ML20198C171
| ML20198C171 | |
| Person / Time | |
|---|---|
| Site: | Paducah Gaseous Diffusion Plant |
| Issue date: | 12/15/1998 |
| From: | Toelle S UNITED STATES ENRICHMENT CORP. (USEC) |
| To: | Paperiello C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| GDP-98-0245, GDP-98-245, NUDOCS 9812210323 | |
| Download: ML20198C171 (25) | |
Text
USEC A Global Energy Company December 15,1998 GDP 98-0245 Dr. Carl J. Paperiello Director, Office of Nuclear Material Safety and Safeguards Atteation: Document Control Desk U.S, Nuclear Regulatory Commission Washington, D.C. 20555-0001 Paducah Gaseous DifTusion Plant (PGDP)
Docket No. 70-7001 Transmittal of Revision 33 to Paducah Certification Application
Dear Dr. Paperiello:
In accordance with 10 CFR Part 76, the United States Enrichment Corporation (USEC) hereby submits twenty (20) copies of Revision 33 (December 13,1998) to USEC-01, Application for United States Nuclear Regulatory Commission Certification, Paducah Gaseous Diffusion Plant.
Revision 33 incorporates changes to the Technical Safety Requirements (TSR.s). These changes were previousiv ubmitted for your review in'accordance with 10 CFR 76.45 and were approved as Amendm. n 18 to Certificate of Compliance GDP-1 in your letter dated November 16,1998 (TAC l
NO. L32082). Re'dsion 33 also incorporates changes to the Quality Assurance Program Description and Emergency Plan that were implemented during the period July 16,1998 to November 15,1998.
The program and plan changes have been reviewed in accordance with 10 CFR 76 and have been determined not ;o require prior NRC approval. Three administrative corrections to USEC-01 are also included with this package: the List of Effective Pages for Volumes 1 and 2 has been changed to correct listed page revision levels, TSR page 2.2-19 has been changed to remove two erroneous revision bars, and TSR page 2.6-3 has been changed to identify the correct year ofissue in the page header. Revision bars are provided in the right-hand margin to identify the non-administrative j
changes. Revision 33 was implemented effective December 13,1998.
Should you have any questions or comments on Revision 33, please call me at (301) 564-3250 or
- Steve Routh at (301) 564-3251. There are no new commitments contained in this submittal.
Sincerely, S. A.
I Steven A. Toelle Nuclear Regulatory Assurance and Policy Manager c;
6903 Rockledge Drive, Bethesda, MD 20817-1818
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Telephone 301-564 3200 Fax 301-564-3201 http://www.usec.com 9812210323 981215
~ %ducah, KY Portsmouth, OH Washington, DC PDR ADOCK 07007001 C
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Dr. Carl J. Paperiello December 15,1998 GDP 98-0245, Page 2
Enclosures:
- 1. Aflidavit
- 2. USEC-01, Application for United States Nuclear Regulatory Commission Certification, Paducah Gaseous Diffusion Plant, Revision 33, Copy Numbers 1 through 20 cc: NRC Region III Office.
Copy Numbers 442,664 NRC Resident Inspector - PGDP Copy Number 697 NRC Resident Inspector - PORTS Copy Number 665 Mr. Joe W. Parks (DOE)
Copy Numbers 641 through 644
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L OATH AND AFFIRMATION
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I, Steven A; Toelle, swear and affirm that I am the Nuclear Regulatory Assurance and i
l Policy Manager of the United States Enrichment Corporation (USEC), that I am authorized by USEC to sign and file with the' Nuclear Regulatory Commission this Revision 33 of the USEC l
l Application for United Stater Nuclear Regulatory Commission Certification, Paducah Gaseous Diffusion Plant (USEC-01), that I am familiar with the contents thereof, and that the statements made and matters set forth therein are true and correct to the best of my knowledge, information, and belief.
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I' Steven A. Toelle On this 15th day of December,1998, the individual signing above personally appeared before L
me, is known by me to be the person whose name is subscribed to within the instrument, and acknowledged that he executed the same for the purposes therein contained.
