ML20133A345
| ML20133A345 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/20/1996 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Patulski S WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML20133A348 | List: |
| References | |
| NUDOCS 9612310055 | |
| Download: ML20133A345 (5) | |
See also: IR 05000266/1996013
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December 20, 1996
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Mr. S. A. Patulski, Site Vice President
Point Beach Nuclear Plant
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6610 Nuclear Road
Two Rivers, Wisconsin 54241
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SUBJECT:
POINT BEACH NRC INSPECTION REPORT
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NO. 50-266/96013(DRP); 50-301/96013(DRP)
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Dear Mr. Patulski:
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This refers to the special inspection conducted by Mr. J. A. Gavula and others
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of this office from October 3 through November 15, 1996, at the Point Beach
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Nuclear Plant Units 1 and 2.
This inspection included reviews of interim
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operability determinations for selected pumps and portions of related design
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basis calculations. At the conclusion of the inspection, the inspection
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results were discussed with those members of your staff identified in the
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enclosed report.
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From our inspection, we determined that your interim operability
determinations provided reasonable assurance that the selected pumps would
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perform within the required design bases. However, several issues were
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identified during this inspection that are of significant concern to us.
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First, your preliminary reviews of potentially degraded equipment were poorly
defined and were not formalized. During the Enforcement Conference on
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September 12, 1996, your. staff stated that preliminary reviews of safety
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related pumps had been completed to ensure design requirements were
incorporated when establishing acceptance criteria for inservice testing.
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Only after requesting copies of the reviews did the NRC later determine that
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these preliminary reviews had never been formalized.
Extensive discussions
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with your staff revealed weaknesses in your preliminary reviews necessitating
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this inspection. A well defined basis for the operability of potentially
degraded equipment is a fundamental concept of a sound corrective action
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program to ensure there is a clear understanding of the basis for operability.
Even after the NRC staff identified the lack of fomal documentation, your
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staff still questioned the need to document operability determinations.
It
also became apparent that the design bases of the plant are not well
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documented, nor well understood, based on the number of design basis questions
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that need to be answered for the service water system. These questions were
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identified as an inspector followup item and were forwarded to NRR for review
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and resolution with your staff.
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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of
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this letter and the enclosures will be placed in the NRC Public Document Room.
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9612310055 961220
ADOCK 05000266
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S. A. Patulski
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We will gladly discuss any questions you have concerning this inspection.
Your cooperation with us is appreciated.
Sincerely,
/s/ John A. Grobe
John A. Grobe, Deputy Director
Division of Reactor Projects
Docket No. 50-?65
Docket No. 50-301
Enclosure:
Inspection Report
No. 50-266/96013(DRS);
No. 50-301/96013(DRS)
cc w/ enc 1:
R. R. Grigg, President and Chief
Operating Officer, WEPC0
A. J. Cayia, Plant Manager
Virgil Kanable, Chief, Boiler Section
Cheryl L. Parrino, Chairman,
Wisconsin Public Service Commission
State Liaison Officer
Docket File w/ enc 1
SRI Point Beach w/ enc 1
PUBLIC IE-01 w/ enc 1
OC/LFDCB w/ enc 1
A. B. Beach, w/ encl
B. L. Burgess, w/ encl
W. L. Axelson, w/ enc 1
CAA1 w/ enc 1 (E-mail)
DRP, w/ enc 1
Enf. Coordinator, RIII w/enci
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(See attached concurrence)
DOCUMENT NAME: G:\\DRS\\P0196013.DRS
To receive a copy of this document,indeste in the boa *C" = Copy estehovt setechnient/enalseine *E' = Copy eveth ettschment/encloeure
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OFFICE
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NAME
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DATE
12/ /96
12/ /96
12/x/96
}"2/14/9 6
OFFICIAL RECORD COPY
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R. Link
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We will gladly discuss any questions you have concerning this inspection. Your
cooperation with us is appreciated.
