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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20211K1201999-08-30030 August 1999 Proposed Tech Specs,Adding New Specification That Addresses Use of Interim Provisions Upon Discovery of Unintended TS Action ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207F7631999-03-0202 March 1999 Proposed Tech Specs Pages Re Application for Amends to Licenses DPR-77 & DPR-79,deleting Iseg from License Conditions ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units 1999-08-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program ML20138F2531996-02-23023 February 1996 Rev 38 to Sequoyah Nuclear Plant Odcm ML20108B4121995-11-0303 November 1995 Rev 37 to Sequoyah Nuclear Plant Odcm ML20094Q2111995-10-30030 October 1995 Rev 1 to ASME ISI Pump Testing Program Basis Document ML20094Q2301995-10-30030 October 1995 ASME ISI Valve Testing Program Basis Document, Rev 0 ML20094Q1971995-10-30030 October 1995 Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2 ML20094Q1931995-10-30030 October 1995 Rev 1 to ASME Sys Pressure Testing Program Basis Document ML20094Q1841995-10-13013 October 1995 ASME Section XI Isi/Nde Program Units 1 & 2, Rev 0 to 0-SI-DXI-000-114.2 ML20094Q1761995-10-13013 October 1995 ASME Section XI Isi/Nde & Augmented Nondestructive Exam Programs, SSP-6.10,rev 2 ML20149L6811994-09-30030 September 1994 Concerns Resolution Program - Sequoyah Nuclear Plant ML20063D6691994-01-24024 January 1994 Rev 4 to Sequoyah Nuclear Plant Restart Plan ML20065Q6251993-10-13013 October 1993 Rev 31 to Sequoyah Nuclear Plant Odcm ML20056F3181993-08-20020 August 1993 Rev 0 of Post-Restart Plan ML20056G1841993-08-10010 August 1993 Rev 2 to Sequoyah Nuclear Plant Restart Plan ML20044F3081993-05-20020 May 1993 Rev 0 to Sequoyah Nuclear Plant Restart Plan ML20034F3191993-02-26026 February 1993 Rev 26 to Offsite Dose Calculation/Environ Monitoring Methodologies ML18036B1961993-01-27027 January 1993 Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training. ML20127P5461992-12-16016 December 1992 Rev 20 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program,Unit 1 ML20127P6361992-12-16016 December 1992 Rev 19 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program,Unit 2 ML20114C8131992-04-17017 April 1992 Rev 27 to Odcm ML20101F2011992-02-0808 February 1992 Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1 ML20101F2081992-02-0808 February 1992 Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2 ML20034C7451990-03-14014 March 1990 Rev 24 to ODCM ML20033F2631990-02-27027 February 1990 Rev 24 to Odcm ML20006C0571990-01-18018 January 1990 Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan ML15264A1571990-01-0202 January 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. ML20012A3771990-01-0101 January 1990 Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station ML20012A3751990-01-0101 January 1990 Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station ML20012A3801990-01-0101 January 1990 Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations ML20012A3791990-01-0101 January 1990 Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station ML20012A3691989-12-0505 December 1989 Rev 8 to, Process Control Program,Mcguire Nuclear Station ML20011D2441989-12-0101 December 1989 Crisis Mgt Implementing Procedures ML20012A3721989-11-27027 November 1989 Rev 4 to, Process Control Program,Cawtaba Nuclear Station. ML20012A3731989-11-15015 November 1989 Rev 4 to, Process Control Program Oconee Nuclear Station. ML19325F1931989-11-0101 November 1989 Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations. ML19332C8451989-11-0101 November 1989 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13 ML19332D2241989-09-22022 September 1989 Rev 23 to Odcm. ML20247H3371989-09-15015 September 1989 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting .. ML20245H1421989-08-15015 August 1989 Rev 22 to Offsite Dose Calculation Manual Changes ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20247M7921989-07-31031 July 1989 Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl ML20247M9151989-07-27027 July 1989 Procedure Generation Package ML20247N0421989-06-19019 June 1989 Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing 1999-06-22
[Table view] |
Text
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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR, PLANT SURVEILLANCE INSTRUCTION SI-673 REACTOR COOLANT SYSTEM LEVEL
~
VERIFICATION USING SIGHT GLASS OR TYGON HOSE Units 1 & 2 REVISION 4 PREPARED BY:
J. M. Anthony
~
RESPONSIBLE SECTION:
Operations l
REVISED BY:
Spencer Childers
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SUBMITTED BY:
,I n
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Rf ~ nsibli Section Supervisor PORC REVIEW DATE.
SEP 151987 2
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1 APPROVED BY:
4 Plant Manager
-l DATE APPROVED:
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Reason for revision (include all Instruction Change Form Nos.):
Revised to add Radiochem Lab sampling requirement per CCTS NCO 870077005.
1 I
l The last page of this instruction is number:
7 l
I 8711040345 871002 PDR ADOCK 05000327 4
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SEQUOYAH NUCLEAR PLANT I.
l PLANT INSTRUCTION REVISIONJ0G r
SURVEILLANCE INSTRUCTION SI-673 REVISION Dati Pages REASONFORREVISIONkINCLUDECOMMITMENTSAND
,l LEVEL App.oved Affected ALL ICF FORM NUMBERS) j 0
06/29/81 ALL Title Chg I
1 10/12/84 ALL b
Revised to increase minimum reactor coolant system water level during filling and draining 2
08/29/86 All to el 695' 6" when RHR pumo(s) running I
Revised to expand scope to include flushing of sightglass, completed references, add Appendix A 3
04/24/87 All instructions for flushino sightolass.
I SEP 1 5 Lc8/ 1,3,5,6 ment per CCTS NCO 870077005.
Revised to add Radiochem Lab sam,pling require-4 s
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.I in The purpose is to visually verify the reanter coolant syw;m level 2;
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.I 695 feet 6 inches to prevent the loss of suction pressure'to runt:ing
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RHR pump (s) and to docu;nent the reactor coolant system water level i I
during filling and draining of,the, reactor coolant systec $<h during i
modes 5' and 6 'oparation. Appendir,A'will. provide in(structWgs for flushingofthes.yhkiasslqlordertoensurethesightgl61tsbes.not get plugged up, thug thsiii 1.xacchrate level indication. MWoched j
Lab will. sample the fluid i.adlyze debris from the sight glass 3
flush.
This'SI does not f Itt11 any Tech. Spec. surveillance s
requirements.-
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2.0 REFERENCES
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2.1 S01-70.1C W
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3.0 PRERE0QISITES y' "
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y 3.1 i$1ght glass and/or tygon hose for indicating RCS lovel is
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inservice per SOI-68.1C.
a 4.0 PRECAUTIONS 4.1 Do not drain below el 695 feet 6 inches ; th RHR 6Mp(
running.
4.2 Remove sight glass and/or tygon hose from'servied hen pressu,12er cold calibration level is indicating 51. and Jd.rvWpc to wold 3
over-fli,ving sight glass (close 68-551). (M[ximumsightJ1 ass E-indication is el 705-5 13/16".)
9-When flooding refueling cavtry, remove sight glass and/<d 'tyy,n nu 4.3 tr g
hose per 501-74.10.
y 4
4.4 When fill,ing,RCS, remove sight glass and/or tygon hose from i bq
.l service per S0I,68.18.
4. c.,
Caserve applicabig radiation protection instructions when j.
~E performing RCS sig]it glass and/or tygon host, levei indicatio,p,
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locally.
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4.6 If RHR pump (s) lose suction, refer to A01-14G.
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5.0 SPELIAL TEST E M PJ @ {
6.0 INSTRUCTIU'S 3
- 6.' Y3 During period of time sight glass and/or tygon hose is in service
,q complete Data Sheet 1 at least once per 30 minutes.
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6.2 If' suction to'RHR pump (s) is lost, refer to AOI-14 section G.
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- - '63 Perform flushing of sightglass per Appendix A once per week.
I;!5, o : 7.0 -ACCEPTANCE CRITERIA h
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?e 7.1 Reector vessel level is maintained.)_695' 6" el.
Immediately ss _
. notify the SRO and UO if level decreases below 695' 6".
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Revision 4 i
DATA PACKAGE COVER SHEET Page 1 of.1 REACTOR COOLANT SYSTEM LEVEL VERIFICATION USING SIGHT GLASS OR TYGON HOSE Unit Performed By Date Time Started Date Time Completed (AU0 U0)
List of data sheets attached.
i Instruction No.
Data Sheet No.,,
No. of Pages t
NOTE:
Refer to data sheet for, evaluation of data acceptance' criteria.
Were Acceptance Criteria satisfied?
Ye\\
No s
Verified by Signature / Title I
NOTE:
If Acceptance Criteria were not satisfied, notify Senior Reactor l
Operator (SRO).
I Remarks:
Reason for test:
Plant condition (explain)
Other (explain) i Review and Approval of Test Results SR0 date Review of Test Results STA Date Remarks:
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SI-673 J
Page 4 Revision 3
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' DATA SHEET 1 Page 1 of 1 REACTOR COOLANT SYSTEM LEVEL VERIFICATION USING SIGHT GLASS OR TYGON HOSE i
SRO Approval SRO l
Filling Level Observed at:
Unit Draining 5,,,
(1) Sight Glass Date 4
Refueling (2) Tygon Hose Sheet of j.
(3) Aligned per 50I-68.lC Observethefollowingguidelinesfor[evels:
NOTE:
Minimum level with RHR pump (s) on el 695' 6" Maximum level when S/G manways are open 696' 4" (overflow will occur at el 696' 8".)
Maximum level for Sea.1 Table work or RCP seal work el 699' (RCP flange 699' 3", Seal Table 702' 1 1/2".)
IF ANY of these levels are exceeded IMMEDIATELY notify the SR0/SE.
Time /Date Elevation Initial Time /Date Elevation Initial
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SI-673 Page 5 Revision 4 Appendix A Page 1 of.3 HEEKLY FLUSHING OF SIGHTGLASS Caution: Coordinate work with Lead UO and Radiochem Lab.
I Note: Phone near tygon bose connection (6354) l Note: Doubl.e person verification is required.
Note: Radio: hem Lab support required.
at Radiochem Lab. Analyst g
SR0 approval SRO 1.0
/
Verify RCDT is not full and pressure is less than 4 psi.
2.0
/
Open valve 68-550, flush for approx. 2 minutes.
3.0
/
Verify RCDT level increases l
4.0
/
Close valve 68-550 5.0
/
Isolate tygon hose valve and V-2 l
4 6.0
/
Disconnect and drain tygon hose to bucket or floor drain.
7.0
/
Verify valve 68-549'open 8.0
/
Verify valve 68-551 open 9.0
/
Ensure Radiochem Lab personnel ready to obtain sample and open valve V-2 and flush to bucket or floor drain.
1 Radiochem Lab personnel will obtain sample while Flush is in progress.
(This will flush piping from Lp #1 crossunder drain piping.)
10.0
/
Close valve V-2 11.0
/
Close valve 68-551 12.0
/
Open valve V-2 (This will drain the sight glass).
13.0
/
Close vi'Ive V-2 I
03461/lds
1 SQN SI-673
,0 Page 6 Revision 4
' ~~
Appendix A Page 2 of. 3 WEEKLY FLUSHING OF SIGHTGLASS 14.0-
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Open valve 68-551-(This will refill sight glass)-
15.0-
/
Close valvo 68-551
'I 16.0-
/
Open valve V-2 (Drain sightglass) and assure Radiochem l
Lab obtains second sample Note:.This completes flushing of Sightglass.
i Note: ;The following. steps will place the Sightglass back in service.
-17.0
/
Close valve.Vi2 and attach tygon hose. '
'18.0
/
_Open valve 68-551
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t 19.0
/
Verify level in sight glass
'20.0
/
Open valve V-2 and Tygon hose valve, compare level in tygon hose with sight glass level-(UO to verify).
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Ensure air bubbles are not trapped in tygon hose and j
21.0 sightglass is free of, obstructions.
22.0
/
Close valve V-2.and tygon hose valve (This takes.the tygon out of service) j 23.0
~/
Ensure Caution Order is on the Tygon Hose Valve.
j' Acceptance criteria:
The piping from the RCS Lp #1 Crossunder leg is free of debris i
and the sightglass has no visible obstructions.
If not, immediately notify the UO and/or SE/SRO.
L' Radlochem Lab will analyze the sample obtainedsto determine i
content of any debris and particulate.
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Aopendix A PEge 3 of 3
'SI-673 Page 7
- 85 3 3 WEEKLY FLUSHDIG OF SIGHTGLASS I
ELE 7ia I
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V-4
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V-3
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INSIDE POLAR CRANE WALL RCS CROSS UNDER LCOP 1 I
68-549 63 550 x
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3 ATTACliMENT S l
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_ _ _ _ _ _ _. _ _ _