ML20197J984
| ML20197J984 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/02/1998 |
| From: | Anton Vegel NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gipson D DETROIT EDISON CO. |
| References | |
| NUDOCS 9812160053 | |
| Download: ML20197J984 (34) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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REGION ilt 3
m 801 WARRENVILLE ROAD e
LISLE. ILLINOls 60532-4351 December 2, 1998 t
g Mr. D. R. Gipson.
Senior Vice President Nuclear Generation The Detroit Edison Company 6400 North Dixie Highway
' Newport, MI 48166
SUBJECT:
MID-YEAR INSPECTION RESOURCE PLANNING MEETING - FERMI
Dear Mr. Gipson:
On November 4,1998, the NRC staff held an inspection resource planning meeting (IRPM).
The IRPM provided a coordinated mechanism for Region ill to adjust inspection schedules, as needed, prior to the conclusion of the Plant Performance Review cycle in April 1999. to this letter advises you of our planned inspection effort for the next 6 months at Fermi.
This attached information is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. The rationale or basis for each inspection outside the core inspection program is provided so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature. contains a historicallisting of plant issues, referred to as the Plant issues Matrix (PIM), that was considered during the IRPM. The PIM includes only items from inspection reports or other docketed correspondence between the NRC and the Detroit Edison Company.
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9812160053 981202 PDR ADOCK 05000341 G
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. D. Gipson l l
Distribution:..
CAC (E-Mail):
RPC (E-Mail) l Project Mgr., NRR w/encls 1
l J. Caldwell, Rlll w/encls C. Pederson, Rllt w/encls B. Clayton, Rlli w/encls SRI Fermi w/encla l
DRP w/encls TSS w/encls DRS (2) w/encls Rlli PRR vy/en s f},
f, PUBLIC IE-0 w/encls Docket File /encls GREENS i
IEO (E-Mail)
DOCDESK (E-Mail) l l
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.We willinform you of any changes to the inspection plan. If you have any questions, please l
contact me at 630-829-9620.
Sincerely, t
I'
/s/ Charles Phillips for Anton Vegel, Chief g
Reactor Projects Branch 6 I
Docket No.: 50 341 License No.: NPF-43
Enclosures:
1.
Inspection Plan 2.
Plant lasues Matrix cc w/encls:
N. Peterson, Director, Nuclear Licensing P. Marquardt, Corporate Legal Department R. Gaston, Compliance Supervisor R. Whale, Michigan Public Service Commission Michigan Department of Envi onmental Quality Monroe County, Emergency Management Division Emargency Management Division, MI Departmant of State Police DOCUMENT NAME: :G:\\insppin7 fer To recolve e copy of this document,Indicete in the box *C' = Copy without ettschmentlenclosure *E' = Copy with attachment / enclosure n = no copy l
OFFICE Rlli Rlli Schweibinz;d[ Vegel yb l
NAME l
DATE 11/#98 1)l/92 OFFICIAL RECORD COPY I
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i FERMI INSPECTION / ACTIVITY PLAN I
l IP -Inspection Procedure Tl-Temporary Instruction Core - Minimum NRC Inspection Program (mandatory all plants)
Regional Initiative - Discretionary inspections
(
1 NUMBER OF TYPE OF INSPECTION NRC INSPECTION /
/
TITLE /
lNSPECTORS/
PLANNED ACTIVITY-l ACTIVITY PROGRAM AREA INDIVIDUALS DATES COMMENTS IP64704 Fire Protection 1
March 8 -12, Core 1999 IP84750 Radwaste Liquid 1
March 8 - 12, Core and Effluent 1999 Monitoring IP81700 Security 1
March 15-19, Core 1998 IP82701 EP Program 1
March 22 - 26, Core 1999 IP37550 E&TS, 6
April 12 - 30, Core IP40500 Effectiveness of 1999 and IP37001 Licensee Controls Regional in Identifying, initiative
- Resolving and Preventing Problems, and 50.59 IP84750 Chemistry 1
June 7 - 11, Core 1999
- Regional Initiative to followup on previously identified issues.
1
PLANT ISSUES MATRIX 1/23/98 Fermi Search Sorted by Date (Descending) and sMM Codes (Ascending)- Search Column = "Date*, Beginning Date = *10/1/97* ; Ending Date = '9/30/98" DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
9/18/1998 Positive IR 98016 NRC Plant 1C The inspectors concluded that the licensee maintained an effective Support intemal exposure control program. Whole Body Counting systems were appropriately used and well maintained. in-vitro bioassays were conducted as required for the torus diving work. The licensee's actions following the discovery of iodine in the main steam reheaters were considered appropriate (Section R1.2).
2 9/18/1998 Positive IR 98016 NRC Plant 1C 3A ALARA Planning and contrcis for the recirculation pump work (Section Support R4.1), drywell insulation removal and replacement (Section R4.2), torus des!udging/recoating and strainer replacement (Section R4.3), and refueling floor activities (Section R4.4) were considered good.
3 9/18/1998 Positive IR 98016 NRC Plant 1C 3A Radiologica postings and controls were well maintained and associated Support surveys were well performed. During walkdowns, the inspectors observed good work practices and observed no significant, radiological impediments to routine work. However, one worker was observed performing an improper whole body frisk, and some problems were identified v>ith radiological access control between the Reactor and Turbine Buildings and with workers frisking after leaving the torus and drywe!! work areas (Section R2.1).
4 9/18/1998 Positive IR 98016 NRC Plant 3A Access to high, locked high and very high radiation areas was well Support controlled and associated keys were properly issued and accounted for by RP staff. One problem with housekeeping and scaffold material condition was identified inside the waste clarifier room, a posted Locked High Radiation Area (Section R2.2).
5 9/18/1998 Positive IR 98016 NRC Plant 3A 1C RFO6 activities were well planned and utilized effective ALARA controls.
Support Accrued dose was consistent with completed work including emergent activities. Shielding and scaffolding support work was well conducted.
Workers exhibited good work practices and Radiation Protection (RP) management and technicians' work oversight was effective (Section R1.1).
Page 1 of 30
PLANT ISSUES MATRIX 1 /23/98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* ; Beginning Date = *10/1/97* ; Ending Date = "9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 6
8/5/1998 NCV IR 98005 Licensee Engineering 4C Based on the information developed during the inspection, and consideration of the information provided in the May 6,1998, meeting, the NRC determined that a violation of NRC requirements occurred. A detailed description of the circumstances resulting in the volation is described in inspection reports 98005 (DRS) and 97011(DRS). After review of the information provided during the May 6,1998 meeting, Region ill determined that the three apparent violations for failure to conduct adequate response time testing were the direct result of an inadequate 10 CFR 50.59 evaluation. The NRC acknowledged that the licensee identified the inadequate 10 CFR 50.59 evaluation in March 1997, and reported the issue to the NRC as required. Additionally, the NP.C finds the corrective actions, as documented in LER 97006 and as communicated at the May 6,1998 meeting, acceptable. Accordingly, the NRC dispositioned this non-repetitive, licensee-identified and corrected violation as a Non-Cited Violatioo, consistent with Section VII.B. i of the Enforcement Policy. EA 98-201 7
8/3/1998 Positive IR 98012 NRC Engineering 1A Fuel receipt activities were well-coordinated requiring the cooperation of several station groups. Fuel receipt activities involved inspections of multiple fuel shipments over an extended period of time and were conducted in accordance with established procedures. Emergent equipment issues were handled in an effective manner. Corrective actions for previously identified fuel handling issues were effectively implemented. (Section E2.1)
Page 2 of 30
= - -
PLANT ISSUES MATFilX
"' 3'98 Fermi Search sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date* ; Begirnng Date = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 8
8/3/1998 eel IR 98012 NRC Operations 1A 3A The inspector concluded that operators in the control room did not perform a required surveillance to verify offsite power supply availability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> subsequent to declaring Combustion Turbine Generator (CTG) 11 inoperable. Specifically, Surveillance Requirement 4.8.1.1.1 requires operators to check the availability of other offsite power sources within one hour when either an Emergency Diesel Generator or CTG 11 are declared inoperable. Instead, after control room operators repositioned the CTG local Mark V contro!!er to the AUTO position, rendering the CTG 11 auto-start feature inoperable from the control room and the remote shutdown panel, Surveillance Requirement 4.8.1.1.1 was not performed for a 90 minute period. Several personnel errors were contributors to this event. These errors included the failure to log the surveillance such that an automatic timing feature was not used and the 4
failure to perform a peer check. Of particular concem was the lack of team work in the control room to ensure that the appropriate Technical Specification actions were performed. This is the third failure to conduct the Surveillance Requirement 4.8.1.1.1 within a one year period. This repetitive failure is considered a violation of 10 CFR 50, Appendix B, Criterion 16, " Corrective Action." However, because the licensee was in the process of determining appropriate actions to address this violation at the end of the inspection period, this item is being tracked as an eel.
