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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20202E1611997-12-0101 December 1997 IST Program Third Ten Yr Interval Submittal. W/32 Oversize Drawings ML20211Q1221997-10-14014 October 1997 Rev 22,change 2 to OP-1903.011, Emergency Response Notifications ML20198J8081997-10-14014 October 1997 Rev 28,Permanent Change 2 to Procedure/Work Plan 1903.061, Communications Equipment Tests ML20217K3001997-08-0808 August 1997 Change PC-03,Rev 21 to Work Plan 1903.030, Evacuation ML20151K2241997-07-29029 July 1997 Change PC-01,Rev 6 to OP-1903.035, Adm Potassium Iodide ML20148T0441997-07-0101 July 1997 Change PC-01 to Rev 12 to Procedures OP-1903.067, Emergency Response Facility - Emergency Operations Facility (Eof) ML20148T0221997-07-0101 July 1997 Change AP-06 to Rev 6 to Procedure OP-1903.035, Adm Potassium Iodide ML20148T0051997-07-0101 July 1997 Change PC-01 to Rev 32 to Procedure OP-1903.060, Emergency Supplies & Equipment ML20141C5421997-06-17017 June 1997 2 to Procedure Work Plan 1903.065, Emergency Response Facility Technical Support Center (Tsc) ML20148T5391997-06-0101 June 1997 Rev 0 to Third Ten-Year Interval ISI Plan for ANO Unit 1 ML20140C0951997-03-26026 March 1997 Rev 11,Change AP-11,to OP-1903.034, Emergency Operations Facility Evacuation ML20137D9271997-03-18018 March 1997 Rev 21-04-00,Change PC-04 to OP-1903.011, Emergency Response/Notifications ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20115D8901996-07-10010 July 1996 Permanent Change (Pc) PC-03 to Rev 11 to OP-1903.065, Emergency Response Facility Tsc ML20107G3981996-04-17017 April 1996 Rev 4 to Procedure 1903.053, Logistical Support, Combining Procedures 1903.054 & 1903.078 in W/Procedure 1903.053 & Deleting Procedures 1903.054 & 1903.078 Completely ML20107G4231996-04-17017 April 1996 Rev 4 to Procedure 1903.078, Emergency Response Support, Deleting Procedure.Info from Procedure Incorporated Into Procedure 1903.053, Logistical Support ML20107G4011996-04-17017 April 1996 Rev 6 to Procedure 1903.054, Addl Personnel, Deleting Procedure.Pertinent Info,Instructions & Requirements from Procedure Will Be Incorporated Into Procedure 1903.053, Logistical Support ML20101E3851996-03-13013 March 1996 Rev 15 to OP-1903.062, Communication Sys OP Procedure ML20101E3571996-03-13013 March 1996 Rev 28 to OP-1903.061, Communication Equipment Test ML20101E3771996-03-13013 March 1996 Rev 8 to OP-1903.066, Emergency Response Facility Osc ML20097B2221996-02-0606 February 1996 Change AP-33 to Rev 33 to OP-1903.010, EAL Classification ML20095F9611995-12-0707 December 1995 Permanent Change (Pc) PC-02 to Rev 27 to Procedure/Work Plan OP-1904.002, Offsite Dose Projection Rdacs Computer Method ML20091K8261995-08-28028 August 1995 Change PC-1 to Rev 9 to Procedure/Work Plan 1903.067, Emergency Response Facility - Eof ML20087B6431995-08-0808 August 1995 Rev 27 to Procedure/Work Plan 1904.002, Offsite Dose Projection Rdacs Computer Method ML20086B3901995-07-0505 July 1995 Rev 9 to Procedure/Work Plan 1903.067, Emergency Response Facility - Eof ML20084U7381995-06-13013 June 1995 Page 14 of Rev 20 to Procedure/Work Plan 1903.011, Emergency Response/Notifications ML20084L9881995-05-25025 May 1995 Rev 20 to Procedure/Work Plan 1903.011, Emergency Response/ Notifications ML20097B2201995-05-16016 May 1995 Change PC-2 to Rev 31 to OP-1903.060, Emergency Supply Equipment ML20083Q2961995-05-16016 May 1995 Rev 13 to Procedure/Work Plan 1905.002, Offsite