ML20217A249
| ML20217A249 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/15/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Patulski S WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML20217A255 | List: |
| References | |
| 50-266-97-10, 50-301-97-10, EA-97-347, NUDOCS 9709190107 | |
| Download: ML20217A249 (4) | |
See also: IR 05000266/1997010
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September 15, 1997
EA 97 347
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Mr. S. A. Patuiski
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Site Vice President
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Point Beach Nuclear Plant
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Wisconsin Electric Power Company
6610 Nuclear Road
Two Rivers, Wisconsin 54241
SUBJECT:
POINT BEACH NRC INSPECTION REPORT 50 266/97010(DRS);
50 301/97010(DRS) AND NOTICE OF VIOLATION
Dear Mr. Patutski:
On June 13,1997, the NRC completed an inspection at your Point Beach Units 1 and 2 reactor
facilities. This special startup issues inspection was initiated following the identification of
significant problems in operations, maintenance, and engineering support at Point Beach. The
enclosed report presents the results of that inspection.
The purpose of this inspection was to examine and verify that Point Beach had thoroughly and
effectively resolved a number of commitment items identified in a December 12,1996 letter
from R. R. Grigg, President and Chief Operating Officer, Wisconsin Electric, to A. B. Beach,
red onal Administrator, and other startup issues. The inspu performed an in depth, multi-
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disciplinary review of operations, maintenance, testing and engineering issues. For the items
reviewed, the inspectors found that, in general, Point Beach met its commitments,
improvements were noted in control room activities, such as in the areas of command and
control, and communications, and in the 50.59 screening and safety evaluation processes,
Overall, the condition report reviews appeared to be conservative and changes to the condition
reporting system appeared to add appropriate guidance to ensure consistent and timely
disposition of deficiencies.
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Based on the results of this inspection, we identified two violations of NRC requirements that
are being cited in the enclosed Notice of Violation. The first violation was for the failure to
initiate a condition report when the G03 emergency diesel generator (EDG) voltage monitor
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relay was found in an out-of calibration condition. This was of concern because the condition
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was not evaluated to determine the impact it may have had on past EDG opmability. The
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second violation was for the failure to perform the steam generator girth weld with a qualified
procedure. Although the weld procedure was subsequently qualified, this is of concern
because unqualified welds could result in the subsequent degradation of related pressure
boundaries. The circumstances surrounding these violations are described in detailin the
enclosed report. Please note that you are required to respond to this letter and should follow
the instructions specified in the enclosed Notice when preparing your response. The NRC will
use your response, in part, to determine whether further enforcement action is necessary to
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ensure compliance with regulatory requirements.
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S. A. Patulski
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Septmber 15, 1997
In addition, four apparent violations were identified and are being considered for escalated
enforcement action in accordance with the " General Statement of Policy and Procedure for
NRC Enforcement Actions"(Enforcement Policy), NUREG 1600. The apparent violations
involve two Licensee Event Reports and associated condition reports that detail the Appendix R
requirements that have not been met. The first apparent violation (item number
50 266/97010-04; 50 301/97010-04) identifies two conditions that do not meet 10 CFR 50,
Appendix R Section Ill.G.2, requirements (Inspection Report (IR) Section E2.5.b.2): (a) the
lack oi 125 Vdc breaker coordination which had the potential to cause the " yellow" safe
shutdown instrument channels to be lost for a fire in the North auxiliary feedwater area; and
(b) the lack of 125 Vdc breaker coordination which had the potential to cause the loss of all
emergency diesel generators during a fire in the North auxiliary feedwater area. The second
apparent violation (item number 50 266/97010-05; 50 301/97010 05) identifies two conditions
that do not meet 10 CFR 50, Appendix R, Section Ill.L.1, requirements (IR Section E2.5.b.2):
(a) the original safe shutdown analysis did not adequately document the capability of the
G01/G02 emergency diesel generators to start and flash their fields with their output breaker
closed and 480 volt loads connected; and (b) the original safe shutdown analysis did not
adequately document the ventilation requirements for certain safe shutdown equipment. The
third apparent violation (item number 50 266/97010-06; 50-301/97010-06) involves an
inadequate safe shutdown procedure (IR Section E2.5.b.2). If performed, the procedure would
have directed operators to isolate the wrong direct current power supplies. The forth apparent
violation (item number 50 266/97010-07); 50-301/97010-07) involves inadequate safe
shutdown emergency lighting in the Circulating Water Pump House (IR Section E2.5.b.4).
Emergency lighting was not provided, as required by 10 CFR 50, Appendix R, Section Ill.J. In
several locations where operators may have to manually operate safe shutdown equipment.
We recognize that these apparent violations were identified by Wisconsin Electric staff and
appropriately reported to the NRC. The circumstances surrounding the apparent violations, the
significance of the issues, and Point Beach's corrective actions were discussed with members
of your staff at the exit meeting on June 13,1997. As a result, we do not believe that it is
necessary to conduct a predecisional enforcement conference in order to enable the NRC to
make an enforcement decision. However, a Notice of Violation is not presently being issued for
the inspection findings. Before the NRC makes its enforcement decision, we am providing you
an opportunity to either: (1) respond to the apparent violations addressed in this inspection
report within 30 days of the date of this letter; or (2) request a predecisional enforcement
conference. Please contact Mr, James W. McCormick Barger at (630) 829-9872 within 7 days
of the date of this letter to notify the NRC of your intended response.
