ML20196D564
| ML20196D564 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 11/20/1998 |
| From: | Burgess B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| References | |
| NUDOCS 9812020276 | |
| Download: ML20196D564 (35) | |
Text
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Novembe 20, 1998 Mr. M. Wadley
- President, Nuclear Generation l
Northern States Power Company l
414 Nicollet Mall Minneapolis, MN 55401
SUBJECT:
MID-YEAR INSPECTION RESOURCE PLANNING MEETING - MONTICELLO
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Dear Mr. Wadley:
On November 4,1998, the NRC staff held an inspection resource planning meeting (IRPM).
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 Monticello.
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 l
onsite. The rationale or basis for each inspection outside the core inspection program is l
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 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 l
reports or other docketed correspondence between the NRC and Northem States Power Company.
We willinform you of any changes to the inspection plan. If you have any questions, please contact Bruce Burgess at (630) 829-9629.
Sincerely, l
Original sijned by it. Kunowski Bruce Burgess, Chief
(
l Reactor Projects Branch 7 l
Docket No.: 50-263 License No.: DPR-22
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Enclosures:
1.
Inspection Plan j
2.
Plant issues Matrix cc w/ encl:
Plant Manager, Monticello State Liaison Officer, State of Minnesota l
DOCUMENT NAME: G:\\MONT\\lRPMLTR.WPD To receive a copy of this document, indicate in the bos "C" e Copy w#o attachtenel T's Copy wlattech/enci'tr a No copy OFFICE Rill lC R!ll l6 l
l NAME Kunowski/mt MAR Burgess cAx A DATE 1100/98 11/M/98 I
OFFICIAL RECORD COPY l
l 9812O20276 981120 i
PDR ADOCK 05000263 G
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Distribution:
1 CAC (E-Mail)
RPC (E-Mail) j-Project Mgr., NRR w/enci J. Caldwell, Rlll w/enci C. Pederson, Rlli w/enci ~
B. Clayton, Rlil w/enct SRI Monticello w/enci DRP w/enci
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DRS (2) w/enci '
Rlli PRR w/enci PUBLIC IE-01 w/enci Docket File w/enci GREENS LEO (E-Mail) TBO)
DOCDESK (E-Mail) l t
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DI ENCLOSURE MONTICELLO INSPECTION PLAN FOR DECEMBER 1998 THROUGH APRIL 1999 NUMBER OF TYPE OF INSPECTION NRC INSPECTION /
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TITLE / PROGRAM AREA INSPECTORSI PLANNED DATES ACTIVITY-ACTIVITY INDIVIDUALS COMMENTS IP83750 Occupational Radiation Exposure 2
December 14 - 18,1998 Core IP86750 Radwaste 2
December 14 - 18,1998 Core IP71001 Ucensed Operator Requal 2
March 8 - 12,1999 Core IP81700 Security 1
October 26 - 30,1998 Core IP82301 EP Exercise 4
June 21 - 25,1999 Core t
Legend:
IP Inspection Procedure Tl Temporary instruction Core Inspection Minimum NRC Inspection Program (mandatory at all plants)
RegionalInitiative AdditionalInspection Effort Planned by Region 111 l
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PLANT ISSUES MATRIX ur23/98; Monticalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area = ' Operations *, Beginning Data = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
9/30/1998 Positive IR 98015(DRP)
Ucensee Operations 2A SA Minor problems identified by the inspectors during system walkdowns had been previously identified by the licensee. The licensee has taken action to correct these concems.
2 9/21/1998 Positive IR 98015(DRP)
NRC Operations 3A 1A Three examples of excellent system awareness were noted. An operator LER 98005 identified a very small leak in the body of a high pressure coolant injection steam line drain valve, a system engineer noticed that a standby liquid control relief valve appeared to lift at too low of a pressure, and a system i
engineer noticed an unusual response in the electrical pressure regulating system. In allinstances, the licensee made conservative operability decisions when degraded equipment conditions were identified.
3 9/15/1998 Positive IR 98015(DRP)
NRC Operations 1A 3A Shift management conservatively decided to delay reactor startup after a manual scram to investigate and repair an instrument air leak. The startup was conducted in a controlled and professional manner.
4 9/9/1998 Misc LER 98004 50.72 Self-Operations 1B 2A An offgas system high pressure alarm was received which resulted in the No.34754 Revealed condensor offgas system tripping. Operators reduced load quickly but manually scrammed the reactor from about 30% power when condensor vacuum could not be reestablished. All contro! rods fully inserted, no safety relief valves lifted, all equipment responded as required. A group 2 and group 3 primary containment isolation iignal was produced from the post-scram response.
5 9/9/1998 Positive IR 98015(DRP)
NRC Operations 1B 3A Operations personnel responded promptly to the isolation of the steam jet air ejector suction valves and the loss of both recombiner trains. Shift management proactively decided to manually trip the reactor.
6 8/31/1998 Positive IR 98012(DRP)
NRC Operations 1A Material condition of three systems reviewed by the inspectors was good:
the combustib!e gas control system, the high pressure coolant injection system, and the residual heat removal service water system. No concems with housekeeping or radiological controls were identified.
However, minor inconsistencies existed between the current configuration of plant equipment and the piping and instrumentation drawings. No operability concems were noted.
Page 1 of 9 l
'*8f PLANT ISSUES MATRIX Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP" ; SALP Area =
- Operations *, Beginning Data = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 7
8/31/1998 Negative IR 98012(DRP)
NRC Operations 1A Operators were knowledgeable of current and planned activities and acted in a professional manner. However, the inspectors observed several operators walk by the emergency core cooling systems' control panels while wearing hard hats and an operator holding a cup of coffee over the control panels, which are ccnsidered to be poor practices in a nuclear power plant control room.
8 8/31/1998 Strength IR 98012(DRP)
NRC Operations 1C A reactor shutdown, in response to arcing on a recirculation pump motor generator set, and the subsequent startup, were well planned. Power reductions, a reactor shutdown, and a reactor startup were controlled in a deliberate manner with good communications and procedure adherence.
9 8/31/1998 Positive IR 98012(DRP)
NRC Operations SA Equipment was taken out-of-service and returned-to-service effectively.
The licensee identified that the equipment " isolation and restoration
- form lacked a check block for the shift supervisor to indicate if independent verification was required for tag removal. A condition report was initiated to prompt tracking and resolution of this discrepancy between the form and the equipment isolation procedure.
10 7/18/1998 Positive IR 98011(DRP)
NRC Operations 1A Operational activities were generally performed in accordance with administrative procedures. Shift tumovers were acceptable and included detailed discussions of equipment status. Shift briefings were informative.
11 7/18/1998 Negative IR 98011(DRP)
Licensee Operations 1A Overall, operators were attentive to panels; however, two examples of inattention-to-details on panels were identified. Also, a plant operator did not follow a pump start procedure, which resulted in a safety-related pump operating 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> without motor cooling. Although the immediate safety significance of this event was minimal, operating safety-related equipment without requiring procedures in-hand was a poor practice.
12 7/18/1998 Negative IR 98011(DRP)
NRC Operations 1A Operations personnel did not anticipate that steam chase area temperatures would exceed procedurallimits. This discrepancy was not identified during panel walkdowns since this parameter was recorded only once during the shift, early in the moming. Operations personnel immediate corrective actions, which included increased monitoring and obtaining engineering personnel support, were acceptable.
Page 2 of 9
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PLANT ISSUES MATRIX u/23/98; Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Operations * ; Beginning Date = *10/1/97* ; Ending Data = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 13 7/18/1998 NCV IR 98011(DRP)
Licensee Operations 18 During a condenser vacuum transient, operators quickly executed a reactor power reduction and appropriately stabilized the decreasing condenser vacuum. However, shift management misread an abnormal procedure step and did not initiate a reactor scram required for turbine protection purposes. The licensee's initial assessment of operator performance during the condenser vacuum transient was critical and thorough. This non-repetitive, licensee-identified and corrected violation is being treated as a Non-Cited Violation, consistent with Section Vlf.B.1 of the NRC Enforcement Policy (NCV 50-263/98011-02(DRP) 14 7/18/1998 Positive IR 98011(DRP)
NRC Operations 18 Operations personnel responded promptly and appropriately to a reactor power transient caused by thunderstorm-induced disturbances to the electrical distribution grid.