Emergency Monitoring ML20083Q3071995-05-16016 May 1995 Rev 31 to Procedure/Work Plan 1903.060, Emergency Supplies & Equipment ML20083Q2891995-05-16016 May 1995 Rev 6 to Procedure/Work Plan 1903.064, Emergency Response Facility - Cr ML20083L6171995-05-0505 May 1995 Rev 9 to Procedure/Work Plan 1903.034, EOF Evacuation ML20083L6141995-05-0505 May 1995 Rev 4 to Procedure/Work Plan 1905.031, Airborne I-131 Determination Using RM-14.HP-210 ML20083L5941995-05-0505 May 1995 Rev 5 to Procedure/Work Plan 1905.004, EOF Radiological Controls ML20082E2211995-03-31031 March 1995 Rev 1 to Procedure/Work Plan 1903.068, Emergency Response Facility - Emergency News Center ML20081K0331995-03-16016 March 1995 Rev 27 to Procedure/Work Plan 1903.061, Communications Equipment Tests ML20078R0771995-02-0909 February 1995 Rev 21 to Procedure/Work Plan 1903.030, Evacuation ML20078G8921995-01-26026 January 1995 Rev 30 to Procedure/Work Plan 1903.060, Emergency Supplies & Equipment ML20078J1101995-01-13013 January 1995 Public Version of Rev 14 to Operating Procedure 1903.062, Communication Sys Operating Procedure ML20095J6271995-01-0303 January 1995 Permanent Change (Pc) PC-01 to Rev 11 to Procedure/Work Plan OP-1903.065, Emergency Response Facility Tsc 1999-08-04
[Table view] |
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ARKANSAS' PO'WER & LIGHT COMPANY 4k Arkansas Nuclear One j
( @ RECORD OF CHANGES AND REVISIONS FOW NO.
1000.06A Nin'T0 ACTIVE WASTE CONTROL REV. # 12 PC # j
'{# DISPOSAL OF SPENT l Safety Related YES s NO O
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.'PAGE REV PC# PAGE REV PC# PAGE REV PC# PAGE REV PC# PAGE REV PC#
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APPROVED BY: APPROVAL DATE
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(General Manager)
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8303290230 830225 PDR ADOCK 05000368 P PDR
l PLANT MANUAL SECTION: PROCEDUAE/ WORK PLAN TITLE: NO-RADIOACTIVE WASTE enMTDAT DT qpnqaf _ np CDFMT DanTnarTTVR QF9TM 160'4 006 PAGE 1 n f r, ARKANSAS NUCLEAR ONE aEvisioN i oATE iO/22in2
(- CHANGE DATE 1.0 PURPOSE The purpose of this procedure is to delineate the sequence of actions re-quired for the disposal of spent radioactive resins, and to document the v~Ws.:_t erC c. critical;p'ot t'iohs~~oT-these act' ions.4- a'
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~ ~- ~ ~-E7MNM M 2.0 SCOPE This procedure applies to spent radioactive resins generated at ANO.
3.0 REFERENCES
i 3.1 References used to develop this procedure.
i None 3.2 References used to implement this procedure.
3.2.1 1104.02, " Makeup and Purification System Operation" 3.2.2 1409.26, " Resin Transfer from T13 to Transfer Cask" l
l 3.2.3 2104.17, " Spent Resin Transfer" (k 3.2.4 2409.13, " Resin Transfer from 2T13" 3.2.5 1622.003, " Radiological Posting Requirements" l 3.2.6 1622.007, "ALARA Job Covarage Practices" 3.2.7 Hittman Nuclear and Development Corp. STD-P-05-004 Process Control Program for Incontainer Solidification of Bead Resin. ,
3.2.8 Chem Nuclear Systems, Inc. procedure FO-AD-002 " Operating Guidelines for Use of Polyethylene High Integrity Containers".
3.2.9 Chem Nuclear Systems, Inc. procedure FO-OP-003 "De-Watering Bead Resins in a Conical Bottom High Integrity Container to less than 1% Free Standing Water.
3.2.10 Chem Nuclear Systems, Inc., procedure FO-0P-015-436 " Operating Procedure for Resin Transfer and Dewatering of Bead-Type Resins at Arkansas Power & Light - Arkansas Nuclear One.