In witness hereof I hereunto set my hand and official seal.
1 0(L1 L lAA W i
I/aurie M. Knisley, Notary Public [/
State of Maryland, Montgomery County My commission expires March I,2002 I
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GDP 98-0245 USEC-01 Application for United States Nuclear Regulatory Commission Certification Paducah Gaseous Diffusion Plant, Revision 33 t
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APPLICATION FOR UNITED STATES NUCLEAR REGULATORY COMMISSION CERTIFICATION PADUCAII GASEOUS DIFFUSION PLANT REMOVAL / INSERTION INSTRUCTIONS REVISION 33 DECEMBER 13,1998 l
Remove Page Insert Page Volume 1 List of Effective Pages List of Effective Pages LOEP-1/LOEP-2 LOEP-1/LOEP-2 Volume 3 Quality Assurance Pror, ram Quality Assurance Program iii/iv. 7/8,9/10,29/30 iii/iv 7/8.9/10,29/30 Emergency Plan Emergency Plan j
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Volume 4 List of Effective Pages List of Effective Pages ii. iii, iv ii, iii, iv Section 2.2 Section 2.2 2.2-19,2.2-3 a 2.2-19,2.2-30a Section 2.6 Section 2.6 2.6 3 2.6-3 i
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i Quality Assurance Program - GDPs December 13, 1998 i/7 Rev. 33
,U 2.3.3.2 Design Process Procedures are established to ensure the following:
1.
Design activities are planned on a timely basis and to the level of detail necessary to permit the design process to be carried out in a correct manner and to permit verification that the design meets requirements. Design inputs are correctly translated into design documents. Design documents shall l
be adequate to support facility design, construction, and operation.
l 2.
Appropriate quality standards are identified and documented and their selection reviewed, approved, and controlled. Changes from specified quality standards and reasons for the changes shall be l
identified, approved, documented, and controlled; l
3.
Design methods, materials, parts, equipment, and processes that are essential to the function of the SSC are selected and reviewed for suitability of application; l
4.
Applicable information derived from experience, as set forth in reports or other documentation, shall l
be made available to cognizant design personnel; and l
5.
Final design output documents including changes thereto are:
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- a. Relatable to the design input by documentation in sufficient detail to permit design verification,
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- b. Identify assemblies and/or components that are part of the item being designed. When such an V
assembly or component pan is a commercial grade item, the requirements of Section 2.7.3.9 are also applied.
2.3.3.3 Design Analyses Procedures for design analyses activities are established to ensure the following:
1.
Design analyses are performed in a planned, controlled, and documented manner; 2.
Design analyses documents are legible and in a form suitable for reproduction, filing, and retrieval; 3.
Design analyses documents contain sufficient detail as to the purpose, method, assumptions, design l
input, references, and units such that a person technically qualified in the subject can review and understand the analyses and verify the adequacy of the results without recourse to the originator; 4.
Calculations are identifiable by subject, originator, reviewer, and date or by other data such that the calculations are retrievable; 5.
When computer programs are utilized for design analyses, the requirements of Section 3.1(a) of Supplement 3 S-1 of ASME NQA-1,1989 are applied; and 6.
Design analyses documents include the requirements of Section 3.l(b) of ASME NQA-1,1989 Supplement 3 S-1.
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Quality Assurance Program - GDPs December 13, 1998 Rev. 33 2.3.3.4 Design Verification Procedures for design verification activities are established to ensure the following:
1.
Design verification is perfonned by competent individual (s) or group (s) other than those who performed the original design. The results of design verification shall be clearly documented with l
the identification of the verifier clearly indicated; l
2.
Verifiers are knowledgeable in the areas to be verified. The verifier may be a supervisor, provided the supervisor was not directly responsible for the design (i.e., did not specify a singular design approach or rule out certain design considerations and did not establish the design inputs used in the design) or provided the supervisor is the only individual in the organization competent to perform l
the verification. Cursory supervisory reviews do not satisfy the intent of this verification; l
3.
