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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N5861999-10-22022 October 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/99-09 Issued on 990827 ML20217H6911999-10-19019 October 1999 Ack Receipt of 990928 Application to Revise Technical Safety Requirements 2.2.3.15 & 2.7.3.14.Initial Administrative Review Finds Application Acceptable.Completion of Review Is Anticipated by 991215 ML20217N9141999-10-15015 October 1999 Forwards Rev 6 of NCS Cap,Providing Addl Details within Subtask 3.3,addl Ncsa/E Reviews & Establishes New Milestone to Conduct Addl Reviews IAW Procedure XP2=EG-NS1037, Review of Non-Priority 1 & 2 ML20217M2961999-10-15015 October 1999 Provides Addl Changes to Updated SAR Certificate Amend Request,Including Changes Made IAW Item 5 of Plan of Action Schedule for Compliance Plan Issue 2 & Changes That Resulted from Reevaluation of Autoclave head-to-shell O-ring ML20217G4671999-10-14014 October 1999 Forwards Proprietary Insp Rept 70-7002/99-207 on 990920-23. No Violations Noted.Under Provisions of Section 2.790(d), Repts Containing Info Related to Licensee MC&A Program, Exempt from Public Disclosure ML20217G1731999-10-14014 October 1999 Requests Addl Info Re Applications Dtd 990924,requesting Amends to Cocs for Paducah & Portsmouth GDPs for Revised QA Programs.Encl Identifies Specific Info Needed.Info Should Be Provided within 30 Days ML20217F5481999-10-0808 October 1999 Discusses Insp Rept 70-7002/99-12 on 990810-0920 at Ports- Mouth Gaseous Diffusion Plant.No Cited Violations of NRC Requirements Were Identified During Insp ML20217B6121999-10-0606 October 1999 Forwards Copy of Security Incident Log for Month of Sept 1999 ML20217A4781999-10-0404 October 1999 Forwards Revised Event Rept 99-17,for Event Resulting from Determination That Sprinkler Sys Not Capable of Meeting Operability Requirements.Caused by Mineral Deposits.Provided Following Completion of Root Cause Evaluation ML20212H5991999-09-27027 September 1999 Responds to Violations Noted in Insp Rept 70-7002/99-09. Corrective Actions:Engineering Evaluated Site Rail Track Insp Process for Improvement ML20216J7891999-09-27027 September 1999 Provides Required 30-day Event Rept 99-19 for Event That Resulted from Failure of Cascade Automatic Data Processing Data Processing Smoke Detection Sys at Portsmouth Gaseous Diffusion Plant.Encl 2 Is List of Commitments Made in Rept ML20212H1251999-09-24024 September 1999 Notifies NRC of Change in Regulatory Commitments Associated with Submittal Date for Update of Application SAR Chapter 3.Specifics of Commitment Changes of Listed ML20212H3801999-09-24024 September 1999 Responds to 990723 RAI Re 1999 Annual Update to Certification Applications ML20212G0551999-09-23023 September 1999 Provides Revised 30-day Event Rept 99-06 for Emergency Condition That Was Declared Alert at Portsmouth Gaseous Diffusion Plant ML20212G9401999-09-23023 September 1999 Responds to 990806 Reply to NOV in Ltr with Insp Rept 70-7002/99-04.Revised Reply Reviewed & Responses to Violations 1.B & 1.C Do Not Fully Address Needs as Clarified in 990715 Telcon.Resubmit Response within 30 Days of Ltr ML20212H3721999-09-22022 September 1999 Forwards NRC Form 790 Classification Record Documents for Paducah & Portsmouth GDPs That Were Generated During Month of Aug 1999.Without Encl ML20217J1211999-09-20020 September 1999 Submits Listed Comments on NRC Proposed Rule, Reporting Requirements for Nuclear Power Reactors ML20216E6911999-09-13013 September 1999 Forwards 30-day Written Rept Er 99-18,re Actuation of Cascade ADP Smokehead in X-333 Bldg Low Assay Withdrawal Station.Caused by UF6 Release from Law A/B Compressor Shaft Seal Area.Planned C/As Will Be Provided in Revised Rept ML20211Q7761999-09-10010 September 1999 Forwards Insp Rept 70-7002/99-205 on 990816-20.No Violations Noted.Insp Consisted of Selective Exams of Computer Systems, Representative Records & Interviews with Personnel ML20211P2091999-09-0909 September 1999 Provides Staff Written Clarification of NRC Reporting Expectations of When Double