ML20205C485

Informs That on 990203,NRC Staff Completed PPR of Nuclear Plant.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance

ML20205C485
Person / Time
Site:	Monticello
Issue date:	03/26/1999
From:	Grant G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Wadley M NORTHERN STATES POWER CO.
References
NUDOCS 9904010225
Download: ML20205C485 (24)

Text

__ _ _ . _ _ -. . . . . _ _ __ _ __ _ ._.

W too UNITED STATES ,

% NUCLEAR REGULATORY COMMISSION REGION lli -

g j 801 wARRENVILLE ROAD e lisle. ILLINols 60532 4351

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March 26, 1999 l

Mr. M. Wadley President, Nuclear Generation Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 l l

SUBJECT:

PLANT PERFORMANCE REVIEW - MONTICELLO I

Dear Mr. Wadley:

On February 3,1999, the NRC staff completed a Plant Performance Review (PPR) of the Monticello Nuclear Plant. The staff conducts these reviews for all operating nuclear power plants to develop an integrated understanding of safety performance. The results are used by NRC management to facilitate planning and allocation of inspec'? msources. PPRs provide NRC management with a current summary of licensee performar...;e and serve as inputs to the NRC's senior management meeting (SMM) reviews. PPRs examine information since the last assessment of licensee performance to evaluate long-term trends, but emphasize the last 6 months to ensure that the assessment reflects current performance. The PPR for Monticello involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period July 18,1998, through January 31,1999. The NRC's most recent summary of licensee performance was provided in a letter of August 26,1998, and was discussed in a public meeting with you on September 9,1998.

As discussed in the NRC's Administrative Letter 98-07 of October 2,1998, the PPR provides an assessment of ' licensee performance during an interim period that the NRC has suspended its i Systematic Assessment of Licensee Performance (SALP) program. The NRC suspended its SALP program to complete a review of its processes for assessing performance at nuclear power plants. At the end of the review period, the NRC will decide whether to resume the SALP program or terminate it in favor of another process.

During this PPR assessment period, Monticello operated in a conservative, safe, and professional manner. On August 27, the Unit was taken offline to replace field brushes on the MG set. The Unit was returned to full power on August 30 and remained there until

~ September 9, when it was manually tripped because of problems in the offgas recombiner system. Full power was restored on September 16. Beginning on October 8, the Unit operated between 85 and 100 percent power for testing associated with the recently approved power rerate license amendment. On October 30, the Unit began operation at the new 100 percent power level (corresponding to 106.3 percent of the formerly authorized 100 percent level).

Overall, performance at the Monticello Nuclear Plant was acceptable. Operator performance in response to several plant transients, and during reacior startups and shutdowns and a refueling outage was very good. Minor attention-to-detail, procedure adherence, and control room formality problems were identified. Maintenance and surveillance testing activities continued to be performed well, with some minor exceptions. Equipment materia: condition, similar to the c

9904010225 990326 PDR ADOCK 0$000263 -

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M. Wadley  !

previous assessment period, was excellent. Engineering personnel provided excellent support to the maintenance staff during maintenance and surveillance test activities. Chemistry staff performance in quality assurance analyses was excellent and security staff performance remained at a high level.- Plant staff performed well during an emergency preparedness drill.

Safety system reliability / availability was high Most of the engineering effort during this period was in the power re-rate amendment. The responses to NRC requests for additional information were timely and of good quality, reflecting excellent work by engineering and licensing personnel. Tho quality and self-assessment processes at Monticello are performing well. Quality control and quality assurance activities in chemistry were excellent, and in  ;

security, the self-assessment program was varied, aggressive, and well documented. The self-assessment of an actual emergency plan activation was detailed and provided good assessments of the event, plant response, specific improvement items, and recommended corrective actions.

In the area of reactor operations, performance was consistent. Occasionalinstances of attention-to-detail, procedural adherence, and control room formality problems were noted but '

were not considered safety significant. Operator response to several plant transients and operator performance during routine operations, several reactor startups and shutdowns, refueling activities, and power re-rate implementation activities was very good, in contrast, no formal process existed for assessing control room activities during routine, steady + tate operations. However, quality assurance personnel were observed to be present Cn the control room during the refueling outage and provided appropriate independent oversight. No inspection activities beyond the core inspection program are warranted. t in the area of maintenance, performance remained consistent. The backlog of corrective maintenance work orders remains small and stable from the previous assessment period and equipment material condition remains excellent. Generally, maintenance and surveillance test activities were conducted well. The assessment and repair of a pinhole' leak on a high pressure coolant injection drain valve was aggressively pursued by the maintenance and engineering groups. The licensee's response to issues identified during an earlier Maintenance Rule inspection was good and its efforts to address the Year 2000 computer problem were comprehensive. No inspection activities beyond the core inspection program are warranted.

