ML20114B982
| ML20114B982 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/04/1992 |
| From: | Knopp R, Denise Wilson IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML20114B975 | List: |
| References | |
| 3410.1, NUDOCS 9209010031 | |
| Download: ML20114B982 (27) | |
Text
e a
i.--.,--,-..--.,., .
RADWASTE HANDLING PROCEDURE 3410.1 PROCESS CONTROL PRO _ GRAM FOR WET RADIOACTIVE WASTES March 19, 1992
( DUANE ARNOLP ENERGY CENTER
! IOWA ELECTRIC LIGHT AND POWER COMPANY l
A'pproved by: WS Date: 2'/.' 92 Radwaste Supervisor l / /
i' Reviewed by: I 6 // -
Date: 2 ,2 ALARA Coordinator '
Approved by: '
M. b Date:
RadiatioY) Protection Manager Reviewed by:o -
Date: ,
ir an, operations Committee Approved by: Date: IA Plant Superintendent - Nuclear 1
STOP, CHECK AND THINK Date: 3-19-92 Page 1 of 27 Rev. 2 RWH 3410.1 9209010031 920821 11 PDR ADOCK 05000331 R PDR
- a. ,
1 4 ,
TABLE OF CONTENTS PAGE 1.0 PURPOSE 4 2.0 PRECAUTIONS AND LIMITATIONS 5 3.0 INSTRUCTIONS 6 3.1 ADMINISTRATIVE CONTROLS 6 3.1.1 Procedures and Verifications 6 3.1.2. Training 7 3.1.3 Quality Assurance / Quality Control 8 3.1.4 Radioactive Waste Manifests and Tracking 9 3.1.5 Requirements for Use of Vendor Processing Services 10
- 3. 2 WASTE CHARACTERISTICS 11 3.2.1 Waste Streams, Sources,-and Types 11 3.2.2 . Waste Classification 14 3.2.3 Waste Form 15 3.3 REQUIREMENTS FOR DEWATERING OF WET SOLID RADI0 ACTIVE WASTE 15 3.3.1 Resins, Sludges, and Other Homogeneous Waste 15 3.3.2 Aqueous Mechanical Filter Elements. 17 Date: 3-19-92 Page 2 of 27 Rev. 2 RWH 3410.1 12
I
. ~.
TABLE OF CONTENTS PAGE I
4 3.4 REQUIREMENTS FOR SOLIDIFICATION OF WET SOLIO AND LIQUID 17 '
RADIOACTIVE WASTES 3.4.1 Batch Sampling, Analysis and Testing for 17 Solidification 3.4.2 Solidified Class A, Class 8 and Class C Waste 19 Products 3.4.3 Solidification Boundary Conditions 20 4.0 RECORDS 21 5,0 REFERENCES 21 APPENDIX 1 - Processing Vendor Dewatering System Description 24 APPENDIX 2 - Processing Vendor Solidification System Description 27 Date: 3-19-92 Page 3 of 27 Rev. 2 RWH 3410.1 13
[
1.0 PURPOSE (1) This procedure establishes the wet radioactive waste Process Control Program for the Duane Arnold Energy Center (DAEC).
(2) The Process Control Program is applicable to solidification, dewatering and/or stabilization of wet solid radioactive wastes generated as a result of the operation and maintenance of the DAEC.
(3) The Process Control Program is applicable to solidification and/or stabilization of liquid radioactive wastes generated as a result of the operation and maintenance of the DAEC.
}
(4) The requirements of this Process Control Program apply to wet solid #
radioactive waste or liquid radioactive waste processing for disposal <
performed by DAEC personnel or by vendor (s) at the DAEC.
(5) The Process Control Program provides the administrative controls and '
process boundary conditions to ensure compliance with Federal and State regulations regarding radioactive waste form requirements for near-surface disposal.
(6) This Process Control Program does not apply to mixed wastes (low-level radioactive and hazardous wastes) for which disposal techniques and facilities do not currently exist.
(7) This Process Control Program does not apply to wet radioactive wastes prepared for shipment from the DAEC to an off-site waste processing facility that will further process the waste for disposal.
(8) This Precess Control Program does not apply to irradiated hardware components or other wastes which are considered inherently stable under the waste form requirements of 10 CPR 61.
Date: 3-19-92 page 4 of 27 Rev. 2 RWH 3410.1 14
2.0 PRECAUTIONS AND LIMITATIChis (1) A processed waste form suspected or known to not comply with waste form requirements shall not be shipped for disposal until full assurance of satisfactory waste form can be established.
(2) Wet solid radioactive wastes are produced from the installed liquid radwaste system or temporary local installations used for system decontamination or desludging operations, They include, but are not 1imitod to:
(a) bead ion exchange resins, (b) powdered ion exchange resins,
.) filter precoat media, (d) waste sludges, (e) charcoals and other (Nueous filter aid media, (f) mechanical aqueous filters.
