ML20236Q291

Summary of 871027 Meeting W/Util in Bethesda,Md Re Util Plans for Second Refueling Outage,Scheduled for Late Mar - Early Apr 1988.List of Attendees & Presentation Matl Encl

ML20236Q291
Person / Time
Site:	Waterford
Issue date:	11/09/1987
From:	Joshua Wilson Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8711190295
Download: ML20236Q291 (27)

Text

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,, November 9, 1987 l Docket No. 50-382 LICENSEE: Louisiana Power and Light Company 1

FACILITY: Waterford Steam Electric Station, Unit 3

SUBJECT:

MEETING

SUMMARY

FOR MEETING HELD ON OCTOBER 27, 1987 IN BETHESDA, MARYLAND A meeting was held in Room P-422 of the Phillips Building in Bethesda, Maryland between Louisiana Power and Light Company (LP&L, the licensee) and the NRC staff to discuss LP&L's plans for their upcoming second refueling outage, currently scheduled for late March - early April,1988. A list of attendees is provided as Enclosure 1.

LP&L discussed their reload schedule; the regulatory reviews that will be needed to support Cycle 3 operation; the Cycle 3 fuel design; and some of the major maintenance, surveillance and work activities to be accomplished during the outage. The handout provided to the staff at the meeting is provided as Enclosure 2.

In summary, a 50.59 reload is possible and the staff will need to conduct on '

the order of a half-dozen reviews to support the reload. LP&L fndicates that very little of the station mod work activity will be involved witn regulatory requirements as most are enhancements directed toward increased operational efficiency and reliability.

j IS I James H. Wilson, Project Manager  ;

Project Directorate - IV j Division of Reactor Projects - III, l IV, V and Special Projects l i

Enclosures:

1 As stated l l

cc w/ enclosures:

l See next page l

DI ION Mocket File NRC PDR Local PDR PD4 Reading J. Calvo J. Wilson 0GC-Bethesda E. Jordan J. Partlow NRC Participants ACRS (10)  ;

l PD4/P PD4/D JWilso 9p JCalvo/J10 11/7/a 11/4 /87 l i

e711190295 071109 PDR ADOCK 05000302 >

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Mr. Jerrold G. Dewease Waterford 3 Louisiana Power & Light Company i

CC:

W. Malcolm Stevenson, Esq. Regional Administrator, Region IV Monroe & Leman U.S.. Nuclear. Regulatory Commission 1432 Whitney Building Office of Executive' Director for New Orleans, Louisiana 70103- Operations j 611 Ryan Plaza Drive,. Suite.1000 i Mr. E. Blake Arlington, Texas '76011 1 Shaw, Pittman, Potts & Trowbridge j 2300 N Street, NW' Mr. William H. Spell, Administrator j Washington, D.C. 20037 Nuclear Energy. Division .

l Office of Environmental Affairs Resident Inspector /Waterford NPS Post Office' Box 14690-Post Office Box 822- Baton Rouge, Louisiana 70898 i J

Killona, Louisiana 70066 <

President, Policy Jury I Mr. Ralpo T.~ Lally Manager of Quality Assurance St. Charles Parris. E

-l Middle South Services, Inc. Hahnville, Louisiana 70057 Post Office Box 61000 New Orleans, Louisiana 70161 Chairman Louisiana Public Service Commission ,

One American Place, Suite 1630 Baton Rouge, Louisiana 70825-1697 l

i Mr. K. W. Cook Nuclear Safety and Regulatory Affairs Manager Louisiana Power & Light Company l 317 Baronne Street New Orleans, Louisiana 70160 l

l l

1 l i l

Enclosure 1 List of Attendees at Meeting Between NRC Staff and LP&L Held on October 27, 1987 in Bethesda, Maryland NRC D. M. Crutchfield J. A. Calvo A. Thadani L. S. Rubenstein K. Manoly M. W. Hodges J. H. Wilson LP&L R. P. Barkhurst l N. S. Carns l K. W. Cook 1 M. J. Meisner l

l l

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Enclosure 2 w

i WATERFORD 3 CYCLE 3 RELOAD AND SECOND REFUELING OUTAGE 1

l l

Presented to the NRC October 27, 1987 O

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WATERFORD 3 i

e Reload Schedule e Regulatory review o Cycle 3 fuel design l

e Second refueling outage activities

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CYCLE 3 RELOAD PLANNING DATES

• Fuel Receipt February 1-22, 1988' Shutdown April 2 i

Fuel Load April 26 - May 8 l Startup (on the grid) June 1  !

l

• Actual dates depend on plant performance

F I

J NRC Review Support e License Changes To Support: l Fuel Receipt l Fuel Load _

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Outage Surveillance l

Cycle 3 Start-Up i

e Other Submittals e Reload Analysis Report I

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OTHER RELOAD-RELATED SUBMITTALS e- Shoulder Gap (License Condition 2.C.7) -

Submitted 7/24/87 )

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e ILRT Test Duration - Submitted 10/6/87 S 4 l

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o RELOAD ANALYSIS REPORT u

e 10CFR50.59 Reload Is Possible e No Unreviewed Methodologies I

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1 e Chapter 15 Events Expected To Be Bounded By Cycles 1 or 2

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_._______m__ __.___ ___ _ _ _ _

1 WATERFORD 3 CYCLE 3 l

i OVERVIEW OF RELOAD DESIGN J e 18-Month Cycle e Low-Leakage. Fuel Management I l

e No Change in Core Licensed Power )

Level (3390 MWt) e No Unreviewed Methodology Changes.

