ML16342D114

Summary of 951005 Meeting W/Pg&E in Rockville,Md Re Plans to Increase Length of Fuel Cycle at Diablo Canyon Units 1 & 2 from 18 Months to 24 Months.Forwards List of Attendees

ML16342D114
Person / Time
Site:	Diablo Canyon
Issue date:	11/13/1995
From:	Stone J NRC (Affiliation Not Assigned)
To:	NRC
References
NUDOCS 9511170096
Download: ML16342D114 (78)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&0001 November 13, 1995 LICENSEE:

Pacific Gas and Electric Company FACILITY: Diablo Canyon, Units 1 and 2

SUMMARY

OF OCTOBER 5,

1995, MEETING WITH PACIFIC GAS AND ELECTRIC COMPANY TO DISCUSS EXTENDING THE FUEL CYCLES FOR THE DIABLO CANYON NUCLEAR POWER PLANT,. UNIT NOS.

1 AND 2 (TAC NOS.

H93629 AND H93670)

On October 5, 1995, representatives from the U.S. Nuclear Regulatory Commission (NRC) met with representatives from the Pacific Gas and Electric Company (PGSE) in the NRC offices in Rockville, Maryland, to discuss plans to increase the length of the fuel cycle at Diablo Canyon Units 1 and 2 from 1S months to 24 months.

Attachment 1 is the list of attendees.

The following is a summary of the issues discussed during the meeting.

The corresponding presentation material provided by PG&E during the meeting is in.

Extended Fuel C cle Im lementation PG&E plans to implement the expanded fuel cycle in two phases.

The first phase will expand the cycle to 20 months, beginning with the Hay 1996 Unit 2 refueling outage.

The surveillances on 18-month intervals will be due by October 1997; all license amendments will have to be issued before that date.

The amendments will be issued for the 24-month fuel cycle interval even though the units will be on a 20-month cycle.

PGKE does not plan to use the 25-percent extension allowance in the current technical specification to implement the 20-month cycle.

The schedule for submitting the amendments is as follows:

December 1995 34 items to be changed, mainly surveillance interval increases April 1996 September 1996 64 items interval 66 items interval to be changed, including surveillance increases and setpoint evaluations to be changed, including surveillance increases and setpoint evaluations January 1997 Technical Issues 42 items to be changed, including surveillance interval increases and setpoint evaluations The licensee has not identified any technical issues associated with the 20-month fuel cycle.

95iii7009b 95iii3 PDR ADOCK 05000275 8

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The licensee identified the following major technical issues as requiring resolution before the 24-month fuel cycle is implemented:

(1)

The reload design will use 5-percent enriched fuel, requiring a higher boron concentration for the reactor coolant system, the refueling water storage

tanks, and the accumulators.

(2)

At each reload 104 to 108 assemblies will be discharged.

(3)

Higher allowable peaking factors, higher moderator temperature coefficient limits, and a revised thermal design procedure will be required.

(4)

Fuel-parameter-dependent transients will have to be reevaluated and may require the use of the loss-of-coolant accident best-estimate technology from Westinghouse.

(5)

The burnup limit of fuel rods will have to be extended to 70 mwd/kgu.

(6)

The current limit on lithium will have to be raised.

The effect of this increase in lithium concentration will have to be addressed.

Laboratory tests have shown an acceleration of pure water stress corrosion cracking of Alloy 600, which is the alloy used in the steam generator tubes.

ORIGINAL SIGNED BY:

James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos.

50-275 and 50-323 Attachments:

1.

Meeting Attendees 2.

Licensee Viewgraphs cc w/atts:

See next page DISTRIBUTION w/Atts 1 and 2:

Docket File PUBLIC PDIV-2 Reading JStone SBloom

JDyer, RIV DISTRIBUTION w/Att 1:

WRussel 1 /FHiragl i a JRoe WBateman OGC NRC Participants JHitchell RZimmerman EAdensam EPeyton EJordan ACRS

KPerkins, WCFO DOCUMENT NAME:

DCOCT.MTS OFC PDIV-2 LA PDIV-2 PH NAME DATE EPeyePn 10 D 95 JStone:

k 95 OFFICIAL RECORD COPY

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The licensee identified the following major technjcal, issues" as requiring resolution before the 24-month fuel" cycle is implemented:

(1)

The reload design will use 5-percent enriched 'fuel, requir'ing a higher boron concentration for the reactor "coolant system, the refueling water storage

tanks, and the accumulators."'

