IR 05000269/1991005
| ML15224A772 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/02/1991 |
| From: | Blake J, Chou R, Coley J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A771 | List: |
| References | |
| 50-269-91-05, 50-269-91-5, 50-270-91-05, 50-270-91-5, 50-287-91-05, 50-287-91-5, NUDOCS 9104240023 | |
| Download: ML15224A772 (14) | |
Text
V REGU4 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, @
ATLANTA, GEORGIA 30323 Report Nos.: 50-269,270,287/91-05 Licensee:
Duke Power Company Docket Nos.: 50-269, 50-270 License Nos.: DPR-38, DPR-47 and 50-287 and DPR-55 Facility Name: Oconee Inspection conducted:
March 4-8, 1991 Inspectors:
J.Date Signed R. ou DUTate g Approved by:
6(,/
3. J lake, Chief Date Signed Mat rals and Processes Section Engineering Branch Division of Reactor Safety SUMMARY Scope:
This routine unannounced inspection was conducted in the areas of inservice inspection -
observation of work and work activities, review of complete records, and pipe snubber inspectio Results:
The inspectors'
review of inservice inspection activities revealed that management was involved in assuring quality, and resolution of technical issues from a safety standpoint were being handled effectively. This was exemplified most noticeably in the area of eddy current evaluation where examination data was conservatively reviewed, personnel were skilled and knowledgeable of the examination method, and computer equipment software was the state-of-the-ar The quality of radiographic film used for inservice examination of ASME Class 2 welds was also very goo However, inattention to details was noted by the inspectors as delineated in non-cited violation 50-287/91-05-02 concerning placement of radiography penetrameters paragraph 2.a, unresolved item 50-269, 270,287/91-05-01 concerning improper gap between washers and snubber rod bearings paragraph 4.,
and inspector follow-up item 50-287/91-05-03 concerning completeness of MT records paragraph In the areas inspected, one non-cited violation was identified, no deviations were identifie PDR ADOCK 05000269 G
REPORT DETAILS 1. Persons Contacted Licensee Employees
- H. Barron, Station Manager 3. Bauman, Supervisor, Eddy Current
- B. Carney, Jr., Senior Engineer
- T. Coleman, Inservice Inspection (ISI) Coordinator T. Hilderbrand, Supervisor, Eddy Current Acquisition
- 0. Kohler, Licensing Coordinator
- F. Linsley, Maintenance Engineer
- B. Milisap, Manager, Maintenance Engineering
- R. Morgan, Director, Quality Assurance (QA)
Perry, Licensing Coordinator 3. Warren, Supervisor, QA Other licensee employees contacted during this inspection included engineers, technicians, and administrative personne Other Organizations Babcock & Wilcox R. Neyman, Supervisor, Eddy Current Analysis R. Barnes, Level III Analyst, Eddy Current Examination D. Honeycut, Level IIA, Analyst, Eddy Current Examination NRC Resident Inspector
- B. Desai, Resident Inspector
- Attended exit interview 2. Inservice Inspection - Observation of Work and Work Activities (73753)
Unit 3 The inspectors observed work activities and reviewed documents and records, as indicated below, to determine whether ISI was being conducted in accordance with applicable approved examination procedures, regulatory requirements, and licensee commitment The applicable code for the Unit 3 ISI is the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME B&PV)
Code,Section XI, 1980 edition with addenda through Winter 198 Unit 3 is presently in the second interval and 12th outag The third period of the second interval starts on March 12, 199 Nondestructive examination personnel are Duke employees with the exception of eddy current analysis where Babcock & Wilcox examiners perform the
-