Your response to the apparent violations (if you choose to provide one) should be clearly
marked as a " Response to Apparent Violations in IR 50 266/97010(DRS); 50-301/97010(DRS),"
and should include: (1) the reason for the apparent violations, or, if contested, the basis for
disputing the apparent violations; (2) the corrective steps that have been taken and the results
achieved; (3) the corrective steps that will be taken to avoid further violations; and (4) the date
when full compliance will be achieved.
Your response to the violations and apparent violations should be submitted under oath or
affirmation and may reference or include previous docketed correspondence, if the
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S. A. Patutski
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Septcrnber 15, 1997
correspondence adequately addresses the required response. If an adequate response is not
received within the time specified or an extension of time has not been granted by the NRC, the -
NRC will proceed with its enforcement decision or schedule a predecisional enforcement
conference.
In addition, please be advised that the characterization of the apparent violations described in
the enclosed inspection reports may change as a result of further NRC review. You will be
advised by separate correspondence of the results of our deliberations on this matter,
in accordance with 10 CFR 2.700 of the NRC's * Rules of Practice," a copy of this letter, its
enclosures, and your response will be placed in the NRC Public Document Room (PDR). To
the extent possible, your response should not include any personal privacy, proprietary, or
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safeguards information so that it can be placed in the PDR without redaction.
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Sincerely,
/s/ J. A. Grobo
John A. Grobe, Acting Director
Division of Reactor Safety
Docket Nos. 50 266; 50-301
Enclosures:
2. Inspection Report 50 260/97010(DRS); 50 301/97010(DRS)
cc w/encls:
R. R, Grigg, President and
Chief Operating Ofilcer, WEPCo
A. J. Cayla, Plant Manager
Virgil Kanable, Chief, Boller Section
Cheryl L. Parrino, Chairman
Wisconsin Public Service Commission
State Liaison Officer
Distribution:
Docket File w/enci .
SRI, Pt. Beach w/ encl
DOCDESK w/ encl
PUBLIC IE-01 w/ encl
LPM, NRR w/enci
CAA1 w/enci
bOC/LFDCB w/ encl
A B. Beach, Rlll w/enci
J. Lieberman, OE w/enci
DRP w/enci
J. L. Caldwell, Rlli w/enci
J. Goldberg, OGC w/enci
DRS w/enct
Rill Enf. Coordinator w/ encl
R. Zimmerman, NRR w/enci
Rlli PRR w/enci
TSS w/ encl
SEE ATTACHED CONCURRENCES
DOCUMENT NAME: G:\\DRS\\ pol 97010.DRS
To roccive a copy of this document. indicate in the box: *c" a Copy w/o attachment' enclosure "E" = Copy with attachment' enclosure *N" a No copy
OFFICE
Rlli:DR_S
Rlll:DRP
Rill:RAO
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Rlll:ElCS
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Rill:DRS _1 ,
NAME
Butlerinjc/lc
McCormick Barger Berson
Clayton
Jacobsof9AuM
DATE
09/ /97
09/
/97
09/
/97
09/
/97
09//6797
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OFFICIAL RECORD COPY
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P
S. A. Patulski
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In addition, please be advised that the characterization of the apparent violations described in
the enclosed inspection reports may change as a result of further NRC review. You will be
advised by separate correspondence of the results of our deliberations on this matter,
in accordance with 10 CFR 2.700 of the NRC's * Rules of Practice," a copy of this letter, its
enclosures, and your response will be placed in the NRC Public Document Room (PDR). To
the extent possible, your response should not include any personal privacy, proprietary, or
safeguards information so that it can be placed in the PDR without redaction.
Sincerely,
John A. Grobe, Acting Director
Division of Reactor Safety
Docket Nos. 50-266; 50 301
Enclosures:
2. Inspection Report 50 266/97010(DRS); 50 301/97010(DRS)
cc w/encis:
R. R. Grigg, President and
Chief Operating Officer, WEPCo
A. J. Cayla, Plant Manager
Virgil Kanable, Chief, Boller Section
Cheryl L. Parrino, Chairman
Wisconsin Public Service Commission
State Liaison Officer
Distribution:
Docket File v.lenct
SRI, Pt. Beach w/ enc!
DOCDESK w/enct
PUBLIC IE-01 w/enct
LPM, NRR w/onci
CAA1 w/enct
OC/LFDCB w/enct
A. B. Beach, Rllt w/enci
J. Lieberman, OE w/ enc!
DRP w/enct
J. L. Caldwell, Rlli w/enci
J. Goldberg, OGC w/enct
DRS w/enct
Rlli Enf. Coordinator w/ encl
R. Zimmerman, NRR w/ erb '
Rlli PRR w/enci
TSS w/enci
DOCUMENT NAME: G:\\DRS\\ pol 07010.DRS
Te receive a copy of this document, Indicate in the box: "C" a Copy w/o attAbment' enclosure "E" a Copy with attachmentrenclosure "N" a No copy
OFFICE
Rill:DRS
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Rlll:DRP
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Rlil: RAM /
Rlll:EICS _dn
Rill:DRS
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NAME
Butler /kic/lc 9nfA McCormick-F3arggr Berson )(lF ,
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ClaytQ R ht-
Jacobson/Grobe
DATE
09/ / /97
/
09/ V/97
- N 09/ /97 \\Mtdf/
09/$ /9'7AA*
09/
/97
OFFICIAL REDORD COPY
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