ML20150B183
| ML20150B183 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/11/1988 |
| From: | Cowles R, Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-002-00, 88-2, NUDOCS 8803160219 | |
| Download: ML20150B183 (5) | |
Text
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- Potential Loose Parts in Feedwater Sparger Nozzles Due to Lef tover Construction Debris -
Soecial Penort 88-00?
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On February 26, 1988 the Inservice Inspection (ISI) group performed a visual surveillance inspection of the reactor vessel feedwater spargers.
During the course of this inspection, two (2) pieces of wire were observed to be lodged in sparger nozzles.
An action plan was developed to retrieve the wires and perform other followup actions required by Regulatory Guide 1.133.
The wires were subsequently removed using a remotely operated tool guided by an underwater camera.
Upon retrieval, the wires were examined.
One of the wires appeared to be.032 gauge stainless steel wire, approximately 3 inches in total
- length, and the other a
tig weld rod approximately 5 inches long.
The retrieved pieces had a
measured contact radiation reading of 15 mren/hr, and after examination on the refueling floor, were discarded as radwaste after determining that the pieces
- were, most
- probably, construction debris.
A visual inspection of the vessel annulus deck area was conducted, and no further debris was noted.
Additionally, an evaluation of past thermal and hydraulic core performance was conducted to determine if any identified anomalies could be attributed to the wires beina lodged in the sparger nozzles.
The evaluation concluded that no anomalies could be attributed to the presence of the wires.
This Special Report is being submitted pursuant to the requirements of Regulatory Guide 1.133 because the wires were classified as potentially loose parts in the reactor vessel.
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- m..nm PLANT AND SYSTEM IDENTIFICATION General Electric - Boiling Water Reactor (BWR/4)
Nuclear Boiler / Reactor Vessel (EIIS Designation: AC)
Loose Parts Monitoring System (EIIS Designation: II)
IDENTIFICATION OF OCCURRENCE Potential Loose Parts In Feedwater Sparger Nozzles Due To Leftover Construction Debris - SPECIAL REPORT 88-002 Event Date:
02/26/88 Event Time:
0800 This Special Report was initiated by Incident Report 88-031 CONDITIONS PRIOR TO OCCURRENCE Plant in OPERATIONAL CONDITION 5 (Refuelina), ISI inspection of vessel internals in progress.
DESCRIPTION OF OCCURRENCE On February 26, 1987 the Inservice Inspection (ISI) group performed a visual surveillance inspection of the reactor vessel feedwater spargers during the course of refueling operations.
This inspection revealed that two (2) pieces of wire were lodged in sparger nozzles.
One wire was located in the 90 degree sparger, extreme right (clockwise lookino down) nozzle, and the other was located in the 150 degree
- sparger, fifth nozzle from the left end.
Meetings were held on 2/26 and 2/27/88 to determine the proper course of action for retrieval of the wires and other followup actions as required by Regulatory Guide 1.133.
APPARENT CAUSE OF OCCURRENCE After the wires were retrieved, a visual examination of the wires for composition and possible origin was conducted on the refueling floor.
It was concluded that the wires were residual construction debris that were not flushed out of the feedwater header during pre-operational testing prior to initial criticality in 1986.
A_J LA 1 Y S I S O F O C C U R R E N C E 1 The following analysis is presented in the chronological order of events, after the initial determination that a potential loose part in the vessel existed:
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03 0F 0 l4 f tKT ff sucre asses e mensen mee em MeC #c,su W3,IIM ANALYSIS OF OCCURRENCE (CON'T) 2/26/88, 0730:
The discovery of the wire sections was brought to the attention of station management by the ISI department.
Systems Engineering and ISI reviewed a video tape recording of the discovery.
The wire in the 90 degree sparger appeared to be a
small gage bare wire across the face of the nozzle, and the wire in the 150 degree sparger appeared to be a flux covered welding rod, bent in half and resting against the back wall of the nozzle.
2/26/88, 1100:
A meeting was held with Reactor Engineering, Systems Engineering, the refueling Shift Manager, General
- Electric, ISI, and the Maintenance Department in attendance to establish responsibilities for removal of the subject wires.
It was determined that General Electric would perform the actual removal, with the other groups providing direction and support as necessary.
At another meeting later in the day, it was decided that retrieval would commence on 2/27/88 at a time to be determined based on the refueling bridge availability and the least impact on the outage schedule.
2/27/88, 2000:
General Electric commenced retrieval of the subject wires.
The small gage bare wire was removed
- first, followed by the apparent welding rod.
After removal, all pieces were placed in a basket and raised to the refueling floor for examination.
The bare wire appeared to be approximately.032 gauge stainless steel
- wire, about 3
inches long.
The second piece was confirmed to be a 3/32 ER-7053 tig weld rod, about.5 inches long.
The retrieved pieces had a combined measured contact radiation reading of 15 mrem /hr, and after examination, were discarded as radwaste after determining that the pieces
- were, most probably, construction debris.
The sparger is an ASME component, therefore, a
deficiency report was initiated to document the findings.
The disposition of the DR constitutes the corrective actions listed in this report.
This is the first documented occurrence of a potentially loose part in the vessel at Hope Creek.
An evaluation of past thermal and hydraulic core performance was preformed to determine if any identified anomalies could be attributed to the prescense of the retrieved pieces of wire in the sparger
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M w w m4.nm ANALYSIS OF OCCURRENCE, CONT'D The evaluation concluded that no anomalies could be attributed to the discovered condition.
This report is made subjr,ct to the requirements of Regulatory Guide 1.133 because the wires were classified as potentially loose parts in the reactor vessel.
CORRECTIVE ACTIONS 1.
The two wire pieces were removed and examined.
2.
An underwater inspection of the reactor vessel annulus deck area was conducted to ascertain that no other construction debris had accumulated in the vessel.
3.
An evaluation of past thermal and hydraulic core performance was conducted as previously described.
Sincerely, ff) ff:w S.
LaBruna General Manager-Hope Creek Operations RBC/
SORC Mtg.88-038 I
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O PSEG Public Sernce Electric and Gas Company P.O. Box L Hancocks Bridge, New Jersey 08038 Hope Creek Operations March 11, 1988 U.,
S. Nuclear Regulatory Commission Dccument Control Desk Washington, DC 20555
Dear Sir:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT NO. 1 SPECIAL REPORT 88-002-00 This Special Report is being submitted pursuant to the requirements of Regulatory Guide 1.133.
Sincerely, S.
LaBruna General Manager -
Hope Creek Operations RBC/
Attachment SORC Mtg.88-038 C Distribution 1
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The Energy People 8/
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