IR 05000423/1999007

Insp Rept 50-423/99-07 on 990614-0715.Violations Noted & Being Treated as Ncvs.Major Areas Inspected:Review of C/A Program Using IP 40500, Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems

ML20211J003
Person / Time
Site:	Millstone
Issue date:	08/27/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20211J002	List: IR 05000423/1999007 ML20211H997
References
50-423-99-07, NUDOCS 9909030015
Download: ML20211J003 (73)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION I

Docket N License N NPF-49 Report N /99-07 Licensee: Northeast Nuclear Energy Company Facility: Millstone Unit 3 Dates: June 14 through July 15,1999 Inspectors: W. Raymond, Team Leader, Division of Reactor Safety (DRS)

R. Urban, Assistant Team Leader, Division of Reactor Projects (DRP)

P. Cataldo, Resident inspector, Millstone 3, DRP D. Dempsey, Reactor Engineer, DRS L. Scholl, Senior Reactor Engineer, DRS J. Carrasco, Reactor Engineer, DRS P. McKee, Contractor Approved By: James C. Linville, Director Millstone inspection Directorate g9030015990827 A

G K 05000423 PDR

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EXECUTIVE SUMMARY Millstone Unit 3 NRC Inspection Report 50-423/99-07 During the weeks of June 14 and June 28,1999, an inspection team reviewed the corrective 1 action program using Inspection Procedure 40500, " Effectiveness of Licensee Controls in Identifying, Resolving, and Preventing Problems." The team assessed the effectiveness of the safety conscious work environment using Inspection Procedure 40001, " Resolution of Employee Concerns." The inspection results, summarized in Attachment 1, were provided at public ,

meetings conducted on July 15,1999, at the Millstone Nuclear Power Station Training Center, I and before the Connecticut Nuclear Energy Advisory Committee in Waterford, C PROBLEM IDENTIFICATION, EVALUATION AND CORRECTIVE ACTION The licensee continued to implement a high volume, low threshold problem reporting syste Opportunities for improvement were noted in identifying discrepancies and initiating condition reports (CRs) for ineffective corrective actions. Management set clear expectations on corrective action program performance goals. The quality of the root cause investigations was acceptable; however, some investigations did not identify all causes for the even Consequently, corrective actions were not always comprehensive. In general, corrective actions were effectively implemented. Opportunities for improvement were noted in examples

- where corrective actions were ineffective, such as those related to organizational changes. The implementation of the design change for the recirculation spray system sump pumps was poor and corrective actions were ineffective on several occasions. The inadequate design change and corrective actions associated with these pumps are violations of the requirements of 10 CFR 50 Appendix B, Section ill, " Design Control," and Section XVI, " Corrective Action,"

respectively. These two violations are being treated as non-cited Violations, consistent with Appendix C of the NRC Enforcement Policy. (1.6)

The licensee had an excellent system to track the recovery backlog through an effective use of key performance indicators (KPI). The change in backlog management plan commitments was supported by a screening process. NNECO was making progress to implement a 12-week -

rolling maintenance planning and scheduling program. The backlog of risk-significant corrective maintenance was being reduced. The licensee had developed tools to track the completion of corrective actions and assignments, which were effectively used to trend performance. One area for improvement was to assure the KPI for maintenance adequately shows progress in reducing the backlog. (1.6)

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The corrective action program was implemented effectively in the maintenance area.

Maintenance rule corrective action plans for the auxiliary feedwater, service water, and high

< pressure injection systems were properly developed and effectively implemented. The

! implementation of the operability determination process, as well as the corrective actions for l items important to safety, were effective. One area for improvement was the licensee's failure to j- evaluate all relevant safety-related breakers for continued operability. The opeiator workaround I

process was effectively implemented, such that the burden on operators was minimized, and an adequate interface existed with the corrective action program for resolution. The licensee had il

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the capability to identify CRs at Millstone 1 that would impact the operation of Millstone 2 and Millstone 3 through an effective use of the system readiness report that identified common systems, the operation manual on system interaction, and the technical requirement manua (2.2)

The self-assessment process was critical, and effectively contributed to problem resolution. The operations work observation program had the elements to be an effective tool to improve performance.' The Millstone 3 maintenance organization performed well-planned and self-critical assessments of several programs. The Employee Concernt. Program's (ECP) self-assessments were generally good and usually critical of the subject areas audited. The self assessment schedule was an appropriate tool to track initiation of self-assessment Engineering self-assessments were generally acceptable; however, the corrective actions associated with some assessment findings were narrowly focused. (3.1)

The Nuclear Oversight's audit of corrective actions was effective. The Plant Operations Review Committee and Station Operations Review Committee were effective in fulfilling the )

requirements of technical specifications, and had appropriately identified, tracked and closed out ;

issues raised during the meetings. The Independent Safety Engineering Group performed the '

functions required by Unit 3 technical specifications.' Evaluations were performed in appropriate areas, detailed recommendations were provided and good follow-up of corrective actions was performed. The industry operating experience program was being implemented effectively. The Nuclear Safety Assessment Board was providing effective oversight of Millstone activities, including a thorough assessment and oversight of the recently completed refueling outage at Unit 3. (4.7)