The area of engineering, performance was consistent. For example, the engineering support for the re-rate power ascension testing program was conducted in a careful and deliberate manner. Also, the assessment and repair of a pinhole leak on a high pressure coolant injection .

system steam inlet drain control valve was aggressively pursued by the engineering and l maintenance departments. No inspection activities beyond the core inspection program are warranted. i l

in the area of plant support, performa..ce was consistent. Programs were generally well implemented. Radiation protection, chemistry, and effluents performance remained excellent.

Security facilities and equipment were well maintained. Security force members performed their duties in an effective and competent manner on a consistent basis. Self-assessment efforts within the security department were also a strength. The emergency preparedness I

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l M. Wadley l program has been maintained in an effective state of operational readiness. Emergency response facilities, equipment, and supplies were well maintained. No inspection activities beyond the core inspection program are warranted.

Enclosure 1 contains a historical listing of plant issues, referred to as the Plant issues Matrix (PIM), that were considered during this PPR process to arrive at an integrated view of licensee performance trends. The PIM includes items summarized from inspection reports or other docketed correspondence between the NRC and the Monticello Nuclear Plant. The NRC does not attempt to document all aspects of licensee programs and performance that may be .

functioning appropriately. Rather, the NRC only documents issues that the NRC believes

)

warrant management attention or represent noteworthy aspects of performance, in addition, l the PPR may also have considered some predecisional and draft material that does not appear )

in the attached PIM, including observations from events and inspections that had occurred  ;

since the last NRC inspection report was issued, but had not yet received full review and consideration. This material will be placed in the Public Document Room as part of the normal issuance of NRC inspection reports and other correspondence.

This letter advises you of our planned inspection effort resulting from the Monticello PPR review, it 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.

Enclosure 2 details our inspection plan for the next 6 months. The rationale er basis for each inspection outside the core inspection program is provided so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing 'I and continuous nature.

We willinform you of any changes to the inspection plan. If you have any questions, please ,

contact Roger Lanksbury at (630) 829-9631. i Sincerely,  !

Original signed by l Geoffrey E. Grant, Director Division of Reactor Projects Docket No. 50-263 License No. DPR-22

Enclosures:

1. Plant issues Matrix

2. Inspection Plan See Attached Distribution .

DOCUMENT NAME: G:\MONT\lNSPPLAN8. MON

• See previous concurrences To receive a co py of this document, Indicate In the box: *C' = Copy w/o attach /enci *E' = Copy w/ attach /enet *N' = No copy OFFICE

• Rill:DRP l

• Rill:DRP l Alli:DRP l l. l NAME Kunowskildp/kic Lanksbury Grant QC/

DATE 03/26/99 03/26/99 03/80/9d/J OFFICIAL RECORD COPY

l M. Wadley supplies were well maintained. No inspection activities beyond the core inspection program are warranted. j I

Enclosure 1 contains a historicallisting of plant issues, referred to as the Plant issues Matrix (PIM), that were considered during this PPR process to arrive at an integrated view of licensee performance trends. The PIM includes items summarized from inspection ieports or other docketed correspondence between the NRC and the Monticello Nuclear Plant. The NRC does not attempt to document all aspects of licensee programs and performance that may be l functioning appropriately. Rather, the NRC only documents issues that the NRC believes '

warrant management attention or represent noteworthy aspects of performance. In addition, the PPR may also have considered some predecisional and draft material that does not appear in the attached PIM, including observations from events and inspections that had occurred since the last NRC inspection report was issued, but had not yet received full review and consideration. This material will be placed in the Public Document Room as part of the normal issuance of NRC inspection reports and other correspondence.

l This letter advises you of our planned inspection effort resulting from the Monticello PPR review. It is provided to minimbe the resource impact on your staff and to allow for scheduling conflicts and personnel availnoility to be resolved in advance of inspector arrival onsite.

Enclosure 2 details our inspection plan for the next 6 months. The rationale or basis for each inspection outside the core inspection program is provided so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature.

We willinform you of any changes to the inspection plan. If you have any questions, please contact Roger Lanksbury at (630) 829-9631.

