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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J1721999-10-13013 October 1999 Forwards Insp Rept 70-1151/99-05 on 990920-21.No Violations Noted ML20216J7131999-10-0202 October 1999 Forwards Response to GL 98-03, NMSS Licensees' & Certificate Holders' Y2K Readiness Programs ML20216J5321999-09-28028 September 1999 Ack Receipt of ,Which Transmitted Application for Amend to License SNM-1107 Re Rev 30 to Fnmc Plan.Staff Has Completed Acceptance Review & No Administrative Omissions or Deficiencies Were Identified ML20212G4171999-09-24024 September 1999 Informs That NRC Has Completed Acceptance Review of License Amend Application & Have Identified No Administrative Omissions or Deficiencies.Nrc Anticipates Completing Technical Review by End of Dec 1999 ML20212G3351999-09-24024 September 1999 Informs That NRC Has Completed Initial Review of License Annex Submitted for Adu Pelleting Sys,Rev 1 with No Administrative Omissions or Deficiencies Identified. Submittal Has Been Assigned TAC L31240 ML20212G4221999-09-24024 September 1999 Informs That NRC Has Completed Initial Review of License Annex Submittal for Storage of U Bearing Metals with No Administrative Omissions or Deficiencies Identified.Nrc Anticipates Completing Technical Review by 991029 ML20216G0581999-09-20020 September 1999 Forwards Proprietary Rev 30 Proposed Changes to 10CFR74 Fundamental Nuclear Matl Control Plan for Columbia Fuel Fabrication Facility. Explanation of Changes Incorporated within Revised Plan,Included.Proprietary Encl Withheld ML20217C7171999-09-15015 September 1999 Ack Receipt of W ,Transmitting Rev 27 to W Physical Security Plan.Nrc Review of Rev Has Found It to Be Acceptable for Inclusion Into Plan.Encl Withheld,Per 10CFR2.790 ML20211K8071999-08-31031 August 1999 Forwards Rev 1 to Criticality Safety Evaluation (Cse) License Annex Pelleting, Replacing Adu Pelleting Cse Summary Previously Submitted on 960628 ML20217M2361999-08-31031 August 1999 Forwards Description of Complete Scenario,Controller Assignments,Simulation Data & Messages That Will Be Used for 990921 Full Scale Emergency Exercise ML20211J1871999-08-27027 August 1999 Submits Proposed Rev 16.0 of Page V & Pages from Chapters 1.0,2.0,3.0,10.0 & 11.0 of Application for Renewal of License SNM-1107.Changes Are Identified by Marginal Lines ML20211J8611999-08-27027 August 1999 Informs That Listed Rept Fulfills Regulatory Requirements as Listed in 10CFR70.59 Effluent Monitoring Requirements, for six-month Period Jan-June 1999.Detailed Summary Rept by Stack Is Provided as Attachment a ML20210R4401999-08-0303 August 1999 Ack Receipt of NRC Ltr & Insp Rept Dtd 990611,pertaining to Insp of Facility Preparedness & Radiation Protection Programs by a Gooden on 990510-0514 ML20210L6091999-07-29029 July 1999 Responds to Providing Update to Site Emergency Plan Emergency Procedure A-01 (Rev 3).No Amend to License Necessary,Since No Change to Plan Was Made ML20210F4601999-07-22022 July 1999 Forwards Insp Rept 70-1151/99-201 on 990628-0702.No Violations Noted ML20209J4131999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for URRS Waste Treatment Sys,Transmitted by .Anticipates Completion of Review by 990830 ML20209J3781999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Un Bulk Storage Sys,Rev 1,transmitted by .Anticipates Completion of Review by 990830 ML20210A0021999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Adu Bulk Powder Bldg Sys (Rev 1),transmitted by . Anticipates Completion of Review by 990830 ML20209J4031999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Solvent Extraction Sys,Transmitted by .Anticipates Completion of Review by 990830 ML20209H6131999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Adu Conversion Sys (Rev 1),trasmitted by .Staff Has Completed Initial Review with No Administrative Omissions or Deficiencies Identified ML20209J3881999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Scrap U Recovery Processing Sys,Transmitted by . Anticipates Completion of Review by 990830 ML20209D5311999-07-0909 July 1999 