ML14259A365

Request for Additional Information, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III

ML14259A365
Person / Time
Site:	Fort Calhoun
Issue date:	09/24/2014
From:	Lyon C Plant Licensing Branch IV
To:	Cortopassi L Omaha Public Power District
Lyon C
References
TAC MF4160
Download: ML14259A365 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 24, 2014 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane. Mail Stop FC-2-4 Omaha, NE 68008

SUBJECT:

FORT CALHOUN STATION, UNIT NO.1-REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO ADOPT ASME CODE, SECTION Ill, 1980 EDITION (NO ADDENDA) AS AN ALTERNATIVE TO CURRENT CODE OF RECORD (TAC NO. MF4160)

Dear Mr. Cortopassi:

By letter dated May 16, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14143A370), Omaha Public Power District submitted a license amendment request to revise the current licensing basis to adopt the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Ill, 1980 Edition, (no . Addenda) as an alternative to the current code of record. The NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its formal review. The enclosed questions were provided to B. Hansher of your staff on September 16, 2014. Please provide a response to the enclosed questions within 30 days of the date of this letter. If you have any questions, please contact meat 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov.

Docket No. 50-285

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT NO. 1 DOCKET NO. 50-285 By letter dated May 16, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14143A370)

Omaha Public Power District submitted a license amendment request to revise the current licensing basis to adopt the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Ill, 1980 Edition, (no Addenda) as an alternative to the current code of record. The NRC staff has reviewed the information provided in your application and determined that the additional information below is required in order to complete its formal review. 1. The application proposed to revise Appendix F by adding NOTES (e) and (f). NOTE (e) provided the loading combinations for the piping. The earthquake and fluid transient loadings are added for combination 2 of Table F-1 in the updated safety analysis report (USAR). However, the proposed NOTE (e) for Table F-1 of the USAR states that earthquake and fluid transient loading are combined with Square-Root-of-the-Sum-of-the-Squares method. Please explain the inconsistency between Table F-1 and its NOTE (e). 2. The service level C of NOTE (e) refers to NOTE (d), which states that these load cases and limits apply only to the pressurizer relief valve piping and supports.

The staff notes that the fluid transient loadings for Class 2 and 3 piping are not limited only to the pressurizer relief valve. For example, main steam lines have relief valves, and a fast valve open and closure event, such as reactor vessel head vent valve opening, may cause hydrodynamic loading. Please explain why the load combination in the proposed USAR does not address all of those loadings for Class 2 and 3 piping and supports.

3. The proposed NOTE (f) states that support analysis will continue to be performed in accordance with the existing licensing basis (i.e., Seventh Edition of AISC, American Institute of Steel Construction).

Please provide documentation for the existing licensing basis. 4. Table F-1 of the USAR lists primary stress limits which cannot be found in the reference standards for both piping and vessel. The primary stress limit for the loading combination 2 expression (PB < 1.5 [1-(PM)2/SD]

SO) does not appear to be correct. For example, PB would be less than a negative value with PM =20ksi and SO =60ksi. Please provide justification for the expressions for primary stress limits for both piping and vessel in USAR Table F-1. Enclosure September 24, 2014 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC-2-4 Omaha, NE 68008

SUBJECT:

FORT CALHOUN STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO ADOPT ASME CODE, SECTION Ill, 1980 EDITION (NO ADDENDA) AS AN ALTERNATIVE TO CURRENT CODE OF RECORD (TAC NO. MF4160)

Dear Mr. Cortopassi:

By letter dated May 16, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14143A370), Omaha Public Power District submitted a license amendment request to revise the current licensing basis to adopt the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Ill, 1980 Edition, (no Addenda) as an alternative to the current code of record. The NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its formal review. The enclosed questions were provided to B. Hansher of your staff on September 16, 2014. Please provide a response to the enclosed questions within 30 days of the date of this letter. If you have any questions, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov.

Docket No. 50-285

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL4-1 Reading RidsAcrsAcnw MaiiCTR Resource RidsNrrPMFortCalhoun Resource RidsNrrLAJBurkhardt Resource RidsRgn4MaiiCenter Resource ADAMS Accession No.: ML14259A365 OFFICE NRRIDORLILPL4-1/PM NRR/DORLILPL4-1/LA NAME FLyon JBurkhardt DATE 9/17/14 9/17/14 Sincerely, IRA/ Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDeEmcb Resource RidsNrrDssSbpb Resource RidsNrrDoriLpl4-1 Resource KHsu, NRRIDE/EMCB EDavidson, NRRIDSS/SBPB

• email dated s eptember 12, 2014 NRR/DE/EMCB/BC(A)*

NRR/DORLILPL4-1/BC(A)

NRR/DORLILPL4-1/PM RPettis EOesterle FLyon 9/12/14 9/23/14 9/24/14 OFFICIAL RECORD COPY