(3) Liquid radioactive wastes include aqueous and non-aqueous wastes, such as decontamination solutions or oils, not suitatle for treatment using the installed liquid radwaste system.
(4) Miscellaneous radioactive waste materials such as metals, control rod drive r echanism f t iter / strainer cartridges, piping or scrap, or otFer materials may be placed into a High Integrity Container or liner for disposal with wet radioactive wastes, in accordance with the Processing Vendor's approved procedures.
Date: 3-19-92 Page 5 of 27 Rev. 2 RWH 3410.1 15
(
(5) lWasta ptocessing by a vendor shall be accomplished using a Topical Report / Process Control Program accepted by the Nuclear Regulatory
-Commission-(NRC) for reference by licensees, 3.0 INSTRUCTIONS 3.1 ADMINISTRATIVE CONTROLS 3,1.1 Procedures and Verifications (1) The DAEC Radwaste group maintains, or requires the Processing Vendor to maintain, procedures that implement the requirements of the DAEC Process Control-Program.
(a) The DAEC Radwaste and/or Processing Vendor's procedures must provide documentation of the performance of key steps, verifications, and process end points.
-(2) The DAEC Radwaste and/or Processing Vendor's procedures must include acceptable methods for:
(a) Waste Classification under 10 CFR 61.55, or equivalent disposal facility license requirements.
(b) Sampling of radioactive waste and analysis for difficult-to-measure radionuclides to meet the requirements of 10 CFR 61.55 and the NRC' Low-level Waste Licensing Branch Te:hnical Pusition on Radioactive Waste Classification.
(c) Waste processing to meet waste form requirements of 10 CFR 61.56, the NRC Low-level Waste Licensing Branch Technical Position on Waste.-Form and specific disposal site criteria.
l l
l l
- j. Date: 3-19 'J2 Page 6 of 27 Rev. 2 RWH 3410.1 L
16 l
l
e
_(3) The Processing Vendor must provide site-specific operating Procedures for the processing system, and have a document control program established for control of subsequent revisions to procedures.
(4) Reviews of the Processing Vendor's site-s9ecific procedures are performed by the UAEC Radwaste Group prior to use at DAEC.
(5) Procedures for wet radioactive waste processing shall include second party verification of key steps and process end points (such as loss of dewatering vacuum or free liquid verifications).
(a) When wet radioactive waste processing has been performed by the Processing Vendor, the second party check (s) must be performed by DAEC staff.
(6) The DAEC Radwaste group is responsible for ensuring that applicable requirements of this Process Control Program procedure are met prior to shipment of a radioactive waste processed under the Process Control
-Program.
3.1.2 Training
-(1) DAEC and contract Radwaste staff involved in processing wet radioactive waste' for. disposal are providnd, as needed by job _
function, with training in:
(a) DAEC radwaste processing policies and procedures, (b) Regulatory disposal requirements, (c) . Radioactive material transportation requirements, and/or (d) ' Disposal site criteria.
i Date: 3-19-92 Page 7 of 27 Rev. 2 RWH 3410.1 17
4 (2) -Training and/or retraining for DAEC and contract Radwaste staff should be held as needed to support processing operations or to implement operational changes; however, the frequency of retrat ing should not exceed 2 years.
(3) Written record of equivalent training for Processing Vendor personnel performing waste processing e' DAEC shall be maintained.
3.1.3 Quality Assurance / Quality Control (1) Quality Assurance audits of the Process Control Program and implementing procedures are conducted at leest once per 24 months under the cognizance of the DAEC Safety Committee, as required by Technical Specification 6.5.2.8.
(2) Quality Assurance audit findings are reviewed by DAEC management to ensure prompt corrective actions when needed.
(3) Iowa Electric's Quality Assurance program, as applied to the processing, packaging, and transportation of wet radioactive waste, is L subject to 10 CFR Part 50, Appendix B.
(4) Services and materials for wet radioactive waste processing, packaging, and transportation of greater than Type-A quantities are procured as Quality Level II, and are procured in compliance with 10 CFR Part 71 and 49 CFR Parts 171, 172, and 173.
(5) Quality Control staff provides verification of process end points and/or acceptance criteria in DAEC and Process Vendor procedures.
Date: 3-19-92 Page 8 of 27 Rev. 2 RWH 3410.1 18
-,. . . ~ - -
-(6) Quality Control staff provides independent review of documentation generated from implementing procedures:for waste processing, container handling and closure, and preparation for shipment.
(a) The <umentation must be maintained as Quality Assurance records in accordance with the OAEC QA Manual, Appent s A, and Technical Specification 6.10.1.7.
(7) Failure to comply with DAEC Quality Assurance and/or Quality Ccatrol requirements, or unsatisfactory verification results, is sufficient to prohibit shipment off-site of the affected waste until evidence of adequate corrective action can be shown.
3.1.4 Radioactive Waste Manifests and Tracking (1) Manifests are prepared for each shipment of radioactive waste for disposal in accordance with 10 CFR 20.311, Transfer for Disposal and Manifests.
