOVES MUST BE WORN WHILE INJECTING l HYDRAZINE. t h) Enter appropriate data in Reagent Addition Check l Sheet, Table 6.7. l i) Place ion exchange columns on line by opening CU4-V4 ! adjusting CU2-V8 to achieve 60 GPM + 15 GPM on s? - FI-202. . Satisfactory Hydrazine levels. ! LNDC/GEQA l ( LONDON NUCLEAR
i MCTsON TsTLE p(ve$CN (FFECTevt 0 ATE PAGE 6.0 Procedures -E- 5/31/64 34 of 97 ' ( di 6.12.3 Reagent Injection
-l i
Add reagent according to the following steps: a)Put information tags on Drywell floor drain and , equipment drain sump pumps to prevent automatic operation during time when reagent is part of the decon flow path. When sump pump out is required, Unit ,
, 2 Operator shall contact the GE Decon Supervisor at ;
extension 4350 or 4441 to verify that reagent has not ' leaked to the sumps. t I Unit 2 Operator [ t b)Open CV5-V1 and monitor pressure indicator PI-103 l until vessel pressure reads O psig. ! t c) Open RD2-V6 until level in vessel as indicated on CI-101 sight glass reaches 1/2 level, i 12 inches, i. then close RD2-V6 and CV5-V1. ( d) Open CIl-V1 and add 25 KG of CAN-DECON reagent, LND-101A to CI-101. { e) Once reagent has been injected, rinse chemical addi-tion valve CIl-V1 with condensate supply then close i CIl-V1 and open CI3-V1 then CI2-V1. f) Keep CI-101 on line for a minimum of 5 minutes, to f ensure reagent has been injected. j g) Close CI2-V1 and CI3-V1. I h) Perform sampling to establish the dissolved reagent { concentration (as per Section 6.24 of this procedure), l repeat steps (a) through (f) as necessary to achieve t 0.1 wtt 1 0.02% concentrations.
- 1) Enter appropriate data in Reagent Addition Check 1
Sheet; Table 6.7. t i Reagent injection completed. ' l 'LNDC/GEQA i r ( l I l( l LONDON NUCLEAR
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.6.0 Procedures -E- 5/31/84 35 of 97 i
i i 6.12.4 Rodine 31 A Injection ; i Add aufficient Rodine 31 A to the decontamination system l;
! via chemical inj'ection vessel CI-101 to obtain a concen-a tration of .014 1 0.005% wt. t Add Rodine 31A according to the following steps: (
r a) Open CV5-V1 and monitor pressure indicator PI-103 un- l s til vessel pressure reads 0 psig. l i b) Open RD2-V6 until level in vessel as indicated on CI-101 sight glass reaches 1/2 level, + 10 inches, l 1 l then close RD2-V6 and CV5-V1. j t l c) Open CIl-V1 and added 0.5 gallons of Rodine 31 A to 3 CI-102. j d) Once Rodine 31A has been injected, close CIl-V1 and [ open CI3-V1 then CI2-V1. !
;( e) Keep CI-101 on line for a minimum of 5 minutes, to en-sure Rodine 31A has been injected. [
i r f) Close CI2-V1 and CI3-V1. l l ! g) Sampling as per Section 6.24 of this procedure. Repeat l
! (a) to (g) as necessary to achieve desired l concentration. !
h) Enter appropriate date in Reagent Addition Check l Sheet, Table 6.7. } Satisfactory Rodine 31A levels. l l LNDC/GEQA ; i j 6.12.5 Reagent Regeneration ; r < a) Add reagent (or reagent components) necessary to l maintain a reagent concentration at 0.1 1 0.02 wtt. , i
& b) Continue sampling, as descriged in ,Section Refer to 6.24. l Maintain temperature at 250 F + 5 F.
j aampling check sheet for verification ~. i' 1 I i
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I ' I LONDON NUCLEAA i
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i l , secteo= istle ma vevo= E88ECfivt Dett PAGE 6.0 Procedures - E- 5/31/94 36 of 97 c) Monitor radiation levels on decontamination flow path lines to ensure levels are satisfactorily decreasing (as per Section 6.28 of this procedure and record readings on Table 6.9). Flow path may be adjusted accordingly to allow for better decontamination flow ; rates in areas that require it. d) If additional resin is required during reagent regeneration, slurry spent resin as per Section 6.14, . add new resin as per Section 6.7.2 and document addition in Table 6.1.2. o) Reverse flow during the decontamination at approximately hourly intervals or as specified by the LN field supervisor: Open CU7-V1 and CU6-V1 and close CU1-V3 and CU3-V2. fi Monitor activity levels around the decontamination equipment at 2 hour intervals. Enter appropriate da-ta in Radiation Monitor Check Sheet Table 6.9. , Repeat Steps c), d), e) and f) as required. ( g) Upon completion of decontamination Flow Path fl, (LN Drawing 3838-B-5001-1), adjust the flow path to incor-parate the RHR Return lines as shown in Flow Path 02, LN Drawing 3838-B-5001-2. ; Align valves as follows: V1 RHR Return "A" Iso.-Skid End Open V2 RHR Return "B" Iso.-Skid End Open V25 Manifold "A" Isolation Close V26 Manifold "B" Isolation Close Cul-V2 Hose Isolation - Skid End Close LNDC/GEQA h) Termination of discharge side decontamination shall be declared by the LN Chemist in conjunction with the ! p' - PEco Chemistry representative, and GE Engineer / Manager. Refer to Section 6.26 for termination criteria. LN/GE/PECo (
,. l LONDON NUCLEAR
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{ 6.0 Procedures - E- 5/31/84 37 of 97 i) When the discharge side regeneration phase has been completed, select pump CU-102 to OFF and isolate decontamination equipment by closing the following valvest V1 R!lR Return Isolation - Skid End V2 RilR Return Isolation - Skid End LNDC/GEQA 6.13 Suction Side Decontamination Upon completion of activity removal on the discharge pip-ing and associated piping segments, preparations will be made to decontaminate the suction piping. .igain, to de-contaminate ef fectively, the suction side piping will be divided into two separate flow paths. Refer to LN Drawings 3838-B-5001-3, Flow Path 4 3 and 3838-B-5001-4, Flow Path 04. Piping and components on Flow Path 03 will be decontaminated first, then Flow Path 64. 6.13.1 Valve Status k Align the decontamination system italves to incorporate the flow path designated in Flow Path 03. Refer to LN Drawing 3838-B-5001-3. , a) Check or adjust valves to be ao per Tables 6.1, 6.3, 6.4 and 6.5. Table 6.1, 6.3 and 6.4 LNDC/GEQA Table 6.5 Unit 2 operator b) Check or close the following valves: V1 Ri!R Return "A" Isolation - Skid End V2 RilR Return "B" Isolation - Skid End V5 R!lR Supply Isolation - Skid End V6 RWCU Isolation - Skid End LNDC/GEQA 6.13.2 Startup and Heatup a) Close CU2-V2 and CU4-V4. Throttle CO2-V8 to one turn open. j .- LONDON NUCLEAR
SE C f *O's fiTLE M ve�as if *ECTivt Daf t paGE 6.0 Procedures -E- 5/31/84 38 of 97 k, b) Start circulating pump CU-102 and raise flow to approx-imately 250 + 50 GPM on FI-101. c) Select heategs CU-105 and CU-401 to auto to commence heatup to 250 F. d) As temperature is rising, bleed-of f system to maintain a system pressure of45psig i 10 as indicated on PI-101. This is accomplished by opening valves CD2-V2 and RD2-V4 as necessary. 6.13.3 Bydrasine Injection Add 6 litres of 354 hydrazine to the suction side as per section 6.12.2 of this procedure. Satisfactory Hydrazine levels achieved.
.- LNDC/GEQA 6.13.4 Reagent Injection .
( Add 6 kg of LND-101A to the suction side as per Section 6.12.3 of this procedure. Reagent injection completed. LNDC/GEQA 6.13.5 Rhodine 31A Injection Add Rhodine 31A as per section 6.12.4 LNDC/GEQA 6.13.6 Reagent Regeneration The reagent regeneration phase for the suction side is 4 performed as per Section 6.12.5 (a) to (f) of this I procedure. a) Upon completion of decontaminating the piping and com-
's . , ponents on Flow Path 93 (LN Drawing 3838-B-5001-3),
the flow path is adjusted to incorporate the RHR sup-ply and RWCU lines as shown in Flow Path 94, LN Drawing 3838-3-5001-4. * ( tonoon euctaan
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StCiao's fift1 sitvessoN 18IECTivt OafE Pact 6.0 Procedures -E- 5/31/84 39 of 97 b) Termination of the suction side decontamination shall be decla red by the LH Chemists in conjunction with PEco Chemistry Representative and GE Engineer / Manager as per Section 6.26. LN/GEQA/PECo 6.13.7 Reagent Removal (suction side) a) On completion of the decontamination process, select all heater control switches to OFF. Open valve V9. b) Provide cooling water to the main circuit cooler (CU-106) by opening valve CW2-V1 (optional). c) Cool the decontamination system to below 180 F (optional). , d) Once the gecontamination system temperature drops to below 180 F, cooling water isolated by closing valve ( CW2-V1 (optional).
. e) Isolate the ion exchange columns, CU-201/202/203 by closing CU5-V1/V2/V3 and CU4-V1/V2/V3.
f) slurry resin from CU-201/202/203 according to the pro-cedure in section 6.14 and refill with mixed bed resin (7:1 by volume ratio of anion / cation according to the procedure in Section 6.7.2. g) Put the ion exchange columns on line by opening CU4-V1/V2/V3 and CU5-V1/V2/V3. Open valve CU2-V2 4 close CU2-V4. Adjust CU2-V2 to obtain a purification flow rate of 90 GPM as indicated on FI-202. h) Adjust flow as recommended by LNFS, during this phase to include the RHR supply and RWCU lines (Flow Path 04). This is accomplished by closing valve CU3-V3 and throttling valve V9. To return to Flow Path 03, open s s- CU3-V3 and V9 and close V5 and V6. i
, LNDC/GEQA
(
. LoN0oM NUCLsAn .
54 Cla0*e 18fL8 #tv$O4 (FFECtevt Oaf t pact 6.0 Procedures -E- 5/31/84 40 of 97 I il Maintain operation until the conductivity on the suc- ' tion side piping is approximately 100 uhmo/cm at which time reagent removal on the discharge side is com-menced. l t LNDC/GEQA 6.13.8 Reagent Removal (Discharge side) a) Select pump CU-102 to OFF, and close V5 and V6. j LNDC/GEQA , b) Set valves as per Tables 6.1, 6.2, 6.3, 6.4, and 6.6 to commence reagent removal on the discharge side. - (Valve status is setup for Flow Path 41.) Tables 6.2, 6.2, 6.3 and 6.4 LNDC/GEQA i ( Table 6.6 Unit 2 Operator l c) Throttle valve CU2-V8 to ,1_ turn open. ! LNDC/GEQA d) start circulating pump CU-102 and adjust flow to 90 ! GPM on FI-202 by opening CU2-V2 and CU4-V4. e) Adjust flow is adjusted, as recommended by LNFS, dur-ing this phase to include the RHR return lines (Flow 1 Path 42). This is accomplished by' opening valves V1 and V2 and closing V25 and V26. To return to Flow Path 01, valves V25 and V26 are opened and V1, v2 are closed, f) Maintain operation until the conductivity on the dis-charge side is approximately 10 umho. (Further slurry-s'- ing and refilling of ion exchange columns may be required, if so, see Section 6.14 and 6.7.2). l 4 LONDON NUCLEAR , I
MCTaON TITtt ag wsS80M EF8ECfivt Oaft pact 6.0 Procedures -E- 5/31/84 41 of 97 k g) Once conductivity on this side is < 10 umhos/cm or as specified by Station, switch the system to check the conductivity levels on the other side (suction pip-ing). For further reagent removal in suction side pip-ing, see section 6.13.7. Operation is continued until the conductivity levels on both the suction and dis-charge piping is within station requirements. LNDC/GEQA h) Remove information tags from drywell floor drain and equipment drain sump pumps Unit 2 Operator
- 1) Remove plastic sheeting from drywell torus vents
( GEQA/LN 6.13.9 system shutdown Once the steps in Section 6.13.9 are complete, the decon-tamination equipment is shutdown as follows: a) Select heater elements CU-105 and CU-401 to OFF. b) Select circulating pump CU-102 to OFF. c) Close the following isolation valves: CUl-V1, CU3-v4, vi, v2, v5 and V6. d) Depressurize decontamination equipment as follows: g,%..
