ML19318B020
| ML19318B020 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/23/1980 |
| From: | Hancock J FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19318B019 | List: |
| References | |
| CS-80-125, NUDOCS 8006240573 | |
| Download: ML19318B020 (2) | |
Text
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- G; b M3 23 April 1980 Power 3-o-3-a-2 co no u no =
CS-80-125 Mr. J. P. O'Reilly, Director Docket No. 50-302 USNRC Office of Inspection & Enforcement License No. DPR-72 101 Marietta St., Suite 3100 Ref:
RII:NE Atlanta, GA 30303 50-302/79-25
Dear Mr. O'Reilly:
The following is offered in response to the concerns of Mr. Nick Economos of your office in regard to Inspector Followup Item number 79-25-01.
During the 1979 refueling outage, the NRC requested that certain weldments in the emergency feedwater, and the main feedwater systems, be radiograph inspected prior to plant startup. This inspection was performed prior to the June 25, 1979 IE Bulletin 79-13, i
Cracking in Feedwater System Piping, which required radiographic in-spections of all feedwater pipe welds inside containment.
The results of the supplemental inspection of June 16 - 19, 1979 of a total of sixteen (16) welds, disclosed no evidence of service-related indications.
Fabrication related ir.dications were noted in three (3) main feedwater welds (weld #FW-130B, MK-124 to 125, and NK-132 to 133).
Commitments were then made by the plant staff to perform two (2) ad-ditional ISI inspections of these welds, so plant startup would not be delayed.(Inspector Followup Item 79-25-01)
After investigating the feedwater nozzle cracking problems experienced by plants with welded feedwater nozzles, and discussions with the NRC,
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Revision 2 of IEB 79-13 was issued by the NRC on October 16, 1979. This revision excluded plants with steam generator designs utilizing Auxiliary Feedwater Systems connected by means of bolted flange connections and where feedwater levels are maintained essentially constant with no inter-mittent cold auxiliary feedwater injections being utilized during plant startup, from performing the required radiographic inspections, specified in 2.b of the Bulletin.
Because of the controls placed on the use of auxiliary feedwater during startup, CR-3 was not required to do any additional radiograph inspections required by IEB 79-13.
Based on the acceptance of the construction related indications by the original construction code and due to the controls which reduce service related OTSG problems placed upon the use of auxiliary feedwater at CR-3, it is proposed that no additional radiographic examinations be performed on feedwater welds FW-130B, MK-124 to 125, and MK-132 to 133, except those welds which are scheduled for normal inservice inspection.
8006240 U3 g,
General Office 32o1 Thiri, :ourin street south. P.O Box 14042, st Petersburg, Florida 33733 81 6-5151
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..,.., ' :.a t,,..,e-lJ. P. O'Reilly Ref: RII:DRQ/79-25
-Page 2 The normal inservice inspection program will be used to monitor the integrity of the welds in the feedwater system and will be used i.o de-tect service related problems.
If there are further questions, please-contact us.
Very truly yours, FLORIDA POWER CORPORATION M
h AN Nuclear Plant Manager J. A. Hancock, Asst. Vice President Nuclear Operations JC/rc L
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