ML20138C808
| ML20138C808 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/25/1997 |
| From: | James Shea NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9704300204 | |
| Download: ML20138C808 (39) | |
Text
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5 g ng C3C- Y g i jh hOf UNITED STATES j
4 J
g NUCLEAR REGULATORY COMMISSION 2 WASHINGTON. D.C. 20666-4001 l
4 ....,l 4
April 25, 1997 LICENSEE: PECO Energy Company, et al.
4 FACILITY: Peach Bottom Atomic Power Station, Units 2 and 3
SUBJECT:
SUMMARY
OF APRIL 10, 1997 MEETING ON SPENT FUEL DRY CASK STORAGE FACILITY On April 10, 1997, the NRC staff met with PECO Energy Company (PECO) representatives at the NRC offices in Rockville, Maryland, to discuss the planned construction of a spent fuel dry cask storage facility for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. A list of meeting participants is enclosed (Enclosure 1). Also enclosed is a copy of PEC0's meeting handout (Enclosure 2).
PECO representatives opened the meeting by stating that the purpose of the meeting was to present an overview of PEC0's plans and schedules for the spent I fuel dry cask storage facility, relate to the NRC staff PECC's understanding '
of current dry cask storage quality issues, and gain feedback from the staff ;
about project implementation and plans. PECO then discussed some background 1 behind the need for a spent fuel dry cask storage facility.
t The licensee gave a project overview including a set of milestones. PEC0 stated that they plan to use the general license process and have the facility available prior to fall 2000 so that they may maintain full core discharge capability. The licensee related that they are basing their timetable around being able to start the dry run of the facility in July 1999 so that they can /
begin cask loading in fall 2000. PEC0 also discussed the implementation of their communications plan to establish and kaep a dialogue with the NRC staff,
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PEC0 employees, state and local governments, and the public. The licensee / '
also described the engineering approach they are taking so that they may
, utilize industry experience and cross-discipline oversight. /)/ g tx e The licensee then described the site selection and design considerations they will employ. PEC0 described possible sites for the facility, but stated that no site had been chosen at that time. PEC0 described that, depending on the site selected, it may be necessary to construct or improve vehicle bridge structures between the plant and the storage site. The staff responded that the licensee should look into the cask drop criteria. PECO also asked the NRC staff about problems with siting the facility along the Susquehanna River.
The staff suggested that PECO have discussions with other licensees with facilities near bodies of water.
The licensee next discussed the storage system selection process, and the evaluation considerations used. PEC0 stated that they were considering 6 vendors, and that no proposals had been submitted to them at that time. PEC0 stated that they have established a dialogue with other users and are looking l
300042 NRC FM.E CENTER COPY 9704300204 970425 PDR ADOCK 05000277 P PDR .
at vendor quality and commercial viability of the vendor as well as the product. The NRC staff responded that they encourage careful vendor selection. r ') also asked about the licensing schedules for cask designs.
The staff re p: 1ded that no safety evaluations have been written for those designs in rt. ew at this time, but did indicate that the rulemaking process for a partict r storage system would typically take up to one year beyond the date of the ,taff's safety evaluation for that system.
The licensee then discussed Quality Assurance (QA) and PECO's plan to use lessons learned from other utilities. PECO discussed their plan to use an interface QA program where PECO would have inspection oversight at subvendor manufacturing locations and would conduct vendor surveillance and inspections.
PECO also stated that they have written a OA plan, and plan to make design requirements up front.
The licensee then discussed how they plan on tracking licensing compliance with a compliance matrix and electronic compilation of the design record. The licensee asked for some feedo'ack about 10 CFR 72.48 evaluations, and the NRC staff responded that the licensee should look at recent inspection reports for additional insight. The staff also indicated that upcoming documents will clarify the general license, seismic censiderations.10 CFR 72.82(e), and inspection issues.
