Letter Sequence Approval |
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MONTHYEARML20135D7081997-02-28028 February 1997 Discusses Ltrs for Portsmouth Gaseous Diffusion Plant & 960419 & 0815,for Paducah Gaseous Diffusion Plant Requesting Exclusions of Areas within Usec Leased Areas from Criticality Accident Alarm Sys Monitoring Project stage: Approval ML20147H0981997-03-31031 March 1997 Forwards Response to Request for Addl Info Re Paducah Gaseous Diffusion Plant & Portsmouth Gaseous Diffusion Criticality Accident Alarm Sys Monitoring Exclusion Requests,Changing Due Date to 970228 Project stage: Request ML20138D4021997-04-0707 April 1997 Forwards Responses to Questions Concerning Paducah & Portsmouth GDP Criticality Accident Alarm Sys Monitor Exclusion Requests Project stage: Other ML20217F4441997-10-0303 October 1997 Ack Receipt of 970915 Application to Amend Coc GDP-1 Re Product & Tails Withdrawal Criticality Accident Alarm Sys. Application Is Acceptable for Formal Review.Completion of Review Is Anticipated by 980115 Project stage: Approval ML20217F8061997-10-0707 October 1997 Requests Technical Assistance in Reviewing Certificate Amend Request for Paducah Gaseous Diffusion Plant to Revise TS Requirement on Criticality Accident Alarm System for Product Withdrawal Facilities Project stage: Approval ML20198R6521998-01-14014 January 1998 Informs That Review Will Not Be Completed by 980115 Due to Other Activities.Review Should Now Be Completed by 980331 Project stage: Other ML20203A2301998-02-12012 February 1998 Requests Addl Info Re 970915 Application for Amend to Certificate of Compliance Revising Technical Safety Requirement 2.3.4.7, Criticality Accident Alarm Sys, Required Action A.1.5 Project stage: Approval ML20248L2121998-03-10010 March 1998 Submits TAR Re Review of Request for Criticality Accident Alarm Sys (CAAS) Exclusion for Portsmouth Gaseous Diffusion Plants & Paducah Gaseous Diffusion Plant Project stage: Approval ML20216J0531998-03-13013 March 1998 Provides Response to NRC RAI on Certificate Amend Request Dealing W/Product & Tails Withdrawal Facility Criticality Accident Alarm Sys.Info Requested Provided in Encl 1 Project stage: Response to RAI ML20216H2691998-04-14014 April 1998 Informs of Inability to Complete Review of Amend Request by 980331 as Indicated in .Currently Anticipates Completion by 980529 Project stage: Approval ML20248K8571998-06-0505 June 1998 Informs That Staff Was Unable to Complete Review of Certificate Amend Request by 980529,due to Other Activities. Completion of Review Anticipated by 980630 Project stage: Approval ML20236N8231998-07-0909 July 1998 Informs That NRC Review of Application Identified Addl Info, Needed Before Final Action Can Be Taken on Request Re Paducah Certificate Amend Request for Product & Tails Withdrawal Criticality Accident Alarm Sys Project stage: Approval ML20237C6991998-08-18018 August 1998 Forwards Response to NRC 980709 RAI Re Certificate Amend Request Revising Technical Safety Requirement 2.3.4.7 Re Product & Tails Withdrawal Criticality Accident Alarm Sys Project stage: Other ML20195J8771998-11-20020 November 1998 Informs That Staff Anticipates Completing Paducah Certificate Amend Request Re Product Tails Withdrawal Criticality Accident Alarm Sys,By 981231 Due to Other Activities Project stage: Approval ML20197G6811998-12-0707 December 1998 Forwards Copy of Compliance Evaluation Rept Prepared to Support Amend of Coc GDP-1 & Copy of Notice of Amend Which Has Been Forwarded to Ofc of Fr for Publication Project stage: Other ML20199G2161999-01-14014 January 1999 Forwards Amend 23 to Coc GDP-1,revising TS Requirement 2.3.4.7 on Product & Tails Withdrawal Facilities Criticality Accident Alarm Sys Project stage: Approval ML20202G2541999-02-0101 February 1999 Rev 37 to USEC-01,application for NRC Certification,Paducah Gaseous Diffusion Plant.Rev Incorporates Changes to Technical Safety Requirements Previously Submitted & Approved as Amend 23 to Coc GDP-1 Project stage: Request ML20195H4541999-03-0101 March 1999 Responds to NRC 981204 RAI Re Licensee Request for Exclusion of Areas within Licensee Leased Areas from Criticality Accident Alarm Sys Monitoring.Update Documents,Originally Submitted as Part of Original Request,Encl Project stage: Request 1998-02-12
