ML20076E297
| ML20076E297 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/15/1991 |
| From: | Floyd S CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-91-198, NUDOCS 9108190220 | |
| Download: ML20076E297 (4) | |
Text
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Carollne Power & Light Company l
AUG 151991 i
i SERIAL: NLS 91 198 10 CfR 50.55a(g)
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L United States Nuclear Regulatory Commission i
ATTENTION: Document Control Desk l
Washington, DC 20555
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URUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 i
DOCKET NO,50 324/ LICENSE NO. DPR 62 ASME CODE RELIEF REOUEST INSERVICE INSPECTION PROGRAM i
MAIN STEAM RELIEF VALVE PRESSURE TEST l
Gentlemen:
In accordance with 10 CFR 50.55a(g)(G)(1), Carolina Power & Light Company (CP&L) hereby f
ter,uesta relief from the ASME Code,Section XI. A plant modification to replace the existing main feedWater containment isolation check valves is being performed to correct the continuing local j
leak rate test failures being experienced with the valves. To support the modification, a portion of
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the dischange piping for the F013H main steam safety /rehef valve is being temporarily removed and t
subsequently re installed. The ASME Code,Section XI, Subparagraph IWD 5223(f) requires a pneumatic test (at a pressure of 90 percent of the pipe submergence head of water) for relici valve piping that discharges into the containment suppression pool The requested relief applies to the j
main steam relief valve discharge piping that runs between safety / relief valve F013H and the containment suppression pool, The detailed relief request is provided in Enclosure 1. Approval of this relief request is needed by October 1,1991 in support the Brunswick Unit 2 refueling outage scheduled to begin September 12,1991.
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i Please refer any questions regarding this submittal to Mr. W. R. Murray at (919) 546-4661, Yours very truly, l
t S, D Flo)
- i Manager i
a Nuclear Licensing Section i
WRM/wrm (relief.wpf)
Enclosure l
i cc:
Mr. S. D. Ebneter Mr, N. B. Le Mr. R. L. Prevatte
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BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50 325 & 50 324 OPERAllNG LICENSE NOS. DPR 71 & DPR 02 ASME CODE RELIEF REQUEST INSERVICE INSPECTION PROGRAM MAIN STEAM REllEF VALVE PRESSURE TEST h
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APPLICABLE COMPO.tiENIS i
This relief request applies to the main stearn rel;ef valvo discharge piping that runs betwoon safety / relief valve F013H and the containment suppression pool, A portion of the piping between safety /rolief valve F013H and the containment suppression poolis being removed 5
and subsequently re installed as part of a plant modification replacing the existing feedwater check valves.
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11.
IMPRACTICAL..IESIJEOUIREMENT The Technical Specifications for the Brunswick Stoa n Electric Plant, Unit 2 state that inservice inspection of ASME Codo Class 1,2, and 3 components shall be performed in l
accordance with the requirements of the applicable edition and addenda of the ASME Code, l
Section XI except where specific written relief has been uranted by the Commission i
pursuant to 10 CFR 50.55alg)(G)(l). The Section XI Code edition and addenda applicablo to the Brunswick Steam E!nctric Plant, Unit 2 are the 1980 Edition with Addenda through the Winter 1981.
The ASME Code,Section XI, IWA 4000 providos requirements fur repairs to pressure retaining components. IWA 4400(a) requires the performance of a system hydrostatic test in accordance with IWA 5000 following welding repairs. IWA 5214(a) and IWA 5214(b) require the pressure test requirernents comply with IWD 5223 for Class 3 components.
t IWD 5223(f) requires a pneumatic test (at a presnure of 90 percent of the pipe submergence head of water) for safety or relief valve piping which discharges into the containment pressuro suppression poolin lieu of a system hydrostatic test.
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BASIS FOR REllEF A plant modification to replace the existing main feedwater containment isolation check l
valves is being performed to correct the continuing localleak rate test failu es being i
experienced with the valves. To support the modification, a portion of the discharge piping for the F013H main steam safety / relief valve is being temporarily removed and subsequently re installed, as shown in the attached isometric drawing from the plant modification package. The affecteo discharge piping is located in the drywell portion of the l
As described above, subparagraph IWD-5223(f) of the ASME Code,Section XI requires a l
pneumatic test at a pressure of 90 percent of the pipe submergente head of water (i.e.,
2.8 psili The centerline of the tee quenchor for the relief valvo discharge piping is 7.25 feet below the high water level in the containment suppression pool. Therefore, the i
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s test pressura corresponding to 90 percent of the pipe submergence head of water, as required by the ASME Code,Section XI, Subparagraph IWD 5223(f), is 2.8 psi.
Implementation of the modification is currently being scheduled af ter performance of a chemical decontamination of the recirculation system piping. Nevertheless, approximately 0.3 man tem of personnel radiation exposure savings can be realized by not performing the pneumatic test in accordance with IWD-5223(fb Performance of the pneumatic pressure test will require disassembly of the F013H safety / relief valve in order to pressurize the piping to the 2.8 osi test pressure and perform the examination. The design presrure and temperature for the piping is 450 psig and 500 degrees F. The test pressure required by IWD 5223(f) (i.e.,2.8 psi)is significantly lower than the design pressure of the piping and the operating pressure typically
- experienced by the piping; therefore, the Company does not believe the IWD 5223(f) test provides assurance of the integrity of the piping commensurate with the personnel exposure associated with performance of the test. Based on the estimated personnel radiation exposure to perform this test, as well as the potential for inadvertently damaging the F013H safety /telief valve, the Company believes the test requirement is impractical and requests relief in accordance with 10 CFR 50.55a(g).
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ALT.fMATE TESTING The field welds will be examined to the most stringent optional requirement of the ASME Code, Section Ill, Class 3 (i.e., using RT examination). Based on the alternate testing, it is highly improbable that a weld that passes a volumetric examination willleak at a test pressure of 2.8 psi (a test pressure of 90 percent of the pipe submergence head of waterb E12
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