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T PLANT MANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO:
. RADI0 ACTIVE WASTE enMTDnf nTRPnghi AF 9PFMT DaninAFTTVF RF97H 1601 006 PAGE 7 nf 6
( ARKANSAS NUCLEAR ONE aevision CHANGE i oATE DATE in/22iR2 t
1 3.3 Related ANO Procedures 3.3.1 1000.31, " Radiation Protection Program" T '* 7:"~~ 3.3.2" 1000.337."ALARk Manual"':ry. ..s... ' ;r: :m , _ ,_ n,_
3.3.3 1603.003, " Radioactive Material Shipments" 3.3.4 1603.007, " Control of Radioactive Material" 3.3.5 1603.010, " Handling of Radioactive Material Containers" 3.3.6 1612.003, " Radiological Work Permits" 4.0 DEFINITIONS None 5.0 RESPONSIBILITIES 5.1 The Radioactive Waste Coordinator is responsible for the following items:
5.1.1 Arranging contractor for resin handling and transportation
( services. I 5.1.2 Securing a work area for resin transfer and packaging.
(This is normally the west end of the train bay).
5.1.3 Coordinating the various ANO Departmental functions.
NOTE: For the disposal of spent radioactive resins, the Radioactive I Waste coordinator is normally the supervisor in charge. .
5.2 The Health Physics Superintendent is responsible for providing an ade-quate number of Health Physics Technicians to provide radiological l
protection.
l 5.3 The Hechanical Maintenance Superintendent is responsible for providing -
an adequate number of Hechanical Maintenance personnel to provide main-tenance support.
)
5.4 The applicable Unit's Shift Supervisor is responsible for providing l sufficient personnel to transfer the resin from the holding tank to I the disposal container.
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PLANT MANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO: ,
RADIOACTIVE WASTE cnument nigpogAt er gppy7 gAgInACyrve occin 1An1 nnA PAGE q np g ARKANSAS NUCLEAR ONE aEvision o*TE ;
( CHANGE 1
DATE inie,ia, 5.5 The Radiochemistry Supervisor is responsible for providing personnel to obtain and analyze a sample of the resin to be disposed of.
6 M EEREQU,ISITES __ , _ ,_
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. . . . .. _ . ~ . . . .. = _ _ . .
6.1 An ALARA review has been completed, and an RWP has been issued.
6.2 A transportation cask or another shielded container is available to move the disposal container.
6.3 If applicable, sufficient contractor personnel have arrived and have been issued TLD's.
6.4 The work area has been lined with protective material.
6.5 The disposal container has been placed inside the shielded container.
6.6 The applicable Unit's Shift Supervisor has been notified that the pre-requisites have been completed and has given his permission to commence the werk.
7.0 INSTRUCTIONS ,
( NOTE: Unless specified, the following steps may be worked simultaneously.
7.1 Place the cask in the work area and wrap with protective covering to avoid contamination of the trailer or cask.
7.2 If necessary, realign the resin transfer hose to the appropriate con-nection as follows:
7.2.1 Health Physics shall set up the area in accordance with the ,
RWP and good radiological practices. Approximately one gallon l of water should be anticipated to leak out when the system is broken.
l Area Set Up Complete a Health Physics Technician l
l l 7.2.2 Unit One and Unit Two operations shall perform a valve lineup, as applicable, in accordance with the applicable i procedures listed in Section 3.2.
l Valve Lineup Complete Waste control Operator i
PLANT MANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO: i RADIOACTIVE WASTE CO - OL DISP 0c AE OF SPE" P2DI m-me orem innt nnc PAGE g np g i ARKANSAS NUCLEAR ONE ams= 1 oarE . in,,,ia, CHANGE DATE 7.2.3 Connect the resin transfer hose to the appropriate connection.
Catch basine or similar devices shall be erected to control l leakage. I
- .c . . J' 7 tasi -.. .gepid' Transfer" Hose'C[nnTcYed#~" ~" # " " " " -
to Appropriate Connection and Catch Basins Erected Mechanic 7.3 Obtain permission from the Unit One Shift Superviser and a Health Physics Supervisor to raise the train bay access hatch to the Unit One Auxiliary Building. Raise the hatch and connect the hoses to the disposal container.