Sincerely, Geoffrey E. Grant, Director Division of Reactor Projects Docket No. 50-263 License No. DPR-22

Enclosures:

1. Plant issues Matrix

2. Inspection Plan See Attached Distribution DOCUMENT NAME: ' G:\MONT\lNSPPLAN8. MON To receive a copy of this document, Indicate in the box: "C' = copy w/o attach /enci *E' = Copy w/ attach /enci *N' = No copy l

OFFICE Rlll:DRP l6 Rlll:DRP lB Alli:DRP l l NAME Kunowski/dp/kJc Lanksbury Wi Grant cErg DATE 030G/99 MK 03/Np/99 03/6/s@U OFFICIAL RECORD COPY

o M. Wadley cc w/encis: Plant Manager, Monticello K. Sanda, Commissioner, Minnesota Department of Public Service J. Rose, Chairman, Wright County Board The Honorable Roger Belsaas -

T. Nagorski, Chairman, Sherburne County  !

R. Wolfsteller, Administrator, City of Monticello INPO Distribution:

CAC (E-Mail)

RPC (E-Mail)

G. Tracy, OEDO w/encls Chief, NRR/ DISP /PIPB w/encls T. Boyce, NRR w/encls Project Director, NRR w/encls Project Mgr., NRR w/encls i J. Caldwell, Rlli w/encls B. Clayton, Rlll w/encls ,

R. Lickus, Rlil w/encls i SRI Monticello w/encls DRP w/encls DRS (2) w/encls i Rill PRR w/ nels

[ QD  !

PUBLIC IE ,w/encist Docket File encls [ l GREENS

/

/ \

l l

010020 R

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Unit:d Stat s Nuclear R;gulatory Comm. ission Tim.:iO m i Region Ill PLANT ISSUE MATRIX MONTICEllo By Primary Functiond Area Functional Template Date Source Area ID Type Codes item Description 01/11/1999- 1998018' Prt OPS NRC POS Pri: 1 A in general the plant was operated in a controlled and deliberate manner. Operators were knowledgeoble 3, , of current and pionned octivities and pe'tormed dutes in accordance with plant procedures.

Tec 01/11/1999 1998018 Prt OPS NRC POS Prt 18 The licensee's response to the loss of the 24 voit direct current. Dinsion 1 battery charger demonstrated Sec- M conservative decision-making and proper opplication of procedures. Technical Specifications, and temporcry modifications.

Tec 01/11/1999 1998018 Prt OPS NRC POS Prk 3A Operators were knowledgeoble and conducted themselves in o professenal manner dunng a power Sec-

• Sec:3B r s wence exW h enanogemed dWM wom cm ord control during the evolution.

Tec 01/11/1999 1998018 Prt OPS NRC POS Prt 5A Licensee reviews of industry events resulted in the identification of admnstrative control deficiencies that 3, ,' g had the potential to impact Technical Specification shift monning requirements. The inspectors noted that the licensee took corrective oct ons to ensure safety and compliance with the Technical Specifications, Tec SB reactivate one oftected license holder. and establish barriers to prevent recurrence. The inspectors reviewed the Technical Specifications and identified no impact on safety. '

01/11/1999 1998018 F::. OPS NRC POS Prt SA The operc+ ions committee (the onsite review committee) meeting met the stoffing requirements of Technical Sec: ENG Sec.*

S ec fication 6 2 B. During review of the proposed test for pressurizing the HPCI discharge line to evoluote  ;

the ettect of the line on steam chose temperatures, the committee members asked detailed and probing Tec questions. This questioning resulted in the decision to revise and resubmit the test. I 11/30/1998 1998016 Prt OPS NRC POS Pri l A 10 general, the plant was operated in o contro!!ed and deliberate manner. Operators were knowledgeable 1 3 , " 3 of Current and planned OCtivlt es and octed in a professional manner The inspectors noted one minor  ;

instance of on operator not highlighting a discrepont tog entry os recommended by stofion procedures. "

Tec 11/30/1998 1998016 Prt OPS NRC POS Prt 1 A A power reduction to o!!ow maintenance on o recirculation pump motor generator set was performed well Sec- Sec- M with a thorough pre-evolution briefing. close supervisiert and smooth reoctivity manipulations.

Tec 11/30/1998 1998016 Prt OPS NRC POS Prt 2A Material condition of the 125 volt direct current electrical system and t'e high pressure coolant injection 3 ,c, 3 system was good. No concerns were identified by the inspectors.

Tec i 11/30/1998 1998016 Prt OPS NRC POS Prt 1A The rerote power ascension testing program was conducted in a careful. deliberate manner. The See: ENG Sec:48 ss cioted test procedure was well written and properly followed. Numerous licensee Groups provided i timely support of the program.

Tec 4C  !

item Type (Compliance. Followup,Other). From 10/01/1998 To 01/31/1999 '

_..___m.-.___._-___________._________________!_ __m__ _ _ _ - _ .

