ML18116A225
| ML18116A225 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 07/27/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| 493A-492A, NUDOCS 7907310255 | |
| Download: ML18116A225 (3) | |
Text
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA 23261 Mr. Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Stello:
Serial Nos. 493A/492A PO/FHT:scj Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 CPPR-78 Surry Power Station Unit Nos. 1 and 2 and North Anna Power Station Unit Nos. 1 and 2 Supplemental Information on PWR Feedwater Lines By this letter we are providing the attached additional information on feedwater piping for North Anna Power Station Unit Nos. 1 and 2 to supplement our earlier letter dated June 20, 1979, Serial No. 493, in response to your request for information dated May 25, 1979.
Note that information requested in item C.3.
is not available at this time.
It is expected to be available by August 31, 1979.
Results of the feedwater piping inspections performed at Surry Power Station Unit Nos. 1 and 2 and North Anna Unit Nos. 1 and 2 will be forwarded in accord-ance with the requirements of IE Bulletin 79-13, Cracking in Feedwater System Piping, dated June 25, 1979.
Vice and Very truly yours, C. M. Stallings President-Power Supply Production Operations
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Supplemental Response to NRC Letter of May 25, 1979 Requesting Information on PWR Feedwater Lines A.
Design
- 1.
Information supplied earlier with exception of steam generator feedwater ring.
Drawing of assembly enclosed.
- 2.
Information supplied e~rlier.
B.
Fabrication History
- 1.
Information supplied earlier with exception of steam generator feedwater ring.
Westinghouse information enclosed.
- 2.
Same as item A 1.
- 3.
Piping & nozzle welds to piping:
- a.
Magnetic particle inspection after root pass and then after 25, 50, 75, and 100% of weld metal deposited.
- b.
After welding and post weld heat treatment:
Radiography and *nydro~
Results of on-site welding are available on site for inspection.
Westinghouse has the data for welding done during fabrication of steam generator.
4/.~ Piping system fabricated under ANSI code B31. 7, 1969 edition, with addenda
. through 1970.
- 5.
Fracture toughness not addressed in ANSI B31.7 ~ For NAS (Stone and Webster) specification on class 601 piping.*
C.
Preservice/Inservice Inspection and Operating History
- 1.
Welds received preservice inspection as per ASME B & PV Code, section XI, as modified in FSAR section 5.2.5.
- 2.
First inservice inspection not performed as of this date~
- 3.
Information unavailable at this time.
Will provide by August 31, 1979.
- 4.
At the present time, there has been no history of vibration or water hammer in the feedwater system.
A preoperational test {l-P0-79) was performed during hot functionals to demonstrate that a water hammer will not occur.
Since the Unit 2 system is essentially the same, the test.results apply to Unit 2 also.
- 5.
A description of feedwater chemistry controls was submitted with our letter serial no. 492, dated June 20, 1979, Surry Power Station Unit Nos. 1 and 2, Information on PWR Feedwater Lines.
This information is applicable to North Anna as well.
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