ML111430724
| ML111430724 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/26/2011 |
| From: | Lynnea Wilkins Plant Licensing Branch IV |
| To: | Bannister D Omaha Public Power District |
| Wilkins, L E, NRR/DORL/LPL4, 415-1377 | |
| References | |
| TAC ME4542 | |
| Download: ML111430724 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 26, 2011 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247
SUBJECT:
FORT CALHOUN STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO RELOCATE OPERATING AND SURVEILLANCE REQUIREMENTS FOR THE POWER OPERATED RELIEF VALVE, SAFETY VALVE POSITION, AND TAILPIPE TEMPERATURE INSTRUMENTATION FROM THE TECHNICAL SPECIFICATIONS (TAC NO. ME4542)
Dear Mr. Bannister:
By letter dated August 16, 2010, as supplemented by letters dated September 27,2010, and April 6, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML102290067, ML102720964, and ML110970356, respectively), Omaha Public Power District requested to relocate operating and surveillance requirements for the power-operated relief valve position, safety valve position, and tailpipe temperature instrumentation from the Fort Calhoun Station, Unit 1 (FCS) Technical Specifications to the FCS Updated Safety Analysis Report.
The U.S. Nuclear Regulatory Commission staff has reviewed your submittals and determined that the information specified in the enclosed request for additional information (RAI) is needed for the staff to complete its evaluation. The RAI was discussed with Ms. Donna Lippy of your staff on May 17, 2011. Ms. Lippy indicated that no clarifying telephone call was needed and that the response would be provided by June 30,2011.
D. Bannister
- 2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov.
Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO RELOCATE OPERATING AND SURVEILLANCE REQUIREMENTS FOR THE POWER-OPERATED RELIEF VALVE, SAFETY VALVE POSITION, AND TAILPIPE TEMPERATURE INSTRUMENTATION FROM THE TECHNICAL SPECIFICATIONS OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO.1 DOCKET NO. 50-285 By letter dated August 16, 2010, as supplemented by letters dated September 27,2010, and April 6, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML102290067, ML102720964, and ML110970356, respectively), Omaha Public Power District (OPPD, the licensee) requested changes to the Technical Specifications (TSs) for Fort Calhoun Station, Unit 1 (FCS). The proposed changes would relocate operating and surveillance requirements (SRs) for the power-operated relief valve (PORV) position, safety valve position, and tail pipe temperature instrumentation from the FCS TSs to the FCS Updated Safety Analysis Report (USAR). Specifically the proposed changes would revise:
TS Table 2-5, "Instrumentation Operating Requirements for Other Safety Feature Functions" TS Table 3-3, "Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls" TS Table 2-5, Functions 3, 4, and 5, the associated Notes a, b, c, and d, and TS Table 3-3, Functions 23 and 24, would be deleted from the FCS TSs and relocated to the FCS USAR.
TS Table 3-3 Function 21 will be revised to be consistent with NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants," Revision 3.0. Additionally, the TS Table 2-5 associated Note e will be re-Iettered as Note a and TS Table 2-5 footnote ito Note c will be deleted.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided by the licensee and determined that the following information is needed in order to complete its evaluation.
- 1.
By letter dated August 16, 2010, the licensee proposed to revise TS Table 3-3 as follows:
Item 21, PORV Operation and Acoustic Position Indication is being revised to delete the words "and Acoustic Position Indication."
Enclosure
- 2 Item 21.a, the frequency is being changed from "Mil to "R" to reflect channel functional testing of PORV operation, which is more aligned with NUREG-1432 surveillance requirements.
The licensee also states:
The proposed change also revises SR 3.1, Table 3-3, Item 21 to maintain the existing channel functional test of the PORVs on a refueling frequency, which is aligned with NUREG 1432, Standard Technical Specifications, Combustion Engineering Plants, Revision 3 [STS].
Please provide the exact SR number of the STS to which the licensee is referring.
- 2.
After the deletion of the words "and Acoustic Position Indication," TS Table 3-3, Item 21 will read "PORV Operation." However, SR 3.4.12.6, on page 3.4.12-4 of the STS, states: "Perform CHANNEL FUNCTIONAL TEST on each required PORV, excluding actuation" with a FREQUENCY of 31 days.
Please explain the discrepancy and justify the proposed revision of the required SR frequency from "M" to "R."
- 3.
By letter dated August 16, 2010, the licensee proposed to relocate the TS for maintaining and testing the acoustic monitors and the tail pipe temperatures.
Please provide the NRC staff with the proposed yvording in the USAR or Technical Requirements Manual that will supplant the revised TS. Also, please describe the plan for identifying what channels will be required, how frequently they are to be tested, and what specific functionality is to be demonstrated by the proposed functional tests. In addition, provide the NRC staff with a description of how the proposed functional testing is to be conducted for each piece of equipment being functionally tested.
- 4.
Please describe how the requirements for establishing limiting conditions for operation as described in paragraph 50.36(c)(2)(ii)(A) of Title 10 of the Code of Federal Regulations (10 CFR) Criterion 1 is still satisfied with respect to the detection of significant degradation of the reactor coolant pressure boundary associated with pressurizer steam leakage, after the proposed amendment goes into effect. In addition, please list the equipment and qualifications (e.g., EQ, seismic, power supply, etc.) that will fulfill this function.
D. Bannister
- 2 If you have any questions, please contact me at 301-415-1377 or v.ia e-mail at Iynnea. wi I kins@nrc.gov.
Docket No. 50-285
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDeEicb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource PChung, NRR/DE/EICB Sincerely, IRAI Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ML111430724
- memo dated NRR/LPL4/LA NRR/DE/EICB NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins JBurkhardt GWilson*
MMarkley LWilkins DATE 5/26/11 5/25/11 4/28/11 5/26/11 5/26/11 OFFICIAL RECORD COPY