View source for LIC-07-0073, Closure of NRC TAC Issues

{{Adams
| number = ML082040634
| issue date = 07/11/2008
| title = Closure of NRC TAC Issues
| author name = Matthews T
| author affiliation = Omaha Public Power District
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000285
| license number = 
| contact person = 
| case reference number = LIC-07-0073, LIC-08-0080
| document type = Graphics incl Charts and Tables, Letter type:LIC
| page count = 4
}}

=Text=
{{#Wiki_filter:OmahaPublic Power Distict 1946 - 2006 Fort Calhoun Station P.O. Box 550 FortCalhoun, NE 68023 July 11,2008 LIC-08-0080 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

==References:==
: 1.                 Docket No. 50-285
: 2. Letter from OPPD (J. L. McManis) to NRC (Document Control Desk), "Closure of NRC TAC Issues for Fort Calhoun Station Unit No. 1," dated July 24, 2007 (LIC-07-0073)

==SUBJECT:==
Closure of NRC TAC Issues for Fort Calhoun Station, Unit No. 1 The Omaha Public Power District (OPPD) has implemented the necessary actions associated with the open TAC issues listed in the Attachment. Subject to agreement by the NRC/NRR Senior Project Manager, these items are ready to close. These actions have been taken since the last TAC Closure letter (Reference 2).
No commitments are made to the NRC in this letter. If you have any questions or require additional information, please contact Mr. Bill Hansher at (402) 533-6894.
Sincerely, T. C. Matthews Manager - Nuclear Licensing TCM/mle                ,
Attachment 4uAc&#xfd;

LIC-08-0080 Attachment Page 1 Table of Implemented TAC Actions
                              - Fort Calhoun Station Amendment                   Description               TAC No.      FCS No.                                                      Implementation Date N/A    In accordance with NRC letter dated July  MD4534     12/31/07.
26, 2007, (NRC-07-0073) a new license condition capturing the interim compensatory measures (ICM) Order (EA-02-026) Section B.5.b mitigation strategy requirements was incorporated into the licensing basis.
250     The amendment deleted the Technical       MD3854     10/04/07 Specification (TS) requirements associated with the hydrogen purge system. The change is consistent with revisions of Section 50.44 of Title 10 of the Code of Federal Regulations, "Combustible Gas Control for Nuclear Power Reactors," that became effective on. October 16, 2003. This operating license improvement was made available by the NRC on September 25, 2003 (68 FR 55416) as part of the consolidated line item improvement process (CLIIP).
251     The amendment revised TSs 2.7(1),         MD6221     05/24/08 2.7(2), and TS 3.7(5), to allow the addition of two safety-related swing inverters to the 120-volt alternating current instrument buses. The TS changes take advantage of the additional operational flexibility provided by the swing inverters.

LIC-08-0080 Attachment Page 2 Amendment                    Description                TAC No.      FCS No.                                                        Implementation Date 252    The amendment revised the TS safety         MD6808     05/23/08 limit (SL) requirements related to the use of a non-cycle specific peak linear heat rate SL of 22 kilowatt hours per foot (kW/ft) to fuel centerline melt. The change is consistent with the objective of TS Task Force (TSTF) 445-A, Revision 1, which determined that the current SL does not clearly conform to paragraph 50.36(d)(1 )(ii)(A) of Title 10 of the Code of Federal Regulations.
253    The amendment removed the footnote to       MD6704     05/20/08 TS 2.3(4) and TS 3.6(2)d, limiting the use of sodium tetraborate to Operating Cycle 24 only. In addition, TS 2.3, Figure 2-3 was revised to increase the volume of sodium tetraborate due to the selection of a different chemical vendor and an increase in mass to provide additional pH margin.
254    The amendment revised emergency             MD6939     06/06/08 diesel generator,(DG) surveillance testing in TS 3.7, to support modification of the DG start circuitry. Prior to the amendment, TS 3.7 required verification of the anticipatory DG start-to-idle speed upon a reactor trip. The amendment deleted the anticipatory DG starting requirement. This amendment also deleted a footnote to TS 3.7(1)e pertaining to a one-time extension of the surveillance interval for DG-1 that was granted in Amendment No. 112.

LIC-08-0080 Attachment Page 3 Amendment                    Description                 TAC No.      FCS No.                                                         Implementation Date 255    The amendment revised TSs 2.4, 2.14,         MD6204     06/03/08 2.15, 3.1, 3.5(4), 3.6(3), and associated    MD7043 TS Basis documents and Updated Safety Analysis Report sections to modify the containment spray system actuation logic to preclude automatic start of the containment spray pumps for a loss-of-coolant accident. The amendment also revised TS 3.6(3)a to delete a surveillance requirement (SR) for testing of the containment air cooling and filtering system emergency mode dampers and replaced it with a SR to verify that the dampers are in their accident positions in all operating plant modes. The SR in TS 3.6(3)b to remotely operate the dampers was deleted. The amendment added license conditions related to the replacement and testing of containment air cleaning and filtering (CACF) unit HEPA (high-efficiency particulate air) filters and surveillance testing of the CACF unit relief ports.
256     The amendment revised TS 2.1.1 and the       MD6993     05/18/08 SR of TS 3.1.6 to increase the shutdown cooling (SDC) system entry temperature from 300&deg;F to 350&deg;F (cold leg), and the SDC entry pressure from 250 pounds per square inch absolute (psia) to 300 psia (indicated at the pressurizer).}}