Verification shall be performed in a timely manner Design verification for the level of design j
activity accomplished shall be performed prior to release for procurement, manufacture, l
construction, or release to another organization for use in other design activities except in those cases l
where this timing cannot be met, such as when insufficient data exist. In those cases, the unverified l
portion of the design shall be identified and controlled. In all cases the design verification shall be l
completed prior to relying upon the component, system, structure, or computer program to perform l
its function; l
4.
The extent of the design verification is a function of the importance to safety, the complexity of the design, the degree of standardization, the state of the art, past performance, and similarity with previously proven designs. Where the design has been subjected to a verification process in l
accordance with this QAP, tne verification process need not be duplicated for identical designs.
l However, the applicability of standardized or previously proven designs, with respect to meeting l
pertinent design inputs, shall be verified for each application. Known problems affecting the l
standard or previously proven designs and their effects on other features shall be considered. The l
original design and associated verincation measures shall be adequately documented and referenced l
in the files of subsequent application of the design. Where changes to previously verified designs l
are made, design verification is performed for the changes, including an evaluation of the effects of the changes on the overall design and on any design analysis for which the design is based that are l
affected by the change to previously verified design; and l
S.
Acceptable methods of design verification are identified which include, but are not limited to, any one or a combination of the following: design reviews, alternate calculations, and qualification testing in accordance with Supplement 3S-1, Sections 4.2.1, 4.2.2, and 4.2.3 of NQA-1,1989.
l Procedures identify the criteria for determining the method of design verification. Verification by testing shall demonstrate adequacy of performance under conditions that simulate the most adverse design conditions. Verification of computer programs includes appropriate testing in accordance l
with the requirements of Section 2.11.3.2.
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Quality Assurance Program - GDPs December 13, 1998
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Rev. 33 2.3.3.5 Design Changes t
Procedures for design change control are established to ensure the following:
1.
Changes to final designs, field changes, modifications, and nonconforming items dispositioned "use-as-is" or " repair" are justified, documented, and evaluated against criteria established by the Engineering Manager; 2.
Design documents, including changes thereto, are controlled in accordance with Section 5 of Supplement 3 S-1 to NQA-1,1989 and Section 2.6 of this QAP. When a significant design change is found to be necessary because of an incorrect design, the design process and verification procedure are reviewed and modified as necessary; and 3.
Changes to the plant are evaluated and processed in accordance with the provisions of 10 CFR 76.68, 2.3.3.6 Design Interfaces Procedures for design interface control are established to ensure the following:
1.
Internal and external design interfaces are identified and controlled and design efforts are coordinated among participating organizations;
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2.
The responsibilities for the preparation, review, approval, release, distribution, and revision of documents involving design interfaces are defined; and 3.
Design information transmitted across interfaces is documented and controlled in accordance with l
Supplement 3S-1, Section 6 of NQA-1,1989.
l 2.3.3.7 Design Documentation and Records Design documentation and records that provide evidence that the design and design verification processes were performed in accordance with this section are collected, stored, and maintained in accordance with Supplement 3S-1, Section 7 of NQA-1,1989 and Section 2.17 of this QAP.
l 2.4 PROCUREMENT DOCUMENT CONTROL 2.4.1 General A procurement document control system is established for Q items and related activities and services within the scope of this QAP as identified in Section 2.2. The procurement document control system is in accordance with ASME NQA-1,1989, Basic Requirement 4, and Supplement 4S-1. The procurement document control system ensures that applicable regulatory requirements, technical requirements, and QAP requirements are included or referenced in procurement documents for the 9
Quality Assurance Program - GDPs August 15, 1998 Rev.26 procurement of items and services. This system also establishes provisions for the preparation, review, approval, and control of procurement documents, including changes thereto.
2.4.2 Responsibilities The Engineering Manager is responsible for the preparation and maintenance of design specifications (including specifications for spare and replacement parts) and for identifying the technical and quality requirements necessary to ensure item acceptability. These specifications are subject to the requirements of Section 2.3 of this QAP. The Engineering Manager is also responsible for development of procedures j
that define these activities. including the criteria for developing the necessary technical and quality requirements for procurement.
