ML20083A209
| ML20083A209 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/15/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8312200212 | |
| Download: ML20083A209 (5) | |
Text
{{#Wiki_filter:. TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374of 400 Chestnut Street Tower II December 15, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
In the Matter of the ) Docket No. 50-259 Tennessee Valley Authority ) Enclosed is a formal request for relief from ASME Section XI Hydrostatic Pressure Test requirements for the Browns Ferry Nuclear Plant unit 1. This request is for relief from performing a hydrostatic pressure test on unit 1 required by the ASME code as a result cf performing through wall replacements on the reactor coolant pressure boundary piping. As explained in more detail in the enclosed request, a pressure test was conducted at nominal operating pressure as a compensatory measure. This request for relief was discussed with your staff by telephone on December 12 and 15, 1983 In those discussions your staff stated that the planned pressure test appeared to be acceptable and that formal granting of relief could be expected. It was confirmed that startup of ur.it 1 could proceed based on performance of the pressure test at nominal operating pressure. Please, forward approval of the enclosed request for relief as soon as possibla. If you have any questions, please get in touch with us through the Browns Ferry Project Manager. Very truly yours, TENNESSEE VALLEY AUTHORITY L. . Mills, M nager Nuclear Licensing Subscribe,d gd sworn to b fore 1983 is Ic - day of me Notary Public 9'5~ t My Commission Expires Enclosure cc: See page 2 8312200212 831215 gDRADOCK 05000259 PDR II An Equal Opportunity Employer
. Mr. Harold R. Denton December 15, 1983 cc (Enclosure): U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgie. 30303 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 i a i l 4
l RELIEF BEQUEST BROWNS FEBRY NUCLEAR PLANT UNIT 1 l f COMPONENTS Browns Ferry Nuclear Plant reactor pressure vessel vent and drain lines are to be capped downstream of valves 10-501 and 10-504, respectively, CLASS Components were originally not given an ASME equivalency. Ilowever, because of leakage (through the valves) discovered during system hydrostatic pressure test, the downstream portion will be classified TVA Safety Class A: ASME Equivalent Class 2. INSPECTION REQUIREMENT Subarticles IWA-4600 and IWA-4400 of the 1980 Edition, Winter 1981 Addenda, ASME Section XI require that a system hydrostatic pressure test be performed for welded replacements greater than NPS 1 penetrating through the pressure boundary. The BFNP pressure test program, in accordance with the 1974 Edition, Summer 1975 Addenda of ASME Section XI, requires a hydrostatic test pressure of 1.25 times the system design pressure. BASIS FOR RELIEF During system hydrostatic pressure testing of unit 1 valves in the head vent (10-500 and 10-501) and reactor vessel drain (10-503 and 10-504) were found to be leaking through. ECN P5036 was issued to cap .the lines downstream of valves 10-501 and 10-504, respectively. The portion downstream of the valves will be considered ASME Class 2 equivalent after the lines are capped. Repair / replacement of the valves is impractical for the reasons listed: A freeze plug would be the only isolation between the vessel and containment if the valves were disassembled for repair / replacement. The valves have a screwed bonnet which is prone to galling and would probably require replacement if an attempt was made to repair the seating surface. A hydrostatic pressure test would still be required if the valves were replaced. The construction code of record NDE to be performed is a surface and visual examination. The RPV head vent and drain lines which are being capped are used for maintenance purposes only and the flow path being s S
capped is designed to be closed during all normal and accident conditions. The lines involved.use primarily socket-welded connections. A hydrostatic pressure test of the capped lines would involve flooding the main steam lines and pressurizing them along with the reactor vessel, recirculation system and a portion of the feedwater system, which TVA feels is unreasonable. The number of hydrostatic pressure tests to be performed on the reactor vessel is limited to avoid affecting the fatigue usage factor. 'TVA proposes to defer the hydrostatic pressure test of the subject lines until the normally scheduled system hydrostatic pressure test of the reactor vessel. The earliest possible date for the system hydrostatic pressure test is during the unit 1, cycle 6 outage scheduled to begin February 1985. ALTERNATE INSPECTION The alternate inspection consists of parforming the construction code NDE (surface and visual exam) after the replacement is made along with a visual examination of the welds affected at nominal operating pressure. (Approximately 1,005 psig and 5000F.) O h i + wby- ~~7 %3_&
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