IR 05000269/1982003
| ML20042B201 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/02/1982 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20042B199 | List: |
| References | |
| 50-269-82-03, 50-269-82-3, 50-270-82-03, 50-270-82-3, 50-287-82-03, 50-287-82-3, NUDOCS 8203250083 | |
| Download: ML20042B201 (8) | |
Text
,
,.
.
/
- o$
UNITED STATES F~ -
^ 3, NUCLEAR REGULATORY COMMISSION
$
E REGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 g
ATLANTA, GEORGIA 30303
- .c Report Nos. 50-269/82-03, 50-270/82-03 and 50-287/82-03
. Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: Oconee Nuclear Station Docket Nos. 50-269, 50-270 and 50-287 License Nos. DPR-38, DPR-47 and DPR-55 Inspection at Ocon e si near eca, SC d@ [2'
Inspector:
/_
_ ec%/wu -c c
N. Econom'
/ Dap igned Approved by:
-
[
_ c1 A. R. Herdt, Section Chief
'Date Signed Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on January 19-22, 1982 Areas Inspected This routine, unannounced inspection involved 33 inspector-hours on site in the areas of inservice inspection. procedure review, program review, record review, work observation, seal replacement 2AIRC pump, reactor vessel internals inspec-tion.
Results a
No violations or deviations were identified.
-
8203250083 h20304
'
PDR ADOCK 05000269 G
-
.
.
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. E. Smith, Station Manager
- R. J. Brakcett, Station Senior QA Engineer
- C, B. Cheezem, Inservice Inspection Engineer
- R. T. Bond, Techncial Service Engineer J. Crowe, QA, NDE/ Welding T. Cribbe, License Engineer R. Rettew, Associate Engineer J. J. McCool, QA Superveillance Supervisor Other Organizations Babcock and Wilcox, Nuclear Power Generation Division (NPGO)
H. W. Stoppelmann, ISI Coordinator / Level II Examiner W. M. Laughlin, ET Level II Interpreter NRC Resident Inspector
- 0. O. Myers
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 22, 1982, with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings
,
Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort a.
Remote Visual Inspection of RPV Thermal Shield Bolts.
At the time of this inspection B&W was conducting a remote visual inspection of the RPV thermal shield bolts in order to determine existing conditions prior to removing and replacing them as was done in Unit 1 earlier. The inspector observed the video tape recording and confirmed an earlier report by the licensee which indicated that two
_
-
_
_ _
_
_
__
_
..
.
-
.
bolts (4 and 37) had been found cracked and that a shock pad (core
_ catcher) mounted on the lower grid assembly on the lower grid flanse,
>
appeared to' be only partially fastened.
Af ter completion of the inspection effort the inspector learned through a telephone conversa-
!
tion with the _ licensee representative that they had found 19 bolts i
cracked and_three(3) broken. More ~ details on the cause of failure will be reported in subsequent inspection. reports as this information becomes available.
t
Within the areas inspected, no violations or deviations were identi-fled.
b.
Seal Replacement 2A1 RC Pump.
Quality records an'd maintenance procedures used to document removal and installation of 2A1 RC pump seal were reviewed. The replacement was performed on work request No. 952568 under NSM #0N1542 Revision 2.
Procedures specific to this task also used as operational checkoff i
lists and QA hold points included the following:
MP/2&3/A/1310/14 Removal
-
MP/2&3/A/1310/12
-
Reassembly MP/2&3/A/1310/14
-
Replacement Quality records for the replacement seal QA tag #31859 and 0-ring QA tab #18662 were reviewed for compliance with applicable B&W specifi-cation CS-3-36-1 requirements, completeness and accuracy.
The licensee's nuclear safety evaluation checklists disclosed no new unreviewed safety questions as covered by the Stations FSAR or the Technical Specification.
Within the areas inspected no violations or deviations were identified.
6.
Inservice Inspection - Program Review (Unit 2)
The inspector reviewed the licensee's Inservice Inspection (ISI) program (Plan) for the current outage in the areas of: program approval; QA program requirements including organizational structure; audit requirements; general QA requirements (examination reports, control of_ deviations from established program; quality documentation and identification of components); work and
_
quality inspection procedures; control of processes; corrective action; document control; control of examinations and examination equipment; quality records; inspection scope; inspection intervals; personnel qualifications;-
and, NDE records including provisions for storage. The applicable code for
,
the ISI is the ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition, with Addenda through the Summer of 1975.
