ML20198B241
| ML20198B241 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/02/1998 |
| From: | Kozak T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Myers L CENTERIOR ENERGY |
| References | |
| NUDOCS 9812180116 | |
| Download: ML20198B241 (28) | |
Text
_.
December 2, 1998 l
l Mr. Lew W. Myers L
Vice President - Nuclear Centerior Service Company P. O. Box 97, A200 Perry, OH 44081 l
SUBJECT:
MID-YEAR INSPECTION RESOURCE PLANNING MEETING - PERRY l
Dear Mr. Myers:
l l
On November 4,1998, the NRC staff held an inspection resource planning meeting (! RPM).
The IRPM provided a coordinated mechanism for Region lll 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 Peny.
l 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 l
inspections are not listed due to their ongoing and continuous nature.
1 l contains a historical listing 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 Centerior Service Company.
We willinform you of any changes to the inspection plan. If you have any questions, please contact me at 630-829-9866.
Sincerely,
/s/ S. DuPont for Thomas Kozak, Chief Reactor Projects Branch 4 Docket No.: 50-440 License No.: NPF-58
Enclosures:
1.
Inspection Plan 2.
Plant Issues Matrix See Attached Distribution DOCUMENT NAME: :G:\\perr\\insppin7.per To receive a copy of thle document, IrHNcate In the box 'C' = Copy without attachment / enclosure *E' = Copy with attachenent/ enclosure
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NAME DuPontk KoDk DATE 11/ /98 #8[8/*Y 11/ /98
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OFFICIAL RECORD COPY l
9812180116 981202
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L Myers,
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H. Hegrat, Manager, Regulatory Affairs i
T. Rausch, Director, Quality and Personnel Development R. Schrauder, Director, Nuclear Engineering Department W. Kanda, General Manager Nuclear Power Plant Department
' l N.- Bonner, Director, Nuclear Maintenance Department H. Bergendahl, Director i
. Nuclear Services Department Ohio State Liaison Officer R. Owen, Ohio Department of Health C. Glazer, State of Ohio Public Utilities Commission i
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180031 Md. Res/DET F
n PERRY INSPECTION / ACTIVITY PLAN l
IP -Inspection Procedure Tl-Temporary instruction Core - Minimum NRC Inspection Program (mandatory all plants)
Regional Initiative - Discretionary inspections NUMBER OF TYPE OF INSPECTION NRC INSPECTION /
/
TITLE / PROGRAM INSPECTORS /
PLANNED ACTIVITY-ACTIVITY AREA INDIVIDUALS DATES COMMENTS IP83750 Occupational 2
March 1 - 5, Core Radiation Exposure 1999 Operator 3
March 15 - 26, Core Examination 1999 IP83750 Occupational 2
April 19 - 23, Core Radiation Exposure 1999 (Outage)
IP73753 Inservice Inspection 1
Outage Core (April /May 1999) i 9
PLANT ISSUES MATRIX Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date', Beginning Data = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
10/7/1998 Negative IR 98017 NRC Plant 1C The inspector found that the most recent audit of the radioactive waste Support management and radioactive waste and material shipping programs did not provide a comprehensive review. The audit focused on the conduct of radioactive waste control room operations and system material condition but did not fully assess the shipping program or process control program implementation.
2 10/7/1998 Positive IR 98017 NRC Plant 1C The inspector noted that personnel involved in the radioactive material Support shipping program were properly trained. In addition, training lesson plans were comprehensive and presented a broad review of the radioactive shipping program.
3 10/7/1998 Positive IR 98017 NRC Plant 1C in general, the Radiological, Environmental, and Chemistry Section Support (RECS) staff property packaged and classified radioactive material and waste shipments in accordance with regulatory requirements. Although some inaccuracies were identified, the shipping documentation and low level waste manifests contained the information required by 49 CFR Part 172 and 10 CFR Part 20.
4 10/7/1998 Positive IR 98017 NRC Plant 1C The REMP was properly implemented in accordance with the Support requirements of the Offsite Dose Calculation Manual. Air sampling equipment was calibrated at the required frequency, and the REMP technician demonstrated good analytical techniques. The 1997 and 1998 REMP sample results were consistent with normal fluctuations in background radiocctivity.
5 10/7/1998 NCV IR 98017 Licensee Plant 1C 2B One Non-Cited Violation was identified conceming the inadequate testing Support of the high alarm function isolation for the containment ventilation exhaust radiation monitor. The licensee identified this problem and performed corrective actions to ensure that the issue was corrected.
6 10/7/1998 Positive IR 98017 NRC Plant 1C SB The licensee performed a thorough audit of the REMP, including REMP Support technician performance and Offsite Dose Calculation Manual implementation. The inspector found that audit findings were evaluated, and the RECS staff took appropriate corrective action.
Page 1 of 24
PLANT ISSUES MATRIX
'3 ' SS8 Perry Search Sorted by Date (Descanding) and SMM Codes (Ascending): Search Column = "Date', Beginning Dats = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 7
10/7/1998 VIO/SL-1V IR 98017 NRC Plant 1C 5B One violation was identified concerr.ing the failure of the licensee to Support ensure that scaling factors used to determine the activity of hard to detect radionuclides in radioactive waste shipments could be correlated with actual plant samples. In April of 1998, the licensee did not adequately evaluate a poor correlation between isotopic data reported by its chemistry laboratory and a vendor. Consequently, the licensee implemented inaccurate radionuclide scaling factors which significantly underestimated the non-gamma radionuclides in radioactive waste shipments.
8 10/7/1998 Negative IR 98017 NRC Plant 1C SC The inspector noted slow progress in the RECS staff's revision of Support radioactive waste and material shipping procedures, which was started in early 1997. In addition, the inspector observed some weakr' asses in the procedures used for 10 CFR Part 61 scaling factor analyses. The RECS staff had developed an action plan to ensure timely completion of the procedure revisions and planned to review the instructions contained in the process control program and additional procedures.
9 9/25/1998 Positive IR 98016 NRC Operations 1A The inspectors determined that while most shift tumover briefings were effective, the quality of the briefings varied from crew to crew. For example, at various briefings, some operators were not sufficiently prepared to discuss watch station status, ambiguous terminology was used to discuss equipment status, and some attendees were unable to hear each speaker.
10 9/25/1998 Positive IR 98016 NRC Operations 1B Operations department personnel took prompt and effective actions in response to the automatic isolation of a feedwater heater, equipment problems associated with shifting reactor recirculation system flow control valve hydraulic control subloops, and the failure of an average power range monitor post-maintenance test. The operators effectively interacted during the events with open communications between alllevels,
of the on-shift operating crews. The operators quickly identified and responded to the situations and initiated corrective action documents in accordance with licensee management expectations.