. LoNOoM NUCLEAR
'I ucies won aavisoa (Fractivs oatt ~ract j 6.0 Procedures -E- 5/31/84 42 of 97
( , r
- 1) check closed, or close, ST1-V1
- 2) open CD2-V2 and CV2-V1 :
f
- 3) check pressure indication on PI-101 and PI-102 l reaches zero !
e) Commence final slurry operations as per Section 6.14 ! and drain down procedures as per Section 6.15. System shutdown. LNDC/GEQA f 6.14 Resin Slurry i The purpose of this step is to transfer the radioactive ' resin from each of the ion exchange columns to the resin liners.. The following procedure is for slurrying the - resin from ion exchange column CU-201. Equivalent equip- ' ment designations for CU-102 and CU-203 are shown in brackets. Do Not proceed further without the specific ( concurrence of GE Engineer /Mana'ger, LNFS, Health Physics and Shift Supervisor. ' 6.14.1 slurry Preparations ! a) Set up radiation monitoring equipment as required to ! measure radiation levels before, during, and after slurry operation. b) Make all personnel involved aware of the hazards dur-ing the slurry process. Personnel not essential to the operation are kept clear of the area. LN/GEQA/SSV i I e I i LONDON NUCLEAR
&(CTCM title p(wt5CN EFFECTivt Oaft PAGE >
6.0 Procedures - E- 5/31/84 43 of 97 ( . 6.14.2 Slurry Operttion i The resins from each ion exchange column are removed sep- ! arately. Valve designations are given below for slurry-ing column CU-201. Equivalent designations for columns CU-202 and CU-203 are shown in brackets respectively. i a) Check closed, or close, CU4-V1 (CU4-V2/v3), CUS-V1 ' (CUS-V2/V3) and CVl-V1 (CVl-V2/v3). i b) Unlock and open RSl-V6. Open CDl-V4 and CDl-V5 to ap-proximately half throttle to establish flow in the slurry hea4er. Confirm water flow to resin liner. c) Open CDl-V1 (CDl-V2/V3) to provide condensate water to i the ion exchange column to initiate slurry. d) Open RSl-V1 (RSl-V2/V3), and confirm resin flow in sight glass RS-201). , e) Monitor sight glass RS-201 remotely with a high range gamma probe for resin flow. Continue slurry flow un-til the sight glass indicates that no resin is float-I- ing and radiation measurements indicate that no significant amount of residual resin is in the column. r f) Stroke RSl-V1 (RSl-V2/V3) and monitor the sight glass ; for additional resin flow. g) Close CDl-V1 (CD1-V2/V3 and CDl-V4). CVl-V1 (V2/V3) are stroked to vent columns. . L h) Enter data in Table 6.12 (Section 6.7.2) and sign l check offs. r Resin slurry complete. - See Table in Section 6.7.2 for sign-off. k ( . 1 LONDON NUCLEAR
- 64CTIO*e 16T LE at vil'Oso 488tCisvt Oaf t .act 6.0 Procedures -E- 5/31/84 44 of 97 6.15 Draining The following steps outline the draining of the decontam-ination system once the system is shutdown and isolated f rom the recirculation system. Verify with SSV that floor drains can be used, or that drain should go to torus.
a) Open valve RD2-V4 to drain the surge tank. b) Once system has depressurized to < 10 psig, then open the following valves: { RDl-Vl/V2/V3 RD2-Vl/V2/V3/V4/VS/V6/V7/v8 cv2-V1 CV3-V1 , CV4-V1 l CVS-V1 CVl-V1/V2/CV3/V4/V5 RS2-Vl/V2/V3 CU4-Vl/V2/V3 ! [ CUS-Vl/V2/V3 f ( CU7-V1 CU6-V1 CVS-V1 CV4-V1 CV2-V1 CV3-V1 RD10-v1, RD10-V3 , c) Open CSI-V1/V2 and CS3-Vl/V3 to drain the sampling lines. LNDC/GEQA d) Remove the threaded cap from the Temporary A and 5 suction Loop drain lines. Attach a hose to the threaded and, running the hose to an adjacent torus vent.
- p. GEQA/LN e) 85V to drain recirculation, piping through recirc-ulation pump drains.
( LoNOoM NUCLEAR l l
MGios fatti at vissoas Ef t(Cteve catt pact 6.0 Procedures -E- 5/31/84 45 of 97 f) Once the ion exchange columns are drained, the remaining radiation fields art checked to make certain they are at acceptable level.s. Draining complete. , SSV SIGNIFICANT DEAD-LEGS ARE TO BE MANUALLY DRAINED TO PLASTIC BOTTLES AND RE-4DDED TO THE LONDO'i NUCLEAR ION EXCHANGE EQUIPMElfr 6.16 Decontamination System Dismaatling Upon completion of the docuntaminetion, dismantle the sys-tem in the following manners al Conduct a post-decontamination radiation survey of the
. reactor recirculation system as detailed in Section 6.18, Radiation Monitoring and Dose Control Procedures.
( b) Conduct a radiation survey of the decontamination equipment to determine if there is any unacceptable ra-diation. Surface areas that are contaminated are washed until the level of radiation is reduced to acceptable levels. c) Uncouple the decontamination equipment from the reac-tor recirculation system. Hoses are drained at a convenient floor drain connection. d) secure service water supply and open valves CW2-V1 and CWJ-V1 to drain the service water lines. Disconnect the service water supply and return lines. e) Secure domin or condensate water and CDI-V4, CDl-V5, CDl-V6 and open CDl-Vl/V2/V3. Close root valve on con-densate or domin water valve, and disconnect the con-densate or domin water line. s .Y ) Remove the radioactive waste drain line. g) Uncouple the 400 V electrica1' connection from skid 2 and 4. ( LOM0oM NUCLEAA
SECTC4 fif L E plvesom (8FtCfsvt Catt pact 6.0 Procedures -S- 5/31/84 46 of 97 I h) Disconnect the resin slurry hose from the connection to the liner.
- 1) Remove decon test coupons.
j) Disconnect the Nitrogen bottle and regulator from the surge tank. k) Remove the temporary shielding walls.
- 1) Disconnect Skid 1, Skid 2 and Skid 4.
m) Seal all open pipe ends on LN equipment with blank flanges. Dismantling complete. LNEC/GEQA 6.17 Crating and Shipping LN Equipment , a) Raise wheels on skids then place on bottom of crate (be sure wheels are fully raised and skids are located in same position as they were when they were uncrated) . b) Bolt sides of crate together insuring proper alignment. Use lag bolts (Do Not use nails or glue). c) Perform all necessary Health Physics surveys. d) If no additional shielding is needed, then place tops on crates assuring proper alignment, use lag bolts (Do Not use nails or glue). e) Load on truck using an overhead crane or fork truck with a minimum rating of 6 tons (12,000 pounds) with a minimum fork length of 8-1/2'. f) Tarp and secure all crates to truck.
' Crating Complete.
LNEC/GEQA LONDON hUCLEAR
SECTsON ISTLE at v85#0N l'84GfivtCatt pact ( 6.0 Procedures -E- 5/31/84 47 of 97 n_n TABLE 6.1 VALVE STATUS: DECONTAMINATION EQUIPMENT STATIC REFERENCE STATE CHECK VALVE 6 SIZE DESCRIPTION POSITION TYPE SKID CUl V1 3" Bose Iso. Process Ball Open End CU1 v2 3" Mose Iso. Skid Ball Open End CUl V3 3" Skid Inlet Iso Ball Open LN-1 CUl V4 3" Circ. Pump Suction Ball Open LN-1 CUl V5 1/2" Press. Instr. Iso. Globe Open LN-1 ' CUl V6 1/2" Press. Instr. Iso. Globe Open LN-1 l CU2 V1 2" Citc. Pump Check Check LN-1 CU2 V2 3" Circ. Pump Bypass Ball Open LN-1 CD.' V3 3" Circ. Pump LN-1 Discharge Iso. Globe Open CU2 V4 1-1/2" Coupon Nolder Inlet Ball Open LN-1 CU2 V5 1-1/2" Coupon Holder Outlet. Ball Open LN-1 CU2 V6 3" Main Cooler In. Ball Closed LN-1 CU2 V7 3" Main Cooler Out. Ball Locked-Open LN-1 CU2 V8 3" Main Cooler Bypass Globe Open LN-1 CU2 V9 3" Heater In. Iso. Ball Locked-Open LN-1 CU2 V10 1/2" Press. Instr. Iso. Globe Open LN-1 CU2-V11 1/2" Press. Instr. Iso. Globe Open LN-1 CU3 V1 3" Heater Out. Iso. Ball Open LN-1 CU3 V2 3" Skid Out. Iso. Ball Open LN-1 CU3 V3 3" Mose Iso. LN-1 Skid End Ball Open
sQU3 V4 3" Nose Iso.-Process Ball Open LN-1 End ,
CU3 V5 1/2" Press. Instr. Iso. Globe Open LN-1 CU4 V1 1-1/2" Exch Column CU-201 Inlet Isolation Globe Open LN-2 CU4 V2 1-1/2" Exch Column CU-202 Inlet Iso. Globe Open LN-2 CU4 v3 1-1/2" Each Column CU-203 ( Inlet Iso.
- Globe Open LN-2
. LON0oM NUCLEAA l
P SECl*0N fiftt et wegsom (8FECitwt 0Af t .act ( 6.0 Procedures - E- 5/31/84 48 of 97 TABLE 6.1 (Continued) CHECK VALVE f SIZE DESCRIPTION POSITION TYPE SKID CU4 V4 2" IX Cleanup In. Iso. Ball Open LN-2 CU4 V5 2" IX Iso. Globe Open LN-2 CU4 V13 2" IX Cleanup Bypass Globe Closed LN-2 CU4 V14 2" Hose CU-301 Iso. Ball Open CU4 V15 2" Hose CU-301 Iso. Ball Open CUS V1 1-1/2" Exch. Col. CU-201 Out. Iso. Ball Open LN-2 CUS V2 1-1/2" Exch. Col. CU-202 Out. Iso. Ball Open LN-2 CUS V3 1-1/2" Exch. Col. CU-203 ' Out. Iso. Ball Open LN-2 CUS V4 2" IX Cleanup Outlet Ball Open LN-2 ( - Isolation CUS V5 2" Hose CU-302 Iso. Ball Open CUS V6 2" Hose CU-302 Iso. Dall Open CUS V7- 2" Purification Reverse Flow Check N/A LN-1 CUS V8 2" Purification LN-1 t' low control Ball closed CUS V9 2" Furification Flow Flow Control Ball Open LN-1 CU6 V1 3" Reverse Flow Iso. Globe Closed LN-1 CU7-V1 3" Reverse Flow Iso. Globe Closed LN-1 CIl-V1 2" chemical Addition Ball Locked Closed LN-1 C21-V2 1/2" Cooling Water Iso. Globe Closed LN-1 CIl V3 1/2" Chemical Injection Pressure Isolation Globe Open LN-1 CI2 V1 1" Chemical Injection LN-1 s ,s - Inlet Isolation Ball closed CI3 V1 1" chemical Injection LN-1 Ball Closed Outlet Iso. STl V1 1/2" Nitrogen Iso. Globe Closed LN-1 CV1 V1 1/2" Exch. Column CU-201 Vent Globe Closed LN-2 ( CV1 V2 1/2" Exch. Column CU-202 Vent Globe Closed LN-2 LONDON NUCLEAR
I f I I l MCt@e tett i ett v4+0se ges(Ctevt Odf4 9444 \ j( 6.0 Procedure -E- 5/31/84 49 of 97 l t j l TABLE 6.1 (Continued) i
$N_fgf VALVE 9 jl],5 DESCRIPTION Iygg g POSITION i CV1 V3 1/2" Each. Column l CU-203 Vent Globe Closed LN-2 l CV1 V4 1/2" Vent Globe closed LN-2 [
CV1 V5 1/2" Vent Globe closed LN-2 j RV1 V4 1/2" Relief Iso.