/S/
Joseph W. Shea Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-277/278
Enclosures:
- 1. Meeting Attendees
- 2. Licensee Meeting Handout cc w/encls: See next page DISTRIBUTION w/ Enclosure 1 (*w/ Enclosures 1 and 2)
Hard Cooy
- Docket File
- PUBLIC
- WPasciak. RGN-I JShea ,
E-Mail SCollins/FMiraglia TKobetz MHart RZimmerman ELeeds WDean SVarga/JZwolinski SMcDuffie CAnderson RI M0'Brien FSturz JStolz Dross (SAM) MWaters WReckley 0FFICE PDI-2/l , PD[-i/PM P0l[TNA% SP0 [ PDI-2/04/[
NAME NiN:@ ASMa(h M0Yib ELeeds JStolz /e^
DATE d/d/97 d kd/97 D/f<//97 c/R3:/97 4 /2 3/97 0FFICIAL RECORD COPY t DOCUMENT NAME: PB4-10.MTS
s 3 at vendor quality and commercial viability of the vendor as well as the
" product. -The NRC staff responded that they encourage careful vendor ;
selection. PECO also asked about the licensing schedules for cask designs; '
4 The staff responded that no safety evaluations have been written for those -
! designs in review at this time, but did indicate that the rulemaking process '
for a particular storage system would typically take up to one year beyond the 1
date of the staff's safety evaluation for that system.
j The licensee then discussed Quality Assurance (QA) and PECO's plan to use i i lessons learned from other utilities. PECO discussed their plan to use an
' interface QA program where PEC0 would have inspection oversight at subvendor manufacturing locations and would conduct vendor surveillance and inspections.
PECO also stated that they have written a QA plan, and plan to make design 4 requirements up front.
4 The licensee then discussed how they plan on tracking licensing compliance t 1 with a compliance matrix and electronic compilation of the design record. The licensee. asked for some feedback about 10 CFR 72.48 evaluations, and the NRC staff responded that the licensee should look at recent inspection reports for additional insight. The staff also indicated that upcoming documents will clarify the general license, seismic cons rations, 10 CFR 72.82(e), and inspection issues.
[/ '
! se h W. Shea, Project Manager
! Project Directorate I-2 i
Division of Reactor Projects - I/II ;
Office of Nuclear Reactor Regulation <
1 j Docket Nos. 50-277/278 i
j
Enclosures:
- 1. Meeting Attendees j
2
- 2. Licensee Meeting Handout i cc w/encls: See next page i
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)
- PECO Energy Company Peach Bottom Atomic Power Station, Units 2 and 3 cc: .
]
J. W. Durham, 5t., Esquite Chief-Divisiali of Hudsai SatEty Sr. V.P & General Counsel PA Dept. of PECO Energy Company Environmental Resources 2301 Market Street, S26-1 P.O. Box 8469 Philadelphia, PA 19101 Harrisburg, PA 17105-8469 PECO Energy Company ATTN: Mr. T. N. Mitchell, Vice President Board of Supervisors Peach Bottom Atomic Power Station Peach Bottom Township 1848 Lay Road R. D. #1 Delta, PA 17314 Delta, PA 17314 PECO Energy Company Public Service Commission of Maryland ATTN: Regulatory Engineer, A4-5S Engineering Division Peach Bottom Atomic Power Station Chief Engineer 1848 Lay Road 6 St. Paul Centre Delta, PA 17314 Baltimore, MD 21202-6806 Resident Inspector Mr. Richard McLean U.S. Nuclear Regulatory Commission Power Plant and Environmental Peach Bottom Atomic Power Station Review Division P.O. Box 399 Department of Natural Resources Delta, PA 17314 B-3, Tawes State Office Building Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Dr. Judith Johnsrud 1 475 Allendale Road National Energy Committee !
King of Prussia, PA 19406 Sierra Club !
433 Orlando Avenue 1 Mr. Roland Fletcher State College, PA 16803 Department of Environment {,
201 West Preston Street Manager-Business & Co-owner Affairs Baltimore, MD 21201 {
Public Service Electric and Gas Company A. F. Kirby, III !
P.O. Box 236 External Operations - Nuclear Hancocks Bridge, NJ 08038-0236 .
