ML20082R377
| ML20082R377 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/09/1983 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| IEB-83-02, IEB-83-2, LAP-83-566, NUDOCS 8312130144 | |
| Download: ML20082R377 (2) | |
Text
T U
1 CD&L CaroHna Power & Light Company SERIAL: LAP-83-566 DEC 091983 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET No. 50-324 LICENSE NO. DPR-62 REQUEST FOR RELIEF FROM CERTAIN ASME CODE TEST REQUIREMENTS
Dear Mr. Vassallo:
Carolina Power & Light Company (CP&L) has recently completed inspections of certain piping welds at Brunswick Steam Electric Plant Unit No.
2 (Brunswick-2) in accordance with IE Bulletin.83-02 and orders contained in your letter dated August 26, 1983'. The results of that inspection and details of certain repairs conducted on Brunswick-2 are contained in CP&L letters BSEP/83-3748 dated November 28, 1983, LAP-83-549 and LAP-83-554, both dated November 30, 1983 The purpose of this letter is to reque.st relief from the hydrostatic pressure test requirements for two weld repairs which resulted from these 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 of 1978 addenda, for the Unit 2 weld overlay repairs on welds 2-B32-12"-K2 and 2-B32-12"-K3 This relief request is applicable to the weld overlay repairs made on Reactor Recirculation piping system welds 2-B32-12"-K2 and 2-B32-12"-K3 The weld configurations are pipe to elbow, and elbow to pipe, 12" nomimal diameter schedule 80 material with a nominal thickness of 0.631 inches. The welds are located on the B loop on the K-riser at an azimuth of 330.
In lieu of these tests CP&L will perform a visual examination (VT-2) for leakage during the inservice leak-pressure test after pressurization to 0
nominal operating pressure (1005 psig) and temperature (540 F).
8312130144 831209 PDR ADOCK 05000324 G
{O i3 nan
Hr. L. B. Vassallo !
l Justification l
l The Reactor Recirculation System piping cannot be isolated from the l
Reactor Pressure Vessel during a hydrostatic pressure test of the K riser weld overlays. Brunswick Unit 2 has a major refueling outage scheduled in the Spring of 1984 at which time the 10 year interval 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 exam' nation i
already performed on the weld overlay provides adequate assurance of the integrity of the repair for return to commercial service until the spring outage.
The inservice leak test pressure is approximately 20 psi less than the hydrostatic test pressure with the hydro performed at the nominal operating 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 0
operating temperature (540 F) is not feasible due to the inordinate amount of time involved attaining the required test temperature in a nonoperational 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 do not hesitate to contact our Licensing Staff.
Yours very tru y P. W. Howe Vice President Brunswick Nuclear Project JSD/kjr (9037JSD) cc:
Mr. D. O. Myers (NRC-BSEP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC)
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