Contingency Losses Should Be Reported to NRC IAW Bulletin 91-001, Reporting Loss of Criticality Safety Controls, & Suppl ML20211Q8041999-09-0808 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/99-05 ML20211Q7171999-09-0808 September 1999 Forwards Required 30-day Written Event Rept 99-14,rev 1,re 990628 Event Involving Actuation of Brake Sys on Liquid U Hexafluoride Handling Crane at Plant.Revised Rept Includes Corrective Actions.Commitments in Rept Also Encl ML20211N8951999-09-0707 September 1999 Forwards Required 30 Day Event Rept 99-17,for Event That Resulted from Determination That 13 Sprinkler Sys Associated with High Pressure Fire Water Sys in Process Buildings Were Not Capable of Meeting Operability Requirements ML20211P3831999-09-0303 September 1999 Forwards Coc GDP-1,amend 3 & Coc GDP-2,amend 4 for Paducah (Pgdp) & Portsmouth (Ports) Gdps,Respectively by Revising Pgdp & Ports QAPs in Vol 3 of Respective Certificate Applications ML20211M6401999-09-0303 September 1999 Forwards Security Incident Log for Month of Aug 1999,per Requirements of 10CFR95.57(b) ML20211M6941999-09-0202 September 1999 Forwards 30-day Written Event Rept 99-09,rev 1,for Event Involving Actuation of Brake Sys on Liquid U Hexafluoride Handling Crane at Plant.Revised Rept Includes Root Cause & Corrective Actions.List of Commitments,Included ML20211L4871999-09-0101 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/99-07 Issued on 990709 ML20211K2081999-08-31031 August 1999 Discusses 990730 Revised Response to RAI Transmitted by NRC Re 990528 Response for Severity Level IV Violations Identified in Insp Rept 70-7002/99-06 ML20211K4041999-08-31031 August 1999 Forwards Responses to Remaining NRC Questions/Comments from 980601 & 0709 NRC RAIs Re SAR Update ML20211M7031999-08-30030 August 1999 Forwards Proprietary Rev 0 to Arming & Arrest Authority Security Plan for Paducah & Portsmouth Gaseous Diffusion Plants, for Review & Approval.Encl Withheld ML20211H2741999-08-27027 August 1999 Forwards Insp Rept 70-7002/99-09 on 990629-0809 & Notice of Violations Re Involving Inadequate Corrective Actions of Concern,Due to Staff Failure to Take Actions to Prevent Recent Derailment ML20211G9891999-08-26026 August 1999 Informs That on 990812,NRC Completed three-day Licensing Review of Activities Associated with Usec 990526,certificate Amend Request (CAR) to Reopen Compliance Plan Issues 8,9 & 23 at Portsmouth Plant ML20211D9311999-08-23023 August 1999 Forwards Required 30-day Written Event Rept 99-16 Re Event Involving Autoclave High Condensate Level Shutoff Actuation at Portsmouth Gaseous Diffusion Plant.List of Commitments, Included ML20211A7011999-08-17017 August 1999 Forwards Copy of Final Amend to 10CFR76 for Info of Subcommittee.Final Rule Is Being Transmitted to Fr for Publication.Final Rule Will Amend Regulations That Apply to Paducah & Portsmouth Gaseous Diffusion Plants ML20211C5951999-08-17017 August 1999 Submits Changes to Authorized Derivative Classifier List for Portsmouth Gdp.Changes Are Current as of 990806 ML20211D6341999-08-16016 August 1999 Forwards Proprietary Info Containing Process That Would Be Followed Once Deposit Identified That Could Cause Usec to Exceed NRC Possession Limit.Proprietary Encl Withheld ML20211D2351999-08-16016 August 1999 Replaces Ltr Forwarding Proprietary Followup to Submittal Re Holdup of U Enriched Greater than or Equal to 10 Weight Percent U-235 in Process Equipment ML20211D5771999-08-16016 August 1999 Submits Rev 1 to Event Rept 99-12,to Clarify That Only One of 50 Ball Lock Pins on Packages Used in Shipment Was Unfastened When Shipment Was Received.Cause Has Not Been Determined.Usec Revised Procedure XP4-TE-UH2400 ML20211C3941999-08-13013 August 1999 Forwards Proprietary Followup to Submittal Re Holdup of U Enriched Greater than or Equal to 10 Weight Percent U-235 in Process Equipment.Encls Withheld ML20211C8031999-08-13013 August 1999 Forwards Proprietary Versions of Rev 33 Changes to Fundamental Nuclear Matls Control Plan & Transportation Security Plan.Proprietary Encl Withheld ML20210P6981999-08-10010 August 1999 Forwards Insp Rept 70-7002/99-11 on 990719-23.