Delmarva Power & Light Company '
P.O. Box 231 Manager-Peach Bottom Licensing Wilmington, DE 19899 PECO Energy Company Nuclear Group Headquarters PECO Energy Company Correspondence Control Desk Plant Manager P.O. Box No. 195 Peach Bottom Atomic Power Station Wayne, PA 19087-0195 1848 Lay Road Delta, PA 17314 Mr. Jim Doman c/o Booz Allen Hamilton, Inc. 1 Mr. George A. Hunger, Jr. 955 L' Enfant Plaza Director-Licensing, MC 62A-1 Suite 1405 PECO Energy Company Washington, D.C. 20024 Nuclear Group Headquarters Correspondence Control Desk P.O. Box No. 195 Wayne, PA 19087-0195
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MEETING ATTENDEES MEETING BETWEEN PECO AND THE NRC APRIL 10. 1997 1
H8ME ORGANIZATION M. Brisan PECO B. Eckman PEC0 4
M. Eyre PECO
' D. Foss PECO M. Gallagher PECO S. Hesse PEC0 J.W. Jones PECO P. Kester PECO i
B. Lubaszewski PECO A. Raush PECO D. Shervin PEC0
- T. Kobetz NRC/NMSS 1
E. Leeds NRC/NMSS
' S. McDuffie NRC/NMSS F. Sturz NRC/NMSS M. Waters NRC/NMSS M. Hart NRC/NRR J. Shea NRC/NRR J. Doman Booz Allen / DOE-0CRWM B. Knieriem Delmarva Power J. Janocha Atlantic Electric J. Signorelli Scientech/NVS P. Highberger JAI S. Maingi Pennsylvania Bureau of Radiation Protection R. McLean State of Maryland Dept. of Natural Resources ENCLOSURE 1
PECO NUCLEAR INTERIM FUEL STORAGE NRC Working Level Meeting g April 10,1997 !
.I
I AGENDA
+ Management Overview -Mike Gallagher
+ Project Overview -Steve Hesse
+ Site Selection /
Design Considerations -Alan Raush
+ Storage System Selection -Matt Eyre -
+ Xuclear Quality Assurance -Bill Eckman
+ Licensing Compliance -Dave Foss 2
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l MANAGEMKNT OVERVIEW i
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+ Background 1
+ Meeting Purpose
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M PROJECT OVERVIEW .
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Peach Bottom Units 2 & 3 l Delta, PA:
+ GE BWR-4's l
+ Rating: 3458 Mwth
+ Commercial Operation: 1974
+ Fuel Supplier: GE
+ Original Pool Capacity: 1110 (each Unit)
+ 1981 Rerack: 2608 (each Unit) l
+ 1986 Rerack: 3819 (each Unit)
+ Current Pool Loading: 2720 (2)/2485 (3) !
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Project Objective:
+ To establish an Interim Spent Fuel Storage System until a Federal Facility becomes available.
On-Site Passive Dry Storage System General License Available Prior to 2R13 (Fall 2000)
No Regulatory Commitment to maintain Full
- Core Discharge Capability '
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MOD P601 -INTERIM FUEL STORAGE PROJECT TEAM SPONSOR Mike Gallagher PROJECT MANAGER COMMUNICARONS Karen Bell / Bill Jones Steve Hesse l Fran Reining ;
ADMIN. ASST.
Karen Cooper
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PLANNING Dominick DiBella i
I I I I I I LEAD LEAD LICENSING / QA NUCLEAR OPERATIONS FUELS STATION REP. ENGINEER PERMITTING BillEckman MAINT. Dave Lewis Matt Eyre :
Bob Alan Raush David Foss Mark Brisan Dan Shervin Lubaszewski Bob Matty ,
I l l l l l REACTOR CIVIL SECURITY EMERGENCY ENGINEER Paul Kester Howard PREPARE.
JeffHolley Owrutsky Norm Yost i FrankCoffey 9-HP RADWASTE CHEMISTRY RAD. PRO. SAFETY TRAINING ,.
George McCarty Fred Crosse AlCzyzewicz Laverne Hostetter Dawn Mills Art Levenite j 7
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..l Engineering Approach:
- + Utilize " Design-Build" Contracting Strategy to tap into Industry Expertise for Interim Fuel Storage Equipment and Civil .