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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 ML20217N7591999-10-18018 October 1999 Provides Monthly Update on Progress of Installation of Seismic Upgrade Mods to Bldgs C-331 & C-335 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 ML20217M3861999-10-15015 October 1999 Provides Addl Changes to SAR Update Certificate Amend Request,Containing Changes That Resulted from re-evaluation of Autoclave head-to-shell O-ring Leakage Analysis Provided by DOE SAR Repts 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 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 ML20217G1811999-10-14014 October 1999 Forwards Reissued Amend to Coc for Usec Paducah Gdp.Coc Corrects Coc Issued on 991006.Amend Number & Effective Date Were Inadvertently Incorporated as 3 & 991026,instead of 4 & 991105 ML20217F6801999-10-12012 October 1999 Forwards Updated Paducah GDP Certificate Amend Requests at NRC for Approval 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 ML20217B2801999-10-0606 October 1999 Forwards Insp Rept 70-7001/99-203 on 990921-23.No Violations Noted ML20217B3521999-10-0606 October 1999 Forwards Amend 3 to Certificate of Compliance GDP-1 to Revise Six Technical Safety Requirements Sections.Sections Are 2.1.4.17,2.1.4.8,2.3.4.1,2.3.4.4,2.3.4.16 & 3.10.4.b. Compliance Evaluation Rept Also Encl 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 ML20212K8941999-10-0404 October 1999 Forwards Insp Rept 70-7001/99-10 on 990720-0907 & Forwards NOV Indicating That Some Personnel Were Incorrectly Granted Unescorted Access to Controlled Access Areas Without Having Necessary Specific Training ML20216J8931999-10-0101 October 1999 Forwards Copy of Security Incident Log & Associated Info for Sept 1999 ML20216J9081999-09-30030 September 1999 Forwards Revised Written Event Rept 99-10,rev 3,pertaining to Corroded Fire Sprinkler Heads Affecting Operability of high-pressure Fire Water (HPFW) Sprinkler Sys.No Commitment Contained in Rept ML20217M3701999-09-29029 September 1999 Submits bi-monthly Update on Progress of Mods to Upgrade Audibility of Criticality Accident Alarm Sys (Caas).Schedule for CAAS Audibility Upgrades Attached 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 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 ML20212H3801999-09-24024 September 1999 Responds to 990723 RAI Re 1999 Annual Update to Certification Applications 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 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 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 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 ML20212F0981999-09-22022 September 1999 Forwards Insp Rept 70-7001/99-12 on 990830-0902.Purpose of Insp Was to Determine If Security Requirements Adequately Implemented & Included Review of Approved Plant Security Plan.No Violations Identified ML20217J1211999-09-20020 September 1999 Submits Listed Comments on NRC Proposed Rule, Reporting Requirements for Nuclear Power Reactors ML20212D4291999-09-17017 September 1999 Forwards Required 30-day Written Event Rept Re Criticality Accident Alarm Sys Response Time in Bldg C-710.Encl 2 Contains Commitments Contained in Submittal ML20212D4231999-09-16016 September 1999 Informs That Review of Event Rept Er 99-12 Revealed Listed Two Statements Inadvertently Omitted from Document ML20212B6611999-09-15015 September 1999 Forwards Insp Rept 70-7001/99-202 on 990816-20.No Violations Noted ML20212D2361999-09-15015 September 1999 Submits Monthly Update on Progress of Installation of Seismic Upgrade Mods to Bldgs C-331 & C-335 ML20212A5441999-09-14014 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7001/99-07 ML20212A5531999-09-14014 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7001/99-08 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 ML20211Q9951999-09-10010 September 1999 Forwards 30-day Written Rept ER-99-12,re Loss of Power to Autoclave Position 1 North & 1 South Process Gas Leak Detection (Pgld) in Bldg C-333-A.Caused by Electrical Short Circuit.Submitted Work Request 501636 for PI SEX-4 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 ML20216E4891999-09-0909 September 1999 Responds to Violations Noted in Insp Rept 70-7001/99-08. Corrective Actions:On 990602 Responsible Organization Manager Met with FP Engineer Performing Bldg Reappraisal & Made Clear Expectation