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| {{Adams | | {{Adams |
| | number = ML20137C726 | | | number = ML20209E806 |
| | issue date = 11/14/1985 | | | issue date = 07/03/1986 |
| | title = Insp Rept 50-341/85-40 on 850701-1015.Violation Noted: Failure to Adhere to Tech Spec 6.8.1.2 Re Startup of Reactor on 850701 & Failure to Place Control Room Emergency Filtration Sys in Recirculation Mode of Operation | | | 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 = Wright G | | | author name = Taylor J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| | addressee name = | | | addressee name = Mccarthy W |
| | addressee affiliation = | | | addressee affiliation = DETROIT EDISON CO. |
| | docket = 05000341 | | | docket = 05000341 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-341-85-40, NUDOCS 8601160395 | | | document report number = EA-86-061, EA-86-61, NUDOCS 8609110359 |
| | package number = ML20137C718 | | | package number = ML20209E709 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 17 | | | page count = 4 |
| }} | | }} |
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| | Attachment 11 GNNTBD AT5s NUCLEAR REGULATORY COMbfl8SMm WaSetMS 7081, D. C. M |
| U.S. NL' CLEAR REGULATORY C0m11SSION
| | \c-) . at o un Docket No. 50-341 License No. NPF-43 EA 86-61 The Detroit Edison Company |
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| REGION III l l
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| Report No. 50-341/85040(DRP)
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| Docket No. 50-341 License No. NPF-43 | |
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| Licensee: Detroit Edison Company ;
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| 2000 Second Avenue !
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| Detroit, MI 48226 i facility Name: Femi 2 Inspection At: Femi Site, Newport, MI Inspection Conducted: July 1 through October 15, 1985 i
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| Management Meetings At: Glen Ellyn, Illinois on July 23 i and September 10, 1985 Inspectors: P. M. Byron
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| ] M. E. Parker
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| D. C. Jones i
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| ! I i dG LO Approved By: ) C. Wright, Chief Projects Section 2C;
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| Date !
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| l Inspection Summary I
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| Inspection on July 1 through October 15, 1985, and Management Meetings on i July 23 and September 10, 1985 (Report No. 50-341/85040(DRP)) !
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| Areas Inspected: Special, unannounced inspection by resident inspectors of activities surrounding the out-of-sequence rod pull, the control room HVAC, the RCIC/ core spray room cooler, the cooling tower bypass valve, the hydrogen :
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| recombiner and the breach of primary containment integrity. The inspection ,
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| involved a total of 246 inspector-hours onsite by three inspectors including '
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| 77 hours onsite during off-shifts. The Management Meetings involved a total of 153 hours by 26 NRC personne Results: Twenty-sixviblations(includingexamples)wereidentified(seven- ,
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| Limiting Condition for Operations and nineteen - Procedural). j j p"um mgb -
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| i DETAILS l
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| 1. Attendees l Persons Attending Management Meeting on July 23, 1985 l ~
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| Deco C. M. Heidel President W. H. Jens. Vice-President, Nuclear Operations R. S. Lenart, Assistant Manager, Nuclear Production A. Wegele, Compliance Engineer D. A. Aniol. Nuclear Shift Supervisor G. R. Overbeck, Superintendent, Operations P. A. Marquardt, General Attorney L. C. Lessor, Advisor, Management Analysis C Public
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| B. Campball, Reporter, Detroit Free Press NRC HQ's E. Jordon, Director, Division of EP B. J. Youngblood, NRR Licensing Chief, Branch No. 1 M. D. Lynch, NRR Licensing Project Manager NRC RI!!
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| J. G. Keppler, Regional Administrator C. J. Paperiello, Director, Division of Reactor Safety E. Greenman, Deputy Director, Division of Reactor Projects l N. J. Chrissotimos, Chief, Branch 2. DRP L. A. Reyes, Chief, Operations Branch, DRS
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| l G. C. Wright, Chief. Section 2C, DRP P. M. Byron, SRI Fermi 2
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| T. E. Lang, Operator Licensing
| | ATTN: Walter J. McCarthy, J Chairman of the Board and Chief Executive Officer 2000 Second Avenue Detroit, MI 48226 - |
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| | Gentlemen: |
| B. Stapleton, Enforcement Specialist W. H. Schultz, Enforcement Coordinator S. Stasek, Project Inspector, Femi R. B. Landsman, Project Manager, Section 2C, DRP 5. G. DuPont, Reactor Inspector R. D. Lanksbury, Reactor Inspector l
| | SUBJECT: ORDER MODIFYING THE LICENSE EFFECTIVE D94EDIATELY AND NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTIES (NR; INSPECTION REPORT N /85040(DRP)) |
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| | This refers to the inspection conducted by the NRC during the period. July 1 - |
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| | 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. |
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| . Persons Attending Management Meeting on September 10, 1985 DECO C. M. Heidel, President W. H. Jens, Vice-President, Nuclear Operations R. S. Lenart Assistant Manager, Nuclear Production T. Randazzo Director, Regulatory Affairs E. P. Griffing Assistant Manager, Regulatory Compliance L. C. Lessor, Advisor, Management Analysis C Wolverine Power Supply C. Borr, Member, Services Coordinator J. Gore, Consultant Public T. Lam, Reporter, Ann Arbor News S. Benkelman, Reporter, The Detroit News B. Campball, Reporter, Detroit Free Press M. Johnston, Member, Safe Energy Coalition of Michigan J. Puntennery, Director, Safe Energy Coalition of Michigan F. Kuron, Monroe County Commissioner J. Eckert. Director, Office of Civil Preparedness NRC HQ's H. D. Lynch, NRR Licensing Project Manager L. P. Crocker, NRR Licensing Section Chief, Quality Branch NRC RIII J. G. Keppler, Regional Administrator A. B. Davis, Deputy Regional Administrator C. E. Norelius Director, Division of Reactor Projects E. Greenman, Deputy Director, Division of Reactor Projects G. C. Wright, Chief, Section 2C, DRP P. H. Byron, SRI, Fermi 2 B. W. Stapleton, Enforcement Specialist J. Strasma. Public Affairs Officer R. Lickus, Chief. State of Government Affairs J. A. Hind. Director, Division of Radiation Safety and Safeguards W. D. Shafer Branch Chief Emergency Preparedness and Radiological Protection R. B. Landsman, Project Manager, Section 2C, DRP C. H. Weil, Compliance Specialist T. E. Long Operator Licensing L. Dimmock, Operator Licensing
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| i 2. Out-of-Sequence Rod Pull While withdrawing control rods to achieve criticality on July 1, 1985, the Nuclear Supervising Operator (NS0) pulled eleven control rods in '
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| Group 3 to position 48 rather than position 04 as required by the control rod pull sheets.
