ML18136A350
| ML18136A350 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/17/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-79-13, NUDOCS 8001030879 | |
| Download: ML18136A350 (3) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 17, 1979
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Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region II.
Serial No. 865A/101779A:
101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
PO/FHT:scj Docket No. 50-281 License No. DPR-37
Subject:
IE Bulletin 79-13 Revision 2 r,*
Surry Power Station Unit 2 Inspection Results In response to the subject bulletin, "Cracking in Feedwater System Piping",
, Virginia Electric and Power Company herewith forwards the attached Report of Feedwater System Piping Inspections, Surry Power Station Unit 2.
If you have any questions or require additional information, please contact this office.
Very truly yours,
/ ! / /-: i I
Lt u. l *. (ji't,.1£{ ly C. M. Stallings Vice President-Power Supply and Production Operations cc:
Director, Office of Inspection and Enforcement Division of Reactor Operations Inspection U. S. Nuclear Regulatory Commission Washington, D. C.
20555 0 8001 030
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e e Attachment m Bulletin 79-13, Pavision 2_
REPORI' OF FEECWATER SYS'IE1 PIPING IlJSPECl'IONS SURRY PO-vER STATION, UNIT NO. 2 In accordance with m Bulletin 79-13, "Cracking in Fee&ater System Piping", all feedwater nozzle-to-pipe areas and all feedwater pipe weld areas inside containnent ha.ve been inspected on Sun:y Unit No. 2. Results of"the inspection ai-e as follCMs:
Steam C':enerator "A":
Circur.:tferential crack indications were discovered in the base netal of the counteroore region an the reducer-side of the redurer-to-nozzle weld.
No crack indications were noted in.the other sixteen welds inspected in the "A" Stearn C'£nerator Feedr,ater piping. One weld was rejected as follows:
W#7 -
Small area of rejectable porosity.
(Reported to' NOC 8/23/79)
Steam Generator "B" :
Cireur:tferential crack indications were discoverea in the base :rretal of the cx:mnteroore region of the reducer side of the, red~r-to-nozzle weld.
No rejectable indications of any-type were discovered in the other fifteen welds i.nsrected in the "B"- Steara Generator Feedwater piping.
Steam (",ene_rator "C":
Incorplete fusion along with. areas of. porosity and slag were*discovered iri the reducer-to-nozzle weld. Weld was rejected. Linear indications were discovered in the root of the redu:er-to-pipe weld. _ i*eld was rejected.
No rejectable indications of arrx ~
were discovered in the other fourteen. ~lds ihsf.EC"ted in the Stearn Generator Feedwater piping.
It must be noted that several welds an the feedater lines (three per line) were replaced as part of the Steam Generator Repl.acer:ent Project. Since these \\rel.ds uere replaced prior to the IE Bulletin 79-13 irnplerrentation on Unit 2, NDE iJ1forr.iation on the original \\Telds \\las unobtainable.
'Ihe 3 nEM welds per feedwater line were radiogra:rned to the SGRP construction -code in force and not to the requirer:ents of m Bulletin 79-13.
Amd..liai:y FeeclY,ater Connections:.
'Ihe 3 in. amd..liary feedwater-tie-in comections on all three nain feedwater lines were I!Bgnetic particle inspected. The main feed lines were radiographed one r>ipe diar:eter.inr.ediately downstrear.i,o"!: the auxilia:i:y tie-ins. The results of these inspections were acceptable.
Visual inspection of all-feedwatersyster:, piping sug:orts and snubbers in containrrent has been conpleted to verify operability and conformance to design. Uo discrepancies were noted.
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Attachment (can't) 2 -
IE BULLErrn 79-13 RESPCNSE: (CDNT'D.)
Corrective actions for the iterrs noted above included replac::er.Eilt of all -three SteaEl Generator Feed reducers and ueld rep:i.ir to Wt7, "A" SG.
No further corrective actions are neces,sary.