for Prompt Reporting of Deficiencies 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) 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 ML20217G1811999-10-14014 October 1999 Forwards Reissued Amend to Coc for Usec Paducah Gdp.Coc Corrects Coc Issued on 991006.Amend Number & Effective Date Were Inadvertently Incorporated as 3 & 991026,instead of 4 & 991105 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 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 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 ML20217B2801999-10-0606 October 1999 Forwards Insp Rept 70-7001/99-203 on 990921-23.No Violations Noted ML20217B3521999-10-0606 October 1999 Forwards Amend 3 to Certificate of Compliance GDP-1 to Revise Six Technical Safety Requirements Sections.Sections Are 2.1.4.17,2.1.4.8,2.3.4.1,2.3.4.4,2.3.4.16 & 3.10.4.b. Compliance Evaluation Rept Also Encl ML20212K8941999-10-0404 October 1999 Forwards Insp Rept 70-7001/99-10 on 990720-0907 & Forwards NOV Indicating That Some Personnel Were Incorrectly Granted Unescorted Access to Controlled Access Areas Without Having Necessary Specific Training 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 ML20212F0981999-09-22022 September 1999 Forwards Insp Rept 70-7001/99-12 on 990830-0902.Purpose of Insp Was to Determine If Security Requirements Adequately Implemented & Included Review of Approved Plant Security Plan.No Violations Identified ML20212B6611999-09-15015 September 1999 Forwards Insp Rept 70-7001/99-202 on 990816-20.No Violations Noted ML20212A5441999-09-14014 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7001/99-07 ML20212A5531999-09-14014 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-7001/99-08 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 ML20211L6441999-09-0202 September 1999 Forwards Insp Rept 70-7001/99-11 on 990802-06.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress 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 ML20211B5021999-08-20020 August 1999 Forwards Amend 2 to Certificate of Compliances GDP-1, Revising Paducah GDP Technical Safety Requirements Re Audibility Requirements for Criticality Accident Alarm Sys at Facility & Related Sections of SAR 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 ML20210P7421999-08-10010 August 1999 Forwards Insp Rept 70-7001/99-08 on 990529-0719 & Nov. Violations of Concern Because Late Reporting of Problems with safety-related Equipment Could Negatively Impact Continued Availability of Equipment 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 ML20210L6571999-08-0404 August 1999 Informs That Staff Completed Initial Review of 990720 Application to Amend Coc GDP-1.Staff Anticipates Completing Review by 990930 ML20211A7901999-08-0404 August 1999 Forwards Info Requested During Briefing by NRC Staff on 990726 Re NRC Interactions with Usec ML20210F9761999-07-28028 July 1999 Forwards Compliance Evaluation Rept Prepared to Support Amend of Coc GDP-1 Re Criticality Accident Alarm Sys Audibility.Notice of Amend Forwarded to Ofc of Fr Also Encl 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 ML20209F0611999-07-0909 July 1999 Forwards Insp Rept 70-7001/99-09 on 990621-25.No Violations Noted 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 ML20209E8711999-07-0909 July 1999 Discusses Insp Rept 70-7002/99-08 on 990614-17 & Forwards Notice of Violation 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 ML20196K0981999-07-0101 July 1999 Forwards Insp Rept 70-7001/99-07 on 990413-0528 & Nov. Violations Re Failure to Fully Evaluate Situation in Which Safety Sys Relied Upon to Mitigate Consequences of Accident Was Inappropriately Returned to Svc 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 ML20196A1571999-06-17017 June 1999 Confirms Discussions Between K O'Brien & L Jackson to Conduct Meeting on 990630 to Discuss Apparent Violation 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 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 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 ML20207F1311999-06-0404 June 1999 Responds to Requesting Copy of OI Rept 3-1998-033 Re Docket Potential Violation of 10CFR76.7 Concerning Employee Protection at Plant.Request Denied for Listed Reasons 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 1999-09-09
[Table view] |
Text
- . . .- . . . - - - - . . . - . . .
