Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program ML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A5121999-08-23023 August 1999 Procedure 71151, Performance Indicator Verification. ML18107A5091999-08-23023 August 1999 Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability. ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML18107A2961999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML18106A5571998-04-16016 April 1998 Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents ML20239A1251998-03-31031 March 1998 Rev 11 to Salem Nuclear Generating Station Odcm ML18106A4241998-03-26026 March 1998 Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A3921998-03-13013 March 1998 Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency. ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. 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[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program ML18107A5121999-08-23023 August 1999 Procedure 71151, Performance Indicator Verification. ML18107A5091999-08-23023 August 1999 Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability. ML18107A2961999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML18106A5571998-04-16016 April 1998 Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents ML20239A1251998-03-31031 March 1998 Rev 11 to Salem Nuclear Generating Station Odcm ML18106A3921998-03-13013 March 1998 Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency. ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML18102B6681997-10-0101 October 1997 Rev 8 to Inservice Testing Manual for Pumps & Valves Program. ML18106A8291997-09-0404 September 1997 Rev 2 to Reactivity Manipulations Documentation Guide. Page to Training Manual NC.TQ-TP.ZZ-0302,encl ML18102A7941997-01-21021 January 1997 Event Classification Guide,Technical Basis, for Hope Creek Generating Station & Salem ML18102A7931997-01-21021 January 1997 Event Classification Guide,Technical Basis, Salem Generating Station ML18102A6661996-11-19019 November 1996 Rev 2 to Pse&G Simulation Facility Certification Program. ML20115B7791996-07-0303 July 1996 Final Draft, Hope Creek Event Classification Guide, Sections 1-9 ML18101B1141995-11-14014 November 1995 Revised Salem Generating Station Event Classification Guide, Including Rev 46 to Table of Contents,Rev 37 to Attachments Signature Page,Rev 26 to Attachment 6,Rev 25 to Attachment 7 & Rev 24 to Attachment 9 ML20091M9911995-10-15015 October 1995 Event Classification Guide HCGS, Including Revised Eals, Technical Basis Document & NUMARC EAL-to-Hope Creek Comparison Summary ML18101A6911995-05-31031 May 1995 Nbu Issue Mgt & Prioritized Action Plan, Dtd May 1995 ML18101A7711995-05-11011 May 1995 Rev 1A to Vol a of Salem Generating Station Unit 2 Second 10-Yr Insp Interval ISI Program Plan. ML20134K0831995-02-27027 February 1995 Pse&G/Nuclear Business Unit Organizational Effectiveness Assessment Plan, ML18101A6751995-02-16016 February 1995 Rev 11 to EOP 1-EOP-TRIP-1, Reactor Trip or Safety Injection. ML18101A6761995-02-16016 February 1995 Rev 12 to EOP 1-EOP-TRIP-2, Reactor Trip Response. ML18101A5381995-01-27027 January 1995 Revised Salem Generating Station Event Classification Guide. ML18101A2111994-08-17017 August 1994 Revised Salem Event Classification Guide. ML18101A6771994-07-11011 July 1994 Rev 10 to EOP 1-EOP-TRIP-3, Safety Injection Termination. ML20147B1601994-04-23023 April 1994 Rev 3 to S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation ML18100A8081994-01-0707 January 1994 Rev 30 to Salem Generating Station Event Classification Guide. ML20147B1491993-11-0202 November 1993 Rev 2 to Procedure S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation ML18100A4201993-06-15015 June 1993 Justification for Sgs Units 1 & 2 Restart & Operation Rod Control Sys Failures. ML18100A3771993-05-0505 May 1993 Rev 27 to Salem Generating Station Event Classification Guide. ML18100A3661993-04-27027 April 1993 Rev 8 to Section 18 to Event Classification Guide, Correcting