ML17158B878

Summary of 960912 Meeting W/Util in Berwick,Pa to Discuss Licensee Plans for Const & Implementation of on-site Dry Cask Spent Fuel Storage Facility

ML17158B878
Person / Time
Site:	Susquehanna
Issue date:	11/24/1996
From:	Poslusny C NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9612020046
Download: ML17158B878 (59)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 November 24, 1996 LICENSEE:

Pennsylvania Power and Light Company FACILITY:

Susquehanna Steam Electric Station (SSES),

Units I and 2

SUMMARY

OF SEPTEMBER 12, 1996 MEETING TO DISCUSS THE DRY CASK STORAGE PROGRAM AT SSES, UNITS I AND 2 On September 12,

1996, a meeting was held between members of the Office of Nuclear Reactor Regulation (NRR), Office of Nuclear Material Safety and Safeguards (NMSS), Region I, and Pennsylvania Power

& Light Company (PP8IL or the licensee) to discuss the licensee's plans for the construction and implementation of an on-site dry cask spent fuel storage facility at the Susquehanna Steam Electric Station (SSES) located in Berwick, Pennsylvania.

Enclosure I is a list of the meeting attendees.

During the first portion of the meeting, PP8IL staff provided a presentation and a discussion of the overall history of the program initiated in 1992 focusing on completed and planned milestones.

Enclosure 2 is a copy of the slides outlining the information that was discussed.

Significantly noted in this portion of the meeting were the following facts:

~

the licensee is adding the storage capacity for spent fuel under the general license for the NUHOMS horizontal sto'rage

design,

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during the site and design selection

process, PPSL established a high level of public participation and has not received any local feedback of a negative nature related to its plans to store spent fuel,

~

the site will not run out of spent fuel pool storage in the current pool until after 2000, but the dry cask facility is planned for initial use in the fall of 1997,

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PPSL quality assurance staff has played an active roll in the oversite of the design process being implemented by Vectra, the vendor,

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the licensee has routinely contacted other licensees and visited sites using the dry cask storage technology to keep abreast of lessons learned during the licensing and implementation

process,

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the first set of draft procedures have been completed and are planned to be in final draft version by December of 1996,

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heavy loads analyses are expected to be completed by the end of 1996 with sensitivity to the lessons learned at Oyster Creek,

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the licensee indicated that it would inform the staff when significant analyses had been completed to facilitate staff inspection planning and

, implementation, and

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~ it was noted that PPLL had not included the need to provide the 72.82e report to the staff in its overall schedule and it was agreed that this would be added.

The second portion of the meeting was dedicated to the staff's comments on regulatory requirements, lessons learned from recent licensing experiences, and comments on the concrete pad design.

Comments included the following:

~

the value of constant and meaningful communication between licensee and regulator was emphasized regarding Part 70 requirements, fabrication and installation schedules, and testing and training activities, the value of conducting dry runs to enhance the effectiveness of the training process and to validate the adequacy of procedures,

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testing programs need to be well planned and executed, noting the experience at Point Beach and Prairie Island,

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the Point Beach Augmented Inspection Team report should be reviewed for lessons

learned,

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fuel loading and unloading usually produces a great deal of public interest based on experience by other licensees,

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planning for unloading considering both Part 50 and 70 requirements should be done well in advance to avoid the need for exigent amendments,

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recent problems have been identified with particular thermal shield paint used in the casks and should be considered in the design process, and

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a management level meeting to discuss an overview of the project will need to be scheduled with PPKL in the future.

NRR staff raised a number of questions on the adequacy of the design of the concrete pad which will support the casks and was provided a copy of the structural analyses that were performed by Vectra.

It was not clear whether the nature of the questions related to the methodology that was used to determine the minimum thickness of the pad to address static loads had a

regulatory basis, in Part 72.,fiHowever, the staff indicated that it would review the information, provide input to a Region I inspection report and would return'he'analyses to 'the licensee subsequent to the review.

I

'Pg/

ll

, Chester

Poslusny, Senior Project Manager

'roject Directorate I-2 Division of Reactor Projects - I/II

,- Office of Nuclear Reactor Regulation Docket Nos. 50-387/388, JI I

Enclos(re's; 1.

Meeting Attendees List Licensee's Handouts J

cc w/encls; See next page DISTRIBUTION: *w/Enclosures 1, and 2

HARD COPY

• Docket File

• PUBLIC,

• PDI-2 Reading OGC ACRS

• WPasciak, RGN-I E-NAIL WRussell/FMiraglia RZimmerman SVarga JZwolinski JStolz

• CPoslusny HO'Brien EJordan (JKR)

PNarbut YKim ELeeds THcGinty WReckley DPersinko GBagchi BThomas FSturz

SPindale, RGN-I CAnderson, RGN-I WDean OFFICE PDI-2 H

DI-2 0 Stolz NAME CPoslusny:rb H '

J(

2u96 DATE

/96 96 OFFICIAL RECORD COPY'OCUMENT NAME:

SU9-12.HTS

FF k

regul,atory basis in Part 72.

