ML20155K075

Rev 26 to USEC-02,application for Us NRC Certification for Portsmouth Gaseous Diffusion Plant

ML20155K075
Person / Time
Site:	Portsmouth Gaseous Diffusion Plant
Issue date:	11/06/1998
From:	UNITED STATES ENRICHMENT CORP. (USEC)
To:
Shared Package
ML20155K052	List: ML20155K049 ML20155K075
References
NUDOCS 9811130093
Download: ML20155K075 (28)

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[V'1 APPLICATION FOR UNITED STATES NUCLEAR REGULATORY COMMISSION CERTIFICATION PORTSMOUTH GASEOUS DIFFUSION PLANT USEC-02 REMOVE / INSERT INSTRUCTIONS Revision 26 Remove Pages Insert Pages VOLUME 1 LIST OF EFFECTIVE PAGES Pages i / ii Pages i / ii Pages xxv through xxviii Pages xxv through xxviii i

SECTION 1 1-9 / l-10 1-9 / l-10 VOLUME 2

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None SECTION 5.7 5.7-1/ 5.7-2 5.7-1/ 5.7-2 SECTION 6.9 6.9-1 through 6.9-4 6.9-1 through 6.9-4 VOLUME 3 EMERGENCY PLAN Pages i / ii Pages i / ii 1-8a / l-8b l-8a / l-8b ENVIRONMENTAL COMPLIANCE STATUS REPORT Pages i / ii Pages i / ii 3/4 3/4 f

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,fam NY 9811130093 981106

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PDR ADOCK 07007002 is C

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APPLICATION FOR UNITED STATES NUCLEAR REGULATORY COMMISSION CERTIFICATION PORTSMOUTH GASEOUS DIFFUSION PLANT USEC-02 REMOVE / INSERT INSTRUCTIONS Revision 26 Remove Pages Insert Pages VOLUME 4 TSR LIST OF EFFECTIVE PAGES Pages il through iv Pages il through iv SECTION 2.1 i

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Table 1-3 (Continesed)

$ D.e.

N "Cf Alumic Ch O Type of Material Nuudwr Physical State Chemical Forrn Possesskm f.inus Descopskin p

f H-

&2 i

O.5 Ci Calibration 93.96,97.99.100 Scaled source '

1.0 Ci Laboratory chemicals Unscaled source Analysis of sannples*

)

93,95-100 Any Any That resulting inau dw tecd <>f Process m - - s and wasses, material hcid in equi mient from previous operations recycled or FSU uraniunf l

95 Scaled annce

. Oakles, metals 15 ci Calibratien, process source tinscaled source Oakles, metals, 0.5 Ci Analysis of samples' adushms I.aboratory chemicals l

-t 1.

I 9 11 Scaled unerce Oamics, inctals 10 Ci f*ahbration NDA Unsealed source -

Omides, uncials.

0.5 Ci Azulysis of saniples*

xduthnis I.athwasury chemicals i

t MRI - Metric Tons Uranium a.

See 10 CFR Part 76 definisions: Special smaclear maserial means: (1) Plutonium, uranium 233, uramum enriched in the isosape 233 or in the isotope 235, ark! any l

a b.

anher material which the C.nunaission, guarsuare so the provisanas of Secensen 51 of dw act, deternunes so Iw sgwetal ansclear material, laat does not include usurce j

material; or (2) any nuscrial artificially enrictied in any of the foregoing, tait ducs not include source nuscriat FSU meets the ASTM Saarmlard C996, Saandard Specification for Uramum Ilcmathawide Enriched to Leu Tiun 5 percent"U; UF. for enrichmesu meets the c.

ASTM Standard C787 Stasaland Specatecaiman for Usaiuusu licaailuusmic tier lauichunens.

l Recycled uraniuna inchales the iced asal processing of Paducah Produca aint the "stockpde* UG tran> fessed from DOE so USEC for enrichment.

d.