Page 2 of 24
PLANT ISSUES MATRIX
*8 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date". Beginning Date = *10/1/1997*
- Ending Data = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 19 9/25/1998 Positive IR 98016 NRC Plant 1C The inspectors determined that the operations superintendent Support appropriately questioned an operator's radiological practices when manipulating equipment and interfacing with fluid in a potentially contaminated system during control rod drive hydraulic control unit (HCU) venting activities. The licensee initiated timely actions in analyzing the radioactive activity level of the HCU fluid which was below that which required protective clothing. The inspectors concluded that the operations superintendent took proactive actions by instituting an enhanced radiation protection practice requiring operators to wear protective gloves when conducting these and similar activities that breach the HCUs.
12 9/25/1998 Positive IR 98016 NRC Plant 1C SC The inspectors concluded that the fire protection supervisor implemented Support effective corrective actions for two fire extinguishers which had been temporarily stored beyond the guidance allowed in the station's housekeeping procedure. However, a condition report was not initiated for this issue until the inspectors identified that licensee management's expectations were not met regarding entering this information into the corrective action program.
13 9/25/1998 Positive IR 98016 NRC Maintenance 2A SC The inspectors concluded that the licensee was proactive in replacing a degraded emergency service water pump in a planned outage prior to its failure. While the outage was completed within the allotted time in the applicable Technical Specification limiting condition for operation, bet *er planning for the outage could have resolved pump shaft design differences and could have reduced the on-line out-of-service time for safety-related equipment.
14 9/25/1998 Positive IR 98016 NRC Engineering 4B The inspectors concluded that engineering department personnel were promptly involved in the testing activities and thoroughly pursued the resolution of the proper testing methodology for the hrs. The inspectors considered that there was good supervisory and senior management oversight during problem discovery, investigation, and resolution of this issue.
Page 3 of 24
PLANT ISSUES MATRIX
' **8 Parry search sorted by Date (Descending) and sMM Codes (Ascending): search Column = *Date". Beginning Date = *10/1/1997*. Ending Date = *10/30/1998*
DATE TYPE SOUF'CE ID BY SALP SMM CODES DESCRIPTION 15 9/25/1998 Positive IR 98016 NRC Operations SA The inspectors concluded that operations department personnel demonstrated a good questioning attitude when assessing the validity of the surveillance data for the hydrogen recomb ners (HR) when initial resistance-to-ground readings did not meet the acceptance criterion of the surveillance test. Also, the on-shift operating crew made the appropriate Technical Specifications entries based on their assessment of the HR test results.
16 9/25/1998 Positive IR 98016 NRC Engineering 5B The licensee performed a comprehensive root cause evaluation of the two reactor core isolation cooling turbine trips and identified that govemor valve stem binding was the root cause of the trips. The information developed through this evaluation was appropriately disseminated to the industry.
17 9/25/1998 Positive IR 98016 NRC Maintenance 5B The inspectors determined that the licensee effectively incorporated probabilistic risk assessment (PRA) techniques into daily plant operations. For example, a shift supervisor (SS) requested a new PRA value for the potential loss of an emergency service water isolation valve after it was discovered that the valve may not open due to missing gear teeth. The SS questioned the initial PRA value that was provided and a recalculation of the value resulted in the identification that the risk category was actually medium as opposed to low for this condition.
18 9/8/1998 Positive IR 98015 NRC J-lant 1C The licensee performed a thorough investigation of an incident (12/97)
Support involving an employee's discovery of an alcoholic beverage in the protected area.
19 9/8/1998 Positive IR 98015 NRC Plant 1C The licensee promptly implemented compensatory measures to Support compensate for damaged security equipment during a severe lightning storm, as required by station security procedures. The damage resulted in significant efforts in order to compensate for and repair failed components. Station management supported the repair effort. The components were repaired or replaced in a timely manner.
20 9/8/1998 NCV IR 98015 Licensee Plant 1C Two non-cited violations were identified conceming a reported FFD event Support involving a licensed operator who tested positive for alcohol on December 19,1997: a supervisor failed to ask alcohol-related fitness-for-duty questions during an unscheduled tour call out; the Supervisor, Nuclear Security Operations failed to conduct a confirmatory test for alcohol.
Page 4 of 24 l
PLANT ISSUES MATRIX
"'88 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date". Beginning Date = *10/1/1997. Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 21 9/8/1998 VIO/SL-IV IR 98015 NRC Plant 1C The inspector identified that the drug portion of a for cause test Support conducted based on the odor of alcohol was not timely. The for cause testing was required on December 19,1998. The drug test was not conducted until December 23,1998. This is a violation of Fitness For Duty Rule which requires a test "as soon as possible" after receiving credible information that an individual is abusing drugs or alcoh'ol. FFD testing data showed four other instances during 1996 and 1997 involving for cause testing based on the odor of alcohol when the drug portion was conducted one to four days after the test was deemed necessary.
22 9/8/1998 Positive IR 98015 NRC Plant 1C The licensee tested and maintained security systems as required by the Support security plan. Test results showed consistent performance. Visual inspections did not identify any material condition problems. However, the inspector identified a problem with the monitoring of the offsite radio by the ' Local Law Enforcement Agency (LLEA). Specifically, the LLEA did not respond to the licensee's test radio transmission. This issue was resolved by the LLEA prior to the conclusion of the inspection.
23 9/8/1998 Positive IR 98015 NRC Plant 1C Based on performance tests, the inspector concluded that the explosive Support and metal detectors and x-ray machines were properly calibrated.
However, the operability of selected models of the explosive detectors has been a challenge for the licensee, based ca a review of the monthly out of sentice hours for search equipment. The licensee was pursing resolution with the vendor. This did not significantly impact the search l
process because the licensee had ample machines in place to assure timely ingress.
24 9/8/i998 Positive IR 98015 NRC Plant 1C 5B Self-assessments of the security program were thorough and provided Support good findings and recommendations. The security staff properly evaluated and addressed identified findings.
25 8/21/1998 Negative IR 98013 NRC Plant 1C The inspectors identified that sleeving used to contain leakage from the Support "B" control rod drive pump was not properly secured and was not terminated within a controlled contamination area. This deficient condition did not result in the spread of contamination and was corrected by the licensee. The area of the plant was readily accessible and the condition should have been identified by p! ant workers who had performed work or tours in the area. The inspectors concluded that this was an additional example of inattention-to-detail by plant workcrs.
Page 5 of 24
PLANT ISSUES MATRIX
*8 Parry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date', Beginning Date = *13/1/1997". Ending Date = "10/30/1998" DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 26 8/21/1998 Positive IR 98013 NRC Maintenance 2B Special turbine centrol valve testing was performed in a controlled and consen/ativo manner. The testing personnel thoroughly evaluated data at each power level prior to increasing power and continuing with the test.
Engineering department personnel provided good support throughout the test by completing a thorough safety evaluation and providing timely evaluation of the test results.
