ML20148K696
| ML20148K696 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 01/19/1988 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8801280022 | |
| Download: ML20148K696 (9) | |
Text
,
1 DUKE POWEn GOMPANY i
P.O. Imx 03180 CitARLOrTE. N.O. 28242 HAL D. TUCKER Tztsenoxz vu en.aaem (704) 073-4531 NttLEAR reoptetton January 19, 1988 U.S. Nuclear Regulatory Commission VI)ocument Control Desk I
Washington, D.C.
20555
Subject:
McGuire Nuclear Station, Unit 1 Docket No. 50-369 Requests for Relief from ASME Code Section XI Requirements Gentlemen:
Pursuant to 10CFR 50.55a(g)(5)(iii), Duke transmitted a relief request dated Oc-i tober 26, 1987 to the NRC.
Subsequently during a visit to McGuire, NRC Region II Inspector B.R.
Crowley requested additional information pertaining to Attach-ments 1, 2, and 5 of the relief request dated October 26, 1987.
Accordingly, please find attached the requested information.
Also, Duke under-stands that no additional application fee is due since this submittal is a fol-low-up of additional information.
Should there be any questions concerning this letter, please contact Steve LeRoy of Duke Licensing at (704)373-6233.
Very truly yours, e
Hal B. Tucker SEL/208/j ge Attachment 8801280022 860119 PDR ADOCK 05000369 P
pg w
Document Control Desk January 19, 1988 Page 2 xc:
Dr. J. Nelson Grace Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, CA 30323 B.R. Crowley U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, GA 30323 Mr. Darl Hood U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station 1
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ATTACHMENT 2 Additional Information Additional'elarity and justification for relief request.
1.
Component for Which Relief is Requested:
A.
Name and Number 1.
Valve IRN134 weld numbers 58-1 and 58-2, pipe size 18" with a wall thickness of.375, SA106 Grade B material, j
2.
Valve IRN235 weld numbers 60-1 and 60-2, pipe size 18" with a wall thickness of.375, SA106 Grade B material.
3.
Valve 1RN130A, weld numbers RN1F-3312, 3313 and 3314, pipe size 2" with a wall thickness of.154 SA106 Grade B material, t
1 3.
Basis for Requesting Relief:
~
A.
Additional Justification for Impracticality of Hydrostatic Test
]
Due to engineering design, by the use of butterfly valves.' it is impossible to hydrostatically test this system without affecting the other operable train of this system.
The possibility exists that other sections of the system could be over pressurized, i.e.,
the capacity is not available to offset leakage by said valves.
In i
addition these sections of the RN system have a low design pressuta
]
and temperature of 135 psig and 95 degrees-F.
The additional burden of performing these tests could potentially lead to the unit being a
l involuntarily removed from service.
4.
The ASME code requires only a dye penetrant (PT) examination on the 1
finished weld surface for greater than 4" NPS.
We impose an additional l
PT inspection on the root pass weld.
4' On 4" and less NPS, only a final visual is required.
We impose a PT i
inspection in addition to a final visual inspection on the finished weld i
surface.
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ATTACHMENT 3 Additional Information Additional clarification is provided to define why a dye penetrant (PT) inspection was not performed.
Component for Which Relief is Requested:
Valve IRN134A This valve was initially removed from service in order to perform extensive welding and machining repairs to the internal valve disc seating area.
Internal inspection revealed that an adjacent weld, RN IF427, had lack of penetration and lack of fusion in the root of the weld. The root of this weld was machined out and rewelded by a qualified welder using qualified materials.
This weld was very near the valve seat area which required extensive welding repairs.
Welding material applied to the valve seat area eventually over-lapped weld RN IF427.
Machining of this weld area was then performed to facilitate the valve seat replacement.
After reseating of the valve and reassembly, the valve was then rewelded into the system. After rewelding into the system, it was discovered that the required dye penetrant (PT) test was not performed.
The request for relief from code requirement as defined in attachment three was then submitted.
ll
r ATTACHMENT 5 Additional Information Additional clarification is provided to define why hydrostatic test was impractical.
1.
Component for Which Relief is Requested:
D.
Materials and Welds Pipe size is 20",
with a wall thickness of.375, SA106 Grade B material.
Design pressure 135 psig and 150 degrees-F.
3.
Basis for Requesting Relief:
A.
Additionti Justification for Impracticality of Hydrostatic Test Due to engineering design by use of butterfly valves it is impos-sible to hydrostatically test this system without affecting the other operable train of the RN system.
The possibility exists that other sections of the system could be over pressurized, i.e.,
butterfly valves will not hold pressure.
Also, additional pump capacity is not available to offset leakage by said valve s.
In addition, these sections of the RN system have a low design pressure and temperature of 135 psig and 150 degrees-F.
4.
The ASME code requires only a dye penetrant (PT) examination on the finished weld surface for greater than 4" NPS.
We impose an additional PT inspection on the root pass weld.
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