ML19321B097
| ML19321B097 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/30/1980 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-08, IEB-80-8, NUDOCS 8007250631 | |
| Download: ML19321B097 (13) | |
Text
V
-7 w PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET y
P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L. D ALTROFF stacInicOo e ion June 30, 1980 Docket Nos.: 50-277 50-278 IE Bulletin 80-08 i
Mr. Boyce H.
Grier, Director Office of Inspection and Enforcement Region I U.S.
Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
This letter is in response to IE Bulletin 80-08, forwarded to us on April 7, 1980, concerning the examination of containment liner penetration welds.
The " Action to be Taken" and our responses for Peach Bottom Units 2 and 3 are treated i
sequentially.
Action to be Taken 1.
Determine if your facility contains the flued head design for penetration connections, or other designs with containment boundary butt weld (s) between the penetration sleeve and process piping as illustrated in Figure NE 1120-1, Winter 1975 Addenda to the 1974 and later editions of the ASME B&PV Code.
Response
Each of Peach Bottom's two units have twenty-six (26) flued head penetrations with a total of forty (40) containment boundary butt welds between the penetration sleeve and process piping.
80072506 3\\
Mr. Boyce H. Grior Page 2 2.
If an affirmative answer is reached for Item 1, determine the following:
a.
Applicability of the ASME Code including year and addenda and/or Regulatory Guide 1.19.
Response
T t applicable code is ANSI B31.1.0 (1967) " Power Piping".
b.
Type of non-destructive examinations performed during construction.
Response
i The NDE methods are listed in Attachment 1.
i c.
Type of weld joint (including pipe material and size) and whether or not backing bars were used.
Response
The containment boundary butt welds are of the full penetration butt tyne.
Backing bars were not used on any of these welds.
Pipe materials and sizes are listed in Attachment 1.
d.
Results of construction non-destructive examinations, i.e.,
if repairs were required, this should be identified including extent of repairs and description of defects encountered during repair, if known.
Response
The defects found and repaired are listed in Attachment 1.
3.
For those facilities committed during construction to perform volumetric examination of such penetrations through SAR commitments which have not performed radiography, justify not performing radiography or submit plans and schedules for performing radiographic examinations.
Response
Philadelphia Electric Company did make SAR commitments to perform volumetric examinations of the welds in question.
Code acceptable radiographs were obtafaed for 26 welds on each Unit.
However, radiographs of acceptable sensitivity were not obtainable for Weld 2 of penetration type A (see Attachment 2).
e Mr. Boyco H. Grier Page 3 There are fourteen (14) of this type weld in each unit, and in all cases, the configuration of the penetration was the limiting factor in obtaining acceptable radiographs.
During construction of Unit 2 eight of the fourteen welds mentioned above were radiographed.
Although the quality of these radiographs did not meet code standards, the radiographs were sensitive enough to detect any major defects, and none were found.
These welds were subsequently examined with ultrasonics for code acceptability.
The remaining six welds of this type on Unit 2 and all fourteen on Unit 3 were examined by ultrasonics only.
Ultrasonic examination for welds without backing bars is an industry accepted alternative when radiography is not practical.
i It is the position of Philadelphia Electric Company that the results of the ultrasonic examinations were meaningful because backing bars were not present in any of the welds concerned and also because the radiography which was performed, showed that there were no major defects.
Very truly yours, m
k(D
^ji-j [T Attachment ec: Director Division of Reactor Construction Inspection U.S.
Nuclear Regulatory Commission Washington, DC 20555 I
i l
l
ATTACINENT 1 Tables 1, 2, 3 and 4 Containment Penetration h' eld Information e
e
ATTACHMENT 1 TABLE 1: TYPE A PENETRATIONS PEACH BOTTOM UNIT No. 2 (1)
Nom.
Nom.
ASTM Materials (2)
(3)
Pcna-Keld Size Thk.
Expansion NDE Defects Found tr tion' Service No.
in.
in.
