ML20210U471
| ML20210U471 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/09/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8702180487 | |
| Download: ML20210U471 (50) | |
Text
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Y S
Y A
DUKE POWER GOMPANY P.O. box 33189 CHARLOTTE. N.C. 28242 HAL H. TUCKER Ten.mn=esown vsom poemsommt (704)073-4531 NEELEAR PRODUCTION February 9,1987 U.S. Nuclear Regulatory Commission Document Control Desk
-Washington, D.C.
20555
Subject:
McGuire Nuclear Station Docket No. 50-369 and 50-370 Requests for Relief from ASME Code Section XI Requirement Deterrined to be Impractical 1
Gentlemen:
Please find attached a request for relief (pursuant to 10CFR 50.55a(g)(5)(iii))
from ASME Code Section XI Hydrostatic Testing requirements for portions of rodifications on the (Unit 1 and 2) nuclear service water (RN) system. These codifications are to reduce problems associated with fouling on the RN system, which has been the subject of numerous telecons, meetings, and correspondence between Duke Power Company and NRC/ Region II (e.g. NRC/0IE Inspection Report 50-369/85-38 and 50-370/85-39), as well as a previously approved relief request (reference my June 27, 1986 submittal). Based on past experiences, hydrostatic testing has been determined to be impractical for these portions.
These modifications, which have previously been discussed in my letters of December 18, 1985 and April 25, 1986 to Dr. J.N. Grace (NRC/ Region II), are to be implemented over the next two years (i.e. during the 1987 and 1988 refueling outages).
Marked up flow diagrams and sketches of the portions affected have been included for your information.
Pursuant to 10CFR 170.3(y),170.12(c), and 170.21, Duke Power proposes that this cxemption request constitutes a required approval for McGuire Units 1 and 2 cubject to fees based on the full cost of the review (to be calculated using the cpplicable professional staff rates shown in 10CFR 170.20) and must be accompanied by an application fee of $150, with the NRC to bill Duke Power at six-month intervals for all accumulated costs for the application or when review is completed, whichever is earlier. Accordingly, please find enclosed a check in the caount of $150.00.
G702100407 870209 PDR ADOCK 05000369 h
P PDR Re. del w}coketc $150 00 M
1 Document Control Desk February 9,1987 Page-2 It is requested that these reliefs receive attention commensurate with the above stated implementation schedule.- Should there be any questions concerning this matter or if additional information is required (such as copies of the referenced flow diagrams), please advise.
Very truly yours, Hal B. Tucker PBN/47/j gm Attachment 1
xc:
(with attachment)
Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission - Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Darl Hood, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station l
DUKE POWER COMPANY MCGUIRE NUCLEAR STATION REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS DETERMINED TO BE IMPRACTICAL I.
Components for which relief is requested:
A.
Name and Number The following modifications on the Nuclear Service Water System (RN) will be implemented during 1987 and 1988 refueling outages.
Presently the modifications are still being designed thus specific 1
weld numbers with exact locations can not be supplied.
1.
MG-1-1887 Rev. 2: All welds associated with the replacement of valves 1RN137A and 1RN238B. Two new slip-on flanges per valve will be installed on this modification.. (see attachment 45 and 46) 2.
MG-2-0666 Rev. 2: All welds associated with the replacement of valves 2RN137A and 2RN238B. Two new slip-on flanges per valve I
will be installed on this modification.
(see attachment 47 and 48) 3.
MG-1-0351 Rev. 0: Welds associated with final tie-in to process header on check valve bypass lines (see attachment 44) and welds associated with final tie-in to process header on high point bypass loop.
(see attachment 43). Final tie-in weld, meaning j
the weld which connects the new piping to the existing piping.
j All other welds within the new piping will be hydrostatically~
tested.
4.
MG-1-1886 Rev. O. MG-1-1888 Rev. O, MG-1-1889 Rev. O, MG-1-1890 Rev. O, MG-1891 Rev. O, MG-1-1892 Rev. O, MG-2-0667 Rev. O, MG-2-0668 Rev. O, MG-2-0669 Rev. O, MG-2-0670 Rev. O, MG-2-0671 Rev. O, MG-2-0672 Rev. 0: All welds between the supply / discharge header and the first isolation valve. All welds between the isolation valves will be hydrostatically tested.
(see attachments 1 thru 42)
B.
Function The following modifications have been written to reduce problems associated with fouling on the Nuclear Service Water system:
1.
MG-1-1887 Rev. 2 and MG-2-0666 Rev. 2 - Containment Spray (NS) heat exchanger downstream isolation valves (1RN137A, 1RN238B, 2RN137A, and l
2RN238B) on the RN system will be replaced. Valves are being replaced to support a wet-layup system for each heat exchanger.
j Wet-layup system is a system to keep the shell side (RN side) of the heat exchangers in a chemically controlled environment.
2.
MG-1-1888 Rev. O and MG-2-0668 Rev. 0 - Replace small diameter carbon steel piping going to the NI (Safety Injection System) pump motor coolers and the NV (Chemical Volume Control System) pump motor coolers with stainless steel piping.
3.
MG-1-1890 Rev. O and MG-2-0670 Rev. 0 - Replace small diameter carbon I
steel piping going to the RN (Nuclear Service Water) pump motor coolers with stainless steel piping.
4.
MG-1-1891 Rev. O and MG-2-0671 Rev. 0 - Replace small diameter carbon steel piping going to the CA (Aux. Feedwater) pump motor coolers with stainless steel piping.
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5.
