ML20236H529

Safety Evaluation Granting Util 870407 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys

ML20236H529
Person / Time
Site:	Mcguire, McGuire
Issue date:	07/31/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236H528	List: ML20236H526 ML20236H529
References
NUDOCS 8708050236
Download: ML20236H529 (4)

Text

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DCLOSURE SAFETY EVALUATION BY'THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM ACHIEVING HYDROSTATIC TEST PRESSURE REQUIREMENT FOLLOWING CAPPING THE UPPER HEAD INJECTION REACTOR HEAD PENETRATIONS DUKE POWER COMPANY McGUIRE NUCLEAR STATION UNITS I and 2 DOCKET NOS. 50-369 & 50-370

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I. BACKGROUND INFORMATION By letter dated April 7, 19'87, Duke Power Company (the licensee) submitted a request for relief and supporting information concerning the hydrostatic test requirements of the 1980 Edition through Winter.1980 Addenda of Section

. XI of the ASME Code to be performed after a modification of the Upper Head Injection (UHI) System at ricGuire Nuclear Station Units 1 and 2. The modifi-cation entailed deletion of the UHI System and capping the reactor head pene-trations. As part of the modification requirements, the licensee is required to perform a hydrostatic test of the capped penetrations, which was determined-to be impractical to perform at the Code test pressure. This report provides an evaluation of the information submitted and the staff's bases for grantina ~ i therequestpursuantto10CFR50.55a(g)(6)(1).

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II. INFORMATION RELATED TO THE RELIEF REQUEST

1. Component for which relief is reouired:

A. Name of Component Reactor Vessel Head ,

B. Scope  ;

CapthefourUpperHeadInjection(UHI)ReactorHeadPenetrations. '

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 All welds to be the groove weld type utilizino 37.5 + 5* bevel made in accordance with an approved welding program. ~

2. ASME CODE SECTION XI REQUIREMENT THAT HAS BEEN l DETERMINED TO BE IMPRACTICAL A5ME B and PV Code,Section XI,1980 Edition, through Winter 1980 Addenda, IWA-4400, IWB-5000. .

870B050236 870731 PDR ADOCK 05000369 P PDR

3. LICENSEE'S BASIS FOR REOUESTING RELIEF j l

y The licensee stated the following as the reason for requesting relief: 1 Inability to achieve the desired pressure and . temperature in. l the reactor coolant system to satisfy Code requirements.

I 4 LICENSEE'S PROPOSED ALTERNATE EXAMINATION 1 The licensee proposed the following alternatives

• A 100% radiographic examination plus 100% PT exam on the o completion of all pressure boundary welds. An additional PT examination of all. root pass welds will be performed.

Additionally during Mode 3 (full pressure and temperature), I an inservice leak test will be performed. A Reactor Coolant i system hydro test will be performed at the 10 year inspection  !

interval per Section XI of the ASME Code. At this time, the i cap welds will be subjected to hydrostatic pressure and tempera- l ture. A UT examination will be performed on the welds for pre-  !

service baseline inspection per ASME Section XI, following weld completion.

5. LICENSEE'S PROPOSED IMPLEMENTATION All additional NDE will be completed prior to the system being declared operable.

III. STAFF EVALUATION l

(he required test pressure for the capped UHI penetrations ranges from 2295 I psig to 2500 psig, depending on the test temperature. . At 500*F or higher temperature, the test pressure required is 2295 psig and at 100"F or less, the test pressure required is 2500 psig. It is impractical to perform the visual examination at the lower pressure / higher temperature condition because of the temperature and radiation levels that would be encountered by examina-tion personnel. The lower temperature / higher pressure condition cannot be im- i posed because of possible fuel damage and the use of a pressure cycle not ac-counted for in the total number of design pressure cycles , allowed during the i plant life. The UHI modification does not alter the original design parameters l or create an impractical situation that did not exist prior to the modification.

The staff has reviewed the modification and the nondestructive examinations to which the welds and base material will be subjected. The welds' design, surface examinations of the root passes and completed welds, ultrasonic and radiographic examinations of the welds and base materials with acceptable-results will provide as.Jrance that the capped penetrations will maintain the structural integrity of the reactor coolant pressure boundary. In addition to the design and nondestructive examinations, the licensee has proposed performing a leakage test of the capped penetrations during MODE 3 of plant operation at which the welds will be subjected to operating temperature and pressure, j

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The staff finds that the combination of weld design, nondestructive examinations, l and leakage test of the capped penetrations provides sufficient justification for not imposing the Code required hydrostatic test;_ that.the measures being exercised by the licensee to assure the ~ structural integrity of capped penetra-tions constitute an acceptable alternative that does not significantly decrease the gain in safety provided by the Code. required hydrostatic test. We therefore conclude that relief from the hydrostatic-test requirements of the 1980 Edition through Winter 1980 Addenda may be granted as requested.

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i Mr..H. B. Tucker l Duke Power Company McGuire Nuclear Station cc:

Mr. A.V. Carr, Esq. Dr, John M. Barry .

Duke Power Company Department of Environmental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, North Carolina 28202 Chairman, North Carolina Utilities Commission Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street Nuclear Production Department Raleigh, North Carolina 27602 P. O. Box 33169 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief Radiation Protection Branch J. Michael McGarry, III, Esq. Division of Facility Services Bishop. Liberman, Cook, Purcell Department of Human Resources and Reynolds 701 Barbour Drive 1200 Seventeenth Street, N.W. Raleigh, North Carolina 27603-2008 l Washington, D. C. 20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Comission Route 4, Box 529

. Hunterville, t? .th Carolina 28078 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 .

L. L. Williams Area Manager, Mid-South Area ESSD Projects Westinghouse Electric Corporation MNC West Tower - Bay 239 P. O. Box 355 Pittsburgh, Pennsylvania 15230 J

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