ML20083D676
| ML20083D676 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/21/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8312280196 | |
| Download: ML20083D676 (7) | |
Text
_
TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 37401 400 Chestnut Street Tower II December 21, 1983 Director of Nuclear Reactor Regulation Attention:
Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commissien Washington, D.C.
20555
Dear Ms. Adensam:
In the Matter of
)
Docket No.
50-327 Tennessee Valley Authority
)
50-328 In accordance with 10 CFR Part 50, enclosed is a request for relief, and a jdstification for the relief, from the hydrostatic test requirements specified in the 1977 Edition, Summer 1978 Addenda of Section XI of the ASME Code. The relief request is being submitted as a result of TVA's plan to install by-pass lines around the 16-inch feedwater check valves 3-508, 3-509, 3-510 and 3-511.
The relief request was discussed with Carl Stahle of your staff in s telephone conversation on December 2, 1983 An expeditious review of this request is needed to support the forthcoming unit 1, cycle 2 refueling outage scheduled for the first quarter of 1984.
If you have any questions concerning this matter, please get in touch with Jerry Wills at FTS B58-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Sworn,t nd subscri ed before me thi of day of 1983 Al Notary Public _
O My Commission Expires /"
Enclosure oc:
U.S. Nuclear Regulatory Commission (Enclosure)
Region II Atta:
Mr. James P. O'Reilly Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 I
8312280196 831221 PDR ADOCK 05000 P
i i
1983-TVA 50m ANNIVERSARY An Equal Oppsrtunity Employer
ENCLOSURE REQUEST FOR RELIEF SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 COMPONENTS Sequoyah Nuclear Plant units 1 and 2 feedwater system. Installation of 2-inch bypass lines around 16-inch feedwater check valves 3-508, 3-509, 3-510, and 3-511 (drawings attached) in accordance with TVA ECN L5024.
CLASS TVA safety Class B, ANSI B31.7; ASME Class 2 equivalent.
INSPECTION REQUIREMENTS The code of record for repairs and replacements at Sequoyah is the 1980 Edition, Winter 1981 Addenda of ASME'Section XI.
This requires a hydrostatic pressure test of the replaced components. The pressure test program is to the 1977 Edition, Summer 1978 Addenda and requires the hydrostatic pressure test be performed at 1.25 times the system pressure Psv.
BASIS FOR RELIEF To accomplish the hydrostatic pressure test would require flooding the secondary side of each steam generator along with the 32-inch main steam lines to the outboard isolation valves. The main steam safety and power-operated relief valves would also require gagging to perform the test. The number of secondary side hydrostatic pressure tests allowed by the plant technical specifications (Section 5.7, Table 5 7 1) is 5 This does not allow for hydrostatic pressure tests other than the normally scheduled ones.
It is our opinion that a significant increase in safety would not result from the hydrostatic pressure test over proposed alternate inspection below.
ALTERNATE INSPECTION In addition to the construction code (B31 7, 1969 Edition, Summer 1970 l
Addenda) surface examination of the welds, an in-service leak check of the subject welds will be performed at operating pressure during startup from the outage in which the replacement is made. The regularly scheduled system hydrostatic pressure test should be performed in 1989-1990.
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