The Central Procurement Director is responsible for purchasing activities and for ensuring that items are procured from approved suppliers on the approved suppliers list.
2.4.3 Requirements The requirements of Section 2.4.3.1 apply to non-commercial grade items. The requirements of Section 2.7.3.9 apply to commercial grade items.
2.4.3.1 Procurement Document Contents Procedures governing procurement document content are established to ensure the following:
1.
Procurement documents shall contain a statement of work as appropriate.
l 2.
Technical requirements are specified in procurement documents by specific reference to drawings, l
specifications, codes, standards, regulations, procedures, or instructions, including revisions thereto, that describe the items or services to be furnished. These procurement documents also are required to provide identification of any special instructions and requirements for designing, fabricating, cleaning, erecting, packaging, shipping, handling, storing, testing, inspecting, and accepting.
3.
Procurement documents, for non-commercial grade items, require that the supplier implement a l
documented quality assurance program that is equivalent to the requirements of ASME-NQA-1, 1989. The procurement documents also require the supplier to extend the applicable requirements of the procurement documents to the supplier's subtier procurement documents. The extent of the program required is dependent upon the importance to safety, type, and use of the item or service being procured.
4.
Procurement documents, for non-commercial grade items, provide for access to the selected l
supplier's facilities and records for inspection or audit by the purchaser, its designated representative, and/or other authorized parties.
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2.12.2 Responsibilities 1
The Maintenance Manager has the overall responsibility for the calibration control system for M&TE l
including plant installed process instrumentation. The calibration control system meets the requirements l
of this section of the QAP.
1 Organization / Group Managers are responsible for implementation of the calibration control system for M&TE including plant installed process instrumentation under his/her cognizance.
2.12.3 Requirements Procedures are established for the control of M&TE to ensure the following:
1.
A list of devices (and their assigned location) is established to identify those items within the calibration control system. This identification listing includes, as a minimum, the due date of the next calibration arxi any use limitations (when it is calibrated for limited use). Calibration controls are not necessary for rulers, tape measures, levels, and other such devices if the commercial equipment provides adeouate accuracy.
2.
M&TE is calibrated at specified intervals or prior to use against certified equipment having known valid relationships to nationally recognized standards. If no nationally recognized standard exists, j
the bases for calibration are documented.
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3.
The method and interval for calibration for each item shall be defined, based on the type of l L
equipment, stability characteristics, required accuracy, intended use, and other conditions affecting l
1 measurement control.
l 4.
When M&TE is found to be out of calibration, an evaluation is made and documented as to the l
validity of previous inspection and test results and of the acceptability of items previously inspected or tested. Out-of-calibration devices are tagged or segregated and are not used until recalibrated.
When M&TE is consistently found to be out of calibration, it is repaired or replaced. Also, calibrations are performed when the accuracy of the equipment is deemed suspect by personnel performing measurements and tests.
5.
M&TE is properly handled and stored to maintain accuracy.
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Records are maintained and equipment is suitably marked to indicate its calibration status.
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Quality Assurance Program - GDPs August 15, 1998 Rev. 26 2.13 IIANDLING, STORAGE, AND SHIPPING 2.13.1 General A system is established for the handling, shipping, and storage of Q items identified as within the scope of this QAP as described in Section 2.2. This system is in accordance with Basic Requirement 13 and Supplement 13S-1 of ASME NQA-1,1989. This system provides the requirements for item handling, storage, and shipping, to prevent damage, loss, or deterioration.
2.13.2 Responsibilities Tl'c Engineering Manager is responsible for specifying the requirements for handling, storage, shipping, cleaning, packaging, and on site movement of items in specifications, drawings, instructions, procedures, procurement documents, and/or other appropriate documents, in accordance with requirements of this section of the QAP.
Organization / Group Managers have the responsibility for the proper handling and on-site movement of items under their cognizance from the point of issuance through installation and use. These activities are accomplished in accordance with procedures consistent with the requirements of this section of the QAP.