- Ball '
Locked ;
/Open LN-2 l CV1 v4 1" Vent Pot check swing LN-2 Check gjg !
( CV2 V1 1/2" surge Tank Vent Globe closed LN-1 CV3 V11 ?./2 " - Nester Vent Globe Closed LN-1 ! CV4 V1 1/2" Main Cooler Out. Line Vent Globe closed LN-1 ! CV5 V1 1/2". Chemical Inj. ! l Vent Globe Closed LN-1 ; CV6 V1 1/2" Main Cooler shell ' Vent Globe Closed LN-1 i CD1 V1 1-1/2" Each. Col. CU-201 ' Cond. Inlet Iso. Ball closed LN-2 l CD1 V2 1-1/2" Each. Col. CU-203 L Cond. Inlet 190. Ball Closed LN-2 i CD1 V3 1-1/2" Euch. Col. CU-203 i l Cond. Inlet Iso. Ball closed LN-2 ! CD1 V4 1-1/2 " Cond . In . Iso . Ball Closed LN-2 CD1 V5 1-1/2" Cond. Bypass to slurry Ball closed { LN-2 , l CD1 V6 1-1/2" Condensate Bypass [ to skid Inlet Ball closed LN-2 : CD2 V1 1" Cond. Supply Iso. Globe Closed LN-1 l 871 V2 1/2" Nitrogen Iso. Globe Closed LN-1 ! 9T1 V3 1/2" Witrogen Iso. Globe Closed LN-1 CD2 V2 1-1/2" surge Tank Isc. Ball Closed LN-1 ( RV1 V1 1/2" surge Tank Relief Relief As 1 Installed LN-1 ! RV1 V2 1/2" Nester Relief Rollef As i Installed LN-1 ;
'SV1 V3 1/2" chemiesi Injection As LN-1 vessel Belief e nelief Installed t
I { r l e , anoonauctaan
1 og we6#0se 188tCitv6 0 aft pet 4 MCte0se tetti 6.0 Procedures -E- 5/31/04 50 of 97 TABLE 6.1 (Continued) l rs &E VALys e n 13 pascni m on Iyf.g gg POSITION l CW2 v1 1-1/2" Cooling Wster l Return Iso. Ball closed LN-1 W3 V1 3/4" Sample Cooler C.W. Supply Iso. Ball open LN-1 W5 V1 1/2" chemical Inj. C.W. Supply Iso. Check N/A LN-1 Wash Down Iso. Globe Closed LN-1 CNS V2 1/2" Cal V1 1/2" Before Sample Isolation Ball closed LN-1 CS1 V2 1/2* Before Sample Iso. Ball closed LN-1 CS3 V1 1/2" After IX Sample Isolation Ball closed LN-1 C83 V2 1/2" After IX Sample Isolation Ball closed LN-1 Globe Closed LN-1 CS4 V1 1/2" (~
~
mS1 V1 1-1/2=sDleSinkIso.
. Col. CU-201 Slurry Iso. Ball closed LN-2 I R$1 V2 1-1/2* Bach. Col. CU-202 Ball closed LN-2 Slurry Iso.
281 V3 1-1/2* such. Col. CU-203 Ball Closed LN-2 Slurry Iso. RS1 V6 1-1/2* Resin Slurry Skid Outlet Iso. Ball Locked-Closed LN-2 RD3 V1 1/2" Each. Col. CU-201 LN-2 l Slurry Drain Ball closed RD3 V2 1/2' Such. Col. CU-202 LN-2 Slurry Drain Ball Closed RD3 V3 1/2" Buch. Col. CU-203 Slurry Drain sail closed LN-2 RD1 V1 1" such. Column LN-2 CU-201 Drain Ball closed RD1 v2 la
- such. Column LN-2 CU-202 Drain Ball closed h
,4 . <
l (
p(vi$eow (H(crivt Daf f PAGI SECTCN fit Lt Procedures -E- 5/31/84 51 of 97 6.0 ( a TABLE 6.1 (Continued) f DESCRIPTION TYPE Skid ^ CHECK VALVE 4 SIZE POSITION RD1 V3 1" Exch. Column Closed LN-2 ! CU-203 Drain Ball Ball Open LN-2 ; RD1 V6 1" Skid Drain RD2 V1 1" Circ. Pump Suction LN-1 Line Drain Ball Closed i Ball Closed LN-1 RD2 V2 1" Heater Drain , Ball Closed LN-1
+
RD2 V3 1" Process Out. Drain Ball Closed LN-1 l RD2 V4 1" Surge Tank Drain ; RD2 V5 1" Coupon Holder LN-1 Drain Ball Closed RD2 V6 1" Chemical Injection LN-1 Ball Closed i ( Drain ' Check N/A LN-1 RD2 V7 1" Sample Sink Check LN-1 Sample Sink Drain Ball Open RD2 V8 1" , HTl V1 1/2" Hydrostatic Test Closed LN-1 Isolation Ball HT2 V1 1/2" Hydrostatic Test Closed LN-2 Isolation Ball e d* *
- i t
LONDON NUCLEAR
u ntciivs oave uct sect.o Sivu l .tv.s o 6.0 Procedures -E- 5/31/84 52 of 97 t TABLE 6.2 - MISCELLANEOUS DECONTAMINATION EQUIPMENT STATUS STATIC REFERENCE STATE Equipment Description Statu s , IX Column Charged with Resin [ CU-201/202/203 Circulating Pump Off CU-102 CU-104 Main Circuit Cooler Isolated Electric Heater Off CU-105 Filters Isolated CU-204/205 i CI-101/ Chemical Injection Vessel Isolated Nitrogen Bottle Surge Tank Charging System Connected and Isolated and Regulator i i k s .' ' l LONDON NUCLEAR
SECTCN TITLE p(vt$Os (FFECievt Oaf E Pact 6.0 Procedures -E- 5/31/84 53 of 97 TABLE 6.3 VALVE STATUS: SKID LN-4 ELECTRIC HEATER STATIC REFERENCE STATE Valve Size Description h Status CU10-V1 3* Bose Ivolation Ball Open CU10-V2 3" Bose Ido. - Skid 4 End Ball 6 pen CD10-V3 3" Process Inlet Ball Open CU10-V4 3" Heater (CU-401) Inlet Ball Open CU10-V5 1/2" Pressure Indicator (PI-401) Isolation Globe Open Cull-V1 3" Heater (CU-401) Outlet Ball Open Cull-V2 3" Heater (CU-401) Bypass Ball Closed
- Cull-V3 3" Process Outlet Ball Open Cull-V4 1/2" Pressure Indicator h -
CV10-V1 1/2" (PI-402) Isolation Process Vent Globe Globe Open Closed CV12-V1 1/2" Heater (CU-401) Vent Globe Closed RD10-V1 1" Heater (CU-401) Drain Ball Closed RD10-V2 1" Heater (CU-401) Drain Check Check --- RD10-V3 1" Drain Isolation Ball Locked /Open h RD10-V4 1" Vent Pot (CU-402) Drain Chack Check -- p RV10-V1 2" Heater (CU-401) Relief) Relief As Installed I l k
~-
( LONDON 64UCLEAR v ,,c- 3
--y y .,,,---~w-.r n -
T -e w=- - tmwe--*-----*'a------- - - - - - - -
*\
SECTION TITLt af viSCN EUECityt Dati Pact 6.0 Procedures - E- 5/31/84 54 of 97 l TABLE 6.4 l l VALVE' STATUS: TEMPORARY VALVES . STATIC REFERENCE STATE CHECK VALVE 6 SIZE DESCRIPTION TYPE POSITION ! L V1 3" RHR Return A - Ball Open Isolation Skid End V2 3" RHR Return B - Ball Open Isolation Skid End V3 3" RHR Return B - Ball Open Iso. Process End i V4 3" RHR Return A - Ball Open i Iso. Process End V5 3" RHR Supply Iso. Ball Open l Skid End V6 3" RWCU Iso. Skid End Ball Open ' V7 3" RWCU Iso. Process Ball Open End ( V8 3" RHR Supply Iso. - Ball Open Process End ' c V9 3" Recirc. Loop A Ball Open Suction V10 3" Recirc. Loop B Ball Open i Suction ! Vll 2" Recirc. Loop A Ball Closed Suction Vent V12 2" Recirc. Loop B Ball Closed , 7 Suction Vent i V13 2" Riser JP 1/2 Iso. Ball Open V14 2" Riser JP 3/4 Iso. Ball Open i V15 2" Riser JP 5/6 Ball Open , V16 2" Riser JP 7/8 Ball Open i V17 2" Riser JP 9/10 Ball Open e V18 2" Riser JP 11/12 Ball Open Vl9 2" Riser JP 13/14 Ball Open
- f. V20 2" Riser JP 15/16 Ball Open
..~- ;
LONDON NUCLEAR
l tint atviseo= <*rectivs oatt eact ! sect.o= 6.0 Procedures - E- 5/31/84 55 of 97 ; TABLE 6.4 continued I CHECK VALVE 6 SIZE DESCRIPTION TYPE POSITION V21 2" Riser JP 17/18 Ball Open V22 2" Riser JP 19/20 Ball Open V25 3" Manifold A Iso. Ball Open V26 3" Manifold B Iso. Ball Open V27 2" RWCU Vent Ball Closed V28 1" 'A' Manifold Drain Ball Closed ! V29 1" 'B' Manifold Drain Ball Closed i i b ( l I l l l l s .S ~ ~ l l , ! l l I i ( LONDON NUCLEAR
SECicN 1sTLE mEviSCN EFFECitvf DATE PAGE 6.0 Procedures - E- 5/31/84 56 of 97 l i TABLE 6.4.2 l RER RETURN LOOP 'A' GOINT ARRANGEMENT DATA SHEET . l JOINT ID COMPONENTS DATA SHEET COMPLIANCE REMARKS Initial Hookup ATy AT2 AT3 4T4 RER-R-A-01 X/ Valve V1 RER-R-A-02 Valve Vl/ , 50' Hose ( RER-R-A-03 50' Hose / X 50' Hose 1 RER-R-A-04 50' Hose / X Valve (V4) RER-R-A-05 Valve V4/ , RER 'A' r s ** ;
=.7
+
i
. LONDON NUCLEAR f
l
$tCTuoq ftTLE stivi5CN (FFECityt DATE PAGE 6.0 Procedures -E- 5/31/84 57 of 97 i
P TABLE 6.4.3 - RER RETURN LOOP 'B' JOINT ARRANGEMENT DATA SHEET , i JOINT ID COMPONENTS DATA SHEET COMPLIANCE REMARKS f Initial Bookup ATy AT2 AT3 AT4 j RER-R-B-01 X/ Valve V2 RER-R-B-02 Valve V2/ 50' Hose RER-R-B-03 50' Hose / , ( valve v3 RER-R-B-04 50' valve v3/ RER 'B' i i l l l
. I e
l i I LONDON NUCLEAR s
p(Vt$4QN (FFECTwt DATE pact 5ECTCN TITLE 6.0 Procedures - E- 5/31/84 58 of 97 TABLE 6.4.4 I RHR-SUCTION JOINT ARRANGEMENT DATA SHEET l COMPONENTS DATA SHEET COMPLIANCC REMARKS JOINT ID Initial Hookup ATy AT2 AT3 AT4 RER-S-01 X/ Valve V5 , f RER-S-02 Valve V5/ F 50' Hose l RER-S-03 50' Hose / X 50' Hose RER-S-04 50' Hose / l X Va} - 1 V8 RER-S-05 Valve Ns/ RER - Suction . I i l i e I ( LONDON NUCLEAR
- - -. %v. - ,, - - - - - - - - - - - , em.yc . , -.
