IR 05000280/1990006
| ML18153C146 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/13/1990 |
| From: | Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18153C145 | List: |
| References | |
| 50-280-90-06, 50-280-90-6, 50-281-90-06, 50-281-90-6, NUDOCS 9003210213 | |
| Download: ML18153C146 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report Nos.:
50-280/90-06 and 50-281/90-06 Licens*ee: Virginia Electric and Power Company Glen Allen, VA 23060 Docket Nos.:
50-280 and 50-281 Facility Name:
Surry 1 ~nd 2, Inspection Conducted: February 12-16, 1990 License Nos.: DPR-32 and DPR-37 Inspector: ~
.~ P, t}, (c~.,J<,oS N. Econom~s
Approved-by: l,.L'?(, l../..
. * : r<<.
Scope:
J. J. Blake, Chief Materials and Processes Engineering Branch Division of Reactor Safety SUMMARY This inspection was performed for the purpose of reviewing the licensee's corrective actions(s) on previously identified inspector followup items (IFI)
unresolved items (UNR) and enforcement matters as applicabl *
Results:
The corrective actions were-consistent with the licensee's commitment The records were* readily retrievable, complete, and accurate. Cognizant personnel were made available to review the subject matter and assist in the interpre-tation of nondestructive records, i.e. radiograph Four unresolved items and one inspector followup item were close In the areas inspected, violations or deviations were not identified *
9003210213 9nn~1~
PDR ADOCK b§65o]so Q
..,
- Persons Contacted Licensee Employees REPORT DETAILS D. R. Dodson - Corporate NOE Level III Examiner
- R. C. Bilyeu - Licensing Supervisor
- E. S. Grecheck - Assistant Station Manager
- D. S. Hart - Quality Assurance (QA) Supervisor
- *M. R. Kansler - Station Manager R. J. Scanlan - Senior Staff Licensing Engineer E.W. Throckmorton, Inservice Inspection {ISI)/NDE Service Project
. Engineer
- *T. B. Sowers - Superintendent Engineering D. W. Wong - ISI Engiheer Other licensee employees contacted during this inspection included security force members, technicians, and administrative personne NRC Resident Inspectors
- W. Holland, Senior Resident Inspector
- J. York, Resident.Inspector (
- Attended exit interview 2. Action on Previous Findings (92701) * (Closed) UNR 281/86-34-03 Reactor Nozzle Indications This item was identified because the inspector of record determined that the licensee had not assigned, via written. procedure, a requirement for technical review of in-process and/or final ISI examination report By revision to the procedures listed below, the licensee has addressed the su~ject concern (1) General Requirements for ISI Nondestructive Examination:
NOE Rev. 2 (2) Ninety Day Inservice Inspection Report Virginia Power ISI Manual-Section 7.14 Rev. 3 Also, the completed remote visual inspection of welds discussed for UNR 86-34-02 and.this inspector's review of construction records and radiographs completes the actions requested of and committed by the licensee in this are (Closed)
UNR 280, 281/89-05-03, Sampling of Nonsafety-Related Fasteners for Testing from Construction Warehouse for Bulletin N This item was identified when the inspector of record ascertained that certain safety and nonsafety-related fasteners stored. in t:he warehouse were not included in the sampling submitted for testing per the subject bulletin requirement Consequently, the inspector of record requested, and the licensee agreed to investigate, a) The types and quantity of each group of nonsafety-rel ated fasteners and b) location of equipment where nonsafety-related fasteners were needed~
Within these areas, this inspector reviewed the licensee's QA memorandum 589-141, entitled Response to Station Corrmitment Assignment/Response (SCAR) 89-0105 Commitment 00 This document, was identified as an interim response to the above commitment and described the methodology used by QA to investigate the use of*
nonsafety-related fasteners referenced in Report 280, 281/89-0 On July 26, 1989, the licensee issued a final report on this matte In summation, the July 26 report stated that no nonsafety-related (NS)
fasteners selected as samples for this investigation were traceable to use in safety-related (SR)
or special quality requirement (NSQ)
application (Closed) Inspector Followup Item (IFI) 280,281/88-39-01, Revise WP-W02 Procedure to Address all Line Items on Weld Joint Record This item was identified when the inspector of record noted that the controlled weld joint record (CWJR), used to document quality control inspecti.ons conducted during weld fabrication did not, in all cases, fully identify each of the two components being welde This was noted, even though the line item had been signed-off by This matter was discussed in detail with the licensee (see Report 88-39)