The Materials Management Manager has the responsibility for the proper handling, storage, and on-site movement of items under his/her cognizance (i.e., upon receipt, during storage, and to the point of issuance). These activities are accomplished according to procedures consistent with the requirements of this section of the QAP.
The Production Support Manager is responsible for selectively verifying that items are properly handled, stored, and shipped.
2.13.3 Requirements 1.
Procedures identify requirements for the handling, storage, cleaning, packaging, shipping, and preservation of items. These requirements are established during the generation of procurement, design, and shipping documents to prevent damage, loss, or deterioration. Periodic inspections are provided to verify compliance with storage requirements and to prevent deterioration; 2.
Proceoures document the training and experience requirements for operate:s of special handling and lifting equipment; 3.
Procedures provide measures for the identification, control, use, and qualification of special handling equipment. These procedures also include inspection and testing requirements, with specified time intervals, to assure adequate maintenance of special handling tools and equipment; 4.
Procedures designate the methods of controlling stored items; 30 i
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Emergency Dlan - PGDP January 19, 1996 i
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- 1. FACILITY DESCRIPTION USEC leases portions 'of Paducah DOE reservation from the Department of Energy (DOE) and conducts uranium enrichment activities at the plant. These uranium enrichment activities are regulated by the NRC. DOE and DOE contractors also conduct activities and operate other facilities at the site, which are not regulated by the NRC.
1.1 DESCRIPTION
OF NRC-REGULATED ACTIVITIES The primary mission of the plant is the enrichment of uranium with the isotope necessary to produce fuel for nuclear reactors ("5U) using the gaseous diffusion process. A basic summary of this process follows.
Uranium hexafluoride is received from the conversion plant operated by Allied Signal Corporation in Metropolis, Illinois, and other conversion facilities. The material is shipped to PGDP by truck and rail in cylinders containing 10 or 14 tons of UF. in accordance with Department of Transportation (DOT) l regulations.
When UF is received, it is assayed and weighed in the toll cylinder facility and stored. When 6
needed, the assayed cylinder is moved to a feed facility, heated, and evacuated to the gaseous diffusion enri+.nent process.
Uranium hexafluoride is a white crystalline solid at ambient pressures and temperature and a gas at process conditions. The enrichment method increases the concentration of "U by the physical process of diffusion. The UF gas is not physically altered nor are its chemical properties changed.
The gaseous diffusion enrichment process employs a series of compressors and converters to enrich UF. in *U.
The fundamental building block of the process consists of a compressor, a converter, and a motor that form a stage. Stages are grouped together to form cells. The cells are then interconnected to provide what is known as a cascade. The compressors, which are driven by electric motors, are used to circulate the process gas and maintain flow through the cascade. The converters contain porous tubes and barriers through which the process gas is diffused. In each converter, a portion of the process gas diffuses through the barrier and is fed to the next higher stage with the undiffused gas being recycled to the next lower stage. The diffused stream is slightly enriched in the 235 isotope while the undiffused portion is slightly depleted in the 235 isotope to the same degree. Each stage also contains a gas cooler to remove the heat of compression from the process gas and a control valve for process control. The process is repeated through numerous cells until the desired enrichment level is reached.
Upon completion of the enrichment process, the enriched portion of the process stream is extracted in the product withdrawal facility and placed in 2%- or 10-ton product cylinders. The product cylinders are shipped by rail or truck, in accordance with DOT and state requirements, to the Portsmouth Gaseous Diffusion Plant (PORTS) for further enrichment or to a licensed or DOE-operated facility for conversion to uranium metal.
1-1
Emergency Plan - PGDP December 13, 1998 Rev. 33 The depleted portion of the process stream is extracted in the tails withdrawal facility in 10. or 14-ton cylinders. The depleted uranium cylinders are moved to the cylinder storage yards located within the fence of PGDP, where they are currently being stored.
PGDP is designed to operate at a capacity of 11.3 million separative work unit (SWU) annually at its rated power level of 3,040 MW.
