ML20206F255
| ML20206F255 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/07/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-65133, TAC-65134, NUDOCS 8704140196 | |
| Download: ML20206F255 (8) | |
Text
...___
's DUKE POWER GOMPANY P.O. BOX 33180 CHARLOTTE, N.O. 28242 HAL B. TUCKER ret.mposons
'Sj"""g**
(704) 373-4531 April 7, 1987 U. S. Nuclear Regulatory Commaission Attention: Document Control Desk Washington, D. C. 20555
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 ASME Code Section XI Hydrostatic Testing Requirements Exemption Gentlemen:
Please find attached a request for relief, pursuant to 10 CFR 50.55a (g)(5)(iii),
from ASME Code Section XI Hydrostatic Testing Requirements on portions of the Unit 1 and 2 Safety Injection (NI) systems. The exemption has become necessary as a result of modifications being performed on the NI system for which conformance to the code requirement, (ASME B and PV Code,Section II, 1980 Edition, through winter 1980 addenda, IWA-4400, IWB-5000) has been determined to be impractical because it I
would require the entire Reactor Coolant (NC) system to be pressurized.
The NI system modification involves capping four Upper Head Injection (UHI) Reactor Head Penetrations as part of the UHI deletion at McGuire, (reference Facility Operating License Amendment 57/38). The modification is currently scheduled for the 1987 Unit I and 2 refueling outages, (UIEOC4 and U2EOC3).
System flow diagrams are attached for your information showing the affected areas.
Pursuant to 10 CFR 170.3(y), 170.12(c), and 170.21, Duke 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 and must be accompanied by an application fee of $150.00, with the NRC to bill Duke Power at six-month intervals for all other accumulated costs for the application or when the review is completed, whichever is earlier. Accordingly, please find enclosed a check in the amount of $150.00.
Very truly yours, d j' 47
,I Hal B. Tucker r
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k Attachment 8704140196 870407 PDR ADOCK 05000369 p
U..S. Nuc1ccr R gulatcry Comiesian April 7, 1987 Page Two xc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station 4
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U..S. Nucirzr Reguletcry Commistica April 7, 1987 Page Three bxc:
P. M. Abraham R. S. Bhatnager D. R. Bradshaw K. S. Canady J. B. Day R. C. Futrell S. A. Gewehr R. L. Gill C. W. Graves G. W. Hallman C. L. Harlin C. L. Hartzell A. R. Hollins T. L. McConnell E. O. McCraw M. D. McIntosh T. E. Mooney P. B. Nardoci R. P. Ruth N. A. Rutherford A. R. Sipes P. L. Stiles J. E. Thomas G. E. Vaughn R. L. Weber L. L. Williams W QA Tech. Services Manager (EC-1258 j
QA Tech. Services NRC Coordinator (EC-1255)
File: MC-801.02 File: MC-802.05
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REQUEST FOR RELIEF FROM ASME SECTION XI CODE REQUIREMENTS DETERMINED TO BE IMPRACTICAL 1.
Component for which relief is required:
A.
Name of Component Reactor Vessel Head B.
Scope Cap the four Upper Head Injection (UHI) Reactor Head Penetrations.
4 C.
ASME Section III Code Class Equivalent Class 1 D.
Materials and Welds Materials per Area 1.
6" Pipe Cap, XX Strong B/W, SA-403WP Type 304 or 316 2.
UHI Reactor Head Penetration, 6.25" 0.D., SA-403 Type 304 or 316 Welds per area j
All welds to be the groove weld type utilizing 37.5 + 5 bevel made IAW an approved welding program.
2.
ASME CODE SECTION XI REQUIREMENT THAT HAS BEEN DETERMINED TO BE IMPRACTICAL ASME B and PV Code,Section XI, 1980 Edition, through winter 1980 addenda, IWA-4400, IWB-5000.
3.
BASIS FOR REQUESTING RELIEF
)
Inability to achieve the desired pressure and temperature in the reactor coolant system to satisfy code requirements.
i 4
4.
ALTERNATE EXAMINATION A 100% radiographic examination plus 100% PT exam on the completion of all pressure boundry welds. An additional PT examination of all root pass i
welds will be performed.
Additionally during Mode 3 (full pressure and temperature), an inservice leak test will be performed. A Reactor Coolant system hydro test will be performed at the 10 year inspection interval per section XI of the ASME Code. At this time, the cap welds will be subjected to hydrostatic
.i pressure and temperature. A UT examination will be performed on the welds
);
for preservice baseline inspection per ASME Section XI, -following weld t
completion.
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5.
IMPLEMENTATION All additional NDE will be completed prior to the system being declared j
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1.
REF OWGS.(DAP) REACTOR GENERAL ASSEMSLY (C)686J437,(OSP)
REACTOR GENERAL ASSEMBLY (C)686J441.
- 2. MATERIALS. DESIGN, CONSTRUCTION, WELDING & WELD EXAMINATION TO BE PER THE APPLICAELE ASME CODE SECTION XI AND/OR SECTION III SUBSECTION N3 CLASS 1.
- 3. APPLICABLE CESIGN SPEC.95S893.
4.
APPLICABLE INSTALLATION GUIDELINES PER MEO-PCE-2S71.
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CERTIFIED FOR CONSTRUCTION CERTIFICATION LTR.NO. DAP-85-145 DETAIL-A AUTHORITY:
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