ML20076F794
| ML20076F794 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/31/1983 |
| From: | Wilgus W FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-SSINS-6820 3F-0583-19, 3F-583-19, IEB-83-03, IEB-83-3, NUDOCS 8306140437 | |
| Download: ML20076F794 (3) | |
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C0#POpatso4 May 31,1983 3F-0583-19 Mr. James P. O'Reilly Regional Administrator, Region 11 U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement 101 Marietta Street, N.W., Suite 2900 Atlanta, Ga. 30303
SUBJECT:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 IE Bulletin No. 83-03 Check Valve Failure in Raw Water Cooling Systems of Diesel Generators
Dear Mr. O'Reilly:
This letter is in response to IE Bulletin 83-03, dated March 10, 1983, concerning the inspection of check valves in the diesel generator cooling water system.
Licensees were requested to submit a report to the NRC within 90 days of the date of the bulletin, which lists the applicable check valves and describes the valve integrity verification procedure methods and schedule. This report was also to include the history of previous check valve failures.
All applicable valves in the flow path of the diesel generator cooling water are noted on the attachment. These valves will be examined for integrity by one of the following methods:
(1)
By removing the valve from the piping and visually inspecting the disk integrity, or (2)
By removing the valve bonnet and visually inspecting the disk integrity.
These inspections have been incorporated into the existing diesel generator inspection as an interim change and will be performed during the current refueling outage which began on March 19,1983. The interim change will be added to the revised IST program prior to the next refueling outage, r306140437 830531 PDR ADOCK 05000302 i
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[ l General Office 3201 in rty sourtn street souin. P.O. Bou 14042. St. Petersburg. Florida 33733 e 813-866-5151 L
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l 3F-0583-19 Page 2 Maintenance records were reviewed in detail and reflected no history of failure of any type regarding the subject valves.
Sincerely, W. S. Wilgu9 Vice President Nuclear Operations BCT/mm Attachment cc:
Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555
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ATTACHMENT l
EMERGENCY DIESEL EGDG-1A i
D3V-1 Suction to standby coolant pump i
D3V-17 Suction to standby coolant pump l
D3V-27 Outlet of jacket coolant radiator l
D3V-29 Outlet of Jacket coolant radiator D3V-31 Outlet of temperature control valve to tube oil cooler inlet D3V-38 Outlet of the radiators to combustion coolers EMERGENCY DIESEL EGDG-1B D3V-2 Suction to standby coolant pump D3V-18 Suction to standby coolant pump D3Y -23 Outlet of jacket coolant radiator D3V-30 Outlet of Jacket coolant radiator D3V-32 Outlet of temperature control valve to lube oil cooler inlet D3V-39 Outlet of the radiators to combustion coolers