The Plan, which is applicable to the three Oconee units, had been approved by the QA Manager of Operations on November 10, 1981.
In addition to the aforementioned Code, Regulatory Guides 1.14, 1.83, and 1.150 have been invoked with certain provisions delineated in the applicable procedures and
,
,
w-
--
,
,,-w
,
, - - - -
--
- -,
-,
-
g-
, --
.
.
the stations Technical Specification, Volume 1. Revision 4 of the Plan lists requests for relief from code required examinations and, augmented in-service inspection, i.e., RC Pump Flywheel, OTSG tube eddy current testing.
The list of relief requests included the following:
Date Submitted Serial to No.
Description Licensing 009 Core Flood Nozzle-To-Safe-End and Safe-End To 5-1-81 Pipe Welds 010 Reactor Coolant Pressure Boundary 5-1-81 011 Reactor Coolant System Piping Branch Connections 5-1-81 012 Reactor Vessel, Pressurizer, Steam Generating 5-1-81 Cladding 013 C1.2 Piping Welds, Pressure Boundary 5-1-81 014 9" and 13" Thick Basic T Calibration Block 5-1-81 Volume 2 Revision 4 Appendices C and D identify items subject to ISI and examination schedule.
Administrative (QA) procedures contained and/or referenced in the Plan include the following.
QA-513 Revision 0
" Control of PSI /ISI Plans" QA-504 Revision 8
"QA Records Operations" QA-508 Revision 4
" Certification of QC Inspectors Operations" QA-509 Revision 6
" Preparation and Issue of QC Procedures" Within the areas inspected no violations or deviations were identified.
7.
Inservice Inspection, Procedure Review (Unit 2)
B&W's procedure governing the ISI of components listed in ASME Code Section XI, under IWE-2000 IWC-2000 were approved by B&W's Level III, NDE examiner and the licensee's QA representative for use during this interval and the current ten (10) year, fifth (5th) unit outage.
Areas subject to examination during this outage, as specified in Tables IWB-2500 /S!C 2500, were 21ected for review to ascertain whether the speci-fied category, method of examination and coverage were delineated and consistent with applicable code requirements. These areas were as follows:
-
.
.
IWB 2500 Category Item RPV welds in beltine region B-A 1.1 Welds in Vessels B-B 1.2 Vessel to Flange & Head to Flange B-C 1.3 Partial Penetration Welds in Vessels B-E 1.5 Ligament Areas G-G-1 1.8 Following are ISI, NDE procedures reviewed for technical content relative to the latest revisions. An earlier review in these areas has been conducted and documented in Reports 50-270/79-38 and /80-34.
151-240, Rev. 12 Penetrant Examination of Welds and Base Materials Including Studs and Nuts ISI-270, Rev. 9 Wet or Dry Methods of Magnetic Particle Examination of Welds, Studs, Bolts, and Pump Motor Flywheels ISI-416, Rev. 3 Multifrequency Eddy Current Examination of OTSG Tubing in Series 177SG(s). Codes: ASME III 1977; V, Articles 7 and 25; XI through S75.
151-131, Rev. 6 Remote UT examination Using the Aris. Codes: ASME XI (74S75), V Article 4, (77S78) except for cali-bration T-432.3.2 and recording criteria T-441.9.1.
- ISI-163, Rev. 0 UT Measurements of Steel or Bolt Preload Using the Pulse - Overlap Techniques.
- This was the initial review for this procedure and the review was in the areas of compilation of required records and procedure technical content relative to: type of apparatus, extent of coverage including beam angles and scanning techniques, calibration requirements, search units, DAC curves, reference level for monitoring discontinui;ies, method cf demonstrating penetration, levels for evaluation and recording indications, and acceptance standards.
Within the areas inspected, no violations or deviations were identified.
8.
Eddy Current (EC) Examination of Once Through Steam Generator (OTSG) Tubes (Unit 1)
ISI activities during this refueling outage (5th) included the eddy current (EC) examination of tubes in both "A" and "B" OTSGs. Data acquisition and analysis was being performed by B&W personnel.