" Analysis of samples" refers so she analysis of samples relased to ensichmess acuvisies or site remedwiun. IPOtt fS. PGDP, DOE-OR) activines undizing existing l

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e.

l facdities aimi analyta:al techniques to prucess low-level radkuctivity saanples bouakled by the posseuksu limtes stated in this table.

Except for Paducah Pnalect aimi the *ssockpile" UF. transferred fnna DOE to USFC for enrichmeen, uraniuni no le fed to the cascade will meet the requirements f.

of ASTM Stasalard CW, "Stasulard Specificasiam for tirannata llenathmuide lituiclwd to less 'Iluu 5%'"l1* ur AS~I M Swalard C787,

• Standard Specuacasksn tor Urannmillenathausede f.u lisa attuness' for regusm essed Uli. All dhen usanusua slut dics sad unxi t!w scapucuwsds ut AS'IM (.W or C787 for segnutessed If t, may tw ar.ygsed for shuage aimi udwipets despaiskuung last wdl suit lie issoudisccal to de casaile, w nli ilm caceptidi of saumfl asimitants fc g.,50 n usals i

d d

Uly assucused wah sami sug, sulmemi mg, aint azulyscs scirused so est.sidah seceiver's vahics

,4 i

O "Ilawe pasenke lunais do ame enchmte sautes ut in USlir leased sp. ace hieu prevkass loti operatman he na1. ale actaumal savensory of uranauta plased amas tai the insmle y

mustaces..I 1.sh simsJon aant.ps.amg caprpucas au sic X 11t.14.ddy; spculac usupancids in the X _Ilt> uw.mle dut anni su he senmeved fur snauscuasse os e4her g

l g.

operathmal pirpnes; nutenial armi espapswns usch as alumina traga, seal calausa ud aimi GP unsauwss inau always sale sacuutus tfut are geswsated as part of g s

onoung ugws stmuis na X-32ti, us ausesul hekt up in X-705 capipuaid (wisuc ut uhk.la nuy have to tw scuawed sur nuintenaire).

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t FSU - Former Soviet Union 00 4-I t

p >v2 a<(N4 Table 1-4, Auttiorized uses of NRC-regulated materials:

O Wd Authorized Use Material Class

1. Enriclunent of uranium up to 10 percent enrichment by weight "U 2

A. Source Material, Element 92'*

2. Receipt, storage, inspection, anal acceptance sampling of cylimlers containing uranium

3. Filling and storage of cylishlers of natural uranium and uranium depleted in '"U l

4. Cleaning and inspection of cylimiers used for the storage and transpott of process product and tails containing source or SNM

5. Storage of process wastes containing uranium, transuranic eles: ents, and ether contaminants and decay products

6. Process, characterize, package, ship, or store low-level radioactive and mixed wastes

7. Radiation protection, process control and environinental sample collecticm, analysis, instrument calibration, and operation checks 8

8. Maintenance, repair, and replacement of pnicess equipment I

9.12horatory analysis and testing I

10. lleating cylinders and feeding contents iato the diffushm process i1. Controlled feeding of cylinders I

12. Transfer between cylinders

1. Cahbration and use of portable radiatkm protection and fixed laboratoay equipment B. Source Material, 1:lement 90

2. l2boratory analysis ami testing

3. Process, characterize, pacLage, ship, or store low-level radkuctive aiki mixed wastes

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SAR-PORTS November 6.1998 V

Rev.26 5.7 ANALT TICAL SUPPORT 5.7.1 Analytical Laboratory Mission and Organization Analytical support to PORTS operations is provided by Production Support. Three functional areas within Production Support comprise the analytical laboratories--Uranium Analytical: Environmental, Safety and Health Analytical; and Process Technology and Non-Destructive Assay. All three groups are supported by Production Services in Production Support with items such as chemical hygiene, surveillances, and training oversight.

The mission of Production Support is to provide quality analytical servica and broad-based technology support to the plant. A secondary mission of Production Support is to provide analytical services in the areas of environmental monitoring and remediation, waste management. disposition of stored materials, and health and safety to the DOE. Analytical services provided utilize existing facilities and analytical techniques to l

process trace and low level radioactivity samples bounded by the limits stated in Table 1-3.