Typo on Pages 3 & 5 of 6 ML20147B1171993-04-13013 April 1993 Rev 1 to Procedure NC.NA-AP.ZZ-0015(Q), Safety Tagging Program ML18096B3251993-02-26026 February 1993 Integrated Scheduling Program. ML18096B2911993-02-10010 February 1993 Revised Event Classification Guide,Including Rev 25 to Table of Contents,Rev 14 to Attachment 6,Rev 13 to Attachment 7, Rev 8 to Attachment 8,Rev 13 to Attachment 9,Rev 3 to Section 10,Rev 4 to Section 17 & Rev 7 to Section 18 ML20147B1021993-01-21021 January 1993 Rev 5 to Procedure NC.NA-AP.ZZ-0009(Q), Work Control Process ML20135B6521992-12-29029 December 1992 Rev 0 to Loss of Overhead Annunciator Sys ML20147B1371992-12-22022 December 1992 Rev to Procedure SC.RP-TI.ZZ-0209(Q), Release of Items from Rca ML20147B2051992-09-21021 September 1992 Rove Time Keeping Procedure ML18096A9601992-08-28028 August 1992 Electrical Distribution Sys Functional Insp (Edsfi) Methodology & Plan. ML18100A3151992-07-28028 July 1992 Rev 1 to Process Computer Maint & Mod Control Program. ML18096B3191992-07-17017 July 1992 Rev 8 to Salem Nuclear Generating Station Odcm. ML20147B1691992-05-0707 May 1992 Rev 1 to Procedure NC.NA-AP.ZZ-0013(Q), Control of Temporary Modifications ML18096A6791992-04-30030 April 1992 Vols A-D of Salem Generating Station Unit 2 Inservice Insp Program (Second Insp Interval) Long-Term Plan. ML18096A4421992-01-15015 January 1992 Rev 17 to Salem Generating Station Event Classification Guide ML18096A3211991-10-0404 October 1991 Rev 13 to Event Classification Guide,Including Table of Contents,Section Signature Pages,Spill/Discharge Notification Form & Related Pages ML18096A1431991-06-28028 June 1991 Rev 12 to Salem Generating Station Event Classification Guide. ML18095A9661991-05-30030 May 1991 Artificial Island Salem Event Classification Guide, Rev 11 ML18096A1191991-05-28028 May 1991 Rev 2 to NFU-0039, Salem Reactor Physics Methods. ML18095A9391991-05-16016 May 1991 Revised Replacement Pages to Facility Inservice Testing Program 1999-09-10
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Text
t SALEI GENERATING STATI~
PUBLIC SERVICE ELECTRIC & GAS COMPANY ELECTRIC PRODUCTION DEPARTMENT PROCEDURE APPROVAL COVER SHEET PROCEDURE: PD-15.7.016 SECURING DEMINERALIZER OPERATIONS AND DE-WATERING REMARKS:
(PROCESS CONTROL PROGRAM)
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SALEM RaMation Protection e Instruction PD-15.7.016 lI GENERATING PAGE 1 OF 7 SECURING DEMINERALIZER OPERATIONS STATION AND DE-WATERING REVISION o Purpose This procedure describes the proper securing operations and de-watering procedures to be followed for the Chem-Nuclear 10, 195, and 300 cubic feet demineralizer units.
Apparatus/Material ..
- 1. Chem-Nuclear demineralizer units - 10, 195 and 300 cubic feet.
- 2. Chem-Nuclear skid mounted pumping system. (TEPS)
- 3. Rad waste collection/storage tanks.
Prerequisites
- 1. Insure compressed air (at least 90 psig) is available.
- 2. Verify at least one flow path to a drain suitable for handling contaminated liquids in the event of leakage is available.
Precautions
- 1. Filter and demineralizer vessels are haav-y. Proper rigging and handling techniques must be followed.
- 2. Special care must be excercised when handling radioactive materials to minimize personnel exposure, prevent overexposures and to prevent the spread of contamination.
- 3. Strict adherence to all applicable Radiation Exposure Permits and any;other established Radiation Protection requirements is mandatory.
- 4. Verify hose connections are secure and properly routed prior to put-ting any water through system.
SALEM Ra ation Protection PD-15.7.016 GENERATING Instruction SECURING DEMINERALIZER OPERATIONS PAGE 2 OF 1 STATION REVISION o AND DE-WATERING Procedure 3
A. Securing Systems Which Have 10 ft 3 Filtration Units or 10 ft Demin-eralizer Units Installed. (Use attachment 1 as a guide to system piping).
- 1. Secure the_pump(s) supplying waste to the TEPS but maintain a flow path for treated waste open until the system has been se-cured.
