ML20212E424
| ML20212E424 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/03/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 2NRC-6-072, 2NRC-6-72, 86-08, 86-8, NUDOCS 8608120682 | |
| Download: ML20212E424 (3) | |
Text
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'Af DucpsesneUsht 2NRC-6-072 Beaver Valley No. 2 Unit Project Organf ration EG Su11 ding (412) 643 5200
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July 3, 1986 United States Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406 ATTENTION:
Dr. Thomas E. Murley Administrator SCBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 21C Reactor Coolant Pump Damage / Cleanliness Control Potential Significant Deficiency 86-08 Gentlemen:
On May 16, 1986, Duquesne Light Company (DLC) identified problems po tentially encountered during testing of reactor coolant pump 21C as reportable under the provisions of 10CFR50.55(e).
On June 16, 1986, R. J.
Wa11auer, Lead Compliance Engineer, contacted Mr. L. Tripp, NRC Region I to request an extension in the time allowed for the written report.
The extension was requested to allow management to review the proj ec t evaluations of the concern.
Mr. Tripp approved the extension and requested that the telephone conversation be referenced in this report.
DUQUESNE LIGHT COMPANY By R
J. J. Carey V
Vice President RJW/ ij r Attachments cc:
Mr. P. Tam, Project Manager
- w/ attachment Mr. J. M. Taylor, Director (3)
- w/ attachment Mr. W. Troskoski, Sr. Resident Inspector
- w/ attachment INPO Records Center
- w/ attachment NRC Document Control Desk
- w/ attachment 1
8608120682 860703 PDR ADOCK 05000412
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SUMMARY
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During filling and venting of the reactor coolant ' system ' (RCS), in preparation for hydrostatic testing, reactor coolant pump "C" (RCP-C) was started several times.
Excess vibration was observed during the last run.
The hydrostatic test was completed without RCP-C.
After the hydrotest, the pump was started. for diagnosis by Westinghouse.
Excessive vibration limited the pump run, thus precluding complete diagnosis.
After the "C"
loop was drained for inspection,.a
- broken, site-fabricated steam generator nozzle dam was found lodged in' the impeller of RCP-C.
Other foreign material identified in the RCS included a rag and several plastic plugs from the reactor vessel internals.
II.
Immediate Action Taken Inspections were conducted to evaluate the cleanliness of the RCS, RCP-C. wa s disassembled and internals were sent to Westinghouse for repairs.
On May 16, 1986, Mr.
S.
D.
Hall notified Mr. L. Tripp, NRC Region I, that DLC considered this issue to be potentially reportable under the requirements of 10CFR50.55(e).
III. Description of Deficiency Loss of cleanliness control on RCS resulted in damage to RCP-C.
IV.
Analysis of Safety Implications 10CFR50.55(e) criteria require that the safety impact be considered for ".
each deficiency.
which, were it to have remained _
uncorrected, could have affected adversely. the safety of operations of the nuclear powe r plant at any time-throughout -the expected life time of the pl ant.
Pieces of the broken plate and excessive RCP-C vibration preclude sa fe plant operation without corrective action.
V.
Corrective Action to Resolve the Deficiency-The corrective actions include:
A.
Repairs to the "C" loop reactor coolant pump.
B.
BVPS-2 programs for establishment and control of cleanness zones have been reviewed.
{
C.
FCP 5.1,
" Requirements for Establishing and Maintaining Cleanness Zones",
wa s changed on May 19, 1986.
Changes included in FCP 5.1 include:
written requests for establishment of cleanness zones.
formal notification to concerned personnel of the effective date and area included in new cleanness zones.
Extending security officer control of access to twenty-four j
hours per day /seven days per week.
' E.1.,
Establishrd Zona II rtquirements whsn bracching a pressure boundary of a turned-over system.
D.
FCP 5.0, " General Housekeeping", was changed on June 16, 1986.
E.
Memorandums have been distributed to clariff cleanliness requirements and to emphasize the need for compliance wi th those requirements.
F.
Westinghouse has been asked to address corrective actions with respect to the Reactor Vesel Internals plugs.
VI.
Additional Reports No additional reports are anticipated with respect to this issue.
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