IR 05000341/1978015
| ML20062C851 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/05/1978 |
| From: | Danielson D, Naidu K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20062C848 | List: |
| References | |
| 50-341-78-15, NUDOCS 7811140269 | |
| Download: ML20062C851 (8) | |
Text
.
.
.
.
U.S. NUCLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-341/78-15 Docket No. 50-341 License No. CPPR-87 Licensee: Detroit Edison Company 200 Second Avenue Detroit, MI 48226 Facility Name: Enrico Fermi, Unit 2 Inspection At: Fermi Site, Monroe, MI I
Inspection Conducted: September 13-14, 1978 O
Inspector:
K. R. Naidu j,. c(.a M/f /78
[Nb-t-t
<
Approved By:
D. H. Danielson, Chief
/4!J/73
,,
Engineering Support Section 2
Inspection Summary Inspection on September 13-14, 1978 (Report No. 50-341/78-15)
Areas Inspected: Welding activities and quality records relative to containment structural steel; quality records relative to safety-related structures and associated welding. This inspection involved a total of 16 onsite inspection hours by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
,
Y s
y 4g Q
.
I
-
.
.
DETAILS Persons Contacted Principal Licensee Employees
- E.
Hines, Assistant Vice President and Manager Quality Assurance
- A. Alexion, Assistant Project Superintendent
- R. W. Barr, Project QA Director
- G.
Carter, QA Engineer
- P.
Cribbs, QA Engineer
- W.
Everett, Project Superintendent
- W.
M. Street, Assistant Project Engineer
- U.
G. Orlando, Supervising Engineer Operations
- J.
D. Ryan, Site Project QA Engineer
- H.
A. Walker, QA Engineer (
Daniel International
- C, B. Bleisener, QC Manager
- J. T. Blixt, QC Welding / Mechanical Engineer
- J.
G. Bolt, Project QA Manager
- D.
Seifert, Project Manager T. Crouse, QA Engineer Reactor Controls Incorporated
- N.
Snellings, Site QC Supervisor
- L.
Wither, Site Manager In addition to those individuals listed above, the inspector talked with several other licensee and contractor employees.
- Denotes those who attended the exit interview.
1.
Review of Containment Structural Steel Quality Records
a.
The inspector reviewed the quality records associated with the containment liner plate sections identified as 11-2 and 14-1 and determined that the documents indicate that the quality requirements were met in the following areas:
(1) Material Verification Summary Sheet (MVSS) #27 prepared by CBI indicates that the daily fabrication report was-2-i l
l
.
.
checked and that the certified test reports were verified for the drywell cylindrical shell liner sections identified as 11-2 on CBI drawing 11, Revision O.
(2) MVSS #20 prepared by CBI indicates that the daily fabrication report was checked and that the certi-fied test reports were verified for the containment roof plate section identified as 14-1 on CBI drawing 14, Revision 5.
,
b.
The inspector reviewed the quality records associated with the various structural components which are currently being welded to the downcomers inside the torus by Reactor Controls Incorporated (RCI). The material was purchased and receipt inspected by RCI. Records indicate that the quality require-ments were met in the following areas:
(1) Receipt Inspection Report (RIR) #504-10 dated April 27, 1978, indicates that eight pieces each of MK RBC-4 and MK RBC-4A were received without any visible shipping damage.
(2) MK RBC-4 is identified as a 1 reinforcing bar (ring-beam plate) on RCI drawing #D4015, Revision 4, and specified to be ASME-SA-516, grade 70.
(3) The plates were fabricated by Northern Steel Corpo-ration (NSC); NSC is listed as an approved vendor for RCI.
(4) Mill Test Reports from Bethlehem Steel Corporation indicate that the material conforms to ASME-SA516, grade 70; the material was normalized at 1650 F and held for hour per inch of thickness of the material.
The NSC shop inspection report was included.
(5) RIR 504-12 dated May 15, 1978, indicates that piece-mark MKDS-1 identified on RCI drawing 4110 sheets 1 and 2 was received onsite without shipping damage.
