ML20211B170
| ML20211B170 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/17/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Patulski S WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML20211B177 | List: |
| References | |
| 50-266-97-17, 50-301-97-17, EA-97-089, EA-97-281, EA-97-89, NUDOCS 9709250096 | |
| Download: ML20211B170 (5) | |
See also: IR 05000266/1997017
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UNITED STATES
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- NUCLEAR REGULATORY COMMISSION
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REGION 111
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801 WARRENvtLLE ROAD
USLE. ILUNOls 60532-4351
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September 17,1997
EA 97-085
EA 97-281
Mr. S. A. Patuiski, Site Vice President
Point Beach Nuclear Plant
6610 Nuclear Road --
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- Two Rivers, Wisconsin 54241'
CUBJECT:
POINT BEACH NRC INSPECTION REPORT NO. 50-266/97017(DRP);
50-301/97017(DRP); AND NOTICE OF VIOLATION
Dear Mr. Patuiski:
On August 5,1997, the NRC completed an inspection at your Point Beach Nuclear Plant, Units 1
. and 2. The inspection was conducted to review the circumstances surrounding facility
management providing inaccurate information to the NRC regarding the capability to cross-
connect the Units 1 and 2 component cooling water (CCW) systems. The enclosed report
presents the results of the inspection.
The inspection disclosed that your Plant Manager provided inaccurate information to the NRC
during conversations on February 19,1997. That inaccurate information indicated that valves
, could be opened to cross-connect Unit 1 and 2 component cooling water systems in the event
_that it was necessary to compensate for inoperable component cooling water system pumps.
That inaccurate oral information was confirmed in writing on February 20,1997, in a letter signed
by your Manager of Regulatory Services and Licensing. NRC inspection and investigation
revealed _that plant operators were aware that many years ago these valves had to be forced
closed with mechanical assistance beyond normal closing force to stop valve leakage resulting in
questionable operability of the valves. In fact, the valves were damaged and one valve could not
be opened.
The inaccurate information that facility managers provide to the NRC was one aspect of the
justification for enforcement discretion while the facility was in continuing violation of its technical
specifications.- While we recognize that in this case had correct information been provided, it
- may not have altered the NRC decision to grant enforcement discretion, the NRC must be able to
depend upon the veracity of information provided by its licensee. Your managers clearly did not
exercise due caution in this situation to assure that the information provided to the NRC was
complete and accurate in all material respects. This matter was complicated in that the affected
valves had not been tested for many y1ars to verify their operability as required by NRC '
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regulations. . Consequently, your valve testing program did not identify the suspect condition of
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the valves.
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Providing information to the NRC that is not complete and accurate in all material respects is a
violation of 10 CFR 50.9 and not testing the cross connect valves is a violation of 10 CFR Part 50, Appendix B. Criterion XI. Beyond the specific violations, we are concerned that facility .
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management did not promptly notify NRC management as soon as the potential was raised that -
- the subject information was incorrect. While this did not represent a violation, it also did not
meet our expectations for prompt and open communication of important information.
The violations are cited in the enclosed Notice of Violation, and the circumstances surrounding
the violations are described in detail in the enclosed report. You are required to respond to_ this -
letter and should follow the instructions specified in the enclosed Notice when preparing your re-
i
sponse _ The NRC will use your response,in part, to determine whether further enforcement
!
. action is necessary to ensure compliance with regulatory requirements.- Regarding the
inaccurate information, you should descnte steps you have taken to assure complete open and
candid communication occurs with NRC staff and management. Regarding violation No. 2, the
recent revision of your Technical Specifications has obviated the need to test the CCW pump
cross-connect valves and thus you do not need to provide corrective actions for that specific
aspect of the violation; however, you are required to describe what you will do to ensure that
other similarly important valves are included in your testing program.
In accordance with 10 CFR 2.790 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).
Sincerely,
.
hn A. Grobe, Acting Director
Division of Reactor Safety
,
Docket Nos: 50-266, 50-301
Enclo'sures:
2." Inspection Report No. 50-266/97017(DRP):
50-301/97017(DRP)
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cc w/ encl:'
R. R. Grigg, President and Chief
Operating Officer, WEPCO
A. J. Cayia, Plant Manager
Virgil Kanable, Chief,
_ Boiler Section
Cheryl L. Parrino, Chairman
Wisconsin Public Service
Commission
State LLison Officer
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S. A. Patutski
2-
management did not promptly notify NRC management as soon as the potential was raised that
the subject information was incorrect. While this did not represent a violation, it also did not
meet our expectations for prompt and open communication of important information.