15 7/18/1998 Negative IR 98011(DRP)
NRC Operations 3A Changes to operations manuals were adequately controlled. Two minor examples of failure to follow administrative processes were identified.
16 7/18/1998 Weakness IR 98011(DRP)
NRC Operations SA Assessment activities by the line organization were event-driven or resulted from industry issues. Corrective actions for identified concems were timely and appropriate. No formal process existed to assess routine operations, which was considered a weakness in the assessment program.
17 5/27/1998 Positive IR 98007 NRC Operations 1A The operations committee review of activities and outstanding issues to support startup was thorough. The initial decision to delay startup because of a cracked control rod drive withdraw line was conservative and reflected safety conscious operation. Reactor startup was controlled in a deliberate manner with good communication and procedure adherence by operations personnel.
18 5/27/1998 Positive IR 98007 NRC Operations 2A No operability concems were identified during tours of normally inaccessible areas and walkdowns of plant systems.
19 5/27/1998 Positive IR 98007 NRC Operations 3A Overall, licensed and non-licensed operator performance inside and outside the control room was satisfactory. Communications observed were clear. Performance of routine and reactive procedures, including entry into Technical Specification limiting conditions for operation, was proper. Pre-evolution briefings were thorough and informative.
Page 3 of 9
PLANT ISSUES MATRIX 11/23/98 Menticallo Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP' ; SALP Area = ' Operations" ; Beginning Date = *10/1/97*. Ending Data = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 20 5/27/1998 Negative IR 98007 NRC Operations 3A Some housekeeping issues identified by the inspectors indicated that non-licensed operators were not identifying some discrepant plant radiological, housekeeping, and equipment staging items.
21 5/27/1993 Positive IR 98007 NRC Operations 3A The identification of an unexpected valve closure resulted from a good questioning attitude by operations personnel. Also, when the third and i
final control rod to be withdrawn to achieve criticality did not move with normal control rod drive pressure, operators displayed conservative decision-making by backing out of a procedure, inserting the three control rods, and performing control rod drive exercise tests. The shift supervisor demonstrated excellent attention-to-detail in the identification of the cracked control rod drive withdraw line.
22 5/27/1998 Negative IR 98007 Self-Operations 3A Operations personnel returned the recombiner trains to service without Revealed verifying a post-maintenance test was complete.
23 5/27/1998 Positive IR 98007 NRC Operations SA General quality services (quality assurance) auditors were present in the control room during the refueling outage. Good interaction between the auditors and operations personnel was noted. The auditors maintained an appropriate independent oversight function.
24 5/7/1998 Negative IR 98007 NRC Operations 1A Operations personnel did not document a May 7,1998, reactor buil ding I
differential pressure indication problem as part of the corrective action process. Operations personnel performed compensatory actions for the indication problem instead of initiating repairs, which demonstrated their willingness to accept discrepant conditions. The root cause of the condition was not adequately corrected until the problem recurred on May 12,1998. A fack of documentation of the problem contributed to the delay in determining the root cause.
l 25 4/14/1998 Positive IR 98004 NRC Operations 1A Pre-outage activities were beneficial to the coordination and execution of outage work. The workload for operations personnel during the power reduction and first days of the outage was managed effectively as a result of pre-outage isolation and vessel disassembly meetings. The shutdown i
training provided to the operators was effective, in that several discrepancies with the shutdown procedure and other scheduled activities l were identified and resolved prior to the actual shutdown.
26 4/14/1998 Positive IR 98004 NRC Operations 1A 3A Refueling operations, which included about 850 separate fuel or core l
component moves, were conducted in a careful, deliberate, and error-free manner.
Page 4 of 9
PLANT ISSUES MATRIX "5 'S8 f
Montic211o i
Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP* ; SALP Area = " Operations", Beginning Date = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 27 4/14/1998 Positive IR 98004 NRC Operations 1A 3A Operations personnel conducted the shutdown in a well-coordinated, controlled manner and in accordance with procedures.
28 4/14AM Positive IR 98004 NRC Operations 1A 3A Operator performance was acceptable. Improvements were noted in the tumover process and communications. No discrepancies were identified during review of isolation tags on equipment. In general, pre-job and infrequent evolution briefings were detailed. However, the inspectors identified two examples of inattention-to-detail by reactor operators during control room panel walkdowns.
29 4/14/1998 Positive IR 98004 NRC Operations 1C The licensee conservatively applied shutdown risk concepts during the planning and execution of the 1998 refueling outage. Implementation of the outage plan was being conducted effectively and in a controlled manner.
30 2/23/1998 VIO/SL-IV 1R 98002 NRC Operations 1A Three concerns were identified with respect to the restoration of equipment to operational readiness after maintenance activities were performed. These included not providing adequate instructions for restoring a reactor core isolation cooling valve to service; declaring a residual heat removal service water pump operable with an outstanding hold-and-secure card located on the control room hand-switch; and not providing adequate instructions to fill a portion of the fire protection system. Two violations (of Criterion V of 10 CFR Part 50, Appendix B) for inadequate procedures and failure to follow administrative procedures were cited. The tracking numbers for these violations are No. 50-263/98002-01(DRP) and No. 50. 263/98002-02(DRP).
31 2/23/1998 Positive IR 98002 NRC Operations 3A The training provided to operations personnel for the handling and inspection of new fuel bundles and channels was adequate. Operators conducted the inspection and handling activities in a controlled manner.
32 2/23/1998 Positive IR 98002 NRC Operations 3A 1A Operator performance during routine operations and surveillance test activities was good. With one exception, operators were knowledgeable of plant conditions and equipment status. An operator's questioning attitude prevented a potential Group I isolation during a routine main steam line high flow surveillance test and standby gas treatment system operability test.
Page 5 of 9
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PLANT ISSUES MATRIX Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Operations * ; Beginning Date = *10/1/97* ; Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES!
DESCRIPTION 33 2/23/1998 Positive IR 98002 NRC Operations 3B Operations personnel displayed good teamwork during three simulator training scenarios. The senior reactor operator verified that actions were taken in accordance with the emergency operating procedures and displayed good command and control over the crew.
34 1/12/1998 Positive IR 97018 NRC Operations 1A 3A Two reactor power reductions (one on December 13,1997, and one on January 10,1998) were conducted in a controlled manner. Operators responded appropriately to a low circulating water and intake star:ture basin level condition. Power ascensions to 100 percent were penbrmed without problems. Teamwork / Skill Level 35 1/12/1998 Positive IR 97018 NRC Operations 3A in general, the conduct of operations was acceptable. Operator performance during routine operations and surveillance test activities was good. However, the inspectors noted inconsistent communication techniques used by operators during responses to annunciators.
Other/NA 36 12/19/1997 Positive IR 97018 LER NRC Operations 3A The operations shift supervisor promptly evaluated operabihty of the 97014 automatic depressurization system when a discrepancy between the Updated Final Safety Analysis and as-built plant conditions w1s identified by the inspectors. The inspectors were following up on the identification by the licensee of improper logic circuit testing per NRC Generic Letter 96-l 01," Testing of Safety-Related Logic Circuits.*
1 37 11/25/1997 Positive IR 97018 LER Self-Operations 1B 3A Operations personnel responded promptly and appropriately to a loss of 97013 50.72 No.
Revealed both recombiner trains and subsequent manual reactor scram. The 33312 reactor was manually scrammed because a potential for a loss of condenser vacuum developed after the condenser offgas recombiner and offgas auxiliary systems tripped because of an electrical fault. Procedure adherence and informative briefings were observed. The shift manager maintained excellent command and control of activities during the event.
