ML20212K867

Summaries of 971111,980317,980505,980623,980707,980806, 980917,981023,981110,981217,990114,990205,990318,990325, 990416 & 990714 Meetings with Licensee Re Implementation of plan-for-excellence Restart Issues.With Minutes & Handouts

ML20212K867
Person / Time
Site:	Clinton
Issue date:	09/30/1999
From:	Dapas M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 9910070072
Download: ML20212K867 (250)

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September 30, 1999 1

l MEMORANDUM TO: Files FROM: Marc L. Dapas, Deputy Director, Division of Reactor Projects, Region lll

SUBJECT:

INSPECTION PLAN FOR CLINTON l

NRC management and staff met in Clinton, Illinois; Lisle, Illinois; and Rockville, Maryland, with l representatives of Illinois Power Company on various occasions. The purpose of these I meetings was to discuss lilinois Power Company's (licensee) progress in preparing its staff and i Clinton Power Gtation for restart, the effectiveness of the licensee in implementing its Plan-For-Excellence restart issues identified on the Case-Specific-Checklist, and any recently identified issues. .

l A list of meeting dates is inhuded as Attachment 1, meeting minutes are provided as Attachments 2 through 16, and copies of the meeting handouts are provided as  !

Attachments 17 through 31. Attachment 32 is the meeting slides used by the NRC Restart j Oversight Panel during the April 16,1999, meeting to present the results of the NRC's Plant l Performance Review of Clinton Power Station. The meeting minutes of the September 17, 1998, meeting held in Rockville, Maryland, were not included in this memorandum.

The meeting minutes were issued in a separate docketed letter from Jon B. Hopkins, Senior Project Manager, Project Directorate lil-3, Office of Nuclear Reactor Regulation, dated November 20,1998.

Docket No. 50-461 License No. NPF-62 Attachments: As stated (32) cc w/atts: PUBLIC IE01 l

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9910070072 990930 PDR P ADOCK 05000461 PDR ,

DOCUMENT NAME: G:\ CLIN \ MEET _ MIN.WPD To receive a copy of this document, indicate in the box:"C" s Copy without enclosure Te Copy with enclosure"N"a No copy l OFFICE Rill l Al Rlli lA Rlli M BLAME DuPont/ dip /co/dpA Kozak W - Dapas#29f)

DATE 09/M99 JW 09/W99 095099 OFFICIA RECORD COPY

z Enclosure 1

- Meetings were held between the Illinois Power representatives, members of the public, and the NRC Restart Oversight Panel on the following dates:

November 11,1997, at lilinois Power Company's Energy and Environmental Center, Clinton, Illinois March 17,1998, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois May 5,1998, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois June 23,1998, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois July 7,1998, at NRC Region Ill, Lisle, Illinois August 6,1998, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois September 17,1998, at the NRC Headquarters, Rockville, Maryland October 23,1998, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois l

November 10,1998, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois December 17,1998, at Illinois Power Company's Energy and Environmental Center,

. Clinton, !!Iinois January 14,1999,' at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois February 5,1999, at lilinois Power Company's Energy and Environmental Center, Clinton, Illinois March 18,' 1999, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois March 25,1G99, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois April 16,1999, at lilinois Power Company's Energy and Environmental Center, Clintor}, Illinois Ju'y 14,1999, at Illinois Power Company's Energy and Environmental Center, Clinton, Illinois 4

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Enclosure 2 l

MINUTES OF NOVEMBER 11,1997, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss the development and implementation of Illinois l Power's Plan-For-Excellence (PFE). The licensee presented the PFE and its goal of organizing i and prioritizing the issues associated with Clinton Station restart.

1. Backaround and Development The licensee recognized the need for a comprehensive plan to direct its efforts towards restart.

The PFE was developed to ensure that issues identified by the NRC and the licensee's assessments were resolved prior to restart of the plant. The responsibility for overview of the <

PFE was assigned to the Recovery Manager.

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I The key improvement activities contained in the PFE included establishing a corrective action l

program, creating a work management process, improving the preventive maintenance program, and improving the quality assurance program effectiveness. The NRC Restart Oversight Panel identified that the proposed PFE did not address concerns with design basis and configuration control. The licensee acknowledged the NRC .:omments.

The licensee identified that the corrective action program aspects of the PFE contained several improvement initiatives. A root cause team and corrective action team were initiated to ensure that causal factors are identified and a comprehensive integrated corrective action plan is developed for issues.

Planned improvements to the work management process were described in terms of three ,

stages. The first stage involved restoring safety systems to an operational status. To

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accomplish this, the licensee initiated plans to fully staff the work week manager positions, re- l establish a 12-week rolling schedule, and develoo performance measures and trend indicators. l The second stage involved establishing a permanent work management staff and implementing i the operations work coordination center. The third stage consisted of finalizing the work i management process which involved development and implementation of training and procedures.

The licensee also addressed initiatives to improve the preventive maintenance p ocess. These initiatives primarily focused on supervisory monitoring of activities and evaluating work practices to develop an optimized program.

3. Meetina Closure The licensee closed the meeting with a discussion of priorities of activities. The licensee established the restoration of safety systems to operational conditions as its highest priority.

Other high priorities included implementing the PFE, improving the staff's performance, and improving training. The NRC Restart Oversight Panel and licensee's representatives agreed to set the next meeting in the future based on progress of implementing the PFE.

Enclosure 3 MINUTES OF MARCH 17,1998, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discusa Clinton Power Station (CPS) plant status, licensee progress in addressing specific issues contained in the Restart Action Plan, and the circumstances associated with the February 13,1998, loss of shutdown cooling event resulting in an " Alert" declaration.

1. Plant Status The iicensee discussed the status of the Division 11 outage work to restore the safety-related systems to an operable condition for the current Mode of Operation. The licensee also discussed the scheduled plans for the Division I outage and the expected delays of the divisional outages due to implementing lessons learned from the February 13,1998, event involving an " Alert" declaration.

2. Conduct of Operations The licensee discussed its plan for improvements in conduct of operations and how this plan would be incorporated into the Plan-For-Excellence (PFE). The licensee's improvement plan included enhancing operator training, revising the equipment tagging process, revising abnormal operating procedures, and establishing a risk assessment process. The licensee also discussed the lessons learned from the February loss of shutdown cooling event that were applicable to the conduct of operations. The principle lesson-leamed from the event was the need for operator and control room supervisor awareness of the integration of various systems and the effects of component operations or malfunctions on interfacing systerns. The licensee j also identified several non-conservative decisions made by the operating crew and  !

management that were key initiators of the circumstances that led to the loss of shutdown j cooling and the subsequent Alert declaration. l i

Another corrective action implemented to address lessons teamed from the February loss of shutdown cooling event was the establishment of workshops for the entire CPS operations organization. The workshops emphasized key areas for focus during conduct of operations, such as, awareness of equipment status, communications, adherence to procedures, and effective use of self-checking methods.

3. Corrective Actions and Lessons Learned from the February 13 Loss of Shutdown )'

Coolina Event The licensee informed the NRC Restart Oversight Panel that a root cause of the loss of '

shutdown cooling event on February 13,1998, was that scheduled work on the nuclear system protection system inverter was performed without an appropriate risk consideration. The licensee identified that the work scheduling process did not include an evaluation of the impact of work on the inverter on other interfaced systems. The licensee concluded as a result of its

< root cause determination process, that its procedures for risk evaluation and determining contingency planning were not clear and were difficult to use. The licensee stopped all work J

Enclosure 3 immediately after the February loss of shutdown cooling event to perform a comprehensive assessment of the work control prowas. The licensee then implemented a management risk j review of scheduled activities. The licensee determined that several activities were scheduled which created unnecessary risk. The licensee, as an immediate corrective action, assigned risk assessors to the work organization to assist in evaluating the risk associated with scheduled work activities. The licensee also incorporated follow-up monitoring activities in the PFE. The licensee committed to establish an effective risk at sessment program. The NRC Restart Oversight Panel stated that the NRC F.estart Action Plan also incorporated an assessment of the effectiveness of the licensee's rish assessment program.

4. Conduct of Maintenance The licensee presented its plan to improve the performance of maintenance activities. The licensee's improvement efforts focused on three areas: organizational roles and ,

responsibilities, process improvements, and establishment of a culture of continuous improvement. .

The licensees efforts to improve the maintenance organizational roles were directed at both first and second level supervisors. The licensee encouraged supervisory monitoring of work activities and emphasized the need to provide direct feedback on observations to the maintenance personnel. The licensee also described its initiatives to improve the effectiveness of conduct of work activities. These initiatives included the establishment of Fix-It-Now (FIN) teams, revision of the monitoring process, re-establishing the 12-week rolling work schedule,

~ and providing training to improve the troubleshooting skill of maintenance personnel.

5. Meptina Closure The meeting was closed with discussions by the NRC Restart Oversight Panel on the licensee's plans for implementing an effective risk assessment program. The next meeting was set for May 5,1998.

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l Enclosure 4 1 MINUTES OF MAY 5,1998, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss Clinton Power Station (CPS) plant status, Illinois Power (IP) Company's progress in implementing the Plan-For-Excellence (PFE), and the results of the licensee's Safety Design and Functional Validation (SDFV) review.

1. Plant Status The licensee restored the safety-related Division 11 systems to operable status for Operational Mode 4. The Division I outage was currently ongoing with expectations of completion of outage activities within 2 weeks. The licensee presented its plans to conduct future outages to restore all three divisions of safety-related systems to operable conditions for Operational Modes 1,2, and 3.

2. Corrective Action Procram The licensee presented its plan for improving the CPS corrective action program. The licensee's plan included a commitment to establish a daily management focus on corrective actions, use operating experience, assess ongoing activities, and to develop improvements to the condition reporting process. The licensee discussed some of its successes. These early successes were primarily the result of CPS management's use of the daily management meetings to focus on corrective actions. The licensee also presented its ongoing challenges.

The licensee identified its challenges as establishing and using safety evaluations, and establishing and disseminating management's expectations. The licensee stated that both of these issues, ineffective safety evaluations and the lack of clear management expectations, had significant impact on the progress of improvements to the corrective action process.

3. SDFV Results The licensee discussed its plans for implementing various portions of the PFE. The licensee presented the findings from its SDFV team. The SDFV team was formed by the licensee to ensure that safety-related systems would be restored to operational conditions prior to restart of CPS following the extended shutdown. The licensee is also conducting reviews of the maintenance processes and past corrective action activities to assess the condition of the safety systems to ensure that they can perform their intended functions when called on.

The licensee selected various systems for its SDFV review. These systems included auxiliary electrical power, control room ventilation, shutdown service water, residual heat removal, and containment monitoring. The results of the SDFV review were independently evaluated by the CPS senior independent review group. The licensee identified weaknesses in its control of design calculations, design change control, post-modification testing, and implementation of resolutions to generic design issues. The licensee identified that the consequences of the weaknesses in its processes affected only the magnitude of the design margins of the safety systems and did not affect the ability of systems to function as designed. The licensee also stated that weaknesses with design control and testing would require additional reviews to determine the appropriate corrective actions to address the weaknesses. The licensee j i

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. Enclosure 4 committed to discuss the results of these reviews during a subsequent meeting and to fully implement the developed corrective actions prior to restart of CPS from the extended shutdown.

4. L'.;dirs Closure The meeting was closed by the NRC Restart Oversight Panel and the next meeting was set for June 23,1998.

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Enclosure 5 MINUTES OF JUNE 23,1998, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss Clinton Power Station (CPS) plant status and Illinois Power (IP) Company's progress in implementing the Plan-For-Excellence (PFE) for the conduct of operations, conduct of rnaintenance, and corrective action program.

1. Plant Status The licensee provided the status of its activities associated with the divisional safety systems.

Currently, Division i and 11 are fully restored to an operational condition for the plants exisRg Mode of Operatien. The licensee is expecting to shortly restore Division lll safety-rela'.ec systems to operational conditions for the current Mode of Operation. The licensee also discussed its schedule for installing the emergency reserve auxiliary transformer load-tap-control system.

2. Manaaement Leadershio The licensee described its accomplishments in establishing an effective CPS management and leadership team for guiding CPS towards restart from its extended shutdown. These accomplishments included a managerial service contract, the establishment of weekly managerial team restart and PFE development meetings, and the establishment of a nuclear review and audit group to monitor and assess progress in implementing the PFE. The licensee's accomplishments also included establishing leadership expectations for the first and second levels of supervisors and holding these supervisors accountable to those expectations.

Other accomplishments included implementing the shift manager position as well as establishing a leadership development institute (LDI) and daily leadership meetings. The NRC Restart Oversight Panel questioned the licensee's progress in implementing the LDI. The licensee was unable to state the degree to which LDI training had been accomplished to date, but provided assurance that all necessary supervisors would receive the LDI training before the restart c' CPS. The licensee also established monthly performance indicator meetings and implemented a revised corrective action program to provide methods of monitoring progress in implementing PFE activities.

3. Conduct of Ooerations The licensee provided the status of various improvement programs affecting the conduct of operations. These programs included the event free operations initiative, the establishment of shift manager and field supentisor positions; and LDI training. The licensee described its challenges associated with modification activides to resolve the degraded voltage issues, implementing Technical Specifications, and taplementing a culture of a questioning attitude with the operators. Other challenges were described by the licensee consisting of raising performance standards of operators to the level of expectations contained in the PFE, and addressing control room deficiencies and operator work-arounds.

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4. Conduct of Maintenance The licensee presented the details of its interactions and involvement with ine staff from another nuclear station assisting the licensee in developing improvements in the conduct of maintenance actMties. The licensee also discussed its challenges which included training to improve troubleshooting skills, addressing quality issues with work packages and instructions, and the large backlog of maintenance tasks.

5. M81g_r[glQgglill90 The licensee discussed the completion of both the electric motor greasing project and the '

. refurbishment of the scram solenoid pilot valves, Most of the licensee's improvement programs were being implemented. Ongoing activities incluc.ed impiamenting the Maintenance Rule, upgrading fire protection systems and structures, completing the degraded voltage modifications, replacing the recirculation pump seals, and inspecting and refurbishing circuit breakers. The licensee also discussed that it was still in the " identification and development" phase of the PFE which involved addressing long-standing issues and assessing the impact of past practices on material condition of plant structures, systems, and components.

6. Meetina Closure The NRC Restart Oversight Panel summarized the licensee's presentation and set the next meeting for July 7,1998.

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Enclosure 6 MINUTES OF JULY 7,1998, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss Clinton Power Station (CPS) plant status and Illinois q

Power (IP) Company's progress in implementing the Plan-For-Excellence (PFE). In addition, the NRC Restart Oversight Panel requested the licensee to discuss the June 29,1999, ,

declaration of an Unusual Event at the discretion of the shift manager after receiving reports of l damage to three of four offsite power sources. 1

1. Plant Status Plant status was not significantly changed from the June 23,1998, meeting. I

2. June 29.1998. Declaration of an Unusual Event j

On June 28,1998, the licensee declared an Unusual Event after receiving reports of damage to j three of four offsite power sources. The 138kV supply to the emergency reserve auxiliary l transformer (ERAT) was momentarily lost when two breakers on the lilinois Power distribution system tripped due to a ground fault. Although the breakers automatically re-closed within 1 second, the loss of voltage condition was of a sufficient duration to cause the Division ill 4160-Volt safety bus to transfer from the ERAT to the reserve auxiliary transformer which resulted in the loss of several systems and components. All affected systems and components were restored within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

The operations department developed two initiatives in response to the event. Operations management requested that engineering personnel perform a post-event review. The results of this review indicated that all systems and components functioned as designed. In addition, the Director of Operations planned to develop just-in-time training to improve each operator's familiarity with electrical transients and component response. This training was intended to prepare operations personnel for possible transients which may occur during an ERAT outage scheduled for mid-July.

3. Conduct of Operations The licensee graduated from the licensed operator class since the June 23,1998, meeting. In addition, some of the licensee's improvement initiatives appeared to be effective with a demonstrated significant improvement trend in selected conduct of operations. Other initiatives had not yet produced similar results.

4. Meetina Closure The NRC Restart Oversight Panel and the licensee representatives summarized the issues and agreed to set the next meeting for August 6,1998.

Enclosure 7 MINUTES OF AUGUST 6,1998, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss implementation of Illinois Power's (IP) Plan-For-Excellence (PFE). The PFE was developed to ensure the readiness of Clinton Power Station (CPS) for restart from the extended shutdown. The meeting was primarily focused on IP's progress in implementing PFE actions for improving maintenance practices at CPS and meeting Maintenance Rule requirements, in addition, the licensee provided plant status to ]

assist the NRC Restart Oversight Panel in assessing CPS's readiness for restart.

1. Plant Status The licensee presented the plant status and discussed overall progress towards restart. The licensee was continuing to perform outage work o all three divisions of safety-related systems l

to restore them to operational conditions for all modes of operation. The licensee completed testing and verification activities for Divisions I and ll for the current mode of operation and declared both divisions operable per Technical Specification requirements. The licensee also ,

completed the installation of the emergency reserve auxiliary transformer (ERAT) load-tap- l l

change modification. Testing of the modification was scheduled for a future ERAT outage. The licensee was in the process of making preparations to start the degraded voltage modifications and replace the essential core cooling systems' suction strainers.

2. Maintenance Practices Improvement The licensee presented the status of initiatives to improve performance of maintenance at CPS.

The licenses completed the evaluation of its technical knowledge and skills assessment. The 1998 training program was revised to address the weaknesses identified during the assessment. In addition, procedure and process revisions were being scheduled with the goal of supporting CPS's restart.

The licensee also addressed actions to ensure that CPS maintenance personnel adhere to maintenance, plant, and radiological procedures and instructions. The licensee discussed the actions in the PFE action plan that were aimed at improving adherence to procedures, improving the technical quality of maintenance procedures and instructions, and improving the use of self-checking practices. The licensee did not present a schedule for completion of these actions, but provided assurance that these efforts would be completed to support CPS restart.

The licensee discussed two performance indicators which demonstrated that the percentage of repeat work required because the original corrective maintenance activities were deficient and post-maintenance testing failures were decreasing.

3. Maintenance Rule implementation and improvements The licensee discussed its progress in implementing of PFE action plans and activities for meeting the Maintenance Rule. The licensee's action plan included establishing Maintenance Rule required monitoring of structures, systems, and components (SSCs) for Operational Modes 1,2, and 3 prior to restart of CPS. The licensee stated that monitoring of SSC performance during Operational Modes 4 and 5 would be established after restart of CPS.

Enclosure 7 .

The licensee also discussed the completion of training on implementing and complying with the Maintenance Rule for engineering, plant operations, maintenance, and work management

. personnel. The licensee discussed the status of implementing other Maintenance Rule requirements necessary for restart of CPS. These included addressing some of the J weaknesses identified during the NRC Maintenance Rule implementation verification team )

inspection completed on April 14,' 1998. The licensee completed activities associated with verifying that the scope and significance classification of SSCs monitored per the Maintenance Rule was appropriate, established criteria to demonstrate that the effectiveness of preventative maintenance for certain SSCs was adequate, enhanced the description of Maintenance Rule functions, documented the basis for SSC performance criteria, and established a process to manage risk associated with removing equipment from service. The licensee stated that not all corrective actions to address the NRC findings and the CPS quality assurance audit findings were completed. Actions not completed included establishing performance goals and corrective action plans for SSCs and effectively monitoring the performance criteria of SSCs.

The licensee also discussed the challenges to being prepared for the September 1998 quality

- assurance audit which was intended to verify effectiveness of Maintenance Rule improvements at CPS. These challenges included the availability of the expert panel and system engineering support, and the large number of systems requiring increased monitoring or corrective actions.

4. Additional improvernents at CPS Based on SDFV Findinas The licensee also presented its plans for establishing additional corrective actions based on the findings and recommendations of the System Design and Functional Validation (SDFV) team.  !

The team recommended that CPS senior management conduct reviews of the various engineering processes to determine their effectiveness, assess the effectiveness and thoroughness of system surveillance tests, and establish the senior engineering review group to provide an oversight function for the various engineering processes. The reviews of engineering products and surveillance testing were currently being performed. ' The engineering l review group was established and the licensee described its plan to continue the group's  ;

function as a long-term improvement initiative. The NRC Restart Oversight Panel agreed that an engineering review organization would be a posit!ve initiative at CPS.

5. Conduct of Ooerations The licensee addressed its progress in improving the conduct of operations. The licensee discussed the continuing trend of decreasing events due to operators' actions. The licensee attributed this improvement to the effective use of supervisory monitoring of operators' performance and the operations department's night orders. The monitoring program provided immediate feedback of observed conduct to the operators, both positive and negative. The night orders provided a method of communicating management's expectations for specific scheduled activities and evolutions.

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- 6. Meetino Closure The licensee summarized its presentations and emphasized its commitment to implement the PFE adion plans, monitor staff performance, and to ensure that CPS is safely restarted. The NRC Restart Oversight Panel acknowledged the licensee's commitment towards restart of CPS. The next meeting was set for September 17,1998, at the NRC Headquarters in Rockville, Maryland.

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Enclosure 8 MINUTES OF OCTOBER 23,1998, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss lilinois Power's (IP) progress in implementing its Pian-For-Excellence (PFE) and the plant status and preparation for readiness to restart Clinton Power Station (CPS) from the extended shutdown. In addition, IP representatives were requested by the NRC Restart Oversight Panel to address the CPS staff's findings, root cause determinations, and corrective actions from their investigation into the high rate of failures by licensed and senior licensed reactor operators during the August through September 1998 re-qualification examinations.

1. Plant Status The CPS staff completed a number of significant Division I safety-related system modifications and activities in preparation to restore systems to operational conditions to support the restart of CPS. These included the modifications to prevent adverse operations due to hot-shorts occurring in major electrical cabling, flow balancing of shutdown service water, and the inspection of safety-related heat exchangers. The modifications for degraded voltage, essential core cooling systems' suction strainers, feedwater check valves' keep-fill system, and resolution of Thermo-lag issues were stillin progress.

2. Restart items Schedule for Comoletion The licensee provided a schedule for completing restart items which is enclosed.

3. Licensee's Root Cause Determinations for the Licensed Ooerator Re-Qualification Examination Failures The licensee discussed the status of its investigation of the examination failures and follow up activities associated with the resulting Level 1 condition report. The licensee found that several contributing factors led to the circumstances that resulted in the examination failures. Many of these contributing factors were associated with ineffective management oversight of simulator training and management changes in both the operations and training organizations. The licensee determined that the following factors were significant contributors to the examination failures: operations management raised the performance expectation of the licensed operators without ensuring that the expectation was communicated or that training would ensure success in meeting the expectation; the number of training position vacancies reduced the overall j effectiveness of training; the availability of the simulator to trainees was reduced without attempts to ensure make-up sessions were conducted; senior operations management did not monitor or ensure that simulator training was monitored; and the use of the operator performance feedback process was not applied to training activities. The licensee identified the root causes of the examination failures as ineffective management involvement by both the operations and training organizations, and weak oversight of the training process.

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n Enclosure 8 - 4. Meetina Closure The NRC Restart Oversight Panel closed the meeting by emphasizing the importance of IP's corrective actions to improve its operator re-qualification training process and that NRC inspectors would closely monitor the licensee's activities.

Enclosure 9 MINUTES OF NOVEMBER 10,1998, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss lilinois Power's progress toward readying Clinton Power Station (CPS) for restart, the effectiveness of implementation of the licensee's Plan-for-Excellence, restart issues identified on the Case Specific Checklist (CSC), recently identified training issues, and the status of implementing the Maintenance Rule.