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| l The afternoon shift NSO had started pulling control rods around 10:21 p.m.
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| ! EDT on July 1, 1985, and completed pulling centrol rods through step 37 l at 11:15 p.m. EDT. The night shift NSO started to pull rods at step 38 one minute and eleven seconds later. The night shift NSO had observed l the off going NSO for a period of time before taking the controls. The l nightshift NSO utilized a Shift Technical Advisor in Training (STAIT) to l monitor the Source Range Monitor (SRM) instrumentation to facilitate the l rod pull rather than perform that function himsel The NSO completed pulling rods in Group 2 and then commenced pulling rods in Group 3 (step 46). Starting with step 46 and for the next 10 steps the NSO pulled each control rod to the full out position (48) rather than position 04 as required by the procedur The NSO verified by his initials, on the rod pull sheet, that each of the eleven control rods was at position 04 when in fact they were at position 4 While pulling the eleventh control rod in Group 3 (control rod 18-51),
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| the Short Period Alarm annunciated five times and the pen for the Channel A SRM recorder failed to ink for about three minutes. When l the pen started inking again the NSO and STAIT observed that recorder was reading approximately 5x103 counts per second and increasing. The
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| ; Shif t Reactor Engineer (SRE) had predicted that criticality should occur
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| between steps 150 and 160, when the NSO observed the increasing count l rata he was only on step 56. The NSO instructed the STAIT to inform the Nuclear Shif t Supervisor (NSS) of the situation and immediately started to insert rod 18-51. It took 14 minutes and 41 seconds to insert all eleven control rods to position 04. Thirty-five (35) seconds later the NSO continued the startup by pulling rods from step 57 of the procedur During the control rod pulls the NSS and the Nuclear Assistant Shift Supervisor (NASS) were in the NSS's office. The SRE was behind the panels and could not observe the rod pulls. The NSO in charge of the control room was at his desk facing the pan 11s and the Shift Technical Advisor (STA) and the Shift Operations Advisor (50A) were by the NSO's desk, Neither the NSO in charge, the SOA, nor the STA were observing the rod pull nor were they aware of the incident. The STAIT Informed the SRC of the event who wrote in his log that the reactor may have been critica The NSS reviewed the event with the NSO (at the controls) and the STAIT and determined that the reactor had not gone critical. lhe NSS then directed that rod pulling recommence. The NSS apparently did not seek the advice or counsel of the SRE, the SOA, or the S1A, The SRE also ,
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| lined out in his log book the reference of the unit being critica Neither the NSS nor the NSO logs contained an entry regarding the
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| out-of-sequence rod pull. The NSS, however, did write a Deviation /
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| Event Report (DER) (No. NP-85-0334) describing the event and stated that the reactor had not gone critica DER No. NP-85-0334 was reviewed by the licensee's Corrective Action Review Board (CARB) on July 2,1985, who concurred with the NSS's determination that the incident was not reportable under either 10 CFR 50.72 or 50.73. It appeared that there was disagreement within the licensee's organization as to whether or not the reactor had been critica The licensee directed that additional engineering review be made. The licensee informed the Resident Inspector (RI) of the event on July 3, 1985, and stated that the unit had not gone critical but that there was a question among the staff and that Reactor Engineering was performing a technical review. The licensee stated that they would get back to the RI when the determination had been made. The RI informed RIII of his meetin A SRE made the determination on July 4,195 that the reactor had been critical on July 1, 1985, with a 114 second period and informed his management of the determination. Several licensee meetingr. were held on July 5 and 6, 1985 to discuss this event and to initiate an investigation into its caus The next discussion with the NRC resident staff, af ter July 3,1985, was on July 15, 1985, when the Senior Resident Inspector (SRI)
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| was asked by licensee management if he was aware of the July 1, 1985 incident and that the reactor had been critical. The SRI was aware of
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| the out-of-sequence rod pull but was not aware that the reactor had been critical. The SRI informed RIII of the meeting, and the new information on criticalit Region !!! Issued a Confirmatory Action Letter (CAL-RI!!-85-10) to the licensee on July 16, 1985. The CAL detailed the corrective action the licensee was to take relating to the out-of-sequence rod pull. The CAL is detailed in Inspection Report 50-341/85043(DRP). The licensee
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| - made a presentation in Region III on July 23, 1985, regarding their corrective action program and finu ngs related to the event which is described in Paragraph 9 of this report. The licensee's presentation is included as an attachment to their response to the CAL, Deco letter RC-LG 85-0017 (Jens to Keppler) dated September 5, 198 During the inspection and review of the event, nine examples of apparent violations of Technical Specification requirements were identified and are as follows:
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| Technical Specification 6.8.1.a requires that written procedures shall be estab11shed, implemented, and maintained covering the applicable procedure recommendations of Appendix A of Regulatory Guide 1.33, Revision 2, 1978. Appendix A of Regulatory Guide 1.33 lists the following activities under Administrative procedures:
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| - Hot Standby to Minimum Load (Nuclear Startup)
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| - Authorities and Responsibilities for Safe Operation...