The reactor startup was conaucted without incident. Conservative Decision Page 6 of 9
PLANT ISSUES MATRIX
/23/98 -
Manticella GA Sorted by Date (Descending) and SMM Codes (Ascending): Searet.Colurnn = *SALP* ; SAlf.%rea = ' Operations * ; Beginning Date = *10/1/97*, Ending Date = "9/30/98*
l DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 38 11/24/1997 VIO/SL-IV IR 97015 NRC O,merations 2A 3A The licensee's program for protecting plant equipment from cold weather conditions appeared adequate. Plant personnel were instructed to consider environmental concems when planning and performing maintenance in the winter months. However, the inspectors identified that the intent of the winter checklist procedure was changed due to an improper use of the temporary change process. The licensee subsequently identified that the procedure had not been approved in accordance with plant procedures. A subsequent operability determination indicated that the procedure change was not safety significant. A violation of 10 CFR 50, Appendix B, Cnterion V,
" Instructions, Procedures, and Drawings," was identified. The tracking number for this violation is No. 50-263/97015-01(DRP). Personnel Performance Deficiency 39 11/24/1997 Positive IR 97015 NRC Operations 3A 1A The operators' performance during routine operations and surveillance activities were acceptable. With one exception, the operators were knowledgeable of plant conditions and equipment status. Operators' questioning attitude resulted in the identification of blockage in a motor cooling line and of a faulty bus insulator. Teamwork / Skill Level 40 11/19/1997 Positive IR 97016 NRC Operations 3A 1C Performance of the Contiol Room Simulator crew during the 1997 Emergency Preparedness exercise was effective. The Shift Manager and Shift Supervisor exercised proper command and control over the operators. The crew detected reactor events and took proper actions.
Operator actions indicated a detailed understanding of plant events.
Teamwork / Skill Level 41 10/30/1997 NCV IR 97015 Self-Operations 3A An operator's failure to follow the electric fire pump startup procedure and Revealed inadequate instruction for shutting down the fire pu'mp resulted in an automatic start of the diesel fire pump without operators' knowledge.
Operations personnel appropriately declared the diesel fire pump inoperable after it operated for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> without a minimum flow path.
Subsequently, the pump was declared operable after a successful operability test was performed. The tracking number for this Non-Cited Violation is No. 50-263/970402(DRP). Inadequate Procedure / Instruction 42 10/13/1997 Positive.
IR 97014 NRC Operations 2A The Division 1 and 2 batteries and the residual heat removal service water system were in good material condition. Involved Management Page 7 of 9
PLANT ISSUES MATRIX
'" 8 1 M:ntic lla Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Cdumn = *SALP* ; SALP Area =
- Ope ations* ; Beginning Date = *10/1/97* : Endrng Date = '9/30S8' DATE TYPE SOURCE-ID BY SALP SMM CODES DESCRIPTION 43 10/13/1997 Positive IR 97014 NRC Operations 3A 1A Operator performance during routine operations and sunreillance activities was good, and operations personnel conducted the planned reactor power decrease in a controlled manner. However, operations personnel were unaware that a condensate storage tank level instrument was inoperable during a maintenance activity. Teamwork / Skill Level Page 8 of 9
11/23/'98 -
GENERAL DESCRIPTION OF PIM TASLE LACELS 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 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.
O CY Identification of who discovered the issue - see table.
SALP SALP Functional Area Codes - Engineering, Maintenance, Operations, Plant Support and All/Mu!!iple (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 violatons of NRC 1
Operational Performance:
ED Escalated Discretion - No Civil Penalty requirements that are being considered for A - Normal EEI' 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 Procedure for NRC Enforcement Action Licensing Licensing issue from NRR (Enforcement Policy), NUREG-1600 2
Material Condition:
Misc Miscenaneous (Emergency Preparedness Finding, etc.)
However, the NRC has not reached its final A - Equipment Condition NCV Non-Cated 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 i% modified when the final decisions A - Work Performance am made. Before the NRC makes its Strength Overall Strong Licensee Performance B - Knowledge, Ski!!s and Abilities enforcement decision, the licensee will be C - Work Environment URt" Unresolved Inspecten item provided with an opportunity to either VIO/SL-1 Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
Engineering' Design:
VIO/SL-il Notice of Violation - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-Ill Notice of Violation - Seventy Level lli conference.
B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV
- URis are unresolved items about wtiich C - Programs and Processes Weekness Overall Weak Licensee Performance 5
Problem Identification and Resolution:
the s
a acceptable item, a deviation, a A - Identification ID BY nonconformance, or a violation. However, B - AnaYs:s the NRC has not reached its final C - Resolution Licensee The licensed utility conclusions on the issues, and the PIM NRC The Nuclear Regulatory Commission entries may be modified when the final Self-Revealed identification by an event (e.g., equipment breakdown) conclusions are made.
Other Identrfication unknown
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Page 9 of 9
PLANT ISSUES MATRIX 1 /23/98 '
Mantic 2110 t
Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Cotumn = *SALP" ; SALP Area =
- Maintenance *, Begoning Date = *1olt!97*, Ending Data = *9/3n/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
9/30/1998 Positive IR 98015(DRP)
NRC Maintenance 3A 2B In general, the observed maintenance and surveillance activities, which involved systems or components such as emergency diesel generators and control rod drives, were conducted in accordance with procedures and in a professional manner.
2 9/30/1998 Positive IR 98015(DRP)
NRC Maintenance SA SB SC The licensee's investigation team was thorough and aggressive, and performed an effective root cause investigation of the offgas system problems. The conclusions reached were reasonable. Maintensnce personnel corrected equipment deficiencies identified during the investigation.
i 3
9/21/1998 Positive IR 98015(DRP)
NRC Maintenance 2B The assessment and repair of a pinhole leak on a high pressure coolant injection system steam intet line drain control valve was aggressively pursued by the maintenance and engineering departments. No similar problems were identified with other steam-Ene drain valves.
4 9/17/1998 Positive NRC Ltr 10/2/98 NRC Maintenance 1C The Monticello Year 2000 (Y2K) readiness program is comprehensive and is based on the nuclear power industry Y2K problem guidance contained in Nuclear Energy Institute (NEI)/ Nuclear Utilities Software Management Group (NUSMG) 97-07,
- Nuclear Utility Year 2000 Readiness.* The Monticello Y2K readiness prorgam is receiving appropriate management support and oversight. The licensee's corporate and Monticello plant-specific Y2K program interfaces are effectively addressing grid reliability and availability issues.
5 8/31/1998 Positive IR 98012(DRP)
NRC Maintenance 3A In general, the observed maintenance and surveillance activities were conducted in accordance with procedures and in a professional manner.
The activities involved spent fuel shuffling and work on several systems, including reactor water cleanup, standby liquid control, fire protection, main steam, emergency core cooling pump room ventilation, and high pressure coolant injection systems.
6 8/13/1998 Positive IR 98013(DRS)
NRC Maintenance 2B The establishment of performance criteria was considered acceptable.
The reiiability and unavailability performance criteria established were adequately linked to the values assun;ed in the probabilistic risk assessment. In addition, specific performance criteria were established for all standby systems to ensure adequate monitoring.
t Page 1 of 7
PLANT ISSUES MATRIX H/23/98 '
Mantic;llo Searth Sorted by Date (Descending) and SMM Codes ( Ascending): Search Column = "SALP* ; SALP Area =
- Maintenance
- Beginning Date = *10/1/97* ; Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY 0 SALP SMM CODES DESCRIPTION 7
8/13/1998 Negative IR 98013(DRS)
NRC Maintenance 4C Although a significant amount of work was performed to ensure compliar>ce with OM-1 [American Society of Mechanical Engineers, Operation and Maintenance of Nuclear Power Plant Standard, Part 1
" Requirements for Inservice Testing of Nuclear Power Plant Pressure i
Relief Devices *] for the testing of relief valves, establishment of certified correlations had not yet been sufficiently completed to close an unresolved item.
8 8/13/1998 Negative IR 98013(DRS)
NRC Maintenance 4C The periodic assessment met the requirements of the maintenance rule; however, the balancing of reliability and availability for 10 CFR 50.65 (a)(1) systems was not well-documented.
9 8/13/1998 Positive IR 98013(DRS)
NRC Maintenance SC As a result of the changes to the structural monitoring program and a better understanding of how the baseline structural inspections were conducted, the structural monitoring program was ccnsidered acceptable.
10 7/18/1998 Positive IR 98011(DRP)
NRC Maintenance 2B in general, the observed maintenance and surveillance activities were conducted in accordance with procedures and in a professional manner.
Pre-job briefings were thorough and supervisory oversight was appropriate. No concems with the technical adequacy of surveillarrce testing were identified by the inspectors.
11 5/27/1998 Negative IR 98007 Self-Maintenance 28 During the refueling outage, maintenance personnel incorrectly installed i
Revealed the switches for flow and pressure controllers in the recombiner system.
