IR 07200028/2014002

IR 07200028/2014002 on 12/2/14 - 6/15/15, NRC Independent Spent Fuel Storage Installation Inspection Report No. 07200028/2014002, Susquehanna Nuclear, LLC, Berwick, Pennsylvania

ML15175A212
Person / Time
Site:	Susquehanna
Issue date:	06/24/2015
From:	Ferdas M S Division of Nuclear Materials Safety I
To:	Rausch T S Susquehanna
References
IR 2014002
Download: ML15175A212 (9)

Text

June 24, 2015 Docket Nos.

07200028License No.

NPF-22 05000388 Timothy Senior Vice President and Chief Nuclear Officer Susquehanna Nuclear, LLC 769 Salem Boulevard

- NUCSB3 Berwick, PA 18603

-0467 SUBJECT: NRC INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT NO. 072000 28/201 4 00 2 , SUSQUEHANNA NUCLEAR, LLC, BERWICK, PENNSYLVANIA

Dear Mr. Rausch:

This refers to the Independent Spent Fuel Storage Installation (ISFSI) reactive inspection conducted between December 2, 2014, and June 15, 2015, at Susquehanna Nuclear, LLC's Susquehanna Steam Electric Station (SSES) Unit 2. The purpose of the inspection was to follow-up on the identification of indications of the siphon/vent block base metal on dry storage canister (DSC) #83. The results of this inspection were discussed with Duane Karchner and other members of your staff at the conclusion of the inspection on June 15, 2015, and are described in the enclosed report. No findings of safety significance were identified.

In accordance with 10 Code of Federal Regulations (CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure, and your response (if any) will be made available electronically for public inspection in the NRC Public Document Room or from the NRC document system (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading

-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.

Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov

select Radioactive Waste; Storage of Spent Nuclear Fuel; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll

-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays).

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406

-2713 No reply to this letter is required. Please contact Steve Hammann at 610

-337-5399 if you have any questions regarding this matter.

Sincerely,

/RA MRoberts f/

Marc S. Ferdas, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure:

NRC Inspection Report No.

07200028/2014002 cc w/encl:

Distribution via ListServ

EXECUTIVE SUMMARY

NRC Inspection Report No. 07200028/2014002

The inspectors reviewed SSES's activities associated with the repair of dry shielded canister (DSC) #83 after the identification of indications on the siphon/vent block base metal. The condition was documented in SSES's corrective action program in Condition Reports (CRs)2014-36107, 37018, and 37033.

The inspectors interviewed SSES and Transnuclear, Inc. (TN)personnel , reviewed SSES and TN documents and procedures, and observed repairs to the DSC between December 2

-5, 2014. The inspection continued through June 15, 2015, and consisted of in-office reviews of information provided by SSES. The inspectors also reviewed SSES's corrective actions and apparent cause investigation report. Based on the results of this inspection, no findings of safety significance were identified.

REPORT DETAILS

1.0 Background On November 19, 2014, during the performance of nondestructive examination (NDE) dye penetrate testing (PT) on DSC #83

, multiple indications (areas of potential imperfections in the base metal) were found in the heat

-affected zone area around the siphon/vent block port cover welds.

The NDE was performed after the completion of welding of the siphon/vent block port covers.

In consultation with the dry cask vendor and CoC holder, TN, it was determined that the siphon/vent block should be repaired by grinding out the base metal indications. Upon completion of the repair work and successful completion of a PT on the vent and siphon port welds , the outer top cover (OTC) was installed and a helium leak rate test was re-performed on November 21, 2014 , as required by the Technical Specifications (TS) for the CoC. The helium leak rate test did not pass the requirements specified in TS 1.2.4a. The test was repeated several times between November 21

-22, 2014, and on each occasion did not meet the TS requirement. All activities associated with the processing of the DSC were placed on hold while SSES and TN developed a repair plan for DSC #83. Prior to implementing the repair plan

, TN demonstrated to SSES

, at their facility in Aiken, South Carolina

, that they could remove the OTC by grinding out the welds without damaging the DSC. On December 2, 2014, SSES approved the final version of the repair plan

, PTIP-30696-5.2, Rev.0, Susquehanna Weld Remediation , and repair activities commenced the same day.

2.0 S cope

a. Inspection Scope

(Inspection Procedures (IPs) 60855 and 60855.1 The inspectors reviewed SSES's activities associated with the repair of DSC #83 after the identification of indications on the siphon/vent block base metal. The condition was documented in SSES's corrective action program in CRs 2014

-36107, 37018, and 37033.

The inspectors interviewed SSES and TN personnel, reviewed SSES and TN documents and procedures, and observed repairs to the DSC between December 2

-5, 2014. The inspection continued through June 15, 2015

, and consisted of in

-office reviews of information provided by SSES.

The inspectors also reviewed SSES's corrective actions and apparent cause investigation report.

b. Observations and Findings

The inspectors reviewed the results of PT and ultrasonic testing (UT) of the edges of the DSC after the OTC was removed

, and verified that the DSC was not damaged by the grinding out of the OTC welds. After the completion of localized helium leak rate testing

, SSES determined the siphon/vent block was the source of the leakage. The inspectors observed the performance of a weld overlay of the entire top of the siphon/vent block up to within 3/16" of the edge of the siphon/vent block. A PT of the weld overlay showed additional indication s on the siphon/vent block in the 3/16" edge that did not have the weld overlay.

The inspectors reviewed the SSES and TN revised repair plan that placed a weld overlay on the portion of the siphon/vent block that had not previously ha d an overlay.