1. Plant Status Electrical Division I activities were complete for Mode 4. Division 3 was considered to be available while Division 2 activities were expected to continue for several additional weeks.

Division 3 was expected to be operable pending a Technical Specification change that was in review by the NRC. Completion of the review was dependent upon additionalinformation being supplied by the licensee.

The licensee also discussed several other accomplishments. These included the completed outages or, the reactor water cleanup and control rod drive systems. Another accomplishment was the completion of the emergency reserve auxiliary transformer modification. However, because of some unexpected early life failures of associated relays, the automatic mode of operation is not expected to be functional until December 1998. The licensee confirmed to the NRC Restart Oversight Panel that the degraded voltage protection function was functional in the manual mode. The last accomplishment that was discussed pertained to the modification of the emergency core cooling system suction strainers.

The licensee also discussed major modifications that were being performed. These included various modifications to improve CPS protection from degraded voltage, the feedwater check valve keepfill system modification, and modifications to protect systems from fire-induced circuit failures. The licensee also discussed its plans for resolving Thermo-Lag issues. The NRC inspectors had identified that additional Thermo-Lag installation issues existed and that additional efforts were needed by the licensee to address these issues. The licensee stated that it would not be able to meet its commitment of resolving all Thermo-Lag issues before the end of the year. The licensee was uncertain about resolving issues associated with safe-shutdown.

Trends of industrial safety indicators continued to reflect good licensee performance.

Indicators associated with radiological safety also continued to show improvement in radworker performance. However, other licensee maintained indicators showed that the licensee was not achieving its as-low-as-reasonably-achievable (ALARA) goals, that a high number of contamination events were still occurring, and that problems existed with incorrect sign-off of the computer dose tracking system.

In the area of nuclear safety, the licensee continued to reduce human errors. Some of the progress was due to self-assessment activities. Although self-assessment efforts were effective in identifying areas of weakness, the licensee appeared to be addressing these problems. The licensee's focus on the temporary lift process resulted in the identification of I

p Enclosure 9 weaknesses in both the temporary lift process and the administrative procedure for tagging. In l both cases, the problems were corrected. The improvements in the tagging and temporary lift processes were well received by the operators, in addition, the licensee instituted four teams as part of its emergency response organization.

The licensee closed the discussion of plant status with a brief description of the goals and focus for the upcoming weeks. Primary efforts were directed at completing the Division 2 outage.

The licensee expected to complete all preventive maintenance requirements in the next few weeks. However, all activities needed to declare Division 2 operable during Operating Modes 1,2, and 3 would not be completed until a future outage (estimated to be in January 1999). The licensee also intends to focus on improving in-plant work processes which  !

includes having jobs planned several weeks in advance of the plant schedule. The licensee l was increasing the Fix-It-Now and minor maintenance efforts to assist in achieving advance planning goals. Many of these efforts were the result of resolutions to findings by the INPO assist audit conducted in October 1998. The licensee's management observation effort was also considered effective in providing feedback to plant personnel. The NRC questioned the licensee on what processes showed results based on management observations. The licensee stated that performance improvements in both industrial and radiological safety were due to plant personnel receiving immediate feedback on their work practices while conducting in-plant activities. The licensee also stated that management, using its management observation program, was effective in re-enforcing procedure compliance policies and ensuring that pre-job i briefings were conducted and were effective.

2. MC 0350 Closure Packaae Status The NRC has completed its inspection of licensee activities descrioed in two packages and the licensee completed its acceptance review of two additional packages. The licensee had not fully completed planned actions for five closure packages: degraded voltage and electrical distribution concerns, performance of readiness reviews, validation of calculations, validation of the setpoint program, reduction of maintenance work request backlog, and a review of the cumulative effect of the backlog. The licensee was not yet satisfied with the completeness or effectiveness of its actions to review and revise abnormal operations procedures, develop a process to review deferrals of preventive maintenance items, establish actions to achieve and sustain improvement in the corrective action program, establish operator training to emphasize Technical Specification adheren:e, and implement work management program improvements for prioritization, planning, and scheduling of work. The licensee discussed the expanded scope of corrective actions associated with three packages due to emergent issues: resolution of issues associated with circuit breaker failures, qualification of materials and parts installed in plant systems (inspections of installed fuses had recently started), and identify and correct deficiencies found during the recent operator requalification exams.

The NRC reminded the licensee that its June 15,1998, response to the NRC Special Evaluation Team (SET) report stated that periodic Plan-for-Excellence progress reports would be available. The licensee acknowledged the NRC's comments and stated that it would review the response to the SET.

l Enclosure 9 , 3. Nuclear Training The licensee discussed the background of its engineering training issues, initially, weaknesses pertaining to the engineering task analysis process were identified in 1997. Early in 1998, additional training weaknesses were identified. Three engineers were added to the training staff to address subjects such as effective root cause determination, the 10 CFR 50.59 safety evaluation process, use of design basis information, and lessons learned training.

In the area of maintenance training, corrective actions were directed towards addressing

- problems identified through the management observation and self-assessment processes.

- These problems were validated by an INPO assessment. The recent October 1998 followup assessment concluded that good progress had been made. However, the licensee acknowledged that additional efforts were still warranted. The licensee has instituted a review committee to assess the effectiveness of maintenance training, a maintenance training council to implement training requirements and to monitor training effectiveness, and the use of subject matter experts.' The use of subject matter experts enables the licensee to assign personnel with practical experience to the training department.

The discussion of training issues in the operations area was mainly focused on the recent high failure rate during the operator re-qualification examinations. Initially, the licensee established an improvement program to address the specific examination weaknesses for each individual operator. The licensee identified that, as a long term improvement initiative, the training program would focus on emphasizing the knowledge basics and being more critical of operators meeting performance standards. Both the licensee and NRC recognized the potential impact of the training weaknesses on the restart of CPS.

4. jmolementation of the Maintenance Rule The licensee was confident that it would be able to support a Maintenance Rule inspection in December 1998.

5. Corrective Action Prooram 1 The licensee stated that it was on track to complete corrective action plans for all Level 1 and 2 condition reports by December 4,1998. The licensee expected to reduce the total backlog to 2 months by December 31,1998, and to about 1% months by February 28,1999.

Another expectation was that about 90 percent of the corrective actions would be completed by December 31,1998. To meet these goals, the station engineering organization was adding additional resources to work off the backlog. Station engineering personnel have the largest

' backlogs.

The licensee's'most recent assessments revealed that most of the 1997 root cause determinations were performed correctly, but that the corrective actions were eith.r inappropriate or not thorough. The licensee implemented event response teams to review l

audits and root cause determinations to ensure that appropriate corrective actions were being applied. This initiative is also expected to enable the licensee to meet its goal of understanding the causes of repeat events.

6. Meetina Closure The meeting was closed with discussion by the NRC on availability of NRC inspector resources.

The NRC expressed its concern that rescheduling the corrective action program inspection and other inspections would require a region-wide rescheduling of inspector resources. The next meeting was set for December 17,1998.

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Enclosure 10 MINUTES OF DECEMBER 17,1998, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss the progress of Illinois Power in preparing Clinton Power Station (CPS) for restart, the effectiveness of the licensee's implementation of its Plan-

. for-Excellence, restart issues identified on the Case Specific Checklist (CSC), corrective actions for identified training and emergency response organization deficiencies, improvements to the licensee's corrective action program, and the status of activities to resolve circuit breaker problems. In addition, the licensee presented information on the circuit breaker failure mechanisms and corresponding corrective actions fulfilling one of the commitments ,

documented in NRC Confirmatory Action Letter (CAL) 50-461/Rlll-97-009 issued on August 6,

)

1997.

1. Plant Status The status of safety-related divisions had not changed from the status presented at the November 10,1998, Clinton Restart Panel public meeting, with Division 2 unavailable due to ongoing outage work, Division 3 available but not declared operable for Operational Mode 4, and Division 1 operable for Operational Mode 4.

Completion of painting the containment dome was considered by the Restart Panel to be a major accomplishment since the November 1998 public meeting. The licensee also discussed major modifications that were being performed. These included various modifications to improve CPS protection from degraded voltage, modifications in the feedwater check valve keepfill system, and modifications to protect equipment from fire-induced circuit failures. The licensee also discussed its plans for resolving Thermo-Lag issues.

The licensee discussed preparations fotthe emergency drill scheduled for March 30,1999.

The licensee described its efforts to improve the training of the emergency response organization. The licensee also projected that the CPS restart date would be April 3,1999, pending completion of several major modifications and the safety-re'ated outages for Divisions 1,2, and 3.

2. Operational Readiness for Restart - Licensed Ooerator Trainina and Error-Free Operations l The licensee established an oversight manager responsibia for operations department training.

The licensee also obtained assistance from experienced industry personnel to assess the i

proposed licensed operator training corrective actions. The licensee expected to have  !

implemented all corrective actions prior to January 1999, and scheduled re-qualification examinations between January 7 and February 5,1999.

The licensee also discussed the findings from an evaluation of operational errors at CPS. This evaluation addressed operator errors since June 1998. The licensee determined that l' operational events involved either safety tagging errors or errors in implementing the Technical Specifications. The licensee conducted a comprehensive review of these weaknesses and

. Enclosure 10  ; incorporated the lessons learned into its correcCve action program impiovement actions. The licensee stated that the monitoring and feedback process included trending of each operation crew's performance. The process provided involved providing individual feedback on observeo performance and discussing lessons leamed with operating crews.

3. Circuit Breaker Corrective Actions ..

The licensee stated that all actions specified in NRC Confirmatory Action Letter (CAL) 50-461/Rlll-97-009, issued on August 6,1997, were completed. The licensee committed to refurbish or replace all Division I safety-related 4160 volt,1200 amp circuit breakers prior to plant restart and to refurbish or replace all similar Division il breakers by September 30,1999.

In addition, the licensee committed to conduct a special interim maintenance activity for those

- Division 11 breakers that would not be completely refurbished or replaced prior to restart.

4. Emeraency Response Oraanization (ERO) Corrective Actions The licensee completed an evaluation of its facility readiness and determined that several areas

-had improved. A significant improvement was the availability of supplies and equipment. The licensee was in the process of revising its administrative procedures and conducting remedial training for the ERO members.

5. Meetina Closure -

The NRC Restart Oversight Panel closed the meeting and summarized the licensee's presentation. The next meeting was set for January 14,1999.

c Enclosure 11 MINUTES OF JANUARY 14,1999, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss lilinois Power's progress in implementing its Plan-For-Excellence (PFE) and the readiness of Clinton Power Station (CPS) to restart from the extended shutdown. The NRC Restart Oversight Panel requested the licensee to provide an

]

updated plant status and to discuss the readiness of the operations and engineering j organizations to support restart as well as the status of the licensee's efforts to address the restart issues identified in the NRC's Restart Action Plan Case-Specific-Checklist. The Panei j also requested the licensee to address the performance of the operators during the January 6, 1999, loss of offsite power event which resulted in an unusual event declaration.

1. Plant Status The licensee reported that the Division il safety-related systems were operable for Operational Mode 4. The licensee described the status of Division lli as "available for Operational Mode 4."  !

Although the Division ill modification activities had been completed to support Mode 4, the  !

required post-modification testing activities and the verification that the Technical Specification requirements for Operational Mode 4 were satisfied, had not been completed yet. Division i safety-related systems were considered operable for Operational Mode 5 and the licensee was scheduled to begin modifications of Division I systems to support Mode 4 in February 1999.

The licensee also completed degraded voltage modifications for the reserve auxiliary transformer (RAT). The modifications included installing Static-VAR-Compensators (SVCs) on the RAT. The SVC installation and degraded voltage modifications for the emergency reserve auxiliary transformer were scheduled to be completed in February 1999.

2. Lanuary 6.1999. Loss of Offsite Power Event The circumstances that led to the event included an electrical line-up where the safety-related vital buses were being supplied by a 138 kilovolt (kV) !!ne via the emergency reserve auxiliary transformer (ERAT). The reserve auxiliary transformer (RAT), which is supplied by three 345 kV lines, was out-of-service. The non-vital buses were powered via a main power transformer back-feed lineup from the 345 kV source. A guy-wire, which provided structural support for an offsite 138 kV power line transmission pole, was pulled out of the ground during a winter storm.

This resulted in a fault condition and the subsequent loss of the 138 kV supply to the ERAT and its vital buses. This resulted in the automatic starting of the emergency diesel generators.

Operations personnel recognized the loss of offsite power as an Unusual Event and made the required notification to the NRC. However, the notification was made about 11 minutes late.

With the exception of the late notification, the licensee stated that the operator response to the event was good. The NRC Restart Oversight Panel agreed that the operators' response to the loss of offsite power was appropriate. However, the Oversight Panel expressed concems that the licensee's initial critique of the event was not thorough. The Oversight Panel discussed the

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Enclosure 11 - - )

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resident inspectors findings that the licensee's critique was not sufficiently critical to identify issues involving operator knowledge weaknesses, procedure discrepancies, timeliness of event

~ declaration, and delays in the shift tumover process.

3. Operationtal Readiness The licensee conti;1ued remediation training of licensed operators who had failed requalification examinations in August and September 19981 One crew had completed a second requalification examination with satisfactory results.

4. Enaineerina Readiness The licensee stated that sufficient progress in refurbishing circuit breakers, completing

. degraded voltage modifications, and in establishing effective control programs for calculations and set points, would be made to support the NRC Safety System Engineering Inspection scheduled for February and March 1999.

5. Meetina Closure The licensee stated that its engineering staff would be ready to support the scheduled NRC engineering inspection. The NRC Restart Oversight Panel closed the meeting with a request to

' discuss the status of the licensee's actions to address the restait issues identifie<f in the NRC Restart Action Plan Case-Specific-Checklist including the licensee's plan for completing corrective actions for cutstanding issues, at the next public meeting which was set for February 5,' 1999,

Enclosure 12 i

MINUTES OF FEBRUARY 5,1999, CLINTON RESTART PANEL PUBLIC MEETING l

The purpose of the meeting was to discuss the status of Illinois Power's actions to address outstanding restart items identified in either the licensee's Plan-For-Excellence (PFE) or the NRC Restart Action Plan Case-Specific-Checklist.

I The enclosed meeting presentation handout provided the status of licensee actions to address ,

those restart items that were still outstanding as of this meeting. The licensee also discussed  !

. when specific corrective actions for outstanding restart issues were expected to be completed.

Meetina Closure i

The NRC Oversight Panel closed the meeting by summarizing the licensee's plan for j completing the various actions associated with the restart issues. The next meeting was set for j March 18,1999.

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Enclosure 13 MINUTES OF MARCH 18,1999, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss the readiness of Clinton Power Station (CPS) for restart from the extended shutdown. Illinois Power (IP) presented a summary of the ac' ions and performance improvement initiatives implemented to address the concems identified in the NRC's Demand-For-information (DFI). The NRC Restart Oversight Panel also presented the findings and conclusions of the Safety System Engineering inspection (SSEI) team.

1. Operations Department Performance and Readiness for Restart The licensee's self-assessment, performed over a 4-month perioc, showed that there were significant improvements in the conduct of operations. Examples of the licensee's improved performance in conduct of operations included th,100 percent pass rate during the recently completed licensed operator requalification examinations following remedial training and the response of operations personnel to the March 3,1999, severe ice storm that resulted in the loss of two of three offsite lines.

2. Discussions of the NRC Safety System Enaineerina inspection (SSEI) Team's Results and Findinas The SSEl team reviewed the licensee's actions to address NRC Manual Chapter 0350, " Staff Guidelines for Restart Approval," Case-Specific Checklist item IV.3, " Resolve issues Associated With Circuit Breaker Failures." Based on observations of ongoing maintenance activities, the review of maintenance procedures, and the review of corrective actions proposed and completed, the team concluded that licensee efforts to address NRC concems regarding circuit breakers had been effective. The team observed measurable improvement in engineering and maintenance activities relative to circuit breakers. The team concluded that the licensee adequately addressed each of the commitments in Confirmatory Action Letter Rlli-97-009 specific to breaker problems.

The SSEl team reviewed the licensee's actions to address Case-Specific Checklist item IV.4,

' Degraded Voltage and Electrical Distribution Concems." The team concluded that planned electrical distribution system changes and other initiatives to address degraded voltage concerns were well-implemented. Case-Specific Checklist item IV.4 remained open pending an NRC review of post-modification testing which had not yet been completed.

The SSEI team reviewed the licensee's actions to address Case-Specific Checklist item VI.1,

" Provide Reasonable Assurance That Safety-Related Structures, Systems, and Components Will Perform Their Intended Safety Functions as Described in the Design and Licensing Basis."

The team concluded that based on the review of the licensee's findings from its System Design and Function Validatior effort, as well as on the results of an independent NRC review of the reactor core isolation cooling system, that the licensee had established reasonable assurance that safety-related structures, systems, and components would perform their intended safety fun;tions as described in the design and licensing basis. However, the team also identified

Enclosure 13 a number of examples where engineering personnel failed to ensure that problems were adequately resolved through the implementation of effective corrective actions.

The SSEl team reviewed the licensee's actions to address Case-Specific Checklist item VI.2,

" Validate the Adequacy and Control of Calculations." The team concluded that the licensee had adequately addressed calculation control issuas and had completed sufficient calculation reviews to provide reasonable assurance that structures, systems and components would be able to perform their specified safety function.

The SSEl ' team reviewed the licensee's actions to address Case-Specific Checklist item VI.3,

" Validate the Adequacy and Control of the Setpoint Program." The team concluded that the licensee had implemented appropriate actions to ensure setpoint calculations would be properly controlled and was performing appropriate setpoint reviews to ensure safety-related setpoints were being properly maintained with equipment in the field. However, the setpoint operability determination for the next operating cycle was not available for review by the team. Case-Specific Checklist Item VI.3 remained open pending NRC review of the safety-related setpoint

. operability determination.

The SSEl team reviewed the licensee's actions to address Case-Specific Checklist item IV.5,

" Resolve Fire Protection Safe Shutdown Concems." The team concluded that the remote shutdown procedure adequately incorporated the assumptions in the revised safe shutdown analysis and that the procedure could be adequately implemented. The licensee also

. committed to complete necessary operator training prior to plant restart. In addition, the team concluded that all modifications to prevent fire induced valve damage to critical safe shutdown valves, as required by fire protection regulations, were completed. Finally, the team concluded that the program to address the fire-resistive technical concems associated with Thermo-Lag was adequate. The licensee committed to complete all remaining Thermo-Lag activities prior to plant restart.

The SSEl team concluded that with regard to the resolution of significant hardware deficiencies, the performance of engineering personnel was good. However, the team identified a number of examples where engineering personnel failed to ensure that less significant pN blems were adequately resolved through the implementation of effective corrective actions.

The SSEI team reviewed a number of modifications and determined that the modifications were adequately designed and installed. However, two deficiencies related to post-modification testing were identified.

The SSE1 team determined that the licensee's efforts to inspect the configuration of all safety-related fuses and replace all incorrectly installed fuses prior to plant restart, would provide reasonable assurance that installed fuses conform to design document requirements. l The SSEI team concluded that the engineering performance 1.)dicators were not stand-alone and were not easy to understand. At the end of the SSEl inspection, corrective actions were being developed to address this issue, j

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n Enclosure 13 The SSEl team concluded that the quality of 10 CFR 50.59 screenings and safety evaluations

' had improved. In addition, the team concluded that the licensee had established an adequate

_ program for ensuring that trained and qualified personnel prepared and reviewed 10 CFR 50.59 screenings and safety evaluations.

3. Licensee's Response to the NRC's Demand-For-information (DFI)

The licensee provided the NRC a written response to the DFl on February 8,1999, and provided additional information pertaining to the resolution of corrective action and root cause determination deficiencies at CPS. The response also contained the results of the licensee's System Design and Function Verification initiative and other verification activities. Based on the results of these activities, the licensee stated that the licensee had reasonable assurance that previously identified weaknesses in the corrective action program had been adequately

addressed such that problems would not recur and that safety-related SSCs would perform their intended functions upon demand.

4. Meetina Closure The NRC Restart Oversight Panel closed the meeting by summarizing both the SSEl findings and the licensee's basis for concluding that the commitments made in response to the DFl had been satisfied. The panel set the next meeting for March 25,1999, and stated that at that meeting the NRC staff would discuss the findings and conclusions from the NRC's corrective action's team inspection.

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Enclosure 14 MINUTES OF MARCH 25,1999, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss the readiness of Clinton Pcwer Station (CPS) for restart from the extended shutdown. The NRC Restart Oversight Panel presented the findings and conclusions of the corrective action program inspection, commonly referred to as the "40500 Inspection." lilinois Power representatives were requested by the NRC to address the October 18,1998, loss of shutdown cooling event.

1. Operations Activities in Preoaration For Restart Based on its recent assessment of the conduct of operations, the licensee identified several areas where improvements had been made. The primary focus of the assessment was an evaluation of the performance of control room operators, supervisors, and managers. The licensee's assessors noted that operator awareness of equipment status had improved.

Another area of noted improvement was work management. The assessors noted that the work management process was effective in minimizing distractions to the control room )

operators. The licensee stated that based on the recent assessment, there was reasonable  !

assurance that CPS operators could conduct a safe restart in late April 1999. j i

2. October 18.1998. Loss of Shutdown Coolina l The licensee identified three significant lessons leamed from the event. The first was that in October 1998, compliance with_ procedures and Technical Specifications was not " culturally ingrained" in the Operations Depattment.

The second lesson learned was that it was important for the operations staff to identify early in 3 an event the applicable Technical Specifications. This would enable control room supervision and management to effectively track compliance with the Technical Specifications.

The third lesson leamed was that abnormal operating procedures needed to be revised. The licensee's investigation team, tasked with determining the root causes for the event, recommended that the procedures include identification of applicable Technical Specifications that could be entered based on the conditions or expected conditions of the plant.

LThe licensee was in the process of determining the appropriate corrective actions to address the identified lessons leamed. The licensee was also in the process of revising the Licensee Event Report to more accurately describe the lack of Technical Specification compliance on the part of operations management.

3. Results of the NRC's 40500 Inspection

. An announced NRC team inspection was conducted from February 1999 through March 25, 1999. The team evaluated the effectiveness of the licensee's controls for the identification and resolution of technical issues and problems that could degrade the quality of l

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4 Enclosure 14  ;-

plant operations or safety. In addition, the team reviewed NRC Manual Chapter 0350, " Staff Guidelins for Restart Approval," Case-Specific-Checklist (CSC) items 1.1, " Management and Supervision - Establish and Imp!sment Management Expectations," and 11.1, " Corrective Actions - Establish and implement Actions to Achieve and Sustain improvement in the Corrective Action Program." The inspectors concluded that implementation of the licensee's corrective action program within the Operations Department was sufficiently adequate to support unit restart. However, weaknesses were identified with the effectiveness of problem resolution in several areas and with consistent quality in problem evaluations.

. Overall, the inspectors concluded that the Operations, Maintenance, and Plant Support organizations had adequately implemented changes to the CPS corrective action program as stated in the licensee's responses to the NRC issued Demand-for-information (DFI) regarding the licensee's corrective action program. Corrective action program improvements were evidenced by the acceptance and participation of licensee personnel in the condition report (CR) process, a low threshold for documenting problems, the ability to identity and properly characterize problems, an increased self-identification of problems through self-assessments, the improved quality of problem evaluations, the improved timeliness of corrective action item implementation, and improving trends in some performance indicators.

The inspectors concluded that implementation of the licensee's corrective action program by the Maintenance Department was sufficiently adequate to support unit restart. However, weaknesses were identified in the maturity of the formal quarterly trending program derived from CRs and in the completeness of training for first line supervisors and managers for some corrective action programs.