It appeared that a post-maintenance test was not completed since the licensee was not able to locate a copy of the test.
{
12 5/27/1998 Positive IR 98007 NRC Maintenance 3A The installation of the new control rod drive withdraw lines was conducted in a controlled manner as a result of good teamwork between operations, radiation protection, maintenance, and construction personnel.
13 5/27/1998 Positive IR 98007 NRC Maintenance SA General quality services (quality assurance) auditors and quality control inspectors observed several maintenance and surveillance testing activities during the refueling outage. Issues identified by the auditors were promptly communicated to licensee management and were appropriately addressed through the condition reporting or employee observation reporting systems. Good interaction between the auditors and maintenance personnel was observed. The auditors maintained an appropriate independent oversight function of maintenance activities.
Page 2 of 7
PLANT ISSUES MATRIX M/23/98 '
Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Coturnn = *SALP*, SALP Area = " Maintenance *, Beginning Date = *10/1/97*. Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 14 4/23/1998 Positive IR 98006 NRC Maintenance 2B Overall, the inservice inspection activities were conducted in accordance with appropriate procedures and the overC inservice inspection program appeared technically sound and effective.
15 4/23/1998 Positive IR 98006 NRC Maintenance 3A 28 Nondestructive examinations were performed in accordance with l
applicable procedures by qualified personnel.
16 4/23/1998 Positive IR 98006 NRC Maintenance SC 2B Corrective action to revise the inservice inspection plan to include the inspection of all reactor shell welds was implemented and effective.
17 4/17/1998 LER LER 98003 IR Licensee Maintenance 2A During a routine scheduled Amercian Society of Mechanical Engineers 98007 Section XI Code Leakage Test of the Reactor Pressure Vessel, a crack was discovered on a control rod drive withdrawl line inside the primary containment. Subsequent visible dye penetrant inspections identified indications on two other control rod drive withdrawllines. Metallurgical analysis identified the cause of the through wall crack to be chloride-induced transgranular stress-corrosion cracking originating on the outside of the pipe. All observed indications were removed (repaired) prior to retuming the reactor to power.
18 4/15/1998 LER LER 98P2 Licensee Maintenance 2A During the recent refueling outage. 7 of 8 inboard main steam isolation valve position switches were found to trip outside their acceptance range and beyond their limiting safety system setting. The purpose of the position switches is to initiate a reactor scram before the main steam isolation valves are beyond 10 percent closed. All 8 position switches were replaced with a different model position switch.
19 4/14/1998 Strength IR 98004 NRC Maintenance 2B The backlog of corrective maintenance work orders was relatively small and stable. Priority work and control room deficiencies received appropriate management and engineering staff attention. Equipment failures which led to Technical Specification limiting-conditions-for-operation were infrequent and rapidly resolved. Work was performed in a :
timely manner and was generally completed correctly the first time.
Overall, a review of the maintenance backlog indicated a strong, well-implemented maintenance program.
20 4/14/1998 Positive IR 98004 NRC Maintenance 2B 4B 3A In general, the observed maintenance and surveillance activities were i
conducted in accordance with procedures and in a professional manner.
Pre-job briefings were thorough and supervisory oversight was appropriate. Engineering personnel provided excellent support to the maintenance staff.
Page 3 of 7
PLANT ISSUES MATRIX Manticsils Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = "SALP* ; SALP Area = " Maintenance *, Beginning Date = *10/1/97*. Ending Data = '97J0/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 21 4/14/1998 Negative IR 98004 NRC Maintenance 48 The inspectors identified a weakness with the modification process in that the installation of a jumper / bypass to support replacement of a condensate service water system relief valve was considered in the associated 10 CFR 50.59 review for this modification.
22 3/23/1998 LER LER 98001 Licensee Maintenance 2A Leakage associated with three containment isolation valves caused the combined maximum flow path leakage and the main steam isolation valve leakage to exceed Technical Specification limits. This was identified during refueling outage localleak rate testing. A!! three valves were subsequently repaired.
23 2/23/1998 Negative IR 98002 NRC Maintenance 2B in general, maintenance staff's performance of observed work activities and surveillance tests was acceptable. However, maintenance personnel '
did not establish proactive foreign material exclusion control during the reactor building closed cooling water heat exchanger work activities.
24 1/21/1998 VIO/SL-IV IR 98002 NRC Maintenance 2B The work order (WO) associated with moving channel crates to the refueling floor did not contain adequate instructions, which resulted in a heavy load movement without proper evaluation. One violation (of Criterion V of 10 CFR Part 50, Appendix B) for an inadequate procedure was identified. The tracking number for this violation is No. 50-263/98002- [
03(DRP).
25 1/12/1998 Positive IR 97018 NRC Maintenance 2A 3B The material condition of equipment was acceptable. The operators interviewed were knowledgeable of degraded conditions, including an inoperable discharge canal radiation monitor and a difficult-to-move control rod drive. Teamwork / Skill Level 26 12/19/1997 LER 1R 97018 LER Licensee Maintenance SA SC 3A During a review of logic circuit surveillances per NRC Generic Letter 96-i 97014 01, " Testing of Safety-Related Logic Circuits," licensee engineering personnel identified that the Division 11 automatic depressurization system inhibit switch was not being tested as required by Technical Specifications. This issue was a Non-Cited Violation and has tracking number No. 50-263/97018-02(DRP). Self-Critical Page 4 of 7
PLANT ISSUES MATRIX ut23ms -
Monticallo Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP'. SALP Area =
- Maintenance
- Beginning Data = *10n/97*, Ending Data = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 27 11/26/1997 NCV IR 97018 NRC Maintenance 2B 18 SA Inadequate planning of surveillance test and maintenance activities by planning, maintenance, and operations personnel resulted in a reactor scram signal for 13 control rods and a reactor water level transient. The licensee initiated a thorough investigation and implemented several corrective actions. This was treated as two examples of a Non-Cited Violation (of Criterion V of 10 CFR 50, Appendix B) for failure to follow a procedure and inadequate procedure. The tracking number for this issue is No. 50-263/97018-01(DRP). Inadequate Oversight 28 11/24/1997 Positive IR 97015 NRC Maintenance 2B 2A 3B in general, work associated with selected maintenance and surveillance activities was conducted in an acceptable manner. Good foreign material exclusion controls were implemented for open systems; however, the return-to-service of the #14 residual heat removal service water pump was delayed due to workers' unfamiliarity with the seal water piping design. Involved Management 29 10/13/1997 Positive IR 97014 NRC Maintenance 2B 3A in general, the work associated with selected maintenance and surveillance activities was conducted in a profersional and thorough manner. For work on the residual heat removal service water system, excellent foreign material exclusion control as well as careful work accomplished in accordance with procedures were observed during the replacement of surge check valves. Good oversight by quality control and engineering personnel was also provided. involved Management 30 10/13/1997 Negative IR 97014 NRC Maintenance 2B 4B The planning and approval of Work Order 9501551, " Repair Interior Coating of #12 CST [ condensate storage tank]," was inadequate. The licensee initially failed to identify that operation with only one CST in service with the high pressure coolant injection (HPCI) and reactor cort:
isolation cooling (RCIC) pump suction valves lined up to the CST was in violation of Technical Specifications. In addition, the licensee aborted a routine surveillance test when the suppression pool supply valves re-opened unexpectedly. An engineer did not fully evaluate plant conditions prior to requesting the initiation of the surveillance test. The tracking number for this Unresolved item is No. 50-263/97014-03(DRP).
Inadequate Procedure / Instruction i
Page 5 of 7
PLANT ISSUES MATRIX 1/23ssy Manticalls Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Cdumn = "SALP* ; SALP Area = "Ma:ntenance' ; Beginning Date = *10/1/97* ; Ending Date = "9/30/98*
DATE
-TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 31 10/1El1997 Negative IR 97014 NRC Maintenance 28 SC The inspectors identified that the surveillance tests for HPCI and RCIC steam line isolation valves could lead to preconditioning of the valves prior to determining the "as found* valve closure times. The system engineer initiated the appropriate corrective action document to resolve the issue prior to performance of the next tests. Inadequate Procedure / Instruction Page 6 of 7
11/23/98 -
GENERAL DESCRIPTION OF PIM TABLE LAEELS A counter number used for NRC miema! 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.