Source material, special nuclear material (SNM), and byproduct material are primarily handled in the buildings and storage yards listed in Table 1-1 and 1-2, respectively. The possession limits for source material, byproduct material, and SNM are shown in Table 1-3 of the Safety Analysis Report.
Uranium hexafluoride (UF ) is a radioactive, poisonous material, which is found at PGDP as a gas 6
liquid and solid. Additionally, UF reacts with water to form hydrogen fluoride (HF) and uranyl fluoride 6
(UO F ). UF and UO.,F are chemical toxological hazards due to the heavy metal properties of uranium.
3 3 6
2 The organs primarily affected are the kidneys. HF is an acid and may cause effects from irritation of skin, eyes, mucous membranes, and lungs to chemical burns causing deep tissue destruction. The radiotoxological effects of uranium at the assays encountered at PGDP are not significant when compared to the chemical toxological effects.
Numerous substances associated with the enrich.nent process could pose hazards if they were released to the environment. Only a few of these substances are highly toxic and present in large quantities at the plant. Based upon the hazards and consequence analyses that have been conducted, USEC has concluded that any nonradiological hazardous release would most likely involve one or more of the following:
Chlorine trifluoride (CIF ) is a poisonous gas, oxidizer, and corrosive. Additionally, CIF reacts 3
3 with water to form hydrogen fluoride and chlorine. CIF is used as a drying agent in the cascade 3
and is purchased and delivered in 160-lb cylinders. Cylinders are stored in the northwest corner of the C '745-B cylinder yard and are transferred as needed to the C-350 drying agent storage building. The C1F is vaporized into tiie C-350 CIF storage drum, which is used for the controlled 3
3 flow of CIF to the distribution piping. This permits the controlled flow of CJF to the C-310 3
building anr1 to the C-331 and C-335 buildings' metering station for cell treatment on an as-needed basis. The inventories are controlled so that no more than 1,000 lbs of CIF are available for 3
release from a single credible accident.
Nitric acid (HNO ) is a volatile, corrosive liquid. HNO up to 70% concentration is delivered by 3
3 truck and is stored in a 12,000 gal tank located outside the southwest corner of building C-400.
l Prior to use, the acid is transferred to and stored in a 500-gal day tank inside the building. HNO3 is used primarily in a solution with water to decontaminate uranium-centaminated metal surfaces.
It is also used for other miscellaneous chemical operations. The maximum inventory of HNO at 3
PGDP is limited by the capacity of the storage tanks.
Hydrochloric acid (hcl) is a volatile, corrosive liquid. hcl is delivered by truck and is stored in a 17,000 gallon, two-section tank each containing 8,500 gallons, inside building C-400. Prior to l
use, the acid is diluted to less than 30% to form a " pickling" solution to be used as part of the cleaning process after degreasing.
1-2
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- TSR-PGDP December 13,1998 j
Rev.33 SECTION 2.2 SPECIFIC TSRs FOR UF FEED FACILITIES (C-333-A AND C-337-A) l
~ 2.2.4 GENERAL LIMITING CONDITIONS FOR OPERATION 2.2.4.4 CYLINDER HEATING - CYLINDER ACCOUNTABILITY WEIGHT l
LCO 2.2.4.4:
Cylinder accountability (net) weight shall be verified less thro or equal to the l
L
" Max. Fill Limit for Shipment" for cylinders other than tails cylinders and i
L
" Max. Fill Limit for In-Plant Tails Storage" for tails cylinders stated in TSR Section 2.2, Appendix A prior to heating the cylinder.
1 APPLICABILITY: Modes: 5 ACTIONS:
- Condition -
Required Action Completion j
Time j.
