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| {{Adams | | {{Adams |
| | number = ML20202H996 | | | number = ML20209E806 |
| | issue date = 12/05/1985 | | | issue date = 07/03/1986 |
| | title = Informs That Closure of Action Item Tracking Sys F03048785 Cannot Be Accomplished Based on Insp Rept 50-341/85-40 Not Issued Pending Receipt of Stated Repts Re 850723 Meeting Concerning 850701 Criticality Event | | | title = Forwards Order Modifying License & Notice of Violation & Proposed Imposition of Civil Penalties in Amount of $300,000 Based on Violations Noted in Insp Rept 50-341/85-40 on 850701-1014 Re Rod Pull Errors & Premature Criticality |
| | author name = Greenman E | | | author name = Taylor J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| | addressee name = Lickus R | | | addressee name = Mccarthy W |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | | | addressee affiliation = DETROIT EDISON CO. |
| | docket = 05000341 | | | docket = 05000341 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | case reference number = FOIA-86-244 | | | document report number = EA-86-061, EA-86-61, NUDOCS 8609110359 |
| | document report number = NUDOCS 8607170003
| | | package number = ML20209E709 |
| | package number = ML20202H992 | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE | | | page count = 4 |
| | page count = 1 | |
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| / # | | Attachment 11 GNNTBD AT5s NUCLEAR REGULATORY COMbfl8SMm WaSetMS 7081, D. C. M |
| ^g UNITED STATES -
| | \c-) . at o un Docket No. 50-341 License No. NPF-43 EA 86-61 The Detroit Edison Company |
| / o NUCLEAR REGULATORY COMMISSION 7 h I REGION 111 ,
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| '}e r Q [ 790 ROOSEVELT ROAD
| | ATTN: Walter J. McCarthy, J Chairman of the Board and Chief Executive Officer 2000 Second Avenue Detroit, MI 48226 - |
| % g'
| | Gentlemen: |
| * GLEN ELLYN, ILLINOIS 80137
| | SUBJECT: ORDER MODIFYING THE LICENSE EFFECTIVE D94EDIATELY AND NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTIES (NR; INSPECTION REPORT N /85040(DRP)) |
| *....
| | This refers to the inspection conducted by the NRC during the period. July 1 - |
| 1985 DEC 5 MEMORANDUM FOR: Roland Lickus, Chief, State and Government Affairs FROM: Edward G. Greenman, Deputy Director, Division of Reactor Projects SUBJECT: AITS NO F03048785, INSPECTION REPORT 50-341/85-040 In a letter dated August 13, 1985 Mr. Richard Petticrew, Chairman, Monroe County Board of Commissioners, requested a copy of our documentation of the July 23, 1985 meeting between DECO and the NRC on the premature criticality event of July 1, 198 As you are aware, documentation of.the July 23, 1985 meeting is contained in Inspection Report 50-341/85-040. By memo dated November 15, 1985, A. B. Davis confinned with C. Norelius that the subject Inspection Report was not to be issued pending receipt of the 01 & OIA reports. After receipt we will be prepared to issue the repor Based on the above, closure of AITS No. F03048785 cannot be accomplished at this tim c$ d'""
| | October 14, 1965, of activities authorized by NRC License Nc. hPF-43 for Ferr.i-2 and interviews conducted by the Office of Investigations with employees involved in the control rod pull error on July 1-2, 1985. While this inspection also identified additional violations that will be addressed in separate correspondence, the ma.jor emphasis was to review the circumstances associated with the control rod pull errors, premature criticality, and subsequent reconsnencement of rod pulling which o: curred July 1-2, 1985. The inspection report (50-341/85040 (DRP)) |
| Edward G. Greenman, Deputy Director Division of Reactor Projects cc: A. B. Davis C. E. Norelius N. J. Chrissotimos
| | identified violations of NRC requirements associated with this incident and was provided to you on January 7,1985. On May 9, 1986 an enforcement conference was held with you and menbers of your staff to discuss the incident, the relatec violations, their causes, and your proposed corrective action. |
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| PUNTENNB6-244 'pDR
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| ~l LELIMINARY N3TIFICATION OF EVEN~ R UNUSUAL OCCURRENCE--PNO-III-8 'O Date August s, 1985 tis preliminary notification crnstitutes EARLY notice cf events of POSSIBLE safety cr i ablic interest significance. The information is as initially received without veri-l cation or evaluation, and is basically all that is known by the staff on this dat cility: Detroit Edison Company Licensee Emergency Classification:
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| Fermi 2 Nuclear Plant Notification of an Unusual Event Newport, MI 48166 Alert Site Area Emergency Docket No. 50-341 General Emergency X Not Applicable Lbject: COUNTY BOARD OF COMMISSIONERS REQUEST INVESTIGATION OF UTILITY AND NRC The Monroe County Board of Comissioners decided on August 6,1985, to request Conaressman John Dingell to conduct a full investigation of the operational procedures
| | On July 3,1985, members of your staff provided information to the resident inspector on a rod pull error, acknowledging that company procedures had been violated and that there may have been a premature criticality. On July 4, 1985, the Shift Reactor Engineer made a detemination that the reactor had been critical with a 114 second perio It was not until after meetings on July 4 and 5,1985 that Detroit Edison Company (Deco) mana9ement initiated an investigation into the cause of the premature criticality. After Region !!! |