(Section 01.3) 9 8/3/1998 Negative IR 98012 NRC Operations 1A SA The fouling of the Reactor Building and Main Turbine Generator Lower Lube Oil Cooler heat exchangers due to Zebra Mussel infestation had an impact on plant operations. In some cases, heat exchanger fouling due to Zebra Mussel infestation caused Technical Specification limits to be approached. The licensee's corrective actions included cleaning the heat exchangers, reducing service water flow, and use of a chemical treatment. Also, flushing of a post accident sampling system line caused some changes to occur in reactor system parameters. Control room operators did not identify the reasons for the changes in reactor system parameters due, in part, to a lack of sufficient procedural.nformation and inadequate communications between chemistry personnel and the operations shift crew. In addition, not all the operators were trained to recognize the changes to reactor system parameters when a post accident sample was in progress. (Section O1.1)
Page 3 of 30
PLANT ISSUES MATRIX
"' 3'98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date*, Beginning Date = *10/1/97*
Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 10 8/3/1998 Positive IR 98012 NRC Operations 1B Control room operators were quick to respond to an unexpected power transient caused by a secondary plant oscillation. An operator manually scrammed the reactor following an unexpected power transient. Operator response was good and all systems responded as expected. The cause of the transient was determined to be a loose muffler in the No. 4 turbine throttle control valve. Station managements' decision to operate with the No. 4 turbine throttle control valve closed was appropriate. (Section O12) 11 8/3/1998 Negative IR 98012 NRC Operations 1C The inspector concluded that current station procedures, in some cases, contained insufficient information and inconsistencies that precluded operators from verifying proper emergency diesel generator (EDG) fuel oil system operation. Further evaluation is needed to determine the appropriate method to verify proper EDG fuel oil system operation.
(Section 08) 12 8/3/1998 Negative IR 98012 NRC Plant 1C 3B Security personnel did not open doors to the Fermi 1 facility in a timely Support manner prohibiting station personnelin the area from immediately obtaining shelter during a severe weather event. Contributing to the event was a lack of training on the task to open doors remotely using the Owner Control Area security system. (Section P8) 13 8/3/1998 Negative IR 98012 NRC Maintenance 3A The inspector concluded that adequate controls were in place to ensure the proper storage of materials that could be used in safety-related applications. Monthly walkdowns were not thorough enough to identify discrepancies in foreign material excludon control. (Section M8) 14 8/3/1998 Positive IR 98012 NRC Maintenance 2B The inspector concluded that maintenance on the EDGs was conducted in an appropriate manner. Good oversight was provided by station management, supervisory, and quality assurance personnel.
Coordination with station work groups including engineering was good.
Infrequently performed maintenance tasks were performed well.
Emergent items were handled in an efficient manner. A trip of the EDG was caused by a loss of field during post maintenance testing of EDG-
- 13. During post maintenance testing runs following removal and replacement of the govemor actuator, problems with controlling EDG frequency and speed were observed. Corrective action included replacement of the govemor actuator assembly (EG-B) and the electronic control box (EG-Ah (Section M1.2)
Page 4 of 30
PLANT ISSUES MATRIX 11/23/98 Fermi Search sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date* ; Beginning Date = *10/1/97*, Ending Date = '9/30,98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 15 8/3/1998 Negative IR 98012 NRC Plant 2B The inadvertent drop of contaminated metal from an elevated low surface Support activity container was caused by a shift in the center of gravity of the contents. The incident was of concem due to potential radiological and personnel safety consequences. Contributing to the event was less than adequate rigging and lack of specific training on the H style beam assembly, (Section E8).
16 8/3/1998 Negative IR 98012 NRC Maintenance 2B The surveillance procedures used to test fire door alarm functions and safety-related batteries contained insufficient information and inconsistencies. However, no adverse impact was identified as a result of the procedure discrepancies. (Section M3.1) 17 8/3/1998 Positive IR 98012 NRC Engineering 4C Replacement motor control center compartments containing thermal overload relays were installed in safety-related applications for the residual heat removal service water system. The vendor's acceptance testing method for the thermal overload heater relays was questioned and determined to be acceptable. The licensee's decision to require that other motor control centers be tested using station procedures was conservative. (Section E1.1) 18 8/3/1998 IR 98012 NRC Plant SA SB SC The licensee's corrective actions were broad and comprehensive to an Support event that resulted in the release of a contaminated tool bag to the owner i
controlled area. Identification, reporting, and the investigation of the event were prompt and thorough. (Section R1.1) 19 7/19/1998 LER LER 98004 Licensee Operations 1B Manual Scram in Response to Reactor Power Fluctuations 20 6/18/1998 Positive IR 98008 NRC Operations 1A 1B Control room operators were observed to respond in a controlled manner to identified problems with the feedwater and recirculation speed control systems. Operators also responded in a conservatrve manner to steam flow and reactor power oscillations, and facilitated replacement of the scram pilot solenoid valves. (Section 01.1)
Page 5 of 30
PLANT ISSUES MATRIX
" /23/98 Fermi Search Sorted t;f Date (Descending) and SMM Codes (Ascending): Search Column = *Date* ; Beginning Date = *10/1/97*. Erdng Date = '9/30G8*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 21 6/18/1998 Positive IR 98008 NRC Operations 18 48 5B The inspectors observed good operator response in controlling unexpected steam flow and power oscillations in the primary coolant system. The condition was apparently caused by unstable steam flows in balance of plant equipment complicated by competing control system responses. Engineering assistance and vendor support resulted in timely investigation of the problems. The operators were provided with instructions on how to respond to the recurrence of power oscillations.
(Section 01.3) 22 6/18/1998 Positive IR 98008 NRC Plant 1C 3B The emergency response organization received good training value from Support periodic site drills. Scenarios challenged all aspects of emergency 4
response, although the inspectors identified one case where unrealistic simulation was provided for hydrogen generation inside containment as a result of simulated fuel damage. Engineering support personnel did not always question the reasons behind reports, and as a result spent time trying to understand unexpected plant conditions. (Section P1.1) 23 6/18/1998 Negative IR 98008 NRC Maintenance 2B The inspectors identified that the licensee performed a hydrogen recombiner heater resistance check before completing the heater and controller functional test. The Technical Specifications implied a test sequence to successfully complete the survei!!ance. The licensee agreed and reperformed all testing after completing corrective maintenance on the heater controller. (Section M1.3) 24 6/18/1998 Positive IR 98008 NRC.
Maintenance 2B 1C 5B The inspectors concluded that the licensee successfully addressed several problems identified during a 1997 TBHVAC system outage. The licensee appropriately performed a safety evaluation and the UFSAR was revised to address elevated temperature effects on safety-related equipment during normal plant operation. (Section M1.2) 25 6/18/1998 Positive IR 98008 NRC Plant 28 2A The spent fuel pool cleanout project was planned in detail, giving high Support priority to "As Low As Reasonably Achievable" considerations in the methods used. This led to several innovative techniques for handling and packaging the radioactive material Supervision, contractor control, administrative controls, log keeping, and communications with operations personnel were significantly improved. Problems were promptly communicated and resolved in a formal manner. (Section R1.1)
Page 6 of 30
PLANT ISSUES MATRIX 11/23/98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending). Search Column = *Date' ; Beginning Date = *10/1/97 Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 26 6/18/1998 Positive IR 98008 NRC Maintenance 28 3A Two outages performed to replace control rod SSPVs were planned and executed in a highly coordinated manner. Maintenance teams from each work group performed a complex sequence of tasks on six control rods simultaneously in a quality manner. Operations and radiation protection personnel provided close support, ensuring prompt equipment restoration and testing. The outages were scheduled so that experience was gained during the first outage on peripheral rods, so that the subsequent work on inner rods, which were time-sensitive, could be performed more smoothly. (Section Mt.4) 27 6/18/1998 Negative IR 98008 NRC Maintenance 3A 2A Some weaknesses in the conduct of maintenance of activities was noted during the period, however, the majority of the activities were conducted in an acceptable manner., Equipment problems with the recirculation and feedwater control systems had minor impact on normal plant operations. Investigation and repair of these systems continue. (Section M1.1) 28 6/18/1998 Positive IR 98008 NRC Engineering 38 4C Training for performing safety evaluations was significantly improved by providing a broad understanding of the licensing process and licensing basis for the plant. Trainee feedback was positive, resulting in many requests for the training from outsde the group requiring the training.
