ML092250701

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

ML092250701
Person / Time
Site:	Crystal River
Issue date:	08/20/2009
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: ML092250701 (7)

Text

August 20, 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 licenses Crystal River Unit 3 Nuclear Generating Plant (CR-3), 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 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

ML092250701 OFFICE PM:RPB2:DLR LA:DLR BC:RER2:DLR BC:RPB2:DLR PM:RPB2:DLR NAME RKuntz SFigueroa RAuluck DWrona RKuntz DATE 08/18/09 08/18/09 08/19/09 08/20/09 08/20/09

REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION FOR CRYSTAL RIVER UNIT 3 DOCKET NO: 50-302 (TAC NO. ME0274)

RAI 2.1-1

Background

10 CFR 54.4(a)(1) requires that safety-related systems, structures, and components required to be within the scope of license renewal are those which are relied upon to remain functional during and following design basis events to ensure (i) the integrity of the reactor coolant pressure boundary; (ii) the capability to shut down the reactor and maintain it in a safe shutdown condition; or (iii) the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a)(1),

50.67(b)(2), or 100.11. During the scoping and screening methodology audit, performed June 23-25, 2009, the staff reviewed the applicants implementing documents and reports relative to the evaluation of safety-related SSCs for inclusion within the scope of license renewal.

Issue The staff determined that there were components identified as safety-related in the equipment data base which were not included within the scope for license renewal in accordance with 10 CFR 54.4(a)(1) as follows:

• As discussed in implementing documents and reports, the applicant had identified SSCs located in the turbine building that were designated as safety-related in the equipment database but were evaluated and determined to not meet the criteria of 10 CFR 54.4(a)(1). In addition, certain SSCs are connected to safety-related cables attached to safety-related buses.

• As discussed in implementing documents and reports, safety-related supports are attached to a common wall between the turbine building and the intermediate building, and located within the turbine building space. However, although the supports are physically located within the turbine building, they have been evaluated as a portion of the intermediate building.

Request The staff requests that the applicant provide the basis for not including the safety-related SSCs and supports, located within the turbine building, in accordance with 10 CFR 54.4(a)(1), and, as applicable, for not performing an evaluation of nonsafety-related SSCs, located within the same space, for inclusion within the scope of license in accordance with 10 CFR 54.4(a)(2).

List any additional SSCs which were included within the scope of license renewal as a result of your review performed in response to this RAI and list those structures and components for which aging management reviews were conducted. For each additional structure and

component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.

RAI 2.1-2

Background

10 CFR 54.4(a)(2) requires that nonsafety-related SSCs whose failure could prevent satisfactory accomplishment of functions identified in 10 CFR 54.4(a)(1) be included within the scope of license renewal. During the scoping and screening methodology audit, performed June 23-25, 2009, the staff reviewed the applicants implementing documents and reports relative to the evaluation of nonsafety-related SSCs for inclusion within the scope of license renewal.

Issue The staff was not able to determine that nonsafety-related pipe, attached to safety-related SSCs and extending beyond the space or structure containing the nonsafety-related/safety-related interface, was included within the scope of license renewal up to, and including, an anchor, equivalent anchor or bounding condition.

Request The staff requests that the applicant provide a discussion on the methodology used to determine the portion of nonsafety-related pipe, attached to safety-related SSCs, where the nonsafety-related pipe extends beyond the space or structure containing the nonsafety-related/safety-related interface, to be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). In addition, provide a discussion on the use of anchors, equivalent anchors and bounding conditions used as the boundary for nonsafety-related pipe, attached to safety-related SSCs, included within the scope of license renewal.

Issue The staff determined that the applicant had performed an evaluation to not include fluid filled nonsafety-related SSCs located in specific portions of structures, which also contained safety-related SSCs, within the scope of license renewal. This evaluation identified approximately five areas located in the auxiliary building which contained low or moderate energy fluid-filled nonsafety-related SSCs in addition to safety-related pipe or cables and connectors (which had been included within the scope of license renewal in accordance with 10 CFR 54.4(a)(1)).

However, the low or moderate energy fluid-filled nonsafety-related SSCs had not been included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).

Request The staff requests that the applicant provide the basis for not including fluid-filled nonsafety-related SSCs, located in the same space as safety-related SSCs, within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).

Issue The staff identified several open penetrations in a wall connecting the turbine building to the intermediate building. The staff was not able to determine if the applicant had performed an evaluation to identify the potential effect of the failure of nonsafety-related SSCs located in the turbine building on safety-related SSCs located in the intermediate building.

Request The staff requests that the applicant provide the basis for not including fluid-filled nonsafety-related SSCs, located in the turbine building, which have the potential to interact with safety-related SSCs located within the intermediate building, within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).

List any additional SSCs which were included within the scope of license renewal as a result of your review performed in response to this RAI and list those structures and components for which aging management reviews were conducted. For each additional structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.

Letter to J. Franke from R. Kuntz, dated August 20, 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)

HARD COPY:

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________

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

Crystal River Nuclear Generating Plant, Unit 3 cc:

Mr. Jon A. Franke, Vice President Mr. R. Alexander Glenn Crystal River Nuclear Plant (NA1B)

Associate General Counsel (MAC-BT15A) ATTN: Supervisor, Licensing & Regulator Florida Power Corporation Programs P.O. Box 14042 15760 W. Power Line Street St. Petersburg, FL 33733-4042 Crystal River, FL 34428-6708 Mr. James W. Holt Senior Resident Inspector Plant General Manager Crystal River Unit 3 Crystal River Nuclear Plant (NA2C) U.S. Nuclear Regulatory Commission 15760 W. Power Line Street 6745 N. Tallahassee Road Crystal River, FL 34428-6708 Crystal River, FL 34428 Mr. William A. Passetti, Chief Ms. Phyllis Dixon Department of Health Manager, Nuclear Assessment Bureau of Radiation Control Crystal River Nuclear Plant (NA2C) 2020 Capital Circle, SE, Bin #C21 15760 W. Power Line Street Tallahassee, FL 32399-1741 Crystal River, FL 34428-6708 Attorney General Mr. David T. Conley Department of Legal Affairs Associate General Counsel II - Legal Dept.

The Capitol Progress Energy Service Company, LLC Tallahassee, FL 32304 Post Office Box 1551 Raleigh, NC 27602-1551 Mr. Ruben D. Almaluer, Director Division of Emergency Preparedness Mr. Daniel L. Roderick Department of Community Affairs Vice President, Nuclear Projects &

2740 Centerview Drive Construction 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. Mark Rigsby 110 North Apopka Avenue Manager, Support Services - Nuclear Inverness, FL 34450-4245 Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Mr. Stephen J. Cahill Crystal River, FL 34428-6708 Engineering Manager Crystal River Nuclear Plant (NA2C) Mr. Robert J. Duncan II 15760 W. Power Line Street Vice President, Nuclear Operations Crystal River, FL 34428-6708 Progress Energy Post Office Box 1551 Mr. Daniel R. Westcott Raleigh, NC 27602-1551 Supervisor, Licensing & Regulatory Programs Mr. Brian C. McCabe Crystal River Nuclear Plant Manager, Nuclear Regulatory Affairs 15760 W. Power Line Street Progress Energy Crystal River, FL 34428-6708 Post Office Box 1551 Raleigh, NC 27602-1551