The inspectors concluded that implementation of the licensee's corrective action program by the Plant Radiation and Chemistry Departments was sufficiently adequate to support unit restart. However, weaknesses were identified in the corrective actions to address minor CRs in that they focused on near-term instead of long-term corrective actions, the level of detail in apparent cause evaluations, the scope of self-assessments, and in the reactive trending program, which had no statistical analysis to identify event precursom and potential trends prior to March 1999.

4. Meetina Closure The NRC Restart Oversight Panel summarized the licensee's presentation and emphasized the importance of compliance with the Technical Specifications. The NRC representatives agreed with the licensee that CPS was nearing readiness for restart. A definitive date was not set for the next meeting, however, it was agreed that a date would be determined in the next several days as to when the licensee was ready to present its final status of CPS's readiness to restart.

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1 Enclosure 15 1

1 MINUTES OF APRIL 16,1999, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss the readiness of Clinton Power Station (CPS) for restart from the extended shutdown. The NRC Restart Oversight Panel discussed the conclusions from the NRC's Plant Performance Review (PPR) of licensee performance during the last 9 months of the extended shutdown and presented its assessment of the licensee's readiness for restart.~

1. The followina is a summarv of the openina remarks made by Mr. M. Daoas. NRC.

Oversicht Manaaer for Clinton. and Deoutv Director. Division of Reactor Proiects:

1 The NRC has been evaluating the licensee's progress in addressing various human performance, hardware, and programmatic issues within the context of the Manual Chapter 0350 process. This Manual Chapter provides the NRC staff with guidelines for restart approval. One of the elements of the 0350 process is the development and use of a

• Case-Specific-Checklist." The Case-Specific-Checklist contains those restart nisues that the NRC and licensee have agreed require resolution before plant restart. The items in the Case-Specific-Checklist are a subset of the items identified by the licensee in its recovery plan, referred to as the Plan-for-Excellence.

Since the NRC Restart Oversight Panel was formed in March 1997, the panel has been

conducting periodic public meetings with selected staff and management of Illinois Power l Company to review their progress in implementing various performance improvement initiatives and to discuss the status of licensee actions to resolve the various restart issues identified in the Case Specific Checklist. Mr. Dapas highlighted, by way of background, some of the major events that led to this final meeting prior to plant restart.

In September 1996, the licensee decided to shut down Clinton Power Station following an event involving the failure of a recirculation pump seal.- This event revealed significant deficiencies

. with licensee performance, including problems with procedural adequacy and adherence, the degree of rigor in conducting operations, and engineering suppod to operations. Clinton Power Station was first discussed during the January 1997 Senior Management Meeting due to an overall decline in plant performance during 1996. Based on the results of the January 1997 Senior Management Meeting, Clinton Power Station received a trending letter.

The licensee's poor performance in operations continued during the riext 6 months. A number j of procedural adherence violations continued to occur. In addition, weak engineering support i for the station, incomplete and untimely root cause evaluations and corrective actions, and design errors hindered equipment performance.

In February of 1997, NRC inspectors identified deficiencies in the licensee's maintenance program for safety-related electrical circuit breakers. Consequently, the licensee pmformed

. inspections and tests in an effort to establish reasonable assurance that safety-related breakers

- would function when called upon. l l

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Enclosure 15  !

1 During a public meeting on July 3,1997, the licensee reported the completion of sufficient inspections and tests to provide reasonable assurance that safety-related breakers would perform their intended functions. On July 22,1997, a safety-related 4160 Volt breaker failed to l open when called upon. Later that same day, a nonsafety related 4160 Volt breaker failed to l close when called upon. On August 5,1997, another safety-related 4160 Volt breaker failed to open upon demand. As a result of these breaker failures, the NRC issued a Confirmatory Action Letter on August 6,1997, documenting the licensee's commitments to determine the failure mechanism for each breaker failure, take effective corrective action to prevent recurrent breaker failures, and establish a basis for reasonable assurance that all safety-related breakers would function when called upon.

During the June 1997 Sersior Management Meeting, NRC senior managers concluded that although the licensee had implemented a number of short-term corrective actions, the licensee had not developed a long-term approach to address performance deficiencies. It was not clear  ;

to the NRC senior managers that the licensee had a full understanding of the depth and scope  !

of the reasons for the performance issues at Clinton Power Station. In lieu of the NRC conducting a Diagnostic Evaluation Team inspection to address this concern, the senior I managers determined that allowing the licensee to conduct an Integrated Safety Assessment, )

(ISA) was an appropriate approach to better understand the reasons for the licensee's performance decline and to develop applicable long-term corrective actions.

The licensee conducted an ISA from August through October 1997 and the NRC evaluated the effectiver ess of the ISA with a Special Evaluation Team (SET). The ISA identified significant weaknesses in the areas of operations, engineering, maintenance, and plant support. The SET confirmed the findings of the ISA.

4 As a result of continuing concems with the licensee's effectiveness in identifying, evaluating, and resolving po'tential safety issues, the NRC issued a Demand-for-Information (DFI) on September 26,1997. The DFl required the licensee to submit information addressing why the licensee had confidence that the deficiencies affecting the operability of safety-related '

structures, systems, and components had been sufficiently identified and corrected so that equipment would function as designed if called upon.

During the January 1998 Senior Management Meeting, the NRC senior managers expressed concern that despite Clinton Power Station having been shut down for a considerable length of time, there had not been substantive progress made in addressing the major performance issues at that facility. Following this Senior Management Meeting, Clinton Power Station was placed on the NRC watch list as a Category 2 plant.

In January 1998, PECO Energy was selected by lilinois Power to provide management services for Clinton for the next 3 years. Since that time, most key managers have been replaced.

Based upon the results of the ISA and SET inspections, Illinois Power developed a comprehensive recovery plan, called the Plan-for-Excellence, which contained strategies for

Enclosure 15 improvement in a broad range of areas, as well as an extensive assessment of the restart

' readiness of systems, organizations, and programs, in addition, the licensee performed an extensive review of selected systems to provide reasonable assurance that safety-related structures, systems, and components would perform their intended functions. This initiative

" was called the System Design and Functional Validation or SDFV, The three areas of most concem with licensee performance at Clinton Power Station were operator performance, corrective action program implementation, and the resolution of engineering design issues.

Since the licensee began implementing tSe Plan-for-Excellence, steady progress has been made in addressing the restart issues in these three areas. Using the Manual Chapter 0350 process, the NRC has continued to assess licensee progress in implementing the corrective actions necessary for safe plant restart. In the past several months, the NRC has conducted a number of inspections. This includes a major team inspection in each of the three areas of most concem, namely, Operations, Engineering, and the Corrective Action Program.

In the area of Operations, the NRC evaluated the licensee's training program to upgrade operator performance, with two inspectors onsite for several weeks. The NRC also conducted an Operations Readiness Team inspection, which consisted of five inspectors evaluating control ro^m and in-plant activities on a continuous basis for two separate 72-hour periods, the first and third weeks of March 1999.

In the area of engineering, the NRC conducted a Safety System Engineering inspection consisting of 11 inspectors onsite for 2 weeks. This inspection involved an evaluation of the scope and rigor applied by the licensee's engineering staff to their SDFV initiative, and included a separate comprehensive design basis type inspection of the residual heat removal system, comparing the results of the NRC's inspection to the type of findings developed during the

, licensee's SDFV. The NRC also assigned one of its engineering specialist inspectors to monitor and assess the licensee's actions in resolving the breaker issues. This individual has been inspecting on a nearly continuous basis for the last several months.

In the area of corrective action, the NRC conducted an extensive evaluation of the licensee's corrective action program, from both programmatic and implementation effectiveness standpoints, using a team of 5 inspectors onsite for a month. This major team inspection also included an evaluation of the licensee's response to the Demand-for-information.

in addition to the extensive onsite time, each of these inspection e' forts involved a significant amount of preparation time in reviewing various NRC and licensee documents, to ensure that the inspections were properly focused and effective in terms of providing an assessment of the licensee's readiness to restart. These major team and specialist inspections were separate from the continuous inspection provided by the four full-time, onsite resident inspectors.

The NRC discussed the results of its major engineering team inspection, the Safety System Engineering inspection, during a public meeting on March 18. During the last public meeting on March 25, the NRC disc sssed the results of its team inspection, referred to as the 40500 team inspection, to assess the licensee's corrective action program. On April 7, the NRC exited with the licensee on the results of its Operations Readiness Team inspection.

Enclosure 15 ..

With that perspective on how the NRC arrived at the April 16,1999, meeting, Mr. Dapas briefly discussed where the NRC Oversight Panel was, in the context of the Manual Chapter 0350 process, wiin respect to an evaluation of Illinois Power's readiness to restart the Clinton Power Station.

. Regarding the Case-Specific-Checklist, the NRC Oversight Panel concluded that all of the restart issues identified in this checklist had been adequately resolved. The Oversight Panel also concluded that all of the issues associated with the 4160 Volt and molded-case circuit

' breakers were adequately addressed and that the licensee had estadished a basis for reasonable assurance that all safety-related breakers would function upon demand.

Consequently, the Oversight Panel was ready to recommend closure of the associated Confirmatory Action Letter.

Regarding the Demand-for-information conceming the effectiveness of the licensee's corrective action program, the Oversight Panel concluded that the licensee had established an effective 1 program for identifying, evaluating, and resolving safety issues.

Based on the results of the Safety System Engineering inspection and 40500 team inspection, the Oversight Panel concluded that the deficiencies affecting the operability of safety-related  !

structures, systems, and components had been sufficiently identified and corrected so that {

equipment would function as designed, if called upon.

{

As a result, the panel wam ready to forward a letter to the Regional Administrator documenting the basis for these conclusions. Mr. Dapas further explained that after the Oversight Panel evaluated the information presented by the licensee and reached a conclusion that all of the restart concems had been adequately addressed, the panel would forward a letter to the Regional Administrator documenting the panel's conclusion that the licensee was ready to restart the plant from both a human performance and equipment perspective.

Mr. Dapas provided some context to the PPR. The PPR was conducted on February 2,1999, and reflects the NRC's assessment of licensee performance over a 9-month period from April 1997 through January 1999. Since the PPR meeting, the licensee had implemented a number of corrective actions to address the restart issues and the NRC had conducted three major team inspections to evaluate the licensee's readiness to restart. Given the significant activity level by the licensee over the last 3-months in implementing corrective actions, particularly in the area of Operations, and the degree of inspection activity by the NRC in assessing the effectiveness of these actions, the PPR assessment was not necessarily ,

indicative of current licensee performance. This was due to the dynamic nature of assessing a licensee approaching restart readiness.

2. NRC's PPR Presentation The NRC Oversight Panel discussed the results of the PPR, which consisted of a historical review of licensee performance at CPS between August 6,1997, and January 31,1999. During this period, CPS was in an extended shutdown and the licensee's staff was making progress in

1 Enclosure 15 resolving the restart issues. The NRC identified three major areas of concern needing to be addressed prior to restart. These were conduct of operations at CPS, engineering and design issues , and the effectiveness of the licensee's corrective action program Each of these areas received significant NRC attention and activities in these areas were subjected to various major team inspections. A hand out for the presentation of the PPR is included as Enclosure 32 of this letter.

- 3. Licensee's Presentation The licensee stated that all actions were complete to ensure a safe startup of CPS and power ascension. The licensee also disecssed some of the planned actions to ensure that continuous performance improvements are achieved after the restart of CPS. However, the details of the

- licensee's action plans were not developed and would be provided to the NRC at a future date.

4. Meetina Closure The NRC Rostart Oversight Panel closed the meeting with a summary of the remaining actions to be completed before the NRC could reach and then document its conclusion on the readiness of CPS for restart. These included notifying the public and the licensee via a letter from the NRC that the CAL and DFl were closed. A separate letter would be issued in the near future to document the NRC's restart readiness conclusion.

I.,

Enclosure 16 MINUTES OF JULY 14,1999, CLINTON RESTART PANEL PUBLIC MEETING The purpose of the meeting was to discuss the licensee's plan to ensure safe operation of the Clinton Power Station (CPS) after the restart from the extended shutdown. The NRC Restart Oversight Panel presented the conclusions from the NRC's Restart inspection. The licensee  !

- presented its plan to transition from the Plan-For-Excellence (PFE) to the CPS Business Plan.

1. NRC Restart inspection Results The NRC initiated an inspection of restart activities on April 22,1999. The inspection was continued through May 2, when initial control rod pulls to criticality began, and through June 2, when the plant reached 100. percent power. Operators methodically and cautiously conducted plant restart activities and, in most cases, exhibited conservative decision-making when challenging situatic',s were encountered. The NRC inspectors conducted extensive control room observations during the restart activities with no major problems identified. The NRC j concluded that the licensee had demonstrated it could safely operate CPS. However, engineering support to operations during the restart activities was weak in that most technical issues that arose were not resolved in a timely manner.

2. ~ Licensee's Transition From the PFE to CPS Business Plan The licensee presented its disposition of PFE actions and concluded that the actions required for the restart of CPS were completed. The licensee addressed the NRC's concern that long-term corrective actions to ensure continuous safe operations were not identified in the PFE.

' The licensee presented the objectives of the CPS Business Plan which contained objectives and goals the licensee plans to meet in order to continue performance improvements at CPS.

- The NRC Restart Oversight Panel stated that the Business Plan did not contain the detail necessary to determine how and when the performance improvements would be accomplished.

The licensee acknowledged the Panel's concern and indicated that the necessary details would

- be forwarded to the NRC on a future date.

3. Meetino Closure The NRC Restart Oversight Panel closed the meeting with a summary of the remaining information needed to determine if long term improvement plans were in place for the Clinton i Power Station.  !

l I

I i

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Enclosure 17 Illinois Power Company Management Meeting with NRC

)

November 14,1997 I

l 1

I IP Representatives:

J. G. Cook Senior Vice President  :

W. D. Romberg Assistant Vice President L. S. Wigley Acting Manager-Nuclear Station Engineering R. F. Phares Manager-Nuclear Safety & Performance Improvement J. F. Palchak Manager-Nuclear Training and Support G. L. Baker Manager-QualityAssurance J. M. Gruber Director-Corrective Action J. A. Hale Director-Planning and Scheduling R. A. Joyce Acting Assistant Plant Manager-Maintenance J. A. Henry RecoveryProgram Manager R. M. Fields ' Project Manager- PM Adequacy Review

Agenda i

introduction John Cook '

i Plan for Excellence Wayne Romberg !

Plan Development Jay Henry Dick Phares Key improvement John Gruber Activities in Progress Jim Hale  !

Bob Joyce Randy Fields Gary Baker Priorities Wayne Romberg Summary John Cook

)

4 Plan for Excellence

. Contents Need for Comprehensive Plan Created by Total CPS Organization Holding Sessions with Various Groups of CPS Employees

• Organization New Recovery Manager Named

Plan Development

. Co-Creating the CPS Plan For Excellence (PFE)

. Organizational Diagram

• Diagram of Recovery Activities

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Improv'ements in Preventive Maintenance {

. Background i l

• Ongoing Initiatives Supervision / Monitoring Maintenance Interfaces Technical Adequacy Review Purpose / Scope Information Reviewed l Discrepancies / Recommendations Conclusions l

• Upgrade Effort Optimize PM Program Consolidated Team

Priorities I

. Restore Operability of Safety Systems

• Plan for Excelience l

. Staffing

. Training

. Documented Response to Findings

Enclosure 18 )

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CPSINRC Management Meeting

{

March 17,1998

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1 I

IP Representatives:

W. G. MacFariand, IV Senior Vice President and Chief Nuclear Officer G. A. Hunger, Jr. Manager-Clinton Power Station W. F. Maguire Director-Operations J. F. Palchak Manager-Nuclear Training and Support J. A. Goldman Manager-Work Management V. J. Cwietniewicz Manager-Maintenance W. D. Romberg Manager-Nuclear Station Engineering G. D. Tierney Supervisor-Eledtrical Maintenance

{

l ILLINSIS P9WER l

l 1

. 1 Agenda ,

i Introduction W. MacFadand l 1

Plant Status G. Hunger Conduct of Operations B. Maguire 2/13/98 Alert ,

- Emergency Response J. Palchak )

- Risk Assessment / Work Control J. Goldman Conduct of Maintenance V. Cwietniewicz !

1 Material Condition

- Inverters W. Romberg

- Main Control Room Deficiencies B. Maguire

- 480 Volt Molded Case Breakers G. Tiemey Corrective Action Follow Through G. Hunger Summary W. MacFarland

h Plant Status Division 11 Status Impact of Alert on Work Division I Plan

CPS Conduct of Operations Human Performance Stand Down Workshop Operations Focus Areas  !

February 13 ALERT

)

Open issues Leadership Assessment - Shift Manager Selection

Human Performance Timeline Wednesday, February 11,1998 l

- Division 11 DG local vs. remote indications

{

- Division 11 inverter Bypass Transformer Tagout

{

)

Wednesday-Thursday, February 11-12,1998

- Operations Workshop - offsite l

Friday, February 13,1998

- ALERT- Loss of NSPS bus and SDC

1

.- i j

Human Performance l

l Non-Conservative Decisions (Wednesday, February 11,1998)

- Division il Inverter Bypass Transformer Tagout

- Division ll DG local vs. remote indications I ALERT (Friday, February 13,1998)

- Work stopped

- Schedule risk assessment by management

- Contingency plan developed

~

1 i

Operations Workshop (February 11-12,1998)

Two days offsite with entire shift organization.

- External assessments (INPO, NRC-SET, ISA)

- Self assessment

- Individualchange

- Operations Focus Areas Future actions assigned to each shift.

Operations Focus Areas Safety Procedure Use and Adherence Communications Self-Check / Peer-Check Professional Operator Attributes Supervisory Performance 1

l

I

- l ALERT - Loss of SDC -

(February 13,1998)

NSPS Bus lost due to inverter transfer coincident with Bypass Transformer work.

Prompt, conservative actions A' RHR tripped while F009 valve strokes closed !

- CRD pump secured to control reactorlevel Shift Supervisor declared ALERT Actions taken to restore NSPS Bus and SDC

\

ALERT - Main Control Room Effective Command and Control Supervisory Oversight Peer-Check and Seli-Check I 3-Part Communications Crew Briefs  !

Procedures Used and Fixed Turnover Well Controlled / Deliberate

ALERT - Follow-Up Contingency plan developed for loss of NSPS bus -

crew briefed.

Formal communication of plan and turnover of plan were inadequate. I

)

Formal communication and turnover ensured.

Procedures revised.

Open issues Control Room Breathing Air Winterization Operator Qualifications (ERO, DG, FB)

Shift Manager Selection and Training Division 11 Restoration Conduct of Operations Plan for Excellence l Technical Specification Training

Shift Manager Leadership Assessment All active CPS SROs interviewed.

Field narrowed to 12 SROs.

Leadership assessment conducted by Applied  ;

Research Corporation.

Shift Managers and Operations Support Manager to be named Friday, March 20,1998.

Management training to follow.

2/13/98 Alert -

Emergency Response Major issues identified Immediate Actions Taken  !

Future Actions Planned l l

l l

l 4

2/13/98 Alert -

Risk Assessment / Work Control Problem: The backup power supply to the NSPS inverter was taken out-of-service for planned maintenance without appropriate schedule risk consideration, communication, and contingency  ;

planning.

h.

Risk ManagementIWork Control Causes ,

Management Attention to Schedule Risk Assessment

- Risk Review involved individualthreshold/

standards for action.

- Little communication about Schedule Safety-Risk.

Poor Planning for Division ll Work

- Pre-planninginadequate.

- Schedule stability was poor.

- Procedures for risk reviews and contingency planning were not clear.

Risk Management / Work Control Immediate Actions Stopped work.

Assessed work in progress.

Implemented Management Risk Review of scheduled activ.ities.

V Assigned PRA personnel to assist WWM/SROs.

I

i l

\

Risk Management / Work Control Completed Follow-up Actions Provided specific guidance for evaluating activities.

Incorporate industry standards for risk, provided guidance for contingency planning.

Briefed each shift.

Trained all WWMs and SROs involved in schedule development.

Risk Management / Work Control Completed Follow-up Actions (cont'd?

Included Risk Assessment in planning meetings.

Required Engineering input for specific evolutions.

Conducted work group briefings.

Displayed Shutdown Safety Function status.

EPRI to evaluate new software tools.

l

CPS Conduct of Maintenance l

l Goal: Improve our ability to safely and efficiently perforrn maintenance activities.

i Focus on 3 Areas: {

Organizational Roles and Respo~nsibilities Process improvements Continuous Improvement Culture

CPS Conduct of Maintenance (cont'd?

l Organizational Roles and Responsibilities

- 2nd Level Supervisors

- Direct Support Group 4

- 1st Level Supervisors Process improvements

- WorkScheduling ,

- FIN Team 1

- Troubleshooting 1

CPS Coriduct of Maintenance (cont'd?

Continuous Improvement Culture

- Corrective Action Effectiveness

- INPO Assist Visit

- Industry Experience -

i I

l

. Material Condition - Inverters l

l 1

l Descriptio~n ofInverters '

History of Transfer Events Previous Corrective Action '

j I

1

- DC Supply Fuse Events

- Reverse Transfer Events

- Reworked Material Deficiencies

- Test Plan Implemented i

1 i

I Material Condition - Inverters (cont'db I

l 1

Efforts initiated since February 13,1998

- Re-evaluated Previous Efforts

- Created New SpecialTest Procedure

- Instrumented Inverter i

- Offsite Analysis of Cards and Calibration Methods I

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Material Condition -

480 Volt Molded Case Circuit Breakers Failures Only During implementation or Restoration of Tagouts.

Interim Actions

- Revised Tagging Procedure to Verify De-energized.

- Breakers Sent to Two Independent Laboratories for Root Cause Evaluation.

Short Term /Long Term Actions

- Ensuring Personnel Safety 1

- Verifying Design is Acceptable.

- Implementing Timely Preventive Maintenance.

Corrective Action Follow Through Assessment

- Follow through effectiveness has been low.

- Responsiveness to NRC identified issues has been low.

- Input of Condition Reports has been high and overwhelming.

Plan

- Improve efficiency of process (immediate).

Average of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> spent per CR in past.

Prioritize issues.

Group CRs and work common corrective

{

action.

Attack problems differently than in past (immediate).

- Inverters

- 480V Circuit Breakers

- Shutdown Schedule Risk 1 Change to learning culture (will take time). l

'- ' Enclosure 19 T' -

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)

I CPS /NRC Management Meeting s

May 5,1998 I

9 i

6 IP Representatives:

W. G. MacFariand, lV Senior Vice President and Chief Nuclear Officer G. A. Hunger, Jc. Manager-Clinton PowerStation W. F. Maguire Director-Operations J. F. Palchak . Manager-Nudear Training and Support R. F. Phares Manager-Nuclear Safety and Performance Improvement W. D. Romberg Manager-NudearStation Engineering R. A. Schenck Supervisor-Mechanical Maintenance D.C.Koons Supervisor-Control and Instrumentation t

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J i

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Agenda J

lntroduction W. G. MacFarland i Plant Status G. A. Hunger Corrective Action R. F. Phams I

SDFV Results W. D. Romberg Maintenance Performance R. A. Schenck D.C.Koons ERO Performance J. F. Palchak Operations Performance W. F. Maguire i

Summary W. G. MacFarland i

. \

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Plant Status .