27 8/21/1998 Negative 1998013 NRC Maintenance 3A The inspectors identified four instances where scaffolds were constructed by maintenance personnel closer to safety-related equipment than was allowed by plant procedures without the proper engineering review. The inspectors concluded that this was a result of inattention-to-detail by maintenance workers and was considered a minor violation of adherence to procedures.
28 8/21/1998 Negative IR 98013 NRC Operations 3A The inspectors identified two instances where valves were not appropriately locked in a closed position as required by plant procedures.
The inspectors concluded that this was a result of inattention-to-detail by non-licensed operators when they installed the valve locking devices.
This was considered to be a minor violation of adherence to procedures.
29 8/21/1998 Positive IR 98013 NRC Maintenance 5B After performing a risk assessment of an online electrical Division I outage, plant management rescheduled some of the planned activities to l Iower the risk associated with the work. The inspectors concluded that this was indicative of effective management involvement in plant activities and conservative decision-making.
30 8/19/1998 Positive IR 98014 NRC Operations SA SB The inspector determined that the licensee was effective in identifying and implementing corrective actions to notices of violation, unresolved items, inspector follow up items and licensee event reports. Root cause evaluations were thorough, accurate and well documented. Staff involvement in the corrective action process was good.
31 7/1/1998 Positive IR 98013 NRC Operations 18 Operator performance was good in response to the July 1,1998, scram and during the subsequent plant startup.1 he Unit Supervisor demonstrated good command and control of plant evolutions during the scram.
Page 6 of 24
PLANT ISSUES MATRIX
"' " 8 Perry Search Sorted by Dato (Descending) and SMM Codes (Ascending): Search Colurno = *Date*, Beginning Date = *10/1/1997*, Ending Date = *10r30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 32 6/18/1998 Positive IR 98013 NRC Maintenance 5B On June 18,1998, the licensee held a site-wide standdown to emphasize the policies for procedural adherence. The inspectors considered the I
stariddown to be an effective method of reinforcing expectations on procedural adherence 33 6/5/1998 Negative IR 98012 NRC Plant 1C The inspector identified a problem with the testing frequency of the B train Support of the annulus exhaust gas treatment system, which would have resulted in a missed surveillance of the high efficiency particulate air filtration train.
34 6/5/1998 Positive IR 98012 NRC Plant 1C The 1997 Annual Environmental and Effluent Release Report was well Support written and demonstrated that radioactive effluents were maintained below regulatory limits. The licensee continued to implement initiatives to reduce the quantity of gaseous and liquid effluents released to the environment. For example, the licensee established goals to reduce plant effluents to levels consistent with top industry performance. The inspector observed that the Radiological, Environmental, and Chemistry Section staff effectively monitored and trended effluent releases and communicated the results to plant management.
35 6/5/1998 Positive IR 98012 NRC Plant 1C The licensee effectively maintained the interim radioactive waste storage Support areas and minimized the quantity of waste held in these areas.
Inventories and radiological surveys effectively identified the contents of these facilities and the radiological conditions. The licensee also achieved progress in removing radioactive waste stored in the Radwaste Building. Although the staff performed inventories of these areas, the contents of some containers were not fully characterized.
36 6/5/1998 NCV 1R 98012 Licensee Plant 1C One Non-Cited Violation was identified conceming the failure to properly I
Support implement procedures during the issuance of a vacuum cleaner on December 20,1997. Due to personnel error and a lack of self-checking, the staff failed to perform a radiological survey of the vacuum cleaner during issuance. The licensee performed a thorough investigation of the
)
incident and implemented corrective actions to prevent recurrence.
37 6/5/1998 Negative IR 98012 NRC Plant 2A The operability of the liquid discharge monitor had been a challenge for Support the licensee. Although the licensee had performed actions to improve performance, the monitor was inoperable for extended periods of time in 1996 and 1997.
Page 7 of 24 l
__o
PLANT ISSUES MATRIX
' SS8 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date*
Beginning Date = *10/1/1997* ; Ending Data = *10/30/1998*
~
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 38 6/5/1998 Positive IR 98012 NRC Maintenance 2A The licensee tested engineered safety features ventilation filtration systems as required by Technical Specifications and station procedures.
Test results indicated consistent system performance, and visual inspections did not identify any material condition problems.
39 6/5/1998 Posit;ve IR 98012 Self-Plant 2A The material condition of process and effluent radiation monitors was Revealed Support acceptable. Based on calibration records, the inspector corcluded that effluent and process radiation monitors were also property calibrated.
40 6/5/1998 Positive IR 98012 NRC Plant 3B A chemistry technician properly replaced filters on an efflueni adiation Support monitor. The technician demonstrated effective procedure adherence and sample handling.
41 6/5/1998 Positive ir 98012 NRC Plant SA Self assessments of the radioactive effluents program were thorough and Support provided a broad review of program elements. The staff property evaluated and addressed audit findings.
t 42 6/4/1998 Negative IR 98010 NRC Maintenance 2A The inspectors identified three procedure adherence violations of minor significance associated with housekeeping and equipment control activities.
43 6/4/1998 Negative IR 98010 NRC Maintenance 2A The inspectors noted an increase in the number of emergent equipment issues over recent inspection periods. Some items resulted in distractions to operators or entry into Limiting Conditions for Operation.
In each case, the licensee resolved the issue promptly.
44 6/4/1998 VIO/SL-IV IR 98010 Licensee Operations 3A Two operator errors occurred, which were primarily due to inadequate attention-to-detail during the performance of routine tasks. Both of the errors also represented a failure to follow a procedure. The inspectors concluded that the failure of operators to appropriately follow procedures on two occasions led to two personnel errors involving the removal of an incorrect fuse and installation of an incorrect light bulb.
45 6/4/1998 Negative IR 98010 NRC Plant 3A The inspectors were concerned that access control procedures were not Support uniformly followed by station and contract personnel. This procedure adherence concem is concurrent with procedure adherence concems seen in other departments throughout this inspection period.
Page 8 of 24
PLANT ISSUES MATRIX
' SS8 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date', Beginning Date = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 46 6/4/1998 Negative IR 98010 NRC Operations 3B The inspectors identified four examples of deficiencies that indicate inconsistent operator attentiveness and awareness of control room panels. The inspectors continus to be concerned about the varying level of attention to detail and questioning attitude exhibited by operators in their routine panel observations.
47 6/4/1998 Positive IR 98010 NRC Engineering SA 48 The licensee demonstrated a good questioning attitude in the identification of inadequate logic testing of radiation monitors. The relay contacts were promptly satisfactorily tested.
48 6/2/1998 VIO/SL-IV IR 98012 NRC Plant 1C The licensee maintained proper radiological postings and barriers for Support contaminated areas and high radiation areas. The inspector also noted improvements in the status of high radiation area barriers and observed that access to safety related equipment was relatively unencumbered by radioactive contamination. However, one violation was identified conceming the failure to adequately post a radiation area within the Radwaste Building. Specifically, the inspectors identified that caution signs were not placed at all entrances to the radiation area.
