ML20140B635
| ML20140B635 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 09/10/1985 |
| From: | Williams J TOLEDO EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 1-569, CAL-85-03, CAL-85-3, NUDOCS 8601270067 | |
| Download: ML20140B635 (2) | |
Text
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i TOLEDO
%mus EDISON Docket No. 50-346 JOE WILUAMS. JR.
License No. NPF-3 senor vce mmm-azwar
[419)249-2300
[419j 2494223 Serial No. 1-569 September 10, 1985 Mr. James G. Keppler Regional Administrator United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr. Keppler:
On April 26, 1985 your office issued Confirmatory Action Letter (CAL) 85-03 (Log No. 1-1154) regarding the auxiliary feedwater pump turbine steam supply (AFPTSS) piping system supports and hangers at the Davis-Besse Nuclear Power Station Unit No. 1.
Item 3 of CAL 85-03 discussed the planned performance of an inservice testing program for the AFPTSS piping system under cold and hot operating conditicas during which support and hanger loadings and displacements would be measured. Toledo Edison planned to utilize these measurements in performing system reanalysis and potential engineering modifications to address the problem of support and hanger degradation. This degradation is believed to be a result of water slug forces created by steam condensing in the cold (ambient temperature) piping during initial steam flow into the piping. The inservice testing program has not been performed primarily due to the plant shutdown result-ing from the June 9, 1985 loss-of-feedwater event.
Toledo Edison is considering maintaining the AFPTSS piping system hot with steam up to newly installed turbine steam admission valves whenever the plant is in Modes 1, 2 or 3.
This would eliminate the situation of the AFW system being put into service under cold conditions. Toledo Edison is presently performing the engineering that would be necessary to accommodate thie operational configuration change.
In addition, operational and main-tenance changes, such as ensuring the adequate drainage of condensate from the piping system prior to the introduction of steam, would be made. As a result, the AFPTSS piping system would no longer be maintained and operated in the same manner under which the hanger and support degradation occurred.
In light of these potential system changes, Toledo Edison discussed, with Mr. Harrison of your Staff on August 22, 1985, the status of CAL 85-03, Item 3 regarding the performance of the inservice testing program. This subject was discussed further with Messrs. Danielson and Yin of your staff 8601270067 850910 PDR ADOCK 05000346' G
PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 3T MADISON AVENUE TOLEDO. OHIO 43652
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Docket No. 50-346
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License No. NPF-3 Serial No. 1-569 September 10, 1985 Page 2 by telephone on August 26, 1985. Messrs. Danielson and Yin concurred that, if the operational and maintenance configuration of the piping is modified, Toledo Edison need not perform the inservice testing program pravided confirmatory testing is performed on the AFPTSS piping system
'.ollowing completion of these modifications. The purpose of this confirmatory testing would be to confirm that excessive piping movements and subsequent support or hanger degradation would'no longer occur on the AFPTSS piping system.
Accordingly, should the operational and maintenance configuration of the AFPTSS piping be modified, Toledo Edison will perform AFPTSS piping system confirmatory testing prior to exceeding Mode 3 from the present shutdown in lieu of the inservice testing program of CAL 85-03.
Test procedures:
(including personnel interface and instrumentation location) and calibration I
procedures for displacement-measuring instrumentation will be developed and j
implemented for this confirmatory testing. Evaluation criteria for j
displacement measurements would be based on the calculated safe shutdown-earthquake (SSE) values.
Very truly yours, hh:!?0::^^:,
- DRW:lah cc: DB-1 NRC Resident Inspector J. J. Harrison, NRC Region III I. N. Jackiw, NRC Region III l
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