Poge: 2 of 6 Dole:03/22/1999 -

United Stat s Nuclear Regulatory Commission n m e:i0 49:ii negion in PLANT ISSUE MATRIX MONTICELLO By Primary Functionc! Area Functional Templote Date Source Areo ID Type Codes item Description 10/08/1998 1998015 Prt OPS NRC POS Prt 3A The Ecensee began its power oscension test program. Operations personnel conducted testog in o Sec* ' *" # # * *

• Sec*4B in the main tu%ne pressure reguionng system and the teensee took conservative action to delay the testog Tec SA until the cause of the unexpected response was determned 01/11/1999 199S018 Pri: MAINT NRC POS Pri: 2A Cbservations of materici condition mode during wo!kdowns of the control rod drive and stondby liquid control systems revealed no deficiencies.

Sec- Sec-Tec 01/11/1999 1998018 Prt MAINT NRC POS Prt 2A Maintenance to remove inappropriate factory-instoned jumpers on o reactor water cleanup isolation ;ogic  ;

Sec- Sec*3A circuit boord was conducted by knowWdgeable technicions in occordance with approved procedures.

Communications among maintenance supervision. technicians, and plant operators was thorough.

Ter: 3B 01/11/1999 1998018 Prt MAINT NRC POS Pri:2A A review and wolkdown of the control rod drive hydroutic system indicated that the system was being 3,c.* e nne ccohe NM mcehs See: 3B and maintenance rule requirements. The licensee wrote o condition report to resolve on incongruity Ten SA between the control rod occumulator Technical Specification and the ossociated basis.

01/11/1999 1998018 Pri: MAINT NRC POS Prt 2B During maintenonce on a control rod drive pump discharge check volve. the system engineer provided Sec: ENG Sec: 3A oppr pri e supp rt to the maintenance activity. Mechanics stopped work and consulted with supervision when unexpected conditions a ose.

Ten 4B 01/11/1999 1998018 Prt MAINT NRC POS Pri: 28 Observed routine maintenance and surveitlance activities. which involved systems or components, including Sec: ENG the control rod drive system and reactor recirculation pump motor generator sets, were conducted in Sec 4B accordance with procedures and in o professionci manner.

Ten j

01/11/1999 1998018 Prt MAINT NRC POS Prt 2B During surveillance testing of the stondby liquid control system. operators were knowledgeoble of their ,

See: OPS See: 3A ss gned duties. Good peer-checking was noted. Operotors responded promptly to on unexpected roped <

increase in pump dischcrge pressure during stondby liquid control system surveillance testing and property Ten notified supervision.

I1/30/1998 1998016 Prt MAINT NRC POS Pri:2B in general the observed maintenance and survei!!cnce activities, which involved systems or components. i See: ENG See: 3A s N y vesve cooM @ch Wem W N WM M cM eMM sysMm. we i conducted in occordance with procedures cM in a professional manner.

Tec i 01/11/1999 1998018 Pit ENG NRC POS Prt 3B System engineers for the stondby liquid control and control rod drive hydraulic systems were cognizont of the

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current condition of and concerns for their respective systems.

Tec 48 i

ltem Type (Compliance, Followup.Other). Frorn 105)1/1998 To 01/31/1999 '

i

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Page: 3 of 6 Date: 03/22/1999 -

United States Nuclear Regulatory Comm ,Gsio' n Tim.: iO , n iregion m PLANT ISSUE MATRIX MONTICELLO By Primary Functional Area Functional Template Date Source - Area ID Type Codes tiem Description 01/11/1999 1998018 Prt ENG NRC POS Prt 4B System engineers provided oppropriate support to operations and maintenance activities.

See: See:

Tec 01/11/1999 1998018 Prt ENG NRC POS Prt 4B Observed routine maintenance and surveillance activitet which hvotved systems or components, includrng Sec: MAINT the control rod drive system and reactor recirculation pump motor generator .,ets were conducted in Sec:3A occordance with procedures and in a professonal manner Engheering stoff provided appropriate support Tec to the maintenance staff.

01/11/1999 199S018 Prk ENG NRC POS Prt 4B During maintenance on a control rod drrve pump dischorge check volve, the system engineer provided Sec: MAINT See: 3A

• 8"PP U *U Tec 11/30/1998 1998016 Prt ENG NRC POS Prt 3A Engineering personnel support to operations and maintenance activities, including the ottempt to 6dentify

'See: Sec:48 s r o sedleoQ W @et was omWe dur@s WMgM Tec 11/30/1998 1998016 Prt ENG NRC POS Prt 3B The system engineers were cognizont of the current condition and concems ossociated with *he 125-volt Sec: e m en e col Wem MM Wrem codon @Mm system.

Sec:4B Ter 01/11/1999 1998018 Prt PLTSUP NRC POS PrtIC During normal resident inspection activities, routine observations were conducted in the orecs of rodiction Sec- Sec.

protection, security, and fire protection. No deficiencies were identified.

Tec 12/18/1998 1998019 Pri: PLTSUP NRC POS Pri: IC Implementation of the Radiological Environmental Monitonng Program (REMP) was effective and no Sec: Sec:

dscernible impoCf on the environment from plant operations wos idenhfed.