49 5/22/1998 Positive IR 98011 NRC Maintenance 2A Treatment of medium and low-voltage power circuit breakers under the Maintenance Rule was satisfactory.
50 5/22/1998 Negative IR 98011 NRC Maintenance 2A SC Most safety related DC breakers had not yet been refurbished despite their age and the observed hardened grease in most of the ABB low voltage breakers. The licensee committed to accelerate the refurbishment plan for the DC breakers.
51 5/22/1998 Weakness IR 98011 NRC Maintenance 2B The implementation of the vendor manual control and vendor interface program in the past was not effective. The program was suffering from inadequate involvement by equipment-knowledgeable staff, insufficiently aggressive or tenacious follow up with uncooperative vendors, and out-of- '
date vendor contact information. The latest version of the vendor manual control and vendor interface program should impove the state of switchgear vendor manuals. This area was considered a weakness.
52 5/22/1998 Negative iR 98011 NRC Maintenance 2B The licensee was using an unevaluated cleaner on the 5 kV and 15 kV 1
medium power circuit breakers. The maintenance procedures specified an ammonia-based glass cleaner to clean the breaker's electrical components. The licensee used "Windex Glass Cleaner" which was not an evaluated cleaner.
Page 9 of 24
PLANT ISSUES MATRIX 11/30/1998 Parry Search Sorted by Date (Descerding) and SMM Codes (Ascending): Search Colurnn = *Date", Beginning Date = *10/1/1997*, Ending Data = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 53 5/22/1998 Negative IR 98011 NRC Maintenance 38 2B The NRC team concluded that lack of training on the Gels contributed to the inadequate implementation of the test procedures and considered this a weakness.
54 5/22/1998 Negative IR 98011 NRC Maintenance SA No documented breaker failures were recorded that could be directly attributed to breaker problems after the licensee refurbished all AC breakers in 1995/1996. The team noted that since breakers had been swapped between switchgear cubicles and breaker serial numbers were not being consistently recorded on work orders, the repetitive breaker failure data could not be easily obtained. The team also noted that the licensee had not yet established a program for trending breaker repeat failures and routine maintenance deficiencies.
55 5/22/1998 Weakness IR 98011 NRC Maintenance SA SB No specific audits or self assessments were performed in the areas of breaker maintenance or operations. This area was considered a weakness.
56 5/22/1998 Strength IR 98011 NRC Maintenance 5B There was very good evaluation and disposition of NRC, vendor, INPO, and other industry experience information. The operating experience reviews (OER) program procedures were generally comprehensive and workable and the OER database was complete with respect to circuit breaker information identified beforehand by the team. The individual OER evaluations were generally thorough and the resolution of issues expressed in NRC generic communications, operating experience reports, Part 21 reports and vendor letters was very good. This area was considered a strength.
57 5/22/1998 Positive IR 98011 NRC Engineering SC The licensee initiated aggressive corrective action to address NRC concems identified in 1994 relative to inadequate breaker maintenance.
Subsequently, in 1995/1996 all AC power circuit breakers were refurbished.
58 5/21/1998 VIO/SL-IV IR 98012 Licensee Plant 3A 5A One violation was identified conceming the failure of an individual to Support adhere to radiation work permit requirements. Specifically, the individual failed to wear a thermoluminescent dosimeter on 13 entries kto the radiologically restricted area, including an entry into a high radiati-1 area.
Although the licensee identified the problem and performed a thorough evaluation of the incident, the RP staff missed severdi opportunities to identify and correct the problem, prior to each of the individual's entries into the radiologically restricted area.
Page 10 of 24
PLANT ISSUES MATRIX
'3 SS8 Parry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date*, Beginning Date = *10/1/1997*. Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
59 5/20/1998 VIO/SL-IV IR 98011 NRC Maintenance 2B 4B The preventive maintenance procedures for the low-voltage power circuit breakers reviewed were generally of a type appropriate to the circumstances and included appropriate qualitative and quantitative acceptance criteria. However, various errors were identified in test reports reviewed for solid state trip devices. Similar errors were identified,
by the licensee as a result of the team's request to review additional test reports. The instantaneous trip function of circuit breaker EF1B04 was tested for instantaneous pickup at 2270 amps instead of the upper limit of 2160 amps. A violation was cited.
60 5/18/1998 VIO/SL-IV IR 98011 NRC Engineering 4A Calculation PRDC-0007,
- Voltage Drop of DC Control Circuits," dated May 18,1998, lacked rigor in terms of design inputs and conclusions. In addition, design control measures were ineffective in that design reviews failed to identify these deficiencies. A safety assessment, performed during the inspection, was acceptable to support an interim operability determination. The licensee indicated that a long term resolution would be developed to conservatively demonstrate on a continuing basis that the DC system could perform its intended function. A violation was cited.
61 5/8/1998 VIO/SL-IV IR 98010 NRC Maintenance 2A The inspectors identified a procedure adherence violation involving the improper control of transient combustibles during maintenance activities.
The inspectors were also concemed that supervisory and fire protection personnel did not display adequate attention to detail in reviewing the administrative control of the transient combustibles.
62 5/4/1998 VIO!SL-IV IR 98010 NRC Maintenance 3A The inspectors identified a procedure adherence concem with the performance of a surveillance test which resulted in a violation. The inspectors were also concemed that operations supervision failed to identify an omitted step during review of the data package.
63 4/20/1998 Positive IR 98009 NRC Operations 1A Shift turnovers and activity briefings continued to be thorough and the overall conduct of operations was conservative and professional.
Annunciators were consistently and appropriately responded to and emergent equipment issues were resolved promptly.
Page 11 of 24
PLANT ISSUES MATRIX Parry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date", Beginning Date = *10/1/1997* ; Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 64 4/20/1998 Positive IR 98009 NRC Maintenance 28 Maintenance and surveillance activities were completed effectively and IR 98009 satisfactori!y, without problems. There were appropriate briefings prior to e
the activities, adequate controls in place during the activities, and results were reviewed in a timely manner. Activities during a reactor downpower and complex surveillance tests such as high pressure core spray system and main steam isolation valve tests were well coordinated and performed without incident.
65 4/20/1998 Positive IR 98009 NRC Maintenance 28 3C The licensee acted in a thorough and conservative manner in response to,
a Division 11 DG surveillance test failure by conducting extensive testing, including tests of associated and redundant systems. The licensee also demonstrated conservative judgement in common mode failure considerations, and by increasing the frequency of testing during its s
investigation for the cause of the DG toad swings experienced during the initial surveillance test.
66 4/20/1998 Negative IR 98009 NRC Maintenance 3A The inspectors concluded that applicable procedural steps were not followed when the ESW pump house crane was left unattended with a load engaged and the electrical disconnects closed.