Engineering Activities. l
+ Mod Team provides Multi-disciplined '
Oversight.
+ Storage, Transportation, and Disposal Capabilities under consideration.
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Milestones:
+ Storage System RFQ Issued Jan.1997 (Complete)
+ Finalize Site Selection Apr.1997
+ Interim Fuel Storage Facility (Des./ Build) RFQ Issued May 1997
+ Storage System Contract Award July 1997
+ Interim Fuel Storage Facility Contract Award July 1997
+- Engineering Design Rev. O Approved Dec.1997
+ Ready to Work Feb.1998
+ Start Excavation Apr.1998
+ Road and Pad Complete Jan.1999
+ Storage Equipment Onsite Mar.1999
+ Dry Run July 1999
- + Ready for Operations Apr. 2000 10
-.-~n SITE SELECTION and DESIGN CONSIDERATIONS
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__g Siting Considerations:
+ Security + Other Considerations Response Time ! Permitting i Accessibility Environmental Impact
+ Radiation Protection Cost .
Transportation
+ Potential Hazards . .
L.ogistics I
l Hydrogen Facility : Road Grade l
Flooding .
- Bridges Seismic - -
l Expansion Capacity i
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l ISFSI Design Considerations: ,
+ Site Preparation (Concrete Storage Pad, Fencing, Barricades)
+ Access Road and Potential Bridge <
l Cpgrade/ Installation l
- + Security System i
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+ Electrical Supply (Lighting) l O
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Concrete Storage Pad Design:
+ NUREG-1567 (draft) specifies that the i concrete storage pad is not typically ,
i classified as important to safety.
+ PECO plans to design the concrete storage pad per ACI 349 and construct per ACI 318.
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PBAPS Unit 2 & 3 Interfacing Design Considerations:
+ Heavy Loads and Structural Evaluation (Spent Fuel Pool / Refuel Floor /RB Access Hatch Loading Capacity)
+ Potential for New South Protected Area Gate
+ Program Evaluations / Revisions i
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j Storage System Candidates:
+ Holtec + Transnuclear
+ NAC + VECTRA
+ Sierra Xuclear + Westinghouse l
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Evaluation Considerations:
+ Vendor Quality / Viability
+ Design / Licensing
+ Schedule / Performance l
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m . -m n - - ~
Holtec: -
+ HI-STAR, HI-STORM
+ XRC RAI 3/27/96 for .HI-STAR
+ Concerns with submittal .
~
+ Resubmittal to NRC of HI-STAR and HI- l STORM '
+ C of C/ Rule Change for HI-STAR expected 7/98, HI-STORM expected 12/98
--W 4 NAC:
+ UMS, STC
+ STC RAIs did not require revision to SAR 1 + Noncompliance Issues identified: /
Maintenance, QA Organization and Program I
i + C of C/ Rule Change for EMS expected 3/99 20
Sierra Nuclear:
- + VSC, TRANSTOR
+ RAI for Storage part of TRANSTOR appeared routine
+ RAI for Transport part of TRANSTOR noted need for enhanced QC of Submittal
+ Noncompliance Issues identified: Procedures, Design Control, Fabrication, and Records
+ Point Beach Hydrogen Burn
+ ANO Closure Weld Seal Area Crack l
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+ C of C/ Rule Change for TRANSTOR expected 3/98 21
r Transnucleat:
- + TN-24, 32, 40, 68 l + Xo Docketed Significant Nonconformances Identified
- + No Storage System currently in XRC i Review Process to meet Peach Bottom's l 1 Dry Storage needs l
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+ C of C/ Rule Change for TN-68 expected 4/99 '
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VECTRA:
+ NUHO MS, MP-187
+ VECTRA only Vendor with BWR Storage C of C Design
+ Noncompliance Issues identified: Fabrication,. ;
Documentation, QA, Recognition of Generic :
Issues, Vendor / Client Communications '
+ Demand for Information 1/13/97 ll l
+ C- of C/ Rule Change for MP-187 expected 12/97,
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BWR Version expected late 1998 23 i
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Westinghouse:
+ MC-10, Commercial MPC l
+ No Storage System currently in NRC :
Review Process to meet Peach Bottom's ]
Dry Storage Needs f
+ C of C/ Rule Change for Commercial MPC expect:ed 4/99 24
l NUCLEAR QUALITY ASSURANCE ,
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. . _ - _ - . . . _ _ . - . _ _ _ = .