(2) Radwaste Handling Procedures for manual and/or computer;7ed preparation of waste manifests implement the applicable requirements of 10 CFR 20.311.
(3) Acknowledgement of receipt for each shipment of radioactive waste to a disposal site is sent to the DAEC Radwaste Group.
NOTE Additional guidance on-_ reporting requirements for shipments requiring a trace are contained in DAEC ACP 1402.3, Plant Regulatory Reporting L Requirements. .
(a) Shipments for which' acknowledgement of receipt is not received within the time limits allowed in 10 CFR 20.311 are traced by the OAEC Radwaste Group.
Date: 3-19-92 Page 9 of 27 Rev. 2 RWH 3410,1 13 J- v
I (b) Upon completion of the trace investigation by DAEC, a report shall be filed with NRC Region 3 within two weeks of completion.
3.1.5 Requirements for Use of Vendor Processing Services (1) Prior to first use of a vendor-supplied waste processing system at the DAEC, ensure that the following criteric are satisfied:
(a) The vendor has supplied a detailed system description, including all needed interfaces between vendor equipment and DAEC systems.
(b) The vendor system, operating precedures, process control program, and acceptance testing have been submitted to the Nuclear Regulatory Commission (NRC) in a Topical Report. The Topical Report shall have been accepted by the NRC for reference in licensee Process Control Programs.
(c) The vendor can provide site-specific operating procedures for the processing system, and has a document control program for control of subsequent revisions to procedures.
(d) Reviews of the Processing Vendor's site-specific procedures are performed by the DAEC Radwaste Group prior to use at DAEC. _
(e) An evaluation is performed by DAEC to ensure that use of the system in compliance with the site-specific operating procedures will produce an acceptable solidified, dewatered, and/or stabilized waste form for the specific types of wet radioactive wcstes generated at DAEC.
Date: 3-19-92 Page 10 of 27 Rev. 2 RWH 3410.1 20
(2) Vendor-supplied waste processing system (s) used at the DAEC should be engineered to_ provide:
(a) Remote or semi-remote operations in order to maintain dose As Low As Reasonably Achievable (ALARA).
(b) Container level indication, overflow protection, temperature monitoring, and other process indicators as needed for the type of waste process.
(c) High efficiency particulate air (HEPA) filter or other acceptable means for controlling the system exhaust path.
(3)- Vendor-supplied waste processing system (s) used at the OAEC shall be operated in accordance with the Topical Report requirements and in accordance with the DAEC Process Control Program.
3.2 WASTE CHARACTERISTICS 3.2.1 -Waste Streams, Sources, and Types (1) Various wet solid radioactive waste streams result from the operation and maintenance of the DAEC. The waste streams include, but are not limited to, the following sources of resins, sludges, and mechanical filters:
, (a) Reactor water clean-un filter-demineralizer resins (b) Fusl pool filter-demineralizer resins (c) Condensate filter-demineralizer resins (d) Radwaste (Equipment and Floor Drain) Powder filter precoat media
. (e) Radwaste (Equipment and Floor Drain) Deep Bed demineralizer resins Date: 3-19-92 Page 11 of 27 Rev. 2 RWH 3410.1 21
1 L'
(f) Filter backwash and radwaste tank sludges (g) Aqueous filter aid media, such as charcoals, activated carbons, and charcoal / resin mixtures.
(h) Miscellaneous mechanical aqueous filters from installed systems and/or from temporary decontamination or desludging operations.
(2) Resins and sludges are transferred to the Radwaste Solids Handling System for accumulation, storage, and decay-, Resins and sludges can also be produced from temporary local installations. The waste media can then be transferred to a waste holding tank piped directly to the Processing Vendor's system.
(3) Wet solid radioactive waste types such as bead ion exchange resins, powdered ion exchange resins, filter precoat media, waste sludges, -
charcoals and other aqueous filter aid media, and mechanical aqueous filters may be processed by dewatering or solidification.
'a) Stability may be achieved by the waste form itself, by processing the waste to a stable form, by placing the waste into a container which provides stability, or by placing the container into a structure that provides stability after disposal. i NOTE Liquid waste treated by absorption shall not be shipped to the Barnwell Waste Management Facility.
Date: 3-19-92 Page 12 of 27 Rev. 2 RWH 3410.1 22
4 -
(4) _ Liquid radioactive aqueous and non-aqueous waste types, such as decon* idnation solutions or oils, not suitable for treatment using the in,talled liquid radwaste system may be processed by absorption (if permitted by the disposal site) or by solidification.
_( a) Aqueous _ liquids should be volume reduced when practicable, using approved plant procedures.
NOTE Wastes which are inherently stable, such as reactor components, are not -
subject to this Process Control Program.
(5) Miscellaneous radioactive waste materials such as metals, control rod drive mechanism filter / strainer cartridges, piping or scrap, .