5.7.1.1 Uranium Analytical Uranium Analytical performs chemical and isotopic analysis for Casccde. Chemical. Utilities, and Feed and Transfer within Operations. Included in these services are product specification analyses, cascade control measurements. Nuclear Criticality Safety (NCS) limitation analyses, uranium accountability analyses.

and mass spectrometry isotopic analysis for barrier performance evaluation; operation of the uranium chain-of-g t"j custody facility for the laboratory; preparation of uranium hexatluoride standards; vent monitoring and cell

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negative testing for Cascade (all shifts): ASTM specification testing of materials for Operations; and High Efficiency Particulate Air (HEPA) filter testing.

5.7.1.2 Environmental, Safety & Health Analytical Environmental. Safety & Health (ES&H) Analytical routinely performs inorganic, organic, asbestos and radiochemistry analyses and physical properties measurements of Environmental Compliance. Waste Management (WM), Industrial Hygiene (IH), Radiation Protection (RP), and Industrial Safety samples.

Services also are provided to Chemical. Utilities, and Power within Operations and, less frequently. to other site functions such as engineering and cascade operations. This group also cperates the environmental chain-of-custody, sample archive and return facilities. The major plant programs supported by ES&H Analytical are bioassay (urine), National Pollutant Discharge Elimination System, personal air monitoring, ambient air monitoring, continuous vent monitoring, environmental monitoring, RP wipe programr potable water testing, Recirculating Cooling Water testing, and Resource Conservation and Recovery Act waste characterization.

5.7.1.3 Process Technology & Non-Destructive Assay Process Technology & Non-Destructive Assay (NDA) provides technical support for continuous vent monitoring, compressor vented cavity line cleaning, infrared analysis, failure analysis, scanning electron microscopy, transmission electron microscopy, x-ray diffraction, portable infrared analyzer nU 5.7-1 I

4 SAR-PORTS May 31,1996 Rev.3 (PIRA) buggies, conditioning services, trapping materials, video scoping, materials testing, and NDA support.

Laboratory Quality Assurance / Statistics is part of Process Technology - ND A. This section provides statistical support to the laboratory, Nuclear Material Control & Accountability (NMC&A), and the plart at large, as well as administering internal and externai laboratory quality control (QC) programs. This section, along with support from Production Services, provides QA oversight of the laboratory.

Included in Process Technology & NDA is Laboratory Services. This section maintains the X-710 facility, including mamtenance to and monitoring of laboratwy hood air flows; procures chemicals and maintains the chemical distribution and reagent preparation facility; and provides in. house laboratory instrument maintenance and equipment fabrication services.

5.7.2 Laboratory Personnel Training and Qualification Laboratory personnelinclude a balanced mix of professional scientists and technicians. Professional personnel typically have a bachelor's degree or higher in a scientific or technical field. With few exceptions, entry level technicians have an associate degree in a scientific or technical field. Job experience may be substituted for erlucational requirements (cr both professional and technician-level positions.

All laboratory persotmel are required to complete the General Emsloyee and Compliance Training modules that arc developed and presented by the training organization, as described in Section 6.6.

On-the-job training (OJT) and qualification requirements are documented in standard operating procedutes. New or inexperienced analytical laboratory employees are provided appropriate safety and texhuical training, including instruction in recordkeeping and in the analytical methods they are assigned. An experienced technician or laboratory supervisor works with the trainee until proficiency in the method or procedure is observed. The qualification process for quantitative analytical work includes assessing l

performance with control samples. Qualification folders are maintained for each analyst.

1 Supplementing lab OJT is required reading. Required reading provides an administratively controlled means of conveying pertinent information re.ated to laboratory pesonnel. Required readings include newly l

revised or developed procedures, lessons learned, guidance from compliance organizations, and other material l

as determined by management.