2 primary review and Duke Power examiners perform the second revie A combination of Babcock & Wilcox and Duke examiners form a final evaluation team when differences are noted between the primary and second review evaluation result Review of Radiographic Film for ISI Class 2 Welds The inspectors reviewed radiographs for the welds, listed below to determine whether they were radiographed and evaluated in accordance with Duke's approved Radiograph Procedure, NDE-12, Revision 8, for preservice and inservice inspectio Weld ID N Item.N Size Comments 1 3-03A-17-22A 6"Dia.x.562" SAT C05.021.201 3-01A-10-6 12"Dia.x.562" 5-0 Penny in Weld C05.021.385 3-03-3FWD-62-B 20"Dia.x1.031" 0-1 Penny in Weld C05.021.304 1-2 Penny in Weld 2-3 Penny in weld 3-4 Penny in Weld 4-5 Penny in Weld 5-0 Penny in Weld 3-O1A-9-15 12"Dia.x.562" 0-1 Penny in Weld C05.021.383 1-2 Penny in Weld 2-3 Penny in Weld 3-4 Penny in Weld 5-0 Penny in Weld 3-0IA-10-1 36"Dia.xl.164" SAT C05.022.017 3-01A-3M520B-B 24"Dia.x.967" 1-2 Penny in Weld C05.021.363 2-3 Penny in Weld 3-4 Penny in Weld 4-5 Penny in Weld 5-6 Penny in Weld 6-7 Penny in Weld 7-0 Penny in Weld 3-O1A-10-1 36"Dia.x1.164" SAT COS.021.380
Weld ID N Item N Size Comments (cont'd)
3-01A-23-07 26"Dia.x.875" 0-1 Penny in Weld C05.021.358 1-2 Penny in Weld 2-3 Penny in Weld 3-4 Penny in Weld 4-5 Penny in Weld 5-6 Penny in Weld 6-7 Penny in Weld 7-0 Penny in Weld 3-01A-23-05 26"Dia.x.875" 0-1 Penny in Weld C05.021.353 1-2 Penny in Weld 3-4 Penny in Weld 4-5 Penny in Weld 5-6 Penny in Weld 6-7 Penny in Weld 7-0 Penny in Weld 3-03-27-15 24"Dia.x1.128" 0-1 Penny in Weld C05.021.310 1-2 Penny in Weld 2-3 Penny in Weld 3-4 Penny in Weld 4-5 Penny in Weld 3-03-28-14 14"Dia.x.750" 0-1 Penny in Weld C05.021.305 1-2 Penny in Weld 2-3 Penny in Weld 3-4 Penny in Weld 4-5 Penny in Weld 5-0 Penny in Weld 3-01A-23-05 26"Dia.x.875" SAT C05.022.005 3-O1A-23-07 26"dia.x.875" 0-1 Penny in Weld C05.022.007 NOTE 1:
PENNY=PENETRAMETER As noted above several, radiographic examinations were made in violation of radiographic procedure, NDE-12, Rev. 8, paragraph 14.1.6, and the ASME Code (80W80)
requirements, in that, image quality indicators (penetrameters) were placed on the weld. However, in every case the inspectors could accurately evaluate the area of concer In addition, the 1983 edition of the ASME Code allows the penetrameter to be placed in the weld, provided the numbers or the letter F for film side penetrameters are not in the area of interest. In none of the radiographs reviewed by the inspectors were the numbers or letter F in the area of interest. This discrepancy resulted from the
fact that Duke uses two radiographic procedures, NDE-10 which is'for plant modification welds and is written to the 1983 edition of ASME Code, and NDE-12 which is for ISI welds and written to the 80W80 edition of the Code, and the examiners performing the radiography and the examiner evaluating the film were not attentive to procedural details when they conducted their examination The above violation was reported to the licensee as non-cited violation (NCV)
50-287/
91-05-02, "Failure to Follow Procedure for Placement of Radiographic Penetrameters."
This violation was not cited because the criteria specified in Section V.A of the Enforcement Policy were satisfied in that, the violation was not intentional; had no safety significance; the licensee immediately wrote a Problem Investigation Report on the item (3-091-0016)
and conducted training for all radiographic examiners on the procedural requirements and the differences between the two approved procedure With the exception of the above violation the inspectors observed that the radiographic techniques used by Duke Power and the quality of the radiographs were very goo b. Liquid Penetrant Examination The inspectors observed while an examiner performed a liquid penetrant examination on Weld No. 3PDB2-11 (Item No. B051.011).