f --- -,.e --,w .-m g ,,,e- ----wy e y -,--- -
SECTCN TITLE REvi$'ON EF8ECitvE DATE paGE
~
(. 6.0 Procedures -E- 5/31/84 59 of 97 TABLE 6.4.5 ' b JOINT ID COMPONENTS DATA SHEET COMPLIANCE REMARKS Initial Hookup ATy g2 M3 AT 4 IA-01 Valve CU3-V3 t IA-02 Valve CU3-V3/ 50' Hose ! IA-03 ' 50' hose / 50' hose j ( IA-04 50' hose / 5 50' hose IA-05 50' Hose / Valve CU3-V4 ' IA-06 Valve CU3-V4/ N6A nozzle l l i l r 1
%+
e t l ( e LONDON NUCLEAR I
SECT C*s flitt mE v@ON EFFECYevt DATE PAGE { 6.0 Procedures - E- 5/31/84 60 of 97 TABLE 6.4.6 NOZZLE N6B JOINT ARRANGEMENT DATA SHEET JOINT ID COMPONENTS DATA SHEET COMPLIANCE REMARKS Initial Hookup ATy $2 03 04 ? LB-01 X/ Valve CUl-V2 s LB-02 Valve CUl-V2/ 50' Hose LB-03 50' Hose / ( Valve CUl-V1 - LB-04 Valve CUl-V1
-/N6B Nozzle 5
7 $4 s m .3 - (
- LONDON NUCLEAR
?
ints at visio= t"ectivt oart act uci.o= 6.0 Procedures -E- 5/31/84 61 of 97 TABLE 6.4.7 ! RWCU JOINT ARRANGEMENT DATA SHEET JOINT ID COMPONENTS DATA SHEET COMPLIANCE REMARKS Initial Hookup ATy AT2 AT3 AT4 RWCU-01 X/ Valve V6 RNCU-02 Valve V6/ 50' hose RWCU-03 50' hose / , 50' hose RWCU-04 50' hose / 50' hose RWCU-05 50' hose / 50' hose RWCU-06 50' hose / 1 C0' hose , RWCU-07 50' hose / 50' hose RWCU-08 Valve V7 RWCU s .s. . . e e ( l LONDON NUCLEAR 1 i
atVi$@N (FFECTivt DATE PAGE ggcta tiggg 6.0 Procedures - E- 5/31/84 62 of 97 TABLE 6.4.8 N2A-N2B MANIFOLD AND JUMPER JOINT ARRANGEMENT DATA SHEET JOINT ID COMPONENTS DATA SHEET COMPLIANCE REMARKS Initial Bookup ATy $2 03 M4 NZA-01 Riser / Valve V17 NZA-02 Valve V17/ ! 20' Hose MFA-01 20' hose / l
'A' Manifold
( NEA-03 Riser / ' Valve V16 NEA-04 Riser /
. Valve V17 MFA-02 15' hose /
'A' Manifold j NEA-05 Riser /
! Valve V15 NZA-06 Valve V15/ 10' hose MFA-03 10' hose /
'A' Manifold NZA-07 Riser /
t Valve V14 NEA-08 Valse 14/ 15' hose MFA-04 15' hose /
'A' Manifold NZA-09 Riser /
s .5 - ~ Valve V13 Valve V13/ NEA-10 20' hose MFA-05 20' hose /
'A' Manifold NZB-01 Riser /
valve V22 ( LONDON NUCLEAR
m(vestON EFFECTIVE DATE PaGE 1 SECfiON IITLE ! 6.0 Procedures - E- 5/31/84 63 of 97 l , 1 TABLE 6.4.8 (Continued) l N2A-N2B MANIFOLD AND JUMPER JOINT ARRANGEMENT j DATA SHEET ' i h COMPONENTS DATA SHEET COMPLIANCE REMARKS j JOINT ID 6 Initial l Hookup ATy g2 03 04 l NEB-02 Valve V22/ 20' hose l MFB-01 20' hose / l i 'B' Manifold j NEB-03 Riser / valve V21 NZB-04 Valve V21/ 15' hose 1 i MFB-02 15' hose /'B' manifold t
-\Q' NZB-05 Riser /
valve V20 ' NEB-06 valve V20/ 10' hose MFB-03 10' Hose / , j
'B' manifold j
N2B-07 Riser / valve Vl9 Valve Vl9/ l N2B-08 l 15' hose ' MFB-04 15' hose / [ s 'B' manifold N2B-09 Riser / l Valve V18 N28-10 Valve V18/ 20' hose MFB-05 20' hose /
'B' manifold l MFA-J-06 'A' manifold /
Valve V25 MFA-3-I7 Valve V25/ : r 50' hose MFB-5-06 50' hose / . Valve V26 MFB-J-07 valve V26/
'B' manifold
( t e LONDON NUCLE.AA i _ _ . . ._____._._._._.__.,___,._, . _..- -.,,_,_... _ _ __.. ___ _ -__ _._,m _
- .. = -
I SEC1cm IIT L E PE viSCN (FFECitvf Daft PAGE r 6.0 Procedures - E- 5/31/84 64 of 97 TABLE 6.4.9 NlA-NlB JOINT ARRANGEMENT DATA SHEET ; JOINT ID COMPONENTS DATA SHEET COMPLIANCE REMARKS j i Initial Bookup gy g2 83 M4 i N1A-01 HlA/ Valve V9 N1A-02 Valve V9/ L 50' hose N1B-01 50' hose / Valve V10 N1B-02 Valve V10/ N1B r [ i d' i l i * \ i . ' LONDON NUCLEAR i
L p(veSiO*s EFFECTtvtDATE pact 5(CfIOes TITLE 6.0 Procedures - E- 5/31/84 65 of 97 ( TABLE 6.5 STATION INSTALLED VALVES SUCTION SIDE DECONTAMINATION STATUS Description Position Des n tion Recirculation Pump A Discharge Iso. Closed ' MO-53A MO-53B Recirculation Pump B Discharge Iso. Closed Recirculation A Suction Iso. Open MO-43A Open MO-43B - Recirculation B Suction Iso. Ring Header A Bypass Open MO-66A Ring Header B Bypass Open l MO-66B Ring Header A Cross-Tie Open MO-65A , Ring Header B Cross-Tie Open MO-65B Open POS-61B RHR Return B Isolation RHR Return A Isolation Open POS-81'A i RHR Supply Isolation Open f MO-10-18 ! Open [ M012-15 RWCU Suction Isolation . Open MAN 12-46 RWCU Suction Isolation i RWCU Supply Open MO-12-18 ! I Temporary A Suction Loop Valve Closed g._ . . : Temporary B Suction Loop Valve Closed ; f [ ( I LONDON NUCLEAR I
l I aco,so. urcenvc o.ta ..c.c secno nra i 6.0 Procedures - E- 5/31/84 66 of 97 g , i TABLE 6.6 STATION INSTALLED VALVES DISCHARGE SIDE DECONTAMINATION VALVE STATUS Valve Position Designation Description Recirculation Pump A Discharge Iso. Open MO-53A Recirculation Pump B Discharge Iso. Open M0-53B Recirculation Pump A Suction Isolation Closed MO-43A Recirculation Pump B Suction Isolation Closed M0-43B Open MO-66A Ring Header A Bypass Open MO-66B Ring Header B Bypass Open M0-65A Ring Header A Cross-Tie Open MO-65B Ring Header B Cross-Tie Open POS-81B RHR Return B Isolation Open POS-81A RHR Return A Isolation Open M0-10-18 RHR Supply Isolation Open M012-15 RWCU Suction Isolation Open MAN 12-46 RWCU Suction Isoir. tion Open MO-12-18 RWCU Supply Temporary A Suction Loop Valve closed Temporay B Suction Loop Valve Closed s .' ' l t b ( to . $ms l
i [ tifLE pt vision EFFECfivE Daft PAGE { 54C1CN 6.0 Procedures -E- 5/31/84 67 of 97 ! TABLE 6.7 ' REAGENT ADDITION CHECK SHEET i SYSTEM BEING DECONTAMINATED: > Chemical Conen Signature Time Date Type h f I ( e 9 f LONDON NUCLEAR
MClacq title My@Om EFFECTaYE DATE 8ME 6.0 ' Procedures -E- 5/31/84 68 of 97 : ( l l i TABLE 6.8 SAMPLING CHECK SHEET . l System Being Decontaminated: , Phase of Decontamination: Sample Quantity: : I Sample Sample No. Date Time Location Signature r l 1 i r t i e* i l ( LONDON NUCLEAR t i l i i
- - --- - - --..-- ,.-. u,,. , -- - - . , - , . . - - - - , ,,r,,,-
,- ...,--w, - - - - . - - - - ,. _ . . . - - , , , , - - , , - - , , _ - , ,
l p(ve$ EON EFFECTIVE DATE pact MCit0N istle 6.0 Procedures - E- 5/31/84 69 of 97 k-TABLE 6.9 RADIATION MONITORING CHECK SHEET l Comments to be Noted Where Necessary LOCATION ION INLET OUTLET SAMPLING EXCHANGE GENERAL DATE TIME HOSE HOSE AREA COLUMN (S) AREA SIGNATURE L
~~
e h LONDON NUCLEAR [
t I mEviscN EFFECTIVE DATE PAGE SECTc= 181LE 6.0 Procedures -E- 5/31/84 70 of 97
- r 1 i TABLE 6.10 r,
OPERATIONS LOG SHEET ! l PI-101 PI-102 PI-103 PI-104 TI-101 FI-101 FI-202 DATE TIME (psig ) (psig) (psig) (psig) ( F) (GPM) (GPM) i i 8 i l t 6 9 I ' 1 l l LONDON NUCLEAR l 1
EFFECisvt DATE paGE mEviseON SECTCN TITLE 6.0 Procedures - E- 5/31/84 J1 of 97 i ( TABLE 6.12 { IX (ION EXCHANGE) RESIN LOADING COLUMN SIGN-OFF IX RESIN LN/GE TYPE NUMBER DATE TIME BATCH LOT I
\e I>
( LONDON NUCLEAR
i FIGURE 6.11 -E- PAGE 72 of 97 i OP-001' . M2 6.11 . I' CHIMISTRY MONI*IORING SCHIDb2. , u . . i s . Decontamination ,
* "" " IRD-101A Readings and LND-101A Addition tamination Analyses .
.. Removal Step ,* ..
- rirst
. . 2 h. .
pH and analyses - 30-min. 30-min or 1-h conductivi'ty
- During the first ,, required intervals, intervals two hours or the.
decontaminati,on,* , more frequent; Temperature ,
* . 1-h -
~
O analysis may be . performed if 5 intervals *
- conditions permit. analyse,s C ,
, Dissolved oxygen as required
** ' toc will be after'N N '
measured when additied4 , conductivity . during cleanup - analyses , falls below 200 Reagent _ unho/cm and at .
- as required -
one hour interval: afterwards. . *
. analyses Crud ** .
as required , Dissolved analyses
~
30 '-ein 30-min or 1-h y hetals .
. Dissolved as required intervals intervals radionuclides
- e s.