. mechanical aqueous filters or other materials may be placed into a High Integrity Container or liner for disposal with wet radioactive wastes in accordance with the Processino Vendo 's procedures.
(a) This method of disposal of miscellaneous materials should only be performed for ALARA, volume reduction, or packaging efficiency reasons. _
(b) The material shall be packaged in a such a manner that ensures protection of the High Integrity Container or liner, in accordance with Processing _ Vendor procedures.
(c) The common method _involycs placement of the miscellaneous materials onto a resin, sand, or other base within the High Integrity Container or liner. Any remaining void space within the container is filled with resin and dewatered in accordance with the_Prc:ess Control Program and Processing Vendor procedures.
Date: 3-19-92 Page 13 of 27 Rev. 2 RWH 3410.1 23
i e, *
.l 2 3.2.2 Waste Classification 1 (1) Scaling factors are developed for the identified waste streams which relate difficult-to-measure (DTM) radionuclides to key gamma-emitting l radionuclides commonly detected in DAEC wet radioactive wastes.
(a) Scaling factors may be developed or updated on an as-needed basis depending on changing plant operational conditions. A change by a factor of 10 (high or low) from existing data may indicate the need for updating the scaling factors.
(b) Radioactive wastes that are typically Class A should have updated scaling factors at least every two years.
(c) Radioactive wastes that are typically Class B, Class C, or that have a high probability for shifting waste class should have u; .ted scaling factors at least once per year.
(2) Waste materials which do not fit within the scope of existing scaling factors and/or waste streams are sampl ad, sent' of f-site for OTM analysis, and have scaling factors developed prior to disposal of the material.
(3) These scaling factors are used in the classifte tion of radioactive waste for disposal in accordance with 10 CFR 61.55, or equivalent disposal: facility license requirements.
(4)~ Datch samples, separator resin or sludge samples are taken for on-site gamma radioisotopic analysis as needed for waste classification determinations.
i Date: 3-19-92 Page 14 of 27 Rev. 2 RWH 3410.1 a
i 3.2.3 Waste Form (1) Wet radioactive waste shall be processed to ensure that the minimum '
physical characteristics required by 10 CFR 61.56 and disposal site criteria are met.
(2) Class A aqueous filter media with a concentration greater than 1 uCi/cc of isotopes with half-lives greater than five years shall be l stabilized.
(a) Stability for this media is normally provided by use of a High integrity Container.
(3) Class A liquids may be absorbed (if permitted by the disposal site) or solidified, but are not required to be stabilized.
(4) All Class B and Class C wastes shall be stabilized.
(a) Stability for this media is normally provided by use of a High Integrity Container that is subsequently placed into an engineered .arrier structure.at the disposal site.
3.3 REQUIREMENTS FOR DER 1 RI M CF WET SOLIO RADIDACTIVE WASTE 3.3.1 Resins, $1udges, and Ociier Homogeneous k *
(1) Dewatering of resins, slu61e4 and other homogeneous wet solid wastes shall be performed in are 6 -!.uce with procedures reviewed by the DAEC Radwaste Group.
(2) Essential waste characteristics after processing shall be tested, documented arid then verified by a second party.
Date: 3-19-92 pa se 15 of 27 Rev. 2 RWH 3410.1 25
- - - - - - - - . - . - . - . _ - - . . - _ . . - _ . . - - . - . _ _ =
.-. 7 - -
(3) After processing, the waste must contain as little free standing and noncorrosive liquid as is reasonably achievable.
(4) Testing for free standing liquid shall be performed on each container of dewatered waste.
l (a) Acceptance criteria for volume of free standing liquid is established for the intended disposal site, and must be clearly stated in the dewatering procedure.
i (b) In the event that a container does not pass the testing for free standing liquid, the waste process must be repeated and retested until the accept. Se criteria are met.
(5) -Testing for ensuring liquid is noncorrosive shall be performed based on knowledge of the waste process (such as chcmical decontamination resins).
(a) Verification that dewatering influent and/or effluent pH is greater than 4 and less than ll, must be included in the procedure for dewatering applicable waste types.
(b) As needed, the pH of the_ waste source may be adjusted to meet the criteria for noncorrosivity.-
(6) High Integrity Containers used for dewatering shall be filled to at least the minimum capacity vsquired for the intended disposal site.
Date 3-19-92 Page 16 of 27 Rev. 2 RWH 3410.1 26
3.3.2 Aqueous Mechanical filter Elements (1) Aqueous mechanical filter elements may be dewatered by placement of the elements onto a resin, sand, or other base within a High Integrity Container or liner. Any remaining void space within the container is filled with r sin and dewatered in accordance with the Proce>> Control Progrem and Processing Vendor procedures.
(2) Aqueous mechanical filter elements may be dewatered by placement of the elements within a High Integrity Container or liner containing a wire-type basket or assembly for holding the elements in a fixed Q geometry to facilitate dewatering.
(3) The requirements of Section 3.3.1 shall apply to either method of .
dewatering aqueous mechanical filter elements.