However, discussions indicated that the site was inconsistent in its implementation and documentation of the 10 CFR 50.59 process.
(Section E5.1) 29 6/18/1998 VIO/SL-IV IR 98008 NRC Operations 4C The inspectors concluded that the licensee failed to conduct a 10 CFR 50.59 evaluation prior to defeating control room annunciators that were described in the Updating Final Safety Analysis Report (UFSAR). The licensee's procedures allowed control room annunciators described in the UFSAR to be defeated by the operators without determining whether or not a safety evaluation was required. The inspectors concluded that the licensee's corrective actions were prompt, oroad, and comprehensive. A no response violation was issued. (Section 01.2) 30 6/18/1998 Positive IR 98008 NRC Plant 5A SB SC Due to a conservative receipt inspection methodology, the licensee was Support able to identify that a shipping cask received from the disposal site contained a highly radioactive pin from a control rod blade which had been inadvertently overlooked during a previous shipment. The licensee did a good job in identifying the material and communicating with federal and state agencies to resolve the issue. (Section Rt.1)
Page 7 of 30
PLANT ISSUES MATRIX ii/23m8 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascerdng): Search Cdurnn = "Date*, Beginning Date = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 31 6/12/1998 Positive IR 98011 NRC Plant 1C The training, procedures, and implementation of the radioactive materials Support transportation program remained effective, as shipping documentation and inspector observations confirmed that the plant met regulatory requirements (Section R1.2).
32 6/12/1998 Positive IR 98011 NRC Plant 1C The program to sample and analyze waste streams for the determination Support of radionuclide scaling factors remained effective and enabled the staff to appropriately classify radwaste for shipment. However, issues with scaling factor determinations for two radionuclides were identified (Section R1.4).
33 6/12/1998 Positive IR 98011 NRC Plant 1C 2A The implementation of the solid radwaste program regarding radwaste Support processing, storage, and shipment continued to be effective. In particular, the dewatering equipment was highly reliable and the On Site Storage Facility surveillances were comprehensive (Section R1.3) 34 6/12/1998 Positive IR 98011 NRC Plant 1C 3A The radiological controls effectively maintained a reasonable dose for the Support spent fuel pool clean out project. The radiation protection staff correctly anticipated and controlled airbome radioactivity to minimize the potential for intemal dose (Section R1.1).
35 6/12/1998 Positive IR 98011 NRC Plant 1C 3A The training self-assessment was comprehensive and identified areas for Support improvement. The licensee's audits and reviews of vendor services were thorough, performance-based, and identifieo significant problems which impacted shipping operations. The radiation protection staff's responses to these vendor problems were appropriate (Section R7.1).
36 S/11/1998 Positive IR 98010 NRC Plant 1C Overall performance during the 1998 Emergency Preparedness exercise Support demonstrated that emergency plan implementation activities met regulatory requirements. (Section P4.1.c) 37 6/11/1998 Positive IR 98010 NRC Plant 1C 3A Performance of Emergency Operations Facility staff efficiently assemb!ed Support to perform their duties. Status boards were well maintained and legible.
Communications to onsite emergency response facilities and offsite agencies were frequent. Notifications to the State and local agencies contained appropriate protective action recommendations. (Section P4.1.c) 38 - 6/11/1998 Positive IR 98010 NRC Plant 1C 3A Overall performance in the Control Room Simulator was effective and Support professiona!. Plant emergency announcements were very informative.
Good communications and teamwork were evident. (Section P4.1.c)
Page 8 of 30
i PLANT ISSUES MATRIX
" /23/98 Fermi Search sorted by Date (Descending) and sMM Codes (Ascending): Search Column = *Date" ; Beginning Date = *10/1/97*, Erxfing Date = "9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION j
39 6/11/1998 Positive IR 98010 NRC Plant 1C 3A The Technical Support Center staff's performance was effective.
(
Support Briefings were concise. The emergency action level, protective action recommendation, and emergency operating procedure flowcharts were proactively reviewed. Priorities were properly established and revised as plant conditions changed. (Section P4.1.c) 40 6/11/1998 Positive IR 98010 NRC Plant 1C 3A The Operational Support Center's staff performed well in coordinating Support activities and maintaining control of the inplant teams. Priorities were clearly communicated. Facility and inplant team briefings were efficient and detailed. (Section P4.1.c) 41 6/11/1998 Positive IR 98010 NRC Plant 1C 5A Self-critiques following termination of the exercise were thorough, self-Support critical, and included inputs from exercise participants as well as controllers. (Section P4.1.c) 42 5/20/1998 Positive IR 98301 NRC Operations 1A 3A 3B Control Roorr. operators displayed proper professionalism and demonstrated an appropriate level of attentiveness to the operating panels and were knowledgeable of plant conditions. (Section O1.1) 43 5/20/1998 Negative IR 98301 NRC Operations 1C The fcensee's knowledge of the examination development guidelines, attention to detail during examination development, and the aDility to develop technically accurate JPMs and written examination material in accordance with the examination guidelines was considered satisfactory.
Several deficiencies were identified by the examiners, the most significant being the need to increase the difficu!!y level of the examination. (Section 05.2) 44 5/20/1998 Negative IR 98301 NRC Operations 1C Several procedures reviewed by the examiners contained weaknesses.
The weaknesses were considered an inspection followup item. (Section 03) 45 5/20/1998 Negative IR 98301 NRC Operations 1C 3B The high failure rate on the examination suggested that the applicants were not weII prepared for the examination. Control and supervision of reactivity manipulations was considered a strength. SRO ability to determine protective action recommendations and the ability to review and use the dose projection report were considered Administrative JPM weaknesses. Applicant performance in annunciator response, event diagnosis, command and control, and the use of and familiarity with operating procedures needed improvement. (Section 05.4)
Page 9 of 30
PLANT ISSUES MATRIX
" /23/98 Fermi Search Sorted by Date (Descending) and sMM Codes (Ascending): Search Column = 'Date* ; Beginning Date = *10/1/97*, Ending Date = "9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 46 5/20/1998 Negative IR 98301 NRC Operations 1C 3B Training staff members demonstrated a lack of attention to detail when they failed to properly prepare the simulator for administration of the operating test. The simulator did not always respond correctly during the examination. Examiners were able to complete the examination and properly evaluate applicants despite the simulator problems. (Section 05.3) 47 5/20/1998 Negative IR 98301 NRC Operations 1C 3B Four Reactor Operator and two Senior Reactor applicants passed their examinations and were issued operator licenses. Two Reactor Operator applicants failed the written examination, one Seninr Reactor Operator applicant and two Reactor Operator applicants failed the operating examination, and one Senior Reactor Operator applicant failed both the written and operating examinations.
48 5/20/1998 Negative IR 98301 NRC Operations 2A 1C SA Twice, the licensee's simulation facility failed to operate. The simulator froze once for no apparent reason during the performance of the simulator scenario examination. On another occasion, during the examination validation week, the simulator failed when the licensee attempted to back t'ack the scenario to review a system response to a malfunction. (Section O5.6) 49 5/15/1998 Strength IR 98009 NRC Plant 1A 1C The security force performance improved significantly since the previous Support inspection and was considered a strengtn (Section S4).
50 5/15/1998 Negative IR 98009 NRC Plant 1C SC SB Security procedures and records reviewed were adequate. A weakness Suppo:1 was noted in reference to compensatory measures for certain type of alarms, and the method of evaluation of the cause for alarms (Section S3).