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| - Equipment Control
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| - Shift and Relief Turnovers
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| - Log Entries Contrary to the above, the licensee failed to adhere to the provisions of Technical Specification 6.8.1.a covering the startup of the reactor on July 1, 1985, as indicated below: P0M Procedure 51.000.08, " Control Rod Sequence and Movement Control," paragraph 3.1.1, requires that rod withdrawals in the region from 100% Rod Density to 20% Reactor Power must be performed according to the rod pull sheet. The rod pull sheets in effect on July 1,1985, required the rods for Group 3 to be pulled in notch control (00-04, 04-08, etc.). The licensee pulle<* :leven control rods in Group 3 to the full out position (48) rather than to the 04 position as required (341/85040-01a). POM Procedure 51.000.08 Paragraph 3.1.4 states, in part, "Following each rod move the Nuclear Supervising Operator (NS0) shall verify the control rod was lef t in the proper position indicated and shall document this verification by initialing the ' Final Position
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| Verified' block of Attachment 1." The NSO verified eleven rods to be at position 04, by initialinj the pull sheet, when in actuality they were at position 48(341/85040-01b). POM Procedures 12.000.57, " Nuclear Production Organization" and 21.000.01, "Shif t Operation and Control Room" delineate the responsibilittee of the NSS to include supervision of all activities and observation and/or direction of major plant evolutions to ensure compliance with Technical Specificatiens, procedures, and regulation The NSS did not appropriately discharge his duties on July 1 and 2,1985, in that Me neither
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| supervised, observed, nor directed the activities essociated ,
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| with the control rod pulls (a major plant evaluation) nor was he in the proximity of the appropriate control panel and associated nuclear instrumentation (341/85040-01c). POM Procedur 21.000.01, Enclosure 1 Item 12, requires the Nuclear Assistant Shif t Supervisor (NASS) to provide direct supervision of shift personnel. The NASS did not provide direct supervision of the NSP manipulating the controls on July 1 and 2,1985 nor was he in the proximity of the appropriate control panel and associated
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| nuclear instrumentation (341/85040 01d). P0H Procedure 21.000.01, Enclosure 2, Item 5 requires the NSO to be responsible for the plant's main control room operatio The control room NSO was unaware of the out-of-sequence rod pull and thus was not successfully discharging his duties (341/85040-01e).
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| . POM Procedure 21.000.01, Enclosure 6, Item 2, requires the Shift Operations Advisor (SOA) observe actuation of annunciators to ensure that they are being promptly and properly addressed with actions taken. Five short period alarms were received in less than four minutes while pulling rod 18-51 on July 1, 1985. The NSO at the controls was allowed to continue pulling rods and the SOA did not discharge his responsibilities by failing to become involved in the resolution of the short period alarms (341/85040-01f). P0M Procedure 21.000.02, " Operating Logs and Records," Section 4.2.5.8, requires the NSS to record the occurrence of significant events in the NSS log. The NSS log for July 1 and 2,1985, contained no entries for the out-of-sequence rod pulls, a significant event, which occurred between 11:40 and 11:59 on July 1,1985(341/85040-01g). POM Procedure 21.000.01, " Shift Operation and Control Room," Section 6.3.8 states, " Reactor Engineering Administrative Procedure N .000.10, ' Reactor Engineering Conduct of Operations,' details the duties and responsibilities of on-shif t Reactor Engineering personnel."
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| Procedure 51.000.10 Section 1.0, states, "The purpose of this procedure is to outline operational interfaces between Reactor Engineering and Plant Operations and to clarify the overall responsi-bilities of on-shif t Reactor Engineering personnel." Procedure 51.000.10 does not detail the duties and responsibilities of the on-shift Reactor Engineer (341/85040-01h). POM Procedure 21.000.01, Section 6.8 addresses shift relief and Section 6.8.4 specifically addresses the control room nuclear supervisingoperator(NS0). The procedure defines the required turnover for the NSO in charge of the control room but does not define any turnuver requirements for the NSO assigned to duties in the control room but not in charge of the control room (341/85040-011).
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| 3. Control Room HVAC On July 11, 1985 PN-21 No. 286934 was issued to inspect the Division !!
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| Control Room HVAC condensate tra For personnel protection the Division !!