Tec 12/18/1993 1998019 Prt PLTSUP NRC POS Pri: IC Ptont wotor quality and fuelintegrity remained excellent. and chemistry stoff used the Data Acquisiton Sec- Sec. System to effectively morutor various chemistry porometers throughout the facility.

Ter 12/18/1098 1998019 Pri: PLTSUP NRC POS Pri: IC The rodiction protectu , toff property implemented radiologico! controls ord assessed radiological S Sec, conditions within the plant, with limited exceptions, so os to odequately limit dose 'o plant personnel Tec item Type (Compliance. Followup,Other). From 10/01/1998 To 01/3t/1999

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Unit d States Nuclear Regulatory Comm,ission Time: iO:49:ii region iii PLANT ISSUE MATRIX MONT! CELLO By Primary Functional Area Functional Template Date Source Area ID Type Codes item Description

'12/18/1998 1998019 Prt PLTSUP NRC POS Prt IC The inline instrumentation system remained operabia. os the licensee had no problems ':ollecting dato and Sec- Sec.-

on lyzing somptes used in verifying operability during the period Tec 12/18/1998 1998019 Prt PLTSUP NRC POS Prt1C The post-occident sompting system (PASS) was montained operable. and with one minor procedure Sec-* Sec'-

change to o!!ow the use of an 18 gouge needle for sample collection. the licensee had no problems collecting and ono!yzing samples.

Tec 12/18/1998 1998019 Pri: PLTSUP NRC POS Pri: IC Chemistry personnel were knowledgeobie of their various responsibilihes. demonstrated good laboratory Sec" Sec.' practice, and disolayed ownership of chemistry deportment octivities. The onolytical performance of the chemistry technicions (cts) was excellent os evidenced by blind OC data for o variety of onclytes.

Tec 12/18/1998 1998019 Pri: PLTSUP NRC POS Prt IC Performance in the interComparison programs for chemistry and radiochemistry was excellent. Analytical Sec* Sec'. instrumentation generally remained within acceptable control porometers. Chemistry stoff effectively reviewed bioses related to nstrument cons +oncy and took oppropriate actiort if required.

Tec 11/30/1998 1998016 41 Pri: PLTSUP NRC V 0 !V PrtIC The fire brigade training requirements of plant procedure MWO8.01.01 were not correcify implemented. A Sec-

• Sec.*

review by plant personnel of a similar finding of Prairie Island could have identified this issue earlier. A Technical Specification violation for a failure to follow a fire protection procedure was cited. The trocking Tec number for the violation is 50-263/9801641(DRP).

11/11/1998 1998016 Prt PLTSUP NRC POS Prt IC During performance of on emergency preparedness drill notifications were promptly mode and technical Sec- ' Sm M support center stoffing was timety. Also good team work was noted between the various emergency resporbe groups. A minor instonce of a senior member of on organization not relieving o junior member os Tec recommended by station procedures was noted.

10/30/1778 1998017 Prt PLTSUP NRC POS Pri: IC Security facilities and equipment observed by the inspector functioned os designed. except for radio Sec*- Sec-*

communications with the Local Low Enforcement Agency (LLEA). Compensatory measures 'or security equipment were seldom required and maintenance support oppeared to be timely.

Tec 10/30/1998 1998017 Prt PLTSUP NRC POS Pri: IC Records and documents reviewed were complete and occurate. Minor deficiencies were noted in Sec-

• Sw.- procedures for documenting loss of communicohon with the Local Low Enforcement Agency (LLEA). and implementanon of 10 CFR 50.54(x). Procedures for secunty equipment testing were detailed ond equipment Tec observed was tested in o:Cordonce w:th the procedures IC/30/1998 1098017 Pri: PLTSUP NRC POS Prt TC Security force members were knowledgeoble of post requirements and performed duties in a professional.

Sec: Sec:

eMec e competed meer on a cmh Ws.

Ter:

Item Type (Comt ance. Followup.Other). From 10/01/1998 To 01/31/1999

. Pogo: 5 of 6 Date: 03A/1999- .

United States Nuclear Regulatory Comm. -ission rime: io:49;ii

. negion c . PLANT ISSUE MATRIX MONTICFLLO . By Primary Functional Area Functional Template Dole Source Area ID Type Codes item Description 10/30/1WS 1W8017 Prt PLTSUP NRC POS PrtIC Security selfossessments were a strength. The self-cssessment program was varied oggressive. and wet documented. Findings were effectively documented and corrective actions were implemented timey -

Ter:

Item Type (Compliance. Followup,Other). From 10/01/1998 To 01/31/1999

Page: . 6 of 6 -

Date: 03/22/1999 . .