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Division 2 Operable Division 1 Status One Million Safe Work-Hours Radiation Protection Leadership Development institute Equipment Testing Observation Programs Focus for Coming Month 1

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System Design and Functional Validation Maintenance Reviews

- Preventive Maintenance Adequacy

- Review of Maintenance Practices Review of Past Corrective Actions

- MWR "D" List item Review - 6/30/98

- Equipment Related CR Review- 7/15/98 Assessments to Confirm Effectiveness

- DepartmentalSelf-Assessments

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I l

il

l Summary The SDFV has been a learning experience for CPS.

We believe we will be able to show confidence in .

functionality of our SSCs.

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I Main Control Room Deficiencies Main Control Room Team Back Log Reduction Long-Term Application i

1 Post Maintenance Testing i What's Different

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Maintenance Performance Maintenance Work Practices

- Recent Events l

- Causal Factors identified

- Develop Matrix )

- Primary Casual Factors l l

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l

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l' Field Verification l Training .

Procedures

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Emergency Planning

- October 8,1997, After-Hours Drill February 13,1998, ALERT

- Issues Emergency Notifications Technical Support Center and Operations Support Center Activation Autodiale~r Operation and Familiarity SED Command and Control Use of ERO Badges Field Samples Brought into the EOF Communications

- Critique /Self-Assessment f

- Corrective Actions Taken Plans for the Future

- SignificantImprovements Planned

- ERO Activities Scheduled for 1998

I 1

CPS Conduct of Operations CPS Event-Free Operations Shift Managers j -

Technical Specifications l l

1 Operations Services Group j

Near-Term Focus l

i.

s 1 CPS Event-Free Operations Based on Six ocus Areas

- Safety

- Procedure Use ,

- Self Check / Peer Check

- Supervisory Performance

- Professional Attributes

- Communications Feedback on Observable Behaviors " Dead Man R e. ' '"

- Started development at Operations Workshop (February 11-12,1998).

} - Followed up with each crew providing input on final product.

l - Rolled out in beginning of April.

~

i' Performance Indicators O

" EVENT FREE OPERATIONS" PERFORMANCE INDICATORS 247 227 225 -

183 175 -

154 150 -

125 - 112 5+

s.

100 -

75 -

50 - 1 25 - 17 15 SAFETY PROCEDURE USE CHE K my PROFE AL COMMUNICATIONS

" EVENT FREE OPERATIONS" Cards Submitted 140 120 -

100 --------

E Total Observations O SUPERVISORY BSELF

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Shift Managers New Managers Named and in Place April 13,1998 Two SROs to Reactivate Their Licenses Management Training - Leadership Development institute (LDI)

- Three-Week Program

- Key Attributes of Program: Personal I Effectiveness, Conflict Management, Coaching, 1 Team Building, Situational Leadership

- All Shift Management will Attend I

l I Shift._ Manager Role Greater Focus on Plant Big Picture (less task)

- Assessing / Managing Risk Oversight and Development of the Crew

- NLO Training Class

- Future License Class (September 1998)

- Establishing Reporting Relationships and Goals (Performance Appraisals and Individual Development Plans)

- Involvement in Departmental Initiatives

- Conduct of Operations Procedure

- Restart Readiness Review / Plan for bxcellence

es6

1 2

)

! Technical Specifications l

1 Training

- Classroom and Simulator I -

Tracking

\

- Improve Existing Paper System

- Development of Electronic System i

4 i

i -

Implementation

- Master List of Surveillance Project e

i

\

i J

o OPS Services Group Group Within Operations to Support Schedule

. Development and Execution Assess Schedule for Risk 5

Develop Tagouts Interface with the Operating Crews and the Other Site Organizations to Facilitate Work Coordination J

i l

i

]

i l

Near-Term Focus l 1

1 Event-Free Operation l

Management Training i 1

Safe Schedule Development and Execution I

Assessing Manpower for Restart Activities i

9

m a Enclosure 20 t ...-

, , (

/ j

.i s

CPS /NRC Management Meeting

l. June 23,1998 1-t IP Representatives:

W. G. MacFarfand, IV G. A. Hunger, Jr. Senior Vice President and Chief Nuclear Officer Manager-Clinton Power Station V. J. Cwietniewicz ,

W. D. Romberg Manager-Maintenance W. F. Maguire Manager-Nuclear Station Engineering i

J. M. Gruber Director-Operations J. A. Uoidman Director-Corrective Action R. F. Phares Manager-Work Management R. J. Reding Manager-Nuclear Safety and Performance Improvement Supervisor-Electrical Maintenance G. L. Baker Manager-QualityAssurance

f 1 Agenda -

i l

introduction Walt MacFarland

Plant Status George Hunger Management Leadership George Hunger I

Conduct of Operations Wi/Ilam Maguire Conduct of Maintenance Vince Cwietniewicz Material Condition Wayne Romberg Work Management JeffGoldman Corrective Action John Gruber Summary Walt MacFarland

' es I

l-Plant Status -

l Division 1 & 2 Operable Division 3 & 4 Work in Progress Impact of Grid Conditions Installation Schedule for ERAT LTC Radiation Protection Industrial Safety-Observation Program Focus for Coming Month

• 1 I W 4

? .

RADIATidN PROTECTION RADIATION WORKER PERFORMANCE 25 -

20 m

>=

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O tt E 10 s

o Z

5 2

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. . u 2 o CATAGORIES I

j 180 --

=

160 -- Clinton Power Station 1998 Y i <o . Exposure h N l i

120 -

Projected Exposure j 1

100 -

Actual Exposure YTD: 32.882 80 -

Goal YTD: 66.763 eo . 1998 Exposure Goal: 185.000

<0 -

20 -

Actual Exposure 22 RREEERRERERRERRENa

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ILLINOIS POWER INDUSTRIAL SAFETY IP OSHA-RECORDABLE CASES 25 -

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GOAL 7

IP LOST WORK DAYS 7- =

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GOAL 1

4 CONTRACTOR INDUSTRIAL SAFETY CONTRACTOR OSHA-RECORDABLE CASES f, 20 -

I 16 m15--

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3 m

0 10 .

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O g M Aug see oct Nov Dec Jan Feb Mar Apr M ay J.m Jul Aug Sep Oct Nov Dec 1997 1996 M MONTHLY  : YEAR TO-DATE ---

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l 3.. .............. ... ... ... ..... ..................... ...... ..... ...

1 0  :  : -

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i M MONTHLY 8 k YEAR-TO-DATE - -

- GOAL  !

I . **

i-I Management Leaders 1io -

I .

1 Accomplishments 1

- Management Service Contract with PECO

Energy

- Plan for Excellence Development & Weekly Restart Meetings

- Nuclear Review & Audit Group Reporting Relationship to CEO-o - Shift Manager Selection

- Leadership DevelopmentInstitute

- Daily Leadership Meetings

- Implemented Revised Corrective Action L Program

- Monthly Performance Indicator Meetings

. Ongoing

- Human Performance improvements

- Observation Program

- CNO's All Hands Meetings

- Emergency Response Organization e

, l f .

I l.' Conc'uct of Operations -

i l

1 Accomplishments

- Event Free Operations Program

- Shift Manager Selection .

- Field Supervisor Position

- Leadership Development Training

- Operations Services Group

- Tagout Performance

^

- License Class Completed

- 12 Equipment Operators Hired Restoration of D/Gs and ECCS to OPERABLE

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. l i Conduct of 0perations (cont.) -

Challenges I

- Training - Simulator, Tech Specs, Next License Class

- Questioning Attitude

- Performance Standards

- OperabilityDeterminations

- Main Control Room Deficiencies & Operator Workarounds 1

- Degraded Voltage l Ongoing Activities I

- Managing Risk Sensitive Work

- SRO Industry Peers - Assessment & Mentoring

- Next License Class

- New Tagging Program Software

- Mode Restraint Database

l Conduct of Maintenance --

I Accomplishments

^

- OrganizationalChanges

- Management / Leadership Skills

- Communications

- Association with South Texas Project Challenges

~

- Procedure / Maintenance Work Package Usage j

- Training

- Backlog Reduction Ongoing Activities '

- Staffing & Contractor Support

- Assessment of Worker Qualification

- Continuing Training

- Quality of Documentation

- Fix It Now Team '

. 1 Material Condition l

Accomplishments

- Division 1 & 2 Operable L t - Battery Chargers, Inverters, Power Supplies

- Scram Solenoid Pilot Valves

- RHR Heat Exchangers

- SDFV

- Silt

- Electric Motor Greasing Challenges

- Identification and Resolution of Long Standing issues I

- Corrective Action Program Support

- Assess Aggregate impact of Material Condition Backlogs 1

i i

Materia Condition (cont.)

I Ongoing Activities

- Maintenance Rule

- Fire Protection

- Degraded Voltage

- RR Pump Seal

- Electrical Circuit Breakers Westinghouse DHP Breakers (4160V and 6900V)

GE Magne-Blast Breakers (Div 111) (4160V)

ABB K-Line Breakers (480V Air Magnetic)

Molded Case Circuit Breakers (480V) 9 9

e

Work Management -

Monthly Performance Indicator Accountability l Meeting l

- Over 70 criticalindicators addressing Safety, 4

Regulatory Performance, Economic Performance and Material Condition Material Condition Backlog Performance Indicators

- Main Control Room Deficiencies  !

- Preventative Maintenance

- Surveillance Tests

- Maintenance Work Requests

- Temporary Modifications

- OperatorWorkarounds -

- Station Leakage ,

- Fire Protection Corrective Maintenance I

i MAIN CONTROL ROOM DEFICIENCIES OUTAGE RELATED 120 - {

103 100 --

86 85 7e

• 80 .

7 7 69

• 6 ., 6 20 . .. .. .. . .. .

O l - l l l l l l l l l l l l l l )** l l Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 1998

'In Progress m PMT *

=

• Coal MAIN CONTROL ROOM DEFICIENCIES NON-OUTAGE 100 - 97 96 80 - ,

78 67 .

6 60 -- '.

48 48

• 0 , , , , ,  ;  ; ' '

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 1998

=

iln Progress M PMT -

Goal

\

l PREVENTIVE MAINTENANCE LATE 800 -

700 -

600 .

I

$500 -

400 --

[ ,

300 '

.h y  % hf j

hj g

2m- -4 M $g

n. >l <

j p ., j b d k@g;  !

i t f.

"E 3 100 -- N ff '

$i l . ., 4 N$

o. i + + __,__ l+ i i e i i e i i i 1997 1998 m Safety-Related IEEE3 Non-Safety-Related - --

-Goal PREVENTIVE MAINTENANCE OVERDUE 1600 -

1400 -

1200 -

simo-- hh i i O 800 -- g>j h wo-$k 4

5 0- i i l E

[ ( l 1 l l l l Jun Jul t i Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1997 1998 s Safety-Related D Non-Safety-Related

c , ,

i l

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MODE 4 LATE SURVEILLANCES 16 -

14 -

m 12 - '. -

go- '

38-z ,

6-1<

4-l

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l l , l Jan Feb - Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 t=:::!::nOperations summune C&lMaint =

= Elect Maint -

Goal MODE 4 OVERDUE SURVEILLANCES 20 -

18 -

it -

14 - "

B .

$ 12- a

,q

$ 10 --

$ 8--

h BETTER g  ! .,

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p .

, 0 , ,  ; , ,

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 M Operations m Cal Maint i = Elect Maint === NSED """"":" FP Chem Goal MODE 1,2 & 3 SURVEILLANCES RESTRAINED 250 -

212

g. 191 167 5

m 150 -

t27 z E!

100 - Ei 76 i:

52 ll _E.

50 -- a  !!

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Jan Feb Mar . Apr May Jun Jul Aug Sep Oct Nov Dec 1998 O Late a Overdue

P 2000..

CORRECTIVE MAINTENANCE OPEN 1800 -

1600 -

1400 - '

$ 1200 -

g1000 ,

g 800 .....,- -

S*- - . . . .

400 --

200 -

{

l 0

• Jul Aug Sep Oct Nov Dec Jan Feb Ms Apr May Jun Jul Aug Sep oct Nov Dec 1997 1998 M Non-Outage Total ' ; Outage Total * * - Non-Outage Goal 1

4500.. TOTAL MAINTENANCE WORK REQUEST BACKLOG BY TYPE (

4000 - 3942

_ ca 32- '" I8I E 3000 -

o g 2500 - -

183#

$ 2000 --

! '5* ~

1000 - yp 1751 500 -

0 '

k Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 0 Corrective EPlanned D Facilities O Predictive sw . . MWRs GREATER THAN ONE YEAR OLD N-- 363 358 358 m 320 5 g  !

300 i!

e ,

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....g .. . .

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 m MWRs = one year old =

'MWRs > 2 years old MWRs >5 years old -

-2 Year Goal

l .

TOTAL TEMPORARY MODIFICATIONS 27 es re .

25 -- 24 ,

22 2 .,

20 - 19 l '.

{ 15 5 ,

!' ' l

,,. i ........ .

l 5'

L I

$4 o ' ' ' ' ' - ' ' ' ' ' ' ' ' ' ' = =

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 1998 E2!ElOutage Support C~'-" 3 Awaiting Perm. Implementation m Testing / Troubleshooting - GOAL OPERATOR WORKAROUNDS 30 . .

27 27 25 -

20 - '

i E 10-- - - - - - -- - - - -- - - - - - - - - - -

5--

o , , , , , , , , , , , , , , 1 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M Workarounds M NSED CC":::'::3 Maint. -

OPS Goat 1

\.

OPEN FIRE PROTECTION CORRECTIVE MAINTENANCE MWRs

! 70 -

62 U 59 M

56 59 51 52 52 ,

50 - 45 m ~ *-

g E a ao y ..

e 3 m 4

- l ., ,

. .., 4

~~ .

.,,," '- g

• l 20 -

! 4. :

g fq' g

$ I!4

' t r

l w

m 5

!@k 4 e!

!fW 0  : #: '

JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1997 1998 r"--"""'I Closure /PMT #amamm inaccessible EXE3 Restrained i iScheduled Planning - Goal Total l

l

\

e.

l i

l Corrective Action .

I i

! Management Leadership  ;

r I 4 -

Work Management Condition Reporting I

Self-assessment

~

Operating Experience Program Effectiveness 1

t CONDITION REPORT INITIATION Vs CLOSURE 3000 -

2500 - -

0 2 "

2000 - $

b

$ 1500 --

S 1000 -

500 - fg g I I, g g !_

0  ;  ;  ;

5 i E O 5 E ' E Jan Feb Mar Apr May Jun Jul ' ug A Sep Oct Nov Dec 1998 alssued a closed o Open ALL OPEN CRs BY DEPARTMENT 32 103 74 1

1223 i 357 A

413 I

ENSED O Maint D OPS ENT&S G RP/ Chem GNSPI DPSS D other 1

Encisoure 21 is , ,

,N' .

l i

i CPS /NRC Management Meeting July 7,1998 j 1

i i

m i

I I

IP Representatives: '

W. G. MacFariand, IV Senior Vice President and Chief Nuclear Officer G. A. Hunger, Jc. Manager-Clinton PowerStation V. J. Cwietniewicz Manager-Maintenance W. D. Romberg Manager-NuclearStation Engineen*ng W. F, Maguire Director-Operations J. A. Goldman Manager-Work Management

n;):

Agenda I

Introduction Walt MacFadand I

Piant Status George Hunger l Management Leadership George Hunger I Conduct of Operations William Maguire Conduct of Maintenance Vince Cwietniewicz Material Condition Wayne Romberg Work Management JeffGoldman b

Summary Walt MacFadand I

l 1

l

)

.l : ,

Plant Status I

6/29/98 Event F

i Safety System Status Installation Schedule for ERAT LTC Focus for Coming Months I

l .

p..

Management Leadership Accomplishments

( - Plan for Excellence Development & Weekly Restart Meetings I

i

- Nuclear Review & Audit Group Reporting Relationship to CEO

- Shift Manager Selection

- Leadership Development Institute

. - Daily Leadership Meetings

- Implemented Revised Corrective Action Program

'l

- Monthly Performance Indicator Meetings I- -

Ongoing Activities

- Human Performance Improvements

- Observation Program

} - CNO's All Hands Meetings

- Emergency Response Organization i

i Conduct of Operations Accomplishments

- Event Free Operations Program j - Shift Manager Selection

- Field Supervisor Position l

- Leadership DevelopmentTraining

- Operations Services Group

- Tagout Performance

- License Class Completed

- 12 Equipment Operators Hired 1

- Restoration of D/Gs and ECCS to OPERABLE l

\

I 4

I i

] .

Conduct of Operations (cont.)

Challenges

- Training - Simulator, Tech Specs, Next License Class

- Questioning Attitude

- Performance Standards

- Operability Determinations

- Main Control Room Deficiencies & Operator 3-Workarounds

- Degraded Voltage Ongoing Activities

- Managing Risk Sensitive Work

- SRO Industry Peers - Assessment & Mentoring  !

- Next License Class l

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_ FE N - .. M awieu e emnC g n ddf na edsta I -

_ NT TWL - / br io e snper n s i. _

EEOL t t v es e n _

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VB R

- 0 o nur l

e a cloo ep 4 pao n ou a ot s t

8 n E S Y -

n mh hs gi oh eaf nit i r SYA -

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9 -

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t a at

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s "ar i od wneerpa e

- r o a "A e utid ol c

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- a apa uuuuu

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- - - - - - JJ J - -

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n e a D l

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5 3

0 3

5 0 5 0 5 0 E G9 2 2 1 1 wFZw>m zmw3W$ O><O m0<5><

M- -

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i.

Conduct of Maintenance Accomplishments 1

- OrganizationalChanges

- Management / Leadership Skills -

- Communications I

- Association with South Texas Project Challenges

- Procedure / Maintenance Work Package

- Training

- Observation & Coaching )

I  !

Ongoing Activities I - Staffing & Contractor Support j - Assessment of Worker Qualification

- Continuing Training I

- Quality of Documentation

20.00 % - PERCENT OF CM MWRs REQUIRING REPEAT MAINTENANCE I

15.00 % -

c.1 % o 11 0.1 g o.i t w

$ 8' e Wq *5'

• 'O g 10.00% -- o. \o 0.oe 8

g O.oo m

D. o.oe o.o, 5**-- . ... . ..$.. . . .[ . . . . . ..T..- . r ...

0.00 %  ;  ;

l .

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 1998 L iMONTH

--S----12 MONTH AVERAGE .. . GOAL 4.50% -- PERCENT OF CM MWRS FAILING POST MAINTENANCE TESTING 4.00 % - ~

3.50 % --

3.00% .-

.ses

$ 2.50% -- ' ' ' ' '

W .s 2. sos 8-"'

@ _ _ _ - - -5 ""

W 2.00% --

a

~

1.a6 %

3.7ss

- = i.eas 1.50% -- . .. ,s {

1.00% - T..m... .. ... . ... .. ... ..

0.50% --

) -

I 0.00 %  ;  ;  ;  ;  ;  ;  ;  ;  ;

Jul Aug Sep Oct Nov Dec Jan Feb Mar I

Apr May Jun 1997 1998

< MONTH . .

GOAL

.---#-12 MONTH AVERAGE i

I l

. i Material Condition Accomplishments

- Division 1 & 2 Operable

- Battery Chargers, Inverters, Power Supplies

{-

- Scram Solenoid Pilot Valves

- RHR Heat Exchangers

- System Design Functional Validation 1

- Silt l t

- Electric Motor Greasing i

Challenges I

- Identification and Resolution of Long Standing

,1 issues

- Corrective Action Program Support  !

- Assess Aggregate Impact of Material Condition Backlogs 1

Material Condition (cont.)

l' Ongoing Activities I -

- Maintenance Rule

[ - Fire Protection

- Degraded Voltage

- RR Pump Seal

- Electrical Circuit Breakers 4

1 f

9

('

1 I

1 1

\

e l

I l-Work Management J l

\

Main Control Room Deficiencies i

f Preventative Maintenance i,

Surveillance Tests I'

m Corrective Maintenance I

i it I

s

. l MAIN CONTROL ROOM DEFICIENCIES OUTAGE RELATED

)

toa 100 -

g 8 85 I 80 -- 78

• 6 70 +

. e2 l03 .

40 -- .,

20 . . .. .. .. ... '.,

0  :  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;'  ;  ;

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 1998 C ln Progress M PMT - - - - Goal MAIN CONTROL ROOM DEFICIENCIES m NON-OUTAGE 100 -- 87 96 l *

. 89 80 - 78 67 ' ' .

60 --

• 48 48 '.,

40 . 37 '.,

O , l , ,

[ Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

'In Progress M PM -

- - Goal

. l

o-PREVENTIVE MAINTENANCE LATE 700 -

600 -

I L-g L .

g. .,

0- i -

. - + . .- + - - l+z ei = a i -+--

1997 i i 1998 i i i L. +_my M Safety-Related s*=== Non-Safety-Related Goal PREVENTIVE MAINTENANCE OVERDUE 1600 -

1400 -

tg.-

l $1000 --

h

,  !" ~ <

l eco ..

j .. -

e q;

_i Jun Jul Aug Sep Oc' Nov Dec Jan Feb Mar Apr May Jun E Safety-Related O Non-Safety-Related i

e 4

e MODE 4 LATE SURVEILLANCES 16 -

14 - M. ,

12 -  : .

cr . ',

20-  ; .

h8-z .

6- j" '

t  !

4- .

I w ...

2' b i . k I .

o l

3. -

Jan Feb Mar  :  :

Apr May Jun Jul Aug Sep Oct Nov Dec 1998 Operations Cal Maint i

' Elect Maint - -

Goal MODE 4 OVERDUE SURVEILLANCES 20 -

18 --

16-14-512- -

m y to- '

1 a ~

z 8- q

. BETTE 0"

4-j; j' O

j  ;

, , ,AI; V 2- fl. i e o 'p ("#j h~5l 7 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 Operatums ammuusCal Maint - ' Elect Maint )

NSED ------ FP w Chem -Goal i

MODE 1,2 & 3 SURVEILLANCES RESTRAINED 250 ..

212

~

200 - 191

~

167

$ 150 - ~

145

$ 127 13f g l Z

E b 76 .

52 E 5 5 50 -- - 5 55 5

=

5 gg E

g g '

l E E s E E =E  !

i O '

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec DLate 8 12 Overdue

\

j

4 e

2000 -

CORRECTIVE MAINTENANCE OPEN 1800 --

1600 --

1400 -

( g;12@-

i em0-J . .

i, ri Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun M i

Aug Sep oct Nov Dec 1997 1990 M Non-Outage Total mMHum outage Total - -

Non-Outage Goal 4500 - TOTAL MAINTENANCE WORK REQUEST BACKLOG BY TYPE 4osa 3500 -- '8' T go  ?

l Q-1934 2008 P*-

231500 -

,, w 1000 -- 375g) 1815 500 - ,

0 Jan Feb Mar Apr May Jun

' Jul Aug Sep Oct Nov Dec O Corrective G Planned 1998 G Facilities D Predictive 9 l MWRs GREATER THAN ONE YEAR OLD 700 -

eso em-  ;

sm-m"'

pm-i g 320 3e3 g

33, 3s.

ii g a

BerreR Po-3 i i i i i @ V E E E

l

• 5o-  ! i s i s is i l 100-8  :  :

i  :

!a  ! R  ! A i M i a  : 78 -=78 m a m;a- hr- -(- --( - :- -- : - -- --

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 MWRs = one year old 'MWRs > 2 years old a

MMWRs >5 years old - - - - 2 Year Goal l l

Enclosure 22 CPS /NRC Management Meeting August 6,1998 IP Representatives:

C. E. Bayiess Chairman, President, and Chief Executive Officer l W. G. MacFarland, lV Senior Vice President and Chief Nuclear Officer W. F. Maguire Director-Operations V. J. Cwietniewicz Manager-Maintenance R. F. Phares Manager-Nuclear Safety and Performance Improvement W. D. Romberg Manager-Nuclear Station Engineering R. W. Deppi Director-Work Coordination M. C. Tacelosky Supervisor-Operations Services m

Aaenda

= Introduction W. G. MacFadand a Plant Status W. F. Maguire a Station Behavior Shaping W. F. Maguire Activities a Maintenance Performance V. J. Cwietniewicz t

a Maintenance Rule Improvements W. D. Romberg a SDFV Follow-up W. D. Romberg i

a Conduct of Operations W. F. Maguim M. C. Tacelosky a Work Management R. W. Deppi a Concluding Remarks W. G. MacFadand C. E. Bayless t-

i Plant Status Divisions 1 and 2 Technical Specification Operable l

ERAT LTC Installed Focus in Coming Weeks

- BulkWork ,

1

- Plan for Excellence Activities .