- s. - ' .
l . 1 ) . as required" ( Total Organic ,
, c Carbon .-
- 1
af v@ON 18FECTevt DATE pact giction letts 6.0 Procedures -E- 5/31/84 73 of 97 TABLE 6.13 DECOffrAMINATION RADIATION LEVEL READINGS At End of Decontamination Initial Final Point Point Location Reading Reading DF (mR/h) (mR/h) Weighted Harmonic Mean
- all points
- suction
- discharge r- .
t LON00N NUCLDA
l p(yg$1Q98 (IF(CIlvt DATE PAGE SECteON fif(( 6.0 Procedures - E- 5/31/84 74 of 97 ( 6.18 CHEMICAL AND RADIOCHEMICAL MONITORING DURING DECONTAMINATION 6.18.1 Parameters to be Monitored Monitor the fol. lowing parameters during the decontamination: , a) Gross Activity ' b) Dissolved Radionuclides c) Dissolved Metals d) Conductivity and pH , j e) LN2 geagent Analysis f) Fe to Total Iron Ratio i g) Crud Sampling h) Hydrazine ! i) Dissolved Oxygen-j) Total Organic Carbon (TOC) ,t The parameters are listed approximately in the descending ! order of their importance and frequency in monitoring. , With the exception of LN reagent analysis, all parameters i are usually routinely monitored at nuclear power stations i {. as part of normal operations. j Install e n-active coupons in the equipment autoclave to de- l termine corrosion rates. Install active coupons, cut from a reactor artifact (pipe, flange, gasket etc.), to deter- : mine decontamination factors. Inactive coupons for Peach Bottom will be stainless steels 304, 316L and carbon steel. ! 6.19 Required Chemi'cals i 6.19.1 Concentrated Acids and Bases (Suppli.ed by station) t Ammonium hydroxide NH,OH ! Hydrochloric acid HCI l Nitric acid , HNO Sulphuric acid H82 4 - s.- i LONDON NUCLEAR
(FFECtevt Oaft paGE m(wi5soes SECToes TITLE 6.0 Procedures -E- 5/31/84 75 of 97 6.19.2 Organic solvents (Supplied by Station) Methanol (OR Ethanol) CH3 0H (CH 3CH 2OH) , 6.19.3 Other Reagents (Supplied by LN) Antimony (III) oxide Sb 230 Buf fers (pH 4, 7 and 10 ) CaCl Calcium chloride (or Calcium nitrate [Ca(ho3 )2 I Chemet Test Kit (Oxygen low range) 0-100 ppb CH p-dimethylaminobenzaldehyde 9 y NO Ethylenediamine tetra acetic acid C10 16"208 (sodium salts may be used) Hydrazine hydrochloride N _y H,.2 hcl Hydroxylamine hydrochloride NH2 OH. hcl Iron (II) ammonium sulphate Fe(NH 4)2(SO4 )2 6H O Iron (III) sulphate Fe (SO4)3 (chloride or nitrate salts may be substitut C H d) o-phenanthroline g 81 KCI Potassium chloride KMnO Potassium permanganate chb ) Salicylic acid NdCHO 2 Sodium acetate Snc 2 Tin (II) chloride i All chemicals supplied by LN under 6.19.3 will be removed by LN upon completion of the job. 6.19.4 Metal Standard Solutions (Supplied by Station) Metal solutions (1000 ug/ml) are required for the following ions (Fe, Ni, Cr, Er, Mn, Cu). s. LoN0oM NUCLEAR
p(vissom (FFECrivt Oaf t , AGE 5(cts 0N fiTLE 6.0 Procedures -E- 5/31/84 76 of 97 i k , 6.20 Analysis 6.20.1 Radionuclide Analysis Radionuclides will be determined by PECo using gamma spectrophotometry. Preferred equipment requirements are a multi-channel analyzer of at least 1024 channels coupled to a GeLi detector. NaI(Tl) detector could be used if re-quired, but resolution is poorer. The energy range of main interest is 0.1 to 2.0 Mev. Computer analysis involving peak identification and printout of concentrations is high-ly desirable. Equipment of this type -is now standard at most nuclear power plants and was used during previous de-contaminations at Peachbottom (1982 and 1983). This in-cludes a GeLi detector. Previous decontamination on Unit 2 RWCU system showed the following major radionuclides: , Radionuclide . Maior Emissions (MEV) I 0.324 l cr-51 Mn-54 0.835 . Co-58 0.81 Co-60 1.17, 1.33 1.11 h Zn-65 Cs-137 may also be present in minor quantities. Its emis- ( sions at 0.662 Mev will also be measured to meet 10CFR61 requirements. I 6.20.2 Direct Current Plasma Jet Analyser I Analyze following elements, Fe, Ni, Cr, Mn, Zn, Cu, simul- ! taneously, using the direct current plasma- jet analyzer. i I h l \ i
- l i
f LONDON NUCLEAR i l l i i \ l _ . . _ _ _ ___ ,-_ _ _ __ _ . _ _ . _ . _ _ _ . _ _ _ _ __ ._ _ _______________a
(FFEC1evt omit pact at w+0m SE CisO*e fiftt 6.0 Procedures ,
- E- 5/31/84 77 of 97 6.20.3 Conductivity A multi-range conductivity meter and cell A sparespanning the conductiv-range 1 umhojco 10,000 umho is required.
ity cell is ' recommended. / The instriment sho ld be checked using sthndard potassium chloride solutions. Specific conductances are given below:
~
~1 cm -1 Grams kcl /kg n. ohm of Solution K[C 18- 2SEC 71.1352 0.09784 0.11134 7.4191 0.01117 0.01286 0.7453 0.001221 0.001409 6.20.4 pH ,
Sensing A typical laboratory pH meter (0-14) is required. electrodes should contain automatic temperature compensa- J
~ tion. Readout of solution temperature is a desirable
( feature. Instrument should be calibrated using standaNd buffer solu-tions (pH 4, 7, and 10 ) . / 6.20.5 Ultraviolet / Visible Spectrophotometer
/,En UV/VIS spectrophotometer is used to measure the
,absorbance of the following complexes:
Iron (II) and o-phenanthroline at 518 nm Hydrazine and p-dimethylaminobonzaldehyde at 458 nm A one (1) em cell is required but larger cells mayAbsorption be used. A flow through cell is a desirable feature. maxima should be checked on the instrument in case of possi-ble errors in wavelength settings.
- p. .
e e i 1 i LoN0oM NUCLEAR O
887tGfivt Daft paGt A( Vi&CN 6(GTQN f f fLE 6.0 Procedures - E- 5/31/84 78 of 97 6.20.6 Total organic Carbon Analyzer A total organic carbon (TOC) analyzer will be used to mea-sure reagent removal during cleanup at the end of the decontamination. 6.20.7 General Laboratory Equipment The following general laboratory support equipment is required: a) Weighing facility to+0.1 mg (or better). b) Supply of dominerallied water c) Supply of water and drainage to active sumps
- 4) stirrers and hot plates
- 5) Filtration equipment
- 6) Fume hood 6.21 Laboratory Familiarization
- The thems two London Nuclear chemists (LNDC) shall familiarize elv e s with the Peach Bottom laboratory.
( Familiarization shall consist of the followings a) Safety procedures for lab (fire, showers, eyewash, chemical cleanup kits etc.). i i LONDON NUCLEAR
af viso. (**tcrivr oast pact g sacros tiitt 6.0 Procedures E- 5/31/84 79 of 97 ( b) Radiological procedures for lab (radiological zoning, radioactive waste handling procedures, storage of ac- ; tive samples. c) Layout and storage of glassware and miscellaneous equipment (beakers, flasks, volumetrics, pipettes, ; kimwipes, marking pencils, weighing boats etc.). d) Operation and location of common laboratory equipment ,
.(balances , stirrers , fume' hoods etc. ) . {
Review complete. __ , LNDC/PEC. l a 6.22 Analytical Equipment Familiarization s The selves twowith London' the Peach NuclearBottom chemistsanalytical shall familiarize equipment. them- ; f- Familiarization will be complete when the chemists can oper-ate the following equipment by themselves. !
- 1) Cond E:tivity Meter ,
- 2) pH Meter LNDC/PECo I
EQUIPMENT FAMILIARIZATION SHOULD TAKE *IMO TO FOUR HOURS.
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MEvtseOh E8FECTivE CATE PAGE HCTtON f6TLE 6.0 Procedures -E- 5/31/84 80 of 97 ( 6 6.23 Preparation of Analytical Solutions I LN shall prepare the following solutions. l 6.23.1 Reagents i Required accuracy of these reagents is + 10%. Unless other- i wise specified, all reagents'are in water. ; a) o-phenanthroline ; (0.5% wt/Vol in menthanol) b) Sodium acetate (2 M) c) Hydroxylamine hydrochloride (10% wt/vol) j d) Salicylic acid (24 wt/vol in methanol) e) Calcium chloride (or calcium nitrate) (0.05 M) [ Sulphuric acid f) ,!l (1 M) g) p-dimethylaminobenzaldehyde 44 g to 200 ml CH OH and 20 ml concentrated hcl)3 THIS COMPOUND IS LIGHT SENSITIVE AND STEPS MUST BE TAK-EN TO PROTECT IT FROM THE LIGHT. h) hcl (1% conc. acid in water) l l i) Descaling solution for stainless steel 304 (Clarke's solution) (1 L 35% hcl 20.0 g Sb 903 50.0 g SnCl 2 ! s..
- s. Preparation of analytical solutions complete.
LNDC/PECo i l l LONDON NUCLEAR
pact a(vissoas EF8ECTivt DATE SECT Os fifLE Procedures -E- 5/31/84 81 of 97 t 6.0 6.23.2 Standards , these standards is i 2%. During the Required decontamination, accuracy ofparameter trends are more important than l absolute values. a) EDTA (0.02% wt/Vol) b) Fe # ; (0.02%) c) KMnO - (0.0IN) i DEPENDING ON REAGENT PURITY, THE FORMALITY MAY BE , STANDARDIZED AGAINST SODIUM OXALATE OR OXALIC ACID. !
