ML19312A443

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License Amendment Request - Revision to License Application for the American Centrifuge Lead Cascade Facility
ML19312A443
Person / Time
Site: 07007003
Issue date: 10/17/2019
From: Wiehle K
American Centrifuge Operating
To: John Lubinski
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
ACO 19-0025
Download: ML19312A443 (24)
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of Nuclear Power October 17, 2019 ACO 19-0025 ATTN: Document Control Desk Mr. John W. Lubinski, Director Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 American Centrifuge Lead Cascade Facility Docket Number 70-7003; License Number SNM-7003 License Amendment Request - Revision to License Application for the American Centrifuge Lead Cascade Facility

Dear Mr. Lubinski:

The purpose of this letter is to request, in accordance with 10 Code of Federal Regulations (CFR) 70.34, U.S. Nuclear Regulatory Commission (NRC) review and approval of the proposed license amendment to the American Centrifuge Lead Cascade Facility (Lead Cascade) License Application to remove the requirement for an emergency plan. to this letter provides a description, justification for the proposed change, and American Centrifuge Operating, LLC (ACO) determination that the proposed change associated with this request is not significant. Enclosure 2 of this letter contains the proposed changes for the NRC's prior review and approval.

ACO requests NRC review and approval of the proposed changes contained within Enclosure 2 at your earliest convenience, but no later than December 3, 2019. If you have any questions regarding this matter, please contact me at (740) 897-3859.

Sincerely,

~xw~

Kelly L. Wiehle Regulatory Manager

Enclosures:

As Stated American Centrifuge Operating, LLC 3930 U.S. Route 23 South-P.O. Box 628 Piketon, OH 45661

Mr. John W. Lubinski October 17, 2019 ACO 19-0025, Page 2 cc:

R. DeVault, DOE, NE-OR3, NE-ORSO R. Edwards, PPPO, LEX Y. Faraz, NRC HQ J. Hutson, Pro2Serve (CONIR), NE-ORSO L. Pitts, NRC Region Il D. Tiktinski, NRC HQ M. Vick, PPPO, PORTS of ACO 19-0025 Description, Justification, and Significam:e Determination for Change Informatnon contained within does not contain Export Controlled mformation Reviewer: #1014 Date: ]. 0/17/2019

Description ACO 19-0025 Page 1 of 3 The proposed changes include a revision of Chapter 8. 0, Emergency Management, of the American Centrifuge Lead Cascade Facility (Lead Cascade) License Application to remove the requirements to maintain an emergency plan. This proposed revision will in turn formally cancel USEC-02, Emergency Plan for the Portsmouth Gaseous Diffusion Plant (PORTS), and remove the commitment to maintain the corresponding Emergency Plan Implementing Procedures (EPIPs).

The proposed changes contained within Enclosure 2 of this letter are annotated with a revision bar in the right-hand margin and identified by the following method:

Blue Strikem1t - Identifies text to be removed Red Underline - Identifies text added Additionally, administrative changes which have been determined through the 10 Code of Federal Regulations (CFR) 70. 72 and/or 70.32 process not to require prior NRC review and approval for Chapter 2.0, Organization and Administration, and Chapter 7.0, Fire Safety, which reference the Emergency Plan (USEC-02) are being provided for information only purposes.

Justification for Change On March 2, 2016 (ACO 16-0010), American Centrifuge Operating, LLC (ACO) notified the U.S.

Nuclear Regulatory Commission (NRC) of ceased operation of the Lead Cascade and subsequently completed decontamination and decommissioning in accordance with the NRC-approved Decommissioning Plan.

On April 19, 2018 (ACO 18-0015), as part of the Lead Cascade decommissioning, ACO submitted the Final Status Survey Report (FSSR) to the NRC for final review and approval. On September 23, 2019, the NRC approved the FSSR, confirming that no radiological materials remain in Lead Cascade areas and the areas meet NRC's radiological free release criteria. 10 CFR 70.22(i)(l )(i) requires an evaluation demonstrating that a maximum dose to a member of the public offsite of 1 rem effective dose equivalent or an intake of 2 milligrams of soluble uranium due to a release ofradioactive materials will not be exceeded or an emergency plan must be implemented. Since the Lead Cascade areas no longer contain any radioactive material, the 10 CFR 70.22(i)(l)(i) criteria cannot be exceeded. Therefore, an emergency plan is no longer required for the Lead Cascade.