3.4 REQUIREMENTS FOR SOLIDIFICATION OF WET SOLIO AND LIQUID RAD 10AC11VE WASTES NOIE Wet radioactive wastes are not currently solidified at the DAEC.
3.4.1 Batch Sampling, Analysis and Testing for Solidification ~
(1) Each waste batch to be solidified shall be sampled, a1alyzed, and tested to ensure compatibility with the parameters of the Process Vendor's Topical Report requirements, Process Control Program, and solidification formulas.
(a) A site specific procedure should be used to perform and document batch sampling, analysis, and testing.
Date: 3-19-92 Page 17 of 27 Rev. 2 RWH 3410.1
- ?
4 (2) A minimum of one sample from the waste batch shall be analyzed for gamma radionuclide content.
i (3) A minimum of three samples from the waste batch shall be tested using the anticipated solidification formula to verify adequate ,
solidification prior to the start of actual waste processing.
(a) As needed, tests should be performed to evaluate potential adverse chemical reactions with the waste solidification agents and/or catalysts. <
(4) If any test specimen fails to solidify, ensure the following is performed:
(a) Solidification of the batch under test shall not be performed until additional samples are obtained, alternative solidification parameters and/or formulas are determined, and subsequent tests verify solidification.
(b) Actual weste processing may then be performed using the alternative parameters and/or formulas, provided the procedures for the solidification process are updated to reflect the parameters and/or formulas to be used, (5) If no test specimen can be adequately solidified, suspend processing
~
of the waste batch, investigate for root cause (such as possible 1 chemical cross-contamination, presence of oils, et cetera), and determine alternative method (s) for processing the waste batch, l
Date: 3-19-92 Page 18 of 27 Rev. 2 RWH 3410.1 28 s . . - _ - , -, , _ . . . - - . _ . . . _ . _ _ _ - - _ . - . . - . _ _ . _ . ~ , _ _ . , _ , . _ . _ . . . _ . . . . _ _ _
e 4
3.4.2 Solidified Class A, Class B and Class C Waste Products (1) Solidtitcation of Class A 11gulds, resins, sludges, and other homogeneous tat wastes shall be performed and documented in accordance with procedures, the Processing Vendor's Process Control Program and the requirements of this Process Control Program.
(2) Solidified Class A waste products which are not required to be stabilized and which will be separated from Class B and Class C wastes at the disposal site must meet the following:
(a) Essential waste characteristics after processing shall be tested, documer',ed and then verified by a second party.
(b) Af ter processing, the waste must contain as little free standing and noncorrosive liquid as is reasonably achievable.
(c) Testing for free standing liquid shall be performed on each container of dewatered waste.
(d) Acceptance criteria for volume of free standing liquid is established at less than 0.5% of i:he waste volume, and must be clearly stated in the solidification procedure. _
(e) In the event that a container does not pass the testing for free standi;g liquid, the affected waste container shall not shipped for disposal until adequate corrective action is taken and until the acceptance criteria are met as shown by retesting.
(f) After processing, the waste must be a free standing monolith.
Date: 3-19-92 Page 19 of 27 Rev. 2 RWH 3410.1 4
29
.. .. _ _ ~ . . - - _ . _ _ _ _ . - . _ _ _ _ _ _ . _ _ - . _ - __ .
-__.7_._.
(3) Solidified Class A waste products which are required to be stabilized and which will not be separated from Class B and Class C wastes at the disposal site must meet the following:
(a) The requirements listed in Steps 3.4.2(1) and (2).
(b) The requirements and guidance provided in the NRC Low-level Waste Licensing Branch, Technical Position on Waste Form, Rev.1.
(4) Class B and Class C waste products which are stabilized by solidification must meet the following:
(a) The requirements listed in Steps 3.4.2(1) and (2).
(b) The requireroents and guidance provided in the NRC Low-level Waste Licensing Branch, Technical Position on Waste Form, Rev.1.
3.4.3 Solidification Boundary Conditions (1) Parameters that are used or monitored while performing solidification include, but are not limited to:
(a) Waste type (b) Waste pH (c) Rattos of waste / liquid to solidification agent / catalyst (d) Waste oil content (e) Principal chemical constituents or compounds of the waste (f) . Mixing and curing times (g) Adequacy of generic testing performed for tne Topical Report as compared to specific waste (s) at DAEC i
Date: 3-19-92 Page 20 of 27 Rev. 2 RWH 3410.1 30
(2) Acceptance criteria for solidification procedures must ensure that:
(a) Solidification is complete, as evidenced by a free standing monolithic form, having as little free standing and noncorrosive liquid as is reasonably achievable.
(b) Requirements of 10 CFR 61.56 and/or specific disposal site ,
criteria for waste form and stability are met, j (c) The waste container is filled to at least the minimum capacity required for the intended tiisposal site.
