ML16161A791

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Enforcement Conference Repts 50-269/87-12,50-270/87-12 & 50-287/87-12 on 870306.Major Areas Discussed:Issues & Concerns Re Inadequate App R Circuit Analysis for Certain high-low Pressure Interfaces
ML16161A791
Person / Time
Site: Oconee  
Issue date: 03/17/1987
From: Conlon T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML16161A792 List:
References
50-269-87-12-EC, 50-270-87-12, 50-287-87-12, NUDOCS 8704030190
Download: ML16161A791 (3)


See also: IR 05000269/1987012

Text

REG,,

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTA STREET, N.W.

ATLANTA, GEORGIA 30323

Report Nos.:

50-269/87-12, 50-270/87-12, and 50-287/87-12

Licensee:

Duke Power Company

422 South Church Street

Charlotte, NC 28242

Docket Nos.: 50-269, 50-270,

License Nos.: DPR-38, DPR-47 and

and 50-287

DPR-55

Facility Name:

Oconee 1, 2, and 3

Meeting at Region II Office in Atlanta, Georgia on March 6, 1987.

Approved by:

-

6

<~

7

T. E. Conlon, Section Chief

Date Signed

Engineering Branch

Division of Reactor Safety

SUMMARY

Scope:

An enforcement meeting was held at the Region II Office on March 6,

1987.

The Director, Division of Reactor Projects,

opened the meeting by

stating the issue and concerns of Region II on Inadequate Appendix R Circuit

Analysis for certain high-low pressure interfaces.

He then turned the meeting

over to Duke Power Company (DPC).

The Vice President of Design Engineering

opened the meeting for DPC by briefly discussing the subject areas to be

covered. The areas covered involved valves LP-1 and LP-2 in the Low Pressure

Injection System and valve HP-4 on the outlet from Letdown Cooler B.

The

licensee responded to NRC questions throughout the meeting.

The Director,

Division of Reactor Projects, thanked DPC for the presentation and closed the

meeting.

8704030190 870325

PDR

ADOCK 05000269

G

PDR

REPORT DETAILS

1. Attendees at Enforcement Meeting

Duke Power Company

R. B. Priory, Vice President, Design Engineering

N. Rutherford, NPD, Licensing

M. S. Tuckman, Oconee Station Manager

T. Coutu, Operations Engineer

H. D. Brandes, Civil Design Engineer

R. L. Dobson, Electrical Design Engineer

E. G. Frampton, Electrical Design Engineer

Nuclear Regulatory Commission

L. A. Reyes, Director, D.RP, RII

V. W. Panciera, Deputy Director, DRS, RH

A. R. Herdt, Chief, Engineering Branch, DRS, RH

T. A. Peebles, Acting Chief, Reactor Projects Branch, DRP, Ru

T. E. Conlon, Chief, Plant Systems Section, DRS, RII

W. H.

Miller, Fire Protection Engineer, PSS, RH

P. J. Fillion, Reactor Inspector, PSS, RH

M. D. Hunt, Reactor Inspector, PSS, RH

L. D. Wert, Resident Inspector, Oconee Site, RII

B. Uryc, Enforcement Specialist, RII

L. Trocine, Enforcement Specialist, RII

H. W. Wong, Senior Enforcement Specialist, IE, HQ

2. Background

The primary issue for discussion was whether or not the licensee had

performed an adequate Associated Circuit Analysis in accordance with

10 CFR 50.48, Appendix R and associated circuits as defined in Generic

Letter 81-12,

dated February 20,

1981.

Specifically with respect to

valves LP-1 and LP-2 in the Low Pressure Injection System (Decay Heat) and

valve HP-4 in the Letdown Cooling System.

3. Enforcement Meeting

During their presentation, DPC made the following points:

a. Motor Operated Valves (MOV) LP-1 and LP-2.

(1) As a result of NRC's concerns on spurious opening of LP-1 and

LP-2, DPC performed additional analysis for these valves.

(2) DPC concluded that a postulated fire in the west penetration

room would not have an adverse effect on LP-1 and LP-2.

2

b. Letdown MOV HP-4

(1) DPC agreed with NRC's finding that MOV HP-4 could open as a

result of spurious signals.

(2) DPC will reroute cables for HP-4 to correct the problem.