I,.

(2)

At each reload 104 to 108 assemblies~will be discharged.

(3)

Higher allowable peaking factors,'igher moderator temperature coefficient limits, and a revised thermal design procedure will be required.

(4)

Fuel-parameter-dependent transients will have to be reevaluated and may require the use of the loss-of-coolant accident best-estimate technology from Westinghouse.

(5)

The burnup limit of fuel rods will have to be extended to 70 mwd/kgu.

(6)

The current limit on lithium will have to be raised.

The effect of this increase in lithium concentration will have to be addressed.

Laboratory tests have shown an acceleration of pure water stress corrosion cracking of Alloy 600, which is the alloy used in the steam generator tubes.

ORIGINAL SIGNED BY:

James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos.

50-275 and 50-323 Attachments:

1.

Meeting Attendees 2.

Licensee Viewgraphs cc w/atts:

See next page DISTRIBUTION w/Atts 1 and 2:

Docket File PUBLIC PDIV-2 Reading JStone SBloom

JDyer, RIV DISTRIBUTION w/Att 1:

WRussel 1 /FMiragl i a JRoe WBateman OGC NRC Participants JMitchell RZimmerman EAdensam EPeyton EJordan ACRS

KPerkins, WCFO NAME EpeeyPn JStone:

k DOCUMENT NAME:

DCOCT.MTS OFC PDIV-2 LA PDIV-2 PM i

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n DATE 10/B 95 Ig+L RECORD COPY 95 n

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The licensee identified the following major technical issues as requiring resolution before the 24-month fuel cycle is implemented:

(2)

(3)

(4)

The reload design will use 5-percent enriched fuel, requiring a higher boron concentration for the reactor coolant system, the refueling water storage

tanks, and the accumulators.

At each reload 104 to 108 assemblies will be discharged.

Higher allowable peaking factors, higher moderator temperature coefficient limits, and a revised thermal design procedure will be-required.

Fuel-parameter-dependent transients will have to be reevaluated and may require the use of the loss-of-coolant accident best-estimate technology from Westinghouse.

(5)

The burnup limit of fuel rods will have to be extended to 70 mwd/kgu.

(6)

The current limit on lithium will have to be raised.

The effect of this increase in lithium concentration will have to be addressed.

Laboratory tests have shown an acceleration of pure water stress corrosion cracking of Alloy 600, which is the alloy used in the steam generator tubes.

Docket Nos. 50-275 and 50-323 James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Attachments:

1.

Meeting Attendees 2.

Licensee Viewgraphs cc w/atts:

See next page

I I

Pacific Gas 8 Electric Company Diablo Canyon Nuclear Power Plant cc:

NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Commission P.

O.

Box 369 Avila Beach, California 93424 Dr. Richard Ferguson, Energy Chair Sierra Club California 6715 Rocky Canyon

Creston, California 93432 Ns.

Nancy Culver San Luis Obispo Mothers for Peace P. 0.

Box 164 Pismo Beach, California 93448 Hs. Jacquelyn C. Wheeler P. 0.

Box 164 Pismo Beach, California 93448 Managing Editor The Count Tele ram Tribune 1321 Johnson Avenue P.

O. Box 112 San Luis Obispo, California 93406 Chairman San Luis Obispo County Board of Supervisors Room 370 County Government Center San Luis Obispo, California 93408 Rr. Truman Burns Hr. Robert Kinosian California Public Utilities Commission 565 Van Ness, Room 4102 Sm Francisco, California 94102 Hr. Steve Hsu Radiologic Health Branch State Department of Health Services Post Office Box 942732 Sacramento, California 94232 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 5 Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Hr. Peter H. Kaufman Deputy Attorney General State of California 110 West A Street, Suite 700 San Diego, California 92101 Christopher J.