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress ML20210Q6061999-08-0909 August 1999 Forwards NRC Form 790 Classification Record Documents for Paducah & Portsmouth Gdps,Per 10CFR95.57.Records Were Generated During Month of July 1999.Without Encl ML20210Q5291999-08-0909 August 1999 Responds to Violations Noted in Insp Rept 70-7002/99-07. Corrective Actions:On 990622,results of Nda Surveys for G-17 Valves Moved Outside Bldg X-744H Were Obtained ML20210N8511999-08-0606 August 1999 Forwards Copy of Security Incident Log for Month of July 1999 ML20210P1841999-08-0606 August 1999 Revised Response to NRC NOV Re Violations Noted in Insp Rept 70-7002/99-04.Corrective actions:DOI-832-99-03 Revised & Reissued on 990729,to Include Any Document Utilized to Support Safety Basis in Ncse ML20211A7901999-08-0404 August 1999 Forwards Info Requested During Briefing by NRC Staff on 990726 Re NRC Interactions with Usec ML20211N2031999-08-0404 August 1999 Forwards Proprietary Versions of Rev 32 Changes to Fundamental Nuclear Matls Control Plan (FNMCP) & Transportation Security Plan.Proprietary Info Withheld,Per 10CFR2.790 & 9.17(a)(4) ML20210L1751999-08-0202 August 1999 Forwards Required 30-day Event Rept 99-15 Re Event That Resulted from Declaration of Alert Emergency Classification at Portsmouth Gaseous Diffusion Plant.Encl 2 Contains List of Commitments Made by Licensee ML20210U8511999-07-30030 July 1999 Forwards Quarterly Status Rept for Portsmouth Nuclear Criticality Safety Program Corrective Action Plan for Period 990421-0716.No New Commitments Are Contained in Submittal ML20210K0291999-07-30030 July 1999 Responds to NRC Expressing Concerns with 990528 Reply to NOVs Re Insp Rept 70-7002/99-006.Revised Response Encl 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217N5861999-10-22022 October 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/99-09 Issued on 990827 ML20217H6911999-10-19019 October 1999 Ack Receipt of 990928 Application to Revise Technical Safety Requirements 2.2.3.15 & 2.7.3.14.Initial Administrative Review Finds Application Acceptable.Completion of Review Is Anticipated by 991215 ML20217G4671999-10-14014 October 1999 Forwards Proprietary Insp Rept 70-7002/99-207 on 990920-23. No Violations Noted.Under Provisions of Section 2.790(d), Repts Containing Info Related to Licensee MC&A Program, Exempt from Public Disclosure ML20217G1731999-10-14014 October 1999 Requests Addl Info Re Applications Dtd 990924,requesting Amends to Cocs for Paducah & Portsmouth GDPs for Revised QA Programs.Encl Identifies Specific Info Needed.Info Should Be Provided within 30 Days ML20217F5481999-10-0808 October 1999 Discusses Insp Rept 70-7002/99-12 on 990810-0920 at Ports- Mouth Gaseous Diffusion Plant.No Cited Violations of NRC Requirements Were Identified During Insp ML20212G9401999-09-23023 September 1999 Responds to 990806 Reply to NOV in Ltr with Insp Rept 70-7002/99-04.Revised Reply Reviewed & Responses to Violations 1.B & 1.C Do Not Fully Address Needs as Clarified in 990715 Telcon.Resubmit Response within 30 Days of Ltr ML20211Q7761999-09-10010 September 1999 Forwards Insp Rept 70-7002/99-205 on 990816-20.No Violations Noted.Insp Consisted of Selective Exams of Computer Systems, Representative Records & Interviews with Personnel ML20211P2091999-09-0909 September 1999 Provides Staff Written Clarification of NRC Reporting Expectations of When Double Contingency Losses Should Be Reported to NRC IAW Bulletin 91-001, Reporting Loss of Criticality Safety Controls, & Suppl ML20211Q8041999-09-0808 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/99-05 ML20211P3831999-09-0303 September 1999 Forwards Coc GDP-1,amend 3 & Coc GDP-2,amend 4 for Paducah (Pgdp) & Portsmouth (Ports) Gdps,Respectively by Revising Pgdp & Ports QAPs in Vol 3 of Respective Certificate Applications ML20211L4871999-09-0101 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/99-07 Issued on 990709 ML20211K2081999-08-31031 August 1999 Discusses 990730 Revised Response to RAI Transmitted by NRC Re 990528 Response