- United States Nuclear Regulatory Comm. .ission Tim.: iO 4,:ii PLANT ISSUE MATRIX By Primary Functional Area Legend Type Codes: Template Codes: Functional Areas-BU Bulletin IA Normal Operations OPS Operations CDR Construction IB Operations Dunng Transients MAINT Maintenance DEV Deviction IC Programs and Processes ENG Engineering eel Esectated Enforcement item 2A Equipment Condition PLTSUP Plant Support IFl inspector follow-up item 2B Programs and Processes OTHER Other LER Ucensee Event Report 3A Work Performance UC Ucensing issue 3B KSA MISC PAscellaneous 3C Work Environment MV Minor Violation 4A Design NCV NonCited Violation 4B ~ Engineering Support  !

NEG Negative AC Programs and Processes l NOED Notice of Enforcement Discretion - SA identification i NON Notice of Non-Conformonce 5B Analysis P21 Port 21 SC Resolution POS Positiva ID Codes:

SGI Safeguard Event Report NRC NRC STR Strength Self Self-Reveoled URt Unresolved item Ucensee Ucensee VIO Vioiotion WK Weckness Eels are apparent violations of NRC Requirements that are being considered for escdoted enforcement action in occordance wth the "Generd Statement of Policy and Procedure for NRC Enforcement Actiorf (Enforcement Policy). NUREG-1600. However, the NRC has not reached its find enforcement decision on the issues identified by the Eels and the PIM entries may be modified when the finol decisions are mode.

URis are unresolved items about which more information is required to determine whether the issue in question is on oc( .e item, o deviation, o nonconformance, or o violation, A URt may otso be o potential viototion that is not likely to be considered for escdoted enforcement action. h ever, the NRC tos not reached ..s find conclusions on the issues. and the PIM entries may be modified when the find conclusions are mode.

Item Type (Compliance.Foilowuo.Other), From 10/01/1998 To 01/31/1999

PLANT ISSUES MATRIX 3/23/99

• Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = *SALP" . SALP Area = " Operations

• Beginning Date = '7/18/98* , Ending Date = '9/30,98*

1. DATE TYPE SOURCE ' ID BY SALP SMM CODES DESCRIPTION 1 9/30/1998 Positive IR 98015(DRP) Licensee Operations 2A 5A 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 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.

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 reostablished. All control rods fully inserted, no safety relief valves lifted, all equipment responded as required. A group 2 and group 3 primary containment isolation signal was produced from the post-scram response.

5 9/9/1996 Jositive 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 or three systems reviewed by the inspectors was good:

the combustible gas control system, the high pressure coolant injection system, and the residual heat removal service water system. No concerns 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 concerns were noted.

Page 1 of 4

/23S9-PLANT ISSUES MATRIX Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP" , SALP Area = "Operatons' , F .c '7/18/98* , Ending Date = '9/30,98*

1. 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 planead 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 considered to be poor practices in a nuclear power plant contrc8 room.

8 8/31/1998 Strength IR 98012(DRP) NRC Operaticas 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 adherenca.

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 restcration* 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 Negative IR 98011(DRP) Licensee Operations 1A Overall, operators were attentive to par.els; 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.

11 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.

12 7/18/1998 Negative IR 98011(DRP) NRC Operations 1A Operations personnel did not enticipate that steam chase area temperatures would exceed procedurallimits. This discTpancy was not identified during panel walkdowns since this parameter was recorded only once during the shift, early in the morning. Operations personnel immediate corrective actions, which included increased monitoring and obtaining engineering personnel support, were acceptable.

Page 2 of 4

a

/23/99-PLANT ISSUES MATRIX Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Saarch Column = *SALP" , SALP Area = ' Operations * , Beginning Date = '7/18/98* , Ending Date = '900,98*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 13 7/18/1998 Positive IR 98011(DRP) NRC Operaticas 1B Operations personnel responded promptly and appropriately to a reactor power transient caused by thunderstorm-induced disturbances to the electrical distribution grid.

14 7/18/1998 NCV IR 98011(DRP) Licensee Operations 1B 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 dentified and corrected violation is being treated as a Non-Cited Violation, consistent with Section Vll.B.1 of the NRC Enforcement Policy (NCV 50-263/98011-02(DRP) 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 :ndustry 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.

Page 3 of 4

3/23/99-GENERAL DESCRIPTION OF PIM TABLE LABELS

1. A counter number used for NRC internal 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 NP.C Inspection Report or LER for Licensee Event Report.

10 BY Identification of who discovered the issue - see table.

SALP SALP Functional Area Codes - Engineering, Maintenance. Operations, Plant Support and All/Muttiple (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 Lic nsing Licensing issue from NRR 2 Material Condition:

(Enforcement Policy), NUREG-1600.