| : nd the credentials of employees perfoming operations at the Fermi 2 plant. The request will also include a full investigation of whether NRC representatives at the site were responsible for the withholding of infomation from the Comission and the public. The request stems from the July 2, 1985 unplanned criticality which was not reported to the Region III office until July 15, 1985. (Reference PNO-III-85-58). The fomal request has not yet been made in writin The Office of Investigations is currently conducting an investigation into the timeliness of reporting and the circumstances related to the event. Mr. Keppler, Reaional Administrator, contacted the Chaiman of the Board of Comissioners
| | was notified of the criticality on July 15, 1985, the licensee's corrective actions were confirmed in a Confimatory Action Letter dated July 16, 198 The inspection and investigations into the events that preceded and followed the premature criticality revealed a major breakdown in the perfomance of control room personnel, in the management of control room activities, and in the evaluation of the incident 1smediately following the rod pull error. This l breakdown wes illustrated in part by the lack of ex serienced shift personnel, ! |
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| | the disregard for established procedures exhibited ny the Nuclear Supervising Operator (N50) and Nuclear shift Supervisor (NS$), the failure of key shift CERT!FIED MAIL-RETuRK RECEly1 RE0uESTED e6ov11oas9 e60e27 RES E PDR ' |
| to infom him of the ongoing investigation and inspection activities and offered to brief the Commission on the event. The Comission will consider this offe The plant is currently in cold shutdown while completing several corrective actions to minimize operational errors, and to perfom maintenanc The State of Michigan will be infome The utility was infomed of the Board of Comissioners' decision late on August 6, and they in turn, informed the Senior Resident Inspector early on August 7,198 ssotimos (388-5716) C. Norelius (388-5603)
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| )ISTRIBUTION: | | ' |
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| )hairmanPalladino t EDO NRR IE NMSS fom. Roberts PA - | | \ |
| OIA RES Nom. Asselstine MPA AEOD fom ELD Air Rights 4'.14 MAIL:
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| | l The Detroit Edison Campasy -2- i l |
| . Zech | | personnel to fully understand their responsibilities and exercise supervisory oversight, failure to properly use the Shift Operations Advisor (504) and a lack of sensitivity to onpoing processes, incidents, and events demonstrated by shift personnel. The 'ack of involvement and awareness by the NSS, a senior licensed operator, to the evolutions in process and their potential consequences was particularly egregiou The premature criticality occurred when the inexperienced N50 who was in |
| | ' control of the reactor startup failed to follow the rod pull sheet and pulled eleven control rods to the Yull-out position (48) rather than position M and mistakenly verified the position as 04 for each rod. The MSO had never taken the reactor critical before and received only casual observation from an unlicensed Shift Technical Advisor in Training. Other members of the shift - |
| | crew were preoccupied with other tasks and at some time during the event were absent from the control room. The MSS who was responsible for managing the shift and overseeing startup activities, and the 50A who was to provide the experience factor for the shift and guidance to inexperienced operators, did not directly observe the rod pulls or respond to the five short period alar annunciations. Wher, the NSO did recognize his rod pull error, he proceeded to reinsert the rods and had the M55 notified. The M55's review of the incident was shallow and he pervitted the N50 to start withdrawing control rods again without adequately analyzing the causal factors that led to the inciden Iter. I described in the enclosed Notice of Violation and Proposed Imposition of Civil Penalties involves the error by a reactor operator (the Nuclear Supervising Operator) in pulling eleven control rods to the full-out position. |
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| | The reactor operator did not follow the specified rod pull procedure and, in additior., improperly verified and documented the position of the cor. trol rod Contributing to this error were the relative inexperience of the reactor operator and the fact that his training on a simulator had used a rod pull sequence different fron. that used in the actual plan Itee II involves violations associated with the lack of the overall oversight of the control roce during rod pulling which was especially important in view of the lack of operator experience of the NSS and NSO. This was compounded by the failure to use the shift advisors who were there, in part, to compensate for the lack of reactor experience on shift. The July 1-2 event demonstrated the significant failure to properly supervise control room activities and a lack of coordinated efforts in the control roor during a significant plant evolutio Item III involves the failure of the MSS to recognize the significance of the rod pull error and his direction that startup be resumed shortly after the mispositioned rods were returned to their proper position. This violation illustrates a lack of understanding of the need to pro of the rod pull error, a significant procedural error,perly assess startup, before resuming the causes to evaluate the consequences of the svent, and to fuplement effective corrective |
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| | actions. The decision by the MS$ to resume rod pulling was based on minimal l |
| | review and evaluation contrary to quality assurance requirements and a management directive to suspend safety-related activities after an event until the problem tes been identified, its cause determined, and a solution formulated and implemente . |