for Severity Level IV Violations Identified in Insp Rept 70-7002/99-06 ML20211H2741999-08-27027 August 1999 Forwards Insp Rept 70-7002/99-09 on 990629-0809 & Notice of Violations Re Involving Inadequate Corrective Actions of Concern,Due to Staff Failure to Take Actions to Prevent Recent Derailment ML20211G9891999-08-26026 August 1999 Informs That on 990812,NRC Completed three-day Licensing Review of Activities Associated with Usec 990526,certificate Amend Request (CAR) to Reopen Compliance Plan Issues 8,9 & 23 at Portsmouth Plant ML20211A7011999-08-17017 August 1999 Forwards Copy of Final Amend to 10CFR76 for Info of Subcommittee.Final Rule Is Being Transmitted to Fr for Publication.Final Rule Will Amend Regulations That Apply to Paducah & Portsmouth Gaseous Diffusion Plants ML20210P6981999-08-10010 August 1999 Forwards Insp Rept 70-7002/99-11 on 990719-23.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress ML20211A7901999-08-0404 August 1999 Forwards Info Requested During Briefing by NRC Staff on 990726 Re NRC Interactions with Usec ML20210G0391999-07-26026 July 1999 Forwards Compliance Evaluation Rept & Fr Notice for Revised Qaps,Per 990212 Application ML20210D8181999-07-23023 July 1999 Submits Response to SA Toelle Ltr Dtd 990614, 10CFR76.68(a)(3) Decreased Effectiveness Reviews & RAI for Paducah & Portsmouth Transmittals of 1999 Annual Update to Certification Applications ML20210V3481999-07-16016 July 1999 Informs That Staff Completed Review of New Payment Surety Bonds (Psb) for Paducah & Portsmouth Gdps,Which Were Provided in .Cancelled Psbs for Liberty Mutual Insurance Co & Safeco Insurance Co of America,Encl ML20209G2501999-07-14014 July 1999 Forwards Copy of Compliance Evaluation Rept Prepared to Support Resolution & Closure of Violation in Insp Rept 70-7002/97-203,re Failure to Have Adequate Benchmarks in Validation Rept Analysis of Models of U Sys ML20209F1031999-07-12012 July 1999 Forwards Insp Rept 70-7002/99-204 Conducted on 990614-17.No Violations Noted.Major Areas Inspected:Mc&A Safeguards Program.Rept Details Withheld,Per 10CFR2.790 ML20209E8711999-07-0909 July 1999 Discusses Insp Rept 70-7002/99-08 on 990614-17 & Forwards Notice of Violation ML20209E8551999-07-0909 July 1999 Forwards Insp Rept 70-7002/99-07 on 990517-0629 & Nov. Violation of Concern Because Staff Displayed Lack of Rigor in Failing to Ensure That Nuclear Facility Criticality Safety Controls Were Implemented as Listed ML20209D4821999-07-0707 July 1999 Discusses Licensee 990702 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by Tsrs 2.2.3.2,2.4.3.1,2.5.3.1 & 2.7.3.2.NRC Concluded That NOED Warranted ML20209B7911999-07-0101 July 1999 Forwards Insp Rept 70-7002/99-203 Conducted on 990607-11.No Violations Noted ML20196H8421999-06-29029 June 1999 Discusses Insp Rept 70-7002/99-06 on 990322-26 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000 ML20196F1121999-06-23023 June 1999 Responds to 990528 Response to NOV Submitted by with Insp Rept 70-7002/99-06.Response Not Fully Addressing Informational Needs in Notice.Response to Notice Requested to Be Resubmitted within 30 Days of Date of Ltr ML20207H5001999-06-11011 June 1999 Discusses Insp Rept 70-7002/99-05 on 990406-0515 & Forwards Notice of Violation Re Weakness in Staff Knowledge & Implementation of Plant Procedures in Several Program Areas ML20195J2001999-06-11011 June 1999 Ack Receipt of Certificate Amend Request Re Reopening of Compliance Plan Issues 8,9 & 23.Staff Has Completed Initial Administrative Review of Application & Anticipates Completing Review by 990831 ML20207G2641999-06-0808 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/99-03 Sent on 990528.Reviewed Corrective Actions & Have No Futher Questions.Actions Will Be Examined During Future Insp ML20207F2571999-06-0202 June 1999 Informs That NRC Disagrees with Usec Conclusion for Not re-opening Issue 2 of Compliance Plan,Since Proposed Change to Sarup Submittal Constitutes Major Rev to Operating Safety Bases Contained in Technical Safety Requirements ML20207A0121999-05-21021 May 1999 Forwards Insp Rept 70-7002/99-04 on 990222-0312 & Notice of Violations Re Inadequate Knowledge & Understanding by Some Staff & Mgt of Corrective Action ML20207E5421999-05-18018 May 1999 Discusses Apparent Violation Involving Usec & Lockheed Martin Utility Svcs,Inc.