MG-1-1886 Rev. O and MG-2-0667 Rev. O Replace small diameter carbon.
steel piping going to the KC (Component Cooling Water) pump motor coolers with stainless steel piping.
6.
MG-1-1889 Rev. O and MG-2-0669 Rev. 0 - Replace smal1~ diameter carbon steel piping going to the ND (Residual Heat Removal) pump air handling units, NS (containment spray) pump air handling unit with stainless steel piping.
7.
MG-1-1892 Rev. O and MG-2-0672 Rev. 0 - Replace small diameter carbon steel piping going to the XF (Spent Fuel Cooling) air handling' unit with stainless steel piping.
j.
8.
MG-1-0351 Rev. 0 - Add drains and bypass lines to the RN system to improve system draining capability.
C.
ASME III Code Class j
Equivalent class 3 D.
Materials and Welds 2
1.
MG-1-1887 Rev. 2 and MG-2-0666 Rev. 2 - Piping and flanges are carbon steel. Welding will be carbon steel to carbon steel.
2.
MG-1-0351 Rev. 0 - All piping is carbon steel. All welds will be carbon steel to carbon steel.
3.
MG-1-1886 Rev. O, MG-1-1888 thru 1892 Rev. O, MG-2-0667 Rev. O thru 0672 All new piping and valves will be stainless steel. All old piping is carbon steel. All welding within the new piping (couplings, elbows, valves, etc.) will be stainless to stainless.
There will be stainless to carbon welds at the junctions of the old and new piping.
i II.
ASME Code Section XI Requirement that has been determined to be impractical ASME B and PV code section XI, 1890 edition through winter 1980 addenda, article IWA-4400, IWD-5000.
III. Basis for Requesting Relief Hydrostatic testing of welds in Section I-A of this request is impractical for the following reasons.
i A.
Sections of piping containing subject welds cannot be adequately isolated for hydrostatic testing.
Isolation valves are large l
Butterfly valves ranging from 10" to 36" in size with a history of
~
leakage.
B.
Alternate testing specified in section IV.
l IV. Alternate Testing i
NSM MG-1-1887 Rev. 2 All welds on this modification will be subjected to l
an MT or PT examination and an in service leak inspection. These are the welds associated with flanges for valve 1RN137A and 1RN2388.
NSM MG-2-0666 Rev. 2 All welds on this modification will be subjected to I
an MT or PT examination and an inservice leak inspection. These are the
)
welds associated with flanges for valve 2RN137A and 2RN238B.
j NSM MG-1-0351 Rev. O On the bypass lines around the check valves, and at the high point, the final tie-ins to the header will be subjected to an MT or PT examination and an in service leak inspection. The other welds will be hydro tested.
NSM MG-1-1888 Rev. 0: The welds between the supply / discharge header and i
the first isolation valve will be subjected to an PT or ifr examination and an inservice leak inspection. The welds between the isolation valve will be hydro tested.
(
s e
_____._-_.,_l.___,.-_
NSM NG-1-1890 Rev. 0: The welds between the supply / discharge header and the first isolation valve will be subjected to an PT or MT examination and an inservice leak inspection. The welds between the isolation valve will.
be hydro tested.
NSM MG-1-1891 Rev. 0: The welds between the supply / discharge header and the first isolation valve will be subjected to an PT or MT examination and
- an inservice leak inspection. The welds between the isolation valve will' be hydro tested.
NSM MG-1-1886 Rev. 0:.The welds between_the supply / discharge header and the first isolation valve will be subjected to an PT or NT examinat. ion and an inservice leak inspection. The welds between the isolation valve will be hydro tested.
NSM MG-1-1889 Rev. 0: The welds between the supply / discharge header and the first isolation valve will be subjected to an PT or MT examination and an inservice leak inspection. The welds between the isolation valve will be hydro tested.
NSM MG-1-1892 Rev. 0: The welds between the supply / discharge header and the first isolation valve will be subjected to an PT or MT examination and an inservice leak inspection. The welds between the isolation valve will be hydro tested.
NSM MG-2-0667 Rev. 0: The welds between the supply / discharge header'and the first isolation valve will be subjected to an PT or MT examination and an inservice leak inspection. The welds between the isolation valve will be hydro tested.
NSM MG-2-0668 Rev. 0: The welds between the supply / discharge header _and the first isolation valve will be subjected to an PT or MT examination and i
an inservice leak inspection. The welds between the isolation valve will i
be hydro tested.
l NSM MG-2-0669 Rev. 0: The welds between-the supply / discharge header and j
the first isolation valve will be subjected to an PT or NT examination and i
an inservice leak inspection. The welds between the isolation valve will be hydro tested.
NSM MG-2-0670 Rev. 0: The welds between the supply / discharge header and i
the first isolation valve will be subjected to an PT or MT examination and i
an inservice leak inspection. The welds between the isolation valve will I
be hydro tested.
NSM MG-2-0671 Rev. 0: The welds between the supply / discharge header and the first isolation valve will be subjected to an PT or MT examination and i
an inservice leak inspection. The welds between the isolation valve will l
be hydro tested.
NSM MG-2-0672 Rev. 0: The welds between the supply / discharge header and l
the first isolation valve will be subjected to an PT or MT examination and an inservice leak inspection. The welds between the isolation valve will be hydro tested.
V.
Implementation 4
i Refueling outages for 1987 and 1988 Unit 1 87 outage start date - 8/10/87 Unit 2 87 outage start date - 4/15/87 Unit 1 88 outage start date - 12/05/88 Unit 2 88 outage start date - 8/23/88
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