IR 05000454/1981003
| ML19347F718 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/10/1981 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19347F713 | List: |
| References | |
| 50-454-81-03, 50-454-81-3, 50-455-81-03, 50-455-81-3, NUDOCS 8105260112 | |
| Download: ML19347F718 (5) | |
Text
.
,
L,m)
,
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCMENT
REGION III
Reports No. 50-454/81-03; 50-455/81-03 Dockets No. 50-454; 50-455
. Licenses No. CPPR-130; CPPR-131 Licensee: Commonwealth Edison Company P. O. Box 767
'
Chicago,-IL 60690 Facility Nanie: Byron Station, Units 1 and 2 Inspection At:
Byron Site, Byron, IL Inspection Conducted: March 19, 25 and 26, 1981 Inspector: $
/
.
hwGs/4~
'
'
Approved By:
D. H. Danielson, Chief
/ o!P/
Materials and Processes Section i
'
Inspection Summary J
Inspection on March 19,, 25 and 26,'1981 (Report No. 50-454/81-03; 50-455/81-03)
Areas Inspected: Reactor coolant pressure boundary piping and safety related.
piping observation of work, selding, NDE, and related record review;.contain-ment post tensioning procedure review. The insp ution involved a total of 21
. inspector-hours on site by one NRC inspector.
,
' Results : Of the areas inspected, one apparent viclation was' identified (failure to comply with ASME Code radiographic technique requirements -
Paragraph 3).
'
.
.
'
!81052 60 //$.q
~
-
-
_
__.
.
.. ~.
.
.
.....
_ _ _ _ _ _ _.
.
,
.
.,
i DETAILS
' Persons Contacted Principal Licensee Employees (CECO)
- G. Sorensen,' Construction Superintendent
- M. A. Stanish, QA Superintendent
!
R. Guse, Construction Engineer - Civil
- L. A. LaBanca, Quality Assurance-i J. Da Rosia, _Censtruction Engineer - Primary System -
Other Personnel
,
- H. Somsag, QA Supervisor, Hunter Corporation.
- G. Seuring,' Production Welding Supervisor, Hunter Corporation A. Simon, QA Administration Supervisor, Hunter Corporation
'
F. Schluter, Supervisor NDE, Pittsburgh Testing Laboratory L. Morales, Radiography L2, Pittsburgh Testing Laboratory
R. Bay, QA/QC Manager, Blount Brothers R. Wilhelm, QC Inspector, Hunter Corporation
- Denotes those present at the exit-interview.
Functional or Program Areas Inspected
,
'
1.
Status of Construction' Work'at Byron Units l'and 2 a.
Post Tensioning for Unit 2 to start in April 1981 by Blount Brothers.
,'
About 1700 craft peopic on site.
Inservice inspection work to start in May by Ebasco.
l_
b.
Piping, Completion for Unit 1
'
96% Large bore, 2-1/2" and up
,
l 60% Small bore
40% Hangers large bore.
c.
Piping Completion for Unit 2 35% Large bore 0% Small bore-25% Large bore hangers d.
Civil - Structural Completion
'
99% Miscellaneous openings, backfits, Units 1 and 2-2-
.
,
,
f k
'
Post tensioning complete Unit 1
_
. Post tensioning to' start April 1981 Unit 2 e.
Electrical Completion.
"
60% Unit 1 40% Unit 2 f.
Ventilation Completion
.
80% Units 1 and 2 2.
Welding, NDE.and Post Weld Heat Treat of Feedwater System and Main
-
Steam System Piping - Unit I and Unit 2 The.above piping to.the first stop valve is installed and inapected to the requirements of S&L Specification F-2739 and.the requirements of ASME Section III,1974 Edition through Summer 1975 Addenda.- Weld'
procedure HCWPS'39, Rev. 2 is used and since the steam generator-nozzle is P-3 material and the piping-is P-1,'a 200*F preheat and'
1150'F post weld heat treat are employed.- A consumable insert is
-
used with the GTAW process for the root of the weld and ccipletion is by the SMAW procese.