(Lmus) Mgt Discriminating Against Lmus Employee at Paducah Gaseous Diffusion Plant. Violation Being Considered for Escalated Ea.W/O Encl 2 ML20206S3091999-05-17017 May 1999 Confirms Meeting Scheduled for 990610 in Lisle,Il to Discuss Failure to Classify Emergency Conditon as Alert IAW Portsmouth EP ML20206N3851999-05-12012 May 1999 Forwards Amend 1 to Coc GDP-1 & Amend 3 to Coc GDP-2 IAW 990316 Applications,Revising Paducah & Portsmouth Gaseous Diffusion Plants Technical Safety Requirement Sections 3.1.1 & 3.10.4 ML20206H5601999-05-0606 May 1999 Ack Receipt of Responding to Notice of Violation Noted During Insp 70-7002/99-202 of 990319.Corrective Actions Acceptable,Per 10CFR2.201 ML20206E9761999-05-0303 May 1999 Forwards Amend 2 to Coc GDP-2,reducing Ports Fundamental Nuclear Matl Control Plan Requirements Re Min Number of UF6 Cylinder Receipts from Russia ML20206E3781999-04-29029 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/99-01.Actions Will Be Examined During Future Insp ML20206E4281999-04-29029 April 1999 Forwards Insp Rept 70-7002/99-03 on 990222-0406 & NOV Re Failure to Understand & Implement Personnel Safety Controls During Maint Evolution ML20206B5611999-04-22022 April 1999 Forwards Insp Rept 70-7002/99-06 on 990322-26 & Nov.One Violation Identified Involving Failure of Plant Shift Superintendent,Acting as Incident Commander for Er to Fire on 981209,to Classify Emergency Condition as Alert ML20205K4251999-04-0707 April 1999 Forwards Compliance Evaluation Rept for GDP-1 & GDP-2, Supporting Change in Title of Executive Vice President, Operations.Notice of Amend,Which Has Been Forwarded to Ofc of Fr for Publication,Encl ML20205J2051999-04-0606 April 1999 Forwards Amend 1 to Coc GDP-2,revising Issue A.2 of Portsmouth Gaseous Diffusion Plant Compliance Plan.Condition 8 Revised to Include Date of 981228 ML20205F6721999-03-31031 March 1999 Forwards Proprietary Copy of Compliance Evaluation Rept Prepared to Support Amend of Coc GDP-2.Notice of Amend,Which Has Been Forwarded to Ofc of Fr for Publication,Also Encl. Proprietary Encls Withheld ML20196K3981999-03-19019 March 1999 Forwards Insp Rept 70-7002/99-202 Conducted on 990222-26. Violation Noted.Major Areas Inspected:Mc&A Safeguards Program.Rept Details Withheld,Per 10CFR2.790(d) ML20204H9611999-03-18018 March 1999 Forwards RAI Re 990212 Applications Requesting Amends to Coc for Paducah & Portsmouth Gaseous Diffusion Plants for Revised QAPs ML20204D7991999-03-17017 March 1999 Discusses Insp Rept 70-7002/99-01 on 990112-0222 & Forwards Notice of Violation.Violation Identified Involved Licensee Staff Returning Sys to Svc Following Safety Actuations Without Appropriately Documenting Safety Actuations ML20204E2341999-03-17017 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7002/98-18 .Reviewed C/As & Have No Further Questions.C/As Will Be Examined During Future Insps ML20207G4991999-03-0505 March 1999 Discusses Rescheduling of 1999 Portsmouth Emergency Preparedness Exercise to 990914.Date Change Acceptable to Local Officials ML20207B3361999-03-0202 March 1999 Ack Receipt of 990212 Applications for Amend to Cocs GDP-1 & GDP-2.Staff Has Completed Initial Administrative Rev of Applications & No Omissions of Deficiencies Were Identified. Staff Anticipates Completing Review by 990416 1999-09-09
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July 21, 1997 EA 97-172 l
Mr. J. H. Miller Vice President - Production United States Enrichment Corporation Two Democracy Center 6903 Rockledge Drive Bethesda, MD 20817
SUBJECT:
RESPONSE TO INSPECTION REPORT 70-97002(DNMS)
Dear Mr. Miller:
This will acknowledge receipt of a response letter from Mr. Dale Allen, Portsmouth General Manager, dated June 6,1997, in response to our letter dated May 9,1997, transmitting a Notice of Violation regarding your failure to comply with Technical Safety Requirements.