A. Accountability A.1 Calculate the cylinder void volume (ullage) at a Prior to entering L
weight exceeds temperature of 230*F and/or 235"F. Use the mode 5 l
the Iwaximum stamped water weight as the basis of the actual i
Fill Limit for volume of cylinders with certified volumes, or use l
Shipment for the minimum design volume (hsed on all minimum cylinders other design tclerances) for cylinders wi:hout certified than tails volumes in the calculation. Determine the category p
cylinders, or of the cylinder based on the following criteria:
Ls the Maximum
['
Fill Limit for Cat. A Void volume =5% at 235'F' In Plant Tails or Storage for Void volume =3% at 235'F for cylinders filled with tails cylinders.
high purity tails Cat. B Void volume 25% at 230*F or L
Void volume 23% at 230'F for cylinders filled with high purity tails Cat. C Void volume <5% at 230*F or Void volume <3% at 230*F for cylinders filled with high purity tails I
AhlD A.2.1 Set the Autoclave Steam Pressure Contral System c
setpoint consistent with the cylinder category per TSR 2.2.3.3 for a Category A or B cylinder. The l
autoclave temperature / pressure controller setpoint 3
[
shall not be set less than 219.9'F.
.OR A.2.2 Administratively control the Category C cylinder to prevent heating until such time as cold / controlled D-feeding is re-instituted as an operating mode.
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TSR-PGDP December 13, 1998 Rev.33 t
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SECTION 2.2 SPECIFIC TSRs FOR UF FEED FACILITIES (C-333-A AND C-337-A) 6 l
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2.2.4 GENERAL LIMITING CONDITIONS FOR OPERATION 2.2.4.13 AUTOCLAVE MANUAL ISOLATION SYSTEM LCO 2.2.4.13:
The autoclave manual isolation system actuation devices shall be operable.
1 APPLI7 ABILITY: Modes: 4, 5.
ACTIONS:
i Condition Required Action Completion Time A.
The actuation device located A.1 Position an operator such that the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in the OMR is inoperable.
"see-ad-flee" path provides access to the actuation device located at the cylinder yard crane bay exit.
TSR 1.6.2.2d is not applicable.
B.
The actuation device located B.1 Provide continuous stationing of an 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at the cylinder yard crane bay operator in the OMR.
exit is inoperable.
TSR 1.6.2.2d is not applicabic.
C.
Both feed facility actuation C.1 Restore operability to at least one 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> devices inoperable.
actuating device.
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TSR 1.6.2.2d is not applicable.
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D.
Required action C not D.1 Place the autoclave in mode 2.
Immediately satisfactorily accomplished.
D.2 Close containment valves XV-503, Immediately l
CV-504, XV-505, CV-511 and CV-510 on each autoclave.
M D.3.1 Establish radio communication with immediately the associated Area Control Room in order to ensure immediate capability to actuate the Autoclave Manual isolation System from the ACR in the event of a release, j
AND D.3.2 Restre operability of the Autoclave 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l
Manual Isolation System.
i i
TSR 1.6.2.2d is not applicable E.
The actuation device located E.1 Ensure both actuation devices in Immediately l
in the associated ACR is appropriate feed facility are inoperable.
operable or appropriate required action A or B completed.
l AND E.2 Restore operability to ACR 3C lays actuation device.
fg TSR 1.6.2.2d is not applicable
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. TSR-PGDP December 13, 1998 Rev.33
,c)
SECTION 2.6 SPECIFIC TSRs FOR CAAS (NON-CASCADE FACILITIES) 2.6.4 GENERAL LIMITING CONDITIONS FOR OPERATION 2.6.4.1 CRITICALITY ACCIDEli.T ALARM SYSTEM
. LCO 2.6.4.la:
Criticality accident detection shall be operable.
APPLICABILITY: In areas, equipment, or processes in the facilities listed in the table below which contain greater than 700 grams of 235U at an enrichment greater than or equal to 1.0 wt % 235U.
Building / Facility Number Building / Facility Name CAAS Cluster and/or Function C-400 Cleaning Building D, E C-409 Stabilization Building P,AE C-710 Technical Services Building AM, AN, AP, AQ, AR l
' C-720 Maintenance and Stores AL l
Buildings l
C-720-C Converter Shop Addition AL
',(
C-728-Motor Cleaning Facility AL C-746-Q-1 High Assay Waste Storage AD l
l l'
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