4.0 RECORDS (1) None
5.0 REFERENCES
(1). 10 CFR 20, Standards for Protection Against Radiation (2) 10 CFR 50, Domestic Licensing of Production and Utilization Facilities (3) 10 CFR 61, licensing Requirements for Land'Oisposal of Radioactive Waste (4) 10 CFR 71, Packaging and Transportation of Radioactive Material (5) 49 CFR Parts 17] to 180, Hazardous Materials Regulations (6) Quane Arnold Energy Center Updated Final-Safety Analysis Report, Chapter ll.4,. Solid Waste Management System Date 19-92 Page 21 of 27 Rev. 2 RWH 3410.1 31
. .. . . _ ._ _ . _ . _ ~ . _ -_ - _ . - .__ _ .
9
. = * .
(7) Duarie Arnold Energy Center Technical Specifications l
(8) Duane Arnold Energy Center Quality Assurance Manual, Appendix A (9) Duane Arnold Energy Center ACP 1402.3, Plant Regulatory Reporting Requirements 1
(10) Nuclear Regulatory Commission (NRC) Documents: I i
(a) NRC Low-Level Waste Licensing Branch, lechnical Position on Radioactive Waste Classification, Rev.0, May, 1983 (b) NRC Low-Level Waste Licensing Branch, Technical Position on Waste form, Rev.0, May, 1983 (c) NRC Low-level Waste Licensing Branch, Technical Pos111on on Wal_te Fo,rm, Rev 1, January, 1991 (d) NUREG-0800, USNRC Standard Review Plan, Chapter 11.4, Solid Waste Mana,qem.ent Systems, Rev.2, July,1981 (e) Inspection and Enforcement Bulletin 79-19, Packaging of Low-level Radioactive Watte for Transport and Burial (f) Inspection'and Enforcement Circular 80-18, 10 CFR 50,59 Safety Evaluations for Changes to Radioactive Wasie Treatment Systems (g) Information Notice 86-20, Low-Level Radioactive Waste Scalina Factors (h) Information Notice 87-07, Quality Control of Onsite DgwaterinalSolidification Operations by Outside Contractors Date 3-19-92 Page 22 of 27 Rev. 2 RWH 3410.1 32
- 7. ,
.- a + .
(1) Information Notice 88-08, Chemical Reactions with Reactive Waste
.$ojidification_fgents (j) Information Notice 89-27, limitations on the Use__of Wa_ste Forms and_Hlqh Integrity Containers for the_Dism sal of low-level RadioacLive Was_te 3
Date: 3-19-92 Page 23 of 27 Rev. 2 RWH 3410.1 33
. l APPENDIX 1 P roc e s sin.g Je n do r Dew a t e r i n g _Sy s t e m De s q_rJp tio n Page 1 of 3
- 1. VENDOR:
Scientific Ecology Group (previously Westinghoute-RS, and Westinghouse Hittman Nuclear)
- 11. TOPICAL RCPORT
REFERENCE:
$10-R-05-Oll-A, "Hittman Mobile Incontainer Dewatering and Solidification System" Accepted for reference by the US NRC on October 31, 1986, Ili, SYSTEM OR MElH00 IN USE: .
Vacuam dewatering of High integrity containers and/or steel liners using the Rapid Dewatering System (RDS) and/or the Press-Pak System (PPS).
IV, PLANT / VENDOR EQUIPMENT INTERFACES:
ll Resin / sludge transfer from the IT-60 EVAPORATOR BOTTOM TANK is performed though a permanently installed pipe, control valve, and terminates at a manual isolation valve C'-1) with quick connect hose fitting, Flexible hose is used to connect from the hose fitting to the process container.
Resin / sludge transfer from temporary local installations utilize a temporary' air. operated-transfer valve. From the temporary transfer valve, a-flexible hose is used to connect from the hose fitting to the process container. '
Dates- 3-19-92 Page 24 of 27 Rev. 2 RWH 3410.1 34
- I t . .
)
APPENDIX 1 6 (Continued)
Page 2 of 3
!V. (Continued) r Service air, water, and electric supply are interconnected to the Process ,
Vendor equipment for use in system operation.
The Process Vendor has local control of transfer flow to the processing container using CV-8250 SOLIDIFICATION CONTROL and the manual isolation valve (V-1) at the piping termination. Line flushing is accomplished using CV-8241 11-60 CONDENSATE FLUSH VALVE, as needed.
Dewatering effluent is piped to the radwaste floor drain system, terminating at the Conveyor Floor Drain Sump for return to the DAEC Liquid Radwaste System.
System venting to atmosphere is accomplished through a HEPA filter installed in the Pr' cess o Vendor's system, since no local off-gas connection is available.
Local radiation monitoring of the processing area is provided with Area Radiation Monitors having both local and remote alarms and readouts.