. d) Ferrous ammonium sulphate 0.1 LN bl
{ e) Metals ions for atomic absorption analysis , To minimize the number of standard solutions, the stan- ' dards can contain more than one metal ion. t uq/1 Solution Iron 10,50,100,150 0.1% LND-101A , Nickel 10,25,50 0.1% LND-101A Chromium 10,25,50 0.1% LND-101A Copper 5,10,25 0.1% LND-101 A Manganese 5,10,25 0.1% LND-101A 5,10,25 0.1% LND-101A -f s,, Zinc t
+
s. f) Hydrazine hydrochloride (if required) i (100 mg/l N H24 in it hcl) , Preparation of all standards complete. LNDC/PECo i f ! LONDON NUCLEAR
f SECIeON IIILE R(VI$@d (FFICIlWC DAIC PAG ( 6.0 Procedures -E- 5/31/84 82 of 97 ( i 6.24 Sampling Method and Schedule j The sampling points on the decontamination skids are con-nected to the ion exchange column outlet (usually called *
"IX out") and to a process line to sample the bulk recircu-lating reagent (usually called "IX in"). The bulk sample f
- provides infermation on the process parameters - pH, dis- i
- solved metals, and dissolved radionuclides, which indicate -
the efficiency of the decontamination process. The after l ion exchange sample provides information on the efficiency i of the ion exchange column in removing dissolved metals and t radionuclides, anC is used to determine column saturation ; or " breakthrough". i A recommended sampling schedule is given in Table 6.11. i The "as required" frequency will be at the discretion of l the LN chemist conducting the decontamination or as requested by PEco chemistry staff or the GE , Engineer / Manager. Most samples will be 250 mL. A ' one-litre sample is required for a crud analysis. All , samples will be clearly labeled to indicate the sampling i date, time, and location of sampling. . Due to the potentially high specific activity of the sam-( ples during the decontamination: i i a) Extra care is required in handling solutions; appropri-ate protective clothing should be worn at all times. b) All samples should be stored in a suitable shielded ar- . ea when the analyses are completed. , 6.25 Analytical Procedures ! The following procedures are used during a decontamination. All results are: a) Logged on a laboratory work sheet and initialed by the chemist performing the work. l b) Results on laboratory work sheet are transferred to c- the decontamination chemistry log book, which is kept in an inactive area. The Jog and work sheet will be i checked and initialed. The work sheets may be de- l stroyed at the end of the decontamination. j c) Plotted on graph paper to show trends. l LONDON NUCLEAR
l t SECTcq 7:Ttt 81E vtS80N EFFECTvt DATE PAGE f 6.0 Procedures -E- 5/31/84 83 of 97 r l . 6.25.1 Gross Activity All filled sample bottles will be checked for grcss gamma f activity at the decontamination skid immediately after sam- ; pling. A standard gamma (or Beta-gamma) survey meter will ' be used in, if available, a shielded location such as a lead castel. This analysis will be used as the first indi- ! cation of activity breakthrough on the cation resin column. l 6.25.2 Dissolved Radionuclide Analysis Dissolved radionuclide analyses will be performed on both bulk and after ion exchange column samples. Samples.sent to the counting laboratory will be diluted as necessary and i analyzed by a multi-channel gamma spectrophotometer : equipped with a GeLi detector, or equivalent. l
\
Radionuclide analysis is one of the more important param- i eters determined and is used to monitor the progress of the : decontamination. For these reasons, the samples should be analyzed as soon as possible af ter arriving in the sample reception area. _ j f All computer printouts of radionuclides must be kept. 6.25.3 Dissolved Metals by Direct Current Plasma Jet Analyzer l Reagents i Analytical standards: l Dissolved metals analysis will be performed on both the bulk and af ter ion exchange column samples during the oxide ; dissolution phase. Other samples will be analyzed on an !
"as required" basis. Simultaneous analysis of iron, I chromium, nickel, manganese, zine and copper will be done. ]
Dissolved iron is a critical process parameter and the anal- ! , ysis should be performed as quickly as possible. ] 1 j ,% . - 1 0 m. l ( < e LONDON NUCLEAR I
i sacr e. tivts na viso. trascievr oatt ;nct Procedures 6.0 -E- 5/31/84 84 of 97 i 6.25.4 Conductivity and pH Measurer.ent Reagents l The electrical conductivity and pH will be measured'for each sample. These measurements will be preformed on Station laboratory calibrated equipment. ' i Temperature will be recorded on samples during measurements and corrections made if required. a) Buffers pH4, 7 and 10 j b) Conductivity standards, i 6.25.5 LN Reagent Analysis i 1 a) EDTA Analysis ; Reagents ;
- 1) 24 salle gic acid in methanol !
- 2) 0.02% Fe solution 3)
{ 0.02% EIrrA solution Procedure
- 1) analyze sample for iron III concentration ;
\
- 2) take a 25 mL aliquot sample
- 3) add 1 mL salicylic acid solution If the resulting solution is colorless, follow item (a) below; if the solution is colored (vi-olet), follow item (b) below.
a) titrate the sample with the standard iron III solution until a violet color appears I one mole EDTA reacts with one mole iron III, EDTA concentration equals origir.al iron III con-g .- centration plus iron III concentration in titer 0 l ( ' I LONDON NUCLEAR ,
l at vissON EFFECivvE Daf t paGE , SECTaON tiftt 6.0 Procedures -E- 5/31/84 85 of 97 I , b) titrate the sample with the standard EDTA solu-tion until the color changes from violet to i colorless. Original EDTA concentration equals iron III con-centration less EDTA concentration added. ! b) Oxalate Analysis j Reagents
- 1) 0.05 M CaCl
- 2) dilute NH 40k :
- 3) 1 M H SO
- 4) 0.01hKknO 4 -
Procedure
- 1) take 25 mL aliquot of sample
- 2) add 50 mL of 0.05 M calcium chloride
- 3) adjust pH to 7.5-8.0 with NH 0H 4
- 4) let stand 10-15 minutes t
- 5) filter solution .
- 6) wash filter cake with water
- 7) dissolve filter cake in 1 M H SO4 2
- 8) heat solution to at least 60 C t
- 9) titrate with 0.OlN KMnO, until a pink endpoint '
persists for at least 30 sdconds 10 ) determine the oxalate concentration from a previ- ! ously determined calibration curve or mL of 0.OlN KMnO 4 reacts with 0.63 mg H 224 C 0 .2H 20. , i l LONDON NUCLEAR l l _ . - _ . _ , . . _ _ _ . . _ _ _ _ . - . _ _ _ - . . . _ _ _ _ _ . . . . _ , _ . _ . _ , . . , , - - _ . _ _ _ . . . _ _ , . . - -, , , . _
ettviS*0N ff FECTivt DATE PAGE MCirom fift( 6.0 Procedures - E- 5/31/84 86 of 97 k 6.25.6 Fe
- to Total Iron Ratio First Fe + is measured us gg o-phenanthroline. Next all iron is reduced to the Fe state and total iron is mea-sured using o-phenanthroline.
+
Fe concentration is the difference between the two values. Feb Analysis Reagents 0.5% o-phrenantroline in CH3 OH Procedure a) Accurately pipette an aliquot (of sample solution con-taining 10 to 100 ug of iron (usually 1 mL of strip-ping solution). b) Add a few millilitres of distilled water and 1 mL of 0.5 percent'o-phenanthroline, to a 25 mL volumetric flask. c) Mix and makeup to mark with distilled water, and deter-mine the optical density at 518 nm. d) Wait 5-10 minutes for color development before making determination. I Total Iron Analysis j Total iron is determined by reducing iron III to iron II with hydroxylamine hydrochloride and anaylzing for iron II. Reagents , l a) 10 wtt hydroxylamine hydrochloride (NH OH. 2 HCL). l > 2 molar sodium acetate. ! j) l b ! ( ! i-
. i
. LONDON NUCLEAR I
l l
.Y SECiioN fifLE p(v>SsON (FFECfivt DATE pact 6.0 Procedures - E- 5/31/84 87 of 97 i l
c) 0.5 percent o-phenanthroline (in CH 0H). 3 Procedure : i a) Accurately pipette an aliquot sample solution contain- ' ing 10 to 100 ug of iron into a 25 mL volumetric flask (usually 1 mL of stripping solution). i b) .i Add a few millilitres of distilled water and 2 mL of 10 percent hydrox1ylamine hydrochloride. ! c) Adjust the volume to approximately 10 mL with dis-tilled water and adjust the pH to between 3 and 6 by j adding 2._mL of .2 molar sodium acetate. i d) Mix and let stand five to 10 minutes, then add 1 mL of ; o-phenanthroline, i e) Makeup to mark with distilled water, mix and wait 5 to ' 10 minutes for color development and determine the op- i tical density at 518 nm. . I ! IF THE ORIGIANL SAMPLE SOLUTION IS COLORED, READ THE l
- SAMPLE AGAINST A BLANK CONSISTING OF THE SAMPLE, PLUS ,
t REAGENTS, LESS O-PHENANTHROLINE. ! IF SAMPLE SOLUTION IS COLORLESS, A BLANK MAY CONSIST , OF WATER, PLUS REAGENTS, PLUS O-PHENANTHROLINE. ; 6.25.7 Crud Sampling i Water samples will be taken both upstream and downstream of the ion exchange column as per schedule given in Table 6.11. ' Selected water samples will be filtered in the laboratory using 0.45-micron filter papers. A standard volume be-tween 500 and 100 mL will be filtered through two identical l filter papers back-to-back. The first will retain the crud and the second is to be used as a blank correction for i s.%reig h t loss. If significant crud is present (greater than 0.5 mg/1), it will be analyzed for weight, specific and gross gamma activity, and elemental composition. 4
. (
I LONDON NUCLEAR
i r 6ECipOm UTLE RE vissON EFFECitvt OAYE paGE ! 6.0 Procedures -E- 5/31/84 88 of 97 k All crud filtrates will be analyzed for dissolved metals , and dissolved radionuclides. t i 6.25.8 Hydrazine (for passivation treatment only) Reagents j a) 1000 mg/L N 24 H standard in 1% hcl b) 2% p-dimethylaminobenzaldehyde in methanol-hcl i Procedure l a) The 100 mg/L standard is diluted with 1% concentrated i BC1 in water to give the followings standards: , 10 mg/L, 25 mg/L, 50 mg/L, 100 mg/L. b) The sample is added as soon as possible to a distilled I water solution containing 1% concentrated hcl. This i dilution step will bring the concentration within the limits of the standards. ! c) Add indicator in the ratio of 1 mL of indicator to 5 ' mL of standard or diluted unknown. Let stand for a ' minimum of 10 minutes, but not more than 100 minutes. The solutions are analyzed in a spectrophotometer at . 458 nm. The blank used is 1 mL of indicator in 5 mL ! of 14 hcl. l 6.25.9 Dissolved Oxygen Prior to reagent addition, hydrazine will be added to the i coolant to remove dissolved oxygen and to initiate reducing conditions. An oxygen analysis will be performed after i hydrazine addition, but before the LND-101A addition to en- < sure less than 100 ppb 0 9 present. A colorimetric method ; such as the chemet dissoIved oxygen test can be used for ; these measurements. THE CHEMET METHOD CANNOT BE USED AFTER LND-101A RE-y AGElfr ADDITION. l ( LONDON NUCLEAR 1 l
SE CisO*e T'fLE mE visiO*e EFFECTlvt Daft pact 6.0 Procedures -E- 5/31/84 89 of 97 ( , If the Station has reagents and equipment setup for dissolved oxygen by other means (i.e. such as iodometric, indigo carmine etc.) the normal Station test procedure may be substituted for the Chemet method. - 6.25.10 Coupon Procedures Coupons (1010 carbon steel 304, 316L stainless steel) will be stored in a dessirator or sealed container be-fore use. All coupon handling must be done using gloves. Ynactive Coupons i a) All coupons must be weighed and measured before installation. LNDC/PECo b) A control set of coupons must be kept. f LNDC/PECo c) Following decontamination, all coupons will be exam-1 ined and descaled as required. Reagent Used: Clarke's solution item (i) of 9.6.1 Descaling solution for stainless steel 304 l t Procedure
- 1) at ambient temperature, insert 304 stainless steel :
coupons for up to 30 seconds or until scale is
- removed
- 2) rinse and dry ,
- 3) perform a blank correction on control specimens l
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SECTIOg TITLE se(vss#oes (FF(CYevt Oatt pact 6.0 Procedures -E- 5/31/84 90 of 97 ( d) All coupons will be weighed af ter decontamination. e) Coupons may be gamma scanned and counted after decon-tamination to note any buildpp of activity. f) ' Corrosion rate will be calculated using the formula: Corrosion Rate (um/h) = 10 M tpA M= weight lost by coupon during decogtamination p= density of coupon material jg cm ) A= surface area of coupons (cm ) t= time coupon exposed to reducing chemistry in hours For stainless steel 304: p= 7.94 gem'3 Radioactive Coupons a) Radioactive coupons will be both gamma scanned and gross counted before decontamination. Scanning counting and geometries and time must be noted. LNDC/PECo b) Af ter decontamination, radioactive coupons will be gamma scanned and counted in the same geometry. LNDC/PECo i 4 'I LONDON NUCLEAR
tittg sig yes.oes EFFECisvt Daft PAGE MCie0ee 6.0 Procedures -E- 5/31/84 91 of 97 c) Decontamination factor (DF) will be calculated for each coupon. DF = Radioactivity Before Decontamination Radioactivity After Decontamination LNDC/PECo 6.26 Decontamination Termination Decision The termination of a decontamination is a judgement de-cision which is made jointly by the PEco, GE Engineer / Manager and LN. The following are all possible imputs to that decisions a) Decontamination has met required radiation field re-duction targets. b) chemical and radiological indications that the decon is essentially complete. Some indications of this are significant reduction in radionuclide levels in f - solution and in radioactivity removal rates
- - reduction in radiation fields to background levels c) Corrosion indications that base metal attack may be occurring. Some indications of this are:
, increases in metal ion cor.eentration
- changes in Fe
- to total iron ratio d) Project scheduling may dictate terminating the decon at a certain point. After a DF of 3 to 5 is ob-tained, PECO or GE Engineer / Manager may wish to pro-coed with other work rather than continue longer with the decontamination and get a higher DF.
