ML113480146
| ML113480146 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/23/2011 |
| From: | Michael Mahoney Plant Licensing Branch III |
| To: | Allen B FirstEnergy Nuclear Operating Co |
| mahoney, m NRR/DORL/LPLIII-2 415-3867 | |
| References | |
| TAC ME6296 | |
| Download: ML113480146 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 23, 2011 Mr. Barry S. Allen Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING DAVIS-BESSE LICENSE AMENDMENT REQUEST TO MODIFY THE SPECIAL VISUAL INSPECTION REQUIREMENTS OF TECHNICAL SPECIFCATION 5.5.8 "STEAM GENERATOR (SG) PROGRAM" (TAC NO. ME6296)
Dear Mr. Allen:
By letter to the Nuclear Regulatory Commission (NRC) dated May 20,2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML11144A289),
FirstEnergy Nuclear Operating Company (FENOC), submitted a license amendment request for Davis-Besse Nuclear Power Station, Unit No.1 to modify the special visual inspection requirements of technical specification (TS) 5.5.8 "Steam Generator (SG) Program." The proposed amendment would change the TS 5.5.8.g requirements for a special visual inspection of the abandoned-in-place auxiliary feedwater heater to be based upon the results of an eddy current examination, rather than a specific frequency.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on December 15, 2011, it was agreed that you would provide a response within 60 days from the date of this letter.
B. Allen
- 2 The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3867.
~!wy Michael Mahoney, Project Manager Plant Licensing Branch 11/-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1 REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDEMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION REQUIREMENT FOR VISUAL INSPECTION OF THE STEAM GENERATOR DOCKET NO. 50-346 By letter to the Nuclear Regulatory Commission (NRC) dated May 20, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML11144A289),
FirstEnergy Nuclear Operating Company (FENOC), submitted a license amendment request for Davis-Besse Nuclear Power Station, Unit No.1 to modify the special visual inspection requirement of technical specification 5.5.8 "Steam Generator (SG) Program."
Question Related to License Amendment Request
- 1. The proposed license amendment would modify the Technical Specifications (TS) to only require the special visual inspections of TS 5.5.8.g if the eddy current inspections required in TS 5.5.8.d.5 identify a gap of less than % inch between the secured internal auxiliary feedwater header (AFWH) and the inspected peripheral tubes of any steam generator (SG). Given that there may be other indications that the secured internal AFWH has degraded (e.g., detection of loose parts on the top of the tubesheet) or moved (tube-to-header gap of less than a % inch), discuss your plans to revise your proposal to perform the special visual inspections if there is any evidence that the secured internal AFWH has degraded or moved. For example, if the peripheral tube to secured internal AFWH gaps are less than % inch or there is evidence that the header is degrading or has moved, the special visual inspections of the secured internal AFWH, header-to-shroud attachment welds, and external header thermal sleeves shall be performed on the affected SG through the auxiliary feedwater injection penetrations.
Enclosure
- .. ML113480146 Sincerely, IRA!
Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorlLpl3-2 Resource RidsNrrLASRohrer Resource RidsOgcRp Resource RidsNrrDorlDpr Resource NEE-088 OFFICE LPL3-2/PE LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME PHernandez(ABi lIoch Colon for)
SRohre(BTully for)
JZimmerman MMahoney DATE 12/22/11 12/20/11 12/23/11 12/23/11