.Date: 3-19-92 Page 25 of 27 Rev. 2 RWH 3410.1 35
_ _ - _ . _ _...,_ . _ .. ~ ._. , _ - . - - . . _ .- _ _ . , . __
e
. APPENDIX 1 (Continued)
Page 3 of 3 V. SYSTEM DRAWING:
TEMPORARY LOCAL VDOOR INSTALLATION J
g TRANSFER VALVE TEMPERATURE g NONITOR y [ WASTE OVERFLOW I
WASTE DEWATERING TRANSFER
' I
- LINER LEVEL l LIE - - CCTV 1 l HEPA
" M l l FILTER l
] l l -@- ' '
l l
RADLOK v V ACUUMl l WASTE VACUUM PUMP- l l @@ OVERFt.0W t ; BOTTLE ORUli L
l FILL / DIVERT M -
'ONTROL DEWATERING VACUUM
~ F '
MANIFOLD RECEIVER LINER LEVEL PANEL TANK ASSEMBLY WMR COLLECTION DRUM i t _ _ - ;
l i
DEWbERINGb, g @
' y VACUUN pygp PUMP SKID DEWATERING y PUMP SKID o y n TO CONVEYOR i FLOOR ORAIN M - OPTIONAL l
Date: 3-19-92 Page 26 of 27 Rev. 2 RWH 3410.1 36
.+
APPENDIX 2 Processing. yencjgr Solidif_1 cation System Descrigtion Page 1 of 1
- l. VENDOR:
Scientific Ecology Group (previously Westinghouse-RS, and Westinghouse Hittn'ar. Nuclear)
- 11. TOPICAL REPORT
REFERENCE:
STD-R-05-Oll-A, "Hittman Mobile Incontainer Dewatering and Solidification System" Accepted for reference by the US NRC on October 31, 1986.
III. S. STEM OR METHOD IN USE: None in current use IV. PLANT / VENDOR EQUIPMENT INTERFACES: None in current use V. SYSTEM ORAWING: None in current use L
I Dates 19-92 Page 27 of 27 Rev. 2 RWH 3410.1 37
d
. 's io August 21, 1992
!G-92-3988 TO: T. Browning J. Klosterbuer K. Young K. Peveler P. Seckman D. Johnson T. Wilkerson K. Putnam J. Thorsteinson FROM: David L. Wilson Plant Superintendent - N~ clear
SUBJECT:
Semi-Annual Effluent Release Report January 1, 1992 through June 30, 1992, for the Duane Arnold Energy Center FILET NRC-7a, A-118e Please find enclosed a copy of the Semi-Annual Report for the Duane Arnold Energy Center, Unit No. 1, for the period January 1, 1992, through June 30, 1992. This report satisfies the requirements for the Semi-Annual Effluent Release Report, as stated in Section 6.11.lf of Technical Specifications, (Appendix A to the Operating License DPR-49).
$LLA Y David L. Wilson Plant Superintendent - Nuclear DLW/RL/hc
Attachment:
Semi-Annual Effluent Release Report A,
a t
lowa Electric Light and Power Company August .; 1, 1992 l
!L;-92-3 90 3 j
i l
Mr. A. Bert Davis Regional Administrator U.S. Nuclear Regulatory Commission Region III 1 799 Roosevelt Road i Glen Ellyn, Illinois 60137 !
l
Subject:
Semi-Annual Effluent Release Report January 1, 1992, through June 30, 1992, for the Duane Arnold Energy Center, Unit No. 1 Docket 50-331
Dear Mr. Davis:
Please find enclosed a copy of the Semi-Annual Report for the Duane Arnold Energy Center, Unit No. 1, for the period January.1, 1992, through June 30, 1992. This report satisfies the requirements for the Semi-Annual Effluent Release Report, as stated in Section 6.11.lf of Technical Specifications, (Appendix A to the Operating License DPR-49).
Sincerely, bA David L. Wilson Plart Superintendent - Nuclear DLW/RL/hc
Enclosure:
Semi-Annual Effluent Release Report cc Director'of Nuclear Regulatory Commission (original w/a)
Attn Document Control Desk U'S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D. C. 20555 NRC Resident Inspector (w/ attachment)
S. P. Sands, NRC Project Manager (w/ attachment)
J. Franz (w/o attachments)
File: A-118e, NRC-7a .!
.,.s a -?
(} k- j'f " j' w... ~
Duane ArnoM i nery Center
- 3:77 D ALC fload
- l'alo lana 3:324
- 319 831 ?611
a
.*.r.
AuTnt 21, 1992 NG-92-3988 TO: T. Browning J. Klosterbuer K. Young K. Peveler P. Seckman D. Johnson T. Wilkerson K. Putnam J. Thorsteinson FROM: David L. Wilson Plant Superintendent - Nuclear
SUBJECT:
Semi-Annual Effluent Release Report January 1, 1992 through June 30, 1992, for the Duane Arnold Energy Center FILE: NRC-7a, A-118e Please find enclosed a copy of the Semi-Annual Report for the Duane Arnold Energy Center, Unit No. 1, for the period January 1, 1992, through June 30, 1992. This repor satisfies the requirements for the Semi-Annual Effluent Release Report, as stated in Section 6.11.lf of Techni al Specifications, (Appendix A to the Operating License DPR-49).