Provides Ack Ltr Which Closes Out TAC L31180,which Was Rev 2 of License Annex Submittal for Plant Ventilation Sys ML20209C9201999-07-0808 July 1999 Forwards Response to NRC GL 98-03, NMSS Licensees & Certificate Holders Y2K Readiness Programs ML20209E0121999-07-0606 July 1999 Ack Receipt of License Annex Submittal for Chemicals Receipt,Handling & Storage Sys at W Plant Transmitted by Ltr Dtd 990430.NRC Has Completed Initial Review of License Annex with No Adminstrative Omissions or Deficiencies Identified ML20209C2421999-06-30030 June 1999 Forwards Rev 0 to Cse License Annex,Solvent Extraction Re Commitment to Submit Upgraded Csa/Cse Summaries in Format of License Annex ML20209C0251999-06-29029 June 1999 Ack Receipt of License Annex Submittal for Rev 1 to Hood & Containment Sys,Transmitted by .Initial Review of Submittal Has Been Completed & Staff Anticipates Completing Review of Annexes by 990830.Ltr Closes Out TAC L31164 ML20209E3661999-06-25025 June 1999 Ack Receipt of NRC Ltr & Insp Rept 70-1151/99-03,dtd 990611. Insp Was Conducted on 990510-14 on Facility Emergency Response & Radiation Protection Programs ML20196H2601999-06-18018 June 1999 Forwards Rev 3 to Site Emergency Administrative Procedure A-01, Emergency Response Organization, in Accordance with Provisions of 10CFR70.32(i) ML20196A3841999-06-11011 June 1999 Forwards Insp Rept 70-1151/99-03 on 990510-14.No Violations Noted.Conduct of Activities at Facility Was Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices ML20196K5701999-06-0303 June 1999 Submits Intent to Change License Annex for Columbia Plant Ventilation Sys ML20206S6981999-05-14014 May 1999 Forwards Rev 1 to Cse License Annex Hoods & Containments. Submittal Is Upgrade to Replace the Criticality Safety Evaluation Summary Submitted on 990228 ML20206L5271999-05-10010 May 1999 Forwards Proprietary Insp Rept 70-1151/99-202 on 990419-23. No Violations Noted.Details of Insp Rept Withheld,Per 10CFR2.790(d) ML20206S9491999-05-0606 May 1999 Forwards One NRC Form 327, Special Nuclear Matl (SNM) Physical Inventory Summary Rept, for Matl Balance Period Ending 990407 at Columbia Fuel Fabrication Facility (Cfff). Final Values for Items 1-9 Included ML20206S8911999-05-0606 May 1999 Informs That Wl Goodwin Has Reviewed Encl Special Nuclear Matl Inventory Rept & Concurs with Authorizing Signature of RA Williams ML20206R3091999-05-0505 May 1999 Ack Receipt of NRC Ltr & Insp Rept 70-1151/99-02 Dtd 990429, Pertaining to Insp of Facility Fire Safety Program on 990405-08 ML20206H4221999-05-0404 May 1999 Forwards Amend 19 to License SNM-1107,incorporating Revised Fundamental Nuclear Matl Control Plan & Safeguards Evaluation Rept,Which Includes Revs of 981201 & 990302 to Read as Listed ML20206P3971999-04-29029 April 1999 Forwards Insp Rept 70-1151/99-02 on 990405-08.No Violations Noted ML20206B2631999-04-22022 April 1999 Ack Receipt of Which Transmitted License Annex Re LLRW Processing Sys at Columbia,Sc Plant.Staff Anticipates Completing Review of Subject Info by 990630 ML20206B2531999-04-22022 April 1999 Ack Receipt of Which Transmitted Revised License Annex for Plant Ventilation Sys at Columbia,Sc Plant.Staff Anticipates Completing Review of Previous License Annexes by 990630 ML20205S9321999-04-14014 April 1999 Submits Comments on RAI for Emergency Response Technical Manual Supplements.Licensee Is Confident That NRC Will Concur That Info in Environ Evaluation Rept & in Licensee Annex Provides Sufficient Detail for Intent of Supplements ML20205H2481999-03-31031 March 1999 Forwards Rev 0 to Cse License Annex LLRW Processing Sys, Which Covers low-level Radwaste Processing Sys ML20205M4191999-03-18018 March 1999 Ack Receipt of License Annex Submittal for Hoods & Containment Sys at Plant Transmitted by Ltr ML20205M4091999-03-18018 March 1999 Ack Receipt of License Annex Submittal for Adu Pelleting Sys at Plant Transmitted by Ltr ML20205A3921999-03-15015 March 1999 Ack Receipt of 990129 Response to NOV Issued on 981231 Re Activities Conducted at Columbia Nuclear Fuel Plant. Response Meets Requirements of 10CFR2.201 ML20207J7671999-03-0404 