IR 05000341/1981007
| ML20009A939 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/26/1981 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20009A931 | List: |
| References | |
| 50-341-81-07, 50-341-81-7, IEB-79-03A, IEB-79-3A, IEB-80-02, IEB-80-08, IEB-80-2, IEB-80-21, IEB-80-8, NUDOCS 8107140521 | |
| Download: ML20009A939 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-341/81-07
Docket No. 50-341 License No. CPPR-87 Licensee: Detroit Edison Company 2000 Second Avenue
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Detroit, MI 48226 Facility Name: Enrico Fermi Atomic Power Plant, Unit 2 Inspection At: Fermi 2 Site, Monroe, Michigan Inspection Conducted: June 16-19, 1981 1. A 4 Inspector:
K. D. Ward I X //
ol5tgleY Approved By:
D. H. Danielson, Chief 6 4 C'/
Materials & Processes Section
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Inspection Summary Inspection on June 16-19, 1981 (Report No. 50-341/81-07)
Areas Inspected: Nuclear Energy Services nondestructive examination (NDE)
procedures, personnel certifications, equipment and review of radiographs:
IE Bulletins79-03A, 80-02, 80-08 and 80-21 activities. The inspection in-volved a total of 30 onsite inspector-hours by one NRC inspector.
Results Of the areas inspected, one apparent violation was identified.
i Failure to comply with ASME Code requirements during radiographic examina-I tion paragraph 3).
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DETAILS
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Persons Contacted Detroit Edison Company (Deco)
- T. Alessi, Director, Project QA
- J.
Gessner, Assistant Director
- C. Bacon, Assistant Director, Field Engineer
- W. Boelter, Assistant Project Manager, Construction
- G. Carter, Lead Engineer Projects QA H. Wa'.ker, Site Project QA Engineer Daniel International Corp. (DIC)
- J. Ard, Project Manager
- T. Cline, Area Manager, Turbine, Auxiliary
- R. Crane, QA Supervisor Wismer and Becker (WB)
P. Edmondson, QA Document Supervisor J. Jobe, QC Inspector Nuclear Energy Services (NES)
M. McDermaid, Day Shift Supervisor B. Dycus, Night Shift Supervisor The inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (341/79-25-05) Unclear method of making changes in procedures and upgrading revision status in index.
The inspector reviewed the program WB-A-114 of making changes in procedures and upgrading revisions and has no questions at this time.
(Closed) Unresolved Item (341/79-21-01) Qualification data not available on plastic sealant (GE No. 1200) being used for safety related HVAC Systems.
The inspector reviewed the qualification data for the plastic sealent being-used and has no questions at this time.
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(Closed) Unresolved Item (341/79-03-06) Welds and storage condition of
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spent fuel storage racks were questioned. The inspector reviewed a purchase order for new high density spent fuel storage racks that are to be sent to the site 8/81 and has no questions at this time.
(Closed) Noncompliance (341/79-13-02) NDE personnel qualification not per procedure. The inspector reviewed; (1) the Daniel Corporate Written Practice for certifying NDE personnel 7.1, Revision 5 dated February 26, 1980, (2) A. Denke, Level III RT and PT personnel certifications, (3) work log of inspection personnel, and (4) WB NDE personnel certification form indisating color tests. The inspector considers appropriate corrective action was taken.
Licensee Action on IE Bulletins References:
a.
IE Bulletin No.79-03A titled " Longitudinal Weld Defects in ASME SA-312 Type 304 Stainless Steel Pipe" dated April 4, 1980.
b.
DECO letter to NRC dated August 26, 1980 and final response dated September 15, 1980 to IE Bulletin 79-03A.
c.
IE Bulletin No. 80-02 titled " Inadequate Quality Assurance For Nuclear Supplied Equipment" dated January 22, 1980.
d.
DECO letter to NRC dated May 13, 1980 and final response dated September 4, 1980 to IE Bulletin 80-02.
e.
IE Bulletin No. 80-08 titled " Examination of Containment Liner Penetration Welds" dated April 8, 1980.
f.
DECO letter to NRC dated February 12, 1981, final response to IE Bulletin 80-08.
g.
IE Bulletin No. 80-21 titled " Valve Yokes Supplied by Malcolm Foundry Company, Inc." dated November 6, 1980.
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DECO letter to NRC dated January 19, 1981 and final j
response dated June 12, 1981 to IE Bulletin 80-21.
i (Closed) IE Bulletin 79-03A. The inspector reviewed the final response and license review of the safety related systems where SA-312 or A-312 Type 300 Series fusion welded pipe may be used. The inspector has no questions at this time.