Documents included a UT report from Lukens Steel
,
!
dated March 9,1978, which identified no unacceptable indications. The UT examination met the requirements of note 3 on RCI drawing 4110.
l No items of noncompliance or deviations were identified in the above areas.
-3-
m
_
m-
_
.
__
__
.
_ _ _ _ _
.
.
.
.
.
2.
Observation of Containment Structural Steel Welding Activities
The inspector observed the welding activities performed by RCI
'
associated with the reinforcements inside the~ torus and deter-mined that the requirements of work performance procedures and inspection procedures were being met in the following areas:
a.
Piecemark MK DS-10-36 was being welded to the downcomer as indicated on RCI drawing 4110; Revision 0.
l b.
The appearance of the completed welds were considered acceptable.
c.
DDR(W) 1948 was initiated to identify excessive fitup gap (1/8-inch to 3/8-inch) between the pieces MK DS-10-36 and the downcomer. Field proposed corrective action was
,
to butter up in the area of excessive gap to acceptable limits.
f d.
Weld rod types E7018 and E8010 were being used; the rods were stored in heated protable electrode ovens.
e.
Depleted electrodes were being discarded in containers assigned to welders.
f Welding Procedure Specifications (WPS) 101, 102 and 103 were available for review; the WPS furnished the size of
,
i electrodes and the corresponding current and voltage i
ranges. The weldrod travel speed range was also specified.
g.
RCI QC Welder Surveillance Sheets (WSS) indicate that the i
'
following were verified:
.
(1) The piecemark on which welding was being performed.
(2) Type of electrode used; heat number and size.
'
i (3) Disposal of depleted elect: ode.
(4) Qualification of the welders.
!
The WSS lists the amperage and voltage as items to be checked.
The inspector noted that only the measured value of the amperage was recorded. The RCI QC Site Supervisor stated he would obtain additional information on the correlation between the weldrod
{
travel speed and the corresponding current and voltage ranges j
for selected weldrod size.
In addition, he stated he would i
furnish information on an acceptable method by which it could be verified that the welding is being performed within the paramenters specified in the WPS.
This is considered an I
unresolved item (341/78-15-01). *
!
-4-l l
i l
.
l
,.. ~. -
, _
.
_. _ _ _-
. - - -
__
.
__ _ _. _ -.__
..
. -..
-
.
-.
- -
.
.
.
.
.
.
No items of noncompliance or deviations were identified in a
the above areas.
i 3.
Review of Safety-Related Structures Quality Records j
a.
The inspector reviewed the quality records associated with the structural steel components installed in the control Room ceiling and determined that the quality requirements were met in the following areas:
(1) Receipt Inspection Report (RIR) #11-3-75-2 dated November 3, 1975, indicates that hangers, beams, channels, columns and miscellaneous material received from Inland Ryerson (IR) were inspected. No shipping damage was identified.
(2) Certified Test Reports (CTR) from IR were available.
(3) Material Test Certificates from United States Steel f
the manufacturer of the components were available.
(4) Review of a typical record drawing DE #6C 721-2605 titled " Plan of High and Low Ceiling Steel Control Room" indicates that the areas where dimensional checks were made were colored red and those concrete anchors which were tested were colored yellow.
(5) A calibration certificate from Toledo Testing Laboratory dated February 18, 1977, indicates that a Tinius Olsen Universal, which was certified by the Cement and Concrete Reference Laboratory, was used to calibrate a 20-ton
!
hydraulic Jack - Enerpac model RCH DE3 and one 10,000 I
psi Enerpac pressure gauge model P-39, serial #243. The hydraulic jack with the pressure gauge was used to test the concrete anchors.
I b.
1he inspector reviewed the quality records of channels
'
i identified as F29117R, G2917, F2917 and N2917 on Detroit Edison drawing 6C 721-3522 entitled " Air Intake Auxiliary Buildf ag."
The documents indicate that the quality require-ments were met in the following areas:
(1) RIR #12-19-75-1 dated December 19, 1975, indicates
'
that the structural steel components identified above, which were fabricated by IR, were receipt inspected and identified no visible damage, i-5-
- -.. - -. -.
