ML13134A186

4/22/2013 - Summary of Meeting with Omaha Public Power District - Potential License Amendment Requests for Fort Calhoun, Unit 1 Related to Flood Protection for Raw Water System, Tornado Missile Protection, Piping/Code Use, and Alternate Sei

ML13134A186
Person / Time
Site:	Fort Calhoun
Issue date:	06/03/2013
From:	Lynnea Wilkins Plant Licensing Branch IV
To:	Omaha Public Power District
Wilkins L
References
TAC MF0598
Download: ML13134A186 (6)

Text

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"'I} ****"" ~o June 3, 2013 LICENSEE: Omaha Public Power District FACILITY: Fort Calhoun Station, Unit 1

SUMMARY

OF PUBLIC MEETING HELD ON APRIL 22,2013, WITH OMAHA PUBLIC POWER DISTRICT TO DISCUSS POTENTIAL LICENSE AMENDMENT REQUESTS FOR FORT CALHOUN STATION, UNIT 1 (TAC NO. MF0598)

On April 22, 2013, a meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Omaha Public Power District (OPPD) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss potential license amendment requests (LARs) for Fort Calhoun Station, Unit 1 (FCS).

A list of attendees is provided in the Enclosure. The meeting notice and agenda, dated April 11, 2013, is available in the Agencywide Documents Access and Management System at Accession No. ML13101A223. The licensee's presentation slides are available at ADAMS Accession No. ML13112A052.

OPPD indicated that LARs would potentially be submitted regarding 1) tornado missiles,

2) alternate seismic criteria and methodologies (ASCM), 3) the intake structure, 4} piping code issues, and 5) equipment reclassification. The licensee indicated that the tornado missiles, ASCM, and intake structure LARs would be submitted later this year. There is currently no submittal schedule for the piping code issues and equipment reclassification LARs. OPPD took an action to provide the NRC staff with a schedule for these three LAR submittals.

The following additional actions were identified during the meeting:

• OPPD took an action to provide Region IV with feedback on why the tornado missile protection vulnerability associated with the intake structure, and the ASCM, which was used for the intake structure, are not core reload restraints.

The NRC staff indicated that because the raw water system is needed to provide shutdown cooling for refueling, it was unclear to the staff why an operability determination in these areas could be deferred until after fuel is loaded in the reactor vessel.

• OPPD has not yet provided the region-based inspectors with the operability evaluations for all of the five issues discussed during the meeting. OPPD stated it will provide these evaluations for NRC review as soon as they become available.

• Regarding the ASCM issue, OPPD indicated that the cage around FW-10 (turbine driven auxiliary feedwater pump) would be removed. OPPD stated that the cage's purpose was associated with security; however, because a different

-2 security strategy is currently being implemented, the cage is no longer needed.

OPPD took an action to get back to the region-based inspectors regarding the purpose of the wall between FW-10 and FW-6 and whether this wall had implications for the license amendments that OPPD is considering.

• OPPD took an action that when it submits the LARs, that it will reference the standard review plan or regulatory guide that provides the guidance and basis for its license amendment. It was not clear to the NRC staff what guidance formed the basis for the potential license amendments that OPPD was considering.

OPPD indicated that one of its structural experts was unable to attend the meeting. The NRC staff expressed confusion regarding slide 17 of OPPD's presentation concerning the issue of liquefaction related to the floor response spectra. OPPD and the NRC staff agreed to discuss this matter during future meetings and interactions.

The public was invited to observe the meeting and was given an opportunity to communicate with the NRC after the business portion, but before the meeting was adjourned. Members of the public were present. Several members of the public questioned whether or not the license amendments discussed above needed to be issued prior to restarting of the unit. The NRC staff noted that the licensee is planning to perform operability determinations of the systems, structures, and components (SSCs) associated with the five issues discussed during the meeting. The NRC staff noted that none of the operability determinations were available for NRC review. As such, it is difficult for the NRC to fully assess whether or not a license amendment is needed prior to restart of the unit.

In response to a question from the public, the staff provided a high-level overview of NRC Inspection Manual 9900, "Operability Determinations and Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety." The staff noted that it is possible that the licensee could determine that the SSCs are "operable" but degraded or nonconforming for various types of issues. Compensatory measures can be used for the degraded or nonconforming condition and may restore plant operating margins. In such a case, the NRC staff would expect the licensee to evaluate the technical acceptability and effectiveness of a compensatory measure. If the licensee determines that the SSCs are inoperable, the licensee would be expected to take actions in accordance with its technical specifications. If inoperable SSCs are needed to support restart of the unit, OPPD will have to resolve the issue prior to restart and restore the SSCs to operable status or process an LAR.