Mirc 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 Licenseo Performance identified by the Eels and the PIM entries 3 Human Performance:

Pzsitive Individual Good Licensee Performance may be modified when the final decisions A - Work Performance Strength Overall Strong Licensee Performance are ma& Bdom me NRC makes its B - Knowledge, Skills, and Abilities enforcement decision, the licensee will be URI, Unresolved Inspection item C - Work Environment provided with an opportunity to either VIO/SL-l Notice of Violation - Severity Level I (1) respond to the apperent violation or 4 Engineering / Design:

VIO/SL-Il Notice of Violation - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-III Notice of Violation - Severity Level 111 conference. B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV ** UR!s are unresolved items about which C - Programs and Processes Wmkness * ""

Overall Weak Licensee Performance '5 Pr blem entification and Resolution:

wh her h sue n ques on s a acceptable item, a deviation, a ID BY nonconformance, or a violation. However, B- AnaYsis the NRC has not reached its final C - Resolution Licinsee 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 4 of 4

PLANT ISSUES MATRIX 3/23e Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP" , SALP Area = " Maintenance

• Beginning Date = '7/18/98* , Ending Data = "9/30/98" l

l# 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 rnaintenance 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. Maintenance personnel corrected equipment deficiencies identified during the investigation.

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 inlet line drain control valve was aggressively pursued by the maintenance and engineering departments. No similar orablems were identified with other steam-line 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 surveil!ance 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 reliability and unavailability performance criteria established were adequately linked to the values assumed in the probabilistic risk assessment. In addition, specific performance criteria were established for all standby systems to ensure adequate monitoring.

Page 1 of 3

PLANT ISSUES MATRIX /23/99-Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP" , SALP Area = ' Maintenance * , Beginning Date = '7/18/98* , Ending Cate = '9f30/98*

1. DATE TYPE SOURCE ID BY SAIP SMM CODES DESCRIPTION 7 8/13/1998 Negative IR 98013(DRS) NRC Maintenance 4C Although a significant amount of work was performed to ensure .

compliance with OM-1 [American Society of Mechanical Engineers, Operation and Maintenance cf Nuclear Power Plant Standard, Part 1,

" Requirements for Inservice Testing of Nuclear Power Plant Pressure 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 50 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 considered 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 surveillance testing were identified by the inspectors.

Page 2 of 3

3/23/99-GENERAL DESCRIPTION OF PIM TABLE LABELS

1. A counter number used for NRC internal 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 Inspectior 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 comidered for A - Normal eel

• Escalated Enforcement Issue - Waiting Final NRC Action escalated enforcement actior . > .1ccordance B - During Transients LER License Event Report to the NRC with the " General Statement of Policy and C - Programs and Processes Lic?nsing Licensing Issee from NRR Procedure for NRC Enforcement Action (Enforcement Policy), NUREG-1600. 2 Material Condition:

Mirc 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:

Pwitive Individual Good Licensee Performance may be modified when the final decisions A - Work Performance Str:ngth Overall Strong Licensee Performance a ma em e NRC makes its B - Knowledge, Skills, and Abilities Unresolved Inspection item enforcement decision, the hcensee will be URl" C - Work Environment 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 - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-ill Notice of Violation - Severity Level lli conference. B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV " URIs are unresolved items about which C - Programs and Processes W:n kness Overall Weak Licensee Performance wh e th e e s 5 Problem Identification and Resolution:

acceptable item, a deviation, a A - Identification nonconformance, or a violation. However, B - Analysts ID BY C - Re ,olution the NRC has not reached its final Lic"nsee 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 3 of 3

PLANT ISSUES MATRIX 3/2 m -

Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP' , SALP Area =

• Engineering * , Beginning Date = '7M8!98* , Endng Date = '9f30/98*

1. 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 level instrument independence.

2 9/30/1998 Positive IR 98015(DRP) NRC Engineering 4B Engineering personnel support to operations and maintenance activities was appropriate during this inspection 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 concerns.

3 9/30/1998 Positive IR 98015(DRP) NRC Engineering 4B 3A Engineering staff provided excellent support to the maintenance staff.

4 9/21/1998 stive 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 stearrJne 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 powe: uprate program were timely and of good quality, reflecting excellent wock by those engineering and licensing personnel who were involved i'1 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 cooiing 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.

Page 1 of 2

^

3/23/99-GENERAL DESCRIPTION OF PIM TABLE LABELS

1. A counter number used for NRC intemal editing.

The date of the event or significa.4 issue. For those items that have a clear date of occurrence use the actual date. If the actua! 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 GY 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 Meetmg Codes - see table.

DESCRIPTION Octails 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 Lic:nsing Procedure for NRC Enforcement Action Licensing Issue from NRR 2 Material Condition:

(Enforcement Policy), NUREG-1600.