- Division 1 and 2 Outages Degraded Voltage Modifications

- ECCS Suction Strainers

r OVERALL PROORESS ON PFE RESTART SCHEDULE ACTIVITIES STATUS THROUGH 7/24/98 160 12M m

M 140 -

g 1000 D"_

g

{ 120*%2 O O

4 u 100 -

-s@

o 18 g j

0 w B0 - 4 39 - .

2 3

• 'R

" - Z W

2* '

f/h44_ z 2

1

~

/[ -

-s37)

_ 400 W d'

w 40 -

d f

1. / ,

2sj

~

2

-- >f s 200 CD 20 - .

ar ,

a f, ,

b

,18,5 gp h

,. ar i .

., g3

1. 4f ' ' -

t '

AY * '

-. 150 Q- ' "

s e e e e geesssssaa $IE$$

e e e

$ !e$ e Ie $ $

.g s a s$IIl$g;e$s s-3 aag C""*"3 Brweekly Targeted to Complete - Biweekly Actually Completed on Time or Early

~*--Cumulative Complete (includes Late) - e - Cumulative Complete on Time or Earty

- *~Cumulativ.a Actniities Let to Work Off - - - Projected Cumulative Activities Let to Work Off OVERALL PROGRESS ON PFE NEAR TERM SCHEDULE ACTIVITIES STATUS THROUGH j 7/24/98 80 900 71 33 . M m 70 2 65 am y B!

D 03 - 700 >-

2 60 - '74 0 H 4 4 34 Q  % 612 ,g3 -

. 6M g

u. 50 -

O 2 m 511 38

. 500 $

W 40 - -, 2 co -

437

.j 3 m m _,

, 4

-Ec . 4m z o 4

_. x s _.

458 W "i -

j f '3

- 2F, 20 , - d R233- 22Qg ar ' l - - D CD *0- '

, ar , ,

100 0 s 'Y , ,

ir 4 .

gsa ,1 s sassss5 s s g_gg5g Biweekly Targeted to Complete - Biweekty Actually Completed

-*-- Cumulative Complete (includes Late) - e - Cumulative Complete on Time or Early through-(6-26-98)

Cumuletrve Activities Let to Work Off - - - Projected Cumulative Activities Let to Work Off

^

E e

.I

9 9

Station Behavior Shaping Activities Values and Behaviors Mid-Year Individual Performance Feedback

~

Operating Experience to Work Groups Observation Program Feedback Change in Expectations Industrial Safety Results 4

Radiological Safety Results

Management Observations - July 1998 (Blue and Yellow Cards) 98 % 100 % 100 % 100% 100 %

$00%

90% -- 83%

80 %

380%- 73 % 73 %

• 70% --

60% --

50%--

40% -- .

- 30% --

- 20% -

10% -

a 0% - i i i i i i E f 8 5 eI $ f jj 3 E z 3,6

[

j j sy A

~

Management Observations - 1998 00 -

k' 79 0 80 --

.f 70 -

60 -

0 50 -

E 40 -

b-o 20 -

n 10-

c. O I f i I l l l l 1 I I' ' ' -- - t Jan. Feb. Mar. Apr. May. Aug. Jul. Aug. Sep. Oct. Nov. Dec.

Human Performance Errors (CR's, Safety incidents, Radworker and Security violations) 250 -

225 -

200 -

175 -

h 150 - 132 d 125 - . 108 95 98 100 - 91 75 -

50 -

25 -

0 ' ' '

. , , l Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

- 1998 l

2s- IP OSHA-RECORDABLE CASES

$20-m O

E 15 -

O o i W  !

q 10 *........... ... 1 g .Q.... ......... 1 85 ,.. - -- -; # _,. -

~

. . . . . . . .w-l 0 0 '

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 MONTHLY + YE AR-TO-DATE --

--GOAL 4- IP LOST WORK DAYS i 1

3-- .

I E

w g2 .................... ................... .................................

D Z

1 O = = = = = = _E - - -i Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov G.

1998 4 M MONTHLY +YEAP TO-DATE - - *

• GO AL l CONTRACTOR OSHA-RECORDABLE RATE 4.00 -

w g 3.50 --

< 3.00 -

o E

0 w 2.50 - 1.81 o 2.00 -- - -- - - - -- - - - - ----------- -==

w q 1.50 - -

4 1.00 -

1 m 0.50 --

0 0.00 . . l l Jan Feb Mar Apr May Jun ,Jul Aug Sep Oct Nov Dec MONTHLY --G--YEAR TO-DATE " " " GO AL CONTRACTOR LOST WORKDAY RATE 2.00 -

w E 1.50 -

1.00 --

0 3

O"

.J 0 50 ---.===-- = =

O.16

= = . - - - - - - . . - - - - - - - - -

0 00 = '

= , _ l  ! I I I l l l l 1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 M MONTHLY + YE AR TO-DATE * *

• GO AL 4

e e en I

RADIATION WORKER PERFORMANCE EVENTS /10,000 RWP 30 - -

HRS.

1 25 --

20 --

m b.

5--

tu 10 --

5--

O  : l l l l l l Jan Feb Mar Apr May Jun Jul Aug PERSONNEL CONTAMINATIONS 60 -- BETTER 50 --

Y 40 -- .

O' .

LU ,

$0-- .. -,

a .

Z ,.

20 -- 17 '

- ~~- --

10 -- 7 5 4 4 y ,.. - 4 2 2 0

,0 ,g,

,0

, d. ,0

,g, Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 1998 m Monthly Year-to-Date -- Goal 4

4

L .  ;

j l

l

)

m ax .

i

= oa Clinton Power Station ~

m om . 1998 Exposure e<2.ci.o cos 120.000 . T*'D*' " ( '****d9 d"*

adjustment in schedule) too ooo .

a0.000 .

so coa . I 1998 Exposun Goal: 185.000 Rera 4 000- Pn@cted Goal iTD: 134.625 Rem Target GoaliTD: 92.847 Rem 20.000 . i Actual Exposun iTD: 51.233 Rem l Actual Esposure 0.000

{

sSWAM8022802Ms82nRu:K23:2M882AR8causetzs8 sag 8DSM82cas i kkkkk????$555EEEEE$$$$kkkkEEEEE$$$$$$$$88888$$$$$$$$b Aug 95,1998 I

s s.

J Maintenance Performance Technician Knowledge and Skills 1988 Training Content

- Results of Qualification Reviews

- Processimprovements 1

Procedure Adherence

- Maintenance Stand Down

- ProcedureImprovements

- Self-identification

- Discipline forViolation

- Supervision in the Field 1

)

Maintenance Performance i cont'dl l

Supervision Managers on Backshift

- Quality of Observations l

- Leadership Development

]

- Behavior Shaping l

- Maintenance Performance Principles

l PERCENT OF CM MWRs REQUIRING REPEAT MAINTENANCE 20% - _

15% -

p. t o.s t % i 379o,y,g to.75%

Z g t o.oe%

h V %E s.so%

q ,g . o3 g e.74 %

10% - g , , , ,

Q. 7.77 %

7.22 %

5% - _

. 0% ' '

, l l l l , l l Jul Aug Sep Oct Nov Dec Jan l'ab Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 1998 MONTH -12 MONTH AVERAGE ---

GOAL 5% . PERCENT OF CM MWRS FAILING POST MAINTENANCE TESTING 4%--

4%--

3% -- -

2.22 %

2.18 %

H E EI% 2.31%

z 3% - -

2.i r% 2.io%

w

~

1. i.85 % 1.75 %

a 2%-- -

4 1.6s %

1.47%

2% -- -

l

- 1 l

1%- T- ~~"--- - -- -- - - - - - - - * - - - - - - - - --

l

)

.1% -- -

1 0% l l l l l l l l l l l l

- Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1997 1998 MONTH --

GOAL --G--12 MONTH AVERAGE

\i

I Maintenance Rule Improvements

Background

Plan for Excellence Action Current Status

- Restart Maintenance Rule Monitoring of SSCs -

Complete Except for Modes 4 and 5.

I Provide Training to Plant Engineering, Operations, Maintenance, Plant Work Management - Complete.

Maintenance Rule Improvements (cont'd)

Current Status (cont'd)

- Near Term Take Corrective Actions on QA, Self Assessment, and NRC Findings -- In progress.

Verify Scope and Significance of SSCs --

Complete.

Expand Detail of Maintenance Rule Functions --

Complete.

Document Basis for Performance Criteria --

Complete.

Establish Program to Manage Risk of Removal of Equipment from Service -- Complete.

Maintenance Rule improvements (cont'd)

Created Four Databases to Support Maintenance Rule Completed 2 Self Assessments since QA Audit Cycle 6 Periodic Assessment Issued July 9 Actions yet to be Completed for Full Implementation

- Monitor Unavailability in Modes 4 and 5 Challenges PRA Capability Expert Panel Support System Engineering Staffing

- Timeliness of Corrective Action Plans

- 25 systems A(1)

QA Audit in September

Post-System Design and Functional Validation (SDFV? Efforts

Background

Engineering Products Review System Surveillance Test Review Senior Engineering Review Group (SERG)

)

i

i Engineering Products Review Approximately 40 Products 3

- Modifications, Calculations, Engineering Work Requests

- Safety Evaluation Screenings and Full Safety Evaluations Review of Corrective Actions (SDFV and NSED Restart)

System Surveillance Test Review Scope (1,441 Items)

- Technical Specification Surveillance Test Requirements l

- Operational Requirements Manual Test Requirements 1

- Off-Site Dose Calculation Manual Test Requirements Results-to-Date J

- 35 Condition Reports initiated Issues Multiple Active Calculations for same Setpoint l No Margin Setpoint - Surveillance Test Control of Calculations Inadequate Corrective Action Corrective Action i

Senior Enaineerina Review Group

- ' Oversight of Engineering Products Review

- Oversight of System Surveillance Test Review

- Review of Selected NSED Condition Reports l

= Review of Selected Current. Engineering Work Products

- Provide Final Report to Management

- Transition to a Long-Term Engineering Review Board (Engineering Assessment Group)

OPERATIONS EVENT FREE PERFORMANCE AVERAGE DAYS BETWEEN EVENTS hg 40 -- YEAR.TO-DATE i BETTER 35 --

30 --

25 -- .

y 20 --

. ays 15 --

10 -- ~

5--

04

, I '

Jan Feb Mar Apr May Jun Jul Aug

(

" EVENT FREE OPERATIONS" FEEDBACK 20 -

Ratio of Positive /Const{uctive Feedback Goal- Greater Than 5-1, Less

, 54 Than 10-1 Ratio 4 11.47 j

g 10.

g 10 < -- --

0.22-2 7.39 10 44 6.14 6.13 6.03 5 3 4.74

- - 6 28 -

O 3.11 40' h , ,

5 B b h hhh s

k $ k

" EVENT FREE OPERATIONS" Cards Submitted 240 -

a Total observations 200 -

IN' 137 134 115 140 334 W E"

99 IM 93 102 i l l,l g gg 97 i . l. l.

b.iiYe ,. .

5 < $ $$$'b,h,b$, $$N s

l I

i i

Conduct of Operations 1

~

{

Event Free Operations

- Observation Feedback to Crews

- Night Orders

]

I Plan For Excellence Activities

- Conduct of Operations Procedure Program Reviews

- Turnover Process improvement I

\

- Team Training

- Aggregate Assessment

OPERATOR WORKAROUNDS 30 -

27 27 23 i

~

9 20 --

10 ff 11 15 15 15 15 15 l

@ 1 o E,R,E.E E. . '. . . . ,

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec SIEEEiB Workarounds M NSED C Maint. C OPS -

Goal Main Control Room Deficiencies Reflect on our ability to operate the plant, on ourprofessionalism and our pride in

,,,, 7,9 the Station 210 - Restrained 200 -

j go .. m Closure 180 -- 171 170 -- 162 160 7 -

Ready to 160 - 148 153 1 Work 130 - 16 m Parts 4 4 140 -- 130 3 4 30 "7 29 29 M Planning 31

} m Engineenng

,' m PMT C"""3 Complete 40 M New 21

] 18 13 15 16 _

O i i I "I l l I f --M-Total 29-Jun 6-Jul 13-Jul 20-Jul 27-Jul 3-Aug 4

Conduct of Operations (cont'd)

Corrective Action and Self Assessment

- Trending of Human Performance issues

- SRO Industry Peers - Assessment and Monitoring

- Main Control Room Deficiencies

- Operability Determinations '

Ongoing Activities Divisional Outages and Degraded Voltage Modifications I

- License Class - GFE Starts August 24,1998 Leadership Development Courses '

TAGOUT PERFORMANCE 3500 - 10 2925 9 g,

0

@ 2500 -- 2304 7 m I T 2016

~

' 88

$ 2000 - 1782 183 5

1!fg4 1528 [ j t 1 '6 1485 5[

$ 1500 -

6 1280 \f f 1386 1350 4 g 1000 -

i g

g, ,Ja

\

)/

1053 783 k

500 - .1/ ( i 1

! ):--Pg 1 0  :.PI f .. O JAN FEB MAR APR MA JUN JUL AUG SEP OCT NOV DEC J TEB MAR APR MAY JUN JUL TAGOUT EVENTS 6-5--

4-3--

2 0- l l l l l l l I JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL 1997 1998 TAGOUT INCIDENT RATE 0.3 - 0.272 0.25 -

0.198 g O.156 g 0.15 - 0.114 0.102 0.05 - 0 037 0

• w ,

2nd 3rd. 4th 1st 2nd 3rd QTR 1997 QTR QTR Otr gr Otr a

Conduct of Operations Tagout Performance 1997 Tagout Issues Past/ Current Corrective Actions Future improvements Planned

. l

L '.

m.. PREVENTIVE MAINTENANCE LATE 700 -

$*' l 7

$ 400 - - "#

y d Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1997 1998 E Safety-Related O Non-Safety-Related 1600 .. PREVENTIVE MAINTENANCE OVERDUE w 1400 --

S1200-51 I l000-- Jun fl8P i M M Jul 1997 E Safety-Related Aug Sep Oct Nov Dec O Non-Safety-Related Jan Feb Mar 1998 Apr May Jun MODE 4 LATE SURVEILLANCES 16 -

14 12

$ 10 - -

$8-S6-4 .

i j

g , , .

. I. , , , ,

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 G Operations E Cal Maint O Elect Maint MODE 4 OVERDUE SURVElLLANCES 20 -- - -

18 --

16 -

6 [' E _

i* ':-

• g

• fj sa y a.

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0 Operations E C&l Maint D Elect Maint DNSED E FP GChem

1 l

Work Management l

Preventive Maintenance l

l Surveillance Testing i i

Material Condition Backlog I Work Management Effectiveness l

l

Preventive Maintenance / Surveillance t Testina Program improvements Schedule Philosophy 4

Increased Staffing Clarified Expectations and Consequences l

. l Developed Targets Within the Work Week Process Created Specific Line items Within the Daily Work Schedule for Each Activity Software Program to identify Daily Those ST/PMs Coming Due, Overdue, or Late Required ST/PMs are Loaded into System Outage Windows a

Moved PM Program Scheduling to Work Management a

Clarified Expectations / Revised Procedure

4

,,, CORRECTIVE MAINTENANCE OPEN 1851 1751 1655 1800-, 1639 1600-1400-  ;

E il 2 -g 535 509 522

.f ,

1200 - k g 470 466 390 s 800 .322 g 600, aa 1248 13I4 1120 1130 1160 822 854 905 893 400 --

O jii Jul IIII Aug Sep Oct Nov Dec Jan Feb Mar 1997 Apr May Jun Jul 1930 Aug Sep Oct Nov Dec

-- 4 e Non-Outage Total m Outage Total TOTAL MAINTENANCE WORK. REQUEST BACKLOG BY TYPE 4500 -

3942 200 3500 -

3000 -

h 1934 2008 o 2500 --

5

@ 2000 -

1500 -- ks k h '

1000 - 1751

g  %

% 6

{$ $$

0

, 4 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 O Cortective G Planned D Facilities O Predictive en

Maintenance Work Request Backloa Backlog has increased Identification

- PFE Reviews ,

Restart Backlog Restart Scheduling i

If Ii

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S W E D

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Scheduls Stability and Schrduls Adherance -

Numbers reflect activities scheduled from T-6 thru T-0 and activities completed (T-C) 2000-1900 -

1800 - 1 1700

- 6 5 T-6 1600 . 01

'71 gT3 1400 - 1 1300< [y '. ;

1200

!OI 'd G T-O 1000 '

, E T-C 8* ' '

.ij f ;

['

600 -

'.f }

O Rollover f

f.) }

500 j pl !'[ E Emergent 400 - 2 5 ,

300 - . 2 '

200 -

5 100>

0 4 "j 0 ,

6-27 to 7-26 T-0 TO T-C ACTIVITIES NOT DONE

SUMMARY

FOR MONTH OF JULY 1998 412 ACTIVITIES CHED OGIC PARTS OPS RESOURCES 15% 4%

E NSED RESTRAINTS

.,, 14%

PLANNING 2%

MAINT RESOURCES 20%

gg EXPAND SCOPE 13%

Work Management Effectiveness Work Scheduling Schedule Stability Schedule Adherence Restart Make-It-Happen Team Meeting l

Concluding Remarks Working to Our Plan

(

Performance Monitoring I

(

)

Management involvement I

[  : t. Enclosure 23

,..a -\.

' .- 1, ,

1 1

IP/NRC Management Meeting I

Clinton Power Station

]

0350 Restart Panel Meeting October 23,1998 l

4 i

l IP Representatives:

W. G. MacFaclard, lV Senior Vice President and Chief Nuclear Officer J. A. Goldman Manager-Work Management W. D. Romberg Manager-Nuclear Station Engineering D. W. Waddell Manager-Recovery W. F. Maguire Director-Cperations G. D. Tierney ElectricalMaintenance Manager l

l

i .

, ) . .

~

Agenda Introduction W. G. MacFadand j

Plant Status J. A. Goldman  ;

Restart item Schedule D. W. Waddell Restart item Status

- Operational Readiness W. F. Maguire

- Circuit Breakers G. D. Tiemey

- Engineering issues W. D. Romberg

- Qualified Materials and Parts J. A. Goldman I 1

Concluding Remarks W. G. MacFadand l

Plant Status Major Division 1 Work Window Completed with the I Following Accomplishments: {

I

- Hot Short Mod on Greater than 50 Circuits

- Tie-ins for Feedwater Keep Fill and Successful Completion of the Check Valve LLRT

- Cleaning and Inspections on Safety Related Heat Exchangers Shutdown Service Water Flow Balance Testing Conducted; Modifications Required for Mode 1,2, and 3 Operability in Subsequent Division Window Other Significant Work Accomplished

- Safe Modification / Rework to Inboard MSIV

- RAT Disconnect Switch Installed to Allow for SVC Tie-in and Testing

- Containment Dome Coating Inspections and Repairs l Approximately 50% Complete, with Remaining Containment and Drywell Areas 100% Complete

- RWCU System Outage

I Plant Status (cont'd)

Major Modifications Ongoing Degraded Voltage ECCS Suction Strainers Feedwater Check Valves' Stay-Fill System Fire-induced Circuit Failures

- Thermo-lag Resolution Industrial Safety 1 Year /2 Million Manhour Milestones OSHA Rates improved Recent Trend Requires Refocus Response to LaSalle Diver Event

- Observation Program Radiological Safety Radworker Performance

- ALARA Personnel Contaminations

ILLINOIS POWER OSHA-RECORDABLE & LWD RATES 3.0 - -

2.5 -

2.0 1.84

c. .  ;  ;  ;  ; g 1994 1995 1996 1997 96YTD E OSHA Rate O LWD Rate ILUNOIS POWER OSHA-RELORDABLE INCIDENT RATE 3.5 - 3 33

, 3.0 --

2.5 -

2.0 -

1.5 - g,97 1.0 -

0.5

^^- 'I l i l l l l l t i I I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec m Monthy 1998 - *--Year-to-date CONTRACTOR OSHA RECORDABLE & LWD RATES 6.0 -

5.0 - 4,37 g, q j n g g g g i 1994  :@s 1996 1997 98YTD Mt,2HA Rate O LWD Rate CONTRACTOR OSHA-RECORDABLE RATE 40-3.5 -

& 3.0 -

y 2.5 -

tg 2 0 - . ......... . ....... . 1.s2 , .. .,, ..

h1.5- -

= =  %

na e i i l i i i i l i t 1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec m MONTHLY ---e- YEAR TO-DATE - -

- GOAL

r-F

+ -

, I RADIATION WORKER EVENTS /10,000 RWP HRS.

g, 8- l w

T g 6:  :.

e

,E 4 -

2 E

2-0 , , , , , , , ,

Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 l

200-Clinton Power Station 1998

^

580 -

Exposure e coas 160-140 -

1998 Esposure Goat: 185.000 Rasa arget Goal (revised goal due to 120 - Projected Goal YTD: 174.685 Resa adjustment in schedule)

Target Cent YTD: 16&637 Rese 100 -

Actual Exposure YTD: 101.343 Resa 80- )

.0 40-ctual Exposure 20 -

0 ESC AR$DERG52R88W ARG2 NR30 T ABSE AREcanget gGECRRsceggerna kkkkk$$$$ENNNNEEEEffff.1kkk33.3335555$$$$88888$}yyyyy PERSONNEL CONTAMINATIONS BETTER 70 - 65 l 60 y l 50 - 48

                                                                                              /
                                        $1 ** '

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                                                                                                                                       I" 4         3 2                                    ..            2 0 --

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                                                                                                                                   =   y    y      y      y             y Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997                                                          1998 Monthly                                     Year to-Date                                         Goat

l Plant Status (cont'dD Nuclear Safety j

             - Key Safety Risk Levels and Risk Awareness
             - Continued improvements in ERO Readiness
            - Conservative Decision Making in Operations Focus in Coming Weeks Division 2 Outage Degraded Voltage Regulating Transformers SX Heat Exchanger Cleaning / inspections SX Flow Balance Modifications Mode 1,2, and 3 PMs and Surveillances Effective Resolution of Condition Reports
          - Work-Off Rates for in-Plant Work
          - Licensed Operator Requalification Training

1 l Restart item Schedule l l l Restart Closure Package Status 1

                                              )
            - Status of Submittals            4
            - Re-opened Packages Restart Readiness Reviews          ,

1

            - Organizations
           - Programs                         '
           - Systems

_ ' ~ h I d -

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                                                                                                                             - 9
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                                                                                                                                 ~

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                                           ..       ...         ..      +           _
                                                                                            +                   +           ..        n  n  n  n   D A._.