~70 9 001 s,
y pr p ee a UNITED STATES !
s' j NUCLEAR REGULATORY COMMISSION .
2 WASHINGTON, D.C. 20665 0001 g
\ ,,,,, # February 28, 1997 Mr. James H. Miller '
Vice President, Production U. S. Enrichment Corporation l 2 Democracy Center
~
6903 Rockledge Drive Bethesda, MD 20817 i
SUBJECT:
CRITICALITY ACCIDENT ALARM SYSTEM MONITORING EXCLUSION REQUESTS - PORTSMOUTH GASEOUS DIFFUSION PLANT (TAC NO. L32009) ;
AND PADUCAH GASEOUS DIFFUSION PLANT (TAC NO. L30576) ;
Dear Mr. Miller:
1 1
This refers to your letters dated May 22,1996, for the Portsmouth Gaseous Diffusion Plant (PORTS), and April 19,1996 and August 15, l' 16, for the Paducah Gaseous Diffusion Plant (PGDP), requesting exclusions of areas wvithin the ' 3EC leased areas from Criticality Accident Alarm System (CAAS) monitoring.
Our review of your requests has identified additional information that is needed before final
,3ction can be taken. The additionalinformation specified in Enclosure 1 for PORTS and belosure 2 for PGDP should be prouacri before April 1,1997. Please reference the above TAO Nos. in future correspondence related to this request.
Please note that 10 CFR Part 76.89 requires criticality monitoring and alarm audibility in all areas of a facility except those that have been exempted by the NRC. The USEC certification application was required by 10 CFR Part ~/6.35(b) to include a plan for achieving compliance with areas of noncompliance with regulations applicable to the Gaseous Diffusion Plants. The NRC staff considers this approved Compliance Plan as a vehicle to bring USEC into compliance with NRC requirements, over an appropriate period of time, during which compensatory measures are implemented as prescribed in the Justification for Continued Operation sections of each Compliance Plan issue. Issue 11 of the PORTS Compliance Plan (DOE /ORO-2027/R3 " Plan for Achieving Compliance with NRC Regulations at the Portsmouth Gaseous Diffusion Plant") and issue 8 of the PGDP Compliance Plan (DOE /ORO-2026/R3 " Plan for Achieving Compliance with NRC Regulations at the Paducah Gaseous Diffusion Plant") recognize that criticality monitoring and alarm coverage is not provided for USEC leased areas identified in the above mentioned USEC exclusion requests at this time. Therefore, af ter March 3,1997, pending completion of our review of your requests, the NRC will not consider activities which are in comformance with the Compliance Plan to be violations. .
9703050426 970229 !
PDR ADOCK 07007001 / '
go011 glC HUEEN /f8
e James H. Miller If you have any questions regarding this matter, please contact Yawar Faraz for PORTS at (301) 415-8113 or Merri Horn for PGDP at (301) 415-8126.