PROGRAMS TO RESOLVE EMPLOYEE CONCERNS The Employee Concems Program (ECP) organization continued to possess the independence, resources and management support to perform thorough, unbiased investigations of employee concerns. Employee surveys, assesst.c.nts and team interviews indicated that the majority of employees were willing to raise concems. Generally, the team observed a healthy safety conscious work environment at Millstone. As part of the review of corrective actions, the team queried employees regarding their willingness to raise concems to management. Based on this limited survey, employees indicated no reluctance to raise safety concems. In particular, employees indicated that they felt comfortable raising issues through the corrective action processes. However, there was an indication that some workers did not want to be obstacles to meeting schedules and deadlines, and another indication that the on-going reduction in the number of supervisors (supervisory cascade) might have some influence on the ease for potential supervisors to raise issues. (5.5)

The ongoing supervisor cascade, the contracting of Entergy to manage the decommissioning of Unit 1, the planned staff reductions in contractor and licensee positions, and the consideration of a revised pay structure represented significant personnel impacts and a potential challenge to the safety conscious work environment. With these major activities, the site's ability to maintain and monitor the safety conscious work environment will be significantly tested. The Human Services organization, in coordination with other organizations, had recognized these challenges, Taking advantage of the SCWE organization and its prmesses, the licensee had initiated actions to mitigate the impact of these changes and their impact. (5.5)

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. SUMMARY Meetings were held periodically with licensee management during this inspection to discuss inspection observations and findings. A summary of preliminary findings was also discussed at the conclusion of the on-site inspection on July 2,1999. Public meetings were held on July 15,1999 at the Millstone Training Center, and before the Connecticut Nuclear Energy Advisory Committee in Waterford, Ct, to discuss the team's findings and conclusions. The slides used at the public meetings are included as Attachment 1 to this repor )

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PARTIAL LIST OF PERSONS CONTACTED D. Amerine VP Engineering Services R. Necci VP Nuclear Oversight and Regulatory Affairs S. Scace Director Nuclear Oversight P. Grossman Director Plant Engineering S. Heard Manager, independent Review Team D. Smith . Manager, Regulatory Affairs W. Watson Regulatory Affairs D. Harris Regulatory Affairs M. Gentry Director, Human Performance and Development D. McCracken . Assistant Unit Director P. Prezkop Manager, Employee Concerns Oversight Panel T. Bums Director, Employee Concerns Program INSPECTION PROCEDURES USED IP 40500 Effectiveness of Controls for Identifying, Resolving, and Preventing Problems IP 71707 Plant Operations IP 92901 Follow-up - Operations ITEMS OPENED, CLOSED, AND DISCUSSED Opened 99-07-01 NCV Inadequate Design Control for RSS Sump Pump Issues 99-07-02 NCV Inadequate Corrective Actions for RSS Sump Pump issues 99-07-03 NCV ' Inadequate Corrective Actions for Organizational Changes Closed 99-07-01 NCV Inadequate Design Control for RSS Sump Pump issues 99-07-02 NCV Inadequate Corrective Actions for RSS Sump Pump issues 99-07-03 NCV Inadequate Corrective Actions for Organizational Changes 98-212-04 URI Medium Voltage Circuit Breaker Maintenance 97-82-02 VIO Oganizational Freedom for HP Functions 97-82-06 .VIO - Boric Acid Pump Air Binding

97-82-08 VIO Service Water Flow Indication Anomalies 98-72-05 VIO Procedures Defining ISEG Process 98-72-10 VIO Safety Functions Requirements Manual 98-208-07 URI ~ Recirculation Spray Cubicle Sump Pumps 98-208-06 IFl Completion of MOV Program Closure issues

.97-82-01 URI Measuring and Test Equipment Program Issues 97-82-07 VIO Incorrect Condition Report Significance Levels 98-06-02 URI Recetitive Waste Test Tank Releases 97-046-00 LER Containment Recirculation Spray System Cubicle Flood Potential 98-036-00 LER Engineering Safety Features Building Sump Pump Design Deficiencies o

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LIST OF ACRONYMS USED i l

i ACR Adverse Condition Report AFW auxiliary feedwater AITTS Action item Tracking and Trending System AR Action Request AWO automated work order CR Condition Reports CSR cable spreading room CVCS component valve cooling system DBA design bases accident DBS design base summary DCM design change manual DCN design change nc>tice j DR discrepancy report ECOP Employee Concerns Oversight Panel ECP Employee Concerns Program ECPM Employee Concerns Processing Manual EPRIPPM Electric Power Research Institute performance prediction methodology EDG emergency diesel generators ESF engineered safeguards features GRITS Generation Records Information and Tracking System HIRD harassment, intimidation, retaliation and discrimination ISEG independent safety engineering group KPI key performance indicators LER Licensee Event Report LHC Little Harbor Consultants M&TE measuring and test equipment MDMRT multi-disciplinary management review team MOV motor-operated valves MR Maintenance Rule MRT management review team NCV Non-Cited Violation NNECO Northeast Nuclear Energy Company NO Nuclear Oversight NOVP Nuclear Oversight Verification Plan NSAB Nuclear Safety Assessment Board NU Northeast Utilities NUTIMS Northeast Utilities Training Information Management System OD operability determinations ODI Operations Department instruction PASS Post Accident Sampling System PM preventive maintenance PORC Plant Operations Review Committee PRA probability risk assessment I

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RCI root cause investigation RG Regulatory Guide RSS Recirculation Spray System SCWE Safety Conscious Work Environment SFR startup field report SORC Station Operations Review Committee SW service water T&Q training and qualification TM temporary modifications TR trouble report TS . Technical Specifications UDIC Unit Deferred item Committee VCT volume control tank WTT waste test tank i

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