Nozzle Joint Flued Head Method and P.cpaired N-7A Main Steam 1
44 0.500 A516 GR 70 A516 G'R 70 RT Local porosity 6 slag 2
44 0.500 A516 GR 70 A105 GR II RT 6 UT None N-7B Main Steam 1
44 0.500 A516 GR 70 A516 GR 70 RT Local porosity 2
<44 0.500 A516 GR 70 A105 GR II RT 6 UT None K-7C Main Steam 1
44 0.500 A516 GR 70 A516 GR 70 RT Local porosity 2
44 0.500 A516 GR 70 A105 GR 11 RT 4 UT None N-7D Main Steam 1
44 0.500 A516 GR 70 A516 GR 70 RT Local porosity 2
44 0.500 A516 GR 70 A105 GR II RT 4 UT None N-9A Feedwater 1
42 0.500 A516 GR 70 A516 GR 70 RT Undercut 6 slag 2
42 0.500 A516 GR 70 A105 GR II RT 4 UT None N-9B Feedwater 1
42 0.500 A516 GR 70 A516 GR 70 RT None 2
42 0.500 A516 GR 70 A105 GR 11 RT 4 UT None N-11 Steam to 1
26 0.500 A516 GR 70 A516 GR 70 RT Slag HPCI Turbine 2
26 0.500 A516 GR 70 A105 GR II UT None N-12 RHR Pump 1
36 0.500 A516 GR 70 A516 GR 70 RT None Suction 2
36 0.500 A516 GR 70 A182, F304 UT None N-13A RHR Pump 1
42 0.500 A516 GR 70 A516 GR 70 RT Local porosity 6 slag Discharge 2
42 0.500 A516 GR 70 A182, F304 UT None N-13B RHR Pump 1
42 0.500 A516 GR 70 A516 GR 70 RT None Discharge 2
42 0.500 A516 GR 70 A182, F304 UT None N-14 Clean-up 1
22 0.500 A516 GR 70 A516 GR 70 RT Local porosity Pump Supply 2
22 0.500 A516 GR 70 A182, F304 RT 4 UT None
ATTACil> TENT 1 TABLE 1: TYPE A PENETRATIONS PEACll BOTT051 UNIT No. 2 (1)
Nom.
Nom.
AST)! Materials (2)
(3)
Pena-Weld Size Thk.
Expansion NDE Defects Found tration Service No.
in.
in.
Nozzle Joint Flued Head Method and Repaired N-16A Core Spray 1
28 0.500 A516 GR 70 A516 GR 70 RT None 2
28 0.500 A516 GR 70 A182, F304 UT None N-16B Core Spray 1
28 0.500 A516 GR 70 A516 GR 70 RT None 2
28 0.500 A516 GR 70 A182, F304 RT 6 UT None N-17 RPV Head 1
22 0.500 A516 GR 70 A516 GR 70 RT None Spray 2
22 0.500 A516 GR 70 A182, F304 UT None (1)
See Attachment 2, " Penetration Type A", for location of Keld Nos. I and 2.
(2)
NDE Method:
RT Radiography
=
UT Ultrasonic
=
RT 6 UT weld was radiographed (but sensitivity was below code requirements)
=
and subsequently examined ultrasonically (3)
In all cases where defects were found, the questionable area was removed and repair welded.
9 e
.s ATTACllMENT 1 TABLE 2:
TYPE B PENETRATIONS PEACil BOTTOM UNIT NO. 2 4
(1)
Nom.
Nom.
(2)
(3)
Ptng-Weld Size Thk.
ASTM Material NDE Defects Found tration Service No.
in.
in.
Nozzle Flued Head Method and Repaired N-8 Main Steam Line Drain 3
8 0.500 A106 GR B A105 GR II RT None N-10 Steam to RCIC Turbine 3
12 0.687 A333 GR 1 A105 GR II RT None N-21 Service Air 3
3 U.300 A333 GR 1 A105 GR II RT None N-22 Instrument Nitrogen 3
3 0.300 A333 GR 1 A182,.F304 RT None N-36 CRD Return Line 3
12 0.687 A333 GR 1 A105 GR II RT None N-41 Reactor Water Sample 3
6 0.500 A333 GR 1 A182, F304 RT slag N-42 Standby Liquid Control 3
4 0.337 A333 GR 1
,A182, F304 RT Localized porosity N-53 Chilled Water Inlet 3
12 0.687 A333 GR 1 A105 GR II RT None N-54 Chilled Water Inlet 3
12 0.687 A333 GR 1 A105 GR II RT None
{
N-55 Chilled Water Outlet 3
12 0.687 A333 GR 1 A105 GR II RT None N-56 Chilled Water Outlet 3
12 0.687 A333 GR 1 A105 GR II RT None N-57 Main Steam Sample 3
6 0.500 A333 GR 1 A182, F304 RT None
^
(1)
See Attachment 3, " Penetration Type B" for location of Weld No. 3.
(2)
NDE Method:
RT = Radiography (3)
In all cases where defects were found, the questionable arcs. was removed and repair welded.
ATTACHMENT 1 TABLE 3: TYPE A PENETRATIONS PEACil BOTTOM UNIT NO. 3 Non.
Som.
ASTM Material Pane-Keld Size Thk.
Expansion NDE Defects Found tration Service No.
in.
in.