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| | The Detroit Edison Compavy -3-To emphasias the need for you to ensure that there is proper oversight of control room activities and that control room personnel and supervisors responsibly and professionally discharge their licensed and procedural dutie I have determined, after consultation with the Commission, to issue the enclosed Notice of Violation and Proposed Imposition of Civil Penalties in the amount of Three Hundred Thousand Dollars (5300,000) for the violations set forth in the enclosed Notice. In accordance with the " General $tatement of Policy and procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985) |
| | (Enforcement Policy), the violations described in the enclosed Notice have been categorized as three separate Severity Level III problems. Each of the problems represents a serious breakdown in the management controls and discipline in the control room and, therefore, the base civil penalty was escalated to |
| | $100,000 for the violations associated with each probles area for a total of |
| | $300,000. ,Given the seriousness of this matter, mitigation was not considered - |
| | cppropriat The enclosed order Modifying the License (Ismediately Effective) is based in part on the supervisory weaknesses of the Nuclear Shift Supervisor exhibited during the July 1-2, 1985 rod pull error and subsequent events. As the most responsible representative of licensee management in the control room at the time of the incident and as a senior licensed operator, he is individually ) |
| | responsible for the activities in the control roan. The July 1-2 incident 1 reflects a failure by this individual to perform at the level expected of licensed supervisory personnel. Therefore, the Order requires that the licensee demonstrate that 'the Nuclear Shift Supervisor has been retrained and reexamined before he is allowed to resume licensed or supervisory responsibilities in the control room. The July 1-2 incident also reflects inadequate procedures and actions of other control root personnel (Nuclear Assistant Shift Supervisor, Nuclear Supervising Operator, shift Reactor Engineer, and Shift Operations Advisor). Thus, the enclosed Order also requires the implementation of a control room audit prograr. to further ensure activities in the control roar are conscientiously carried out. Letters will also be sent to the shift personnel in the control room during the rod pull incident to emphasize their individual responsibilities for safe operation of the facilit An additional matter of considerable concern to me is the lack of forthrightness i exhibited by DECO management in effectively communicating to the NRC in a timely |
| | ! manner all of the information concerning the rod pull error known to Deco. We recognize that while this was not a reportable event, you provided some information te the Resident Inspector about the event on July 3,1985. However, even though the decision on full power licensing was imminent, you did not inform the Resident Inspector, the Region III Office, or NRR that you had determined on July 5,1985 that Femi had, in fact, gone critical on July 1, 1985. More importantly, notwithstanding that this event represented a gross error caused by inexperienced personnel with insufficient management control, neither Mr. Lenart. Assistant Manager, Nuclear production Dr. Jens Vice president, Nuclear Operations, nor anyone else employed by Deco prior to the issuance of full power license on July 15,1985 corrected the impression left by the staff at the July 10, 1985 Cosuission meeting that DECO was en outstanding perfomer in the area of control room operation Deco should have recognized that the performance of personnel and management had significance beyond the technical issues associated with the rod pull error , |
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| | The Detroit Edison Caspary -4-itself and, therefore, corrected the erroneous impression which the staff had at the time'of licensing. Without addressing whether this failure constitutes a legal violation, it clearly represents a departure from the highest standards of cossanication and candor that we expect from licensees at all times and especially at sensitive times in the regulatory process such as at the time of licensing. I espect that in the future Deco will fully emot these standard You are required to respond to this letter and should follow the instructions specified in the enclosed Notice and Order when preparing your msponse. Your response should specifically document the corrective actions taken or any additional actions to increase management attention and direction over the operation of the Fermi-2 facility. After reviewing your response to this : |
| | Notice and Order, including your proposed corrective actions, the NRC will l determine whether further enforcement action is necessary to ensure compliance ! |
| | with regulatory requirement I In accordance with 2.790 of the NRC's " Rules of Practice," Part 2, Title 10 Code of Federal Regulations, a copy of this letter and its enclosure will be placed in the NR; Public Document Roc The responses directed by this letter and the enclosed Notice and Order are not subject to the clearance procedure of the Office of Managemsnt and Budget, as required by the Paperwork Reduction Act of 1980, PF 96-51 |
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| | Sincerely, |
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| | 1' |
| | . JamesM. Taylor / rector |
| | .fice of Inspe: tion and Enforcene Enclosures: |
| | 1. Order Modifying License 2. Notice of Violation and Proposed Imposition of Civil Penalty cc w/ enclosure: |
| | L. P. gregni Licensing Engineer P. A. Marquardt, Corporate Legal Department Licensing Fee Management Branch Resident Inspector. RIII Ronald Callen, Michigan Pubite service Cosmission * |