Sincerely,
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Geoff y/E. Grant, Director
Division! f Reactor Safety
Docket No. 50-266
Docket No. 50-301
Enclosure:
Inspection Report
No. 50-266/96013(DRS);
No. 50-301/96013(DRS)
cc w/ encl:
S. A. Patuiski, Site General Manager
A. J. Cayia, Plant Manager
Virgil Kanable, Chief, Boiler Section
Cheryl L. Parrino, Chairman,
Wisconsin Public Service Commission
State Liaison Officer
Distribution:
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Docket File w/ encl
DRS w/enct
A. B. Beach, Rlll w/enct
PUBLIC IE-01 w/enci
Rlli PRR w/enci
Enf. Coordinator, Rill w/enci
OC/LFDCB w/ encl
SRI, Pt. Beach w/enci
CAA1 w/enci (E-mail)
DRP w/enct
LPM, NRR w/enct
W. L. Axelson, Rill w/enci
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DOCUMENT NAME: G:\\DRS\\ pol 96013.DRS
To receive a copy of this document, Indicate in the bon 'C" = Copy without attachment / enclosure 'E' = Copy with attachment / enclosure
m = w. cop,
OFFICE
Rlli
Rlli
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Rlli
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JGavula:nh {/ MRingM[F
WKropp
McCormick-Barger
JGrobe
HClayton/GGrant
NAME L
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DATE
11//f/96 #
11/jq/96
11/ /96
11/ /96
11/ /96
OFFICIAL RECORD COPY
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION lil
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801 WARRENVILLE ROAD
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USLE. ILUNOIS 60532-4351
December 20, 1996
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Mr. S. A. Patulski, Site Vice President
Point Beach Nuclear Plant
6610 Nuclear Road
Two Rivers, Wisconsin 54241
_
SUBJECT:
P0 INT BEACH NRC INSPECTION REPORT
NO. 50-266/96013(DRP); 50-301/96013(DRP)
Dear Mr. Patulski:
This refers to the special inspection conducted by Mr. J. A. Gavula and others
of this office from October 3 through November 15, 1996, at the Point Beach
Nuclear Plant Units 1 and 2.
This inspection included reviews of interim
operability determinations for selected pumps and pcrtions of related design
basis calculations. At the conclusion of the inspection, the inspection
results were discussed with those members of your staff identified in the
enclosed report.
From our inspection, we determined that your interim operability
determinations provided reasonable assurance that the selected pumps would
perform within the required design bases. However, several issues were
identified during this inspection that are of significant concern to us.
First, your preliminary reviews of potentially degraded equipment were poorly
defined and were not formalized.
During the Enforcement Conference on
September 12, 1996, your staff stated that preliminary reviews of safety
related pumps had been completed to ensure design requirements were
incorporated when establishing acceptance criteria for inservice testing.
Only after requesting copies of the reviews did the NRC later determine that
these preliminary reviews had never been formalized.
Extensive discussions
with your staff revealed weaknesses in your preliminary reviews necessitating
this inspection. A well defined basis for the operability of potentially
degraded equipment is a fundamental concept of a sound corrective action
,
program to ensure there is a clear understanding of the basis for operability.
Even after the NRC staff identified the lack of formal documentation, your
staff still questioned the need to document operability determinations.
It
also became apparent that the design bases of the plant are not well
documented, nor well understood, based on the number of design basis questions
that need to be answered for the service water system.
These questions were
identified as an inspector followup item and were forwarded to NRR for review
and resolution with your staff.
'
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of
this letter and the enclosures will be placed in the NRC Public Document Room.
.
.
S. A. Patulski
-2-
We will gladly discuss any questions you have concerning this inspection.
Your cooperation with us is appreciated.
Sincerely,
f 0_, L;b k.~b
_/<
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d$hn A. Grobe, Deputy Director
Division of Reactor Projects
,
Docket No. 50-266
Docket No. 50-301
Enclosure:
Inspection Report
No. 50-266/96013(DRS);
No. 50-301/96013(DRS)
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cc w/ encl:
R. R. Grigg, President and Chief
Operating Officer, WEPC0
A. J. Cayia, Plant Manager
Virgil Kanable, Chief, Boiler Section
Cheryl L. Parrino, Chairman,
Wisconsin Public Service Comission
State Liaison Officer
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