However, the staff indicated that it would review the info'rmation, provide input to a Region I inspection report and would return the analyses to the licensee subsequent to the review.

I Docket Nos. 50-387/388 Chester

Poslusny, Senior Project Nanager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

I.

Meeting Attendees List 2.

Licensee's Handouts cc w/encls:

See next page

Pennsylvania Power

& Light Company Susquehanna Steam Electric Station, Units 1

& 2 CC:

Jay Silberg, Esq.

Shaw, Pittman, Potts

& Trowbridge 2300 N Street N.W.

Washington, D.C.

20037 Bryan A. Snapp, Esq.

Assistant Corporate Counsel Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Nr. J.

M. Kenny Licensing Group Supervisor Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. K. Jenison Senior Resident Inspector U.

S. Nuclear Regulatory Commission P.O.

Box 35 Berwick, Pennsylvania 18603-0035 Hr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.

Box 8469 Harrisburg, Pennsylvania 17105-8469 Nr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.

212 Locust Street P.O.

Box 1266 Harrisburg, Pennsylvania 17108-1266 Chairman Board of Supervisors 738 East Third Street

Berwick, PA 18603 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Nr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,

Box 1797 Berwick, Pennsylvania 18603 George T. Jones Hanager-Engineering Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. Robert G.

Byram Seni or Vice President-Nucl ear Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803

EETING ATTENDEES LIST DRY CASK STORAGE PROGRAM MEETING SEPTEMBER 12 1996 NAME J. Stolz C. Poslusny Y. Kim W. Reckley G. Bagchi B. Thomas P. Narbut F. Sturz E.

Leeds T. HcGinty D. Persinko S. Pindale C. Anderson R. Saccone R. Matthews D. Reinsmith K. Kelenski R. Sgarro A. Maron D. Parsons B. Maiers A. Nelson T. Wittig ORGANIZATION NRC/NRR NRC/NRR NRC/NRR NRC/NRR-NRC/NRR NRC/NRR NRC/NHSS NRC/NHSS NRC/NHSS NRC/NHSS NRC/NMSS NRC/RGN-I NRC/RGN-I PP&L PP&L PP&L PP&L PP&L PP&L PP&L PADEP-DRP NEI Vectra ENCLOSURE I

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SPENT FUEL S TORAGE AT SUS UEHANNAS TEAM ELECTRIC STATION WORKINGLEVELMEETINGWITHTHE U.S. NRC September 12, 1996 Rockville, MD

+ Introductions

+ PPRL's Plans for Spent Fuel Storage at Susquehanna Steam Electric Station

+ Management Perspective.................................

R. A. Saccone Manager-Nuclear Modifications

+ Project Overview................................................

K. J. Kelenski Project Manager

+ Quality Assessment...........................................

R. E. Matthews Sr. Analyst-Nuclear Assessment Services NRC Licensing Requirements NRC Planned Inspection Activities

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'MANAGEMENTPERSPECTIVE

+ PP8zL has a Strong Record Regarding the Design and Operation of Susquehanna.

Standards Applied to this Project Include:

+ Strong Management Involvement and Comjmitment of Resources

+ Proactive Approach

+ Good Public Involvement

+ Engineering Accountability

+ Lessons Learned

+ Regulatory Compliance

+ Strong Quality Assurance Program/Assessment

+ Susquehanna Steam Electric Station - 2 Unit Site, each consisting of a General Electric BoilingWater Reactor, BWR/4 with a 1150 MWe nominal rating.

+

Rated core thermal power is 3441 MWtwith a corresponding net electrical output of 1122 1VI'We for Unit 1 and 1126 MWe for Unit 2.

+ Unit 1 original fuel load - July 27, 1982; commercial operation June 8, 1983.

+ Unit 2 original fuel load March 28, 1984; commercial operation February 12, 1985.

INTRODUCTION(coNTINLIED)

+ Each Unit has its own spent fuel storage pool.

+

Each pool has 24 high density storage racks equating to a storage capacity of 2840 fuel assemblies plus 10 multipurpose cavities for storage of control rods, control rod guide tubes, and defective fuel containers.

+ Current Storage:

+ Unit 1 - 1832 Fuel Assemblies

+ Unit 2 - 1696 Fuel Assemblies

+ Roughly 304 fuel assemblies are offloaded per outage per Unit

+ Project Plan calls for the first fuel moves to the Independent Facility to begin in September 1997.