# e) Operation factors (such as LW or Station equipment performance, need to change resin etc.) may have an impact on the termination decision, particularly af-ter the DF has risen to 3 to 5.
LoN0oM NUCLsAA
ucro. rme u m.o= tretcme o re ..cc 6.0 Procedures - E- 5/31/84 92 of 97 , 6.27 SAFETY, DOSE CONTROL AND RADIATION MONITORING f 6.27.1 (:eneral This section details the procedures required to: a) Maintain a safe work environment throughout the decontamination. l l b) Access the net effect of the decontamination on the recirculation piping, RHR return and supply ( segments and RWCU system. c) Monitor and control personnel dose expenditure. d) Contamination control. I' 6.27.2 General Safety Procedures
- A safe work environment is maintained by regular in-spection of all work areas by LN to ensure all unneces-
-sary hazards have been eliminated. All personnel must i C be aware of the following:
a) Proper clothing to be worn in plant such as hard hats, safety glasses and shoes. .
) b) Knowledge of station emergency procedures for the working area.
c) Response and notification requirements to any ab-normal equipment operation (see Section 11.0). [ I d) Maintenance of a clean work area. , e) Minimize personnel traffic through work area. f) Instructions concerning plant procedures and gen-eral good practices, as presented in the " General i ) Employee Training", shall be followed. u ** s t O r I I LONDON NUCLEAR i '
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l SECisO's fifLE fatvisso+e EFFECfivt DATE PAGE l 6.0 Procedures - E- 5/31/84 93 of 97 t g) Follow all instructions while handling hazardous materials, h) Keep personnel informed of potential hazards that I may be present during the decontamination. l
?
i 6.28 Radiation Field Monitorinq ! In order to assess the effectiveness of the CAN-DSCON process, contact radiation field readings will be tak- i en at various locations inside and outside of the dry- i well area both before and after the decontamination. ! 6.28.1 Instrumentation setup Place Gamma meter (s) strategically in the decontamina- , tion system, in order to monitor the radiation levels throughout the decontamination, as follows: a) Place a remote probe between the ion exchange col- > umns, behind the shield wall and located to read p- at the mid-section of the columns. The probe ; T used must have a meter range of 0 to 100 R/hr. ! LN will assist during installation to ensure prop- l er location of the probe. The meter must be lo- l' cated in a readily accessible, low dose location. b) Minimize personnel dose b'y placing at least two ; Gamma meters with remote probes at the most active-on-contact spots. Typically, the } recirculation pump bowls, ringheader and risers are ideal locations for monitoring the radiation 1 fields. , t Location of the probes will be determined at ; site, af ter the initial radiation survey has been taken. c) Monitor the decontamination equipment for local-ised hot spots and recorded in Table 6.9 to en- , g ., sure personnel are aware of high dose areas. j i
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l MCison teTLE pt v@Om t'FECtevt Oaft paGE
! 6.0 Procedures - E- 5/31/84 94 of 97 i
d) Monitor the decontamination flow path lines ini- l tially 8 to 10 hours after injecting chemical, , then regularly every 2 hours. The "*" asterisk I points shown in Figure 6.2 are used to give a gen-eral estimat e of how the decontamination is prog- i ressing. Localized hot spots may develop on the l decontamination equipment. All data must be re-corded in Table 6.9 and personnel made aware of i high dose areas. , i i e) As the regeneration phase of the decontamination reaches completion, take a general survey of 8 to 10 points to give a gross estimate of the DF achieved and to ensure all the " hot spots" have i been removed. Continue the decontamination on ' the recirculation system piping until the hot spots are reduced as much as possible. This may [ be achieved by adjusting flow rates through pipe ' sections as instructed by the LN. i 6.28.2 Initial Radiation Survey j l: a) Take the initial radiation survey immediately af- l ter the system leak test has been completed (see Section 6.9.3). b) Drywell entry by qualified personnel equipped with the Eberline E-530N meter and shielded probe. ! 4 1. c) Check meter battery operation and calibration da- ! ta taken. [ d) Record information on Radiation Survey Map, I- , Figure 6.2 ( protected in plastic) at the predes- h
- j. ignated points. F e) Upon completion, transfer data points to Table
- s.'- 6.13, Decontamination Radiation Level Readings, and are kept as an official record.
LONDON NUCLEAR
- - , . , - - , - . . - , , , - , , - . - - - . . , . . , _ - - - . _ _ , , .,,.,_.-.--,.n.n ._.yn,.-,w,_.,,,._ mwm, ,,,,,,.,,--w--,--wn,,ne,--
t MC1ces TITLE atvisioes EfftCTwtDatt pact (- 6.0 Procedures - E- 5/31/84 95 of 97 l l [ 6.28.3 Radiation Monitoring 1 a) Throughout the decontamination, installed remote probes are read hourly and recorded on the f Radiation Monitoring Check Sheet, Table 6.9. This will determine the effectiveness of the process during operation. 6.28.4 Final Radiation Survey a) Take the final radiation survey af ter the reagent removal step has been completed (Section 6.13.7) prior to draining the system. b) Use qualliied personnel to enter drywell area ! with the shielded probe and Eberline E-530N I meter. > l c) check meter battery operation and calibration date. [ d) Record date on the Radiation Survey Map, Figure ! ( 6.13 (protected in plastic) at the predesignated I points. l l e) Transfer date, upon completion, to Table 6.13 and l are kept as an official record. 6.28.5 Evaluation of Decontamination Factors ! London Nuclear determines the Decontamination Factors l (DFs) by using the Weighted Harmonic Mean (WHM) meth-od. The WHM is simply the total sum of the "before" ! readings divided by the total sum of the "after" read- i ings. If discrepancies are encountered such that one - or two points influence the end result unrealistically a different approach is used. This avoids giving un- , due weight to those points having low DFs. A WHM DF : will now be calculated for each of several areas or !' components throughout the system being contaminated. i : I i i e LoN0oN NUCLE.AR
SECT e fift( p(vig@e (FF(Cfiv( Daft PAG ( 6.0 Procedures -E- 5/31/84 96 of 97 For a typical recirculation system, these might be: re-circulation risers, ring headers, pump area, and main piping. For each of these areas, an average (total di-vided by number of points) initial and final readings would be calculated and the DF calculated by dividing the average of the initial readings by the average of the final readings. Calculate the overall DF by taking a single average of these before and after readings and dividing the aver-age before by the average after. . 6.29 Personnel Dose and Contamination Control 6.29.1 Personnel dose is controlled in the following manners a) All LN staf f members are to wear a TLD supplied by LN, TLD and pencil chamber supplied by Station. b) Strive for ALARA at all times. c) Routinely check for changing radiation levels around the decontamination equipment. d) Review radiation survey data sheets taken by HP assigned to area. 6.29.2 All LN staf f entering the radiation areas shall read and understand the RWP associated with the decontamina-tion. All necessary protective clothing and dosimetry requirements, as well as special instructions shall be described and followed. A good understanding of the latest survey data will ba helpful in minimizing per-sonnel exposures. Any questions on the requirements or special concerns should be resolved with a Station health physics representative, s , e l l LoN0oM NUCLEAR wesmas __ _ . _ _ . . _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
H C f sO** fifLE at v$0*s (88tCfivt Daf t pact ( 6.0 Procedures -E- 5/31/84 97 of 97 6.29.3 Carry out personnel contamination control out in the following manners a) The required protective clothing is worn as spec-ified on the Station RWP's. b) Minimize contact with the decontamination equip-ment. valve manipulation and sampling are the on-ly occasions normally requiring direct contact. c) Ensure all spillages are properly cleaned up. ( LONDON NUCLEAR
Section: R2 vision: Effective Page: ' Date: London ' OP-001 - E- 5/31/84 97-A Nuclear. m ie PROJECT OPERATING APPENDIX A PROCEDURES i ABNORMAL OPERATIONS b I l [ l f P
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r i r i MCT*0= TsTLE mEwmom EF'ECYevt Oaf t pact t OP-001 Abnormal Operations - E- 5/31/84 97A l k D-23 f i l APPENDIX A ABNORMAL OPERATIONS i i
- The following sections outline potentially abnormal oper-ating conditions which could occur during the CAN-DECON [
i application. Below is a listing of operator response re- 6 quired to ensure personnel safety, to prevent further ! damage to system components, and/or to permit continued ! saf e system operation. The information is summarized in ; Table 11-1. {
.1 Loss of Temperature Control a) Failure to control Rising Temperature f
This could* occur should the heater temperature con- [ troller (CU-204 or TC-401).. fall to de-energize. (" Should the process temperature continue to rise, the LN operator.would manually shutoff the heaters. l A high temperature cut out switch (CU-203 ,or i
. TSH-401) will also shutdown the heater at 300 F. i The LN operators are able to run the heaters manual- {
ly with no detrimental effects on the decontamination. j b) Failure to Maintain Temperature l l The failure to maintain temperature could be the re-sult of: !
- 1) Inadequate power supply l
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- .- l
! LONDON NUCLEAR f 1 i
HCTsoes titti et v$ose isatCitytOatt pact t OP-001 Abnormal Operations -E- 5/31/84 97A
- 2) Failure of temperature controller (CU-204, TC-401), or an inadequate power supply would be detected during pre-application testing. This would be corrected by the appropriate support personnel. Failure of the temperature control-lors would be handled as in 11.1. by operating the heaters manually. Failure of the 300 Kw LN-4 heater elements would require the backup 300 KW LN-5 heater skid to be shipped. The 150 KW geater will maintain system temperature at 200 F while the 300 KW LN-5 heater is shipped and connected to the system. This would allow the decontamination to proceed out at a slower dissolution rate.
Failure of the 150 KW heater would slow down the heatup rater however, process temperature can be maintained at 250 F using the 300 KW heater alone. Spare elements for the 150 KW heater are readily available.
- 3) Failure of heater elements.
(
.l.1 Beater Isolate / Drain Procedure a) Heater CU-105
- 1) check all heater controls are OFF
- 2) allow heater to cooldown. , Monitor TI-101 until temperature drops below 200 F
- 3) shut circulating pump CU-102 to 0FF
- 4) close valves CO2-V9 and CU3-V1
- 5) vent heater by slowly opening valve CV3-V1.
Monitor sight glass SG-101 p. LoN0oN NUCLEAR
64 Cf *Oso fiftt 84 WiS*0se E88tCievt Caft Pact OP-001 Abnormal Operations -E- 5/31/84 97A
- 6) open heater drain valve RD2-V2 until all water has drained out IF PUMP OPERATION IS PERMITTED, THEN IT IS ADVISABLE TO LOWER THE SYSTEM TEMPERATURE.
THIS IS ACCOMPLISHED BY USING MAIN COOLER CU-104 AND OPENING VALVES U2-V2, CO2-V6 CU2-V7 AND CLOSING VALVE CO2-V8. ONCE SYSTEM MAS COOLED SUFFICIENTLY, THEN STEPS 11.1.1 (a) THROUGH (f) ARE FOLLOWED. b) usater CU-401 Neater CU-401 may be removed from system while pump is operating.
- 1) open valve Cull-V2 and close Cul0-V4 and CU11-V1
- 2) slowly open vent valves Cv10-V1 and CV11-V1.