This was a Class 1, 3.5-inch diameter nozzle to safe-end wel The inspectors'
observations were compared with Duke Power's Liquid Penetrant Examination Procedure No. NDE-35, Revision 13 and the ASME B&PV Code. The test was performed in a satisfactory manne c. Volumetric Examination of Steam Generator Tubes Using the Eddy Current Technique The inspectors reviewed the following applicable procedures used by Babcock & Wilcox (B&W) and Duke Power Company (DPC) for acquisition and evaluation of eddy current examination dat Eddy 360 Analysis Instruction (B&W)
-B&W Procedure for Inspection of Roll Expanded Plugs In 0.625" OD Steam Generator Tubing Dwg. No. 1196093A-B&W Nuclear Service Procedure ISI-418 Rev. 7, "Technical Procedure For The Multifrequency Eddy Current Examination of OTSG Tubing in Model 177 Steam Generators"
-B&W Nuclear Service Procedure ISI-430 Rev. 6, Eddy Current Examination of Sleeved OTSG Tubes"
-B&W Nuclear Service Procedure ISI-469, Rev. 3 "Technical Procedure for the Evaluation of Eddy Current Data of Roll Expanded Sleeve OTSG-Tubing" SII
-B&W Nuclear Service Procedure ISI-444, Rev. 0 "Technical Procedure for the ID Profiling of OTSG tubing in 177 Steam Generator Using Zetec's Tubesheet Profilometry Software"
-B&W Nuclear Service Procedure ISI-460, Rev. 15, "Technical Procedure for the Evaluation of Eddy Current Data of Nuclear Grade Steam Generator Tubing"
-B&W Nuclear Service Procedure ISI-462, Rev. 4, "Technical Procedure for Evaluation of Eddy Current Data for Debris, Sludge, and Secondary Side Loose Parts in Steam Generators"
-DPC Eddy-Current Acquisition Procedure NDE-701, Rev. 1, "Multi-frequency Eddy Current Examination of Steam Generator Tubing at McGuire, Catawba, and Oconee Nuclear Stations"
-DPC Eddy Current Acquisition Procedure NDE-707, Rev. 1, "Multi frequency Eddy Current Examination of non-Ferrous Tubing Using a Motorized Rotating Pancake Coil"
-B&W Nuclear Service Procedure ISI-476, Rev. 0, "Evaluation of Eddy Current Data for non-Ferrous Tubing Motorized Rotating Pancake Coil"
-B&W Dwg. No. 1208553, "Procedure for Inspection of Explosive Welded Plugs in.625" OD Steam Generator Tubing" In addition to the above review, the inspectors concurrently evaluated recorded eddy current data with B&W Level III and IIA Analysts for the following rotating pancake coil (RPC) and bobbin coil examinations in steam generators A and B:
Steam Generator Exam Analyst Row Tube Tape N Method A-D.H. L-IIA
.60
143 outlet Bobbin Coil A-D.H. L-IIA 102
143 outlet Bobbin Coil A-D.H. L-IIA
4 143 outlet Bobbin Coil A-D.H. L-IIA
43 143 outlet Bobbin Coil A-D.H. L-IIA 128
143 outlet Bobbin Coil A-D.H. L-IIA
68 143 outlet Bobbin Coil B-R.B. L-III
77 127 inlet Bobbin Coil B-R.B. L-III
76 127 inlet Bobbin Coil B-R.B. L-III
67 127 inlet Bobbin Coil B-R.B. L-III
66 127 inlet Bobbin Coil B-R.B. L-III
56 127 inlet Bobbin Coil B-R.B. L-III
99 127 inlet Bobbin Coil B-R.B. L-III
96 127 inlet Bobbin Coil B-R.B. L-III
95 127 inlet Bobbin Coil B-R.B. L-III
113 127 inlet Bobbin Coil B-R.B. L-III
114 127 inlet Bobbin Coil
Steam Generator Exam Analyst Row Tube Tape N Method (cont d B-R.B. L-III
112 127 inlet Bobbin Coil B-R.B. L-III
110 127 inlet Bobbin Coil B-R.B. L-III