67 4/20/1998 Negative IR 98009 NRC Maintenance SC Although the human factor problems associated with a poorly designed diesel generator (DG) jacket water level gage have been known for several years, the licensee has not resolved the problem and, therefore, operators were unable to always accurately monitor jacket water level when the DG was in a standby readiness condition.
68 4/8/1998 Negative IR 98005 NRC Plant 1C A number of fire protection program discrepancies were identified by the Support inspector with regard to the penetration seal program and the coefficient of friction used in the hydraulic calculation for the sprinkler system.
69 4/8/1998 Positive IR 98005 NRC Engineering 4B Overall, engineering support to fire protection activities improved through the effective resolution of discrepant fire door seal ratings and fire hazard analysis revisions.
70 3/10/1998 Positive IR 98006 NRC Operations 1A The inspectors concluded that shift tumovers and briefings were thorough, emergent equipment issues were usually addressed in a timely manner, and the overall conduct of operations was professional with appropriate focus on safety (Section O1.1).
Page 12 of 24
PLANT ISSUES MATRIX
'3 S8 Parry
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Search Sorted by Date (Decending) and SMM Codes (Ascending): Search Colurnn = "Date". Beginning Date = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 71 3/10/1998 Negative IR 98006 Licensee Operations 1A The failure to establish and maintain an adequate verification process resulted in an operator error during control rod manipulations (Section 01.2).
72 3/10/1998 Negative IR 98006 NRC Operations 1A The quality and frequency of control panel walkdowns continued to be of concem to the inspectors. Although a licensed operator identified that a containment isolation valve had failed, he did not report this condition to management. In addition, other operators failed to identify the condition during panel walkdowns for four hours (Section 01.3).
73 3/10/1998 Negative IR 98006 Licensee Maintenance 3A Work control was not fully effective in two instances. During repair of the combustible gas compressor, poor communications between engineering and maintenance personnel resulted in the installation of the wrong part.
During work on a hydraulic control unit, loose items were not properly controlled within the suppression pool swell region (Sections M1.1 and M1.2).
74 3/10/1998 Negative IR 98006 NRC Maintenance 3A Licensee personnel did not always adhere to scaffolding storage and installation instructions which led to scaffolding being stored improperly and erected in close proxirrity to safety-related equipment (Section M2.1).
75 3/10/1998 Negative IR 98006 Licensee Maintenance 3C 2B The licensee identified that environmental qualification program recommendations to disassemble and inspect residual heat removal and t
low pressure core spray system motors every ten years were not appropriately implemented. Once identified, the issue was thoroughly evaluated (Section E2.1).
t 76 3/5/1998 Negative IR 98007 NRC Operations 1A A wide diversity in time intervals between panel walkdowns and the quality of panel monitoring raised a concem that operators were indifferent to indication problems and, in some cases, lacked a questioning attitude.
77 3/5/1998 Negative IR 98007 NRC Operations 1A Shift crew briefings and tumovers were consistent and effective sources IR 98007 of information to ensure continued safe operations. However, special evoletion briefings and tumovers were not always conducted in accordance with program guidance.
78 3/5/1998 Positive IR 98007 NRC Operations 1A Formal communications resulted in an effective exchange of information IR 98007 among operators and other plant personnel. Generally, commands and directions were clear and concise with repeat backs being expected.
Page 13 of 24
PLANT ISSUES MATRIX
*8 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date*, Beginnirg Date = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 79 3/5/1998 Positive IR 98007 NRC Operations 1A Control room operators effectively coordinated plant personnel during maintenance and testing evolutions to identify expected plant response and annunciator alarms.
80 3/5/1998 Negative IR 98007 NRC Operations 1A Werk control pre-job briefings emphasized procedure compliance, contingency action plan, and termination criteria with attention on self checking and personal safety. However, the pre-job briefing for a reactor core isolation cooling post-maintenance test failed to include quality control personnel which resulted in an unnecessary challenge to plant operators when an unanticipated heatup of the suppression pool above an administrative limit occurred.
81 3/5/1998 Negative IR 98007 NRC Operations 1C Control room deficiency identification and tagging guidelines were not clearty established and communicated through procedures and instructions.
82 3/5/1998 Negative IR 98007 NRC Maintenance 2B A reactor core isolation cooling system testing evolution was conducted within procedural guidelines. However, a number of deficiencies had been identified in the planning and implementation of the testing process.
83 3/5/1998 Negative IR 98007 NRC Maintenance 2B Prior to reactor core isolation cooling system maintenance, a pre-job walkdown failed to identify the inaccessibility of several steam jet plugs.
Additionally, maintenance personnel failed to document management's action to correct work procedure problem.
84 3/5/i998 Negative IR 98007 NRC Operations 3A During the performance of work under a safety tagout, an operator removed the wrong safety tag and installed a fuse in the wrong panel which energized a system tagged out for maintenance and jeopardized personnel safety.
85 2/28/1998 NRC Operations SALP 15 Ends 86 2/27/1998 Strength IR 98003 NRC Plant 1C Overall performance during the 1998 Emergency Preparedness exercise Support demonstrated that emergency plan imp lementation was effective. The technical support center, operations support center, public information response team, emergency operations facility, fire brigade, and medical response were effective. (Section P4.1.c)
Page 14 of 24
PLANT ISSUES MATRIX
S8 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date*. Beginning Date = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 87 2/27/1998 Strength IR 98003 NRC Plant 1C Overall, emergency response perfomlance in the Control Room Simulator Support was adequate. The licensee effectively addressed and initiated corrective actions for inadequate entry conditions for a Plant Emergency Instruction,,
identified in the Control Room Simulator. (Section P4.1.c).
88 2/27/1998 Positive IR 98003 NRC Plant 1C The licensee's classifications were appropriate and offsite notifications Support were made within the required times for the two declared Unusual Events. Plant personnel emergency response appeared to be effective.
(Section P1.1) 89 2/27/1998 Strength IR 98003 NRC Plant 1C Licensee critiques following termination of the exercise were self-critical Support and included controllers and exercise participants. (Section P4.1.c) 90 2/27/1998 VIO/SL-IV IR 98007 NRC Engineering 4B 4C A calculation deficiency existed in the licensee's deterraination of the 7-day diesel generator (DG) fuel oil supp!y quantity for division-3. The calculation revealed a required amount that was not consistent with TS and no corrective action had been implemented for almost two years.
The calculated difference required a TS change to address a non-conservative requirement which constituted a violation of regulatory requirements.
91 2/20/1998 Positive IR 97021 NRC Operations 1B Good preparations for activities associated with unusual plant conditions and the relatively good material condition of the plant, notwithstanding the electro-hydraulic control system and off gas cooling system problems, led to effective operator responses to the automatic reactor scram and the chemical spill during this inspection period (Section O1.3).
Teamwork / Skill Level 92 2/20/1998 Negative IR 97021 NRC Maintenance 2A The licensee inadvertently allowed the degradation of required raceway markings over time to the extent that some were either illegible or missing, which was a violation of NRC requirements (Section M7.2).