O 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 Requirr ments Eels are apparent violations of NRC 1
Operational Performance:
ED Escalated Discretion - No Civil Penalty requirements that are being considered for A - Normal EE!*
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 Procedure for NRC Enforcement Action Licensing Licensing issue from NRR (Enforcement Policy), NUREG-1600.
2 Material Condition:
Misc Miscerianews (Emergency Preparedness Finding, etc.)
However, the NRC has not reached its final A - Equipment Condition NCV Non-CiteJ 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 Strength Overall Strong Licensee Performance are made. Before the NRC makes its B - Knowledge, Skills, and Abilities enforcement decision, the licensee will be C - Work Environment URt**
Unresolved Inspection item provided with an opportunity to either VIO/SL-l Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
Engineering / Design:
VIO/SL-il Notice of Violation - Seventy Lovel 11 (2) request a predecisional enforcement A - Design VIO/SL-ill Notice of Violation - Seventy Level 111 conference.
B - Engineering Support VIO/SL-!V Notice of Violation - Seventy Level IV
- URis are unresolved items about which C - Programs and Processes Weakness Overall Weak Licensee Performance 5
Problem Identi ation and Resolution:
i e
ue n ques nsa acceptable item, a deviation, a ID BY nonmnfonnanm, 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 NRC The Nuclear Regulatory Commission entries may be modified when the final Self-Revealed Identification by an event (e.g., equipment breakdown) conclusions are made.
Other Identification unknown Page 7 of 7
PLANT ISSUES MATRIX
/23/98 ;
Manticalb Search Sorted by Date (Descordng) and SMM Codes (Ascerdng): Search Column = *SALP* ; SALP kea =
- Engineering *, Beginning Date = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
9/30/1998 Negative IR 98015(DRP)
NRC Engineering 4A The safety review for a proposed modification to the condensate storage tank level detectors was considered weak because the review did not address the loss of condensate storage tank levelinstrument independence.
2 9/30/1998 Positive IR 98015(DRP)
NRC Engineering 4B Engineering personnel support to operations and maintenance activities was appropriate during this insoection period. A safety review performed by engineering personnel for replacement of a high pressure coolant injection valve was reviewed by the inspectors, who identified no concems.
3 9/30/1998 Positive IR 98015(DRP)
NRC Engineering 48 3A Engineering staff provided excellent support to the maintenance staff.
4 9/21/1998 Positive IR 98015(DRP)
NRC Engineering 4B The assessment and repair of a pinhole leak on a high pressure coolant injection system steam inlet line drain control valve was aggressively pursued by the maintenance and engineering departments. No similar problems were identified with other steam-line drain valves.
5 9/16/1998 Positive NRC Ltr 09/16/98 NRC Engineering 4B The licensee's responses to numerous NRC staff requests for additional information regarding the power uprate program were timely and of good quality, reflecting excellent work by those engineering and licensing personnel who were involved in formulating the responses.
6 8/31/1998 Strength IR 98012(DRP)
NRC Engineering 4B Engineering personnel provided excellent support to the maintenance staff during maintenance and surveillance activities involving spent fuel shuffling and work on the reactor water cleanup, standby liquid control, fire protection, main steam, emergency core cooling pump room ventilation, and high pressure coolant injection systems.
7 7/18/1998 Strength IR 98011(DRP)
NRC Engineering 4C Engineering personnel provided excellent support to the maintenance staff during routine maintenance and surveillances.
8 6/12/1998 Positive IR 98009(DRS)
NRC Engineering 3B Engineering personnel were well qualified, experienced and cognizant of work activities and issues.
9 6/12/1998 Positive IR 98009(DRS)
Ucensee Engineering 4A in most cases, design changes and modifications were weil controlled and implemented. In a few cases, as with the control room ventilation
)
system modification, the design changes created additional unanticipated problems. No significant concems were identified during the inspection even though some deficiencies and weaknesses were noted. Design and configuration controls were maintained and were adequate.
Page 1 of 6
PLANT ISSUES MATRIX 1/23/98 '
Monticalla Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Engineering *, Beginning Date = *10/1/97* ; Ending Data = '9/3098*
DATE TYPE SOURCE ID BY SALP _ SMM CODES DESCRIPTION 10 6/12/1998 URI 1R 98009(DRS)
NRC Engineering 48 The procedure for temporary modifications allowed bypass of 10 CFR 50.59 requirements for an " urgent or emergency condition" without defining or qualifying these terms, within the context of 10 CFR 50.54(x).
This item is unresolved pending demonstration of adequate controls to preclude the potential for inappropriate bypass of 10 CFR 50.59 requirements. The tracking number for this item is 50-263/98009-01(DRS).
11 6/12/1998 Positive IR 98009(DRS)
NRC Engineering 4B Overall safety evaluations and screenings were thorough, with one I
exception noted.
12 6/12/1998 Negative IR 98009(DRS)
NRC Engineering 4B Engineering support to maintenance was acceptable; however, weaknesses existed in support to preventive maintenance. In a number of cases, engineering had identified the need for additional PM tasks or the need to revise existing tasks to preclude failures and the renuired actions had not been completed and had been open for years.
13 6/12/1998 Positive IR 98009(DRS)
NRC Engineering SA identification and documentation of both internal and extemal problems were good. Employee Observation Reports were reviewed and converted <
to condition reports as appropriate.
14 6/12/1998 Negative IR 98009(DRS)
NRC Engineering SA The operating experience program provided adequate assessment of operating experience originating from both inside and outside the licensee's organization. In most cases, the information received was reviewed, evaluated and the necessary actions appropriately determined.
In some cases, however, completion of tha te9d actions was untimely and some actions had not been completeo :
- s "eral years.
15 6/12/19S8 Negative IR 98009(DRS)
NRC Engineering SA Quality trending was poor. Transmittal of daia trcMing had recently been discontinued and quarterly trending and pr%'-
- eports were no longer being prepared and distributed. Use of both.nanual and computerized trending was considered weak. There was no objective evidence that repetitive foreign material exclusion issues, noted by the inspectors, were detected and addressed by the trending program.
Page 2 of 6
PLANT ISSUES MATRIX 11/23/98 '
Monticello Search Sorted by Date (Descending) and SMM Codes (Ascend =ng): Search Column = 'SALP', SALP Area =
- Engineering * : Beginning Date = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 16 6/12/1998 Negative IR 98009(DRS)
NRC Engineering SC in most cases, actions to correct identified problems was adequate.
However, in some cases, the time required to complete actions to correct identified problems was excessive. Ninety-nine actions to correct condition report related problems had not been completed and had been open for more than two years. Although no delays in specific priority safety related items were noted, the timeliness of the actions to address the problems was considered a weakness. The closing of condition reports prior to completion of required actions obscured the length of time some issues had been open.
17 5/27/1998 Positive IR 98007 NRC Engineering 4B The license's investigation into the cause of the cracked control rod drive line was thorough. Defect indications on the line were removed or repaired. Engineering personnel provided a strong technical justification for continued operation. The initial decision to delay reactor startup was conservative and subsequently determined to be appropriate.
18 4/23/1998 Positive IR 98006 NRC Engineering 4B Engineering involvement in the oversight of inservice inspection activities and jet pump hold down beam replacement was excellent.
19 4/14/1998 Negative IR 98004 NRC Engineering SA The root cause of the February 16,1998, minor water hammer in the high pressure coolant injection piping was not aggressively pursued by engineering personnel until questioned by the inspectors. The subsequent evaluation and corrective actions were appropriate.
20 2/23/1998 VIO/SL-IV IR 98002 NRC Engineering 2B The acceptance criterion in a Technical Specification (TS)-required surveillance test did not reflect the TS requirements. The licensee had several opportunities to identify the discrepancy, including during the biennial review of the surveillance test. Also, the inspectors identified a weakness in the licensee's TS change process, in that the process did not assure that changes to TSs are reflected in related procedures in a timely manner. The incorrect acceptance criterion in a required test was a violation of 10 CFR Part 50, Appendix B, Criterion V,
- Instructions, Procedures, and Drawings.* The tracking number for this violation is No.
50-263/98002-04(DRP).
