LIC-14-0141, Update to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements

Update to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements

ML14353A461
Person / Time
Site:	Fort Calhoun
Issue date:	12/19/2014
From:	Cortopassi L Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-14-0141
Download: ML14353A461 (3)

Text

th 444 South 16 Street Mall Omaha, NE 68102-2247 LIC-14-0141 December 19, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285

References:

1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), License Amendment Request (LAR) 14-10, One-Time Extension of Technical Specification Surveillance Requirements, dated November 7, 2014 (LIC-14-0128)

(ML1404311A158)

2. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), Response to NRC Request for Additional Information Regarding License Amendment Request (LAR) 14-10, One-Time Extension of Technical Specification Surveillance Requirements, dated November 21, 2014 (LIC-14-0131) (ML14303A465)

3. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), Supplement to License Amendment Request (LAR) 14-10, One-Time Extension of Technical Specification Surveillance Requirements, dated December 10, 2014 (LIC-14-0135)

(ML14344B017)

SUBJECT:

Update to License Amendment Request (LAR) 14-10; One-Time Extension of Technical Specification Surveillance Requirements On December 17, 2014, at 10:14 AM CST, Fort Calhoun Station, Unit No. 1 experienced an automatic reactor and turbine trip due to the lockout of the stations main generator. Plant equipment responded as expected and the plant safely entered Hot Shutdown (Mode 3) where it remained while troubleshooting and repairs were performed.

Currently, the station is preparing to resume power operations and this submittal is to inform the NRC of the status of the surveillance tests (STs) that are the subject of References 1, 2, and 3. Specifically, to report on those STs that were completed and those STs that could not be completed along with an explanation as to why they could not be completed.

It must be noted that the STs remaining to be completed are normally performed when the station is in either Cold Shutdown Condition (Mode 4) or Refueling Shutdown Condition (Mode 5) due to industrial safety/nuclear safety concerns or simply because conditions do not allow the test to be performed.

Accordingly, the Attachment to this letter lists each of the STs and provides the necessary explanation.

No regulatory commitments are contained in this submittal.

U. S. Nuclear Regulatory Commission LlC-14-0141 Page 2 In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated State of Nebraska official.

If you should have any questions regarding this submittal or require additional information, please contact Mr. Bill R. Hansher a (402) 533-6894.

Lo IS P. Cortopassi Site Vice President and CND LPC/mie c: M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S. M. Schneider, NRC Senior Resident Inspector Director of Consumer Health Services, Department of Regulation and Licensure, Nebraska Health and Human Services, State of Nebraska

LIC-14-0141 Attachment Page 1 Surveillance Test (ST) Status Surveillance Test Complete Explanation (Y/N)

IC-ST-IA-0001 N The attempt to complete IC-ST-IA-0001 was not successful due to concerns with reactor coolant system (RCS) pressure control and inventory control. The test is normally performed during cold shutdown.

OP-ST-ESF-0019 N Plant conditions do not support performance of OP-ST-ESF-0019. (Requires Mode 4 or 5)

IC-ST-MS-0005 N Could not perform ST due to concerns of performing ST with single valve isolation and risk of causing an inadvertent actuation of auxiliary feedwater actuation signal (AFAS) channel relay, reactor protective system (RPS) trip signal, or engineered safety feature (ESF) actuation if the isolation valve did not hold.

IC-ST-MS-0018 N Unable to isolate A/LT-901 to calibrate transmitter; the manifold leaked by and did not isolate. The transmitter was restored to service and verified to match readings on other level loops.

IC-ST-MS-0034 N Attempted to perform ST but backed out at step 7.4 due to concerns of performing ST with single valve isolation and risk of causing an inadvertent actuation of AFAS channel relay, RPS trip signal, or ESF actuation if the isolation valve did not hold.

IC-ST-MS-0035 N ST requires lead to be lifted and was not performed to prevent an inadvertent actuation of steam generator low signal (SGLS), which is on the same tap.

SE-ST-VA-0002 Y Completed on December 6, 2014; change to Technical Specification 3.6(3)d was withdrawn by OPPD letter LIC-14-0135 dated December 10, 2014.

OP-ST-ESF-0015 N Plant conditions do not support performance of OP-ST-ESF-0015. (Requires Mode 4 or 5)

SE-ST-SI-3027 N Plant conditions do not support performance of OP-ST-ESF-0015. (Requires Mode 4 or 5)