Inadequate Oversight 93 2/20/1998 Positive IR 97021 NRC Maintenance 28 Effective preparations led to the completion of a number of maintenance activities during an unanticipated two day reactor shutdown which resulted in the resolution of several outstanding material condition deficiencies. Effective planning and work execution led to a relatively low corrective and preventative maintenance item backlog (Section M7.1).
Other/NA Page 15 of 24
PLANT ISSUES MATRIX
"'3 SS8 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Dre*
Beginning Date = *10/1/1997* ; Ending Date = *10/30/1998*
DATE TYPE l
SOURCE ID BY SALP SMM CODES' DESCRIPTION 94 2/20/1998 Negative IR 97021 NRC Operations 3A Communications among operators and within the operations department were not as effective as had been observed during previous inspection periods (Section 01.1). Teamwork / Skill Level 95 2/20/1998 Negative IR 97021 NRC Operations 3C 3A The guidelines and expectations for the change in the equipment tagging policy were not initially clearly communicated to the operators which resulted in some degraded equipment not being tagged as expected by operations management (Section O2.1). Inadequate Procedure / instruction 96 2/20/1998 Negative IR 97021 Self-Engineering 4A An inadequate evaluation of a design change to the electro-hydraulic Revealed control system contributed to an automatic scram (Section E2.2).
Engineering / Design Deficiency 97 2/20/1998 VIO/SL-IV IR 97021 NRC Plant SA 1C Actions to verify fire doors were closed on a daily basis were generally Support effective. However, the licensee failed to recognize that a floor sealant applied in the EDG rooms introduced the possibility for fire doors to stick open, which resulted in a violation of NRC requirements when a fire door was identified by an inspector to be stuck open (Section P1.1).
Inadequate Oversight 98 1/30/1998 Positive IR 98002 NRC All/ Multiple 2B The licensee's tracking and trending of personnel errors was good and showed a slight reduction in the personnel error rate over the past year (Section 07.1.1).
99 1/30/1998 Positive IR 98002 NRC All/ Multiple SA The team concluded that the Company Nuclear Review Board and the Plant Operations Review Committee were effectively identifying areas of weakness in the corrective action program. The committees gave good attention to issues, promoted free discussion, and focused appropriately on safety and effective corrective action (Section O7.4).
100 1/30/1998 Positive IR 98002 NRC Engineering SA The team concluded that appropriate mechanisms were in place for self-assessment and quality assurance activities and that a number of plant and organizational problems were being identified (Section O7.3).
101 1/30/1998 Strength IR 98002 NRC All/ Multiple SA The Operating Experience Report program effectively assessed operating experience originating from both inside and outside the licensee's organization, informed the proper personnel of the assessments, generated technically sound corrective actions when appropriate, and correctly implemented these actions (Section 07.2).
Page 16 of 24
PLANT ISSUES MATRIX
"' 858 '
Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date', Beginning Date = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION ig 102 1/30/1998 Negative IR 98002 NRC All/ Multiple SA Personnel errors remained a proaiem; however, programs had been set in place to mitigate the errors and both management and the staff were aware of and accept the use of those tools. The team concluded that the licensee had taken reasonable measures to reduce the errors and that continued efforts would be necessary to resolve this issue (Section 071.1).
103 1/30/1998 Positive IR 98002 NRC All/ Multiple SA 5B SC The team concluded that the corrective action program at Perry had shown improvement in the past year. Improvements were noted in identification, resolution, and prevention of problems. However, continued attention will be required for effective resolution of ongoing personnel error and corrective action timeliness problems (Section 07.1).
104 1/30/1998 Negative IR 98002 NRC All/ Multiple SC Plant problems not always fixed in a timely manner or on first try and a lack of diligence in problem analysis were two areas of corrective action that will require continued effort for their resolution (Section 07.3).
105 1/30/1998 Positive IR 98002 NRC Maintenance SC 2A Effective correction actions since Refueling outage (RFO)5 resulted in improvements in leak reduction and equipment availability (Section O7.1).
106 1/21/1998 Positive IR 97017 NRC Plant 1C Overall, the EP program had been maintained in an effective state of Support operational readiness. Emergency response facilities, equipment, and supplies were well maintained. Management support to the program was strong. Interviewed key emergency response personnel demonstrated competent knowledge of responsibilities and emergency procedures.
Teamwork / Skill Level 107 1/16/1998 Strength IR 98004 NRC Plant 1A The radiological environmental monitoring program was effectively Support implemented. The environmental sample data indicated that there had been no discernable radiological impact on the environment from the operation of the facility (Section R1.2).
108 1/16/1998 Strength IR 98004 NRC Plant 1C A strong commitment to advanced technologies for source term reduction Support and reactor component protection was demonstrated through the implementation of the depleted zinc oxide program, and the plans for the chemistry optimization program which was to include hydrogen water chemistry and noble metal chemical addition (Section R1.1).
Page 17 of 24
PLANT ISSUES MATRIX
"'3 ' 888 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date*, Beginning Data = '10/1/1997. Ending Date = *10/30/1998" DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 109 1/16/1998 Positive IR 98004 NRC Plant 1C Overall, material condition of the chemistry instrumentation was good, Support maintenance was performed in a timely manner, and calibrations were performed as required. Some problems were observed with personnel not reviewing calibration results in a timely manner, and with personnel not communicating instrumente' ion problems to other departments relying on those instruments; however, ulese problems did not adversely impact any required analyses (Section R2.2).
110 1/16/1998 Weakness IR 98004 NRC Plant 1C The licensee had effectively maintained the material condition of the post Support accident sampling system. Annual comparisons between post accident sampling system and reactor water samples were generally within agreement, with one exception noted for the results from the first half of 1997. These comparison results were outside of the acceptance criteria and no contingency actions were taken indicating a weakness in the comparison progiam (Section R2.1).
111 1/16/1998 Strength IR 98004 NRC Plant 1C Overall technician performance was good with strong communication Support skills, good procedural adherence, and a thorough understanding of the sample process identified (Section R4.1).
112 1/16/1998 Positive IR 98004 NRC PMt 1C Plant water quality continued to be excellent, remaining well beneath St.. crt industry guidelines (Section R1.1).
113 1/16/1998 Strength IR 98004 NRC Plant 1C 3B Overall, the quality assurance program was effectively implemented.
Support Laboratory comparison results were satisfactory, with one exception noted in the first half of 1996. The instrumentation quality control program was effective, with the licensee using a comprehensive computer program to track parameters, and to identify trends (Section R7.1).
114 1/13/1998 Negative IR 97020 NRC Plant 1C in general, implementation of the security program was professional and Support well managed with improvement noted in the working relationship between the security staff and the maintenance support organization. A weakness was noted in the intemal self-assessment area.