21 2/23/1998 Positive IR 98002 NRC Engineering 3A Training provided to station personnel for the inspection of new fuel bundles and channels was adequate. Engineering personne! performed a very detailed and meticulous inspection of the new fuel bundles and channels.
Page 3 of 6
PLANT ISSUES MATRIX M/23/98 -
Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP*, SALP Area =
- Engineering * ; Beginning Date = *1o/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 22 1/12/1998 URI 1R 97018 NRC Engineering 4A 28 The inspectors identified three discrepancies among the USAR (Updated Safety Analysis Report), a General Electric design specification, the plant configuration, and a surveillance test procedure for the HPCI (high pressure coolant injection) and the RCIC (reactor core isolation cooling) systems. The tracking number for this Unresolved item is No. 50-263/97018-04(DRP).
23 1/12/1998 URI IR 97018 NRC Engineering 4C The inspectors questioned whether the low pressure instruments for HPCI (high pressure coolant injection) and RCIC (reactor core isolation cooling) should be included in Technical Specification Table 3.2.1,
" Instrumentation That initiates Primary Containment isolation Functions.*
The tracking number for this Unresolved item is No. 50-263/97018-03(DRP).
24 12/19/1997 Positive IR 97018 LER NRC Engineering 48 Engineering personnel responded appropriately by confirming operability 97014 and evaluating safety significance of licensee-identified problems with the adequacy of testing the Division 11 automatic depressurization system inhibit switch (identified during a review sf logic circuit surveillances per NRC Generic Letter 96-01, " Testing of Safety-Related Logic Circuits").
25 11/6/1997 Positive IR 97015 Ucensee Engineering 48 3A Engineering personnel demonstrated an excellent questioning attitude during review of setpoint calculations for the turbine stop valve limit switch actuations. Self-Critical 26 10/17/1997 Positive IR 97015 NRC Engineering 4B SC Engineering personnel performed an acceptable operability determination for the residual heat removal service water pump motor cooler low flow condition. Comprehensive corrective actions were planned to address flow restrictions in the piping and to trend performance. Involved Management 27 10/13/1997 Positive IR 97014 Licensee Engineering 4B 3A SA An engineer demonstrated a good questioning attitude and identified that continued operation with one CST and the HPCI and RCIC suction valves aligned to the #11 CST was contrary to Technical Specifications. Self-Critical Page 4 of 6 i
PLANT ISSUES MATRIX ur23ss -
Manticzllla Search Sorted by Date (Descending) and SMM Codes (Ascendin0): Search Column = *SALP* ; SALP Area =
- Engineering * ; Beginning Date = *10df37* ; Erdng Dato = '9/3a98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION -
28 10/13/1997 Positive IR 97014 LER Licensee Engineering 4C 3A SC Engineering personnel demonstrated a good questioning attitude in 97012 identifying a vortex concem and a non-conservative Technical Specification low level setpoint for the condensate storage tanks. The licensee initiated prompt corrective actions including establishing an administrative limit and implementing procedure changes. The tracking number for the Unresolved item involving the non-conservative low level setpoint is No. 50-263/97014-03(DRP). Self-Critical 29 10/13/1997 Positive IR 97014 NRC Engineering SA 48 Engineering personnel responded appropriately to an industry event conceming potential effects of ventilation on tank levels. Self-Critical r
Page 5 of 6
11/23/98 -
GENERAL DESCRIPTION OF PIM TABLE LABELS i
A emter number used for NRC 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 CY Identrfication 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 w th 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. %c.)
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 made f
th NRC makes i Strength Overall Strong Licensee Performance B - Knowledg,
ils, and Abilities URl" Unresolved Inspection item provided with an oppo!* unity to either VIO/SL-l Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
EngineeringOesign:
VIO/SL-Il Notice of Violation - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-ill Notice of Vk>lation - 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 Weakness Overall Weak Licensee Performance 5
Pr fem en ation and Resolution:
h e e
=
s acceptable item, a deviation, a 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 NRC The Nuclear Regulatory Commission entries may be modified when the final Self-Revealed Identification by an event (e.g., equipment breakdown) conclusions are made.
Other identification unknown Page 6 of 6
PLANT ISSUES MATRIX
/23/98 -
Monticello Search Sorted by Date (Descending) and sMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Plant Support". Beginning Date = *10/1/97*, Ending Date = "9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION i
1 9/30/1998 Positive IR 98015(DRP)
NRC Plant 1C Routine observations were conducted of radiological protection and Support chemistry controls, security and safeguards activities, and fire protection facilities and equipment. No concems were identified.
2 8/31/1998 Positive IR 98012(DRP)
NRC Plant 3B SA The oral critique for the annual medical drill was self-critical and focused Support on ways to improve. The subsequent written critique accurately reflected drill observations and concems.
3 8/14/1998 Positive IR 98014(DRS)
NRC Plant 1C The gaseous effluent program collected and analyzed samples for all the Support appropriate radionuclides. The Semi-Annual Effluent Reports contained all the applicable information and listed a single abnormal liquid release i
which did not result in a discemable offsite dose. The calibrations of meteorological tower components were conducted properly.
4 8/14/1998 Positive IR 98014(DRS)
Licensee Plant 2A The PRM calibrations and functional checks were conducted Support appropriately, and no materiel condition issues were identified. The PRM operability remained high and the control functions were tested regularly.
The identification of a condenser room steam leak through increased PRM readings demonstrated that these units functioned as intended to inform the plant staff of plant problems.
5 8/14/1998 Positive IR98014(DRS)
NRC Plant 2A 1C The gaseous radwaste system functioned to maintain offsite doses from Support gaseous radioactive effluents As-Low-As-is-Reasonably-Achievable (ALARA). In addition, there were no materiel condition or operational issues with the system. The calculated offsite doses were verified by the NRC's PC DOSE program and were well below the regulatory limits.
6 8/14/1998 Negative IR 98014(DRS)
NRC Plant 3A 1C The questioning, self-checking attitude exhibited by plant staff was Support inconsistent. Although some personnel questioned anomalous data and identified significant PRM issues, other staff continued to work without sufficiently understanding written instructions for implementing plant requirements and did not exhibit a questioning, self-checking attitude as evidenced by the fact that the alarm setpoint for a main steam line radiation monitor exceeded the correct value for several months.
7 8/14/1998 Negative IR 98014(DRS)
NRC Plant SA The RP staff calibrated and tested the ARMS properly. The inspector Support verified the operability of local ARM alarms and did not identify any materiel condition issues. However, the inspector identified errors in the calibration documentation and noted that the licensee was not trending t
Out-of-Tolerance data, which may preclude the identification of potential performance problems.
Page 1 of 10
PLANT ISSUES MATRIX
"' 'S8 '
Manticzllo Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP" ; SALP Area = " Plant Support" ; Beginning Date = *10/1/97*. Ending Date = '9/30/98*
DAic TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 8
8/14/1998 Negative IR 98014(DRS)
Licensee Plant 5A The radiation protection (RP) staff identified several scaffolding items with :
Support fixed, low-level contamination outside the Radiologically Controlled Area.
The contamination did not present a health and safety hazard and there was no evidence of any release of material with detectable contamination offsite. The licensee has planned to implement corrective actions to strengthen the free release program.
9 5/27/1998 Positive IR 98007 NRC Plant 3A Radiation protection support for the control rod drive withdraw line repairs Support was excellent. Technicians were actively engaged in the job by assisting maintenance, construction, and engineering personnel.
10 5/27/1998 Positive IR 98007 NRC Plant SA General quality services (quality assurance) auditors assessed plant Support personnel performan with respect to radiological protection. Concems, such as maintenanc ersonnel feaning over a contaminated area boundary and a prot' tive clothing changeout area located over grating, were promptly and appropriately addressed. The auditors findings were similar to the inspectors
- observations.
11 4/30/1998 Positive IR 98010 NRC Plant 1C Reviewed sections of the emergency plan and implementing procedures Support were consistent with regulatory guidance. The emergency implementing procedures were very detailed and thorough. Shift Emergency Communicator notification packages and preprinted classification guideline labels were an effective enhancement to the program.
12 4/30/1998 Positive IR 98010 NRC Plant 1C Overall, the emergency preparedness program had been maintained in Support an effective state of operational readiness. Emergency response facilities, equipment, and supplies had been well maintained.
