ML20204G659
| ML20204G659 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/17/1999 |
| From: | Richard Ennis NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9903260226 | |
| Download: ML20204G659 (20) | |
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UNITED STATES g
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WASHINGTON, D.C. 205SM001 March 17, 1999 LICENSEE:
Public Service Electric and Gas Company FACluTY:
Hope Creek Generating Station
SUBJECT:
DESIGN CHANGES
SUMMARY
OF FEBRUARY 25,199 This summary refers to the meeting with Public Service Electric an Rockville, Maryland. The meeting was held at t mpany (PSE&G) en changes for the Hope Creek Generating Station (HCGS). A lis ss fuel design and a copy of the slides presented by PSE&G are enclosed.
e meeting (Enclosure 2). The presentation provided the s e meeting from General Electric (GE) to Asea Brown Boveri (AB c ange fuelvendors following major topics were discussed:up to a similar meeting b e ng was a follow-e 1.
HCGS plant status including the planned schedules and fuel es 9 and 10; 2.
Status of the Core Monitoring System replacement; 3.
Status of the transition plan including project team staffing, the AB communication plan, current project status, and near-term activities;
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4.
SVEA-96+ fuel design; andDesign considerations including nu
,and 5.
PSE&G and ABB licensing submittal schedules to support HCGS
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ABB stated that they intend to submit a topical report related to the PO March 1999. The NRC staff stated that the submitta code by the end of support HCGS Cycle 10 or Cycle 11 so that the appropriate NR e ed to ned.
PSE&G stated that there will be three license change requests asso will request NRC review of these changes t ycle 10 that are a
ey scheduled to end on April 22,2000.
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ABB requested that the NRC complete the review of topical report CENPD-389-P (submitted by ABB ir June 1998) before September 1999. The NRC staff said that the review is currently scheduled to be completed before September.
It was proposed that a non-plant specific meeting between ABB and the NRC be scheduled in the spring of 1999. The purpose of the meeting would be to discuss the latest ABB fuel product line design.
original signed by:
4 Richard B. Ennis, Project Manager i
Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
- 1. Attendance List
- 2. PSE&G Slides cc w/encis: See next page DISTRIBUTION:
Docket File PDI-2 Reading File OGC PUBLIC REnnis ACRS i
E-MAIL:
SCollins/RZimmerman AAttard BSheron EKendrick JZwolinski/SBlack SWu EAdensam GShear MO'Brien GMeyer, RGN-l MChatterton JWermiel OFFICE PDI-2/P_M PQlj9L6R SRXB/f}C Ph NAME REnni[w NbhYi[n#
J el EAdensam h /[h99 3 [/4 /99 3 d$ /99 DATE 3 /If/99 OFFICIAL RECORD COPY '
DOCUMENT NAME: A:\\HC2-25.MTS
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1 2-ABB requested that the NRC complete the review of topical report CENPD-389-P (submitted by ABB in June 1998) before September 1999. The NRC staff said that the review is currently scheduled to be completed before September.
It was proposed that a non-plant specific meeting between ABB and the NRC be scheduled in the spring of 1999. The purpose of the meeting would be to discuss the latest ABB fuel product line design.
~
Richard B. Ennis, Project Manager Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosures:
- 1. Attendance List
- 2. PSE&G Slides cc w/encts: See next page
~
Puolic Service Electric & Gas Hope Creek Generating Station Company cc:
Jeffrie J. Keenan, Esquire Manager-Joint Generation Nuclear Business Unit - N21 Atlantic Energy P.O. Box 236 6801 Black Horse Pike Hancocks Bridge, NJ 08338 Egg Harbor Twp., NJ 08234-4130 Hope Creek Realdent inspector Richard Hartung U.S. Nuclear Regulatory Commission Electric Service Evaluation Drawer 0509 Board of Regulatory Commissioners Hancocks Bridge, NJ 08038 2 Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz Sr. Vice President - Nuclear Operations Lower Alloways Cwek Township Nuclear Department c/o Mary O. Henderson, Clet P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Br:dge, NJ 08038 1
General Manager-Hope Creek Operations Mr. Elbert Simpson l
Hope Creek Generating Station Senior Vice President-P.O. Box 236 Nuclear Engineenng Hancocks Bridge, NJ 08038 Nuclear Department
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P.O. Box 236 Director-Licensing Regulat;on & Fuels Hancocks Bridge, NJ 08038 Nuclear Business Unit - N21 P.O. Box 236 4
i Mr. Harold W. Keiser Hancocks Bridge, NJ 08038 Chief Nuclear Officer & President Nuclear Business Unit j
Regional Administrator, Region i Public Service Electric and Gas l
U.S. Nuclear Regulatory Commission Company F
475 Allendale Road Post Office Box 236 King of Prussia, PA 19406 Hancocks Bridge, NJ 08038 l
Dr. Jill Lipoti, Asst. Director i