N
$ltlh David L. Wilson Plant Superintendent - Nuclear DLW/RL/hc
Attachment:
Semi-Annual Effluent Release Report l
l
o
. =a.
Iowa Electric Light and Power Company August 21, IM2 NS-~92- n87 Department of Water, Air and Waste Management Henry A. Wallace Building 900 East Grande Avenue Des Moines, Iowa 50319 -
Re: Duane Arnold Enercy Center
Subject:
Semi-Annual Effluent Release Report January 1, 1992, through June 30, 1992, for the Duane Arnold Energy Center, Unit No. 1 Filet NRC-7a, A-118e Dear Siri Please find enclosed a copy of the Semi-Annual Report for the Duane Arnold Energy Center, Unit No. 1. for the period January 1, 1992, through June 30, 1992. This report satisfies the requirements for the Semi-Annual Eftluent Release Report, as stated in Section 6.11.lf of Technical Specifications, (Appendix A to the Operating License DPR-49).
Sincerely, d.41 ll David L. Wil::on Plant Superintendent - Nuclear DLW/RL/hc
Enclosure:
Semi-Annual Effluent Release Report cc: J. Franz (w/o attachments) ouane u nut snery center . 3:.- a uc nud ra:a:n.a m :t 3Is831 nsI i
r o 1
.9<.
Iowa Electric Light and Power Company tagust 21, 19 );.
- -o
- -39 acs l
l Dr. George Breuer University of Iowe University Hygia".ic Lab Oakdale Campus Iowa City, Iowa 52240 1
Ret Duane Arnold Energy Center
Subject:
Semi-Annual Effluent Release Report January 1, 1992, through June 30, 1992, for the Duane Arnold Energy Center, Unit No. 1 File! NRC-7a, A-118e Dear Dr. Breuer Please find enclosed a copy of the Semi-Annual Report for the Duane Arnold Energy Center, Unit No. 1, for the period January 1, 1992 through June 30, 1992. This report satisfles the requirements for the Semi-Annual Effluent Release Report, as stated in Section 6.11.lf of Technical Specifications, (Appendix A to the Operating License DPR-49).
Sincerely, htLLL W David L.- Wilson Plant Superintendent - Nuclear -
DLW/RL/hc Semi-Annual Effluent Release-Repor't
Enclosure:
P cc t - J. Franz (w/o attachments)
I' lluane Vnold t.nergv Center
- 3:?* U AFC naad
- Pala. Iona 3:3:4
- 319 M3 8 76II
a e .
Iowa Electric Light and Power Company August .71, 1992 ,
NG-92-3?a5 Mr. Dennis Murdock i General Manager >
Central Iowa Power P. O. Box 2517
-Cedar Rapids, Iowa 52406 Ret Duane Arnold Energy Center
Subject:
Semi-Annual Effluent Release Report January 1, 1992, through June 30, 1992, for the Duane Arnold Energy Center, Unit No. 1 Filot NRC-7a, A-118e
Dear Mr. Murdock:
Please find enclosed a copy of the Semi-Annual Report for the Duane Arnold Enessy Center, Unit No. 1, for the period t January-1, 1992, through June 30, 1992. This report satisfies the requirements for the Semi-Annual Effluent Release Report, as stated-in Section 6.11,1f of Technical Specifications, (Appendix A to the Operating License DPR-49).
Sincerely, David L. Wilson Plant Superintendent - Nuclear DLW/RL/hc Enclosure Semi-Annual Effluent Release Report cc ~J. Fran: (w/o attachments) l Duant \rnold t nergs Center
- 3:?* DAt C had
- Palo. kma 3:324
- 319 851 *blI
,. ~ . . , .. , . . . - . . , .
r .
- i .'
E lowa Electric Light and Power Company August 21, 1992 NG-92-D92 Dr. Keith Cherryholmes University of Iowa University Hygienic Lab Oakdale Campus Iowa City, Iowa 52240 Re Duane Arnold Energy Center
Subject:
Semi-Annual Ef fluent Release !!eport January 1, 1992, through June 30, 1992 for the Duane Arnold Energy Center, Unit No. 1 Files NRC-7a, A-118e
Dear Dr. Cherryholmes:
Please find enclosed a copy of the Semi-Annual Report for the Duane Arnold Energy Center, Unit No. 1, for the period January 1, 1992, through June 30, 1992. This report satisfies the requirements for the Semi-Annual Eftluent Release Report, as stated in Section 6.11.lf of Technical Specifications, (Appendix A to the Operating License DPR-49).
Sincerely, b
David L. Wilson Plant Superintendent - Nuclear DLW/RL/hc
Enclosure:
Semi-Annual Effluent Release Report cc: J. Franz (w/o attachments)
(-
(
nuane Arnold Enery Center . 3:f* U AEC fload
- Palo. Iona 3:3:4
- 319 M317611