Week Ending

Operational Readiness Licensed Operator Training Licensed Operator Annual Requal Exams

             - Conducted August 24 - September 25
             - Crew Performance (5 Shift / 2 Staff Crews) 3 Shift Crew Failures (23 Exams Given)   l 1 Staff Crew Failure (5 Exams Given) 1 Individual Performance - 63% Pass Rate ,

1 Level 1 Condition Report Generated Fact Finding / Problem Solving

            - All Licensed Operators
            - RequalInstructors
            - Operations Management

                           ~

O_perational Readiness Licensed Operator Training <' cont'd) investigation Findings Operations Management Raised Performance Expectations 0 - Significant Personnel Changes (Operations and Training) Training Position Vacancies Reduced Simulator Time Decreased Management Observations in Simulator Ineffective Assessment and ineffective Follow-Through on Identified Actions No Trending of Performance Feedback Database Not Reviewed Instructor Certification issues

                                                       \

l i Operational Readiness Licensed Operator Training (cont'dD Root Cause Change Management Within the Operations and Training Organizations was ineffective Weak Corrective Action Program and a Lack of Program Oversight Corrective Action Change Management Guidance in Conduct of Operations Operations Management Expectations to Training "Back to Basics" Training Re-examination of All Crews Address Programmatic Training issues

         - Systematic Approach to Training
         - Curriculum Review Feedback /PerformanceIndicators

1

 .   .                                                           {

Operational Readiness { Safety Tagging i Recent increase in Safety Tagging Events

               - Six in Last Two Months
                     " Temp Lifts" Common bi Geveral             !
               - Immediate Hold on " Temp Lift" Activities
         -                                                       I Assessment Performed (Reached Threshold)

Improved Safety Tagging Procedure

              - Clearly Defined " Temp Lift" Philosophy
              - Clearly Defined Roles and Responsibilities for Changes to Tagouts
              - Additional Checks imposed on Tagging Change Activities Training Provided
             - Just in Time Training on Shift Prior to Procedure issuance
             - Reinforced in This Cycle of Requal

Operational Readiness Technical Specifications and Configuration Management Focus on improved Technical Specifications

            - White Paper on Performance
            - One-on-One With All SROs "Back to Basics" Training Main Control Room Deficiencies Operability Determinations                    i 1

OperatorWorkarounds Out-of-Service Annunciators Temporary Modifications 1 1 Fire impairments  ! AR/PR Modification

Circuit Breakers GE Magne-Blast Westinghouse DHP

               - Safety Class 1E
               - Safety Class Non-1E ABB K-Line
             - Safety Related Non-Safety Related 1

Molded Case Circuit Breakers

1 i Engineerina issues 1 Bounding of Design issues Control of Calculations Control of Setpoints l l i I 1

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EVENT AND CAUSAL FACTOR CHART

SUMMARY

                                                              ~

RHR "B" Loop Shutdown Cooling Suction Valve Interlock issue (F0068) Human Error soumed ConAguraban ofirdertock A

                     -allure to Adequately Perf                          IrWwa independent Impact Assessment as                          Reviewas Required byCPS Required by CPS 1003.01                                    1003.01 7

_. J did k (12-22-97 ) ld w ,'48',a'240' l J CR Written to Address QA Ad on RWed in inability to Remotely Fire Protection  ; inabildy to Place B Loop RHR in N Swession Pool Estabhsh B Loop Cooling Suppression En0 Pool Cooling pg

                                                           -5 Evalumuon o

50.59 did not Address Hardware Imped on Circuit and Safety and Failed to idenOfy USQ ineffective 50.59 Ineffective 50.59 Evaluation as Required Review as Required by by CPS 1005.06 CPS 1005.06 LEGEND c (ca"';-ga) numan c,, - . - . . . soumed ConfigWWtion of OrlierioCk

      ~

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Qualified Materials and Parts Issue V.2D issue: Several Examples of Weaknesses in the Control of Materials Requires Additional Review to Ensure Qualified Materials and Parts are installed in Plant Systems. Primary Cause Lack of Understanding of General Plant Use (GP) and General Plant Limited Use (GL) Verification Requirements Additional Contributing Weaknesses

                    - Excessive " Satellite" Storage Locations in the         !

Maintenance Shops j

                    - Receipt inspection Training and Procedures not          '

Rigorous Corrective Actions

                   - Training for Maintenance Planners on GP/GL
                   - Awareness of GP/GL Limitations in the Shops and Requirements for Planner Approval via the Work Package for Specific Applications
                  - Additionalinformation included in Station Parts Lists (MEL)
                  - Satellite Storage Locations Cleaned up
                  - Training and Procedure improvements for Receipt inspection em..

• Enclosure 24 g

IP/NRC Management Meeting Clinton Power Station 0350 Restart Panel Meeting November 10,1998 lP Reoresentatives: W. G. MacFariand, IV Senior Vice President and Chief Nuclear Officer G. A. Hunger, Jr. Manager-Clinton Power Station W. D. Romberg Manager-Nuclear Station Engineedng D. W. Waddell Manager-Recovery R. F. Phares Manager-Nuclear Safety and Performance Improvement J. A. Hanson Director-Nuclear Training

Agenda Introduction W. G. MacFadand Plant Status G. A. Hunger 0350 Closure Package Status D. W. Waddell Training J. A. Hanson Maintenance Rule W. D. Romberg Corrective Action R. F. Phares

Plant Status Safety Division Status

       - Division 1 Operable for Mode 4 Division 2 Work Ongoing
       - Division 3 Available                                  1 Awaiting Technical Specification Change Request Approval from NRC for Diesel Droop Mode MajorAccomplishments
      - RWCU and Control Rod Drive System Outages
      - ERAT Automatic LTC Operable
      - Completion of ECCS Suction Strainer Modification Major Modifications Ongoing
      - Degraded Voltage SVCs Regulating Transformers Feedwater Check Valves' Stayfill System Modification
     - Fire-induced Circuit Failures
     - Thermo-Lag Resolution

4 Plant Status (cont'd) Industrial Safety

         - Current Trends Radiological Safety
         - Radworker Performance
         - ALARA Nuclear Safety
         - Licensed Operator Requalification
         - Event Free Performance
         - Human Performance
         - Observation Program Feedback
         - ERO Readiness Focus in Coming Weeks
         - Completion of Division 2 Outage Modes 1,2, and 3 PMs and STs
         - Effective Resolution of Condition Reports
         - Work-off Rates for in-Plant Work

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ILLINOIS POWER OSHA-RECORDABLE & LWD RATES 2.57 2.5 - 2.0 - 1 84 g i i , 1994 1995 1996 1997 98YTD E OSHA Rate DLWD Rate ILLINOIS POWER OSHA-RECORDABLE INCIDENT RATE 3.5 - 3.33 g' 3 0 - 2.5 - 2.0 - 1.5 - q 9 7, 1.0 - - g 0.5 - 0.0 l I I I I I I I I I I ( Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 M MontNy --*- Year-to-da% g, CONTRACTOR OSHA RECORDABLE & LWD RATES 5.0 - 4 4.37 0 -- 1 I I I i 1994 1995 1996 1997 98YTD 50$HA Rate O LWD Rate CONTRACTOR OSHA-RECORDABLE RATE 40 [.[.3.5-3 g '0 E ': y1.5- N ________ _ _ i >2_ l l l l l l l 1 1 I I i Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M MONTHLY -e--- YE AR-TO-DATE - =

                                                                                                                                           = GOAL

200 - Clinton Power Station 1998 Exposure 180 - 1998 Esposure Goet: 185.000 Rem 160 Projected Goal Projected GoaliTD: 178.J76 Reni 140 - Target Goal YTD: 169.630 Ren, Target Goal (revised goal due to adjustment in 120 - Actual E3Pom YTD: 115.266 Rem scNd*) 100 - 80 - - 60 - J l 40-20 - Actual Exposure 0 E5: $in'alasalats:== g: 5'ala:5:5:5 5t al m E Ea>>=>>L5: a 5 E =: sts dd>=p=RRXtR>XRsXRRXR 5:s s"Eax? ai n:RkMRsbtRRXCRadtR6 st at at a: at at at =:a:$:p>>>>>=2=adwpwa> dtt tXERR Sad >>===; aar2=ad>>

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m OPERATIONS EVENT FREE PERFORMANCE - 45 -- DAYS BETWEEN EVENTS ON A 90 DAY ROLLING AVERAGE 40 -- 35 -- co W g 30 - .---...................................... ........... 2 td 25 -- to

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i l Jul Aug' Sep Oct l m Events - - - Goal 90 Day Average i 104ug ERAT bus voltage went below the minimum operable and not recognized to adjust the ERAT-LTC untd notified ty load despatch 22-Aug Failure to enter LCO 3.6.1.3 when RHR shutdown cochng suction valves were tar.med out for maintenance l 04-Sep Drain hoses incorredly restored on temp hft of tegout 9tLO881 1 12-Sep Inadequate Review of Tagout Temp kft resuns in approximately 300 gallons of water bemg sprayed on VG "A" filter train. l 18-Sep Tagout 964392 did not have boundary valve tag on handwheel 1833F067A to prevent flow rotaten of recirc pump and motor. 22-Sep Due to the incorrect performance of 9082.01, the ERAT was considered operable when it should have been considered INOP. 03-Oct During performance of temp kft of tegout 984953,1 B21-F067A automaticahy closed due to group 1 isolation signal 07-Oct Mrainterpretaten of 1-9tMP 201-OE led to not complying wnh 1-98-04-047-0D requirements to maintain B RHR operable. 18-Oct 4160V Bus 1 A1 de energized momentarily due to As P.T. fuse cubicle door was opened inadvertently, Div 1 DG auto started.

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0350 Closure Package Status l Approved Closure Packages Since October 23, 1998 Meeting

       -  Review of Existing 0350 Packages
       -  Status of Remaining 0350 Issues Those Packages That Are Awaiting the Completion of Planned Actions:

0 Resolve Degraded Voltage and Electrical Distribution Concerns (IV.4) O Perform Readiness Reviews (VI.4C) 0 Validate the Adequacy of Calculations (VI.2) 0 Validate the Adequacy of Setpoint Program (VI.3) 0 Reduce Backlog of MWRs and Review the Cumulative Effect of the Backlog (IV.9C) I l 1

l l 0350 Closure Package Status fcont'd) . Those issues For Which We Are Not Yet Satisfied ' With The Completeness or Effectiveness of Actions Taken: 0 Review and Revise At normal Operations Section of Operations Procedures (11.3) 0 Develop a Process to Review Deferrals of Preventive Maintenance items (V.1) 0 Establish and implement Actions to Achieve and Sustain improvement in the Corrective Action Program (111.1) O Establish and Implement Continuing Operator Training Emphasizing Technical Specification Adherence / Knowledge and Recognition of Degraded Conditions (ll.1)  ! l O Work Management Program Changes to improve Prioritization, Planning, and Scheduling of Work (IV.8C) Those issues Having Emergent issues to Resolve or increased Scope: O Resolve issues Associated with Circuit Breaker Failures (IV.3) 0 Qualified Materials and Parts are Installed in Plant Systems (V.2) 0 Identify and Correct Deficiencies Found During Operator Requalification Exams

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                                                                                   ~

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                                    ~

ddressable Observations Goal 80 - -- ...- ..................................--- ......-...--.....- - 80% 70 - 64 64 -70% 62 62 Operations instructors exempted from g 60 - in-plant observations for rest of 1998

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N' CORRECTIVE MAINTENANCE OPEN TOTAL MAINTENANCE WORKORDER BACKLOGSY .. . . 2400 5000, ME ( .,,. 8* '"'

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k. aao  ;

l  ! IW _ i r

Jan Feb Mar Apr May Jun Jul L

Aug o Sep 0 Oct Nov Dec 1998 O MWOs inanted D RF4 Inthsted 5 MWOs Closed

m- ALL LEVELS COND N REPORT STATUS 2473 2495 2000 - 163 1 1 1500 - 13 l t000 . 600 500 - 384 397 i 418 7 g 405 0- t l l l 1 Jun-98 Jul-98 Aug-98 Sep-98 Oct-98 E CRs issued 0 CRs Closed D Without CA Plan (Backlog) W CR Open I

Corrective Action Performance Goals No Overdue Level 1 and 2 Without Corrective ) Action Plans by December 4,1998 Total Backlogs

         - 2 Month Backlog by December 31,1998 1-1/2 Month Backlog by February 28,1999 Corrective Action Implementation
         - 90% Will be Completed On Time by December 31, ,

1998  ! 1 Root Cause and Apparent Cause Quality

         - Maintained Above Established Limits Causes of Repeat Events Will be Understood I

1 I ROOT CAUSE ANALYSIS QUALITY INDEX (RCAQI) 13 - I l 12 - 11 10.75 Goal 9.98 10 - ....................... ........... ............. ..... .. .. . g. 8.5 8-7.5 7-6-- 5 , , , , May Jun Jul Aug Sep Oct Nov Dec 1998 APPARENT CAUSE QUALITY INDEX 100- - 100 % 90 - - 90% 80 - --- ------------ ------------ ------ - 80% 76% 70 - -70% 65 % A 60 <- A 60% 60% 3

 $                                                                                                                                     4
 $' 50 --                                                                                                                      - 50%   m 52                                                                            42 M

40 - - 40% 30 - - 30% j 20 - 2I ' i 1 20 % i 9 10 - -10% 5 3 0 ," 0% , Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1 M Accepted - > Reviewed --*- Acceptance Rate - - - Goal I 1

o e Condnion Status 400 , Con ition po tatus 1,245 1.278 1,269 1M 1,251 341 M4 3,4, 337 88 81 88 86 m,

                       ~

400 < . 75 150 < 13 I4 100 < 40 48 43 63 M 200 < 125114 130 97 tot M. 37 10 < 0 - 0 - Jua.-98 M98 Aut90 Sep06 Oct9s Jurv98 Ju6 98 Aut98 Sep98 Oc098 a CRe seeues DCRs Ckseed DWeisue CA Man tBeeMeg) ECR Open S CRa leeuer. DCRe ceeed Gwessut CA mon (BecMeg) ECR Cpen Condit n Re Status Woe knogement 120 < Condition Report Status 350 < 100 < 300 , g, y g 23 64 68 N Jun-98 Ju6 98 Aup 06 6ep-98 Oct-98

                                                                                                                   "             "                  E' B CRe leeued      DCRe Oeses         DVdthout CA men (Seeise)         WCR Open                    A Cne leeund   DCRs Oceed        5 Wheut CA men tBeamegl      OCR Open     j 130'                                                                                                                                      It on e et       s 107                                                                            450 '                                                             423 97                    400                                               #7                             377 too ,                                                                                                                              374 84                                                           350 <             322 Jun 98            Jul D8            Aup 98            SeP98              Oct 98 Jun-98         M98              Aut98            Sep98          Oct-98 BCRe naeued        OcRo oesee         BW1heut CA Men (Seelogi            SCR Qpen            E sseued         DCRe CM            SWhout CA egan ggggyegy        SCp Qpen

tnclosure zo 4' IP/NRC Management Meeting Clinton Power Station 0350 Restart Panel Meeting December 17,1998 IP Representatives: J. P. McEl wain Vice President-Recovery G. A. Hunger, Jr. Manager-Clinton Power Station W. D. Romberg Manager-Nudear Station Engineering R. F. Phares Manager-Nuclear Safety and Performance Improvement J. A. Goldman Manager-Work Management D. W. Waddell Manager-Recovery W. F. Maguire Director-Operations D. L. Smith Director-Security and Emergency Planning G. D. Tiemey ElectricalMaintenance Manager l i I ILLIN91S P(uWER

4 Aaenda ' 1 i Introduction J. P. McElwain i I l Piant Status G. A. Hunger Operations Performance W. F. Maguire ERO Exercise Corrective Actions D. L. Smith Corrective Action R. F. Phares B'reakers G. D. Tiemey Backlog Manag6 ment J. A. Goldman Preparations for Restart I D. W. Waddell Conciusion J. P. McElwain ILLIN91S P&WER

e Plant Status Safety Division Status Division 1 Operable for Mode 4 Division 2 Unavailable Due to Ongoing Outage Work

                 - Division 3 Available Recent Major Accomplishments
                - Completed Containment Dome Painting Major Modifications Ongoing
                - Degraded Voltage SVCs Regulating Transformers
               - Feedwater Leakage Control System
               - Fire-induced Circuit Failures
               - Thermo-Lag Resolution Industrial Safety Radiological Safety ILLIN 91S P&WER
                                                                      )

3.0 . ILLINOIS POWER OSHA-RECORDABLE & LWD RATES 2.57 -- 2.5 - 2.0 - 1 84 g g g g g 1994 1995 1996 1997 98YTD E OSHA Rate ulWD Rate 3.5 - lLLINOIS POWER OSHA-RECORDABLE INCIDENT RATE 3.0 - E 2.5 2.0 - 1,5 - 1.24 y1.0-0.5 -

     ^^

l l I I I I I I I I l-Jan Feb t Mar Apr May Jun Jul Aug Sep Oct Nov Dec mMonthly --o--Year-to4 ate 6.0 . CONTRACTOR OSHA RECORDABLE & LWD RATES 5.0 " 4,33 4.37 00 1 I I 1994 I i 1995 1996 1997 98YTD E OSHA Rate O LWD Rate 60 - CONTRACTOR OSHA-RECORDABLE RATE 5.53 g5.0-40-

                                                                              .... ... ....                                       17 . .
         ^

l I I i i i l I I I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 M MONTHLY ---4-YEAR-TO DATE -

                                                                                                                    - - GOAL

200- \ Clinton Power Station 1998 Esposurr 180- - __ itSu F p sure coat: taitN>0 Rein Targes Gomi YTD: 17s.453 Ren* Projected Goal 140' Projected Comi Y1 D: INI.518 Rent TarDet Goal (revised goal ) 1 Actual Espesure YTD: 130.09J Rern due to adjustinents an j schedule 100 - 80 - 60 - 40 - 20 - Actual Exposure 0# E> E BF2 E P S E E R * * * * ' * *

• E E E S E E E E W E E E E E E E f!
• R E E F F F *
• E E E *
• E E E E E E R s44R'sss &

BEA BE(dnB>>RsRERT>E.eiP'

                                       -ss      ssR GEGGES802GGGG33333SSCS88883GGGGS8888SS$9gst299:::        sssRsssRksRs               ssRRsss s WAR'_nkADER.E<.2k'Ph>>>hd>>          sssssssss  22000 i

i i l RADIATION WORKER PERFORMANCE j 10 - EVENTS /10,000 PWP HRS. 8< 6'  ; m t G  ! i 8 l 4-- 2-0 . Mar Apr May Jun Jul Aug Sep Oct Nov Dec PERSONNEL CONTAMINATIONS 85 - BETTER 77 75 -- Y l 65 -- l l 55 -- 48 85 45 -- /

   $                             .f g 35-     -

25 - 20 . t9 ~ ~ 15 - - 4 5 *z . 9' 9 2 4 3 5' 0 o i 3 aus t 3

                                  -.Ey               1 sum #Y unu      -                                        =

U T 4 y y y T U I 3 ,

      " " Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997                                                                                 1998 m Monthly                                                   Year-to-Date                                          Goal

Plant Status (cont'd? Nuclear Safety

             - Event Free Performance
             - Human Performance l
             - ERO Training                             !

1 l Focus in Coming Weeks

            - Completion of Division 2 Outage
            - Effective Resolution of Condition Reports
            - Work-off Rates for in-Plant Work
            - Use of Controlled Documents Scheduled Restart Date i

l ILLIN91S P&WER

F.' e prrors/10,see Man 4tourg 5, i

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03

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                   . .e    QW. nse eror m      : Tam enz Rae         x .aw.sywesterarame       -,_ syvest Bra Rae i

I l i i

9 Operational Readiness Licensed Operator Trainina Operations Training Actions

                - Operations Training Lead - M. W. Lyon
                - Experienced Industry Personnel Brought in
               - Comprehensive CR Investigation Completed Program Remedial Actions
               - Behavioral Focus - Four Rules
               - Daily Video Review
               - Scoring of Desired Competencies
              - Dynamic Simulator Examination Conducted Emergency Preparedness Drill Weaknesses Licensed Operator Requalification Examinations
              - Scheduled January 7 - February 5,1999 ILLINSIS P49WER                                              l

{ l

Operational Readiness Event Free Operation l - Operations Events

               - SafetyTagging I
               - TechnicalSpecifications Comprehensive Review of Weaknesses Operators involved in Corrective Action Event investigation Expectations
              - Crew involvement in Human Performance
              - Clear Expectations on Quality and Timeliness Performance Feedback
             - CrewSpecificIndicators Individual Feedback on Observations
             - Night Orders, Lessons Learned Utility Sentice Alliance (USA) Assessment
             - >800 Observations of 170 Behaviors
             - Positive Feedback, Some Focus Areas ILLIN91S P&WER

I .

             ~                              OPERATIONS EVENT FREE PERFORMANCE DAYS BETWEEN EVENTS ON A 90 DAY ROLLING AVERAGE 45
                                                                                                                                     )

40 35 m. E g 30 - - ~ ~ - - - - ~ ~ = = = = = = ~ - - - ~ ~ ~ - - - ~ ~ ~ . = = = = = = = = = =

                                                                                                                                     ~

5 l

    " 25 W 20 25 r

w if15 ce Y k 10 ' M N J ' ' u u ,r 5 0 8 '  ;' ' ' ' '; ' '  : Aug Sep Od Nov m Events

                           - G oal 90 Day Average 04-Sep Drain hoses incorrectly restored on temp hft of tagout 980881 12-Sep Inadequate Review of Tagout Ternp hit resuts in approximately 300 gallons of water being sprayed on VG *A* hiter train.

18-Sep Tagout 98-0392 did not have boundary valve tag on handwheel 1833F067A to prevent now rotaten of recirc pump and motor, 22-Sep Due to the incorrect performance of 9082.01, the ERAT was considered operable when it should have been considered INOP. 03-Oct During performance of temp kR of tagout 98-0953, iB21-F067A automatically closed due to group 1 isolaton signal. 07-Oct Misinterpretaten of 1-98 09-201-OE led to not complylng with 19644 047-OD requirements to maintain B RHR operable. 15 Oct 4160V Bus 1 A1 de-energized momentarily due to its P.T. fuse cubicle door was opened inadvertently, Div 1 DG auto started. 25.Nov Added VX work with indequate tagout barrier

Event Free Operation OPS CREW 1

                              ............................u.                                                  .
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0 $ CREW 4 CREW 5 i

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                                                                                                                          - ~ . . . - _ . . . . - . - . . ~ . - - - - - ,

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i i 4 r lTAGOUT EWNrs c r i 1997 1998 9 I 3 2 3p _._. 2 f __2., I 1 1 1 1 1 1 1 , 0 0 0 0 0 0 0 0 0 0 0  !, 4E!Iii45&9ffigggg'sigggg l l

          =      - - - - . - . , - . _
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ERO Exercise Corrective Actions ' 1 i Overall Results Facility Performance 1 1

            - Facility Evaluation
           - Strengths
           - Areas forImprovement Corrective Actions
           - Procedural Revisions
           - RemedialTraining
           - Facility / integrated Drills l

ILLIN91S P(uWER

1 Corrective Action Performance Results f Level 1 and 2 Condition Report Goal l

         - Corrective Action Plan Development Goal
         - Quality Indices Repeat Significant Events 40500 Inspection Readiness
        - Condition Reports
        - Self Assessments
        - Trending                                 l Use of Operating Experience l

ILLIN91S P(uWER

4 SITE CONDITION REPORTINITIATION AND CLOSURE 3000-l 2599 21 2%S 2500 - ~ 2493 2487 2502 - 2431 - _ 2Of 2328 - l 2099

                             -                                                                                                                    2108 2000     .