We have reviewed your corrective actions and have no further questions at this time. These corrective actions will be examined during further inspection.
if you have any questions, please contact Patrick Hiland of my staff at (630) 829-9603.
Sincerely, Original Signed by T. Kozak Roy J. Caniano, Acting Director Division of Nuclear Materials Safety Docket No. 70-7002 cc: R. M. DeVault, DOE S. A. Polston, Paducah General Manager D. I. Allen, Portsmouth General Manager R. W. Gaston, Portsmouth Nuclear Regulatory {.
Affairs Manager 1 R. L. Woolley, Manager, Nuclear Regulatory ]
Assurance and Policy, USEC bec w/Itr dtd: 6/6/97: J. Caldwell, Rill T. Simmons, Rlli Office of Enforcement J. Goldberg, OGC E. Ten Eyck, FCSS
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! To rtceive a copy of this document, Indicate in the box:"C" = Copy without enclosure "E" = Copy with enclosure'lN" = No copy A/
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NAME Reidin}r:dp" Hiland W 7dL/ CaniandMt-DATE 07/P/97 07/L//97 V 07/1)/97" V
~ OFFICIAL RECORD COPY 9707250099 970721 PDR ADOCK 07007002 C PDR
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, ' Id) heed Martin Utihty services. Inc.
- , 6903 Rockledre Drive Bethe:da, MD 20817
- Telephong 3015718270 Facsimile 301 571-3278
. LOCKNEED M A R TIN Gregory II. Baker President June 6,1997 GDP-97-2006 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 I l
Portsmouth Gasecus Diffusion Plant (PORTS)
Docket No. 70-7002 l Response to Inspection Report (IR) 70-7002/97-002 Notice of Violation (NOV)
Nuclear Regulatory Commission (NRC) letter dated May 9,1997, transmitted the subject Inspection Report (IR) that contained two violations involving three examples of failure to comply with j Technical Safety Requirements. USEC's response to these violations is provided in Enclosures 1 i and 2 Enclosure 3 lists the commitments made in this report. Unless specifically noted, the corrective actions specified in each enclosure apply solely to PORTS.
In page 8 of the IR, NRC states that the events that led to the NOVs were indicative of a generic ,.
problem with the plant staffs implementation of the TSRs. We concur with this concern and have taken positive actions to raise the staff's awareness and expectation for TSR compliance, to improve the plant's understanding of operability, and improve identified incomplete TSR procedures.
Specifically, a senior manager of my staff was assigned to facilitate a management analysis into why TSR violations were occurring and determine the root causes of this negative trend. A TSR compliance enhancement plan was developed and is being implemented to address those awareness and expectation issues which led to our poor performance. The Plant Shift Superintendent (PSS) f roles and responsibilities have been expanded to strengthen the conunand and control function providing greater control over operability evaluations related to TSR Mode changes. Additionally, f as communicated in the attached responses, my staff is taking actions to improve weak TSR.
implementation procedures and we are committed to strengthen TSR implementation procedures as procedure weaknesses are identified.
y,er I have taken a personal interest in improving TSR compliance and have communicated my expectations through meetings, articles, and personal discussions with my staff. I believe ve are being responsive to this very important subject and I will continue my personal involvement to ensure plant personnel develop a questioning attitude which includes an improved awareness of TSR requirements, an increased level of knowledge related to regulatory compliance, and continued self-
, assessments to identify compliance weaknesses. Our goal is to achieve a high level of regulatory compliance through a position of self-reg cn ; id control.
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( 'U.S. uclear Regulatory Commission June 6,1997 Page Two If you have any questions regarding this submittal, please contact Charly Blackston at (614) 897-3120. ,
I l Sincerely, i Dale Allen General Manager DIA:CB .
' 1 Enclosures l
cc: Regional Administrator, Region Ill NRC Resident Inspector - PORTS L u
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U.S. uclear Regulatory Commissioner June 6,1997 Page Three Distribution:
Robert L.~ Woolley - 001 bec:
J. 'Adkins, HQ J. Dietrich,~ LMUS L. Fink,' PORTS R. Gaston, PORTS J. Labarraque, PGDP A. Rebuck-Ma i n, HQ S. Routh, HQ D. Scott, HQ D. Silvennan, ML&B
. J. Slider, HQ
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B. Sykes, PGDP R. Wells, HQ f;\ rob \jdale\ ports \nov97002. pts Concurrence line CRS / /97 l
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i Enclosure 1 l UNITED STATES ENRICIIMENT CORPORATION (USEC)
REPLY TO NOTICE OF VIOLATION (NOV) 70-7002/97002-01 Restatement of Violation ;
l 1
Technical Safety Requirement (TSR) 3.2.2.a states that minimum stafling requirements for 1 each facility are shown in Table 3.2.2-1.