Warner, Esq.

Pacific Gas 8 Electric Company Post Office Box 7442 San Francisco, California 94120 Hr. Warren H. Fujimoto Vice President and Plant Hanager Diablo Canyon Nuclear Power Plant P. 0.

Box 56 Avila Beach, California 93424 Diablo Canyon Independent Safety Committee ATTN:

Robert R. Wellington, Esq.

Legal Counsel 857 Cass Street, Suite D

Honterey, California 93940 Hr. Gregory H. Rueger Nuclear Power Generation, B14A Pacific Gas and Electric Company 77 Beale Street, Room 1451 P.O.

Box 770000 San Francisco, California 94106

0 I

Attachment 1

MEETING WITH PACIFIC GAS AND ELECTRIC COMPANY TO DISCUSS EXTENDING THE FUEL CYCLES FOR DIABLO CANYON NUCLEAR POWER PLANT UNIT NOS.

1 AND 2 OCTOBER 5 1995 ATTENDANCE LIST Paci fic Gas and Electri c Com an Vickie Backman Alan Nicholson Suvesh Kamdar Mike Angus Roger Johnson Westin house Jeffrey Bass Nick Liparulo NRC James Stone Bill Bateman Phillip Rush Christopher Jackson Steven Bloom Subinoy Mazumdar

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EXTENDED FUEL CYCLES DIABLOCANYONPOWER PLANT NRCIPG8 E MEETING ROCKVILLE,MARYLAND OCTOBER 5, 2995

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AGENDA

~ Introduction

~ Overview of Extended Cycle Plans

~ Details of First License Amendment Request

~ Overview of Later License Amendment Requests nrc1 0/5-2

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Extended Cycle Plans and Feasibili Studies Diablo Canyon Power Plant Presentation to NRC October 5, 1995 Suresh Kamdar Pacific Gas and Electric Company

'tives o 24-Month Cycles O'<< '<'<<aC<<4<iC<v

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Fewer refuelings

~ reduced personnel dose and radwaste

~ increased DCPP generation One refueling each year

~ levelized earnings and workload

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more efficient workforce

~ Spring refueling aufages

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reduced chances of DCPP backdowns

~ supports PGBE loadlcapacity seasonal profile

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<'oal to attain 24-month long fuel cycles Phased approach

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Phase I: planning, studies, 5% enrich. license (complete)

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Phase II: '20 mo-nth'ycles from /996 to 200'I

~

Phase III: 24 mo-nth cycles beginning 200/

a Fallback plan

~

Stay on 20 mon-th cycles or return to 78 mon-th cycles

1995 1996 1997 1998 1999 2000 2001 2002 IF HAMI SAS0N0 IF MAMIlAS0N0IF MANI lAS0HDI

F HAMII AS0NDI F MAMJ J AS 0H0 IF MANII AS 0N0 IF MAMAlAS0HDI F HAMI I AS0ND 5% Enrichment License 21wMonth Cycle Feasibility Study ~

Fuel Feature Decision V

PHASE II, 20 Month Cycles,!=8Pe~~s'A Int. Safety Eval Month Cycle Instrument Drift/Setpolnt Study Surveillance Evaluations Tech Spec Changes SZP MlMARRevls PHASE III. 24 MOnth CyCleS

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1 Best Estimate LOCA Accident Analysis RAOC Analysis Bumup Extension (W Effort)

Chemistry Issue Resolution Zinc Injection Alternative (WOG)

Corrosion Testing Alternative Boron Enrichment Alternative Tech Spec Changes P ~62 mwd/kg u V

P ~ed mwd/kgu

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- sibilityStudies

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'20 m-onth'nd 24-month cycle studies complete PGBE and Westinghouse effort Mostly qualitative - except reload design Areas ofassessment

~ Nuclear fuel (reload design analysis)

~ Accident analysis

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Plant operation and maintenance

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Surveillance extensionlTechnical Specifications