51 5/15/1998 Positive IR 98009 NRC Plant 2A 1A Facilities and equipment observed were operational and well maintained.
Support Two Vehicle Barrier System (VBS) gates required installation of a mechanism that increased the effectiveness of the barriers. One of the VBS gates was compensated for an excessive period of time (Section S2).
52 5/15/1998 Positive IR 98009 NRC Plant SA Security self-assessment efforts were effective and offered flexibility Support (Section S7).
Page 10 of 30
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PLANT ISSUES MATRIX
"'2 'S8 Fermi Search Sorted by Date (Descending) and sMM Codes (Ascending): Search Column = *Date* ; Beginning Date = *10/1/97*. Erdng Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 53 4/27/1998 Positive IR 98006 NRC Operations 1A Operators maintained a professional atmosphere in the control room.
IR 98006 Operators were observed to be generally focused, and peer checking was frequently performed. A new policy was implemented to conduct heightened level of awareness briefings for the three most significant evolutions each shift, and to conduct a c-itique of one of them. Despite generally good operator performance, one isolated operator error occurred which resulted in the tripping of both fuel pool cooling pumps.
(Section O1.1) 54 4/27/1998 Positive IR 98006 NRC Operations 1A SA Operators aggressively identified equipment concems and assisted in the prompt resolution of problems. Operators responded in an appropriate and conservative manner to each problem encountered. (Section O1.2) 55 4/27/1998 Positive IR 98006 NRC Maintenance 2A Based on material condition assessment, the inspectors concluded that equipment is being properly maintained. The licensee was effective in identifying and documenting equipment problems. Maintenance resources were appropriately focused on systems specified as important within the maintenance rule. The average age of work requests and the number of control room deficiencies were slightly high, but the work that had not yet been completed was not adversely impacting plant operations. (Section M1.2) 56 4/27/1998 Negative IR 98006 NRC Engineering 2B 4B SA The inspectors concluded that the two primary programs u'J!ized by the licensee to track system performance, namely the System Health Report and the Maintenance Rule Programs, did not accurately reflect system performance for the hydrogen injection system. Licensee management attention was closely focused on system reliability and efforts to improve the system, but the licensee did not question the " good' system performance reported by these tracking systems. In response to the inspectors' identifying this disparity, the licensee was reclassifying the system in both programs. (Section E2.2)
Page 11 of 30
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PLANT ISSUES MATRIX 11/23/98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): search Column = *Date" : Beginning Date = *10/1/97* ; Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 57 4/27/1998 Positive IR 98006 Licensee Maintenance 3A 3B The inspectors observed that mai.itenance work was performed within the bounds of the work instructions. Work instructions and documentation were genera!!y complete and accurate. Technicians were knowledgeable of their assigned tasks. Pre-job walkdowns were performed sufficiently in advance of the work, and were generally effective in enabling the licensee to identify and avoid potential problems.
One concem was identified by the inspectors inv?!ving inadequate fall protection at a job site. In addition, a concem wa. identified with inconsistent valve stroke time testing. (Section M1.")
58 4/27/1998 Negative iR 98006 NRC Maintenance 3A 3B Local indications on four of the six average power range monitor (APRM) channels were adjusted improperly during a calibration by a trainee due to inadequate oversight. The error was identified by a nuclear engineer not directly involved with the calibration. The inspectors identified procedural weaknesses, including lack of a requirement to verify that power level was adjusted correctly and inconsistencies in verification methods between the reactor engineering APRM calibration procedure and a similar APRM calibration procedure performed by maintenance personnet (Section M1.3) 59 4/27/1998 Positive IR 98006 NRC Engineering 48 During safety system outages and surveillance testing, inspectors observed that system engineers were frequently monitoring work performance and progress. System engineer involvement was less prevalent for non-safety systems. (Section M1.1) 60 4/27/1998 Positive IR 98006 NRC Maintenance SA 5B The inspectors concluded that the independent Safety Engineering Group (ISEG) assessment of switchyard programs was both broad and detailed. The assessment report described numerous deficiencies, incomplete corrective actions from switchyard events of the past year, and numerous recommendations for areas to improve. The report, and ISEG involvement in site activities overall, represented an improvement in ISEG effectiveness. (Section M7.1) 61 4/27/1998 Positive IR 98006 NRC Engineering SA 58 SC System engineering personnel provided close support during
~
trouble:. hooting and investigations of several significant equipment problems. The 24-hour coverage helped minimize the time spent in limiting condition for operations action statements and provided for timely resolution of the problems. When needed, Generic Letter 91-18 evaluations were appropriately performed. (Section E2.1)
Page 12 of 30
PLANT ISSUES MATRIX M/23/98 Fermi search sorted by Date (Descending) and SMM Codes (Ascending): search Column = *Date*. Beginning Date = *10/1/97*. Ending Date = "9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 62 4/27/1998 Positive IR 98006 NRC Engineering 5B SA The inspectors concluded that the licensee's effectiveness followup assessment of the safety evaluation process was adequate and detailed.
Continued attention was needed to address previously identified deficiencies, but the inspectors noted improvements in safety evaluation quality. Recent improvement efforts appeared to be effective in this area. (Section E7.1) 63 4/27/1998 Negative IR 98006 NRC Engineering SC The inspectors concluded that the licensee did not permanently correct a l
deficiency in a dedicated shutdown procedure that could have caused the inadvertent draining of the condensate storage tank. This could have potentially impacted the ability to bring the reactor to a cold shutdown condition during a postulated fire as defined in 10 CFR 50, Appendix R.
Further evaluation was needed to determine if additiona! discrepancies exist within the dedicated shutdown procedure and the licensee's corrective actions. (Section E1.1) l 64 4S/1998 Positive IR 98007 NRC Plant 1A 1C 2A The low number and the remote location of hot spots throughout the Support facility indicated a continuing strong ALARA emphasis. However, a number of hot spots which were either de-posted over the past three years or which no longer existed were stiti listed in the hot spot database as open. Taken together with other documentation inconsistencies, the oversight of the hot spot database was weak (Section R1.3).
65 4/9/1998 NCV IR 98007 NRC Plant 1A 1C 2A The programs for radiological surveys, postings, and labeling were well Support implemented. Controls of contamination, airbome radioactivity, radiation dose, radiation sources, and radworker practices were effective. No radiological impediments, materiel condition, or housekeeping issues were identified in any areas of the faci!rty. One Non-Cited Violation for the failure to place an access control gate at the entrance to a contaminated radiation arca was identified (Section R1.2).
66 4/9/1998 Positive IR 98007 NRC Plant 1A 1C 2A The program for control of access to high radiation and locked high Support radiation areas (HRA/LHRA) was well implemented. All keys were contro!!ed, issued, and accounted for appropriately by the RP staff. The locked doors were checked daily and RP staff provided all the required controls for NRC inspector entries into HRA/LHRAs. No materiel condition or housekeeping issues were identified in these areas (Section R1.1).
Page 13 of 30
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PLANT ISSUES MATRIX
"' 3'98 Fermi Search sorted by Date (Descending) and sMM Codes (Ascending): search Coturnn = *Date* ; Begoning Date = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 73 3/16/1998 Negative IR 98003 NRC Maintenance 1C 28 An inadvertent load F ad on Safety Bus 72E was caused by an unclear surveillance test procedure step. Inadequate reviews of the procedure revision and a lack of questioning attitude by maintenance workers contributed to the event. A violation was identified for an inadequate procedure. The licensee's investigation was prompt and thorough.
(Section M3.2) 74 3/16/1998 Negative IR 98003 NRC Maintenance 2A Residual Heat Removal Pump B developed multiple indications of unusual wear. The inspectors expressed concem about the pump's long term operability when the licensee evaluated the motor as acceptable.