| | Harry H. Voigt. Es Nuclear Facilities and Environmental Monitoring Section Monroe County Office of Civil Preparedness |
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| SP INPO (4 W ADM:DMB 1 NS AC u_: )') DOT: Trans Only
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| - i (A Applicable Resident Site 4: 6f" i FDR Regions 1 4.0 , II O : Mi, IV 4 :r'), V y : 2 Licensee (Corporate Office)'4 ;io Rev. 07/06/84 l
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Forwards Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted.Weak Procedural Guidance,Communications Issues & Configuration Control Weaknessess Were Evident
NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999
Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions
ML20196J5511999-07-0202 July 1999
Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses
ML20209C6141999-07-0101 July 1999
Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999
Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included
1999-09-09
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20058D1151990-10-26026 October 1990
Forwards Insp Rept 50-341/90-15 on 901009-12.No Violations Noted
ML20059H9821990-09-13013 September 1990
Forwards Safeguards Insp 50-341/90-12 on 900827-31.No Violations Noted
ML20059L2861990-09-10010 September 1990
Informs That Operator & Senior Operator Written & Operating Exams Scheduled for Wk of 901210.Ref Matls Listed on Encl Should Be Provided at Least 30 Days Prior to Exam
ML20059H2421990-09-0707 September 1990
Forwards Insp Rept 50-341/90-11 on 900625-0824.No Violations Noted
ML20059G4731990-09-0404 September 1990
Discusses 900822 Site Visit to Discuss Proposed Security Measures for Next Scheduled Refueling Outage.Proposed Security Measures Discussed May Require Change to Chapter 7, Per 10CFR50.54(p) or 10CFR50.90 as Applicable
ML20059E1581990-08-30030 August 1990
Advises That Util 900425 Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow, Acceptable
ML20059E9291990-08-30030 August 1990
Advises That Util 900126 Response to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type-410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S350W Swing Check Valves... Acceptable
ML20059B7831990-08-22022 August 1990
Advises That NRC Considers 900724 Application for Amend to License NPF-43 Re Turbine Overspeed Protection Sys Withdrawn
ML20059A4111990-08-20020 August 1990
Accepts Util 881003 Response to NRC Bulletin 88-008 & Suppl 1, Thermal Stresses in Piping Connected to Rcss. NRC Recommends That Analysis Prepared in Response to Bulletin & Suppl Be Kept on File for Further Review
ML20059A5981990-08-15015 August 1990
Advises That 900724 Rev 15 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20059A7341990-08-0909 August 1990
Advises That 890721 & 1109 Responses to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning, Satisfactory
ML20059A7611990-08-0909 August 1990
Advises That Response to Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers, Acceptable,Per 890331,0706 & 1106 Ltrs
ML20058N8821990-08-0808 August 1990
Advises That 890724 Application for Amend to License NPF-43, Re RCIC Sys Actuation Instrumentation Considered Withdrawn
ML20058N8851990-08-0808 August 1990
Advises That 881222 Application for Amend to License NPF-43, Re Isolation Actuation Instrumentation Considered Withdrawn
ML20058N8881990-08-0808 August 1990
Advises That 881222 Application for Amend to License NPF-43 Re Control Room Emergency Filtration Sys Considered Withdrawal
ML20058M6141990-08-0707 August 1990
Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date
ML20056A4981990-08-0101 August 1990
Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls
ML20056A6201990-07-31031 July 1990
Advises That Requirements in CAL-RIII-88-09,satisfied & Confirmatory Action Ltr Closed,Per
ML20056A4911990-07-30030 July 1990
Confirms Plans for Mgt Meeting on 900821 in Glen Ellyn,Il to Discuss Plant Status,Refueling 2 Planning & Mgt Changes
ML20055J3301990-07-28028 July 1990
Ack Receipt of 900309 Response to 900212 Order Modifying License & Notice of Violation from Investigation Repts. Util Corrective Actions Acceptable
ML20058L6351990-07-26026 July 1990
Forwards Safety Insp Rept 50-341/90-09 on 900514-0706. Violations Re Inadequacies Associated W/Emergency Diesel Generator Surveillance & Process Computer Changes Noted,But Not Cited
ML20055G3891990-07-16016 July 1990
Forwards Exam Rept 50-341/OL-90-02 Administered on 900528 & 0601-03
ML20055G3351990-07-11011 July 1990
Agrees w/900614 Ltr Re Commitment Change to Inservice Test Program,Per Violation Noted in Insp Rept 50-341/87-09. Effectiveness of Calibr Program Will Be Monitored to Ensure That Inservice Test Program Reliability Not Jeopardized
ML20055D8361990-06-27027 June 1990
Forwards Safety Insp Rept 50-341/90-07 on 900331-0525 & Notice of Violation.Failure to Establish Effective Contractor Control & Inability of Operators to Utilize Reactor Core Isolation Cooling Flow Test Mode Discussed
ML20055D2831990-06-26026 June 1990
Ack Receipt of 900604 Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Now Has Appreciation of Intent of Ltr & NRC Position in 900515 Re Rhr.Issue Considered Closed
ML20059M9221990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20248G3621989-10-0303 October 1989
Forwards SSOMI Insp Rept 50-341/89-200 on 890717-21 & 0731-0804.Weaknesses Identified,Including Lack of Definitive post-mod Test Criteria for Packages & Failure to Establish Proper Controls for Receipt of Vendor Info
ML20248G0111989-09-29029 September 1989
Forwards Synopsis of OI Investigation Into Util Implementation of Facility Licensed Requalification Training Program Under Case 3-87-009.Enforcement Action Associated W/Potential Violation Not Warranted
ML20248C3431989-09-28028 September 1989
Forwards Safety Insp Rept 50-341/89-21 on 890717-0905.No Violations Noted
ML20248C9471989-09-26026 September 1989
