IR 05000220/2012009

IR 05000220-12-009 and 05000410-12-009, on 7/23/12 - 9/19/12, Nmpnps, Preoperational Testing of ISFSI at Operating Plants, Review of 10 CFR 72.212(b) Evaluations, and Operation of Isfsi'S at Operating Plants

ML12299A355
Person / Time
Site:	Nine Mile Point
Issue date:	10/25/2012
From:	Ferdas M S Decommissioning Branch I
To:	Langdon K Nine Mile Point 3 Nuclear Project
References
IR-12-009
Download: ML12299A355 (11)

Text

UNITED STATES NUGLEAR REGULATORY COMiIISSION REGION I 21OO RENAISSANCE BOULEVARD, SUITE .IOO KING OF PRUSSIA, PENNSYLVANIA 19406-2713 October 25,2012 Mr. Kenneth Langdon, Site Vice President Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093-0063

SUBJECT: NINE MILE POINT NUCLEAR STATION - NRC INDEPENDENT SPENT FUEL sroRAGE TNSTALLATTON (lSFSl) INSPECTION REPORT NOS.05000220t201 2009 AN D 05000 41 0 1201 2009

Dear Mr. Langdon:

On September 14,2012, the U.S. Nuclear Regulatory Commission (NRC) completed an ISFSI inspection at your Nine Mile Point Nuclear Station, Units 1 and 2. The enclosed inspection report documents the inspection results which were discussed on September 19, 2012, with Ken Phy, ISFSI Project Manager, and other members of your staff.The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

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

ln accordance with 10 CFR Part 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/(" >,4A -Marc S. Ferdas. Chief Decommissioning Branch Division of Nuclear Materials Safety Docket Nos. : 50-220, 50-410, 72-1036 License Nos.: DPR-63, NPF-69 Enclosure:

lnspection Report 0500022012012009 and 0500041012Q12O09 MAttachment:

Supplementary Information cc w/encl: Distribution via ListServ

SUMMARY OF FINDINGS

lR 0500022012012009 and 0500041012012009:0712312012-0911412012;

Nine Mile Point Nuclear Station, Units 1 and 2; Preoperational Testing of lndependent Spent Fuel Storage f nstallations (lSFSl) at Operating Plants, Review of 10 CFR 72.212(b)

Evaluations, and Operation of ISFSI's at Operating Plants.This report covers the ISFSI operational dry run and initial loading inspection conducted by a team of six NRC inspectors.

The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.No findings were identified.

3

REPORT DETAILS

4. OTHER ACTTVTTTES (OA)4OA5 Other Activities

.1 Preooerational

Test Proqram (60854, 60854.1. and 60856)a. Inspection Scope The inspectors evaluated NMPNS's performance during NRC observed pre-operational dry run activities that were performed in order to fulfill requirements in Technical Specifications (TS) 1.1.6. The inspectors observed NMPNS dry run activities on July 23-26,2012, and August 27-31,2012.

During the first week the inspectors observed cask processing activities including:

blowdown, vacuum drying, helium backfilling, reflooding, gas sampling, welding, non-destructive examinations, and helium leak testing. During the second week the inspectors observed canister loading operations including:

insertion and removal of the dry shielded canister (DSC) from the transfer cask (TC), movement of the TC/DSC into the spent fuel pool, movement of a dummy fuel assembly into several locations in the DSC, removal of the TC/DSC from the spent fuel pool, moving of the TCIDSC to the cask processing area, down-ending the TC onto the transporter, transporting the TC to the ISFSI pad, and retrieving and inserting a weighted DSC into a horizontalstorage module (HSM).The inspectors reviewed DSC loading, unloading, and processing procedures to ensure that they contained commitments and requirements specified in the Certificate of Compliance (CoC), TS, Final SafetyAnalysis Report (FSAR), and Title 10 of the Code of Federal Regulations (CFR) Part7Z. The inspectors reviewed the ISFSI seismic calculations and the analysis of the heavy haul path from the reactor building to the ISFSI pad. Also, the inspectors reviewed fuel selection procedures to ensure they appropriately incorporated the requirements in the TS.The inspectors evaluated NMPNS's compliance with the requirements of 10 CFR 72.212 and 10 CFR72.48.