March 1999 Forwards Amend 17 to License SNM-1107 & Ser.Amend Changes Pages V & 1.4 of License Application to Rev 15.0.Safety Condition S-1 Has Been Revised to Include Date of 990212 & License Conditions 6E,7E & 8E Have Been Added as Listed ML20204E7481999-03-0202 March 1999 Ack Receipt of NRC Insp Rept 70-1151/99-01 Re Insp of Facility Operational Safety & Environ Programs 1999-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J1721999-10-13013 October 1999 Forwards Insp Rept 70-1151/99-05 on 990920-21.No Violations Noted ML20216J5321999-09-28028 September 1999 Ack Receipt of ,Which Transmitted Application for Amend to License SNM-1107 Re Rev 30 to Fnmc Plan.Staff Has Completed Acceptance Review & No Administrative Omissions or Deficiencies Were Identified ML20212G4171999-09-24024 September 1999 Informs That NRC Has Completed Acceptance Review of License Amend Application & Have Identified No Administrative Omissions or Deficiencies.Nrc Anticipates Completing Technical Review by End of Dec 1999 ML20212G3351999-09-24024 September 1999 Informs That NRC Has Completed Initial Review of License Annex Submitted for Adu Pelleting Sys,Rev 1 with No Administrative Omissions or Deficiencies Identified. Submittal Has Been Assigned TAC L31240 ML20212G4221999-09-24024 September 1999 Informs That NRC Has Completed Initial Review of License Annex Submittal for Storage of U Bearing Metals with No Administrative Omissions or Deficiencies Identified.Nrc Anticipates Completing Technical Review by 991029 ML20217C7171999-09-15015 September 1999 Ack Receipt of W ,Transmitting Rev 27 to W Physical Security Plan.Nrc Review of Rev Has Found It to Be Acceptable for Inclusion Into Plan.Encl Withheld,Per 10CFR2.790 ML20210L6091999-07-29029 July 1999 Responds to Providing Update to Site Emergency Plan Emergency Procedure A-01 (Rev 3).No Amend to License Necessary,Since No Change to Plan Was Made ML20210F4601999-07-22022 July 1999 Forwards Insp Rept 70-1151/99-201 on 990628-0702.No Violations Noted ML20209J3881999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Scrap U Recovery Processing Sys,Transmitted by . Anticipates Completion of Review by 990830 ML20209H6131999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Adu Conversion Sys (Rev 1),trasmitted by .Staff Has Completed Initial Review with No Administrative Omissions or Deficiencies Identified ML20209J4031999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Solvent Extraction Sys,Transmitted by .Anticipates Completion of Review by 990830 ML20209J4131999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for URRS Waste Treatment Sys,Transmitted by .Anticipates Completion of Review by 990830 ML20210A0021999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Adu Bulk Powder Bldg Sys (Rev 1),transmitted by . Anticipates Completion of Review by 990830 ML20209J3781999-07-16016 July 1999 Ack Receipt of Revised License Annex Submittal for Un Bulk Storage Sys,Rev 1,transmitted by .Anticipates Completion of Review by 990830 ML20209D5311999-07-0909 July 1999 Provides Ack Ltr Which Closes Out TAC L31180,which Was Rev 2 of License Annex Submittal for Plant Ventilation Sys ML20209E0121999-07-0606 July 1999 Ack Receipt of License Annex Submittal for Chemicals Receipt,Handling & Storage Sys at W Plant Transmitted by Ltr Dtd 990430.NRC Has Completed Initial Review of License Annex with No Adminstrative Omissions or Deficiencies Identified ML20209C0251999-06-29029 June 1999 Ack Receipt of License Annex Submittal for Rev 1 to Hood & Containment Sys,Transmitted by .Initial Review of Submittal Has Been Completed & Staff Anticipates Completing Review of Annexes by 990830.Ltr Closes Out TAC L31164 ML20196A3841999-06-11011 June 1999 Forwards Insp Rept 70-1151/99-03 on 990510-14.No Violations Noted.Conduct of Activities at Facility Was Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices ML20206L5271999-05-10010 May 1999 Forwards Proprietary Insp Rept 70-1151/99-202 on 990419-23. No Violations Noted.Details of Insp Rept Withheld,Per 10CFR2.790(d) ML20206H4221999-05-0404 May 1999 Forwards Amend 19 to License