ML16239A071

ISFSI - Thirty-Day Report for Engagement of Active Cooling for OS197 Fc Transfer Cask During Transfer of a Loaded Dry Shielded Canister

ML16239A071
Person / Time
Site:	Robinson, 07201004, 07200060
Issue date:	08/25/2016
From:	Hoffman D Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
RNP-RN16-0068
Download: ML16239A071 (3)

Text

David S. Hoffman H. B. Robinson Steam Electric Plant Unit 2 Director - Nuclear Org Effectiveness Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0 . 843 857 5239 F: 843 857 1319 David.hoffman@duke-energy.com 10 CFR 72.238 Serial: RNP-RN16-0068 AUG 2 5 2016 Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards United States Nuclear Regulatory Commission Washington, DC 20555-0001 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 INDEPENDENT SPENT FUEL STORAGE INSTALLATION DOCKET NO. 72-60 THIRTY (30) DAY REPORT FOR ENGAGEMENT OF ACTIVE COOLING FOR 05197 FC TRANSFER CASK DURING TRANSFER OF A LOADED DRY SHIELDED CANISTER Ladies and Gentlemen:

Pursuant to 10 CFR 72.238, Certificate of Compliance (CoC) 1004, Amendment Number 13, Article 3.d.5, and Technical Specification 3.1.3 (TS 3.1.3), Duke Energy Progress, hereby provides the following information to comply with the requirement to submit a 30 day report, for engagement of active cooling for the OS 197 FC Transfer Cask during transfer of a loaded Dry Shielded Canister (DSC), into the Horizontal Storage Module (HSM) on the Independent Spent Fuel Storage Installation (ISFSI) at the H. 8. Robinson Steam Electric Plant (HBRSEP), Unit No.

2, dated July 28, 2016. It is noted, HBRSEP remained compliant with the requirements and the expectation of TS 3.1 .3, Updated Final Safety Analysis Report (UFSAR) and governing procedures throughout the entire operational evolution.

A narrative describing major occurrences during the evolution, detailed information related to the cask, key actions, and evaluations and analyses supporting the basis for the conclusion of no adverse impact to the health and safety of the public follows.

United States Nuclear Regulatory Commission Serial: RNP-RA/16-0068 Page 2 of 3 Cask Information:

Licensee Name: Duke Energy Progress Licensee Address: H. 8 . Robinson Steam Electric Plant (HBRSEP), Unit No. 2 3581 West Entrance Road Hartsville, SC 29550 Reactor License Number: DPR-23 Reactor Docket Number: 50-261 ISFSI Docket Number: 72-1004 Information

Contact:

Tony Pilo, Manager (Acting) - Nuclear Regulatory Affairs 843-857-1409.

Cask Certificate Number: 1004, Amendment 13 Cask Model Number: NUHOMS- 24PTH-L-1C-HZ19 Date Placed in Service 07/29/2016 Horizontal Storage HSM27 Module Number Heat Load (kW) 26.51 While attempting to insert DSC RNP-24PTH-L-1C-HZ19 (DSC HZ19) into HSM 27 on July 28, 2016, the DSC stalled and was unable to be inserted. DSC HZ19 is a type 1C basket with heat load zone 1 fuel and a decay heat load of 26.51 kW per the fuel selection package. Per CoC 1004 Amendment 13 Technical Specification (TS) 3.1.3, DSC HZ19 had a 9.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> limit from beginning of annulus draining to full insertion of the DSC into the HSM. After consulting with AREVA TN engineering and before the 9.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> time limit expired, partially inserted DSC HZ19 was retracted from the HSM back into the transfer cask (TC) and forced air cooling was started on diesel generators within the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limit in TS 3.1 .3 condition A2. While retracting DSC HZ19, it was noted that the digital distance readout on the non-safety related hydraulic power unit (HPU) was showing a negative number when a positive or zero number was expected. As DSC HZ19 was retracted, the DSC shell, TC lip, and HSM rails were visually inspected but no damage or wear was noted. A backup HPU was rented from AREVA TN in the event the utility-owned HPU was unable to be fixed but was not used.

After troubleshooting, it was discovered that the hydraulic ram that is supplied by the HPU, was stalling out between the 3 stages of the ram where the diameter of the ram becomes smaller.

Some set-points in the HPU software that calculate ttie distance that the ram is extended were adjusted with AREVA TN guidance such that the HPU would produce the correct needed pressure for the ram at the specified distance. No other systems or components were affected.

United States Nuclear Regulatory Commission Serial: RNP-RN16-0068 Page 3 of 3 AREVA TN engineering provided a calculation that allowed a minimum forced air cooling time of 30 minutes to reset the conditions of TS 3.1.3 such that the 9.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> insertion time limit was restarted when forced air cooling was stopped. This 30 minute limit was based conservatively on basket type and total decay heat load. After being on forced air cooling for approximately 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />, forced air cooling was stopped, and DSC HZ19 was successfully inserted into HSM 27 on July 29, 2016.

Additional troubleshooting following the insertion of DSC HZ 19, AREVA TN discovered an error in the calculation software of the HPU as the cause of the issue. The calculation and set-points are part of the manufacturer's controlled settings on the HPU. AREVA TN representative corrected the calculation in the software. This issue was not caused by human performance, lack of training, bad or incorrect communications, lack of oversight, or lack of maintenance during insertion of DSC HZ 19. The HPU was successfully used in subsequent DSC insertions.

During the entirety of the evolution, no TS, UFSAR, or procedure steps or limits were violated.

Although the 9.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> insertion time limit was not met, forced air cooling was started within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and maintained per TS 3.1.3 condition A2 without interruption until the minimum 30 minute run time required was met per AREVA TN calculation 11165-0400, dated July 29, 2016.

This AREVA TN calculation shows that even without forced air cooling, fuel and TC integrity were not challenged and the health and safety of the public was not adversely impacted.

Sincerely, David S. Hoffman Director - Nuclear Organization Effectiveness DSH/am cc: NRC Regional Administrator, NRC, Region II Mr. Robert Carrion, NRC, Region II, ISFSI Coordinator NRC Resident Inspector, HBRSEP, Unit No. 2 Mr. Dennis Galvin, NRC Project Manager, NRR