ML20204G659

Summary of 990225 Meeting with Util in Rockville,Md Re Fuel Design Changes for Hcgs.List of Attendees & Viewgraphs Encl

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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t y UNITED STATES o 4" NUCLEAR REGULATORY COMMISSION

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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 25,1999 This summary refers to the meeting with Public Service Electric an mpany (PSE&G)

Rockville, Maryland. The meeting was held ss fuel design en at t changes for the Hope Creek Generating Station (HCGS).

and a copy of the slides presented by PSE&G are enclosed. e meeting A lis (Enclosure 2). The presentation cprovided e meeting the s ange fuelvendors from General Electric (GE) to Asea Brown following major topics were discussed:up to a esimilar ng wasBoveri a follow-meeting b (AB e

1.

HCGS plant status including the planned schedules es 9 and 10; and fuel 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; )

4.

SVEA-96+ fuel design; andDesign considerations including ,and nu 5.

PSE&G and ABB licensing submittal schedules to support HCGS /

[,0 ABB stated that they intend to submit a topical report related to the PO code by the end of March 1999. The NRC staff stated that the submitta support HCGS Cycle 10 or Cycle 11 so that the appropriate e ed to NR ned.

PSE&G stated that there will be three license change requests asso ycle 10 that are will request scheduled NRC review of these changes to to end on April 22,2000.

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PDR ADOCK 05000354 -..

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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.

4 original signed by:

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 DATE 3 /If/99 h /[h99 3 [/4 /99 3 d$ /99 OFFICIAL RECORD COPY ' '

DOCUMENT NAME: A:\HC2-25.MTS <

- - . . . . . .. . - . ~ .a _ -

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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

' P.O. Box 236 Director- Licensing Regulat;on & Fuels Hancocks Bridge, NJ 08038 Nuclear Business Unit - N21 4

P.O. Box 236 Mr. Harold W. Keiser i

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 1

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 Enclosure 1

. . . . l PSE&G Reload Fuel Transition  !

i Status  !

i i

Don Notigan - PSE&G l Derek Ebeling-Koning - ABB

[

Bill Harris - ABB ,

i 1

NRC Meeting February 25,1999 i a

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'l e m, l c e ionenomeenna.u<.  ;'

1 O PSEG nAues,D ED E Enclosure 2 i

W e

Meeting Agenda ~

<< 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; E==

O PSEG ABB

Hope Creek Generating Station

~~

Operating Schedule .

+ Current Plant Operating Plan i

- 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 t

j

{' ,

9 Apr.1,1999 Apr. 22, 2000 12 8,247 l

10 May 23,2000 Oct. 6, 2001 16 10,500

• l!

• Includes 3 week coastdown "

i ',

l!

'h =0 0 PSEG ABB l l

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. i

- Cycle 10 Core i

First transition core of SVEA-96+ (non-Barrier Fuel) and GE9. [

Optimize SVEA-96+ bundle design for transition from GE9.  % ii

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O PSEG ABB 1

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i Hope Creek Generating Station .

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CMS Project Status .

i

+ Core Monitoring System Replacement Status- f

- Cycle 9

(

Pseudo-parallel Operation Y2K concerns - Y2K Fix tested for Honeywell Process Computer o n

Off-line Testing and Evaluation with plant data ll n

Core Monitoring training

- Licensed Operators j

- Reactor Engineers  !!

- Fuels Engineers h

- Cycle 10

i)

NSSS Process Computer installation ['l Upgrade to ABB Core Monitoring System  ;,

System of Record ll l' t o 1999 P =0 0 PSEG ABB

. . **i PSE&G/ABB Reload Fuel Program

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for Hope Creek Generating Station i i

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i

+ Three Reloads - Cycle 10,11, and 12

+ Reload Engineering Services 1 L

- Vendor Transition Condition for Design Documentation [

iL

- Reload Design ll

!; - Reload Licensing and Safety Analyses  !!

u

+ Transfer of Technology to Hope Creek Reactor and i:

. Safety Analysis Group 0 i'

u y!