SNM-1107,incorporating Revised Fundamental Nuclear Matl Control Plan & Safeguards Evaluation Rept,Which Includes Revs of 981201 & 990302 to Read as Listed ML20206P3971999-04-29029 April 1999 Forwards Insp Rept 70-1151/99-02 on 990405-08.No Violations Noted ML20206B2531999-04-22022 April 1999 Ack Receipt of Which Transmitted Revised License Annex for Plant Ventilation Sys at Columbia,Sc Plant.Staff Anticipates Completing Review of Previous License Annexes by 990630 ML20206B2631999-04-22022 April 1999 Ack Receipt of Which Transmitted License Annex Re LLRW Processing Sys at Columbia,Sc Plant.Staff Anticipates Completing Review of Subject Info by 990630 ML20205M4191999-03-18018 March 1999 Ack Receipt of License Annex Submittal for Hoods & Containment Sys at Plant Transmitted by Ltr ML20205M4091999-03-18018 March 1999 Ack Receipt of License Annex Submittal for Adu Pelleting Sys at Plant Transmitted by Ltr ML20205A3921999-03-15015 March 1999 Ack Receipt of 990129 Response to NOV Issued on 981231 Re Activities Conducted at Columbia Nuclear Fuel Plant. Response Meets Requirements of 10CFR2.201 ML20207J7671999-03-0404 March 1999 Forwards Amend 17 to License SNM-1107 & Ser.Amend Changes Pages V & 1.4 of License Application to Rev 15.0.Safety Condition S-1 Has Been Revised to Include Date of 990212 & License Conditions 6E,7E & 8E Have Been Added as Listed ML20204E0001999-03-0101 March 1999 Forwards Certificate of Compliance 6400,rev 25 for Model 6400 Package,As Requested in 980928 Application ML20207J8101999-02-26026 February 1999 Informs That NRC Has Received License Submittal for Adu Bulk Powder Blending Sys at Plant Transmitted by Ltr Dtd 981231.Submittal Has Been Assigned TAC Number L31155 ML20207D3601999-02-26026 February 1999 Forwards Insp Rept 70-1151/99-01 on 990201-05 at Columbia Nuclear Fuel Plant.No Violations or Deviations Were Cited ML20207J8871999-02-22022 February 1999 Requests That Info Re Nuclear Fuel Mfg Process Descriptions & Corresponding Nuclear Safety Analyses Conducted for W Columbia,Sc,Plant Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4) ML20199E0441999-01-0404 January 1999 Requests Addl Info for Info Not Found During Review of Listed Licensing Documents.Nrc Is in Process of Preparing Rtm Suppl for Each Fc Facility,Per .Suppl Assist NRC Incident Response Staff as Emergency Assessment Tool ML20199E0161998-12-31031 December 1998 Responds to Ltrs & 30,with Attached Affidavit ,requesting That Info Re Nuclear Fuel Manufacturing Process Descriptions & Corresponding Nuclear Safety Analyses Conducted for W,Columbia,Sc Plant,Be Withheld ML20199F2281998-12-31031 December 1998 Forwards Insp Rept 70-1151/98-10 on 981207-11 & NOV Re Failure to Ensure Physical Condition of Radioactive Matl Shipping Containers & Failure to Follow Operating Procedures ML20198M8511998-12-18018 December 1998 Ack Receipt of License Annex Submittal for URRS Dissolver Sys,Dtd 981030.Initial Review of License Annex Has Been Completed with No Administrative Omissions.Projection of Technical Review Schedule Will Be Provided ML20198E8291998-12-17017 December 1998 Forwards Amend 16 to License SNM-1107,revising Pages 3.18 Through 3.20 of License Application.Safety Condition S-1 Revised to Include Dates of 980403,1021 & 30.SER Including Categorical Exclusion Determination Encl ML20198A8341998-12-0303 December 1998 Forwards Insp Rept 70-1151/98-09 on 981109-13.No Violations Noted.Purpose of Insp Was to Determine Whether Activities Authorized by License Were Conducted Safely & in Accordance with NRC Requirements ML20196B0421998-11-23023 November 1998 Informs That NRC Has Received License Annex Submittals for Several Operating Sys at W Plant.List of Submittals NRC Has Received,Dates of Documents & Assigned TAC Numbers,Listed. TAC Numbers Should Be Used on Associated Correspondence ML20195J1831998-11-18018 November 1998 Forwards Partially Withheld Insp Rept 70-1151/98-205 on 981019-23.Violations Noted.Rept Details Withheld (Ref 10CFR2.790) ML20195B9681998-11-12012 November 1998 Responds to & Affidavit ,requesting That Info Concerning Nuclear Fuel Manufacturing