ML090560698

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Request for Additional Information, Relief Request -08-001-MX, Revision 0, Regarding Inservice Inspection Program for Fourth 10-Year Interval
ML090560698
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 03/05/2009
From: Farideh Saba
Plant Licensing Branch II
To: Young D
Florida Power Corp
Saba, F E, NRR/DORL/LPL2-2 301-415-1447
References
TAC ME0227
Download: ML090560698 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 5, 2009 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA 1B)

ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 08-001-MX, REVISION 0, INSERVICE INSPECTION PROGRAM FOR THE FOURTH 10-YEAR INTERVAL (TAC NO: ME0227)

Dear Mr. Young:

By letter dated December 10, 2008, Florida Power Corporation submitted Relief Request 08-001-MX, Revision 0 (Agencywide Documents Access and Management System Accession No. ML083590224) for Crystal River Unit 3, requesting relief from the examination frequency requirement of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Table IWL-2521-2 that requires an initial inspection of tendons affected by repair/replacement activities within one year (plus or minus 3 months) following completion of repair/replacement activities.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided and determined that additional information is required in order to complete the evaluation. The NRC staff's request for additional information (RAI) is enclosed.

Please respond to the enclosed RAI within 45 days of the date of this letter. I can be reached at 301-415-1447, if you have any questions.

Sincerely, rtV1J~ b;;;:;~

Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

As stated cc w/encl: Distribution via ListServ

REQUEST FOR ADDITIONAL INFORMATION CRYSTAL RIVER UNIT 3 RELIEF REQUEST 08-001-MX, REVISION 0 INSERVICE INSPECTION PROGRAM FOR THE FOURTH 10-YEAR INTERVAL DOCKET NO. 50-302, LICENSE NO. DPR-72 The Nuclear Regulatory Commission staff has determined that the following information is needed to facilitate the review of Relief Request 08-001-MX, Revision 0, for the fourth 10-year inservice inspection interval at Crystal River Unit 3 (CR-3), submitted by Florida Power Corporation (the licensee) in letter dated December 10, 2008.

1. Please provide the required vertical tendon force according to the CR-3 current licensing basis along with the minimum predicted force, expected during the refueling outage R17 in 2011, for the affected vertical tendons.
2. Based on the information provided in the licensee's letter dated December 10, 2008, 30 vertical tendons will be affected by post-tensioning repair/replacement activities.

If any of these 30 vertical tendons or other tendons in close proximity of the affected tendons were selected for inspection during previous tendon surveillances, please provide results of those inspections.

3. Please discuss if there have been any indications of water intrusion or corrosion in the vertical tendons.

Enclosure

March 5, 2009 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA 1B)

AnN: Supervisor, Licensing &Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708 SUB~IECT:

CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 08-001-MX, REVISION 0, INSERVICE INSPECTION PROGRAM FOR THE FOURTH 10-YEAR INTERVAL (TAC NO: ME0227)

Dear Mr. Young:

By letter dated December 10, 2008, Florida Power Corporation submitted Relief Request 08-001-MX, Revision 0 (Agencywide Documents Access and Management System Accession No. ML083590224) for Crystal River Unit 3, requesting relief from the examination frequency requirement of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Table IWL-2521-2 that requires an initial inspection of tendons affected by repair/replacement activities within one year (plus or minus 3 months) following completion of repair/replacement activities.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided and determined that additional information is required in order to complete the evaluation. The NRC staff's request for additional information (RAI) is enclosed.

Please respond to the enclosed RAI within 45 days of the date of this letter. I can be reached at 301-415-1447, if you have any questions.

Sincerely, Ira!

Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

As stated cc w/encl: Distribution via ListServ Distribution:

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