109 127 inlet Bobbin Coil B-R.B. L-III
108 127 inlet Bobbin Coil B-R.B. L-III
96 127 inlet Bobbin Coil B-R.B. L-III
94 127 inlet Bobbin Coil B-R.B. L-III
59 127 inlet Bobbin Coil B-R.B. L-IIA
63 128 outlet Bobbin Coil B-D.H. L-IIA
68 128 outlet Bobbin Coil B-D.H. L-IIA
69 128 outlet Bobbin Coil B-D.H. L-IIA
70 128 outlet Bobbin Coil B-D.H. L-IIA
80 128 outlet Bobbin Coil B-D.H. L-IIA
83 128 outlet Bobbin Coil B-D.H. L-IIA
91 128 outlet Bobbin Coil B-D.H. L-IIA
77 128 outlet Bobbin Coil B-D.H. L-IIA
74 128 outlet Bobbin Coil B-D.H. L-IIA
69 128 outlet Bobbin Coil B-D.H. L-IIA
75 128 outlet Bobbin Coil, B-0.H. L-IIA 99100 74 128 outlet Bobbin Coil B-D.H. L-IIA 100
128 outlet Bobbin Coil B-0.H. L-IIA 101
128 outlet Bobbin Coil B-R.N. L-1II
9 Explosive Plug 360 MRPC outlet B-R.N. L-III
15 Explosive Plug 360 MRPC outlet B-R.N. L-III
16 Explosive Plug 360 MRPC outlet B-R.N. L-III
21 Explosive Plug 360 MRPC outlet A-R.B. L-III
1 15th Tube Support 360 MRPC Plate A-R.B. L-III
6 13th Tube Support 360 MRPC Plate A-R.B. L-III
1 Upper Tube Sheet 360 MRPC Secondary Face A-R.B. L-III
3 14th Tube Support 360 MRPC Plate A-R.B. L-III
129 12th Tube Support 360 MRPC Plate The above evaluations were conducted in a conservative, thorough, and professional manner by knowledgeable B&W examiner Equipment and computer software were state-of-the-art. The examinations revealed that the tubes in A&B steam.generator were in very good condition and that plugging efforts should be minima '0I d. Visual Inspection of ISI Pipe Supports The inspectors randomly selected 22 pipe supports for a walkdown reinspection. The 22 pipe supports in various systems are located in the Reactor Building, Turbine Building, and Auxiliary Building. The inspection results were compared with the applicable procedure, QAL-14, Revision 11, "ISI Visual Examination, VT-3 and VT-4," dated October 1, 199 The visual inspection included a check on configuration; defects such as distortion, cracks, or bent members, or weld failures induced by operation; condition of connections to supporting structures; and/or component setting The inspectors'
observations generally agreed with the information reported by the licensee's ISI examiners except for the discrepancies as noted below:
Support N Rev. N Discrepancies 3-O1A-0-2480A-H1A
A temporary pulley hung over this support, inside of the end attachment, on top of the spring can. The licensee agreed to remove this pulley and require that QC reinspect this suppor A-6-2401B-H1O
The load readings from the spring can were recorded in the wrong location of the inspection sheet. The licensee will revise the A-3-0-2435B-SR6
This support was installed with two spring cans which were not shown on the drawings. This discrepancy was identified by the licensee's QC inspecto During this refueling outage, the licensee's QC inspector identifed that Support N A-3-0-2435B-SR6 was installed with two spring cans instead of the two rods required by the drawing This is another example of wrong support installation in addition to the one found in Unresolved Item 50-287/90-31-01 and this will be added into that unresolved ite Within the areas inspected, one non-cited violation (paragraph 2.a)
was identified. No deviations were identifie.