Advises That 890908 Rev 4 to Security Personnel Training & Qualification Plan Meets Provisions of 10CFR50.54(p) & Acceptable
ML20248D5181989-09-25025 September 1989
Forwards Safety Insp Rept 50-341/89-23 on 890814-18.No Violations Noted
ML20247P4331989-09-13013 September 1989
Confirms 890901 Telcon W/Ws Orser to Conduct Presentation on Refueling Outage Issues During 890914 Meeting in Newport,Mi
ML20247K0341989-09-0808 September 1989
Summarizes 890831 Meeting W/Util to Discuss Multiple Control Sys Failures Study
ML20246L3561989-08-24024 August 1989
Advises That 881018 Amend Request,Deleting Commitment to Complete 100% Audit Coverage of Tech Spec Line Items within Five Yrs,Disapproved.Subj Disapproval Concurred in by NRR & Region III
ML20246F1301989-08-24024 August 1989
Forwards Safety Team Insp Rept 50-341/89-20 on 890626-30 & 0720 & Notice of Deviation.Requests Info Re Standby Gas Treatment Sys CO2 Tank Level Gauge Calibr Practices
ML20245K1151989-08-14014 August 1989
Forwards Safety Insp Rept 50-341/89-18 on 890606-0724.No Violations Noted
ML20245H6071989-08-10010 August 1989
Advises That 890801 Rev 14 to Physical Security Plan Meets Provisions of 10CFR50.54(p) & Acceptable
ML20247R1771989-07-31031 July 1989
Confirms Monthly Meeting on 890815 in Glen Ellyn,Il to Discuss Plant Status,Schedules & NRC Commitments,Per 890726 Telcon
ML20247K4521989-07-25025 July 1989
Advises That Citation of Violation 341/88037,re Qualification of Core Spray Piping,Found Inapplicable Against 10CFR50,App B,Criterion III & That Citation Against Criterion Xvi Found Applicable,Per of Denial
ML20247J1371989-07-24024 July 1989
Forwards Safety Insp Rept 50-341/89-16 on 890531-0602 & 26-29.No Violations Noted
ML20247A3501989-07-14014 July 1989
Forwards Insp Rept 50-341/89-12 on 890225-0623.No Violations Noted
ML20246Q2631989-07-14014 July 1989
Forwards NRR Director to Ecological Ctr of Southern California Ack Receipt of Petition & Stating That Petition Being Treated Under 10CFR2.206
ML20246K4351989-07-11011 July 1989
Forwards Safety Insp Rept 50-341/89-11 on 890411-0605 & Notice of Violation.Util Will Be Notified of NRC Decision Re Enforcement Action
ML20246E0201989-07-0606 July 1989
Confirms 890712 Meeting in Newport,Mi to Discuss First Refueling Outage at Plant,Per 890705 Discussion.Notice of Significant Licensee Meeting Encl
ML20246E7431989-06-28028 June 1989
Advises That Rev 3 to Security Personnel Training & Qualification Plan Transmitted by 890525 & 0616 Ltrs Consistent w/10CFR50.54(p) & Acceptable
ML20245L0341989-06-27027 June 1989
Forwards Safety Insp Repts 50-016/89-01 & 50-341/89-14 on 890522-26.No Violations Noted
IR 05000341/19880211989-06-27027 June 1989
Informs of Postponement of Decision Re Whether or Not to Withdraw Violation Noted in Insp Repts 50-341/88-21 & 50-341/86-39.Listed Values for LPCI & Core Spray Sys Requested within 60 Days of Receipt of Ltr
ML20245H4021989-06-23023 June 1989
Forwards Safety Insp Rept 50-341/89-19 on 890613-15.No Violations Noted.Exercise Weakness Discussed
ML20245H7261989-06-19019 June 1989
Ack Receipt of Util 890405 Request to Withdraw 881222 Application for Amend to License NPF-43 Re Objective of Maintaining Radioactive Gaseous Releases ALARA
ML20244E2941989-06-12012 June 1989
Forwards Insp Rept 50-341/89-13 on 890508-12.No Violations Noted
1990-09-07
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217N4261999-10-25025 October 1999
Forwards Amend 17 to License DPR-9 & Safety Evaluation. Amend Revises TS by Deleting SR D.3.c,which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building
ML20217P1661999-10-21021 October 1999
Forwards Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted
ML20217M0771999-10-19019 October 1999
Confirms Discussion Between GL Shear,M Mitchell,E Kosky, D Williams,B Rumins,D Harmon & W Rutenberg in Public Meeting on 990923.Purpose of Meeting Was to Discuss Current Status RP Program at Enrico Fermi 2
ML20217E5671999-10-14014 October 1999
First Partial Response to FOIA Request for Documents.Records in App a Already Available in Pdr.App B Records Encl & Being Released in Entirety
ML20217F5931999-10-0707 October 1999
Forwards Insp Rept 50-341/99-11 on 990724-0908.Two Violations Re Failure to Follow Procedures While Sampling Standby Liquid Control Tank & Wear Dosimetry Properly Being Treated as Noncited Violations
ML20217B8261999-10-0404 October 1999
Forwards Summary of Decommissioning Insp Plan for Fy 2000. Plan Will Be Updated Annually & May Be Revised at Any Time Based Upon Future Insp Findings,Events & Resource Availability
ML20212J8121999-10-0101 October 1999
Discusses Plant,Unit 2 Completion of Licensing Action for GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at Npps. Ack Efforts That Licensee Have Completed to Date in Preparing Plant for Y2K Transition
ML20212K8881999-09-30030 September 1999
Refers to 990928 Meeting Conducted at Fermi Unit 2 to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff
ML20212J8331999-09-27027 September 1999
Responds to Licensee 990924 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3/4.6.1.8.Ltr Documents 990923 Telcon with Util in Which NRC Orally Issued NOED
ML20216H4541999-09-23023 September 1999
Informs That During 990914 Telcon L Sanders & M Bielby Made Arrangements for Administration of Licensing Exams at Fermi Nuclear Station for Week of Jan 31,2000.NRC Will Make Exam Validation Visit to Facility During Week of Jan 10,2000
ML20216H3561999-09-23023 September 1999
Informs That During 990914 Telcon,L Sanders & M Bielby Made Arrangements with NRC to Inspect Licensed Operator Requalification Program at Fermi Nuclear Station for Week of 991129 Which Coincides with Util Regularly Scheduled Exam
ML20217A9421999-09-0909 September 1999
Informs That NRC Plan to Conduct Addl Resident Insps Beyond Core Insp Program Over Next 6 Months to Assess Improvements in Areas of Procedural Compliance & Quality of Work. Historical Listing of Plant Issues Encl