Nuclear Quality Assurance:
+ Active Involvement
+ Incorporate Key Lessons ,
+ Project QA Plan, Rev. O, issued 1/21/97 l i ,
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g e e XQA Integrated Activities:
+ Pre-Award QA Surveillances
+ Design Reviews / Technical Evaluations
+ Procurement / Fabrication Oversight
+ On Site Construction Oversight
+ Source Verifications
+ Document Review
+ Oversight of Security Modifications
+ Assessments /Surveillances
+ Training Activities
+ Implementation Activities i
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! Procurement / Fabrication
- Oversight Activities
+ Communicating with other L tilities on l Lessons Learned
+ Significant Inspection Oversight at Sub- -
l Vendor Manufacturing Locations
+ Vendor Surveillances l + Hold / Witness Point Inspections
- l + Documentation Reviews
+ Audits ,
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- ~ - . _ - . . ~ . . . - - . . . _ , . . . . . .
Areas for NQA Surveillance:
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+ Dry Shield Canisters
+ Storage Modules ,
- + Transfer Casks ,
+ Facility Construction 29
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!+
- LICENSING <
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- COMPLIANCE <
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- 30 t
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Compliance Matrix:
+ Ensure Compliance with requirements
+ Scope of Compliance Matrix to include Part >
72 requirements, C of C requirements, etc. l
+ See attached sample i
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Draft Compliance Matrix for General Liernse ct PBAPS i
Requerernent Doocription Actions 72.10(oM1) Ensure NRC Form 3 posung at heansed faceity Postng l 72.104 Evaluate and revies OOCM to ensure done IAW 72.104 and opershonal reatnchone/Irruts are in piece to ensure ALARA (see also 72.44(dX1)) OOCM 72.106 Ensure a mnerosed area is =.a=Ni=hed th .t is at least 100 m and maintens does less then 5 rum for an arrwinnt Ed e 72.11 Reportsbety - revise progren to address reporting i accuracy of irdo is dancient Progwn 72.190 Ensure that operations of spent fuel adMbes are performed by personnes IAW 71190 and R44(bX5) Admin Proc 72.194 pa rar.:. Ensure program to most code M=rer=8 {
72.212(a) Set up contois such that only spent fuel teensed for the site is eBoned to be stored, may only be stored in Part 212 casks and wis hane timely renosals of C of Admin Proc .
Cs (see steo n240 and 72.42) !
I 72212(bX1XI) Notfy NRC 90 prior to first fuel storage canpagn Lamer to NRC 72.212(bXIXE) Regletor casks 30 days ener use (needs programmabc contrds) Admin Proc ;
72212(bX1XW) Ensure 8ess charged by NRC se armsted for Evolumban 72.212(bX10) Muse remrds of cooks aveIshie for NRC inspection Adnin Proc R212(bX2) Perform written eweiuseens that ensure condeans of C d C se met, storage pods have boon artswy % designed and the requwements of 72.104 have been Report i met Anno ensure site parameters analyses me induded in this report. (Nucteer Record) 72212(bX2Xi) Prowde an eweiuston that the storage pad has been designed to adequately support the stued casks E d uean 72.212(bX3) Provide swelushan that documents that site parameters ind earthquakes and tomadoes are artsuy=sdy bounded by the SAR, C of C, and SER (consader E d = man 72.40(C),72.90. 72.92,72.94,72.98,72.100,72.104 and 72.108) l 72.212(bX4) Pirform 50.59 to ensure impeds on mostng see are addressed and docasnent in *212 report E d = man 72.212(bX5) Revise Secunty plan, prrw=6=es to meet USS with scaphons/condmons noted in 71212(bX5). Also ensure sectiort 72.180 through 72.186 are addressed as Plantproc [