Mi?c 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:

Po:itive Individual Good Ucensee Performance may be modified when the final decisions A - Work Performance Strength Overall Strong Licensee Performance are m de. Before the NRC makes its B - Knowledge, Ski!!s, and Abilities enforcement decision, the hcensee will be URI'* Unresolved Inspection item C - Work Environment 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 - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-ill Notice of Violation - Severity Levellli conference. B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV ** UR!s are unresolved items about which C - Programs and Processes W mkness Overall Weak Licensee Performance 5 Problem Identification and Resoluhon:

wh e sue q es o s acceptable item, a deviation, a nonconformance, or a violation. However, B - Analysis ID BY C - Resolution the NRC has not reached its final Licrnsee The licensed util:ty 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.

Othrr Identification unknown Page 2 of 2

" S" PLANT ISSUES MATRIX Monticello Search Sorted by Dat t (Descending) and SMM Codes (Ascending): Search Column = *SALP" SALP Area =

• Plant Support

• Beginning Date = '7/1&98* , Ending Date = '9/30/98*

1. DATE TiPE SOURCE ID BY SALP SMM CODES DESCRIPTION 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 980PNoi NRC Plant 3B 5A 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 '

which did not result in a discemable offsite dose. The calibrations of rneteorological 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 apppriately, and no materiel condition issues were identified. The PRM

• operability r071ained 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-Reasonab!y-Achievable (ALARA). In addition, there were no materiel condition or operational issues with the system. The calculated offsite doses were venfied 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 rnain 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 identif, any materiel condition issues. However, the inspector identified erron in the calibration documentation and noted that the licensee was not trending Out-of-Tolerance data, which may preclude the identification of pc tential performance problems.

Page 1 of 3

PLANT ISSUES MATRIX /23/9F Monticello Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP" , SALP Area =

• Plant Support' , Beginrung Date = '7/18/98* , Ending Date = '9/30/98*

1. DATE 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.

Page 2 of 3

3/23/99-GENERAL DESCRIPTION OF PIM TABLE LABELS

1. 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 thy date

~

the issue was identified. For issues that do not havc an actual date or a date of identification, use the LER or inspection report date.

TYPE The categorization of the issue - see the TYPE ITEM CODE table.

SOURCE- The document that contains the issue information: IR for NRC Inspection Report or LER for Licensee Event Report.

ID BY Identification of who discovered the issue - see table.

SALP SALP Functional Area Codes - Engineering, Maintenance, Operations, Plant Support and A !/ 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 conside ed 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 Lic nsing Licensing issue from NRR Procedure for NRC Enforcement Action (Enforcement Policy), NUREG-1600. 2 Material Condition:

Mire 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 Negstive Individual Poor Licensee Performance identified by the Eels and the PIM entries 3 Human Performance:

Po:itive Individual Good Licensee Performance may be modified when the final decisions A - Work Performance Str ngth Overall Strong Licensee Performance am mah Befom h E makes its B - Knowledge, Skills, and Abilities enforcement decision, the l,icensee will be URI, Unresolved Inspection item C - Work Environment provided with an opportunity to either VIO/SL-l Notice of Violation - Severity Leve . I (1) respond to the apparent violation or 4 Engineering / Design:

V!O/SL-il Notice of Violation - Severity Level II (2) request a predecisional enforcement A - Design VIO/SL-ill Notice of Violation - Severity Level ill conference. B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV ** URis are unresolved items about which C - Programs and Processes Wu:kness " ' "

Overall Weak Licensee Performance wf e sue ques s 5 Problem entification and Resolution:

acceptable item, a deviation, a nmcmformance, or a violation. However, B - Analysis ID BY C - Resolution the NRC has not reached its final Lietnsee 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.

Ottnr ident!fication unknown Page 3 of 3

MONTICELLO INSPECTION I ACTIVITY PLAN IP - Inspection Procedure T1 - Temporary Instruction Core - Minimum NRC Inspection Program (mandatory all plants)

Regional Initiative - Discretionary Inspections NUMBER OF TYPE OF INSPECTION NRC INSPECTION /

/ TITLE I PROGRAM AREA IN""'9CTORSI PLANNED DATES ACTIVITY-ACTIVITY  !! i' DUALS COMMENTS IP71001 Licensed Operator Requalification 2 March 8 - 12,1999 Core IP82301 Emergency Preparedness 4 June 21 - 25,1999 Core IP82302 Exercise IP83750 Radiation Protection, Solid 1 June 21 - 25,1999 Core IP86750 Radwaste Licensed Operator Examination 2 August 23 - 27,1999 IP64704 Fire Protection 1 TBD @ Core Notes:

@ TBD - Date to be determined.