ML16161A791
| 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
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
ADOCK 05000269
G
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.