Review of Completed ISI Records (73755) Unit 3 The inspectors reviewed the completed surface examination records listed below to determine whether the NDE data covered the scope of the examinations required during the current inspection period. In addition, the records were reviewed to verify the method, extent, examination technique and certification of personnel conducting the examinations; equipment used; and disposition of inspection finding Liquid penetrate examination records for the following welds were reviewed:
Weld N Item N PHB-13 B05.051.015 3PHB-14 B05.051.016 3PHB-15 B05.051.017 3-51A-69-26A-B09.021.040 3-51A-61-43 B09.021.119 3-51A-61-44A B09.021.0120 3-RPV-CRD-62WH9 B14.010.005 3-RPV-CRD-62-W60 B14.010.006 3-RPV-CRD-62 B14.010.007 3-RPV-CRD-W61 B14.010.008 Magnetic particle examination records for the following welds were also examined:
Weld N Item N Comments 3SGA-WG-23-1 C02.021.001A Record did not indicate technique used, AC/DC current, or if field indicator was used 3-01A-H7A C03.040.014 Same as above 3-OA-H1A C03.040.018 Same as above 3-03A-17-22A C05.021.201A AC or DC yoke not indicated 3-03-3FWD-62-B C05.021.304A AC or DC yoke not indicated 3-03-28-14 C05.021.305A AC or DC yoke not indicated 3-03-27-15 C05.021.310A AC or DC yoke not indicated 3-03-27-25 C05.021.316A SAT 3-03-27-25 C05.021.317A AC or DC yoke not indicated 3-03-27-25 C05.021.353A AC or DC yoke not indicated The above records have been completely reviewed and signed off by the Code Inspector and the ISI Coordinato As noted above 9 of 10 Magnetic Particle examination reports were incomplet The inspectors did not consider this item to be safety-signficant but rather inattention to detail by the applicable personne Inspector Follow-up Item 50-287/91-05-03,
"Incomplete MT Records" was issued on this item to re-verify record completeness during a subsequent outag Although several instances of
inattention to detail were identified this outage, the safety significance was very mino However, they are indicators of weaknesses that could create serious problems if not properly manage Within the areas examined, no violations or deviations were identifie. Snubber Inspection and Testing (70370) Unit 3 All snubbers in the safety-related sytems and non-safety related systems required to protect safety-related systems in each unit are required to be operable, and 100 percent inspected, 10 percent functionally tested during the refueling outage per Technical Specification (TS) 3.14 and 4.1 TS 4.18.1 states that snubbers located in the accessible areas can be inspected during normal operation, while those located in the inaccessible areas, are to be inspected during refueling outage Procedure No MP/3/A/3018/010 for hydraulic'snubbers and MP/3/A/3018/019 for mechanical snubbers are used in the inaccessible areas. Procedure Nos. MP/3/A/3018/
011 for hydraulic snubbers and MP/3/A/3018/020 for mechanical snubbers-are used in the accessible area The licensee had completed visual inspection on all the snubbers during or before this refueling outag The licensee found only snubbers in Support Nos. 3-01A-0-2481B-H2A and 3-01A-0-2401B-R14 to have reservoir leakage and issued Work Requests (WR)
53405K and.53745K to fix the The NRC inspectors conducted independent visual examination verification on 27 snubbers at random. Six hydraulic and eight mechanical snubbers were located in inaccessible area Four hydraulic and nine mechanical snubbers were located in the accessible area These examinations were conducted in order to evaluate the adequacy of the examination procedures being used by the licensee and to assess the validity of the information reported by the examiner These verification examinations generally agreed with the findings of the visual examiners except as noted below with the licensee's remedies:
Mechanical or Accessible Discrepancies/
Support N Hydraulic Area Comments/Remedies 3-O1A-4-0-2403D-R1O Mechanical Yes Design cold setting is 6" (+/-1" for tolerance). The as-found cold setting was 3 1/16".