TSR Table 3.2.2-1 requires that the minimal staffing level for the Tails Withdrawal Station have one assigned Operator during Modes II and III.
Contrary to the above, on March 21,1997 between 2:00 p.m. and 2:30 p.m., there was no assigned Operator present at the Tails Station during Mode II.
I. Reasons for Violation I
The reason for this violation was that a process / procedure was not in place to address manning requirements for the cascade facilities as outlined in the TSR Table 3.2.2-1 nor were these requirements flowed into the appropriate operating procedures. Contributing to the failure was the unavailability of TSRs at the floor level and a Eck of understanding of the new TSR manning requirements by the facility's operating staff.
II. Corrective Actions Taken and Results Achieved
- 1) The TSR minimum staffing requirements were documented in the cascade facilities 4
Daily Operating Instructions (DOI) and communicated to cognizant personnel in the three process buildings and Plant Control Facility (PCF).
- 2) Operators in the cascade buildings were briefed on the minimum staffing requirements specific to their facility to ensure operations personnel understood the manning requirements as stated in the TSR, the requirements of the DOI, and how these manning requirements are to be implemented.
- 3) Additional controlled TSR manuals were distributed to process areas in the X-333, X-330, X-326, and X-300 to make TSRs available at the floor level.
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' III. Corrective Steps to be Taken
- 1) USEC will develop a procedure that describes process facilities manning requirements, .
establishes ag methodology of how minimum stafling levels are maintained, and designates a more descriptive area of operation for assigned personnel. This action item will be completed by June 30,1997,
- 2) Once the procedure is complete and approved for use, appropriate operations l personnel will be trained to ensure personnel-adequately understand manning expectations. This action item will be completed by July 30,1997.
IV. Date of Full Compliance Full compliance was achieved when the TSR manning requirement at the Tails Withdrawal Station was restored at or about 2:30 p.m. on March 21,1997. The corrective actions to mitigate / prevent recurrence will be completed by July 30,1997.
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', c j Enclosure 2 i UNITED STATES ENRICHMENT CORPORATION (USEC)
REPLY TO NOTICE OF VIOLATION (NOV) 70-7002/97002-02 Restatement of Violation Technical Safety Requirement (TSR) 1.6.2.2.d states that entry into an OPERATIONAL MODE that is applicable to the particular LIMITING CONDITION for OPERATION (LCO) shall not be made unless the conditions for the LCO are met without reliance on provisions contained in the ACTION statement.
TSR 2.7.3.13 and TSR 2.2.3.14 require DC control power for uranium hexafluoride stage motors to be operable for Mode II and Mode III.
TSR 2.2.3.1 requires the coolant high pressure relief system to be operable and their block i l
valves verified open prior to entry into Modes 11 or 111.
Contrary to the above, between March 3 and April 6,1997, the plant entered Mode II with DC control power for uranium hexafluoride (UF 6) stage motors inoperable for four cells and without verifying that the coolant high pressure relief system block valves were open.
I. Reasons for Violation The reason for the violation was a weakness in the process used to determine equipment operability at the time of transition to NRC oversight and inadequate administrative controls goveming TSR LCOs. Specifically, operators relied upon surveillance data performed under DOE Operational Safety Requirements (OSRs) to confirm equipment operability under the new TSR specifications. However, the OSR surveillance data was not properly evaluated to ensure it satisfied the applicable TSRs prior to transition to NRC regulatory oversight. A similar condition with the High Pressure Fire Water System was self-identified and reported to NRC [ Event Report 97-05] on April 9,1997. Further discussion on each of the above examples is provided below:
Examnle 1:
On March 3,1997, when USEC transitioned to NRC regulatory oversight, a condition existed in which the DC control power should have been declared inoperable because specific gravities in cells were documented as below the minimum acceptance specification of 1.180 specified in TSR surveillance requirements 2.7.3.13 and 2.2.3.14. This is because the surveillance procedure for battery cells, which existed prior to March 3,1997, did not specify that a TSR LCO had to be entered if the specific gravity was below 1.180. Additionally, plant personnel did not perform an adequate review of this, and other, surveillances, to ensure the E2- 1
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conditions of the applicable.TSR LCOs were satisfied prior to transition to NRC regulatory oversight.