1971 l 1500-i 1000 - #6 30' l + 371 l 332 42 m 423 42d 345 33E ' 599 60' > 538 500- 451 449 476 46 401 l 3 14 316 2

                                                                                                                     +

151 I 0 + h+h '+

                                    -+         -+           1-e               -+            +         +      -+        -+                +                       l
                                                                                                                                                  - -e        4
                       @          8          8             8               8            8        8        8         8 8            8         8 k          $          $             $               $            k        k        $         $             $            $         $

N CRs issued R CRs Closed D CR Open

I LEVEL 1 AND 2 ACTIONS DUE IN THE NEXT 12 MONTHS 140 140

        .        122 120                                                                                                   )

j 100 - 84 80 - o m. M 2 40 - 34 g, 17 19 0 ~~ = + -+- + + + + -+- -+- -+- -+- + + -4 j E 8 8 8 8 8 8 8 8 8 8 8 $

          ;      $       48          $         1       I4           4        IA$              $   5 E

o M Level 1 and 2 Actions Schedule for next 12 Months NSED Plant Engireenng Total Past Due = 34 1 NTD-Maint Training 1 3% 3% Maintenance Piarnng 1 Management 1 3% 3% Expenence Assessment 1 3% Maintenance Electncal 1 3% NSED Engineer NSPIIAG 17 49 % Projects 1 3% plant Operations 2 6% FRG 2 6% NSED Design Engineenng 6 18 %

e l ROOT CAUSE ANALYSIS QUALITY INDEX (RCAQl) 12 7 l 10.75 10.45 9 98 10 - 10 8.5 8.75 8- . 7.5 4 8 j 5.28 4 2-0s- --+--- -+-- -+-- i -+- ----+- t May-98 Jun-98 Jul-98 Aug-98 Sep-98 Oct-98 Nov-98 Dec-98 APPARENT CAUSE QUALITY INDEX 100 - 100% 90 - 90% 90% 00 - M- - -- M - -.- -w- - - x. - -x - -.- --x- - - M -- - -K- - -- M- - - - M -- -M- - - X - 80% 6% 70 - 70 % 65% 60 - 00 % -60% 50 -

                                                                                                                           - 50%

42 40 - 40% 30 - 30 2 30% 23 21 20 1% i 16 20 % 10 1 5 10% 3 0- + -+-

                                                                                               +        -+-      -

0% Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M Accepted m Reviewed --*- Acceptance Rate

STE Plan Development Backlog Status 1499 1500 g479 1400-1242 1200

                                                                                                                                     \

1000-935 836 800 600 - 400 - 200 - O! i i i i i i i Jun-98 Jul-98 Aug-98 Sep-98 Oct-98 Nov-98 Dec-98 M W/O Plan (Backlog) "4+-W/O Plan (Backlog) DEC. 31 Goal 804 -#-W/O Plan (Backlog) FEB,28 Goal 603 l ACTIONS COMPLETED ON TIME 1200

                                                                                                            !6               100 %

m._ __

                                              -. _. _ _                  _ _ _ m                                          - 90%

80% 866 800 J57 713 c% 72 m _ 56 % 600 $65 4t % rn _.rA% 3 400 324 30% 251 200-- - - - - - 10% 0- - + - - w- -+--- - , - - ---0% Jul-98 Aug-98 Sep-98 Oct 98 Nov 98 Dec-98 M Actions Due arxj Complete MMEN Actans Due

             ^

Percent Comp;eted on time. -X-Corrective Action 90% Goal

REPEAT SIGNIFICANT EVENTS 10 - 9 - B - 7-6- M e 8 5-5 5 m lE 4- ^' 04 00 0' 04 .4 3- ^2 0 .3 2- ^2 02 02 .2 1 1 1 1 1 1 0 0 0 0 0 0 0-

• E E k k
• k 3 3 3 $ 2 3 3 3 *

                                                                                         <    3   3 k      $     $     $     h $   $   $   k   k   $    $    k     $           $   $ b ammus Events                              -+-- 1998 Total

\. Breakers Confirmatory Action Letter Westinghouse DHP Breakers

              - Failure Mechanism
             - Corrective Actions
             - Basis for Reasonable Assurance Future Actions Westinghouse DVP Breakers GE Magne-Blast Breakers ABB Breakers ILLIN 91S P(&WER a

Westinghouse 1E DHP Breakers Status / Schedule - 25 -22 22 20 16 16 16 14 14 15 15 13 11 33 10 10 6 5 0 0 0 0 0 0 0 0- -+- 0 0 00

                                                                       ~.+-                     >

a Total a Refurbished /New a Reworked per 8410.21 Pending Refurbishment / Replacement Westinghouse Non-1E DHP Breakers Status / Schedule 60 50 39 41 39 40 37 35 32 30 30 - 29 22 U 20 20 - 2 M 9 8 8 8 10 3 5 0 ' I E si!5 a Total 5 i i  ! E i E i s a Refurbished /New u Reworked per 8410.21 Pending Refurbishment / Replacement l E Pending rework per 8410 21 i G.E. Magne-Blast Breaker Rework Status / Schedule 5 5 5 6 5 s Total 4 4 3 m Refurbished 2 ., f . Pending Refurbishment 0 0 -- --4--- -- a 6/18 10/30 2/19

ABB 480V K-Line Safety Related Breakers-Status 35 33 33 30 25 20 15 10 5 0

                              # of Breakers                                 # of Breakers in Service                                  Refurbished i

l ABB 480V K-Line Critical Non-Safety Related Breakers Status / Schedule 88 90 - 80 - 70 j 60 50 40 40 30 28 20 16 12 10 5 4 , 0- ---+ E -+- -+- Total 9/30 10/31 11/30 12/31 1/31 2/28 3/31

                                     ._ . . _ . _ _ _ _ _ _ _ _ . _ .          . _ _ _ . . . _ _ _      _      _ _ . - . --. -]

I Backlon Management ' Corrective Maintenance Main Control Room Deficiencies I Preventive Maintenance Surveillance Tests t I I l ILLIN91S P&WER

Z HZ p 98ea E!B.

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MAIN CONTROL ROOM DEFICIENCIES MAIN CONTROL ROOM DEFICIENCIES 120 -- 120 - 100- 87 9a 100 -- as a4 as as 80 - ~ 80 - 73 60 - 58 60 - - 54 40 , 40 -

• 21 20 - ~

Jan Feb Mat Apr Wy Jun Jul Aug Fep Oct Nov Dec 39 E in Progress OPMT m in Progress 'PMT j 1

r, (RFS) PM Workoff Projection Safety Malated Pfers me

                                                                                                                                                                                                                                                       --- Befesy feed Past Due & Late see                                         - - -                       /., ',                       .-              -
                                                                                                                                                                                                                                            .                  gPngected)
                                                                                                                                                                                                                                                       -*-$ebly fatal Past Due & Late see                                                                                                                                                                                                                                                         I
                                                                                                                                                                                                                                                             . RF6 Safety Peat Late (Protected) g m           .-
                                                                                                     - -.. '*., N -                                                                                                                                            Ocel 0 Lane
                                                                                                                                                                                                                                                       - +-seresy Pein Law w) r 3 suo         - - -
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                                                                                                             .            i.            i.

I i i i 1i 1 i i i i i 1 Propeeed open 6n sach week

                                                                                                                                                                                                                                                                                                                             )

(RFS)PM Workoff Projection ) i Maintenance Rule PM's ano . too . . . . . . _. ',% . . . .

                                                                                                                                                                                                                                                --- Maril Rds Total Past Due & Late g%g
            . too .      - + - . - . .                                                                                                                       '*,, .                                                                             -e-heart Rue icool Past Due & Late too                                     ..                  - . . - . - . . . .

• heert Rue Past Late (Protected)

                                                                                                                                                                                     . ' 's e                                                                                                                                                                                                                                              Goal 0 Leio s

g 930 - . . - .-  %

                                                                                                                                                                                                                                                - o- Mont Rde Pastlate (ActJel) 3    too .
                                                                                                                                                                                  .                       . ' ,. s . '. . . + . , .                                                    -         . . . . - . _ . . . -

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                   !             !               !!!!                                                         !!l                                         1             !

Projected Open in Each Week

                                                                                                                                                                                    !               I         i            i                i i i                                    i         i              i (RF6) PM Workoff Projection ma-                                                                                                                                           Non-Safety PM's eno .

ano - - . . - . . . . _

                                                                                                               . . . . . , ' E.I ~.' g g..  .

_ - -- Nm5afety folg Pesl Due & Late

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                                                                                                                                                                                                                                                                -*-Nor> Safety Tolal Past Due & Late fI  ges     . ~ - . . . .                                                             . . .
                                                                                                                                                                                              =,
                                                                                                                                                                                                  . N--
                                                                                                                                                                                                                                                                      ' Nebately Past Lale (Protected)

Goal 0 Late

                                                                                                                                                                                                        's g                                                       +- Non.Wety Past Late (ActJel) gee                   w.       .
                                                                                                                                                                                                                       'm too     . - .                                                                                                                                                                                                               ..*

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                                                                                                                                                                                                                                                                                                               .           l Protected Open en Each neet

MODE 4 LATE SURVEILLANCES ~ MODE 4 OVERDUE SURVEILLANCES 16 60 BETTER 14 55 - 50 h )f 12 ~; 45 - 10 4 40 - !E b

          .1 cr35 -

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                                     "                    '   '                                                                                                                                      4 Q                                                                        -- -

Mar Apr May Jun Jul Aug Esp Od Nov Dec Jan Feb Mar Apt May J Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1998 1999 1998 m e Operations C::::lll:E:!ll Operations M C&l Maint C&l Maint - Elect Maint

                    -          , Elect Maint e NSED                          n=:n= FP                                Chem
                                                                               - - Goal                              -

Goal 4 l l PREVENTIVE MAINTENANCE LATE PREVENTIVE MAINTENANCE 500 (PAST 1.25 DATE) "'"- OVERDUE 450- 1400 400-1200 - w 350-3 ' 2 o-

        = 300                                                                                                   a Y

g250- . ba g 200- ', $ gnoo. 150- '

                                                                                                  ,                 ,gg ,   ,

100 - N ', '

                                                                                          \                         200 -

g . , 50 - s , s-s ,, . .. .q^ O I - \' '- ~ } - Jan Feb Mar Apr May Jun Jul Aug Sep Oct teos Dec Jan Feb Met gg 1998 i 1999a I m Safety-Related r""""'""I Non-Safe ** ***

• Maint Rule Goal (NS )'Related - - Goal (SR)

          - - - Goal (MR)                                                                                         ' . _ .' Maint       Rulo Goal (NSR)                - e - Goal (MR)

I l l Restart Decision Process l Startup and Power Ascension

            - Chief NuclearOfficerRecommendation
            - Chief Executive Officer Decision
            - Mode Restraints Cleared
            - NRC Authorization to Proceed Chief Nuclear Officer Recommendation               I
            - Nuclear Review and Audit Group Recommendation    l
            - Senior Advisory Team Recommendation              l
            - Management ReviewTeam (MRT) Recommendation
            - Power Plant Manager's Recommendation MRT Integrated Evaluation
            - Three Broad Areas of Evaluation Oversight and Commitment Organization and Support Operations and Maintenance
            - Variety ofinputs Used
            - Restart Readiness Review Program ILLIN91S P(uWER

       =*
     ,                                                                           Enclosure 26 L l.

1 I IP/NRC Management Meeting Clinton Power Station

   ,                                   0350 Restart Panel Meeting January 14,1999 I

i l m IP Representatives: J. P. McElwain ChiefNudearOfficer G. A. Hunger, .Jr. Manag.er-Clinton P6mrStation

                . W. D. Romberg          .

Manager-NuclearStation Engineering R. l'. Phares $anager-Nuclear Safety and Performance improvement D. W. Waddell Manager-Recovery

                                 ~

G. L. Baker Manager-QualityAssuranco W. F. Maguire Director-Operations ILLIN91S l P&WER

                                                                                                )

_ _ i

    ,                                      Agenda                        j t

Introduction J. P. McElwain I Plant Status G. A. Hunger I i - Operational Readiness W. F. Maguire Engineering Readiness W. D. Romberg 1 Corrective Action R. F. Phares Recirculation Pump Seal J. P. McElwain i QA Oversight G. L. Baker Case Specific Checklist D. W. Waddell Restart 1.ssue S.tatus - - Conclusion J. P. McElwain ILLIN9IS P@WER

4 Plant Status Response to Notification of Unusual Event Event and Cause Plant Response

                    - Operator Response Safety Division Status
                   - Division 1
                   - Division 2 Operable for Mode 4
                   - Division 3 Available
                   - ERAT Out-of-Service for Final Tie-in Recent Major Accomplishments
                 - Division 2 Outage SX Flow Balancing Feedwater Leakage Control System Tie-in Implemented Severe Accident Management Guidelines Major Modifications Ongoing
                - Degraded Voltage SVCs (RAT Complete)
                -- Feedwater Leakage Control System Division 1
                - Thermo-Lag Resolution ILLEN91S PC/WER

ILLINOIS POWER OSHA-RECORDABLE & LWD RATES 3- ~ ~ ~ 2.57

  ,          2.5 -

2 1 84 1994 1995 { 1996 1997 1998 m OSHA Rate O LWD Rate i 35-lLL1NOIS POWER OSHA-RECORDABLE INCIDENT RATE 3.0 - W I 5 2.5-2.0 - b 1.5 - n W - - . 1.13 n I l i I I I I I i i i i Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec M Monthly 0

                                                                                                                                -+-- Year-to-date 6.0   .

CONTRACTOR OSHA RECORDABLE & LWD RATES W- 50' o,33 4.37 n g , g i g 1994 1995 1996 1997 1998

                                                       , uOSHA Rhte                           .

OLVyDRate

                    ,                            CONTRACTOR OSHA-RECORDABLE RATE g 5.0 --

4.0 3.0 w 2.0 . .. . ....... . >24 0 t i I I I I I I I I I ( Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1998 RhlMlWE MONTHLY + YEAR.TO-DA TE - -

                                                                                                                                                       - GOAL

i r. 200 - Clinton Power Station 1998 Exposure

                   ,y.                 ...                                                .           -.            .                                      -
 ;f               160~            1998 Exposure Goal: 185.000 Rem                                                       rget Goal ( revised goal due
    ;                            Projected Goal: 185.000 Rem                                                        to adjustment in schedule) 140 -          Target Goal: 145.000 Rem Actual Exposure 145.415 Rem
                ' 100 -

80 - 60 - I 40 - Actual Exposure 20 - 0 I sasassamasasssssssssssssssssssssssssssssssssssssssssa I hbhbbhh bhk$$$$$$$$$ hhbbbb b $$$$$$$$$hhhhhhhhhhhh RADIATION WORKER PERFORMANCE EVENTSI10,000 RWP HRS. 10 - 8-I g 6:  : j z l 4-l I 2 0 Mar Apr May Jun Jul Aug Sep Oct Nov Dec PERSONNEL CONTAMINATIONS 85~ * . 81 75 -- Y 65-- 55 -- 43 5 45 -- / 9 y p 35 -- , 25 -- 20 19 ~ 15 -- 0- 9 4 5 4 4 4 2 i 3 . 5- a o 3 n ' ' n ' ' ' _.m E E . _3 ' Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1997 1998 lisuuss Monthly Year-to-Date -- Goal

         . 4 4

P-i HUMAN ERROR RATE (Errors /10,000 Man-Hours) S. 0.4 1 4 I\

                                . .I . \. . . . .

g. - 0.3

,; I \ e so 3 , , . .. . /. e . . . \ . . . 6 . .. . . . 6 . . 6. . . . . . . . O

                                                                                             .......6.........6.........e..   ... 6.    .
                                                                                                                                          ..6.........n     2 w
                                                                                                                                                       >     b w

La.3

                                                                                                                                                       -0.2" s                                                                                                                                              C
             ,,9 2 ;      . . .                                                                                                                              8
                                                                                                                                                            -c
                         /                                           / N                                                                                    "
                                                  \

x .x. . _ . .x Z . _ _ _xx u x.__.x___x___x.__x.__.x0., 3 C... . .. .*....

                                                                                                 . .N .s. . . .               ..     .. .       .

C ~ l \ d' 0 V \ /

                                                                                                                                                                 \

_# FO.0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 4 - Goal- Total Error Rate  : Total Error Rate -X - Goal Significant Error Rate --4B -Signirmant Error Rate S 94

• G l-

1 Plant Status (cont'd? Scheduled Restart Date '

                   - Appropriate STs and PMs Scheduled for Mid-Cycle Outage
                   - Re-analysis of Number of Circuit Modifications Required with Technical Specification Change Approval
                   - Corrective Maintenance Coded for This Outage will be Performed a

b L e llAINSIS P9WER

Operational Readiness Operations Training Actions

               - Continue Remediation Plan (Cycle 99-1)
               - Completed First Crew Examinations- All 3 Exam     !

Results were Satisfactory

               - Preparing Startup Training including Just-in-Time Training Operator Performance Improvements
              - Continued Improvement in Event Free Performance (Event Free December)
              - Improved Technical Specification Performance
              - Improved SafetyTagging Performance
              - Good Response to Loss of Offsite Power Areas for improvement and Continued Focus
             - Log Keeping
             - Configuration Management
             - Operational Focus                      -

Restart Readiness

             - Resolution of Startup Actions
             - System Walkdowns
            - Mode 2 Operability Testing
            - Startup Training
            - Management Monitoring PGWER

r ., j l a. l I l OPERATIONS EVENT FREE PERFORMANCE DAYS BETWEEN EVENTS ON A 90 DAY ROLLING AVERAGE 45 40- .1.

• 35 i b ' 30 -

gi

                                                                                                                                     =:

5 ' w g 25

  !               a m 20                                                                                                           I 8
 .                u'    15

^ ' i

                  $              A I                                                                n          s                                      l
                  < 10 - v v                                                                               l
 ~

5 , 1 0 ' ' ' '  ;' ' ' ' Sep Oct Nov Dec Jan Events

                                - - - Goal 90 Day Average 04 Sep Drain hoses incorrectly restored on temp M of tagout 98-0881 '
      ,        12.Sep Inadequate Review of Tagout Temp M results in approxtrnately 300 gallons of water being sprayed on VG "A" Mer train.
              .18-Sep Tagout 964302 did not have boundary valve tag on handwheel 1833F067A to prevent now rotation of recirc pump and motor.
      .       22-Sep Due to the incorrect performance of 9082.01, the ERAT was considered operable when it should have been considered INOP.

03-Oct During performance of temp M of tagout 964953,1821-F067A automatically closed due to group 1 isolation signal. 07-Oct Misinterpretation of 1-9649-201-OE led to not complying with 1-9644 047-0D requirements to maintain B RHR operable. 18-Oct 4160V Bus 1 A1 de-energtzed momentarily due to its P.T. fuse cubicle door was opened inadvertently, Div 1 DG auto started. 25 Nov Added VX woric with indequate tagout barrier

r-4 f

            ~                      *      ~                     ~

PLANT CONFIGURATION CONTROL INDICATOR 1-0: - Jaf A Sep Oct Nov Dec Jan Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan

          *1 *                              :

l PLANT CONFIGURATION CONTROL DATA l Con 6gurabon Control Trerv$ng indcator Feb-98 Mar 98 Apr98 May 98 Jun-98 Jul-98 Aug-98 Sep 98 Oct 98 Nov.98 T-w-y Mod Acahons 22 22 27 Dec418 26 25 23 23 25 26 23 23 Man Control Room del -. 181 203 140 141 148 171 149 137 123 93 88 Operatulity C_^_.. a 20 21 23 21 31 30 33 38 40 30 17 War Mtwherourds 23 27 28 27 28 27 Fas h ' 24 24 23 11 5 v_. es 111 118 107 119 139 139 182 187 228 272 233 Long Term TP= 0 0 0 0 0 0 0 0 131 134 125 Out of Sarwca Annunciators 0 0 0 0 0 0 0 0 104 127 110 Con 69 uraten Control Trondm0 Fet>98 Mar-98 Apr 98 May-98 Jun-98 .M-98 Aug W Sep-98 Te-, ,-y Mod:Acatens Oct.98 Nov-98 Dec-98 1 0 1 1 1 1 0 -1 1 Mam Control Room %= u:ses 1 O 1 1 1 1 1 1 1 1 Cg. 1 1 1

                 ; C;_.._ amns                  1       -1           1       1          1          1       1           1       -1         1        1 F. - -- k^a _ _-was                       1         1 Fire Protecten 1 _.. ;.

1 1 1 1 1 0 1 1 1 0 1 1 1 1 0 1 .t 1 1 1 Long Term Tagouts 0 0 0 0 0 0 0 0 0 -1 1 Out of Servce Annunciators 0 0 0 0 0 0 0 0 0 1 1 ConAgurahon Hamith 0 -4 1 1 1 -2 2 2 8 conAgursion :. wor O 1 1 1 2 1 1 1 1 .i 1 1 1 . l l

I _ Engineerina Readiness SSEI

                   - Circuit Breakers
                   - Degraded Voltage and Electrical Distribution
                  - Control of Calculations
                  - Control of Setpoints Fire Protection
                  - Safe Shutdown Procedures
                 - Thermo-Lag
                 - SprinklerSystems Degraded Voltage Project
                - SVCs                            ,

Regulating Transformers ' l

                - Revised Undervoltage Setpoint Technical Specification Change Required ILLINSIS P9WER

1.033 - m----------------------------l-----------------.

i 1. 0 2 - i  :

1.OO - ._.With

                                                                        ._...__ ..S V C-.               ...._.-.. _.! _ _ -..

M

                                                          /, e, -

0.98 - i

                                                     /
                                                       /            N 0.96' --                  i/                  io9                                                 i 6                                                        !

O.9 4 -- i  ; O.92

                                          -                  Existing DGR Relay                                   i-0.94               0.96    0.98      1.00           1.02            1.04             1.06 345 KV

.4 . i 1.033- ------------------------------- - - - - - -.1 ----:------ --- i S i 1.02 -  !

                                                                  $0                                            !

i 1.00 - i. With SVC SD -

                                                                                                         /i
          >'                  ,/                         /                                                     !

M' y'  : / -

          + 0.p 8. --                                                                                          :

l., Proposed DGR Relay, .  ! 0.96 --  : i 0.9 4 -- i  : 0.92 _ i i 0.94 0.66 0.98- 1.00 1.02 1.04 1.06 345 KV

Corrective Action Condition Report Progress l 1 l Root Cause Quality / Apparent Cause Quality -- SelfAssessment Industry Operating Experience Trending 4 ILLINSIS P&WER

f .. - {i. 'I _ LEVEL 1 AND 2 ACTIONS DUE IN THE NEXT 12 MONTHS I 160 - 146 140 - 120 - 113 100 60 - 62 so - 40 -

,                                                   22      22 20 -

2 5 4 4 4 0 - E E m e m 6 j s a a a a a a a a a a m a k k g y 8 i k $ A

                                                                                       $       k      e       i        s     . y a

E 60 - Corrective Action Restart Restraint Scheduling n n

,       70 -

66 1

             ~

Past Due 50 - # 47 40  ! 37 3S

• 36 3,

33 32 g, 3 3 - 24 25 23 20 21 . II 15 15 16 g to 10 - b .1. ' . ' ) r .r . ..j.