Subsequently, tM decision was made to replace the motor. (Section M2.1) 75 3/16/1998 Positive IR 98003 NRC Maintenance 2B Plant management discussed three instances of potential preconditioning, idantified by the NRC and licensee personnel, with plant staff to further sensitize personnel to potential preconditioning issues during maintenance and testing. The licensee intended to evaluate the response to specific issues after creation of a station policy on the subject based on industry and regulatory practices in this area. A systematic review of maintenance and testing practices against this policy was also planned. (Section M1.2) 76 3/16/1998 Negative IR 98003 NRC Maintenance 28 2A The inspectors concluded that the licensee's failure to provide adequate IR 98003 instructions to ensure proper configuration control of switchyard electrical components resulted in the installation of a protective relaying circuit card with an improper configuration. Switchyard configuration control was assigned to an offsite organization, which did not use the station's configuration control program. The licensee's corrective actions were comprehensive, including an extensive verification of switchyard component configuration. (Section M3.1) 77 3/16/1998 Positive IR 98003 NRC Maintenance 28 2A The licensee effectively addressed emergent equipment problems identified during the forced cutage and the subsequent plant startup. A good questioning attitude was demonstrated during the replacement of the control room chlorine detector, but inadequate preparation for the work resulted in the inability to complete the job after entering a limiting condition for operation. A motor-operated potentiometer was not property adjusted prior to installation, resulting in a challenge to the emergency diesel generator and delays in retuming it to service. (Section M1.1)
Page 15 of 30
PLANT ISSUES MATRIX
'1/23/98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Scarch Column = *Date* ; Beginning Date = *10/1/97* : Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP l SMM CODES DESCRIPTION 78 3/16/1998 Negative IR 98003 NRC Maintenance 2B 38 The inspectc,rs identified *. hat maintenance personnel incorrectly concluded that es-fon.~! relay timing data for an alarm circuit associated with the scram dischcae instrument volume could be copied from a previously performed test. The relay was repisced as part of regularly scheduled preventive maintenance. The old relay was successfully tested after the inspectors questioned the lack of as-found testing. The omission was caused by a confusing work package step. (Section M3.3) 79 3/16/1998 Positive IR 98003 NRC Engineering 4B 2A The inspectors concluded that the licensee acted in a conservative manner and declared both systems of low pressure coolant iniection inoperable when it was discovered that manual operator action was required for proper low pressure coolant injection actuation. The conditions resulted in some complications in the conduct of surveillance testing. (Section E2.1) 80 3/16/1998 Negative IR 98003 NRC Engineenng 4B 2A The inspectors concluded that slow turbine valve stroke times, which caused higher than design turbine speeds during a load rejection, were the result of corrosion products found in the EHC system from in leakage in the turbine hydraulic oil coolers. Th;s condition went unnoticed for a longer period of time because of the reduced frequency of valve testing.
The inspectors were concemed with the corrective actions to apply a graphite lubrication in a high temperature and moist environment, since ihat lubricant would lose its effectiveness over time in that environment-(Sectiori E2.2) 81-3/1t/1998 NCV IR 98J03 NRC Engineering 48 SB The licensee appropriately conducted a thorough resw of all inputs to -
and calculations used to support the core thomal power computation. No other errors were identified. A non-cited vioiation was identified for having exceeded the licensed core thermal power at one or more tines in the past by a small fraction of a percent. (Section E8.1)
~
Page 16 of 30
PLANT ISSUES MATRIX
'1/23/98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Sear 64 Colurnn = *Date* ; Beginning Date = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SxLP SMM CODES DESCRIPTION 82 3/5/1998 Licensing TELEPHONE NRC Engineering 4C Problems Encountered in Fermi Licensing Submittals CONFERENCE MEMO The original submittal for valve relief requests VR-63 & VR-64 (NRC 0001) did not conform with the guidance of NUREG-1482, AGuidelines for Inservice Testing at Nuclear Power Plants,@ April 1995. No attemative testing was proposed short of the current exercise aithough the NUREG specifically stated that simply verifying that the valves function is not an acceptable attemative. A revised submittal was prepared after the NRC raised this issue.
83 3/5/1998 Licensing TELEPHONE NRC Engineering 4C Problems Encountered in Fermi Licensictg Submittals CONFERENCE MEMO The recirculation motor-generator set stops amendment (NRC-97-0037) contained a substantive word omission in the no significant hazards consideration discussion. The response to question 2 originally read, in part The proposed... change does result in any changes to the design...or operation of the plant...
84 3/5/1998 Ucensing TELEPHONE NRC Engineering 4C Problems Encountered in Fermi Licensing Submittals CONFERElCE MEMO The power range neutron monitoring amendment was missing an affected technical specification page (NRC-97-0105). The missing page was 3/4 3-44a which contains control rod block setpoints. The contents of the section on that page for rod Hocks associated with reactor coolant system recirculation flow were to be removed or ralocated.
85 3/5/1998 Licensing TELEPHONE NRC Engineering 4C Problems Encountered in Fermi Licensing Submittals CONFERENCE MEMO The original submittal for the Cycle 6 minimum critical power ratio (MCPR) amendment (NRC-96-0075) failed to provide adequate information to support the MCPR Safety Limit adjustment for single loop operation. Previous single loop adders for this same fuel were 0.01. In the Cycle 6 submittal this value was changed to 0.02. The staff requested and received additional information to explain this change.
Page 17 of 30
PLANT ISSUES MATRIX
"'2"8 Ferm.
Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = "Date*, Beginning Data = *10/1/97*, Ending Date = "9/30'98" DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 86 3/5/1998 Ucensing TELEPHONE NRC Engineering 4C Problems Encountered in Fermi Licensing Submittals CONFERENCE MEMO After Project Manager presented the problems that existed in some recent submittalo, the licensee explained steps that it has taken to ensure high quality submittals. The licensee entered the problems into its corrective action program for evaluation and action. A small team was formed for the evaluation. The six submittats from the licensee dated January 28,1998, received extra reviews by editors and technical personnel. The licensee has also developed a template intended to guide authors through the development of a submittal that supplies all of the necessary information in the correct format. It appears that the actions described should correct the problems that were encountered. The NRC will continue to assess the quality of submittals in the future.
87 3/4/1998 VIO/SL-IV IR 97011, EA 97-NRC Engineering 4A The licensee failed to identify an apparent unreviewed safety question in 479 that a possibility of equipment malfunctions due to inadequate emergency equipment cooling water flow was not previously analyzed in the Updated Final Safety Analysis Report (UFSAR), despite the need for operator actions to rectify the situation.
88 2/26/1998 VIOiSL-IV IR 98004 NRC Operations 1C The complex evolution involving fuel inspection was performed without an appropriate level of administrative controls. The work request used to control the evolution was inappropriate to the circumstances for which a violation was issued. The inspectors concluded that the hmitations of using a work request contributed to unclear roles and responsibilities for operators and other supervisory personnel. Licensee corrective actions for this problem were appropriate and comprehensive. (Sr, tion O3.1) 89 2/26/1998 Negative IR 98004 NRC Operations 1C The inspector concluded that operators were unfamiliar with the prerequisites required to be performed prior to granting permission to move fuel and conduct fuel inspection activities. This appeared to be due primarily to a lack of administrative control and documentation. In addition, control room operators were not as involved in the movement and inspection of fuel as they would be during refueling activities.
(Section 01.1)
Page 18 of 30
PLANT ISSUES MATRIX
"/23sa Fermi Search Sorted by Date (cescending) and SMM Codes (Ascending): Search Column = *Date' ; Beginning Data = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP l SMM CODES DESCRIPTION 90 2/26/1998 DEV 1R 96004 NRC Operations 1C Operators did not question the practice of storing fuelin the fuel 4
preparation machine (FPM) ovemight, even though this practice was not specified in the goveming work request or discussed during shift briefings. When tre inspector questioned the practice, the nuclear shift supervisor acted conservatively to place the bundle in question back in the normal storage rack until the issue could be further evaluated. The a
licensee intended to store fuel ovemight in the FPM, but did not document the intent, did not brief it during the shift briefing with plant operators, and did not evaluate the acceptability of storage of spent fuelin the FPM prior to its use. A deviation from a regulatory commitment was identified.
(Section O1.2) 91 2/26/1998 Positive IR 98004 NRC Plant 3A The inspector observed that radiation protection personnel were closely Support involved in all phases of the preparation and execution of the fuel inspections. Workers were observed to follow good radiation worker practices. The inspectors observed good foreign material controls and tool accountability during the work. (Section R1.1) 92 2/26/1998 Negative IR 98004 NRC Engineering 3B The inspector concluded that the licensee had an informal training and.
qualification process with respect to refueling and associated work tasks.