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SPENT FUEL STORAGE PROJECT PROJECT ORGANIZATION Project Sponsor Tony lorfida High Level Waste Team Public I Internal Communication Project Manager K. Kelenski Vectra Technologies Design Procurement Licensing System Eng Training QAIQC Nuclear Fuel Effluent HP Operation Security

EVALUATIONSPERFORMED TO S UPPORT PROACTIVE APPROACH

+ Siting Report September, 1992

+ Phase I Technical Assessment - February, 1993

+ Performance Specification Developed for, Reracking and Dry Cask Storage - June, 1993

+ Final Technical Assessment Completed-October, 1994

+ Avrarded Contract - January 1995

+ A Public Involvement Program was initiated to ensure Public awareness and to solicit feedback.

+ Various methods of presenting PP8zL's plans were implemented:

+ Presentations to the Susquehanna Citizens Committee

+ Personal Notification of Area Officials

+ Media Day

+ Presentations to Volunteer Organizations which support the Susquehanna Emergency Response Organization

+ Articles in the Susquehanna Quarterly Newsletter which is distributed to the surrounding communities

DRY STORAGE TECHNOLOGY AT SSES

+ VECTRA"NUHOMS" (Horizontal Storage Technology)

+ Certificate of Compliance (Certificate Number 72-1004)

+ Implementing under General License

NUHOMS KEYSYSTEM COMPONENTS

+Dry Shielded Canister DSC's

+Horizontal Storage Modules HSM's

+Transfer Cask

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+ Design Note:

Lessons Learned based on experiences at other utilities have been incorporated into the SSES design, complementing a thorough PP&L Engineering review.

10 CFR 72.210 has been the basis for the irnplernentation of the NUHOMS System at SSES.

HSM s, DSC's etc. - Utilized Certified Design reconciled for SSES Plant Specific Differences Independent Reviewer by a Third Party of the Plant Specific Differences Design Change Control

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S TRATEGYFOR IMPLEMENTATION(coNTINLIED)

+ Summary of Analysis/Calculations Performed to Support Heavy Loads Issue and Structural Analysis

+ Refuel Floor

+ Ensured Crane Certification (single failure)

+ Cask Tip-over Analysis

+ Canister Tip-over analysis

+ Safe Load Path

+ Floor Loading for Staging Equipment

+ Equipment Pit Floor Loading

+ Cask Pit Floor Loading

+ Train Bay Floor Loading

STRATEGY FOR IMPLEMENTATION(coNTINUED)

+ Summary of AnalysisjCalculations Performeci to Support Canister Movement

+ Load Path to Storage Pad

+ Evaluated Roadways and Underground Utilities

+ Developed Instantaneous Dose Calculation Evaluated Inclines to ensure withinbounds of Transfer System

S TRATEGYFOR IMPLEMENTATION(coNTINUED)

+ Summary of Analysis/Calculations Performed to Support Storage Pad Construction

+ Storage Pad (Seismic)

+ Soil Bores to support seismic design

+ Shear Wave Velocity Testing

+ Hydrology Testing (Test bore/pipe in place to monitor ground water)

+ Replaced existing soil with engineered fill compacted and tested every 4-6 inches

+ Utilized state of the art computer analysis for development of concrete pad design

+ Developed Integrated Dose Calculation

'A STRATEGY FOR IMPLEMENTATION(cONTINUED)

+ Construction

¹te:

SSES ISFSI is being constructed inside the protected area and is encompassed by the existing Security and Emergency Plans

+ Spent Fuel Storage Pad

+ (6) Concrete slabs totaling 262 ft. x 215 ft. x 18 1D.

+ Reinforced with wire welded fabric

+ Fencing

+ 8 ft. high chain linkfence

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STRATEGY FOR IMPLEMENTATION(co@TINUED)

+ COI1Stl llCt1011 Continued

+ Lighting

+ 500 watt high pressure sodium light located on east and west sides of pad

+ Temperature Monitoring

+ GE FANUC Programmable logic controller

+ Thermocouple for each module

+ Tied to plant computer

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sf/Fg.jgj STRATEGY FOR IMPLEMENTATION(CONTINUED)

+ Fabrication of Components

+ HSM's (9) -Bayshore, Cape Charles VA.

+ DSC's (8) - Ranor, Westminster MA.

+ Transfer Cask-Leased from VECTRA Technologies

S TRATEGYFOR IMPLEMENTATION(coxTINUzD)

+ Operation-Entire evolution willbe accomplished by PPkL personnel.

+ Procedures under Development:

+ Fuel Transfer Evolution

+ Unloading HSM and Cutting Open DSC

+ Preparation of HSM's/DSC's

+ Dry Run Procedures

+ Welding Procedures

S TRATEGYFOR IMPLEMENTATION(coNrrNUED) e Operation-Entire evolution vrillbe accomplished by PPEzL personnel.