Radiation Protection Programs NJ Deparvsnt of Environmental Protectiori and Energy CN 415 Trenton, NJ 08625-0415 I
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MEETING ATTENDANCE LIST Licensee: Public Service Electric and Gas Comoany Plant:
Hope Creek Generatina."13119D
Subject:
Fuel Desian Chanaes Date: February 25.1999 Time: 10:00 a.m Location: NRC Offices. OWFN Room 3-B-6 fBME
- TITLE ORGANIZATION NRC STAFF R. Ennis Project Manager NRR/DLPM/PDl-2 M. Chatterton Nuclear Engineer NRR/DSSNSRXB A. Attard Nuclear Engineer NRR/DSSA/SRXB E. Kendrick Reactor Engineer NRR/DSSA/SRXB S.Wu Reactor Engineer -
NRR/DSSA/SRXB PSE&G D. Notigen Supervisor, Hope Creek Nuclear Fuels F. Safin Principal Engineer, Hope Creek Reactor & Safety Analysis G. Salamon Manager, Hope Creek Licensing P.Duca Senior Engineer, Salem Licensing eBE D. Ebeling-Koning Supervisor, BWR Reload Analysis W. Harris Engineer. BWR Reload Analysis
l l
PSE&G Reload Fuel Transition i
Status i
i Don Notigan - PSE&G l
Derek Ebeling-Koning - ABB
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Bill Harris - ABB i
1 NRC Meeting February 25,1999 i
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Meeting Agenda
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<< Purpose
- Present PSE&G/ABB Status of Reload Fuel Transition Project
- Present Status of Core Monitoring System Replacement Project
- Update NRC Staff on Progress to Date
<< Presentation Outline
- Hope Creek Plant Status
- Core Monitoring System Project Status
- Reload Fuel Transition Project Status
- Open Discussion / Comment i;
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i Hope Creek Generating Station Operating Schedule
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+ Current Plant Operating Plan
- Achieve Equilibrium 18-month Cycles of 513 Operating Days
- 97% Rated Power Operating Capacity Factor assumed in Design
- Power Coastdowns of up to 3 weeks may be utilized Cycle Start End months Cycle Exposure (mwd /StU) l 8
Dec.13,1997 Feb.13,1999 14 8,914 j~
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9 Apr.1,1999 Apr. 22, 2000 12 8,247 l
10 May 23,2000 Oct. 6, 2001 16 10,500
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- Includes 3 week coastdown i ',
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Hope Creek Generating Station
~j Current Status i
+ Fuel Loading Plan
- Cycle 9 Core 100% GE9 Fuel Design (8x8 Barrier Fuel).
Batch avg. w/o U-235 2.80% to maximize GE9 fuel design margins during fuel transition.
4 Planned short operating cycle - 387 days.
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- Cycle 10 Core i
First transition core of SVEA-96+ (non-Barrier Fuel) and GE9.
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Optimize SVEA-96+ bundle design for transition from GE9.
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Hope Creek Generating Station
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CMS Project Status
+ Core Monitoring System Replacement Status-f i
- Cycle 9
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Pseudo-parallel Operation Y2K concerns - Y2K Fix tested for Honeywell Process Computer o
n Off-line Testing and Evaluation with plant data lln Core Monitoring training j
- Licensed Operators
- Reactor Engineers
- Fuels Engineers h
- i)
- Cycle 10 NSSS Process Computer installation
['l Upgrade to ABB Core Monitoring System System of Record ll l'
- i PSE&G/ABB Reload Fuel Program
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for Hope Creek Generating Station i
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+ Three Reloads - Cycle 10,11, and 12
+ Reload Engineering Services 1
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- Vendor Transition Condition for Design Documentation
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- Reload Design ll
- Reload Licensing and Safety Analyses u
+ Transfer of Technology to Hope Creek Reactor and i:
Safety Analysis Group 0
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Project Team for Vendor Transition ~
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+ Hope Creek Reactor and 18"P'"'=. HOPE Creek Fuel
.lj D. Notigan Safety Analysis Staffing ll
,c, Principal / Senior Engineer
+ Overall Reload Project
- g. sa,in jj Mananers
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U Open Posdion
- PSE&G - Don Notigan stan Engineer
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- ABB - Dick Matheny C. William i,
- s. soucy li Mark strohecher ll
+ Project Team Supporting
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Transition Projects Open Position
- PSE&G
- R~
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' - ABB Tech. Analyst
- r. gre.eiia j.
- URA
- Scientech StaN Augmenhuon i
M. Timm (ABB)
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- s. Ganthner (URA) i o 1999 Combusbon Engmeenng. Inc.
Pubhc Serwce Esectnc & Gas A ED ED i } :
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ABB/PSE&G Communication Plan
+ Close, frequent communications between PSE&G and ABB.