Contributing to the error was the plant's lack of understanding of the difference between
" operable" and " functional." Personnel believed that if a system was functional and was able 1 to provide DC control power to the motor trip circuit, the system could be considered
- operable. This misinterpretation of the operability' concept is contrary to management expectations and contrary to the Operability Determination procedure, UE2-TO-NS1032,- ;
currently in effect. J Example 2:
The second example describes a condition whem personnel failed to recognize that restart and i start-up of a cell from a " shut-down" state (Mode VI) are the same and have the same TSR
- limiting conditions for operation. Past practice allowed a cell to be quickly restarted when a cell tripped off-line if the cause of the trip was known and the brakes were verified disengaged. If a cell was shutdown (i.e., did not trip off-lir.e), the cell would be started-up following a detailed prestart-up check which included verifying the Freon block valve was scaled open. In this example, where the cell tripped off-line, the application of the TSR requirement for the mode change was not clearly understood by cascade personnel.
II. Corrective Actions Taken and Results Achieved
- 1) All DC power control batteries that were identified on March 19,1997 as being in an LCO have been restored to operable status in accordance with the new TSR procedures which were made effective as of March 3,1997.
- 2) Systems Engineering performed a review of TSR surveillance test data submitted in preparation for transition to ensure that other systems were not inoperable due to failed surveillances. Identified discrepancies were documented on problem reports, reported :
to the PSS for a operability. determination, and appropriate corrective actions were taken.
- 3) A Daily Operating Instruction (DOI) has been written to address the implementation of TSR required actions when an LCO condition is entered or mode changes occur.
The DOI ' establishes a consistent approach to LCO monitoring ar.d tracking by instructing the PSS to verify TSR required actions and surveillances are completed each time an LCO condition is entered. To document the approval the PSS reviews the TSR requirements and logs the condition in the PSS logbook and instructs the field organizations to document the same information in their operating logs.
- 4) Status Boards are also used to make LCO conditions very visible to the PSS and others in the control room.
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. 5) A briefing was held with each PSS to communicate management's expectations related
- to surveillan'c e testing and operability, TSR Limiting Conditions of Operation, LCO tracking and documentation, and mode changes.
- 6) LCOs are tracked on the Daily Status Report issued each moming by the PSS. The report communicates to management across plant site the condition and status of the plant.
- 7) Operations First Line Managers have been briefed by their Group Managers on how
-surveillances relate to operability and how Limiting Conditions of Operations are .
entered. .I III. Corrective Steps to be Taken
- 1) A procedure is currently being developed which will establish a formal program to control LCOs. The procedure will provide guidance for the tracking of Limiting Conditions for Operations. The use of this tracking program will establish a process to ensure compliance with the TSR. The procedure is expected to be completed by August 30,1997.
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- 2) Once the procedure is complete and approved for use, appropriate operations )
- personnel will be trained to ensure personnel adequately understand the LCO trackmg i process. This action item is expected to be completed by September 30,1997.'
Additional corrective actions concerning a similar condition are documented in Event Report 97-05 and were forwarded to the United States Nuclear Regulatory Commission under cover letter dated May 9,1997 from Mr. Dale Allen, General Manager. 1 IV. Date of Full Compliance USEC is in full compliance with the TSRs as confirmed by the in-depth engineering review of TSR surveillance data completed May 30, 1997. The corrective actions to prevent recurrence will be completed by September 30,1997.
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I Enclosure 3 i
l UNITED STATES ENRICIIMENT CORPORATION (USEC) l LIST OF COMMITMENTS 70-7002/97002 NOV 97002-01 I
l 1) USEC will develop a procedure that describes process facilities manning requirements, establishes a methodology of how minimum staffing levels are maintained, and designates a more descriptive area of operation for assigned personnel. This action item will be completed by June 30,1997.
- 2) Once the procedure is complete and approved for use, appropriate operations personnel will be trained to ensure personnel adequately understand manning expectations. This action i'em will be completed by July 30,1997.
NOV 97002-02
- 1) A procedure is currently being developed which will establish a formal program to control LCOs. The procedure will provide guidance for the tracking of Limiting Conditions for Operations. The use of this tracking program will establish a process to ensure compliance with the TSR. The procedure is expected to be completed by August 30,1997.
- 2) Once the procedure is complete and approved for use, appropriate operations personnel will be trained to ensure personnel adequately understand the LCO tracking process. This action item is expected to be completed by September 30,1997, i