On March 22, 2019, the U.S. Department of Energy (DOE) notified of its intent to transition to a three-tier classification system and to fully comply with DOE Order 151. ID, Comprehensive Emergency Management System, at the Portsmouth Site. General emergency response for ACO leased activities will continue to be conducted through an approved Reverse Work Authorization with the DOE for fire and emergency preparedness services.

Based upon the above justification, the proposed changes do not introduce an undue risk to the public health and safety, the environment, or common defense and security.

ACO 19-0025 Page 2 of3 On May 31, 2019, the DOE issued a letter contract to ACO to deploy a 16-machine AClOOM high assay, low-enriched uranium (HALEU), cascade in ACO leased areas at DOE's site in Piketon, Ohio. Moving forward under the HALED Program, ACO will update and amend the American Centrifuge Plant (ACP) NRC Materials License (SNM-2011) for NRC review and approval to allow HALED production. At that time, if required, new proposed emergency plan requirements will be addressed in a future License Amendment Request for the NRC's prior review and approval.

Significance Deten-mhnation ACO has reviewed the proposed changes associated with this request and has determined the following:

1.

No significant change to any condition to the License.

None of the conditions to the Materials License specifically address the Emergency Plan that is being deleted. Thus, the proposed change will have no impact on any of the conditions to the Materials License.

2.

No significant increase in the probability of occurrence or consequences of previously evaluated accident.

As confirmed by the NRC-approved Final Status Survey Report, there is no radiological material within the Lead Cascade leased areas; therefore, the performance requirements in 10 CFR 70. 61 are no longer applicable to the Lead Cascade license. NRC has amended the Lead Cascade NRC Materials License to add a license condition that ACO cannot receive any licensed material at the Lead Cascade without prior NRC approval.

3.

No new or different type of accident.

As confirmed by the NRC-approved Final Status Survey Report, there is no radiological material within the Lead Cascade leased areas; therefore, the performance requirements in 10 CFR 70. 61 are no longer applicable to the Lead Cascade license. NRC has amended the Lead Cascade NRC Materials License to add a license condition that ACO cannot receive any licensed material at the Lead Cascade without prior NRC approval.

4.

No significant reduction in margins of safety.

As confirmed by the NRC-approved Final Status Survey Report, there is no radiological material within the Lead Cascade leased areas; therefore, the performance requirements in 10 CFR 70. 61 are no longer applicable to the Lead Cascade license. NRC has amended the Lead Cascade NRC Materials License to add a license condition that ACO cannot receive any licensed material at the Lead Cascade without prior NRC approval.

5.

No significant decrease in the effectiveness of any programs or plans contained in the licensing documents.

ACO 19-0025 Page 3 of3 Consistent with the requirements in 10 CFR 70.22(i)(l )(i), an emergency plan is no longer required for the Lead Cascade and is being deleted. No licensed material remains within the Lead Cascade leased areas; therefore, the Fundamental Nuclear Material Control Plan is no longer applicable to the Lead Cascade license. Deletion of the Emergency Plan does not affect any other plant safety, safeguards, or security programs contained in the License Application.

6.

The proposed changes do not result in undue risk to: 1) public health and safety; 2) common defense and security; and 3) the environment.

There is no radiological material within the Lead Cascade leased areas, therefore, there are no conditions associated with the Lead Cascade license that result in any risk to public health and safety, the environment, or to the common defense and security. The Emergency Plan is not required due to the absence of radiological material and is being deleted consistent with 10 CFR 70.22(i)(l)(i).

7.

There is no change in the type or significant increases in the amounts of any effluents that may be released off-site.