+ Trauung;

+ Trainjing course being developed to certify personnel involved withfuel transfer

+ Utilize OJT Davis-Besse Spring 1997

+ One week training in Spring/Summer 1997

UALITYASSESSMENT Appendix OPS-1-K to the SSES Operational Quality Assurance Program, "Independent Spent Fuel Storage Installation, Quality Assurance Plan," Revision 0, dated January 19, 1996.

UALITYASSESSMENT (CONTINUED)

+ Integrated Assessment Plan

+ Design Review/Technical Evaluations

+ Procurement/Fabrication Oversight

+ On Site Construction Oversight

+ Operations

UALITYASSESSMENT (CONTINUED)

+ Integrated Assessment Plan (continued)

+ Inspections

+ Source Verifications

+ Surveillances

+ Document Reviews

+ Audits

UALITYASSESSMENT (CONTINUED)

+ Leadership Initiatives

+ Vectra Project Instruction FS-PPL-96-01

+ NUHOMS Owners'roup QA Subcommittee

+ NUHOMS Owners'roup Audit Team Leader

+ Vectra, San Jose, CA

+ Ranor~ Westminster, MA

+ Leased Equipment Control Issues

+ Reactor Water Chemistry Issues

+ Load Test Calibration Issues

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UALITYASSESSMENT (CONTINUED)

+ Audits

+ Audit 93-134, Vectra Fuel Services Group

+ Audit 96-001, NUHOMS OG Auditof Vectra

+ Audit 96-083, NUHOMS OG Auditof Ranor

UALITYASSESSMENT (CONTINUED)

+ Source Verifications (Onsite Transfer Cask)

+ 95-012, Gamma Scan Inspection of Lead Pour*

+ 95-013, Dimensional Inspection Prior to Lead Pour

+ 95-025, Dimensional Inspection - Trurunion Locations

+ 95-026, Trurunion Pull/Load Test

+ 95-027, Final Gamma Scan Inspection of Lead Pour"

+ 95-036, Shell CylindricityTest and Wall Thickness Inspection"

+ 95-043, Pressure Test and Helium Leak Test*

+ 95-048, Final Documentation Package",

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UALITYASSESSMENT (CONTINUED)

+ Source Verification Transfer Cask Hook Yoke

+ 95-042, Performance Tests 1,2,& 3

+ 95-044, Performance Test 4

+ 95-047, Final Documentation Package

UALITYASSESSMENT (CONTINUED)

+ Ongoing Activities

+ Storage Pad Welded Wire Fabric

+ Manufacturer of Welded Wire Fabric (Structural Reinforcement Products, Survey 96-078)

+ Developed Procurement Plan

+ Conducted Source Verification

+ Storage Pad

+ Independent Concrete Testing (United Inspection Services, Survey 96-054)

+ Full Time PP&L QC Coverage

+ Selected Surveillance Coverage

UALITYASSESSMENT (CONTINUED)

+ Plaruzed Activities (Hook Adapter, DSCs, HSMs)

+ Conduct Audit/Survey

+ Determine extent of Vectra Coverage (Project Instruction)

+ Develop Source Verification Plan (Each Component)

+ Develop Source Verification Critical Characteristics (Each Verification)

+ Establish "HOLD"Points

+ Perform Source Verifications

UALITYASSESSMENT (CONTINUED)

+ Planned Activities Subvendors

+ For Ranor

+ Approve all subvendors

+ To Be Reviewed during Source Verification

+ For Others - Implement Project Instruction FS-PPL-96-01

+ Determine extent of Vectra Coverage

+ Implement Audit/Survey/Source Verification

SUSQUEHANNA STEAM ELECTRIC STATION SPENT FUEL STORAGE PROJECT MILESTONE SCHEDULE K. Kelenski Project Manger Data Date 9/10/96 Run 9/11/96 1996 1997 R MAY. JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC CONSTRUCT DRYSTORAGE PAD FABRCATEF/RST 9 HShh PLANTOEUVERYOF RRST HSMI PROCEDURE PREPARATiON COMPLETE TRAMNGMODULEDEVELOPMENTCOMPLETE PART 72 EVALUAllCNCOMPLETE PART 50.59 EVALUATIONCOMPLETE FABRICATEDSCs PLANTDEUVERYOF OSCAR TRANOPERATCNS ANDSUPPORT PERSONAL PREPARAllON/STAGING FOR DRYRUN SUBM/TNOTICE TO NRC DRYRUN TEST COMMENCE FUEL MOVES TO NEW FACUTY 10SEP96 11/01/98 11/1$96 Q 11/15/98 12/31/98 Q 12/31/98 12/31/98 Q 12/31/98 12/31/98 Q 12/31I98 12/31/96 Q 12/31$ 8 01/15$ 7 05/06/97 07/2$ 97 0$05/97 0$09/97 I

0802/97 07/25$ 7 07/26$7 or/26$ 7 11/17/97

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