No Public Meeting Feedback forms were received.

-3 Please direct any inquiries to me at 301-415-1377 or Lynnea.Wilkins@nrc.gov.

~. Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv

LIST OF ATTENDEES U.S. NUCLEAR REGULATORY COMMISSION APRIL 22,2013. MEETING WITH OMAHA PUBLIC POWER DISTRICT TO DISCUSS POTENTIAL LICENSE AMENDMENT REQUESTS FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 Name Organization Bruce Rash OPPD George Wilhelmsen OPPD Matt Anielak OPPD Chris Scofield T6PPD Don Macisaac OPPD Terry Simpkin Exelon/Fort Calhoun Station Scot Greenlee Exelon Sean Clark Black & Veatch Anthony Vegel NRC/RIV

• Mike Hay NRC/RIV Louise Lund NRRlDORL Jacob Wingebach NRC/RIV John Kirkland* NRC/RIV Rick Deese* NRC/RIV Chris Smith* NRR/RIV Mike Markley NRRIDORL

• Lynnea Wilkins NRR/DORL

• Joe Sebrosky NRR/DORL Greg Casto NRR/DSS Bob Dennig NRR/DSS Christopher Jackson NRR/DSS rl Schulten NRR/DSS Evan Davidson NRR/DSS Sam Miranda NRR/DSS

~Mathew NRR/DE Kamal Manoly NRR/DE

• Participated via phone Enclosure

-2 Name Organization Chakrapani Basavaraju NRR/DE Elaine Hiruo Platts Erin Golden* Omaha World Herald Wally Taylor* Sierra Club of Iowa Ronald R Freeman*

Katie Schubert* Omaha Public Radio, KIOS-FM Don Ferraro* Assistant General Counsel, Exelon Business Services Co.

Felicia Rogers* Congressman Lee Terry Darrell Podany* Sen. Mike Johanns (R-NE)

Kahan Jabbour*

Lynn Moorer*

Mike Ryan*

Smith*

• Partlclpated via phone

-3 The NRC region-based inspectors have reviewed some operability determinations associated with these five issues. In other areas, the NRC staff is waiting for the licensee to complete the operability determinations. The staff has not yet come to a conclusion on whether or not it agrees with the licensee's operability determinations it is still reviewing and will make a determination regarding the other operability evaluations when the staff has had a chance to review them.

Please direct any inquiries to me at 301-415-1377 or Lynnea.Wilkins@nrc.gov.

IRA!

Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrDssStsb Resource JSebrosky, NRR/DORULPL4 LPLIV Reading RidsNrrLAJBurkhardt Resource CSchulten, NRR/DSS/STSB RidsAcrsAcnw_MailCTR Resource RidsNrrPMFortCalhoun Resource RDennig, NRR/DSS/SCVB RidsNroDseaRhmb Resource RidsNsirDpr Resource GCasto, NRR/DSS/SBPB RidsNrrDe Resource RidsNsirDso Resource EDavidson, NRR/DSS/SBPB RidsNrrDeEeeb Resource RidsNsirDsp Resource CJackson, NRR/DSS/SRXB RidsNrrDeEmcb Resource RidsRgn4MailCenter Resource AVegel, RIV RidsNrrDorl Resource DHuyck, EDO RIV JKirkland, RIV/DRP/RPB-F RidsNrrDorlLpl4 Resource TWertz, NRR JWingebach, RIVlDRP/RPB-F RidsNrrDraApla Resource KManoly, NRR/DE MHay, RIVIDRP/RPB-F RidsNrrDssSbpb Resource RMathew, NRR/DE/EEEB RDeese, RIVlDRP/RPB-F RidsNrrDssScvb Resource CBasavaraju, NRR/DE/EMCB CSmith, RIV/DRP/RPB-F RidsNrrDssSrxb Resource LLund, NRRlDORL ADAMS Accession Nos. Meeting Notice ML13102A189; Meeting Summary ML13134A186; Slides ML13112A052

• via email R/DORULPL4/PM NRR/DORULPL4/LA RP/RPB-F/BC kins JBurkhardt 113 5/14/13 OFFICE N RR/DORULPL4/BC NRR/DORULPL4/PM NAME MMarkley LWilkins 6/3/13 6/3/13 OFFICIAL RECORD COpy