- Weekly status calls between PSE&G/ABB-CE/ABB Atom i
- Quarterly Review Meetings - Technical and Management
+ Periodic communications with NRC on Transition Plan i;
progress.
- April 7,1998 at NRC
- August 17-20,1998 at PSE&G
- October 20-21,1998 at ABB
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- February 24-25,1998 at NRC f
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+ Raise potential issues early for proactive resolution.
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+ Apply Lessons Learned on fuel vendor transitions.
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- e Fuel Transition Plan - Progress L
+ Current Status (where se are today)
- Exchange ofinformation l
1 GE Proprietary - fuel descriptions and performance
- Plant Information - description, performance, licensing basis
- Benchmarking Nuclear Methods to Cycles 1-8 of Hope Creek
- Constructing Hydraulics Models for GE9 Co-resident Fuel i,
+ Near Term Activities (where we are headed)
- Completing Licensing Analysis Models j
- Complete Thermal-Hydraulics Models for GE9 Co-resident Fuel Iy CPR Performance R
- Cycle 10 SVEA-96+ Bundle (s) Nuclear Design U
- Establish Cycle 10 Reference Core Design
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- Initiate ABB Manufacturing Campaign d
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%==0PSEG ABB ll a
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Hope Creek Nuclear Benchmark l
+ Benchmarked POLCA14 and POLCA/7 with Hope Creek i
core follow data for cycles 1-8
+ Compare TIP data, cold critical, hot critical I
- Establish Target Cold and Hot Eigenvalues
+ Observed smaller uncertainties for POLCAl7 n
+ Wi!! be closely following cycle 9 core operations
+ Will be updating reload design parameters with observed core follow data.
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+
i Hope Creek Thermal-Hydraulic-Models
+ Hydraulic Models i
+ PSE&G provided to ABB the thermal-hydraulic performance data for GE7 and GE9 fuel in Hope Creek r
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+ ABB models performance with Condor code it
+ Designing SEA-96+ to be compatible with co-resident GE
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+ CPR Models
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+ PSE&G to provide CPR performance data l
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+ ABB to model performance with Condor code t
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+ Implement in design and licensing codes j
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+ integral Performance Confirmation jj ui
+ Comparison of Plant Measured Statepoint Data with ABB ij I
Predictions o 1999
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Hope Creek SVEA-96+ Fuel Design a
+ Standard SVEA-96+ Fuel Design i
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- Seven spacer (vs. six for SVEA-
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96)
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- Non-barrier Cladding 3
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- Integral Debris Filter sy g.
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- LK3 Cladding Material II g
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- I o 1999 i 'i NN7MN)O. PSEG j [
A 5959 a sene y
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n integrated Debris Filter 1
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+ Solid Stainless Steel Piece Integral to Bottom Support t
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+ Loop Testing Confirm:
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- Range of debris testing - 70 to 95% efficient L
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- Endurance testing - No Wear
+ In-Reactor Experience in Europe
- 1996,1997 Lead Fuel Assemblies inserted in Leibstadt i
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- 1997,1998 Inspections of LFAs in Leibstadt ll n
- 1998 Reload Deliveries - Oskarshamm-1, -3, and 1
Leibstadt h
-- 1999 Reload Deliveries - Oskarshamm-1, -3, and 1
Leibstadt, Barseback-1,-2, Cofrentes, Forsmark-2, H
Hope Creek H
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Hope Creek Reload Licensing
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> PSE&G Licensing Schedule for Hope Creek Cycle 10
- OPRM Option 111 LTSS Implementation - April 1999
- Vendor Fuel Transition Tech Spec. Changes - May 1999 i
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- Cycle 10 Specific Tech. Spec. Changes - June 1999 l
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+ ABB Licensing Schedule Supporting Hope Creek Cycle 10 Reactor Operation
- Requirements NRC approval of SVEA-96+ CPR Correlation l
(CENPD-389-P)
NRC Submittal-June 1998 o
.0 NRC RAI-August 1998
- ABB Response to RAI-Planning March 1999 h
NRC Approval-Before September 1999.
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$== O PSEiG ABB
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s Summary
+ Hope Creek Core Monitoring System Status i
- Pseudo-parallel operation for cycie 9
- Off-line testing and evaluations of new CMS r
- Y2K Fix in place for Honeywell Process Computer
- Upgrading NSSS Process Computer for cycle 10
- Replacing Core Monitoring System for cycle 10
+ Hope Creek Fuel Vendor Transition Progress
- Design SVEA-96+ bundle compatible with GE9 fuel 4
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- Progressing toward acceptance of Conditions for Design
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- Challenges being proactively managed for a successful fuel vendor transition project.
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+ NRC Staff Comments S
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O PSFli ABB c