ML092370669

Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Unit Plant, License Renewal Application

ML092370669
Person / Time
Site:	Crystal River
Issue date:	09/22/2009
From:	Robert Kuntz License Renewal Projects Branch 2
To:	Franke J Progress Energy Florida
KUNTZ R, NRR/DLR/RPB2 415-2989
References
TAC ME0274
Download: ML092370669 (6)

Text

September 22, 2009 Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B)

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

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION (TAC NO. ME0274)

Dear Mr. Franke:

By letter dated December 16, 2008, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3733 or by e-mail at robert.kuntz@nrc.gov.

Sincerely,

/RA/

Robert F. Kuntz, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

As stated cc w/encl: See next page

ML092370669 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB2:DLR NAME IKing RKuntz DWrona RKuntz DATE 09/16/09 08/31/09 09/22/09 09/22/09

REQUEST FOR ADDITIONAL INFORMATION CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION DOCKET NUMBER 50-302 RAI 2.4.2.1-1 The watertight sleeves around the raw water sump vents that protect the Auxiliary Building (AB) at an elevation of 95 ft against flood levels up to an elevation of 129 ft are listed as additional components required for local protection in the Crystal River Unit 3 Nuclear Generating Plant (CR-3) AB final safety analysis report (FSAR) Section 2.4.2.4. This commodity/component is not listed in Table 2.4.2-1 of the CR-3 license renewal application (LRA) for the AB. Please justify its exclusion from the scope of license renewal.

RAI 2.4.2.3-1 As mentioned in the CR-3 LRA, the borated water storage tank (BWST) and shield wall structure include an attached reinforced concrete structure that has been abandoned but contains several components that are included in scope of license renewal, as stated in the CR-3 LRA on page 2.4-15. Clarify if this abandoned structure has been included in scope or justify its exclusion as having no impact, especially on the flood barrier capabilities on the adjacent structures that are included in scope of license renewal and therefore subject to an aging management review (AMR).

RAI 2.4.2.3-2 STYROFOAM' covers a full range of extruded polystyrene building products used primarily for insulation of floors, walls and roof systems. Please clarify if the one inch thick STYROFOAM' filler, located in the gap between the concrete missile barrier and side of the borated water storage tank, is included in scope of license renewal or justify its exclusion from the scope of license renewal.

RAI 2.4.2.3-3 The BWST is listed as a Class 1 structure per CR-3 FSAR, Section 5.1.1.1. Its foundation is made of reinforced concrete and its primary use is to support and provide missile protection to the BWST which is a mechanical component. Please clarify if this Class 1 reinforced concrete foundation is completely above grade or else justify why the below grade concrete is not listed in Table 2.4.2-3 of the CR-3 LRA, as in scope of license renewal and subject to an AMR.

RAI 2.4.2.4-1 Both bridges forming the cable bridge span the discharge canal and provide support for electrical circuits required to mitigate a postulated station blackout (SBO) event. The SBO ENCLOSURE

conduits are considered to be within the cable bridge structure from where they exit the ground on one side to cross the bridge to where they re-enter the ground on the other side of the bridge. Due to the proximity to a body of water and the entrance/exit of electrical cables required to mitigate an SBO event, from the ground and their supports, please indicate if there are any seals, gaskets or any other applicable flood barriers or insulation that should be included in Table 2.4.2-4 of the CR-3 LRA, and therefore subject to an AMR.

RAI 2.4.2.4-2 In Table 2.4.2-4 for the cable bridge section of the CR-3 LRA, the cable tray, conduit, heating, ventilation, and air conditioning (HVAC) ducts and tube tracks are listed as being in scope of license renewal and therefore subject to an AMR. Please clarify if the HVAC ducts system component supports are needed and included in scope of license renewal or justify its exclusion from Table 2.4.2-4 of the CR-3 LRA.

RAI 2.4.2.8-1 Protection of the intake structure during a postulated probable maximum hurricane peak tide is provided by a cut-off wall extending downward into the competent caprock at the entrance to the structure (See CR-3 FSAR 2.4.2.4). Please confirm that this wall is considered part of the intake structure and thus included in scope of license renewal or else justify its exclusion from the scope of license renewal.

RAI 4.5-1 The fourth column of the first row in CR-3 LRA, Table 4.5-1, Summary of Tendon Data, lists the tendon force value extrapolated to the end of the period of extended operation for dome tendons as 1255 kips. However, in CR-3 LRA, Figure 4.5-1, Projected Force in Dome Tendons, the trend line based on individual lift-off forces from surveillance data indicates that the projected lift-off force in the dome tendons at the end of the period of extended operation (i.e., 63 years after initial tensioning) would be approximately 1330 kips. Please explain the discrepancy between the projected tendon force values at the end of the period of extended operation in the dome tendons indicated in CR-3 LRA, Table 4.5-1, and in CR-3 LRA, Figure 4.5-1 and identify the correct value.

Letter to J. Franke from R. Kuntz, dated September 22, 2009 DISTRIBUTION:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)

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RKuntz DBrittner AJones, OGC LLake, RII MSykes, RII TMorrissey, RII RReyes, RII

Crystal River Unit 3, Nuclear Generating Plant cc:

Mr. R. Alexander Glenn Senior Resident Inspector Associate General Counsel (MAC-BT15A) Crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Commission P.O. Box 14042 6745 N. Tallahassee Road St. Petersburg, FL 33733-4042 Crystal River, FL 34428 Mr. James W. Holt Ms. Phyllis Dixon Plant General Manager Manager, Nuclear Assessment Crystal River Nuclear Plant (NA2C) Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, FL 34428-6708 Crystal River, FL 34428-6708 Mr. William A. Passetti, Chief Mr. David T. Conley Department of Health Associate General Counsel II - Legal Dept.

Bureau of Radiation Control Progress Energy Service Company, LLC 2020 Capital Circle, SE, Bin #C21 P.O. Box 1551 Tallahassee, FL 32399-1741 Raleigh, NC 27602-1551 Attorney General Mr. Daniel L. Roderick Department of Legal Affairs Vice President, Nuclear Projects &

The Capitol Construction Tallahassee, FL 32304 Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Mr. Ruben D. Almaluer, Director Crystal River, FL 34428-6708 Division of Emergency Preparedness Department of Community Affairs Mr. Mark Rigsby 2740 Centerview Drive Manager, Support Services - Nuclear Tallahassee, FL 32399-2100 Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Chairman Crystal River, FL 34428-6708 Board of County Commissioners Citrus County Mr. Robert J. Duncan II 110 North Apopka Avenue Vice President, Nuclear Operations Inverness, FL 34450-4245 Progress Energy P.O. Box 1551 Mr. Stephen J. Cahill Raleigh, NC 27602-1551 Engineering Manager Crystal River Nuclear Plant (NA2C) Mr. Brian C. McCabe 15760 W. Power Line Street Manager, Nuclear Regulatory Affairs Crystal River, FL 34428-6708 Progress Energy P.O. Box 1551 Mr. Daniel R. Westcott Raleigh, NC 27602-1551 Supervisor, Licensing & Regulatory Programs Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428-6708