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PG8 E system loads/capacity

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k$WgP'Yg4P~g Dimensional analysis performed for Unit 2 Cycles 8,9 and 10 (bounds Unit 1) 96 or fewer assemblies replaced each cycle Willuse ZIRLO clad and fullyenriched solid blankets Willuse 132 inc-h 1 5X.IFBAs

~ RCS boron slightly over current levels

~ No fuel related tech spec changes

ear Fuel Month Cycle ll CCRC 844k

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Challenging but feasible reload design

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High energy cycles, 5% enrichment, 104-108 assm reload, higher burnable absorbers

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Would need higher peaking factors, MTC limits, and Revised Thermal Oesign Procedure

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Would result in higher discharge burnups

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Willhave higher RCS boron

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Need Advanced fuel design Minoreffect on pressure vessel life

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ident Analysis

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'<<4'8 SR Evaluation included LOCA, non LO-CA, containmentintegrity, SG tube rupture, and energy 8, mass releases

'20 m-onth'ransition cycles

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May need to re-evaluafe fransienfs ifany sefpoinf changes

~

Integrated safefy evaluafion would be performed 24 mon-th cycies

~

Would need fo re-evaluafe fuel parameter dependent transients

~

Margins available except forlarge break LOCA

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W's Best Estj'mate technology forLOCA may be needed

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Need higher refueling, RWST, and accumulafor boron

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Hofleg swifchover time would decrease

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.ration and Maintenance

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"'ll k~4kipi 'Q No significant effects on forced outage rates expected No significant effect on refueling outage length expected MinorImpact on major systems and components and PMs RCS Chemistry

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Minoreffect on RCS chemistry for '20-month'ycles

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Elevated lithium levels in RCS forpH control for24-month cycles May need higher boric acid tank and spray additive tank volumes for 24 mon-fh cycles Potential operatingissues, but believed to be manageable Reduced radwaste and personnel dose

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hnical Issues MSak ote: No technicalissuesidentified for '20 m-onth'cycles

,0 Long term RCS material integrity (from elevated Li)

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Lab tests showed accelerated PWSCC ofalloy 600 i4444v.M6

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Plant experiences nof conclusive

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Alternatives foraddressing the issue Burnup limiton fuel rod

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Current burnup limitwould be exceeded

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Wplans forseeking burnup limitextension Best Estimate LOCA technology yet to be approved

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< Cw QC<<< <CC'<Ci'0<<4C" '<<<<<<<<<<<<<<<<<<C<C 20 monfh cycles offer economic benefits and smoother transitioning fo 24 m-onth cycles 24 m-onth cycles offer economic and other benefits Regulatory requirements for 20 an-d 24 m-onfh cycles are believed to be addressable There are no significant fechnical issues with 20 month cycles 24 mo-nth cycle's technical issues are believed to be resolvable

FIRST LICENSE AMENDMENTREQUEST FOR EXTENDED FUEL CYCLES DIABLOCANYONPOWER PLANT UNITS 1 AND 2 Vickie Hackman Pacific Gas and Electric Company

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TECHNICAL SPECIFICA TION SURVEILLANCEREQUIREMENTS

~ GL 91-04 provides guidance for surveillance interval extensions

~ Over 200 Surveillance Requirements (SR) require interval extension

~ PG8 E decided to complete the licensing for 24-month refueling intervals to support "20-month" cycles

~ Need all SERs issued before passing 18 months for Unit 2 Cycle 8 (October 1997)

SURVEILLANCETES T SCOPE

~ All Surveillance Requirements (SR) currently required to be performed during refueling outages 18 month "R"

Refueling outage

~ New SR frequency New definition of REFUELING INTERVAL-not to exceed 24 months Subject to TS 4.0.2 25'/o extension Special designator will be used - "R24"

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SURVEILLANCEREQUIREMENTS

~

lVlajorareas affected IBC Trip actuating device operational tests Functional tests RPS/ESFAS and PAMS setpoints Electrical Batteries Diesel generators Breakers Protective devices Mechanical Fluid systems actuations Pump and valve performance HVACsystems Steam generators

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FIRST LARSUBMITTAL

~ December 1995

~ 32 TS interval extensions Trip actuating device operational tests (10)

Fluid system actuation tests (12)

Miscellaneous specifications (10)

~

2 new TS in accordance with NUREG-1431, Rev.