Sincerely, Original Signed By Robert C. Pierson, Chief Special Projects Branch Division of Fuel Cycle Safety and Safeguards, NMSS Dockets 70-7001 and 70-7002 Certificates GDP-1 and GDP-2
Enclosures:
As stated cc: Mr. Randall DeVault, DOE-OR Ms. Janie Benton, DOE-HQ Mr. Dale Allen, PORTS Mr. Steve Polston, PGDP DISTRIBUTION: w/ encl (Control Nos. 010S,040S) '
Dockets 70-7001, 70-7002 NRC File Center PUBLIC KO'Brien, Rlli NMSS r/f FCSS r/f SPB r/f GShear, Rlli CCox, Rill WSchwink, FCOB MWeber, FCLB G:\CASEXCLX.RAI
- See previous concurrence d.phl OFC SPB C SPB 4 "SPB 'FCLB Rlli SP$ SPB ,
NAME YFarak M orn DHoadley DDamon h, 'h bhartin RPihrhon DATE 24f/97 2/jS/97 2/26/97 2/27/97 2/'d /b 2/N97 2/2 f97 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL. RECORD COPY i
I j
-_. - - .- -- . .- ~. -. _- - - - - -. -- -
February 27, 1997 a . .
l
- r. James H. Miller l
V President, Production 1 i U. S. (nrichment Corporation 2 Dem% racy Center 6903 Roc edge Drive Bethesda, 20817
SUBJECT:
CRITI ITY ACCIDENT ALARM SYST MONITORING EXCLUSION
, REQUES - PORTSMOUTH GASEOU DIFFUSION PLANT (TAC NO. L32009)
AND PADUC GASEOUS DIFFUS N PLANT (TAC NO. L30576) l . Deser Mr. Miller:
1 This refers to your letters dated May ,1996, for the Portsmouth Gaseous Diffusion Plant (PORTS), and April 19,1996 d gust 15,1996, for the Paducah Gaseous i Diffusion Plant (PGDP), requestin exclusions of areas within the USEC leased areas from
, Criticality Accident Alarm Syst (CAAS) mo 'toring.
d I Our review of your reques has identified addition information that is needed before final ,
action can be taken. Th additional information speci d in Enclosure 1 for PORTS and !
Enclosure 2 for PGDP ould be provided before April 1, 997. Please reference the above I
- TAC Nos. in future rrespondence related to this request.
If you have any estions regarding this matter, please contact awar Faraz for PORTS at (301) 415-81 or Merri Horn for PGDP at (301) 415-8126.
j Sincerely, eMnst Signed By 1
Rob'ert C. Pierson, Chief Special Projects Branch Division of Fuel Cycle Safety l and Safeguards, NMSS s i
l Dockets 70-7001 and 70-7002 Certificates GDP-1 and GDP-2
Enclosures:
As stated j cc: Mr. Randall DeVault, DOE-OR !
! Ms. Janie Benton, DOE-HO I Mr. Dale Allen, PORTS Mr. Steve Polston, PGDP
. DISTRIBUTION: w/ encl. (Control Nos. 010S,040S) l
, Dockets 70-7001, 70-7002 NRC File Center PUBLIC 1 KO'Brien, Rlli NMSS r/f FCSS r/f SPB r/f GShear, Rlll CCox, Rlli 4 WSchwink, FCOB MWeber, FCLB 2
G:\CAASEXCL.RAI
, *See previous concurrence lOFC "SPB 'SPB 'SPB , ,QLE} 6 'SFB SPp g lNAME YFaraz:ij MHorn DHoadley DDaN DMartin RPh son lDATE 2/26/97 2/26/97 2/26/97 2/ 27/97 2/26/97 7 /D/97 4
C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY I
Request for Additional Information CAAS Exclusion Request Dated May 22,1996 United States Enrichment Corporation Portsmouth Gaseous Diffusion Plant Docket 70-7002 Please provide the following information:
Reference:
POEF-LMUS-10 Criticality Accident Alarm System Coverage and Exclusions,"
April 1996, D. M. D'Aquila and J. A. Rapp, Jr.
