ML20044G263
| ML20044G263 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/24/1993 |
| From: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Sieber J DUQUESNE LIGHT CO. |
| Shared Package | |
| ML20044G264 | List: |
| References | |
| NUDOCS 9306020248 | |
| Download: ML20044G263 (3) | |
See also: IR 05000334/1993006
Text
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MAY 2 41993
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Docket Nos. 50-334
50-412
Mr. J. D. Sieber
Senior Vice President
Nuclear Power Division
Duquesne Light Company
-Post Office Box 4
Shippingport, Pennsylvania 15077
Dear Mr. Sieber:
SUBJECT: NRC INSPECTION REPORT NOS. 50-334/93-06 AND 50-412/93-06
This letter refers to the announced inspection conducted by Mr. Joseph E. Carrasco of this
office on April 5-9,1993, at the Beaver Valley Power Station, Units 1 and 2. The inspector
discussed the results of the inspection with Mr. D. Spoerry, Mr. G. Thomas and other
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members of your staff at the conclusion of the inspection.
This inspection focused on activities important to the public health and safety and was
directed towards engineering activities with emphasis on the root causes and corrective
actions to address the anomalies observed with the auxiliary feedwater (AFW) system for
Beaver Valley 2 (BV-2) Power Station, including Licensee Event Report (LER) No. 50-
412/93-001-00, " Design Stress for the Auxiliary Feedwater System Exceeded Due to Water
Hammer." In addition, we reviewed your staff's actions to address a Unit I condition
outside the design basis due to MSIV closure not considered in the original design (LER
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No. 50-334/93-001-00).
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Details on the areas examined during the inspection are described in the NRC Region I
inspection report, which is enclosed with this letter. Within these areas, the inspection
consisted of selected examinations of procedures and representative records, interviews with
personnel, and observations by the inspector.
Within the scope of this inspection, no violations were observed. Based on the review of-
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assumptions, methodology and the results of the AFW piping calculations, we concluded that
you have established reasonable assurance for continued operation of the Unit 2 AFW System
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until the next refueling outage. The AFW system walkdown and the Inservice Testing (IST)
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of the AFW check valves, revealed that your staff was taking the proper steps to monitor the
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AFW lines to identify conditions that could cause a water hammer.
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9306020248 930524
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MAY
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Mr. J. D. Sieber
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It is our understanding that the Unit 1 main steam supports and Unit 2 AFW Loop C piping
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will be modified or analyzed to demonstrate that their stresses are within the industry code
allowables specified in the FSAR at the end of your next refueling outage. Please advise us
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if this understanding does not agree with your intended corrective action.
No reply to this letter is required. Your cooperation in this matter is appreciated.
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Sincerely,
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Jacque P. Durr, Chief
Engineering Branch
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Division of Reactor Safety
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Enclosure: NRC Region I Inspection Report Nos.
50-334/93-06 and 50-412/93-06
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cc w/ encl:
G. S. Thomas, Vice President, Nuclear Services
D. E. Spoerry, Vice President, Nuclear Ope 1ations
L. R. Freeland, General Manager, Nuclear Operations Unit
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K. D. Grada, Manager, Quality Services Unit
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N. R. Tonet, Manager, Nuclear Safety Department
H. R. Caldwell, General Superintendent, Nuclear Operations
K. Abraham, PAO (2)
Public Document Room (PDR)
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Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
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NRC Resident Inspector
Commonwealth of Pennsylvania
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State of Ohio
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Region I Docket Room (with concurrences)
SRI, Perry, Region III
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W. Butler, NRR
G. Edison, NRR
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