ML20212P585
| ML20212P585 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/27/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| TAC-62269, TAC-62270, NUDOCS 8609030198 | |
| Download: ML20212P585 (10) | |
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6 DuxE POWER GOMPANY P.O. box 33189 4
CHARLOTTE, N.C. 28949 HAL B. TUCKER Tatzenown Nos Paessmen?
(704) 373-4838 NUCLEAR PenstFT104 4
August 27, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Consission Washin8 ton, D.C.
20555 ATTENTI0tt:
B.J.' Youngblood, Director PWR Project Directorate #4
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 ASME Code Section XI Hydrostatic Testing Requirements Exemption
Dear Mr. Denton:
l Please find attached a request for relief (pursuant to 10CFR 50.55a(g)(5)(iii))
from ASME Code Section XI Hydrostatic Testing Requirements on portions of the Units 1 and 2 Safety Injection (NI) Systems. This exemption is necessitated as a result of modifications being performed on the NI' System for which conformance with certain cude requirements has been determined to be impractical.
These NI System modifications involve replacing the discharge check valves for the cold leg accumulators. These valves also serve as a path for return flow to the Reactor Coolant (NC) System from the Decay Heat Removal (ND) System during a shutdown mode. A total of sixteen valves will be replaced due to excessive seal and hinge pin wear. The reasons for these a:odifications are further discussed in i
Licensee Event Report (LER) 369/85-11.
System flow diagrams MC-1553-1.0, i
MC-1562-2.0, and MC-1562-2.1 are also attached showing the affected Unit I areas (Unit 2 is similar to Unit 1). Note that an exemption from hydrostatic testing has previously been granted for this same portion of the NI, System (reference Mr.
T.M. Novak's (NRC/0NRR) letter to Mr. H.B. Tucker (DPC) dated December 29, 1982.
Pursuant to 100FR 170.3(y), 170.12(c), and 170.21, Duke Power proposes that this exemption request constitutes a required approval for McGuire Units 1 and 2 subject to fees based on the full cost of the review (to be calculated using the applicable professional staff rates shown in 10CRR 170.20) and must be accompanied by an application fee of $150, with the NRC to bill Duka Power at six-month intervals for all accumulated costs for the application or when review is com-3 i
plated, whichever is earlier. Accordingly, please find enclosed a check in the amount of $150.00.
3O nrSnatanHe.
k P
Harold R. Denton August 27, 1986 Page 2 Replacement of four of the check valves is presently being performed during the current Unit 1 end of cycle (EOC) 3 refueling outage (which is scheduled to end September 2,1986), with the remaining valves to be replaced during the next re-fueling outages (Unit 1 EOC-4, Unit 2 EOC-3) on each unit. Because of the dif-ficulties in performing a Hydrostatic test on these portions of the systems, and the return of the systems to operation in a timely schedule, it is requested that these reliefs receive immediate attention. The alternate examinations specified in this relief request are equal to or better than the required testing per the code. Should there be any questions concerning this matter or if additional information is required, please advise.
Very truly yours, is Hal B. Tucker PBN/25/j gm Attachments xc:
Dr. J. Nelson Grace Regional Administrator U.S. Nuclear Regulatory Commission 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 Senior Resident Inspector McGuire Nuclear Station 1
DUKE POWER COMPANY MCGUIRE NUCLEAR STATION REQUEST FOR RELIEF FROM CODE SECTION XI REQUIREMENT 1)ETERMINED TO BE IMPRACTICA 1.
Component For Which Relief is Reauired:
A.
Name and Numbers Replacement of the Unit 1 & 2 Safety Injection System (NI) Primary and Secondary check valves to the Reactor Coolant System (Reference Fig. 1 & 2)
B.
Function The NI system provides emergency core cooling to the Reactor Vessel.
This particular portion of the system also provides a flow path for removal of decay heat in the shutdown condition, and is the primary flow path for the cold les accumulators.
C.
ASME SECTION III CODE CLASS Equivalent Class 1 D.
VALVE CATEGORY 1
Valves designed and fabricated IAW ASME B&PV code Section III -
Class 1, 1983 Edition - Winter 1984 Addenda.
2.
Valve rated IAW ANSI B16.34-1981 1515 # special class-interpolated.
E.
MATERIALS AND WELDS Materials Per Area 10" x 10" x 6" Reducing tee, schedule 140 x 160 (1.00" x.718")
1.
SA-403 WP316 (P No. 8 Group 1) 2.
10" 90' Elbow, Sch. 140, (1.00") SA-403 WP316 SMLS BW (P NO. 8 Group 1) 3.
10" Pipe, Sch 140, (1.00") SA 376 TP 316 (P No. 8 Group 1) 4.
Valves, SA351 Grade CF8M (P No. 8 Group 1) (Reference Fig. 1 &
2).
l Welds Per Area All welds to be the open root groove type utilizin:: a 37.5't5' bevel made IAW an approved welding program. Root op2nings (1/8"I 1/32") to be filled by gas tungsten are welded, minimum of two passes finished up by shielded metal are welding.
i
i l
l 2.
ASME Code Section XI Requirement That Has Been Determined To Be Imoractical ASME B and PV Code,Section XI, 1980 Edition, through Winter 1980 Addenda, IWA - 4400, IMI - 5000.
3.
Basis For Recuestina Relief There are no isolation valves downstream of these primary and secondary check valves to the NC system, therefore it is impossible to isolate these portions of systems. However, there are several approaches to partially pressurising the system.
The first approach would be to pressurize the (NC) Reactor Coolant System to 2235 pounds, and then use the (NI) Safety Injection pumps to pressurize the NI Systems against one of the check valves. However, this pump pressure is only 1600 pounds, which falls far short of the required test pressure.
The second approach would be to remove the internals from the primary check valves, which go to the NC System, and then pressurise.the NC System to 1.02 of 2236 pounds 9 500* temperature. However,'this method would still not achieve the desired test pressure per the code, because this would be a dead les pipe with no flow, and the convective and
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conductive effect of heat transfer possibly would not reach ths 500*
temperature minimum, as this portion of the system is uninsulated. This would also require draining the system in order to replace the internals into the check valve, a very timely and very costly procedure.
Therefore, due to orientation of the valves within the system, it is not possible to hydrostatically test the system. However, the alternate examinations as specified in Item 4 are equal to or better than the required testing per the code.
4.
Alternate Examination A 100% radiographic examination plus 100% PT exam on the completion of all pressure boundary welds. An additional PT examination of all root pass welds will also be performed.
Also, a hydro test will be performed at the 10-year inspection interval l
per Section XI of the ASME Code. An inservice leak test cannot be performed on this system because if the check valves hold, the system i
will not see system pressure. In addition a UT examination will be performed on the welds for Preservice Baseline Inspection per ASME Section XI.
5.
Imolementation These examinations, with the exception of the hydrostatic test, will be carried out after the modification on the (NI) Safety Injection System is complete, and prior to the system being declared operable.
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