1 Alllaboratory personnel receive initial and follow-up training in the Chemical Hygiene Plan, in basic nuclear criticality safety, and in radiation worker safety. Mandatory mc;nthly safety meetings reinforce safety principles. These meetings serve two purposes: to alert laboratory personnel to potential safety concerns, and to familiarize personnel with proper procedure., in the unlikely event an emergency arises.

l 5.7-2

e SAR-PORTS April 15,1998 Rev.19 6.9 EVENT INVESTIGATIONS AND REPORTING USEC is required by 10 CFR 76.35(a)(7) to describe its management controls and oversight program l-governing activities directly relevant to nuclear safety and saguards and security. This section describes the event investigations and reporting elements or the management controls and oversight program. USEC management ensures that activities directly relevant to nuclear safety and safeguards and secutity are conducted in a controlled manner to protect employees and public health and safety, the environment, and national security interests. As part of this program, abnormal events are identified, reported, and investigated. This includes identification and categorization of the event as well as an analysis to de; ermine the root cause and its effect upon nuclear safety and safeguards and security. The corrective actions developed as a result of the investigation are entered into a comminnent management database, which is a dedicated database used to track and trend corrective actions and plant commitments. This database also facilitates management's review of the corrective actions and plant commitments.

USEC is required by 10 CFR 76.120 and other applicable sections of the regulations referenced in 10 CFR 76.60 to notify the NRC of certain plant events and conditions and to determine the cause, corrective actions, and lessons learned. USEC shall satisfy these requirements by following administrative procedures l

relating to problem reporting (Problem Reporting Procedure) and nuclear regulatory event reporting (Nuclear Regulatory Event Reporting Procedure). Key aspects of the problem reporting and event reporting procedures

- are described in Section 6.8 and this section. These procedures work together to ensure that abnormal events I

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and conditions occurring at the plant are promptly reported to anpropriate plant personnel, assessed. and when

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required, reported to the NRC Operations Center or designate NRC office. Table 6.9-1 indicates those events I

for which a notification is required and those events for which a written report will be provided to the NRC.

l 6.9.1 Event Identification In accordance with the Problem Reporting Procedure (PRP), plant personnel are required to report to their line manager or directly to the Plant Shift Superintendent (PSS) abnormal events or conditions that may have the potential to harm the safety, health, or securuy of on-site personnel, the general public, or the emironment. The initial reporting to the PSS is as described in the PRP. Plant personnel are also required to immediately report conditions which may require emergency response.

6.9.2 Event Categorization In accordance with the Nuclear Regulatory Event Reporting Procedure (NERP), the PSS assesses and categorizes abnormal events or conditions using the notification and reporting criteria set forth in 10 CFR 76 l

and the other applicable regulations referenced in 10 CFR 76.60. Table 6.9-1 provides a list of the initial event notification and reporting criteria. In macing the assessn. cat, the PSS may consult with plant management or other personnel possessing expertise or knowledge concerning the type of event or condition being assessed.

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November 6,1998 SAR-PORTS Rev.26 6.9.3 NRC Notification if an event or condition within the USEC-leased area, or from 1 USEC directed activity outside the goverrunent reservation, is categorized as a reportable event, the PSS shall provide initial notification (verbal or written, as required) to the NRC Operations Center or designated NRC office and provide, to the extent known at the time of noti ication. the information specified in 10 CFR 76.120(d)(1) and other applicable sections of the regulations reatenced in 10 CFR 76.60. Notification shall be made as soon as possible but not later than the time period (s) stated in the regulations. Reporting time periods are shown with the reporting criteria listed in Table 6.9-l. Verbal and/or written communication involving classified information shall be conducted in accordance wit:i the Security Plan for the Protection of Classified N1atter that is part of this application.

Site events that occur within the DOE managed property (USEC non-leased area) shall be categorized by the PSS. Events classified as an occurrence shall be reported to DOE by the PSS. These events shall be assessed by the PSS and other plant management, as needed, to determine whether further action is required to be taken by USEC/LNIUS personnel. including reports to the NRC.

