ML20210T719

Enforcement Conference Rept 50-213/86-17 on 860903.Major Areas Discussed:Util 860703 Commitments Re Ability to Safely Shut Down in Event of Fire

ML20210T719
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/26/1986
From:	Anderson C, Krasopoucos A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20210T709	List: ML20210T706 ML20210T719 ML20210T726
References
50-213-86-17-EC, NUDOCS 8610090159
Download: ML20210T719 (3)

See also: IR 05000213/1986017

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

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< Report No. 86-17

1 Docket No. 50-213

License No. DPR-61 Priority -

Category C

Licensee: Connecticut Yankee

P.O. Box 270

Hartford, Connecticut 0610'1 ,

i Facility Name: Haddam Neck

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Meeting At: USNRC, Region I

King of Prussia Pennsylvania 19406

i Meeting Conducted: September 3,1986

NRC Personnel:

A. Wasppou

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s,' Reactor' Engineer, DRS

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Approved by: V/ >,-, 9 24 F4

C. J. A/iderson, Chief, da'e t signed

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Plant System Section DRS

, Meeting Summary: Enforcement conference at NRC Region I on September 3, 1986

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to discuss the findings identified in Inspection Report No. 86-17, whicli

reviewed the licensee's ability to safely shutdown the plant in the event of a

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fire. The items discussed were the four violations identified in the report

i and the commitments made to NRC via letter dated July 3,1986 concerning the

l findings of the above inspection.

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The licensee discussed the NRC concerns along with proposed near term and long

j term corrective actions

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8610090159 860926

PDR

G ADOCK 05000213

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DETAILS

1.0 Participants

1.1 Connecticut Yankee Atomic Power Co.

E. Mroczka, Vice President Nuclear Operations

R. Kacick, Licensing Supervisor

R. Graves, Station Suoerintendent

J. Ferguson, Unit Superintendent

G. Van Noordennen, Sr. Engineer Licensing

W. Lepper, Electrical Engineer, Special Studies

J. Roncatoli, Supervisor, Fire Prevention Engineering

B. Pokora, Sr. Engineer Reactor Plant Systems

W. Lepper, Electrical Engineer Special Studies

T. Bransfield, Engineer

1.2 U.S. Nuclear Regulatory Commission (NRC)

T. Murley, Regional Administrator

J. Allan, Deputy Regional Administrator

S. Ebneter, Director, Division of Reactor Safety -

W. Kane, Director, Division of Reactor Projects

W. Johnston, Deputy Director, Division of Reactor Safety

J. Durr, Chief Engineer Branch

C. Anderson, Chief, Plant Systems Section

E. McCabe, Chief, Division of Reactor Projects

M. Kray, Reactor Engineer

D. Holody, Enforcement Specialist

2.0 Purpose

This Enforcement Conference was held at the request of the NRC Region I

management to discuss the findings of the inspection conducted to assess

the licensee's compliance with the requirements of 10 CFR 50 Appendix R.

These findings appear in the Inspection Report No. 86-17.

3.0 Presentation and Discussion

Following the initial introductions and the opening remarks by the

Regional Administrator, Dr. T. E. Murley, the Director of the Division of

Reactor Safety, Mr. S. Ebneter, stated the purpose of the meeting.

Mr. Ebneter also briefly discussed, the sequence of events leading to the

Enforcement Conference and the nature of the findings to be discussed.

The licensee at this point was asked to present their perspective on the

findings and the reasons the non-compliances occurred. The licensee

distributed a document titled " Management Meeting 10 CFR 50 Appendix R"

for discussion purposes. This document is included in this report as

Attachment I.

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The licensee, in their presentation objected to the characterization of

two of the findings as violations. These findings are the inadequate

cooldown analysis and the inadequate emergency lights for certain plant

areas. For the former, the licensee's objection is based on the fact,

that the inadequate cooldown analysis resulted when figures from an

erroneous calculation, developed by an NRC consultant were used in this

analysis, without their reverification.

With regard to the inadequate emergency lighting the licensee stated

that the affected areas are used for shutdown purposes only in the interim

period until the Appendix R modifications are completed in 1989.

The licensee also presented their plans for compliance. These plans are

described in detail in a letter transmitted to NRC on July 3,1986.

4.0 Concluding Statements

The Regional Administrator and the Director of the Division of Reactor

Safety thanked the licensee for their presentation and stated that this

information would be considered in the NRC's determination of enforcement

actions related to these issues.

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