Management support to the program was apparent and interviewed key emergency response personnel demonstrated appropriate knowledge of responsibilities and emergency procedures.
13 4/30/1998 Positive IR 98010 NRC Plant 1C The inspected emergency response facilities, equipment, supplies, and Support prompt alert and notification system sirens were well maintained. Semi-annual augmentation tests have been acceptably conducted by the licensee on a quarterly basis.
Page 2 of 10
PLANT ISSUES MATRIX
"' 'S8 ~
Monticello Search Sorted by Date (Descending) ar'd SMM Codes (Ascending): Search Column = *SALP* ; SALP Area = "Ptant Support' ; Beginnirig Date = *10/1/97*, Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 14 4/30/1998 Positive IR 98010 NRC Plant 1C The emergency preparedness training program appeared effective.
Support Appropriate knowledge of emergency responsibilities and procedures was demonstrated by selected key emergency response organization personnel. All personnel reviewed were qualified for their emergency response positions. Appropriate performance was observed during a Radiation Protection / Field Team drill 15 4/30/1998 Positive IR 98010 NRC Plant 1C 5A in an actual emergency plan activation, the emergency plan was Support effectively implemented by proper classification of the event. The subsequent self-assessment was detailed and provided good assessmen's of the event, plant response, specific improvement items, and recommended corrective actions.
16 4/30/1998 Positive IR 98010 NRC Plant SA 1C The licensee's 1996 and 1997 Quality Generation Services emergency Support preparedness (EP) program audits and the 1998 program observation reports were effective and satisfied the requirements of 10 CFR 50.54(t).
The audits were of good scope and depth and the 1998 observation reports indicated an improving trend in effectiveness for the EP program related to offsite interface.
17 4/14/1998 Positive IR 98004 NRC Plant 1C Radiation protection personnel provided excellent support to Support maintenance, engineering, and operations personnel during the refueling outage. Radiation protection technicians discussed radiation fields and contamination levels during pre-job briefings and at the drywell personnel access point. The technicians monitored job-sites and provided guidance to the workers. Excellent planning and execution of the removal of highly radiated reactor water cleanup piping were noted.
18 4/9/1998 Positive IR 98008 NRC Plant 1C The ALARAT;ob piaaning for the safety relief valve topworks rebuild and Support replacement evolution was adequate. Appropriate engineering controls, dosimetry placement, and radiation protection staff visual coverage contributed to the safe and efficient execution of this job. However, the inspector also noted a lack of radiation protection staff involvement in the mockup training for the workers, as well as the absence of any feedback to the job ALARA planner from the post-job ALARA review.
Page 3 of 10
PLANT ISSUES MATRIX n/2at98 Monticello Search Sorted by Date (Descerxting) and SMM Codes (Ascending): Search Corumn = "SALP" ; SALP Area =
- Plant Support' ; Beginning Date = *10/1/97*. ErJu y Data = "9/30/
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 19 4/9/1998 Positive IR 98008 NRC Plant 1C The drywell in-service inspection activities were carefully monitored and Support controlled by radiation protection personnel and had been assigned appropriate radiological controls based on the dose rates and risk of contamination involved. The plant continued to see a benefit from depleted zinc oxide injection through reduced dose rates in the drywell.
20 4/9/1998 Positive IR 98008 NRC Plant 1C The reactor water cleanup flow element installation and pipe replacement Support job was implemented safely and eflectively. Improvements were made from lessons teamed in a previous similar evolution and effective methods were used to minimize worker dose. In addition, an appropriate level of radiation protection coverage was assigned to the job and the as- )
low-as-is-reasonably-achievable (ALARA) planning was detailed and comprehensive. The licensee's decision to include the pipe replacement in the flow element job demonstrated a commitment to future worker dose reduction.
21 4/9/1998 Positive IR 98008 NRC Plant 1C Plant housekeeping was effective in maintaining the plant relatively free of Support unnecessary materials, equipment, and debris.
22 4/9/1998 Positive IR 98008 NRC Plant 1C Radiation protection (RP) staff support of plant work was very effective in Support reducing radiological risks. In particular, the drywell entry RP staff was very active in explaining transit routes and survey results to radiation
(
workers, and the refueling floor RP staff actively enforced good RP l
practices by workers on the deck.
(
23 4/9/1998 Positive IR 98008 NRC Plant 1C Plant walkdowns revealed that radiation workers were cautious and Support conscientious of radiological hazards during outage activities. For instance, workers were careful with donning and doffing of personal contamination clothing (PCS), requested RP assistance for various tasks, were knowledgeable of their radiation work permit (RWP) requirements, and were aware of radiological conditions in their work areas.
24 3/13/1998 Negative IR 98005 NRC Plant 1C The reliability of an important security system component has not Support improved since the previous inspection. Other secunty equipment observed functioned as designed and compensatory measures for equipment failure were seldom required. Maintenance support for security equipment appeared timely and effective.
Page 4 of 10
PLANT ISSUES MATRIX "5 8 ~
Mcnticalls Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Plant Support", Beginning Date = *10/1/97*, Erwing Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 25 3/13/1998 Negative IR 98005 NRC Plant 1C Records reviewed were complete and accurate. Procedura! guidance Support was for recovery actions after loss of some specific dual security systems was weak and upgraded during the inspection. A category of material exempted from search upon entry into the protected area was questionable.
26 3/13/1998 VIO/SL-IV IR 98005 NRC Plant 1C A violation was noted pertaining to failure to adequately protect Support safeguards information on three occasions between October 9,1997 and February 17,1998. The procedures for compensatory measures for extended security computer outages will be upgraded. Protected area access control measures were effective.
27 3/13/1998 Positive IR 98005 NRC Plant 1C Security training records reviewed were complete and accurate.
Support 28 3/13/1998 Positive IR 98005 NRC Plant 1C 3A Security force performance has been consistent within the past year.
Support Security force members were knowledgeable of post requirements.
Security supervisors were active in providing good oversight of ongoing security activities. Plant personnel demonstrated a high level of awareness and compliance with security requirements during entry into the protected area.
29 3/13/1998 Positive IR 98005 NRC Plant SC 1C The self-assessment program within the security section was extensive, Support well monitored, and effective.
30 2/23/1998 Positive IR 98002 NRC Plant 1C The inspectors noted that effective radiological controls were established Support for the new fuel inspections and that radiation protection technicians provided support during maintenance and surveillance activities.
31 2/13/1998 Positive IR 98003 NRC Plant 1C P! ant housekeeping was effective in maintaining areas free of Support unnecessary equipment and debris. Radiological posting and labeling in the plant was appropriate, and station efforts to reduce instances of unsecured items crossing contaminated area boundaries were effective.
One concem was noted, however, with the plant's survey maps at access control not being updated in a timely manner.
32 2/13/1998 Positive IR 98003 NRC Plant 1C The radioactive waste processing systems, storage areas, control room, Support and radioactive materials storage warehouses were well-organized, and waste containers were properly sealed and labeled.
Page 5 of 10
PLANT ISSUES MATRIX
"' 'S8 '
Mantic;llo Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP" SALP Area = *Piant Support' ; Beginning Date = *10/1/97*, Ending Date = '9/30S8" DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 33 2/13/1998 Positive IR 98003 NRC Plant 1C The RP staff properly implemented the 10 CFR Part 61 waste Support characterization program. The staff sampled waste streams and evaluated the results of the analyses in accordance with procedures. The inspectors identified some minor problems conceming the lack of independence of the review of 1996 data.
34 2/13/1998 Misc IR 98003 NRC Plant 1C The licensee's radioactive waste program procedures were acceptable.
Support 35 2/13/1998 Positive IR 98003 NRC Plant 2A SB SC The station has had intermittent operability problems over the past Support several years with the discharge canal radiation monitor sample pump.
Licensee staff had progressed logically and expeditiously to determine the cause of the pump failures during this time period and had attempted numerous types of corrective actions without success. At the time of this inspection, plant engineering staff developed a reasonable course of corrective actions to eliminate the problem.
36 2/13/1998 Misc IR 98003 NRC Plant 2B The licensee performed periodic inspections of filtration systems Support associated with the Radwaste Building exhaust and the Reactor Water Cleanup (RWCU) system room exhaust. As the licensee was not committed to Regulatory Guide 1.140, the testing methodology was not fully consistent with the guidance contained in the regulatory guide; however, the testing was adequate.