6.9.4 Event Investigation All reportable events, where a 30-day follow-up written report is required, are investigated to I

determine the root cause and corrective actions necessary to prevent recurrence. This investigation is I

conducted and documented. as required. by the plant corrective action process. Other events not requiring a i

30-day follow-up report are evaluated using the corrective action process to determine actions to be taken. The I

magnitude of this investigation is dependent upon the significance and complexity of the reportable event. This I

I may range from the assignment of an event investigation team or may be as simple as a one-person investigation. Documentation related to the event investigation may be separate from the event report and will I

be retained in accordance with Records Alanagement and Document Control requirements described in Section 6.10.

6.9.5 Written Report When required by Table 6.9-1. a report summarizing the results of the event investigation is prepared in accordance with the NERP. The report shall contain. at a minimum, the information specified in 10 CFR 76.120(d)(2) or other applicable sections of the regulations referenced in 10 CFR 76.60. The written report shall be forwarded to the NRC within the time specified in Table 6.9-1 or applicable NRC regulations.

The PORC is required to review each written event report prior to submission to the NRC.

l 6.9.6 Corrective Actions For each reportable event, corrective actions to prevent recurrence shall be developed by responsible I

management. These actions shall be validated and tracked to ensure proper implementation and closure, in I

accordance with the plant corrective action process. Prior to closure, the actions taken to prevent recurrence I

shall be reviewed by management. Evidence files used to support action closure shall be maintained in I

accordance with approved records management procedures.

6.9-2

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i 6.9.7. Lessons Learned Lessons learned from observations, experiences, events, and problem reports are reviewed and effectively communicated across both plants. The Operating Experience Review Program (OERP)

Administrator reviews gaseous diffusion operations and the USEC OERP Manager reviews related industry operating experience information to determine whether it warrants informational review or action by the o ganization with responsibility within the area of concern. Lessons learned from NRC regulated facilities, as &y apply to gaseous diffusion operations, shall be included.

6.9.8 Section Deleted 1

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Table 1-1. (Continued)

4. oo -

r a

Atomic N

Type of Material Numler '

Physical State Cl cruiul Form Possession Linut Description

-3 t

10 Ci -

Cahbration, intemal

)

27CoI 7 '

Scaled Source 5

Ingrumens standard, NDA 450 Ci Calibration, NDA, Process sources

(

27 Ct40 Scaled Smrce v) i 0.5 Ci Laboratory chemicals Analysis of samples

• l

{

Unsealed Soitrce l

10 Ci Process sources, internal instrument 28 Ni43 Seated Smrce standards 0.5 Ci Cahbration 38 St-90 Scaled Source Unsealed Source 0.5 Ci Laboratory chemicals,

}

. Analysis of samples

• l l

i 10 C Cahbration 43 Tc-99 Scaled Source i

y T

5 Ci Laboratory chemicals, g

Analysis of samples

• l

[

Unsealed Source Any Any That resulting trom the feed of Process contaminants and wastes, p

recycled or FStr uranium material held in equipment from l

previous operations 55 Cs-137 Scaled Source 2,000 Ci Calibration. NDA, Process sourus Unsealed Source 0.5 Ci laboratory chemicals Analysis of samples

• l

[

61 Pr 147 Scaled &mrce 0.5 Ci Calibration c

70 Yh-169 Scaled Source 5.0 Ci Calibration, NDA C

81 11-207 Seald Source 1.0 Ci Calibration

)

88 Ra-226 Scaled Source 15 Ci Cald>raticm 5:5 t

tJ.*

i

I I

l l

i 1

mm l

\\

Table 1-1 (Continued)

Description Atomic Possessica Lima y

Type of Material Number Physical State Clemical Form 3

0.5 Ci Cahbration y

93S6,97,99,I(x)

Scaled source 1.0 Ci Latusakary t.hemicals y

thiscaled source Anetysis of 5.tmples*

O N

Psucess contaminants armt wastes, nuterial intd in M

'lhas sesuhing frusa de feed of recycled or FSU uraniunt eququnent from previous operations 91, %1tn Any Any l

15 Ci Calibration, process source 95 Scaled source Oxides, metats Analysis of sampics' 0.5 Cs thiscaled umrce Oakles, urtats.

Lateratory chemicals soluthwis in Ci Cahbration, NDA 98 Scaled source Omnics, metals 0.5 Cs Analysis of samples

• thiscaled source Gamics, urtals, 1.aluratory chemicals l

soluinas MTU - Metric Tons ifranium s.

Special nuclear material mesns: (I) Plutunum, uramum 233, uranium ein kled in die isotope 233 or in the See 10 CFR Part 76 definnkes:

I b.

which the Conunissum, pusuant ni the provismuisof Scotkua 51 of siw act, dctesumies so le spetbl nuclear mater arutwially enriched in any of the toregoing, to des sad include source n:aterbl.

FSU rnects the ASTM Starmiard C9%. Standard Specification for Usanium llexatluormte Endctwd no Less Than 5 percent "U; U 2

c.

C787, Standard Specification for Uramum IIcmatluurkle for Emictuneau.

Recycled uranium irthales the feed asal processing of Paducah Primiuct ans) tiie "stuckpile* UR transferred finni DOE to (ISEC for enrichmer l

d l

' Analysis of samples" refers to dw analysis of samples related to cutihnent activitics er sire remediatkua (PORTS, PGDP, !)OE snal)tical tecitnk ues km psucesslow-level radmusctivity samples tumukled by the gussession huuts sured in das tab!c.

c.

t insterred frosn Doli so USLC tos cuskhment, uranium to I:s led to the cascade wdl meet the requirquents of ASTM t;xcett for Paducah Pnaluct atal & *stockpde* tr Sammlard C% "St.umi.ud SpetHKatmus for Iisannun licaailmu nic lisuihed t. I cu 'than 5 % "Il* ur AS'l M Stainted C787, "Stasalard Specification fo l

31 8

his Emkhmens" for acpocessed UF,. All ortwr uranuun dus ars smaa mces Ibc icipucincuts of AS'lM (We os C7s? h i tepruocacd Ulinuy le accep 50 pinnkls UlD assuciated with sampling, subsampfmg, armi l

t Subsequent thspouimusiiig ' us will ime is intiinluced to the cascade, wuh the caception ut suul annumt> e g.,

t l

anulyses required to c>tabhsh receiver's values.

O y

'these gussessun hmits di saw irstude material an USEC leased spae foun pcsmes l>OE oscrathms ha ukhate retained inventory of uraniurn gilate d for anairus nance or odier operational

-3 ui toth shinduwn anni egeratmg equipucru in the X-326 tacihty; spccahc conpurur> m the X 326 cam.ade that tred to be reinove g.

7 l

pupdes; nutetul aimi cqmpmend stAh as khumna traps, seat caluust ud anal GP containcr> inun always wie satuums tlut aie generated as part m

or nuterial hcid up in L705 equipuent (some of whih nuy have to tw restu>ved hu nuuiteinancel.

p D

FSU - Forn=t Soviet Unkm W

O 1

ECSR.-PORTS November 6,1998

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ECSR-PORTS April 15,1998 Rev.19 1

Blank Page O

o(j ECSR-PORTS November 6.1998 Rev.26 None of the exceedances were considered a significant honcompliance by the OEPA and none had any measurable impact on water quality or aquatic life. The following information was provided to the OEPA, who took no further action.

All of the fcam exceedances were traced to operational problems at the plant laundry. These problems caused excess concentrations of laundry detergent to intermittently accumulate in the wash water which, in turn, caused foam at the Sewage Treatment Plant (Outfall 003).

The TSS exceedances at Outfalls 010 and 005 were caused by heavy rainfalls. TSS concentrations at Outfall 010 were within the daily limits, but the flow-weighted average exceeded the 30-day average limit.

Outfall 005 is aormally dry and consequently collects windborne solids (i.e. dust) between flow events. A permit modification is being pursued to address this problem. The TSS exceedance at Outfall 003 was a mass limit exceedance caused by a high flow rate rather than a high concentration of suspended solids.

No source of trichloroethylene at Outfall 004 could be identified and its actual presence in the outfall has been questioned. Trichloroethylene has not been used at PORTS for several years, although it is present in onsite groundwater plumes. The original sample analysis could not be refuted. however, due to the lack of a suitable duplicate sample.

The pH exceedance was caused by a malfunctioning pH control system on the X-700 Biodenitrification Facility (Outfall 604). This is an internal outfall which discharges to the onsite Sewage Treatment Plant rather than to the environment. There was no corresponding exceedance or disturbance at the Sewage Treatment V

Plant.

The unanticipated bypass was caused by a heavy rainfall which overfilled the lagoon at X-621 (internal Outfall 602). The lagoon overflowed directly to the South Holding Pond without intended treatment at the X-621 facility. There was no impact at the discharge of the South Holding Pond (Outfall 002).

l He two unpermitted discharges were caused by two separate pumping problems which caused a water l

tank to overtlow to the Northeast Holding Pond (Outfall 011) in May and an equalization basin at the X-611 j

Water Treatment Plant to overflow directly to Little Beaver Creek in November. In both cases, there was no j

adverse impact on the environment.

l 2.3 RESOURCE CONSERVATION AND RECOVERY ACT USEC generates hazardous and mixed waste, and complies with all requirements for generators, including accumulation of waste in satellite accumulation areas SAAs) and accumulation of was e in 90-day accumulation areas (90-DAAs). DOE operates all permitted treatment and storage facilities under a RCRA I

permit. USEC received one NOV in 1997 regarding the control of two SAAs. The OEPA noted that these SAAs could not be locked while the process operators were out of sight of the S AAs for lunch or other breaks.

The plant installed locks on the waste containers in both the electrical maintenance cage and the electronic l

maintenance area and full compliance was achieved by July 1,1997. The NOV was closed by OEPA without l

further action in a July 15, 1997 letter.

I p

I 3

ECSR-PORTS April 15.,1998 Rev.19 USEC is currently shipping the majority of USEC-generated hazardous and mixed waste directly from l

90-DAAs to offsite treatment, storage, and disposal (TSD) facilities. Until treatment facilities are found for l

all mixed wastes some USEC mixed waste will be sent to DOE-operated storage units.

l USEC is also in compliance with OEPA requirements for management of used oil.

2.4 STORAGE TANKS USEC operates 11 underground storage tanks (USTs): 9 containing diesel fuel,1 gasoline, and 1 kerosene. The tanks are registered under and in full compliance with all regulations governing USTs as issued by the Ohio State Fire Marshall Bureau.

USEC also operates approximately 100 aboveground storage tanks.

A Spill Prevention.

Countermeasures, and Control Plan has been submitted to the United States Environmental Protection Agency (USEPA) and OEPA for these tanks pursuant to the CWA and a Facility Response Plan has been prepared pursuant to the Oil Pollution Act of 1990, 2.S POLYCHLORINATED BIPHENYLS USEC leases transformers and capacitors from DOE that contain greater than 50 parts per million (ppm) polychlorinated biphenyls (PCBs). Matters regarding the management of equipment. as well as the storage, disposal, and attention to past spills of PCBs are the responsibility of DOE pursuant to a Federal Facilities Compliance Agreement between DOE and the USEPA and the lease agreement between DOE and USEC.

2.6 ENIERGENCY PLANNING AND CONINIUhTI'Y RIGIIT-TO-KNOW ACT; RELEASE REPORTING UNDER TIIE CONIPRElIENSIVE ENVIRONSIENTAL RESPONSE, CONIPENSATION, AND LIABILITY ACT USEC is in compliance with requirements of the Emergency Planning and Community Right-to-Know Act (EPCRA). including the preparatiot. of an emergency response plan under Section 302. hazardous chemical reporting under Sections 311 and 312, and toxic chemical release reporting under Section 313. In addition, during 1997, USEC had no releases of hazardous substances in reportable quantities subject tJ l

reporting requirements under Section 103 of the Comprehensive Environmental Response. Compensation, and Liability Act (CERCLA), as amended.

l 2.7 SECTION DELETED O

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TSR-PORTS November 6.1998 Rev.26 p

SECTION 2.1 SPECIFIC TSRs FOR X-342, X-343, AND X-344 FACILITIES 2.1.3 LIMITING CONTROL SETrlNGS, LBIITING CONDITIONS FOR OPERATION, SURVEILLANCES 2.1.3.14 Liquid UF Movement 6

APPLICABILITY:

Autoclave Operational Mode I LCO:

Cylinders containing liquid UF shall be moved by overhead cranes, scale carts and 6

railcars.

SURVEILLANCE REQUIREMENTS:

Frequency Surveillance Prior to cylinder movement by forklift SR 2.1.3.14.1 Verify the cylinder cooling or straddle carrier time for solidification has been met BASIS:

jq U

A liquid UF release is significantly more severe than a release from a solid UF, source.

6 Equipment reliability of straddle carriers and forklifts and road traffic conditions increase the risk of having a liquid UF release. The handling ofliquid UF, cyli.nders with cranes, scale carts, l

6 and railcars (X-330 Tails operations only) is more reliable and therefore represents a lower risk.

l In the event a cylinder containing solid UF is dropped, while the cylinder integrity may be 6

compromised the rate of escaping UF is sufficiently low enough to limit the release to several 6

pounds upon taking emergency actions. SAR Section 3.2.7 provides the general guidelines used in determining UF, solidification [SAR Section 4.2.3,4.2.3.1 Case R-27].

Solidification Criteria 48-inch cylinders containing less than 4000 pounds ofliquid UF must cool for at least 6

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

48-inch cylinders containing 4000-8000 pounds of liquid UF must cool for at least 48 6

hours.

48-inch cylinders containing more than 8000 pounds of liquid UF must cool for at least 5 days.

30-inch cylinders (all assumed to be filled to limit) must cool for at least 3 days.

5-inch. 8-inch, and 12-inch cylinders must cool for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

f3 V

2.1-24

~

e TSR PORTS November 6.1998 Rev.26

/G V

SE'CTION 2.5 SPECIFIC TSRs FOR X-326 ERP, X-333 LAW, AND X-330 TAILS WITHDRAWAL STATIONS 2.5.3 LIAIITING CONTROL SE'ITINGS, I IAIITING CONDITIONS FOR OPERATION, SURVEILLANCES 2.5.3.9 Liquid UF Cylinder Movement 6

APPLICABILITY:

Withdrawal Operational Modes III, V LCO:

Cylinders containing liquid UF shall be moved by overhead cranes, scale carts and 6

railcars.

SURVEILLANCE REQUIRESIENTS:

Frequency Surveillance i

Each cylinder disconnection SR 2.5.3.9.1 Verify the cylinder valve protector has been installed prior to removing cylinder from withdrawal cart Prior to cylinder movement by SR 2.5.3.9.2 Verify the cylinder cooling time for l p)

(

forklift or straddle carrier solidification has been met.

BASIS:

l A liquid UF release is significantly more severe than a release from a solid UF,, source, j

6 i

Equipment reliability of straddle carriers and forklifts and road traffic conditions increase the risk of having a liquid UF release. The handling ofliquid UF cylinders with cranes, scale carts, 6

6 and railcars (X-330 Tails operations only) is more reliable and therefore represents a lower risk.

In the event a cylinder containing solid UF is dropped, while the cylinder integrity may be 6

[

compromised the rate of escaping UF is sufficiently low enough to limit the release to several 6

i pounds upon taking emergency actions. SAR Secticn 3.2.7 provides the general guidelines used in determining UF solidification [SAR Section 4.2.3.1 Case R-27].

[

6 l

Solidification Criteria 48-inch cylinders containing less than 4000 pounds of liquid UF must cool for at least 6

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

48-inch cylinders containing 4000-8000 pounds of liquid UF must cool for at least 48 6

' hours.

48-inch cylinders containing more than 8000 pounds of liquid UF must cool for at least 6

5 days.

g) 30-inch cylinders (all assumed to be filled to limit) must cool for at least 3 days.

5-inch, 8-inch, and 12-inch cylinders must cool for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 2.5 17 L'