IR 05000341/19990131999-08-19019 August 1999
Discusses Insp Rept 50-341/99-13 & OI Rept 3-98-039 Conducted Into Potential Misconduct of Operator Formerly Employed by De.Nrc Determined That Violation of NRC Regulations Occurred.Synopsis of IO Rept Encl
ML20211C0521999-08-17017 August 1999
Forwards Tables for Sections 3.6 & 3.7 of Draft Safety Evaluation of Proposed Conversion of Current TS to Improved Standard TS
IR 05000341/19990011999-08-10010 August 1999
Forwards Insp Rept 50-341/99-01 on 990619-0723 & Nov. Violation of Concern Because Operators Did Not Understand License Requirements & Placed Plant in Configuration Where EDG 11 Was Removed from Service
IR 05000341/19990121999-08-0606 August 1999
Forwards Insp Rept 50-341/99-12 on 990712-0716.No Violations Noted.Insp Focused on Implementation of Plant Chemistry & Radiological Environ Monitoring Programs & Operation of post-accident Sampling Sys
ML20211C4761999-08-0606 August 1999
Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS
ML20210J2121999-07-23023 July 1999
Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation
ML20209F6571999-07-12012 July 1999
Forwards Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted.Weak Procedural Guidance,Communications Issues & Configuration Control Weaknessess Were Evident
ML20196J5511999-07-0202 July 1999
Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses
ML20209E9991999-06-30030 June 1999
Forwards Insp Rept 50-016/99-01 on 990614-17.No Violations Noted.Potential Weakness in Airborne Effluent Concentration Assessment Identified
ML20209B2471999-06-29029 June 1999
Informs That NRR Revised Schedule for Conversion of Fermi 2 TS to Improved Std Ts.Planned Amend Date Has Been Moved to 990930 & Date for Draft Amend Has Been Moved to 990806
ML20207E4961999-06-0101 June 1999
Forwards Insp Rept 50-341/99-07 on 990402-0515.One Violation of NRC Requirements Occurred Re Failure to Keep TS Requirements Re Approval of Overtime Deviations.Violations Being Treated as non-cited Violations,Consistent with App C
ML20207D3311999-05-26026 May 1999
Forwards Insp Rept 50-341/99-04 on 990503-07.No Violations Noted.During Insp,Nrc Observation of Licensee Activities Showed Radiological Emergency Response Preparedness Program Maintained in Effective State of Operational Readiness
ML20206N7351999-05-14014 May 1999
Forwards RAI Re Plant Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions
ML20206N4621999-05-13013 May 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl
ML20206J9131999-05-10010 May 1999
Forwards SE Finding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves,
ML20206Q7041999-05-0606 May 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-341/99-02 on 990308
ML20206G4931999-05-0505 May 1999
Refers to DE 980804 Requests for Relief (PR-8,Rev 2 & PR-12) from IST Requirements of ASME Code for RHR Pumps.Review of Relief Requests Completed.Se Approving Relief Requests Encl
ML20206K4031999-04-29029 April 1999
Forwards Partially Withheld (Ref 10CFR73.21) Insp Rept 50-341/99-08 on 990405-09.No Violations Noted.Concern Expressed Over NRC Observations of Poor Performance Demonstrated During Some Contingency Response Drills
ML20205T3841999-04-23023 April 1999
Forwards Insp Rept 50-341/99-03 on 990218-0401.Two Violations Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20205S8481999-04-20020 April 1999
Informs That Changes in Rev 22 Do Not Decrease Effectiveness of Emergency Plan & Plan Continues to Meet Stds of 10CFR50.47(b) & Requirements of App E to 10CFR50.NRC Approval Is Not Required
ML20205Q7001999-04-15015 April 1999
Forwards Amend 16 to License DPR-9,allowing Possession of Nominal Amount of Special Nuclear Matl,In Response to 980717 Application.Related SER & Notice of Issuance Also Encl
ML20205P1691999-04-14014 April 1999
Forwards Insp Rept 50-341/99-06 on 990315-19.No Violations Noted.Insp Focused on Aspects of Radioactive Effluent Monitoring,Liquid Waste Processing,Esf Filtration & CR Habitability & Solid Waste Mgt & Transportation Programs
ML20204E4061999-03-19019 March 1999
Forwards Insp Rept 50-341/99-05 on 990308-11.No Violations Noted.Insp Concluded That Fire Protection Program Was Effective
ML20204E0271999-03-17017 March 1999
Forwards SE Accepting Licensee & Suppl, ,which Requested NRC Approval of Alternative Rv Weld Exam,Per 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5), for Plant,Unit 2 for 40-month Period
ML20207L7281999-03-0909 March 1999
Informs That Util Ltrs & 981026 Responding to GL 96-01, Testing of Safety-Related Logic Circuits, Completes Licensing Action for Fermi 2
ML20207J1401999-03-0808 March 1999
Forwards Insp Rept 50-341/99-02 on 990111-29 & Notice of Violation.One Violation Identified in Area of Design Control.Violation of Concern Because Errors Existed in Three of Six Calculations Reviewed
ML20207G5711999-03-0404 March 1999
Discusses 990301 Meeting Between GL Shear,M Mitchell, D Williams,C Budnik & M Clements Re Current Status of Radiation Protection Program at Facility
ML20207E2491999-02-22022 February 1999
Discusses Licensee 980617 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program for MOV Periodic Verification for Fermi-2.Forwards RAI Re Fermi-2 Response to GL 96-05
ML20207E6451999-02-22022 February 1999
Submits Correction to Insp Rept 50-341/98-15 Issued on 981207.Rept Incorrectly Documented That Loose Internal Sleeving on Turbine Control Valve Caused Power Oscillations Greater than 10% During Plant Operation
ML20203F6761999-02-11011 February 1999
Forwards Request for Addl Info Re Conversion to Improved Standard Ts,Section 3.6 for Fermi 2
ML20203F2541999-02-10010 February 1999
Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function
ML20203F6911999-02-10010 February 1999
Discusses Completion of Licensing Action for Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors,
