ML20141D750

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Forwards Insp Repts 50-456/97-05 & 50-457/97-05 on 970222- 0407 & Notice of Violation
ML20141D750
Person / Time
Site: Braidwood  Constellation icon.png
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

NOTICE OF VIOLATION

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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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H. Stanley

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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

License Nos: NPF-72, NPF-77

Enclosures:

1.

Notice of Violation

2.

Inspection Report

50-456/97005; 50 457/97005

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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,

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to determine whether further enforcement action is necessary to ensure compliance with

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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

License Nos: NPF-72, NPF-77

Enclosures:

1.

Notice of Violation

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

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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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