No specific deficiencies related to training activities were identified and workers were observed to be knowledgeable of the work activities.
However, knowledge weaknesses were noted in emergency response to a fuel handling mishap. (Section E5.1) 93 2/26/1998 VIO/SL-IV IR 98004 NRC Engineering 3B 1C 4B The inspector concluded that the licensee did not analyze for or implement adequate criticality controls for fuel bundle disassembly and handling of multiple ftsi rods simultaneously, which was considered a violation. The condition was briefly considered and di mositioned informally without using any documented analysis, since none was available onsite. Subsequent analyses demonstrated that no potentially critical configuration existed. However, the first of these analyses was not available for more than a month after the fuel inspection. (Section E3.1) 94 2/26/1998 Negative IR 98004
'NRC Engineering 4C The inspector identified a lack of formol design control rneasures and documentation for the FPM's upper travel limit and radiation monitor interlock. No regulatory requirements were violated. (Section E3.2) 95 2/20/1998 LER LER 98002 Licensee Maintenance 2B Inadvertent Load Shed of ESF Bus 72E During Performance of Surveillance Test Resulting in ESF Acutations Page 19 of 30
E PLANT ISSUES MATRIX 11/23/98 Fermi Search Sorted by Date (Dercending) and sMM Codes (Ascending): Search Column = "Date", Beginning Date = *10/1/97*, Endinn Date = '9130/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIP110N 96 2/13/1998 Positive IR 98002 NRC Maintenance 28 The structural monitoring program was effective. Inspections adequately assessed the conditions of structures and corrective actions were initiated to correct deficiencies. (Section M1.6.b.4) 97 2/13/i998 VIO/SL-IV IR 98002 NRC Maintenance 2B The sccping determinations were appropriate for most structures.
systems, and components (SSCs) and functions. However, a weakness in the scoping process resulted in a violation in that four SSCs/ functions were inappropriately excluded from the scope of the MR program.
(Section M1.1) 98 2/13/1998 Negative IR 98002 NRC Maintenance 28 The approach to ectablishing the risk ranking for SSCs was adequate, although the downgrading of systems were not always sufficiently justified. (Section M1.2.b.2) 99 2/13/1998 Positive IR 98002 NRC Maintenance 28 Although the periodic assessment was adequate to meet the requirements of the MR, some areas were not assessed in great detailin the report. (Section M1.3) 100 2/13/1998 Positive IR 98002 Licensee Maintenance 2B The processes for assessing plant risk resulting from equipment being out-cf-service for on-line maintenance and shutdown risk management were determined to be good. The use of the initiating Events Guidance Document was considered a good additional initiative to assess the risk associated with on-line maintenance. (Section M1.5) 101 2/13/1998 VIO/SL-IV IR 98002 NRC Maintenance 2B The performance criteria for reliability and unavailability were good.
However, one isolated violation was identified conceming monitoring an SSC reliability at the system versus the divisionallevel. (Section M1.6) 102 2/13/1998 VIO/SL-IV IR 98002 NRC Maintenance 28 Several functional failures were not identified by the program process, which showed a weakness in evaluating problems for MR applicability.
Specifically, failures were not always assessed bas t on a system I
licensing basis and design functionality; and poter tiany allowing compensatory measures to satisfy the system function. Inappropriate fu anal failure determinations were also identified as a concem by the
, recent self-assessments. One violation was identified for failure to adequately monitor an (a)(1) SSC against goals. (Sections M1.6.b.1.3).
Page 20 of 30
PLANT ISSUES MATRIX
"' '88 Fermi Sr. arch Sorted by Date (Descending) and SMM Codes (Ascending): Search Coturnn = *Date' ; Beginning Date = *10/1/97*, Ending Date = '9/30/96-DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 103 2/13/1998 Positive IR 98002 NRC Engineering 4B The system engineers were experienced and knowledgeable about their systems and their responsibilities with respect to the MR. Several tools available to the system engineers were beneficial to provide support in the monitoring of system performance with respect to the MR. (Section E4.1) 104 2/13/1998 Misc IR 98002 NRC Maintenance SA 28 The recent assessments of the MR program were acceptable. The use of outside personnel provided independent insights into the MR program and added to the overall quality of the audit. (Section M7.1) 105 2/1/1998 LER LER 98001 Licensee Maintenance 2A 18 Automatic Raactor Scram due to Main Turbine Trip 106 1/5/1998 Negative IR 97016 NRC Operations 1A The inspectors concluded that power uprate testing was conducted in a coordinated manner. However, the determination of plant response at higher pcwer levels was limited in scope. The inspectors concluded that Ly not performing a detailed plant walkdown, unanticipated changes in plant conditions may have beer missed (Section O2.2).
107 1/5/1998 Posnive IR 97016 NRC Operations 1A 1C 3A The inspectors concluded that general, the operators performed well during this inspectior, period. b visibility operations were well coordinated and conducted. (Section O1.1) 108 1/5/1998 Negative IR 97016 NRC Operations 1A 2A Operators continued to accept a lower standard of available documentation, equipment labeling, and training related to switchyard equipment than for regular plant equipment. (Section O1.2.b) 109 1/5/1998 Positive IR 97016 NRC Operations 1B On December 29,1997, operators identified a feedwater controller anornaly and obtained assistance from support organizations. The licensee acted promptly to reduce power below 25 percent in order to remove the affected controller from service and avoid challenging the plant (Section O1.1.b).
110 1/5/1998 Negative IR 97016 NRC Operations 1C Two procedural weaxnesses were identified; one that delayed identification of the loss of the process computer by the operators and the other that could potentially result in missed commitments due to changes to operator round sheets. (Section 01.1) (PIM ltem dated 1/5/98, IR 97016).
Page 21 of 30
PLANT ISSUES MATRIX
" '23'98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colume = "Date*, Beginning Date = *10/1/97*, Ending Date = "9/30/98*
DATE l
TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 111 1/5/1998 Positive IR 97016 NRC Operations 1C 1A The licensee promptly identified two safety tagging errors and took appropriate imrnediate actions. The inspectors concluded that each event had minirnal safety significance. However, the inspectors weie concemed that multiple barriers designed to make safety tagging error-free were rendered ineffective by operator practices. The licensee's corrective actions included a human performance review day for all site personnel that included a detailed review of the safety tagging errors (Section 01.2).
112 1/5/1998 Negative IR 97016 NRC Maintenance 2A in general, the freeze protection program was adequately implemented; however, system design and equipment deficiencies in the turbine building ventilation and reactor building ventilation system continued to challenge operators (Section M2.1).
113 1/5/1998 Negative IR 97016 NRC Maintenance 2B The inspectors concluded that the accepted practice of disregarding gauge use restriction labels could potentially result in the introduction of foreign materialinto plant systems. Also, the use of the data from an imprecise gauge reading resulted in maasurements that were close to the alert range of the Division 2 Emergency Equipment Cooling Water pump.
The alert range testing would result in increased unnecessary testing and equipment wear. The inspecto s concluded that lack of a questioning attitude and training contributed to the event (SecCon M1.3).
114 1/5/1998 Positive IR 97016 NRC Maintenance 2B SB Maintenance workers and component engineers work effectively with system engineers and operations personnel to troubleshoot and repair the feedwater controller in an expeditious manner. (Mt.1.b) 115 1/5/1998 Negative iR 97016 NRC Maintenance 3A Two personnel errors were promptly investigated and corrective actions implemented. The licensee's planned corrective action %ded a comprehensive assessment and review of the two evem dring a human performance review day, which will include all station personnel. Neither error was safety significant, but these events indicated a continuing trend in personnel errors during maintenance activities previously documented in inspection Report No. 50-341/97013 (Section M1.2).
t Page 22 of 30
PLANT ISSUES MATRIX M/23/98 Fermi Search Sorted by Date (Descending) and sMM Codes (Ascending): Search Column = "Date', Beginning Data = *10/1/97*, Ending Data = '9/30/98*
_DATE TYPE SOURCE ID BY l l SALP SMM CODES DESCRIPTION 116 1/5/1998 Weakness IR 97016 NRC Plant 3A The inspectors concluded that the licensee performed appropriate Support surveys following changes in plant conditions, such as starting up the hydrogen water chemistry system. However, general area survey maps were not superseded when conditions on a portion of the map changed.