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| Control Room HVAC supply fan control switch was placed in the off position at 8:35 a.m. on July 18, 1985 and the feeder break was opened and red tagged at 8:50 a.m. The Nuclear Supervising Operator (NS0) entered the action in his log but did not list the Technical Specification appitcabilit The NSO also entered the action in the Control Room Information System (CRIS) equipment status file and placed the applicable CRIS dot next to the switch on the sanel. The NSO also advised the protection leader that protection had to )e removed by 3:00 ).m. on July 25, 1985, however, the NSO failed to notify the NSS of the c1ange in equipment status. Neither the NSS log nor the out-of-specification log contain any entries on the inoperable Division !! HVAC. The work was completed and the request to 7 .
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| removeprotectionwasmadeat1:20g.m.onJuly 18, 1985. However, the package was misfiled in the " active file rather thar, the " protection to be cleared" fil The out-of-specification condition went unnoticed for 27 shift turnovers by the oncoming NSS, NASS, and NS0's even though the switch was marked, a log entry had been made, and it was entered in the CRIS equipment status fil It was not until July 27, 1985 that a nightshift NSS questioned the status of the Division II Control Room HVAC fan and had the fan returned to service at 5:38 a.m. on July 27, 198 During the inspection and review of the event, two apparent violations of Technical Specification requirements were identified as follows:
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| l Technical Specification 3.7.2.C.1 requires that with the control center emergency filtration system supply fan inoperable, with the plant in cold shutdown, the fan be made operable in seven days or initiate and maintain operation of the system in the recirculation mode of operatio Centrary to the above, the licensee failed to place the control room emergency filtration system in the recirculation mode of l
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| operation on July 25, 1985; seven days after the system was l rendered inoperable on July 18, 1985. This condition existed l for aroroximately forty-five (45) hours (341/85040-02). Technicsl Specification 6.8.1.a requires that written prac#dures shall be established, implemented, and maintained covering the l applicable procedure reconinendations of Appendix A of Regulatory Guide 1.33 Revision 2, 1978. Appendix A of Regulatory Guide 1.33
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| lists the following activities under Administrative Procedures:
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| - Authorities and Responsibilities for Safe Operation...
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| - Equipnent Control
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| ! - Shif t and helief Turnovers
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| - Log Entries...
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| Contrary to the above, the licensee failed to adhere to the provisions of Technical Specification 6.8.1.a as follows:
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| (1) POM Procedure 21.000.01 "Shif t Operations and Control Room,"
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| delineates the shift turnover responsibilities of the Nuclear Shif t Supervisor (NSS) the Nuclear Assistant Shift Supervisor (NAJS) and the Nuclear Station Operator (NS0). Included in the responsibilities is a review of past log entries, and a review of each Combination Operating Panel for off-normal conditions or the addition of CRIS " dots." The NSS NASS, and NSO all l failed to adequately perform the required activities as indicatedbelow(341/85040-03a):
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| (a) The Control Center Division II HVAC supply fan switch was placed in the off position on July 18, 1985, and not observed to be out of position until July 27, 1985. The out-of-specification switch position went unobserved for 27 shift turnover (b) The NSO entered the switch position in the equipment status file and placed a CRIS " dot" by the switch on July 18, 1985. The CRIS " dot" went unobserved for 27 shift turnover (c) The NS0 had logged placing the Division II Control Center HVAC supply fan in the off position at 8:35 on July 18, 1985. Subsequent reviews of the log either failed to note the entry or failed to recognize its significance. (6 NSS turnovers, 15 NASS turnovers, and 27 NSO turnovers)
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| (2) P0H Procedure 21.000.01, Section 6.19.1.1 states, in par " Evaluate the consequences of removing the system or component from service considering such items as Technical Specifications L.initing Condition for Operations which require an action
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| ! statement to be carried out...." The licensee failed to I evaluate the consequences of removing cornponents from service in that no acknowledgernent of any Technical Specification applicability was made in either the NSO log of the Control Room Information System (CRIS) when the Division !! Control Center HVAC was removed from service (341/85040-03b).
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| l 4. RCIC/ Core Spray Room Cooler The NSS observed whilt. reviewing the combination o)erating panels during his turnover on July 24, 1985, at 6:30 p.m. that tie control switch for the Division ! Reactor Core Injection Cooling (RCIC)/ Core Spray Room Cooler was in the off-reset position, this made both RCIC and Division !
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| I core spray inoperable. The NSS who discovered the out-of-position switch stated that it was in the proper position at 3:30 p.m. on July 23, 198 The Itcensee also determined that the Motor Control Center (MCC-728-3A Position 20) feeding the room cooler was found in the off positio Subsequent investigation by the licensee did not reveal any reason for the coolers status nor could any PN-215 be identified which would have authorized de-energizing the MCC feeder breaker. The room cooler was returned to service and the licensee documented the incident in DER NP-85-039 Theunitwasinthestartupmodeofoperation(OperationalCondition2)
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| at the time the room cooler was taken out of service, but was in a planned shutdown due to the loss of the South Reactor Feed Pump when the cooler was found out of service. (Reactorpressurehadbeenreduced to less than 150 psig at 7:30 a.m. on July 24,1985.) RCIC is not l
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| | 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 !!! |
| I l required to be operational below 150 psig; however, the High Pressure ;
| | 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 ' |
| CoreInjection(HPCI)hadbeeninoperablesinceJuly 11, 1985 thus for
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| ! approximately sixteen (16) hours the HPCI, RCIC and Division I core spray systems were all inoperabl i
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| During the inspection and review of the event, two apparent violations l l of Technical Specification requirements were identified as follows:
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| ! Technical Specification 3.5.1.C.1 requires that during the startup l l modeofoperation,theHighPressureCoreInjection(HPCI) system may be inoperable provided that the Core Spray (CS) system, the Low Pressure Coolant Injection (LPCI) system, the Automatic Depressurization System (ADS), and the Reactor Core Isolation Cooling (RCIC)systemareoperabl Contrary to the above, the licensee failed to ensure that the ;
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| RCIC and Division ! core spray systems were operable when they i allowed the RCIC/CS room cooler to be removed from service at j 3:30 p.m. on July 23, 1985 with the HPCI system already inoperable ;
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| as of 3:00 a.m. on July 11, 1985. This condition existed for approximately sixteen hours, with the reactor in the Startup condition (341/85040-04). Technical Specification 6.8.1.a requires that written procedures shall be established, implemented, and maintained covering the applicable procedure recomendations of Appendix A of Regulatory Guide 1.33 Revision 2, 1978. Appendix A of Regulatory Guide 1.33 lists the following activities under Administrative Procedures:
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| - Authorities and Responsibilities for Safe Operation...