B&W approved procedure, ISI-416, devision 3 which referenced R.G. 1.83 R/1 was the governing docu-ment.
The inspector observed the examination of tubes 117 - 108, 103 -98, 109 - 103, 81 - 72,110 - 103,114 - 107,106 - 97,109 - 101, and 113 - 105 and the 4-hour calibration check performed at 9: 45 a.m. on January 21, 1982 on OTSG "A" Subsequent discussions with the licensee disclosed that two l
.
.
tubes in OTSG "A" and 7 in OTSG "B" required plugging - these are listed below:
Tube Location of Indication
% of Wall Violated 0TSG "A" 106-116
43%
107-118
42%
OTSG "B" 89-30 12th Support Plate 48%
97-32 12th Support Plate 45%
104-33 12th Support Plate 59%
110-52 12th Support Plate 50%
114-65 12th Support Plate 68%
119-42 12th Support Plate 50%
119-62 12th Support Plate 44%
After completion of this inspection effort the inspector learned through a telephone discussion with the licensee's representative that the inspection involved 2926 tubes in OTSG "A" and 3600 in OTSG "B".
l In addition to the aforementioned work observation, the inspector reviewed quality records of EC calibration standards on site, equipment certifica-tions and personnel qualifications. Technicians performing the examination appeared to be thoroughly familiar with procedural requirements and ade-quately qualified to perform their assigned tasks.
Within the areas inspected, no violations or deviations were identified.
9.
Inservice Inspection - Observation of Work and Work Activities (Unit 2)
The inspector observed the ISI activities described below to determine whether these activities were being performed in accordance with regulatory requirements and licensee procedures. See paragraph 6 above for applicable code ( s).
Personnel qualification records for one Level I, two Level II and one Level III examiner were reviewed.
=
In process ultrasonic (UT) inspection of welds FIG. C2. 01. 052 and C2.01.050 were observed and compared with the requirements of the applicable j
procedure and code in the following areas:
l (1) Availability of and compliance with approved NDE procedures (2) Use of knowledgeable NDE personnel (3) Use of NDE personnel qualified in the proper level j
(4) Recording of inspection results (5) Type of apparatus used (6) Extent of coverage of weldment l
(7) Calibration requirements
'
(8) Search units (9) Beam angles
!
t l
t
..
.
(10) DAC curves (11) Reference level for monitoring discontinuities (12) Method of demonstration of penetration (13) Limits for evaluating and recording indications (14) Recording significant indications (15) Acceptance limits Within the areas inspected no violations or deviations were identified.
10.
Inservice Inspection - Data Review and Evaluation (Unit 2)
Selected NDE records generated during this outage were reviewed to ascertain whether they contained information through documentation or by reference in the areas of: examination results, examination equipment, certification (s),
calibration data sheets, evaluation of indications, extent of examination, programmatic deviations, disposition of findings and identification of NDE material, e.g., UT couplant, penetrant materials, etc. Records selected for this review were as follows:
. Radiography Fig. C2.01.082 Weld #2-01A-16-X5 12" x.562" Slag indi 4. ions between '.tions 2-3 forwarded to Level III for disposition.
Ultrasonic Examination 2A1 Pump Suction B4-05-089 Pipe to Elbow Weld: 2-50-7.1-30 84-05-090 Elbow to Pipe 2-50-7.1-34 2A2 Pump Suction 64-05-091 Elbow to Pipe Weld: 2-50-7.1-17 B4-05-092 Pipe to Elbow 2-50-7.1-20 Low Pressure Inj_ection C2.01-007 Reducer to Valve Weld: 2-53B-17.1-124 C2.01-010 Valve to Pipe 2-53B-17.4-82 C2.01-013 T to Pipe 2-53B-14.4-83 e
....
-
Magnetic Particle Pressurizer 82.08.001A Integrally Weld
.
82.03.003A Supports B2.08.005A B2.08.007A Liquid Penetrant Decay Heat (Suction)
C2.05.004 Integrally Welded 1" linear indica-Pipe Support tions documented for disposition on NCI-0720 Within the areas inspected, no violations of deviations were identified.
a