.
.
.-.
.
.
.
.
(2) Qualification records of welders who performed welding in the shop were included in the documentation.
Records indicate that IR subcontracted the fabrication to Industrial Fabricating Incorporated, (IFI). The welder qualifications identify the IFI welders, c.
The inspector reviewed the quality records associated with the Fuel Oil Day Tanks (F0DT) and the Diesel Fuel Storage Tanks (DFST) for the Emergency Service Diesel Generator (ESDG) and determined that the records indicate that the quality requirements were met in the following areas:
(1) RIR dated September 8, 1975, indicates that four pieces of 550 gallon capacity F0DT manufactured by Irwin Steel Fabricators, (ISF) Canton, Ohio, were visually inspected for shipping damage and determined acceptable. A deviation identified that the serial numbers on the material differed from those on the bill of materials (
(BM). The identification plates on the tanks were altered to read the same as on the BM.
ISF shipping
-
documents state that the tank was fabricated to draw-ings H-2139 and H-2140 and stamped ASME Section III, Class 3 (codes 331 through 334). Review of a typical form N-1A, manufacturers data report for nuclear vessels for tank serial #334, indicates that the tank successfully withstood a hydrostatic pressure of 225 psig without leaks.
(2) RIR dated July 22, 1977, indicates that two of the four 42,000 gallon DFST's fabricated by Graver Tank and Manufacturing Company were received with no visible shipping damage. The documentation included the following records:
(a) ASME Section III code data report.
,.
\\
(b) Material identification lists.
(c) Magnetic particle examination reports.
(d) Qualifications of nondestructive examination personnel to ANSI-TC-1A requirements.
(e) Hydrostatic test report certifying that the tank successfully withstood 25 psig for 20 minutes without leaks.
(f) Coating application records.
l (g) Weld material certification.
'
(h) Welder qualification records (i) Radiographic test reports.
.
t
'
-6-i l
l
.
.
.
.
.
No items of noncomplainee or deviations were identified in the above areas.
4.
Review of Safety-Related Structures Welding Records The inspector reviewed welding records associated with the structural components installed in the Control Room Ceiling and the Air Intake Structure, and determined that the records indicate that quality requirements were met in the following areas:
a.
Detail of elevation D-D of the DE drawing 6C721-3519 entitled
" Reactor Building Control Room Ceiling Miscellaneous Framing Plan, Section and Details." The inspector selectively verified that the sizes of the welds on the structural components in the control room ceiling were as specified in the drawing.
b.
Haven-Busch Erection procedure #1, Revision 0, dated r
i January 20, 1977, was used to inspect in process work including fitup, welding or bolting and documentation review, Deviation Disposition Request (DDR) #W 1043 dated May 23, c.
1977, documented several defects in the weldments on the control room miscellaneous steel structures. The defects included inadequate weld size, undercut, slag inclusion, are strikes on surrounding base metal and porosity. A QC welding inspector signed the DDR on June 17, 1977, in-dicating that the completed repairs were acceptable, d.
Process control sheets were available which indicate that fitup of weld joints and bolting were inspected as applicable.
e.
DE drawing 6C 721-3522 entitled " Air Intake Auxiliary Buildup" specifies 3/16-inch fillet weld to attach channels
,
!
!
F29117R, G29176 and N2917 to amendments. QC structural welding checklist dated May 19, 1976, documents the welder i
who performed the welds and visual acceptance of the welds.
No items of noncompliance or deviations were identified in the above areas.
!
-7-
l l
l l
l l
.. _ _,
-
_
__ _
_
_
,_
.
.
.
.
.
-
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during
'.
the inspection is discussed in paragraph 2.
Exit Interview _
The inspector met with site staff representatives (denoted under Persons Contacted) at the conclusion of the inspection on September 14, 1978. The inspector summarized the purpose and findings of the inspection. The licensee acknowledged the findings reported herein.
l
.
<
-8-
, -.
-
-
-
..