It was not always clear that additional survey maps needed to be reviewed (Section R3.1).
117 1/5/1998 URI IR 97016 URI NRC Engineering 4B The inspectors concluded that the licensee did not process the 10 CFR 97016-02 URI 21 notice conceming Asea Brown Boveria K-Line breakers in a timely 97C16-03 manner. This delayed an operability evaluation of breakers which were associated with multiple safety components. The inspectors were concemed that an adequate evaluation of the use of cross tie breakers was not performed prior to using maintenance crosstie breakers to supply power to Residual Heat Removal service water crosstie valves. Two unresolved items were identified pending review by the licensee (Section E2.2).
118 12/5/1n97 Negative IR 97017 NRC Operatione 1A Communications were at times informal and did not always meet management expectations for three way communication. Also, some lapse in formal controls to restrict personnel access to vital control arens in the control room was observed. (Section 01.1) 119 12/5/1997 Positive IR 97017 NRC Operations 1A Control Room operators demonstrated an appropriate level of attentiveness to the operating panels and were knowledgeable of plant conditions. (Section 01.1) 120 12/5/1997 Positive IR 97017 NRC Operations 1A 1C The licensee's continued implementation of the Operational Excellence Plan have shown improvements in the conduct of operations as noted in recent resident inspection reports. (Section 05.1) 121 12/5/1997 Weakness IR 97017 NRC Operations 3B The simulator scenarios lacked sufficient complexity. Some scenarios had no component or instrument failures following the major malfunction, and the.cenarios did not readily incorporate equipment out-of-service or -
have existing technical specification limiting conditions for operation as part of the initial conditions. (Section 05.2.1) 122 12/5/1997 Weakness IR 97017 NRC Operations 3B The excessive repetition of examination material from week to week and during remeddon re-evaluation generated questions pertaining to examination integrity. (Gections 05.3.2, O5.5)
Page 23 of 30 m 7-
PLANT ISSUES MATRIX 11/23/98 Fermi Search Sorted by Date (Descending) and sMM Codes (Ascending): Search Colurnn = *Date', Beginning Date = "10/1/P7'. Ending Data = "9/30/98*
lDATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 123 12/5/1997 Positive IR 97017 NRC Operations 3B in general, all portions of the annual requalification examination met the minimum criteria in accordance with the guidance given in NUREG 1021
" Operator Licensing Examination Standards for Power Reactors," Interim Revision 8. (Sections O5.2,05.3) 124 12/5/1997 Positive IR 97017 NRC Operations 3B The licensee's controls to revise the licensed operator requalification training program were satisfactory. (Section 05.4) 125 12/5/1997 Positive IR 97017 NRC Operations 3B The licensee's incorporation of current industry events into the operator training program.vas good. (Section 05.2.2) 126 12/5/1997 Weakness IR 97017 NRC Operations 3B in general, the requalification examination material bank contained tne minimum qualitative attribute 9 to provide an adequate evaluation of cperator skills; however, the quantity of examination material in the bank was marginal. (Section 05.2.1) 127 12/5/1997 Negative IR 97017 NRC Operations 38 1A Some knowledge and operating weaknesses were observed during the requalification examination (written and operating). The operating weaknesses included erroneous emergency classification and weak command and control. (Sections 01.2, O5.3.1) 128 12/5/1997 Weakness IR 97017 NRC Operations SC The differences between assessments and formal evaluations posed potential prcblems for meeting the requirements of an annual evaluation of licensed operators. The licensee's procedure allowed the use of the same failed simulator scenario for the remedial re-evaluation fo!!owing an unsatisfactory assessment. (Section 05.5) 129 11/7/1997 IR 97001
"* SALP 16 ENDS *"
130 11/7/1997 Positive IR 97014 NRC Operations 1A Both startup and shutdown evoluti0ns were performed smoothly and without error. Licensed operator trainees in the control room were properly supervised and contributed positively to crew performance.
Briefings were frequent and effective. (Section O1.2) 131 11/7/1997 Positive IR 97014 NRC Operations 1A The reactor vessel pressure test at the cor.clusion of the mid-cycle outage was performed expeditiously in a coordinated and controlled manner. Preparations, particularly the use of the simulator, were effective in minimizing the time spent with shutdown cooling secured during a relatively high decay heat condition. However, the inspectors concluded that distractions from the test were not effectively minimized in the control room. (Section O1.3)
Page 24 of 30
PLANT ISSUES MATRIX 11/23798 i
Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = Tate *, Beginning Date = *iO/1/97* ; Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY !!
SALP SMM CODES DESCRIPTION 132 11/7/1997 Positive IR 97014 NRC Operations 1A The inspectors concluded that operators continued to exhibit improved performance in monitoring plant conditions. Personnel on rounds continued to be effective in identifying and reporting problems.
Supervisory presence in the field for operations increased, partly as a result of having reduced the administrative burden in the control room.
(Section 01.1) 133 11/7/1997 VIO/SL-IV IR 97014 NRC Operations 1A 3A The licensee identified that operators violated a TS required situational IR97014 surveillance check of electrical power source operability, when it was I
completed nine minutes late. This TS violation is of additional concem because it is similar to a recP Silure to verify electrical power availabi:ity documented in inspection Ry 30-341/97007. Prompt corrective actions significantly raised the visibility of TS actions among operators.
(Section 01.4) 134 11/7/1997 Negative IR 97014 NRC Operations inspectors identified concems with a lack of documentation of entries into allowed Technical Specification (TS) exceptions with limited time duration. (Sect!on O1.1).
135 11/7/1997 Positive IR 97014 NRC Operations 1C 2A The licensee was able to reduce the number of Limiting Condition for Operations (LCOs) entries by maintaining good equipment performance and by operations staff actively pursuing resolution of all LCO issues and holding organizations accountable for timely resolution. (Section O2.1) 136 11/7/1997 Negative IR 97014 NRC Maintenance 2A The inspectors ioentified that the standby liquid control system configuration challenged operators while performing surveillance testing, and that the high pressure coolant injection surveillance test procedure did not include guidance to pump down the suppression pool. (Section Mt.1) 137 11/7/1997 Negative IR 97014 NRC Maintenance 28 Coordination of switchyard maintenance with offsite personnel, though improved over the last several months, continued to need additional improvement. (Section M1.1) e l
e Page 25 of 30
m PLANT ISSUES MATRIX
"' 'S8 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = *Date* ; Begrnning Date = *10/1/9,. Ending Data = '9/30/98*
DATE TYPE SOURCE ID BY l SALP SMM CODES DESCRIPTION 138 11/7/1997 Positive IR 97014 NRC Maintenance 2B The mid-cycle outage was planned in greater detail than past cutages, resulting ir, better reviews, more complete preparations, and few schedule-related problems. Problems observed during the previous refueling outage were observed to have been effectively corrected.
Teamwork and coordination were evident in identification of equipment problems and performance of refueling floor activities. Outage management personnel effectively communicated the results of risk analyses to the entire site. These improvements resulted in completing an aggressive outage schedule slightly ahead of schedule with a minimum of problems. (Section M1.2) 139 11/7/1997 Negative IR 97014 NRC Maintenance 28 2A During a turbine building HVAC system outage, turbine building temperature rose to within 10 degrees of the trip setpoint for Main Steam isolation Valve (Group 1) closure. The outage was terminated due to high temperatures in the turbine building. Inspectors identified that high temperatures affected resistanco temperature detectors ( Section M1.1.b) 140 11/7/1997 Negative IR 97014 NRC Operations 3A 3B Operators inadvertantly doenrigized the west station air compressor necessitating entry into abnormal procedures for a loss of air due to failure to update a load list. A similiar problem occurred with the inadvertant deenerpzing loads that occurred during motor control center fused disconnect switch lubrication efforts in March -April 1997. ( Section O1.1.b) 141 11/7/1997 NCV IR 97014 NRC Engineering 4A inverted Boratlex panels in SFP storage racks were not documented in UFSAR. The licensee determined that the combined effects of the two conditions discussed in Section E8.4 were not accounted for because the results of the eight storage cells with inverted panels were not documented in the UFSAR. Failure to maintain the UFSAR updated with the current configuration of the SFP storage racks was a violation of 10 CFR 50.71. However, this non-repetitive, licensee-identified and corret,ted violation is being treated as a non-cited violation (Section E8.5).