Process Be Withheld Per 10CFR2.790(b)(4).Determined That Info Sought to Be Withheld Contains Proprietay Info & Will Be Withheld ML20195B7701998-10-29029 October 1998 Requests Addl Info on 980331 Application for Amend to License SNM-1107 for Changes to Chapters 3.0 & 6.0 Re Criticality Safety.Addl Info Needed Specified in Encl ML20155A9431998-10-13013 October 1998 Forwards Insp Rept 70-1151/98-07 on 980921-25.No Violations Noted ML20155C4821998-10-0707 October 1998 Forwards Amend 15 to License SNM-1107,revising Chapters 1,2, 3,4,5 & 8 & Revising Safety Conditions S-1 & S-2.Safety Evaluation Rept,Including Categorical Exclusion Determination,Encl ML20154D4921998-09-25025 September 1998 Responds to Requesting Certain Info Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4).Not All of Six Reasons Apply to Subject Document.Licensee Has Thirty Days from Date of Ltr to Submit Properly Marked Document ML20153C4751998-09-18018 September 1998 Ack Receipt of Licensee Response to Violations Noted in Insp Rept 70-1151/98-203.Staff Determined That Corrective Actions Meet Requirements of 10CFR2.201 & Implementation of Corrective Actions Will Be Reviewed During Future Insps ML20153F1101998-09-0909 September 1998 Ack Receipt of Transmitting Rev 26 to Physical Security Plan,Reflecting Current Organization Names & Documenting W Annual Review of Security Program.Rev Acceptable for Inclusion Into Plan ML20151T0621998-08-26026 August 1998 Forwards Insp Rept 70-1151/98-06 on 980803-07 & Notice of Violation.Violation Involved Three Individuals,Not Adequately Instructed in General Safety Info Required by 10CFR19.12 ML20239A4051998-08-21021 August 1998 Forwards Insp Rept 70-1151/98-05 on 980727-31.No Violations Noted.Purpose of Insp,To Determine Whether Activities Authorized by License Conducted Safely & in Accordance W/Nrc Requirements ML20151S9101998-08-21021 August 1998 Ack Receipt of Transmitting Rev 25 to Physical Security Plan.Rev Has Been Found to Be Acceptable ML20237D7941998-08-21021 August 1998 Forwards Insp Rept 70-1151/98-204 on 980810-13.No Violations Noted 1999-09-28
[Table view] |
Text
_ _ _ . _ . _ - _ __ - _ . _ _ . _ _ . _ . _ _ _ .- _ _ _ _ .
pn teouq y k UNITED STATES
- 5 j
NUCLEAR REGULATORY COMMISSION WASHINCToN, D.C. 20656-0001
. 8 July 28, 1997
. . . . . ,o f
EA 97-244 Westinghouse E ectric Corporation l Commercial Nuclear Fuel Division ATTN: Mr. J. A. Fici, Division General Manager Energy Center l P.O. Box 355 Pittsburgh, PA 15230-6600
SUBJECT:
MOTICE OF VIOLATION (NRC SPECIAL INSPECTION REPORT NO. 70-1151/97-203)
Dear Mr. Fici:
l This refers to the inspection conducted on May 5 - 7,1997, at the Westinghouse l Commercial Nuclear Fuel Division facility in Columbia, South Carolina. The inspection was i conducted to review the circumstances that led to the reported event on April 15,1997, )
involving two low-enriched fuel rods that could not be located. On May 27,1997, the i NRC conducted a re-exit briefing via telephone with members of your staff, and on June 25,1997, issued the inspection report detailing'our findings. A predecisional i enforcement conference was held with you and members of your staff on July 9,1397, to I discuss the apparent violations, their root causes, and your corrective action. !
Based on the information developed during the inspection, and the information that you provided during the conference, the NRC has determined that five violations of NRC requirements occurred. These violations are cited in the enclosed Notice of Violation (Notice) and the circumstances surrounding them are described in detail in the subject inspection report. Specifically, the v;oistions involved Westinghouse's failure to:
(1) implement proper notification procedures of the event to the NRC; (2) provide adequate training for certain employees that handled Special Nucicar Material (SNM); (3) provide adequate procedures for handling and testing of lead-filled rods; (4) comply with numerous Department of Transportation (DOT) requirements; and (5) adequately implement Westinghouse's Material Control and Accounting (MC&A) program.