1 Component cooling water pump automatic actuation Auxiliary saltwater pump automatic actuation

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LARF'REPARA TION

~ PG8 E reviewed submittals for Indian Point 2 and 3 and Millstone 3 Justifications consistent Identify areas where NRC questions were asked

~ SRs were reviewed for conflicts with NUREG-1431 (STS)

Lessen NRC review burden for TS being relocated Additional refueling interval TS

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LAR ORGANIZATION

~ LAR composed of main document providing generic information and justification

~ Each SR or functionally similar group of SRs will have a separate safety evaluation attached

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SAFETYEVALUATION FORMAT

~ Description of change

~ Background (safety function and equipment information)

~ Safety evaluation

~ No significant hazards evaluation

I I

SAFETYEVALUATION

~ Evaluation for surveillance interval extension will be specific to each SR and its related components

~ Criteria used Operating history Surveillance history Maintenance history Industry experience

~

4

~

OPERA TING HISTORY

~ Component performance when challenged by plant events

~ Plant problems caused by components

~ Other redundant system design features

S URVEILLANCEHISTORY

~ Review surveillance testing to satisfy the SR All refueling outage tests ifperformed at refueling frequency Last 3 fuel cycles if performed quarterly

~ Review for time dependent results

~ Impact of performing surveillance at power

~ Other tests relied on for operability

~ Safety significance of test to system operability

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MAINTENANCEHISTORY

~ Review of corrective maintenance for major components for last 3 fuel cycles

~ Evaluation of time dependence for degradation mechanisms

~ Vendor maintenance requirements

~ Preventative maintenance requirements

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INDUSTRYEXPERIENCE

~ Review of NRC Bulletins, GLs, and INs

~ Review of industry operating experience INPO nuclear network ISEG

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STATUS OF SUBMITTAL51 SR EVALUATIONS

~ All SRs reviewed merit extension to the refueling interval testing frequency

~ Process supports December 1995 submittal date

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~ 1995 - 1997 Changes needed to support 19-to 21-month cycles (each change for 24 months)

Primarily surveillance interval increases Possibly some setpoint changes Staggered over 14-month period

~ 1998 - 2000 Additional changes needed for 24-month cycles (2001)

Expected to primarily involve fuel and boration requirements

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KEYDATES - EXTENDED FUEL CYCLES

~ May 1996 - Unit 2 Cycle 8 begins (24-month cycle)

~ October 1997 month surveillances due (all license amendments need to be issued)

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1995 - 1997 AMENDMENT REQUESTS December 1995 - First Request (34 Items)

~ Tech Spec surveillance interval increases:

Trip actuating device tests (10)

Fluid system actuation tests (14)

Miscellaneous specifications (10)

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1995 - 1997 AINENDMENT REQUESTS April 1996 - Second Request (64 Items)

~ Tech Spec surveillance interval increases:

HVAC (control room, auxiliary 8 fuel handling buildings ) (21)

~ Setpoint evaluations:

RPS/ESFAS protection channels (43)

~ ~

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<gg~ - 'Igg7 AMENDMENT REQUESTS September 1996-Third Request (66 items)

~ Tech Spec surveillance interval increases:

Electrical (28)

Miscellaneous (3)

~ Setpoint evaluations:

Remote shutdown monitoring (9)

Accident monitoring (2Q)

Miscellaneous (6)

~

~ )

1995 - 1997 AMENDMENT REQUESTS January 1997 - Fourth Request (42 Items)

~ Tech Spec surveillance interval increases:

Appendix J (ILRT/LLRT)(4)

Slave relay tests (9)

ISI relief requests (1)

IST (5)

SG tube inspection (1)

Snubbers (1)

Miscellaneous (2)

~ Setpoint evaluations:

RMS (9)

Seismic monitoring (10)