POEF-LMUS-10 divides the alarm coverage of the plant into five sections:
- 1) Areas covered by criticality alarm systems
- 2) Non-process buildings
- 3) Roadways
- 4) Cylinders of UF6 in certain storage yards
- 5) X-622T Water Treatment Facility (Section 2) EXCLUSION OF NON-PROCESS BUILDINGS in Table 2 (p.5) of POEF-LMUS-10 areas are specified that are to be excluded from coverage on the grounds that they "do not contain operations enriched to 1% or higher U-235, and 15 grams or more of U-235." Additional information is requested showing a commitment to practices sufficient to ensure that containers or pieces of equipment with material exceeding these limits are not brought into these areas. Information is needed showing that allindividuals who might, even inadvertently, move special nuclear material are trained in these measures.
(Section 3) EXCLUSION ON ROADWAYS FOR CERTAIN MATERIALS Four specific classes of materials are described in the section on roadways, each treated differently. With respect to Class 11, " materials for which spacing is required":
Is there a requirement for Class 11 materials to be loaded and unloaded from the transporting vehicles in areas covered by criticality alarms? Additional materials, diagrams, or images defining the type of objects that constitute Class ll material shipments are requested. Additional description of the structures which ensure the maintenance of required spacing during transport is requested. Information concerning the robustness of these spacing structures to normal vibrations and moderate mishaps is requested. What plans exist for measures to be taken by accident response teams to consider the possibility of criticality ir the event of a major upset of the '/ehicle during transport of Class ll materials?
Enclosure 1 i
I 2 l l
i With respect to transportation of individual items or components that may contain greater than a safe mass of 35U,2 such as equipment classified for Planned Expeditious Handling:
What commitment has been made, and what measures will be taken to ensure that such shipments will always be made under criticality alarm coverage? What will be done if a criticality alarm covering the planned route is temporarily inoperative?
With respect to Class I;l, Large UF, Cylinders, as long as no loading or unloading is done on these roadways, the primary concern is the possibility of cylinder damage during transport. Is such transport done in such a way as to preclude cylinder damage as a result of vehicle accidents? Con the cylinders be dropped during transport? What would be the effect of a vehicle fuel fire on a cylinder? Why is criticality alarm coverage of these l roadways not feasible? What accident response measures would be taken in the event of vehicle fires and accidents?
(Section 4) EXCLUSION OF CYLINDERS OF UF, IN STORAGE YARDS There are amounts and enrichments of UF6 sufficient to produce criticality in these locations. The Paducah GDP document KY/S-271 is referenced as the primary justification that an accidental criticality is not a credible event in these cylinder storage situations.
The arguments in KY/S-271 that criticality is of low likelihood do not provide a degree of !
[ assurance high enough to warrant complete exclusion from CAAS coverage. Unless I additional information can be provided showing that cylinder damage producing holes larger than 1 inch diameter cannot occur, measures providing the function of the criticality monitoring described in 10 CFR 70.89 must be provided. If it is proposed that a criticality monitoring system providing continuous coverage as described in 10 CFR 70.89 is not feasible, the following additional information is requested:
- 1) Information is requested showing why continuous monitoring is not feasible. All feasible rearrangements and spacing of cylinders should be considered. Various locations and types of detectors should be considered.
Detection of skyshine, reflection, and other indirect paths should be considered.
- 2) Information is requested describing an alternative to complete continuous monitoring that provides assurance that: a) those areas that are feasible to monitor continuously are so monitored, and b) that measures are taken to detect and mitigate criticalities when and where personnel are present. This information should describe how inadvertent entry of unmonitored personnel is to be prevented at all times.
Request for Additional Information i
. CAAS Exclusion Requests Dated April 19,1996 and August 15,1996 United States Enrichment Corporation Paducah Gaseous Diffusion Plant Docket 70-7001 i
Please provide the following information:
Reference 1): United States Enrichment Corporation letter GDP 96-0172 of August 15, 1996 from R. L. Wooley to J. W. N. Hickey.
Reference 1 requests exclusions grouped into four categories based on the type of justification as follows:
Category 1. < 15 grams 23sU.
Category 2. < 1 wt percent 23sU.