7.3.1 Permission granted to raise hatch HP Supv.
7.3.2 Permission granted to raise hatch Unit one Shift Supervisor NOTE: This step is not applicable if the resin transfer is not being done in the Train Bay.
7.4 Complete contractor (if used) and radiological equipment setup in the
( work area.
7.5 Transfer the resin in accordance with the appropriate procedures listed in Section 3.2. Adequate precautions shall be taken in accordance with the RWP and Health Physics instruction to maintain exposures ALARA.
Secure resin transfer upon instructions from Health Physics or the Radio-active Waste Coordinator, or other involved personnel.
7.6 De-water the transferred resin in accordance with the applicable con- ,
tractors procedure as listed in Section 3.2.
l I NOTE: De-watering to be performed by contractor using contractors proce-
, dures and not by AP&L.
l l 7.7 Repeat Steps 7.5 and 7.6 until the required amount of resin has been l transferred.
7.8 Radiochemistry shall obtain and analyze a sample of the de-watered resin.
! A copy of the sample results shall be provided to the Radioactive Waste l Coordinator.
Resin Sample for Analysis Radiochemist l(
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PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO: 4 l
RADIOACTIVE WASTE
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( ARKANSAS NUCLEAR ONE aEvisioN CHANGE
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- DATE inie,in,
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7.9 If solidification is to be performed, disconnect the transfer o hoses and replace the hatch.
NOTE: When the connection to the disposal container is broken, highly
~,.~6 O _ , L _.://WCconinated resin beads "and/6r 'w~a~t'eFifayTk' ou6 6f 'thelose He C)L l 7.9.1 Perform solidification in accordance with the applicable con-tractors procedures listed in Section 3.2. -
NOTE: Solidification to be performed by contractor using contractors procedures and not by AP&I..
7.10 If resin is to be shipped in a de-watered form, complete dewatering in accordance with the applicable contractor's procedure listed in Section 3.2.
NOTE: Dewatering to be performed by contractor using contractors procedures and not by AP&L.
7.10.1 After completion of de-watering, disconnect hoses and replace the hatch, as applicable.
NOTE: When the connection to the disposal container is broken, highly contaminated resin beads and/or water may leak
( '
out of the hose.
7.11 Install and seal the lid on the disposal container.
7.12 Remove the protective covering from the cask and trailer. This material should be set aside for decontamination.
7.13 Health Physics shall perform a comprehensive radiation and contamination ,
survey of the cask and trailer. The maximum allowable y contamination l is 1,000 dpm/100cm2 Decontaminate the cask and trailer as necessary. A copy of the completed survey shall be provided to the Radioactive Waste Coordinator.
7.13.1 Cask and trailer is acceptable for transfer to radwaste.
l HP Technician 7.14 Remove the trailer from the work area and store as directed by the Radio-active Waste Coordinator. Post the storage area in accordance with 1622.003 " Radiological Posting Requirements".
7.14.1 Storage area properly posted HP Technician j
NOTE: If further resin transfers are to be performed prior to job completion, repeat steps 7.1 through 7.14 as appli-cable.
T PLANT MANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO: !
RADI0 ACTIVE WASTE
('nMTDnf MTCpochi n9 A p9hfT DanTnarTTVF RFCTM 1601 006
_PAGE 6 nf 6 ARKANSAS NUCLEAR ONE aevisioN i oArm in/>>in,
( CHANGE DATE 7.15 After completion of the final resin transfer, decontaminate the equip-ment, used protective coverings, and the work area.
7.16 Haterial that was not successfully decontaminated shall be packaged f 2. ._ -.. - ~Mnd 'surv6?edTin~ acMance'with71603'.'010 '"HandlSf Ra'dioactive .A 'C d Haterial Containers" and transferred to the Radioactive Waste Storage Building in accordance with 1603.007 " Control of Radioactive Haterial" for storage or disposal.
7.17 Health Physics shall perform a comprehensive contamination survey of the work area and decontaminate as necessary.
7.17.1 Work Area released for unrestricted access.
HP Supervisor 8.0 FORMS AND ATTAC191ENTS None
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