• f

.i kb =0 0 PSEG ABB

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Project Team for Vendor Transition ~ U ti y

+ Hope Creek Reactor and 18"P'"'=. HOPE Creek Fuel D. Notigan

.lj Safety Analysis Staffing ll

,c, Principal / Senior Engineer

+ Overall Reload Project _

g. sa,in jj Mananers U

• ""'**h**'

Open Posdion  !! -

- PSE&G - Don Notigan stan Engineer [

C. William i,

- ABB - Dick Matheny

s. soucy li Mark strohecher ll

+ Project Team Supporting 3 ,,,,,,,,,,  ;

Transition Projects _

Open Position  !, ,

- PSE&G  : R

", i Tech. Analyst

' - ABB r. gre.eiia

- URA j.

, - Scientech StaN Augmenhuon i M. Timm (ABB)

{'

o 1999 s. Ganthner (URA) i Combusbon Engmeenng. Inc. '!

Pubhc Serwce Esectnc & Gas A ED ED i} <

7 MEDED 'l I

..t ABB/PSE&G Communication Plan

+ Close, frequent communications between PSE&G and ABB. ,

i

- Weekly status calls between PSE&G/ABB-CE/ABB Atom

- 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  !

.i

- February 24-25,1998 at NRC i1

+ Raise potential issues early for proactive resolution. i'

+ Apply Lessons Learned on fuel vendor transitions. !l n

E =# 0 PSIKi H ABB

O

• e Fuel Transition Plan - Progress  :

_ + Current Status (where se are today) L

- 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 I y

CPR Performance "

R

- Cycle 10 SVEA-96+ Bundle (s) Nuclear Design

- Establish Cycle 10 Reference Core Design !j U

- Initiate ABB Manufacturing Campaign d M

%==0PSEG ABB ll

- - - - - _ - - - - - _ - - _ - - - - - - - - a

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Hope Creek Nuclear Benchmark i

+ 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.

I i

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===# 0 PSEG ABB i] ,

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 i

+ ABB models performance with Condor code it

+ Designing SEA-96+ to be compatible with co-resident GE !I fuel E i

+ CPR Models  !

j

+ PSE&G to provide CPR performance data l i

i + ABB to model performance with Condor code t

+ Implement in design and licensing codes j l

+ integral Performance Confirmation lj jj ui

+ Comparison of Plant Measured Statepoint Data with ABB ij I

Predictions o 1999

!l!

=== 0 11 PSEG ABB 1 l

f

k Hope Creek SVEA-96+ Fuel Design a

+ Standard SVEA-96+ Fuel Design i with '

}

- Seven spacer (vs. six for SVEA- [.

96) -

• "d

- Non-barrier Cladding 3

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- Integral Debris Filter sy g. .

- LK3 Cladding Material II g .

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\ lb q

n

I o 1999 i 'i j [

NN7MN)O. PSEG 12 A 5959 a sene y

_ _ _ _ _ . . _ _ _ . _ _ . _______-__________-_-.________________-_______________________-______-_____-__-______--______-______t

n integrated Debris Filter -

1 sh t

+ Solid Stainless Steel Piece Integral to Bottom Support 7

+ Loop Testing Confirm: 4 E

- Range of debris testing - 70 to 95% efficient L ii!

- Endurance testing - No Wear

+ In-Reactor Experience in Europe

- 1996,1997 Lead Fuel Assemblies inserted in Leibstadt i 4

- 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, Hope Creek H H

i Om = O PSEG

,e ABB 'l s

- - - - - - _ _ - - - - - - - _ - - _ - - - _ - - _ _ _ - - -_1

r s.

Hope Creek Reload Licensing

~

> PSE&G Licensing Schedule for Hope Creek Cycle 10

- OPRM Option 111 LTSS Implementation - April 1999

- Vendor Fuel Transition Tech Spec. Changes - May 1999 ie

- Cycle 10 Specific Tech. Spec. Changes - June 1999 l t

+ ABB Licensing Schedule Supporting Hope Creek Cycle  !

10 Reactor Operation  !

- Requirements NRC approval of SVEA-96+ CPR Correlation l (CENPD-389-P)  !

o NRC Submittal- June 1998 .0 NRC RAI- August 1998  !

• ABB Response to RAI- Planning March 1999 h NRC Approval- Before September 1999.  :

eim r!

$== O PSEiG ABB

_ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ ________\

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 !t

! - Design SVEA-96+ bundle compatible with GE9 fuel 4 it

- Progressing toward acceptance of Conditions for Design .r

- Challenges being proactively managed for a successful fuel .

vendor transition project.

7

+ NRC Staff Comments S eim  !!

=== O PSFli ABB c