ML20100M484
| ML20100M484 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/04/1984 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| GL-84-11, NLS-84-504, NUDOCS 8412120337 | |
| Download: ML20100M484 (2) | |
Text
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.n CD&L p
Carolina Power & Light Company DEC 041984 SERIAL:
Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Comaission Washington, DC 20555 BRUNSWICK, STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NO. 50-325/ LICENSE NO. DPR-71 REQUEST FOR RELIEF FROM CERTAIN ASME CODE TEST REQUIREMENTS
Dear Mr. Vassallo:
Carolina Power & Light Company (CP&L) has recently completed inspection of certain piping welds at Brunswick Steam Electric Plant Unit No. 1 (Brunswick-1) in accordance with Generic Letter 84-11.
The results of that-inspection and details of certain repairs conducted on Brunswick-1 have been provided to you separately. The purpose of this letter is to request, pursuant to 10CFR50.55a(g), relief from the hydrostatic pressure test requirements for one weld repair which resulted from those inspections.
Specific Relief Requested Relief is requested from the hydrostatic pressure test requirements of IWA-4400 and IWA-5000 of Section XI of the ASME Code edition 1977 through the summer.f 1978 addenda. This relief request is applicable to the weld overlay repair made on Reactor Recirculation piping systen weld 1-B32-RECIRC-4"-A10.
The defect was in the weldolet where the 4" bypass line branches from the 23" g-pump discharge line.
In lieu _of this test, CP&L will perform a visual examination (VT-2) for leakage during the inservice leak-pressure test after pressurization to nominal operating pressure (1005 psig) and temperature (540*f).
Justification The Reactor Recirculation System piping cannot be isolated from the Reactor Pressure Vessel during a hydrostatic pressure test of the 1-B32-RECIRC-4"-A10 weld overlay. Brunswick Unit I has a rajor refueling outage scheduled in the spring of 1985 at which time a hydrostatic pressure test will be performed prior to returning the unit to service.
Considering the exposure rates, expense, and short service duration until the spring outage, performance of a hydrostatic pressure test to satisfy Section XI is impractical. The utilization of the inservice leak pressure test coupled with the visual, liquid penetrant, and ultrasonic non-destructive examination already performed on the weld overlay provides adequate assurance of the integrity of the repair for return to commercial service until the spring outage.
8412120337 841204 PDR ADOCK 05000325 0
, Street
- P. O. Box 1551
- Raleigh, N. C. 27602
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a Mr. D. B. Vassallo The inservice leak test pressure is approximately 20 psi less than the hydrostatic test pressure with the hydro performed at the nominal cperating temperature (see Table IWB-5220-1):
1.02 Po = 1025.1 psi Po = 1005 20.1 psi The performance of the hydrostatic pressure test at nominal operating temperature (540*f) is not feasible due to the inordinate amount of time involved attaining the required test temperature in a non-operational status, and~the cooldown time after hydro to prepare the unit for operational status before return to service. The performance of the hydrostatic test at lower temperature would also be time consuming, would involve considerable unnecessary exposure to personnel (for equipment installation and removal),
and would be an unnecessary cycle of the pressure vessel when compared to the minimal additional safety margins it might provide with respect to the integrity of the weld overlays.
Should you have any questions regarding this request, please contact Mr. S. R. Zimmerman at (919) 836-6242.
Yours very truly, A - ~ e -- =
hhisA.B.
ter - Vice President Nuclear Engineering & Licensing MAT /pgp (916 MAT)
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cc:
Mr. D. O. Myers (NRC-BNP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC)
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