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| l - Equipment Control l - Shift and Reitef Turnovers ( - Log Entries...
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| Contrary to the above the licensee failed to ad (n to the
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| provisions of Technical Specification 6.8.1.a as voilows: i (1) POM Procedure 12.000.15"PN-21jWorkOrder) Processing,"
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| Section 7.2.1 states, in part, All work activities at Fermi 2...sha11 be controlled by a PN-21 and Attachmeet 'A' ,
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| , to the PN-21." The licensee failed to write a PN-21 to !
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| de-energize the feeder breaker (NCC-728-3A Position 20) for the RCIC/ Core Spray room cooler fan on July 23 and 24,1965 (341/8504005a).
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| (2) POM Procedure 21.000.01, " Shift Operations and Control Room " ,
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| l delineates the shif t turnover responsibilities of the Nuclear ! | | ; |
| l Shif t Supervisor (NSS) the Nuclear Assistant Shif t Supervisor ! | | \ |
| (NASS) and the Nuclear Station Operator (NS0). Included in the !
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| responsibilities is a review of past log entries, and a review '
| | l The Detroit Edison Campasy -2- i l |
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| | 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 - |
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| | 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. |
| 10 l l
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| O of each Combination Operating Panel for off-normal conditions or the addition of CRIS " dots." The NSS, NASS, and NSO all failed to adequately perform the required activities as the RCIC/ Core Spray room cooler fan switch was in the "off-reset" l position for approximately 24 hours on July 23 and 24,1985. The normal position for the switch is in the " Auto" position. The
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| out of position switch went unobserved for two shift turnovers (341/85040-05b).
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| (3) P0M Procedure 21.000.01, Section 6.19.1.1 states, in part.
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| l " Evaluate the consequences of removing the system or component from service considering such items as Technical Specifications
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| Limiting Condition for Operations which require an action statement to be carried out...." The licensee failed to evaluate the consequences of removing components from service
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| ! as he did not take into account the existing inoperability of l the HPCI system prior to removing the RCIC/ Core Spray room l cooler from service nor was the action entered into the NSO log or the CRIS equipment status file (341/85040-05c).
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| 5. Cooling Tower Bypass Valve On July 26, 1985, while performing surveillance testing on Division I, l Emergency Diesel Generator (EDG) #11, a Diesel Generator Service Water l
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| (DGSW) Low Flow Alarm was received. The alarm indicated a lack of cooling water for the EDG. The operator verified the low flow and l
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| innediately shutdown the EOG. The licensee, upon further investigatib determined that the mechanical draft cooling tower bypass valve E1150-F603A was closed and de-energized. This valve is required by a condition of the license to be open and de-energized, or one of the cooling tower shutoff valves E1150 F604A/F605A is to be open and de-energized to prevent spurious closure due to hot shorts in the event of a fire in the plant. The nomal position for this motor operated va'te is de-energized and open per POM Procedure 23.208, Revision Thi . is an apparent violation of License Condition 2.C.(9)(d) (341/85010-06).
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| Invtstigation into the rcason why the bypass valve was out of proper position, identified that the valve was last manipulated on July 23, 1985, while running the Reactor Heat Removal Service Water (RHR$W)
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| system. The valve had exhibited a tendency to trip either the thermal overloads or the torque switches during stroking and an operator had been required to partially stroke the valve to the desired position as well as reset the thermal overloads to allow continued stroking from the control room. It appears that clear instructions were not given to the Reactor Building Rounds Operator as he was not aware of the necessity of leaving the Ell 50 F603A valve in the open de energized conditio The E1.50 F603A valve is located in the discharge flow path to the coolin$ water reservoir and its closure affects multiple systems. With the valve closed, flow of Erwrgency Equipment Service Water (EESW),
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| RHR$W, and DGSW is blocked. Besides affecting the Division I EDG's, with the bypass valve closed all Division I emergency core cooling systems were inoperable including the core spray and residual heat removal system At the time the bypass valve was discovered in the closed position, the reactor was in cold shutdown, Condition 4, with the reactor temperature at approximately 130*F and atmospheric pressure. In cold shutdown the plant is required to have one operable division of ECCS, and one operable divisionofEDG's(twodiesels). This condition was satisfied, however, the bypass valve E1150-F603A had been closed since about 1:19 p.m. on July 23, 1985. On July 23, 1985, theunitwasinCondition2(Startup)
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| which requires both divisions of ECCS and both divisions of the onsite electrical power source (EDG's) to be operable. As a result of the bypass valve being closed, only one division was operable. The failure to take remedial action with one division of the EDG's inoperable is an apparent violation of T.S. 3.8.1.1.b (341/85040-07).
