View source for 3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments

{{Adams
| number = ML20206R617
| issue date = 05/14/1999
| title = Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments
| author name = Roderick D
| author affiliation = FLORIDA POWER CORP.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000302
| license number = 
| contact person = 
| document report number = 3F0599-17, 3F599-17, GL-97-06, GL-97-6, NUDOCS 9905200162
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
}}

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May 14,1999 3F0599-17 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

==Subject:==
Generic Letter 97-06, " Degradation of Steam Generator Internals," Response Update

==Reference:==
FPC to NRC letter,3F0398-06, dated March 30,1998, " Generic Letter 97-06, Degradation of Steam Generator Internals"

==Dear Sir:==

The referenced letter provided Florida Power Corporation's (FPC's) response to Generic Letter (GL) 97-06, " Degradation of Steam Generator Internals." In the letter, FPC committed to I      submit an update within 90 days of the completion of an evaluation [by Framatome Technologies, Inc (FTI)] of Once Through Steam Generators (OTSGs) versus the Electricite de France (EdF) steam generators. This submittal fulfills that commitment. The conclusion in the previous FPC response has not changed based on the evaluation performed by FTI.
An objective of the FTI evaluation was to evaluate the OTSGs relative to the degradation                               ,
reported in the Electric Power Research Institute (EPRI) Report CG-109558, " Steam Generator                          j Internals Degradation: Modes of Degradation Detected in EdF Units," and other domestic                                )
experience. Another objective was to define and identify any mode of degradation to which the OTSGs secondary side may be susceptible to, and to recommend appropriate inspection techniques to monitor such degradation. FTI completed the evaluation and issued a report to the Babcock and Wilcox Owners Group (B&WOG), "OTSG Internals Degradation Evaluation," on February 18,1999.                                                                                                   U i
The evaluation from FTI concluded that OTSG internals are not at risk for failure from similar degradation experienced at the EdF plants. The FTI evaluation recommends no inunediate inspections of the OTSGs for Crystal River Unit 3. Therefore, no immediate secondary side inspections are warranted.                                                                                        ,
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           ' tL ,  , ; ,1 KO 9905200162 990514 PDR      ADOCK 05000302 P                      PDR CRYSTAL RIVER ENERGY COMPLEX: 15760 W. Power une Street
* Crystal Filver, Floride 34428-6708 + (352)795-6486 A Floride Progress Company
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v 3- : U.S. Nuclear Regulatory Commission                                                 Page 2 of 2 3F0599-17
      ,This letter establishes no new regulatory commitments. If you have any questions concerning this submittal, please contact Mr. Sid Powell, Manager, Nuclear Licensing, at (352) 563-4883. l Sincerely, p                                                      ' -
l Daniel L. Roderick, Director Nuclear Engineering & Projects DLR/lyc xc:     Regional Administrator, Region II Senior Resident Inspector NRR Project Manager I
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