ML20150C581: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 3
| page count = 3
| project =  
| project = TAC:67032
| stage = Approval
| stage = Approval
}}
}}
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==SUBJECT:==
==SUBJECT:==
RELIEF FROM ASME CODE TEST REQUIREMENT FOR THE NUCLEAR SERVICE WATER SYSTEM, MCGUIRE NUCLEAR STATION, UNIT 1 (TAC 67032)
RELIEF FROM ASME CODE TEST REQUIREMENT FOR THE NUCLEAR SERVICE WATER SYSTEM, MCGUIRE NUCLEAR STATION, UNIT 1 (TAC 67032)
By letter dated January 28, 1988, you submitted Relief Request No. CA-01 which requested relief from the ASME Boiler and Pressure Vessel Code recuirement for hydrostatic testing of repair welds RN1F 841A, RN 507-? and IPN-EXP4B-1 in the N"clear Service Water System at the McGuire Nuclear Station, Unit 1. You had
By {{letter dated|date=January 28, 1988|text=letter dated January 28, 1988}}, you submitted Relief Request No. CA-01 which requested relief from the ASME Boiler and Pressure Vessel Code recuirement for hydrostatic testing of repair welds RN1F 841A, RN 507-? and IPN-EXP4B-1 in the N"clear Service Water System at the McGuire Nuclear Station, Unit 1. You had
             . ermined that the test reauirement of Section XI, 1980 Edition, Winter 1980 A,denda, Articles IWA-4000 and IWD-5000, was impractical to perform because the piping containing these welds could not be isolated for pressurization. The pump capacity to pressurize the piping is insufficient to offset the leakage through the butterfly valve used to isolate the welded section. The Nuclear Service Water. System is a 24-in. diameter plain carbon steel line designed to operate at 35 osig pressure and 95*F temperature.
             . ermined that the test reauirement of Section XI, 1980 Edition, Winter 1980 A,denda, Articles IWA-4000 and IWD-5000, was impractical to perform because the piping containing these welds could not be isolated for pressurization. The pump capacity to pressurize the piping is insufficient to offset the leakage through the butterfly valve used to isolate the welded section. The Nuclear Service Water. System is a 24-in. diameter plain carbon steel line designed to operate at 35 osig pressure and 95*F temperature.
The integrity of the weld repair is assured by performing either a dye penetrant or magnetic particle inspection of both the root and final weld passes. In addition, a radiographic examination is made on the repair weld irvolving the base metal. An inservice leak test at system pressure and temperature is performed wnen the system is placed in service to detect weld defects and through wall leakage.
The integrity of the weld repair is assured by performing either a dye penetrant or magnetic particle inspection of both the root and final weld passes. In addition, a radiographic examination is made on the repair weld irvolving the base metal. An inservice leak test at system pressure and temperature is performed wnen the system is placed in service to detect weld defects and through wall leakage.

Latest revision as of 08:33, 11 December 2021

Advises That Relief from ASME Code Hydrostatic Test Requirement for Repair Welds Granted,In Response to 880128 Relief Request 88-01.Requirement Impractical to Perform
ML20150C581
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 03/14/1988
From: Hood D
Office of Nuclear Reactor Regulation
To: Tucker H
DUKE POWER CO.
References
TAC-67032, NUDOCS 8803210100
Download: ML20150C581 (3)


Text

't .

' f#'%, UNITED STATES 3" ~*1 NUCLEAR REGULATORY COMMISSION j j

  • WASHING TON, D. C, 20655 e

,, March 14, 1988 Docket No. 50-369 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 4EP South Church Street Charlotte, Forth Carolina 28242

Dear Mr. Tucker:

SUBJECT:

RELIEF FROM ASME CODE TEST REQUIREMENT FOR THE NUCLEAR SERVICE WATER SYSTEM, MCGUIRE NUCLEAR STATION, UNIT 1 (TAC 67032)

By letter dated January 28, 1988, you submitted Relief Request No. CA-01 which requested relief from the ASME Boiler and Pressure Vessel Code recuirement for hydrostatic testing of repair welds RN1F 841A, RN 507-? and IPN-EXP4B-1 in the N"clear Service Water System at the McGuire Nuclear Station, Unit 1. You had

. ermined that the test reauirement of Section XI, 1980 Edition, Winter 1980 A,denda, Articles IWA-4000 and IWD-5000, was impractical to perform because the piping containing these welds could not be isolated for pressurization. The pump capacity to pressurize the piping is insufficient to offset the leakage through the butterfly valve used to isolate the welded section. The Nuclear Service Water. System is a 24-in. diameter plain carbon steel line designed to operate at 35 osig pressure and 95*F temperature.

The integrity of the weld repair is assured by performing either a dye penetrant or magnetic particle inspection of both the root and final weld passes. In addition, a radiographic examination is made on the repair weld irvolving the base metal. An inservice leak test at system pressure and temperature is performed wnen the system is placed in service to detect weld defects and through wall leakage.

The staff has evaluated Relief Request No. 88-01. We conclude that the ASME Code requirement is impractical to perforn at the McGuire Nuclear Station, Unit 1, and that the alternative tests provide an acceptable level of structural integrity for the Nuclear Service Water Systen. Compliance with tne specific ASME Code requirement would result in hardship without a compensating increase in the level of quality and safety.

8803210100 880314 PDR ADOCK 05000369 P PDR

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i Mr. H. B. Tucker Accot dingly, reliaf from the hydrostatic test reonirement is granted for McGuire Unit 1 as reouested, pursuant to 10 CFR 50.55a(g)(6)(i). This relief is authorized by law and will not endanger life or property or the common defence and security and is otherwise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

Sincerely, Original signed by:

Darl Hood, Acting Director Project Directorate II-3 Division of Reactor Projects-I/II cc:

See next page DISTRIBUTION:

Docket File NRC PDR' Local POR PDII-3 Reading S. Varga G. Lainas P. Rood D. Food OGC F. Miraglis l E. Jordan i J. Partlow l ACRS (10)

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Y Mr. H. B. Tucker Duke Power Company McGuire Nuclear Station ec:

Mr. A.V. Carr, Esq. Dr. John M. Barry Duke Power Company Department of Environmental Pealth P. O. Box 33189 Mecklenburg County 422 South Church Stree'. 1200 Rlythe Boulevard Charlotte, North Caro'aina 28242 Charlotte, North Carolina PPP03 County Manager of Mecklenburg County Mr. Oayne H. Brown, Chief 720 East Fourth Screet Radiation Protection Branch Charlotte, Nortt Carolina 26202 Division of Facility Services Department of Human Resources 701 Barbour Drive Mr. Robert Fill Paleigh, North Carolina 27603-7008 Duke Power Company Nuclear P'coduction Department P. O. Box 33189 Charlotce, North Carolina 28?42 J. M'.chael McGarry, III, Esq.

Bishop, Libernan, Cook, Purcell ard Reynolds

?.200 Seventeenth Street, N.W.

Washington, D. C. 20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Comission Route 4, Box 5?9 Hunterville, North Carolina 78078 Regional Administrator, Degion II U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 7900 Atlanta, Georgia 30323 S. S. Kilborn Area Manager, Mid-South Area ESSD Proiects Westinghouse Electric Corporation MNC West Tower - Bay 239 P. O. Box 355 Pittsburgh, Pennsylvania 15730

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