ML20138K092

Informs That on 970306 NRC Staff Completed Semiannual Plant Performance Review of Point Beach Nuclear Plant.Nrc Inspections Will Be Required Upon Completion of Improvement Initiatives & Prior to Restart of Unit 2

ML20138K092
Person / Time
Site:	Point Beach
Issue date:	05/02/1997
From:	Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Grigg R WISCONSIN ELECTRIC POWER CO.
References
NUDOCS 9705120149
Download: ML20138K092 (5)

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May 2,1997 Mr. Richard R. Grigg, President and i

Chief Operating Officer j.

Wisconsin Electric Power Company 231 W. Michigan Milwaukee, WI 53201

Dear Mr. Grigg:

On March 6,1997, the NRC staff completed the semiannual Plant Performance Review' (PPR) of the Point Beach Nuclear Plant. The staff conducts these reviews for all operating nuclear power plants to develop an integrated understanding of safety perforrnance. The results are used by NRC management for planning and allocation of inspection resources.

The PPR for Point Beach involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period October 1996 through March 1997. PPRs provide NRC management with a current summary of licensee performance and serve as inputs to the NRC Systematic Assessment of Licensee Performance (SALP) and senior management meeting reviews.

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In our letter dated February 12,1997, issued after the previous PPR, we described the formation of a Point Beach oversight panel and the development of an Oversight Plan.

i These actions were taken to assure close NRC oversight of your actions to address performance issues. In addition, following the last Senior Management Meeting held 1

January 14-15,1997, a letter was sent to Mr. Abdoo on January 27,1997, informing him of the NRC's concerns with the decline in performance at Point Beach during the last assessment period. Since the previous PPR, we have observed an increase in your staff's efforts to identify and address problems at Point Beach. NRC inspections will be required j

upon completion of your improvement initiatives and prior to restart of Unit 2. The oversight panel will continue its review of your staff's preparations for the Unit 2 restart and your continued performance improvement initiatives for Units 1 and 2.

j Our specialist inspections scheduled for the next six months are shown on the attached inspection plan. Resident and Region-based project engineer inspections, are not listed on the schedule due to their ongoing and continuous nature. An in-depth assessment of Unit 2 fuel load and restart activities is also not on the attached schedule. In addition, we plan to evaluate your actions pursuant to the commitments in CAL 3-96-005 and -OO5A, and the resumption of spent fuel dry cask storage activities. We understand you have not scheduled further dry cask storage activities, but estimate that they may begin in the late summer of 1997.

i 9705120149 970502 PDR ADOCK 05000266 G

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R. R. Grigg We plan to continue to meet with Point Beach management approximately every two weeks prior to the Unit 2 restart and monthly thereafter to discuss our inspection results and progress on your performance improvement initiatives. We willinform you of any major changes to the inspection plan. If you have any questions, please contact Jim McCormick-Barger at (630) R29-9872.

Sincerely,

/s/ John A. Grobe John A. Grobe, Deputy Director Division of Reactor Projects Docket Nos. 50-266; 50-301;72-005 License Nos. DPR-24; DPR-27

Enclosure:

Inspection Plan cc w/ encl:

S. A. Patuiski, Site Vice President A. J. Cayia, Plant Manager Virgil Kanable, Chief, Boiler Section Cheryl L. Parrino, Chairman, Wisconsin Public Service Commission State Liaison Officer (See attached continued distribution)

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R. R. Grigg the Office of Nuclear Reactor Regulation will be reviewing Unit 2 fuelload and restart activities, focussing on the main control room. This is also not on the schedu!e. In addition, we plan to inspect your commitments associated with CAL 3-96-005 and -OO5A, and the resumption of spent fuel dry cask storage activities. We understand you have not schedulec d v nask storage activities, but estimate that they may begin in late summer of 1997.

We will inform you of any major changes to the inspection plan. If you have any questions, please contact Jim McCormick-Barger at (630) 829-9872.

Sincerely, John A. Grobe, Deputy Director Division of Reactor Projects Docket Nos. 50-266; 50-301;72-005 License Nos. DPR-24; DPR-27

Enclosure:

Inspection Plan cc w/enci:

S. A. Patuiski, Site Vice President A. J. Cayia, Plant Manager Virgil Kanable, Chief, Boiler Section Cheryl L. Parrino, Chairman, Wisconsin Public Service Commission State Liaison Officer (See attached continued distribution)

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Docket File w/enci DRS w/ encl PUBLIC lE-01 w/ encl Rlli PRR w/ encl Enf. Coordinator, Rlli w/enci OC/LFDCB w/enci SRI, Pt. Beach w/ encl DRP w/ encl LPM, NRR w/ encl C. D. Pederson, Rlli w/enci A. B. Beach, w/enci l

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ENCLO2URE POINT BEACH

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INSPECTION PLAN INSPECTION TITLE /

NUMBER OF PLANNED TYPE OF INSPECTION - COMMENTS f

PROGRAM AREA INSPECTORS INSPECTION DATES IP 40500 Restart-Corrective 4-5 5/19-23/97 & 6/2-6/97 U2 Restart inspection (RI)

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Actions / Engineering IP 83750 Radiation Protection /

2 5/5-9/97 Routine Radiation Protection (Cl)

Plant Support i

IP 81700 Security / Plant Support 1

6/2-6/97 Security inspection (Cl) i IP 82701 Emergency Preparedness / Plant 2-3 6/23-27/97 EP inspection (Cl)

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Support IP 62706 Maintenance Rule / Maintenance 4-5 7/7-11/97 Maintenance Rule Inspection (RI) f IP 84750 Radiation Protection /

1 7/7-11/97 Effluents, REMP, Chemistry l

Plant Support Inspection (Cl)

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IP 86750 Radiation Protection / Plant Support 1

8/25-29/97 Solid Radwaste and Shipping inspection (Cl) '

IP 64704 Fire Protection / Plant Support 1

Unannounced Fir's Protection Inspection (Cl) i IP 92703 Spent Fuel Dry Cask Storage CAL 1

2 Days, Actual Dates Followup to CAL and Bulletin 96-04 Followup are Dependent on commitments (RI)

Licensee's Compietion of Actions IPs Spent Fuel Dry Cask Storage 1-2 To 8e Determined Routine inspection of all aspects of I

60851 When Cask Loading an independent spent fuel storage 60853 Resumes installation (Cl) 60854 i'

60855 i

IP - Inspection Procedure Ti - Temporary Instruction Cl - Core inspection - Minimum NRC Program (mandatory all plants)

RI - Regional Initiative i

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