/
Page 26 of 30
PLANT ISSUES MATRIX ii/23r98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date' ; Beginning Date = *10/1/97*, Ending Date = *r$G0/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 142 11/7/1997 Misc IR 97014 NRC Engineering 4B The inspectors were concemed that the licensee did not formally evaluate and document the operationalimpact of the potential failure of selected solenoid operated valves remaining in service. Consequently, the licensee implemented additional measures to periodically verify operability of the affected valves. The licensee's corrective action of increasing surveillance of selected systems was acceptable. (Section E1.1) 143 11/7/1997 Positive IR 97014 NRC Engineering 4B The licensee effectively utilized several teams designated to conduct equipment walkdowns, particularly in normally inaccessible areas of the plant. These walkdowns were scheduled at appropriate times during both startup and shutdown sequences when dose was acceptably low but the systems of concem were hot and pressurized. During startup, this effort included a vacuum leak team which was effective in ensuring the plant retumed to operation with a low air inteakage rate. Although these walkdowns were performed jointiy by operators, system engineers, and RP personnel, this is an example of increased engineering support (Section M1.2.b.5) 144 10/10/1997 Positive IR 97015 NRC Plant 1C ALARA planning for the 97-02 Mid-Cycle Outage was based on historical Support data and actual job doses coincided well with the dose estimates. In addition, the outage ALARA planning demonstrated contingency planning and use of dose reduction techniques to minimize radworker occupational dose (Section R1.1).
145 10/10/1997 Positive IR 97015 NRC Plant 3A The fuel sipping and reactor head activities were efficiently performed.
Support The jobs were well-planned and implemented with appropriate AL ARA considerations. These evolutions incorporated extensive research and evaluations, attention to lessons teamed, and effective preventative maintenance (Section R1.3).
146 10/10/1997 Positive IR 97015 NRC Plant 3A Radiological posting and labeling, housekeeping, and solid radwaste Support control measures were effectively implemented. Contamination control practices in the plant were thorough and included radiation surveys to detect alpha contamination; no alpha contaminc. tion was detected (Section R1.2).
4 Page 27 of 30
PLANT ISSUES MATRIX 11/23/98 Fermi Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date', Beginning Date = *10/1/97*, Ending Date = 9/30S8' DATE TYPE SOURCE
_ID BY SALP SMM CODES DESCRIPTION 147 10/10/1997 Positive IR 97015 NRC Plant 3A The chemistry staff successfully implemented a process to expedite Support floodup and improve water quality /clari:y, and plant personnel effectively monitored fuel integrity issues throughout the fuel cycle. The Dep!eted Zinc Oxide injection continued to minimize cobalt deposition on plant piping (Section R2.1).
148 10/10/1997 Positive iR 97015 '
NRC Plant 3A The licensee's records incident to decommisioning were well-maintained Support and were in compliance with 10 CFR 50.75(g) and other NRC guidance (Section R3.1).
149 10/10/1997 NCV IR 97015 NRC Plent 3A The radiation protection support and radworker practices were generally Support good. However, the inspectors observed one instance of inappropriate contamination control and one Non-Cited Violation was identified regarding the issuance of alarming dosimetry with an incorrect dose alarm setpoint (Section R4.1).
150 10/10/1997 Positive IR 97015 NRC Plant 3A 2A 1C The reactor water cleanup (RWCU) pre-job briefings informed radworkers Support of the radiological conditions, dosimetry requirements, and ALARA measures. Both the RWCU repair work and radiation protection job oversight were effective. The RWCU materiel condition continued to challenge the staff and theEfficulties with pump disassembly wdl be reviewed further by Region Ili (Section R1.4).
a Page 28 of 30
PLANT ISSUES MATRIX i/2ns Fermi search Sorted by Date (Descending) and sMM Codes (Ascending): search Column = *Date* ; Beginning Date =
- 0/1/97". Ending Date = "9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 151 10/10/1997 LER LER 97014 Licenssa Engineering 4A Turbine Building and Auxiliary Building Mezzanine Not Fully Meeting License Condition 2.C.9. During independent design verification of an Engineering Design Package, unsealed electrical penetrations were discovered in the auxiliary building wall fire rated separation barrier and in the adjacent and parallel turbine building fire barrier.. This prompted a review of the fire hazards analysis and the 10CFR50, Appendix R assumptions used for this area. This review was completed on October 10,1997 and revealed that of the 20 penetrations in these wa!!s,16 were not sealed at the auxiliary building wall and 4 were not sealed at the turbine building wall. There were no open;ngs which were unsealed at both the turbine building wall and the auxiliary building waii. The 16 unsealed penetrations in the auxiliary building wall are located over a horizontal distance in excess of 25 feet and interface with areas which contain both redundant shutdown divisions. The lack of penetration seats in the fire barriers could allow a fire in the turbine building to exit the turbine building through any of the 4 unsealed penetrations and enter the auxiliary building at any of the sixteen unsealed penetrations. These 16 unsealed penetrations could then introduce a fire hazard within 20 feet of cable trays containing both Division I and Division ll shutdown divisions.
This condition is not in compliance with 10CFR50, Appendix R and is also reportable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> under License Condition 2.C(9).
o e
Page 29 of 30
11/23/98 GENERAL DESCRIPTION OF PIM TABLE LABELS A counter number used for NRG intemal editing.
DATE The date of the event or significant issue. For those items that have a clear date of occurrence use the actual date. If the actual date is not known, use the date the issue was identified. For issues that do not have an actual date or a date of identification, use the LER or inspection report date.
TYPE The categorization of the issue - see the TYPE ITEM CODE table.
SOURCE The document that contains the issue information: IR for NRC Inspection Report or LER for Licensee Event Report.
ID BY Identification of who discovered the issue - see table.
SALP SALP Functional Area Codes - Engineering, Maintenance, Operations, Plant Support and All/ Multiple (i.e., more than one SALP area affecW).
SMM CODES Senior Manager Meeting Codes - see table.
DESCRIPTION Cetails of the issue from the LER text or from the IR Executive Summaries.
TYPE ITEM CODE NOTES SENIOR MANAGEMENT MEETING CODES DEV
' Deviation from NRC Requirements Eels are apparent violations of NRC 1
Operational Performance:
ED Escalated Discretion - No Civil Penalty requirements that are being considered for A - Narmal EEI' Escalated Enforcement issue - Waiting Final NRC Action escalated en'orcement action in accordance B - During Transients LER License Event Report to the NRC with the " General Statement of Policy and C - Programs and Processes Procedure for NRC Enforcement Action" Licensing Licensing Issue from NRR (Enforcement Policy), NUREG-1600.
2 Material Condition:
Misc Miscellaneous (Emergency Preparedness Finding. etc.)
However, the NRC has not reached its final A - Equipment Condition NCV Non-Cited Violation enforcement decision on the issues B - Programs and Processes Negative Individual Poor Licensee Performance identified by the Eels and the PIM entries 3
Human Performance:
Positive Individual Good Licensee Performance may be modified when the final decisions A - Work Performance are made. Before the NRC makes its Strength Overall Strong Licensee Performance B - Knowledge, Skills, and Abilities enforcement decision, the licensee will be C - Work Environment URI*
Unresolved Inspection item provided with an opportunity to either VIO/SL-I Notice of Violation - Seventy Level I (1) respond to the apparent violation or 4
Engineering / Design:
VIO/SL-il Notice of Violation - Severity Level II (2) request a predecisional enforcement A - Design VIO/SLC Notice of Violation - Severity Level ill conference.
B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV
- URis are unresolved items about which C - Programs and Processes Ceakness Overall Weak Licensee Performance 5
Pr blem enti cation and Resolution:
wh h e
e in s n sa acceptable item, a deviation, a ID BY nonconformance, or a violation. However, B - Analysts the NRC has not reached its final
- Resolution Licensee The licensed utility conclusions on the issues, and the PIM NRC The Nuclear Regulatory Commission entries may be modified wtien the final Self-Revealed Identsfication by an event (e.g., equipment breakdown) conclusions are made.
OtIter Identification unknown Page 30 of 30