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l WATERFORD 3 - CYCLE 3 i QUARTER CORE LOADING PATTERN I

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8 9 10 11 12 13 C El E2 00 D3 E3 14 I 15 16 17 18 19 20 C El Di D2 D3 D0 D2 21 22 23 24 25 26 27 28. - ,

C Ei 01 E2 D3 E3 C E3 29 30 31 32 33 34 35 36 E0 E2 D2 D3- DO C E4 D3 37 38 39 40 41 42 43 44 45 E1 00 D3 E3 C 00 D2 E4 46 47 48 49 50 51 52- 53 54 E2 D3 00 C E4 D2. Di D3 EO 55 56 57 58 59 60 61 62 D2 E3 02 'E3 D3 E4 D3 C

WATERFORD 3 CYCLE 3 l

i FUEL MECHANICAL DESIGN e No Significant Mechanical Design Changes From Batch D to Batch E-i 3

e Fuel Assembly Shoulder Gap Batch C Fuel Assemblies Are Limiting .

Acceptable Shoulder Gap For All Fuel Assemblies in Cycle 3 (Letter W3P87-1675 Dated 7/24/87) e

WATERFORD 3 CYCLE 3 CORE COMPONENT REPLACEMENT.

e No CEA Replacement u

o in-Core Instrumentation Replacement 44 In-Core Strings Will Be Replaced 12 In-Core Strings .Will Be Returned To Service .

I

1 WATERFORD 3 CYCLE 3 CORE PHYSICS CHARACTERISTICS i CYCLE 2 CYCLE 3 Cycle Length (EFPD) 380 424 Maximum Radial Planar Peaking Factor (ARO, HFP) 1.58 1.57 i l

Critical Boron Concentration (BOC, HFP, ARO) 1125 1110 CEA Worth (% Ap)

(BOC, ARl, HFP) -11.0 -10.5 (EOC, ARI, HFP) -12.1 -11.2 -

Moderater Temperature Coefficient, (x10-' Ap / F)

(BOC, HZP, ARO) +0.50 +0.25  ;

(BOC, HFP, ARO) -0.08 . -0.50

_ _ . _ _ _ _ _ _ ____________m._.__m____

1 WATERFORD 3 CYCLE 3 SAFETY ANALYSES o Safety Analyses Cycle 3 Physics inputs ~ Mostly Bounded-By Cycle 2 Values Cycle 3 Chapter 15 Events Should Be l Bounded By Cycles 1 or 2 )

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i e Core P'rotection Calculator Update No Algorithm Changes I Cycle 3 Update Through Changes To Addressable And Reload Data Block )

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WATERFORD 3 CYCLE 3 1 l

i SAFETY ANALYSES l (Continued) e Potential Technical Specification Changes Tech. Spec. 3.2.1 and 3.2.4: Margin Penalties With COLSS And/Or CEACS i Inoperable l

No Other Reload-Related Tech. Spec.

Changes Anticipated

- _ _ _.___.-__..____.__m_ _ . _ _ _ _ _

,' j WATERFORD 3 4 1

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REFUELING OUTAGE 2 OUTAGE PREPARATION l READINESS STATUS READY FOR OUTAGE: 3/4/88 PLANNED START: 4/2/88 e Organization Preparation Team - Established / Active Outage Supplemental / Support - Key Positions Filled e Scoping MAL Revision 2 " Detailed Scope" Issued 9/10/87 Scope " Locked" - Department Head Approval e Baseline Development Baseline Schedule - 60 Days Critical Path: Refueling - RCP Seals - lLRT Major Projects Scheduled

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REFUELING OUTAGE 2 OUTAGE PREPARATION READINESS STATUS e Planning >

I Initial Readiness Reviews - Major Activities (Completed) l Refueling Manual - Initial Walkthrough Completed -

1 SIMS Conversion On Schedule l Staging - Utilize MMIS Start 12/1/87 Contract Notices issued - Reduction From Refueling 1 Incorporating Numerous RF1 Lessons Learned i

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M&TE - All itemsjT6 Plant Program Quality - Increase Shift Coverage Cost.& Budgets Improved Outage 1

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REFUELING OUTAGE 2 MAJOR ' ACTIVITIES PLANNED START: ;4/2/88 DURATION: . 60 DAY TARGET e Refueling ' Evolution integrated Containment Service Contract Extended- Fuel Cycle - Approx. 420 Days-FOSAR/Rx Vessel ISI

. :l e Reactor Coolant Pumps Improved Design Seal Installation .

j Motor Oil Leakage Repairs e Steam Generator Primary ISI/ Batwing Investigation  :

Secondary " Sludge Lancing" Waived i

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REFUELING OUTAGE 2 l MAJOR ACTIVITIES )

l e Refueling Interval Surveillance Testing Integrated Leak Rate Test Emergency Diesel Generator - 5 Yr Inspection

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l Snubber Reduction Program l e Turbine Generator Heavy Disc Low Pressure Turbine. Rotors e Enhancements '

Containment Chiller Addition RCS Water Level Remote Indication NMC Rad Monitor Replacement H2 Analyzer Replacement Feed Pump Gland Leak Off Tank

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