Category 3. Probabilistic Analysis Category 4. Low Level Waste (CATEGORY 1) FACILITIES WITH LESS THAN 15 GRAMS 23sU AND (CATEGORY 2)
AREAS WITH URANIUM ENRICHED TO LESS THAN 14 For those defined areas that are to be excluded from coverage on the grounds that they ;
"do not contain operations enriched to 1% or higher U-235, and 15 grams or more of U- !
l 235," additional information is requested showing a commitment to practices sufficient to !
ensure that containers or pieces of equipment with material exceeding these limits are not brought into these areas. Information showing that allindividuals who might, even inadvertently, move special nuclear material are trained in these measures?
(CATEGORY 3. a) CYLINDERS OF UF6 IN STORAGE YARDS If amounts and enrichments of UF, sufficient to produce criticality are to be stored in these I locations, then the following information is requested. The Paducah GDP document KY/S-271 is referenced as the primary justification that an accidental criticality is not a credible event in these cylinder storage situations. The arguments in KY/S-271 that ,
l criticality is of low likelihood do not provide a degree of assurance high enough to warrant complete exclusion from CAAS coverage. Unless additional information can be provided i showing that cylinder damage producing holes larger than 1 inch diameter cannot occur, ,
l l measures providing the function of the criticality monitoring described in 10 CFR 70.89 l must be provided. If it is proposed that a criticality monito, ring system providing continuous coverage as described in 10 CFR 70.89 is not feasible, the following additional information is requested:
l .
' 1)Information is requested showing why continuous monitoring is not feasible. All feasible rearrangements and spacing of cylinders should be
}
considered. Various locations and types of detectors should be considered.
Detection of skyshine, reflection, and other indirect paths should be f considered.
Enclosure 2
i
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, , i 2
l
- 2) Information is requested describing an alternative to complete continuous monitoring that provides assurance that: a) those areas that are feasible to monitor continuously are so monitored, and b) that measures are taken to detect and mitigate enticalities when and where personnel are present. This information should describe how inadvertent entry of unmonitored personnel ,
is to be prevented at all times.
Are all roadways along which movements of special nuclear material above a critically safe mass are made covered by the criticality monitoring system?
(CATEGORY 3.b) C-710 FACILITY DRAIN SYSTEM The C-710 Facility drain system empties into the C-712 Acid Neutralization Pit prior to discharge to sewer systems. The rationale for exclusion of the C-712 Acid Neutralizat'an Pit by probabilistic analysis, is deficient in two respects. Additional information, which might adequately address the deficiencies is identified below. The two deficiencies are: 1) the probabilistic analysis is deficient due to lack of independence, and 2) the criticality evaluation may not be sufficiently conservative. j I
- 1) The probabilistic analysis argues that six independent human error events must occur to !
have a cn'icality (see Appendix E). Inadequate information is presented to justify that l these evente are truly independent, since all 6 occur in the same room, Room 21. If the i I
same personnel 6rc involved as operators or supervisors, the events are not independent.
In principle, measures might be taken that would provide such independence. If such measures exist, please provide additional information demonstrating the independence of the discharges and of the supervisory monitoring of them. Please provide hazards analysis which attempts to identify ways in which independence might be defeated.
- 2) The criticality evaluation argues that 426.8 Kg of uranium is necessary in order for the I C-712 tank to be critical. The analysis appears not to have considered concentration of the uranium in a layer at the bottom of the tank. Rather it appears to have considered only the homogeneous distribution of uranium in a tank full of water. Since the single ;
parameter mass limit for of 5% enriched UO 2 2F is 1.64 Kg of contained 2"U (43 Kg U). It !
would appear that only slightly more than this, in an optimal configuration, might be critical. Thus further information is needed to justify that 426 Kg is required to be critical in an unstirred tank receiving discharges that are not measured. -
To justify CAAS exclusion the argument is made that the likelihood of a criticality is less than 104 Certain types of events that might enhance the likelihood of criticality are not discussed. Among these are conditions or events that might lead to formation of layers or deposits of enhanced fissile content in the tank, leakage of the tank, events that might cause unusually low water levels in the tank, etc. Although many of these events may be highly unlikely, to achieve the goal of less than 10 8, all such unusual events must be addressed.