Teamwork / Skill Level 115 1/9/1998 Positive IR 98004 NRC Plant 1C A strong commitment to advanced technologies for source term reduction Support and reactor component protection was demonstrated through the implementation of the depleted zinc oxide program, and the plans for the chemistry optimization program which was to include hydrogen water chemistry and noble metal chemical addition (Section R1.1).
Page 18 of 24
1
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PLANT ISSUES MATRIX 11/30/1998 Parry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date* ; Beginning Date = *10/1/1997* ; Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 116 1/7/1998 Positive IR 97022 NRC Operations 3B The response by control room personne! to the inadvertent loss of reactor vessel water inventory was satisfactory overall. The diagnosis of the event and the determination to insert a manual scram to terminate the event were well thought-out. However, a weakness in the response was a delay by the operator at the controls in reporting the problem to the Control Room Unit Supervisor. Teamwork / Skill Level 117 1/7/1998 VIO/SL-IV IR 97022, LER NRC Operations 3B 1A Personnel involved with a tag-out generated for scram air (SA) header 97013 valve work incorrectly believed that the scram discharge volume (SDV) vent and drain valves would close before the scram inlet and outlet valves started opening as the SA header slowly depressurized. However, the scram inlet and outlet valves started opening before the SD vent and drain valves closed which created a water flowpath from the reactor pressure vessel to the suppression pool. The inadequate evaluation of the effects that the tag-out would have on the plant conditions was a violation. Personnel Performance Deficiency 118 12/21/1997 Strength IR 97015 NRC Maintenance 2B The use of Performance Demonstration Initiative examinations and qualified personnel, etched weld identification numbers, and the proactive use of ISI component tags, demonstrated a conservative ISI program focused on safety (Section M1.1). Other/NA 119 12/21/1997 Strength IR 97015 NRC Maintenance 2B The licensee's independent evaluation of indications found during ISI exams for comparison with the flaw dispositions made by the contractors indicated a strong ISI program commitment to safety and active oversight of ISI contract personnel (Section M1.1). Other/NA I
120 12/21/1997 Positive IR 97015 NRC Maintenance 2B Inservice inspection activities were effectively implemented and in accordance with the licensee's program and ASME Section XI,1983 Edition Summer Addenda, requirements (Section M1.1). Other/NA 121 12/21/1997 Positive IR 97015 NRC Engineering 3C Overall, the suction strainer hardware installation was well executed with proper procedural adherence and active management and engineering oversight (Section E2.1). Involved Management 122 12/21/1997 Negative IR 97015 NRC Engineering 4C The initial receipt inspection for suction strainer components did not identify openings larger than the design criteria or a weld that was not complete. The licensee committed to evaluate the process and procedures for procuring items for major modifications and repairs, including Quality Assurance p.ogram oversight during fabrication and installation phases (Section E7.1). Other/NA Page 19 of 24
?
PLANT ISSUES MATRIX
" '3
- 898 Perry
~
Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date". Beginning Date = "10/1/1997-, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 123 11/30/1997 Negative IR 97016 Licensee Operations 1A 3A Poor communications resulted in a violation when a control rod was moved without the required pressure in its accumulator. Teamwork / Skill Level 124 11/30/1997 Negative IR 97016 Self-Operations 3A Tagging removal coordination resulted in an automatic reactor scram Revealed during shutdown conditions. Personnel Performance Deficiency 125 11/30/1997 Negative IR 97016 Self-Operations 3B Reactor water clean up system isolation caused by an operator failing to Revealed effectively verify the system's isolation logic status. Personnel Performance Deficiency 126 11/26/1997 Positive IR 97009 NRC Operations 3;
During observations of the receipt, inspection, and storage of new fuel, the inspectors observed that personnel were aware of their responsibilities and procedural requirements, procedures were properly used, and records were correctly maintained. Proper reactivity controls were emphasized and maintained during fuel movements. Preparations for refueling were also well controlled (Section O3.2). Teamwork / Skill Level 127 11/25/1997 NCV IR 97019 NRC Plant 1C The inspectors noted several instances when high radiation area controls Support were not as stringent as had been expected by the radiation protection i
section, resulting in three non-cited violations. While each example had been licensee identified and corrected, these problems indicated that there were several weaknesses in the high radiation area control program. Personnel Performance Deficiency 128 11/1/1997 Positive IR 97014 NRC Plant 1C Overall radiological control of activities associated with ECCS strainer Support replacement was very thorough, and the ALARA review for this activity was appropriately implemented. Involved Management 129 11/1/1997 Negative IR 97014 NRC Plant 1C Numerous problems, due in part to poor communications and poor Support implementation of the ALARA plan, were identified during the main steam line plug installation including the following items: unclear scope for the radiological survey; changes to the divers orientation not incorporated into the ALARA plan; confusion regarding stop work requirements; and a lax self assessment of activities immediately following the evolution.
Personnel Performance Deficiency Page 20 of 24
PLANT ISSUES MATRIX Perry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date* ; Beginning Date = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CObebll DESCRIPTION 130 11/1/1997 Positive IR 97014 NRC Plant 3A Planning and preparation for activities in the bioshield annulus were Support comprehensive, and the ALA RA brief demonstrated strong communications between the inservice inspection personnel and the radiation protection personnel Teamwork / Skill Level 131 11/1/1997 Positive IR 97014 NRC Plant 58 1C Licensee effectively tracked increasing refueling outage dose trends, and Support promptly addressed adverse trends in radiation worker practices Teamwork / Skill Level 132 10/14/1997 Negative LER 97014 Licensee Operations 3B Withdrawal of inoperable control rod results in operation prohibited by Technical Specifications. Personnel Performance Deficiency 133 10/8/1997 Misc IR 97007 NRC Operations 1A Maintenance activities were well controlled by operations. However, there were variations in attention to detail (Section 04.4). Teamwork / Skill Level 134 10/8/1997 NCV IR 97007 LER NRC Operations 1A 3B Operators responded appropriately to a high pressure core spray 97004 (HPCS) pump suction shift. Compliance determined that past HPCS suction shifts had not been reported to the NRC. This was a Non-Cited Violation (Section O2.1). Personnel Performance Deficiency 135 10/8/1997 URI 1R 97007 Self-Operations 1B 3A An operator error caused a reactor feedwater pump turbine trip. Operator Revealed actions were appropriate in recovering from the transient. The inspectors' evaluation of the root cause of the transient is an Unresolved item (Section O4.2). Personnel Performance Deficiency 136 10/8/1997 Positive IR 97007 NRC All/ Multiple 1C The licensee's strike contingency plan addressed appropriate issues (Section 04.3).
137 10/8/1997 Misc IR 97007 NRC Operations 2A Drywell and containment closeout activities were effective. How3ver, the inspectors identified some material missed by the licensee (Section O2.2). Personnel Performance Deficiency 138 10/8/1997 Positive IR 97007 NRC All/ Multiple 2B Maintenance and surveillance activities were appropriately performed.