Design engineer will revie II
Mechanical or Accessible Discrepancies/
Support N Hydraulic Area Comments/Remedies (cont'd 3-07A-6-0-2400A-H72 Mechanical Yes A 5/8" gap was found between the spacer washer and bushing bearing on the load pin of the pipe clamp. Work Request 53409K was issued to repair i A-3-803E245-1-R3 Hydraulic Yes 1. Oil leaks on the reservoi Work Request 53749K was issued to repair i. A nearby hanger for a fire protection line is broken and contacting this hydraulic snubbe The licensee will repair this fire protection hanger based on Work Request 53750 O1A-4-2-0-2403D-R4 Hydraulic Yes A excessive gap was found between spacer washer and bushing on the pipe clamp. The licensee's engineer will inspect and if necessary, write a Work Request for repai O1A-0-2401B-R5 Hydraulic Yes The bushing is 3/16" out of plac Work Request 53751K was issued to restake the bushin Ill)
Mechanical or Accessible Discrepancies/
Support N Hydraulic Area Comments/Remedies (cont'd)
3-03-2480A-H6036 Mechanical No The design cold setting is 3".
The as-found cold setting was 3 1/2".
The licensee will check the setting during preopera tional checkou A-H6038 Mechanical No 1. "S" dimension measured was apparently out of tolerance. A bolt and nuts were loose on pipe clamp. 3. A 3/16-"
gap was found on the top washer and bushin The licensee will resolve all above discrepancies in Work Request 53408 A-H1 Hydraulic No The adjacent support, 3-51-0 2481A-EWD-1701, contacted the extension 'piece of this snubber. The licensee's engineer will review and fix i A-H9 Hydraulic No The design cold setting is 4 1/8" with +/-1/2" tolerance. The as-found cold setting wa /16".
The licensee's engineer will revie During the snubber inspection, the inspectors observed that the licensee's snubber examiners measured the "S" dimension which is the net end opening near the load pin between the two clamp ear The measurements were not recorded since the inspection sheet does not have a line to check if it is acceptable or no The licensee's examiners used their judgement to determine if it is acceptable or not,'rather than recording the dimension to compare with the "S" dimension shown in the manufacturerer's applicable catalog The purpose of measuring the "S" dimension is to confirm that the as-found "S" dimension is within the 1/16" construction tolerance with the requirements of the catalog The inspectors discussed this "S" dimension measurement with the licensee's snubber engineers who said that the criteria of the "S" dimension measurement plus +/-1/16" construction tolerance was recommended by the manufacturer after consulting with them about the gap proble During the snubber inspection, documented in the report for Inspection 90-13, on May 14-18, 1990, the NRC inspectors noted that the licensee's applicable procedures did not have acceptance criteria for, nor did it require inspection of the gap between the bushing and washer at the rod end near the rear bracket or the piston rod eye near the pipe clamp Conceivably, with an excessive gap, the snubber movement or impact due to the pipe movement could cause damage to the rods or pins. During the last inspection documented in Inspection Report 90-31, on October 15-19, 1990, the licensee used a 1/4" - gap tolerance as temporary inspection guidelines, with plans to establish an adequate gap tolerance in the procedure and inspect the snubbers. Pending the licensee's establishment of a tolerance for the gap between the bushing and washers this item is identified as Unresolved Item 50-269,270,287/91-05-01, Improper Gap Between Washer and Snubber Rod Bearin The licensee inspected two PSA-100 snubbers, per the manufacturer's request, during this outage and found them to be acceptable. The purpose of this inspection was to identify possible defective ball screw plating if high friction is encountere The licensee had completed all snubber functional testing which included 11 hydraulic and 14 mechanical snubbers, plus a recheck of snubbers installed during the last outag The snubbers rechecked on Support No. 3-01A-3-0-2403D-DEO07A failed due to lock u The licensee will fix and evaluate i All snubbers functionally tested were satisfactory except as stated abov Within the areas inspected, no violations or deviations were identifie. Exit Interview The inspection scope and results were summarized on March 8, 1991, with those persons indicated in paragraph The inspectors described the areas inspected and discussed in detail the inspection results listed belo Proprietary information is not contained in this repor Dissenting comments were not received from the license (Open)
Unresolved 'Item 50-269,270,287/91-05-01, Improper Gap Between Washer and Snubber Rod Bearing, paragraph (Open/Close)
Non-cited Violation 50-287/91-05-02, Failure to Follow Procedure for Placement of Radiographic penetrameters, paragraph (Open)
Inspector Follow-up Item 50-287/91-05-03, Incomplete Magnetic Particle Records, paragraph 3.