Monitor sight glass SG-401
- 3) open drain valve RD10-V1 and monitor sight glass SG-402 until all water has been drained
.2 Loss of Circulatino Pumo The most likely failure to occur on a centrifugal pump would be a mechanical failure. A complete set of spare parts is available at site. LN operators are trained to trouble shoot and repair the pump as necessary. In the event the pump cannot be repaired, a spare pump is avail-able on short notice.
.2.1 Circulating Pump Isolate / Drain Procedure a) Close valves CUl-V3, Cul-V4, CU7-V1, CD2-V2, CU2-V3 and CO2-V5.
b) Open valve RD2-V1 and allow pump to depressurise to O psig as indicated on PI-101. s c) Loosen drain plug, located in pump bowl and allow pump to completely drain.' ( LONDON NUCLSAR
. . _ _ _ _ . _ - . _ _ _ _ _ _ _.. _._ m_.m. = _ _ _ _ _ _ _ _ . . __ _._ _ .mm._
I at v+0m (FFECTivt Dait pact j MCiaom Tsitt OP-001 Abnormal operations - E- 5/31/84 97A l t i I l
.3 Loss of System Fluid i
A loss of system fluid can occur through a variety of i
)
means; most notably would be: a) Major leakage from a decontamination system component. I l b) Hose failure at fittings or weak spot. l All system components and hoses are pressure tested at h twice the maximum operating pressure prior to decontam-ination startup. All hoses have isolation valves at each end to minimise leakage from a hose failure. In ad-dition, the LN operator hourly inspects all hoses and
! process piping for leaks.
.4 Loss of Power j Loss of power would essentially shutdown the decontamina- f tion system. .If the power loss appears to be short [
! (\ lived (less than 10 days to repair) the LN operator will ' secure the decontamination equipment for the duration of repairs. If the power loss appears to be long term, i then an alternate source of power (480V/30A) will be pro- ; vided by the SP to remove any reagent in the piping. ! l
.5 Slurry Rose railure t As per 0.3 above, the slurry hose is tested at twice the
' dead head" pressure which could be applied through inad- l vertent valve operation.
During the slurry operation, the line will constantly be monitored (at a safe distance) to verify that there is [ no leakage. Adequate communication lines will be set up l ! in advance between personnel monitoring the slurry line 1 and the LN equipment operator to respond rapidly to any problem which might occur during the operation. ' t l i i l l . [ r LoN00M NUCLEAR
- l ABNORMAL O NRATIONS '
5 of 6 TABLE 11.1 PRELIMINARY , RECOMMENDED ABNORMAL CONDITIONS PRECAttrIONS PRIMARY CONTROL BACKUP OPERATOR ACTION AA.1 Ioss of Temperature Control (a) Failure to control Testing heater Equipment operator High temperature Manually switch heater rising temperature control circuits available 24 h,urs cutout switch to circuits to "OFF"
- POSSIBLE CAUSE before decon as taking readings at trip heaters and let system cool per operating regular intervals (CU-203/TSH-401) down. Continue to Failure of Temperature procedure circulate. Operate controller CU-204/TC-401 * ** *# "*" I*
(b) Failure to maintain Testing heater Equipment operator Backup 300 KW Operate at lower process temperature control circuits available 24 hours heater. Skid 0 temperature (200 F) before decon taking readings available on until 300 MN heater is POSSIBLE CAU3E as Per operating +. regular short notice. replaced.
- Inadequate power supply Procedure intervals 150 KW heater -
- Failure of temperature elements available controller CU-204 or TC-401 on a t notice.
- Failure of heater elements .
A1.2. Loss of circulating pump Functional test- Equipment operator Manufacturer's Select pump CU-108 ing of circulat- available 24 hours recommended spare to "OFF" and initiate POSSIBLE CAUSE Jng Pump before taking readings parts available repairs to circulating Mechanical failure ec n as per at regdar M ng decon- pump. of carculating pump operating pro- intervals tamination CU '104 Backup pump available in short notice. la.3. Ioss of system fluid - Leak testing Equipment operator Manufacturer's -Select pump Cu-104 before decon as available 24 V urs recommended spare to "OFF" and isolate POSSIBLE CAUSE per operating taking readings at parts available area of leakage
- ?.ajor leakage from procedure, regular intervals during decontam- -Initiate cleanup
- s a n a e8 na n-decontamination system at critical an C ***nce rePahs as necessary
- Hose failure at fittings or fracture in weak spot J.
11.4 Loss of 463/440V power #-Secure Decontamination Equ Testing of Station backup Operator -Investigate cause circuitry n ar supplies POSSIBLE CAUSE -Perform necessary available repairs various causes -Remove chemicals from system if necessary g +
's w
Section: Revision: Effective Pages Date: London ~ OP-001 -E- 5/31/84 97-B ( U 600 rities - PROJECT OPERATING APPENDIX B PROCEDURES PIPE ISOLATION ( - e 6 e e I s .' " a l
Section: Revicirnt Effcetiv3 Pcg3:
- Dato London '
OP-001 - E- 5/31/84 97-C ( Nuclear nu. PROJECT OPERATING APPENDIX C PROCEDURES 4 P SPECIAL HOSE COUPLING ASSEMBLY INSTRUCTIONS i e O f ' , 4 t S 9 ./
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PROCEDURE FOR APPLICATION OF 1 BOLT TOROUE ON FLANGED JOINTS BOLT TOROUE PROCEDURE
/
l STEP 1. 5 s. ( ALICN COMPONENT PARTS AND CLAMP TOGETHER WITH NOLD DOWN. JIJ* dj STEP s. LUSRICATE STUD (OR SOLT) THREADS IN AREA OF NUT (OR FORCED RING) ENOACEMENT. ALSO LUBRICATE F, ACE 4 Otto, f, OF Nt/N (OR SOLT HEAD) USING A yo a SUITASIA LUBRICANT. i
,8 811 P 8.
INSTALL TIONT. ALL BOLTS AND Ntt!M FINGER l STEF 4. Ol##, , Mt/MaER BOLTS SO THAT TORQUING RE. 6 ! 7 qutREMENTs CAN st roLLowED. /JJ'o / 8 [. , STEP s. Arrev 'rORQUE IN 30% (t/s) STEPS Or REQUIRED FINAL TORQUE, LOADING 2 AIJ. BOLTS AT EACH STEP SEFORE PRO-CEEDING 10 NEXT STEP. _8BDLTS ~ STEP 4 110M11tM SOLTS IN REQUENTtAL ORDER . 6140*, se*.sto*,46*.324* a 1ss'.sts* AT EACH STEP UNT1L FINAL TORQUE 18 SEdUENCI A_t. ORDER REACHED,-(SEE ATTACHED SKETCHES) R_OTATIONAL ORDER STEF T. 12 USE ROTA110NAL 110HTENINO UNTIL 34 1 ALL SOLTS ARE STABLE AT FINAL , 56 5 TORQUE IJtvEt. (Two coMPlJtTE TIMES 3 Aa0UND IS USUALLY REQUlAED.) SEE 7,3 ATTACHED SKrtCHES. . 7 2 6 . 4 ' 3 i k , 15
- l e
k,
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k O _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _.______..._._________.___...___)
i Ssetion: Revisions Effsetiva pige
- London C 6/1/84 1 of 3
( Nuclear - t London Nuclear Hose D-HI couclina Procedure ( Step 1 i If hose end is to be cut prior to coupling installation, place t on a bench or other support .and secure in place. Wet the knife blade for easier cutting; nome typec .'. hose will cut more ! easily if flexed slightly. Step 2 Cut hose ends squarely; square ends are necessary to insure the preper alignment and depth of the hose on the coupling shank ; (n'pple).- : Step 3 Lubricate the hose and coupling shank for easier insertion; soap l and water, or water alone, are recommended lubricants. Step 4 . f Do not cut or burn out any of the inner tube to accommodate a coupling shank thgt is too large; however, countersinking the ; end of the tube 45 may help to insert the coupling. l Step 5 Do not alter the shank of the coupling; doing so may either re-duce some- of the holding power or create sharp edges which could ; puncture the hose tube. - Step 6 , l i Keep hose and coupling shank aligned as they are being pressed ' together to avoid damaging the' hose tube and to assure that they reach full insertion depth; place the coupling in a vise so it can be held securely. s.- l l s u l , , l J
- e - -.----,--,,~..,,,,----.---,n-- ey - _ . , - . . - , . , , - . e.,_-..
f L Ssetien Title Revision Effectiv2 Page Date Ho'se Coupling. Procedure C 6/1/84 2 of 3
.( .
i Step 7 i Locate clamp (s) over hose barb and tighten. Tighten clamp hex nuts with a wrench or socket. Turn nuts until clamp halves are ; pulled tight around hose, but leave a litle space between clamp ears for later takeup. Note: After hose has cycled from hot to cold, retighten all clamp bolts. ' Step 8 ' Do not remove any part of the hose cover (except in accordance with manufacturer's specific coupling instruction). Doing so can expose the reinforcement and shorten the life of the hose. Step 9 .. After assembly of couplings, inspect the inside of the hose at i the end of the coupling for cuts, tears, folds, or bulges result-ing from improper assembly. ! Note: Refer to London Nuclear Procedure for bolting of d C-
- flanged joints in process systems for interconnection details, j
Step 10 Once joint interconnection is complete, install coupling securing wire (see Figure 1, Item G). 6 i ( I 4
1 i i Title Revision Effectlye Page l Date: i g ,
. Hose Coupling Procedure C 6/1/84 3 of 3 l I
FIG.I HOSE COUPLING i i 1
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m .s , , U b fr- , r - - - [ b- f,L.,_J l ,, 4 'b-l o ga: , . v ! ( ! A C D E F E G , D I I l ! l l : r A - HOSE ' B - BOLTING (CARBON STEEL) C - OFFSET INTERLOCKING CLAMPS D - TURNED BACK HOSE NIPPLE
- s. , (STAINLESS STEEL)
E - BACKUP FLANGE (CARBON STEEL ) F - SPIRAL WOUND GASKET - G - COUPLING SECURING WIRE l NOTE
- USE TWO STRANDS OF 16GA.
' TIE WIRE (WRAP AROUND CLAMP 'C' THEN PASS
( TIGHTLY OVER FLANGES 'E' l AND St.MILARLY ATTACH TO -
, ADJOINING F1TTING.)
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Secticn: R2 Visions Effective Page: .i Date: > London 0e-001 -E- s/31/84 97-D i ( Nuclear nues e APPEND H D PROJECT OPERATING f PROCEDURES 6 AS BUILT FLANGE JOINT ARRANGEMENT DATA SHEETS . i h e I \ l l 1 f 1 l l l l r?" ( e r,- , , , _ . , , , , , _
I
/ 5/31/84 REV -E- .
", PAGE 9 7*D.
APPENDIX D .
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- SECTION TITLE REVISION E g { IVE p OP-001 FIANGE JOINT ARRANGEMENT -E- 97-c 5/31/84 [
k f i I EL139' RHR RETURN LOOP'A' ! RHR-R__ i A-05 9 p RHR-R A-04 f i EL 135' '~ HOSE CLAMP M, (SECURE AS ll AVAILABLE) ,
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1 Revision 5/31/84 OP-001 FLANGE ARRANGEPI.hT 97-G l
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-E- 5/31/64 97-G ;
OP-001 FIANGE JOINT ARRANGEMENT k RHR SUCTION EL 139' RHR-7__ , 05 V A RHR-S
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i I L OP-001 FIANGE JOINT ARRANGEMEhT -E- 5/31/84 97-c ( i i i
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OP-001 FIANGE JOIrrr ARRANGEMENT -E- 5/31/84 97-c k ,. EL 135' o EL116' _ HOSE CL AMPS (SECURE AS AVAIL ABLE ) LB__ 03 V A LB
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