ML20141D750
| ML20141D750 | |
| Person / Time | |
|---|---|
| Site: | Braidwood |
| Issue date: | 05/09/1997 |
| From: | Caldwell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Stanley H COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20141D753 | List: |
| References | |
| 50-456-97-05, 50-456-97-5, 50-457-97-05, 50-457-97-5, NUDOCS 9705200190 | |
| Download: ML20141D750 (3) | |
See also: IR 05000456/1997005
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May 9, 1997
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Mr. H. G. Stanley
Site Vice President
Braidwood Station
Commonwealth Edison Company
RR #1, Box 84
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Braceville,IL 60407
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SUBJECT:
NRC INSPECTION REPORT 50-456/97005; 50-457/97005
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Dear Mr. Stanley:
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On April 7,1997, the NRC completed an inspection at your Braidwood 1 & 2 reactor
facilities. The enclosed report presents the results of that inspection.
During the 6-week period covered by this inspection period, your conduct of activities was
generally characterized by safety-conscious operations. Specifically, the preparation for
and conduct of the Unit 1 shutdown and cooldown, as observed by the inspectors on
March 28-29, demonstrated excellent safety focus and strong control room teamwork. In
addition, the preparation for future work on the Unit 1 "C" reactor coolant system cold leg
stop valve demonstrated good safety focus and communications between maintenance,
engineering, and radiation protection personnel.
We are concerned, however, about several specific problems:
First, the inspectors made several observations that indicated that control room
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panel attentiveness in late February and early March was weak.
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Second, the inspectors observed a step in an emergency operating procedure that
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referred to a piece of equipment that had not operated in about 10 years. The
inspectors concluded that the emergency operating procedure did not meet
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technical specification requirements and had been improperly maintained.
Third, the inspectors identified an example where the charging pumps auxiliary oil
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pumps were operated and exercised prior to a timed start to fulfill a technical
specification surveillance requirement. The inspectors concluded that operating the
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equipment immediately prior to timing its start test was preconditioning the
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equipment and was not meeting test control regulatory requirements.
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' Finally, plant barrier impairments were used to track maintenance which resulted in
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a failure to take corrective actions to repair a heat and smoke boundary described in
the fire protection report, instead of a 10 CFR Part 50.59 safety evaluation prior to
placing the auxiliary building ventilation system in an abnormal lineup. This
demonstrated an improper reliance on the plant barrier impairment program.
These violations are cited in the enclosed Notice of Violation, and the circumstances
surrounding the violations are described in detail in 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 ensure compliance with
regulatory requirements.
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.
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Sincerely,
/s/ J. A. Grobe for
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James L. Caldwell, Director
Division of Reactor Projects
Docket Nos: 50-456, 50-457
Enclosures:
1.
2.
Inspection Report
50-456/97005; 50 457/97005
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See Attached Distribution
DOCUMENT NAME: G:\\BRAl.lR\\ BRA 97005.DRP
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DATE
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05/ /97
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OFFICIAL. RECORD COPY
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H. Stanley
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Finallyi plant barrier impairments were used to track maintenance which resulted in
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a failure to take corrective actions to repair a heat and smoke boundary described in
the fire protection report,instead of a 10 CFR Part 50.59 safety evaluation prior to
placing the auxiliary building ventilation system in an abnormal lineup. This
demonstrated an improper reliance on the plant barrier impairment program.
These violations are cited in the enclosed Notice of Violation, and the circumstances
surrounding the violations are describod in detail in 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,
i
to determine whether further enforcement action is necessary to ensure compliance with
'
regulatory requirements.
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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.
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Sincerely,
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James L. Caldwell, Director
Division of Reactor Projects
Docket Nos: 50-456, 50-457
Enclosures:
1.
2.
Inspection Report
50-456/97005; 50-457/97005
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See Attached Distnbution
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DOCUMENT NAME: G:\\BRAl.lR\\ BRA 97005,DRP
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DATE
04/30/97
04/p/97
04/30/97
04/ /97
04/ /97
OFFICIAL RECORD COPY
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H. Stanley
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cc w/encis:
T. J. Maiman, Senior Vice President
Nuclear Operations Division
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D. A. Sager, Vice President,
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Generation Support
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H. W. Keiser, Chief Nuclear
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Operating Officer
T. Tulon, Station Manager
T. Simpkin, Regulatory
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Assurance Supervisor
1. Johnson, Acting Nuclear
Regulatory Services Manager
Richard Hubbard
Nathan Schloss, Economist
Office of the Attorney General
,
State Liaison Officer
Chairman, Illinois Commerce
Commission
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Document Control Desk-Licensing
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Distribution
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Docket File w/enci
DRP w/ encl
OC/LFDCB w/ encl
Rlli PRR w/enct
PUBLIC IE-01 w/ encl
CAA1 w/enci (E-mail)
SRI Byron, Braidwood, Zion w/ encl
Rill Enf Coordinator, w/enct
Project Mgr., NRR w/enci
A. B. Beach, w/enci
RAC1 (E-Mail)
Deputy RA, w/ encl
TSS w/enci
DRS (2)
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