Nozzle Joint Flued llead Method and Repaired N-7A Main Steam 1
44 0.500 A516 GR 70 A516 GR 70 RT None 2
44 0.500 A516 GR 70 A105 GR II UT None N-7B Main Steam 1
44 0.500 A516 GR 70 A516 GR 70 RT Slag 2
44 0.500 A516 GR 70 A105 GR II UT None N-7C Main Steam 1
44 0.500 A516 GR 70 A516 GR 70 RT None 2
44 0.500 A516 GR 70 A105 GR II UT None N-7D Main Steam 1
44 0.500 A516 GR 70 A516 GR 70 RT None 2
44 0.500 A516 GR 70 A105 GR II UT None N-9A Feedwater 1
42 0.500 A516 GR 70 A516 GR 70 RT None 2
42 0.500 A516 GR 70 A105 GR II UT None N-9B Feedwater 1
42 0.500 A516 GR 70 A516 GR 7(,
RT None 2
42 0.500 A516 GR 70 A105 GR II UT None N-11 Steam to 1
26 0.500 A516 GR 70 A516 GR 70 RT None llPCI Turbine 2
26 0.500 A516 GR 70 A105 GR II UT None N-12 Ri!R Pump 1
36 0.500 A516 GR 70 A516 GR 70 RT None Suction 2
36 0.500 A516 GR 70 A182, F304 UT None N-13A RilR Pump 1
42 0.500 A516 GR 70 A516 GR 70 RT None Discharge 2
42 0.500 A516 GR 70 A182, 7304 UT None N-13B RilR Pump 1
42 0.500 A516 GR 70 A516 GR 70 RT None Discharge 2
42 0.500 A516 GR 70 A182, F304 UT None N-14 Clean-up 1
22 0.500 A333 GR I A516 GR 73 RT Slag Pump Supply 2
22 0.500 A516 GR 70 A182, F304 UT None
ATTACll>!ENT 1 TABLE 3: TYPE A PENETRATIONS PEAGI BOTTOM UNIT NO. 3 (1)
Nom.
Nom.
ASTM Material (2)
(3)
Pcnn-Keld Size Thk.
Expansion NDE Defects Found traticn Service No.
in.
in.
Nozzle Joint Flued Head Method and Repaired N-16A Core Spray 1
28 0.500 A516 GR 70 A516 GR 70 RT None 2
28 0.500 A516 GR 70 A182, F304 UT None N-16B Core Spray 1
28 0.500 A516 GR 70 A516 GR 70 RT None 2
28 0.500 A516 GR 70 A182, F304 UT None N-17 RPV llead 1
22 0.500 A333 GR I A516 GR 70 RT Slag Spray 2
22 0.500 A516 GR 70 A182, F304 UT None (1) See Attachment 2, " Penetration Type A", for location of Weld Nos. I and 2.
(2) NDE Method:
RT Radiography
=
UT Ultrasonic
=
(3)
In all cases where defects were found, the questionable area was removed and repair welded.
e i
e
ATTACilMENT 1 TABLE 4: TYPE B PENETRATIONS PEACil BOTTOM UNIT NO. 3 (1)
Nom.
Nom.
(2)
(3)
Pcn;-
Weld Size Thk.
ASTM Material NDE Defects Found tr2ticn Service No.
in.
in.
Nozzle Flued licad Method and Repaired N-8 Main Steam Line Drain 3
8 0.500 A106 GR B A105 GR II RT None N-10 Steam to RCIC Turbine 3
12 0.562 A106 GR B A105 GR II RT Local porosity N-21 Service Air 3
3 0.216 A333 GR 1 A105 GR II RT None N-22 Instrument Nitrogen 3
3 0.300 A106 GR B A182, F304 RT None N-36 CRD Return Line 3
12 0.687 A333 GR 1 A105 GR II RT Incomplete fusion S Local porosity N-41 Reactor Water Sample 3
6 0.432 A333 GR 1 A182, F304 RT None N-42 Standby Liquid Control 3
4 0.337 A333 GR 1 A182, F304 RT None N-53 Chilled Water Inlet 3
12 0.687 A333 GR 1 A105 GR II RT None N-54 Chilled Water Inlet 3
12 0.687 A333 GR 1 A105 GR II RT None N-55 Chilled Water Outlet 3
12 0.687 A333 GR 1 A105 GR II RT None N-56 Chilled Water Outlet 3
12 0.687 A333 GR 1 A105 GR II RT Incomplete fusion N-57 Main Steam Sample 3
6 0.432 A333 GR 1 A182, F304 RT None (1) See Attachment 3, " Penetration Type B" for location of Weld No. 3.
(2) NDE Method:
RT = Radiography (3)
In all cases where defects were found, the questionable area was removed and repair welded.
ATTACIBIENT 2 6 3 Typical Penetration Configurations -
Penetration Type A Penetration Type B
O WELD WELD 2
PRIM ARY SHIEL DING CONCRETE CONTAINNENT S, ELL f
if 5 TABLE Two PLY EILPAN510N JOINT f:
DRYWELL N0ZZLE I
s
' 'I s
GUARD PIPE 1
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gngpygg PROCESS PIPEm
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OEFLECTOR PL ATE J'
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ANCH00 LUGS lNSULATION o
s AS REQUltED g
P E N E-R A-~ O \\
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ATTACilMENT 2
WE LD 3
,e PRIMARY CONTAINMENT SHELL-~
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CONCRETE SHIELO
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FLUED HEAD PRIMARY CONTAINMENT N0ZZLE FITTING
- .. 'el' A
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PIPE
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FIELD WELD t..*.,,,. -
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SHOP WELO s.
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6 IN SUL ATio.'1 AS REQUIRED 3 E \\ E-~ R A~~ O N
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ATTACllMENT 3
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