who agreed to revise the subject procedure to include this and other related attributes on the CWJ recor The revised subject procedure was approved for field use on April 17, 198 The inspector reviewed the revised procedure and found it satisfactor (Closed) UNR 280,281/88-39-02~ Fabrication Preservice and Repair Records of Rejected Welds This matter refers to an inspection performed in response to information received from the NRC resident inspector involving rejectable weld indications found in socket welds of the Unit-2 Loop Fill Heade For further details see Report 88-39 paragraph The subject item was identified to assure that certain concerns which the licensee agreed to take action on, were implemente Specifi-ca 11 y these actions were as follows:
(1)
(2)
(3)
(4)
Document in detail the defect removal, evaluation, and measure-
. ments taken during the repair of the rejected weld Following grinding, measure welds, fitting and/or piping to assure design thickness has not been violate Provide original fabrication records of all rejected weld Provide Preservice Inspection records of all rejected welds, as applicabl On January 13, 1989, the licensee submitted a surmnary report which was reviewed in the office by the inspector. * While on site between February 12-16, 1990, the inspector reviewed background information on these welds, nondestructive examination results and evaluations which indicated that none of the indications were service related and had no direct impact on nuclear safet (Closed) UNR 281/86-34-02, QA Records Do Not Agree with Visual Examination Conclusions This item was identified as a result of the October 1986 remote reactor vessel inservice examination of the outlet nozzle-to-safe end, dissimilar metal (DM) welds during which ultrasonic indications were noted in loop 11A 11 (vessel azimuth 144.83 degrees).* These indications were present along the entire inner surface of the wel Meaningful visual examination of the weld's inside diameter condition during the 1986 examination was limited to an air pocket at the top of the wel Based on the results of the limited visual examination and the nature of the ultrasonic responses, it was concluded that these indications were caused by inside diameter weld geometr Review of the fabrication data by the NRC did not indicate weld geometry present in any of the outlet nozzle-to-safe end welds (See Report 88-15, paragraph 3.a.).
As a result of these findings, the NRC was not in complete agreement with the conclusion drawn during the 1986 examination; therefore, requiring that a more conclusive visual examination of the outlet nozzle-to-safe end welds be performe During the Fall 1988 Unit-2 refueling outage, Westinghouse (W) with the aid of a remote control Deep Sea Mini Rover submersible and a high resolution color TV Camera recorded, on video-tape, the physical condition of the root surface of these DM welds for the outlet nozzel s in Loops 11A
,
118 11 and 11C
- On February 14, 1990, this inspector observed the aforementioned video-tape and noted the following:
Field weld #1 on loop A appears to have weld metal added to the I. D. 360°.
The weld metal appeared to be added in a narrow
,,,.
. 4 band at the weld root from 0° azimuth to about 260° azimuth
- (looking from the nozzel into the pipe going clockwise).
At 260°, the weld area appeared to widen and become more pronounce Individual stringer beads were visible from 260° to 0°.
The weld contour was g~nerally rough and made a sha~p re-entry angle into the base metal, on the pipe side *
. Field weld #13 on loop B was built up 360°. * The weld build up was ground flat/flush to slightly conve There were several areas around the build up with an irregular surface condition~
Field weld #25 on loop C was built up in two areas from about 0° to 45° and from 135° to 270°.
The weld build up was ground Flat to slightly conve There were several areas around the build up with an irregular surface condition *
. A review* of construction radiographs confirms the root condition_s described above and explains the ultrasonic indications observed*
during the subject examination~ Exit Interview The Inspection Scope and Results were summarized on February 16, 1990, with those persons indicated in paragraph The inspector described the areas inspected and discussed in detail the inspection result Proprietary information is not contained in this report. Dissenting comments were not received from the licensee.