The violations are cited in the enclosed Notice of Violation, and the circumstances surrounding
the violations are described in detailin the enclosed report. You are required to respond to this
letter and should follow the instructions specified in the enclosed Notice when preparing your re-
sponse. The NRC will use your response, in part, to determine whether further enforcement
action is necessary to ensure compliance with regulatory requirements. Regarding the
inaccurate information, you should describe steps you have taken to assure complete open and
cand:d communication occurs with NRC staff and management. Regarding violation No. 2, the
reced revision of your Technical Specifications has obviated the need to test the CCW pump
cross-connect valves and thus you do not need to provide corrective actions for that specific
aspect of the violation; however, you are required to describe what you will do to ensure that
other similarly important valves are included in your testing program.
j
in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its
i
enclosures, and your response will be placed in the NRC Public Document Room (PDR).
Sincerely,
I
/s/ John A. Grobe
John A. Grobe, Acting Director
Division of Reactor Safety
Docket Nos: 50-266, 50-301
License Nos: DPR-24, OPR-27
Enclosures:
2. Inspection Report No. 50-266/97017(DRP);
50-301/97017(DRP)
(See attached concurrence)
(See attached distribution)
Document: R:/Insprpts/ powers /poin/ poi 97017.drp
To receive a copy of this document, indicate in the box "C" = Copy without attach /enci "E"
= Copy with attach /enci "N" = No copy
OFFICE
Rill
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NAME
Kunows i:
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Berson
DATE
9/t?/97
9/G97
9/ !97
9/IT97
9//697
OFFICIAL RECORD COPY
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(Distribution)
cc w/ encl:
R. R. Grigg, President and Chief
Operating Officer, WEPCO
A. J. Cayia, Plant Manager -
Virgil Kanable, Chief,
Boiler Section
Chetyl L. Parrino, Chairman
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- Wisconsin Public Service
Commission
'
State Liaison Officer
- Docket File w/ encl
SRI Point Beach w/enci
PUBLIC IE-01 w/enci
OC/LFDCB w/enci
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A. B. Beach, w/enci
Rlll Enf. Coordinator, w/en:l
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Deputy RA, w/enci
CAA1 w/enci (E-mail)
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Project Manager, NRR, w/enci
DRP, w/enci
Rlli PRR w/ encl
DRS (2) w/enci
TSS w/enci -
DOCDESK (E-mail)
J, Lieberman, OE
R. Zimmerman, NRR
J. Goldberg, OGC
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S. A. Patuiski
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In accordance with 10 CFR 2.790 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).
Sincerely,
John A. Grobe, Acting Director
Division of Reactor Safety
Docket Nos: 50-266, 50-301
Enclosures:
2, inspection Report No. 50-266/97017(DRP);
50-301/97017(DRP)
cc w/ encl:
R. R. Grigg, President and Chief
Operating Officer, WEPCO
A. J. Cayia, Plant Manager
Virgil Kanable, Chief,
Boiler Section
Cheryl L. Parrino, Chairman
Wisconsin Public Service
Commisslor,
State Liaison Officer
Docket File w/enci
SRI Point Beach w/enct
PUBLIC IE-01 w/enci
OC/LFDCB w/ encl
A. B. Beach, w/enct
Rlli Enf. Coordinator, w/enct .
Deputy RA, w/enci
CAA1 w/enci (E-mail)
Project Manager, NRR, w/ enc!
DRP, w/enci
Rlli PRR w/enci
DRS (2) w/enct
TSS w/enci
DOCDESK (E-mail)
J. Lieberman, OE
R. Zimmerman, NRR
J. Goldberg, OGC
Document:
To receive a copy of this document, indicate in the box "C" = Copy without attach /enci "E"
= Copy with attach /enci
"N" = No copy
OFFICE
Rlli
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Rill
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Rlli B
Rlli
Rlli
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NAME
Kunowski dr/7,4 L JMcB %
Ber onIM
Grobe
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DATE
9/fl97
9/5797
9/5/97
9(0/97
9/ /97
OFFICIAL RECORD COPY