IR 05000266/1998019
| ML20198B524 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/04/1998 |
| From: | Burgess B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reddemann M WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML20198B527 | List: |
| References | |
| 50-266-98-19, 50-301-98-19, NUDOCS 9812210004 | |
| Download: ML20198B524 (3) | |
Text
December 4, 1998
SUBJECT:
L 50-301/90019(DRP)-
I
Dear Mr. Reddemann:
'On November 20,1998, the NRC completed an inspection at your Point Beach 1 and 2 reactor
facilities. The enclosed inspection report presents the results of that inspection.
During the 6-week period covered by this inspection, the conduct of activities at the Point Beach facility was characterized by safety conscious operations and consistent management focus l
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l towards program improvement initiatives. For example, training plans for preparing control
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room operators for the transition to an 18-month operating cycle were considered robust. Also,
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industry data was used in lieu of poor quality plant specific data to evaluate equipment failure
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histories performed in support of the transition to an 18-month operating cycle.
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in contrast, multiple and/or repetitive failures of nonsafety-related equipment caused planned and unplanned reactor power changes. Specifically, problems with instrument air compressors, i
the Unit 1 "A" steam generator main feed pump, and the Unit 2 auxiliary transformer challenged l
control room operators, had significant impacts on the work scheduling process, and required
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maintenance personnel to re-allocate resources to address emergent work items, in addition, your identification of continued problems with the American Society of Mechanical Engineers L
7 (ASMi-) Code,Section XI, pressure test program was of particular concern. Although L
! numerous problems with this program had been identified in the past, many of these concerns were not effectively addressed by previous corrective actions. We are aware that a new j
corrective action process has been implemented at your facility and that corrective actions to a
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remedy the problems identified in the attached report with the pressure test program were still r
, being formulated at the end of the inspection period. Evaluation of the results of this inspection indicated that additional attention is needed to address balance 'of plant problems that can q
impact the primary system and to ensure that identified problems with the ASME Section XI
. pressure test program are adequately addressed.
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. in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosure will be placed in the NRC Public Document Room.
Sincerely,
/s/ B. L. Burgess Bruce L. Burgess, Chief Reactor Projects Branch 7 Docket Nos.: 50-266;50-301 License Nos.: DPR-24, DPR-27 Enclosure:
Inspection Report
50-266/98019(DRP);
50-301/98019(DRP)
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cc w/ encl:
R. Grigg, President and Chief
Operating Officer, WEPCO
M. Sellman, Chief Nuclear Officer
R. Mende, Plant Manager
J. O'Neill, Jr., Shaw, Pittman,
Potts & Trowbridge
K. Duveneck, Town Chairman
Town of Two Creeks
B. Burks, P.E., Director
Bureau of Fie!d Operations
J. Mettner, Chairman, Wisconsin
Public Service Commission
S. Jenkins, Electric Division
Wisconsin Public Service Commission
State Liaison Officer
DOCUMENT NAME: G:\\POIN\\ pol 98019.DRP
To receive a copy of this document, indicate in the box "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure *N" = No
Copy
OFFICE
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DATE
12/4f/98
12It498
OFFICIAL RECORD COPY
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M. Reddemann.
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Distribution:
CAC (E-Mail)
RPC (E-Mail)
Project Mgr., NRR w/encls
J. Caldwell. Rlli w/encls
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C. Pederson, Rlll'w/encls
B. Clayton, Rill w/encls
SRI Point Beach w/encls
DRP w/encls
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TSS w/encls
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DRS (2) w/encls
Rlli PDR w/encls
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PUBLIC IE-01 w/encls :
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Docket File w/encls
GREENS
LEO (E-Mail)
DOCDESK (E-Mail)
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180041
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