- 2. Observe flow rate and inlet pressure on FM-1 (System Inlet Flow Rate), PI-1 (System Inlet Pressure), and when flow and pressure fall to near zero or stabilize, shut WS-1 (System Inlet Isolation).
Follow step 3 or 4 below as applicable.
- 3. If the system is to be shut down a.nd neither of the uni ts are to be removed, observe outlet pressure on PI-6 (Deroin Outlet Pressure).
When pressure stabilizes, shut DM-2 (De-water Pump Bypass). The system has now been secured.
- 4. If the system is to be shut down and a filtration or demineralizer unit is to be removed, adjust SA-1 (Filter/Demineralizer Service Air Regulator) to 20 psi and slowly open SA-3 (Service Air to Filter Inlet) and observe pressure indicators, PI-2 (Filter In-let Pressure), PI-5 (Filter Inlet Pressure), and PI-6 (Deroin Out-let Pressure) .
NOTE: If filter inlet pressure is not greater than demin outlet, air pressure may be increased to 30 psi using SA-1 Filter/Demin-eralizer Service Air Regulator, provided the differential pressure across either unit does not exceed 20 psi. Continue the air flow until the water has been replaced BY air as in-dicated by periodically opening DM-5 (System Outlet Sample) and noting the absence of water from the sample line, then shut SA-3 (Service Air to Filter Inlet) and when pressure sta-bilizes, shut DM-2 (De-water Pump Bypass) and open FT-1 (Filter Outlet Sample) to relieve any residual pressure. The system has now been secured and de-watered. (Sup. witness; Doc. on check-off sheet)
SALEM Ralation Protection 41 PD-15.7.016 GENERATING Instruction SECURING DEMINERALIZER OPERATIONS PAGE 3 OF 1 STATION AND DE-WATERING REVISION ° 3
B. Securing Systems Which Have 10 ft 3 Filtration Units and 195 ft and 3
300 ft Demineralizer Units Installed.
- 1. Secure the pump(s) supplying waste to the TEPS but maintain the
.flow path for treated waste open until the system has been secured.
- 2. Observe flow rate and inlet pressure on FM-l *(System Inlet Flow Rate) and PI-1 (System Inlet Pressure). When flow and pressure fall to ne*ar zero pr stabilize, shut WS-1 (System Inlet Isolation) and continue operating the de-watering pump until the pump looses suction, then secure the pump by shutting PR-1 (Service Air to De-water Pump Flow Regulator) and follow step B.3, B.4 or B.5 be-low as applicable.
- 3. If the system is to be shut down and neither of the units are to be removed, shut DM-3 De-water Pump Outlet Isolation. The sys-tem is secured.
- 4. If the system is to be shut down and the filtration unit is to be removed, adjust SA-1 (Filter/Demineralizer Service Air Reg-ulator) to 20 psi and slowly open SA-3 (Service Air to Filter Inlet}and continue the air flow until the water has been replaced by air as indicated by periodically opening FT-1 (Filter Outlet Sample) and noting the absence of water from the sample line then shut SA-3 (Service Air to Filter Tnlet) and when pressure sta-bilizes, shut FT-2 (Filter Outlet Isolation) and open WS-4 (Sys-tem Inlet Sample Valve) to relieve any residual pressure. The system has been secured unless the 195 ft 3/300 ft 3 demin unit is to be removed, in which case go to step 5 below. (Sup. witness; Doc. on check-off sheet)
- 5. Establish or verify the following valve positions:
SW-3 Primary Grade Water to Deroin Outlet Closed DM-1 Dewater Pump Inlet Isolation Open DM-2 Dewater Pump Bypass Closed DM-3 Dewater Pump Outlet Isolation Closed DM-5 System Outlet Sample Closed SA-2 Service Air to Demin Inlet Closed
SALEM iation Protection PD-15.7.016 GENERATING Instruction SECURING DEMINERALIZER OPERATIONS PAGE 4 OF 1 STATION AND DE-WATERING REVISION o SA-3 Service Air to Deroin Outlet Closed SA-4 Service Air Isolation Closed FT-1 Filter Outlet Sample Closed FT-2 Filter Outlet Isolation Closed VT-3 Deroin Inlet Vent
- 6. Verify that water from the dewatering operation is aligned to a liquid Rad.Waste storage tank.