The NRC is particularly concerned that your staff had prior opportunities to identify the unaccounted for fuel roda. Specifically, on October 16,1996, the "7-day report" included r /
the two fuel rods in question, but was not acted upon by the responsible Material Service h Attendant (MSA). In addition, from October 16,1996, to March 20,1997, the MSA team b manager neither required that the location of the fuel rods be determined, in accordance with the "7-day report" requirements, nor reported the status of the fuel rods to the safeguards coordinator, as required by your procedures.
\ \
9707300238 970728 PDR C
ADOCK 07001151 PDR
~
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Westinghouse, Electric Corporation The NRC recognizes that the actual or potential safety consequences were minimalin this case. However, the violations in the enclosed Notice are of significant regulatory concern because, collectively, they are indicative of inadequate management attention toward licensed activities. The lack of management oversight is evidenced by the fact that Westinghouse employees and management did not have a high level of sensitivity to item control and accounting. Given the loss of control of the two unirradiated fuel rods, the number of violations that are related to this sing!e event, and the number of prior opportunities that could have identified the event progression sooner, the violations have been classified in the aggregate in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600 as a Severity Level 111 problem.
In accordance with the Enforcement Policy, a base civil penalty in the amount of $12,500 is considered for a Severity Level ill problem. Because your facility has not been the subject of escalated enforcement actions within the last 2 years, the NRC considered whether credit was warranted for Corrective Action in accordance with the civil penalty assessment process in Section VI.B.2 of the Enforcement Policy. In this case, the NRC has determined that credit is warranted for your prompt and comprehensive corrective action.
Specifically, your corrective action that you discussed during the July 9,1997 conference included: (1) stopping shipments of all replica fuel assemblies and non-product fuel rods; (2) holding a management meeting to emphasize the importance of item control and to ensure that all managers understood NRC requirements; (3) providing immediate training to personnel involved in the event; (4) establishing a new procedure for manufacture and movement of replica fuel rods; (5) developing a plan to provide an improved method to ensure a timely final accounting of all fuel rods when a region of fuel has been completed; and (6) instilling a high level of sensitivity to item control and accounting. Of particular note is the seriousness with which you viewed this event as demonstrated by your plans to shut down the facility, if the fuel rods had not been found by April 18,1997.
Therefore, to encourage prompt and comprehensive correction of violations, and in recognition of the absence of previous escalated enforcement action, I have been authorized, after consultation with the Director, Office of Enforcement, not to propose a civil penalty in this case. However, significant violations in the future could result in a civil ponalty. You should note that issuance of this Severity Level 111 violation constitutes escalated enfo'rcement action that may subject you to increased inspection effort.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. In addition, given that the violations occurred during a non-routine operation, the NRC is concerned that similar problems may occur in other non-routine activities. Therefore, as part of your response, please provide any corrective actions taken or planned to prevent recurrence of similar violations in other q non-routine activities. The NRC will use your response, in part, to determine whether further enforcement action is necessary to ensure compliance with regulatory requirements.
i
j i
. l
. e Westinghouse Electric Corporation I
J In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its enclosure, and your response will be placed in the NRC Public Document Room.
i Sincerely, Original signed by Elizabeth O. Ten Eyck, Director Division of Fuel Cycle Safety And Safeguards, NMSS l
Docket No. 70-1151 l License No. SNM-1107 i
Enclosure:
Notice of Violation i
f i
j Distribution: ,
Docket File 70-1201 PDR SECY CA LJCallan, EDO HThompson, DEDR EJordan, DEDO LReyes, Ril JLieberman, OE
- Case file CPaperiello, NMSS EWBrach, FCSS !
FDavis, OGC CHughey, Ril EMcAlpine, Ril l BMallet, RilB Uryc, Rll MWeber, FCLB
, MLamastra, FCLB VBeaston, OE EA File, OE j EEaston, SFPO NMSS R/F FCOB R/F l FCSS R/F HBell, OlG DWhaley, FCOB ;
Enforcement Coordinators WSchwink, FCOB GCaputo, 01 RI, Rlli, RIV l
CBassett, Ril '
i I l Doc. Name: G:\97203NOV.NM OFFICE IMNS v A C FCOB C FCjiiS) FCSSh l pa v NAME NMamish/ PTing f Wdrdph ETenEyck DATE ;z /w/97 h/97 -
7h97 1/M7 C = COVER E = COVEll & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY l