IR 05000456/1981007
| ML20009B016 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/25/1981 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20009B001 | List: |
| References | |
| 50-456-81-07, 50-456-81-7, 50-457-81-07, 50-457-81-7, NUDOCS 8107140663 | |
| Download: ML20009B016 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-456/81-07; 50-457/81-07 Do'ket Nos. 50-456; 50-457 Licenses No. CPPR-132; CPPR-133 c
Licensee: Commonwealth Edison Company Post Office Fox 767 Chicago, I~
60690 Facility Name: Braidwood Station, Units I and 2 Inspection At: Braidwood Site, Braidwood, IL Inspection Conducted: June 3-5, 1981 6.?v 0 4-Inspector:
C. M. Erb
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uut AM /9 fI d~
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m Approved By:
D. H. Danielson, Chief I8
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Materials and Processes Section Inspection Summary Inspection on June 3-5, 1981 (Reports No. 50-456/81-07; 50-457/81-07)
Areas Inspected: Documentation review and observation of pipe restraints and structural supports; observation of welding of primary coolant pipe welds; documentation review and observation of process pipe penetrations.
This inspection invclved a total of 18 inspector-hours onsite by one NRC inspector.
Results: Of the areas inspected one apparent violation was idcntified.
(Inadequate cleanliness of NSSS equipment - Paragraph 2.b corrective action was taken by the licensee before the inspection was complete.
Consequently, no reply to this violation is required.)
8107140663 810630 PDR ADOCK 05000456
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DETAILS Persons Contacted Commonwealth Edison Company (CECO)
- R. Cosaro, Site Construction Superintendent
- T. R. Sommerfield, QA Superintendent
- D. A. Brown, Quality Assurance
- J. Merwin, Project Construction
- C. D. Gray, Project Construction
- M. A. Gorski, Quality Assurance Engineer
- W.
Carlson, Project Construction
- S. C. Hunsader, Quality Assurance
- L. J. Tapella, Quality Assurance Other Personnel J. Perryman, Site QC Supervisor, Newberg Brothers M. Dal Canton, Superintendent Iron Workers, Newberg Brothers B. Widman, General Foreman, Phillips Getschow Company A. Rubino, Manager, Quality Control, Phillips Getschow Company
- Denotes those attending the exit interview.
Functionai or Program Areas Inspected 1.
Documentation Review and Observation of Installation of Structural Supports - Units 1 and 2 a.
Teledyne Brown Engineering Company fabricated the supports for the main coolant pumps and steam generators. Certifications were examined and chemical and mechanical properties were acceptable to the various procurement specifications. Tubing, plates, bolts, pins, and nuts were subject to charpy impact tests which were acceptable. Steel plate and other items were furnished to the requirements of ASME Section III, Subsection NF, 1974 Edition, Summer 1975 Addenda, and Code Cases 1644-4 and N-1160.
A reactor coolant pipe restraint, drawing No. 22286, was observed.
l This restraint, and the supports met S&L Specification FL-2797.
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The specification was approved by a Registered Structural l
Engineer in the State of Illinot ASTM A-325 and ASTM A-490 l
bolts were used to attach stru.tural shapes together. A Carbo l
Zinc No. 11 coating material br..
3een applied in all areas requiring paint.
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b.
The W procedure for setting up major NSSS components was checked.
l This procedure requires that the reactor vessel be set to proper elevation and azimuth and then all attached equipment, such as I
steam generators and primary coolant pumps can be set to proper dimensions.
j No items of noncompliance or deviations were identified.
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A 2.
Observation of Welding of Primary Coolant Pipe Welds - Units 1 and 2 The following welds were observed, some in process and some a.
after completion.
Plant Identification Weld No.
Weld Procedure Unit 1 Line M196 LP2 FW9 WP-1 AMA 88, Rev. 10
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Unit 1 Line M196 LP2 FW10 WP-1AMA88, Rev. 10 Unit 1 SI4F FW6 WP-1AMA88, Rev. 10 Unit 2 SI4 FW3A 50% Complete WP-1AMA88, Rev. 10 Unit 2 SI4 FW3B 50% Coaplete WP-1AMA88, Rev. 10 Unit 2 M1962LP1 FW10 WP-1AMA88, Rev. 10 The above welds were made using a consumable insert. A root radiograph and then an in process radiograph at \\ inch intervals are taken by PTL for information on the primary recirculation loops. Radiographs to Procedure RT-QC-RT-1, Revision 11 are taken for final acceptance.
In Unit 1, the cover passes have been made by the automatic GTAW welder, which saves grinding time for the required surface finisi.
b.
While examining the Unit I reactor loop piping, the inspector noticed that both inlet and outlet openings in the loop 4 steam generator were uncovered. The loop 1 steam generator tad an open inlet and the top of the loop 4 main coolant Iump asing was open. Further examination revealed two worn out flapper wheels and many cigarette butts in the loop 4 generator while the other generator had dirt and some scraps of paper lying in it.
The main coolant pump casing was open with a platform suspended about eight feet below the top which had drawings or newspapers on it.
There was no evidence that work was in progress which required these NSSS systems to be open.
Licensee management and QA personnel were notified and corrective action was begun immediately. The contractor was instructed to remind his personnel of the requirements for cleanliness and closures over openings. The steam generator plenums were cleaned out and temporary closures were fabricated for the openings. This is an apparent violation that was cor-rected during the inspection. No reply is required.
3.
Process Pipe Penetrations, Observation of Work Activities and Documentation Review - Units 1 and 2 Many of the penetrations were fabricated by Gulf and Western Company while some of the guard pipe to end piece welds were made onsite by Fid111ps Getschow Company.
The specification for these penetrations is Sargent and Lundy L-2787, with the code requirements being ASME Section III, 1974 Edition, Summer 1976 Addenda. The N-stamp is an NPT-2, MC since the process pipes are Class 2 and the guard pipe to disc weld being part of the containment seal are MC.
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i Documentation and hardware for the following penetrations were examined.
Identification Process Line Overall Size Weld IPC-65 1" & 3/4" drain 12 3/4" x 7' 1" stainless steel to carbon steel
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IPC-69 3" off gas 18" x 6' 9" carbon steel to
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carbon steel IPC-66 12" safety 34" x 7' 10" carbon steel to injection carbon steel The smaller penetrations are made by welding a disc tc the outside guard pipe. This MC weld is a full penetration weld and was made using a backing ring.
he backing ring can not be removed, and meaningful radiography is not possible. Volumetric examination for inservice inspection is required and ultrasonic examination (UT) is the only inspection method remaining. However, there are two difficulties with UT (1) backing ring, and (2) dissimilar welu material in many dimensional c>r.ligurations are found in the penetrations. Presently this is an open item with the licensee while steps are being taken to develop the necessary calibration blocks and procedures for the UT.
This is an unresolved item (456/81-07-01).
Unresolved Items
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Unresolved item; are matters about which more information is required in order to ascertain whether they are acceptable items, items of concompli-ance, or deviations. One unresolved item disclosed during the inspection is discussed in Paragraph 3.
Exit Interview The inspector met with licensee representatives (denoted in Persons Contacted paragraph) on June 5, 1981. The inspector summarized the purpose and findings of the inspection, which were acknowledged by the licensee.
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