ML20203G6411999-02-0808 February 1999
Informs of Receipt of Encl FEMA Correspondence Received 990119,transmitting FEMA Final Exercise Rept for 980608 Plume Exposure Pathway Exercise at Enrico Fermi II Npp.No Deficiencies Were Identified During Exercise
ML20202H8881999-02-0404 February 1999
Clarifies Intent of RAI Re Plant Staff Qualifications & Reg Guide 1.8,Rev 2, Qualification & Training of Personnel for Nuclear Power Plants, Dtd Apr 1987.Staff Position on Issue Neither New Nor Different Position from Previous Position
ML20202H6111999-01-25025 January 1999
Requests Addl Info Re Conversion to Improved Std Tss, Section 3.5 for Fermi 2
ML20206S1111999-01-21021 January 1999
Forwards Insp Rept 50-341/98-19 on 981110-990104.No Violations Noted.Inspectors Noted Potential Trend Re Documented Operability Assessments That May Not Have Been Performed for C/A Resolution Documents
ML20199G7561999-01-14014 January 1999
Forwards Request for Addl Info Re Conversion to Improved Stds Tss,Section 3.3 for Plant
ML20198S3101999-01-0606 January 1999
Forwards Amend 15 to License DPR-9,consisting of Changes to TS in Response to 980128 Application.Related SER & Notice of Issuance,Also Encl
1999-09-09
[Table view] |
Inspection Report - Fermi - 1985040 |
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Attachment 11 GNNTBD AT5s NUCLEAR REGULATORY COMbfl8SMm WaSetMS 7081, D. C. M
\c-) . at o un Docket No. 50-341 License No. NPF-43 EA 86-61 The Detroit Edison Company
,
ATTN: Walter J. McCarthy, J Chairman of the Board and Chief Executive Officer 2000 Second Avenue Detroit, MI 48226 -
Gentlemen:
SUBJECT: ORDER MODIFYING THE LICENSE EFFECTIVE D94EDIATELY AND NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTIES (NR; INSPECTION REPORT N /85040(DRP))
This refers to the inspection conducted by the NRC during the period. July 1 -
October 14, 1965, of activities authorized by NRC License Nc. hPF-43 for Ferr.i-2 and interviews conducted by the Office of Investigations with employees involved in the control rod pull error on July 1-2, 1985. While this inspection also identified additional violations that will be addressed in separate correspondence, the ma.jor emphasis was to review the circumstances associated with the control rod pull errors, premature criticality, and subsequent reconsnencement of rod pulling which o: curred July 1-2, 1985. The inspection report (50-341/85040 (DRP))
identified violations of NRC requirements associated with this incident and was provided to you on January 7,1985. On May 9, 1986 an enforcement conference was held with you and menbers of your staff to discuss the incident, the relatec violations, their causes, and your proposed corrective action.
!
On July 3,1985, members of your staff provided information to the resident inspector on a rod pull error, acknowledging that company procedures had been violated and that there may have been a premature criticality. On July 4, 1985, the Shift Reactor Engineer made a detemination that the reactor had been critical with a 114 second perio It was not until after meetings on July 4 and 5,1985 that Detroit Edison Company (Deco) mana9ement initiated an investigation into the cause of the premature criticality. After Region !!!
was notified of the criticality on July 15, 1985, the licensee's corrective actions were confirmed in a Confimatory Action Letter dated July 16, 198 The inspection and investigations into the events that preceded and followed the premature criticality revealed a major breakdown in the perfomance of control room personnel, in the management of control room activities, and in the evaluation of the incident 1smediately following the rod pull error. This l breakdown wes illustrated in part by the lack of ex serienced shift personnel, !
the disregard for established procedures exhibited ny the Nuclear Supervising Operator (N50) and Nuclear shift Supervisor (NS$), the failure of key shift CERT!FIED MAIL-RETuRK RECEly1 RE0uESTED e6ov11oas9 e60e27 RES E PDR '
_ ,
'
\
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l The Detroit Edison Campasy -2- i l
personnel to fully understand their responsibilities and exercise supervisory oversight, failure to properly use the Shift Operations Advisor (504) and a lack of sensitivity to onpoing processes, incidents, and events demonstrated by shift personnel. The 'ack of involvement and awareness by the NSS, a senior licensed operator, to the evolutions in process and their potential consequences was particularly egregiou The premature criticality occurred when the inexperienced N50 who was in
' control of the reactor startup failed to follow the rod pull sheet and pulled eleven control rods to the Yull-out position (48) rather than position M and mistakenly verified the position as 04 for each rod. The MSO had never taken the reactor critical before and received only casual observation from an unlicensed Shift Technical Advisor in Training. Other members of the shift -
crew were preoccupied with other tasks and at some time during the event were absent from the control room. The MSS who was responsible for managing the shift and overseeing startup activities, and the 50A who was to provide the experience factor for the shift and guidance to inexperienced operators, did not directly observe the rod pulls or respond to the five short period alar annunciations. Wher, the NSO did recognize his rod pull error, he proceeded to reinsert the rods and had the M55 notified. The M55's review of the incident was shallow and he pervitted the N50 to start withdrawing control rods again without adequately analyzing the causal factors that led to the inciden Iter. I described in the enclosed Notice of Violation and Proposed Imposition of Civil Penalties involves the error by a reactor operator (the Nuclear Supervising Operator) in pulling eleven control rods to the full-out position.