- 7. Open DM-3 (Dewater Pump Outlet Isolation)
- 8. Valve in air to the pump oy opening SA-I (Service Air Isolation Valve) and adjust Pump Pressure Regulator PR-1 to establish a de-watering flow rate of approximately 15 gpm. Continue pumping for two hours, increasing the pump rate to approximately 3 Strokes/
second when the pump begins to draw air. This will de-water the inner annulus.
- 9. Close FT-2 (Filter Outlet Isolation Valve) and PR-1 (Service Air to De-water Pump Flow Regulator Valve}.
- 10. Open FT-1 (Filter Outlet Sample Valve) to drain the Demineralizer feed leg.
- 11. Connect the Deroineralizer Unit outlet hose to the de-watering leg of the outer annulus of the demin vessel and open PR-1 (Service Air to De-Water Pump Flow Regulator Valve). Continue pumping .for two hours, with an initial de-watering flow rate of approximately 15 gpm. Increase the pump rate to approximately 3 stroke~/second when the pump begins to draw air. (Sup. witness1 Doc. on check-off sheet)
- 12. Close SA-4 (Service Air to Deroin Inlet Valve)
- 13. Close PR-1 (Service Air to De-water Pump Flow Regulator Valve).
- 14. Close DM-3 (De-water Pump Outlet Isolation Valve).
- 15. Prior to transportation or after a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> stand repeat steps 5 thru 14 by connecting demineralizer connections as indicated in attachment 1, but only pump for l hour on each annulus. (Sup. wit-nes*s: Doc. on cfieck~off s-heet)
- 16. Measure the water level in the center annulus standpipe. If this
J SALEM Ra ation Protection - PD-15.7.016 GENERATING Instruction SECURING DEMINERALIZER OPERATIONS PAGE s OF 7 STATION AND DE-WATERING REVISION o level exceeds 2 inches, the unit contains more than 1% free standing water. Additional corrective action will be required to reduce the water below 2 inches. Contact Rad Waste Coordin-a tor. (Inspec'tion Irold QC}
- 17. Disconnect the inlet, outlet and vent connectors at the unit as applicable.
- 18. Close the unit access port with a bolted plate with gasket, a barrel top with gasket. Pipes may be closed with pipe caps or "Kam-Lok" devices. (Sup. witness7 Doc. on check-off sheet)
References
- 1. Filtration/Demineralization System, Unit No. 3 - Desigg Analysis and Specifications - Chem-Nuclear Systems, Inc. Nov. 10, 1978.
- 2. Demineralizer De-watering Test - Chem-Nuclear Systems, Inc. - E0-204, Dec. 6, 1979
'* ' I ....
SALEM ation Protection PD-15.7.016 GENERATING Instruction DEMINERALIZER OPERATION AND DE-WATERING PAGE 6.0F7 STATION REVISION o
- U<.TION l.EG-I
~ ;-
'------- J
~
J L ATTACHMENT 1
SALEM Ra ation Protection 9 PD-15.7.016 GENERATING Instruction SECURING BEMINERALIZER OPERATIONS PAGE 1 OF 1 STATION AND DE-WATERING REVISION o SPENT DEMINERALIZER SHIPMENT PREPARATION CHECK-OFF FORM
- 1. Has the 10 Cu. ft. filter been de-watered by procedure step A.4 or B.4?
YES NO_ _
Supervisory Witness ------------------------
- 2. Has the 195/300 Cu. ft. demineralizer, Serial *--------~-----'
been initially dewatered by procedure steps B.5 thru B.ll?
YES NO Supervisory Witness --------------~---------
- 3. Has the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or prior to shipment if greater that 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> de-water been completed as required by procedore step.B.15?
YES NO Supervisory Witness -----------------------
- 4. Is the center annulus standpipe water level less than 2" as required by procedure step B.16?
YES _ _ _ NO_ _
Inspection Bold Point QC -------------------------
- 5. Is the access port adequately closed as required by procedure step B.18?
YES _____ NO_ _
Supervisory Witness --------------------------
Rad Waste Supervisor QC ATTACHUENT 2
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