The existence of an emergency plan has no influence on the creation of any sources of hazardous substances, hazardous waste, or new waste streams that could be released off-site.

8.

There is no significant increase in individual or cumulative occupational radiation exposure.

There is no radiological material within the Lead Cascade leased areas and the areas meet NRC' s free release criteria. Therefore, occupational radiation exposure is not relevant to activities associated with the Lead Cascade license.

9.

There is no significant construction impact.

The existence of an emergency plan has no influence on any construction activities.

of ACO 19-0025

Proposed Changes to License Application and Supporting Documents for the American Centrifuge Lead Cascade Facility lnfo!!'mation contained within does not contain Export Controlled fuformation Reviewer: #1014 Date: !0/17/2019

License Application for the American Centrifuge Lead Cascade Facility Proposed Change 8.0 EMERGENCY MANAGEMENT 8.1 Emergency Plan October 2019 The Lead Cascade ts m a leased area of the U.S. Department of Energy's (DOE)

Portsmouth Gaseous Diffusion Plant (PORTS) reservation, adjacent to the Former Uranium Enrichment Facilities (FUEF) as shown in Figure 8.1-1 (located in Appendix B of this license application).

When the U.S. Nuclear Regulatory Commission (NRC) assumed regulatory oversight responsibility over PORTS, leased by the United States Enrichment Corporation (USEC) from DOE, USEC implemented an NRC-approved Emergency Plan on the PORTS reservation in accordance with the requirements of 10 Code o(Federal Regulations (CFR) 76.91. The NRC notice promulgating IO CFR Part 76 confirmed that the emergency planning requirements set forth in 10 CFR Part 70 for other nuclear fuel cycle facilities were appropriate for the gaseous diffusion plants and that the requirements in 10 CFR 76. 91 were based upon the emergency planning provisions in 10 CFR Part 70. The Emergency Plan design adhered to the 10 CFR 70.64 Emergency Capability Baseline Design Criteria. Accordingly, the Emergency Plan format was generally based upon NRC Regulatory Guide 3.67, Standard Fom,at and Content for Emergencr Plans for Fuel Cycle and Materials Facilities (January 1992). Additionally, the emergency action levels were developed using examples provided in this Regulatory Guide. Based on these factors, and to ensure a consistent response by emergency response personnel, the existing PORTS Emergency Plan was utilized to meet the 10 CFR 70.22(i)(l)(ii) and (i)(3) requirements for the Lead Cascade during Lead Cascade operation.

While the PORTS Emergency Plan contained pertinent information specific to the Lead Cascade, the overall elements of the Emergency Plan apply to the entire PORTS reservation and the activities conducted on the PORTS site. DOE Decontamination and Decommissioning contractor, Fluor-BWXT Portsmouth LLC (FBP); DOE Facility Support Services contractor, Portsmouth Mission Alliance, LLC (PMA);

-the-llOe.J4.m.le-{ 'ontrnemt fut -the--PQRT-S -stt-e -ftH-t-1 ti-le-hu+Het Uttttltttffieft+t:Htttffit l*ac1l1lle<; tfUef:), and Mid-America Conversion Services, LLC (MCS) Depleted Uranium Hexafluoride (DUF6) Conversion Facility also conduct activities and operate non-leased facilities at the site that are regulated by DOE. FBP is responsible for the safe operation of the FUEF and is responsible for the day-to-day management and operation of the FUEF. Upon the return of the PORTS leased areas by USEC to DOE in 2011, the program of emergency management and response services became the responsibility of FBP.

Operation of the Lead Cascade has ceased and all decommissioning activities have been completed American Centrifuge Operating, LLC submitted, and NRC subsequently approved (Reference 1) the Final Status Survey Report confirming that no radiological materials remain in Lead Cascade areas and the areas meet NRC's radiological free release criteria. Conseguently. the Lead Cascade satisfies the 10 CFR 70.22(i)(l)(i) criteria of not exceeding a maximum dose to a member of the public offsite of l rem effective dose equivalent or an intake of 2 milligrams of soluble uranium due to a release of radioactive materials. Therefore, an Bemergency flplan is no longer required for the Lead Cascade.+he-1,eaa {'Rscade;-q. located III a leai,ed areR-ef the l I S Deparlment ~ ~ID' -'T (.{}()el Po1tsmou1h Gaseous D1ffus1on --Pl-rult (PORT ' resen.1al1on, ud1aeeAt to the gnseouc, d1ffucaoA plant as shoWH m Figure ~ I I (loeated IA Ap~enam H of tHt'.l Hff+lSe-itf)f kftt-tefl-}-

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  • forms ~*;essnient aelleR'l, 8-5

License Application for the American Centrifuge lead Cascade Facility Proposed Change October 2019 htt Lettd (.~ emef~lCI~~ tttltes ~t-tt,M iO ew:tttfC ffittt ttcms rel~i 00 fot saktf :are ussessed fuf collateral dumage httttttt~ tG-~~ me1m1allv w,-~ -ef 1nvllnt10A~ li~g,!lsg,e~~eAt:'¥' *;ut~poit 01~0t11,'ut101v1 thut AltW ae eal lea t-1~1011 to re':lfJOAa ta e1'l10rgene1 es et tht11 plt1AI, tRt.11 tl!J11~

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-beeti C'eseede 1-ttt' rey1i;ion.., to the PORTS l*mefgt!fl--Y- -llktfl-attd WlP-s-t'fl-OOl-ltpft-'nttlg the'le lflp1ec,-were rn-1rtk*mentea puer-to ~Arn~ opernt1on ef th~-1--,eat-l.('escaae

+ht>- l we1rnee will contmue lo perl-01m add1l1011al revlEW"1 of the Emergency Plan and mcot13onlte any 111:11t:e*,snrv ndd1t1onal *;pee1fie emergeRey RUiAagemeAt U'IJ'ICet*10f the I,end Ca!'it.1ade 1me the~-ng-Emergencv -P-ffifl mcludmg adding any hOLardous ehenuea.l::i ns!.oemted wHh lhe l,ettd Cac,eade-t:e -ttte mustmg h.r.;t-e.f ehem,eals, wtth clear md1cut1on thnt the lrn;,ardous eht*m1cel*1 pertam to the I,ead Casoade 8-6

Proposed Change License Application/or the American Centrifuge Lead Cascade Facility October 2019 J.he-mft-trn m++nn \\....itl H rt tttl'i-f1-gttrn-+i-tt5-i:}et*n 4:te rn 1111 ed -ttt -ttltl-ftttl ~

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.(.'.ft.seffde-1,o ell ti 011 8-7

License Application for the American Centrifage Lead Cascade Facility Proposed Change

~ws.~~

"' 1-+*

(rl'IWt'-ftl ~(~Hf;-& Radiuq et: A1,1n-o,imatell 1-0 Miles front fhe POR n, Re'lv1*,,ntio11 8-8 October 2019

License Application/or the American Centrifage Lead Cascade Facility Proposed Change 8-9 October 2019

license Application for the American Centrifuge Lead Cascade Facility Proposed Change

.. ~'t'-8.l

'l ~

  • ffflhwm Miljl ot' Wml~

dh*lt*1ent>t' It 8-10 October 2019 J

License Application for the American Centrifage Lead Cascade F aci/ity Proposed Change October 2019 1 ht> mfontttttmn 'n'l~hm -t+H-. ftgwe hw. ~l fie~ mtttee $ rent-tt1tt 4~ jltl*Ft ( tmt+nH~ ltt*ffifttttttmn und,., lorntetl 111 AppendP( U of till': lteen 1H? 11prlteflt1011 Fi~tffl' 8.1 4 ANim-M-ttJl-O.f-the-PORTS Resen*etion (f{et eren1:1e I )

8-11

License Application for the American Centrifuge Lead Cascade Facility Proposed Change October 2019 8.2 References

1.
2.

+-

ll ~ DepmlHlt'Ht (~f the 1-tttetHH -l~ ~ttt,itl- ~ttvev. Re-+t-en VA. WcllStl(>

1-H!tt +J.Www w;g; 1;tw +!~-ltttH+NRC letter dated September 23, 2019, regarding Approval of Centrus Energy Corp. Final Status Survey Report and Request to Cancel Its Decommissioning Funding Instrument for the American Centrifuge Lead Cascade Facility NllKI*(, I S20 l<a*1t~"*tl 1frl"<'II P/.i1*1 '"r 11*e '~t1we11 o/t1 1 tee'"t< *l*n1*t*t"10" 1oi* t' '"*el Pl i

I ff I"

{

I" f

jfV (V

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ffi

, f( n if ff F 1

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{ v,

~

J,.tft'+Hft'

- --NRC Regulatory Guide 3.67, Ke1t'l'*H)n o. Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities. January 1992 8-12

Portsmouth Gaseous Diffusion Plant (PORTS) Emergency Plan Revision 204 PORTSMO TH GAS DIFFUSIO P A (PORT rllE Revision 212 Informati n contained within does not contain Export ControUed Information Reviewing Official:. #152 Date:

06/08/2017 November 2013 UScC-02 June 2017

Proposed Change license Application for the American Centrifi1ge lead Cascade Facility October 2019 FOR INFORMATION ONLY 2.2 Management Contrnls The Licensee has established management systems with associated policies, administrative procedures, and management controls to ensure: the Lead Cascade equipment, facilities and procedures; the staff (including training and qualifications); and the programs provide for the protection of the health and safety of workers and the public, protection of the environment, and for the common defense and security. Management controls have been established to maintain configuration management of the Lead Cascade. These controls are described in Section 11.1 of this license application. Organizations with environmental, health, safety, safeguards, security, and quality responsibilities have been established with a reporting chain, independent from the operations organization. Effective lines of communication and authority among the organizations involved in the engineering, environmental, safety, and health, and operations functions of the facility are clearly defined.

The management controls established by the Licensee for the Lead Cascade include policies, management systems, and administrative procedures that are communicated to Lead Cascade personnel. Policies related to the protection of health and safety of workers and the public, protection of the environment, and providing for the common defense are discussed in pertinent sections of this license application.

Activities that are essential for effective implementation of the environmental, safety, and health functions are documented in approved, written procedures, prepared in compliance with a document control program.

Procedure development and document control are described in Section 11.4 of this license application and Sections 5 and 6 of the QAPD.

Management measures required to ensure the availability and reliability of IROFS are described in Chapter 11.0 of this license application.

Controls specific to Lead Cascade programs are identified in the QAPD, Fundamental Nuclear Material Control Plan, and Security Program.

The commitment tracking and corrective action management systems are integrated to prioritize Lead Cascade actions consistent with their safety and safeguards significance. Any person working in the facility may report potentially unsafe conditions or activities by submitting a problem report. Reported concerns are investigated, assessed, and resolved as described in Section 11.6 of this license application.

Where safety, security, or safeguards might be adversely impacted by cost or schedule considerations, it is the policy of the Licensee to subordinate cost and schedule considerations to ensure adequate treatment of safety and safeguards in full compliance with applicable regulatory requirements.

The integration of Lead Cascade operations and the various programs and requirements is accomplished through a variety of management practices, including:

S aff meetings to discuss issues and policy implementation 2-13

License Application for the American Centrifi1ge Lead Cascade Facility Proposed Change Review of performance indicators Review of identified events or conditions Multi-discipline reviews by the FSRC October 2019 Plant work permit systems that provide the integration in the field of various health, safety, and environmental program requirements and hazard evaluations Additionally, oversight of the integration of various program elements is provided by the QA Organization.

Written interface agreements exist with offsite emergency resources such as fire, police, ambulance/rescue units, and medical services. th~ttttt>-rlttff-tt~n.*etHt~nt-rnre-tttWt~ m more

~+ +t+ ~

!Jo rt "illlOHth.( r!l',t"tH 1*; l)+U+t*+H*t-~4an+-f-lJ(..}R-W F mt1 1 ~en C'I' Pl nn 2.2.1 Facility Safety Review Committee The FSRC performs multi-discipline reviews of day-to-day and proposed Lead Cascade activities to ensure that these activities are and/or will be conducted in a safe manner. The FSRC advises the General Manager, American Centrifuge Plant Operations and Decommissioning on matters related to RP, Nuclear Safety, Chemical Safety, Fire Safety, and Environmental Protection. The specific membership, qualifications, meeting frequency, quorum, functions, responsibilities, and required records are provided in a facility procedure.

Auditing and oversight of FSRC activities is the responsibility of the QA Manager.

Subcommittees may be established by the FSRC chairperson to provide assistance in conducting reviews and assessments as described in the FSRC procedure.

The FSRC chairperson approves the subcommittee procedures, membership, and member qualifications.

The FSRC maintains the overall responsibility for any required reviews.

2.3 Pre-ope.-ational Testing and Initial Sta1*t-up Specific plans have been established to ensure the safe and efficient turnover, testing, and start-up of Lead Cascade centrifuge machines, equipment, and support systems. These plans cover the transition from the refurbishment/construction phase to the operations phase of the Lead Cascade Project.

The Integrated Systems Test/Start-up Manager is responsible for development and implementation of testing to provide for the turnover and acceptance of equipment and systems from contractors/vendors to the Licensee.

2-14

License Application for the American Centrifage Lead Cascade Facility Proposed Change 2.4 References October 2019

1.

NR-3605-0003, Quality Assurance Program Description for the American Centrifuge Plant

2.

NUREG-1324, Proposed Method for Regulating Major Materials Licensees

3.

NUREG-1520, Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility 2-16

License Application for the American Centri.fi1ge lead Cascade Facility Proposed Change 7.1.4 Personnel T1*aining October 2019 Fire services personnel are trained and equipped to handle anticipated types of emergencies.

Firefighter training is equivalent to the state certified firefighter training curriculum. Emergency medical response personnel meet requirements for state certification as Emergency Medical Technicians (these are typically also firefighters). Qualified instructors provide a range of classroom and hands-on training to maintain standards of performance for all response personnel. Training needs are reviewed annually and the training program modified to meet identified needs.

Records of the training activities are maintained in accordance with Records Management and Document Control requirements. Training is based on national standard emergency response methodology with site-specific training on issues unique to the site.

Specific training activities include firefighting, hazardous material response, confined space rescue, emergency medical response, radiological emergencies, and rescue. Drills are periodically conducted-ttuilt telly RG part of~ l-111ergen'1' Pl an. Training requirements of fire services personnel are described in Section 11.3 of this license application. Fire Officers have at least five years experience in fire service with management and leadership training.

An on-site emergency squad provides additional support for the fire services group. This group is on call for response to assist emergency responders at emergency scenes. Training is provided for the type of activities they may be called upon to perform.

Employees receive initial and biennial fire safety training as part of General Employee Training (GET) on emergency preparedness. This includes emergency reporting, facility evacuation, and fire extinguisher familiarization. GET is described in Section 11.3 of this license application.

7.1.5 Impairment Cont1*ol Closure of valves on the water system supplying the fire suppression systems is controlled by a written permit system. Fire services controls the valve closure permit system; therefore, fire services is notified of the impairment of fire suppression systems. Only groups authorized by Fire Safety/Emergency Management Manager have the authority to issue permits and operate fire protection valves.

This permit system provides for the notification of the facility manager and the Plant Shift Superintendent (PSS) of the reason for the impairment, the expected duration of the impairment, the person doing the valving, system restoration time, person restoring the system, and residual partial system impairment (e.g., branch line removed). Compensatory actions are initiated when building sprinkler systems are out of service. These may include suspension of hot work or other hazardous processes, personnel notifications, fire patrols, or other action necessary as determined by the Fire Safety/Emergency Management Manager. Systems taken out of service for repair are usually returned to service within an 8-hour period; actual required repairs will affect the actual time needed to complete the repair.

7-4

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