,
The reactor operator did not follow the specified rod pull procedure and, in additior., improperly verified and documented the position of the cor. trol rod Contributing to this error were the relative inexperience of the reactor operator and the fact that his training on a simulator had used a rod pull sequence different fron. that used in the actual plan Itee II involves violations associated with the lack of the overall oversight of the control roce during rod pulling which was especially important in view of the lack of operator experience of the NSS and NSO. This was compounded by the failure to use the shift advisors who were there, in part, to compensate for the lack of reactor experience on shift. The July 1-2 event demonstrated the significant failure to properly supervise control room activities and a lack of coordinated efforts in the control roor during a significant plant evolutio Item III involves the failure of the MSS to recognize the significance of the rod pull error and his direction that startup be resumed shortly after the mispositioned rods were returned to their proper position. This violation illustrates a lack of understanding of the need to pro of the rod pull error, a significant procedural error,perly assess startup, before resuming the causes to evaluate the consequences of the svent, and to fuplement effective corrective
actions. The decision by the MS$ to resume rod pulling was based on minimal l
review and evaluation contrary to quality assurance requirements and a management directive to suspend safety-related activities after an event until the problem tes been identified, its cause determined, and a solution formulated and implemente .
.
.
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The Detroit Edison Compavy -3-To emphasias the need for you to ensure that there is proper oversight of control room activities and that control room personnel and supervisors responsibly and professionally discharge their licensed and procedural dutie I have determined, after consultation with the Commission, to issue the enclosed Notice of Violation and Proposed Imposition of Civil Penalties in the amount of Three Hundred Thousand Dollars (5300,000) for the violations set forth in the enclosed Notice. In accordance with the " General $tatement of Policy and procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985)
(Enforcement Policy), the violations described in the enclosed Notice have been categorized as three separate Severity Level III problems. Each of the problems represents a serious breakdown in the management controls and discipline in the control room and, therefore, the base civil penalty was escalated to
$100,000 for the violations associated with each probles area for a total of
$300,000. ,Given the seriousness of this matter, mitigation was not considered -
cppropriat The enclosed order Modifying the License (Ismediately Effective) is based in part on the supervisory weaknesses of the Nuclear Shift Supervisor exhibited during the July 1-2, 1985 rod pull error and subsequent events. As the most responsible representative of licensee management in the control room at the time of the incident and as a senior licensed operator, he is individually )
responsible for the activities in the control roan. The July 1-2 incident 1 reflects a failure by this individual to perform at the level expected of licensed supervisory personnel. Therefore, the Order requires that the licensee demonstrate that 'the Nuclear Shift Supervisor has been retrained and reexamined before he is allowed to resume licensed or supervisory responsibilities in the control room. The July 1-2 incident also reflects inadequate procedures and actions of other control root personnel (Nuclear Assistant Shift Supervisor, Nuclear Supervising Operator, shift Reactor Engineer, and Shift Operations Advisor). Thus, the enclosed Order also requires the implementation of a control room audit prograr. to further ensure activities in the control roar are conscientiously carried out. Letters will also be sent to the shift personnel in the control room during the rod pull incident to emphasize their individual responsibilities for safe operation of the facilit An additional matter of considerable concern to me is the lack of forthrightness i exhibited by DECO management in effectively communicating to the NRC in a timely
! manner all of the information concerning the rod pull error known to Deco. We recognize that while this was not a reportable event, you provided some information te the Resident Inspector about the event on July 3,1985. However, even though the decision on full power licensing was imminent, you did not inform the Resident Inspector, the Region III Office, or NRR that you had determined on July 5,1985 that Femi had, in fact, gone critical on July 1, 1985. More importantly, notwithstanding that this event represented a gross error caused by inexperienced personnel with insufficient management control, neither Mr. Lenart. Assistant Manager, Nuclear production Dr. Jens Vice president, Nuclear Operations, nor anyone else employed by Deco prior to the issuance of full power license on July 15,1985 corrected the impression left by the staff at the July 10, 1985 Cosuission meeting that DECO was en outstanding perfomer in the area of control room operation Deco should have recognized that the performance of personnel and management had significance beyond the technical issues associated with the rod pull error ,
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The Detroit Edison Caspary -4-itself and, therefore, corrected the erroneous impression which the staff had at the time'of licensing. Without addressing whether this failure constitutes a legal violation, it clearly represents a departure from the highest standards of cossanication and candor that we expect from licensees at all times and especially at sensitive times in the regulatory process such as at the time of licensing. I espect that in the future Deco will fully emot these standard You are required to respond to this letter and should follow the instructions specified in the enclosed Notice and Order when preparing your msponse. Your response should specifically document the corrective actions taken or any additional actions to increase management attention and direction over the operation of the Fermi-2 facility. After reviewing your response to this :
Notice and Order, including your proposed corrective actions, the NRC will l determine whether further enforcement action is necessary to ensure compliance !
with regulatory requirement I In accordance with 2.790 of the NRC's " Rules of Practice," Part 2, Title 10 Code of Federal Regulations, a copy of this letter and its enclosure will be placed in the NR; Public Document Roc The responses directed by this letter and the enclosed Notice and Order are not subject to the clearance procedure of the Office of Managemsnt and Budget, as required by the Paperwork Reduction Act of 1980, PF 96-51
Sincerely,
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1'
. JamesM. Taylor / rector
.fice of Inspe: tion and Enforcene Enclosures:
1. Order Modifying License 2. Notice of Violation and Proposed Imposition of Civil Penalty cc w/ enclosure:
L. P. gregni Licensing Engineer P. A. Marquardt, Corporate Legal Department Licensing Fee Management Branch Resident Inspector. RIII Ronald Callen, Michigan Pubite service Cosmission *
Harry H. Voigt. Es Nuclear Facilities and Environmental Monitoring Section Monroe County Office of Civil Preparedness
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