ML20207Q819
| ML20207Q819 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/02/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8703100032 | |
| Download: ML20207Q819 (2) | |
Text
- 4 h
-t DUKE POWER Gourm P.O. HOX 33189 CHAMLOTTE, N.C. 28242 IIAL 11. TUCKEH TELEPHONE m m.
m
(*) NNn
,,mo..
mio.
March 2, 1987 U.S. Nuclear Regulatory Commission
? MIContiroliDesk!"v5
~ Washingt'on, D.C." 20555
~'
Subject:
McGuire Nuclear Station Docket Nos. 50-369, 50-370 Gentlemen:
By letter dated February 13, 1987, Duke responded to a request for additional information from Mr. D.S. Hood dated January 12, 1987. Additional review has revealed that the response to the first item, the section dealing with the actual performance of the surveillance as modified, was inaccurate. Accordingly, please find attached a revised response to Item 1 of Mr. Hood's letter, with notation in the right margin where the response is revised.
We apologize for any inconvenience this may have caused. If additional information is needed, please contact us through normal licensing channels.
Very truly yours, i
\\
Hal B. Tucker JBD/174/j gm Attachment xc:
Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station Mr. Darl Hood Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission Region II
[\\
101 Marietta St. NW, Suite 2900 Atlanta, Georgia 30323 g
G703100032 870302 DR ADOCK 05000369 PDR
~
DUKE POWER COMPANY McGUIRE NUCLEAR STATION RESPONSE-TO REQUEST FOR ADDITIONAL INFORMATION SURVEILLANCE REQUIREMENTS FOR COLD LEG ACCUMULATOR ISOLATION VALVES 1.
You state (incorrectly) that - the ' proposed TS change is to allow the imple-mentation of-planned modifications (i.e., installation of a power disconnect switch on the control board for the cold leg accumulator discharge isolation valves). We find that the effect of the proposed TS change would be to provide for use of the design modification as the basis for verifying that power to the isolation valve operator is disconnected, without additionally verifying removal of the breaker from the circuit. Provide a technical justification.for your proposed request accordingly. Explain how the veri-fication required by the TS, as modified, would be accomplished.
Include in this discussion the conformance of the design modification to NRC Branch Technical Positions ICSB-4(PSB) and ICSB-18 (PSB).
Include electrical
. drawings and schematics as appropriate to support your technical discussion.
[
~ RESPONSE:
Referring to MCEE-151-00.15,' (attached) when the NI54/Close pushbutton is pressed contacts B5 and B6 close applying 120VAC control power to coil M/C. This closes a set of contacts (M/C) in the 600VAC motor control center. If the valve does not move to close position, this will signal that power disconnect circuit is in effect. Valve position can be confirmed by observing'the green indicator light on E30JYS control switch.
Conformance with NRC Branch Technical Position ICSB-4 (PSB) is assured as power is removed and the isolation valve is open. The position of the valve may be veri-fied from the control room as described above. Power is removed from the operator cnd would require deliberate operator action to restore power and move the valve.
and no bypass is used for any testing as the valve is not required to move when 4
the reactor coolant system is at pressure.
I Conformance with NRC Branch Technical Position ICSB-18 (PSB) is assured as power is disconnected from the valve operator. With power removed from the operator and the valve in the proper (open) position, precludes any function of the valve, and, l
renders it a non-active valve. As the valves are no longer active, no failure to l
function or undesirable function may occur. No operator action is required to l
casure desired performance of these valves under accident conditions.
l l
Post modification testing involves switching the power disconnect position and then pressing the close pushbutton. As discussed above, the valve would not move to the closed position with the power disconnect in effect. Valve position is confirmed by an indicator light. It has been confirmed on Unit I that the valve J_
will not move with the power disconnect in effect.
Routine surveillance is accomplished by verifying that the power disconnect switch is in the disconnect position and the valve indicator light indicates the valve is cpen.
It should also be noted that power disconnect switches are in use with other valves (specifically FW27, nil 00, NI147) to prevent spurious actuations.
This is i
described in the FSAR, subdivision 6.3.2.16.
m