IR 05000456/1989027
| ML19332C509 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/20/1989 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19332C503 | List: |
| References | |
| 50-456-89-27, NUDOCS 8911280208 | |
| Download: ML19332C509 (5) | |
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U.S. NUCLCAR REGULATORY COMMISSION
REGION III
Report No. 50-456/09027(DRS)
Docket No. 50-456 1.icense No. NPF-72 Licensee: Commonwealth Edison Company Post Office Box 767
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Chicago, IL 60690 Facility Name:
Braidwood Station, Unit 1 Inspection At:
Braidwood Site, Braidwood, Illinois Inspection Conducted: September 25, October 11, 19, 26-27, and November 14, 1989
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Inspector:
K. D. Wa d
// /20/91 Date staalw Approved By:
D. H. Danielson, Chief
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Materials and Processes Section trate Inspection Sumary l -
. Inspection On September 25, October 11.19,26-27, and November 14, 1989 (Report No. 50-456/89027(DR5))
Areas Inspected: Routine, unannounced safety inspection of inservice l
inspection (ISI) activities including review of programs (73051), procedures L
(73052), observation of work activities (73753), and data review (73755).
Results: No violations or deviations were identified. Based on the results
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of the inspection, the NRC inspector noted the following:
The first ISI program planning was adequate and stayed on schedule.
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The program had strong management support and was implemented with
approved, workable procedures.
The ISI contractor personnel were very knowledgeable, and utilized state
of the art equipment.
The licensee had an adequate ISI staff that was well trained and competent.
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DETAILS 1.-
Persons Conta,gted a
I Connonwealth Edison Company (Ceco)
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- R. Querio Station Manager
- D. O'Brien, Technical Superintendent
- J. Kuchenbecker, Assistant Technical Staff Supervisor
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- R. Francocar. ISI Group Leader
_ H. Sears, Technical Staff ISI Coordinator i.
- C, Barrett, Technical Staff ISI
- F. LeSage, QA Engineer c
- P. Holland, Regulatory Assurance
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- E. Carrol, Regulatory Assurance
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R. Lemke, Technical Staff Supervisor j.-
B. Wilson, Level III NDE L
U.S. Nuclear Regulatory Commission (NRC)
- T. Taylor, Resident Inspector
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T. Tongue, Senior Resident Inspector G. Van Sickel, Resident Inspector Hartfnrd Steam Boiler Engineering and Insurance Company (HSB)
- W. Caldwell, ANII
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Westinghouse Electric Corporation (W)
B. Humphries, Site Supervisor Ebasco Services Incorporation (EBASCO)
J. Sengenberger, HDE Supervisor The NRC inspector also contacted and interviewed other licensee and contractor personnel.
- Denotes those present at the exit interview November 14, 1989
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'2.
Inservice Inspection (ISI) Unit 1 a.
Review of Program (73051)
Ebasco Services Incorporated and Westinghouse Electric Corporation performed the ISI in accordance with ASME Section XI,1983 Edition -
Summer 1989 Addenda. There was sufficient organizational staff to
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ensure that acceptable ISI work was performed. Where ASME requirements were determined to be impractical, specific relief
requests were requested from NRR in writing. The NRC inspector reviewed the specific relief requests including the related correspondence between the licensee and the NRC. The NRC inspector reviewed audits /surveillances of ISI activities conducted by '
qualified personnel to verify compliance with the ISI program.
No violations or deviations were identified.
c.
Data Review and Evaluation (73755)
The examination data was within the criteria as outlined in the applicable NDE procedures and ASME Code requirenents. The NRC inspector's review included examination of documents relating to NDE equipment, data, and evaluations. The eddy current examinations (ET) cov red 100% of all accessible tubing within the steam generators (SG). The NRC inspector reviewed the ET reports and found them acceptable. The total number of tubes plugged in each
SG, including factory and baTeline plugging are as follows:
SG Factory Baseline This Outage Total Plugs
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A
3
9 B
0
2 C
8
8 D
1
1 During this outage all the SG mechenical plugs were Westinghouse,
Inconel 690, heat number NY6441 HK. No sleeving was performed this outage.
No violations or deviations were identified.
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d.
Observation of Work Activities (73753)
The NRC inspector observed work and had discussions with personnel
during the ISI activities. These observations included the following:
(1) EBASCO personnel performing magnetic particle examinations on the following:
Weld No.
ISO No.
Reinforcement Ring Weld No. 27A IMS-04 Reinforcement Ring Weld No. 27B IMS-04 Pipe Weld No. 20 IMS-04
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(2) EBASCO personnel performing ultrasonic examinations on the following:
Weld No.
ISO No.
t Pipe Weld No. 20 IFW-11 Pipe Weld No. 39 105-07
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Pipe Weld No.
105-03 i
(3) A Ceco QA individual performing surveillance of the heat treating of the U-bends in the steam generators.
(4) A CECO QC individual performing surveillance of Ebasco personnel e
examining welds with the magnetic particle method.
(5) Westinghouse personnel performing eddy current examinations on SG tubes in A, B., C, and D SG's.
(6) Westinghouse personnel evaluating the eddy current examinations l
data with the MIZ-18 equipment.
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(7) Westinghouse personnel using the video probe for examining the top of the tube sheets secondary side looking fo* loose
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parts and to determine the general condition of the tubes.
l (8) Westinghouse personnel heat treating rows 1 and 2 U-bends in the Westinghouse Model D-4 steam generators.
The Unit 1 Model D-4 generator tubing is mill annealed Inconel 600
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which was not thermally treated after being formed into U-Bends.
The Unit 2 D-5 steam generator tubing is also Inconel 600 tubing,
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however, it was thermally treated at the factory.
In addition, this model received thermal stress relief of the U-bend area on the first
seven rows after bending.
In those models generators which did not receive stress relief of the inner rows after bending, cracking of the rows 1 and 2 U-Bends usually begins with the first few cycles, i
To alleviate this problem Westinghouse was contracted to perform in place U-bend stress relitf of rows 1 and 2 tubing for the Model D-4 steam generators. This totals 228 tubes per steam generator.
The process involved placing an induction heater into the U-Bend area of each tube and heating it to approximately 1400'F, for a soak time of 5 minutes. With the time required to ramp up to the proper temperature and cool down, a complete cycle runs a) proximately 30 minutes per tube. Laboratory tests qualified tie process so that tubes could be stress relieved up to three times before any reanalysis was required. After all stress relief was complete, eddy current
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examination was again used to verify that the proper area of the tube t
was heated. This examination was also used to verify the tube had not i
been damaged during the heating process.
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The NRC inspector reviewed the qualifications and certifications of all inspection personnel on site to ensure conformance with SNT-TC-1A.
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No violations or deviations were identified.
3.
Exit Interview (30703)
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i The NRC inspector met with site representatives (denoted in paragraph 1)
g at'the conclusion of the. inspection.. The NRC inspector summarized the
scope and' findings of the inspection noted in this report. The NRC
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inspector also discussed the likely informational content of the
inspection report with regard to docunents or processes reviewed by the
NRC inspector during the inspection. The licensee did not identify any
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such documents / processes'as proprietary.
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