Operators exhibited good questioning attitudes and engineering support was appropriate (Section M1.1). Teamwork / Skill Level 139 10/8/1997 Positive IR 97007 NRC Maintenance 2B 3A During online maintenance, safety equipment was retumed to service more promptly than in the past. There were unrealized opportunities for additional improvements which could have reduced out of service time for safety-related equipment (Section M1.2). Teamwork / Skill Level Page 21 of 24 I
PLANT ISSUES MATRIX
*88 Parry Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date" Beginning Date = *10/1/1997*. Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 140 10/8/1997 Positive IR 97007 NRC Opar;0ns
~3A Operators and reactor engineers performed well during plant power changes (Section O3.2). Teamwork / Skill Level 141 10/8/1997 Positive IR 97007 NRC Operations 3A Formal communication by operators was well developed and use of procedures was well established (Section 01.3). Teamwork / Skill Level 142 10/8/1997 LER IR 97007, LER Self-Maintenance 3B A maintenance personnel error caused a HPCS pump start. The 97006 Revealed inspectors will complete evaluation of this event after the licensee event report is issued (Section M4.2). Personnel Performance Deficiency 143 10/8/1997 Misc IR 97007 NRC Operations 3B Shift and pre-evolution briefings were effective, although there was cce exception and minor problems were observed (Section 04.1).
Teamwork / Skill Level 144 10/8/1997 Negative IR 97007 Licensee Operations 3C Before testing emergency closed cooling water va!ves, operators did not adequately review the operability requirements in the operational requirements manual. Poor performance by compliance and management contributed to this. Conscientious execution of testing prevented a TS violation and an oncoming operator identified the problem (Section O3.1). Inadequate Oversight 145 10/8/1997 VIO/SL-IV IR 97007 Licensee Maintenance 3C The licensee identified a violation of the safety tagging procedure.
Although this isolated error was promptly given appropriate management attention, corrective actions were not completed (Section M4.1).
Inadequate Oversight 146 10/8/1997 Positive IR 97007 Self-All/ Multiple 48 2A in general, plant equipment was well maintained, work priority was Revealed appropriate, and engineering provided prompt support. Although manageable, emergent work was higher that desirable, and engineering and maintenance needed to continue to improve the reliability of plant equipment. Although equipment problems contributed to two plant transients, equipment performed well during the transients (Sections M2, O1.2, O4.2). Other/NA 147 10/8'1997 Negative IR 97007 NRC Engineering SC The inspectors identified that the licensee was slow to implement short-term corrective actions for three potential unreviewed safety questions.
After discussions with NRC management, the licens se was prompt and thorough in restoring the plant to compliance with it:; licensing basis. Tne inspectors identified that detailed control of valve testing and construction of temporary tomado missile protection was not fultr effective (Section E2.2). Personnel Performance Deficiency Page 22 of 24
PLANT ISSUES MATRIX
**8 Perry Search Sorted by Date (Descending) and SMM Codes (Ascending).- Search Column = "Date*, Beginning Date = *10/1/1997*, Ending Date = *10/30/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 148 10/6/1997 Enf Conf (EAs 96-Enforcement Conference held to discuss violations associated with IR 97-482,-542,97-047 008 and continue a April 18,1997 enforcement conference associated and -430) with a November 1996 reactivity event.
149 10/4/1997 Positive IR 97012 NRC Operations 1A Operations personnel effectively took the plant through several mode changes and power changes. In particular, the shutdown activities to I
commence Refueling Outage 6 (RFO6), including simulator practice sessions, were well planned and performed (Section O4.1).
Teamwork / Skill Level 150 10/4/1997 Positive IR 97012 NRC Plant 1C 3C Security activities were handled well, including increased personnel Support access controls and monitoring for the refueling outage (Section S1.1).
Involved Management 151 10.4. W VIO/SL-IV IR 97012 NRC Maintenance 2B The inspectors identified a violation of administrative requirements associated with improper implementation of a surveillance procedure (Section M1.1). Inadequate Procedure / Instruction 152 10/4/1997 Positive IR 97012 NRC Maintenance 2B The inspectors observed good coordination between work groups as the Work Control Center effectively handled a large volume of work for the commencement of RFO6 (Section M1.1). Teamwork / Skill Level 153 10/4/1997 NCV IR 97012 Self-Operations 3A A non-conservative decision regarding the authorization of a functional Revealed check of a source range monitor concurrent with the authorization for core activities in the same core region resulted in the identification of a non-cited violation (Section O1.5).
Inadequate Oversight 154 10/4/1997 Misc 1R 97012 NRC Operations 38 Tumover briefings continued to be clear and effective. However, evolution briefings were sometimes weak in communicating required I
personnel responses to abnormal conditions during evolutions (Sections 01.1, O1.2 and 04.2). Other/NA 155 10/4/1997 Positive IR 97012 NRC Engineering 4C The inspectors observed that engineering work packages were detailed and presented in an easily understood manner. Engineering packages had in-depth analyses and calculations to support the associated i
activities (Section E2.1). Teamwork / Skill Level I
1 Page 23 of 24
11/30/1998 GENERAL DESCRIPTION OF PIM TABLE LABELS A counter number used for NRC Intemal editing.
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 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 CY 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 affected).
SMM CODES Senior Manager Meeting Codes - see table.
DESCRIPTION Details 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 - Normal eel
- Escalated Enforcement issue - Waiting Final NRC Action escalated enforcement action in accordance B - During Transients LER License Event Report to the NRC with the " General Statement of Policy and C - Programs and Processes Licensing Licensing issue from NRR Procedure for NRC Enforcement Action (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 *.he Eels and the PIM entries 3
Human Performance:
Positive Individual Good Licensee Performance may be modified when the final decisions A - Work Performance Strength Overa:1 Strong Licensee Performance are made. Before the NRC makes its B - Knowledge, Skills, and Abilities
- URI, Unresolved Inspection ftem enforcement decision, the licensee will be C - Work Environment provided with an opportunity to either VIO/SL-l Notice of Violation - Severit'f Level I (1) respond to the apparent violation or 4
Engineering /Desigre VIO/SL-il Notice of Violation - Severity Level II (2) request a predecisiona! ?nforcement A - Design VIO/SL-ill Notice of Violation - Severity Lavel 111 conference.
B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV
- URis are unresolved items about which C - Programs and Processes Weakness Overall Weak Licensee Performance determin 5
Problem Identification and Resolution:
wh e e
sa acceptable item, a deviation, a A - Identification ID BY nonconformance, or a violation. However, B - Analysis the NRC has not reached its final C - Resolution Licensee The licensed utility conclusions on the issues, and the PIM j
NRC The Nuclear Regulatory Commission entries may be modified when the final Self-R;vealed Identification by an event (e.g., equipment breakdown) conc'usions are made.
Other Identification unknown Page 24 of 24 1
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