+
The QC documentation on Main Steam System welds 110A, 127 and 131-were examined except for radiography and found.to be acceptable.
The heat charts for 110A and 127 indicated the required temperature
,
1100' - 1200*F for the minimum time of one hour at temperature per.
inch of wall thickness.
The QC documentation on Feedwater System welds 210 and 246 was
.
acceptable with PWHT requirements also met for the.797.844 wall thickness of the pipe.
The Main Steam System oiping was made to Specification SA 155, Grade 65 and, is 30.25" Dia. x 1.25" wall normalized after welding. This p oe has one longitudinal weld'and is manufactured by Taylor Forge
'
-
Co.
'outhwest Fabricating and Welding fabricated the piping spools.
'
The longitudina) weld is 100% radiographed and also has 100% magnetic
particle inspection.
No items of norcompliance or deviations were identified.
3.
Primary Coolant System Pipiag and Containment Spray Piping - Units 1 and 2 Cameron Iron Works forged tb.e primary coolant piping, but thet a.
fittings were centrifuga11y cast. The pipe is stainless steel l'
been impossible to inspect ultrasonically. The Inservice 27.5" Dia. x 3.280"/3.340" wall. This thickness in the past has Inspection Program has not begun, but a weld between a similar-3-
.
E
-.
_. ~ _..
. -..
..
._
,. _ _.. ~..
_
_ _ _
.
-
-
.
a pipe and fitting has been prepared, which will act as a cali-bratica standard for the Class 1 primary coolant piping. The RIII inspector will examine the ultrasonic effort in this heavy walled piping area during subsequent inservice inspections.
.
b.
Weld No. FW-45 in Unit 1, which is a pump to pipe weld in spool piece IH-CAE-4, was made to TG'S 53 and 100% radiography is re-quired. Weld No. FW-191 in spool piece 2H-CBE-2, Unit 2, also was made to WPS 53 and requires 100% radiography. The radiography was performed to Pittsburgh Testing Lab (PTL) procedure QC-RT-1.
The inspector noted when examining the films for the above two welds that while two penetrameters were shown on-the. film, no shim was used. There was a considerable variation in density since the.
above welds involved a pipe and fitting juncture. This practice is not in compliance with ASME Section V, 1974 Edition, Summer 1975 Addenda, and FLT Procedure QC-RT-1 and is an item of noncompliance identified in Appendix A.
(454/81-03-01; 455/81-03-01)
Welding records of Containment Spray Weld No.'306 and No. 294, c.
which are stainless steel to stainless steel joints', were examined.
This pipe 3" Dia. x.216" wall was welded to Procedure No. WP50, Rev. I and was by the GTAW entirely. The weld slip sheets were
-
attached to the process sheet and the ANI had a hold point fo.r visual of the final weld. Except as noted no items of noncom-pliance or deviations were identified.
4.
Containment Post Tensioning Procedure Review - Unit 2 The following procedures to be used for post tensioning were examined:
Procedure No. 31, Rev. 3, Receiving, Storing and Inspection of
.
Post Tensioning Tendons.
Addendum A to Procedure 45, Buttonheading.
.
Procedure No. 46, Rev. 11 Stressing.
.
.
Procedure No. 47, Rev. 2, Bearing Plate Preparation and Grease Cap
.
Installation.
Procedure 48, Rev. 2, Grecsing.
.
Calibration of Post Tensioning Equipment Gauges and Instruments.
.
Post Tensioning has been completed for Unit 1.
Approximately one year after completion and after the SIT test a random sampling will be per-formed for broken wires and lift off force.
No item of noncompliance or deviations were identified.
I
!
l 4-
-
.
g
~ - -
w-
-
g,
+nme*,-
,
--s
--
w
~-
- - -,
.,r-
_. -
..
4 Exit Interview
.
TheIIspectormetwithlicenseerepresentatives(denotedunderPersons
Contacted) at the ' conclusion of the inspection March '26,1981. - The' inspector.
susunarized the purpose and findings of the inspection, which were acknowledge by the licensee.
'
+
i J
!
I s
e a
!
h
i
i
!
$
J-5-
.