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(Closed)
The inspector reviewed the final response GE l
response dated July 18, 1980, and quality certifications furnished by GE and considers appropriate corrective action was taken.
l (Closed) IE Bulletin 80-08.
The inspector reviewed the final response and
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nondestructive examination records of the penetrations and has no questions at this time.
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(Closed) IE Bulletin 80-21.
The inspector reviewed the final response and s
none of the safety related valves furnished to the Fermi II Project by General Electric used parts made by the Malcolm Foundry Company.
Licensee Action on 10 CFR 50.55(e) Items Reference:
a.
DECO letter to NRC dated November 25, 1980, " Defective GE-1 & SE Welds."
b.
DECO letter to NRC dated February 24, 1981, " Interim Report on Defective GE-1 & SE Welds."
Dravo letter to NRC dated January 26, 1981, "Possible c.
Defective Piping Subassemblies."
d.
DECO telephone conversations to NRC dated May 8, 1981 and May 22, 1981, " Dravo NDE Problem."
(0 pen) Defective GE-1 and SE welds. The final actions are not completed and a final report may be submitted to RIII by July 2, 1981.
(0 pen) Possible Defective Piping Subassemblies from Dravo. Dravo is to respond to DECO stating the exact problem and at that time it will be deter-mined if there is a Code violation involved.
Functional or Program Areas Inspected 1.
Review of Nuclear Energy Services (NES) NDE Activities NES was contracted to perform NDE in accordance with ASME Section a.
III, 1971 Edition, Winter 1971 Addenda.
b.
The inspector reviewed the following NDE procedures:
WB, Ultrasonic Material Thickness Measurement WB-Q-105, Revision 2,
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dated May 19, 1978.
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WB, Magnetic Particle Examination, WB-Q-108, Revision 9, dated May 20, 1980.
WB, Ultrasonic Examination, WB-Q-109, Revision 3, dated June 20, 1978.
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WB, Radiographic Examination, WB-Q-110, Revision 10, dated March 12, 1981.
t WB, Radiographic Film Processing, WB-Q-111, Revision 1, dated April 30, 1981.
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NES, Procedure for Training and Certification of Nondestructive
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Examination Personnel, 99-CNTP-001, Revision 0, dated June 20, 1979.
c.
The following NDE personnel certifications were reviewed in accord-ance with SNT-TC-1A, 1975 Edition.
Name RT UT PT MT M. McDermaid II II II II B. Dycus II M. Ivins II II II K. Sumrall II J. Stine II G. Wallace II d.
The inspector made a tour of the NES facilities escorted by the Day and Night Shift 5s,ervisors. The following are the inspector's findings:
(1) Radiograph Examination (RT)
The NRC license expires October 31, 1981 and covers IR 192 up to 100 curies and CO 60 up to 100 curies.
NES does not have a CO 60 source or an X-ray machine on site that operates.
The lab has seven IR 192 sources on site.
A Pako automatic film processer is used to process film and a hand film processing tank is available.
Survey meters are calibrated every three months.
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Pocket dosimeters are read and recorded every day when performing RT.
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Film badges are processed and recorded every month.
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Acceptable color rope and signs were available for securing l
areas when RT is being performed.
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Decay curves of the IR 192 source are posted in the lab for l
the NDE personnel to use.
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The lab used Kodak industrial radiographic film, Types I and II.
Outdated film was observed which is used as a cleaner for the automatic processor.
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Film cassettes were in acceptable condition.
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Lead screens are checked and replaced when needed.
Flourescent screens are not used nor are there any onsite.
The films are stored in the dark room prior to exposure.
NES uses lead numbers for the number belt and a flasher or lead numbers for the identification.
The lab uses an X Rite 201 densitometer.
NES uses a film density step wedge traceable to the Bureau of Standards for calibration of the densitometer.
ASTM penetrameters are the only penetrameters used onsite.
NES had various thicktesses of shims to be used under the penetrameters.
The lab uses a high intensity viewer for interpreting radiographs.
The NDE personnel mcve the IR 192 sources around the site themselves with no transportation.
The inspector reviewed radiographs and reports of the following field welds in accordance with ASME Section III, 1971 Edition, Winter 1971 Addenda.
Line No.
