ML18136A307
| ML18136A307 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 12/17/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| IEB-79-13, NUDOCS 7912200378 | |
| Download: ML18136A307 (4) | |
Text
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V:u~GlNIA ELECTR.rc AND PowER CoMPANY RICHMOND,VIHGINIA 23261 December 17, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Albert Schwencer, Chief Operating Reactors Branch 1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
Serial No. 49 2D PO/FHT:scj Docket Nos. 50-281 50-338 License Nos. DPR-37 NPF-4
Subject:
Feedwater System Piping Inspections Surry Power Station Unit 2 North Anna Power Station Unit 1 In response to your earlier request and consistent with previous correspondence (Serial No. 492C dated August 31, 1979, Docket No. 50-280 and Serial No. 711A dated September 18, 1979, Docket No. 50-339) we are forwarding the results of the recently completed Feedwater System Piping Inspections for Surry Unit 2 and North Anna Unit 1.
These inspections were performed as requested by IE Bulle-tin 79-13.
The Inspection Reports for Surry Unit 2 and North Anna Unit 1 are enclosed as Attachments 1 and 2, respectively.
If you have any questions or require additional information, please contact this office.
cc:
Mr. James P. O'Reilly Very truly yours,
- 67. );J,?, 0f
,t? t' L, ~---p C. M. Stallings Vice President-Power Supply and Production Operations AooJ 5
1/1
IE Bulletin 79-13, Revision~
REFDRI' OF FEEIJiJATER SYS'IEM PIPING IlJSPECTION.S SURRY ro-IBR STATION, UNIT' NO. 2
- Attachment 1 In accordance with IE Bullet.m 79-13, "Cracking in Feemater System Piping", all feecwater nozzle-to-pi:i;:e areas and all feedwater pipe weld areas inside containrrent h.1.ve been inspected on Sun:y Unit No. 2. results of"the inspection are as follavs:
Steam Generator "A":
- Circur.:iferential crack.mdications were discovered in the base rretal of the counterlx>re region on the reducer side of the reducer-to-nozzle weld.
No crack indications were noted in the other sixteen welds inspected in the "A" Steam C-,enerator Feed-,ater piping..
One weld was rejected as.follows:*
Wi7 - Small area of rejectable porosity.
(Reported to :tOC 8/23/79)
Steam Generator "B":
Circu:rferential crack indications were discovered, in the base metal of the a:::>unterb:>re region of the redu:=er side of the reducer-to-nozzle weld.
No reject.able indications of-any type were discovered in the other fifteen welds insp:2-'"2d in the "B" Steara Generator Feedwater piping...
Steam Generator "C".:
Incor.plete fusion along with areas of porosity and slag were discovered in the reducer-tcr-nozile weld. Weld was rejected. Linear indications were discovered in the root of t.l-i.e rooi.:cer-to-pipe welde i*leld was rejectede I'b rejectable indications of arr.1 type were discovered in the other fourteen welds ihsr,ected in the s~ Generator Feeo-,ater piping.
0 It must be noted that several welds on the feedwa:ter lines ( three per line} wa.re replaced as part of the Steam Generator ReplacerEnt Projecto Since these,ields \\le...re replaced prior to the IE Bulletin 79-13 irnplerrentation on Unit 2, NDE inforr:ation on t..'"le original welds Has mobtainable.
'Ihe 3 net, welds p;3r feem*,ater line were radiograr:hed to the SGRP con~truction code in force and not to the requirer:ents of IE Bulletin 79-13.
Auxi.liaiy Feec1,ater Cc.>nnections:
'lhe 3 in. auxiliary feedwater tie-in connections on all three main feed.-m.ter lines were r.:agnetic particle inspected. The main feed lines were radiographed one r,ipe diar.eter imrediately downstrear.i. of the auxilia:cy tie-ins., The :results of these inspections were acceptable.,
Visual inspect.ion of all feedwater sys tef:\\ piping SupJ:X>rts and snubbers in containrrent has been conpleted to verify oi;erability and confonnance to design. Uo discrepancies were noted.
____J
2 -
~tachment 1 (con't)
IE BULLI:l'IN 79-13 RESPCNSE: (OJNT'D.)
Corrective actions for the iterrs noted arove included replacer.-ent of all three Stear:l c.enerator Feed redocers and weld repair to.Wfl, "A" SG.
No further corrective actions are necessary.
Virginia Electric and Power Company North Anna Power Station, Unit #1
~ocket No. 50-338 Results of Examinations Required by IE Bulletin 79-13 "Cracking in Feedwater System Piping" On November 4, 1979, during the first refueling outage for Unit 1, the *examina-tions required by IE Bulletin 79-13 were completed.
The examinations, which were performed in accordance with Vepco NDT procedures, found no indications of any cracking problems in the feedwater nozzles or piping weld areas.
The examinations performed included the following:
- 1.
Radiography of:
- a.
Tilree feedwater nozzle to pipe welds.
- b.
All feedwater piping welds in containment.
- c.
An area of 16 inches downstream of the auxiliary feedwater to main feedwater connection on all three loops.
2..
Ultrasonics of:
- a.
Base material on main feedwater piping around the area of the auxiliary feedwater connections on all three loops.
3..
Magnetic particle of:
- a. Auxiliary feedwater to main feedwater connections on all three loops.
- 4. Visual Inspection of:
- a. All welded supports on main feedwater piping inside containment
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