The inspectors verified NMPNS's written evaluations were in accordance with 10 CFR72.212(bX2Xi)and confirmed:

(1) the conditions set forth in the CoC had been met prior to use,

(2) the ISFSI pad had been designed to support the load of stored casks, and

(3) the radiological requirements of 72.104 had been met. The inspectors verified that applicable reactor site parameters, such as fire and explosions, tornadoes, wind-generated missile impacts, seismic qualifications, lightning, flooding and temperature, had been evaluated for acceptability with bounding values specified in the FSAR and the NRC Safety Evaluation Report (SER). The inspectors also verified that a 50.59 evaluation of the construction and operation of the ISFSI and plant interfaces were not required and that ISFSI related work activities would not impact the safe operation of Nine Mile Point. Units 1 and 2.Enclosure b.a.4 Findinqs No findings were identified.

Initial Loadinq of the ISFSI (60855 and 60855.1)Inspection Scope The inspectors observed and evaluated the licensee's loading of the first of six DSCs associated with the initial ISFSI dry cask campaign on September 10-14, 2O12. The inspectors also reviewed the licensee's planned activities related to long-term operation and monitoring of the lSFSl. The inspectors verified compliance with the CoC, TS, regulations, and station procedures.

The inspectors observed the heavy load movement of the TC and loaded DSC from the spent fuel pool to the cask decontamination and processing area. The inspectors also observed DSC processing operations including:

decontamination and surveying, welding, non-destructive weld examinations, DSC draining, vacuum drying, and helium backfilling.

During performance of these activities, the inspectors verified that procedure use, communication.

and coordination of ISFSI activities met established standards and requirements.

The inspectors reviewed the licensee's program associated with fuel characterization and selection for storage. The inspectors reviewed the first cask fuel selection package to verify that the licensee was loading fuel in accordance with the CoC, TS, and procedures.

The inspectors reviewed radiation protection procedures and radiation work permits (RWPs) associated with the ISFSI loading campaign.

The inspectors also reviewed the established radiological controls.

The inspectors assessed whether workers were aware of the radiological conditions in their work area and the RWP controls/limits.

The inspectors reviewed radiological records from the first DSC loading to confirm that radiation survey levels measured were within limits specified by the TS and consistent with values specified in the FSAR.The inspectors performed a walk-down of the heavy haul path and toured the ISFSI pad to assess the material condition of the pad and the HSMs. The inspectors also verified that transient combustibles were not being stored on the ISFSI pad or the vicinity of the HSMs. The inspectors also confirmed that vehicle entry onto the ISFSI pad was controlled in accordance with procedures.

The inspectors reviewed corrective action reports and the associated follow-up actions that were generated since NMPNS started planning for their initial ISFSI campaign to ensure that issues were entered into the corrective action program, prioritized, and evaluated commensurate with their safety significance.

b.5 Findinss No findings were identified.

Meetinqs.

includino Exit On September 19, 2012, the team presented the results via telephone to Ken Phy, ISFSI Project Manager, and Madhav Shanbhag, Licensing Engineer.

The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.Attachment:

Supplementary Information A-1

=SUPPLEMENTARY

INFORMATION=

KEY POINTS OF CONTACT

PARTIAL LIST OF PERSONS CONTACTED NMPNS

D. Bensel, Reactor Engineer G.Connor, Design Engineer

J. DeSando, Fleet Maintenance

J.Henry, Radiation

Protection

J.Jock, ISFSI Foreman J.Kidd, Quality Assurance M.Lavery, ISFSI Supervisor

P. Mills, Radiation

Protection

J.Olmundsen, ISFSI Supervisor

S.Penney, Reactor Engineer K.Phy, ISFSI Project Manager M.Philippon, Plant General Manager A.Ross, Reactor Engineer M.Shanbhag, Licensing

Engineer T.Sollenberger, Radiation

Protection

.,

NRC Personnel

D.Dempsey, Resident Inspector E.Miller, Resident Inspector ITEMS OPEN. CLOSED. AND DISCUSSED Opened/Closed/Discussed

None

LIST OF DOCUMENTS

REVIEWED Procedures

lNER-FU-045, Rev. 3,'lSFSl Bundle Characterization Data for NMP1 and NMP2"

CNG-AM-1.01

-1006, "Qualification and Certification of NDE Personnel"

CNG-MN-1.01-1003, Rev. 00400, "Load Handling"

CNG-PR-2.01

-1 000, Revision 00200, "Document Control"

CNG-PR-3.01

-1 000, Revision 00201, "Records Management" N1-ST-D2001, "lSFSl Daily Checks" N2-PM-SO14

Revision 15, "Building Rounds" Attachment

NMP-

NDEP-PT-3.00, Rev. 01900, "Dye Penetrant Inspection"