Further localized helium leak rate testing did not indicate any further leaks after the completion of the weld overlays and SSES re

-entered their procedure for processing of DSC #83. On December 12, 2014, processing of DSC #83 was completed and the inspectors confirmed that the DSC met all the TS requirements prior to it being moved to the ISFSI pad on December 16, 2014. The inspectors verified that throughout the repair the DSC was in a safe stable condition and all TS requirements were met.

The inspectors review ed the root cause investigation report that documented the determination that the siphon/vent block had been fabricated from a thick rolled plate and contained inherent inclusions resulting during ingot solidification. The inclusions induced in the rolled plate were brought to the block face by weld

-induced stresses. The inspectors confirmed that SSES has two unused canisters on

-site that had their siphon/vent blocks fabricated from the same lot of rolled plate as DSC #83. Planned corrective actions include placing a weld overlay on the siphon/vent block of one of the unused canisters and returning the other canister to the manufacturer.

These activities are being tracked in the corrective action program

.

c. Conclusions

Based on the results of this inspection, no findings of safety significance were identified.

3.0

Exit Meeting Summary

On June 15, 2015, the inspectors presented the inspection results, via teleconference, to Duane Karchner, Refuel Floor Manager, and other members of SSES's staff.

PARTIAL LIST OF PERSONS CONTACTED Susquehanna

• Duane Karchner, Refuel Floor Manager

• Justion Mirilovich, Refuel Floor Shift Manager

• Anthony Nestico, Refuel Floor Shift Manager Brenda O'Rourke, Senior Engineer Robert Rose, Engineering Robert Specht, NDE Transnuclear Mike Williams, Director of Operations Pam Waite, Work Package Coordinator David Wright, Project Coordinator

• Indicates attendance at the exit meeting ITEMS OPEN, CLOSED, AND DISCUSSED None LIST OF

DOCUMENTS REVIEWED

Analysis and Tests

AREVA Examination Summary Sheet, Ultrasonic Exam, SSE

-61BTH-1-B-2-050, SSE-61BTH-1- B-2-051 AREVA Root Cause Investigation of Siphon and Vent Block Base Metal Indications (AREVA TN

Root Cause Investigation 2014

-339) Helium Leak Rate Test, Inner Lid to Shell, Port Cover Plate & outer Top Cover, Canister 81

Helium Leak Rate Test, Vent and Siphon Port Cover Plates, Canister 81

Helium Leak Rate Test, Inner Lid to Shell, Port Cover Plate & outer Top Cover, Canister 82

Helium Leak Rate Test, Vent and Siphon Port Cover Plates, Canister 82 Liquid Penetrant Examination, Final Pass Welds for Inner Vent & Siphon Port Covers, Canister 83

Liquid Penetrant Examination, Rework of Indication Areas at Vent & Siphon Port Covers, Canister 81

Liquid Penetrant Examination, Root Pass Weld for Inner Top Cover Plate, Canister 81

Liquid Penetrant Examination, Root Pass Weld for Inner Top Cover Plate, Canister 82

Liquid Penetrant Examination, Top surface of Block, Cannister S/N

-SSE-61BTH-1-2-050 Condition Reports

CR 2014-35887, 2014

-36107, 20 14-37018, 2014

-37033, 2014

-37036 Transnuclear Nonconformance Report No: 2014

-313, Rev. 0

Attachment

Procedures

NDE-LT-001, Rev. 2, Helium Mass Spectrometer Leak Test Procedure for Dry Fuel Storage

Casks NDE-PT-001, Rev. 4, Color Contrast Liquid Penetrant Examination

NDE-PT-003, Rev. 2, Color Contrast Liquid Penetrant Examination High Temperature

NDE-UT-014, Rev. 7, Ultrasonic Examination

PTIP-30696-5.2, Rev. 0, Rev. 0, Susquehanna Weld Remediation

PTIP-30696-5.2, Rev. 0, Rev. 1, Susquehanna Weld Remediation Procedure

Miscellaneous

2014 Dry Fuel Storage, Status Report

- Campaign No. 8

2.48 Screening, Susquehanna Weld Remediation of DFS Canister

AREVA E-41005, Executive Summary of PPL and TN Review of Fabrication Issues

AREVA E-42068, DSC Procurement Specification, May 22, 2015

AREVA TN Form 15.1

-1, Rev. 10, Reportability Determination, CAR No. 2014

-339 AREVA Presentation "SSE

-61BTH-1-2-052 Repair Plan"

Certificate of Compliance No. 1004, Amendment 10

Form 3.5-1, Rev.8 10 CFR Part 72.48 Applicability and 10 CFR Part 71 Review, LR No.

21004-1388 Rev. 1

PPL Susquehanna Pool to Pad 30969 TN Logbook 2014

Radiation Work Permit 2014

-0204, Repair Dry Fuel Storage Canister #83

TC/DSC Monitoring Log

WPS TN-P8-P8-GT1, Rev. 1

WPS TN-P8-P8-GT2, Rev. 1

LIST OF ACRONYMS USED

CoC Certificate of Compliance

DNMS Division of Nuclear Material Safety

DSC Dry Shielded Canister

IP Inspection Procedure

ISFSI Independent Spent Fuel Storage Installation

NDE Nondestructive Examination

NRC Nuclear Regulatory Commission

OTC Outer Top Cover

PT Dye Penetrant Test

SSES Susquehanna Steam Electric Station

TN Transnuclear, Inc.

TS Technical Specifications

UT Ultrasonic Testing