                                                                                                                 '           3 o O                       .1. '        1. ' . ' .1. ' . '  ' . ' . ' . ' . ' . ' . ' . '.1.2 .' ..

j.;ll1111soIs'!.!,!I1_l,l'1s!'g'11!a'11[a't5 i s= tI g

                                                                                       !                    ss                   ,

2g IJ 3 Nurnber of Corrective Actions E E Corrective Actions Due WClosed Correctue Actions

ROOT CAUSE ANALYSIS QUAU1Y ROOT CAUSE REVIEW INDEX (RCAQl) Historical Data 30 <

                                                                                                                                             -100%

f

                                                                                                                                            - 90%

24 - * < -* x -x- R -<- x -x -x- < -x- K -- 80% 10.75 10 45 - 70%

                          '~         ~                       "

8I9" ~ ~ " g"75 18 - - 60%

                                                                                    ~

e. 7.5 13 - 50%

14

                     .                                                          12 -

0'~ - 40% 10 -

                                                                                                                                            -M%

4<- 6< -M% i 2 10% l 0 . , , , . , , . , ,. , 0% a a a 12 a s x bN h5$b $v bhb I 4 I A 8 I mMet Expectations MReviewed i* m Score - - - Goal a Success Rate - H - Goal APPARENT CAUSE QUALITY INDEX 100

                                                                                                                                         - 100 %

90 ,0 0.9 o.g - Ma M i 80 < x--x--x--x--x--x--x--x--x--x -x--x -80% 70

                                                                                                                                         - 70%
                                                                                                           .7 60 -                                                              0.6                                                             3
                                                                                                                                         - 60% p 50
                                                                                                                                         - 50%

g 42 40 m 40 < 3 40%m{

                                                                                                      ,                   30 30 26                - 30%

21 20 - 2 15 1 - 20% 10 < 3 5 10 % 0 ,

                                                                                                                              ,            0%

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

                   -           = Accepted            m Reviewed                       t. Acceptance Rate                 - K - Goat

[ , 1 en ~

                                                                                 ,;a* 3 ,       m.

REPEAT SIGNIFICANT EVENTS f 10

                                                                                                             * ?O e te : to : 10 9 .

8 8 7- 7 6 -5 :S OS .6 8 5- ^5 05 .5-T is 4 3 3- 'l 2 2- -2 02 2 02 .2 g 1 1 1 l 1 1 .l 1 1 o o o o o ow p EmmsEvents -+-18 Month Total This indicator shows the number of repeat events.for a rolling eighteen month period. A Signifidant Repeat Event is an event that is identified'on a level 1 or 2 CR that is reasonably similar in nat,ure. to an event that occurred during the past 18 months identified on a level 1 or level 2 CR with one or more of the same root causes. l

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   ~

.l. QA Oversight Programs / Processes

             - Fire Protection, Maintenance Rule, Corrective Action
             - Procedure Compliance / Adequacy     ,
             - Control of Contractors Planned Assessments Prior to Startup
            - Follow-up Assessments Maintenance Rule Trending Welding Troubleshooting
            - Continue 0350 Package Review
            - DFl Response
           - Operational Readiness
           - MCR Deficiencies / Tags
           - FIN Team Process                                       j
           - ERO Lessons Learned                                    '

l ILLINSIS P9WER

1 i Case Specific Checklist Restart issue Status i Submitted Closure Packages II.4 Establish and Implement an Effective Risk Assessment

                                 - Complete On-line Risk Assessment Training IV.1      Establish Program to Reduce and Maintain Main Control Room Deficiencies Improve Effectiveness of implementation IV.3      Resolve issues Associated with Circuit Breaker Failures Install Remaining Circuit Breakers (see SSEl letter)

Complete Testing of Sample of Molded Case Circuit Breakers IV.5 Resolve Fire Protection Safe Shutdown Concems i Safe Shutdown Procedures

                                                                                           ]

Evaluation of installed Thermo-Lag Configurations Evaluation of Adequacy of Sprinkler System IV.6 Complete RCA of RR Seal Failures and Develop Field Performance Measures Lesson Plans Ready RR Pump for Operating Cycle IV.7 Resolve EDG Concerns

                            - Approval of License Amendment for Droop ILLINSIS P9WER 1

l Case Specific Checklist Restart issue Status i ' cont'dD Submitted Closure Packages (cont'd) V.3 Establish Maintenance Rule Program Vll.1 Develop and implement EP Improvement initiatives Successful Integrated Drill Closure Packages Not Yet Submitted

11. 5 Provide Reasonable Assurance that Deficiencies Found l During Requalification Exams Have Been Identified and a Corrected

                          - Successful Completion of Requalification Exams Ill.1   Establish and implement Actions to Achieve and Sustain Improvement in the Corrective Action Program Implement Additional improvements in Trending (see 40500 Letter)                .

Sustain Achievement of Establishsd Goals IV.2 Provide Reasonable Assurance that Deficiencies Affecting Safety Related SSCs Have Been identified and Corrected ILLINSIS P9WER

l . .

   !                            Case Specific Checklist Restart issue Status (cont'd) i               Closure Packages Not Yet Submitted (cont'd)

IV.4 Resolve Degraded Voltage and Electrical Distribution Concerns Complete Testing of RAT and ERAT SVCs (see SSEI Letter)

                            - Complete Degraded Voltage Calculations VI.1    Provide Reasonable Assurance that Safety Related SSCs Will Perform Their Intended Safety Functions as Described in the Design and Licensing Basis 4

Complete SDFV Follow-up Activities (see SSEl Letter) VI.2 Validate the Adequacy and Control of Calculations

                          - Complete Assessments of Calculation Technical Adequacy (see SSEI Letter)

VI.3 Validate the Adequacy and Control of the Setpoint Program .

                          - Approve and issue Setpoint Control Procedure (see SSEI Letter)
                          - Perform Reviews of Designated Setpoint Calculations ILLINSIS P9WER t

t Case Specific Checklist Restart issue Status fcont'dh Closure Packages Not Yet Submitted With_ Minor Restraints 1.1 Establish and implement Management Expectations

11. 1 Establish and implement Continuing Operator Training Emphasizing TS Adherence / Knowledge and Recognition of Degraded Conditions II.3 Review and Revise Abnormal Operations Sections of Operating Procedures V.1 Develop Process to Review Deferrals of Preventive Maintenance items V.2 Provide Reasonable Assurance that Qualified Materials and Parts are installed in Plant Systems ILLINGIS P4WWER

tnC105UYUd/ f t' I 8 1 4 IP/NRC Management Meeting Clinton Power Station 0350 Restart Panel Meeting February 5,1999 6

     .                                                                                       1 d

i l IP Representatives: J. P. McElwain Chief Nuclear Officer

    ]

G. A. Hunger, Jr. Manager-Clinton Power Station W. D. Romberg Manager-Degraded Voltage J. A. Goldman Manager-Work Management V. J. Cwietniewicz Manager-Maintenance W. B. Carsky Director-Design Engineering W. V. Magulre Director-Operations Director-Licensing

 }             J. V. Sipek een 0

P9WER 1 J

r /.- i .i

      !                  0350 Case Specific Checklist                             !

Item Status l Case Specific item 1, I j l.1 Management Expectations G. A. Hunger i 0350 Package to be Submitted February 8 Remaining Actions: l Actions Complete

    )     111.1 Corrective Action Program l          0350 Package Submitted Remaining Actions:
     )                 Actions Complete                                           j j    Vll.1  Emergency Preparedness 1
     ,          0350 Package Submitted                                            1
     ,          Remaining Actions:

i Conduct Training / Facility Drills - March 8

                    -   Compiete Appropriate Corrective Actions from 1998 Graded Exercise - February 15 Complete First Quarter 1999 ERO Integrated
   ;                    Drill - March 10 J

ILLIN4fS POWER

-) T I 0350 Case Specific Checklist Item Status (cont'd) Case Specific item II.1 Operator Training / Technical Specification W. F. Maguire Adherence

   !             0350' Package to be Submitted by February 25                     k Remaining Actions:

1

                   . Complete Assessment of Operators'                          )

l Ability to Recognize Degraded and i Non-Conforming Conditions - February 12 I. i Abnormal Operations Coctions of l1.3 Operations Procedures 0350 Package to be Submitted by March 1

 '               Remaining Actions:                            '

Revise Loss of 5DC Procedure - i February 12

                    -   Comments on Abnormal Operating Procedures J                        Need to be Incorporated Prior to Restart -

t February 25 i - Present Training Ops Crews on Changes to Abnormal Operating Procedures - March 19 1 J ILLINetS ' l P9WER 1 i a

1 0350 Case Specific Checklist Item Status (cont'dl Case Specific Item

11. 5 Operator Requalification W. F. Maguire 0350 Package to be Submitted by February 24 Remaining Actions:

Completion of Simulator Requalification Exams for Operating Crews - February 5 IV.1 Main Control Room Deficiencies 0350 Package Submitted Remaining Actions:

                 -   Complete Assessment - February 17 IV.6   Recirculation Pump Seal Failures Performance Measures 0350 Package Submitted Remaining Actions:

Complete Training - March 19 i I J , ILLINSIS l P9WER  ! I

0350 Case Specific Checklist 1, Item Status (cont'd) 1 l Case Specific Item 4 IV.2 Deficiencies Affecting SSCs Have Been W. B. Carsky Identified and Corrected i

 ,          0350 Package to be Submitted by February 8
 ,          Remaining Actions:
                -   Confirm Outstanding Backlogs Do Not Affect i                  Operability of Safety-Related SSCs - per the restart schedule
 ;              -   Resolve Material Condition Deficiencies (Examples)
                       - GL 89-13 Service Water issues - March 16 f                     - Reactor Recirculati6n Pump B -

February 28

~
                       - Motor Greasing Inspections - February 16
                 -  Complete Final System Readiness Af6rmations -

per the restart schedule

                 -  Complete Electrical Soldering Connections j                   inspections - February 13 3

J .J ILLINSIS P9WER

I I 1 0350 Case Specific Checklist

}                              ltem Status (cont'd) 1 Case Specific item
 . VI.1   SSCs Will Perform Their Intended Safety              W. B. Carsky
 .           Functions i                                                                             1
 ,          0350 Package Submitted                                            l I          Remaining Actions:

Complete Corrective Actions for Identified

 /                  Deficiencies - March 22                                   j 1

4 IV.5 Fire Protection 0350 Package Submitted Remaining Actions: Safe Shutdown Capability

                        - Issue Operating Procedure Revisions -
 ,                          Febmay 19
                        - Train Operators - February 15 through j                           March 15
                        - Resolve Spurious Actuations - March 20 IN 92-18 MOV Circuit Modifications
                        - 54 MOV Modification Installations -

Complete

                        - Last Modification RFO - February 10 Thermo Lag
                        - Thermo Lag Modifications -
                           ' Last RFO - March 17 9
,   ILLIIISIS POWER 1

1

i 0350 Case Specific Checklist Item Status (cont'd? Case Specific item l IV.7 EDG Concems W. B. Carsky 0350 Package Submitted

       ;           Remaining Actions:

Revise DG Loading Calculation / l Update USAR - February 22 VI.2 Calculations I l 0350 Package Submitted

       }           Remaining Actions:
                       -   Complete Training and Issue Rev.10 to NSED Procedure E.1 - March 10
     ]

b l l J d a q P9WER e

0350 Case Specific Checklist Item Status (cont'di Case Specific item VI.3 Setpoint Program W. B. Carsky I 0350 Package to be Submitted by February 8 l Remaining Actions: { ' Complete Remaining TS Parameter Channel Uncertainty Calculations and Resolve Open items - March 8 Complete Verification of Remaining AE Setpoint Packages and Resolve Open items - March 12 Resolve Open items from GE Calculation Verification - March 19 Complete Operability Evaluation for Setpoint Documentation Deficiencies - March 21 1 I . ed f 9 ILLINSIS P9WER , ~ l

0350 Case Specific Checklist Item Status (cont'd) 1 Case Specific item

        ,      IV.4   Degraded Voltage                                        W. D. Romberg
       ,              0350 Package To Be, Submitted March 1 Complete integrated RAT SVC Testing -

l February 12 Complete Plant Load Flow Calculations - February 22 Complete 120V CKT Calculations - l February 26 Complete Integrated ERAT SVC Tests - j March 7 Complete 120V CKT Mods - per the restart schedule 3 IV.3 Circuit Breakers V. J. Cwletn/ewicz 3 0350 Package Submitted a Remaining Actions:

                            . Complete Field Activities - March 15 t

1

J ILLINSIS P9WER e

m -

       -                                                                          1 1

0350 Case Specific Checklist Item Status (cont'dh Case Specific Item l i 11.4 On-Line Risk Assessment (Submitted) J. A. Goldman i I 0350 Package Submitted 1 Remaining Actions: Complete On-Line Risk Assessment 1 Training - February 28 V.1 Defeirals of Preventive Maintenance items 1 1 0350 Package Submitted Remaining Actions:

  -                    -   Resolve Equipment Availability /                       I
    .                      PM Deferralissue i

V.2 Qualified Materials 0350 Package to be Submitted by February 12 Remaining Actions: " - Complete Safety-Related Fuse inspections and issue Final Report - March 24 ~ .J ." ' ILLINSIS P9WER em

0350 Case Specific Checklist

  ~~

ltem Status icont'db Case Specific item 1 Vill.1 Licensing Actions J. V. S/pek i I Remaining Actions:

                       -   Complete Calculations Associated with item IV.4
    *M i

2 l

  .a w

om i d l ILLINSIS P9WER

Enclosure 28 IP/NRC Management Meeting Clinton Power Station 0350 Rostart Panel Meeting March 18,1999 I

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_lP Reprosontatives: i J. P. McElwain Chief Nuclear O/#cer ) G. A. Hunger, Jr. . Manager-Clinton Power Station W. D. Romberg Manager-Degraded Voltage ' J. A. Goldman Manager-Work Management V. J. Cwietnicwiat Manager-Maintenance D. B. Wario Manager-Engineering W. F. Maguire Director-Operations ELLINetS ' P(&WER

r I Agenda

• Operations Performance W. F. Maguire Work Management Impacts J. A. Goldman l

Discussion of SSEl Results NRC f Case Specific Checklist items Various r i Demand for Information J. P. McElwain I ILLINSIS PGWER

t I l Operations Performance Assessment of Current W. F. Maguire , Performance I OperatorTraining/ Technical ( Specification Adherence (Item 11.1) System Readiness Work Management interface i i i i ILLIN915

POWER

Work Management Impacts i Issue J. A. Goldman l , l l Background / Approach to l

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Analyzing the issue I Causes Corrective Actions i

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ILLIN 91S PGWER

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  -                                                                            1 0350 Case Specific Checklist                            l l                                     Item Status Case Soecific itern

,I l.1 Management Expectations G. A. Hunger 111. 1 Corrective Action .' Ongoing Actions: Near-Term Actions Long-Term Actions II.3 Abnormal Operations Sections of W. F. Maguire Operations Procedures Ongoing Actions: Revise Loss of SDC Procedure Present Training to Operations Crews ! on Changes to Abnormal Operating Procedures I

,      IV.1     Main Control Room Deficiencies I                Ongoing Actions:                                               .

Assessment Completed ILLINSIS PGWER

0350 Case Specific Checklist

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l Item Status fcont'd) i

Case Specific item IV.3 Circuit Breakers V. J. Cwietniewicz Ongoing Actions:

Westinghouse 4160V Breakers Molded Case Circuit Breakers IV.4 Degraded Voltage W. D. Romberg i Ongoing Actions: p. Complete RAT SVC Testing i - Complete Integrated ERAT SVC Tests Complete 120V Circuit Mods i - DG Calculations V1 Deferrals of Preventive Maintenance items J. A. Goldman i Ongoing Actions: Equipment Availability /PM Deferral ,l Root Cause and Corrective Actions ILLINels POWER

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0350 Case Specific Checklist item Status (cont'd) Case Specific item VI.3 Setpoint Program D. B. Warfel i

Ongoing Actions:

Complete Analysis / Resolve Open items ! - Complete Operability Evaluation for Setpoint Documentation Deficiencies

 ;           The following packages have been submitted. Adequate perfomiance has i           been demonstrated in these areas to merit the NRC's closure of these case specific items.
   -         Case Specific item

11. 2 , Equipment Clearance Program

11. 4 , On-Line Risk Assessment.

II.5, Operator Requalification 111.2, Performance Indicators IV.2, Deficiencies Affecting SSCs Have Been identified and Corrected I IV.5, Fire Protection IV.6, Recirculation Pump Seat Failures Performance Measures IV.7, EDG Concems V.2, Qualified Materials V3 Maintenance Rule Program VI.1, SSCs Will Perform Their Intended Safety Function VI.2, Calculations i Vll.1, Emergency Preparedness ILLINSIS PGWER l

i I i Demand for Information i 1 Basis for Confidence that the J. P. McElwain Corrective Action Program is i Effective i I I i l 1 1 1 I i ILLINels i PGWER

Enclosure 29 O l IPINRC Management Meeting Clinton Power Station 0350 Restart Panel Meeting March 26,1999 IP Representatives: J. P. McElwain Chief Nuclear Of#cer G. A. Hunger, Jc. Manager-Clinton Power Station D. B. Wariel Manager-Nuclear Station Engineering W. D. Romberg Manager-Degraded Voltage W. F. Maguire Director-Operations ILLINSIS P4pWER

I Aaenda Operations Activities w. F. Maguire I October 18,1998 Loss of SDC G. A. Hunger 1 40500 Results NRC l l 0350 Case-Specific Checklist Various i Item Status Concluding Remarks J. P. McElwain ILLIN915 P4pWER

e _ W. F. Maguire Operations Activities Assessment of Current Performance Challenges and Focus Areas

        - Main Control Room Conduct
        - SupervisoryOversight/ Leadership
        - Equipment Status and Awareness
        - WorkManagement
        - Self Assessment / Corrective Action ILLIN915 P4tWER I

G. A. Hunger October 18,1998 Loss of SDC Summary of the issue Lessons Learned Corrective Actions ILLIN91S P&WER

6 0350 Case Specific Checklist -- - - Item Status (cont'd) Case Specific item - IV.4 Degraded Voltage W. D. Romberg Ongoing Actions: Complete Integrated RAT SVC Testing Complete integrated ERAT SVC Tests Complete 120V Circuit Mods Complete / Submit DG Calculations VI.3 Setpoint Program D. B. Waifel Ongoing Actions: - Complete Analysisimotve Open items Complete Operabilig Evaluation for Setpoint Documentation Deficiencies l l t ILBJNSIS PtWWER ' j

fl e . . . . tnclosure 30 o 1 l l l l i IP/NRC Management Meeting I I Clinton Power Station 0350 Rostart Panel Meeting i April 16,1999 i l l l IP Representatives: J. P. McElwain Chief Nuclear Of5cer G. A Hunger. Jr. Manager-Clinton Power Station P. D. Hinnenkamp Assistant Manager-Clinton Power Station D. B. Warfel Manager-NucIcar Station Engineering l L

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Agenda

      - Safe, Event-Free Startup and   P. D. Hinnenkamp Power Ascension 1

Continuous Improvement Actions i

Safe, Event-Free Startup and Power Asc_ension _ a Specific Training for Critical Activities 1 Plant and Bosrd Awareness

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I Use of Industry Operating Experience I Assessments of Plant and Personnel Performance Senior Management Expectations l l l l

Continuous improvement Actions Operations Staffing Plan Plant / Process improvements Plant Material Condition Operations Training

      'Self Assessments l

l Benchmarking External Assessments Shift Management Development l l

Enclosure 31 l lP/NRC Management Meeting Clinton Power Station July 14,1999

      . NRC Introduction                     M.L.Dapas

• CPS Introduction J. P. McElwain 1

      . NRC Restart inspection Results       T. J. Kozak
      . Trans,Jon to CPS Business Plan       P. D. Hinnenkamp Disposition of PFE Actions                        l 1

Operational Objectives

             . Safety                                         1
             . Plant Material Condition
             . Continuous improvement
             . Financial
       . Concluding Remarks                  J. E. Dyer /

J. P. McElwain R.LINSIS P4pWER i

ENCLOSURE 32 l l PLANT PERFORMANCE REVIEW BACKGROUND CLINTON POWER STATION I resented at the April 16,1999 Public Meeting l

   .                               tnC 105tre 44 PLANT PERFORMANCE REVIEW BACKGROUND NRC REGULATES COMMERCIAL NUCLEAR POWER PLANTS. THIS PROCESS PROVIDES A MEANS OF FEEDING BACK NRC PERSPECTIVES ON PERFORMANCE TO UTILITIES AND THE PUBLIC.

i COMMISSION DIRECTED SUSPENSION OF THE SYSTEMATIC ASSESSMENT OF LICENSEE ' '- - PERFORMANCE (SALP) WHICH WERE PERFORMED EVERY 12 TO 24 MONTHS A REVIEW OF THE NRC's PROCESSES FOR l ASSESSING PERFORMANCE AT NUCLEAR l PLANTS IS ONGOING l l

NEW INSPECTION AND ASSESSMENT PROCESS EXPECTED TO BE IN PLACE BY JANUARY 1,2000 REVIEW Pls AND FINDINGS QUARTERLY MORE DETAILED REVIEWS SEMIA.NNUALLY SENIOR MANAGEMENT REVIEWS ANNUALLY AFTER EACH REVIEW - ADJUST INSPECTION SCHEDULE TWO PILOT PLANTS SELECTED IN EACH REGION - BEGINS JUNE 1999 QUAD CITIES - CORDOVA, IL PRAIRIE ISLAND - RED WING, MN

5 PLANT PERFORMANCE REVIEWS

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INTERIM ASSESSMENT VEHICLE l PREVIOUSLY ASSESSED SHORTER PERIOD AND WAS USED FOR INSPECTION PLANNING DO NOT PROVIDE SALP GRADES NEXT PPR LETTERS EXPECTED IN ABOUT 1 YR i

CLINTON PLANT PERFORMANCE REVIEW HISTORICAL REVIEW - AUG 6,1997 to JAN 31,1999 PLANT REMAINED SHUTDOWN PROGRESS MADE RESOLVING RESTART ISSUES 1 SEVERAL REVIEWS NEEDED TO CLOSE ITEMS u____________

9 THREE AREAS OF MOST CONCERN TEAM INSPECTIONS PRIOR TO RESTART CONDUCT OF OPERATIONS RESOLUTION OF ENG/ DESIGN ISSUES CORRECTIVE ACTION PROGRAM

n , CONDUCT OF OPERATIONS l PERFORMANCE CONSISTENT WITH PREVIOUS ASSESSMENT ) l l MORE REPETITIVE ISSUES THAN RESOLVED l I e COMPENSATORY ACTIONS e TECHNICAL SPECIFICATION ADHERENCE l e POOR PERFORMANCE DURING REQUAL l l IMPROVEMENT NOTED IN CERTAIN AREAS l e SHIFT TURNOVERS IMPROVED  !

• EQUIPMENT TAGOUT PROGRAM

e CONDUCT OF MAINTENANCE l PROGRAMMATIC DEFICIENCIES NOTED EARLY EFFECTIVE ACTIONS TAKEN TO ADDRESS ISSUES SUPPORT TO OPS IN NEED OF IMPROVEMENT ENGINEERING PERFORMANCE ISSUE IDENTIFICATION IMPROVED e FIRE PROTECTION e DEGRADED VOLTAGE l e SDFV MANY CORRECTIVE ACTIONS WERE NEEDED TO ADDRESS IDENTIFIED ISSUES PRIOR TO RESTART

r-PLANT SUPPORT 4 RADIATION PROTECTION, CHEMISTRY, FIRE PROTECTION PROGRAM IMPROVEMENTS

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EMERGENCY PREPAREDNESS PROGRAM PERFORMANCE IN NEED OF IMPROVEMENT I I l I

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