NMP-NDEP-SP-7.02, Revision 01 100, "Visual Examination of Welding Operations" NMP - Vendor Procedure -

MSLT-DSC0NMP, Rev. 0, "Helium Mass Spectrometer Leak Test Procedure" S-MMP-ISFSl-001, Rev. 00100,'lSFSl Equipment Preparation" S-MMP-ISFSl-002

Rev. 00100, "Dry Shielded Canister Pre-Use Inspection" S-MMP-lSFSl-003, Rev. 00000, "DSC Loading Operations" S-MMP-lSFSl-004, Rev. 00000, "DSC Sealing Operations" S-MMP-lSFSl-005, Rev. 00000, "Site Cask Transportation" S-MMP-lSFSl-006, Rev. 00000, "HSM Operations" S-MMP-lSFSl-007, Rev. 00000,'DSC

Unsealing Operations" S-MMP-lSFSl-008, Rev. 00000,'DSC

Unloading Operations" S-MMP-lSFSl-009, Rev. 00100, "Transfer Cask Annualand Pre-Use Inspection" S-MMP-lSFSl-010, Rev. 00000,'lSFSl Shipping Logistics" S-MMP-lSFSl-011

Revision 0, .lSFSl Abnormal Events" S-REP-S, Rev. 0, "Fuel Selection for

NUHOMS-618T

Type A Basket DSC'S-REP-7, Rev. 0, 'NUHOMS DSC Verification and Inspection" S-RPIP-3.0, Rev. 01800, "Radiological Surveys" S-RPIP-5.1, Rev. 01000, "Dosimetry Use Placement and Dose Tracking" S-RPIP-5.3, Rev. 05, "Neutron Dose Assessment" Calculations

W-1-129, "Concrete Heavy Haul Path For lSFSl" W-1-134, "Underground Utilities Evaluation for The Nine Mile Point lSFSl, Phase 2" H21C11 1, Rev. 0, "Decay Heat Calculation for lSFSl" SORX261CMO1, "Evaluation For ISFSI Related Activities" SORX340CS09, "Spent Fuel Pool Structure Analysis For High Density Rack" SORX261CS06, "Evaluation Of Transfer Cask For Seismic Stability" Corrective Action Condition Reports

CR-20 1

2-002237, C R-2 0 1

2-0070 53, a n d C R-20 1

2-008494 Drawinos 09-000007, ISFSI Storage Area, Final Site Layout 09-000008, ISFSI Pad and Approach Slabs 09-00001 1, ISFSI Storage Area Grounding Plan Maintenance

Work Orders

Work Order -

C91432655 Attachment

Miscellaneous

Constellation Energy Generation Group, LLC, "Quality Assurance Topical Report" Revision 6 Duke Energy Letter to NRC, Cask Certificate of Compliance, Docket No. 72-1004, 30-Day Report for Higher Canister Heat Loading per General Requirement Section 1.1.7, dated Aug ust 8, 2007 (ML07 2340622)lndependent Spent Fuel Storage installation Pre-Operational Testing Exercise Dry Run Plan, Welding Documents:

NMP-PQR-210R,

NMP-WPS-8-8-B-104, and NMP-WPS-8-8-BA-102

NMPNS Engineering Change Package 10-00034 revision 0, lmplement Dry Fuel Storage at

NMP-ISFSl, Licensing

,212 Analyses, Programs, Procedures, and lmplementation Changes Nine Mile Point (Design Criteria Document 115 revision 1), Criteria for Seismic Analysis Progress Energy Letter to NRC, "Registration and Use of Cask to Store Spent Fuel and System Thermal Performance Assessment," dated February 24,2011 (ML1 10670429)Nine Mile Point Nuclear Station Independent Spent Fuel Storage Installation

10CFR72.212

Evaluation Report for Docket 72-1036

RWP-1 12014, ISFSI Activities Updated Final Safety Analysis Report for the Standardized

NUHOMS@ Horizontal Modular System for lrradiated Nuclear Fuel in accordance with CoC Number 1004, Transnuclear Report No.: NUH-003

LIST OF ACRONYMS

USED [[]]

CFR Code of Federal Regulations

CoC Certificate

of Compliance

DSC Dry Shielded Canister

FSAR Final Safety Analysis Report HSM Horizontal

Storage Module ISFSI Independent

Spent Fuel Storage Installation

NMPNS Nine Mile Point Nuclear Station

NRG Nuclear Regulatory

Commission

OA Other Activities

RWP Radiation

Work Permit SER Safety Evaluation

Report

TC Transfer Cask

TS Technical

Specifications

Attachment