r=====ry i 72212(bX5Xii) instait a prr*=r+=rt ses for the site inluding apprepnete secunty equipment Equipment j 72212(bX6) Reemt and revise rad pro progran to include spent fuel storage program Program f 72.212(bX6) Rowow and rowse trening progren b address spent fuel sacrage progran Ensure it meets apphcable parts of 72.192 and 72.44(bX4) Program 72.212(bX6) Renew QA progren and revise as r==neary to encore spent fuel facNity is inr*=isw' Ensure appropnete parts of 72.140 through 72.175 se addressed. Program ;
72212(bX6) Rowow Emergency Pian and rowse as r=wanary to ensure spent fuel storage is consadored Ensure re turements of 72.32 and 50.47 are addressed as Plan $ roc
=prar.w. in perfomung this imek. .,
71212(bX7) Monten a cxpy of C of C and referenced documents for ife of cask (Nuclear Remrds retanton) Admin Proc [
72212(bM8Xi) Dewesop coness to menten records of cask wendor, tassors, and list of spent fuel stored in cooks (Nw4==r Records) Admin Proc 72212(bXsXE) Dewatop progren that ensures testing and mentonsnm on cask is documented in a NRC approved QA program Programs 72 212(bM8Xiii) Develop controis for the transfening of casks between owners (see also 7244(bX1) and 7250) Admin Proc ,
72212(bX9) Dovutop prar=*=es to condum as aceMess ancaming casks Per=== =
71216 Redse reportsbety progran to incorpersos norwouune reports requbed air cask events Program ,
7132(d) License departures - ensure programmene anpois for lloones departures (A.C-79) Progran }
i n
Draft Compliance Matrix for General License et PBAPS .
i 72.4 Connunimbons - ensure NRC coneepondena program rewtood to irwerman a$dressee is NMSS Pro p e n Reportetely W beniawicy h Program
- 72.44(6)
Ensure operaeng pre for control of emuents if =ryhe=No Procedums 72.44(d)(1) 7244(oY2) Ensure an environmental monitoring progren f sprdraNa PropWn Annumiredeffluentreport-addstatement 6sISFSI Roulme Report 72.44(d)(3)
Secunty Plan changes - ensure controle are in pleos and address ISFSI Program 72.44(e)
EP pien changes - ensure progran in pleos for managmg changes and addresses ISFSI Program R44(f) ,
Ensure NRC approved program tiet meets Part 72, satirart i Program 72.44b(4) 72.48 Change promes - ensure a pmgren meses including manlanno documentaten of changes Program 72.52 Program for credbor consul for licensed matenal Program 72 54 osoommemonog - ensure controis se addressed Program 72.56 Lloense amendments - ensure program in pisco Progran Program !
72.70 SAR antrod - ensure an on.gomg program to W and report to the NRC the SAR R c ; 's
- 72.72(a) Malenal balance records - Ensure program to control for ISFSI fuel 72.72(b) Irwentary - ensure contrces to perform a 12 month irwentary Remrds Duplicate and dnense records storaga of fuelinformaban Records 72.72(d) -
n 72(c) Matense accounang and congol procedures - ensure in plom Pnvwh ees 72.74 Loos of irwentory or criticauty- ensure reportstery program addresses Progren 72.75 Verify reportsbety program is implemented for 72.75 Pmgren E76 Ensure routine matenal status reports we satmetod Rouhne Report 72 80 Montaming records and qumRty Admin Proc Financial report - ensure annual financial report is prowded to NRC Roubne Report 72.80(e) 7282 NRC inar=*m - by NRC-ensure Program R 82(e) Preep report within 30 days prior to recewing spent fuel Letter to NRQ
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. g *S Other Licensing Issues:
+ Electronic compilation of SAR, NRC SER, 72.48 evaluations
+ No expected affect on Units 2 & 3 Operating License or Tech Specs Part 70 in Operating License Design Features 4.0 ITS Relocated Heavy Loads Handling ,
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+ Are there other NRC Initiatives / Rule Changes we should know about? '
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