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| On July 23, 1985, the licensee connenced a reactor shutdown at about 1:15 p.m. as a result cf the failure of the South Reactor Feed Pum It was fortuitous that the licensee coemenced a recctor shutdown a>out the same time the cooling tower bypass valve was de-energized in 'le closed position, as the licensee was by chance co.. plying with the Limiting Condition for Operation (LCO) action statements in reducing power and proceeding to cold shutdown. Without this action, the plant would have been in further violation of technical specification . Hydrogen Recombiner On June 20, 1985, the licensee completed maintenance on the Division !!
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| hydrogen recombiner per Work Order PN-21269327 to replace a leaking blower seal. The work order stated that post maintenance testing was required, and identified Plant Operations Manual (POM) Procedures 43.409.01, " Post LOCA Thermal Recombiner System Test," and 24.409.01
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| " Post LOCA Thermal Recombiner Functional Test." These procedures were required to demonstrate leak tight integrity and operability, respectively. The work order was stoned off as completed by the Nuclear !
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| Shif t Supervisor on June 20,1985, w' thout the leakage test having been perforned per P0M Procedure 43.409.01. This is an apparent violation of TechnicalSpecifications(T.S.)6.8.1.aand6.8.4.ainthatthelicensee failed to follow estabitshed procedures and comply with the leakage reduction program (341/85040 08). i On August 26 1985, the licensee initiated a Deviation / Event Report LNo. I'P-85-0I55) to document the failure to perform the post maintenance leak rate testing on the Olvision !! hydrogen recombiner. After i determining the failure to the licensee had sufficient l wrfom testing}ner infomation to declare the aydrogen recomb inoperable, as a result j of exceeding the 30 day LCO limit, and the licensee did not take action per technical specification 3.0.3. to place the unit in hot shutdown
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| * l within six hours. The licensee proceeded to determine the leakage rate and on August 28, 1985, declared the Division II hydrogen recombiner innperable as a result of the initial leakage rate testing. Subsequently on August 29, 1985, at 2:46 p.m. the licensee determined that the leakage rate was in excess of the allowable containment leakage. This is an apparent violation of T.S. 3.6.6.1, and 3.0.3 in that the licensee failed to comply with the LCO action statements (341/85040-09).
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| At 6:00 p.m., on August 29, 1985, the licensee cummenced preparations to proceed to hot shutdown. The hydrcgen recombiner was repaired, leak tested, and declared operable on August 29, 1985, at 9:00 p.m. The plant was returned to the startup mode with pressure at 950 psig and 3.8% power for HPCI and SCRAM time testing at 10:40 p.m.
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| During the time period from June 21 to July 21, 1985, the plant entered l Operational condition (Startup) on five (5) occasions including initial criticality (June 21, 1985, June 29, 1985, July 2, 1985, July 6, 1985,
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| and July 10,1985) without both divisions of hydrogen recombiners l operable. This is an apparent violation of T.S. 3.0.4(341/85040-10).
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| 7. Breach of Primary Containment Integrity l ThelicenseediscoveredaContainmentMonitoringSystemValve(T50-071A)
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| ! which is a primary containment boundary, in the open position and uncapped I on September 2, 1985. The valve was shut upon discovery. The Nuclear l Shif t Supervisor (NSS) was informed of the event on September 4,1985, l approximately 39 hours af ter discovery. ADeviation/EventReport(DER)
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| l (No.NP-85-0469) was written to document the open valv Valve T50-071A was installed under Engineering Design Package (EDP)
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| No. 1970 dated March 25, 1985. The EDP included the installation of four test connection cutoff valves in the primary containment monitoring system. Valves T50-068A and B were installed in piping from the bottom of the torus while valves T50-071A and B were installed in piping from the top of the torus. PN-21(WorkOrder)No. 814949 was written to install the "A" valves in Division I and PN-21 No. 814948 was written to install the "8" valves in Olvision !!. Both PN-21s were signed off as
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| " Order Completed" on June 20, 198 It should be noted that neither EDP 1970 nor the four PN-21s associated with it were closed out as of September 10, 198 Doth PN-21s for the primary containment monitoring system required Local Leak Rate Tests (LLRTs) plus Plant Operations Manual Procedure 24.000.05, " Monthly Continuity Light and Channel Check Test," Section 4
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| " Precautions and Limitations" to be completed. The NSS signed the PN-21s as order complete on June 20, 1985. The licensee reviewed EDP 1970 and detemined that the LLRTs for the primary containment monitoring system modifications had not been performed. DER No. NP-85-471 dated September 5, 1985, was written to document this discrepancy. The licensee subsequently performed the missed LLRTs and three of the four LLRTs met
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| ! procedural criteria. The LLRT for Penetration.X203A.(P0M Procedure 43.401.386) which contains valve T50-071A did not meet the leakage criteria. Two of the three boundary valves were repaired and the penetration subsequently met the test criteria, p During the inspection and review of the event, three apparent violations
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| were identified as follows:
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| i Technical Specification 3.6.1.1 requires that PRIMARY CONTAINMENT INTEGRITY shall be maintained in Operational Conditions 1, 2,-and 3.
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| e Without PRIMARY CONTAINMENT INTEGRITY restore PRIMARY CONTAINMENT.