Weld Diameter Thickness Date RT G33-3096 10WF2 4"
0.593" 3/20/80 E21-3053 OW4 12" 0.906" 4/10/81 E21-3144 OW2 12" 0.531" 6/18/78 E21-3144 OW4 12" 0.468" 3/9/79 i
G633-3096 10WF3 4"
0.500" 8/28/80
N30-3258 OW1 26" 1.343" 1/27/79 E41-3167 8WF1 14" 0.875" 3/25/81 P44-5252 13LS12 2"
0.237" 3/10/81 P44-3048 9WF2 4"
0.300" 3/30/79 (
E41-3172 SW9 10" 0.906" 3/23/81 B21-4229 OW1 10" 1.250" 1/25/80 B21-4411 OW1 12" 0.686" 11/12/80 B21-4230 3W33 12" 0.688" 10/3/80 B21-4403 OW2 12" 0.750" 11/14/80 B21-4406 2W3 12" 0.749" 12/2/80 B21-4411 IW2 12" 0.749" 2/13/80 i
B21-2591 3WF5 12" 0.688" 5/19/81 i
B21-2586 IW2 10" 0.625" 4/23/81
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(2) Liquid Penetrant Examination (PT)
The lab uses Magnaflux materials and receive certifications.
(3) Magnetic Particle Examination (MT)
The lab has one field prod unit and three yokes.
Red and gray Magnaflux magnetic particles are used.
(4) Ultrasonic Examinations (UT)
NES has one ultrasonic instrument and various calibration blocks.
The couplant on site has certifications.
There were transducers and various sizes and MHZ.
(5) Leak Testing (LT), Visual Examination (VT) or Eddy Current Exariration (ET)
Not performed on site.
No items of noncompliance or deviations were identified.
2.
Welding The inspector visually examined the appearance of several weld a.
surfaces including System N21, ISO 2336, weld #4W5R1 and weld 18W0, and also reviewed the following documents for the welds:
(1) Material release.
(2) Process control sheets.
(3) Welder certs.
(4) Weld rod certs.
l (5) Weld filler material issue.
(6) Weld process control traveler.
(7) NDE reports.
(8) Weld repair records.
(9)
WB, Handling, Storage Shipping and Preservation procedure, WB-A-102, Revision 8, dated March 7, 1980.
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a (10) WB, Procurement of Permanent Material, Equipmand and Services i
procedures, WB-A-107, Revision 3, dated October 25, 1978.
(11) WB, GTAW and/or SMAW of P1 Material, Groove Welding 2-1/2" NPS and Larger procedure, WPS-103, Revision 20, dated March 17, 1981.
No items of noncompliance or deviations were identified.
3.
Interpretation of Shop Radiographs The inspector reviewed radiographs and icports of the following shop welds in accordance with ASME Section III, 1971 Edition, Winter 1971 Addenda. Dravo performed the radiographs and the ANI and/or DECO accepted the radiographs.
Line No.
Weld Diameter Thickness Date RT NRC Results B21-2587-2 1366 12" 0.687"/0.787" 7/20/78 Acceptable E51-3175-1 598T 6"
0.482" 4/4/77 Acceptable
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E51-3174-19 2979-C 4" 0.538" 1/7/79 Acceptable T23-4524-4 3064A 20" 0.475" 4/12/79 Accep;able In reviewing the radiographs of the following shop welds, Dravo also performed the radiography in accordance with ASME Section III,1971'
Edition, Winter 1971 Addenda and Bechtel Corporation accepted them for DECO. The inspector found that the wrong penetrameters were used.
These wrong penetrameters are normally used in ASME Section VIII radio-graphy in accordance with paragraph UW-51 and other non-nuclear work.
The correct penetrameters should have been in accordance with ASME Section III,1971 Edition, Winter 1971 Addenda, Appendix IX, paragraph IX-3325 which requires penetrameters be in accordance with ASTM E142.
It is not known to date how many welds were radiographed using the wrong penetrameters. The radiographs met all other Code requirements.
This i, a violation identified in Appendix A.
(341/81/07-01)
Line No.
Weld Dia. Thick.
Date RT NRC Results
A155-KC70CLI HAJ0187 36" 1-3/8" 12/6/72 Unacceptable E51-2192-4 423D 6"
0.692" 6/6/74
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C11-2750-4 449H 4"
0.631" 6/18/74
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C11-2750-1 4460 T
0.538" 6/10/74
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E11-3035-3 452L 6'
O.380" 5/16/74
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G33-3096-12 477D 4"
0.631" 6/4/74
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G41-3669-2 2068D 8"
0.422" 11/2/73
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C11-2756-4 449A 3"
0.438" 12/6/74
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E11-3171-10 363B 12" 0.506" 12/16/74
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E21-3145 a 224A 3"
0.316" 7/11/73
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E11-3153-14 288C 4"
0.337" 7/27/73
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t Exit Interview
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i The inspector met with site representatives (denoted in Persons Contacted paragraph) at the conclusion of the inspection.
The inspector summarized i
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the scope and findings of the inspection noted in this report.
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