37 2/13/1998 Positive IR 98003 NRC Plant 3B 1C The licensee's training program for plant workers handling radioactive Support wastes or materials was effective and current. Staff had appropriate educational credentials, experience, and qualifications to perform their assigned tasks.
38 1/12/1998 Positive IR 97018 NRC Plant 3A 1C The fire brigade responded promptly and appropriately during two routine Support fire drills. Good interaction between the fire brigade leader and the security force was evident. Teamwork / Skill Level 39 11/21/1997 Negative IR 97017 NRC Plant 1C Severalinstances of unsecured items crossing contaminated area Support boundaries indicated that additional attention was needed in the area of contamination control practices. These instances appeared to reflect an ongoing problem at the plant with items crossing contaminated area boundaries. Inadequate Oversight Page 6 of 10
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PLANT ISSUES MATRIX M/23/98
- Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP" ; SALP Area =
- Plant Support" ; Beginning Date = *10/1/97*. Ending Date = "9/30/98*
l DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 40 11/21/1997 Positive IR 97017 NRC Plant 1C in general, radiological posting and labeling in the plant was appropriate, t
Support though one instance of possible overposting was identified in the upper torus area, involved Management i
41 11/21/1997 Positive IR 97017 NRC Plant 1C Respiratory protection equipment was well-maintained and property Support stored. Involved Management 42 11/21/1997 Positive IR 97017 NRC Plant 1C Plant personnel requiring respirator use in the performance of their Support regular or emergency duties were properly qualified. However, one issue regarding the wearing of beards by control room personnel will be reviewed during a future inspection. Other/NA
[
43 11/21/1997 Positive IR 97017 NRC Plant 1C 3B The accessible radioactive waste storage areas, processing areas, and Support tank room; were organized, and waste containers were, for the most part, L properly se tied and labeled. Radwaste personnel were very j
knowledger.ble about radwaste systems, operations, and procedures.
Involved IGanagement i
44 11/21/1997 Positive IR 97017 NRC Plant 1C 3C The plant's new survey maps were very effective at informing radiation Support workers of plant radiological hazards and conditions. Invo;ved Management 45 11/21/1997 Negative IR 97017 NRC Plant 1C 3C 3B The respiratory protection program was generally well-implemented; l
Support however, administrative oversight of the program was minimal.
l Specifically, the radiation protection supervisor responsible for oversight of the program was tasked with many other responsibilities and, as a result, was unfamiliar with various aspects of the program. Inadequate Oversight 46 11/21/1997 Positive IR 97017 NRC Plant 2A 1C Plant housekeeping was effective in maintaining areas free of debris, and Support the station's effort to reduce the total contaminated area within the plant was successful. Involved Management 47 11/19/1997 Positive IR 97016 NRC Plant 1C The scenario for the 1997 Emergency Preparedness exercise was Support adequately challenging, and specifically designed to provide greater realism. Overali exercise control was very good. Involved Management Page 7 of 10
PLANT ISSUES MATRIX ir23n;8; Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP', SALP Area = " Plant Support', Beginning Date = *10/1/97* ; Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES l DESCRIPTION 48 11/19/1997 Positive IR 97016 NRC Plant 3A 1C Overall performance during the 1997 Emergency Preparedness exercise Support demonstrated that onsite emergency plan implementation was adequs Licensee personnel demonstrated their ability to implement the plan by correctly classifying scenario emergencies, notifying offsite agencies of the classified events, activating emergency facilities, providing protective action recommendations when warranted, and taking accident mitigation actions. Interfacility transfers of command and control of event response were orderly and timely. Teamwork / Skill Level 49 11/19/1997 Positive IR 97016 NRC Plant 3A 1C Overall, the Technical Support Center staff's performance during the Support 1997 Emergency Preparedness exercise was very effective. The Emergency Director made effective use of his staff to provide information, projections, and suggestions. He evaluated their inputs and then made rapid decisions which were then plainly commun;cated. Mitigation activities were well-prioritized. Involved Management 50 11/19/1997 Positive IR 97016 NRC Plant 3A 1C Performances of Operational Support Center management and staff Support during the 1997 Emergency Preparedness exercise were very competent. Involved Management 51 11/19/1997 Positive IR 97016 NRC Plant 3A 1C The overall performance in the Emergency Operations Facility during the Support 1997 Emergency Preparedness exercise was good. However, the lack of sufficient criteria for identifying the loss of the fuel clad fission product barrier in the Emergency Classification Guidelines led to a brief delay in declaring a General Emergency. Involved Management 52 11/19/1997 Positive IR 97016 NRC Plant 3A 1C Field monitoring teams performed well, and exhibited efficient ard timely i
Support checking and loading of equipment, as well as proficient operaaon and knowledge of their survey instrtments. The teams generally accomplished their assigned tasks; however, some were slowed down considerably by problems with communications, equipment handling, and maps. Teamwork / Skill Level 53 11/19/1997 Positive IR 97016 NRC Plant 3A 1C Performance demonstrated during the Recovery phase of incident Support response (during the 1997 Emergency Preparedness exercise),
demonstrated after a scenario
- time jump," was acceptable. Recovery discussions observed in the Technical Support Center and Emergency Operations Facility were adequate. Involved Management t
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PLANT ISSUES MATRIX "5 8f Monticalls Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP" ; SALP Area =
- Plant Support", Beginrsng Date = *10/1/97* ; Ending Date = '9/30/98*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 54 11/19/1997 Positive IR 97016 NRC Plant 3A 1C Event classifications for the 1997 Emergency Preparedness exercise Support were correct. However, there was a delayed declaration of the General Emergency. Offsite notifications and offsite protective action recommendations were correct and timely. Inplant activities were well thought out and well coordinated. Transfers of command and control were appropriately coordinated. Involved Management 55 11/19/1997 Positive IR 97016 NRC Plant SA 1C The licensee's self-assessment of the 1997 Emergency Preparedness Support exercise was comprehensive and closely mirrored the NRC evaluation team's conclusions. Self-Critical 56 10/28/1997 VIO/SL-IV IR 98003 NRC Plant SC A violation of 10 CFR 20.1502 was identified for a failure to perform an Support adequate radiological evaluation of a job prior to the start of work. This violation resulted from an incident on October 28,1997, in which an instruments and controls specialist became contaminated with radioactive resin during calibration of a pressure indicator on a radioactive waste (radwaste) system. The plant staff's immediate response to the event and the personnel dose assessment were executed properly. However, the licensee's subsequent corrective actions were not comprehensive.
The tracking number for this Severity Level IV violation is No. 50-263/98003-01(DRS).
57 10/23/1997 Negative IR 97201 NRC Plant 1C During an OSRE (Operational Safeguards Response Evaluation), the Support NRC identified that the issue and control of security keys required improvement to enhance ingress and egress during emergency conditions.
58 10/23/1997 Negative IR 97201 NRC Plant 1C During an OSRE (Operational Safeguards Response Evaluation), the Support NRC identified that the licensee should verify the effectiveness of a designated security defensive position.
59 10/13/1997 Positive IR 97014 NRC Plant 3A 1C 5A Durir'g two security training drills, good communication was established Support between field and alarm station personnel, and the guard force responded appropriately to the " events." The licensee's critiques of the drills were informative and sei!-critical. Teamwork / Skill Level i
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11/23/98
- GENERAL DESCRIPTION OF PIM TABLE LACELS A counter number used for NRC intemal editing.
DAM 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 de 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.
O 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 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 EEI*
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 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 Strength Overall Strong Licensee Performance 0w!
Skills, and Abilities rce d si e
se !! W 4
m URi" Unresolved Inspection item provided with an opportunity to either VIO/SL-i Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
Engineering / Design:
VIO/SL-It Notice of Violation - Severity Level II (2) request a predecisional enforcement A - Design VIO/SL-ill Notice of Violation - Seventy 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 Weakness Overall Weak Licensee Performance 5
Problem Identification and Resolution:
e ue e
s 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
[
NRC The Nuclear Regulatory Commission entries may be modified when the final Self-Revealed identification by an eve'rt (e.g., equipment breakdown) conclusions are made.
Other Identification unknown t
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