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| *
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| INTEGRITY within one hour or be in at least HOT SHUTDOWN within the
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| [ next 12 hours and in COLD SHUTDOWN within the following 24 hours.
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| 4 Contrary to the above, the licensee failed to maintain containment i integrity from June 21 to September 2,1985, in that primary containmentmonitoringsystemvalve(T50-F071-A)wasintheopen position and the line downstream of the' valve was uncapped which 4 resulted in an open pathway from the primary containment to the.
| | 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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| L reactor building. Primary containment integrity was required during l this time frame except for 6.25 days of the interval-(341/85040-11).
| | 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 . |
| ! Technical Specification 6.8.1.a requires that written procedures shall be established, implemented, and maintained covering the-applicable procedure recommendations of Appendix A of-Regulatory-
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| Guide 1.33 Revision 2, 1978. Appendix- A of Regulatory Guide'1.33.
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| l lists the following activities under Administrative Procedures:
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| (1) Equipment Control (2) Log Entries...
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| i Contrary to the above, the licensee failed to adhere to the
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| provisions of Technical Specification 6.8.1.a as follows:
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| ! P0M Procedure 12.000.15, "PN-21 (Work Order) Processing," Revision 11,
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| August 20, 1985, paragraph 7.3.16 states: "Upon completion of all-
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| ; maintenance, testing, STR or EPC and after_the ' Accepted for Service-
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| By' slot has been signed, the pink copy-of PN-21 is forwarded to the Nuclear Shift Supervisor who will review the order and sign ' Order
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| i Completed.'" Contrary to the above, the licensee failed to adhere - ' ,
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| i to the requirements of POM Procedure 12.000.15. in that Work Order- ,
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| i PN-21 No. 814945 (covering the addition of leak rate test conriectio '
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| : valve T50-F071A) was signed " order completed" on June 20, 1985,
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| ; without the post installation leak rate testing being performed a ;
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| ; specified.onthework-order-(341/85040-12)..
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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) |
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| | (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 |
| . CFR 50, Appendix B, Criterion VI,; states, in part,a" Measure. shall: !
| | $100,000 for the violations associated with each probles area for a total of |
| : be established to control the issuance of documents, such as *
| | $300,000. ,Given the seriousness of this matter, mitigation was not considered - |
| instructions, procedures,'and drawings,. including changes'thereto, which prescribe all activities affecting quality. These measures
| | 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 ) |
| ; shall assure that documents including changes are reviewed for '
| | 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 |
| adequacy...." '
| | ! 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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| ,3 -
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| i I
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| POM Procedure' 12.000.64, "EDP1 Implementation Procedure,": Revision 2, ..;
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| dated March 5, 1985, Section 6.5.1; states, in part, "The responsible !
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| PSE shall identify the plant documents requiring revision when the - 4
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| package is prepared."
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| Contrary to the above, the EDP. Implementation Procedure for EDP'
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| : No.1970, covering.the installation of the containment sample system . '
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| !- leak rate test connection valve T50-f CIA, did not. identify.all -
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| I the plant documents requiring revision in that it did not identif .l POM Procedures 24.425.01, " Primary Containment Integrity i l Verification for Valves Outside Containment," or 47.000.77, " Test *
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| Vent and Drain (TVD) Cap:and Plug Verification." The failure to :
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| identify these documents resulted in valve T50-F071A (an_d seven-. :
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| ; other valves) not being incorporated into the procedures used to .
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| ; verify containment integrity (341/85040-13). !
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| 8. 'Sumary ];
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| 1 ;
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| Twenty-six -violations (including multiple examples) of NRC requirements j are identified in this report. The majority of these fall into the
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| ; category of failure to follow procedures._ This represents a-breakdown j i in the licensee's ability to operate the plant in accordance wit !
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| prescribed procedures as required by the Technical Specification lj
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| The licensee's Operational Assurance (0A) organization has a program !
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| called. Procedure Compliance Module (PCM) which monitors, on a monthly : !
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| bases, procedural compliance by various organizations. The results'of
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| six monthly surveillances (January-June 1985) clearly' revealed that the
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| ; operations section had had problems in following procedures. (Procedural i
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| ; compliance ran from 74% to 100% and there was no trend--the results were -
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| erratic. The six-month average was 87% with 99% compliance as a goa ['
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| It should be noted that the findings of-the PCM program are not absolute
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| but are excellent indicators of potential-problem areas. The'results, l
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| ; both current and cumulative, are issued monthly. Theslicensee had 1 ( sufficient knowledge of procedural compliance problems to initiate !
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| j, corrective actions rather than wait for a larger' data bas !
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| Seven of the violations were failures to meet Technical Specification
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| LimitingConditionforOperations(LC0's).1 Each of these were serious and !
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| [ collectively represented a breakdown in the licensee's administrative and i management controls design to safely operate the plant. The safety; !
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| significance!of the violations was. mitigated considerably by two' items- i
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| . the plant had only operated for 20 days at an average power of,2 percent; .i
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| ! and the failure of the South Reactor Feed Pump turbine which resulted in- j
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| <
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| the licensee shutting the reactor down. The inspectors consider the . !
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| second item to be fortuitous.in-that the: reactor was removed from an
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| 4 ;
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| i operating condition which required certain equipment to be operable or '
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| "ractions to'be taken when the licensee wasLunaware that the actions o ,
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| J equipment were. required..
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| [ 'N !
