ML20205Q262

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Forwards Insp Repts 50-454/99-03 & 50-455/99-03 on 990217-0329.Five Violations Identified & Treated as Ncvs. Expresses Continued Concern with Configuration Control & Human Performance Errors at Byron Station
ML20205Q262
Person / Time
Site: Byron  Constellation icon.png
Issue date: 04/14/1999
From: Jordan M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Kingsley O
COMMONWEALTH EDISON CO.
Shared Package
ML20205Q263 List:
References
50-454-99-03, 50-454-99-3, 50-455-99-03, 50-455-99-3, NUDOCS 9904210147
Download: ML20205Q262 (4)


See also: IR 05000454/1999003

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April 14, 1999

Mr. Oliver D. Kingsley

President, Nuclear Generation Group

Commonwealth Edison Company

ATTN: Regulatory Services

Executive Towers West 111

1400 Opus Place, Suite 500

Downers Grove,IL 60515

SUBJECT:

BYRON INSPECTION REPORT 50-454/99003(DRP); 50-455/99003(DRP)

Dear Mr. Kingsley:

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On March 29,1999, the NRC completed an inspection at the Byron 1 and 2 reactor facilities.

The enclosed repori presents the results of that inspection.

During this inspection period, control room operations were performed in a safe and

professional manner. Operators adhered to the station's standards for reactivity management,

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professionalism, control room conduct, procedural adherence, annunciator response, and

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generally used three-way communication This observation has been consistent over the past

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severalinspection periods. We also noted that the conduct of maintenance was generally

performed well, with two notable exceptions. The first example, which the inspectors identified,

resulted in the improper installation of flexible hoses on the Unit 1 A emergency diesel generator

and the second example resulted in the over-torquing of coupling fasteners on the Unit 1 A

chemical and volume control pump couplings. In both of these examples, mechanical

maintenance first-line supervisors improperly changed the work instructions which caused the

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deficiencies.

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We continue to be concerned with configuration control and human performance errors at

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Byron Station. Following three incidents during the second week of March 1999, you conducted

a 10-day stand down period beginning on March 11,1999, to focus on performance standards.

Two of those incidents are addressed in this report. In the first incident, the Unit 1 A emergency

diesel generator was rendered inoperable for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> while the north door to the

1 A diesel oil storage tank room was left open and unattended. The second incident involved a

potential chemical transfer accident, in which sodium hydroxide was nearly transferred from a

delivery truck into a storage tank containing sulfuric acid. While we recognize that you are

aggressively implementing corrective actions to address configuration control and human

performance events, the effectiveness of your actions has yet to bo demonstrated.

Based on the results of this inspection, the NRC has determined that five violations of NRC

requirements occurred. Thesc /iolations are being treated as Non-Cited Violations (NCVs),

consistent with Appendix C of the Enforcement Policy. These NCVs are described in the

subject inspection report. If you contest any of the violations or the severity level of these

NCVs, you should provide a response within 30 days of the date of this inspection report, with

9904210147 990414

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the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control

Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region ill; the

Senior Resident Inspector, Byron Station; and the Director, Office of Enforcement, United

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States Nuclear Regulatory Commission, Washington, DC 20555-0001.

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On February 5,1999, Byron Station implemented Amendment No.106 to the Technical

Specifications (TS). The amendment reflects the full conversion of the TS to a set of Improved

Technical Specifications (ITS) based on NUREG-1431, " Standard Technical Specifications --

Westinghouse Plants," Revision 1, dated April 1995. Inasmuch as some of the violations

discussed in the enclosed report occurred prior to ITS implementation, reference is made to

applicable sections of the TS as they existed prior to ITS implementation for those violations.

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its

enclosure and your response, if you choose to provide one, will be placed in the NRC Public

Document Room.

We will gladly discuss any questions you have concerning this inspection.

Sincerely,

/s/ M. J. Jordan

Michael J. Jordan, Chief

Reactor Projects Branch 3

Docket Nos. 50-454; 50-455

1

License Nos. NPF-37; NPF-66

Enclosure: Inspection Report 50-454/99003(DRP);

50-455/99003(DRP)

cc w/ encl:

D. Helwig, Senior Vice President

H. Stanley, PWR Vice President

C. Crane, BWR Vice President

R. Krich, Vice President, Regulatory Services

DCD - Licensing

W. Levis, Site Vice President

R. Lopriore, Station Manager

B. Adams, Regulatory Assurance Manager

M. Aguilar, Assistant Attorney General

State Liaison Officer

State Liaison Officer, State of Wisconsin

Chairman, Illinois Commerce Commission

DOCUMENT NAME: G:\\BYRO\\BYR99003.DRP

  • See previous concurrences

To receive a copy of this document. Indicate in the box: 'C' = Copy w/o attach /enci *E' = Copy w/ attach /enct *N* = No copy

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04/14/99

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OFFICIAL RECORD COPY

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Distribution:

SAR (E-Mail)

RPC (E-Mail)

Project Mgr., NRR w/enci

J. Caldwell, Rlli w/enct

B. Clayton, Rill w/ enc!

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the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control

Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region Ill; the

Senior Resident inspector, Byron Station; and the Director, Office of Enforcement, United States

Nuclear Regulatory Commission, Washington, DC 20555-0001.

On February 5,1999, Byron Station implemented Amendment No 106 to the Technical

Specifications (TS). The amendment reflects the full conversion of the TS to a set of improved

Technical Specifications (ITS) based on NUREG-1431, " Standard Technical Specifications --

Westinghouse Plants," Revsion 1, dated April 1995. Inasmuch as some of the violations

discussed in the attached report occurred prior to ITS implementation, reference is made to

applicable sections of the TS as they existed prior to ITS implementation for those violations.

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.

We will gladly discuss any questions you have concerning this inspection.

Sincerely,

Michael J. Jordan, Chief

Reactor Projects Branch 3

Docket Nos.: 50-454; 50-455

License Nos.: NPF-37; NPF-66

Enclosure: Inspection Report 50-454/99003(DRP);

50-455/99003(DRP)

cc w/ encl:

D. Helwig, Senior Vice President

H. Stanley, PWR Vice President

C. Crane, BWR Vice President

R. Krich, Vice President, Regulatory Services

DCD - Licensing

W. Levis, Site Vice President

R. Lopriore, Station Manager

,

B. Adams, Regulatory Assurance Manager

M. Aguilar, Assistant Attorney General

State Liaison Officer

i

State Liaison Officer, State of Wisconsin

Chairman, Illinois Commerce Commission

DOCUMENT NAME: R:\\l N S PR PTS \\POWE R S\\BYRO\\BY R 99003. D R P

To receive a copy of this document, indicate in the box *C" * Copy without attachment! enclosure *E" = Copy with attachment /enclosuee

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