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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 ! |
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| | 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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| ;,.s p -' E
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| *
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| .ns,,,-.,,w~, - r vi, r n , ~~-~~m ~r~-~e so Iv~v h , ew"e =~ ~Ow~~'*"'- ~*A'' *^~*"*N""""*~-~"
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| ''^"A ' " " " " *
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| .,
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| Twenty-six violations, many of them repetitive, have been identified-in this. report.- Operating history mitigated their safety significance; however, they demonstrated a major breakdown in the licensee's administrative controls to safely operate the plan . Management Meetings OutJof-Sequence Rod Pull DECO management.(denoted in Paragraph 1) met with RIII managemen in' Glen Ellyn, Illinois,-on July 23, 1985', to' discuss the sequence of events surrounding the out-of-sequence rod pull which occurred on July 1 and 2,.1985, and their subsequent actions. This meeting was, attended by the publi The . licensee's presentation included a' detailed sequence.'of events imediately preceding and following the event, the rod pull _ sheets, and the Source Range Monitor (SRM) strip chart which. corresponded to-the time of the incident. .The licensee also presented a layout of the control room and the relative location in the control room of those on shift at the time of the event. A great deal of discussion was focused on the events and licensee' actions subsequent.to the incident. The adequacy of the onshift review was discussed; RIII's position was that the onshift review was insufficient. Considerable discussion was focused around the adequacy, completeness, and timeliness of the reporting of the incident to the NRC. The licensee did not consider the event to he reportable under 10 CFRs 50.72 or 50.73. Region III concurred that the incident was.not reportable under 10 CFR 50.72 or 50.73, but given;the proximity of r the Comission's full-power briefing, Deco should have been more-
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| sensitive to the importance of keeping.the NRC informed.- The Regional Administrator informed the licensee that he had requested
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| [ the Office of Investigations (OI) to. investigate the even The licensee also discussed their actions pertaining to whether or
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| not the unit had been critical, as a ' result of the out-of-sequence .
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| rod pull, and their corrective action. program. The licensee was informed that Region III would send an inspection team to Femi.2 -
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| to assess control room operations and the effectiveness of. the -
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| corrective action progra The licensee's presentation is included as-an-attachment to DECO letter No. RC-LG-85-0017~ (Jens to Keppler) dated September 5, .198 Corrective Action Program DECO management (denoted in Paragraph 1) net with Region III-management in Glen Ellyn,' Illinois, on September 10, 1985, to discuss their corrective action program to preclude the repetition of the ~
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| events which were reported to the NRC during July and. August 1985'and documented elsewhere in this report. -The meeting was attended by
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| representatives of the. Monroe County. Government and the public.
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| The licensee proposed a corrective action program based on observations and recommendations made by the Institute of Nuclear Power Operations (INP0) assistance inspection team, findings of two recent NRC team inspections, conditions of the Confimatory Action Letter (CAL-RIII-85-10) dated July 16, 1985, findings by the resident NRC inspectors, and recommendations made by Management AnalysisCorporation(MAC). The program was divided into short and long term actions. Short term actions were to be completed prior to power escalation above five percent. Long term actions addressed programmatic areas with the licensee indicating a phased implementation to minimize pertubations to plant operation Long term actions were to be initiated prior to exceeding five percent power but not to be completed until some later date with the longest date of December 1, 198 Deco requested that the five percent power restriction be lifted but that they would commit to not exceeding twenty percent power until after the forthcoming outage which is scheduled to start during October 1985. The request was denie Region III requested that the licensee docket the corrective action program which had been presented and include methods of monitoring the effectiveness of the corrective actions. The licensee subsequently submitted their " Reactor Operations Improvement Plan" in a letter from Jens to Keppler (DECO No. VP-85-0198)
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| dated October 10, 1985 (copy attached).
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| The licensee was also informed that another inspection team would be sent to Femi 2 to observe operations and review the corrective action program and its effectiveness before .the five percent restriction could be lifted. This action was predicated upon a satisfactory resolution of the 01 investigatio . Enforcement Conference The NRC staff met with licensee representatives (denoted in Paragraph 1)
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| during the management meetings and at various times during the inspection and reviewed the issues discussed in this repor The staff also discussed the likely informational content of the inspection report with regard to documents or processes review by the inspectors during the inspection. The licensee did not identify any such documents / processes as proprietary.
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| l l
| | 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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| | -- -_- _ - _L |
| }} | | }} |
Similar Documents at Fermi |
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Category:CORRESPONDENCE-LETTERS
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 NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999 Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl NRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999 Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed 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 ML20217N9231999-10-15015 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40 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 NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999 Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal ML20217D5331999-10-0707 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39 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 ML20217A3261999-09-30030 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38 NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations 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 ML20216G9791999-09-24024 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37 NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999 Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys 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 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 ML20212F3241999-09-20020 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36 NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999 Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public 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 NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999 Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev ML20211Q0991999-09-0303 September 1999 Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999 Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999 Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d) ML20211G4951999-08-24024 August 1999 Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999 Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval 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 NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999 Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation 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 NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999 Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev ML20217E6181999-08-13013 August 1999 FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available 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 NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999 Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS ML20210N5451999-08-0303 August 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33 NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999 Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS ML20210J2121999-07-23023 July 1999 Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999 Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl ML20209H7211999-07-14014 July 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32 NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999 Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal 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 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 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 ML20247A3501989-07-14014 July 1989 Forwards Insp Rept 50-341/89-12 on 890225-0623.No Violations Noted 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
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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
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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.
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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.
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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
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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. 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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